ML021280324

Part B - Indian Point 3 Nuclear Plant Annual Radioactive Effluent Release Report for Period of January 1, 2001 Through December 31, 2001

ML021280324
Person / Time
Site:	Indian Point
Issue date:	04/25/2002
From:	Barrett R Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
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Download: ML021280324 (125)

Text

Part I ODCM - Rev. 15 4.0 BASES RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (2/3.1)

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 to 10 CFR 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (2/3.2)

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

LIQUID EFFLUENTS CONCENTRATION (2/3.3.1)

This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 to 10 CFR 20. The Control provides operational flexibility for releasing liquideffluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides.

reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the restrictions authorized by 10 CFR Part 20.1301(e). The concentration limit for the dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its EFFLUENT CONCENTRATION in air (submersion) was converted to an equivalent concentration in water.

This control does not affect the requirement to comply with the annual limitations of 10 CFR Part 20.1301(a).

This Control applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in Currie, L.A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR 4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

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Part I ODCM - Rev. 15 DOSE FROM LIQUID EFFLUENTS (2/3.3.2)

This Control is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control statement implements the guides set forth in Section Ul.A of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"April 1977.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

LIQUID RADWASTE TREATMENT SYSTEM (2/3.3.3)

The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

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ODCM - Rev. 15 Part I GASEOUS EFFLUENTS DOSE RATE (2/3.4.1) in gaseous This Control provides reasonable assurance that radioactive material discharged an UNRESTRICTED effluents will not result in the exposure of a MEMBER OF THE PUBLIC in excess of the design objectives of Appendix I AREA, either at or beyond the SITE BOUNDARY in effluents from all units on the to 10 CFR Part 50. This Control is provided to ensure that gaseous gaseous for releasing site will be appropriately controlled. It provides operational flexibility I to 10 CFR Part 50.

effluents to satisfy the Section II.A and II.C design objectives of Appendix BOUNDARY, the For MEMBERS OF THE PUBLIC who may at times be within the SITE be sufficiently low to compensate for occupancy of that MEMBER OF THE PUBLIC will usually to that for the SITE the reduced atmospheric dispersion of gaseous effluents relative with the PUBLIC, BOUNDARY. Examples of calculations for such MEMBERS OF THE release rate limits appropriate occupancy factors, shall be given in the ODCM. The specified a MEMBER OF THE restrict, at all times, the corresponding dose rates above background to to the total than or equal to 500 mrem/year PUBLIC at or beyond the SITE BOUNDARY to less rate limits also These release body or to less than or equal to 3000 mrem/year to the skin. to a child via the restrict, at all times, the corresponding thyroid dose rate above background Control does not affect the inhalation pathway to less than or equal to 1500 mrem/year. This requirement to comply with the annual limitations of 10 CFR 20.1301 (a).

site.

This Control applies to the release of gaseous effluents from all units at the DOSE FROM NOBLE GASES (2/3.4.2)

III.A and IV.A of Appendix This Control is provided to implement the requirements of Sections II.B, set forth in Section lI.B of I, 10 CFR Part 50. The Control statements implement the guides and at the same time Appendix I. The Action statements provide the required operating flexibility that the releases of implement, the guides set forth in Section IV.A of Appendix I to assure achievable." The radioactive material in gaseous effluents will be kept "as low as is reasonablyof Appendix I that Surveillance Requirements implement the requirements in Section III.A procedures based on conformance with the guides of Appendix I be shown by calculational THE PUBLIC through models and data such -that the actual exposure of a MEMBER OF appropriate pathways is unlikely to be substantially underestimated.

ODCM for calculating the The dose calculation methodology and parameters established in the gaseous effluents are doses due to the actual release rates of radioactive noble gases in of Annual "Calculation consistent with the methodology provided in Regulatory Guide 1.109, Purpose of Evaluating the Doses to Man from Routine Releases of Reactor Effluents for I," Revision 1, October 1977 and Regulatory Guide Compliance with 10 CFR Part 50, Appendix of Gaseous Effluents in 1.111, "Methods for Estimating Atmospheric Transport and Dispersion July 1977. The ODCM Routine Releases from Light-Water Cooled Reactors," Revision 1, SITE BOUNDARY are based equations provided for determining the air doses at and beyond the upon the historical average atmospheric conditions.

at the site. For units This Control applies to the release of gaseous effluents from each reactor the shared system are with shared radwaste treatment systems, the gaseous effluents from proportioned among the units sharing that system.

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Part I ODCM - Rev. 15 DOSE FROM IODINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM (2/3.4.3)

This Control is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section II.C of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-131, Tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man (determined to be not applicable at Indian Point), and 4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

GASEOUS RADWASTE TREATMENT SYSTEM (2/3.4.4)

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

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ODCM - Rev. 15 Part I TOTAL DOSE (2/3.6)

Part 190 that have been This Control is provided to meet the dose limitations of 40 CFR and submittal of a incorporated into 10 CFR Part 20.1301(d). The Control requires the preparation to radiation from and Special Report whenever the calculated doses due to releases of radioactivity uranium fuel cycle sources exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

to a MEMBER OF For sites containing up to 4 reactors, it is highly unlikely that the resultant dose reactors remain within THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual from the reactor units and outside storage tanks, etc., are kept small. The Special radiation twice the dose design objectives of Appendix I, and if direct Report will doses describe a course of action 11h PUBLIC to within the that should result in the limitation of the annual dose to a MEMBER OF THE be assumed that the dose 40 CFR Part 190 limits. For the purposes of the Special Report, it may sources is negligible, commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle fuel cycle facilities at the same site or with the exception that dose contributions from other nuclear THE PUBLIC is MEMBER OF within a radius of 8 km must be considered. If the dose to any Report within 30 of the Special estimated to exceed the requirements of 40 CFR Part 190, submittal in violation of 40 CFR days with a request for a variance (provided the release conditions resulting 40 CFR Part of Part 190 have not already been corrected), in accordance with the provisions request and fulfills the 190.11 and 10 CFR Part 20.2203(a)(4), is considered to be a timely variance only relates to requirements of 40 CFR Part 190 until NRC staff action is completed. The requirements for dose the limits of 40 CFR Part 190, and does not apply in any way to the other An individual is not limitation of 10 CFR Parts 20, as addressed in Controls 2.3.1 and 2.4.1.

is engaged in carrying considered a MEMBER OF THE PUBLIC during any period in which he/she out any operation that is part of the nuclear fuel cycle.

with the design objectives of Demonstration of compliance with the limits of 40 CFR Part 190 or with the 0.1 rem limit Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance of 10 CFR Part 20.1301.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (213.7) this Control provides The Radiological Environmental Monitoring Program required by exposure pathways materials in those representative measurements of radiation and of radioactive of MEMBERS OF exposures and for those radionuclides that lead to the highest potential radiation THE PUBLIC resulting from the station operation.

Part 50 and thereby This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR that the measurable supplements the Radiological Effluent Monitoring Program by verifying than expected on the concentrations of radioactive materials and levels of radiation are not higher exposure pathways.'

basis of the effluent measurements and the modeling of the environmental Annual Effluent the applicable Isotopes identified in REMP are compared to those identified in experiences.

Report. Program changes may be initiated based on these operational in terms of the The required detection capabilities for environmental sample analyses are tabulated optimum for are considered lower limits of detectiOn (LLDs). The LLDs required by Table 3.7-1 should be recognized that the routine environmental measurements in industrial laboratories. It capability of a measurement LLD is defined as an a Prid.(before the fact) limit representing the system and not as an a Posteriori (after the fact) limit for a particular measurement.

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Part I ODCMV - Rev. 15 LAND USE CENSUS (2/3.8)

This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to door survey, from aerial survey or from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

2 Restricting the census to gardens of greater than 50 m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf 2

vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kgl/M .

INTERLABORATORY COMPARISON PROGRAM (2/3.9)

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

LIQUID HOLDUP TANKS (2/3.10)

Pusuant to Technical Specification 5.5.1 1.c, the tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the values given in Appendix B, Table 2, Column 2 to 10CFR20, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICED AREA.

GAS STORAGE TANKS (2/3.11)

Pursuant to Technical Specification 5.5.1 1.b, the tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another specification to a quantity that is less than the quantity that provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with NUREG-01 33.

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ODCM - Rev. 15 Part I 5.0 ADMINISTRATIVE REQUIREMENTS 5.1 RECORDS RETENTION Code of Federal In addition to the applicable record retention requirements of Title 10, schedule of TRM 5.5.

Regulations, records shall be retained in accordance with the retention duration of The following specific Effluent and Environmental records shall be retained for the the unit operating license:

"* Records of any drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

"* Records of gaseous or liquid radioactive material released to the envrions.

"* Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

" Records of analyses required by the radiological environmental monitoring program This that would permit evaluation of the accuracy of the analysis at a later date. these should include procedures effective at specified times and records showing that procedures were followed.

" Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.}

5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT the previous A Radioactive Effluent Release Report covering the operation, of the unit during year. A single submittal may be made for a year shall be submitted prior to May 1 of each to all sections that are common multiple unit station. The submittal should combine those submittal shall systems, the units at the station. However, for units with separate radwaste specify the releases of radioactive material from each unit.

information:

The Annual Radioactive Effluent Release Report shall include the following solid waste A summary of the quantities of radioactive liquid and gaseous effluents and and released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, in Uquid Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials Power Plants," Revision 1, June and Gaseous Effluents from Ught-Water-Cooled Nuclear B the format of Appendix 1974, with data summarized on a quarterly basis following thereof or as modified in the RECS.

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Part I ODCM - Rev. 15

" For solid wastes, the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period will be presented in tabular form similar to that of Table 3 of Regulatory Guide 1.21:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate,

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

" An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on electronic media of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

"* An assessment of the radiation doses due. to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

" An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in the report. Approximate and conservative approximate methods for determining the meteorological conditions shall be used for determining gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

" An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, when required by Sections 2.6 and 3.6, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109 Rev. 1, October, 1977.

"* A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

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ODCM - Rev. 15 Part I of liquid or

" Pursuant to Controls 2.1 and 2.2, an explanation as to why the inoperability corrected within the time specified.

gaseous effluent monitoring instrumentation was not the provisions of

"* Pursuant to Controls 2.1 and 2.2, a discussion of all deviations from these Controls.

of the

" Pursuant to Control 2.7 and Table 2.7-1, Notation (a), identify the causes for obtaining unavailability of samples for pathway analysis and identify the new locations the for the ODCM reflecting replacement samples. Include revised figure(s) and table new locations.

a discussion of

" Pursuant to Table 3.3.1-1, Notation (c) and Table 3.4.1-1, Notation (b),

specified in Tables 3.3.1-1 and identifiable gamma peaks, including those of nuclides 3.4.1-1.

and/or

" Pursuant to Control 2.8, a listing of new location(s) for dose calculations revised figure(s) and environmental monitoring identified by the land use census. Include table for the ODCM reflecting the new location(s).

liquid holdup

" Pursuant to Controls 2.10 and 2.11, a description of the events leading to tanks or gas storage tanks exceeding the Control limits.

liquid, gaseous,

" Pursuant to RECS 5.4, a discussion of the major changes to radioactive and solid waste treatment systems.

period to the

" Pursuant to RECS 5.5 and 5.6, any changes made during the reporting DOSE CALCULATION PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE MANUAL (ODCM), respectively.

REPORT 5.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING the operation of the unit An annual Radiological Environmental Operating Report covering 15t of each year, to May during the previous calendar year shall be submitted prior may be made for a multiple according to Technical Specification 5.6.2. A single submittal unit station.

include:

The Annual Radiological Environmental Operating Report shall Radiological

" Summaries, interpretations, and an analysis of trends of the results of the a comparison, as Environmental Monitoring Program for the report period, including and with previous appropriate, with preoperational studies, with operational controls, of the observed impacts of the environmental surveillance reports, and an assessment plant operation on the environment.

to a table giving distances

"* At least two legible maps covering all sampling locations keyed shall cover stations near the and directions from the centedine of one reactor. One map site boundary and the second shall include the more distant stations.

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Part I ODCM - Rev. 15

" The results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

"* A summary description of the Radiological Environmental Monitoring Program.

" A discussion of the reasons for not conducting the Radiological Environmental Monitoring Program as specified by Control 2.7 and the plans for preventing recurrence.

" Pursuant to Control 2.7, a discussion of environmental sample measurements that exceed the reporting levels of Table 2.7-2 but are not the result of plant effluents.

"* Pursuant to Table 2.7-1, Notation (a), a discussion of all deviations from the sampling schedule of Table 2.7-1.

" Pursuant to Table 3.7-1, Notation (c), a discussion of the contributing factors for cases in which the LLD required by Table 3.7-1 was not achievable.

" Pursuant to Table 3.7-1, Notation (a), a discussion of identifiable nuclide peaks, including those of nuclides specified in Table 3.7-1.

"* Pursuant to Control 3.8, the results of the land use census.

"* Pursuant to Control 2.9, the corrective actions taken to prevent a recurrence if the Interlaboratory Comparison Program is not being performed as required.

"* Pursuant to Control 3.9, the results of licensee participation in the Intedaboratory Comparison Program.

5.4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each shall contain:

"* A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59.

" Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information

" A detailed description of the equipment, components and processes involved and the interfaces with other plant systems 5-4

Part I ODCM - Rev. 15

" An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto

" An evaluation of the change, which shows the expected maximum exposures to an individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto

" A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made

" An estimate of the exposure to plant operating personnel as a result of the change

" Documentation of the fact that the change was reviewed and found acceptable by the PORC

"* A single submittal may be made for a multiple unit station

"* The information called for in this Specification will be submitted as part of the annual FSAR update 5.5 PROCESS CONTROL PROGRAM (PCP) 5.5.1 The PCP shall be approved by the Commission prior to implementation.

5.5.2 Licensee initiated changes to the PCP:

5.5.2.1 Shall be documented and records of reviews performed shall be retained as required by RECS 5.1. This documentation shall contain:

"* Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s); and

"* A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

5.5.2.2 Shall become effective upon review and acceptance by the PORC and the approval of the Site Executive Officer.

5.5.2.3 Shall be submitted to the Commission as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the PCP was made. Each change shall be identified by marking in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

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Part I ODCM - Rev. 15 5.6 OFFSITE DOSE CALCULATION MANUAL (ODCM) 5.6.1 The ODCM shall be approved by the Commission prior to implementation.

5.6.2 Licensee initiated changes to the ODCM:

5.6.2.1 Shall be documented and records of reviews performed shall be retained as required by RECS 5.1. This documentation shall contain:

0 Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes(s); and 0 A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations; 5.6.2.2 Shall become effective upon review and acceptance by the PORC and the approval of the Site Executive Officer.

5.6.2.3 Shall be submitted to the Commission as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by marking in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

5.7 SPECIAL REPORTS In lieu of a Licensee Event Report (LER), the following special reports must be generated within 30 days:

" Pursuant to Control 2.3.2, identify the cause(s) for exceeding the specified limits for dose or dose commitment to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents to UNRESTRICTED AREAS. Define the corrective action(s) taken to reduce the releases and the proposed corrective action(s) to be taken to assure subsequent releases will be in compliance with limits.

Include the results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.

" Pursuant to Control 2.3.3, explain why liquid radwaste was discharged without treatment and identify any inoperable liquid radwaste treatment system equipment or subsystems and the reason for the inoperability. Include the action(s) taken to restore the inoperable equipment to OPERABLE status and a summary description of the action(s) taken to prevent a recurrence.

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Part I ODCM - Rev. 15

"* Pursuant to Control 2.4.2, identify the cause(s) for exceeding the specified limit(s) for the air dose due to radioactive noble gases released in gaseous effluents. Define the corrective actions taken to reduce the releases and define the proposed corrective actions to be taken to assure subsequent releases will be in compliance with limits specified in the Control.

" Pursuant to Control 2.4.3, identify the cause(s) for exceeding the specified limits for the dose to a MEMBER OF THE PUBLIC from the release of iodine-1 31, tritium, and radionuclides in particulate form with half lives greater than 8 days in gaseous effluents. Define the corrective actions taken to reduce the releases and define the proposed corrective actions to be taken to assure subsequent releases will be in compliance with limits specified in the Control.

" Pursuant to Control 2.4.4, explain why gaseous radwaste was discharged without treatment and identify inoperable gaseous radwaste treatment system equipment or subsystems and the reason for the inoperability. Include the action(s) taken to restore the inoperable equipment to OPERABLE status and a summary description of the action(s) taken to prevent a recurrence.

" Pursuant to Control 2.6 and 10 CFR Part 20.2203(a)(4), define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified total dose limits. Include a schedule for achieving conformance with the limits and describe the course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by this report.

Also describe the levels of radiation and the concentrations of radioactive material involved as well as the cause of the exposure levels or concentrations. Include a request, if required by the provisions of the Control, for a variance in accordance with the provisions of 40 CFR Part 190.

" Pursuant to Control 2.7, identify the cause(s) for exceeding the reporting levels of Table 2.7-2 and define the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 2.3.2, 2.4.2, and 2.4.3. Report when more than one radionuclide in Table 2.7-2 is detected and Concentration (1) + Concentration (2) +... > 1.0 Reporting Level (1) Reporting Level (2)

"* Report when radionuclides other than those in Table 2.7-2 are detected and are the result of plant effluents and the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Controls 2.3.2, 2.4.2, and 2.4.3.

5-7

OFFSITE DOSE CALCULATION MANUAL ODCM PART II REVISION 15

Part 11 ODCM - Rev. 15 1.0 INSTRUMENTATION AND SYSTEMS 1.1 Effluent Monitoring System Discription Effluent monitor information is provided in Table 1-1, including an indication of which monitors use effluent setpoints. Figures 2-1 and 3-1 show a schematic of the possible radioactive release points which monitor locations for liquid and gaseous pathways, respectively.

1.2 Setnoints This section provides equations and methodology used for each alarm and trip setpoint on each effluent release point according to Sections 2.1 and 2.2 of the RECS.

1.2.1 Setpoints for Gaseous Effluent Monitors Setpoints for gaseous monitors are based on the permissible discharge rate as calculated in Section 3 of the ODCM. These setpoints are inherently conservative due to the assumed mixture (Table 3-8) and the use of the most restrictive setpoints (annual average dose limit), which are used whenever practical. Higher release rates may be authorized with the proper concurrence, as delineated in Section 3.1.8. The methodology identified in Section 3, along with an isotopic mix described in Table 3.8, are used to generate the following noble gas discharge rates (normally utilized for alarm setpoints):

Permissible Discharge Rate (LLCVsec)

Basis of Limit Iodine/Particulate* Noble Gases Annual Average 11.04E-2 3.08E+3 Quarterly Average 2.08E-2 6.15E+3 Instantaneous *1.20E+1 3.81 E+4

• Half-lives greater than 8 days

• • These limits are not part of Section 2.4.1 of the RECS, but are included for information, as these limits are used for operational control of releases.

Derived from Section 2.4.1 of the RECS.

1.2.1.1 The Plant Vent Wide Range Gas Monitor (R-27) reads and alarms in pCi/sec, hence, the alarm setpoints are set directly in g.Ci/sec.

1.2.1.2 If the monitor reads and alarms in gCi/cc, the maximum alarm set point is calculated as follows:

S = D / [(F)* (4.72E+2)]

where: S = Maximum alarm setpoint in t.Ci/cc D = Permissible discharge rate in g.Ci/sec F = Vent duct flow in ft3/min 4.72E+2 = unit conversion factor (28317 ccomin/ft3 ,60sec) 1-1

Part II ODCM - Rev. 15 1.2.1.3 Ifthe monitor reads and alarms in cpm, then the maximum alarm setpoint is calculated as follows:

S = D / [(F) * (4.72E+2) * (CF)]

where:

S, D, F, and 4.72E+2 are defined in the previous step CF = Rad Monitor Conversion Factor (JACi/cc per net cpm) 1.2.1.4 Normally, maximum allowable limits are calculated using a standard nuclide mix. However, setpoints may be determined based on the actual mix, on a case by case basis. This method is usually performed when the instantaneous release rate is applied. Should this method be applied, extra care should be applied to setpoint partioning (for all j rzh release points) to ensure site dose rate limits are not approached.

1.2.1.5 During normal operation, the Unit 3 main plant vent is the only significant release point. Hence, monitors on the plant vent are routinely set at the annual limit, which is approximately 10% of the conservative instantaneouslimit.

Monitor setpoints on other pathways are routinely set to 1% of the instantaneouslimit. If multiple pathways become significant, each j

pathway's permissible release rate is apportioned with the Plant Vent's to ensure the total discharge rate for all release points remains less than the maximum permissible discharge rate.

1.2.2 Setpoints for Liquid Effluent Monitors 1.2.2.1 Liquid Effluent Monitors have setpoints based on limiting the concentrations in the discharge canal to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20 in accordance with 10CFR20.1302(2)(i). Monitor setpoints are inherently conservative Il due to the routine use of Circulating Water Pumps for liquid waste I releases, and Service Water for continuous releases. In actuality, both Circulating and Service Water systems contribute to site dilution.

1.2.2.2 For monitors that read and alarm in A.Ci/ml, such as the liquid waste disposal monitor (R-18), the service water monitors (R-16 A and B and R-23), and the steam generator blowdown monitor (R-19) the alarm setpoint is calculated as follows:

S = [(ADC) (F)]/[f] = Maximum alarm setpoint in pCi/mI where:

F= Available discharge canal dilution flow for this release in gal/min f= calculated allowable release rate in gal/min (Section 2.2.6) 1-2

Part 11 ODCM - Rev. 15 ADC = Allowed diluted concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (beta and gamma emitters). This parameter is further clarified in Section 2.2.

NOTE: The gamma equivalent MPCW or ADC must be used due to the insensitivity of the radiation monitor to beta emitters and the time necessary to analyze liquid releases for these beta emitters.

1.2.2.3 Alert setpoints should be used on batch liquid release monitors to ensure the contents of the batch tank have not changed since sampling. The alert setpoint is calculated as follows:

AS = (C) * (M) where:

AS = Alert setpoint in pCi/ml C = Average monitor reading at time of sample M = A conservative factor based upon the mixing ratio of two tank volumes and an expected monitor response error term (typically 1.25, coinciding with 25%).

NOTE: Liquid Monitor alert setpoints do not control any auto functions but simply provide indication to the operators.

1.3 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be shown in Figure 1-1.

The definition of UNRESTRICED AREA used in implementing the Radiological Effluent Controls (RECS or ODCM Part I) has been expanded over that in 10 CFR 20.1003. For calculations performed pursuant to 10 CFR 50.36a, the concept of UNRESTRICTED AREAS refers to areas at or beyond the SITE BOUNDARY and does not include areas over water bodies. This definition is utilized in the RECS to keep levels of radioactive materials in liquid and gaseous effluents as low as reasonably achievable.

1-3

0 '

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1-4

Part 1I ODCM - REV. 15 TABLE 1 -1 (Paae 1 of 2)

EFFLUENT MONITORING SYSTEM DATA ALARM CHANNEL MONITOR SAMPLING LOCATIONS RANGE EFFLUENT CONTROL SETPOINT DESCRIPTION FUNCTIONS USED R-12 G Containment Gas Samples drawn from 32 and I E-7 to 1E-1 JCi/cc Containment Ventilation Isolation Note I

_Monitor 35 Containment Fan Coolers In Plant Vent at 1Secures waste gas tank release R-14 G Plant Plt Monitor VE-6Radiogas Vent approximately 105' elevation to E-1 Ci/cc and Containment Ventilation Isolation Note I Air Ejector In-line detector on the air tOn alarm diverts air ejector flow to Condenser 1E-6 to 1E+0 i/cc VC, to condenser steam stopped priming Note 1 R-15 G MondensertAi G

Monitor ejector eexhaustt header tornlejdector theader air ejector and steam to reheater secured R-20 G Waste Gas Disposal Adjacent to line monitor on None Note 3 System Monitor suction to waste gas 1E-2 to 1E+3 pCilcc compressors Secure waste gas tank release R-27 G Plant Vent Wide-Range Sample drawn from inside 1E-7 to I E+5 pCi/cc and Containment Ventilation Note 1 Monitor Plant Vent Isolation R-46 G Administration Building th Floor Administration E+6 cpm 1E+1 to 15E-8 None Note I Vent Radiogas Monitor 4Building Monitor Exhaust (typically to 5E-Plenum for Controlled Areas 2gCVcc)

R-59 G RAMS Building Vent 55' RAMS Building Monitor 1E-6 to 1E+2 pCilcc None Note I Radiogas Monitor Exhaust Plenum I II_ I 1-5

0 Part II ODCM - REV. 15 TABLE 1 - 1 (Page 2 of 2)

EFFLUENT MONITORING SYSTEM DATA I II CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS RANGE EFFLUENT CONTROL ALARM FUNCTIONS USED Fan Cooler and Motor Adjacent to service water return line from 1E-7 to I E-1 R-16 A/B L Cooler Service Water Return V.C. fan cooler units and motor coolers jtCi/cc None Note 1 Component Cooling System Adjacent to line monitors on each pump I E-6 to 1E-1 R-17 A/B L pump outlet outlet l.Ci/ml None Note 2 Component Cooling Heat Adjacent to line monitor mounted on 1E-7 to 1E-1 R-23 L Exchanger Service Water service water return line from Component i None Note 1 Monitor Cooling Heat Exchanger Aci/cc Waste Disposal Liquid In-line monitor on monitor tank recirc 1E-7 to 1E-1 Terminates monitor R-18 L Effluent Monitor pump discharge pCi/cc tank release on alarm Note 1 PAB blowdown room monitors steam I E-6 to I E+2 Closes blowdown SG Blowdown Monitor generator blown RCi/cc isolation valves and SG Note 1 R-19 L

__sample valves Monitor recirculation of HTDS and LTDS 1E-7 to 1E-1 Terminates HTDS or Note CPF Regen Waste Release tanks in condensate polisher (used when 17Ci/cc LTDS tank release R-61 L Monitor primar to scna l elease Iprimary to secondary leakage exists). I IV Note I Alarm setpoint used for effluent considerations. G = Gaseous L = Liquid Note 2 Alarm setpoint NOT used for effluent considerations, used for information only.

Note 3 Ensures 50000 Ci limit in gas decay tanks is not exceeded.

Note 4 Alarm setpoint based on effluent considerations ONLY if a Primary to Secondary Leak exists (otherwise there is no basis).

I A primary to secondary leak is defined by the presence of fission or activation products in the secondary fluid, verified as Steam Generator U-tube leaks (and not from other known contamination, such as IVSWS leaks) - or - a Tritium activity of greater than 5.00E-6 uCi/mI identified in the secondary fluid.

1-6

Part 11 ODCM - Rev.-15 2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Information 2.1.1 The surveillance and lower limit of detection requirements for liquid radioactive effluents are contained in Section 3.3.1 of the Radiological Effluent Controls (RECS). Lower limit of detection calculations are listed in ODCM Part II,Appendix B.

2.1.2 A completed and properly authorized Liquid Radioactive Waste Permit should be issued pdor to the release of any radioactive waste from an isolated tank to the discharge canal. A permit is required for each radioactive tank to be discharged.

2.1.3 All activity determinations for liquid radioactive effluents will be performed in such a manner as to be representative of the activity released to the river.

2.1.4 The radioactivity in liquid waste tanks shall be continuously monitored during release except as allowed by Section 2.1 of the RECS. If the flowmeter is inoperable, the flow shall be estimated every four hours by difference in tank level or by discharge pump curves.

2.1.5 Prior to discharge, the radioactive waste tank contents shall be recirculated for at least two tank volumes. After this recirculation, and prior to discharge, a sample shall be taken and analyzed for activity with a portion of the sample set aside for composite analysis. The measured activity shall be used for calculating allowable discharge rate and the alarm setpoint for the liquid waste discharge monitor.

2.1.6 Radioactive releases of steam generator blowdown during primary to secondary leaks when released to the river should be documented on Liquid Radioactive Waste Release Permits using data supplied by the Chemistry Technician.

2.1.7 Assurance that combined liquid releases from Units 2 and 3 do not exceed Section 2.3 requirement of the RECS limits for the site are provided by administrative controls. These administrative controls are agreed to in the Memorandum of Understanding (#15) between units 2 and 3 concerning liquid discharge and the requirements of this document.

2.1.8 The dilution flow from Unit No. 3 should be used for calculating discharge canal concentrations during the discharge. Per Memorandum of Understanding #15, however, one unit can reduce or eliminate radioactive liquid waste discharge for a period of time to allow the other unit to use the full site dilution flow, or a specified portion thereof, for a discharge when necessary. Additionally, time average dose calculations are performed with MOU-1 5, which allocates dilution flow for the time period, apportioned between Unit 3 and Unit 2.

2-1

ODCM - Rev. 15 Part II 2.1.9 Steam Generator Blowdown activity is determined by samples taken at least three times per week. These "grab" samples of the steam generators are collected in a manner to be proportional to the rate of flow of individual steam generator to total steam generator blowdown. These samples are then analyzed for the various radionuclides at frequencies specifiied in Table 3.3.1-1 of the RECS. Further flow proportional composites are made where appropriate.

2.1.10 The discharge canal flow rate is determined by the use of pump flow characteristics curves. Nominal maximum flow for condenser cooling pumps is 140,000 gpm. During the cold weather months, the condenser cooling pumps are operated at reduced speed, nominally 64,000 gpm.

2.1.11 Radioactivity content in outdoor tanks is to be limited to less than 10 curies, excluding tritium and noble gas, as per Section 2.10 of the RECS.

Compliance with'this requirement is demonstrated by limiting the radioactive concentration in these tanks to the value which results in 10 curies when the tank is at full liquid capacity, except as modified below.

The radioactive concentration limits for these tanks are:

RWST: l0curiesxlO6 pCi/curie = 7.3x10-31UCi/ml 358,500galx 3785ml/gal PWST: l0curiesxl0 61uCi/curie = 1.6xlO 2 pCi/ml.

165,000gals x 3785m1 / gal 31 & 32 MT:

10 curiesx 106 pCi/ curie = 2.2 x 10-1 Ci/ ml 11,750galsx 3785m//gal Condensate Polisher High and Low Total Dissolved Solids Tanks:

10 curies x 106 PCi/ curie = 410-2pCi/Ml

/ gal 60,O00gals x 3785ml Outside TemDorary Tanks:

10 curiesx l0-6 , Ci/curie=lici Iml Volume (gal) x 3785ml/ gal 2-2

Part 11 ODCM - Rev. 15 The refueling water storage tank has the potential to be filled from the reactor cavity with liquid which exceeds the limits stated. Therefore, prior to filling the RWST from the reactor cavity after refueling operations, the reactor cavity (or residual heat removal system) must be sampled for radioactivity and action taken to ensure that the total activity in the tank does not exceed 10 curies.

Outside temporary tanks should not be filled with liquid which could exceed the concentration limit calculated. Therefore, prior to transfer to outside temporary tanks, the source of liquid shall be sampled for radioactivity. If it exceeds the concentration limit calculated, action shall be taken to ensure that the total activity in the tank does not exceed 10 curies.

2.1.12 Although R-19 continuously monitors steam generator blowdown to the river, there are no continuous composite samples for steam generator blowdown. The method of determining release concentration is as follows:

Individual blowdown Sample Composite flow rate to river X Blowdown - activity being (by flowmeter or curves) Concentration released 2.1.13 The service water radioactivity monitors listed in Table 2.1-1 of the RECS are defined as the process radiation monitors which monitor components discharging into or are cooled by the service water system. These and other liquid effluent process radiation monitors are:

Service Water.

R-16 A or B: Fan Cooler and Motor Cooler unit service water return monitors R-23: Component cooling service water return Liquid Waste (separate release points):

R-1 8: Liquid waste release monitor I-/

R-1 9: Steam generator blowdown radioactivity monitor R-61: Condensate Polisher waste monitor. Applicable only after a Primary to Secondary Leak, as per ODCM Part II, Sec 1, Table 1-1, Note 4.

If all monitors on the effected release path are taken out of service and the removal of that monitor from service is not specifically addressed in the RECS, releases may continue via this pathway provided that samples are taken on the effected stream every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2-3

1. ~E~%I~ I5~ C Part II V %..uIVI - r'wv. I 2.1.14 Liquid effluent concentrations must be within the limitations of 2.3.1 of the RECS. The total dose per quarter and per year must be within the limitations of 2.3.2 of the RECS.

2.1.15 There are no drinking water intakes within 3 miles downstream of the site on the Hudson River (see Section 2.4.1 for further details).

2.1.16 A turbine hall drain system which would collect leakage of contaminated secondary plant waters during operation does not exist at IP3. The sumps present in the turbine hall (five foot elevation) receive drains from areas containing secondary plant components at sub-atmospheric pressures.

These sumps do not meet the intent of a turbine hall drain system as defined in NUREG 0472.

Quantification of effluents is performed on this pathway during a Primary to Secondary leak, as defined by ODCM Part II,Section 1, Table 1-1, Note 4.

In these cases, releases from this pathway would be quantified by periodic sampling and determination of the release rate to the river.

At elevated Steam Generator activity levels (approximately 1.OE-4 or above), turbine hall drains may require temporary processing, should effluents via this pathway approach the 31 -day dose projection limits per RECS 2.3.2. In this case, water is directed to the Condensate Polishing Facility or otherwise processed prior to release.

[Turbine Activity released via this pathway is determined as follows:

Hall (Feedwater') "SteamPlant SG Blowdown'"

Drain Specific Makeup - Rate to the

,Effluent Activity', Activity ) Rate River )

2.1.17 Carbon 14 is released at a rate of .07 curies per GW(e)/yr with an average make up rate of 0.5 gal/min based upon studies performed by the New York State Department of Health. The estimate of Carbon 14 releases are included in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. These estimates are not included in dose calculations for routine releases.

2.1.18 Several normally non-radioactive systems are periodically analyzed for radioactivity. These include condensate polisher regenerant waste and the Spent Fuel Pool Backup Heat Exchanger secondary cooling system (when in use). The monitoring program for these release points is consistent with the direction set forth in NRC IE Bulletin 80-10 "Contamination of Non radioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment". Should a system become contaminated, releases will be evaluated and quantified (as either batch or continuous) in accordance with the requirements listed in the RECS.

2-4

Part II ODCM - Rev. 15 2.1.19 The liquid waste monitor tanks have an airborne release pathway. The original plant design limited the gases through this pathway by reducing the entrained gases to less than 2E-3 pCi/ml. When the entrained gas concentration in the monitor tank inlet exceeds 2E-3 gCi/ml, the noble gas release will be quantified by calculating the difference (in g.Ci's) between the gaseous activity added to the tank and the gaseous activity present in the effluent release sample. This difference will be the activity released through the tank vents and is quantified as an airborne release.

2.1.20 Due to the addition of Hafnium control rods in fuel cycle 11, an offsite dose may need to be calculated for Hafnium isotopes in waste pathways. In the absence of site-specific bioaccumulation and dose factors for Hafnium, factors for Zirconium will be used, as suggested in ICRP 30. Should these calculations become necessary, they will be performed per Section 2.5 and manually added to other totals.

2.2 Liquid Effluent Concentrations 2.2.1 This section provides a description of the means that will be used to demonstrate compliance with the RECS, Section 2.3.1.

2.2.2 Compliance with the instantaneous limits of 10CFR20 is achieved by observance of discharge limits and described in Section 2.1.14. Normally for instantaneous release rate purposes, only dilution water from Unit 3 circulators is taken credit for, except as allowed by the Memorandum of Understanding between units 2 and 3. A monthly report is issued which summarizes the radioactive releases from the site for the preceding month.

This report provides information necessary to comply with quarterly and annual average limitations on discharge.

2.2.3 Each isolated liquid waste tank must be recirculated for at least two tank volumes prior to sampling in order to ensure a representative sample is obtained. A default minimum recirculation time may be used for 31 and 32 monitor tank in lieu of the actual calculation. This value is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, based upon the following calculation:

11750 gals *2 Tank Volumes =3.9 Hours st 4 Hours 100 gal/wain Note: Nominal monitor tank pump flow rate is approximately 135 gpm. For conservativism however, 100 gpm is used for the recirculation flow rate, while 150 gpm is used for the discharge flow rate in all release calculations.

2.2.4 The concentration in liquid effluents prior to dilution in the discharge canal is determined by sampling prior to release for batch releases. For continuous release the concentration can be determined by either grab sampling as in the batch release method or by direct reading radiation monitor. Ifthe process radiation monitor is utilized care should be taken to ensure the calibration factor used is appropriate for the mixture being released.

2-5

Part 11 ODCM - Rev. 15 For non-direct reading monitors, the following calculation is used:

C=CF*CR C= Concentration of liquid effluent (pCi/ml) prior to dilution CF = Conversion factor of monitor POCi/mI ncpm CR = Count rate of monitor (ncpm) 2.2.5 The final diluted concentration in the discharge canal is determined by the following:

CD = (C) I(f)(F)

Where: CD = Diluted concentration in the discharge canal in aCilml C = Concentration in the liquid to be released prior to dilution in uCi/ml F = Dilution flow in the discharge canal in gal/min f = Release rate of liquid effluent in gal/min NOTE: This equation is not used for calculating allowable release rates.

2.2.6 Calculation of Maximum Permissible Concentration in Liquid Effluents

a. This section describes the methodology used to ensure the requirements of section 2.3.1 of the RECS are satisfied. The total discharge canal concentration of radionuclides must be maintained less than those identified by section 2.3.1 of the RECS. The noble gases will be included using the limit 2E-4 pCi/ml as specified in section 2.3.1 of the RECS. This will normally be ensured by using an Allowed Dilution Concentration on each discrete release. This differs from the ADC calculated in 10CFR20 appendix B in that for radioisotopes that do not have gammas greater than 60 kev emitted during decay, default values are included to estimate their contribution. The Allowed Diluted Concentration is derived and calculated as follows:

=PCWt

• CG MPCtt* CG MPCWt ADCC or ADC= MP]TADC= or Total activity CG+CB 1+

where:

ADC = Allowed diluted concentration in p.Ci/ml 2-6

Part 11 ODCM - Rev. 15 MPCWt = Maximum permissible concentration in water for all isotopes (beta & gamma), in gCi/ml, as defined in RECS, Section 1.8, as follows:

ZCi MPCWt =

S(Cii)

Ci and MPCWi = Concentration and MPCW for each isotope CB = The concentration of the non gamma emitters, in +/-Ci/cc CG = The concentration of the gamma emitters in uCi/ml

b. A representative sample must be obtained. In the case of a batch release this is ensured by having the contents of the tank recirculated for at least two tank volumes after the tank has been isolated. The minimum recirculation time is determined as follows:

T = 2(V)/(G) where; T = Minimum recirculation time in min V = Volumes in the tank to be discharged, in gal G = Recirculation rate in gal/min NOTE: As stated in Section 2.2.3, a default recirculation time for 31 and 32 Monitor tanks of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> may be used to simplify routine calculations.

c. After the tank has been sampled, determine the Allowed Diluted Concentration as per step 2.2.6a.

d. Determine if other liquid radioactive discharges are being made from this unit and obtain the radioactive concentration and discharge rate. If another release is occurring, the available dilution flow must be adjusted. This may be performed by allocation or by calculation. The required dilution flow is calculated as follows:

E =Dr* CG where; ADC Dr = Current release discharge rate (gpm)

E = Required dilution flow for current release (gpm)

CG and ADC are defined in Section 2.2.6.a 2-7

Part 11 ODCM - Rev. 15

e. Calculate the permissible discharge rate as follows:

D= ADC *B Where:

CG D = Permissible discharge rate in gal/min ADC = Calculated and described in Step 2.2.6.a CG = Gamma emitter concentration in pCi/mI B = Adjusted dilution flow from the unit, in gpm, from Step 2.2.6.d, above, as follows:

B= [ Available Dilution FLow] - [ Required Dilution FLow (E)]

2.3 Liquid Effluent Dose Calculation Requirements 2.3.1 Section 2.3.2 of the RECS requires that the dose or dose commitment above background to an individual in an unrestricted area from radioactive materials in liquid effluents released from each reactor unit shall be limited:

a) During any calendar quarter Less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b) During any calendar year Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

NOTE: If either of the above limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per Section 2.6.A of the RECS.

2.3.2 Section 2.3.3 of the RECS requires that appropriate portions of the radwaste treatment system be used to reduce the radioactive material in liquid waste prior to their discharge when the projected dose due to liquid effluent from each reactor unit when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses due to liquid release shall be projected at least once per 31 days. These doses are projected based on the dose methodology in Section 2.4. or 2.5. The average of previous months' doses is used to project future dose:

[major 1 Dose 1] Current Month Dose + Previous months' Dose : planned Levodutionsi

[ProjectionJ number of months used The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

2-8

Part 11 ODCM - Rev. 15 2.3.3 Section 2.3.1 of the RECS requires that the concentration of radioactive material released from the site shall be limited to 10 times the concentration values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases the concentration shall be limited to 2E-4 .LCi/mltotal activity.

2.4 Dose Methodology (Computer Calculation) 2.4.1 NUREG 0133 (Ref. 1, Section 4.3, Pg. 14) states that cumulative dose contributions should consider the dose contribution from the maximum exposed individual's consumption of fish, invertebrates, and potable water as appropriate. The river at IP3NPP is considered to be fresh water when in reality it is a tidal estuary and never completely fresh. Observed average chlorosity at IP3NPP has ranged as high as 2.5 gm/liter or about 13% sea water and 87% fresh water.

Hence, use of the Hudson River for water supply purposes is precluded south of Chelsea (mile point 65) which is the nearest point of potable water supply (approximately 15 miles upstream of IP3NPP). Radionuclide concentrations in the nearest water supply have been calculated (Ref. 2) to be a factor of at least 500 lower than the river water in the Indian Point area.

Due to the absence of a potable water pathway downstream of IP3NPP, RECS 2.3.2 reporting regulations for a 3 mile downstream limit do not apply. Exposures from ingestion of drinking water is therefore negligible.

Based on these factors, potable water consumption is not considered to be a pathway at IP3NPP. Thus, at IP3NPP, the cumulative dose considers only the dose contributions from the maximum exposed individuals consumption of fish and invertebrates. Tables of dose factors for three age groups were developed as per Section 2.4.3 and are included as Tables 2 1, 2-2, and 2-3. (infant dose factors are 0 and are not included).

2.4.2 The relationships and methods that form the calculational base for dose accounting for the liquid effluent pathway are described in this section.

These relationships can be used to meet the calculational requirements of Section 2.3.1. The cumulative dose factors (AiT) are calculated in Section 2.4.3. The following equation is generally applicable and can be used for any number of isotopes released over any time period. The equation for D(T) is to be summed over all i nuclides:

m nt D(T) = m~ k D(TA, Z (dtk)(Ckk)(Fk) 1=1 k=1 2-9

t"%nfRA 4A Part II ,1.,,V, - EoV.

Where:

D(M)= The cumulative dose commitment from nuclides to the total body or any organ,: T, from liquid effluents for the total time period equal to the sum from k=1 to n of dtk, in mrem.

dtk = The length of the time period, k over which Cik and Fk are averaged for all liquid releases, in hours.

Cik = The average concentration in pCi/ml of radionuclide, i, in undiluted liquid effluent during time period dtk from any liquid release.

n = The total number of releases considered.

An- = The site related ingestion dose commitment factor to the total body or any organ for each IP3NPP identified principal gamma and beta emitter listed in Table 2-1, 2-2, and 2-3, in mrem-ml per hr-iCi.

Fk = The total dilution factor for C. during any liquid effluent releases. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters, times an applicable factor.

The term Cik is the composite undiluted concentration of radioactive material in liquid waste at the release point as determined by the radioactive liquid waste sampling and analysis program as contained in the RECS. All dilution factors beyond'the sample point are included in the Fk and An terms.

The term Fk is a total dilution factor and is determined as follows:

Liquid Radioactive Waste Flow Fk = [Discharge Structure Exit Flow

• Applicable Factor]

The liquid radioactive waste flow is the flow from all continuous and batch radioactive effluent releases specified in the RECS from all liquid l,.l radioactive waste management systems. The discharge structure exit flow is the average flow during disposal from the discharge structure release point into the receiving body of water. Based on studies by New York University Medical Center (ref. 14 page 7), the appropriate "Applicable Factor' (also known as the "near field dilution factor") is 5.

In order to accurately determine Fk, it is calculated based on actual dilution flow from its site for the time period considered. This affords a quantitative assessment of radiation dose resulting from liquid effluent releases at IP3NPP. The determination and use of dilution factors is discussed in Section 2.2.

2-10

Part 11 ODCM - Rev. 15 2.4.3 Dose Factor for Liquid Effluent Calculations 2.4.3.1 The equation for dose from liquid effluents requires the use of a dose factor AT for each nuclide, i, which embodies the dose factors, pathway transfer factor, pathway usage factors, and dilution factors for the points of pathway origin. IP3NPP has followed the guidance of NUREG 0133 and has calculated Arr for the total body and critical organ of the maximum exposed individual (e.g. the adult). All the factors needed in the equation were obtained from Regulatory Guide 1.109 (Ref. 3) with the exception of the fish and invertebrate bioaccumulation factors (BF 1 and B11) for Cesium, Niobium, Silver, and Antimony.

For Cesium a site specific factor of 224 was used instead of the 2,000 presented in Table A-1 of the Regulatory Guide for fish.

Similarly, a factor of 224 was used for invertebrates instead of the Regulatory Guide value of 1000. For Silver, the fish and invertebrate factors are 2.3 and 3300, respectively. For Niobium, the fish and invertebrate factors are 300 and 100 respectively. For Antimony, the fish and invertebrate factors are 1 and 300 respectively. The justification for these substitutions is discussed in Section 2.6. The summary dose factor is as follows:

4 = K[(UF)BF,+ (UI)BI,]Df Where:

Arr = Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, mrem/hr per g.CVml.

K = Units conversion factor, 114155 = (1E6pCi/iLCi) * (1E3ml/ka) 8760 hr/yr UF = kg/yr fish consumption from Table E-5 of Regulatory Guide 1.109:

21 Adult 6.9 Child 16 Teen 0 Infant BFi = Fresh Water Fish Bioaccumulation factor for nuclide, i, in 2. i pCi/kg per pCi/I from Table A-1 of Regulatory Guide 1.109.

UI = kg/yr invertebrate consumption from Table E-5 of Regulatory Guide 1.109:

5.0 Adult 1.7 Child 3.8 Teen 0 Infant Bli = Salt Water Invertabrates Bioaccumulation factor for nuclide, i, in pCi/kg per pCi/I from Table A-1 of Regulatory Guide 1.109. 'l 2-11

ODCM - Rev. 15 Part lI DF1 = Dose conversion factor for nuclide i, for age groups in pre selected organs, T, in mrem/pCi, from Tables E-1 1, 12 & 13 of Regulatory Guide 1.109.

IP3NPP has compiled Art factors for 3 age groups and various organs for the maximum exposed individual. These are included as Table 2-1, 2-2, and 2-3. For completeness, this table includes all isotopes found in Reg Guide 1.109, however, several isotopes listed are not routinely identified at IP-3. In addition, the values for Antimony, Silver, Cesium, and Niobium are site specific as previously discussed.

2.5 Backup Calculation Methodology in Section 2.4.

Note: These methods provide backup calculations identical to those 2.4 2.5.1 An alternate computer method which completely complies with Section should be used when the primary computer system is inoperable.

2.5.2 Hand Calculations which completely comply with Section 2.4 can be employed if the primary and secondary computer codes are inoperable.

Because they are time consuming and subject to calculational errors, procedural guidance in the actual flow of calculations should be used to maintain a standard format. These procedures are also used for periodic benchmark tests of the computer codes.

2.6 Site Specific Bio-Accumulation & Dose Factors 2.6.1 As stated in Section 2.4.3 the bioaccumulation factor (BF 1) for Cesium in fish is assumed to be 224 instead of the 2000 listed in Regulatory Guide 1.109 (Ref. 3). Similarly, the bioaccumulation factor for invertebrates is 224. This is based on the fact that the Hudson River at IP3NPP is not completely fresh, the Bioaccumulation Factor for salt water is 40 (Ref. 2),

and that the behavior of Cesium in the Hudson is a complex phenomenon.

The NYU Study (Ref. 2) shows that Cesium concentrations in fish are regulated at a relatively constant value independent of the concentration of Cesium in water, and the bioaccumulator factors are thus inversely proportional to the water concentration of Cesium. This explains the lower bioaccumulation factor for Cesium reported by numerous investigators for salt water fish as opposed to fresh water fish because of the higher stable Cesium content of sea water. The NYU Report states that water at Indian Point has a dissolved Cesium concentration which is much higher than would be expected from simple mixing between sea water and fresh water and postulates that these higher concentrations result from leaching of Cesium from bottom sediment by saline water.

2-12

Part 11 P ODCM -Rev. 15 Use of the bioaccumulation factors of Regulatory Guide 1.109 for a fresh water site will thus substantially overestimate fish ingestion doses because no account is taken of the phenomena just discussed. However, radiocesium concentrations in fish may still be estimated through the use of a bioaccumulation factor, provided that this factor is determined from the body of water of interest. This factor has been estimated (Ref. 12, page

33) to be about 224 for the flesh of indigenous fish caught in the Indian Point area. In contrast, the Cesium fresh water bioaccumulation factor presented by Regulatory Guide 1.109 for fish is 2000.

Fish ingestion doses would therefore be overestimated by a factor of 13 if the Regulatory Guide values were used.

Similarly for invertebrates, the site specific bioaccumulation factor of 224 is used. This is larger than the value of 25 given in Reg Guide 1.109 for salt water invertebrates.

A second conservatism in the NRC model concems the location at which the concentrations in the river of the discharged Cesium are evaluated.

Use of this model implies that these fish have grown directly in such a location prior to being caught, which is unrealistic and adds about a factor of five in conservation. This conservatism remains in the calculation, thus the use of the NYU (Ref. 12) bioaccumulation factor is justifiable since this remains as a conservative calculation.

2.6.2 No bioaccumulation factor for Silver is listed in Rev. 1 of Regulatory Guide 1.109, Table A-1. The values of 2.3 and 5000 for fish and invertebrates were obtained from ORNL-4992 (sponsored by ERDA 660, Ref. 25) and are included in the ODCM in the interests of increased accuracy since Ag 11 mOn is a potential component of IP3NPP liquid releases.

2.6.3 International Atomic Energy Agency Report No. 57 provides data more recent than that presented in Regulatory Guide 1.109 for niobium bioaccumulation factors. The factor in the Regulatory Guide appears to be substantially overconservative and, therefore, the more recent IAEA information is incorporated into the dose calculation methodology for liquid releases of radioniobium. The values from Table XVII of IAEA No. 57 are 300 and 100 for freshwater fish and marine invertebrates respectively and are incorporated into this ODCM.

2.6.4 Antimony isotopes are not listed in Reg. Guide 1.109. As for Niobium above, IAEA Report No. 57 was used to provide bioaccumulation factors for the Antimony isotopes in Table 2-1. Dose factors were calculated for Antimony as per Reference #13.

2.6.5 In summary, with the exception of the bioaccumulation factors discussed above, all remaining factors are as follows: fish factors are for fresh water and invertebrate factors are for salt water.

2-13

Part 1 ODCM - Rev. 15 Table 2 - 1 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 BE-7 3.29E-01 7.45E-01 3.69E-01 O.OOE+00 7.83E-01 O.OOE+00 1.28E+02 NA-24 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 P-32 4.96E+07 3.08E+06 1.92E+06 O.OOE+00 O.OOE+00 O.OOE+00 5.57E+06 CR-51 O.OOE+00 O.OOE+00 4.31E+00 2.58E+00 9.50E-01 5.72E+00 1.08E+03 MN-54 O.OOE+00 5.43E+03 1.04E+03 O.OOE+00 1.61E+03 O.OOE+00 1.66E+04 MN-56 O.OOE+00 1.37E+02 2.42E+01 O.OOE+00 1.73E+02 O.OOE+00 4.36E+03 FE-55 3.21E+04 2.21E+04 5.16E+03 O.OOE+00 O.OOE+00 1.24E+04 1.27E+04 FE-59 5.06E+04 1.19E+05 4.56E+04 0.0OE+OO O.OOE+00 3.32E+04 3.96E+05 CO-58 O.OOE+00 5.15E+02 1.15E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.04E+04 CO-60 O.OOE+00 1.48E+03 3.26E+03 O.OOE+00 O.OOE+00 O.OOE+00 2.78E+04 NI-63 4.97E+04 3.45E+03 1.67E+03 O.OOE+00 O.OOE+00 O.OOE+00 7.19E+02 NI-65 2.02E+02 2.62E+01 1.20E+01 O.OOE+00 O.OOE+00 O.OOE+00 6.65E+02 CU-64 O.OOE+00 9.08E+01 4.26E+01 O.OOE+00 2.29E+02 0.00E+00 7.74E+03 ZN-65 1.61E+05 5.13E+05 2.32E+05 O.OOE+00 3.43E+05 O.OOE+00 3.23E+05 ZN-69 3.43E+02 6.57E+02 4.57E+01 O.00E+00 4.27E+02 O.OOE+00 9.87E+O0 BR-83 O.OOE+00 O.OOE+00 4.05E+01 O.0OE+O0 O.OOE+00 O.OOE+00 5.84E+01 BR-84 O.OOE+00 O.OOE+00 5.25E+01 O.OOE+00 0.00E+00 O.OOE+00 4.13E-04 BR-85 O.OOE+00 0.OOE+OO 2.16E+00 O.0OE+OO O.OOE+00 O.OOE+00 O.OOE+00 RB-86 O.OOE+00 1.01E+05 4.72E+04 O.OOE+00 O.OOE+00 O.OOE+00 2.OOE+04 RB-88 O.OOE+00 2.91E+02 1.54E+02 O.OOE+00 O.OOE+00 O.OOE+00 4.02E-09 RB-89 O.OOE+00 1.93E+02 1.35E+02 O.0OE+OO O.OOE+00 O.OOE+00 1.12E-11 SR-89 2.57E+04 O.OOE+00 7.37E+02 O.0OE+OO O.OOE+00 O.OOE+00 4.12E+03 SR-90 6.32E+05 0.OOE+OO 1.55E+05 O.OOE+00 O.OOE+00 O.OOE+00 1.82E+04 SR-91 4.72E+02 0.06E+00 1.91E+01 O.OOE+00 O.OOE+00 O.OOE+00 :2.25E+03 SR-92 1.79E+02 O.OOE+00 7.75E+00 O.OOE+00 O.OOE+00 O.OOE+00 3.55E+03 Y-90 6.07E+00 0.OOE+OO 1.63E-01 O.OOE+00 O.OOE+00 O.OOE+00 6.43E+04 Y-91M 5.73E-02 O.OOE+00 2.22E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.68E-01 Y-91 8.89E+01 O.OOE+00 2.38E+00 O.OOE+00 O.OOE+00 O.OOE+00 4.89E+04 Y-92 5.33E-01 0.0OE+OO 1.56E-02 O.OOE+00 O.O0E+OO O.O0E+OO 9.33E+03 Y-93 1.69E+00 0.OOE+OO 4.67E-02 O.OOE+00 O.OOE+00 O.OOE+00 5.36E+04 ZR-95 1.63E+00 5.22E-01 3.54E-01 O.OOE+00 8.20E-01 O.OOE+00 1.66E+03 ZR-97 9.OOE-02 1.82E-02 8.30E-03 O.OOE+00 2.74E-02 O.OOE+00 5.63E+03 NB-95 4.83E+00 2.69E+00 1.44E+00 O.OOE+00 2.65E+00 O.OOE+00 1.63E+04 MO-99 O.OOE+00 1.28E+02 2.43E+01 O.OOE+00 2.90E+02 O.OOE+00 2.97E+02 TC-99M 1.59E-02 4.50E-02 5.73E-01 O.OOE+00 6.84E-01 2.21E-02 2.66E+01 TC-101 1.64E-02 2.36E-02 2.32E-01 O.OOE+00 4.25E-01 1.21E-02 7.09E-14 RU-103 1.10E+02 O.OOE+00 4.74E+01 O.OOE+00 4.20E+02 O.OOE+00 1.28E+04 RU-105 9.16E+00 O.OOE+00 3.62E+00 O.OOE+00 1.18E+02 O.OOE+00 5.60E+03 RU-106 1.64E+03 O.OOE+00 2.07E+02 O.OOE+00 3.16E+03 O.OOE+00 1.06E+05 AG-110M 4.58E+02 4.23E+02 2.51E+02 O.OOE+00 8.32E+02 O.OOE+00 1.73E+05 SB-122 3.47E+01 7.99E-01 1.20E+01 5.38E-01 O.OOE+00 2.08E+01 1.32E+04 jtizi SB-124 4.86E+02 9.20E+00 1.91E+02 1.18E+00 O.OOE+00 3.79E+02 1.38E+04 SB-125 3.11E+02 3.47E+00 7.40E+01 3.16E-01 O.OOE+00 2.40E+02 3.42E+03 2-14

Part 11 ODCM - Rev. 15 Table 2 - 1 Site Related Adult Ingestion Dose Coruuitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/iul TOT BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE BONE LIVER 8.19E+02 1.11E+04 0.OOE+O0 l.09E+04 TE-125M 2.72E+03 9.87E+02 3.65E+02 1.76E+03 2.79E+04 O.OOE+O0 2.31E+04 TE-127M 6.88E+03 2.46E+03 8.38E+02 2.42E+01 8.28E+01 4.55E+02 0.OOE+0O 8.82E+03 TE-127 1.12E+02 4.01E+01 4.01E+03 4.88E+04 0.OOE+OO 5.88E+04 TE-129M 1.17E+04 4.36E+03 1.85E+03 2.45E+01 1.34E+02 0.OOE+0O 2.41E+01 TE-129 3.19E+01 1.20E+01 .7.77E+00 1.36E+03 8.71E+03 0.OOE+00 8.53E+04 TE-131M 1.76E+03 8.60E+02 7.16E+02 1.65E+01 8.77E+01 0.OOE+00 2.83E+00 TE-131 2.OOE+01 8.36E+00 6.32E+00 1.83E+03 1.60E+04 0.OOE+0O 7.83E+04 TE-132 2.56E+03 1.66E+03 1.55E+03 1.22E+04 2.24E+02 0.OOE+O0 1.24E+02 1-130 4.88E+01 1.44E+02 5.68E+01 1.26E+05 6.58E+02 0.OOE+00 1.01E+02 1-131 2.68E+02 3.84E+02 2.20E+02 1.23E+03 5.58E+01 0.OOE+00 6.58E+00 1-132 1.31E+01 3.50E+01 1.23E+01 2.34E+04 2.78E+02 0.OOE+0O 1.43E+02 1-133 9.16E+01 1.59E+02 4.86E+01 3.22E+02 2.95E+01 0.OOE+00 1.62E-02 1-134 6.84E+00 1.86E+01 6.64E+00 4.93E+03 1.20E+02 O.OOE+00 8.45E+01 1-135 2.86E+01 7.48E+01 2.76E+01 8.04E+04 0.OOE+O0 3.18E+04 1.06E+04 1.72E+03 CS-134 4.14E+04 9.84E+04 1.23E+04 O.OOE+00 9.51E+03 1.30E+03 1.94E+03 CS-136 4.33E+03 1.71E+04 0.OOE+00 2.46E+04 8.18E+03 1.40E+03 CS-137 5.30E+04 7.25E+04 4.75E+04 0.OOE+00 5.33E+01 5.26E+00 3.09E-04 CS-138 3.67E+01 7.25E+01 3.59E+01 0.OOE+00 4.31E-03 2.61E-03 1.15E+01 BA-139 6.47E+00 4.61E-03 1.89E-01 8.87E+01 0.OOE+00 5.78E-01 9.73E-01 2.79E+03 BA-140 1.35E+03 1.70E+00 0.OOE+O0 2.21E-03 1.35E-03 1.48E-09 BA-141 3.14E+00 2.37E-03 1.06E-01 0.OOE+0O 1.23E-03 8.27E-04 2.OOE-18 BA-142 1.42E+00 1.46E-03 8.93E-02 0.OOE+00 0.OOE+O0 O.OOE+00 5.83E+04 LA-140 1.58E+00 7.95E-01 2.10E-01 0.OOE+0O 0.OOE+O0 O.OOE+00 2.68E+02 LA-142 8.07E-02 3.67E-02 9.15E-03 0.OOE+00 l1.01E+00 O.OOE+OO 8-35E+03 CE-141 3.23E+00 2.18E+00 2.48E-01 0.OOE+0O 1.85E-01 0.OOE+O0 1.57E+04 CE-143 5.69E-01 4.21E+I02 4.66E-02 0.OOE+00 4.17E4-01 O.OOE+0O 5.69E+04 CE-144 1.68E+02 7.04E+01 9.04E+i00 0.OOE+00 1.34E+00 0.OOE+00 2.54E+04 PR-143 5.80E+00 2.33E+00 2.88E-01 9.65E-04 0.OOE+00 4.45E-03 O.OOE+00 2.73E-09 PR-144 1.90E-02 7.88E-03 2.74E-01 O.OOE+00 2.68E+00 O.OOE+O0 2.20E+04 ND-147 3.97E+00 4.59E+00 0.OOE+00 0.OOE+00 0.OOE+O0 8.16E+04 W-187 2.98E+02 2.49E+02 8.71E+01 0.OOE+00 1.08E-02 0.OOE+O0 7.12E+02 NP-239 3.53E-02 3.47E-03 1.91E-03 0.+OOE+00 0.OOE+00 0.OOE+O0 0.OOE+O0 K-40 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.07E+03 CO-57 0.OOE+00 1.21E+02 2.01E+02 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 SR-85 0.OOE+O0 0.OOE+00 0.OOE+00

.Y-88 0.OOE+O0 0.OOE+00 O.OOE+00 O.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+0O 0.OOE+O0 O.OOE+00 0.OOE+00 NB-94 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 1.20E-02 0.OOE+00 3.78E+01 NB-97 4.05E-02 1.02E-02 3.74E-03 O.OOE+O0 0.OOE-I-0 0.OOE+00 O.OOE+00 CD-109 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+06 0.00E+00- 0.OOE+OO 0.OOE+00 SN-113 0..OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BA-133 0.OOE+O0 0.OOE+0O 0.OOE+00 2.88E+01 2.08E+02 0.OOE+00 3.65E-02 TE-134 3.29E+01 2.15E+01 1.32E+01 0.OOE+00 0.OOE+O0 O.OOE+00 0.OOE+00 CE-139 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE-I00 0.OOE+00 HG-203 0.OOE+00 0.OOE+O0 O.OOE+OO 2-15

Part II ODCM - Rev. 15 Table 2 - 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml N----------------------------------

ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 BE-7 3.58E-01 8.02E-01 4.01E-01 0.00E+00 8.50E-01 0.00E+00 9.76E+01 NA-24 4.20E+02 4.20E+02 4.20E+02 4 .20E+02 4.20E+02 4.20E+02 4.20E+02 P-32 5.4 OE+07 3.35E+06 2.09E+06 0.00E+00 0.OOE+00 0.00E+00 4.54E+06 0.OOE+00 0. OOE+00 4.44E+00 2.47E+00 9.73E-01 6.34E+00 7. 46E+02 CR-51 MN-54 0.OOE+00 5. 33E+03 1.06E+03 0.OOE+00 1.59E+03 0.0OE+00 1.09E+04 MN-56 0.OOE+00 1. 43E+02 2.54E+01 0.OOE+00 1.81E+02 0.OOE+00 9. 40E+03 FE-55 3.35E+04 2.37E+04 5.54E+03 0.OOE+00 0.OOE+00 1.51E+04 1.03E+04 5.20E+04 1.21E+05 4.69E+04 0.OOE+00 0.OOE+00 3.83E+04 2.87E+05 FE-59 0.OOE+00 5. 10E+02 1.18E+03 0.OOE+00 0.OOE+00 0.OOE+00 7.04E+03 CO-58 0.OOE+00 1. 48E+03 3.32E+03 0.OOE+00 0.OOE+00 0.OOE+00 1. 92E+04 CO-60 5.15E+04 3.64E+03 1.75E+03 0.OOE+00 0.OOE+00 0.00E+00 5.7 9E+02 NI-63 2.18E+02 2.79E+01 1.27E+01 0.00E+00 0.OOE+00 0.O0E+00 1. 51E+03 NI-65 CU-64 0.OOE+00 9.53E+01 4.48E+01 0.00E+00 2.41E+02 0.OOE+00 7.39E+03 ZN-65 1.46E+05 5.07E+05 2.36E+05 0.OOE+00 3.24E+05 0.OOE+00 2.15E+05 3.73E+02 7.10E+02 4.97E+01 0.OOE+00 4.64E+02 0.OOE+00 1.31E+03 ZN-69 0.OOE+00 0.OOE+00 4.41E+01 O.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 BR-83 0.00E+00 0.OOE+00 5.55E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BR-84 0.OOE+00 0.OOE+00 2.34E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BR-85 0.OOE+00 1.09E+05 5.12E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.61E+04 RB-86 0.OOE+00 3.12E+02 1.66E+02 0.OOE+00 0.OOE+00 0.OOE+00 2.67E-05 RB-88 0.OOE+00 2.01E+02 1. 42E+02 0.OOE+00 0.OOE+00 O.OOE+00 3.09E-07 RB-89 2.79E+04 0. OOE+00 8.OOE+02 0.OOE+00 0.OOE+00 0.OOE+00 3.33E+03 SR-89 5.27E+05 0.OOE+00 1.30E+05 0.OOE+00 0.OOE+00 0.OOE+00 1.48E+04 SR-90 5.12E+02 0. 00E+00 2.04E+01 0.OOE+00 0.OOE+00 0. OOE+00 2.32E+03 SR-91 1.94E+02 0.OOE+00 8.25E+00 0.OOE+00 0.OOE+00 0. OOE+00 4.93E+03 SR-92 6.57E+00 0.OOE+00 1.77E-01 0.OOE+00 0.OOE+00 0.OOE+00 5.42E+04 Y-90 6.18E-02 0.OOE+00 2.36E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.92E+00 Y-91M 9.64E+01 0.OOE+00 2.58E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.95E+04 Y-91 5.80E-01 0.OOE+00 1.68E-02 0.OOE+00 0.OOE+00 0.OOE+00 1.59E+04 Y-92 Y-93 1.84E+00 0.OOE+00 5.03E-02 0.OOE+00 0.OOE+00 0.OOE+00 5. 61E+04 ZR-95 1.68E+00 5.29E-01 3.64E-01 0.OOE+00 7.78E-01 0.00E+00 1.22E+03

9. 65E-02 1. 91E-02 8.80E-03 0.OOE+00 2.90E-02 0.OOE+00 5.17E+03 ZR-97 NB-95 4.86E+00 2.70E+00 1.48E+00 0.OOE+00 2.61E+00 0.OOE+00 1.15E+04 MO-99 0.OOE+00 1.36E+02 2.60E+01 0.OOE+00 3.12E+02 0.OOE+00 2.44E+02 TC-99M 1.63E-02 4.55E-02 5.89E-01 0.OOE+00 6.77E-01 2.52E-02 2.98E+01 TC-101 1.77E-02 2.51E-02 2.47E-01 0.OOE+00 4. 55E-01 1.53E-02 4.30E-09 4.93E+01 0.OOE+00 4.06E+02 0.OOE+00 9.63E+03 RU-103 1.15E+02 0.OOE+00 3.82E+00 0.OOE+00 1.24E+02 0.OOE+00 7.96E+03 RU-105 9.85E+00 0.OOE+00 RU-106 1.77E+03 0.OOE+00 2.23E+02 0.OOE+00 3.42E+03 0.00E+00 B.50E+04 0.OOE+00 8.04E+02 0.OOE+00 1.18E+05 AG-110M 4.45E+02 4.22E+02 2.56E+02 halli 8.47E-01 1.27E+01 5.53E-01 0.OOE+00 2.72E+01 9.13E+03 SB-122 4.35E+01 0.OOE+00 4.45E+02 1.03E+04 SB-124 5.09E+02 9.40E+00 1.99E+02 1.16E+00 0.OOE+00 2.85E+02 2.53E+03 SB-125 3.27E+02 3.58E+00 7.64E+01 3.11E-01 2-16

Part II ODCM - Rev. 15 Table 2 - 2 Site Related Teen Ingestion Dose Conmitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.96E+03 1.07E+03 3.96E+02 8.28E+02 0.00E+00 0.00E+O0 8.75E+03 TE-127M 7.48E+03 2.65E+03 8.90E+02 1.78E+03 3.03E+04 0. 0OE+O0 1.87E+04 TE-127 1.22E+02 4.33E+01 2.63E+01 8.4 4E+01 4. 95E+02 0.001E+O0 9.44E+03 TE-129M 1.26E+04 4.68E+03 2.OOE+03 4.07E+03 5.28E+04 0.0OE+00 4.74E+04 TE-129 3.47E+01 1.29E+01 8.44E+00 2.48E+01 1.46E+02 0.00E+00 1. 90E+02 TE-131M 1.89E+03 9.06E+02 7.55E+02 1.36E+03 9.44E+03 0.0OE+00 7.27E+04 TE-131 2.16E+01 8.90E+00 6.75E+00 1.66E+01 9.44E+01 0.00E+00 1. 77E+00 TE-132 2.70E+03 1.71E+03 1. 61E+03 1.80E+03 1. 64E+04 0.OOE+00 5.42E+04 1-130 5.06E+01 1.46E+02 5.84E+01 1.19E+04 2.25E+02 0.001E+00 1. 12E+02 1-131 2.87E+02 4.02E+02 2.16E+02 1.17E+05 6.92E+02 0.00E+O0 7. 95E+01 1-132 1.37E+01 3.58E+01 1.29E+01 1.21E+03 5.64E+01 0.001E+00 1. 56E+01 1-133 9.87E+01 1.67E+02 5.11E+01 2.34E+04 2.94E+02 0.001E+O0 1. 27E+02 1-134 7.17E+00 1. 90E+01 6.82E+00 3. 17E+02 2.99E+01 0. 0OE+O0 2.50E-01 1-135 2.99E+01 7 .71E+01 2.86E+01 4.96E+03 1.22E+02 0.001E+O0 8.54E+01 CS-134 4.24E+04 9.97E+04 4. 63E+04 0.00E+00 3.17E+04 1.21E+04 1.24E+03 CS-136 4.35E+03 1.71E+04 1.15E+04 0.001E+00 9.32E+03 1.47E+03 1.38E+03 CS-137 5. 67E+04 7.54E+04 2.63E+04 0.OOE+00 2.57E+04 9. 97E+03 1.07E+03 CS-138 3. 93E+01 7.54E+01 3;77E+01 0.OOE+00 5.57E+01 6.48E+00 3.42E-02 BA-139 7.05E+00 4 .96E-03 2.05E-01 0.001E+00 4. 67E-03 3.42E-03 6.28E+01 BA-140 1.44E+03 1.76E+00 9.28E+01 0.OOE+00 5.98E-01 1.19E+00 2.22E+03 BA-141 3.40E+00 2.54E-03 1.14E-01 0.00E+00 2.36E-03 1.74E-03 7.25E-06 BA-142 1.52E+00 1 52E-03 9.33E-02 0.001E+00 1.28E-03 1.01E-03 4. 65E-12 LA-140 1.67E+00 8.20E-01 2.18E-01 0. OOE+00 0.001E+00 0.00E+00 4.71E+04 LA-142 8.58E-02 3.81E-02 9.49E-03 0.001E+00 0.001E+00 0.0OE+O0 1.16E+03 CE-141 3. 49E+00 2.33E+00 2.67E-01 0. OOE+00 1.10E+00 0.001E+00 6.66E+03 CE-143 6.16E-01 4.48E+02 5.01E-02 0.OOE+00 2.01E-01 0.00E+O0 1.35E+04 CE-144 1.82E+02 7.55E+01 9.80E+00 0.00E+00 4.51E+01 0.00E+00 4.59E+04 PR-143 6.28E+00 2.51E+00 3.13E-01 0.OOE+00 1.46E+00 0.OOE+00 2.07E+04 PR-144 2.06E-02 8.44E-03 1.05E-03 0.00E+00 4.84E-03 0.00E+00 2.27E-05 ND-147 4.50E+00 4.8 9E+00 2. 93E-01 0.00E+00 2.87E+00 0.00E+00 1.7 6E+04 W-187 3.22E+02 2.62E+02 9.19E+01 0.00E+00 0.OOE+00 0.00E+00 7.10E+04 NP-239 3. 98E-02 3.75E-03 2.08E-03 0.00E+00 1.18E-02 0.OOE+00 6. 03E+02 K-40 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.0OE+00 0.0OE+00 CO-57 0.OOE+00 1.25E+02 2.10E+02 0.00E+00 0.OOE+00 0.00E+00 2.33E+03 SR-85 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.001E+00 0.001E+00 0.00E+00 Y-88 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.001E+00 0.00 E+00 0.OOE+00 NB-94 0.OOE+00 0.001E+00 0.OOE+00 0.00E+00 0.OOE+00 0.0OE+0O 0.00E+OO NB-97 4.36E-02 1.08E-02 3.95E-03 0.00E+00 1.27E-02 0.001E+00 2.58E+02 CD-109 0.OOE+00 0.001E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 O.OOE+00 SN-113 0.00E+00 0.001E+00 0.00E+00 0.00E+00 0.001E+00 0.OOE+00 0.0OE+00 BA-133 0.OOE+00 0.001E+00 0.OOE+00 0.OOE+00 0.001E+00 0.001E+00 0.OOE+00 TE-134 3.46E+01 2.22E+01 2.32E+01 2.84E+01 2.12E+02 0.00E+00 1.28E+00 CE-139 0.OOE+00 0.001E+00 O.OOE+00 0.OOE+00 0.001E+00 0.00E+00 0.0OE+0O HG-203 0.OOE+00 0.OOE+00 0.OOE+00 0.001E+00 0.001E+00 0.00E+00 0. OOE+00 2-17

Part I1 ODCM - Rev. 15 Table 2 - 3 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml L-------------------------------------

ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI

--- --------------------------------- 7---------------------------------------

0.OOE+00 1.81E-01 1.81E-01 1.81E-01 1.81E-01 1.81E-01 1.81E-01 H-3 4.52E+01 4.77E-01 8.08E-01 5.33E-01 0.OOE+00 7. 96E-01 0. OOE+00 BE-7 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 NA-24 1.93E+06 2.69E+06 0.OOE+00 0.OOE+00 0.OOE+00 P-32 6.98E+07 3.27E+06 0.OOE+00 0.00E+00 4.86E+00 2.70E+00 7.37E-01 4. 92E+00 2.58E+02 CR-51 3.53E+03 MN-54 0.OOE+00 4.20E+03 1.12E+03 0.00E+00 1.18E+03 0. OOE+00 1.31E+02 2.96E+01 0. OOE+00 1.59E+02 0.OOE+00 1.90E+04 MN-56 0.OOE+00 7.48E+03 0.OOE+00 0.OOE+00 1.37E+04 4.47E+03 FE-55 4.55E+04 2.42E+04 1.06E+05 5.27E+04 0.00E+00 0.OOE+00 3.07E+04 1.10E+05 FE-59 6.53E+04 1.29E+03 0.OOE+00 0.OOE+00 0.OOE+00 2.45E+03 CO-58 0.OOE+00 4.20E+02 6.84E+03 CO-60 0.OOE+00 1.23E+03 3.64E+03 0.OOE+00 0.OOE+00 0. OOE+00 2.33E+03 0.OOE+00 0.OOE+00 0.OOE+00 2.47E+02 NI-63 6.85E+04 3.67E+03 2.66E+01 1.55E+01 O.OOE+00 0.OOE+00 .0.00E+00 3.26E+03 NI-65 2.83E+02 O.OOE+00 9.05E+01 5.47E+01 0.OOE+00 2.19E+02 0.OOE+00 4.25E+03 CU-64 0.00E+00 7.23E+04 1.55E+05 4.12E+05 2.56E+05 0.00E+00 2.59E+05 ZN- 65 0.OOE+00 4.50E+04 4.94E+02 7.14E+02 6.60E+01 0.OOE+00 4.33E+02 ZN-69 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.67E+01 0.OOE+00 0.OOE+00 BR-83 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 6.56E+01 0. OOE+00 0.OOE+00 BR-84 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 3.02E+00 0.00E+00 0.OOE+00 BR-85 0. 00E+00 6.80E+03 0.OOE+00 1.06E+05 6.50E+04 0.OOE+00 0.OOE+00 RB-86 1. 47E+01 3.OOE+02 2.08E+02 0.OOE+00 0.OOE+00 0.OOE+00 RB-88 0.OOE+00 1.61E+00 1.64E+02 0.OOE+00 0. OOE+00 0.OOE+00 RB-89 0.OOE+00 1.85E+02 0.OOE+00 1.04E+03 0.OOE+00 0.OOE+00 0.OOE+00 1.41E+03 SR-89 3.63E+04 0.OOE+00 1.19E+05 0.OOE+00 0.OOE+00 0.00E+00 6.30E+03 SR-90 4.68E+05 2.49E+01 0.OOE+00 0.OOE+00 0.OOE+00 1.46E+03 SR-91 6.60E+02 0.OOE+00 9.96E+00 0.OOE+00 0.00E+00 0.OOE+00 4.70E+03 SR-92 2.48E+02 0.OOE+00 0.OOE+00 2.35E-01 0.OOE+00 0.OOE+00 0.OOE+00 2.50E+04 Y-90 8.79E+00 0.OOE+00 0. OE+00 1.60E+02 Y-91M 8.17E-02 0.OOE+00 2.97E-03 0.OOE+00 1.71E+04 0.OOE+00 3.44E+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91 1.29E+02 2.20E-02 0.OOE+00 0.OOE+00 0.OOE+00 2.22E+04 Y-92 7.70E-01 0.OOE+00 0.OOE+00 6. 69E-02 0.OOE+00 0. OOE+00 0.OOE+00 3.63E+04 Y-93 2.44E+00 4.11E-01 0.OOE+00 6. 62E-01 0.OOE+00 4.82E+02 ZR-95 2.10E+00 4.62E-01 1.83E-02 1.08E-02 0.OOE+00 2.63E-02 0. OOE+00 2.77E+03 ZR-97 1.27E-01 0.OOE+00 2.10E+00 0. OOE+00 4.14E+03 NB-95 5.75E+00 2.24E+00 1.60E+00 1.31E+02 3.23E+01 0.OOE+00 2.7 9E+02 0.OOE+00 1.08E+02 MO-99 0.OOE+00 0.OOE+00 5.66E-01 1. 98E-02 2.22E+01 TC-99M 1.99E-02 3.89E-02 6.46E-01 7. 66E-02 3.06E-01 0.OOE+00 4. 11E-01 1.27E-02 TC-101 2.30E-02 2.41E-02 3.82E+03 5.67E+01 0.OOE+00 3.72E+02 0.OOE+00 RU-103 1.48E+02 0.OOE+00 8.50E+03 1.30E+01 0.OOE+00 4.73E+00 0.OOE+00 1.15E+02 0.OOE+00 RU-105 3. 68E+04 RU-106 2.36E+03 0.OOE+00 2.95E+02 AG-IIOM 5.24E+02 3.54E+02 2.83E+02 0.OOE+00 0.OOE+00 3.19E+03 6.59E+02 0.OOE+00 0.OOE+00 4.21E+04 Itxj 8.56E-01 1.70E+01 7.43E-01 0.60E+00 2.36E+01 4.46E+03 SB-122 5.80E+01 3.63E+02 4.09E+03 SB-124 6.55E+02 8.50E+00 2.29E+02 1.44E+00 0.OOE+00 8.85E+01 3.91E-01 0.OOE+00 2.35E+02 1.01E+03 SB-125 4.22E+02 3.25E+00 2-18

Part II ODCM - Rev. 15 Table 2 - 3 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE BONE TE-125M 3.8 1E+03 1.03E+03 5.08E+02 1.07E+03 O.00E+00 0.0OE+O0 3.68E+03 2.60E+03 1.15E+03 2.31E+03 2.76E+04 0.OOE+00 7.83E+03 TE-127M 9.67E+03 4.25E+01 3.38E+01 1.0 9E+02 4.48E+02 0.OOE+00 6.15E+03 TE-127 1.58E+02 4.55E+03 2.53E+03 5.25E+03 4.78E+04 0.OOE+00 1.99E+04 TE-129M 1.63E+04 1.25E+01 1.06E+01 3.20E+01 1.31E+02 0.0OE+00 2.79E+03 TE-129 4.48E+01 8.86E+02 1.71E+03 8.06E+03 0.OOE+00 3.38E+04 TE-131M 2.41E+03 8.33E+02 8.46E+00 8.26E+00 2.12E+01 8.40E+01 0.0OE+0O 1.46E+02 TE-131 2.78E+01 1.50E+03 1.81E+03 2.18E+03 1.39E+04 0. 0OE+O0 0.00E+00 1.51E+04 TE-132 3.38E+03 1.27E+02 6.54E+01 1.40E+04 1. 90E+02 O.0OE+O0 5.94E+01 1-130 6.28E+01 3.31E+01 3.70E+02 3.72E+02 2.12E+02 1.23E+05 6.11E+02 0.0OE+00 1-131 3.72E+01 1.72E+01 3.16E+01 1.45E+01 1.47E+03 4.84E+01 0.OOE+00 1-132 6.35E+01 1.27E+02 1.58E+02 5.96E+01 2. 93E+04 2.63E+02 0.OOE+00 1-133 1.1lE+01 9.02E+00 1.67E+01 7.70E+00 3.85E+02 2.56E+01 1-134 0.OOE+O0 5.16E+01 3.77E+01 6.78E+01 3.21E+01 6.OOE+03 1.04E+02 1-135 9.39E+03 4.55E+02 5.15E+04 8.44E+04 1.78E+04 0.OOE+00 2.62E+04 CS-134 1.13E+03 4. 99E+02 5.17E+03 1.42E+04 9.19E+03 0.OOE+00 7.56E+03 CS-136 8.07E+03 4.31E+02 7.19E+04 6.88E+04 1.02E+04 0. 00E+00 2.24E+04 CS-137 5.28E+00 3.21E+01 5.01E+01 6.97E+01 4.42E+01 0. OOE+00 4. 90E+01 CS-138 2.93E-03 5.39E+02 9.34E+00 4.99E-03 2.71E-01 0. 00E+00 4.35E-03 BA-139 9.79E-01 9.50E+02 1.87E+03 1.64E+00 1.09E+02 0.OOE+00 5.35E-01 BA-140 1.48E-02 2.57E+00 4.51E+00 2.53E-03 1.47E-01 0.0OE+00 2.19E-03 BA-141 8.35E-04 2.57E-02

1. 97E+00 1.42E-03 1.10E-01 0.OOE+00 1.15E-03 BA-142 0.00E+00 2.1OE+04 2.16E+00 7.55E-01 2.54E-01 0.OOE+00 0.O0E+00 LA-140 0.OOE+00 7.08E+03 1.12E-01 3.57E-02 1.12E-02 0.OOE+00 0.0OE+00 LA-142 0.OOE+00 2. 90E+03 4.65E+00 2.32E+00 3.45E-01 0.OOE+00 1.02E+00 CE-141 4.44E+02 6.44E-02 0.OOE+00 1.86E-01 0.00E+OO 6.51E+03 CE-143 8.19E-01

7. 64E+01 1.30E+01 0. 0OE+00 4.23E+01 0.00E+O0 1.99E+04 CE-144 2.44E+01 2.52E+00 4.17E-01 0.OOE+00 1.37E+00 0.00E+00 9.06E+03 PR-143 8.40E+00 1.84E+01 8.53E-03 1.39E-03 0.OOE+00 4.51E-03 0.OOE+00 PR-144 2.7 6E-02 4.83E+00 3.74E-01 0.OOE+00 2.65E+00 0.00E+O0 7.65E+03 ND-147 5.96E+00 3.4 OE+04 2.42E+02 1.08E+02 0.OOE+00 0.OOE+00 0.O0E+00 W-187 4.08E+02 2.60E-03 0.0OE+00 1. 07E-02 0.O0E+00 2.74E+02 NP-239 5.15E-02 3.70E-03 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 K-40 0.OOE+00 0.00E+00 1.15E+02 2.33E+02 0.OOE+00 0.0OE+00 0.00E+00 9.43E+02 CO-57 0.O0E+00 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 SR-85 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 O.0OE+00 Y-88 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 NB-94 0.OOE+00 3.09E+03 1.OOE-02 4.68E-03 0.OOE+00 1.11E-02 0.OOE+00 NB-97 5.55E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.O0E+OO 0.OOE+OO CD-109 0.O0E+0O 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.0OE+00 SN-113 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.O0E+OO 0.0OE+00 BA-133 0.OOE+00 1. 97E+02 1.94E+01 2.59E+01 3.41E+01 1.80E+02 0.OOE+00 TE-134 4.31E+01 0.OOE+00 0.OOE+00 0.0OE+00 O.OOE+00 0.OOE+00 0.0OE+O0 CE-139 0.OOE+00 o OOE+00 0.OOE+00 0.OOE+00 0. 00E+OO 0.OOE+00 0.OOE+00 HG-203 0.OOE+00 2-19

Part 11 ODCM - Rev. 15 Table 2-4 Bjo-Accumulation Factors for Liquid Effluent Isotopes (pci/kg per pCi/liter)

Freshwater Saltwater I Freshwater Saltwater ISOTOPE Fish Invertebrates i ISOTOPE Fish Invertebrates BFi Bli I BFi Bli

-- - - - - I------------------------------------

H- 3 9.OOOE-01 9.300E-01 TE-1 25M 4 . OOOE+02 1.OOOE+02 BE-7 2. OOOE+00 2. OOOE+02 TE-127M 4 .OOOE+02 1 .OOOE+02 NA-24 1 . OOOE+02 1. 900E-01 TE-127 4. OOOE+02 1 .OOOE+02 P-32 1.000OE405 3. OOOE+04 TE-12 9M 4. OOOE+02 1. OOOE+02 CR-51 2. OOOE+02 2. OOOE+03 TE-129 4. OOOE+02 1 . OOOE+02 M'N-54 4 . OOOE+02 4 . OOOE+02 TE-131M4 4. OOOE+02 1 .OOOE+02 MN1-56 4.000OE402 4 . OOOE+02 TE-1 31 4. OOOE+02 1 . OOOE+02 FE-S55 1.OOOE+02 2. OOOE+04 TE-132 4. OOOE+02 1 .OOOE+02 FE-59 1.OOOE+02 2.OOOE+04 1-130 1. 500E+01 5 .OOOE+01 co-5B 5.OOOE+01 1. OOOE+03 1-131 1. 500E+01 5 .OOOE+01 CO-60 5. OOOE+01 1. OOOE+03 1-132 1. 500E+01 5.OOOE+01 NI1-63 1.OOOE+02 2+.500E+02 1-133 1.500E+01 5.OOOE+01 NI1-65 1.OOOE+02 2. 500E+02 1-134 1.500E+01 5. OOOE+01 CU- 64 5. OOOE+01 1.700E+03 1-135 1.500E+01 5. OOOE+01 ZN-65 2. OOOE+03 5. OOOE+04 CS-134 2.240E+02 2.240E+02 ZN-69 2. OOOE+03 5. OOOE+04 CS-136 2. 240E+02 2.240E+02 BR- 83 4 .200E+02 3. 100E+00 CS-137 2.240E+02 2 .240E+02 BR-84 4.200E+02 3. 100E+00 CS-138 2. 240E+02 2 .240E+02 BR-85 4 .200E+02 3. 100E+00 BA- 139 4 i OOOE+00 1.OOOE+02 RB-8 6 2.ObOOE+03 1.700OE+01 BA- 140 4 .OOOE+00 1.OOOE+02 R~B-88 2 . OOOE+03 1.700E+01 BA-14 1 4. OOOE+00 1 .OOOE+02 RB-89 2 . OOOE+03 1.700E+01 BA-1 42 4. OOOE+00 1 .OOOE+02 SR-89 3. OOOE+01 2.OOOE+01 LA-14 0 2. 500E+01 1.OOOE+03 SR-90 3 . OOOE+01 2. OOOE+01 LA-14 2 2.500E+01 1. OOOE+03 SR-91 3.OOOE+01 2.OOOE+01 CE-141 1.OOOE+00 6.OOOE+02 SR-92 3. OOOE+01 2.OOOE+01 CE-1 43 1. OOOE+00 6.OOOE+02 Y-90 2. 50OE+01 1.OOOE+03 CE-1 44 1. OOOE+00 6.OOOE+02 Y-91M 2.500E+01 1.OOOE+03 PR-i143 2. 500E+01 1 .OOOE+03 Y-91 2.500OE+01 1. OOOE+03 PR-144 2 .500E+01 1.OOOE+03 Y-92 2. 500E4-01 1. OOOE+03 N4D-147 2.500OE+01 l.OOOE+03 Y- 93 2. 500E+01 1. OOOE+03 W-187 1.200E+03 3.OOOE+01 ZR-95 3.300E+00 B.OOOE+01 NP-239 1.OOOE+01 1 .OOOE+01 ZR-97 3.300E+00 8. OOOE+01 K- 40 0. OOOE+00 0. OOOE+00 NB-95 3. OOOE+02 1. OOOE+02 CO-57 5. OOOE+01 1. OOOE+03 MO- 99 1. 000E40l 1.OOOE+01 SR- 85 0.OOOE+00 0. OOOE+00 TC- 99M4 1. 500E+01 5.OOOE+01 Y- 88 0.OOOE+00 0 .OOOE+00 TC-101 1. 500E+01 5. OOOE+01 NB-94 3. OOOE+02 1. OOOE+02 RU-10 3 1.OOOE+01 1.OOOE+03 NB-97 3. OOOE+02 1.OOOE+02 RU-105 1.OOOE+01 1.OOOE+03 CD-1 09 0. OOOE+00 0.OOOE+00 RU-106 1.OOOE+01 1. OOOE+03 SN-113 0.OOOE+00 0. OOOE+00 BA- 13 3 0.OOOE+00 0. OOOE+00 AG-110M SB-122 2.300E+00 1 . OOOE+00

5. OOOE+03

3. OOOE+02 TE-13 4 4. OOOE+02 1.OOOE+02 I M~II 1 . OOOE+00 3.OOOE+02 CE-139 0. OOOE+00 0.OOOE+00 SB-124 SB-125 1.OOOE+00 3. OOOE+02 HG-203 0. OOOE+00 0.OOOE+00 Bio-Accumulation Factors and DFi'Is for N~oble Gases - 0 2-20

ODCM - Rev. 15 Part II Figure 2-1 II2/

Radioactive Liquid Waste Effluent System Flow Diagram D

I S

C H

A R

G E

Waste Holdup 1 Waste Tanks Processing C

A N

A L

LI Hudson River 2-21

ODCM - Rev. 15 Part II 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Releases - General Information for gaseous 3.1.1 The surveillance and lower limit of detection requirements of detection Lower limits radioactive effluents are contained in the RECS.

B.

calculations are addressed in ODCM Part II, Appendix Waste Release 3.1.2 A completed and properly authorized Airborne Radioactive from the waste activity Permit shall be issued prior to the release of airborne purge exceeds gas holding system and containment purge. If a containment a continuous, long term 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> in duration then the purge will be considered release for reporting purposes (See Section 3.1.16).

RCi/sec limits 3.1.3 Since Indian Point is a two unit site, the derived instantaneous time-average The delineated in Section 3.2.1 are apportioned to each site. the full dose limits are limits and limits in 3.2.2, 3.2.3, and 3.2.4 are "per reactor" applicable to IP3.

from the Condenser 3.1.4 During Modes 5 and 6, there is no flowpath for a release Effluent in Radiological Air Ejector, and the monthly grab sample described operation without a plant Controls Table 3.4.1-1 is not required. During normal are through the main primary to secondary leak, almost all gaseous releases Administration Building in the Plant Vent. A negligible amount may be identified In the event of extended operation with and Radioactive Machine Shop vents. from both the a primary to secondary leak, low level releases are expected the limits on However, blowdown flash tank vent and condenser air ejector. those for effluent steam generator leakage are much more restrictive than release rate to these various releases. Allocation of portions of the allowable rate is used release release points is not warranted. Ifthe instantaneous 3.3.1 or 3.4.1), then all by (taking advantage of the one hour averaging allowed alarm setpoint per release points will be considered when establishing the ODCM Part II, Section 1.

over two days, a new 3.1.5 For releases that are expected to continue for periods purge release release permit will normally be issued each day. ContainmentGeneral permits may be terminated at the discretion of the Chemistry until the purge is Supervisor (and be considered as a continuous release) will cause the activity that terminated. However, when plant conditions change shall be issued.

in containment to significantly change, a new permit Units 2 and 3 do not 3.1.6 Assurance that the combined gaseous releases from administrative controls exceed Section 3.2.1 limits for the site is provided by between units 2 and 3

(#16) agreed to in the Memorandum of Understanding of the document.

concerning gaseous effluent discharge and the requirements 3-1

Part 11 ODCM - Rev. 15 3.1.7 By mutual agreement with units 2 and 3 Shift Supervisors, one unit can reduce or eliminate discharges for a period of time to allow the other unit to use the full site permissible discharge rate, or a specific portion thereof, for discharge when necessary.

3.1.8 Conservative release rate limitations have been established to aid in controlling time average dose limits. The annual average limit shall normally be used for calculating limitations on discharge. Ifthis limitation unduly restricts an individual release, the quarterly average release rate limit (R.Ci/sec) may be used for the release provided the quarterly time average dose limit will not be exceeded and the Operations Manager or Assistant Operations Manager is in agreement. The instantaneous limit may be used if the Vice President, Operations - IP3 or his Designee is in agreement. The instantaneous limit should be checked by the Chemistry Department when applied.

When the instantaneous limit is applied, the release may be averaged over a one-hour time interval.

3.1.9 Containment Pressure Reliefs Containment pressure reliefs occur frequently enough to be considered continuous releases. Grab samples of containment atmosphere are obtained periodically to ensure the use of accurate mixtures in effluent calculations. To ensure that the release rate will not be exceeded, the containment noble gas monitor (R-12) and the expected flowrate are used to calculate release rates from containment and at the stack effluent. The effluent noble gas monitor in the plant vent is used to verify these calculations.

3.1.10 Composite Particulate Samples One of the following methods will be used to obtain a composite sample:

"* Samples will be taken weekly and integrated monthly; or

"* Samples will be taken weekly and counted together once per month.

3.1.11 Gas Storaae Tank Activity Limit The quantity of radioactivity in each gas storage tank is limited to 50,000 Ci of noble gas, per RECS 2.11. This limit was calculated using the equations from Section 5.6.1 of NUREG 0133 and the following parameters:

Ki = 294 mrem-m3 /jLCi-yr, Xe-1 33 equivalent Table B-1 (RG 1.109)

X/Q = 1.03 x 10" sec/m 3, Indian Point 3 FSAR Qit must be calculated so that the dose is less than 500 mrem in a year:

Qit= (500mrem)

• 3.15E+7 sec/yr (1E6pCi/Ci)(294mrem-m 3 luCi-yr)(1.03E-3 sec/m 3) 3-2

Part II ODCM - Rev. 15 This limit assumes 100% Xe-133 as per NUREG 0133. Utilizing the Ki from an expected mixture during RCS degasification K=gmrem-m3 Ki = 787 me PCi- yr the gas tank conservative administrative limit should be 19,400 curies.

The basis for assuring that accidental gas releases from liquid holdup tanks do not exceed Section 3.2.1 limits, is Technical Specifications 3.4.16 (*< 1 Ci/cc Dose Equivalent Iodine-131 in Reactor Coolant). Using the assumptions discussed in FSAR section 14.2.3, the potential total curies in the liquid holdup tanks is limited to less than the conservative limit for the Gas Storage Tanks (19,400 curies).

3.1.12 Gas Storage Tank Surveillance Requirements There are two methods available to ensure that the activity in the gas storage tank is within the conservative administrative limit (19400 Ci).

1.94E + 4

• lE6pCi/ Ci _ = 1.17E+2 1uCi/cc 525 ft3 *(164.7psiaJ* 2.83E4cc/ft3

1. The total gaseous activity will normally be limited to less than 117 plCi/cc.

Ifthis concentration limit is exceeded, then the contents of the tank will be monitored and actions taken to ensure the 19,400 curie per tank limit is not exceeded.

2. The waste gas line monitor (R-20) reads in j.Ci/cc. It allows for control of waste gas tank curie content by limiting the input concentration to 117 JACi/cc, thereby limiting the curies to 19,400.

Large gas decay tanks on fill and CVCS tanks (which are indicative of the gas mixture in or from the reuse system) are continuously monitored for H2 and 02 through in-line instrumentation. With either in-line instrument out of service, a grab sample of the tank on receipt shall be taken daily, unless in degassing operation, when the periodicity is every four hours.

Other primary system tank cover gases can be manually directed through these instruments for individual samples.

3.1.13 The normal flow rate measurement for the Radioactive Machine Shop (RAMS) and the Plant Vent (PV) is obtained from the installed process monitor. When the instrument is out of service, the estimated flow from the RAMS is obtained by summing each operable exhaust fan's design flow rate. Estimated flow from the PV is obtained similarly, or from an alternate flow instrument (still considered an estimate). The design system flow rate of 12500 CFM is used for Administration Building ventilation. The process flow rate monitor surveillance requirements specified in RECS Table 3.2-1 are not applicable for the Administration Building, nor are they applicable when the RAMS or PV installed instruments are out of service and rated fan flow is used.

3-3

Part 11 ODCM - Rev. 15 3.1.14 The activity released via the blowdown flash tank vent is determined by obtaining the steam generator blowdown Tritium, Noble Gas, and Iodine activity, partitioned per Regulatory Guide 1.42 "Interim Licensing Policy On As Low As Practicable for Gaseous Radioiodine Releases from Light Water Cooled Nuclear Power Reactors" (from NUREG 0472, Rev3, DRAFT 6, TABLE 3.3-13), or Reference 4, "An Evaluation to Demonstrate the Compliance of the Indian Point Reactors with the Design Objectives of 10CFR50, Appendix 1".

3.1.15 Carbon 14 is released at a rate of 9.6 curies per GW(e)/yr based upon studies performed by the New York State Department of Health at Indian Point 3. This is released in a gaseous form, the primary dose from which is in the CO 2 form.

Therefore, these are exempt from the dose limits specified in Sections 2.4.1, 2.4.3 and 2.4.4 of the RECS. The Carbon 14 doses resulting from these releases are calculated in accordance with the methodology in Reg. Guide 1.109 and listed in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. This calculation is performed using the fraction of carbon 14 released in the CO2 form (26%).

3.1.16 Evaluations of previous gas decay tank and containment purge releases have been performed. These evaluations indicate that these "Short Term Releases" (less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year and less than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per quarter) are sufficiently random to utilize the long term meteorological dispersion factor (NUREG 0133, Section 3.3, Page 8). The short-term correction factor, will only be used when non-random releases are to be made an a routine basis.

3.1.17 The liquid waste Monitor Tanks have an airborne release pathway. The original plant design limited the gases through this pathway by reducing the entrained gases to less than 2E-3 pLCi/ml. The removal of the CVCS gas stripper under modification 86-3-122 CVCS requires the quantification of these gases when the entrained gaseous activity in the Monitor Tank inlet exceeds 2E-3 IgCVml.

No action is required if the inlet noble gas concentrations is less than 2E-3 g.Ci/ml. This gas release will be quantified by calculating the difference (in pCi's) between the gaseous activity added to the tank and the gaseous activity present in the effluent release sample. This difference will be quantified as an airborne ground level batch release, using a X/Q of 5.OE-5 sec/im 3 . A separate release permit evaluating this release is not required prior to release.

Calculation of this rate of release is not required, however the time average dose contribution shall be calculated and controlled per Sections 3.3 and 3.4 of the ODCM. Section 3.6 provides additional detail relative to the finite cloud correction assumptions for this pathway.

3.1.18 Airborne releases from the Steam Generator Safety or Atmospheric Dump Valves can occur during a Primary to Secondary leak. Tritium, Noble Gas, and Iodine effluent doses are determined using a source term activity (Main Steam or Steam Generator Blowdown), an Iodine partition factor (per Section 3.1.14),

and a release rate, determined from Engineering Design Calculation 187 (Steam Generator Atmospherics), or design flowrate (from Steam Generator Safeties) at specific pressures in the Steam Generator.

3-4

ODCM - Rev. 15 Part II include 3.1.19 Other release pathways resulting from Primary to Secondary leakage the gland seal exhaust vent, the air the steam driven auxiliary feed pump vent, Offsite doses from ejector vent, and the Feed Water heater flash tank vent.

obtaining the these or other abnormal airborne release points are calculated by for release rate (from system descriptions and/or steam tables corrected term activity (eg. Main Steam, system pressure, as applicable) and source Reactor Coolant, or best estimate) for Tritium, Noble Gas, and Iodine, partitioned as per Section 3.1.14.

the Gland Seal 3.1.20 Ground level release points include the Monitor Tank vent and Section 3.6.

exhaust. All other release points are considered mixed mode, per 3.2 Gaseous Effluent Dose Calculation Requirements 3.2.1 Section 2.4.1 of the RECS requires that the dose rate due to radioactive site materials released in gaseous effluents from the site at or beyond the boundary shall be limited to:

body and a) For noble gases: Less than or equal to 500 mrem/yr to the total less than or equal to 3000 mrem/yr to the skin; and form b) For Iodine 131, Tritium, and for all radioactive materials in particulate to with half lives greater than 8 days: Less than or equal to 1500 mrem/yr any organ.

Sections The methodologies for performing these calculations are discussed in 3.3.1 and 3.3.2, respectively.

gases 3.2.2 Section 2.4.2 of the RECS requires that the air dose due to noble the site released in gaseous effluents from each reactor unit at or beyond boundary shall be limited to:

a) During any calendar quarter. Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.

b) During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

3.3.3.

The methodology for calculating these doses is discussed in Section NOTE: If either of the above limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per Section 2.6. of the RECS.

3-5

Part 11 ODCM - Rev. 15 3.2.3 Section 2.4.3 of the RECS requires that the dose to a member of the general public from Iodine 131, Tritium, and radionuclides in particulate form (half-lives

> 8 days) in gaseous effluents released from each reactor unit shall be limited to:

a) Less than or equal to 7.5 mrem to any organ during a calendar quarter b) Less than or equal to 15 mrem to any organ during a calendar year.

Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined at least once every 31 days. The methodology for calculating these doses is discussed in Section 3.3.4.

NOTE: If either of the previous limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per Section 2.6 of the RECS.

3.2.4 Section 2.4.4 of the RECS requires that for each reactor unit, the appropriate portions of the gaseous radwaste treatment system shall be used to reduce radioactive effluents in gaseous waste prior to their discharge when projected gaseous effluent air dose at the site boundary when averaged over 31 days, would exceed 0.2 mrad for gamma radiation or 0.4 mrad for beta radiation.

These doses are projected based on the dose methodology discussed in Section 3.3.3 (noble gas) and 3.3.4 (iodine). The average of previous months' doses is used to project future dose as follows: I' Dose 1 Current Month Dose + Previous months' Dose

[major 1 number of months used planned

[Projection.i

-evolutions The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

The appropriate portions of the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous releases when the projected doses averaged over 31 days, would exceed 0.3 mrem to any organ (at nearest residence). Dose due to gaseous releases from the site shall be calculated at least once every 31 days.

3.3 Dose Methodology (Computer Calculation) 3.3.1 Instantaneous Dose Rates - Noble Gas Releases When the instantaneous limit applies, the process radiation monitor response or release rate can be averaged over a one-hour time interval.

3.3.1.1 The equations developed in this section are used to meet the calculational requirements of paragraph 3.2.1. The magnitude of this pathway is the same for all age groups so there is no critical group.

3-6

Part II ODCM - Rev. 15 Based on an agreement with Unit 2, Indian Point Unit 3 utilizes 50% of the site release limit as measured in Ci/sec which translates to 55.4% of the applicable dose rate limit for noble gas releases.

Each unit has different dispersion factors due to their relative positions to the critical sector of the unrestricted area boundary. The conversion from dose rate to Ci/sec was determined with the use of a model which incorporates a finite cloud exposure correction. The methodology is discussed in Section 3.6.

A calculation showing the relationship between Cilsec and dose rates from Units 2 and 3 is shown in Appendix 3-A. The equations for calculating the dose rate limitations are obtained from NUREG 0133 (Ref. 1, Section 5.2.1).

Utilizing the above assumptions, these equations reduce to the following which are to be summed for each nuclide, i. (Note Section 3.1.6 allows use of higher release rates up to the maximum of the allowable maximum permissible discharge rate.)

[(Ki)* (*)* i)]< 275 mremryr whole body tIl'

('*XQ*.) (

S[(Li+1.lMi).* 1,766 mremlyr to the skin; Where:

Ki = The total body dose factor due to gamma emissions for3 each identified noble gas radionuclide, in mrern/yr per JLCi/m (finite cloud correction included, per Table 3-4).

Li = The skin dose factor due to beta emissions for each identified in mrem/yr per 3

, per Table 3-5. IIZ.-I noble gas radionuclide, giCi/m Mi = The air dose factor due to gamma emissions3 for each identified noble gas radionuclide, in mrad/yr per .Ci/m (finite cloud correction included, per Table 3-6).

Ni = The air dose factor due to beta emissions for each identified noble 3

gas radionuclide, in mrad/yr per iCi/m , per Table 3-7.

Qi = The release rate of radionuclides, i, in gaseous effluent for all release points in ýCi/sec.

(X/Q) = For all vent releases, the highest calculated annual averaged relative concentration for any area at the site boundary (4.85E-6 sec/im 3), in the SSW sector at 380 meters. (Note: SSW is critical IP3 sector for external gamma radiation exposure.)

The Ki, Li, Mi, and Ni factors were obtained from Table B-1 of Regulatory Guide 1.109 and are included in this document as Tables 3-4, 3-5, 3-6, and 3-7 respectively. The Ki and Mi factors have a finite cloud correction factor included.

3-7

Part 11 ODCM - Rev. 15 3.3.1.2 These equations can also be expressed in the following manner.

(K) (Qt) (X /Q) = mremlyr dose to whole body (L + 1.M) (XI Q) (Qt) = mrem/yr dose to skin Where:

Qt = The release rate of all noble gases summed together in pCi/sec, i.e., the sum of all Q i.

(It)Z n 0)(Ki) iIt (I/&) +/- 0i) (D)

MQ (/Q) -6Qn 5i) (Mi) i-I n

SZ(1/) Qi) NO 6

i-I The values of K, L, M, and N are listed in Table 3-8 for the unrestricted area boundary.

3.3.2 Instantaneous Dose Rates 131, Part w/>8 day tY2. and H-3 The equation developed in this section is used to meet the calculational requirements of RECS 2.4.1. The critical organ is considered to be the child thyroid as stated in Section 4.0 of the RECS. Based on a previous agreement with unit 2, Indian Point unit 3 utilizes 50% of the site release limit as measured in Ci/sec which translates to 67.2% of the applicable dose rate limit. This is a result of the different dispersion to the critical sector of the unrestricted area boundary. A calculation showing the relationship between Ci/sec released and dose rates from Units 2 and 3 is shown in Appendix 3-A. The equation for calculating the dose rate limitation is obtained from NUREG 0133 (Ref. 1, Section 5.2.1, Pg. 25). Utilizing the above assumptions, this equation reduces to the following:

S(Pi * (X/Q)

• Qi) must be less than 1008 mrem/yr Where:

Pi = The dose parameter for radionuclides other than noble gases for the inhalation pathway in mrem/yr per j+/-Ci/m 3 . These parameters (calculated in Section 3.3.2.1) are calculated separately for each isotope, age group, and organ.

3-8

ODCM - Rev. 15 Part II Qi = The release rate of radionuclide 131 and particulates, i, in gaseous effluents for all release points in IRCi/sec.

the X/Q = 5.21 E-6 sec/rm3. The annual average dispersion parameter for location (350 meters SW) due to all inhalation pathway at the controlling vent releases (see Section 3.5).

3.3.2.1 Calculation of Pi(in): Inhalation Dose Factor 3

Pi (inhalation) = K' (BR) DFAi (mrem/yr per p.Ci/m )

Where:

K' = A constant of conversion, 106 pCi/p.Ci BR = The breathing rate of each age group as per 3.3.4.5.a (Table E-5 of Reg. Guide 1.109).

DFAi = The inhalation dose factor for each age group, organ, and nuclide, in mrem/pCi. These values are taken from Reg Guide 1.109, Table E-7 through E-9 and are reproduced in Tables 3-1a through 3-1d.

3.3.3 Time Average Dose - Noble Gas Release 3.3.3.1 The equations in this section are used to meet the calculational are requirements of Paragraphs 3.2.2 and 3.2.4. All releases at IP3NPP assumed to be mixed mode unless indicated otherwise. The magnitude for this pathway is the same for all age groups so there is no critical group. Dispersion parameters are discussed in Section 3.5.

from 3.3.3.2 The equation for calculating the dose limitations are obtained NUREG 0133 (Ref. 1, Section 5.3). The doses are evaluated at the unrestricted area boundary in the worst meteorological section (SSW sector at 380 meters). These equations reduce to the following:

(4im,)]

gamma air mrad = 3.17E - 8* "Mi [(X/Q) (Qi) + (x/q) (4i) + (x/q,,)

beta air mrad = 3.17E - 8* Ni [(X/Q) (Qi) + (x/q) (4i) + (x/q,) (4im,)]

Where:

Air dose limits are as follows:

Any Calendar Quarter Any Calendar Year Gamma Air 5 mrad 10 mrad Beta Air 10 mrad 20 mrad 3-9

Part II ODCM - Rev. 15 (X/Q) =The highest calculated annual average relative concentration for the unrestricted area boundary in the SSW sector at 380 meters for long term releases (greater than 500 hrs/yr or 150 hrs/qtr or as noted in 3.1.16) 4.85E-6 secIm3.

(x/q) = The relative concentration for the unrestricted area boundary for short term releases (equal to or less than 500 hrs/yr or 150 hrs/qtr and not random as defined in NUREG 0133, Section 3.3). This value is calculated as per Section 3.5.

(x/qm)=The relative concentration for the unrestricted area boundary for ground level releases from the monitor tank vents in the SW sector at 350 meters, 5E-5 sec/m3 .

Mi = The air dose factor due to gamma emission for each 3 identified noble gas radionuclide in mrad/yr per p.Ci/m .

Ni = The air dose factor due to beta emissions for each 3 identified noble gas radionuclide in mrad/yr per pCil/m .

Wirt= The total releases of noble gas radionuclides in monitor tank vents in pCi. Releases shall be cumulative over the calendar quarter or years as appropriate.

q= The total release of noble gas radionuclides in gaseous effluents, i, for short term releases (equal to or less than 500 hrs/yr or 150 hrs/qtr and not random as defined in NUREG 0133, Section 3.3) from all vents, in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

ýi= The total release of noble gas radionuclides in gaseous effluents, i, for long term releases (greater than 500 hrs/yr or 150 hrs/qtr or as noted in 3.1.16) from all vents in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

3.17 E-8 = The inverse of the number of seconds in a year.

The air dose factors Mi and Ni were obtained from Table B-1 of Regulatory Guide 1.109 and are listed in Table 3-6 and 3-7 respectively. The M air dose factors are finite cloud corrected.

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Part 11 ODCM - Rev. 15 3.3.4 Time Averaged Dose - Radioiodine 131, Part wltY2 >8 days, and Tritium 3.3.4.1 The equations in this section are used to meet the calculational requirements of Paragraphs 3.2.3 and 3.2.4.

3.3.4.2 The pathways considered in this analysis are inhalation, ground plane, and vegetable ingestion at the nearest resident. The meat and milk ingestion pathways are not considered because of the lack of milk producing cows within ten miles of the plant, and because of the high degree of commercial, industrial, and residential land usage in the area, as defined by the land use census. Doses are calculated at the nearest resident using meteorlogical data from the worst sector (SSW sector at 1525 meters) for conservativism.

3.3.4.3 The equations for calculating the dose limitations are obtained from NUREG 0133 (Ref. 1, Section 5.3). These equations reduce to the following :

During any calendar quarter.

(3.17E-08)*' (Ri(WQi + w~i) must be less than 7.5 mrem I

During any calendar year.

(3.17E-08)*E (Ri(WQi + w4i) must be less than 15 mrem Where:

i= The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for long term releases as defined in Section 3.1.16, in 4.Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.

i= The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for short term releases as defined in Section 3.1.16, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

W = The dispersion or deposition parameter (based on meteorological data defined in Section 3.5) for estimating the dose to an individual at the nearest resident for long term releases as defined in Section 3.1.16.

3-11

Part 11 ODCM - Rev. 15 w = The vent dispersion or deposition parameter for estimating the dose to an individual at the nearest resident for short term releases (as defined in Section 3.1.16) and calculated as in Section 3.5.

3.17 E-08 = The inverse number of seconds in a year.

Ri = The dose factor for each identified pathway, organ, and radionuclide, i, in m2 - mrem/yr per I.Ci/sec. or mrem/yr per PCi/m 3 . These dose factors are determined as described in Sections 3.3.4.5a-d.

3.3.4.4 Utilizing the assumptions contained in Section 3.3.4.3, these equations for the nearest resident reduce to the following:

DN=(3.17E- 8) '[Ri(I)* [Wn(in)Qi + wn(in)4i] + (Ri(G)+ Ri(V))* [Wn(dep)Qi + wn(dep)i]]1 ,

Where:

DN = total dose at the nearest residence, and must be less than or equal to 7.5 mrem per quarter, and less than or equal to 15 mrem Annually.

Wn(in) = The highest calculated annual average dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area located in the SSW sector at 1525 meters, 8.96E-7 sec/m 3 .

wn(in) = The dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area located in the SSW sector at 1525 meters, 8.96E-7 sec/m3 ,

corrected for short term releases.

Wn(dep)= The highest calculated annual average deposition parameter for the nearest residence in the unrestricted area located in the South sector at 1280 meters, 6.14E-9 m-2 for all isotopes except Tritium, which uses the X/Q value instead (8.96E-7 sec/m 3 ).

wn(dep)= The deposition parameter for the nearest residence in the unrestricted area located in the South sector at 1280 meters, 6.14E-9 m"2 for all isotopes except Tritium, which uses the X/Q value instead (8.96E-7 sec/m3 ), corrected for short term releases.

3-12

ODCM - Rev. 15 Part I1 Qi = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for long term releases as defined earlier, (uCi).

i= The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for short term releases as defined earlier (uCi).

Ri (I): Inhalation pathway factor for each radionuclide, i.

Ri (G): Ground plane pathway factor for each radionuclide, i.

Ri (V): Vegetation pathway factor for each radionuclide, i.

3.3.4.5 Calculation of Dose Factors 3.3.4.5.a Calculation of Ri (1)(X/Q) Inhalation Pathway Factor 3

Ri (I) (x/Q) = K'[(BR) a] [(DFAi) a](mremlyr per p.Ci/m )

Where:

K' = Constant of unit conversion, 106 pCi/uCi 3

(BR) a = Breathing rate of the receptor of age group (a) in m /yr.

(DFAi) a = The maximum organ inhalation dose factor for the receptor of age group (a) for the ith radionuclide in mrem/pCi. The total body is considered as an organ in the selection of (DFAi)a.

Child and infant inhalation dose factors are generally more restrictive, however, doses from each age group are calculated separately. The (DFAi)a values are listed in Tables 3-1 a through 3-1d. The Ri values for the inhalation pathway are listed in Table 3-1 Oa through 3-1 Od.

3-13

Part 11 ODCM - Rev. 15 Breathing rates: (from Regulatory Guide 1.109, Table E-5)

Infant = 1400 (m3/yr)

Child = 3700 (m3/yr)

Adult/Teen = 8000 (m3/yr) 3.3.4.5.b Calculation of Ri(G)(DIQ) Ground Plane Pathway Factor K'K"(SF)(DFGi)(1- e(-k1) = m2 mrem/ yr Ri(G)(D) =Ki uCi/sec Where:

K' = A constant of conversion, 106 pCi/ACi.

K" = A constant of conversion, 8760 hr/yr.

ki = Decay constant for the ith radionuclide sec"1 .

t = The exposure time, 4.73 x 108 sec (15 years).

DFGi = The ground plane dose conversion factor for ith radionuclide (mrem/hr per pCi/m2).

SF = Shielding factor (dimensionless) = 0.7 (from Table E-15 of Regulatory Guide 1.109).

The values of DFGi were obtained from Table E-6 of Regulatory Guide 1.109 and are listed in Table 3-2. These values were used to calculate Ri(G), which is the same for all age groups and organs and is listed in Table 3-12.

3-14

Part 11 ODCM - Rev. 15 3.3.4.5.c Calculation of Ri(V)(D/Q) - Vegetation Pathway Factor K'(r) .(DFLia.[(UaL)fl *e(_-,L) + (UaS)fg e e(-h)]

Ri(V)(D1Q) = Yv(ki +kw)

Where:

K' = Constant of conversion, 106 pCi/g.Ci r = Dimensionless correction factor for Iodine and Particulate from Table E-1 5 of Reg Guide 1.109, as follows:

0.2 for particulates 1.0 for radioiodine DFLia = Reg Guide 1.109 dose factor for each nuclide, in mrem/pCi UaL = Consumption rate of fresh leafy vegetation by the receptor in age group (a) in kg/yr.

ki = Decay constant for the radionuclide, in sec UaS = Consumption rate of non-leafy vegetables by the receptor in age group (a) in kg/yr.

fL = The fraction of the annual intake of leafy vegetation grown locally.

fg = The fraction of the annual intake of non-leafy vegetation grown locally.

kw = Decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec -'(corresponding to a 14 day half-life).

tL = The average time between harvest of leafy vegetation and its consumption in seconds.

th = The average time between harvest of stored vegetation and its consumption in seconds.

Yv = The vegetation area density in kg/mr2 .

3-15

ODCM - Rev. 15 Part II The concentration of Tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri(M)is based on X/Q:

3 (RiV) (XJQ) = K'K"[(UaL)fL+(UaS)fg](DFLi)a (0.75)(0.5/H) (mrem/yr per gCi/m )

Where:

K" = A constant of unit conversion, 1000 gm/kg 3

H = Absolute humidity of the atmosphere in gm/m . This value may be considered as 8 gm/m 3 (NUREG 0133, pg 27) in lieu of site specific information.

0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water DFLia for each age group is given in Tables 3-3a through 3-3d.

Ri(V) values are listed in Table 3-11 a through 3-11 c.

3-16

ODCM - Rev. 15 Part II Ri(V) Parameters Are From The Following Sources:

PARAMETER VALUE Reg Guide 1.109 Table 1.0 for radioiodines E-1 5 r (dimensionless) 0.2 for particulates (DFLi) a (mremrpCi) Each radionuclide E-1 I to E-14 UaL (kg/yr) - infant 0 E-5

- child 26 E-5

- teen 42 E-5

- adult 64 E-5 UaS (kglyr) - infant 0 E-5

- child 520 E-5

- teen 630 E-5

- adult 520 E-5 fL- (dimensionless) 1.0 E-1 5 0.76 E-1_5 fg (dimensionless) 8.6E4 (1 day) E-15 tL (seconds) 5.18E6 (60 days) E-1 5 th (seconds) 2.0 E-15 Yv (kg/mr2 )

3-17

Part 11 ODCM - Rev. 15 3.4 Backup Simplified Dose Methodology The dose calculation procedures described in this section are provided for use as a backup whenever the primary computer methodology cannot be followed.

3.4.1 Instantaneous Dose Rates - Noble Gas Releases Note: When the instantaneous limit applies, the process radiation monitor response or release rate can be averaged over a one hour time interval.

3.4.1.1 This section describes the alternative calculational methods to meet the requirements of Paragraph 3.2.1. These methods provide calculational results as per section 3.3.1.

3.4.1.2 To determine an acceptable noble gas instantaneous release rate in A.Ci/sec, a standard isotopic mixture of noble gases may be assumed.

This isotopic mixture was measured for a mixture of isotopes typical of reactor coolant with exposed fuel. This requirement is evaluated at the worst sector of the unrestricted area boundary. Based on this isotopic mixture, standard Ks, Ls, Ms, and Ns (lower case s denotes a weighted sum, see Table 3-8) can be determined using the technique presented in paragraph 3.3.1.2 and Ki, Li, Mi, and Ni values from Tables 3.4-7. The data and results of this calculation are shown in Table 3-8.

3.4.1.3 The isotopic mixture chosen was obtained from a reactor coolant sample during an operating period with exposed fuel. Table 3-8 contains the mixture data and the fractional relative abundance of each isotope. These standard factors can be used with the equations and limits presented in Section 3.3.1.

3.4.1.4 Utilizing the equations from Paragraph 3.3.1.2 and the values from Table 3-8, maximum release limits for all noble gases in p.Ci/sec can be calculated as follows:

Maximum instantaneous release rates:

275 275 < 3.81E + 4 Lt(Whole Body)

Ks(X/Q)- (1.49E+3X4.85E-6) sec Qt_< 1766 < 1766 <1.15E+5 pCi (Skin)

(Ls+1.IMs)(X/Q) (3.16E+3)(4.85E-6) sec 3-18

Part II ODCM - Rev. 15 3.4.1.5 For individual release rate determinations, alternate computer codes and/or a Hand Calculation Template serve as back up methodologies should the primary computer method be inoperable. These methods comply with calculations in Section 3.3.1.

3.4.2 Instantaneous Dose Rates-I-1 31, Particulates w/t1/2 >8 days, & H-3 3.4.2.1 This section describes the alternative calculational method to meet the requirements of Paragraph 3.2.1. The purposes of this method is to provide backup calculational techniques,both computer aided and hand calculated, which approximate section 3.3.2.

3.4.2.2 To determine an acceptable iodine and particulate release rate, it is assumed that the limit on these releases shall be met if the total noble gas concentration in the VC is at least a factor of 20,000 more than the concentration of radioiodine and long lived particulates or VC iodines and long lived particulates are less than I E-7 gCi/cc. This has historically been the case and this assures that the noble gas activity will be limiting.

3.4.2.3 Backup instantaneous dose rate calculations can be performed with an alternate computer code or by formatted hand calculations. These methods are identical to section 3.3.2.

3.4.3 Time Averaged Dose - Noble Gas Releases 3.4.3.1 This section describes alternative methods of meeting the requirements of Paragraphs 3.2.2 and 3.2.4, and the alternative methods of implementing the calculation techniques presented in Section 3.3.3.

3.4.3.2 The values of Ki, Li, jMi, and Ni for the Plant Vent (PV) mixed mode releases and the Monitor Tank (MT) ground plane releases are determined for each release using the dispersion parameter for the site boundary in the worst sector. The calculations are as follows:

PVKi = (Ki)*(X/Q)PV and M'T1K = (Ki)*(X/Q)MT PV7L = (Li)*(X/Q)PV and MTLi = (LJi)*(X/Q)MT PVMi = (Mi)*(XIQ)PV and MTMi = (Mi)*(X/Q)MT PVNi = (Ni)*(XIQ)MT and MTNi = (Ni)*(XIQ)MT Where:

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per

.Ci/m 3 (finite cloud correction used).

3-19

Part I1 ODCM - Rev. 15 Li = The skin dose factor due to beta emissions for each 3

identified noble gas radionuclide in mrem/yr per gACi/m .

Mi = The air dose factor due to gamma emissions for each 3

identified noble gas radionuclide in mrem/yr per igCi/m (finite cloud correction used).

Ni = The air dose factor due to beta emissions for each 3

identified noble gas radionuclide in mrad/yr per gLCi/m .

(X/Q)PV = The highest calculated annual average dispersion parameter for the noble gas pathway at the unrestricted area boundary, 4.85E-6 sec/m 3 and applicable to plant vent mixed mode releases.

(X/Q)MT = The highest calculated annual average X/Q for ground level monitor tank noble gas release pathway, 5.OOE-5 sec/m 3 .

3.4.3.3 Determine weighted average dose factors as follows:

All values of Ki, Li, Mi, and Ni are shown in Table 3-4 through 3-7 for the unrestricted area boundary.

Each of the following expressions is summed over all the nuclides:

PVKt = X[Ki*(Ci/Ct)]

PVLt = [Li*(Ci/Ct)]

PVMt = X[Mi*(Ci/Ct)]

PVNt = *[Ni*(CiICt)]

For the monitor tank pathway, MTKt, MTLt, MTMt, and MTNt are calculated in the same way as for plant vent (PV) releases above, except that Ci and Ct apply to gaseous activity for the monitor tank vent pathway.

Where:

Ci = Concentration of isotope i (gCi/cc) in analysis, t (for either PV or MT pathway)

Ct = Concentration of all noble gas isotopes (p.Ci/cc) for a specific analysis, t, (for either the PV or MT pathway)

These calculations can be performed by hand (via formatted procedure) or by using alternate computer codes to compute all or part of the dose calculation.

3-20

Part 11 ODCM - Rev. 15 3.4.3.4 Calculate resultant doses and compare with limits as per 3.3.3. The sum of all releases in a calendar quarter or calendar year should be compared to the limits of Section 3.2.2 and 3.2.4 as appropriate for gamma air dose and beta air dose.

3.4.4 Time Averaged Dose-Iodine 131 and Particulates w/tY2 days& H-3 3.4.4.1 This section describes the alternate methods of meeting the requirements of Paragraphs 3.2.3 and 3.2.4 and of implementing the calculational techniques presented in Section 3.3.4.

3.4.4.2 Ifthe primary computer method is inoperable, dose calculations can be performed by:

a) an alternate computer code which complies with Section 3.3.4, using all identified Iodine and Particulate isotopes;

- or b) hand calculations (via a formalized departmental procedure) which comply with Section 3.3.4.

3.4.4.3 Sum the Iodine, Particulate, and Tritium dose contributions and compare quarterly and annual totals to the limits described in Section 3.2.3.

3.5 Calculation of Meteorological Dispersion Factors 3.5.1 For the purpose of these calculations, the site boundary was taken to be the unrestricted area boundary. The distances to the site boundary, as measured from the plant vent on top of the IP3NPP primary containment, are shown in Table 3-9 for each of the 16 major compass sectors. The distances to the nearest residence in each of these sectors is also shown on this table. In the sectors where the Hudson River is the site boundary, the opposite shore is assumed as the boundary of the unrestricted area. This is based on the definition of unrestricted area in NUREG 0133 (Ref. 1, Section 2.2, Page 6) which states that the unrestricted area boundary does not include areas over bodies of water. The nearest opposite shore distance is five times that of the closest land restricted area boundary. Therefore, these locations are unimportant when evaluating the maximum unrestdcted area boundary concentrations.

3-21

Part 11 ODCM - Rev. 15 3.5.2 The atmospheric transport and diffusion model used in the evaluation of dispersion and deposition factors is the sector-average straight-line model in Regulatory Guide 1.111 (Ref. 15) for mixed-mode releases with plume-rise effects, downwash, and building-wake correction.

The analyses were carried out using the AEOLUS-3 computer code (Ref. 16) and are documented in detail in Ref. 17. Use was made of 10-years' worth of hourly meteorological data collected on site during the period 1981 through 1990 in accordance with the accuracy requirements of Regulatory Guide 1.23 (Ref. 18); the data recovery index for that period was in excess of 99%.

Comparison of the new meteorological data with previous data shows no difference in the overall dispersion conditions at the site. In the analyses, wind speed coefficients in Regulatory Guide 1.111 were used to extrapolate the measured wind speeds to the height of the main vent (on top of the primary containment). Also, the regulatory plume entrainment model was used to determine plume partitioning between ground-level and elevated releases, and no credit was taken for decay and depletion in transit.

Recirculation effects were accounted for by confining in-valley flows within the valley out to a distance of 10 miles (up or down the valley) and allowing a portion of them to return to the site without additional dilution.

3.5.3 To meet the calculational requirements of Paragraphs 3.2.1, 3.2.2, and 3.2.4 the annual average dispersion factors were calculated for each compass sector at the site unrestricted area boundary. The most restrictive X/Q was determined to be 5.2E-06 s/m 3 in the SW sector at 350 meters for inhalation 3

and the SSW sector at 380 meters with an X/Q of 4.85E-6 s/m for external gamma radiation. The distances to the site boundary in each sector are listed in Table 3-9.

For the monitor tank release pathway, ground level X/Q values were assessed using the same data base as discussed in Section 3.5.2. The most restrictive XIQ was determined to be in the SW sector at 350m with a value of 5.OOE-5 sec/m 3 (concentration X/Q per Ref. 21).

3.5.4 To meet the calculational requirements of Paragraph 3.2.3 iodines and particulates, the annual average deposition and dispersion parameters were calculated for the nearest residence in each of the compass sectors. Distance to the nearest residence in each sector are listed in Table 3-9. Because no real dairy exists within 5 miles of the power plant, the grass-cow-milk pathway and its dispersion factor are not included.

3-22

ODCM- Rev. 15 Part II were calculated Dispersion and deposition parameters for the nearest resident are as follows:

using the models and data described in Sec. 3.5.2 above and for Wn(in) = The highest calculated annual average dispersion parameters the inhalation pathway for the nearest residence in the unrestricted area 3

located in the SSW sector at 1525 meters, 8.96E-7 sec/m for Wn(dep)= The highest calculated annual average deposition parameters the ground plane and vegetation pathways for the nearest residence in the unrestricted area located in the S sector at 1279 meters, 6.14E-9 m-2 . For Tritium in the vegetation pathway Wn(in) is used.

NOTE: For the monitor tank pathway, iodines and particulates are effectively removed by demineralization, therefore dispersion parameters are not needed for this pathway.

3.2.3 and 3.2.4 3.5.5 To meet the calculational requirements of Paragraphs 3.2.2, and 3.3.3, short and the calculation methodologies described in Sections 3.3.4 be calculated.

term release dispersion and deposition factors may need to factors are For this document, short term release dispersion and deposition a method determined from the long term annual average parameters and by NUREG presented by Sagendorf in NUREG 0324 (Ref. 5) as recommended 0133 (Ref. 1, Section 3.3, Page 8). This method makes use of a factor (F),

is simply developed for a particular compass sector and distance, which for the multiplied by the annual average dispersion or deposition parameterparameter.

same sector and distance to develop the corresponding short-term This factor is defined as:

F = [NTOTAL/8760]m Where:

F = The non-dimensional correction factor used to convert annual average dispersion or deposition factors to short term dispersion or deposition factors.

3-23

Part 11 ODCM - Rev. 15 NTOTAL = The total duration of a short-term release (or releases) in hours, during a chosen reporting period.

8760 = The total number of hours in a year.

ANMX = The calculated historical average dispersion (sec/m 3) or deposition (m2 ) factor for the compass sector and distance of interest.

F15MX = The short term dispersion (sec/m 3) or deposition (m-2 )

factor for the compass sector and distance of interest.

This is the 15th percentile value such that worse weather conditions can only exist 15% of the time and better weather conditions 85% of the time.

M =log(ANMXW/F15MX) 1og(8760)

The atmospheric transport and diffusion model used in the evaluation of short-term dispersion and deposition parameters (F15MX) is the Gaussian plume-centerline model in Regulatory Guide 1.145 (Ref. 19),

adapted for mixed-mode releases with plume-rise effects, downwash, building-wake correction and plume meander considerations.

As was the case with the annual average parameters, the analyses were carried out using the AEOLUS-3 computer code (Ref. 16) and the 10-year hourly meteorological data base; they are documented in detail in Reference 17.

Note that, in line with the guidance in NUREG-01 33 (Ref. 1, Sec. 5.3.1, page 29), short-term releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year) are considered to be cumulative over the calendar quarter or year, as appropriate. However, from Sec. 3.1.16 of the ODCM Part II, and in line with Sec. 3.3, page 8 of NUREG-0133, gas-decay tank releases and containment purges have been determined to be sufficiently random so as to permit use of the long-term dispersion and deposition parameters for assessment of their radiological impact.

3-24

Part 11 ODCM - Rev. 15 3.5.6 The short term 15th percentile dispersion or deposition factor for use in the equation of the preceding paragraphs and the simplified F factor equation are as follows:

a) Site Boundary Noble Gas:

F15MX (380m, SSW, inhalation) = 9.67E-5 smin ANMX (380m, SSW, inhalation) = 4.85E-6 smin F = [NTOTALI876Of; m log(4.85E- 6/9.70E-5) -0.330 log(8760) 0 F = [NTOTAUI876 ]"°330 b) Nearest Residence Inhalation:

F1 5MX (730m, E, inhalation) = 3.OOE-5 sm-3 ANMX (1526m, SSW,.inhalation) = 8.96E-7 smin m; in = log(8.96E- 7/ 3.0E- 5) -0.387 F = [NTOTAL876] -

log(8760) 387 F = [NTOTAL/8760]"'

c) Nearest Residence Deposition:

2 F15MX (730m, E, Dep.) = 2.61E-7 sm ANMX (1280m, S, Dep.) = 6.14E-9 smin F=[NTOTAI876'; in =log(6.14E -9/2.61E -7) -0.413 log(8760) 413 F = [NTOTAL/8760]"

3-25

Part 11 ODCM - Rev. 15 3.6 Justification for and Use of Finite Cloud Assumption for Assessingq Site Boundary Dose Two models are available for the computation of doses from external gamma radiation:

a) The semi-infinite cloud model, which is conservatively applicable only for ground level releases assumes ground level airborne concentrations are the same throughout a cloud that is large in extent relative to the photon path lengths in air.

b) The finite-cloud model, which takes into consideration the actual plume dimensions and the elevation above the receptor.

The semi-infinite cloud model (which is normally used in a variety of applications because of its simplicity) has two drawbacks:

1. It could be overly conservative for receptors close to the release point (particularly for ground-level releases under stable conditions with limited plume dispersion) due to the basis that the high concentration at the receptor is assumed to exist everywhere, and;

2. It is not suitable for elevated releases since gamma radiation emanating from the radioactive cloud could still reach a receptor on the ground even though the plume is still aloft (the concentration at ground level is equal to zero).

For practical applications, it is possible to define isotope-dependent finite-cloud correction factors to express the difference in external radiation exposures between a finite cloud (which may be either at ground level or elevated) and a semi-finite cloud.

Physically, when such a correction factor is applied to the calculated ground-level concentration resulting from a given plume, it will define the equivalent concentration in a semi-infinite cloud which would yield the same external exposure as the finite cloud.

Such a correction factor is a function of both the airborne radionuclide energy and of plume dispersion under the prevailing conditions. At distant receptors, where the plume dimensions reach limiting conditions, such correction factors reduce to unity.

The AEOLUS-3 code (which was used for the determination of the annual average dispersion and deposition parameters listed in Section 3.5), also has the capability of providing a basis for computation of isotope-specific finite-cloud correction factors based on the models in "Meteorology and Atomic Energy" (Ref. 20, Sec. 7.5.2). The code was used (along with the mixed-mode release option and the 10-year hourly meteorological data base) for the determination of the correction factors as would be applicable at the IP3 site boundary. Note that the correction factors can be viewed as adjustment factors to the dose conversion factors in Regulatory Guide 1.109 (Ref. 3) for immersion in semi infinite clouds. The nuclide specific correction factors and adjusted dose factors are presented in Tables 3.4 and 3.6 for the IP3 site boundary.

For the monitor tank pathway (ground release concentration X/Q), use of the finite cloud corrected data presented in tables 3-4 and 3-6 will provide a conservative result. The conservativism is due to the indicated correction factors for the mixed mode case yielding larger correction factors per nuclide. However, in the event that a ground level specific finite cloud correction factor is desired (which will yield lower calculated doses) the Xe-133 gamma X/Q value may be used as described in Reference 21.

3-26

Part 11 ODCM - Rev. 15 3.7 Direct Radiation Measurements and Total Dose Calculations (40CFR1 90)

Per RECS 3.6, the direct radiation component for potential offsite dose is determined by Radiological Engineering (using References 26 through 29) as follows:

Direct Radiation Dose = VC + IRWSF + SGM + RMHA, + etc where; VC = The Vapor Containment structure.

IRWSF = The Interim Radioactive Waste Storage Facility SGM = The Steam Generator Mausoleum RMHA = A Radioactive Material Handling Area, as posted i = The ith RMHA Other structures or tanks are included as determined by Radiological Engineering.

The calculations in References 26 through 29 were performed in order to meet the requirements of NRC Generic Letter 81-38, 11/10/1981, Storage of Low-Level Radioactive Wastes at Power Reactor Sites.

"MOffsite doses from onsite storage must be sufficiently low to account for other uranium fuel cycle sources (e.g., an additional dose of <1 mrem/year is not likely to cause the limits of 40 CFR 190 to be exceeded). On site dose limits will be controlled per 10 CFR 20..."

The IRWSF, SGM, and RMHAs fenceline dose rates are limited by department proedures to keep dose rates at the SITE BOUNDARY fence < 1 mrem/yr based on calculations performed in References 26 through 29. These calculations contain realistic occupancy factors for the SITE BOUNDARY fence (including the IP2 shared fence) and the nearest neighbor.

3.8 Gaseous Effluent Dose to MEMBERS OF THE PUBLIC Visiting the Site Per RECS Section 4 (bases) and the discussion regarding gaseous effluent dose rate, visiting MEMBERS OF THE PUBLIC will receive negligible dose, as calculated per ODCM Part II,Sections 3.3.3 and 3.3.4, due the application of multiplicative occupancy factors. These factors are determined by comparing the expected hours on site to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> (the number of hours in a year, which is used in the calculations demonstrated in Sections 3.3.3 and 3.3.4). Examples of these calculations are as follows:

example 1: Several students visit the site for an 8-hour guided tour.

Their occupancy factor is: 8/8760 or .0009.

example 2: A man drives his wife to work and drops her off at the security gate each morning, with a total stay-time on site for 2 minutes per day. His occupancy factor is calculated as follows:

2 min/60 min per hour =.0333 hr; : 0.0333 / 8760 = 3.8E-6 These factors, when multiplied by doses calculated per Sections 3.3.3 and 3.3.4, demonstrate that dose to these MEMBERS OF THE PUBLIC is negligible, despite any potential reduction in the atmospheric dispersion.

3-27

Part II ODCM - Rev. 15 Table 3-1a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0. OOE+00 1.58E-07 1.58E-07 1.58E-07 1. 58E-07 1.58E-07 1.58E-07 Be-7 0. OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 Na-24 1.2BE-06 1.28E-06 1. 2BE-06 1.28E-06 1. 28E-06 1.28E-06 1.28E-06 P-32 1. 65E-04 9.64E-06 6.26E-06 0.OOE+00 0. OOE+00 0.00E+00 1.08E-05 Cr-51 0.OOE+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0. 00E+00 4.95E-06 7.87E-07 0.OOE+00 1.23E-06 1.75E-04 9. 67E-06 Mn-56 0. 00E+00 1.55E-10 2.29E-11 0.OOE+00 1. 63E-10 1.18E-06 2.53E-06 Fe-55 3. 07E-06 2.12E-06 4. 93E-07 0.OOE+00 0. OOE+00 9.01E-06 7.54E-07 Fe-59 1. 47E-06 3.47E-06 1. 32E-06 0.OOE+00 0.OOE+00 1.27E-04 2.35E-05 Co-58 0. OOE+00 1.98E-07 2.59E-07 0.OOE+00 0.OOE+00 1.16E-04 1.33E-05 Co-60 0. 00E+00 1.44E-06 1. 85E-06 0.OOE+00 0. OOE+00 7.46E-04 3.56E-05 Ni-63 5. 40E-05 3.93E-06 1. 81E-06 O.OOE+00 0. OOE+00 2.23E-05 1. 67E-06 Ni-65 1. 92E-10 2.62E-11 1.14E-11 0.OOE+00 0.OOE+00 7. OOE-07 1. 54E-06 Cu-64 0. 00E+00 1.83E-10 7.69E-11 0.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.OOE+00 8. 62E-06 1.08E-04 6. 6BE-06 Zn-69 4.23E-12 8.14E-12 5. 65E-13 0.0OE+O0 5.27E-12 1.15E-07 2.04E-09 Br-83 0.OOE+00 0.OOE+00 3.01E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.90E-08 Br-84 0.OOE+00 0.OOE+00 3.91E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.05E-13 Br-85 0.0 0E+00 0.OOE+00 1. 60E-09 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Rb-8 6 0.0OE+00 1.69E-05 7.37E-06 0.OOE+00 0.OOE+00 0.OOE+00 2. 08E-06 Rb-88 0.OOE+00 4.. 4E-08 2.41E-08 0.OOE+00 0.OOE+00 0. OOE+00 4. 18E-19 Rb-8 9 0.OOE+00 3.20E-08 2.12E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.16E-21 Sr-89 3.80E-05 0.OOE+00 1.09E-06 0.OOE+00 0.OOE+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.OOE+00 7. 62E-04 0.OOE+00 0.OOE+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.OOE+00 3.13E-10 0.OOE+00 0. OOE+00 4.56E-06 2.39E-05 Sr-92 8. 43E-10 0.OOE+00 3.64E-11 0.OOE+O0 0.OOE+00 2.06E-06 5.38E-06 Y-90 2. 61E-07 0.OOE+00 7.01E-09 0.OOE+00 0.OOE+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.OOE+00 1.27E-12 0.OOE+00 0.OOE+00 2.40E-07 1. 66E-10 Y-91 5. 78E-05 0.OOE+00 1.55E-06 0.OOE+00 0.OOE+00 2.13E-04 4.81E-05 Y-92 1. 29E-09 0.OOE+00 3.77E-11 0.OOE+00 0.0OE+00 1.96E-06 9.19E-06 Y-93 1. 18E-08 0.OOE+00 3.26E-10 0.OOE+00 0.0OE+O0 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.OOE+00 6.77E-06 2.21E-04 1.8BE-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.OOE+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.OOE+00 9. 67E-07 6.31E-05 1.30E-05 Mo-99 0. OOE+00 1.51E-08 2.87E-09 0.OOE+00 3. 64E-08 1.14E-05 3. lOE-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.OOE+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.OOE+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1. 91E-07 0.OOE+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.3BE-05 Ru-105 9. 88E-11 0.OOE+00 3.89E-11 0.OOE+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8. 64E-06 0.OOE+00 1.09E-06 0 0OE+00 1.67E-05 1.17E-03 1. 14E-04 Ag-110m 1. 35E-06 1.25E-06 7.43E-07 0 OOE+00 2. 46E-06 5.79E-04 3.78E-05 Sb-122 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sb-124 3. 90E-06 7.36E-08 1.55E-06 9.44E-09 0.OOE+00 3.1OE-04 5. 0BE-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.OOE+00 2.18E-04 1.26E-05 3-28

ODCM - Rev. 15 Part II Table 3-la ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope

.83E-06 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 155.72E-06

.55E-06 31 .92E-05

.20E-04 81 .87E-05 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.37E-10 I.14E-07 8 7 .17E-06 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6L.57E-06 1 .45E-04 4 .79E-05 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 42.34E-11 22.42E-07 1 .96E-08 2

Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 .86E-08 L.82E-05 E5.95E-05 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 5.46E-12 L.74E-07 22.30E-09 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 L.82E-07 3.60E-05 E6.37E-05 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 2.61E-06 0.00E+00 ).61E-07 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 7.66E-06 0.OOE+00 T.85E-07 1-131 3.15E-06 4. 47E-06 2.56E-06 1.49E-03 6.48E-07 0.00E+00 5.08E-08 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 3.23E-06 0.00E+00 1.11E-06 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.4 4E-07 0..00E+O0 1.26E-10 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 1.39E-06 0.OOE+00 6.56E-07 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 3.59E-05 1.22E-05 1.30E-06 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.OOE+00 1.07E-05 1.50E-06 1.46E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 O.OOE+00 2.78E-05 9.40E-06 1.05E-06 Cs-137 5. 98E-05 7.76E-05 5.35E-05 0.OOE+00 6.OOE-08 6.07E-09 2.33E-13 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.OOE+00 7.78E-14 4.70E-07 1.12E-07 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+00 2.09E-09 1. 59E-04 2.73E-05 Ba-140 4.88E-06 6.13E-09 3.21E-07 O.OOE+00 8.75E-15 2.42E-07 1.45E-17 Ba-141 1.25E-11 9. 41E-15 4.20E-13 O.OOE+00 2.8 6E-15 1.49E-07 1.96E-2 6 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.OOE+00 0.OOE+00 1.70E-05 5.73E-05 La-140 4.30E-08 2.17E-08 5.73E-09 0.OOE+00 0.OOE+00 7. 91E-07 2. 64E-07 La-142 8.54E-11 3. B8E-11 9.65E-12 O.OOE+00 7.83E-07 4.52E-05 1. 50E-05 Ce-141 2.49E-06 1. 69E-06 1.91E-07 O.OOE+00 7.60E-09 9.97E-06 2.83E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 0.OOE+00 1.06E-04 9.72E-04 1.02E-04 Ce-144 4.29E-04 1.7 9E-04 2.30E-05 0.OOE+00 2.70E-07 3.51E-05 2.50E-05 Pr-143 1.17E-06 4. 69E-07 5.80E-08 0.OOE+00 8. 81E-13 1.27E-07 2.69E-18 Pr-144 3.76E-12 1.56E-12 1.91E-13 O.OOE+00 4.45E-07 2.7 6E-05 2.16E-05 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.OOE+00 0.00E+00 3.63E-06 1.94E-05 w-187 1.06E-09 8.85E-10 3.10E-10 O.OOE+00 8.75E-09 4.70E-06 1.49E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 O.OOE+00 0. OOE+00 0.OOE+00 0.. 00E+00 K-40 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.62E-05 3.93E-06 Co-57 0.OOE+00 8.65E-08 8.39E-08 0.OOE+00 0.OOE+00 6.OOE-05 7.60E-06 Sr-85 4.OOE-06 0. OOE+00 9.70E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-88 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOEE+00 0.OOE+00 0.OOE+00 Nb-94 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 8.18E-12 3.OOE-07 3.02E-08 Nb- 97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 4.70E-05 9.IOE-05 8.20E-06 Cd-109 0.OOE+OC1 4.90E-05 1.60E-06 0.OOE+00 0.OOE+00 1.20E-04 1.50E-06 Sn-113 8.20E-OE ; 2.70E-07 5.60E-07 1.70E-07 2.10E-09 1.90E-04 1.OOE-05 Ba-133 9.50E-OE5 4.20E-07 2.50E-06 0.OOE+00 2.18E-11 4.34E-07 2.97E-11 Te-134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 0.OOE+00 0.OOE+00 0.OOE+00 Ce-139 0.OOE+OCI 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Hg-203 0.00E+0CS0.OOE+00 0.OOE+0O 0.OOE+00 3-29

Part 11 ODCM - Rev. 15 Table 3-lb TEEN INHALATION DOSE FACTORS

.(zurem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.OOE+00 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 Be-7 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+OO Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-64 1.37E-05 8.95E-06 0.OOE+00 0.OOE+00 0.OOE+Ob 1.16E-05 Cr-51 0.OOE+00 0.OOE+00 1.69E-08 9.37E-09 3. 84E-09 2. 62E-06 3.75E-07 Mn-54 0.OOE+00 6.39E-06 1.05E-06 0.OOE+O0 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.OOE+00 2. 12E-10 3.15E-11 0.OOE+O0 2.24E-10 1. 90E-06 7.18E-06 Fe-S55 4.18E-06 2. 98E-06 6.93E-07 0.OOE+00 0.OOE+OO 1.55E-05 7.99E-07 Fe-5 9 1.99E-06 4.62E-06 1.79E-06 0.OOE+00 0.00OE+00 1.91E-04 2.23E-05 Co-5 8 0.OOE+00 2. 59E-07 3.47E-07 0.OOE+O0 0.OOE+00 1.6BE-04 1.19E-05 Co- 60 0.O0E400 1.89E-0 6 2.48E-06 0.OOE+00 0.OOE+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5. 43E-06 2.47E-06 0.OOE+00 0.OOE+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.OOE+O0 0.OOE+00 1.17E-06 4.59E-06 cu-64 0.OOE+00 2.54E-10 1.06E-10 0.OOE+00 8.O01E-10 l.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.8OE-0 6 O.OOE+00 1.08E-05 1.55E-04 5.83E-06 zn-69 6.04E-12 1.1SE-11 8.07E-13 0.OOE+O0 7.53E-12 1. 98E-07 3.56E-08 Br-83 0.OOE+00 0.OOE+O0 4+.30E-08 0.OOE+00 0.OOE+00 0.00OE+00 0.OOE+00 Br-84 0.OOE+00 0.OOE+00 5.41E-08 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 Br-85 0.OOE+00 0. OOE+O0 2.29E-09 0.OOE+O0 0.OOE+OO 0.OOE+00 0.OOE+00 Rb-86 0.OOE+00 2.38E-05 1.O05E-05 0.OOE+00 0.OOE+O0 0. 0OE+O0 2.21E-06 Rb-B88 0.OOE-I00 6.82E-08 3.40E-08 0. OOE+00 0.OOE+00 0.OOE+00 3.65E-15 Rb-89 0.OOE+00 4.40E-08 2.91E-08 0.OOE+00 0.OOE+00 0.OOE+00 4.22E-17 Sr-89 5.43E-05 0.OOE+O0 1.56E-06 0.OOE+00 0.OOE+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00OE+O0 8.35E-04 0.OOE+00 0.O0E+00 2.06E-03 9.56E-05 Sr- 91 1.10E-08 0.OOE+O0 4.39E-10 0. 00E+00 0.OOE+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0. OOE+O0 5.08E-ll O.OOE+00 0.OOE+0O 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00OE+O0 1.OOE-08 0.OOE+00 0.OOE+00 3.66E-05 6. 99E-05 Y-91M 4.63E-11 0.OOE+O0 1.77E-12 0.00E+00 0.OtE+00 4. OOE-07 3.77E-09 Y- 91 8.26E-05 0. OOE+O0 2 .21E-06 0.OOE+00 0.OOE+00 3.67E-04 5. 11E-05 Y-92 1.84E-09 0.OOE+00 5.36E-11 0.OOE+00 0.OOE+O0 3.35E-06 2.06E-05 Y-93 1.69E-08 0.OOE+O0 4.65E-10 0.0 OE4-0O 0.O00E+06 1.04E-05 7. 24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.OOE+00 8.42E-06 .3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.OOE+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.OOE+00 1.25E-06 9.39E-05 1.21E-05 Mo- 99 0.OOE+00 2.IIE-08 4 .03E-09 0.OOE+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.OOE+00 7.20E-12 1.44E-07 7.66E-07 Tc-l 01 7.40E-15 1.05E-14 1.03E-13 0.OOE+00 1.90E-13 8.34E-08 1.09E-16 Ru- 103 2.63E-07 0.00OE+O0 1.12E-07 0.OOE+00 9.29E-07 9.7 9E-05 1.36E-05 Ru-lOS 1.40E-10 0.OOE+00 5.42E-11 0.OOE+00 1.76E-10 2.27E-ý06 1.13E-05 Ru-106 1.23E-05 0.00OE+00 1.55E-06 0.OOE+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.OOE+00 3.13E-06 8.4 4E-04 3.41E-05 Sb- 12 2 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.00E+00 0.OOE+00 0.OOE+00 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.8BOE-09 0. OOE+O0 3.42E-04 1.24E-05 3-30

ODCM - Rev. 15 Part II Table 3-lb TEEN INHALATION DOSE FACTORS

((mrem per pCi inhaled)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope 6.lOE-07 2.8OE-07 8.34E-08 1.75E-07 O.OOE+00 6.70E-05 9 .38E-06 Te-125m 2.73E-07 5. 48E-07 8.17E-06 2.07E-04 1 L.99E-05 Te-127m 2.25E-06 1.02E-06 1.40E-06 1L.01E-05 1.77E-10 9.IOE-10 2.51E-10 1.14E-10 5.52E-11 Te-127 6.49E-06 2.47E-04 5 *.06E-05 1.74E-06 8.23E-07 2.81E-07 5.72E-07 Te-129m 6.48E-12 3.32E-11 4.12E-07 2T*.02E-07 8.87E-12 4.22E-12 2.20E-12 Te-129 5.49E-08 2.97E-05 7 .76E-05 1.23E-08 7.51E-09 5.03E-09 9.06E-09 Te-131m 7.72E-12 2.92E-07 3.. 89E-09 1.97E-12 1.04E-12 6.30E-13 1.55E-12 Te-131 3.07E-08 2.44E-07 5.61E-05 5.79E-05 Te-132 4.50E-08 3.63E-08 2.74E-08 . 14E-06 3.44E-06 O.OOE+00 1-130 7.80E-07 2.24E-06 8. 96E-07 1.86E-04 O.OOE+00 3.11E-07 3.30E-06 1.83E-03 1.05E-05 4.43E-06 6.14E-06 1-131 8.65E-07 O.OOE+00 1. 59E-07 1-132 1. 99E-07 5.47E-07 1.97E-07 1.89E-05 4.49E-06 O.OOE+00 1.29E-06 1.52E-06 2.56E-06 7.78E-07 3. 65E-04 1-133 4.58E-07 0.OOE+00 2.55E-09

1. 11E-07 2.90E-07 1. 05E-07 4. 94E-06 1-134 7.76E-05 1.86E-06 O.OOE+00 8.69E-07 4.62E-07 1.18E-06 4.36E-07 1-135 4. 69E-05 1.83E-05 1.22E-06 6.28E-05 1.41E-04 6.86E-05 0.OOE+00 Cs-134 0.OOE+00 1.38E-05 2.22E-06 1. 36E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 3.80E-05 1.51E-05 1.06E-06 8.38E-05 1.06E-04 3.89E-05 0.00OE+00 O.OOE+00 Cs-137 8.28E-08 9.84E-09 3.38E-11

5. 82E-08 1.07E-07 5.58E-08 0. O0E+00 Cs-138 1.lIE-13 8.08E-07 8. 06E-07

1. 67E-10 1.18E-13 4.87E-12 0.0 KE+00 Ba-139 2.85E-09 2.54E-04 2.86E-05 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.OOE+00 1.23E-14 4.11E-07 9.33E-14 1.78E-11 1.32E-14 5. 93E-13 0.OOE+00 Ba-141 3.92E-15 2.39E-07 5. 99E-20

4. 62E-12 4.63E-15 2.84E-13 0.0 E+00 Ba-142 0.OOE+00 2. 68E-05 6.09E-05

5. 99E-08 2.95E-08 7.82E-09 0.OOE+00 La-140 0.OOE+00 1.27E-06 1.50E-06 1.20E-10 5.31E-1I 1.32E-11 La-142 .00E+00 1.11E-06 7.67E-05 1.58E-05 3.55E-06 2.37E-06 2.71E-07 0O.OOE+00 Ce-141 1. 08E-08 1.63E-05 3.19E-05 3.32E-08 2.42E-08 2.70E-09 0.OOE+00 Ce-143 1.51E-04 1.67E-03 1.08E-04 Ce-144 6. 11E-04 2.53E-04 3.28E-05 O.OOE+00 3.86E-07 6.04E-05 2.67E-05 Pr-143 1.67E-06 6. 64E-07 8.28E-08 O.OOE+00 1.26E-12 2.19E-07 2.94E-14 5.37E-12 2.20E-12 2.72E-13 O.OOE+O0 Pr-144 6.28E-07 4.65E-05 2.28E-05 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.OOKE+O 0.OOE+OC I 5.92E-06 2.21E-05 w-187 1.50E-09 1.22E-09 4.29E-10 O.OOE+00

) 1.25E-08I 8.11E-06 1.65E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 O.OOE+0C 0.00E+0CI O.OOE+00 O.OOE+00

0. O0E+O0 0.OOE+00 0.00E+0CI O.OOE+OC K-40 I O.OOE+OCI 7.33E-05 3.93E-06 Co-57 0.OOE+00 1.18E-07 1.15E-07I 0.OOE+OC S0.OOE+OC 8.80E-05 6. 90E-06 Sr-85 5.00E-0 6 0.OOE+00 1.30E-OE* 0.OOE+OC 0.OOE+O( O0.OOE+00 0.OOE+00 Y-88 0.OOE+00 0.OOE+00 0.OOE+OC 0.OOE+OC 0.OOE+O( O0.OOE+00 O.OOE+00 Nb-94 0.0 0E+00 0.OOE+00 O.OOE+OC 0.OOE+OC 31.14E-11L 4.91E-07 2.71E-07 Nb-97 3.93E-11 9.72E-12 3.55E-12i O.OOE+O(

6.70E-O0 5 1.60E-04 8.60E-06 0.0OE+00 1.OOE-04 3.40E-OE Cd-109 7 2. 90E-07 r 0.OOE+0( ) 2.OOE-04 1.50E-06 Sn-113 1.50E-05 4.70E-07 9.7OE-01 6 0.OOE+O( 2.80E-0! ? 2.90E-04 9.70E-06

)

4.70E-05 8.OOE-07 3.30E-O(

Ba-133 4.35E-12 3.64E-i2 4.4 6E-1, 2.91E-1: L 6.75E-07 1.37E-09 5.31E-12 Te-134 O.OOE+O( ) 0.OOE+0O) O.OOE+00 0.00E+00 0.OOE+00 0.0 0E+00 O.OOE+O(

Ce-139 ) 0.OOKE+0 0 0.OOE+00 0. OOE+00 Hg-203 0.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O(

3-31

Parti11 ODCM - Rev. 15 Table 3-ic CHILD INHALATION DOSE FACTORS (mxem per pCi inhaled) isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.00E4-OO O.OOE+OO O.OOE+OO Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35F.-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-05 Cr-51 O.OOE+OO O.OOE+OO 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 O.OOE+OO 1.16E-05 2.57E-06 O.OOE+OO 2.71E-06 4.26E-04 6.19E-06 Mn-56 O.OOE+OO 4.48E-10 8.43E-11 O.OOE+OO 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 O.OOE+OO O.OOE+OO 3.OOE-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 O.OOE+OO O.OOE+OO 3.43E-04 1.91E-05 Co-58 O.OOE+OO 4.79E-07 8.55E-07 O.OOE+OO O.OOE+OO 2.99E-04 9.29E-06 Co-60 O.OOE+OO 3.55E-06 6.12E-06 O.OOE+OO O.OOE+OO 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 O.OOE+OO O.OOE+OO 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 O.OOE+OO O.0OE+00 2.21E-06 2.27E-05 Cui-64 O.OOE+OO 5.39E-10 2.90E-10 O.OOE+OO 1.63E-09 2.59E-06 9.92E-06 Zn-ES 1.15E-05 3.06E-05 1.90E-05 O.OOE+OO 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 O.OOE+OO 1.58E-11 3.84E-07 2.75E-06 Br-83 O.OOE+OO O.OOE+OO 1.28E-07 O.OOE+OO O.OOE+OO O.OOE-I-O O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.48E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 6.84E-09 O.OOE+OO O.OOE+OO O.OOE-I-O O.OOE+OO Rb-86 O.OOE+OO 5.36E-05 3.09E-05 O.OOE+OO O.0OE004O O.OOE+OO 2.16E-06 Rb-88 O.OOE+OO 1.52E-07 9.90E-08 O.00E4-OO O.OOE+OO O.OOE+OO 4.66E-09 Rb-89 O.OOE+OO 9.33E-08 7.83E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E-10 Sr-89 1.62E-04 O.OOE+OO 4.66E-06 O.OOE+OO O.OOE+OO 5.83E-04 4.52E-05 Sr-90 2.73E-02 O.OOE+OO 1.74E-03 O.OOE+OO O.OOE+OO 3.99F.-03 9.28E-05 Sr-91 3.28E-08 O.OOE+OO 1.24E-09 O.OOE+OO O.OOE+OO 1.44E-05 4.70E-05 Sr-92 3.54E-09 O.OOE+OO 1.42E-10 O.OOE+OO O.OOE+OO 6.49E-06 6.55E-05 Y-90 1.11E-06 O.OOE+OO 2.99E-08 O.OOE+OO O.OOE+OO 7.07E-05 7.24E-05 Y-91M 1.37E-10 O.OOE+OO 4.98E-12 O.OOE+OO O.OOE+OO 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+OO 6.59E-06 O.OOE+OO O.OOE+OO 7.10E-04 4.97E-05 Y-92 5.50E-09 O.OOE+OO 1.57E-10 O.OOE+OO O.OOE+OO 6.46E-06 6.46E-05 Y-93 5.04E-08 O.OOE+OO 1.38E-09 O.OOE+OO O.OOE+OO 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.OOE-05 O.OOE+OO 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 O.OOE+OO 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 O.OOE+OO 2.33E-06 1.66E-04 l.OOE-05 Mo-99 O.OOE+OO 4.66E-08 1.15E-08 O.OOE+OO 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 O.OOE+OO 1.37E-11 2.57E-07 1.30E-06 Tc-i0i 2.19E-14 2.30E-14 2.91E-13 O.OOE+OO 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 O.OOE+OO 2.90E-07 O.OOE+OO 1.90E-06 1.79E-04 1.21E-05 Ru-lOS 4.13E-10 O.OOE+OO 1.50E-10 O.OOE+OO 3.63E-10 4.30E-06 2.69E-05 Ru-1OE 3.68E-05 O.OOE+OO 4.57E-06 O.OOE+OO 4.97E-05 3.87E-03 1.16E-04 Ag-11rn 4.56E-06 3.08E-06 2.47E-06 O.OOE+OO 5.74E-06 1.48E-03 2.71E-05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 1.55E-05 2.OOE-07 5.41E-06 3.41E-08 O.OOE+OO 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 O.OOE+OO 6.27E-04 1.09E-05 3-32

ODCM - Rev. 15 Part II Table 3-1c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

TOT BODY THYROID KIDNEY LUNG GILLI Isotope BONE LIVER 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. OOE+00 1.29E-04 9.13E-06 1.93E-05 Te-125m 2.31E-06 8.16E-07 1. 64E-06 1.72E-05 4.OOE-04 Te-127m 6.72E-06 1. 91E-09 2.71E-06 1.52E-05 5.30E-I0 Te-127 7.49E-10 2.57E-10 1.65E-10 I.36E-05 4.76E-04 4.91E-05 1.71E-06 5.19E-06 1.85E-06 8.22E-07 6.89E-06 Te-129m 1.93E-i1 6. 94E-il 7. 93E-07 Te-129 2.64E-11 9.45E-12 6.44E-12 1.08E-07 5.56E-05 8.32E-05

2. 64E-08 Te-131m 3.63E-08 1.60E-08 1.37E-08 4.59E-12 1.59E-11 5. 55E-07 3.60E-07 5.87E-12 2.28E-12 1.78E-12 3.72E-05 Te-131 8.58E-08 4.79E-07 1.02E-04 Te-132 1.30E-07 7.36E-08 7.12E-08 0. OOE+00 1.38E-06 4.99E-04 6.61E-06 1-130 2.21E-06 4.43E-06 2.28E-06 2. 13E-05 0. OOE+00 7. 68E-07 4.39E-03 131 1.30E-05 1.30E-05 7.37E-06 0.OOE+00 8.65E-07 5.23E-05 1.69E-06 1-132 5.72E-07 1.10E-06 5.07E-07 9.13E-06 0. OOE+00 1. 48E-06 1.04E-03 1-133 4.48E-06 5.49E-06 2.08E-06 0. 0OE+00 2.58E-07 1.37E-05 8.92E-07 1-134 3.17E-07 5.84E-07 2.69E-07 3.62E-06 0. OOE+00 1.20E-06 2.14E-04 1-135 1.33E-06 2.36E-06 1.12E-06 3.27E-05 1.04E-06 0.OOE+00 8.93E-05 Cs-134 1.76E-04 2.74E-04 6.07E-05 2.58E-05 3.93E-06 1.13E-06 0.OOE+00 Cs-13 6 1.76E-05 4.62E-05 3.14E-05 0.OOE+00 7. 63E-05 2.81E-05 9.78E-07 Cs-13 7 2.45E-04 2.23E-04 3.47E-05 1. 68E-07 1. 84E-08 7.29E-08 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.OOE+00 2.33E-13 1.56E-06 1.56E-05 0.OOE+00 4.98E-10 2. 66E-13 1. 45E-11 2.75E-05 Ba-139 1.17E-06 0.00E+00 5.71E-09 4.71E-04 Ba-140 2.OOE-05 1.75E-08 2.56E-14 7.89E-07 7.44E-08 0.OOE+00 5.29E-11 2.95E-14 1.72E-12 7.41E-10 Ba-141 0.OOE+00 7.87E-15 4.44E-07 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 0.OOE+00 4. 94E-05 6.1OE-05 1.74E-07 6.08E-08 2.04E-08 2.05E-05 La-140 0.OOE+00 0.OOE+00 2.35E-OE 1.53E-05 La-142 3.50E-10 1.11E-10 3.49E-11 i. 47E-04 0.OOE+00 2.31E-06 1.06E-05 5.28E-06 7.83E-07 5 3.44E-05 Ce-141 7.77E-09

• 0.OOE+00 2.26E-08 3.12E-0! 1.05E-04 Ce-143 9.89E-08 5.37E-08 3.23E-01 I 0.OOE+00 ) 3.17E-04 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.OOE+OC 8. lIE-01 1.17E-041 2.63E-05 4.99E-06 1.50E-06 2.47E-07 P 5.32E-08 Pr-143 0.OOE+OC I 2.64E-12 4.23E-0*

Pr-144 1.61E-11 4.99E-12 8.OE-132 1.30E-0( i 8.87E-0! 5 2.22E-05

• 0.OOE+OC Nd-147 2.92E-06 2.36E-06 1.84E-01 0.OOE+0( ) 1.11E-0! 5 2.46E-05 0.OOE+OC 4.41E-09 2.61E-09 1.17E-OS 5 1.73E-05 W-187 I 0.OOE+0( 2.63E-0E1 1.57E-0!

Np-239 1.26E-07 9.04E-09 6.35E-OS 0.00E+01 ) 0.OOE+00 S0.OOE+0( O0.OOE+0(

0.OOE+00 0.OOE+00 0.OOE+OC7 0.OOE+0( 0.OOE+0( 0 1.37E-0,I 3.58E-06 K-40 0.OOE+00 2.44E-07 2.88E-0* 4 5.50E-06 Co-57 6 0.OOE+0( 0.OOE+O(2 1.50E-0, Sr-85 1.20E-05 0.OOE+00 3.20E-O( 0 0.OOE+0( 0 0.OOE+01 0 0.OOE+00 0.OOE+0(

Y-88 0.OOE+00 0.OOE+00 0.OOE+OC 0.OOE+0( 0 0.00E+0( 0 0.OOE+01o 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O( 7 7.51E-06 Nb-94 0.OOE+0( O 2.31E-1: L 9.24E-0' Nb-97 1.16E-10 2.08E-I1 9.73E-1I 1.70E-0, 1 4 3.OOE-0 4 8.10E-06 5 0.OOE+0(

Cd-109 0.OOE+00 1.90E-04 8.00E-01 0 3.60E-0 4 1.30E-06 5 7.10E-0' 7 0.OOE+01 Sn-113 3.80E-05 8.90E-07 2.30E-01 0 5.40E-0* 9 5.20E-0 4 8.30E-06 5 0.00E+01 Ba-133 1.10E-04 1.1OE-OE I. OOE-0! 1 1.23E-0 6 4.87E-07 2 1.24E-1: 1 5.71E-lI Te-134 1.53E-11 8.81E-12 9.40E-i. 0 0.OOE+0 0 0.OOE+0 0 0.OOE+00 0 0.OOE+01 Ce-139 0.OOE+00 0.00E+0C1 0.OOE+0( D 0.OOE+O 0 0.OOE+0 0 0.OOE+00 00.OOE+0' Hg-20 3 0.OOE+00 0.O.OE+OC I 0.OOE+0(

3-33

Part 11 ODCM - Rev. 15 Table 3-id INFAN~T INHALATION DOSE FACTORS

.(mrem per pCi inhaled)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope H-3 0. OOE+00 4 .62E-07 4.62E-07 4.62E-07 4. 62E-07 4.62E-07 4 .62E-07 Be-7 0. OOE+00 0.OOE+O0 0. OOE+00 0. OOE+00 0.OOE+O0 O.OOE+00 0~.0OE+O0 7.54E-06 7.54E-06 7.54E-06 7.54E-06 .54E-06 Na-2 4 7.54E-0 6 7.54E-06 P-32 1.45E-03 8.03E-05 5. 53E-05 0. OOE+O0 0. OOE+O0 0. OOE+O0 3 .15E-05 Cr-5i 0. OOE+00 0.OOE+00 6.39E-08 4. 11E-08 9.45E-09 9.17E-06 ; ~.55E-07 Mn-54 0. OOE+0O 1.81E-05 3.56E-06 0. OOE+00 3. 56E-06 7.14E-04 5.04E-06 Nn-5 6 0. OOE+00 1.1OE-09 1. 58E-10 0. OOE+0O 7. 86E-10 8 *95E-06 5.12E-05 Fe-55 1. 41E-05 8.3 9E-06 2.38E-06 0. 0OK+0O 0.OOE+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1. 68E-05 6.77E-06 0. OOE+0O 0.OOE+O0 7.25E-04 1.77E-05 Co-SB 0. OOE+00 8.7 1E-07 1.30E-06 0. OOK+0O 0.O0OE+0O 5.55E-04 7.95E-06 Co-60 0.OOE+00 5.73E-06 8.41E-06 0.OOE+00 0.OOE+00 3.22E-03 2. 28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.OOE+00 0.0OE+0O 1. 4 9E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.7 9E-11 0.OOK+00 0.OOE+00 5.80E-06 3.58E-05 Cu-64 0.OOE+0O 1.34E-09 5.53E-10 0. OOE+0O 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4. 47E-05 2.22E-05 0. OOE+OO 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-1i 6.91E-11 5. 13E-12 0.OOE+O0 ,2.87E-11 1.05E-06 9.44E-06 Br-83 0.OOE+0O 0.OOE+00 2'.72E-07 0.OOE+OO 0.OOE+OO 0. OOE+0O 0.OOE+OO Br-84 0.OOE+00 0.OOE+00 2.8 6E-07 0.OOE+00 0.OOE*0O O.OOE+O0 0.OOE+0O Br-85 0. OOE+00 0.OOE+O0 1.46E-08 0.OOE+0O 0.OOE+00 0.OOE+0O O.OOE+00 Rb-8 S 0.O0OE+ 00 1.36E-04 6.30E-05 0.O0OE+ 00 0.OOE+O0 0. OOE+00 2.17E-06 Rb-B88 0.O0OE+ 00 3.9BE-07 2.05E-07 O.OOE+O0 O.OOE+0O 0.OOE+00 2. 42E-07 Rb-89 0.OOE+O0 2.29E-07 1. 47E-07 O.OOE+00 0. OOE+O0 0.OOE+O0 4.87E-08 Sr-B 9 2.84E-04 0.OOE+00 8.15E-06 0.OOE+0O 0.OOE+00 1. 45E-03 4 .57E-05 Sr-90 2.92E-02 0.OOE+00 1.85E-03 0.OOE+00 0.0 OE+00 B. 03E-03 9.36E-05 Sr- 91 6.83E-08 0.OOE+O0 2.47E-09 0. 0OOE+ 00 0.OOE+00 3.7 6E-05 5.24E-05 Sr-92 7.50E-09 0.OOE+O0 2.7 9E-10 0.00E4-00 .0.00E+00 1.70E-05 1.OOE-04 Y- 90 2.35E-06 0.OOE+00 6.30E-08 0.OOE+0O 0. O0E400 1. 92E-04 7.43E-05 Y- 91M 2.91E-10 0.OOE+00 9. 90E-12 0. 0 OE+0O 0.OOE+00 1.99E-06 1.6SE-06 Y- 91 4.20E-04 0. OOE+00 1.12E-05 0.OOE+00 0. OOE+00 1.75E-03 5.02E-05 Y- 92 1.17E-08 0. OOE+00 .3.29K-10 0. 00E+00 O.OOE+00 1.75E-05 9.04E-05 Y- 93 1.07E-07 0. OOE+00 2.91E-09 O.OOE+O0 0.OOE+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1. 99E-05 1.4 5E-OS 0.OOE+00 2.22E-05 1. 25E-03 1.55E-05 Zr-97 1.07E-07 1. 83E-08 8.3 6E-09 O.OOE+0O 1.85E-08 7.88E-05 1.OOE-04 Nb-95 1.12E-05 4.59E-06 2.70EK-06 0.OOE+0O 3.37E-06 3.42E-04 9.05E-06 mo-99 O.OOE+0O 1. 18E-07 2.31lE-08 0.OOE+00 1.89E-07 9.63E-05 3. 48E-05 Tc-9 9M 9. 98E-13 2.06E-12 2.66K-il 0. OOE+00 2.22E-11 5.79E-07 1.45E-06 TC-101 4.65E-14 5.88E-14 5.80OE-13 0.OOE+00 6.99E-13 4 . 17E-07 6.03E-07 Ru-103 1.4 4E-06 0. OOE+00 4.85E-07 0.OOE+0O 3.03E-0E 3.94E-04 1. 15E-05 Ru-105 8.74E-10 0. OOE+0O 2. 93E-10 0.OOE+OO 6.42E-lC I1.12E-0 5 3.4 6E-05 Ru- 106 6.20E-05 0.OOE+00 7.77E-06 0 .OOE+00 7.61E-0-c 8.26E-03 1. 17E-04 Ag-110n 7.13E-06 5.16E-06 3.57E-06 0.OOE+00 7. 80E-0( 2. 62E-03 2.36E-05 Sb-i22 0.OOE+00 0. OOE+0O 0. OOE-I00 0.00E+00 0.OOE+OC 1 0.OOE+00 0. OOE+OO Sb-124 2.71E-05 3.97E-07 8.5 6E-06 7.18E-08 0. OOE+OC I 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.7 8E-06 4.45SE-08 0. OOE+OC )l.17E-03 1.05E-05 3-34

Part II ODCM - Rev. 15 Table 3-id INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.OOE+00 3.19E-04 9.22E-06 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127m 1.19E-05 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-127 1.59E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129m 1.01E-05 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-129 5. 63E-11 2.48E-11 3.93E-08 2.59E-08 6.38E-08 1. 89E-07 1.42E-04 8.51E-05 Te-131m 7.62E-08 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-131 1.24E-11 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 Te-132 2.66E-07 3.98E-06 1.14E-03 L.09E-05 0.OOE+00 1. 42E-06 1-130 4.54E-06 9.91E-06 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.OOE+00 7.56E-07 1-131 2.71E-05 8.99E-07 1.21E-04 2.82E-06 0.OOE+00 1.36E-06 1-132 1.21E-06 2.53E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 0.OOE+00 1.54E-06 1-133 9.46E-06 4.75E-07 3.18E-05 1.49E-06 0.OOE+00 9.21E-07 1-134 6.58E-07 1.34E-06 1.98E-06 4. 97E-04 6.05E-06 0. OOE+00 1.31E-06 1-135 2.76E-06 5.43E-06 5.02E-04 5.32E-05 O.OOE+00 1..36E-04 5. 69E-05 9.53E-07 Cs-134 2.83E-04 9.61E-05 3.78E-05 0. OOE+00 4..03E-05 8.40E-06 1.02E-06 Cs-136 3.45E-05 4.37E-04 3.25E-05 0.0OE+00 1.23E-04 5.09E-05 9.53E-07 Cs-137 3. 92E-04 2.84E-07 0. OOE+00 2.93E-07 4.67E-08 6.26E-07 Cs-138 3. 61E-07 5.58E-07 7.03E-13 3.07E-11 O.OOE+O0 4.23E-13 4.25E-06 3.64E-05 Ba-139 1.06E-09 4.OOE-08 2.07E-06 0.0OE+00 9.59E-09 1.14E-03 2.74E-05 Ba-140 4.OOE-05 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-141 1.12E-10 7.70E-14 2.36E-14 1.40E-12 0.OOE+00 1.36E-14 1. 11E-06 4.95E-07 Ba-142 2.84E-11 3.68E-08 0.OOE+00 0.OOE+00 1.20E-04 6.06E-05 La-140 3.61E-07 1.43E-07 6.46E-11 0. OOE+00 0.OOE+00 5.87E-06 4.25E-05 La-142 7.36E-10 2.69E-10 1.42E-06 0.OOE+00 3.75E-06 3. 69E-04 1.54E-05 Ce-141 1.98E-05 1.19E-05 1.38E-07 1.58E-08 0. OOE+00 4.03E-08 8. 30E-05 3.55E-05 Ce-143 2.09E-07 8.65E-04 1.26E-04 0.OOE+00 3.84E-04 7.03E-03 1.06E-04 Ce-144 2.28E-03 2.66E-05 3.74E-06 4.99E-07 O.00E+00 1.41E-06 3.09E-04 Pr-143 1.OOE-05 1.32E-11 1.72E-12 0.OOE+00 4.80E-12 1.15E-06 3.06E-06 Pr-144 3.42E-11 5.81E-06 3.57E-07 0.OOE+00 2.25E-06 2.30E-04 2.23E-05 Nd-147 5.67E-06 6.44E-09 2.23E-09 0.OOE+00 0.OOE+00 2.83E-05 2.54E-05 W-187 9.26E-09 1.78E-05 2.65E-07 2.37E-08 1.34E-08 0.OOE+00 4.73E-08 4.25E-05 Np-239 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 K-40 2.71E-04 3.47E-06 0.OOE+00 4.65E-07 4.58E-07 0.OOE+00 0.OOE+00 Co-57 3.OOE-04 4. 80E-06 2.70E-05 0.OOE+00 5.40E-06 0. OOE+00 0.OOE+00 Sr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-88 0. OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0. OOE+00 0. OOE+00 0.OOE+00 Nb-94 4.07E-l1 2.37E-06 1.92E-05 Nb-97 2.44E-10 5.21E-11 1. 88E-11 0.OOE+00 2.60E-04 1. 00E-05 0.OOE+00 2.OOE-04 6.20E-04 8.00E-06 Cd-109 0.OOE+00

3. 60E-06 1. 30E-06 0.OOE+00 7.80E-04 1.20E-06 Sn-113 6.OOE-05 1.60E-06 1.70E-06 1. 30E-05 0.OOE+00 8.90E-09 9.1OE-04 7.70E-06 Ba-133 1.90E-04 2.04E-11 1. 68E-11 2.91E-I1 9.59E-11 2.93E-06 2.53E-06 Te-134 3.18E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ce-139 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Hg-203 0.OOE+00 3-35

Part 11 ODCM - Rev. 15 Table 3-2 2

Total Body & Skin Ground Plane Dose Factors (mrem/hr per pCi/m) with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody (DFg) Skin(DFs) 1.OOE-02 0.OOE+00 0. 00E+00 H-3 12.350 53.300 1.OOE-04 0.OOE+00 0. OOE+00 Be-7 Na-24 15.000 4.OOE-02 2.50E-08 2.90E-08 P-32 14.290 2.50E-02 0.OOE+00 0.OOE+00 27.704 2.20E-03 2.20E-10 2.60E-10 Cr-51 312.500 2.50E-04 5.80E-09 6.80E-09 Mn-54 Mn-56 2.578 2.50E-04 1.10E-08 1. 30E-08 2.700 1.20E-03 0.OOE+00 0. OOE+00 Fe-55 Fe-59 44.529 1.20E-03 8.OOE-09 9.40E-09 70.800 1.OOE-03 7.OOE-09 8.20E-09 Co-58 5.271 1.OOE-03 1.70E-08 2. OOE-08 Co-60 96.000 6.70E-03 0.OOE+00 0.OOE+00 Ni-63 2.520 6.70E-03 3.70E-09 4.30E-09 Ni-65 Cu-64 12.701 1.40E-02 1.50E-09 1.70E-09 243.900 3.90E-02 4.0OE-09 4. 60E-09 Zn-65 0.950 3.90E-02 0.OOE+00 0.OOE+00 Zn-69 2.390 5. OOE-02 6.40E-11 9.30E-11 Br-83 0.530 5.OOE-02 1.20E-08 1.40E-08 Br-84 0.050 5.OOE-02 0.OOE+00 0. OOE+00 Br-85 18.660 3.00E-02 6.30E-10 7.20E-10 Rb-86 0.297 3.OOE-02 3.50E-09 4. OOE-09 Rb-88 Rb-89 0.253 3.OOE-02 1.50E-08 1. 80E-08 Sr-89 50.500 8.00E-04 5.60E-13 6.50E-13 29.120 8. OOE-04 0.OOE+00 0.OOE+00 Sr-90 9.500 8.OOE-04 7.10E-09 8.30E-09 Sr-91 Sr-92 2.710 8;OOE-04 9.OOE-09 1.OOE-08 2.667 1.00E-05 2.20E-12 2.60E-12 Y-90 0.829 1.OOE-05 3.80E-09 4.40E-09 Y-91m 58.510 1.OOE-05 2.40E-11 2.70E-11 Y-91 3.540 1. OOE-05 1. 60E-09 1. 90E-09 Y-92 10.100 1.OOE-05 5.70E-10 7.80E-10 Y-93 63.980 5. OOE-06 5.OOE-09 5. 80E-09 Zr-95 16.900 5.OOE-06 5.50E-09 6.40E-09 Zr-97 35.150 2.50E-03 5.10E-09 6.OOE-09 Nb-95 2.750 7.50E-03 1.90E-09 2.20E-09 Mo-99 6.020 2.50E-02 9.60E-10 1.IOE-09 Tc-99m 0.237 2.50E-02 2.70E-09 3.OOE-09 Tc-101 39.280 1.OOE-06 3.60E-09 4.20E-09 Ru-103 4.440 1.OOE-06 4.50E-09 5.1OE-09 Ru-105 368.200 1.OOE-06 1.50E-09 1.80E-09 Ru-106 249.900 5.OOE-02 1.80E-08 2.lOE-08 Ag-ll0m 2.700 1.50E-03 0.OOE+00 0.OOE+00 Sb-122 60.200 1.50E-03 1.30E-08 1.50E-08 Sb-124 2.770 1.50E-03 3.10E-09 3.50E-09 Sb-125 3-36

ODCM - Rev. 15 Part II Table 3-2 2

Total Body & Skin Ground Plane Dose Factors (mrem/hr per pCi/m )

(Fm, cow) with Isotope half-life and Stable Element Tranfer Data Ground Plane Dose Factors Halflife unit Fm TotBody (DFg) Skin (DFs)

Isotope 4.80E-11 Te-125m 58.000 D 1.OOE-03 3.50E-11 1.30E-12 D 1.OOE-03 1.lOE-12 Te-127m 109.000 1.lOE-11 H 1.00E-03 1.OOE-l1 Te-127 9.350 9.00E-10 D 1.OOE-03 7.70E-10 Te-129m 33.600 8.40E-10 H 1.OOE-03 7.1OE-10 Te-129 1.160 9.90E-09 H 1.OOE-03 8.40E-09 Te-131m 30.000 2.60E-06 H 1.OOE-03 2.20E-09 Te-131 0.417 2. OOE-09 D 1.OOE-03 1.70E-09 Te-13 2 3.258 1.70E-08 H 6.OOE-03 1.40E-08 1-130 12.360 3.40E-09 D 6.OOE-03 2.80E-09 1-131 8.040 2.00E-08 H 6.OOE-03 1.70E-08 1-132 2.300 4.50E-09 H 6.OOE-03 3.70E-09 1-133 20.800 1.90E-08 H 6.OOE-03 1. 60E-08 1-134 0.877 1.40E-08 H 6.OOE-03 1.20E-08 1-135 6.610 1.40E-08 Y 1.20E-02 1.20E-08 Cs-134 2.062 1.70E-08 D 1.20E-02 1. 50E-08 Cs-136 13.100 4.90E-09 Y 1.20E-02 4.20E-09 Cs-137 30.000 2.40E-08 H 1.20E-02 2. 1OE-08 Cs-138 0.537 2.70E-09 H 4. OOE-04 2.40E-09 Ba-13 9 1.378 2.40E-09 D 4.OOE-04 2.1OE-09 Ba-14 0 12.740 4. 90E-09 H 4.OOE-04 4.30E-09 Ba-141 0.304 9.00E-09 H 4.OOE-04 7.90E-09 Ba-142 0.177 1.70E-08 D 5.OOE-06 1.50E-08 La-140 1.678 1.80E-08 H 5.OOE-06 1.50E-08 La-14 2 1.542 6.20E-10 D 1.OOE-04 5.50E-10 Ce-141 32.501 2.50E-09 H 1. OOE-04 2..20E-09 Ce-143 33.000 3.70E-10 D 1. OOE-04 3.20E-10 Ce-14 4 284.300 0.0 0E+00 D 5.OOE-06 0.OOE+00 Pr-14 3 13.560 2.30E-10 H 5.OOE-06 2.OOE-10 Pr-14 4 0.288 1.20E-09 D 5.OOE-06 1.OOE-09 Nd-147 10.980 3.1OE-09 3.60E-09 23.900 H 5. OOE-04 W-187 5. OOE-06 9.50E-10 1.10E-09 2.360 D Np-239 0.OOE+00 0.OOE+00 1.28E+09 Y 1.OOE-02 K-40 9. 1OE-10 1.OOE-09 270.900 D 1.OOE-03 Co-57 0.OOE+00 0.OOE+00 64.840 D 8.OOE-04 Sr-85 0.00E+00 0.OOE+00 106.640 D 1.OOE-05 Y-88 0.OOE+00 0.00E+00 2.03E+04 Y 2.50E-03 Nb-94 4. 60E-09 5.40E-09 1.202 H 2.50E-03 Nb-97 0.OOE+00 0.OOE+00 1.271 Y 1.20E-04 Cd-109 0.OOE+00 0.OOE+00 115.100 D 2.50E-03 Sn-113 4.OOE-04 0.00E+00 0.OOE+00 10.740 Y Ba-133 1.OOE-09 1.20E-09 0.697 H 1.OOE-03 Te-13 4 1.OOE-04 0.OOE+00 O.OOE+00 137.660 D Ce-139 0.OOE+00 0.OOE+00 46.600 D 3.80E-02 Hg-203 3-37

ODCM - Rev. 15 Part II Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

TOT BODY THYROID KIDNEY LUNG GILLI Isotope BONE LIVER

.05E-07 1 .05E-07 0.00E+00 1.05E-07 1.05E-07 10.OOE+00 1 .05E-07 1 .05E-07 H-3 6 *.58E-09 0 .00E+00 1 .08E-06 2.77E-09 6.26E-09 3.10E-09 ( 1 .70E-06 Be-7 L.70E-06 1 .70E-06 1 .70E-06 Na-24 1.70E-06 1.70E-06 1.70E-06 I 0 .00E+00 2 *.17E-05 0.00E+00 C .00E+00 P-32 1.93E-04 1.20E-05 7.46E-06 5 .86E-10 3 .53E-09 6 .69E-07 1.59E-09 Cr-51 0.00E+00 0.00E+00 2.66E-09 0).00E+00 1 .40E-05 0.00E+00 1*.36E-06 Mn-54 0.OOE+00 4.57E-06 8.72E-07 I 0).00E+00 3 .67E-06 0.00E+00 *.46E-07 Mn-56 0.00E+00 1. 15E-07 2.04E-08 0.OOE+00 CO.00E+00 1L.06E-06 1 .09E-06 2.75E-06 1.90E-06 4.43E-07 31.40E-05 Fe-55 0.00E+00 0).00E+00 2 .85E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 ).00E+00 C C1.00E+00 1 .51E-05 0.OOE+00

0. OOE+00 7.45E-07 1.67E-06 Co-58 0.00E+00 C0.OOE+00 C3.OOE+00 41.02E-05 0.00E+00 2.14E-06 4.72E-06 . 88E-06 Co-60 0.00E+00 (0.OOE+00 C1.00E+00 I Ni-63 1.30E-04 9. 01E-06 4.36E-06 0.OOE+00 C).00E+00 3L.74E-06 0.00E+00 Ni-65 5.28E-07 6.86E-08 3.13E-08 .OOE+0.0 7.10E-06 8.33E-08 3.91E-08 0.OOE+00 2.10E-07 Cu-64 0.00E+00 1.03E-05 ).OOE+00 9.70E-06 0.OOE+00 Zn-65 4 .84E-06 1. 54E-05 6.96E-06 L.28E-08 ).00E+00 2. 96E-09 0.00E+00 1.03E-08 1. 97E-08 1.37E-09 5.79E-08 Zn-69 0.00E+00 I0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.OOE+00 4.09E-13 0.OOE+00 Br-84 0.OOE+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0. 003+00 2.14E-09 4. 16E-06 Br-85 0.00E+00 0.00E+00 0.OOE+00 Rb-86 0.OOE+00 2. 11E-05 9.83E-06 0. OOE+00 8 .36E-19 0.00E+00 0.OOE+00 Rb-88 0. 00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 2.33E-21 0.00E+00 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.OOE+00 4.94E-05 0.OOE+00 0.OOE+00 Sr-89 3.08E-04 0. 00E+00 8.84E-06 0.00E+00 0.0 0E+00 0.00E+00 2.19E-04 7.58E-03 0.00E+00 1.86E-03 2.70E-05 Sr-90 0. 00E+00 0.OOE+00 0.00E+00 Sr-91 5.67E-06 0. 00E+00 2.29E-07 0.OOE+00 0.OOE+00 4.26E-05 0.00E+00 2.15E-06 0. 00E+00 9.30E-08 1.02E-04 Sr-92 0.00E+00 0.00E+00 0.OOE+00 Y-90 9.62E-09 0.00E+00 2.58E-10 0.OOE+00 0.00E+00 2.67E-10 3.523-12 0.OOE+00 Y-91m 9.09E-11 0. 00E+00 0.00E+00 7.76E-05 0.00E+00 0.00E+00 Y-91 1.41E-07 0. 00E+00 3.77E-09 0.00E+00 0. 00E+00 1. 48E-05 0.OOE+00 Y-92 8.45E-10 0. 00E+00 2.47E-11 0.OOE+00 0.00E+00 0.OOE+00 8.50E-05 2.68E-09 0. 00E+00 7.40E-11 3.09E-05 Y-93 0. OOE+00 1.53E-08 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.05E-04 0.00E+00 5.12E-10 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 3.42E-09 0.00E+00 2. 10E-05 6.22E-09 3.46E-09 1.86E-09 9. 99E-06 Nb-95 0.OOE+00 9.76E-06 0.00E+00 Mo-99 0. 00E+00 4.31E-06 8.20E-07 0.00E+00 1.06E-08 3.42E-10 4.13E-07 2.47E-10 6.98E-10 8.89E-09 1.10E-21 Tc-99m 0.OOE+00 6;59E-09 1.87E-10 Tc-101 2.54E-10 3.66E-10 3.59E-09 0. 00E+00 7.06E-07 0. 00E+00 2.16E-05

1. 85E-07 0. 00E+00 7.97E-08 9.42E-06 Ru-103 0.00E+00. 1.99E-07 0 OOE+00 Ru-105 1. 54E-08 0. 00E+00 6. 08E-09 5.31E-06 0.00E+00 1.78E-04 0.00E+00 Ru-106 2.75E-06 0. 00E+00 3.48E-07 2.91E-07 0.00E+00 6.04E-05 0.00E+00

1. 60E-07 1.48E-07 8.79E-08 7.60E-05 Ag-1ift 3. 1OE-09 0.00E+00 1.20E-07 Sb-122 2. 00E-07 4.60E-09 6.90E-08 6. 80E-09 0.00E+00 2.18E-06 7. 95E-05

2. 80E-06 5.30E-08 1.10E-06 1.97E-05 Sb-124 1.82E-09 0.00E+00 1.38E-06 Sb-125 1.79E-06 2. 00E-08 4.26E-07 3-38

ODCM - Rev. 15 Part 11 Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope

2. 68E-06 9.71E-07 3.59E-07 8.06E-07 1 .09E-05 CI.OOE+00 1 .07E-05

.27E-05 Te-125m 1.73E-06 2 .75E-05 CI.OOE+00 2 Te-127m 6.77E-06 2.42E-06 8.25E-07 .48E-07 C .OOE+00 8 . 68E-06 8.15E-08 4 Te-127 1.lOE-07 3.95E-08 2.38E-08 .00E+00 5 .79E-05 3.95E-06 4 .80E-05 C Te-129m 1.15E-05 4.29E-06 1.82E-06 i.32E-07 ).OOE+00 0 2 *.37E-08 2.41E-08 1 Te-129 3.14E-08 1.18E-08 7.65E-09 I.57E-06 C).OOE+00 8 *.40E-05 1.34E-06 8 1.73E-06 8.46E-07 7.05E-07 Te-131m EI.63E-08 ().OOE+00 2:.79E-09 Te-131 1. 97E-08 8.23E-09 6.22E-09 1.62E-08 1.57E-05 0.00E+00 7 .71E-05 1.80E-06 1 Te-132 2.52E-06 1.63E-06 1.53E-06 .48E-06 0.OOE+00 I .92E-06 7.56E-07 2.23E-06 8.80E-07 1.89E-04 1-130 1.95E-03 L.02E-05 ).OOE+00 1*.57E-06 4.16E-06 5.95E-06 3.41E-06 .02E-07 1-131 1.90E-05 3.65E-07 0.00E+00 3 1-132 2.03E-07 5.43E-07 1. 90E-07 4.31E-06 0.OOE+00 2.22E-06 3.63E-04 1.42E-06 2.47E-06 7.53E-07 2.51E-10 1-133 4.99E-06 4.58E-07 0.00E+00 1-134 1.06E-07 2.88E-07 1.03E-07 1.86E-06 0.OOE+00 3L.31E-06 7.65E-05 1-135 4.43E-07 1.16E-06 4.28E-07 1.59E-05 2.59E-06 0.OOE+00 4.79E-05 Cs-134 6.22E-05 1.48E-04 1. 21E-04 1.43E-05 1.96E-06 Z.92E-06 0.OOE+00 Cs-13.6 6.51E-06 2.57E-05 1.85E-05 1.23E-05 2. 1lIE-06 0.OOE+00 3.70E-05 Cs-137 7.97E-05 1.09E-04 7.14E-05 8.01E-08 7.91E-09 4. 65E-13 I

Cs-138 5.52E-08 1.09E-07 5.40E-08 0.OOE+00 6.46E-11 3.92E-il 1.72E-07 0.OOE+00 9.70E-08 6.91E-11 2.84E-09 4.18E-05 Ba-139 2.55E-08 1.33E-06 0.ooE+0O 8.67E-09 1.46E-08 Ba-140 2.03E-05 2.02E-11 2.22E-17 0.OOE+00 3.31E-11 Ba-141 4.71E-08 3.56E-11 1.59E-09 1.85E-i1 1.24E-11 3. OOE-26 0.OOE+00 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.OOE+00 9.25E-05 0.OOE+00 0.OOE+00 La-140 2.50E-09 1.26E-09 3.33E-10 0.OOE+00 O.OOE+00 4.25E-07 0.OOE+00 La-142 1.28E-10 5.82E-11 1.45E-li 0.0 0E+00 2.42E-05 0.OOE+00 2.94E-09 Ce-141 9.36E-09 6.33E-09 7.18E-10 5.37E-10 0.OOE+00 4.56E-05 0.OOE+00 Ce-143 1.65E-09 1.22E-06 1. 35E-10 0.OOE+00 1.65E-04 0.OOE+00 1.21E-07 Ce-144 4.88E-07 2.04E-07 2.62E-08 2.13E-09 O.OOE+00 4.03E-05 0.OOE+00 Pr-143 9.20E-09 3.69E-09 .4.56E-10 0.OOE+00 4.33E-18 0.OOE+00 7.05E-12 Pr-144 3.01E-11 1.25E-11 1.53E-12 4.25E-09 0.OOE+00 3.49E-05 Nd-147 6.29E-09 7.27E-09 4.35E-10 0. OOE+00 0.OOE+00 0.OOE+00 2.82E-05 0.OOE+00 W-187 1.03E-07 8.61E-08 3.01E-08 2.40E-05 1.17E-10 6.45E-11 0. OOE+00 3.65E-10 0.OOE+00 Np-239 1.19E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 K-40 0.OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 4.44E-06 0.OOE+00 Co-57 0.OOE+00 1.75E-07 2.91E-07 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 Sr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 Nb-94 0.OOE+00 0.OOE+00 0.OOE+00 1.54E-lI 0.OOE+00 4.87E-08 0.OOE+00 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Cd-109 0.OOE+00 0.OOE+00 0.OOE+00 Sn-113 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00

0. OOE+00 Ba-133 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 3.59E-11

2. 83E-08 2.05E-07 Te-134 3.24E-08 2.12E-08 1.30E-08 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Ce-139 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 Hg-203 0. OOE+00 0.OOE+00 O.OOE+00 3-39

Part 11 ODCM -Rev. 15 Table 3-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.OOE+00 1.0 6E-07 1.0 6E-07 1.06E-07 1.06E- 07 1. 06E-07 1.06E-07 Be-7 3.96E-09 8.87E-09 4.4 3E-09 0.OOE+00 9. 40E-09 0.OOE+00 1.08E-06 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.7 6E-04 1.71E-05 1.07E-05 0. OOE+00 0. OOE+00 0.OOE+0O 2.32E-05 Cr-Si 0.OOE+00 0.00OE400 3.60E-09 2.OOE-09 7.8 9E-10 5. 14E-09 6.05SE-07 Mn-54 0.OOE+00 5.90E-06 1.17E-06 0. OOE+O0 1.7 6E-06 0. 00E+00 1.21E-05 Mn-S 6 0.OOE+00 1. 58E-07 2.81E-08 O.OOE+00 2.OOE-07 0. OOE+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.OOE+00 0.OOE+O0 1.70E-06 1.16E-06 Fe-S 9 5.87E-06 1. 37E-05 5.2 9E-06 0.OOE+00 0.OOE+O0 4.32E-06 3.24E-05 Co-58 0. OOE+00 9.72E-07 2.24E-06 0. OOE+00 0.OOE+0O 0.OOE+0O 1.34E-05 Co- 60 0.0OE+00 2.8 1E-06 6.33E-06 0.OOE+00 0.00E+00 0.OOE+0O 3.66E-05 Ni-63 1. 77E-04 1.25E-05 6. OOE-06 0. OOE+00 O.OOE+OO 0.00E+0O 1.99E-06 Ni-65 7 . 4 9E-07 9.57E-08 4.3 6E-08 0.OOE+00 O.OOE+OO 0.00OE+00 5.19E-06 Cu- 64 0.OOE+00 1.15E-07 5.4 1E-08 0.OOE+00 2. 91E-07 0.OOE+00 8.92E-06 Zn-65 5.7 6E-06 2.OOE-05 9.33E-06 0.OOE+00 1.28E-05 0. 0OE+00 8. 47E-06 Zn-69 1.47E-08 2.80E-08 1. 96E-09 0.OOE+00 1.83E-08 0. OOE+0O 5. 16E-08 Br-83 0. OOE+00 0.O0E+00 5.7 4E-08 0.OOE+00 0. OOE+OO 0. OOE+0O 0. 0OE+00 Br-84 0.OOE+0O 0.00E+00 7 .22E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-85 0.OOE+00 0.00E+00 3.05E-09 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Rb-86 0.OOE+0O 2.98E-05 1.40E-05 0.00E+00 O.OOE+00 0.O0OE+O00 4.41E-06 Rb-8 8 0.OOE+00 8. 52E-08 4 .54E-08 0.OOE+00 0.OOE+00 0. OOE+00 7.30E-15 Rb-8 9 0.OOE+0O 5.50E-08 3.8 9E-08 0.OOE+0O 0.OOE+00 0. OOE+0O 8.43E-17 Sr-89 4.40E-04 0. O0E+00 1.26E-05 0.OOE+00 0.OOE+00 5.24E-05

0. OOE+O0 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.OOE+00 0.OOE+00 2.33E-04 Sr-92. 8.07E-06 0. OOE+00 3.21E-07 0.OOE+00 0.OOE+00 0.OOE+00 3.66E-05 Sr-92 3.05E-06 0.OOE+00 1. 30E-07 0.OOE+00 0.OOE+00 0.OOE+00 7.77E-05 Y-90 1.37E-08 0.OOE+00 3. 69E-10 0.OOE+00 0.OOE+O0 0.OOE+00 1.13E-04 Y- 9 m 1.29E-10 0.OOE+00 4 .93E-12 0.OOE+00 0.OOE+00 0.OOE+00 6.09E-09 Y-91 2.01E-07 0.OOE+00 5.3 9E-09 0.OOE+00 0.OOE+OO 0.OOE+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.OOE+00 0.OOE+00 0.OOE+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1. 05E-10 0.OOE+00 0. OOE+0O 0.OOE+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8. 94E-09 0.OOE+O0 1. 91E-08 .0. OOE+0O 3.OOE-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0. OOE+00 7.l11E-10 0.OOE+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00OE+00 4. 42E-09 0.OOE+00 1. 95E-05 mo-99 0.OOE+00 6.03E-06 1.15E-06 0.OOE+00 1.38E-05 0.OOE+00 1.OBE-05 Tc-99m 3.32E-10 9.2 6E-10 1.20E-08 0.OOE+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5. 12E-10 5.03E-09 0. OOE+00 9.26E-09 3.12E-10 8.7 5E-17 Ru-103 2.55E-07 0.OOE+00 1.09E-07 0.OOE+00 8.99E-07 0.OOE+00 2.13E-05 Ru-10 5 2.18E-08 0.OOE+00 8.4 6E-09 0.OOE+00 0.OOE+00 1.7 6E-05 Ru-10 6 3.92E-06 0.OOE+00 4.94E-07 0. OOE+00 7.56E-06 0.OOE+00 1.88E-04 Ag-li Om 2.05E-07 1.94E-07 1. 18E-07 0.OOE+00 3.70E-07 0.OOE+00 5.45E-05 Sb-122 3.30E-07 6.4 2E-09 9. 64E-08 4.19E-09 0.OOE+0O 2.06E-07 6.92E-05 Sb-124 3.8 6E-06 7.12E-08 1.51E-06 8.79E-09 0.00OE+00 3.37E-06 7.81E-05 Sb-125 2.4 8E-06 2.71E-08 5.7 9E-07 2.36E-09 0.OOE+00 2.16E-06 1.92E-05 3-40

ODCM - Rev. 15 Part II Table 3-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.OOE+00 0.OOE+00 1.13E-05 2.41E-05 Te-127m 9. 67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.OOE+00 3.40E-08 1.09E-07 6.40E-07 0.OOE+00 1.22E-05 Te-127 1.58E-07 5.60E-08 6.12E-05 Te-129m 1. 63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.OOE+00 3.20E-08 1.88E-07 0.OOE+00 2.45E-07 Te-129 4.48E-08 1. 67E-08 1.09E-08 9.3 9E-05 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 Te-131m 2. 44E-06 0.00OE+00 2.29E-09 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 Te-131 O.OOE+00 0.OOE+00 7. OOE-05 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 O.00E+00 2.29E-06 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+00 1.62E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 2.46E-05 1.15E-06 O.OOE+00 3.18E-07 1-132 2.79E-07 7.30E-07 2.62E-07 2.58E-06 1-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.OOE+00 5.10E-09 6.45E-06 6. lOE-07 0. OOE+00 1-134 1.46E-07 3.87E-07 1.39E-07 0.00E+00 1.74E-06 1-135 6. lOE-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 6.26E-05 2.39E-05 2.45E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-136 8.59E-06 3.38E-05 5.07E-05 i. 97E-05 2.12E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Cs-138 7.76E-08 1.49E-07 9.78E-11 4.05E-09 0.OOE+00 9.22E-11 6.74E-II 1.24E-06 Ba-139 1.39E-07 2.34E-08 4.38E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 Ba-140 2.84E-05 3.43E-11 1.43E-13 5.01E-11 2.24E-09 0.OOE+00 4.65E-11 Ba-141 6.71E-08 l1.99E-11 9.1BE-20 2.99E-ll 1.84E-09 0.00E+00 2.53E-I1 Ba-142 2.99E-08 0.OOE+00 9.82E-05 1.71E-09 4.55E-10 0.00E+00 0.00E+00 La-140 3.48E-09 0.OOE+00 2.42E-06 La-142 1.79E-10 7.95E-11 1.98E-11 0.OOE+00 0.OOE+00 4.18E-09 0.OOE+00 2.54E-05 8.88E-09 1.02E-09 0.00E+00 I Ce-141 1.33E-08 I 0.OOE+00 5.14E-05 1.71E-06 1.91E-10 0.00E+00 7.67E-IC Ce-143 2.35E-09 0.OOE+00 1.75E-04 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.OOE+00 1.72E-07

• 4.31E-05 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-0SI 0.OOE+00 4.74E-14 1.01E-13

• 0.OOE+00 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 3.68E-05 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-0 I 0.OOE+00 ) 3.22E-05 0.00E+0( o0.OOE+00 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+0CI 2.67E-05 Np-239 1.76E-09 1. 66E-10 9.22E-11 0.00E+00 ) 5.21E-1(

0.OOE+OC I 0.OOE+0( 0.OOE+OCI 0.OOE+00 K-40 0.OOE+00 0.OOE+00 0.OOE+00 3.99E-07 0.OOE+OC I 0.OOE+0( 0.00E+0c S4.44E-06 Co-57 0.OOE+00 2.38E-07

0. OOE+OC1 0.OOE+0( 0.00E+0c 1 0.OOE+00 Sr-85 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.o0E+0C 1 0.00E+0( 0 0.00E+0C1 0.00E+00 Y-88 0.OOE+00 0.OOE+00 0.00E+00 1 0.OOE+0( 00.OOE+OC Nb-94 0.00E+00 0.OOE+00 0.OOE+00 0.00E+0C 6.68E-12 0.OOE+OC 2.14E-1: L 0.OOE+OCI 4.37E-07 Nb-97 7.37E-11 1 83E-11 0 0.00E+0C 0.OOE+00 Cd-109 0.OOE+00 0.OOE+00 0. OOE+00 0.OOE+0( 0.OOE+0(

0.005+00 0.OOE+OC O.OOE+0O o 0.OOE+OC O0.OOE+00 Sn-113 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+0C 0.0OE+0I 0 0.OOE+OC 0.OOE+00 Ba-133 7 0.OOE+0( 1.66E-09 Te-134 4.47E-08 2.87E-08 3.00E-08 3.67E-0E3 2.74E-0"

) 0.OOE+0( o0.OOE+00 Ce-139 0.OOE+00 0.OOE+00 0.00E+00 0.00E+0( O0.00E+01

) 0.0OE+0I 0 0.OOE+0( 0.OOE+00 Hg-203 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+0(

3-41

ODCM -Rev. 15 Part 11 Table 3-3c CHILD INGESTION DOSE FACTORS (mr~em per pCi ingested)

LIVER TOT BODY THYROID KIDNEY LUNG GILLI isotope BONE H-3 0. OOE+00 2.03E-07 ý.03E-07 2~.03E-07 2~.03E-07 2~.03E-07 2 .03E-07 Be-7 1. 18E-08 2.OOE-08 1. 32E-08 ().OOE+0O 1 97E-08 0I.OOE+00 1 . 12E-06 Na-24 5.80E-06 5.80E-06 5. BOE-06 1 ,.80E-06 I B.OE-06 5,.80E-06 5 .80E-06 8.25E-04 3.8 6E-05 3. I8E-05 ). OOE+000 0OOE+00 0).OOE+00 2*. 28E-05 P-3 2 I ~.02E-09 4 .72E-07 0.O00E+06 0.OOE+0O 8.90E-09 4. 94E-09 L.35E-09 Cr-51 ý.00E-06 ( ).OOE4-0 8I. 9SE-06 0.OOE+O0 1.07E-05 2. 85E-06 ).OOE+O0 Mn- 54 ~.O0E+00 4 .84E-05

0. 0OE+0O 3.34E-07 7.54E-08 0.OOE+00 4.04E-07(

Mn-S 6 3.45E-06 1 .13E-06 1.15E-05 6.10E-06 1. 89E-06 0. OOE+0O ).OOE+00 Fe-55 ).OOE+00 7.74E-06 2 ~.78E-05 Fe-59 1.65E-05 2.67E-05 1.33E-05 ).OOE+00 4.OOE+00 ).OOE+00 ).OOE+00 3 . 05E-05 co-58 0.OOE+00 1.80E-06 5.51E-06 co-60 0.OOE+00 5.29E-06 1.56E-05 D.OOE+00 0.OOE+0O 0.OOE+00 ,~.93E-05 6

Ni-63 5.38E-04 2.88E-05 1.83E-05 0.OOE+00 ).OOE+OO D.OOE+00 L.94E-0 1.22E-07 0.00E4-00 L0. E+00 ).OOE+00 . 56E-05 Ni-65 2.22E-06 2.09E-07 Cu- 64 0.OOE+0O 2.45E-07 1.4 8E-07 0..OOE+O0 5.92E-07 O4.OOE+0O 1. 15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.OOE+00 2.30E-05 0.OOE+00 6.41E-06 Zn- 69 4.38E-08 6.33E-08 5.85E-09 0.OOE+00 3.84E-08 D.OOE+00 3.99E-0 6 Br-83 0.OOE+0O 0.OOE+0O 1.7 1E-07 0.OOE+0O 0.OOE+0O 0.OOE+00 0 . OOE+00 Br-84 0.OOE+00 0.OOE+00 1.9BE-07 0.OOE+0O 0.OOE+OO 0.OOE+OO 0.OOE+O0 Br-85 O.OOE+00 0.OOE+00 9.12E-09 0.OOE+O0 0.0 OE+O0 0.OOE+00 0.OOE+00 Rb-86 0.OOE+00 6.70E-05 4.12E-05 0.OOE+O0 0.OOE+00 0.OOE+00 4.31E-06 Rb-8 8 0.OOE+00 1.90E-07 1.32E-07 O.00E+00 0.OOE+O0 0.OOE+00 9.32E-09 Rb-8 9 0.OOE+00 1,17E-07 1.04E-07 0.OOE+00 0.OOE+0O 0.OOE+O0 1.02E-09 Sr-89 1.32E-03 0.OOE+0O 3.7 7E-05 0.OOE+00 0.OOE+00 0.OOE+00 5.11E-05 Sr-90 1.70E-02 0.OOE+00 4.31E-03 0.OOE+O0 0.OOE+00 0.OOE+00 2.2 9E-04 S r-91 2.40E-05 0.OOE+00 9.0 6E-07 0.OOE400 0.OOE+O0 0.OOE+00 5.30E-05 Sr- 92 9.03E-06 0.OOE+O0 3.62E-07 0.OOE-'00 0.OOE+00 0.OOE+00 1.71E-04 Y-90 4. 11E-O8 0.OOE+O0 1.IOE-09 0.OOE+00 0.OOE+O0 0.OOE+OO 1.17E-04 Y-91M 3.82E-10 0.OOE+OO 1.39E-11 0.OOE+O0 0.OOE+00 0.OOE+00 7. 48E-07 Y- 91 6.02E-07 O.OOE+00 1.61E-08 0.OOE+00 0.OOE+00 0.OOE+O0 8.02E-05 Y-92 3.60E-09 0.OOE+00 1.03E-10 0.OOE+00 0.OOE+00 0.OOE+00 1. 04E-04 Y-93 1.14E-08 0.OOE+OO 3.13E-10 0. OOE+0O 0.OOE+0O 0.OOE+00 1. 70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.OOE+O0 3. 65E-08 0.OOE+O0 2. 66E-05 Zr-97 6.99E-0 9 1.01E-09 5.96E-10 O.OOE+O0 1.45E-09 0.OOE+00 1.53E-04 Nb-95 2.25E-08 8.7 6E-09 6.26E-09 0.OOE+0O 8.23E-09 O.OOE+00 1. 62E-05 mo-9 9 0.OOE+00 1.33E-05 3.29E-06 0.OOE+00 2.84E-05 0.OOE+O0 1. IOE-05 Tc-9 9m 9.23E-10 1.81E-09 3.OOE-08 0.OOE+0O 2. 63E-08 9.19E-10 1. 03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.OOE+0O 1. 91E-08 5.92E-10 3-56E-09 Ru-103 7.31E-07 0.OOE+O0 2.81E-07 0.OOE+O0 1.84E-06 0.OOE+00 1.89E-05 Ru-105 6.45E-68 0.OOE+O0 2.34E-08 0O.O0OE+OO. 5. 67E-07 0. OOE+ý00 4.21E-05 Ru-10 6 1.17E-05 0.OOE+O0 1.4 6E-0 6 0.OOE+00 1. 58E-05 0.OOE+00 1. 82E-04 Ag-110n 5.39E-07 3.64E-07 2.91E-07 0.OOE+00 6.7 8E-07 0.OOE+O0 4.33E-05 Sb-122 9.83E-07 1.45SE-O8 2.88E-07 1.26E-08 0.OOE+00 4.OOE-07 7.56E-05 Sb- 124 1. liE-05 1.4 4E-07 3.88E-06 2.44E-08 0.OOE+00 6.15E-06 6.93E-05 Sb-125 7.ISE-06 5.51E-08 1.50E-06 6.63E-09 0.OOE+00 3.98E-0 6 1.71E-05 3-42

ODCM - Rev. 15 Part 11 Table 3-3c CHILD INGESTION DOSE FACTORS 0

(mrem per pCi ingested)

TOT BODY THYROID KIDNEY LUNG GILLI Isotope BONE LIVER, Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.OOE+00 C IOOE+0O 1-.~.34E-05 lOE-05 C .OOE+0O Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 L.84E-05 0 OO0E+O0 Te-127 4.71E-07 1.27E-07 1.OlE-07 3.26E-07 1.34E-06 5.94E-05

1. 57E-05 1.43E-04 ( 0.OE+O0 Te-12 9m 4.87E-05 1.36E-05 7.56E-06

( )OOE+00 8.34E-06 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 2.41E-05 .OOE+0O 1.01E-04 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.47E-08 6.35E-08 2.51E-07 0. OOE+OO 4.36E-07 Te-1 33 8.30E-08 2.53E-08 4.15E-05 0. OOE+OO 4.5OE-05 Te-132 1.01E-05 4.47E-06 5.4OE- 06 6.51E-06 3.04E-06 6.50E-04 8.82E-06 0. OOE+00 2 .76E-06 1-130 2. 92E-06 5.90E-06

0. OOE+0O 1.54E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05

6. 82E-05 2.25E-06 0. OOE+O0 1.73E-06 1-132 8.OOE-07 1.47E-06 6.7 6E-07 7.32E-06 2.77E-06 1.36E-03 1. 22E-05 0.OOE+O0 2.95E-06 1-133 5.92E-06 0.OOE+0O 5.16E-07 1-134 4.19E-07 7.78E-07 3.58E-07 1.7 9E-05 1.19E-064 3.15E-06 1. 4 9E-06 2.7 9E-04 4.83E-06 0i.OE+0O 2.40E-06 1-135 1.75E-06

0. OOE+OO 1.19E-04 4.27E-05 2.07E-06 Cs- 134 2.34E-04 3.84E-04 8.2LOE-05 S.13E-06 2.27E-06 cs-136 2.35EH-05 6.46E-05 4.18E-05 O.OOE+0O 3.4 4E-05 0.OOE+OO 1.02E-04 3.67E-05 1. 96E-06 cs-137 3.27E-04 3.13E-04 4.62E-05 2.40E-08 1.4 6E-07 cs-138 2.28E-07 3.17E-07 2.01E-07 0.OOE+OO 2.23E-07 08 0.OOE+OO 1. 93E-10 1.30E-10 2.39E-05 Ba-139 4.14E-07 2.21E-10 1.2OH-4.34E-08 4.21E-05 Ba-140 8.31E-05 7.28E-08 4 .85E-06 0.OOE+0O 2 .37E-08 O.OOE+O0 9.69E-11. 6.58E-10 1.14E-07 Ba-141 2.OOE-07 1.12E-10 6.5 1E-0 9 6.29E-11 4 .88E-09 O.OOE+0O 5.09E-11 3.70E-11 1. 14E-09 Ba-142 8.74E-08 0.0 OE-I00 .OE+00

.0 0.0OE+00 9.84E-05 La-140 1.O01E-08 3.53E-09 1.19E-09

1. 67E-10 5.23E-11 0. OOE+OO 0. OOE+OO 0.OOE+OO 3.31E-05 La-i 42 5.24E-10 0.OOE+0O 8.68E-09 O.OOE+OO 2.47E-05 Ce-i 41 3. 97E-08 1.98E-08 2. 94E-09 3.7 9E-06 5.4 9E-10 O.00E+00 1.59E-09 0.OOE+00 5-55E-05 Ce-143 6.99E-09 O.OOE+O0 3. 61E-07 0.OOE+OO 1.70E-04 Ce-144 2.08E-06 6.52E-07 1.11E-07 1.18E-08 1.95E-09 O.OOE+OO 6.39E-09 0.OOE+O0 4.24E-05 Pr-143 3. 93E-08 9E-12 0. OOE+O0 2. 11E-11 0.OOE+0O 8.59E-08 Pr-144 1.2 9E-10 3.99E-11 6.4 1 .75E-09 O .OOE+00 1.24E-08 O.OOE+00 3. 58E-05 Nd-147 2.7 9E-08 2.26E-08

1. 14E-07 O.OOE+00 0 .OOE+00 0. OOE+OO 3.57E-05 W-187 4.29E-07 2.54E-07 2.79E-05 O.OOE+O0 Np-2 39 5.25E-09 3.77E-10 2.65E-10 0.OOE+00 1.09E-09 0.OOE+OO

0. OOE+00 0. O0E+0O O.OOE+00 K-4 0 0. 0OE+O0 0.0OE+00 0.OOE+O0

4. 93E-07 9.98E-07 0.OOE+O0 0.OOE+00 0.00E+00 4.04E-06 Co-57 0.OOE+O0 0.OOE+O0 0. OOE+00 Sr-85 0.0OE+O0 0.OOE+00 0.OOE+0O 0.OOE+00 0.OO0E+O0 OOE+00 0. OOE+O0 0. OOE+00 0. OOE+0O 0.OOE+OO 0.OOE+OO Y-88 0. OOH+0O 0.

0.OOE+0O 0. O0E+O0 0.OOE+O0 0.OOE+OO Nb- 94 0. OOHO0O 0.OOE+O0 0.O0OE+00

3. 92E-11 1.8 3E-11 0.OOE+00 4.35E-11 0.OOE+0O 11.21E-05 Nb- 97 2.17E-10

0. OOE+00 0 O0E+00 O.OOE+O0 0.OOE+0O Cd-lO 9 0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+0OO 0.OOE+O0 0: OOE+0O 0.OOE+00 0.OOE+O0 Sri-113 0.OOE+00 0.O0H+O0 OOE+0O 0.OOE+OO 0. OOE+00 Ba-133 0.OOE+0O 0.OOE+00 0.OOE+0O 0.OOE+OC I0.

7 .74E-08 1. 02E-01 5.37E-07 O.OOE+OO 5.8 9E-07 Te-134 1.29E-07 5.80E-08 O.OOE+OO 0.OOE+OO Ce-139 0. OE+0OO 0.OOE+0O 0.OOE+Q0 0.OOE+OC IO.OOE+O0 0.0 OE-iOC 1 0.O0OE+0O 0.OOE+O0 0.OOE+00 Hg-203 0.OOE+OO O.OOE+00 0.OOE+00 3-43

ODCM - Rev. 15 Part 11 Table 3-3d INFAN~T I-NGESTIO14 DOSE FACTORS (mrem per pCi ingested)

BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope H-3 0. OOE+OO 3.08E-07 3.08E-07 3.08E-07 3.O8E-07 3. OBE-07 3 .08E-07 Be-7 2.26E-08 4.72E-08 2.51E-08 O.OOE+OO 3.34E-08 0. OOE+00 1 . lIE-06 Na-24 1.O01E-05 1.O01E-05 1.01E-05 1.01E-05 1.01E-05 1.O1E-05 1. OIE-05 P-3 2 1.70E-03 1.OOE-04 6.5 9E-05 O.OOE+00 0.OOE+00 0 . OOE+0O 2.30E-05 Cr-Si 0.OOE+00 0.OOE+0O 1.41lE-08 9.20E-09 2.01E-09 1.79E-08 4. 11E-07 Mn-S 4 0.OOE+00 1.99E-05 4 .51E-06 0.OOE+O0 4.4 1E-06 0.OOE+00 7 . 31.E-06 Mn- 56 0.OOE+OO 8.18E-07 1.4 1E-07 0.OOE+0O 7.03E-07 0.O0E+0O 7 .43E-05 Fe-S55 1.39E-05 8. 98E-06 2.40OE-0 6 O.OOE+00 0.OOE+00 4.39E-06 1.14E-06 Fe-S 9 3.08E-05 5.38E-05 2.12E-05 0.OOE+O0 0.OOE+00 1.59E-05 2 .57E-05 Co-58 0.OOE+O0 3.60E-06 8.98E-06 0.OOE+O0 0.OOE+00 0.OOE+OO 8. 97E-06 Co-60 0.OOE+0O 1. 08E-05 2 .55E-05 0.O0E+OO 0.OOE+O0 0.OOE+00 2. 57E-05 Ni-63 6.34E-04 3.92E-05 2 .20E-05 O.OOE+00 O.OOE+OO 0.OOE+0O 1 . 95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 o .OOE+0O 0.OO0E+OO 0.00E4-00 4.05E-05 Cu- 64 0.OOE+00 6.09E-07 2 .82E-07 0.OOE+O0 1.03E-06 0.0 OE+00 1. 25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.OOE+OO 3.06E-05 O.00E+00 5. 33E-05 Zn-69 9.33E-08 1. 6SE-07 1 .25E-08 0.OOE+OO 6. 98E-08 0.0OE+ 0O 1 . 37E-05 Br-83 0. OOE+OO O.'OOE+OO 3.63E-07 0.O0E+OO 0.0OE+O0 0. 0OE+0O 0.OOE+00 Br-84 0. OOE+0O 0. OOE+OO 3.82E-07 0.OOE+0O 0.00E+OO 0. OOE+00 0.OOE+00 Br-85 0. OOE+0O 0. OOE+OO 1. 94E-68 0.OOE+O0 90.E+00 0.OOE+OO 0.OOE+00 Rb-8 6 0. OOE+0O 1. 70E-04 8.40E-05 O.OOE+O0 0.OOE+0O 0. 0OE+0O 4. 35E-06 Rb-88 0.OOE+O0 4.98E-07 2.73E-07 0.OOE+OO 0.OOE+0O 0. 0OE+0O 4. 85E-07

0. OOE+00 2.86E-07 1.97E-07 0.O0OE+OO .0.E+O00.OOE+OO 9.7 4E-08 Rb-89 0. OOE+O0 0.OOE+00 S.16EE-05 Sr- 89 2.51E-03 O.OOE+OO 7 .20E-05 0.OOE+OO Sr-90 1.85E-02 0. OOE+O0 4 .71E-03 0.OOE+O0 0.OOE+O0 0.OOE+00 2.31E-04 Sr-91 5. OOE-05 0. OEE-OO 1.8 1E-06 0.0OE+00 O.OOE+OC 0.OOE+00 5. 92E-05 Sr-92 1.92E-05 0. OOE+O0 7 . 13E-07 0.OOE+00 0.OOE+OO 0.OOE+00 2.07E-04 B. 69E-08 0. OOE+OO 2.33E-09 0.O0OE+0 0.OOE+OC I0.OOE+O0 1.20E-04 Y-90 Y-91iM 8.10E-10 0.OOE+0O 2.76E-11 0.OOE+OO 0.OOE+OC I0. OOE+00 2.70E-06 Y-91 1. 13E-06 O.OOE+OO 3.01E-08 0.OOE+0O 0.OOE+OC 1 0.OOE+O0 8. lOE-05 2.15E-10 0.OOE+OC p0. OOE+OCI 0.OOE+OC 1. l46E-04 Y-92 7.65E-09 0. OOE+OO 6.62E-10 0.OOE+OC 0. OOE+OC ) .OOE+OC I1. 92E-04 Y-93 2.43E-08 0.0 0EE-OO zr-95 2.06E-07 5. 02E-08 3. 56E-08. O.OOE+OC 5.41E-OE1 0.OOE+OC I2.50E-05 zr-97 1. 48E-08 2.54E-09 1. 16E-09 0.OOE+OC I2.SEE-OS 0.OOE+OC1 1.62E-04

1. OOE-08 0.OOE+OC I .24E-OE 0. OOOE+OC I1. 46E-05 Nb-95 4 .20E-08 1.73E-08 6.63E-06 0.OOE+OC S .08E-0! i0. 00E+0c I1. 12E-05 Mo- 99 0. OOE+00 3.40E-05 Tc-9 9M 1.92E-0 9 3.96E-09 5. IOE-08 0. OOE+OC 34.26E-OE3 2.07E-OS 1.15E-06 Tc-101 2.27E-09 2.86E-09 2. 83E-08 0.OOE+OC I3.40E-OE 1.56E-O S 34.86E-07 Ru-103 1. 48E-06 0. OOE+0O 4. 95E-07 0. OOE+OC 33.08E-015 0.OOE+OC 1.80E-05 Ru-lOS 1.3 6E-07 0. OOE+O0 4.58E-08 0.OOE+OC I1. OOE-015 O.OOE+OC 5.41lE-05 Ru-106 2.41E-05 0.OOE+O0 3.OIE-06 0.OOE+0C 2.85E-0.'5 0.OOE+0( 1.83E-04 Ag-illOi 9.96E-07 7.27E-07 4. 81E-07 0.OOE+O( 1.04E-015 0.OOE+0( 23.77E-05 6.13E-07 3.14E-OE 3 .0OE0E4O 21.09E-015 7. 65E-05 Sb-122 2.lOE-06 3.85E-08

6. 63E-06 5. 68E-Oi3 O.OOE+OI 21. 34E-O!5 6.60E-05 Sb-124 2.14E-05 3.15E-07 Sb-125 1. 23E-05 1. 19E-07 2.53E-06 1.54E-OE3 0.OOE+01 7.72E-015 1.64E-05 3

3-44

Part 11 ODCM - Rev. 15 Table 3-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te- 125m 2.33E-05 7 .79E-06 3.15E-06 7.84E-06 0.OOE+00 0. OOE+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.OOE+00 2.36E-05 Te-127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.O0E+00 2.lOE-05 Te-i2 9m 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.OOE+00 5.97E-05 Te-129 2.84E-01 9.79E-08 6.63E-08 2.38E-07 7 .07E-07 0.OOE+00 2.27E-05 Te-i 31m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4 .21E-05 0.OOE+00 1.03E-04 Te-131 1 .76E-07 6.50E-08 4.94E-08 1.57E-07 4 .50E-07 0.OOE+O0 7.lIiE-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.OOE+00 3.81E-05 1-130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.O0E+O0 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4 .94E-05 O.OOE+00 1.51E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3 .76E-06 0.OOE+00 2.73E-06 1-133 1.25E-05 i.82E-05 5.33E-06 3 .31E-03 2.14E-05 0.OOE+00 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.OOE+00 1. 84E-06 1-135 3.64E-06 7.24E-06 2. 64E-06 6.4 9E-04 8.07E-06 O.OOE+00 2. 62E-06 Cs-i34 3.71E-04 7.03E-04 7. lOE-05 0.OOE+00 1.81E-04 7 .42E-05 1.91E-06 Cs-i 36 4.59E-05 1.35E-04 5.04E-05 0.OOE+00 5.38E-05 1.10E-05 2.05E-06 Cs-i37 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1. 64E-04 6.64E-05 1. 91E-06 Cs-i38 4.81E-07 7.82E-07 3.7 9E-07 0.OOE+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10, 2.55E-08 0.OOE+U0 3.51E-10 3.54E-10 5.58E-05 Ba-i 40 1.71E-04 1.71E-07 8.81E-06 0.OOE+60 4 .06E-08 1.05E-07 4. 20E-05 Ba-141 4.25E-07 2. 91E-10 1.34E-08 0O.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.0 6E-0 9 0.OOE+0O 8.81E-11 9.26E-11 7.59E-07 La-i 40 2.11E-08 8.32E-09 2.14E-09 0.OOE+00 0.OOE+00 0.OOE+00 9.77E-05 La-i 42 1.10E-09 4.04E-10 9.67E-11 0.OOE+00 0.OOE+00 0.OOE+00 6.86E-05 Ce-i 41 7.87E-68 4.80E-08 5.65E-09 0.OOE+00 1.48E-08 0.OOE+00 2.48E-05 ce-143 1.48E-08 9.82E-06 1.12E-09 0.OOE+00 2.86E-09 0.OOE+O0 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.OOE+00 4.93E-07 0.OOE+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 0.OOE+00 1.13E-08 0.OOE+00 4.29E-05 Pr-I 44 2.74E-10 1.06E-10 1.38E-11 0.OOE+00 3.84E-11 0.OOE+O0 4. 93E-06 Nd-i 47 5.53E-08 5.6BE-08 3.4 8E-09 0.OOE+00 2.19E-08 0.OOE+00 3. 60E-05 W-18 7 9.03E-07 6.28E-07 2.17E-07 0.OOE+0O 0.OOE+00 0.OOE+0O 3. 69E-05 Np-239 1.lIiE-08 9. 93E-10 5.61E-10 0.00E+00 1.98E-09 0.OOE+00 2.87E-05 K-4 0 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+O0 0.OOE+00 0. OOE+00 Co-57 0.OOE+00 1.15E-06 1.87E-06 0.OOE+00 0.OOE+00 0.OOE+00 3. 92E-06 Sr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-88 0.OOE400 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Nb- 94 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+OO 0.OOE+00 0.OOE+00 Nb-97 0.OOE400 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Cd-109 0.QOOE+0O 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Sn-113 0.OOE+00 0.OOE+00 0. OOE+O0 0.OOE+O0 0.OOE+00 0.OOE+0O 0.OOE+00 Ba-133 0.OOE+00 0.OOE+O0 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-i34 0.OOE+00 0.OOE+00 o .OOE+00 0.OOE+OO 0.OOE+O0 0.OOE+00 0.00OE+00 Ce-139 0.OOE+00 0. OOE+O0 0.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00 0.00OE400 Hg-203 0.OOE+00 0.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 3,45

Part II ODCM - Rev. 15 Table 3 - 4 TOTAL BODY DOSE FACTORS Ki FROM NOBLE GASES (GAMMA)

FINITE CLOUD **

CORRECTION Gamma TB* X (pCi/uCi) X FACTOR Ki***

NUCLIDE 1.OOE+6 7.62E-01 5.76E-02 Kr-83m 7.56E-08 1.17E-03 1.OOE+6 6.22E-01 7.28E+02 Kr-85m 1.61E-05 1.OOE+6 5.31E-01 8.55E+00 Kr-85 5.92E-03 1.00E+6 4.21E-01 2.49E+03 Kr-87 1.47E-02 1.OE+6 3.90E-01 5.73E+03 Kr-88 1.66E-02 1.OOE+6 4.13E-01 6.85E+03 Kr-89 1.56E-02 1.OOE+6 4.49E-01 7.01E+03 Kr-90 9.15E-05 1.OOE+6 7.49E-01 6.86E+01 Xe-131m 2.51E-04 1.OOE+6 7.10E-01 1.78E+02 Xe-133m 7.62E-01 2.24E+02 Xe-13 3 2.94E-04 1.OOE+6 3.12E-03 1.OOE+6 5.34E-01 1.67E+03 Xe-135m 6.36E-01 1.15E+03 Xe-13 5 1.81E-03 1.OOE+6 5.02E-01 7.13E+02 Xe-13 7 1.42E-03 1.OOE+6 8.83E-03 1.OOE+6 4.28E-01 3.78E+03 Xe-138 8.84E-03 1.OOE+6 4.37E-01 3.86E+03 Ar-41

• From Regulatory Guide 1.109, Table B-i (mrem/yr per pCi/cu mtr)

The finite cloud correction factor is described in Section 3.6.

• • • ~Ki (mrem/yr per uCi/cu mtr) 3-46

Part 11 ODCM - Rev.. 15 Table 3 - 5 SKIN DOSE FACTORS Li FROM NOBLE GASES (BETA)

NUCLIDE Beta Skin* X (pCi/uCi) = Li**.

1.OOE+6 O.QOE+QO Kr-83ra O.OOE+OO 1.OOE+6 1.46E+03 Kr-85m .1.46E-03 1.OOE+6 1.34E+03 Kr-85 1.34E-03 l.OOE+6 9.73E+03 Kr-87 9.73E-03.

l.OOE+6 2.37E+03 Kr-88 2.37E-03 1.OOE+6 1.01E+04 Kr-89 1.01E-02 1.OOE+6 7.29E+03 Kr-90 7.299-03 1.OOE+6 4.76E+02 Xe-131m 4.76E-04, 1.OOE+6 9.94E+02 Xe-133m 9.94E-04 1.OOE+6 3.06E+02 Xe-133 3.06E-04 1.OOE+6 7.11E+02 Xe-135m 7.11E-04 i.OOE+6 1.86E+03 Xe-135 1.86E-03 1..OOE+6 l.22E+ý04 Xe-137 1.22E-02 l.OOE+6 4.13E+03 Xe-138 4*.13E-03 l.OOE+6 2.69E+03

.Ar-41 .2.69E-03 (mrem/yr per pCi/cu. mtr)

Guide 1.109, Table B-i

• From Regulatory (mremfyr per uCi/cu mtr)

• • Li 3-47

Part II ODCM -Rev. 15 Table 3 - 6 AIR DOSE FACTORS Mi FROM NOBLE GASES (GAMMA)

FINITE CLOUD **

CORRECTION X (pCi/uCi) X FACTOR = Mi***

NUCLIDE Gamma*

Kr-83m 1.93E-05 1.OOE+6 7.62E-01 1.47E+01 1.23E-03 1.OOE+6 6.22E-01 7. 65E+02 Kr-85m 1.72E-05 1. OOE+6 5.31E-01 9.13E+00 Kr-85 6.17E-03 1.OOE+6 4.21E-01 2. 60E+03 Kr-87 1.52E-02 1.OOE+6 3.90E-01 5. 93E+03 Kr-88 1.73E-02 1.00E+6 4.13E-01 7. 14E+03 Kr-89

1. 63E-02 1.OOE+6 4.49E-01 7.33E+03 Kr-90 1.56E-04 1.00E+6 7.49E-01 1. 17E+02 Xe-131m 3.27E-04 1.OOE+6 7. 1OE-01 2.32E+02 Xe-133m 3 3.53E-04 1. OOE+6 7.62E-01 2.69E+02 Xe-13 3.36E-03 1.OOE+6 5.34E-01 1.79E+03 Xe-135m 35 1.92E-03 1.OOE+6 6.36E-01 1.22E+03 Xe-1 1.OOE+6 5.02E-01 7.58E+02 Xe-13 7 1.51E-03 9.21E-03 1.00E+6 4.28E-01 3.94E+03 Xe-138 9.30E-03 1.00E+6 4.37E-01 4.06E+03 Ar-41

• From Regulatory Guide 1.109, Table B-i (mrad/yr per pCi/cu mtr) described in Section 3.6.

• • The finite cloud correction factor is

• • • Mi (mrad/yr per uCi/cu mtr) 3-48

Part I ODCM - Rev. 15 Table 3 - 7 AIR DOSE FACTORS Ni FROM NOBLE GASES (BETA)

NUCLIDE Beta* X (pCi/uCi) Ni**

--- ------------------------------------------------- w----------------------

Kr-83m 2.88E-04 1.00E+6 2.88E+02 Kr-85m 1.97E-03 1.OOE+6 1.97E+03 Kr-85 1.95E-03 1.OOE+6 1.95E+03 Kr-87 1.03E-02 1.OOE+6 1.03E+04 Kr-88 2.93E-03 1.OOE+6 2.93E+03 Kr-89 1.06E-02 1.OOE+6 1.06E+04 Kr-90 7.83E-03 1.OOE+6 7.83E+03 Xe-131m 1.llE-03 1.OOE+6 1.1lE+03 Xe-133m 1.48E-03 1.OOE+6 1.48E+03 Xe-133 1.05E-03 1.OOE+6 1.05E+03 Xe-135m 7.39E-04 l.OOE+6 7.39E+02 Xe-135 2.46E-03 1.O0E+6 2.46E+03 Xe-13 7 1.27E-02 1.OOE+6 1.27E+04 Xe-138 4.75E-03 1.OOE+6 4.75E+03 Ar-41 3.28E-03 1.00E+6 3.28E+03

• From Regulatory Guide 1.109, Table B-i (mrad/yr per pCi/cu mtr)

• • Ni (mrad/yr per uCi/cu mtr) 3-49

Part 11 ODCM - Rev. 15 TABLE 3 - 8 DOSE FACTORS FOR SITE BOUNDARY USING STANDARD ISOTOPIC MIXTURES INSTANTANEOUS RELEASE MIXTURE Nuclide Relative Abundance WEIGHTED DOSE FACTORS Kr 85m 5.56E-2 K = 1.49E+3 (mrem - m3 per PCi-yr)

Kr 87 5.70E-2 L =.42E+3 (mrem.- m per pCi-yr)

Kr 88 11.95E-2 M=1.58E+3 (mrad - m3 per gCi-yr)

Xe 133m 1.14E-2 T= 2.02E+3 (mrad - m 3 per pCi-yr)

Xe 133 53.57E-2 12.01 E-2 (SEE SECTION 3.3.1)

Xe 135m Xe 135 3.25E-2 Ar 41 6.82E-2 TIME AVERAGED RELEASE MIXTURE Ial Nuclide Relative Abundance WEIGHTED DOSE FACTORS Kr 85 5.33E-5 K= 4.*1 E+2 (mrem - m3 per jRCi-yr)

Kr 85m 1.63E-2 L= 6.25E+2 (mrem - m3 per p.Ci-yr)

Xe 131m 4.72E-4 M= 4.61E+2 (mrad - m3 per gCi-yr)

Xe 133m 4.46E-4 N= 1.34E+3 (mrad - m3 per j+/-Ci-yr)

Xe 133 7.89E-1 Xe135 1.93E-1 3-50

Part II ODCM - Rev. 15 TABLE 3-8 BASES Instantaneous Mix:

These dose factors are generated from the mixture that would be seen in the reactor coolant (undecayed) if the unit were operated with several leaking rods with exposed fuel. The mixture was chosen based upon review of pressurized reactor coolant samples taken during operation with varying fuel conditions (pct, exposed fuel, tramp only). This mixture provided the most restrictive mixture and is used to calculate a conservative instantaneous release rate in uCi/sec before an actual sample of the release is available (see Appendix 3A).

Time Averaged Release Mixture:

This mixture is the conservative time averaged release mixture taken from a review of three years of semi-annual effluent reports. This mixture was from the most restrictive release period (first quarter 1984) reviewed.* These dose factors are used to determine representative time averaged release rates in curies/seconds.

3-51

Part 11 ODCM - Rev. 15 TABLE 3 - 9 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCE SECTOR DISTANCE* NEAREST POINT OF SITE DISTANCE* NEAREST BOUNDARY (Meters) RESIDENCE (Meters)

N RIVER 1950 NNW RIVER 1740 NW RIVER 1830 WNW RIVER 1830 W RIVER 1890 WSW RIVER 2135 SW 350 2745 SSW 380 1525 S 580 1280 SSE 595 1220 SE 580 1100 ESE 580 704 E 625 730 ENE 760 1370 NE 790 1525 NNE RIVER 3050

• Measured from Indian Point 3.

3-52

ODCM - Rev. 15 Part I1 Table 3-10a 3

Ri(I) (mrem/yr per uCi/m ADULT INHALATION THYROID KIDNEY LUNG GILLI Isotope BONE LIVER TOT BODY 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.2 6E+03 0.OOE+00 H-3 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.02E+04 Be-7 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 8.64E+04 Na-24 1.02E+04 7.71E+04 5.01E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.32E+06 3.32E+03 P-32 0.00E+00 1.OOE+02 5. 95E+01 2.28E+01 1.4 4E+04 0.00E+00 7.74E+04 Cr-51 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1. 40E+06 0.00E+00 2.02E+04 mn-54 1.24E+00 1.83E-01 0.OOE+00 1.30E+00 9.44E+03 0.00E+00 6.03E+03 mn-56 1.70E+04 3.94E+03 0.OOE+00 0.OOE+00 7.21E+04 2.46E+04 1.88E+05 Fe-55 2.78E+04 1.06E+04 0.00E+00 0.OOE+00 1.02E+06 1.18E+04 1.06E+05 Fe-59 1.58E+03 2..07E+03 0.OOE+00 0.OOE+00 9.28E+05 0.00E+00 2. 85E+05 Co-58 1.15E+04 1. 48E+04 0.00E+00 0.OOE+00 5.97E+06 0.00E+00 1.34E+04 Co-60 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 4.32E+05 1.23E+04 Ni-63 2.10E-01 9.12E-02 0.00E+00 0.OOE+00 5.60E+03 1.54E+00 4.90E+04 Ni-65 1.4 6E+00 6.15E-01 0. 00E+00 4.62E+00 6.78E+03 0.00E+00 5.34E+04 Cu- 64 1.03E+05 4. 66E+04 0.00E+00 6. 90E+04 8.64E+05 3.24E+04 1.63E+01 Zn-65 6.51E-02 4.52E-03 0.00E+00 4.22E-02 9.20E+02 3.38E-02 2.32E+02 Zn-69 0.OOE+00 2.41E+02 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1.64E-03 Br-83 0.OOE+00 3.13E+02 0.00E+00 0.OOE+00 0.OOE+00 Br-84 0.00E+00 0400E+00 0.OOE+00 0.00E+00 0. OOE+00 0.00E+00 0.00E+00 1.28E+01 1.66E+04 Br-85 1.35E+05 5.90E+04 0.OOE+00 .0.OOE+00 0.OOE+00 0.00E+00 3.34E-09 Rb-86 3.87E+02 1. 93E+02 0.00E+00 0.OOE+00 0.0 0E+00 0.00E+00 9.28E-12 Rb-88 2.56E+02 1.70E+02 0. 00E+00 0.OOE+00 0.OOE+00 0.00E+00 3.50E+05 Rb-89 0.OOE+00 8.72E+03 0. 00E+00 0.OOE+00 1.40E+06 3.04E+05 7.22E+05 Sr-89 0.OOE+00 6. 10E+06 0.00E+00 0.OOE+00 9.60E+06 9.921+07 1. 91E+05 Sr-90 0.OOE+00 2. 50E+00 0.00E+00 0.OOE+00 3.65E+04 6.19E+01 4.30E+04 Sr-91 0.00E+00 2. 91E-01 0.00E+00 0.OOE+00 1. 65E+04 6.74E+00 5.06E+05 Sr-92 0.00E+00 5.61E+01 0.00E+00 0.OOE+00 1.70E+05 2.09E+03 1.33E+00 Y-90 0.OOE+00 1.02E-02 0.00E+00 0.OOE+00 1. 92E+03 Y-91m 2.61E-01 0.00E+00 0.OOE+00 1.70E+06 3.85E+05 4.62E+05 0.00E+00 1.24E+04 7.35E+04 Y-91 0.00E+00 3.02E-01 0.00E+00 0.OOE+00 1.57E+04 Y-92 1.03E+01 0.00E+00 0.00E+00 4.85E+04 4.22E+05 9.44E+01 0.00E+00 2.61E+00 1.50E+05 Y-93 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.07E+05 5.23E+05 Zr-95 1.96E+01 9.04E+00 0.00E+00 2. 97E+01 7.87E+04 Zr-97 9.68E+01 0.00E+00 7.74E+03 5.05E+05 1.04E+05 1.4 1E+04 7.82E+03 4.21E+03 2.48E+05 Nb-95 1.21E+02 2.30E+01 0.00E+00 2. 91E+02 9.12E+04 0.00E+00 4.16E+03 Mo-99 2.91E-03 3.70E-02 0.OOE+00 4.42E-02 7. 64E+02 1.03M-03 1.09E-11 Tc-99m 6.02E-05 5.90E-04 0.00E+00 1.08E-03 3. 99E+02 4.18E-05 1.10E*05 Tc-101 0.00E+00 6.58E+02 0.OOE+00 5.83E+03 5.05E+05 1.53E+03 4.82E+04 Ru-103 0.00E+00 3.11E-01 0.00E+00 1.02E+00 1.10E+04 7.90E-01 9.12E+05 Ru-105 0.OOE+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 6.91E+04 3.02E+05 Ru-106 1.00+E04 5. 94E+03 0.OOE+00 1.97E+04 4. 63E+06 1.08E+04 0.OOE+00 Ag-110m

0. OOE+00 0.OOE+00 0.00E+00 O.00E+00 0.OOE+00 0.00E+00 4.06E+05 Sb-122 5.89E+02 1.24E+04 7.55E+01 0.OOE+00 2.48E+06 3.12E+04 1.01E+05 Sb-124 5.95E+02 1.26E+04 5.40E+01 0.OOE+00 1.74E+06 Sb-125 5.34E+04 3-53

Part il ODCM - Rev. 15 Table 3-10a 3

(mrem/yr per uCi/m)

ADULT INHALATION Ri(I)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-125m 1.26E+04 5. 77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127m Te-127 1.40E+00 6. 42E-01 3. OE-01 1.06E+00 5.10E+00 6.51E+03 5.74E+04 Te-129m 9.76E+03 4.67E+03 1 58E+03 3. 44E+03 3. 66E+04 1.16E+06 3.83E+05 Te-129 4. 98E-02 2.39E-02 1.24E-02 3. 90E-02 1.87E-01 1.94E+03 1.57E+02 Te-131m 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 1.1lE-02 5. 95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-131 Te-132 2. 60E+02 2.15E+02 1 62E+02 1. 90E+02 1.46E+03 2.88E+05 5.10E+05 1-130 4 .58E+03 1.34E+04 5.28E+03 1. 14E+06 2.09E+04 0.OOE+00 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1. 19E+07 6. 13E+04 0.OOE+00 6.28E+03 1.16E+03 3.26E+03 1.16E+03 1. 14E+05 5.18E+03 0.OOE+00 4.06E+02 1-132 8.64E+03 1.48E+04 4 .52E+03 2.15E+06 2.58E+04 0.OOE+00 8.88E+03 1-133 6.44E+02 1.73E+03 6.15E+02 2. 98E+04 2.75E+03 O.OOE+00 1.01E+00 1-134 1-135 2.68E+03 6. 98E+03 2.57E+03 4.48E+05 1.11E+04 0.OOE+00 5.25E+03 3.73E+05 8.48E+05 7 .28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 Cs-134 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 Cs-136 Cs-137 4.78E+05 6.21E+05 4 .28E+05 O.00E+00 2.22E+05 7.52E+04 8.40E+03 3.31E+02 6.21E+02 3.24E+02 0.OOE+00 4.80E+02 4.86E+01 1.86E-03 Cs-138 Ba-139 9.36E-01 6.66E-04 2.74E-02 0.OOE+00 6.22E-04 3.76E+03 8.96E+02 Ba-140 3. 90E+04 4. 90E+01 2.57E+03 0.OOE+00 1.67E+01 1.27E+06 2.18E+05 Ba-141 1.OOE-01 7.53E-05 3.36E-03 0.OOE+00 7.OOE-05 1.94E+03 1.16E-07 Ba-142 2.63E-02 2.70E-05 1 66E-03 0.OOE+00 2.29E-05 1.19E+03 1.57E-16 La-140 3. 44E+02 1.74E+02 4.58E+01 0. OOE+00 0. OOE+00 1.36E+05 4.58E+05 6.83E-01 3.1OE-01 7.72E-02 0.OOE+00 0.00E+00 6.33E+03 2.11E+03 La-142 Ce-141 1.99E+04 1.35E+04 1 53E+03 0.OOE+00 6.2 6E+03 3.62E+05 1.20E+05

1. 86E+02 1.38E+02 1 53E+01 0.OOE+00 6.08E+01 7.98E+04 2.26E+05 Ce-143 Ce-144 3.43E+06 1.43E+06 1.84E+05 0.OOE+00 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 0. 00E+00 2.16E+03 2.81E+05 2.OOE+05

3. 01E-02 1.25E-02 1 53E-03 0. 00E+00 7.05E-03 1.02E+03 2.15E-08 Pr-144 Nd-147 5.27E+03 6.10E+03 3.65E+02 0. OOE+00 3.56E+03 2.21E+05 1.73E+05 W-187 8. 48E+00 7.08E+00 2.48E+00 0.60E+00 0.OOE+00 2.90E+04 1.55E+05 Np-239 2.30E+02 2.26E+01 1.24E+01 0.OOE+00 7.OOE+01 3.76E+04 1.19E+05 K-40 0.OOE+00 0.OOE+00 0 00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 6.92E+02 6.71E+02 0.OOE+00 0.OOE+00 3.70E+05 3.14E+04 Co-57 Sr-85 3.20E+04 0.OOE+00 7.7 6E+05 0.OOE+00 0.OOE+00 4.80E+05 6.08E+04 Y-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Nb-94 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-97 2.22E-01 5.62E-02 2.05E-02 0.OOE+00 6.54E-02 2.40E+03 2.42E+02 Cd-109 0. OOE+00 3. 92E+05 1.28E+04 0.OOE+00 3.76E+05 7.28E+05 6.56E+04 Sn-113 6.56E+04 2.16E+03 4.48E+03 i.36E+03 0.OOE+00 9.60E+05 1.20E+04 Ba-133 7.60E+04 3.36E+03 2.OOE+04 0.OOE+00 1.68E+01 1.52E+06 8.00E+04 3.07E-02 2.58E-02 1.26E-02 2.75E-02 1.74E-01 3.47E+03 2.38E-01 Te-134 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ce-139 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Hg-203 3-54

Part 11 ODCM - Rev. 15 Table 3-l0b 3

TEEN INHALATION Ri(I)' (mrem/yr per uCilm isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.27E+03 1.27E+03 l.27E+03 1.27E+03 1.27E+03 1.27E+03 Be-7 O.OOE+OO O.OOE+OO 0.OOE+OO O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 P-32 1.89E+06 1.10E+05 7.16E+04 O.OOE+OO O.OOE+O0 O.OOE+OO 9.28E+04 Cr-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 Mri-54 O.OOE+OO* 5.11E+04 8.40E+03 O.OOE+OO 1.27E+04 1.98E+06 6.68E+04 Mn-56 0.OOE+O0 1.70E+00 2.52E-01. O.OOE+OO 1.79E+00 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 O.OOE+O0 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+OO 0.OOE+OO 1.53E+06 1.78E+05 Co-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO 0.00E400 1.34E+06 9.52E+04 Co-60 O.OOE+OO 1.51E+04 1.98E+04 O.OOE+OO O.OOE400 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+0O 3.07E+05 1.42E4-04 Ni-65 2.18E+00 2.93E-01 1.27E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+00 8.48E-01 O.OOE+0O 6.41E+00 1.11E+04 6.14E+04 Zn-65 3.86E+I04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 1.24E+06 4.66E+04 Zn-69 4.83E-02 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1.58E+03 2.85E+02 Br-83 O.OOE+0O O.OOE+OO 3.44E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+0O O.OOE+OO 4.33E+02 O.OOE+0O O.OOE+OO O.OOE+OO 0. OOE+OO Br-85 O.OOE+0O O.OOE+OO l..83E+Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 Rb-86 O.OOE+OO 1.90E+05 8.40E+I04 +O.OOE+OO D.OOE+OO O.OOE+OO 1.77E+04 Rb-88 O.OOE+06 5.46E+02 2.72E+02 O.OOE+OO 0.OOE+OO O.OOE+OO 2.92E-05 Rb-89 .0.00E+00 3.52E+02 2.33E+02 O.OOE+OO O.OOE+0O O.OOE+OO 3.38E-07 Sr-89 4.34E+05 O.OOE+OO 1.25E+04 .0O*OOE+OO +O.OOE+0O 2.42E+06 3.71E+05 Sr-90 l.08E+D8 O.OOE+OO 6.68E+06 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Sr-91 8.80E+01. O.OOE+OO 3.51E+00 0.OOE+OO O.OOE+OO 6.07E+04 2.59E+05 Sr-92 9.52E+00 O.OOE+OO 4.06E-01 O.OOE+OO O.OOE+OO 2.74E+04 1.19E+05 Y-90 2.98E+03 O.OOE+OO 8.OOE+01 O.OOE+OO O.OOE+OO 2.93E+i05 5.59E+I05 Y-91m 3.70E-01 0.00E+00 1.42E-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 Y-91 6.61E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09E+05 Y-92 1.47E+01 O.OOE+OO 4.29E-01 O.OOE+OO O.OOE+O0 2.68E+04 1.65E+05 Y-93' 1.35E+02 O.OOE+OO 3.72E+00 O.OOE+OO O.OOE+OO 8.32E,+04 5.79E+05 Zr-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+00 6.74E+04 2.69E+06 1.49E4-05 Zr-97 1.38E+02 2.72E+01 1.26E+01 O.OOE+OO 4.12E+01 1.30E+05 6.30E+05 Nb-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+OO l.OOE+04 7.51E+05 9.68E+04 Mo-99 O.OOE+OO 1.69E+02 3.22E+01 O.OOE+0O 4.11E+02 1..54E+05 2.69E+05 Tc-99m 1.38E-03 3.86E-03 4.99E-02 O.OOE+0O 5.76E-02 1.15E+03 6.13E+03 Tc-l0l 5.92E-05 8.40E-05 8.24E-04 O.00E4-OO 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+00 O.OOE+OO 4.34E-01 O.OOE+0O 1.41E+00 1.82E+04 9.04E+04 Ru-106 9.84E+04 O.OOE+0O 1.24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 Ag-11rn 1.38E+04 1.31E+04 7.99E+03 O.OOE+0O 2.50E+04 6.75E+06 2.73E+05 Sb-122 0.00t+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 O.OOE+OO 3.85E+06 3.98E+05 Sb-125 7.38E+04 8.08E+02 1.72E+04 7.04E+01 O.OOE+OO 2.74E+06 9.92E+04 3-55

Part II ODCM -Rev. 15 Table 3-10b 3

TEEN INHALATION Ri(I) (mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.OOE+00 5.36E+05 7. 50E+04 Te-127m 1.80E+04 8.16E+03 2. 18E+03 4 .38E+03 6. 54E+04 1. 66E+06 1. 59E+05 Te-127 2.01E+00 9.12E-01 4.42E-01 1.42E+00 7.28E+00 1.12E+04 8. 08E+04 Te-129m 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1. 62E+03 Te-131m 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2. 34E+03 1.51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4. 49E+405 4.63E+05 1-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 0.OOE+00 9. 12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.4 6E+07 8.40E+04 0.OOE+00 6. 49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 0.OOE+00 1.27E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2. 92E+06 3.59E+04 0.00E+00 1.03E+04 1-134 8.88E+02 2.32E+03 8.4 OE+02 3. 95E+04 3.66E+03 0. 00E+00 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1. 49E+04 0 OOE+00 6. 95E+03 Cs-134 5. 02E+05 1.13E+06 5.4 9E+05 0.OOE+00 3.75E+05 1. 46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 0.OOE+00 1.10E+05 1.78E+04 1. 09E+04 Cs-137 6.70E+05 8.48E+05 3.11E+05 0.OOE+00 3.04E+05 1.21E+05 8. 48E+03 Cs-138 4.66E+02 8.56E+02 4. 46E+02 0.OOE+00. 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+00 9.44E-04 3. 90E-02 0.OOE+00 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+01 3.52E+03 0.OOE+00 2.28E+01 2.03E+06 2.29E+05 Ba-141 1.42E-01 1.06E-04 4.74E-03 0.OOE+00 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 0.OOE+00 3.14E-05 1.91E+03 4.79E-10 La-140 4.7 9E+02 2.36E+02 6.26E+01 0.OOE+00 0.OOE+00 2.14E+05 4.87E+05 La-142 9. 60E-01 4.25E-01 1. 06E-01 0.OOE+00 0.OOE+00 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 0.OOE+00 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+01 0.OOE+00 8. 64E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2. 62E+05 0.OOE+00 1.21E+06 1.34E+07 8. 64E+05 Pr-143 1.34E+04 5.31E+03 6. 62E+02 0.OOE+00 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 0.OOE+00 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+00 5.02E+03 3.72E+05 1.82E+05 W-187 1.20E+01 9.76E+00 3.43E+00 O.O0E+00 0.OOE+00 4.74E+04 1.77E+05 Np-239 3.38E+02 3.19E+01 1.77E+01 0.OOE+00 1.00E+02 6.49E+04 1.32E+05 K-40 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-57 0.OOE+00 9.44E+02 9.20E+02 0.OOE+00 O.0OE+00 5.86E+05 3.14E+04 Sr-85 4.OOEE+04 0.00E+00 1. 04E+04 0.OOE+00 0.OOE+00 7.04E+05 5.52E+04 Y-88 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-94 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-97 3.14E-01 7.78E-02 2. 84E-02 0.OOE+00 9.12E-02 3.93E+03 2.17E+03 Cd-109 0.O0E+00 8.OOE+05 2.72E+04 0.OOE+00 5.36E+05 1.28E+06 6.88E+04 Sn-113 1.20E+05 3.76E+03 7.76E+03 2.32E+03 0. OOE+00 1.60E+06 1 20E+04 Ba-133 3.76E+05 6.40E+03 2. 64E+04 0.OOE+00 2.24E+01 2.32E+06 7.76E+04 Te-134 4.25E-02 3.48E-02 2. 91E-02 3.57E-02 2.33E-01 5. 40E+03 1.10E+01 Ce-139 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Hg-203 0.OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0..OOE+00 0.OOE+00 3-56

Part 11 ODCM -Rev. 15 Table 3-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.OOE+0O 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 Be-7 0.OOE+00 O.OOE+O0 0.OOE+00 0.0 OE+00 0.OOE+00 0.OOE+00 0.OOE+00 Na-2 4 1.61E+04 1..6E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1. 61E+04 P-32 2.60E+06 1.14E+05 9.88E+04 0.OOE+0O 0. OOE+00 0.O0E400 4.22E+04 Cr-51 0.OOE+00 0.OOE+00 1.54E+i02 S.55E+01 2. 43E+01 1.70E+04 1.08E+03 Mn-54 0.OOE+00 4.29E+04 9.51E+03 0.OOE+00 1.O0E+04 1.58E+06 2.29E+04 Mn-S 6 0..00E+00 1.66E+00 3.12E-01 0.00OE+00 1.67E+60 1.31E+04 1.23E+05 Fe-55 2.52E+04 7 .77E+03 0.00OE+0O 0. O0E+O0 1.l11E+05 2.87E+03 Fe-S 9 2.01E+04 3.34E+f04 1.67E+04 0.00E+00 0.O0E+00 1.27E+i06 7. 07E+04 Co-58 0..00E+00 1.77E+03 3.16E+03 0.0OE+00 0.OOE+O0 1.11E+06 3. 44E+04 Co-60 O.OOE+O0 1.31E+04 2.2 6E+04 0.O0E+00 0.O0E+00 7.07E+06 9.62E+04 Ni-63 8.21E+05 4 . 63E+04 2.80i+04 0.OOE+00 0.OOE+00 2.75E+05 6.33E+03 Ni-65 2.99E+00 2.96E-01 1.64E-01 0.OOE+00 0. O0E+00 8.18E+03 S. 40E+04 Cu-64 0.OOE+OO 1.90E+00 1.07E+00 0.OOE+00 6.03E+00 9.58E+03 3. 67E4-04 Zn-65 4 .26E+04 1.13E+05 7.03E+04 0.O0E+0O 7.14E+04 9.95E+05 1. 63E+04 Zn-69 6.70E-02 9.66E-02 8.92E-03 0.OOE+00 5.85E-02 1.42E+03 1.02E+ 04 Br-83 0 . 00E+00 0.OOE+0O 4 .74E+02 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 Br- 84 0.OOE+00 0.OOE+00 5.48E+02 0.OOE+O0 0.OOE+00 0.OOE+OO 0.OOE+00 Br-85 0.OOE+00 0.OOE+00 2.53E+01 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+0O Rb-B 6 0.OOE+0O 1. 98E+05 1.i14E+05. 0.OOE+00 0..OOE+00 0.00OE+00 7. 99E+03 Rb-B B 0.OOE+0O 5.62E+02 3.66E+02 0.OOE+ 00 0.OOE+00 0.OOE+O0 1.72E+01 Rb-89 0.OOE+O0 3.45SE+02 2.90E+02 0.OOE+O0 0.OOE+0O 0.00E+00 1.8 9E+ 00 Sr-89 5. 99E+05 0.OOE+00 1.72E+04. 0.OOE+00 0.OOE+00 2.16E+06 1. 67E+05 Sr-90 i.0iE+08 O.OOE+00 6.4 4E+06 O.OOE+O0 0.00E+0O 1.48E+07 3.43E+05 Sr-91 1.21E+02 0.00E+O0 4.59E+00 0.OOE+O0 0.00E+00 5.33E+04 1.74E4-05 Sr-92 1.31E+01 0.OOE+O0 5.25E-01 0.OOE+00 0.OOE+0O 2.40E+04 2.42E+05 Y-90 4.l11E+03 0. 00E+00 1.11E+02 0.00E+00 0.OOE+0O 2. 62E+05 2. 68E+05 Y-91M 5.07E-01 0.+.OOE+O0 1.84E-02 O.OOE+O0 0.OOE+0O 2.81E+03 1.72E+03 Y-91 9.14E+05 0. 00E+O0 2.4 4E+04 0.00E+60 0.00E+00 2. 63E+06 1.84E+05 Y-92 2.b4E+Ol 0.OOE+O0 5.81E-01 0.OOE+00 0.OOE+00 2.39E+04 2.3 9E+05 Y-93 1.86E+02 0.OOE+00 5.11E+00 0.00E+00 0.OOE+0O 7. 44E+04 3.89E+05' Zr-95 1.90E+05 4.1i8E+04 3.70OE+04 0..O0E+O0 5.9 6E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 0.GOE+O0 3.88E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 0.00E+O0 S.62E+03 6.14E+05 3.70E+04 Mo-99 0.O0OE+O 0 i1. 72E+02 4.25E+01 O.OOE+00 3. 92E+02 1.35E+05 1.27E+05 Tc-9 9m 1.7BE-03 3.48E-03 5.77E-02 0.00OE+00 5.07E-02 9.51E+02 4.81E+03 TC-i0i 8.iDE-0S 8.51E-05 1.08E-03 0.OOE+00 1.45E-03 5.85E+02 1.63E+01 Ru-i03 2.7 9E+03 0.OOE+0O 1.07E+03 0.OOE+00 7.03E+03 6. 62E+05 4.4 BE+04 Ru-lOS 1.53E+00 0.OOE+0O 5.55E-01 0.00E+00 1.34E+00 1.59E+04 9. 95E+04 Ru-i 06 1.36E+05 0.00E+0O 1.69E+04 0.OOE+00 1.84E+05 1.43E+07 4.29E+05 Ag-i l0i 1.69E+04 1.i14E+04 9.14E+03 0.O0E+00 2.12E+04 5.48E+06 1.OOE+05 Sb-i22 0.OOE+0O O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+O0 0.OOE+00 Sb-i24 5.74E+04 7.40OE+02 2.00OE+04 1.26E+02 0.OOE+00 3.24E+06 1. 64E+05 Sb-i25 9.84E+04 7.59E+02 2.07E+04 9.10E+01 O.OOE+00 2.32E+06 4.03E+04 3-57

Part II ODCM - Rev. 15 Table 3-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.OOE+00 4.77E+05 3.38E+04 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+00 9.51E-01 6.10E-01 1.96E+00 7.07E+00 1.00E+04 5.62E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-131m 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.OOE+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.00E+00 5.11E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.OOE+00 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 0.00E+00 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.OOE+00 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 0.00E+00 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 O.OOE+00 4.44E+03 Cs-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 O.OOE+00 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 0.OOE+00 6.22E+02 6.81E+01 2.70E+02 Ba-139 1.84E+00 9.84E-04 5.36E-02 0.OOE+00 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 0.OOE+00 2.11E+01 1.74E+06 1.02E+05 Ba-141 1.96E-01 1.09E-04 6.36E-03 O.OOE+00 9.47E-05 2.92E+03 2.75E+02 Ba-142 4.99E-02 3.60E-05 2.79E-03 0.OOE+00 2.91E-05 1.64E+03 2.74E+00 La-140 6.44E+02 2.25E+02 7.55E+01 0.OOE+00 0.00E+00 1.B3E+05 2.26E+05 La-142 1.29E+00 4.11E-01 1.29E-01 0.OOE+00 0.OOE+00 8.70E+03 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90E+03 0.OOE+00 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+01 0.OOE+00 8.36E+01 1.15E+05 1.27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+00 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 O.OOE+00 3.OOE+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.OOE-03 0.OOE+00 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73E+03 6.81E+02 0.OOE+00 4.81E+03 3.28E+05 8.21E+04 W-187 1.63E+01 9.66E+00 4.33E+0O 0.OOE+00 O.OOE+00 4.11E+04 9.10E+04 Np-239 4.66E+02 3.34E+01 2.35E+01 0.OOE+00 9.73E+01 5.81E+04 6.40E+04 K-40 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Co-57 0.OOE+00 9.03E+02 1.07E+03 0.OOE+00 0.OOE+00 5.07E+05 1.32E+04 Sr-85 4.44E+04 0.OOE+00 1.18E+04 0.OOE+00 0.OOE+00 5.55E+05 2.04E+04 Y-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 Nb-94 0.OOE+0O 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Nb-97 4.29E-01 7.70E-02 3.60E-02 0.00E+00 8.55E-02 3.42E+03 2.78E+04 Cd-109 0.OOE+00 7.03E+05 2.96E+04 0.OOE+00 6.29E+05 1.11E+06 3.OOE+04 Sn-113 1.41E+05 3.29E+03 8.51E+03 2.63E+03 O.OOE+00 1.33E+06 4.81E+03 Ba-133 4.07E+05 4.07E+03 3.70E+04 0.OOE+00 2.OOE+01 1.92E+06 3.07E+04 Te-134 5.66E-02 3.26E-02. 3.48E-02 4.59E-02 2.11E-01 4.55E+03 1.80E+03 Ce-13 9 O.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Hg-203 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3-58

Part 11 ODCM -Rev. 15 Table 3-l0d S3 INFANT INHALATION Ri(I) (mremlyr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG .GILLI H-3 0. OOE+00 6.47E+02 6.47E+02 6.4 7E+02 6.4 7E+02 6.4 7E+02 6. 47E+02 Be-7 0.OOE+00 0.O00E+00 0.O0E+00 0.00E+00 0.0 OE+00 0.OOE+00 0.OOE+00 Na-24 1.06E+04 1.06E+04 1.06E+04 1.0 6E+0 4 1. 0 6E+04 1.06E+04 1.06E+04 P-32 2.03E+06 1. 12E+05 7.7 4E+04 0.OOE+00 0. OOE+00 0. OOE+00 1. 61E+04 Cr-51 0.OOE+00 0.O00E+00 8.95E+01 5.7 5E+01. 1. 32E+01 1.2 8E+I04 3. 57E+02 Mn-S 4 0.OOE+00 2.53E+04 4..98E+03 0.OOE+00 4. 98E+03 1.OOE+06 7. 06E+03 Mn-56 0.OOE+00 1. 54E+00 2.21E-01. 0.00OE+00 1.l1OE+00 1.2 5E+04 7. 17E+04 Fe-55 1. 97E+04 1.17E+04 3.33E+03 0.OOE+00 0.0 OE+00 8.-69E+04 1. 09E+03 Fe-59 1.36E+04 2.35E+04 9.4 8E+03 0.0 0E400 0. OOE+00 1.02E+06 2. 4 8E+04 Co-58 0.00E+00 1.22E+03 1. 82E+03 0.OOE+00 0. OOE+00 7.7 7E+05 1.11E+04 Co-60 0.OOE+00 8. 02E+03 1.18E+04 0.OOE+00 o0. OOE+00 4.51E+06 3. 19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 0.0 0E400 0. OOE+00 2.09E+05 2.42E+03 Ni-65 2.39E+00 2.84E-01 1. 23E-01 0.0 OE+00 0.O0OE+00 8.1L2E+03 5. 01E+04 Cu- 64 0.OOE+00 1.88E+00 7.7 4E-01 0.OOE+00 3.98E+00 9.30E+03 1. 50E+04 Zn-65 1.93E+04 6.26E+04 3. 11E+04 0.0 0E400 3.25E+04 6.4 7E+05 5. 14E+04 Zn-69 5.39E-02 9. 67E-02 7. IBE-03 0.OOE+00 4.02E-02. 1. 47E+03 1. 32E+04 Br-83 0.OOE+00 0. OOE+00 3.81E+02 0.OOE+00 0.OOE+00 0.00,E+00 0. OOE+00 Br-84 0.OOE+00 0..OOE+00 4.OOE+02 0.OOE +00 0. OOE+00 .0. OOE +00 0.OOE+00 Br-85 0.OOE+00 0.OOE+00 2.04E+01 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Rb-86 0. OOE+00 1. 90E+05 8.82E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.04E+03 PRb-8 8 0. OOE+00 5.57E+02 2.87E+02 0.OOE+00 0.0 OE+00 0.OOE+00 3.39E+02 Rb-8 9 0. OOE+00 3.21E+02 2.06E+02 0.OOE+bO 0.OOE+00 0.OOE+00 6.82E+01 Sr-89 3. 98E+05 0.OOE+00 1. 14E+04 0.OOE+00 0.OOE+00 2.03E+06 6.40E+04 Sr-90 4. 09E+07 0.OOE+00 2.59E+06 0.OOE+00 0.OOE+00 1.12E+07 1.31E+05 Sr-91 9.56E+01 0.OOE+00 3. 46E+00 O.OOE+00 0.OOm+00 5.2 6E+04 7.34E+04 Sr-92 1. 05E+01 0.OOE+00 3. 91E-01 0.OOE+00 0.OOE+00 2.38E+04 1.40E+05 Y- 90 3.2 9E+03 0. OOE+00 8.82E+01 O.00E+00 0.OOE+00 2. 69E+05 1.04E+05 Y-91m 4. 07E-01 0. OOE+00 1.3 9E-02 0.OOE+00 -. 0.OE+00 2.7 9E+03 2.35E+03 Y-91 5.88E+05 0. OOE+00' 1.57E+04 0.OOE+00 0.OOE+00 2. 45E+06 7.03E+04 Y-92 1.64E+01 0.OOE+00 -4. 61E-01 0.OOE+00 0.00E+00 2.45E+04 1. 27E+05 Y-93 1. 50E+02 0.OOE+00 4.07E+00 0.OOE+00 0.OOE+00 7. 64E+04 1. 67E+05 Zr-95 1. 15E+05 2.79E+04 2.03E+04 0.OOE+00 3.11E+04. 1.75E+06 2.17E+04 Zr-9'7 1. 50E+02 2.56E+01 1.17E+01 0.OOE+00 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.43E+03 3.7 8E+03 0.OOE+00 4.7 2E+03 4.7 9E+05 1.27E+04 Mo- 99 0.OOE+00 1. 65E+02 3.23E+01 0.OOE+00 2 . 65E+02 1.35E+05 4.87E+04 Tc- 99m 1.40E-03 2. 88E-03 3.72E-02 0.OOE+00 3.11E-02 8.11E+02 2.03E+03 Tc-101 6.51E-05 8.23E-05 B. 12E-04 0.OOE+00 9.7 9E-04 5.84E+02 8. 44E+02 Ru-103 2.02E+03 0.OOE+00 6.7 9E+02 0.OOE+00 4.24E+03 5.52E+05 1. 61E+04 Ru-lOS 1.22E+00 0.OOE+00 4. lOE-0l 0.00OE+00 8.99E-01 1.-57E+04 4. 84E+04 Ru-106 8.68E+04 0.O00E+00 1.09E+04 0.OOE+00 1. 07E+05 1.16E+07 1. 64E+05 Ag-il Om 9. 98E+03 7.22E+03 5.OOE+03 0.OOE+00 1.09E+04 3.67E+06 3.30E+04 Sb-122 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 Sb-124 3.79E+04 5.56E+02 1.20E+04 1.O01E+02 0. OOE+00 2.65E+06 5. 91E+04 Sb-125 5.17E+04 4. 77E+02 1.09E+04 6.23E+01 0. OOE+00 1.64E+06 1. 47E4-04 3-59

Part I ODCM - Rev. 15 Table 3-10d 3

INFANT INHALATION Ri (I) (mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.OOE+00 4.47E+05 1.29E+04 Te-127m 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+04 9.53E-01 4.89E-01 1.85E+00 4.86E+00 1.03E+04 2.44E+04 Te-129m 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.OOE+03 2.63E+04 Te-131m 1.07E+02 5.50E+0l 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.OOE-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 1-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 0.OOE+00 1.99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.OOE+00 1.06E+03 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 0.OOE+00 1.90E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+00 2.16E+03 1-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+00 1.29E+03 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 0.OOE+00 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 0.OOE+00 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04 1.35E+05 5.29E+04 0.OOE+00 5.64E+04 1.18E+04 1.43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 0.OOE+00 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 0.OOE+00 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+00 9.84E-04 4.30E-02 0.OOE+00 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 0.OOE+00 1.34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-01 1.08E-04 4.97E-03 0.00E+00 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 0.OOE+00 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.OOE+02 5.15E+01 0.OOE+00 0.OOE+00 1.68E+05 8.48E+04 La-142 1.03E+00 3.77E-01 9.04E-02 0.OOE+00 0.OOE+00 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.67E+04 1.99E+03 0.OOE+00 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E+02 1.93E+02 2.21E+01 0.OOE+00 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1.76E+05 0.OOE+00 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 0.OOE+00 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 0.OOE+00 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.OOE+02 0.OOE+00 3.15E+03 3.22E+05 3.12E+04 W-187 1.30E+01 9.02E+00 3.12E+00 0.OOE+00 0.OOE+00 3.96E+04 3.56E+04 Np-239 3.71E+02 3.32E+01 1.88E+01 0.OOE+00 6.62E+01 5.95E+04 2.49E+04 K-40 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Co-57 0.OOE+00 6.51E+02 6.41E+02 0.OOE+00 0.OOE+00 3.79E+05 4.86E+03 Sr-85 3.78E+04 0.OOE+00 7.56E+03 0.OOE+00 O.OOE+00 4.20E+05 6.72E+03 Y-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-94 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 O.OOE+00 Nb-97 3.42E-01 7.29E-02 2.63E-02 0.OOE+00 5.70E-02 3.32E+03 2.69E+04 Cd-109 O.OOE+00 3.64E+05 1.40E+04 0.OOE+00 2.80E+05 8.68E+05 1.12E+04 Sn-113 8.40E+04 2.24E+03 5.04E+03 1.82E+03 0.00E+00 1.09E+06 1.68E+03 Ba-133 2.66E+05 2.38E+03 1.82E+04 0.OOE+00 1.25E+01 1.27E+06 1.08E+04 Te-134 4.45E-02 2.86E-02 2.35E-02 4.07E-02 1.34E-01 4.10E+03 3.54E+03 Ce-139 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Hg-203 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 3-60

Part II ODCM -Rev. 15 Table 3-11a ADULT INGESTION (Leafy Vegetable) Ri(V 2 3 m

• mrem/yr per uCi/sec (H-3: rnrem/yr per uCi/m Isotope BONE. LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0. OOE+00 2.26E+03 2.26E+03 2.2 6E+03 2.2 6E+03 2.2 6E+03 2.26E+03 Be-7 9.3 6E+04 2.i11E+ 5, 1.05E+05 0.OOE+00 2.22E+05 0.OOE+00 3. 65E+07 Na-24 2. 69E+05 2.69E+05 2.69E+05 2. 69E+0 5 2. 69E+05 2. 69E+05 2. 69E+05 P-32 1.40E+09 8.73E+07 5.43E+07 O.OOE+00 0.00OE400 0.OOE+00 1.58E+08 Cr-5i 0.OOE+O0 0.OOE+00 4 . 64E+04 2.78BE+04 1.02E+04 6.16E+04 1.17E+07 Mn-54 0.OOE+O0 3.13E+08 5.97E+07 0.OOE+00 9.31E+07 0.00OE+00 9.58E+08 Mn-56 0. OOE+00 1.59E+Oi1 2.82E+00 0.OOE+00 2.02E+01 0.OOE+00 5.07E+02 Fe-S55 2.10E+08 1.45E+08 3 .38E+07 0.OOE+00 0.OOE+00 8; 08E+07 8.31E+07 Fe-S 9 1.26E+OB8 2.9 6E+08 1.13E+08 0.OOE+00 0.00OE+0O 8.27E+07 9.86E+08 Co-58 0.OOE+00 3.07E+07 6.8 9E+07 0.OOE+00 0.OOE+00 0.OOE+00 6.23E+08 Co-60 0.OOE+0O 1.67E+08 3.69E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.14E+09 Ni-63 1.04E+10 7.21E+08 3.4 9E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.50E+08 Ni-65 6.15E+01 7.99E+00 3.64E+00 0.OOE+00 0.OOE+00 0.OOE+00 2.03E+02 Cu-64 0.OOE+00 9.20E+03 4.32E+03 0.OOE+00 2.32E+04 0.OOE+00 7.84E+05 Zn-65 3.17E+08 1.O01E+0 9 4.56E+08 0.OOE+00 6.75E+08 0.OOE+00 6.36E+08 Zn-69 8.73E-06 .1.67E-05 1.16E-06 0.OOE+00 1.09E-05 0.OOE+00 2.51E-06 Br-83 0.OOE+00 0.OOE+00 3.11E+00 O.00E+00 0.OOE+00 0. OOE+00 4.47E+00 Br-84 0 .+OOE+00 0.OOE+00 2.48E-11 0.OOE+00 0.OOE+00 0. OOE+00 1. 94E-16 Br-85 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.600E+00 0. OOE+00 0.OOE+00 Rb-86 0.O0OE+ 00 2.19E+08 1.02E+08 0.OOE+bo 0.00OE+00 0. OOE+00 4.33E+07 Rb-88 0.OOE+00 3.43E-22 1.82E-22 0.OOE+00 0.OOE+00 0. 00E+00 4.74E-33 Rb-B 9 0.OOE+00 1.39E-26 9.74E-27 0.OOE+00 0.OOE+00 0. OOE+00 8.05E-40 Sr-B 9 9.96E+09 0.00E4-00 2.8 6E+08 0.OOE+00 0.OOE+00 0. OOE+00 1.60E+09 Sr-90 6.05E+ll 10.OOE+00 1. 48E+l1 0.OOE+00 0.OOE+00 0.OOE+00. 1.75E+10 Sr-91 3.05E+05 0.OOE+00 1 .23E+04 0.OOE+00 0. OOE+00 0. OOE+00 1.45E+06 Sr-92 4.27E+02 0.OOE+00 1.85E+01 0.OOE+O0 0.OOE+00 0. OOE+00 8.45E+03 Y-90 1.33E+04 0.OOE+00 3.56E+02 0.OOE+00 0.OOE+00 0. OOE+00 1.41E+08 Y-91za 5.22E-09 0.OOE+00 2.02E-10 0.OOE+00 0.OOE+00 0.00E+O0 1.53E-08 Y-91 5.l11E+06 0.OOE+00 1 .37E+05 0.OOE+00 0.OOE+00 0. OOE+O0 2. 81E+09.

Y-92 9.15E-01 0.OOE+00 2.68E-02 0.OOE+00 0.OOE+00 0. OOE+00 1. 60E+04 Y-93 1.70E+02 0.OOE+00 4 . 68E+00 0.OOE+00 0.OOE+00 0.OOE+00 5.38E+06 Zr-95 1.17E+06 3.77E+05 2.55E+05 0.OOE+00 5. 91E+05 0. OOE+O0 1.19E+0 9 Zr- 97 3.37E+02 6.8B1E+01. 3.11E+01 0.OOE+00 1.03E+02 0. OOE+O0 2. 11E+07 Nb-95 1.43E+05 7.94E+04 4 .27E+04 0.OOE+00 7.85E+04 0. OOE+00 4.82E+08 Mo-9 9 0.OOE+00 6.15E+06 1.17E+06 0.OOE+00 1.3 9E+07 0.OOE+O0 1.43E+07 Tc- 99m 3.10E+00 8.77E+00 1 . 12E+02 0.OOE-I00 1.33E+02 4.30E+00 5. 19E+03 Tc-i01 8.22E-31 1.1BE-30 1.16E-29 0,OOE+00 2.13E-29 6.05E-31 3.56E-42 Ru-i 03 4.7 6E+06 0.OOE+00 2.05E+06 0.OOE+00 1.82E+07 0.OOE+00 5.56E+08 Ru-lOS 5.39E+02. 0.OOE+00 2. 13E+01 0.OOE+00 6. 96E+02 0.OOE+00 3. 29E+04 Ru-106 1.93E+08 0.OOE+00 2. 44E+07 0.OOE+00 3.72E+08 0.OOE+00 1.25E+10 Ag-i h0r 1.05E+07 9.75E+06 5.7 9E+06 0.OOE+00 1.92E+07 0.OOE+00 3. 98E+09 Sb-122 2.80E+05 6.43E+03 9.65E+04 4.34E+03 0.OOE+00 1.68E+05 1.0 6E+0 8 Sb-i24 1.04E+08 1.96E+06 4.07E+07 2 .52E+05 6.OOE+00 8.07E+07 2. 94E+09 Sb-i25 1.37E+08 1.53E+06 3.25E+07 1.39E+05 0.OOE+00 05M+-08 1-509+09 I1.

3-61

Part II ODCM - Rev. 15 Table 3-11a ADULT INGESTION (Leafy Vegetable) Ri(V) 2 3 m

• ntrem/yr per uCi/sec (H-3: mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 9.66E+07 3.50E+07 1.29E+07 2. 90E+07 3.93E+08 0.00E+00 3.86E+08 Te-127m 3.49E+08 1.25E+08 4.26E+07 8. 92E+07 1.42E+09 0.OOE+00 1.17E+09 Te-127 5.66E+03 2.03E+03 1.22E+03 4.19E+03 2.31E+04 0.00E+00 4.47E+05 Te-129m 2.51E+08 9.38E+07 3. 98E+07 8. 63E+07 1.05E+09 0.OOE+00 1.27E+09 Te-129 7.62E-04 2.87E-04 1. 86E-04 5. 85E-04 3.20E-03 o.OOE+00 5.75E-04 Te-131m 9.12E+05 4.46E+05 3.72E+05 7.06E+05 4.52E+06 0.OOE+00 4. 43E+07 Te-131 1.50E-15 6.27E-16 4.74E-16 1. 23E-15 6.57E-15 0.OOE+00 2.13E-16 Te-132 4.30E+06 2.78E+06 2. 61E+06 3.07E+06 2. 68E+07 o.OOE+00 1.32E+08 1-130 3.92E+05 1.16E+06 4.57E+05 9.81E+07 1 81E+06 o.00E+0 9.9 6E+05 1-131 8.08E+07 1.16E+08 6. 62E+07 3.79E+10 1. 98E+08 0.00E+00 3.05E+07 1-132 5.76E+01 1.54E+02 5.39E+01 5.39E+03 2.45E+02 o.OOE+00 2.89E+01 1-133 2.09E+06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 o.OOE+00 3.26E+06 1-134 9.65E-05 2.62E-04 9*38E-05 4.54E-03 4.17E-04 o.OOE+00 2.29E-07 1-135 3.90E+04 1. 02E+05 3.77E+0. 6.73E+06 1.64E+05 o.OOE+00 1.15E+05 Cs-134 4. 67E+0 9 1.11E+10 9.08E+09 0.OOE+00 3.59E+09 1.19E+09 1. 94E+08 Cs-136 4.24E+07 1. 68E+08 1.21E+08 0.OOE+00 9.32E+07 1.28E+07 1. 90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 0.OOE+00 2.95E+09 9.81E+08 1. 68E+08 Cs-138 3. 91E-11 7.73E-11 3.83E-11 0.OOE+00 5.68E-11 5.61E-12 3.30E-16 Ba-139 2. 68E-02 1.91E-05 7.86E-04 0.OOE+00 1.79E-05 1.08E-05 4.76E-02 Ba-140 1.28E+08 1.61E+05 8.38E+06 0. OOE+00 5.46E+04 9.20E+04 2. 63E+08 Ba-141 1. 15E-21 8.70E-25 3.89E-23 0. OOE+00 8. 09E-25 4.94E-25 5. 43E-31 Ba-142 2. 46E-39 2.53E-42 1.55E-40 0.OOE+00 2.14E-42 1.43E-42 0.OOE+00 La-140 1. 98E+03 9.98E+02 2.64E+02 0.OOE+00 O.OOE+00 0.OOE+00 7.33E+07 La-142 1.41E-04 6.43E-05 1. 60E-05 0.OOE+00 0.OOE+00 0.OOE+00 4. 69E-01 Ce-141 1. 97E+05 1.33E+05 1.51E+04 0.0 0E+00 6.19E+04 0.OOE+00 5. 10E+08 Ce-143 9.98E+02 7.38E+05 8.16E+01 0.OOE+00 3.25E+02 0.OOE+00 2.7 6E+07 Ce-144 3.29E+07 1.38E+07 1.77E+06 0.OOE+00 8.16E+06 0.OOE+00 1.11E+10 Pr-143 6.26E+04 2.51E+04 3.10E+03 0.OOE+00 1.45E+04 0.OOE+00 2.74E+08 Pr-144 3.09E-26 1.28E-26 1.57E-27 0.OOE+00 7.23E-27 0.OOE+00 4. 44E-33 Nd-147 3.33E+04 3.85E+04 2.31E+03 0.OOE+00 2.25E+04 0.OOE+00 1.85E+08 W-187 3.82E+04 3.19E+04 1. 12E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.05E+07 Np-239 1. 43E+03 1.41E+02 7.76E+01 0.OOE+00 4.39E+02 0.OOE+00 2. 89E+07 K-40 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 0.OOE+O0 0.OOE+00 Co-57 0.OOE+00 1.17E+07 1.95E+07 0.OOE+00 0.OOE+00 0.OOE+00 2.97E+08 Sr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0. OOE+00 Y-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Nb-94 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0. OOE+00 0.OOE+O0 0.OOE+00 Nb-97 2.15E-06 5.45E-07 1. 99E-07 0.OOE+00 6.35E-07 0.0 0E+00 2.01E-03 Cd-109 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Sn-113 0.60E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-133 0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Te-134 3.56E-08 2.33E-08 1. 43E-08 3. 11E-08 2.25E-07 0.OOE+00 3. 95E-11 Ce-139 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Hg-203 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3-62

Part 11 ODCM - Rev. 15 Table 3-11b, TEEN INGESTION (Leafy Vegetable) Ri(V 3

2 m *mxem/yr per uCi/sec (H-3: mrexufyr per uCilm BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Isotope O.OOE+OO. 2.59E+03 2.59E+03 2.59E+03 2ý59E+O3 2.59E4-03 2.59E+03 H1-3 l.43E+0 5 3.20E+05 1.60E+05 O.OOE+OO 3.39E+05 O.OOE+OO 3.90E+07 Be-7 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E4-05 Na-24 1.61E+09 9.97E+07 6.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+08 P-32 O.OOE400 O.OOE+OO 6.17E+04 3.43E+04 1.35E+04 8.81E+04 1.04E4-07 Cr-51 O.OOE+OO 4.54E+08 9.01E+07 O.DOE+OO 1.36E+08 O.OOE+00 9.32E4-08 Mn-54 O.OOE+OO 1.43E+01 2..55E+00 O.OOE+OO 1.81E+01 O.OOE+OO 9.44E+02 Mn-56 3.26E+08 2.31E+08 .5.39E+07 O.OOE+OO O.OOE+OO 1.47E+08 l.OOE+08 Fe-55 1.79E+08 4.18E+08 1.61E+08 O.OOE+OO O.OOE+OO 1.32E+08 9.88E+08 Fe-59 0O*OOE+OO 4.36E+.07 1.OOE+08 O.OOE+OO O.OOE+OO O-OOE+00 6.01E+'08 Co-58 O.OOE+OO 2.49E+08 5.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 Co-60 1.61E+10 1.13E+09 5.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+08 Ni-63 5.72E+01 7.31E+00 3.33E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.97E+02 Ni-65 O.OOE+OO 8.34E+03 3.92E+03 O.OOE+OO 2.11E+04 O.OOE+00 6.47E+05 Cu-64 4.24E+08 1.47E+09 6.86E+08 O.OOE+OO 9.42E+08 O.OOE+OO 6.23E+08 Zn-65 8.18E-06 1..56E-05 1.09E-06 O.OOE+OO 1.02E-05 O.OOE+OO 2.87E-05 Zn-69 O.OOE+OO O.OOE+OO 2.91E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 2.25E-11 O.OOE+OO 6.00E+00 O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 0.OOE+00 0.06E+00 O.OOE+0O O.OOE+OO O.OOE+OO Br-85 O.OOE+OO 2.74E+08 1.29E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.05E+07 Rb-86 O.OOE+OO 3.17E-22 l;69E-22 O.OOE+OD O.OOE+OO O.OOE+OO 2.71E-29 Rb-88 O.OOE+OO 1.25E-26 8.82E-27 O.OOE+OO O.OOE+OO O.OOE+OO 1.91t-35 Rb-89 1.51E+10 O.OOE+OO 4.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+09 Sr-89 7.51E+11 O.OOE+OO 1.85E+11 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+10 Sr-90 2.85E+05.O.OOE+OO. 1.13E+04 O.OOE+OO. O.OOE+OO O.OOE+OO 1.29E+06 Sr-91 3.97E+02 O.OOE+OO 1.69E+01 O.OOE+0O O.OOE+OO O.OOE+OO 1.01E+04 Sr-92 1.24E+04 O.OOE+00O 3.34E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Y-90 4.86E-09 O.OOE+OO 1.86E-10 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-07 Y-91M 7.84E+06 O.OOE+OO 2.10E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+09 Y-91 8.60E-01 O.OOE+OO 2.49E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.36E+04 Y-92 1.59E+02 O.OOE+OO 4.36E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.86E+06 Y-93 1.72E+06 5.43E+05 3.73E+05 O.OOE+OO 7.98E+05, O.OOE+OO 1.25E+09 Zr-95 3.12E+02 6.18E+01 2.85E+01 O.OOE+OO 9.37E+01 O.OOE+OO 1.67E+07 Zr-97 1.93E+05 l.07E+05 5.89E4-04 O.OOE+OO 1.04E+05 O.OOE+OO 4.57E+08 Nb-95 O.OOE+OO 5.65E+06 1.08E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.OlE+07 Mo-99 2.74E+00 7.63E+00 9.89E+01 O.OOE+OO 1.14E+02 4.24E+00 5.01E+03 Tc-99m 7-64E-31 1.09E-30 1.07E-29 O.OOE+OO 1.97E-29 6.62E-31 1.86E-37 Tc-1O1 6.81E+06 O.OOE+OO 2.91E+06 O.QOE+OO 2.40E+07 O.OOE+OO 5.69E+08 Ru-103 5.OOE+O1 O.OOE+OO l.94E+Ol O.OOE+0O 6.31E+02 O.OOE+OO 4.'04E+04 Ru-105 3.10E+08 O.OOE+OO 3.90E+07 O.OOE+OO 5.97E+08 O.OOE+OO 1.48E+10 Ru-lOE 1.52E+07 1.43E+07 8.72E+06 O.OOE+OO 2.74E+07 O.OOE+0O 4.03E+09 Ag-110n 3.03E+05 5.89E+03 8.85E+04 3.85E+03 O.OOE+OO 1.89E+05 6.35E+07 Sb-122 1.54E+08 2.84E+06 6.02E+07 3.50E+05 O.OOE+OO 1.34E+08 3.11E+09 Sb-124 2.14E+08 2.34E+06 5.OOE+07 2.04E+05 O.OOE+OO 1.86E+08 1.66E+09 Sb-125 3-63

Part 1 ODCM - Rev. 15 Table 3-11b TEEN INGESTION (Leafy Vegetable) Ri(V) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.OOE+0O 0.OOE+00 4.37E+08 Te-127m 5.51E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 O.OOE+00 1.37E+09 Te-127 5.34E+03 1.89E+03 1.15E+03 3.68E+03 2.16E+04 0.OOE+00 4.12E+05 Te-129m 3.62E+08 1.34E+08 5.73E+07 1.17E+08 1.51E+09 O.OOE+00 1.36E+09 Te-129 7.14E-04 2.66E-04 1.74E-04 5.10E-04 3.OOE-03 0.OOE+00 3.90E-03 Te-131m 8.44E+05 4.05E+05 3.38E+05 6.09E+05 4.22E+06 0.OOE+00 3.25E+07 Te-131 1.39E-15 5.75E-16 4.36E-16 1.07E-15 6.10E-15 0.OOE+00 1.14E-16 Te-132 3.91E+06 2.47E+06 2.33E+06 2.61E+06 2.37E+07 0.00E+00 7.84E+07 1-130 3.51E+05 1.01E+06 4.05E+05 8.28E+07 1.56E+06 0.00E+00 7.80E+05 1-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 1-132 5.19E+01 1.36E+02 4.88E+01 4.58E+03 2.14E+02 0.OOE+00 5.92E+01 1-133 1.94E+06 3.29E+06 1.OOE+06 4.59E+08 5.76E+06 O.00E+00 2.49E+06 1-134 8.73E-05 2.31E-04 8.31E-05 3.85E-03 3.65E-04 0.00E+00 3.05E-06 1-135 3.52E+04 9.07E+04 3.36E+04 5.83E+06 1.43E+05 0.00E+00 1.00E+05 Cs-134 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.34E+07 1.71E+08 1.15E+08 0.00E+00 9.30E+07 1.47E+07 1.37E+07 Cs-137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 Cs-138 3.61E-11 6.93E-11 3.47E-11 0.OOE+00 5.12E-11 5.96E-12 3.15E-14 Ba-139 2.52E-02 1.78E-05 7.35E-04 0.OOE+00 1.67E-05 1.22E-05 2.25E-01 Ba-140 1.37E+08 1.68E+05 8.85E+06 0.00E+00 5.70E+04 1.13E+05 2.12E+08 Ba-141 1.08E-21 8.04E-25 3.59E-23 0.00E+00 7.46E-25 5.50E-25 2.29E-27 Ba-142 2.27E-39 2.27E-42 1.40E-40 0.00E+00 1.92E-42 1.51E-42 0.00E+00 La-140 1.81E+03 8.89E+02 2.37E+02 0.OOE+00 0.00E+00 0.OOE+00 5.11E+07 La-142 1.30E-04 5.76E-05 1.43E-05 0.OOE+00 0.00E+00 0.00E+00 1.75E+00 Ce-141 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.89E+04 0.00E+00 5.40E+08 Ce-143 9.33E+02 6.79E+05 7.58E+01 0.OOE+00 3.04E+02 0.00E+00 2.04E+07 Ce-144 5.27E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.OOE+00 1.33E+10 Pr-143 7.00E+04 2.80E+04 3.49E+03 0.OOE+00 1.63E+04 0.00E+00 2.30E+08 Pr-144 2.89E-26 1.18E-26 1.47E-27 0.OOE+00 6.80E-27 0.OOE+00 3.19E-29 Nd-147 3.62E+04 3.94E+04 2.36E+03 0.OOE+00 2.31E+04 0.00E+00 1.42E+08 W-187 3.55E+04 2.90E+04 1.02E+04 0.OOE+00 0.00E+00 0.OOE+00 7.84E+06 Np-239 1.39E+03 1.31E+02 7.28E+01 0.00E+00 4.11E+02 0.00E+00 2.11E+07 K-40 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Co-57 0.00E+00 1.79E+07 3.OOE+07 0.00E+00 0.00E+00 O.OOE+00 3.33E+08 Sr-85 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Nb-97 2.OOE-06 4.95E-07 1.81E-07 0.00E+00 5.79E-07 0.OOE+00 1.18E-02 Cd-109 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Te-134 3.23E-08 2.07E-08 2.17E-08 2.65E-08 1.98E-07 0.00E+00 1.20E-09 Ce-139 0.00+E00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Hg-203 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3-64

ODCM - Rev. 15 Part 11 Table 3-11c CHILD INGESTION (Leafy Vegetable) Ri(VM 2 3 m

• mrem/yr per uCi/sec (H-3: nrem/yr per uCi/m LUNG GILLI Isotope BONE LIVER ,TOT BODY THYROID KIDNEY 0.OOE+00 4.01E+03 4.01E+03 4.01E+I03 4 .01E+03 4.O01E+03 4.01E+03 H-3 5. 63E+05 0.OOE+00 3.20E+07 3.37E+05 5.7 2E+05 3.77E+05 0. OOE+00 Be- 7 3.73E+05 3.73E+05 3. 7 3E+05 3.7 3E+05 3.7 3E+05 3 .73E+05 3.7 3E+05 Na-24 0. OOE+00 0. OOE+O0 9.31E+07 3.37E+09 1.58E+08 1. 30E+08 0. OOE+00 p-3 2 6.21E+06 0.OOE+00 0.OOE+00 1.17E+05 6.560.+04 1.78E+04 1.19E+05 Cr-51 1. 86E+08 0.OOE+O0 5. 58E+0 8 0.OOE+00 6.65E+08 1.77E+08 0. O0E+O0 Mn-54 2.7 2E+03 0 .OOE+00 1.88E+01I 4 .24E+00 0.OOE+00 2.27E+01. 0.OOE+00 mn-S 6 0 . OOE+00 2.40E+08 7. 87E+07.

8.O01E+08 4.25E+08 1.32E+08 0. OOE+00 Fe-55 0.OOE+00 1.8 6E+08 6. 68E+08 3 . 97E+08 6.42E+08 3.20E+08 0.OOE+00 Fe-59 0.OOE+00 0. OOE+O00 3.7 6E+08 0.0OE+00 6.4 4E+07 1. 97E+08 0.OOE+00 Co-58 0.OOE+00 0.OOE+00 2. 1iOE+09 0.OOE+00 3.7 8E+08 1.12E+09 0.OOE+00 co- 60 0. OOE+00 0. OOE+O0 1. 4 2E+0 8 3.95E+10 2.11E+09 1.34E+09 0.OOE+0O Ni-63 0. OOE+O0 0. OOE+O0 1.2 1E+03

1. 05E+02 9.8 9E+00 5.77E+00 0.OOE+00 Ni-65 2.66E+04. 0. OOE--00 5. 16E+05 0.OOE+00 1.10E+04 6. 64E+03 0. OOE+00 Cu- 64 3. 8 E+08 8.12E+08 2.16E+09 1.35E+09 0.OOE+00 1. 36E+09 0.OOE+O0 Zn-65 1. 32E-05. 0.OOE+00 1. 37E-03 1.51E-05 2.18E-05 2. 02E-0 6 0. OOE+00 Zn-69 0. OOE+O0 0.OOE+O0 0. OOE+00 0.OOE+00 0.OOE+00 5. 37E+00 0.OOE+00 Br-83 0. OOE+00 0.OOE+00 0. OOE+0O 0.OOE+00 0.OOE+00 3.82E-11 0.OOE+00 Br-84 0. OOE+0O 0. OOE+OO 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-85 0. OOE+00 0.OOE+00 2. 91E+07 0.OOE+00 4.52E+08 2.78E+08 0.OOE+bO Rb-86 0. OOE+0O 0.OOE+00 2. 15E-23 0.OOE+00 4.37'E-22 3.04E-22 0.OOE+00 Rb-8 8 0. OOE+00 0. OOE+00 1. 43E-28

0. OOE+00 1.64E-26 1.4 6E-2 6 0.OOE+00 Rb-8 9 0. OOE+00 0.00E+00 1.39E+09 3.59E+10 O.OOE+00 1.03E+09 0.OOE+00 Sr-8 9 0. OOE+00 0.OOE+O0 1. 67E+10 1.24E+12 0.OOE+00 3.15E+11 0.OOE+00 Sr-90 0. OOE+O0 0. OOE+00 1. 16E+0 6 5.24E+05 0.OOE+00 1.98E+04 0.OOE+00 Sr-91 0.OOE+00 0.OOE+00 1.38E+04 7 .28E+02 0.OOE+00 2.92E+01 0.OOE+00 Sr-92 6. 56E+07 2.30E+04 0.OOE+00 6.17E+02 O.OOE+00 10.OOE+O0 0. OOE+00 Y- 90 0.O60E+00 0. OOE+00 1.7 4E-05 8.91E-09 0.0OE+00 3.24E-10 0.OOE+00 Y- 91M 2.48E+09

1. 86E+07 0. OOE+00 4.99E+05 0.OOE+00 0. OOE+00 0. OOE+00 Y-91 O.OOE+00 0.OOE+0O 4 .58E+04 1.58E+00 0.OOE+00 4.53E-02 0.OOE+00 Y-92 0.OOE+o0 0. OOE+00 4.37E+06

2. 93E+02 0. OOE+00 8.04E+00 0. OOE+00 Y-93 1.21E+06 -0.OOE+0O 8.8 4E+08 3.86E+06 8.48E+05 7.55E+05 0.OOE+00 zr-95 1. 18E+02 0.OOE+00 1. 25E+07 5.70E+02 8.24E+01 4.86E+01 0. OOE+00 Zr-97 1. 51E+05 0.OOE+00 2. 97E+08 4.12E+05 1.60E+05 1.15E+05 0.OOE+00 Nb- 95 1. 65E+07 0.OOE+00 6.38E+06

0. OOE+00 7.71E+06 1.91E4-06 0.OOE+00 mo-99 1. 34E+02 4. 69E+00 5.26E+03 4.71E+00 9.24E+00 1. 53E+02 0.OOE+00 Tc-9 9m 2.51E-29 7.78E-31 4. 68E-30 1.41E-30 1.47E-30 1.87E-29 0.OOE+00 Tc-101 3.85E+07 0. OOE+00 3.96E+08

1. 53E+07 0.OOE+00 5.88E+06 0.OOE+00 Ru-103 8.05E+.02 0.OOE+0O 5.98E+04 Ru-105 9.16E+01 o. OE+00 3.32E+01 O.OOE+00 1.16E+10 7.45E+08 0.OOE+00 9.30E+07 0.OOE+00 1.O01E+09 0.OOE+00 Ru-10 6 2.58E+09 3.21E+07 2.17E+07 1.73E+07 0.OOE+00 4.04E+07 0. OOE+00 Ag-110m O.OOE+00 2.27E4-05 4.30E+07 5.58E+05 8.2 4E+03 1.64E+05 7.16E+03 Sb-122 0. OOE+00 1. 95E+0 8 2.20E+09 3.52E+08 4 .56E+06 1.23E+08 7.7 3E+05 Sb-i 24 0.OOE+00 2.78E+08 1.19E+09

4. 99E+08 3.84E+06 1.05E+08 4. 63E+05 Sb-125 3-65

Part II ODCM - Rev. 15 Table 3-iic CHILD INGESTION (Leafy Vegetable) Ri(V) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.51E+08 9.50E+07 4. 67E+07 9.84E+07 0.0 0E+00 0. OOE+00 3.38E+08 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.OOE+00 1.07E+09 Te-127 9.85E+03 2. 65E+03 2. 11E+03 6. 81E+03 2.80E+04 0.00E+00 3.85E+05 Te-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.OOE+00 1. 03E+09 Te-129 1.32E-03 3.69E-04 3.14E-04 9.43E-04 3.87E-03 0.OOE+00 8.23E-02 Te-131m 1.54E+06 5.33E+05 5.68E+05 1.10E+06 5.16E+06 O.00E+00 2.16E+07 Te-131 2.57E-15 7.83E-16 7.64E-16 1. 97E-15 7.77E-15 0.OOE+00 1.35E-14 Te-132 7.00E+06 3.1OE+06 3.74E+06 4.51E+06 2.8 8E+07 0.OOE+00 3. 12E+07 1-130 6.16E+05 1.24E+06 6.41E+05 1.37E+08 1.8 6E+06 0.OOE+00 5.82E+05 1-131 1.43E+08 1.4 4E+08 8.17E+07 4.75E+I0 2.36E+08 0.OOE+00 1. 28E+07 1-132 9.22E+01 1. 69E+02 7.79E+01 7.86E+03 2.59E+02 0.OOE+00 1. 99E+02 1-133 3.53E+06 4.37E+06 1. 65E+06 8. ilE+08 7.28E+06 0.00E+00 1. 76E+06 1-134 1.55E-04 2.88E-04 1.32E-04 6.62E-03 4.40E-04 0.OOE+00 1. 91E-04 1-135 6.26E+04 1. 13E+05 5.33E+04 9.97E+06 1.73E+05 0.00E+00 8.58E+04 Cs-134 1.60E+10 2.63E+I0 5.55E+09 0.OOE+00 8.15E+09 2. 93E+0 9 1.42E+08 Cs-136 8.17E+07 2.25E+08 1.45E+08 0.00E+00 1.20E+08 1.78E+07 7. 90E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 0.OOE+00 7. 46E+09 2.68E+09 1. 43E+08 Cs-138 6.57E-11 9.13E-II 5.79E-11 0. OOE+00 6.43E-11 6. 91E-12 4. 21E-I1 Ba-139 4. 65E-02 2.48E-05 1.35E-03 0. OOE+00 2.17E-05 1.46E-05 2. 69E+00 Ba-140 2.75E+08 2. 41E+05 1.60E+07 0.OOE+00 7.84E+04 1.44E+05 1.39E+08 Ba-141 1.99E-21 1.IIE-24 6.47E-23 0.OOE+00 9.62E-25 6.53E-24 1.13E-21 Ba-142 4.11E-39 2.96E-42 2.29E-40 0.00E+00 2.39E-42 1. 74E-42 5.36E-41 La-140 3.25E+03 1.14E+03 3.83E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.17E+07 La-142 2.35E-04 7.49E-05 2.35E-05 0.OOE+00 0.00E+00 0.OOE+00 1.48E+01 Ce-141 6.56E+05 3'.27E+05 4.86E+04 0.OOE+00 1.43E+05 0.OOE+00 4.08E+08 Ce-143 1.72E+03 9.31E+05 1.35E+02 0.OOE+00 3.91E+02 0.00E+00 1. 36E+07 Ce-144 1.27E+08 3.98E+07 6.78E+06 0.OOE+00 2.21E+07 0.OOE+00 1.04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 0.OOE+00 2.37E+04 0.OOE+00 1.57E+08 Pr-144 5.37E-26 1.66E-26 2.70E-27 0.OOE+00 8.79E-27 0.00E+00 3.58E-23 Nd-147 7.15E+04 5.79E+04 4.48E+03 0.OOE+00 3.18E+04 0.00E+00 9.17E+07 W-187 6.47E+04 3.83E+04 A.72E+04 0.OOE+00 0.OOE+00 0.OOE+00 5.38E+06 Np-239 2.57E+03 1.84E+02 1.29E+02 0.OOE+00 5.33E+02 0.OOE+00 1. 36E+07 K-40 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.001E+00 Co-57 0.00E+00 2.99E+07 6.04E+07 0.OOE+00 0.00E+00 0.00E+00 2.45E+08 Sr-85 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0. OOE+00 0.00E+00 0.001E+00 Y-88 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-94 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.001E+00 Nb-97 3.64E-06 6.57E-07 3.07E-07 0.OOE+00 7.29E-07 0.OOE+00 2.03E-01 Cd-109 0.OOE+00 0.00E+00 0,OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.001E+00 Sn-113 0.00E+00 0.00E+00 0.0 0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-133 0.00E+00 0.OOE+00 0. 00E+00 0.OOE+00 0.00E+00 0.OOE00 0.00E+00 Te-134 5.76E-08 2.59E-08 3.4 6E-08 4.56E-08 2. 40E-07 0.OOE+00 2.63E-07 Ce-139 O.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Hg-203 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.001E+00 3-66

Part II ODCM - Rev. 15 Table 3-12 Total Body & Skin Ground Plane Dose Factors Ri(G) and Ri(S) 2 (m

• mrem/yr per uCi/sec)

-1 Isotope Decay Constant (sec) Ri (G) Ri (S)

H-3 1. 78OE-09 0.OOE+00 0.OOE+00 Be-7 1.505E-07 0.OOE+00 0.OOE+00 Na-24 1.284E-05 1 19E+07 1.39E+07 P-32 5.614E-07 0. OOE+00 0.OOE+00 Cr-51 2.896E-07 4.66E+06 5.51E+06 Mn-54 2.567E-08 1. 39E+409 1. 62E+09 Mn-56 7.467E-05 9.03E+05 1.07E+06 Fe-55 8.141E-09 0 00E+00 0.OOE+00 Fe-59 1. 802E-07 2.72E+08 3.20E+08 Co-58 1. 133E-07 3. 79E+08 4. 44E+08 Co-60 4.170E-09 2. 15E+i0 2.53E+10 Ni-63 2.290E-10 0. OOE+00 0.0 OE+00 Ni-65 7.641E-05 2. 97E+05 3. 45E+05 Cu-64 1.516E-05 6. 07E+05 6. 88E+05 Zn-65 3.289E-08 7. 46E+08 8.58E+08 Zn-69 2.027E-04 0.OOE+00 0. OOE+00 Br-83 8.056E-05 4. 87E+03 7. 08E+03 Br-84 3.633E-04 2.03E+05 2.36E+05 Br-85 3.851E-03 0.OOE+00 0.0 0E+00 Rb-86 4.299E-07 8. 99E+06 1.03E+07 Rb-88 6. 490E-04 3.31E+04 3. 78E+04 Rb-89 7.600E-04 1.21E+05 1.45E+05 Sr-89 1.589E-07 2.16E+04 2.51E+04 Sr-90 7.548E-i0 0.OOE+00 0.OOE+00 Sr-91 2.027E-05 2.15E+06 2.51E+06 Sr-92 7.105E-05 7.77E+05 8. 63E+05 Y-90 3.008E-06 4 .48E+03 5.30E+03 Y-91m 2.324E-04 1.OOE+05 1.16E+05 Y-91 1.371E-07 1.07E+06 1.21E+06 Y-92 5.439E-05 1.80E+05 2. 14E+05 Y-93 1. 906E-05 1.83E+05 2.51E+05 Zr-95 1.254E-07 2.45E+08 2.84E+08 Zr-97 1.139E-05 2.96E+06 3. 44E+06 Nb-95 2.282E-07 1.37E+08 1.61E+08 Mo-99 2. 917E-06 3.99E+06 4.62E+06 Tc-99m 3.198E-05 1.84E+05 2.11E+05 Tc-101 8.136E-04 2.04E+04 2.26E+04 Ru-103 2.042E-07 1.08E+08 1.26E+08 Ru-105 4.337E-05 6.36E+05 7.21E+05 Ru-106 2. 179E-08 4.22E+08 5.07E+08 Ag-li0m 3.210E-08 3.44E+09 4.01E+09 Sb-122 2. 971E-06 0.OOE+00 0.OOE+00 Sb-124 1.333E-07 5.98E+08 6.90E+08 Sb-125 7. 935E-09 2.34E+09 2.64E+09 3-67

Part II ODCM - Rev. 15 Table 3-12 Total Body & Skin Ground Plane Dose Factors Ri(G) and Ri(S) 2 (m

• mrem/yr per uCi/sec)

-1 Isotope Decay Constant (sec) Ri (G) Ri (S)

Te-125m 1..383E-07 1.55E+06 2.13E+06 Te-127m 7.360E-08 9.16E+04 1. 08E+05 Te-127 2.059E-05 2.98E+03 3.28E+03 Te-129m 2.388E-07 1.98E+07 2.31E+07 Te-129 1. 660E-04 2.62E+04 3.10E+04 Te-131m 6.4 18E-06 8.03E+06 9.46E+06 Te-131 4.621E-04 2.92E+04 3.45E+07 Te-132 2.462E-06 4.23E+06 4. 98E+06 1-130 1.558E-05 5.51E+06 6.69E+06 1-131 9.978E-07 1.72E+07 2.09E+07 1-132 8. 371E-05 1.25E+06 1.46E+06 1-133 9.257E-06 2.45E+06 2.98E+06 1-134 2. 196E-04 4.47E+05 5.30E+05 1-135 2.913E-05 2.53E+06 2.95E+06 Cs-134 1.066E-08 6.86E+09 8.00E+09 Cs-136 6. 124E-07 1.50E+08 1.70E+08 Cs-137 7.327E-10 1.03E+10 1.20E+10 Cs-138 3.588E-04 3.59E+05 4.10E+05 Ba-139 1.397E-04 1.05E+05 1.19E+05 Ba-140 6.297E-07 2.04E+07 2.34E+07 Ba-141 6.323E-04 4.17E+04 4.75E+04 Ba-142 1. 090E-03 4. 44E+04 5.06E+04 La-140 4.781E-06 1.92E+07 2. 18E+07 La-142 1.24 9E-04 7.36E+05 8.84E+05 Ce-141 2.468E-07 1.37E+07 1.54E+07 Ce-143 5.835E-06 2.31E+06 2.63E+06 Ce-144 2.822E-08 6. 95E+07 8.04E+07 Pr-143 5. 916E-07 0.00E+00 o.00E+00 Pr-144 6. 685E-04 1.83E+03 2. 11E+03 Nd-147 7.306E-07 8.39E+06 1.01E+07 W-187 8.056E-06 2.36E+06 2.74E+06 Np-239 3.399E-06 1.71E+06 1.98E+06 K-40 1.717E-17 0.00E+00 0.OOE+00 Co-57 2.961E-08 1.88E+08 2.07E+08 Sr-85 1.237E-07 0.00E+00 0.OOE+00 Y-88 7.523E-08 0.00E+00 0.00E+00 Nb-94 1. 083E-12 0.00E+00 0.00E+00 Nb-97 1. 602E-04 1.76E+05 2.07E+05 Cd-109 1.729E-08 0.OOE+00 0.00E+00 Sn-113 6. 970E-08 0.00E+00 0.00E+00 Ba-133 2.047E-09' 0.OOE+00 0.00E+00 Te-134 2.764E-04 2.22E+04 2.66E+04 Ce-139 5.828E-08 0.OOE+00 0.OOE+00 Hg-203 1.722E-07 0.OOE+00 0.OOE+00 3-68

Part II ODCM - Rev. 15 Page 1 of 7 APPENDIX 3-A CALCULATION OF ALLOWABLE RELEASE RATES Primary Assumptions:

1. Unit 3 and Unit 2 effective dose factor K-bar, values are equivalent.

2. Each unit shares 50% of the total allowable release rate, Q, in Ci/sec.

Therefore, Q3 = Q2 for instantaneous releases.

Given:

1i121 LOCATION UNIT 3 UNIT 2 LOCATION Noble Gas X/Q SSW 380m 4.85E-6 2.54E-6 SSW 579m

3) 3)

(sec/m (sec/m Wv(in) Annual Average Site SW 350m 5.21 E-6 2.54E-6 SSW 579m Boundary X/Q (sec/r 3) (sec/m3 )

Wv(gp) Annual Average SSW 380m 2.72E-8 Ground Plane Site Boundary Deposition m Wv(in) Inhalation Pathway SSW 1525m 8.96E-7 Nearest Residence sec/m 3 Wv(gp) Annual. Average S 1379m 6.14E-9 Ground Plane Deposition m-Parameter Nearest Residence 3-69

Part II ODCM - Rev. 15 Appendix 3-A Page 2 of 7 INSTANTANEOUS RELEASE RATE VS. DOSE RATE UNITS 2 & 3 Indian Point 3 and 2 share a common site boundary limit of 500 mrem/yr. This 500 mrem/yr limit is divided between units 3 and 2 based upon a 50-50 split of the release rate in giCi/sec. Because each unit has its own X/Q and K-bar, equal igCi/sec discharges from each plant will result in different dose rates for each plant at the most restrictive site boundary location. In order to define the split of the 500 mrem/yr limit, units 3 and 2 have agreed to base the dose split on the mixture presented in Table 3A-1 (Appendix 3-A, page 4).

Dose Split Between IP2 and IP3 A. Instantaneous Dose Rate: Calculation of Allowable Release Rate: Noble Gas Release Including Finite Cloud Correction for Site Boundary.

L Whole Body Given:

a) site limit is 500 mrem/yr 3

b) IP3 X/Q for SSW sector = 4.85E-6 sec/rn

- m3 K-bar for IP3 SSW sector = 1.55E+3 mrem c) pUCi- yr 3

d) IP2 X/Q for SSW sector = 2.54E-6 sec/m 3 mrem - m e) IP2 K-bar for SSW sector = 2.43E+3

) Q =jCitsec Solve for Q:

-6 (X/Q 3) (K bar3) + (X/Q2) (K bar 2)] = 500 mremlyr Q[(4.85E-6) (1.55E+3) + (2.54E-6) (2.43E+3) ] = 500 mremlyr

-6=3.65E+4 gCi/sec ii. Skin Given:

a) site limit is 3,000 mremlyr 3

b) IP3 X/Q for ssW sector = 4.85E-6 sec/n mrem - m pr i- yr IP3 (Li + 1.1 Mi) =3.31E+3 c) 'UCi- yr sec/m3 d) IP2 X/Q for SSW sector = 2.54E-6 mrem - m3 e) IP2 (Li + 1.1 Mi) = 4.38E+3 f)Ci - yr f) =uCi/sec 3-70

Part II UL)L;M - Kev. lb Page 3 of 7 Appendix.3-A Solve for Q:

S[(X/Q) 3 (Li + 1.1 Mi) 3 + (X/Q)2 (Li + 1.1 Mi)] = 3,000 mrem/yr S[(4.85E-6) (3.31 E+3) + (2.54E-6) (4.38E+3)] = 3,000 mrem/yr S= 1.10E+5 1.Ci/sec (less restrictive than Whole Body)

Solve for dose commitments per site with Q = 3.65E+4 uCi/sec (WVB dose and the most restrictive rate).

Indian Point 3:

mrem - m3 ) = 275 mrem/yr

3) (1.55E+3 (3.65E+4 gCi/sec) (4.85E-6 sec/r p'Ci -yr Indian Point 2:

) = 225 mrem/yr (3.65E+4 gCi/sec) (2.54E-6 sec/m3) (2.43E+3 pCi - yr Unit 3 has 55.4% and Unit 2 has 44.6% of the 500 mrem/yr WB Dose instantaneous release rate limit.

Solve for the less restrictive skin dose rate limit for IP3:

3 rem - m (1.10E+5 uCi/sec) (4.85E-6 sec/m3) (3.31E+3 , - 1766 mrem/yr B. The conservative instantaneous release rate calculated in above step A.1 is based upon the mixture presented in Table 3A-1 solely for the purpose of splitting the dose rate as shown above. To determine an administrative release rate for IP3 based on the 275 mrem/yr dose rate (i.e., no sharing), the mix in Table 3-8 is used. The 275 mrem/yr limit and the mixture presented in Table 3-8 are used to calculate a uCi/sec instantaneous limit for IP3.

Given:

a) IP3 site boundary limit is 275 mrem/yr sec/m3 b) IP3 X/Q ssw sector = 4.85E-6 mrem - m c) IP3 K-bar (Table 3-8) = 1.49E+3 torer- plCi-yrm d) Q = uC/sec Solve for Q:

Q(4.85E-6) (1.49E+3) = 275 mrem/yr S= 3.81 E+4 pCi/sec 3-71

F-'ar* ii Page 4 of 7 Appendix 3-A Table 3A-1 MIXTURE FOR SHARED LIMITS ISOTOPE ABUNDANCE IP3 iP2

.0362 1.55E+3 2.43E+3 Kr-85m Ki*

.0790 Li 1.51 E+3 1.51E+3 Kr-88

.4027 Mi* 1.63E+3 2.61 E+3 Xe-133 Xe-135m .0740 Xe-138 .1467 Xe-I 35 .2614 mrem - m Ki units PCi-yr mrem - m Li units mrem- m Mi units The SSW sector is the most restrictive for both whole body exposure and skin exposure for both units 2 and 3.

Dose factors Ki and Mi are finite cloud corrected for each reactor unit and hence they are not identical.

3-72

UJLIVI -- raiv. IU Part II Page 5 of 7 Appendix 3-A RELEASE RATE LIMITS QUARTERLY AND ANNUAL AVERAGE NOBLE GAS RELEASES For a Calendar Quarter For a Calendar Year 5 mrad limit 10 mrad limit gamma air dose 10 mrad limit 20 mrad limit beta air dose I. Assumptions: Doses are delivered to the air at the site boundary.

3. Finite cloud geometry is assumed for noble gas releases at site boundary.

4. XIQ for Unit 3 = 4.85E-6 sec/m3, (Q = release rate uCi/sec)

5. Gamma air dose factor (M), Corrected for finite cloud geometry is:

mrem - m3 M= 4.6.1 E+2 (time average mix from Table 3-8)

XCi- yr

6. Beta air dose factor (N)is unaffected by finite cloud assumption:

N = 1.34E+3 mt'rem'- im (from Table 3-8) pCi .yr I1. Calculation of Quarterly Release Rates:

a) for gamma dose: (Q )*[(M)(X/Q)] less than or equal to 5 mrad/qtr (20 mrad/yr) b) for beta dose: (Q )*[(N)(X/Q)] less than or equal to 10 mrad/qtr (40 mradlyr)

Solve for a. = 5mrad /qtr = 8.95E+3 +/-Ci/sec = 8.95E-3 Ci/sec (I / 4yr)(M)(X / Q)

Solve for b. Q = lOmrad /qtr = 6.15E+3 PCi/sec = 6.15E-3 Ci/sec (1l 4yr)(M)(X /Q)

Based on the above analysis, the beta dose is limiting for time average doses. Therefore, the allowable quarterly average release rate is 6.15E-3 Ci/sec.

Ill. Calculation of Calendar Year Release Rate Annual limits are one half of quarterly limits. Therefore (using Beta air dose as most limiting), the maximum allowable annual average release rate is 3.08E+3 uCi/sec or 3.08E-3 Ci/sec.

NOTE: M and N values are taken from Table 3-8 for time average release mixture.

3-73

Part II vuuLIM - mev. 1i Page 6 of 7 Appendix 3-A ALLOWABLE INSTANTANEOUS RELEASE RATE IODINE 131/PARTICULATES (TM/2 GREATER THAN 8 DAYS)

Given: Wv(in): X/Q for IP3 = 5.21E-6 sec/m 3 @ 350m SW Wv(in): X/Q for IP2 = 2.54E-6 sec/r 3 @ 579m SSW mrem lyr PI(c)= 1.62 E7 m .,UCiI/m3 Assumed Pathway: Child Inhalation at Unrestricted Area Boundary Solve the following equation for Q:

[(9 )PI(c)(Wv(in)) Unit 3] + [(O)PI(c)0Nv(in)) Unit 2] = 1500 mrem/yr

• 84.4 mremr /syr IP3: (9 )PI(c)(Wv(in))3 =.

• 1.62E7 rem/ yr 5.21 E-6 sm3 =

,"Ci/rM3 uCi/see 2.54E-6 s/r 3 = 41.1 remyr IP2: (Q)PI(c)(Wv(in))2= 6* 1.62E7 mre /yr uCi/sec uCi/ m 3 The sum equals (125.5)( Q) mrem/yr per uCilsec Limit is 1500 mrem/yr per site:

Therefore: 125.5 mrem/yr 1500 mrerm/yr

.5Ci / see 0 = 1.20E+1 giCVsec 0 = 1.20E-5 Cil/sec per unit zCi mrern m3 see IP3 Dose Contribution: 1.20E+1 - *1.62E7 - *5.21E -6 3 - 1008 mrem/yr see yr PCi m 1.20E+1 pCi *l.62E7mrem r 3 2.54E-6see - 492 mremlyr IP2 Dose Contribution: Wn sec yr PCi Sum = 1500 mrem/yr Approximately a 67.2% / 32.8% dose split for IP3 and IP2 respectively.

3-74

Part II ODCM - Rev. 15 Appendix 3-A Page 7 of 7 ALLOWABLE RELEASE RATES FOR IODINE / PARTICULATE TIME AVERAGE QUARTERLY AND ANNUAL DOSE LIMITS AT THE NEAREST RESIDENT Iodine 131 and particulates with half-lives greater than 8 days are assumed to be 1-131 for the purposes of this calculation which is a conservative assumption since this nuclide has the highest thyroid dose factor of all iodines and particulates. The H-3 dose factor is about 4 orders of magnitude less than the Iodine dose factor. Therefore, its contribution to the total dose is considered negligible.

Critical age group is Child:

Given: X/Q = 8.96E-7 sec/mf at 1526m SSW inhalation D/Q = 6.14E-9 m"*' at 1279m S ground plane deposition factor mrem/ y" RI(c) = 1.62E+7 ým , child inhal. dose factor for 1-131

'U0i/rn 2 troem/yr RG = 2.1E+7m pCi//sec RV(c) 4.77E+10 m2 mrem/yr vegetation path for child pCi/sec

• Calculate the allowable time average release rate by solving the following equation for Q:

Q [(RIc)(X/Q) + (RG)(D/Q) + (RVc)(D/Q)] = limit in mrem/yr Q(RIc)(X/Q) = 14.5

• Q mrem/yr per uCVsec Q (RG) (D/Q) = 0.1

• _Qmrem/yr per uCi/sec 2(RVc)(D/Q) = 293

• Q mrem/yr per uCi/sec The sum equals 308

• Q mrem/yr per uCi/sec.

Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr).

• 308 rnrem/yr _ 30 mre-/yr Solving for Q yields:

puCil sec 0 = 9.74E-2 pCi/sec = 9.74E-8 Ci/sec (Quarterly Limit)

Annual limit is %quarterly limit: 15 mrem to any organ (15 mrem/yr).

= 9.74E- 4.87E-8 Ci/sec (Annual Limit) 2 3-75

-i'*lL 11 UUU;M - KeY. I b Figure 3-1 24d Gaseous Radioactive Waste Effluent System Flow Diagram Batch Release Points Vents Cont.

Release Monitor iser Point Tanks LiquidCot Waste Cont.

R15 Release RIB Point ser J" Recirc( ý See uigh alarm) R0 River Figure 2-1 PV Auxiliary , -_.

• L* Fill as RCV-0 14 ICont.

S.Release Point R Cont,

• Release R

• IPoint

!.adiocti 3-76

ODCM - Rev. 15 Part II 4.0 SAMPLE LOCATIONS Figure 4-1 is a map which shows the location of environmental sampling points within 2.5 miles of the Indian Point Plant and Figure 4-2 is a map providing the same information for points at greater distances from the plant. Table 4-1 provides a description of environmental sample locations and the sample types collected at each of these locations.

The locations listed in Table 4-1 are the RECS designated locations only. The air sample locations were chosen considering the highest average annual D/Q sectors and the practicality of locating continuous air samplers. There are additional sample locations not listed in Table 4-1 that may be maintained to provide the program with additional supporting information.

4-1

UUuM - Kev. lb Part II FIGURE 4-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING STATIONS Near Site N

N Peekskill Rockland County I mile Key:. A - Waterborne; Surface (HR) Wa# Ic# - Broadleaf Vegetation O - Direct Radiation Sample Location DR# 0 - Shoreline Sediment r- Airborne Sample Location A# Ibl - Fish and Invertebrates 4-2

-u 000) 4N..

0M G)

'~o0CD

'Is I>

tA rn C/

UULUM - Rev. 1b Part II TABLE 4-1 INDIAN POINT STATION ENVIRONMENTAL SAMPLING STATION POINTS RECS SAMPLE DISTANCE DESIGNATION LOCATION Exposure Pathway/Sample: As measured from the Direct Radiation superheater stack DR1 Roa Hook 2 mi N DR2 Old Pemart Ave 1.8 mi NNE DR3 Charles Point 0.8 mi NE DR4 DR5 Lents Cove Broadway and Bleakley 0.5 mi ENE On site E I'

DR6 Sector Six Reuter Stokes Pole (#6) 0.5 mi ESE DR7 Water Meter House On site SE DR8 Service Center Building 0.4 mi SSE DR9 SE Comer On site S DR10 NYU Tower 0.8 mi SSW DR1 1 DR12 White Beach Tompkins Cove West Shore Ddve South 0.9 mi SW 1.5 mi WSW j.

DR13 West Shore Drive North R/S Pole #13 1 mi W DR14 Rt. 9W, east side, R/S Pole #14 1.2 mi WNW DR15 Rt. 9W. South of Ayers Road 1 mi NW DR16 Ayers Road I mi NNW DR17 Rt. 9D Garrison 5 mi N DR18 Gallows Hill Road 5 mi NNE DR19 Westbrook Drive 5 mi NE DR20 Lincoln Road - Cortlandt 4.8 mi ENE DR21 Croton Ave. - Cortlandt 5 mi E DR22 Colabaugh Pond Rd. Cortlandt 5 mi ESE DR23 Mt. Airy & Windsor Road 5 mi SE DR24 Warren Road 3.7 mi SSE DR25 Warren Ave. Haverstraw 4.8 mi S DR26 Railroad Ave. & 9W Haverstraw 4.6 mi SSW DR27 Willow Grove Road & Birch Dr. 5 mi SW DR28 Palisades Parkway-Exit 19 4.7 mi NW DR29 Palisades Parkway 4.2 mi W DR30 Anthony Wayne Park 4.5 mi WNW DR31 Palisades Pkwy South Exit 16 4.7 mi WSW DR32 Rt. 9W Fort Montgomery 4.7 mi NNW DR33 Hamilton Street 3 mi NE DR34 Furnace Dock 3.5 mi SE DR35 Highland Ave.& Sprout Brook Road (near 3 mi NNE rock cut)

DR36 Lower South Street 1.3 mi NE DR37 Verplank-Broadway & Sixth Str 1.3 mi SSW DR38 Cortlandt Yacht Club 1.6 mi S DR39 Grassy Point 3.3 mi SSW DR40 Roseton 20 mi N DR41 Croton Point 6.4 mi SSE 4-4

ODCM - Rev. 15 Part II TABLE 4-1 (Continued)

RECS SAMPLE DESIGNATIO N ILOCATION DISTANCE Exposure Pathway/Sample: Airborne Al Algonquin Gas Line 0.25 mi SW A2 NYPA Training Bldg 0.4 mi S A3 Met Tower 0.4 mi SSW A4 NYU Tower 0.8 mi SSW A5 Roseton 20 mi N Exposure Pathway/Sample: Waterbome- Surface (Hudson River Water)

Wal IPlant Inlet N/A Wa2. Discharge Canal N/A Exposure Pathway/Sample: Waterborne- Drinking Wbl Camp Field Reservoir 3.5 mi NE Exposure Pathway/ Sample: Sediment from Shoreline Wcl White Beach 0.9 mi SW Wc2 Manitou Inlet 4.5 mi NNW Exposure Pathway/Sample: Milk There are no milk animals within 8 km distance of Indian Point; therefore, no milk samples are taken.

See Note 2.

Exposure Pathway/Sample: Ingestion - Fish and Invertebrates The RECS designate two required sample locations labeled IbIl and Ib2. The downstream Ibl location and samples will be chosen where it is likely to be effected by plant discharge. Ib2 will be a location upstream that is not likely to be effected by plant discharge. The following fish species are considered acceptable sample species:

Striped Bass Bluegill Sunfish White Perch Pumpkin Seed Sunfish White Catfish Blueback Herring American Eel Crabs Exposure Pathway/Sample: Ingestion-Food Products (Broad Leaf Vegetation) (See Note 1)

Icl Met Tower, SSW Sector 0.4 miles - SSW Ic2 NYPA Training Bldg, S Sector 0.4 miles - S Ic3 Roseton (North) 20 miles - N 4-5

UUL;M - I-Kev. 1b Part II TABLE 4-1 NOTES NOTE I Radiochemical separation and analysis is not required for 1-131 vegetation samples:

as long as the required RECS LLD is met using gamma spectroscopy.

NOTE 2 The requirement to obtain and analyze samples from milch animals within 8 km of the site is intended to ensure monitoring of the "cow-milk" and vegetation pathways.

Such samples would only be of value where the milk is used for human consumption.

Thus, only milch animals whose milk is used for human consumption are considered in the pathway and sample evaluation.

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ODCM - Rev. 15 Part II APPENDIX B DETECTION CAPABILITIES The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

271+ 3.29 Sb LLD= T- £E* E VJ* k

• y *e where:

LLD = The lower limit of detection as defined above (as picocurie per unit mass or volume)

"TS= The sample counting time in minutes sb = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

Tb = The background count time in minutes E= The counting efficiency (as counts per transformation)

V= The sample size (in units of mass or volume) k= A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per pCi)j '*

Y= The fractional radiochemical yield (when applicable)

,= The radioactive decay constant for the particular radionuclide t= The elapsed time between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times. The IP3 Radiological Environmental Monitoring Program, REMP, uses an LLD formula that assumes equal background and sample count times, in accordance with the RECS. When the above LLD formula is more appropriate for the effluents program, it may be used.

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ODCM - Rev. 15 Part II The constants 2.71 and 3.29 and the general LLD equation were derived from the following two sources:

1) Currie, L.A. "Limits for Qualitative Detection of Quantitative Determination". (Anal.

Chem. 40:586-593, 1968); and,

2) Mayer, Dauer "Application of Systematic Error Bounds to Detection Limits for Practical Counting". (HP Journal 65(1): 89-91, 1993)

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that the LLD is defined as an a Pdriori (before the fact) limit representing the capability of a measurement process and not as an a Posteriori (after the fact) limit for a particular measurement.

To handle the a Posteriori problem, a decision level must be defined. The remainder of Appendix B discusses the use of the Critical Level concept. Following an experimental observation, one must decide whether or not a real signal was, in fact, detected. This type of biknary qualitative decision is subject to two kinds of error: deciding that the radioactive material is present when it is not (a: Type I error), and the converse, failing to decide that it is present when it is (b: Type II error). The maximum acceptable Type I error (a), together with the standard deviation, Snet, of the net signal when the net signal equals zero, establish the Critical Level, Lc, upon which decisions may be based.

Operationally, an observed signal, S, must exceed Lc to yield the decision, detected.

Ic = kaSb(l+Tb/Ts)°'s where:

k. is related to the standardized normal distribution and corresponds to a probability level of 1-a. For instance, selection of a = 0.01 corresponds to a 99% confidence level that activity is present. When determining the Lc for different measurement processes, it is allowable to set a at less than or equal to 0.05 as long as the following condition is met:

To set a for L..determination at less than 0.05, the equation for the LLD (which places a less than or equal to 0.05) should be employed to verify that the calculated LLD is less than or equal to the LLDs specified in the IP-3 RECS. This calculation, if necessary, will be performed on a case by case basis.

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