Text

Offsite Dose Calculation Manual, Rev. 9
	ML052770533
Person / Time
Site:	Indian Point
Issue date:	08/19/2005
From:	; Entergy Nuclear Northeast
To:	; Document Control Desk, NRC/FSME
References
	IP-SMM-AD-103, Rev 1
	Download: ML052770533 (191)
	v • d • e

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LIS SIMULATOR RESIDENT INSPECTOR EOF CHAPMAN N TADEMY L. SHARON GSB TECHNICAL LIBRARY SIMULATOR CONROY PAT BARANSKI J (ALL)

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I IPEC SITE QUALrTy RELATED IP-SMM-AD-1 03 RevisIon 1

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ODCM Revision 9

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Entergy Nuclear Northeast Indian Point Units 1, 2 TITLE: OFFSITE DOSE CALCULATION MANUAL (ODCM)

Rev. 9 WRITTEN BY:

---. date REVIEWED BY:

L7w Ep7/

/

date OSRC REVIEW:

7 -P/8-O M1t, Ms. o f

/A date APPROVED BY:

W EFFECTIVE DATE:

- 5 date

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL PAGE List of Tables vi List of Figures viii Introduction ix PART I - RADIOLOGICAL EFFLUENT CONTROLS D 1.0 USE AND APPLICATION D 1.0-1 D 1.1 Definitions D 1.1-1 D 1.2 Logical Connectors D 1.2-1 D 1.3 Completion Times D 1.3-1 D 1.4 Frequency D 1.4-1 D 2.0 SAFETY LIMITS (Not Used)

D 3.0 APPLICABILITY D 3.0 ODCM Limiting Condition for Operation (DLCO)

D 3.0-1 D 3.0 ODCM Surveillance Requirement (DSR)

D 3.0-2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluents Concentration D 3.1.1-1 D 3.1.2 Liquid Effluents Dose D 3.1.2-1 D 3.1.3 Liquid Radwaste Treatment System D 3.1.3-1 D 3.1.4 Liquid Holdup Tanks D 3.1.4-1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate D 3.2.1-1 D 3.2.2 Gaseous Effluents Dose - Noble Gas D 3.2.2-1 D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate D 3.2.3-1 D 3.2.4 Gaseous Radwaste Treatment System D 3.2.4-1 D 3.2.5 Ventilation Exhaust Treatment System D 3.2.5-1 D 3.2.6 Gas Storage Tanks D 3.2.6-1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1-1 D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2-1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose D 3.4.1-1 Indian Point 2 i

Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL PAGE D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Monitoring Program D 3.5.1-1 D 3.5.2 Land Use Census D 3.5.2-1 D 3.5.3 Interlaboratory Comparison Program D 3.5.3-1 D 3.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System D 3.6.1-1 D 4.0 DESIGN FEATURES D 4.1 UNRESTRICTED AREA D 4.1-1 D 5.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report D 5.1-1 D 5.2 Radioactive Effluent Release Report D 5.2-1 D 5.3 Special Reports D 5.3-1 D 5.4 Major Changes to Radwaste Treatment Systems D 5.4-1 D 5.5 Process Control Program D 5.5-1 Indian Point 2 ii Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL BASES B D 3.0 PAGE APPLICABILITY B D3.0 B D 3.0 B D 3.1 B D 3.1.1 BD3.1.2 B D 3.1.3 B D 3.1.4 B D 3.2 B D 3.2.1 B D 3.2.2 B D 3.2.3 B D 3.2.4 B D 3.2.5 B D 3.2.6 B D 3.3 B D 3.3.1 B D 3.3.2 B D 3.4 B D 3.4.1 B D 3.5 B D 3.5.1 B D3.5.2 B D 3.5.3 B D 3.6 B D 3.6.1 ODCM Limiting Condition for Operation (DLCO)

ODCM Surveillance Requirement (DSR)

RADIOACTIVE LIQUID EFFLUENTS Liquid Effluents Concentration Liquid Effluents Dose Liquid Radwaste Treatment System Liquid Holdup Tanks RADIOACTIVE GASEOUS EFFLUENTS Gaseous Effluents Dose Rate Gaseous Effluents Dose - Noble Gas Gaseous Effluents Dose - Iodine and Particulate Gaseous Radwaste Treatment System Ventilation Exhaust Treatment System Gas Storage Tanks INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation RADIOACTIVE EFFLUENTS TOTAL DOSE Radioactive Effluents Total Dose RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological Environmental Monitoring Program Land Use Census Interlaboratory Comparison Program SOLID RADIOACTIVE WASTE Solid Radwaste Treatment System B D 3.0-1 B D 3.0-1 B D 3.1.1-1 B D 3.1.2-1 B D 3.1.3-1 B D 3.1.4-1 B D 3.2.1-1 B D 3.2.2-1 B D 3.2.3-1 B D 3.2.4-1 B D 3.2.5-1 B D 3.2.6-1 B D 3.3.1 -1 B D 3.3.2-1 B D 3.4.1-1 B D 3.5.1-1 B D 3.5.2-1 B D3.5.3-1 B D 3.6.1-1 Indian Point 2 iii Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL PART II CALCULATIONAL METHODOLOGIES PAGE 1.0 LIQUID EFFLUENT METHODOLOGY 1.1 Liquid Effluent Model Assumptions and Information 1

1.2 Determination of Setpoints for Liquid Effluent Monitors 2

1.3 Determining the Dose for Radioactive Liquid Effluents 2

1.4 Dose Calculations 3

2.0 GASEOUS EFFLUENT METHODOLOGIES 2.1 Gaseous Effluent Model Assumptions and Information 13 2.2 Determination of Releases from Indirectly Monitored Sources 15 2.3 Noble Gas Releases Dose Rates for Total Body and Skin 15 2.4 Determining the Radioiodines, 8-day Particulate and Tritium Instantaneous Doses from Gaseous Releases 17 2.5 Gamma Air Dose for Noble Gas Releases 18 2.6 Beta Air Dose for Noble Gas Releases 20 2.7 Determining the Radioiodines, 8-day Particulate and Tritium Cumulative Doses from Gaseous Releases 20 2.8 Gas Storage Tank Activity Limit 25 3.0 TOTAL DOSE DETERMINATIONS 3.1 10CFRI90 Dose Evaluation 68 3.2 Doses from Liquid Releases 68 3.3 Doses from Atmospheric Releases 68 4.0 SETPOINT CALCULATIONS 4.1 Liquid Monitor Setpoints 69 4.2 Gaseous Monitor Setpoints 70 5.0 LOWER LIMIT OF DETECTION 72 REFERENCES 74 APPENDICES Appendix A:

Dispersion and Deposition Factors 75 Appendix B:

Liquid Effluent Simplified Flow Diagram 76 Appendix C:

Gaseous Effluent Simplified Flow Diagram 77 Appendix D:

Steam Partition Factor Calculation (f )

78 Indian Point 2 iv Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL APPENDICES (Continued)

PAGE Appendix E:

Appendix F:

Appendix G:

Appendix H:

Appendix I:

Allowed Diluted Concentration (ADC)

Conversion Factors for Liquid Effluent Monitors Environmental Sampling Points Interlaboratory Comparison Program Calculation of Allowable Release Rates for Indian Point Units 2 and 3 79 80 81 88 89 Indian Point 2 v

Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES PART I - RADIOLOGICAL EFFLUENT CONTROLS PAGE D 3.1.1-1 Radioactive Liquid Waste Sampling and Analysis D 3.2.1-1 Radioactive Gaseous Waste Sampling and Analysis D 3.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.5.1-1 Radiological Environmental Monitoring Program D 3.5.1-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples D 3.5.1-3 Detection Capabilities for Environmental Sample Analysis D 3.1.1-2 D 3.2.1-2 D 3.3.1-6 D 3.3.2-5 D 3.5.1-6 D 3.5.1-9 D 3.5.1-10 Indian Point 2 vi Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES PAGE PART II CALCULATIONAL METHODOLOGIES 1-1 Summary of Liquid RECS 5

1-2 Site Related Adult Ingestion Dose Commitment Factors 6

1-3 Site Related Teen Ingestion Dose Commitment Factors 8

1-4 Site Related Child Ingestion Dose Commitment Factors 10 1-5 Bio-Accumulation Factors for Liquid Effluent Isotopes 12 2-1 Summary of Gaseous RECS 27 2-2a Adult Inhalation Dose Factors 28 2-2b Teen Inhalation Dose Factors 30 2-2c Child Inhalation Dose Factors 32 2-2d Infant Inhalation Dose Factors 34 2-2e Total Body and Skin Ground Plane Dose Factors, with Isotope Half Life and Stable Element Transfer Data 36 2-3a Adult Ingestion Dose Factors 38 2-3b Teen Ingestion Dose Factors 40 2-3c Child Ingestion Dose Factors 42 2-3d Infant Ingestion Dose Factors 44 2-4 Total Body Dose Factors, Ki, from Noble Gas (Gamma) 46 2-5 Skin Dose Factors, U, from Noble Gas (Beta) 47 2-6 Air Dose Factors, Mi, from Noble Gas (Gamma) 48 2-7 Air Dose Factors, Ni, from Noble Gas (Beta) 49 2-8 Noble Gas Dose Factors for Instantaneous and Time Average Mixtures at the Site Boundary 50 2-9 Locations of Site Boundary and Nearest Residence 51 2-10a Adult Inhalation Ri(l) 52 2-1Ob Teen Inhalation Ri(l) 54 2-10c Child Inhalation Ri(l) 56 2-1Od Infant Inhalation Ri(l) 58 2-1 la Adult Ingestion (Leafy Vegetable) Ri(V) 60 2-1 lb Teen Ingestion (Leafy Vegetable) Ri(V) 62 2-11c Child Ingestion (Leafy Vegetable) Ri(V) 64 2-12 Total Body and Skin Ground Plane Dose Factors Ri(G) and Ri(S) 66 Indian Point 2 vii Revision 9

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES PAGE PART I - RADIOLOGICAL EFFLUENT CONTROLS 4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE D 4.1-2 GASEOUS AND LIQUID EFFLUENTS Indian Point 2 Revision 9

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts:

Radiological Effluent Controls, Part I, and Calculational Methodologies, Part II.

Part I, Radiological Effluent Controls, includes: (1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3 respectively.

Part II, Calculational Methodologies: provides the methodology to manually calculate radiation dose rates and doses to individual persons in UNRESTRICTED AREAS in the vicinity of Indian Point due to the routine release of gaseous and liquid effluents. Long term cumulative effects are usually calculated through computer programs employing approved methodology, often using real-time meteorology in the case of gaseous effluents. Other computer programs are utilized to routinely estimate the doses due to radioactivity in liquid effluents. Manual dose calculations are performed when computerized calculations are not available. The ODCM also provides setpoint methodology that is applied to effluent monitors and optionally to other process monitors. Reference numbers are bracketed [ ] to assist users.

The ODCM implements the Units 1 and 2 Radiological Effluent Control Specifications with respect to 10CFR20 Appendix B (pre-1994) permissible concentration criteria and also the design objectives of IOCFR50 Appendix I. The ODCM implements the methodology of Reg.

Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I" and NUREG-0133 "Guidance Manual for Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." Other references may be cited to permit reasonable handling of a situation not covered by either of the two cited references. Simplifying assumptions have been made and justified to permit formulation of more workable methodologies for implementing RECS dose calculation requirements.

Indian Point 2 ix Revision 8

Definitions D 1.1 D 1.0 USE AND APPLICATION D 1.1 Definitions

~~~~-~-NOTE----------

Terms defined in Technical Specifications and the following additional defined terms appear in capitalized type and are applicable throughout these specifications and bases.

Term Definition GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S) OF THE PUBLIC MAXIMUM PERMISSIBLE CONCENTRATION WATER (MPCW)

OFFSITE DOSE CALCULATION MANUAL PROCESS CONTROL PROGRAM PURGE - PURGING SITE BOUNDARY SOLIDIFICATION A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF THE PUBLIC includes all persons who are not occupationally associated with the site. This category does not include employees of the utility, their contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

MPCW is that concentration of a radionuclide equal to the most conservative of the soluble or insoluble liquid concentration limits specified in (pre-1984) 10CFR20, Appendix B, Table II, Column 2.

The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program.

The PROCESS CONTROL PROGRAM is a manual containing and/or referencing selected operational information concerning the solidification of radioactive wastes from liquid systems.

PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

The SITE BOUNDARY is that line beyond which the land is neither owned, leased, nor otherwise controlled by either Entergy Nuclear Indian Point 2 (ENIP2), Entergy Nuclear Operations, Inc. (ENO), or other site licensee.

SOLIDIFICATION is the conversion of wet wastes into a form that meets shipping and burial ground requirements.

Indian Point 2 D 1.1 - 1 Revision 9

Definitions D 1.1 D 1.1 Definitions SOURCE CHECK UNRESTRICTED AREA VENTILATION EXHAUST TREATMENT SYSTEM VENTING A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

An UNRESTRICTED AREA is any area at or beyond the SITE BOUNDARY, access to which is not controlled by either ENIP2, ENO, or other site licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. (See Figure D 4.1-1)

A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required.

Indian Point 2 D 1.1 - 2 Revision 9

Logical Connectors*

D 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and are applicable throughout the Offsite Dose Calculation Manual and Bases.

Indian Point 2 D 1.2-1 Revision 9

Completion Times D 1.3 1.0 USE AND APPLICATION 1.3 Completion Times Completion Times are discussed in Section 1.3 of the Technical Specifications and are applicable throughout the Offsite Dose Calculation Manual and Bases.

Indian Point 2 D 1.3-1 Revision 9

Frequency D 1.4 1.0 USE AND APPLICATION 1.4 Frequency Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the Offsite Dose Calculation Manual and Bases Indian Point 2 D 1.4-1 Revision 9

Indian Point 2 Offsite Dose Calculation Manual PART I - RADIOACTIVE EFFLUENT CONTROLS

APPLICABILITY D 3.0 D 3.0 ODCM Limiting Condition for Operation (DLCO) Applicability DLCO 3.0.1 DLCOs shall be met during the MODES or other specified condition in the Applicability, except as provided in DLCO 3.0.2.

DLCO 3.0.2 Upon discovery of a failure to meet a DLCO, the Required Actions of the associated Conditions shall be met, except as provided in DLCO 3.0.5.

If the DLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

DLCO 3.0.3 When a DLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to:

a.

Restore compliance with the DLCO or associated ACTIONS, and

b.

Enter the circumstances into the Corrective Action Program.

NOTE-----------------------------

DLCO 3.0.3.b shall be completed if DLCO 3.0.3 is entered.

Exceptions to this Specification are stated in the individual Specifications.

DLCO 3.0.4 Not Applicable to ODCM Specifications.

DLCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TRO 3.0.B for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

Indian Point 2 D 3.0-1 Revision 9

APPLICABILITY D3.0 D 3.0 ODCM Surveillance Requirement (DSR) Applicability DSR 3.0.1 DSRs shall be met during the MODES or other specified conditions in the Applicability for individual DLCOs, unless otherwise stated in the DSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the DLCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the DLCO except as provided in DSR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

i DSR 3.0.2 The specified Frequency for each DSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per.... basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

DSR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the DLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the DLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the DLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

Indian Point 2 D 3.0-2 Revision 9

Liquid Effluents Concentration*

D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluents Concentration DLCO 3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure D 4.1-1) shall be limited to:

a.

The MPCW concentrations as defined in D1.1 for radionuclides other than dissolved or entrained noble gases; and

b.

2 x 10 4pCi/mI total activity concentration for dissolved or entrained noble gases.

APPLICABILITY:

At all times.

ACTIONS I

CONDITION REQUIRED ACTION COMPLETION TIME A.

Concentration of A.1 Initiate action to restore Immediately radioactive material concentration to within limits.

released in liquid effluents to UNRESTRICTED AREAS exceeds limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.1.1 Perform radioactive liquid waste sampling and activity In accordance with analysis.

Table D 3.1.1-1 DSR 3.1.1.2 Verify the results of the DSR 3.1.1.1 analyses to In accordance with assure that the concentrations at the point of release Table D 3.1.1-1 are maintained within the limits of DLCO 3.1.1.

Indian Point 2 Page 3.1.1 -1 Revision 9

Liquid Effluents Concentration D 3.1.1 Table D 3.1.1-1 (Page 1 of 2)

Radioactive Liquid Waste Sampling and Analysis LIQUID SAMPLE LOWER RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE LIMIT OF TYPE TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)

___(a),(g),(c)

Principal

1. Batch Waste Gamma Emitters 5 x 10' CVml Release Grab Sample Each Batch (h)

Each Batch (h)

Tanks (b)

Mo-99, Ce-144 5 x 106 RCVmI 1-131

, xle4 pCVmi One batch per 3Dissolved and Grab Sample 31 days (h) 31 days Entrained Gases 1 x 10 5 ACVmI GrabSampe 31days(h)(gamma emitters)

H-3 I x 1'5 PoCiwml Composite (d) Each batch (h) 31 days l

Gross Alpha 1 x 1 &' ilC~ml Sr-89 5 x I10 pCI/ml Composite (d) Each batch (h) 92 days Sr-90 5 x le ;+/-CVmi Fe-55 1 x 104 gCVmI

2. Continuous Composite (d) 7 days 7 days Principal Gamma Releases (e)

Cmoie()

7dy7dasEmitters (c) 5 x 10- p~Ci/ml Mo-99, Ce-144 5 x 104 pCjiml 1-131 1 x le 4 Cvml Dissolved and Grab Sample 31 days 31 days Entrained Gases 1 x 10 5 LCVmI (gamma emitters)

Composite (d) 31 days 31 days H-3 1 x 104 pCi/mI Composite (d) 31 days 31 days Gross Alpha 1 x 10'7 AiCVml Composite (d) 92 days 92 days Sr-89 5 x 104 pCVmI Composite (d) 92 days 92 days Sr-90 5 x 1 04 pCi/ml Composite (d) 92 days 92 days Fe-55 1 x 10.6 PCimI Indian Point 2 Page 3.1.1 -2 Revision 9

Liquid Effluents Concentration D 3.1.1 Table D 3.1.1-1 (Page 2 of 2)

Radioactive Liquid Waste Sampling and Analysis (a) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a wreal" signal. The LLD shall be determined in accordance with the methodology and parameters in the ODCM. It should be recognized that the LLD is defined as an a priori (before-the-fact) limit representing the capability of a measurement system and not as an a posterior (after-the-fact) limit for a particular measurement.

(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by the method described in Part II, Section 1.4 to assure representative sampling.

(c) The principal gamma emitters for which the LLD applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5 x 1 O4jpCiml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identified, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification D 5.2.

(d) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(e) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(f) When operational or other limitations preclude specific gamma radionuclide analysis in batch releases, the provisions of Regulatory Guide 1.21 (Revision 1), Appendix A Section C.4 and Appendix A, Section B shall be followed.

(g) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentration near the LLD. Under these cTrcumstances, the LLD may be increased in inverse proportion to the magnitude of the gamma yield (i.e., 5 x 10. /I where I is the photon abundance expressed as a decimal fraction).

(h) Complete prior to each release.

Indian Point 2 Page 3.1.1 - 3 Revision 9

Liquid Effluents Dose D 3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.2 Liquid Effluents Dose DLCO 3.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials released in liquid effluents from each unit to UNRESTRICTED AREAS (Figure D 4.1-1) shall be limited to:

a.

< 1.5 mrem to the whole body and < 5 mrem to any organ during any calendar quarter; and

b.

< 3 mrem to the whole body and < 10 mrem to any organ during any calendar year.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Calculated dose to a A.1 Prepare and submit to the 30 days MEMBER OF THE NRC, pursuant to D 5.3, a PUBLIC from the release Special Report that of radioactive materials in (1) Identifies the cause(s) liquid effluents to for exceeding the limit(s)

UNRESTRICTED AREAS and exceeds limits.

(2) Defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.1.2.

Indian Point 2 D 3.1.2 - 1 Revision 9

Liquid Effluents Dose*

D3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units times the limits.

(including outside storage tanks, etc.).

AND Immediately B.2 Verify that the limits of DLCO 3.4 have not been exceeded.

C.

Required Action B.2 and C.1 Prepare and submit to the 30 days Associated Completion NRC, pursuant to D 5.3, a time not met.

Special Report, as defined in 10 CFR 20.2203 (a)(4), of Required Action A.1 shall also include the following:

(1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2) An analysis that estimates the 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 release(s),

and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

Indian Point 2 D 3.1.2 - 2 Revision 9

Liquid Effluents Dose D 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.2.1 Determine cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year.

Indian Point 2 D 3.1.2 - 3 Revision 9

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System DLCO 3.1.3 The Liquid Radwaste Treatment System shall be in operation when projected liquid effluent doses, from each unit, to UNRESTRICTED AREAS (Figure D 4.1-1) would be:

a.

> 0.06 mrem to the total body in a 31 day period; or

b.

>0.2 mrem to any organ in a 31 day period.

APPLICABILITY:

Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Radioactive liquid waste A.1 Prepare and submit to the 30 days being discharged without NRC, pursuant to D 5.3, a treatment.

Special Report that includes:

(1) An explanation of why AND liquid radwaste was being discharged without Projected doses due to the treatment, identification liquid effluent, from the of any inoperable unit, to UNRESTRICTED equipment or AREAS would exceed subsystems, and the limits.

reason for the inoperability, (2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.3.1 Project the doses due to liquid effluents from each unit 31 days to UNRESTRICTED AREAS.

Indian Point 2 D 3.1.3 - 1 Revision 9

Liquid Holdup Tanks D 3.1.4 D 3.1 LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks DLCO 3.1.4 Radioactive liquid contained in unprotected outdoor liquid storage tanks shall be limited to < 10 Curies excluding tritium and dissolved or entrained gases.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.

listed tank.

AND A.2 Initiate measures to reduce 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months content to within the limits.

AND A.3 Describe the events leading to Prior to submittal of the condition in the next Radioactive Radioactive Effluent Release Effluent Release Report.

Report SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.4.1 Sample and analyze radioactive liquid located in 31 days during unprotected outdoor liquid storage tanks for level of addition of radioactivity.

radioactive liquid to the tanks Indian Point 2 D 3.1.4 - 1 Revision 9

Liquid Holdup Tanks*

D 3.1.4 D 3.1 LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks DLCO 3.1.4 Radioactive liquid contained in unprotected outdoor liquid storage tanks shall be limited to

10 Curies excluding tritium and dissolved or entrained gases.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.

listed tank.

AND A.2 Initiate measures to reduce 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months content to within the limits.

AND A.3 Describe the events leading to Prior to submittal of the condition in the next Radioactive Radioactive Effluent Release Effluent Release Report.

Report SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.4.1 Sample and analyze radioactive liquid located in 31 days during unprotected outdoor liquid storage tanks for level of addition of radioactivity.

radioactive liquid to the tanks Indian Point 2 D 3.1.4 - 1 Revision 9

Gaseous Effluents Dose Rate D3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D3.2.1 Gaseous Effluents Dose Rate DLCO 3.2.1 The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (Figure D 4.1-1) shall be limited to:

a.

For noble gases, < 500 mrem/yr to the whole body and

< 3000 mrem/yr to the skin and

b.

For 1-131, tritium (H-3) and all radionuclides in particulate form with half-lives > 8 days, < 1500 mrem/yr to any organ.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

The dose rate(s) at or A.1 Restore the release rate to Immediately beyond the SITE within the limit.

BOUNDARY due to radioactive gaseous effluents exceeds limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.1.1 The dose rate from noble gases in gaseous In accordance with effluents shall be determined to be within the limits Table D 3.2.1-1 of DLCO 3.2.1.a.

DSR 3.2.1.2 The dose rate from 1-131, H-3 and all In accordance with radionuclides in particulate form with half-lives Table 03.2.1-1

> 8 days in gaseous effluents shall be determined to be within the limits of DLCO 3.2.1.b.

Indian Point 2 D 3.2.1 - 1 Revision 9

Gaseous Effluents Dose Rate*

D 3.2.1 Table D 3.2.1-1 (Page 1 of 2)

Radioactive Gaseous Waste Sampling and Analysis SAMPLE GASEOUSLOWER GASEOUS SAMPLE SAMPLE ANALYSIS SAMPLE LIMnT OF TYPE TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD) (a)

Principal

1. Waste Gas Grab Noble

-4xlo Storage Tank Sample Each Tank (h)

Each Tank (h)

Gas (NG) 1Ci1m0 Gamma

~

Cm Emitters (b)

Grab Principal NG Purge Sample Each Purge (h)

Each Purge (h)

Gamma 1 x-4

2.

Emitters (b) iItCVml Vapor Containment Press Grab Principal NG 1

1 Relief Sample 31 days (i) 31 days (i)

Gamma

(

1Ci/mI Emitters (b) iCm

3. Condenser Air Grab Principal NG

.x4e Ejector Sample 31 days 31 days Gamma 1 X 1 Emitters (b) HiCiml Principal NG 14

4. Continuous Sram 31 days (c) 31 days (c)

Gamma1X1 Ventilation:

Sample Emitters (b)

.CIml

a. Main Plant H-3 Continuous 31 days (e)

H-3 1 X 10 Vent (unit 2)

Specif ic ViCVmI

b. Stack Vent Charcoal Continuous (f) 7 days (c) (g) 1-131 1 X 10.12 (unit 1)

Sample i1Ci/ml Principal Gamma 1 x 10o1 Particulate Continuousitters/mb Sample Cotnos(f) 7 days (c)1()

1Eiter (b)

VM Others)

Composite 1 x 10o1 Particulate Continuous (f) 31 days Gross Alpha ti/mI Sample Composite 1 x 1o0.

Particulate Continuous (f) 92 days Sr-89 / Sr-90 pCxmI Sample Noble Gas Cniuu()

Cotuos Noble Gases 1 x 10 6 Monior Cntinous(f) ontiuous(f)

Gross Beta tim(d Monitor

~~or Gamma pim d Indian Point 2 D 3.2.1 - 2 Revision 9

Gaseous Effluents Dose Rate D3.2.1 Table D 3.2.1-1 (Page 2 of 2)

Radioactive Gaseous Waste Sampling and Analysis (a) The LLD is defined, for purposes of these Spe cifdctidos, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

The LLD shall be determined in accordance with the methodology and parameters in the ODCM.

It should be recognized that the LLD is defined as an a Dnori (before the fact) limit representing the capability of a measurement system and not as an a oosteriori (after the fact) limit for a particular measurement.

(b) The principal gamma emitters for which the LLD Control applies exclusively are the following~radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-1 41 and Ce-1 44 for particulate emissions. Other identifiable gamma peaks (1-1 31 in particulate form, for example), together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Section D 5.2.

(c) IF following a shutdown, startup, or a thermal power change (within one hour) exceeding 15 percent of RATED THERMAL POWER, analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased by a factor of 3 or more, AND the noble gas monitor shows that effluent activity has increased by a factor of 3 or more THEN:

1) Sample the main Plant Vent (unit 2) for Noble Gases within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , AND

2) Sample the main Plant Vent (unit 2) for Iodine and Particulate once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days with analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of sample changeout. The LLDs of these samples may be increased by a factor of 10.

(d) This value is the established Radiation Monitor sensitivity (minimum).

(e) Grab samples can be used as aftemative to continuous sampling, provided the periodicity of these grab samples is increased from monthly to once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded, or at least once per 7 days when spent fuel is in the Spent Fuel Pool.

(f) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications D 3.2.1, D 3.2.2 and D 3.2.3.

(g) Continuous samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

Additionally, IF routine Iodine sampling indicates 1-131 in the main Plant Vent (unit 2) or the Stack Vent (unit 1), THEN collect a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sample from the applicable vent (within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) for short-lived Iodine isotope quantification, on a periodicity not to exceed once per 31 days. The LLDs of these samples may be increased by a factor of 10.

(h) Complete prior to each release.

(i) Vapor Containment noble gas shall be sampled at least monthly to ensure Pressure Reliefs are quantified with an accurate isotopic mixture. Containment noble gas radiation monitor readings can be used for quantification of Pressure Reliefs, provided the monitor readings are consistent with those observed during recent (at least monthly) grab samples. Sample data is adjusted by the noble gas radiation monitor reading for purposes of quantification of each release. Should the monitor be inoperable, a containment noble gas grab sample is required within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the Pressure Relief.

Indian Point 2 D 3.2.1 - 3 Revision 9

Gaseous Effluent Dose - Noble Gas D 3.2.2 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.2 Gaseous Effluent Dose - Noble Gas DLCO 3.2.2 The air dose from noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (Figure D 4.1-1) shall be limited to:

a.

< 5 mrad to the whole body from gamma radiation and

< 10 mrad to the skin from beta radiation during any calendar quarter, and

b.

< 10 mrad to the whole body from gamma radiation and

< 20 mrad to the skin from beta radiation during any calendar year.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

The calculated air dose at A.1 Prepare and submit to the 30 days or beyond the SITE NRC, pursuant to D 5.3, a gases released in gaseous Special Report that effluents exceeds limits.

(1) Identifies the cause(s) for exceeding the limit(s) and (2) Defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.2.2.

Indian Point 2 D 3.2.2 -1 Revision 9

Gaseous Effluent Dose - Noble Gas D 3.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct airborne effluents exceeds radiation from the units 2 times the limits.

(including outside storage tanks, etc.).

AND Immediately 8.2 Verify that the limits of DLCO 3.4 have not been exceeded.

C.

Required Action B.2 and C.1 Prepare and submit to the 30 days Associated Completion NRC, pursuant to D 5.3, a time not met.

Special Report, as defined in 10 CFR 20.2203 (a)(4), of Required Action A.1 shall also include the following:

(1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2) An analysis that estimates the 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 release(s),

and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

I Indian Point 2 D 3.2.2 - 2 Revision 9

Gaseous Effluent Dose - Noble Gas D 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.2.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year.

Indian Point 2 D 3.2.2-3 Revision 9

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.3 Gaseous Effluent Dose - Iodine and Particulate DLCO 3.2.3 The dose to a MEMBER OF THE PUBLIC from 1-131, tritium, and all radionuclides in particulate form with half-lives > 8 days, in gaseous effluents, released from each unit to areas at or beyond the SITE BOUNDARY (Figure D 4.1-1) shall be limited to:

a.

< 7.5 mrem to any organ during any calendar quarter, and

b.

< 15 mrem to any organ during any calendar year.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

The dose from 1-131, A.1 Prepare and submit to the 30 days tritium, and radioactive NRC, pursuant to D 5.3, a material in particulate form Special Report that with half-lives > 8 days (1) Identifies the cause(s) released in gaseous for exceeding the limit(s) effluents at or beyond the and SITE BOUNDARY (2) Defines the corrective exceeds limits.

actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.2.3.

Indian Point 2 D 3.2.3 - 1 Revision 9

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units times the limits.

(including outside storage tanks, etc.).

AND B.2 Verify that the limits of DLCO Immediately 3.4 have not been exceeded.

C.

Required Action B.2 and C.1 Prepare and submit to the 30 days Associated Completion NRC, pursuant to D 5.3, a time not met.

Special Report, as defined in 10 CFR 20.2203 (a)(4), of Required Action A.1 shall also include the following:

(1)The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2) An analysis that estimates the 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 release(s),

and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

Indian Point 2 D 3.2.3 - 2 Revision 9

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 SURVEILLANCE REQUIREMENTS

_I SURVEILLANCE FREQUENCY DSR 3.2.3.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year for 1-131, tritium, and radioactive material in particulate form with half-lives > 8 days.

Indian Point 2 D 3.2.3-3 Revision 9

Gaseous Radwaste Treatment System*

D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System DLCO 3.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure D 4.1-1) would be:

a.

> 0.2 mrad for gamma radiation; and

b.

> 0.4 mrad for beta radiation in a 31 day period.

APPLICABILITY:

Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 5.3, a without treatment.

Special Report that includes AND the following:

(1) Identification of any Projected doses due to the inoperable equipment or gaseous effluent, from the subsystems and the unit, at and beyond the reason for the SITE BOUNDARY would inoperability, exceed limits.

(2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.4.1 Project the doses due to gaseous effluents from each 31 days unit at and beyond the SITE BOUNDARY.

Indian Point 2 D 3.2.4 - 1 Revision 9

Ventilation Exhaust Treatment System D 3.2.5 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.5 Ventilation Exhaust Treatment System DLCO 3.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure D 4.1-1) would be:

a.

> 0.2 mrad air dose from gamma radiation; and

b.

> 0.4 mrad air dose from beta radiation in a 31 day period; or

c.

> 0.3 mrem to any organ in a 31 day period.

APPLICABILITY:

Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Radioactive gaseous A. 1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 5.3, a without treatment.

Special Report that includes the following:

AND (1) Identification of any inoperable equipment or Projected doses due to subsystems and the gaseous effluent, from reason for the each unit, to areas at or inoperability, beyond the SITE (2) Action(s) taken to restore BOUNDARY would the inoperable equipment exceed limits.

to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.5.1 Project the doses from gaseous releases from each 31 days unit to areas at and beyond the SITE BOUNDARY when the GASEOUS RADWASTE TREATMENT SYSTEMS are not being fully utilized.

Indian Point 2 D 3.2.5 - 1 Revision 9

Gas Storage Tanks D 3.2.6 D 3.2 GASEOUS EFFLUENTS D 3.2.6 Gas Storage Tanks DLCO 3.2.6 The radioactivity contained in each gas storage tank shall be limited to

29,761 Curies of noble gas (considered as Xe-133).

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits.

radioactive material.

AND A.2 Reduce content to within the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.6.1 Sample and analyze radioactive material contained in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during gas storage tank for level of radioactivity.

addition of radioactive material to the tank Indian Point 2 D 3.2.6 - 1 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DLCO 3.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table D 3.3.1-1 shall be OPERABLE with:

a.

The minimum OPERABLE channel(s) in service.

b.

The alarm/trip setpoints set to ensure that the limits of DLCO 3.1.1 are not exceeded.

APPLICABILITY:

According to Table D 3.3.1-1.

ACTIONS NOTE Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Liquid effluent monitoring A.1 Suspend the release of Immediately instrumentation channel radioactive liquid effluents alarm/trip setpoint less monitored by the affected conservative than required.

channel.

OR A.2 Declare the channel Immediately inoperable.

OR Immediately A.3 Change the setpoint so it is acceptably conservative.

Indian Point 2 D 3.3.1 - 1 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more required B.1 Enter the Condition Immediately channels inoperable.

referenced in Table D 3.3.1-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

C.

As required by Required C.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in release in Table D 3.3.1-1.

accordance with Table D 3.1.1-1.

AND C.2

NOTE------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the Prior to initiating a release rate calculations and release discharge line valving.

D. As required by Required D.1 Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B.1 and referenced samples for radioactivity at a in Table D 3.3.1-1.

limit of detection of at least AND 5 x 10i7 RCVml.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Indian Point 2 D 3.3.1 - 2 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

As required by Required E.1 Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B.1 and samples for radioactivity at referenced in a limit of detection of at AND Table D 3.3.1-1.

least 5 x 10i7 ItCml, when specific activity is Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 0.01 plCVgm DOSE thereafter EQUIVALENT 1-131.

OR E.2 Collect and analyze grab 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months samples for radioactivity at a limit of detection of at AND least 5 x 10'7 pCi/ml, when specific activity is Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

< 0.01 p+/-CVgm DOSE thereafter EQUIVALENT 1-131.

F.

As required by Required F.1 Action B.1 and Pump performance curves referenced in generated in place may be Table D 3.3.1-1.

used to estimate flow.

Estimate the flow rate during 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months actual releases.

AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter G.

As required by Required G.1 Estimate tank liquid level.

Immediately Action B.1 and referenced in AND Table D 3.3.1-1.

During liquid additions to the tank H.

Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met.

Release Report why the Release Report inoperability was not corrected in a timely manner.

Indian Point 2 D 3.3.1 - 3 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

Required Action and 1.1 Suspend liquid effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E, inoperable channel(s).

or F not met.

J.

Required Action and J.1 Suspend liquid additions to Immediately associated Completion the tank monitored by the Time for Condition G not inoperable channel(s).

met.

SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table D 3.3.1-1 to determine which DSRs apply for each function.

SURVEILLANCE FREQUENCY DSR 3.3.1.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DSR 3.3.1.2 Perform CHANNEL CHECK by verifying indication of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on any flow during periods of release.

day on which continuous, periodic, or batch releases are made DSR 3.3.1.3 Perform SOURCE CHECK.

Prior to release DSR 3.3.1.4 Perform SOURCE CHECK.

31 days DSR 3.3.1.5 Perform CHANNEL OPERATIONAL TEST 92 days Indian Point 2 D 3.3.1 - 4 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY DSR 3.3.1.6 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation (or control panel indications/display) occurs if the instrument indicates measured levels above the alarm/trip setpoint DSR 3.3.1.7 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate control room alarm annunciation (or control panel indications/display) occurs if any of the following conditions exist, instrument indicates measured levels above the alarm setpoint, instrument controls not set in operate mode.

DSR 3.3.1.8 Perform CHANNEL CALIBRATION 92 DAYS DSR 3.3.1.9 Perform CHANNEL CALIBRATION.

24 months Indian Point 2 D 3.3.1 - 5 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 1 of 2)

Radioactive Liquid Effluent Monitoring Instrumentation CONDITIONS APPUCABILITY REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B.1 REQUIREMENTS

1.

Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a.

Uquid Radwaste (a) 1 C

DSR 3.3.1.1 Effluent Une (R-54)

DSR 3.3.1.3 DSR 3.3.1.6 e)

DSR 3.3.1.9 (d

b.

Steam Generator (a) 1 E

DSR 3.3.1.1 Effluent Blowdown DSR 3.3.1.4 Une (R-49)

DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

2.

Gross Beta or Gamma Radioactivity Monitors Providing Alarm but not Providing Automatic Termination of Release

a.

Service Water (a) 1 D

DSR 3.3.1.1 Effluent Unes DSR 3.3.1.4 (R-46, R-53, R-39, DSR 3.3.1.7 (e)

R40, and R-52)

DSR 3.3.1.9 (d)

b.

Unit 1 -

(a) 1 D

DSR 3.3.1.1 Secondary Boiler DSR 3.3.1.4 Blowdown Effluent DSR 3.3.1.7 (e)

Line (R-51)

DSR 3.3.1.9 (d)

c. Unit 1 -

(a) 1 D

DSR 3.3.1.1 Sphere Foundation DSR 3.3.1.4 Drain Sump Effluent DSR 3.3.1.7(e Une (R-62)

DSR 3.3.1.9 (d

3.

Flow Rate Measurement Devices DSR 3.3.1.2

a.

Uquid Radwaste (a) 1 F

DSR 3.3.1.5 Effluent Une DSR 3.3.1.9

b.

Steam Generator DSR 3.3.1.2 Blowdown Effluent (a) 1 F

DSR 3.3.1.5 Une DSR 3.3.1.9

c.

North Curtain Drain DSR 3.3.1.2 Effluent Une (f)

(a) 1 F

DSR 3.3.1.9

d.

Sphere Foundation DSR 3.3.1.2 Drain Sump (f)

(a) 1 F

DSR 3.3.1.9 I

I I

Indian Point 2 D 3.3.1 - 6 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D3.3.1 Table D 3.3.1-1 (page 2 of 2)

Radioactive Liquid Effluent Monitoring Instrumentation CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B.1 REQUIREMENTS

4.

Tank Level Indicating Devices (c)

a.

13 Waste Distillate (a) 1 6

DSR3.3.1.1 (b)

Storage Tank PSR 3.3.1.5 DSR 3.3.1.9

b. 14 Waste Distillate (a) 1 G

DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR 3.3.1.9

c.

Primary Water (a) 1 G

DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR 3.3.1.9

d.

Refueling Water (a) 1 G

DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR 3.3.1.8 (a) During release via this pathway. Channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the specified action for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION or CHANNEL OPERATIONAL TEST.

(b) During liquid addition to the associated tank.

(c) Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

(d) Radioactive calibration standards used for CHANNEL CALIBRATIONS shall be analyzed with instrumentation which Is calibrated with NBS (NIST) traceable standards. Standards from suppliers who participate in measurement assurance activities with NBS (NIST) are acceptable). NBS or National Institute of Standards and Technology (NIST) are acceptable traceable standards.

(e) Test will include: Low sample flow, no counts per minute failure, and alarm setpoint reached. The CHANNEL OPERATIONAL TEST does not include testing or trouble shooting and equipment diagnostic capabilities provided with the monitor installation.

(f) Flow rate for these continuous intermittent release pathways is normally obtained from a flow totalizer on the system outlet.

Indian Point 2 D 3.3.1 - 7 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 D 3.3 INSTRUMENTATION D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DLCO 3.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table D 3.3.2-1 shall be OPERABLE with:

a.

The minimum OPERABLE channel(s) in service.

b.

The alarm/trip setpoints set to ensure that the limits of DLCO 3.2.1 are not exceeded.

APPLICABILITY:

According to Table D 3.3.2-1.

ACTIONS NOTE Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Gaseous effluent A.1 Suspend the release of Immediately monitoring instrumentation radioactive gaseous channel alarm/trip setpoint effluents monitored by the less conservative than affected channel.

required.

OR A.2 Declare the channel Immediately inoperable.

OR A.3 Change the setpoint so it is Immediately acceptably conservative.

B.

One or more channels B.1 Enter the Condition Immediately inoperable.

referenced in Table D 3.3.2-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

Indian Point 2 D 3.3.2 - 1 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

As required by Required C.1 Take grab samples.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B.1 and referenced in Table D 3.3.2-1.

AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereahter AND C.2 Analyze samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time of activity.

sampling completion D. As required by Required D.1 Estimate the flow rate for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action B.1 and referenced the inoperable channel(s).

in Table D 3.3.2-1.

AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter E.

As required by Required E.1 Continuously collect 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action B.1 and referenced samples using auxiliary in Table D 3.3.2-1.

sampling equipment as re uired in Table D 3.2.1-1.

Indian Point 2 D 3.3.2 -2 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F.1 Determine radioactive 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action B.1 and referenced content of gas decay tank in Table D 3.3.2-1.

is in compliance with AND DLCO 3.2.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter G. As required by Required G.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in release in Table D 3.3.2-1.

accordance with Table D 3.2.1-1.

AND G.2

NOTE-------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the Prior to initiating a release rate calculations and release discharge line valving.

H.

Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met.

Release Report why the Release Report inoperability was not frequency corrected in a timely manner.

I.

Required Action and 1.1 Suspend gaseous effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E inoperable channel(s).

or F not met.

J.

Required Action and J.1 Suspend gaseous effluent Immediately associated Completion releases from Waste Gas Time for Condition G not Holdup System.

met.

Indian Point 2 D 3.3.2-3 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.3.2.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DSR 3.3.2.2 Perform CHANNEL CHECK.

7 days DSR 3.3.2.3 Perform SOURCE CHECK.

Prior to release DSR 3.3.2.4 Perform SOURCE CHECK.

31 days DSR 3.3.2.5 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate the automatic isolation capability of this pathway and that control room alarm annunciation (or control panel indications/display) occurs if the instrument indicates measured levels above the alarm/trip setpoint.

DSR 3.3.2.6 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate control room alarm annunciation (or control panel indications/display) occurs if any of the following conditions exist, instrument indicates measured levels above the alarm setpoint, instrument controls not set in operate mode.

DSR 3.3.2.7 Perform CHANNEL CALIBRATION.

18 months DSR 3.3.2.8 Perform CHANNEL CALIBRATION.

24 months Indian Point 2 D 3.3.2-4 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation*

D3.3.2 Table D 3.3.2-1 (page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED CONDITIONS APPLICABILITY CHANNELS REFERENCED OR OTHER PER FROM SURVEILLANCE INSTRUMENT SPECIFIED INSTRUMENT REQUIRED REQUIREMENTS CONDITIONS ACTION B.1

1. Waste Gas Holdup System DSR 3.3.2.1

a.

Noble Gas (b) 1 F

DSR 3.3.2.4 Activity Monitor DSR 3.3.2.6 (d)

Providing Alarm DSR 3.3.2.8 (c)

(R-50)

2.

Condenser Evacuation System DSR 3.3.2.1

a.

Noble Gas (a) 1 C

DSR 3.3.2.4 Activity DSR 3.3.2.6 (e)

(R-45)

DSR 3.3.2.8 c)

3.

Plant Vent Radiation Monitor:

a. Noble Gas Activity (a) & (b) 1 C & G DSR 3.3.2.1 Radiation DSR 3.3.2.4 Monitor (R-44)

DSR 3.3.2.5 Md DSR 3.3.2.8 (c)

Other Effluent Instrumentation:

b.

Iodine Sampler (a) 1 E

DSR 3.3.2.2

c.

Particulate Sampler (a) 1 E

DSR 3.3.2.2

d.

Flow-Rate Monitor (a) 1 D

DSR 3.3.2.1

e.

Sample Flow-DSR 3.3.2.7 Rate Monitor (a) 1 D

DSR 3.3.2.1 DSR 3.3.2.8 I

I I

Indian Point 2 D 3.3.2 - 5 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D3.8.2-1 (page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS FROM SURVEILLANCE INSTRUMENT SPECIFIED PER REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

4.

Main Stack Effluent (Unit 1)

Radiation Monitor

a.

Noble Gas Activity (a) 1 C

DSR 3.3.2.1 Monitor DSR 3.3.2.4 (R-60)

DSR 3.3.2.6 (d)

DSR 3.3.2.8 (c)

Other Effluent Instrumentation:

b.

Iodine (a) 1 E

DSR 3.3.2.2 Sampler

c.

Particulate (a) 1 E

DSR 3.3.2.2 Sampler

d.

Flow-Rate (a) 1 D

DSR 3.3.2.1 Monitor DSR 3.3.2.7

e.

Sample (a) 1 D

DSR 3.3.2.1 Flow-Rate DSR 3.3.2.8 Monitor (a) During release via this pathway. Channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the specified action for the purpose of maintenance and performance of required CHANNEL CHECK. SOURCE CHECK, CHANNEL CALIBRATION or CHANNEL OPERATIONAL TEST.

(b) During waste gas holdup system operation (treatment for primary system off-gases).

(c) Radioactive Calibration Standards used for channel calibrations shall be traceable to the National Bureau of Standards or an aliquot of calibration gas shall be analyzed with instrumentation which is calibrated with NBS traceable standards (standards from suppliers who participate in measurement assurance activities with NBS are acceptable). NBS or National Institute of Standards and Technology (NIST) are acceptable traceable standards.

(d) Test will include: Low sample flow, no counts per minute failure, and alarm setpoint reached. The CHANNEL OPERATIONAL TEST (COT) does NOT include testing of troubleshooting and equipment diagnostic capabilities provided with the monitor installation.

(e) Test will include: no counts per minute failure and alarm setpoint reached. The COT does NOT include testing of troubleshooting and equipment diagnostic capabilities provided with the monitor installation.

Indian Point 2 D 3.3.2-6 Revision 9

Radioactive Effluents Total Dose D3.4.1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose DLCO 3.4.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to < 75 mrem.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Estimated dose or dose A.1 Verify the condition resulting Immediately commitment due to direct in doses exceeding these radiation and the release limits has been corrected.

of radioactive materials in liquid or gaseous effluents exceeds the limits.

B.

Required Action and B.1

NOTE-----------

associated Completion This is the Special Report Time not met.

required by D 3.1.2, D 3.2.2, or D 3.2.3 supplemented with the following.

Submit a Special Report, 30 days pursuant to D 5.3, including a request for a variance in accordance with the provisions of 40 CFR 190.

This submission is considered a timely request, and a variance is granted until staff action on the request is complete.

Indian Point 2 D 3.4.1 - 1 Revision 9

Radioactive Effluents Total Dose D3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.4.1.1 Perform a cumulative dose calculation due to 12 months radioactive material in gaseous and liquid effluents to determine compliance with DLCO 3.4.1.

Indian Point 2 D 3.4.1 - 2 Revision 9

Radiological Environmental Monitoring Program D3.5.1 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D3.5.1 DLCO 3.5.1 Monitoring Program The Radiological Environmental Monitoring Program shall be conducted as specified in Table D 3.5.1-1.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Radiological A.1 Prepare and submit to the In accordance with Environmental Monitoring NRC in the Annual the Annual Program not conducted as Radiological Environmental Radiological specified in Operating Report, a Environmental Table D 3.5.1-1.

description of the reasons Operating Report for not conducting the frequency program as required and the plans for preventing a recurrence.

B.

Level of radioactivity in an B.1 NOTES--

environmental sampling

1. Only applicable if the medium at a specified radioactivity/radionuclides location exceeds the are the result of plant reporting levels of effluents.

Table D 3.5.1-2 when

2. For radionuclides other averaged over any than those in Table calendar quarter.

D 3.5.1-2, this report shall indicate the methodology OR and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

Indian Point 2 D 3.5.1 - 1 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME More than one of the radionuclides in Table D 3.5.1-2 are detected in the environmental sampling medium and Concentration 1

+

reporting level 1 concentration 2 +... 2 1.0.

reporting level 2 OR Radionuclides other than those in Table D 3.5.1-2 are detected in an environmental sampling medium at a specified location which are the result of plant effluents and the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is 2 the calendar year limits of Specifications D 3.1.2, D 3.2.2 or D 3.2.3.

Prepare and submit to the NRC, pursuant to D 5.3, a Special Report that (1) Identifies the cause(s) for exceeding the limit(s) and (2) Defines 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 Specifications D 3.1.2, D 3.2.2, or D 3.2.3.

OR B.2 --

NOTES-1.Only applicable if the radioactivity/radionuclides are not the result of plant effluents.

2.For radionuclides other than those in Table D 3.5.1-2, this report shall indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

30 days In accordance with the Annual Radiological Environmental Operating Report frequency Report and describe the condition in the Annual Radiological Environmental Operating Report.

___________________________________ £ L

Indian Point 2 D 3.5.1 - 2 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Milk or fresh leaf C.1 Identify specific locations 30 days vegetation samples for obtaining replacement unavailable from one or samples and add them to more of the sample the Radiological locations required by Environmental Monitoring Table D 3.5.1-1.

Program.

AND C.2 Delete the specific 30 days locations from which samples were unavailable from the Radiological Environmental Monitoring Program.

AND C.3 Pursuant to D 5.2, submit In accordance with in the next Radioactive the Radioactive Effluent Release Report Effluent Release documentation for a Report change in the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

D.

Environmental samples D.1 Ensure all efforts are made Prior to the end of required in Table D 3.5.1-1 to complete corrective the next sampling are unobtainable due to action(s).

period sampling equipment malfunctions.

AND D.2 Report all deviations from In accordance with the sampling schedule in the the Annual Annual Radiological Radiological Environmental Operating Environmental Report.

Operating Report Indian Point 2 D 3.5.1 - 3 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Samples required by Table E.1 Choose suitable alternative 30 days D 3.5.1-1 not obtained in*

media and locations for the the media of choice, at the pathway in question.

most desired location, or at the most desired time.

AND E.2 Make appropriate 30 days substitutions in the Radiological Environmental Monitoring Program.

AND E.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a Report change in the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

Indian Point 2 D 3.5.1 - 4 Revision 9

Radiological Environmental Monitoring Program D3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.1.1 Collect and analyze radiological environmental In accordance with monitoring samples pursuant to the requirements of Table D 3.5.1-1 Table D 3.5.1-1 and the detection capabilities required by Table D 3.5.1-3.

Indian Point 2 D 3.5.1 - 5 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 1 of 3)

Radiological Environmental Monitoring Program EXPOSURE NUMBER SAMPLING AND PATHWAY OF COLLECTION TYPE AND FREQUENCY AND/OR SAMPLES SAMPLE FREQUENCY OF ANALYSIS SAMPLE STATIONS LOCATIONS (a)

1. Direct 40 routine (1) An inner ring of stations Once per 3 months Gamma dose: once per 3 Radiation monitoring (DRI-DR16), one in each months stations (b) meteorological sector in (DRI-DR40) the general area of the SITE BOUNDARY (2) An outer ring of stations (DR17-DR32), one in each meteorological sector In the 6 to 8 km range from the site (3) The balance of the stations (DR33-DR40), should be placed In special interest areas such as population centers, nearby residences, schools, and In one or two areas to serve as control stations

2. Airborne 5 locations (1) 3 samples (AI-A3) from Continuous sampler Radiolodine canister Radiolodine (AI-A5) offsite locations dose to operation with sample Analyze weekly for 1-131 and the site boundary in collection weekly or Particulates different sectors, of the more frequently If Particulate sampler highest calculated annual required by dust (1) Analyze for gross beta average ground level D/O loading radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (2) 1 sample (A4) from the following filter change vidnity of an established (2) Perform gamma Isotopic year-round community analysis on each sample having the highest (e) In which gross beta calculated annual average activity is> 10 times the ground level DQ previous yearly mean of (3) 1 sample (A5) from a control samples.

(3) ollctin 1 0km()Gamma Isotopic control locaIon, 15-30 km analysis of composite distant and in the least sample (e) (by location) prevlentwinddiretion(c)once per 3 months

3. Waterborne

a. Surface (f)

I sample Upstream (Wal)

Composite sample (1) Gamma Isotopic over a one month analysis of each sample period (g)

(e) once per month I sample Downstream (Wa2)

(2) H-3 analysis of each composite sample and once per 3 months Indian Point 2 D 3.5.1 - 6 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 2 of 3)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY SAMPLING AND AND/OR NUMBER OF SAMPLE COLLECTION TYPE AND FREQUENCY OF SAMPLE SAMPLES LOCATIONS (a)

FREQUENCY ANALYSIS

3. Waterbome (continued)

b. Drinking 1 sample Nearest water supply Grab sample: Monthly (1) Gross beta and gamma (Wb1)

Isotopic analyses of each composite sample (e) monthly (2)

H-3 analysis of each composite sample once per 3 months

c. Sediment 2 samples Downstream area (Wcl)

Twice per year at least Gamma Isotopic analysis of from with existing or potential 90 days apart each sample (e) semiannually Shoreline recreational value Upstream area (Wc2) control sample

4. Ingestion

a. Milk (1) 3 samples In 3 locations (lal-la3)

Twice per month when (1) Gamma Isotopic (e) and I-from within 5 km having the animals are on pasture; 131 analysis of each MILK highest dose potential monthly at other times sample twice per month SAMPLING April through December LOCATIONS (2)

Gamma isotopic (g) and I-131 analysis of each (2) If there are In each of 3 areas (Ia1-1a3) sample once per month none, then 1 5 to 8 km distance, If January through March If sample available, where doses are required from MILK calculated to be > Imrem SAMPLING per year (h)

LOCATIONS (3)1 sample from At a control location (1a4),

Concurrently with a MILK 15 to 30 km distant and In indicator locations SAMPLING the least prevalent wind LOCATION direction

b. Fish and (1) 1 sample each In the vidnity of a plant Sample In season, Gamma Isotopic analysis of Invertebrates of 2 discharge area (Ibl) or each sample (e) on edible commercially Semiannually If sample portions or Is not seasonal recreationally Important species (2) 1 sample of If available In areas not the same Influenced by plant species discharge (Ib2)

Indian Point 2 D 3.5.1 - 7 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 3 of 3)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY SAMPLING AND TYPE AND FREQUENCY OF AND/OR NUMBER OF SAMPLE COLLECTION ANALYSIS SAMPLE SAMPLES LOCATIONS (a)

FREQUENCY

4. Ingestion (continued)

c. Food (1) Samples of 3 Grown nearest to each Monthly when Gamma Isotopic (e) and 1-131 Products different kinds of 2 different offsite available analysis of broad leaf locations of highest vegetation (such predicted annual as vegetables) average ground level (2) 1 sample of D/Q If milk sampling Is each of the not performed (Icl-lc2) similar broad leaf vegetation.

Grown 15 to 30 km distant In the least prevalent wind direction If milk sampling Is not performed (Ic3)

(a) The code letters in parenthesis, e.g., DRI, Al define generic sample locations. Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent, shall be provided for each and every sample location in Table D 3.5.1-1. Refer to NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,' October 1978, and to Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

(b) One or more Instruments, such as a pressurized Ion chamber, for measuring and recording dose rate continuously may be used in place of, or In addition to Integrating dosimeters. Each of the 40 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 Instrument for measuring and recording dose rate continuously. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; 2 or more phosphors in a packet are considered as 2 or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(c) The purpose of these samples is to obtain background Information. If it Is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites, which provide valid background data, may be substituted.

(d) Airborne particulate sample filters shall be analyzed for gross beta activity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.

(e) Gamma Isotopic analysis means the identification and quantification of gamma -emitting radionuclides that may be attributable to the effluents from the facility.

(f) The 'upstream samples shall be taken near the Intake structures as described in the ODCM. The downstream' sample shall be taken from the mixing zone at the diffuser of the discharge canal.

(g) In this program, a composite sample Is one in which the quantity (aliquot) shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(h) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

Indian Point 2 D 3.5.1 - 8 Revision 9

Radiological Environmental Monitoring Program D3.5.1 Table D 3.5.1-2 (page 1 of 1)

Reporting Levels for Radioactivity in Environmental Samples AIRBORNE PARTIUCLATE 9R FISH MILK WATER GASES (pCVm )

(pCVkg, wet)

(pCVL)

FOOD PRODUCTS (pCVkg, wet)

RADIONUCLIDE ANALYSIS H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 (pCGL) 20,000 (a) 1,000 400 1,000 300 300 400 400 2 (b) 30 50 30,000 10,000 30,000 10,000 20,000 0.9 3

10 20 1,000 2,000 60 70 100 1,000 2,000 Ba-140 200 300 La-140 200 300 (a) For drinking water samples. This is a 40 CFR 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.

Indian Point 2 D 3.5.1 - 9 Revision 9

Radiological Environmental Monitoring Program D 3.5.1 Table 3.5.1-3 (page 1 of 1)

Detection Capabilities for Environmental Sample Analysis (a)

LOWER LIMIT OF DETECTION (LLD) (b) (c)

AIRBORNE PARTIUCLATE FOOD RADIONUCLIDE WATER OR GASES FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/L)

(pCi/M )

(pCi/kg, wet)

(pCiVL)

(pCi/kg, wet)

(pCi/kg, dry) 4 0.01 Gross Beta H-3 2,000 (e)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 1 5 Nb-95 1 5 1-131 1 (d) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 15 15 La-140 15 15 (a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification D 5.1.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

(c) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a 'real signal.

(d) LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

(e) If no drinking water pathway exists, a value of 3000 pCi/L may be used.

Indian Point 2 D 3.5.1 -10 Revision 9

Land Use Census D 3.5.2 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.2 Land Use Census DLCO 3.5.2 A land use census shall:

a. Be conducted,

b. Identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal and the nearest residence, and the nearest garden (broad leaf vegetation sampling controlled by Table D 3.5.1-1, par 4.c may be performed in lieu of the garden census) of > 50 m2 (500 ft ) producing broad leaf vegetation, and

c. For elevated releases, identify within a distance of 3 miles the locations, in each of the 1 6 meteorological sectors, of all milk animals and all gardens > 50 m" producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Land use census identifies A.1 Identify the new location(s)

In accordance with location(s) that yields a in the next Radioactive the Radioactive calculated dose, dose Effluent Release Report.

Effluent Release commitment, or D/Q value Report

> than the values currently being calculated in DSR 3.2.3.1.

Indian Point 2 D 3.5.2 - 1 Revision 9

Land Use Census D 3.5.2 ACTIONS (continued)

CONDITION

]

REQUIRED ACTION I COMPLETION TIME B. Land use census identifies location(s) that yields a calculated dose, or dose commitment (via the same exposure pathway) a factor

> 2 than at a location from which samples are currently being obtained in accordance with Table D 3.5.1-1.

B.1 Add the new location(s) to the Radiological Environmental Monitoring Program.

AND B.2 Delete the sampling location(s), excluding the control station location, having the lowest calculated dose, dose commitment(s) or D/Q value, via the same exposure pathway, from the Radiological Environmental Monitoring Program.

AND B.3 Submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

30 days After October 31 of the year in which the land use census was conducted In accordance with the Radioactive Effluent Release Report Indian Point 2 D 3.5.2 - 2 Revision 9

Land Use Census D 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.2.1 Conduct the land use census during the growing 366 days season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

DSR 3.5.2.2 Report the results of the land use census in the In accordance with Annual Radiological Environmental Operating Report.

the Annual Radiological Environmental Operating Report Indian Point 2 D 3.5.2 - 3 Revision 9

Interlaboratory Comparison Program D 3.5.3 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.3 Interlaboratory Comparison Program DLCO 3.5.3 The Interlaboratory Comparison Program shall be described in the ODCM.

AND Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Analyses not performed as A.1 Report the corrective In accordance with required.

actions taken to prevent a the Annual recurrence to the NRC in Radiological the Annual Radiological Environmental Environmental Operating Operating Report Report.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.3.1 Report a summary of the results obtained as part of In accordance with the Interlaboratory Comparison Program in the the Annual Annual Radiological Environmental Operating Report.

Radiological Environmental Operating Report Indian Point 2 D 3.5.3 - 1 Revision 9

Solid Radwaste Treatment System*

D 3.6.1 D 3.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System DLCO 3.6.1 The appropriate equipment of the Solid Radwaste Treatment System shall be in operation process wet radioactive wastes in accordance with the Process Control Program.

APPLICABILITY:

During solid radwaste processing ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Radioactive solid waste A.1 Suspend shipments of Immediately does not comply with solid radioactive waste.

Process Control Program requirements.

Indian Point 2 D 3.6.1 - 1 Revision 9

Solid Radwaste Treatment System D 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.6.1.1 Verify solidification of specimens in accordance with Prior to each the Processing Control Program.

shipment DSR 3.6.1.2 Record the following information for each class of Prior to each solid waste (as defined by 10 CFR Part 61) shipment shipped offsite during the Radioactive Effluent Release Report period:

a.

Container volume,

b.

total curie quantity (specify determined by measurement or estimate),

c.

principal radionuclides (specify 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).

Indian Point 2 D 3.6.1 - 2 Revision 9

UNRESTRICTED AREA D4.1 D 4.0 DESIGN FEATURES D 4.1 UNRESTRICTED AREA D 4.1.1 Information which will allow identification of structures and release points for radioactive gaseous and liquid effluents is shown in Figure D 4.1-1.

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.

D 4.1.2 For the purpose of satisfying 10 CFR Part 20, the 'Restricted Area" is the same as the "Exclusion Area" defined in Figure 2.2-2 of Section 2.2 of the UFSAR.

Indian Point 2 D4.1 - 1 Revision 9

(

JRESTRICTED AREA D4.1 C

Figure D 4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS

-J 1

0

-0P#

P.

P..f i-I -

I, MAP MMiIN tMR07MC1E ARMA FOM RAMOAC~ft GASEOUS AMD UiJUD EFLUENTS (AT OR BEYOND THE SITE BOUNDARY) &

RESTRICTED AREAS WITHN THE SITE BOUNDARY, AS DEFINED BY IOCFR20 fpz nn)

Indian Point 2 D 4.1 - 2 Revision 9

Annual Radiological Environmental Operating Report D 5.1 D 5.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Reports shall include:

a.

Summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment;

b.

The results of land use censuses required in DSR 3.5.2;

c.

A summary description of the radiological environmental monitoring program;

d.

At least two legible maps (one map shall cover stations near the SITE BOUNDARY; a second shall include more distant stations) covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor;

e.

The results of licensee participation in the Interlaboratory Comparison Program, required by Section D 3.5.3;

f.

Discussion and all deviations from the sampling schedule of Table D 3.5.1-1; and,

9.

Discussion of all analyses in which the LLD required by Table D 3.5.1-3 was not achievable.

Indian Point 2 D5.1 - 1 Revision 9

Radioactive Effluent Release Report D5.2 D 5.0 ADMINISTRATIVE CONTROLS D 5.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include:

a.

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

I

b.

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 magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution 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 onsite in a file that shall be provided to the NRC upon request

c.

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

d.

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 (Figure D 4.1-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. Gaseous pathway doses are determined from sampling and measurements at the exhaust points, coupled with the use of annual-averaged meteorological data collected from a period of live data to verify its validity. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

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

e.

The following information for each class of solid waste (in compliance with 10 CFR Part 61) shipped offsite during the report period:

1.

Container volume,

2.

total curie quantity (specify whether determined by measurement or estimate),

Indian Point 2 D 5.2 - 1 Revision 9

Radioactive Effluent Release Report D 5.2 D 5.2 Radioactive Effluent Release Report (continued)

3.

principal radionuclides (specify whether determined by measurement or estimate),

4.

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

5.

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

6.

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

f.

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.

9.

Any changes made during the reporting period to the Process Control Program (PCP) and to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification D 3.5.2.

Indian Point 2 D 5.2-2 Revision 9

Special Reports D 5.3 D 5.0 ADMINISTRATIVE CONTROLS D 5.3 Special Reports Special reports shall be submitted to the NRC Regional Administrator of the Region I Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the applicable Specification:

a.

Radioactive Effluents (Specifications D 3.1, D 3.2 and D 3.4)

b.

Radiological environmental monitoring (Specification D 3.5)

Indian Point 2 D 5.3 - 1 Revision 9

Major Changes to Radioactive Waste Systems D 5.4 D 5.0 ADMINISTRATIVE CONTROLS D 5.4 Major Changes to Radioactive Waste Systems Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the change was made. The discussion of each change shall contain:

a.

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

b.

sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information,

c.

a detailed description of the equipment, components and processes involved and the interfaces with other plant systems, d

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,

e.

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

thereto,

f.

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 in which the changes are to be made;

9.

an estimate of the exposure to plant operating personnel as a result of the change, and

h.

documentation of the fact that the change was reviewed and found acceptable by the OSRC.

Indian Point 2 D 5.4 - 1 Revision 9

Process Control Program D5.5 D 5.0 ADMINISTRATIVE CONTROLS D 5.5 Process Control Program Licensee initiated changes to the Process Control Program (PCP):

a.

Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

I

1.

sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,

2.

a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes, and

3.

documentation of the fact that the change has been reviewed and found acceptable by the OSRC.

b.

Shall become effective upon review and acceptance by the OSRC.

Indian Point 2 D 5.5 - 1 Revision 9

Indian Point 2 Offsite Dose Calculation Manual BASES

Applicability B D 3.0 B 3.0 APPLICABILITY BASES DLCOs 3.0.1, 3.0.2, and 3.0.5, and DSRs 3.0.1, 3.0.2, and 3.0.3 reflect parallel requirements in the Technical Specifications. Refer to Technical Specification Bases for appropriate discussions.

ODCM Specification DLCO 3.0.3, in lieu of imposing a plant shutdown as paralleled in Technical Specification LCO 3.0.3, requires: (a) an Action to initiate efforts to restore compliance with the ODCM or associated Actions; and (b) an Action that requires entering the circumstances Into the Corrective Action Program (CAP). These requirements ensure that the appropriate actions continue to be focused on and that the circumstances concerning failure to comply with the ODCM Actions would be reviewed. This review will be conducted in accordance with the procedural guidance for CAP Notifications.

There are no ODCM 3.0 Specifications that parallel Technical Specification LCO 3.0.4 or SR 3.0.4. Restrictions in entering MODES or other specified conditions In the Applicability have historically not been applied to ODCM Specifications. There are also no ODCM 3.0 Specifications that parallel Technical Specification LCO 3.0.6 and LCO 3.0.7, which allow for exceptions and revisions of other Technical Specifications. They are not applicable to the ODCM since it is not permitted to allow the ODCM to revise a Technical Specification.

(Note, currently no identified ODCM DLCOs support Technical Specification systems; however, this discussion is presented to address the philosophy that would be applied.) An allowance similar to Technical Specification LCO 3.0.6 does not apply to the ODCM. When a Technical Specification supported system LCO is discovered to be not met solely due to a ODCM support system DLCO not met, appropriate Technical Specification ACTIONS are required to be entered immediately. This applies even in instances where the ODCM contains a delay prior to declaring a Technical Specification supported system inoperable. In this case, certain ODCM inoperabilities may not directly impact the OPERABILITY of the Technical Specification supported system and delayed declaration of inoperability of the supported system is acceptable. In other cases, discovered support system inoperabilities that directly result in supported system inability to perform the safety function, should result in immediate declaration of inoperability of the supported system.

Technical Specification LCO 3.0.7 has no parallel in the ODCM since it provides for explicit changes to specified Technical Specifications by the Section 3.1.8 Specifications. However, in the event that LCO 3.0.7 provides for changes to the Technical Specification MODE definitions by the Section 3.1.8 Specifications, the revised MODE definitions apply to all plant references, including ODCM references.

Indian Point 2 B D 3.0-1 Revision 9

Liquid Effluent Concentrations B D 3.1.1 B D 3.1 RADIOACTIVE LIQUID EFFLUENTS B D 3.1.1 Liquid Effluent Concentrations BASES It is expected that the release of radioactive materials in liquid and gaseous effluents to UNRESTRICTED AREAS will not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as reasonably achievable (ALARA) in accordance with the requirement of 10 CFR 50.36a. While providing reasonable assurance that the design objectives will be met, these Specifications permit the flexibility of operation, compatible with considerations of health and safety, to ensure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20. It is expected that using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive materials in liquid and gaseous wastes as low as reasonably achievable, releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience, taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with 10 CFR Part 50.36a.

The Indian Point site is a multiple-unit site. There exist shared radwaste treatment systems and shared effluent release points. Where site limits must be met, the effluents of all the units will be combined to determine site compliance. For instances where unit-specific information may be required for radwaste processed or released via a shared system, the effluents shall be proportioned among the units sharing the system(s) in accordance with the methods and agreements set forth in the ODCM.

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20. This limitation provides additional 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 limits of 10 CFR Part 20.1302 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

This specification applies to the release of liquid effluents from all units on site.

Indian Point 2 B D3.1.1 - 1 Revision 9

Liquid Effluents Dose D 3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.2 Liquid Effluents Dose BASES This Specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The DLCO implements the guides set forth in Section IL.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 reasonably achievable'. Also, for fresh water sites to UNRESTRICTED AREA 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 concentration 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 In, April 1977.

In addition to the limiting conditions for operation, the reporting requirements specify that the licensee shall identify the cause whenever the dose from the release of radioactive materials in liquid waste effluent exceeds the above limits and describe the proposed program of action to reduce such releases to design objective levels on a timely basis.

Indian Point 2 B D 3.1.2 - 1 Revision 9

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System BASES This Specification requires that the licensee maintain and operate appropriate equipment installed in the liquid waste systems, when necessary, to provide assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable'. This Specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section I.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 I.A of Appendix I to 10 CFR Part 50 for liquid effluents.

Indian Point 2 B D3.1.3 - 1 Revision 9

Liquid Holdup Tanks D 3.1.4 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks BASES The tanks listed in this Specification include 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. These tanks include the following:

a.

Refueling Water Storage Tank

b.

Primary Water Storage Tank

c.

13 Waste Distillate Storage Tank

d.

14 Waste Distillate Storage Tank

e.

Outside Temporary tank Restricting the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of any such tank's contents, the resulting concentration would be less than the limits of 10 CFR 20 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

Indian Point 2 B D 3.1.4 - 1 Revision 9

Gaseous Effluents Dose Rate D3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate BASES This Control provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10 CFR Part 50. This Control is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled.

It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50.

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmospheric dispersion of gaseous effluents relative to that for the SITE BOUNDARY.

Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. This Control does not affect the requirement to comply with the annual limitations of 10 CFR 20.

This Control applies to the release of gaseous effluents from all units at the site.

Indian Point 2 B D3.2.1 - 1 Revision 9

Gaseous Effluents Dose - Noble Gas D 3.2.2 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.2 Gaseous Effluents Dose - Noble Gas BASES This Specification is provided to implement the requirements of Sections Il.B, IlI.A, and IV.A of Appendix I to 10 CFR Part 50. The DLCO implements the guides set forth in Section II.B 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 gaseous effluents to UNRESTRICTED AREAS will be kept 'as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section IIL.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 dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous 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 l," Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases form Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This Control applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B D3.2.2 - 1 Revision 9

Gaseous Effluents Dose - Iodine and Particulate D 3.2.3 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate BASES This Specification is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I to 10 CFR Part 50. The DLCOs are the guides set forth in Section I.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 to UNRESTRICTED AREAS will be kept Was low as 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 1.1 11, "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 specifications for iodine-1 31, 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, and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B D 3.2.3 - 1 Revision 9

Gaseous Radwaste Treatment System D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System BASES This Specification requires that the appropriate portions of the Gaseous Radwaste Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept Was low as reasonably achievable." This Specification 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 I.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 ll.B and I.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B D 3.2.4 - 1 Revision 9

Gaseous Radwaste Treatment System' D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System BASES This Specification requires that the appropriate portions of the Gaseous Radwaste Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept 'as low as reasonably achievable." This Specification 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 I.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 Il.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B D3.2.4 - 1 Revision 9

Ventilation Exhaust Treatment System D 3.2.5 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.5 Ventilation Exhaust Treatment System BASES This Specification requires that the appropriate portions of the Ventilation Exhaust Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept 'as low as reasonably achievable." This Specification 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 IL.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 11.8 and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B D 3.2.5 - 1 Revision 9

Gas Storage Tanks' D 3.2.6 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.6 Gas Storage Tanks BASES The tanks included in this Specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by other specifications to a quantity that is less than the quantity that provides assurance that, in the event of an uncontrolled release of the tank's 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months duration.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurances that, in the event of an uncontrolled release of the tank's 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 Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.

Indian Point 2 B D 3.2.6 - 1 Revision 9

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation BASES The radioactive liquid effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with methods set forth 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. 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.

Indian Point 2 B D 3.3.1 - 1 Revision 9

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 D 3.3 INSTRUMENTATION D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in 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. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.

Indian Point 2 B D3.3.2 - 1 Revision 9

Radioactive Effluents Total Dose D3.4.1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose BASES This Specification is provided to meet the dose limitation of 40 CFR Part 190 that has been incorporated into 10 CFR Part 20 by 46 FR 18525. The Specification requires the preparation and submittal of a special report whenever the calculated doses from plant-generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The special report will describe a 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. For the purposes of the special report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the special report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications D 3.1.1 and D 3.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Indian Point 2 B D 3.4.1 - 1 Revision 9

Radiological Environmental Monitoring Program D3.5.1 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Radiological Environmental Monitoring Program BASES The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of members of the public resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. Program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table D 3.5.1-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Indian Point 2 B D 3.5.1 - 1 Revision 9

Land Use Census D 3.5.2 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.2 Land Use Census BASES This specification 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.

Restricting the census to gardens of greater than 50 m2 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 vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2.

Indian Point 2 B D 3.5.2 - 1 Revision 9

Interlaboratory Comparison Program D 3.5.3 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.3 Interlaboratory Comparison Program BASES 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 (developed using the guidance in Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April 1975) in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

Indian Point 2 B D 3.5.3 - 1 Revision 9

Solid Radwaste Treatment System D 3.6.1 D 3.6 SOLID RADWASTE TREATMENT SYSTEM D 3.6.1 Solid Radwaste Treatment System BASES This Specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the process control program may include, but are not limited to, waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

Indian Point 2 B D 3.6.1 - 1 Revision 9

Indian Point 2 Offsite Dose Calculation Manual PART 11-CALCULATIONAL METHODOLOGIES

ODCM Part II - Calculational Methodologies Radiation Monitor Setpoints and associated compliance with 1 OCFR20 involve an -awareness of all radioactive liquid waste releases on site. For example, setpoints may be increased with additional dilution flow "borrowed" from unit 3, provided there is documented communication between the shift managers. Conservatively, a minimum dilution flow of 100,000 gpm is normally dedicated to one unit's routine liquid effluent to ensure sufficient operational margin to comply with 10CFR20 limitations.

The Liquid Radwaste Effluent monitor shall alarm and suspend a release in the event that setpoints are exceeded or approached. The setpoints derived in Section 4.1 and Appendix E ensure diluted concentrations of each isotope is below the required MPC for all release pathways and modes. The setpoint does not account for decay or dispersion beyond the restricted area boundary and thus conservatively controls the effect at the junction of the discharge canal and river.

Monitor conversion factors are generally determined experimentally with actual plant fluid or with calibration mixtures. Noble gases may contribute to monitor response and must be included in the determination of a monitor conversion factor, as shown in Appendix F. The general requirements for setpoints and conversion factors apply to all releases.

1.3 Determining the Dose for Radioactive Liquid Effluents The RECS require a calculation at least once per 31 days, to verify required operation of the radwaste cleanup systems when cumulative releases of radioactivity in liquid effluents are expected to cause a dose in excess of 0.06 mrem total body, or 0.2 mrem to any organ.

The 10CFR50 quarterly and annual time averaged limits are also defined in the RECS as follows:

Total Body Any Oroan Quarterly limit 1.5 mrem 5 mrem Annual limit 3 mrem 10 mrem The drinking water pumping station on the Hudson River (Chelsea) is beyond the distance requiring impact consideration. Similarly, REMP samples and calculations of doses from historical shoreline deposits indicate that potable water and shoreline deposit pathways need not be considered for offsite dose calculations. Therefore, consumption of fish and shellfish (invertebrates) alone is considered.

The Hudson River at Indian Point is a mixture of fresh and saltwater. The average salinity of the river is about 15% of ocean salinity so that there is an admixture of freshwater and saltwater fish and shellfish in the plant environs. Using data provided from References 18 and 20, the optimum bioaccumulation factors for Indian Point are the values from Reg Guide 1.109 for fresh water fish and salt water invertebrates, coupled with those site-specific values identified in the referenced studies. Resulting site-specific bioaccumulation and dose factors, as well as their justification are further explained in part 11 of the Indian Point 3 ODCM, section 2.6.

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. Although the calculations use the same models, these estimates are not included in dose calculations for routine releases due to their inflated contribution from natural causes.

Indian Point 2 Page 2 Revision 9

ODCM Part II - Calculational Methodologies 1.4 Dose Calculations The organ dose from all radionuclides i released in a specific calendar period, T, is:

DT = I (AIDFi Z AtjcjjF')

(L-1)

[7]

Where:

D-e organ dose commitment (mrem)

A, site related ingestion dose commitment factor (mrem/hr per VCVml) for nuclide i At e

incremental release period j for release of nuclide i within the calendar period (hours)

DF e

Environmental Transit Time factor (tp from RG 1.109 and unitless),

represented as e ~, where t is the delay between sampling and start of release, and X is the decay constant (sec -1) for nuclide i. This term is conservatively set to 1.0, but may be applied as needed, in rare cases of short-lived isotopes in liquid waste.

cii e

undiluted concentration of nuclide i during release period Atj (VCi/mI)

F' e

near-field average dilution (unitless)

=

liquid radioactive waste flow/ (circulating flow x K)

K site specific applicable factor (determined by New York University to have a value of 5)

To better manage a hand calculation, a limited analysis based on the dominant contributors to dose can be performed. The 1988-90 data shows that, in order of decreasing impact, the following nuclides require consideration in the limited analysis: Cs-137, Cs-134, Ni-63, H-3, Co-60. It is advisable to also include Fe-55, Co-58, and any Iodine identified, especially in Steam Generator Blowdown, where Iodine can dominate the total activity.

From Appendix E, with the dilution applied to the isotopic concentrations, the equation becomes:

DT = E (ADF E At.Ci)

(L-2) i i

where; Cj = (f/F) x cj = dilute concentration Indian Point 2 Page 3 Revision 9

ODCM Part II - Calculational Methodologies.

From NUREG-0133 (page 17), the summary dose factor is defined as:

A-T= K[(UF)BFi + ( UI)BI j ]DF, (L-3)

Where:

AZr =

Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, mrem/hr per pCi/ml.

K =

Unitsconversionfactor, 114155= (lE6CVUCi)C*(1E3mVkg) 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 pCVkg per pCiA from Table A-1 of Regulatory Guide 1.109.

Ul =

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 Invertebrates Bioaccumulation factor for nuclide, i, in pCi/kg per pCiA from Table A-1 of Regulatory Guide 1.109.

DF1 = Dose conversion factor for nuclide i, for age groups in pre-selected organs, T, in mrem/pCi, from Tables E-11, 12 & 13 of Regulatory Guide 1.109.

Compiled A-r factors for 3 age groups and various organs for the maximum exposed individual are provided in Tables 1.2, 1.3, and 1.4. Bio-accumulation factors for liquid effluent isotopes are provided in Table 1.5. These tables include all isotopes found in Reg Guide 1.109. Some non-routine isotopes and site-specific data were added from studies at Indian Point units 2 and 3, including bioaccumulation factors for Antimony, Silver, Cesium, and Niobium.

Indian Point 2 Page 4 Revision 9

ODCM Part II - Calculational Methodologies TABLE 1-1

SUMMARY

OF LIQUID RECS DOSE RATE RECS The diluted concentration of each isotope in UNRESTRICTED AREAS is limited to the Maximum Permissible Concentration identified per RECS Section DA.1. The diluted concentration of dissolved or entrained noble gases are limited to 2E-4 uCi/ml.

DOSE RECS Dose commitment to any member of public in UNRESTRICTED AREAS'is limited to:

1 )

In any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ.

2)

In a calendar year, 3 mrem to the total body and 10 mrem to any organ.

PROJECTIONS Projection of liquid doses shall be computed at least every 31 days, as follows:

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

If projected doses would exceed the limits in the RECS:

0.06 mrem total body, or 0.2 mrem critical organ, clean-up treatment systems are required to be operational.

Indian Point 2 Page 5 Revision 9

ODCM Part II - Calculational Methodologies.

TABLE 1-2 Page 1 of 2 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTO____E__BO__E__LIVER___TOT___BODY___TYROID____KIDNEY____LUNG_____-LL____

ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 BE-7 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-58 CO-60 NI-63 NI-65 CU-64 ZN-65 ZN-69 BR-83 BR-84 BR-85 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-90 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M TC-101 RU-103 RU-105 RU-106 AG-llOM SB-122 SB-124 SB-125 0.OOE+00 3.29E-0l 4.08E+02 4.96E+07 0.OOE+00 0.OOE+00 0.OOE+00 3.21E+04 5.06E+04 0.OOE+00 0.OOE+00 4.97E+04 2.02E+02 O.OOE+00 1.61E+05 3.43E+02 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 2.57E+04 6.32E+05 4.72E+02 1.79E+02 6.07E+00 5.73E-02 8.89E+01 5.33E-01 1.69E+00 1.63E+00 9.00E-02 4.83E+00

0. OOE+00 1.59E-02 1.64E-02

1. lOE+02 9.16E+00 1.64E+03 4.58E+02 3.47E+0l 4.86E+02 3.11E+02 2.82E-0l 7.45E-0l 4.08E+02 3.08E+06

0. OOE+00 5.43E+03 1.37E+02 2.21E+04

1. 19E+05 S. 15E+02 1.48E+03 3.45E+03 2.62E+01 9.08E+01 5.13E+05 6.57E+02 O.OOE+00 O.OOE+00 O.OOE+00 l.O1E+05 2.91E+02 1.93E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 5.22E-0l 1.82E-02 2.69E+00 1.28E+02 4.50E-02 2.36E-02

0. OOE+00

0. OOE+00 4.23E+02 7.99E-01 9.20E+00 3.47E+00 2.82E-0l 3.69E-01 4.08E+02

1. 92E+06 4.31E+00

1. 04E+03 2.42E+0l 5.16E+03 4.56E+04

1. 15E+03 3.26E+03 1.67E+03 1.20E+0l 4.26E+01 2.32E+05 4.57E+01 4.05E+01 5.25E+01 2.16E+00 4.72E+04 1.54E+02 1.35E+02 7.37E+02 1.55E+05

1. 91E+0l 7.75E+00 1.63E-0l 2.22E-03 2.38E+00 1.56E-02 4.67E-02 3.54E-0l 8.3OE-03 1.44E+00 2.43E+0l 5.73E-0l 2.32E-0l 4.74E+0l 3.62E+00 2.07E+02 2.51E+02 1.20E+0l

1. 91E+02 7.40E+0l 2.82E-01

0. OOE+00 4.08E+02 0.OOE+00 2.58E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.38E-01 1.18E+00 3.16E-01 2.82E-01 7.83E-0l 4.08E+02 0.OOE+00 9.50E-01

1. 61E+03 1.73E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00 2.29E+02 3.43E+05 4.27E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.20E-0l 2.74E-02 2.6SE+00 2.90E+02 6.84E-0l 4.25E-0l 4.20E+02

1. 18E+02 3.16E+03 8.32E+02 O.OOE+00 0.OOE+00 O.OOE+00 2.82E-0l O.OOE+00 4.08E+02 O.OOE+00 5.72E+00 O.OOE+00 O.OOE+00 1.24E+04 3.32E+04 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 2.21E-02 1.21E-02 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00

2. 08E+0l 3.79E+02 2.4OE+02 2.82E-0l 1.28E+02 4.08E+02 5.57E+06 1.08E+03 1.66E+04 4.36E+03 1.27E+04 3.96E+05 1.04E+04 2.78E+04 7.19E+02 6.65E+02 7.74E+03 3.23E+05 9.87E+01 5.84E+01 4.13E-04 O.OOE+00 2.OOE+04 4.02E-09 1.12E-ll 4.12E+03 1.82E+04 2.25E+03 3.55E+03 6.43E+04 1.68E-0l 4.89E+04 9.33E+03 5.36E+04 1.66E+03 5.63E+03 1.63E+04 2.97E+02 2.66E+0l 7.09E-14 1.28E+04 5.60E+03

1. 06E+05

1. 73E+05 1.32E+04 1.38E+04 3.42E+03 Indian Point 2 Page 6 Revision 9

ODCM Part 11 - Calculational Methodologies TABLE 1-2 Page 2 of 2 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml

___O__O_____BO_____LIVER___TOT___BODY___THYROID____KID____Y__LUNG_____-LLI___

ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.72E+03 TE-127M 6.88E+03 TE-127 1.12E+02 TE-129M 1.17E+04 TE-129 3.19E+01 TE-131M 1.76E+03 TE-131 2.OOE+01 TE-132 2.56E+03 I-130 4.88E+01 I-131 2.68E+02 I-132 1.31E+01 I-133 9.16E+01 I-134 6.84E+00 I-135 2.86E+01 CS-134 4.14E+04 CS-136 4.33E+03 CS-137 5.30E+04 CS-138 3.67E+01 BA-139 6.47E+00 BA-140 1.35E+03 BA-141 3.14E+00 BA-142 1.42E+00 LA-140 1.58E+00 LA-142 8.07E-02 CE-141 3.23E+00 CE-143 5.69E-01 CE-144 1.68E+02 PR-143 5.80E+00 PR-144 1.90E-02 ND-147 3.97E+00 W-187 2.98E+02 NP-239 3.53E-02 K-40 0.OOE+00 CO-57 0.00E+00 SR-85 0.OOE+00 Y-88 0.OOE+00 NB-94 0.OOE+00 NB-97 4.05E-02 CD-109 0.00E+00 SN-113 0.00E+00 BA-133 0.00E+00 TE-134 3.29E+01 CE-139 0.OOE+00 HG-203 0.OOE+00 9.87E+02 2.46E+03 4.01E+01 4.36E+03 1.20E+01 8.60E+02 8.36E+00 1.66E+03 1.44E+02 3.84E+02 3.50E+01 1.59E+02 1.86E+01 7.48E+01 9.84E+04

1. 71E+04 7.25E+04 7.25E+01 4.61E-03 1.70E+00 2.37E-03 1.46E-03 7.95E-01 3.67E-02 2.18E+00 4.21E+02 7.04E+01 2.33E+00 7.88E-03 4.59E+00 2.49E+02 3.47E-03

0. OOE+00 1.21E+02 0.00E+00 0.OOE+00 0.OOE+00 1.02E-02 0.OOE+00 0.OOE+00 0.OOE+00 2.15E+01 0.OOE+00 0.OOE+00 3.65E+02 8.38E+02 2.42E+01 1.85E+03 7.77E+00 7.16E+02 6.32E+00 1.55E+03 5.68E+01 2.20E+02 1.23E+01 4.86E+01 6.64E+00 2.76E+01 8.04E+04 1.23E+04 4.75E+04 3.59E+01 1.89E-01 8.87E+01 1.06E-01 8.93E-02 2.10E-01 9.15E-03 2.48E-01 4.66E-02 9.04E+00 2.88E-01 9.65E-04 2.74E-01 8.71E+01

1. 91E-03 0.OOE+00

2. 01E+02

0. OOE+00 0.OOE+00 0.OOE+00 3.74E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.32E+01 0.00E+00 0.OOE+00 8.19E+02 1.76E+03 8.28E+01 4.01E+03 2.45E+01 1.36E+03 1.65E+01

1. 83E+03 1.22E+04 1.26E+05 1.23E+03 2.34E+04 3.22E+02 4.93E+03

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 2.88E+01

0. OOE+00

1. 1lE+04 2.79E+04 4.55E+02 4.88E+04 1.34E+02 8.71E+03 8.77E+01 1.60E+04 2.24E+02 6.58E+02 5.58E+01 2.78E+02 2.95E+01 1.20E+02 3.18E+04 9.51E+03 2.46E+04 5.33E+01 4.31E-03 5.78E-01 2.21E-03 1.23E-03 0.OOE+00 0.OOE+00 1.01E+00 1.85E-01 4.17E+01 1.34E+00 4.45E-03 2.68E+00 0.OOE+00 1.08E-02

0. OOE+00

0. OOE+00 O.OOE+00 0.OOE+00 1.20E-02 0.OOE+00 0.OOE+00 0.OOE+00

2. 08E+02

0. OOE+00

0. OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 1.06E+04 1.30E+03 8.18E+03 5.26E+00 2.61E-03 9.73E-01 1.35E-03 8.27E-04

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.09E+04 2.31E+04 8.82E+03 5.88E+04 2.41E+01 8.53E+04 2.83E+00 7.83E+04 1.24E+02 1.01E+02 6.58E+00 1.43E+02 1.62E-02 8.45E+01

1. 72E+03 1.94E+03 1.4OE+03 3.09E-04

1. 15E+01 2.79E+03 1.48E-09 2.OOE-18 5.83E+04 2.68E+02 8.35E+03 1.57E+04 5.69E+04 2.54E+04 2.73E-09 2.20E+04 8.16E+04 7.12E+02 0.OOE+00 3.07E+03 0.OOE+00 0.OOE+00 0.OOE+00 3.78E+01 0.OOE+00 0.OOE+00 0.OOE+00 3.65E-02

0. OOE+00 O.OOE+00 Indian Point 2 Page 7 Revision 9

ODCM Part 11 - Calculational Methodologies.

TABLE 1-3 Page 1 of 2 Site Related Teen 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 2.17E-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 O.OOE+00 8.50E-01 O.OOE+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 5.40E+07 3.35E+06 2.09E+06 O.OOE+00 O.OOE+00 O.OOE+00 4.54E+06 CR-51 O.OOE+00 O.OOE+00 4.44E+00 2.47E+00 9.73E-01 6.34E+00 7.46E+02 MN-54 O.OOE+00 5.33E+03 1.06E+03 O.OOE+00 1.59E+03 O.OOE+00 1.09E+04 MN-56 O.OOE+00 1.43E+02 2.54E+01 O.OOE+00 1.81E+02 O.OOE+00 9.40E+03 FE-55 3.35E+04 2.37E+04 5.54E+03 O.OOE+00 O.OOE+00 1.51E+04 1.03E+04 FE-59 5.20E+04 1.21E+05 4.69E+04 O.OOE+00 O.OOE+00 3.83E+04 2.87E+05 CO-58 O.OOE+00 5.10E+02 1.18E+03 O.OOE+00 O.OOE+00 O.OOE+00 7.04E+03 CO-60 O.OOE+00 1.48E+03 3.32E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.92E+04 NI-63 5.15E+04 3.64E+03 1.75E+03 0.00E+00 0.00E+00 0.OOE+00 5.79E+02 NI-65 2.18E+02 2.79E+01 1.27E+01 0.00E+00 0.00E+00 0.00E+00 1.51E+03 CU-64 0.00E+00 9.53E+01 4.48E+01 0.00E+00 2.41E+02 0.00E+00 7.39E+03 ZN-65 1.46E+05 5.07E+05 2.36E+05 0.00E+00 3.24E+05 0.OOE+00 2.15E+05 ZN-69 3.73E+02 7.10E+02 4.97E+01 0.OOE+00 4.64E+02 0.00E+00 1.31E+03 BR-83 0.00E+00 0.00E+00 4.41E+01 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 BR-84 0.00E+00 0.OOE+00 5.55E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-85 0.00E+00 0.00E+00 2.34E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 RB-86 0.00E+00 1.09E+05 5.12E+04 0.OOE+00 0.00E+00 0.00E+00 1.61E+04 RB-88 0.00E+00 3.12E+02 1.66E+02 0.OOE+00 0.00E+00 0.00E+00 2.67E-05 RB-89 0.OOE+00 2.01E+02 1.42E+02 0.00E+00 0.OOE+00 0.OOE+00 3.09E-07 SR-89 2.79E+04 0.00E+00 8.00E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.33E+03 SR-90 5.27E+05 0.00E+00 1.30E+05 0.OOE+00 0.OOE+00 0.00E+00 1.48E+04 SR-91 5.12E+02 0.00E+00 2.04E+01 0.OOE+00 0.00E+00 0.00E+00 2.32E+03 SR-92 1.94E+02 0.OOE+00 8.25E+00 0.00E+00 0.00E+00 0.00E+00 4.93E+03 Y-90 6.57E+00 0.00E+00 1.77E-01 0.00E+00 0.OOE+00 0.00E+00 5.42E+04 Y-91M 6.18E-02 0.OOE+00 2.36E-03 0.OOE+00 0.00E+00 0.00E+00 2.92E+00 Y-91 9.64E+01 0.00E+00 2.58E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.95E+04 Y-92 5.80E-01 0.00E+00 1.68E-02 0.00E+00 0.00E+00 0.OOE+00 1.59E+04 Y-93 1.84E+00 0.00E+00 5.03E-02 0.00E+00 0.00E+00 0.00E+00 5.61E+04 ZR-95 1.68E+00 5.29E-01 3.64E-01 0.00E+00 7.78E-01 0.00E+00 1.22E+03 ZR-97 9.65E-02 1.91E-02 8.80E-03 0.00E+00 2.90E-02 0.00E+00 5.17E+03 NB-95 4.86E+00 2.70E+00 1.48E+00 0.00E+00 2.61E+00 0.00E+00 1.15E+04 MO-99 0.OOE+00 1.36E+02 2.60E+01 0.00E+00 3.12E+02 0.00E+00 2.44E+02 TC-99M 1.63E-02 4.55E-02 5.89E-01 0.00E+00 6.77E-01 2.52E-02 2.98E+01 TC-101 1.77E-02 2.51E-02 2.47E-01 0.00E+00 4.55E-01 1.53E-02 4.30E-09 RU-103 1.15E+02 0.OOE+00 4.93E+01 0.00E+00 4.06E+02 0.OOE+00 9.63E+03 RU-105 9.85E+00 0.OOE+00 3.82E+00 0.00E+00 1.24E+02 0.00E+00 7.96E+03 RU-106 1.77E+03 0.00E+00 2.23E+02 0.OOE+00 3.42E+03 0.00E+00 8.50E+04 AG-llOM 4.45E+02 4.22E+02 2.56E+02 0.OOE+00 8.04E+02 0.00E+00 1.18E+05 SB-122 4.35E+01 8.47E-01 1.27E+01 5.53E-01 0.OOE+00 2.72E+01 9.13E+03 SB-124 5.09E+02 9.40E+00 1.99E+02 1.16E+00 0.OOE+00 4.45E+02 1.03E+04 SB-125 3.27E+02 3.58E+00 7.64E+01 3.11E-01 0.OOE+00 2.85E+02 2.53E+03 Indian Point 2 Page 8 Revision 9

ODCM Part 11 - Calculational Methodologies TABLE 1-3 Page 2 of 2 Site Related Teen Ingestion Dose Cozzitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TE-125M 2.96E+03 TE-127M 7.48E+03 TE-127 1.22E+02 TE-129M 1.26E+04 TE-129 3.47E+01 TE-131M 1.89E+03 TE-131 2.16E+01 TE-132 2.70E+03 I-130 5.06E+01 I-131 2.87E+02 I-132 1.37E+01 I-133 9.87E+01 I-134 7.17E+00 I-135 2.99E+01 CS-134 4.24E+04 CS-136 4.35E+03 CS-137 5.67E+04 CS-138 3.93E+01 BA-139 7.05E+00 BA-140 1.44E+03 BA-141 3.40E+00 BA-142 1.52E+00 LA-140 1.67E+00 LA-142 8.58E-02 CE-141 3.49E+00 CE-143 6.16E-01 CE-144 1.82E+02 PR-143 6.28E+00 PR-144 2.06E-02 ND-147 4.50E+00 W-187 3.22E+02 NP-239 3.98E-02 K-40 0.OOE+00 CO-57 O.OOE+00 SR-85 0.OOE+00 Y-88 0.00E+00 NB-94 0.OOE+00 NB-97 4.36E-02 CD-109 0.OOE+00 SN-113 0.OOE+00 BA-133 0.OOE+00 TE-134 3.46E+01 CE-139 0.OOE+00 HG-203 0.OOE+00

1. 07E+03 2.65E+03 4.33E+01 4.68E+03 1.29E+01 9.06E+02 8.90E+00

1. 71E+03 1.46E+02 4.02E+02 3.58E+01 1.67E+02

1. 90E+01 7.71E+01 9.97E+04 1.71E+04 7.54E+04 7.54E+01 4.96E-03

1. 76E+00 2.54E-03 1.52E-03 8.20E-01

3. 81E-02 2.33E+00 4.48E+02 7.55E+01 2.51E+00 8.44E-03 4.89E+00 2.62E+02 3.75E-03 0.OOE+00 1.25E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.08E-02

0. OOE+00 0.OOE+00 0.OOE+00 2.22E+01 0.OOE+00 0.OOE+00 TOT BODY THYROID KIDNEY LUNG GI-LLI 3.96E+02 8.28E+02 0.OOE+00 0.OOE+00 8.75E+0:

8.90E+02 1.78E+03 3.03E+04 0.OOE+00 1.87E+0O 2.63E+01 8.44E+01 4.95E+02 0.00E+00 9.44E+0:

2.OOE+03 4.07E+03 5.28E+04 0.OOE+00 4.74E+0O 8.44E+00 2.48E+01 1.46E+02 0.OOE+00 1.90E+0; 7.55E+02 1.36E+03 9.44E+03 0.OOE+00 7.27E+0i 6.75E+00 1.66E+01 9.44E+01 0.OOE+00 1.77E+0O 1.61E+03 1.80E+03 1.64E+04 0.OOE+00 5.42E+04 5.84E+01 1.19E+04 2.25E+02 0.OOE+00 1.12E+0; 2.16E+02 1.17E+05 6.92E+02 0.OOE+00 7.95E+0:

1.29E+01 1.21E+03 5.64E+01 0.OOE+00 1.56E+0:

5.11E+01 2.34E+04 2.94E+02 0.OOE+00 1.27E+0; 6.82E+00 3.17E+02 2.99E+01 0.OOE+00 2.50E-0:

2.86E+01 4.96E+03 1.22E+02 0.OOE+00 8.54E+0:

4.63E+04 0.OOE+00 3.17E+04 1.21E+04 1.24E+0-1.15E+04 0.OOE+00 9.32E+03 1.47E+03 1.38E+0-2.63E+04 0.OOE+00 2.57E+04 9.97E+03 1.07E+0-3.77E+01 0.OOE+00 5.57E+01 6.48E+00 3.42E-0O 2.05E-01 0.00E+00 4.67E-03 3.42E-03 6.28E+01 9.28E+01 0.OOE+00 5.98E-01 1.19E+00 2.22E+03 1.14E-01 0.OOE+00 2.36E-03 1.74E-03 7.25E-Of 9.33E-02 0.OOE+00 1.28E-03 1.01E-03 4.65E-1l 2.18E-01 0.OOE+00 0.OOE+00 0.OOE+00 4.71E+04 9.49E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.16E+03 2.67E-01 0.00E+00 1.10E+00 0.OOE+00 6.66E+03 5.01E-02 0.OOE+00 2.01E-01 0.OOE+00 1.35E+04 9.80E+00 0.OOE+00 4.51E+01 0.OOE+00 4.59E+04 3.13E-01 0.OOE+00 1.46E+00 0.OOE+00 2.07E+04 1.05E-03 0.OOE+00 4.84E-03 0.OOE+00 2.27E-0!

2.93E-01 0.OOE+00 2.87E+00 0.OOE+00 1.76E+04 9.19E+01 0.OOE+00 0.OOE+00 0.OOE+00 7.10E+04 2.08E-03 0.OOE+00 1.18E-02 0.OOE+00 6.03E+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 2.10E+02 0.OOE+00 0.OOE+00 0.OOE+00 2.33E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0C 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0C 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.95E-03 0.OOE+00 1.27E-02 0.OOE+00 2.58E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0C 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+OC 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+OC 2.32E+01 2.84E+01 2.12E+02 0.OOE+00 1.28E+OC 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OC 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OC 3

3 2

I D

2 L

L a

L L

L Indian Point 2 Page 9 Revision 9

ODCM Part 11-Calculational Methodologies.

TABLE 1-4 Page 1 of 2 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE_____BONE___LIVER___TOT___BODY___THYROID____KIDNEY____LUNG_____--L____

ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 BE-7 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-58 CO-60 NI-63 NI-65 CU-64 ZN-65 ZN-69 BR-83 BR-84 BR-85 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-90 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M TC-101 RU-103 RU-105 RU-106 AG-110M SB-122 SB-124 SB-125 0.OOE+00 4.77E-01 4.57E+02 6.98E+07 0.OOE+00 0.OOE+00 0.OOE+00 4.55E+04 6.53E+04 0.OOE+00

0. OOE+00 6.85E+04 2.83E+02

0. OOE+00 1.55E+05 4.94E+02 0.OOE+00

0. OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 3.63E+04 4.68E+05 6.60E+02 2.48E+02 8.79E+00 8.17E-02 1.29E+02 7.70E-01 2.44E+00 2.10E+00 1.27E-01 5.75E+00 0.OOE+00 1.99E-02 2.3OE-02 1.48E+02 1.30E+01 2.36E+03 5.24E+02 5.80E+01 6.55E+02 4.22E+02 1.81E-01 8.08E-01 4.57E+02 3.27E+06 0.OOE+00 4.20E+03 1.31E+02 2.42E+04 1.06E+0S 4.20E+02 1.23E+03 3.67E+03 2.66E+01

9. 05E+01 4.12E+OS

7. 14E+02 0.OOE+00

0. OOE+00 0.OOE+00 1.06E+05 3.OOE+02

1. 85E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.62E-01 1.83E-02 2.24E+00 1.31E+02 3.89E-02 2.41E-02 0.OOE+00 0.OOE+00 0.OOE+00 3.54E+02 8.56E-0l 8.50E+00 3.25E+00 1.81E-01 5.33E-01 4.57E+02 2.69E+06 4.86E+00 1.12E+03 2.96E+01 7.48E+03 5.27E+04 1.29E+03 3.64E+03 2.33E+03 1.55E+01 5.47E+01 2.56E+05 6.60E+01 5.67E+01 6.56E+01 3.02E+00 6.50E+04 2.08E+02 1.64E+02 1.04E+03 l.19E+05 2.49E+01 9.96E+00 2.35E-01 2.97E-03 3.44E+00 2.20E-02 6.69E-02 4.11E-01 1.08E-02 1.60E+00 3.23E+01 6.46E-01 3.06E-01 5.67E+01 4.73E+00

2. 95E+02 2.83E+02 1.70E+01 2.29E+02

8. 85E+01 1.81E-01

0. OOE+00 4.57E+02

0. OOE+00 2.70E+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 O.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.43E-01 1.44E+00 3.91E-01 1.81E-01 7.96E-01 4.57E+02 0.OOE+00 7.37E-01 1.18E+03 1.59E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.19E+02 2.59E+05 4.33E+02 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.62E-01 2.63E-02

2. 10E+00 2.79E+02 5.66E-01 4.11E-01 3.72E+02 1.15E+02 3.19E+03 6.59E+02

0. OOE+00

0. OOE+00 0.OOE+00

1. 81E-Ol

0. OOE+00 4.57E+02

0. OOE+00 4.92E+00

0. OOE+00

0. OOE+00 1.37E+04 3.07E+04

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 1.98E-02 1.27E-02

0. 0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.36E+01 3.63E+02 2.35E+02 1.81E-01 4.52E+01 4.57E+02

1. 93E+06 2.58E+02 3.53E+03 1.90E+04 4.47E+03 1.10E+05 2.45E+03 6.84E+03 2.47E+02 3.26E+03 4.25E+03 7.23E+04 4.50E+04 0.0OE+00 0.OOE+00 0.0OE+00 6.80E+03 1.47E+01 1.61E+00 1.41E+03 6.3OE+03 1.46E+03 4.70E+03 2.50E+04 1.60E+02 1.71E+04 2.22E+04 3.63E+04 4.82E+02 2.77E+03 4.14E+03 1.08E+02 2.22E+01 7.66E-02 3.82E+03 8.50E+03 3.68E+04 4.21E+04 4.46E+03 4.09E+03 1.01E+03 Indian Point 2 Page 10 Revision 9

ODCM Part 11 - Calculational Methodologies TABLE 1-4 Page 2 of 2 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTO________ON____LIVER___TOT___BO__Y__TYROID_____IDNEY____LUNG_____-LL____

ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 3.81E+03 TE-127M 9.67E+03 TE-127 1.58E+02 TE-129M 1.63E+04 TE-129 4.48E+01 TE-131M 2.41E+03 TE-131 2.78E+01 TE-132 3.38E+03 I-130 6.28E+01 1-131 3.70E+02 I-132 1.72E+01 I-133 1.27E+02 I-134 9.02E+00 I-135 3.77E+01 CS-134 5.15E+04 CS-136 5.17E+03 CS-137 7.19E+04 CS-138 5.01E+01 BA-139 9.34E+00 BA-140 1.87E+03 BA-141 4.51E+00 BA-142 1.97E+00 LA-140 2.16E+00 LA-142 1.12E-01 CE-141 4.65E+00 CE-143 8.19E-01 CE-144 2.44E+02 PR-143 8.40E+00 PR-144 2.76E-02 ND-147 5.96E+00 W-187 4.08E+02 NP-239 5.15E-02 K-40 O.OOE+00 CO-57 0.OOE+00 SR-85 0.OOE+00 Y-88 0.OOE+00 NB-94 0.OOE+00 NB-97 5.55E-02 CD-109 0.OOE+00 SN-113 0.OOE+00 BA-133 0.OOE+00 TE-134 4.31E+01 CE-139 0.OOE+00 HG-203 0.OOE+00 1.03E+03 2.60E+03 4.25E+01 4.55E+03 1.25E+01 8.33E+02 8.46E+00 1.50E+03 1.27E+02 3.72E+02 3.16E+01 1.58E+02 1.67E+01 6.78E+01 8.44E+04 1.42E+04 6.88E+04 6.97E+01 4.99E-03 1.64E+00 2.53E-03 1.42E-03 7.55E-01 3.57E-02 2.32E+00 4.44E+02 7.64E+01 2.52E+00 8.53E-03 4.83E+00 2.42E+02 3.70E-03 0.OOE+00

1. 15E+02 0.OOE+00

0. OOE+00 0.OOE+00 1.OOE-02

0. OOE+00

0. OOE+00 0.OOE+00

1. 94E+01 0.OOE+00 0.OOE+00 5.08E+02 1.15E+03 3.38E+01 2.53E+03 1.06E+01 8.86E+02 8.26E+00 1.81E+03 6.54E+01 2.12E+02 1.45E+01 5.96E+01 7.70E+00 3.21E+01

1. 78E+04 9.19E+03

1. 02E+04 4.42E+01 2.71E-01

1. 09E+02 1.47E-01 1.10E-01 2.54E-01 1.12E-02 3.45E-01 6.44E-02 1.3OE+01 4.17E-01 1.39E-03 3.74E-01 1.08E+02 2.60E-03 0.OOE+00 2.33E+02 0.OOE+00

0. OOE+00 0.OOE+00 4.68E-03 O.OOE+00 o.OOE+00 0.OOE+00 2.59E+01

0. OOE+00 0.OOE+00 1.07E+03 2.31E+03 1.09E+02 5.25E+03 3.20E+01

1. 71E+03 2.12E+01 2.18E+03 1.40E+04 1.23E+05 1.47E+03 2.93E+04 3.85E+02 6.OOE+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 o.OOE+00

0. OOE+00 3.41E+01 0.OOE+00 0.OOE+00 o.OOE+00 2.76E+04 4.48E+02 4.78E+04 1.31E+02 8.06E+03 8.40E+01 1.39E+04 1.90E+02 6.11E+02 4.84E+01 2.63E+02 2.56E+01

1. 04E+02 2.62E+04 7.56E+03 2.24E+04 4.90E+01 4.35E-03 5.35E-01 2.19E-03 1.15E-03 0.OOE+00 0.OOE+00 1.02E+00 1.86E-01 4.23E+01 1.37E+00 4.51E-03 2.65E+00 0.OOE+00 1.07E-02 O.OOE+00 0.OOE+00 O.OOE+00

0. OOE+00 0.OOE+00 1.llE-02 O.OOE+00 0.OOE+00 0.OOE+00 1.80E+02 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 9.39E+03 1.13E+03 8.07E+03 5.28E+00 2.93E-03 9.79E-01 1.48E-02 8.35E-04 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 3.68E+03 7.83E+03 6.15E+03 l.99E+04 2.79E+03 3.38E+04 1.46E+02 1.51E+04 5.94E+01 3.31E+01 3.72E+01 6.35E+01 l.llE+01 5.16E+01 4.55E+02 4.99E+02 4.31E+02 3.21E+01 5.39E+02 9.50E+02 2.57E+00 2.57E-02 2.10E+04 7.08E+03 2.90E+03 6.51E+03 l.99E+04 9.06E+03 1.84E+01 7.65E+03 3.40E+04 2.74E+02 0.OOE+00 9.43E+02 0.OOE+00 0.OOE+00

0. OOE+00 3.09E+03 0.OOE+00 0.OOE+00 0.OOE+00

1. 97E+02 0.OOE+00 0.OOE+00 Indian Point 2 Page 1 1 Revision 9

ODCM Part 11 - Calculational Methodologies TABLE 1-5 Bio-Accumulation Factors for Liquid Effluent Isotopes (pCi/kg per pCi/liter)

Freshwater Saltwater ISOTOPE Fish Invertebrates BFi BEi Freshwater Saltwater ISOTOPE Fish Invertebrates BFi BIi H-3 BE-7 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-s9 CO-58 CO-60 NI-63 NI-65 CU-64 ZN-65 ZN-69 BR-83 BR-84 BR-85 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-90 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M TC-101 RU-103 RU-105 RU-106 AG-llOM SB-122 SB-124 SB-125 9.00OE-01 2.000E+00 1.OOOE+02 1.OOOE+05 2.000E+02 4.000E+02 4.000E+02 1.000E+02 1.000E+02 5.000E+01 5.000E+01 1.000E+02 1.000E+02 5.OOOE+01 2.000E+03 2.000E+03 4.200E+02 4.200E+02 4.200E+02 2.000E+03

2. 000E+03

2. OOOE+03 3.OOOE+01 3.000E+01 3.000E+01 3.000E+01 2.500E+01 2.500E+01 2.500E+01 2.500E+01 2.500E+01 3.300E+00 3.300E+00 3.OOOE+02 1.OOOE+01 1.500E+01

1. 500E+01

1. OOOE+01

1. OOOE+01 1.000E+01 2.300E+00

1. OOOE+00

1. OOOE+00 9.300E-01

2. OOOE+02 1.900E-01

3. OOOE+04

2. OOOE+03

4. OOOE+02

2. OOOE+04

2. OOOE+04 1.OOOE+03 1.OOOE+03 2.500E+02 2.500E+02

1. 700E+03 S. OOOE+04 S. OOOE+04

3. 100E+00 3.100E+00 3.100E+00

1. 700E+01

2. OOOE+01

2. OOOE+01 1.000E+03

1. 000E+03

1. OOOE+03 1.OOOE+03 1.OOOE+03

8. 000E+01

8. 000E+01 1.OOOE+02

1. OOOE+01

5. OOOE+01

5. 000E+01 1.OOOE+03 1.000E+03 1.OOOE+03 5.OOOE+03 3.OOOE+02 3.000E+02

3. 000E+02 TE-125M TE-127M TE-127 TE-129M TE-129 TE-131M TE-131 TE-132 I-130 I-131 I-132 I-133 I-134 I-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239 K-40 CO-57 SR-85 Y-88 NB-94 NB-97 CD-109 SN-113 BA-133 TE-134 CE-139 HG-203 4.OOOE+02 4.OOOE+02 4.000E+02 4.000E+02 4.OOOE+02 4.OOOE+02 4.OOOE+02 4.OOOE+02 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 2.240E+02 2.240E+02 2.240E+02 2.240E+02 4.OOOE+00

4. OOOE+00

4. OOOE+00 2.500E+01 2.500E+01 1.000E+00

1. OOOE+00

1. OOOE+00 2.500E+01 2.sOOE+01 2.500E+01 1.200E+03 1.000E+01

0. 000E+00 5.000E+01

0. 000E+00

3. 000E+02 3.000E+02 0.OOOE+00 0.OOOE+00 0.000E+00 4.000E+02 0.000E+00 0.OOOE+00 1.000E+02 1.000E+02 1.OOOE+02

1. 000E+02

1. OOOE+02

1. OOOE+02 S. OOOE+01

5. OOOE+01 5.000E+01 5.OOOE+01

5. OOOE+01

5. OOOE+01 2.240E+02 2.240E+02 2.240E+02 2.240E+02 1.OOOE+02 1.OOOE+02 1.OOOE+02 1.000E+02 1.000E+03 1.OOOE+03 6.OOOE+02 6.OOOE+02 6.OOOE+02 1.000E+03 1.000E+03 1.000E+03

3. OOOE+01 1.OOOE+01 0.OOOE+00 1.OOOE+03 0.000E+00 0.000E+00

1. 000E+02 1.OOOE+02 0.OOOE+00

0. OOOE+00

1. OOOE+02

0. OOOE+00

0. OOOE+00 Bio-Accumulation Factors and DFi's for Noble Gases = 0 Indian Point 2 Page 12 Revision 9

ODCM Part 11 - Calculational Methodologies All releases (including batch) are considered "long term" in relation to the definitiorl in NUREG 0133 because they total greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months and are sufficiently random. However, if short-term releases occur, the appropriate short-term dispersion factor should be utilized.

Such factors can be derived from the cited calculation in unit 3's ODCM or taken from another appropriate reference. The impact of short-term releases is considered simultaneously with all other releases with regard to setpoint selection and dose or dose rate computations.

Normally, releases of noble gases are the most limiting with regard to approaching site limits.

For this reason and because it is considered impractical to apply trip points and alarms to integrating monitors sensitive to radioiodines and particulates, radiation monitor trip points for release points are based on the noble gas component of gaseous effluents.

Because the particulate and iodine contribution to receptor dose equivalents is historically very low, and full analytical results from associated radiochemical analyses require months to complete, releases are administratively controlled from noble gas values. Typically, the ratio of noble gas to iodine is greater than 10,000. The ratio is conservatively reduced to 100 when applied to the design basis accident scenario for IPEC to ensure Iodine is conservatively modeled in accident calculations after a SG Tube Rupture. Despite this modeling used to justify administratively using noble gas setpoints for control, actual calculations are performed in detail after-the-fact, per the ODCM, in the case of any actual Iodine or particulate releases.

The RECS require a dose projection at least once per 31 days to determine the need for use of the cleanup systems. Although most of these systems are in service at all times, cleanup systems such as iodine removal charcoal beds or gas tank holdup would be required if the 31-day dose projection approached the associated limits in the RECS. Proximity to these limits can be evaluated at any time from the use of a database tracking system for I OCFR50 doses to date.

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 CO2 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 C02 form (26%).

Though the methodologies for calculating doses for noble gases, iodines and particulates allow for accurate dose modeling with any type of mixture, it is beneficial to back-calculate release rates (uCi/sec) for use in Operations procedures with a standard conservative mix.

Mixtures established in Table 2-8, and methodology demonstrated in Appendix I were used to derive annual, quarterly, and instantaneous release rate setpoints shown is Section 4.2.

Table 2-1 is a compilation of gaseous RECS dose and dose rate criteria. The dose rate criteria are used in radiation monitor setpoint calculations in Appendix I. The integrated dose limits are applied in the database tracking mechanism for 10CFR50 compliance.

Tables 2-2 through 2-12 are listings of dose factors, descriptions of various release mixtures, distances to the site boundary and nearest residence, and other data required to calculate doses in the following sections.

Indian Point 2 Page 14 Revision 9

ODCM Part II - Calculational Methodologies 2.2 Determination of Releases from Indirectly Monitored Sources The effluents from the Blowdown Flash Tank Vent and the Secondary Purification System Vent are not directly monitored. This section describes appropriate methodology for determining release rates from these vents. The methodology is based on NUREG-0133 Section 5.6.3. Usually, only H-3 and potentially 1-131 and 1-133 are of interest.

A determination of the iodine releases via a flash tank can be made by calculating the iodine content in secondary water and using the following equation:

q = CRf (1-SO)

(release rate from tank vent in ACi/sec)

Where:

C e iodine concentration in secondary coolant water (ijtCiml) averaged over a time not in excess of one week R

letdown rate to the tank (ml/sec) f e

The fraction of liquid flashed in the tank as determined by a heat balance taken around the tank at the applicable reactor power level SQ e measured steam quality, or an assumed value of 0.85, at the vent Appendix D provides guidance on the calculation of f. C and R are process variables and SQ is assumed to be 0.85 in the absence of a measurement.

2.3 Noble Gas Releases Dose Rates for Total Body and Skin The following is the calculational method for determining instantaneous noble gas dose rates to the total body and skin. According to approved maximum-individual methodology, all releases use the annual average meteorological constants, unless a ground level or short-term release is identified. Maximum total body and skin dose rates are assumed to occur in the critical receptor (highest dose). Ground level X/Q values are used for Condenser Air Ejector releases.

The total body dose rate from noble gas releases is:

DRTB = (X/Q) Y KN q (G-1) i and the skin dose rate from noble gas releases is:

DRSKIN = 1.1 (X/Q) F Miq1+ (X/Q) F Lqi (G-2)

Where:

DRTB total body dose rate from noble gas releases (mremlyr)

Indian Point 2 Page 15 Revision 9

ODCM Part II - Calculational Methodologies.

DRSKIN skin dose rate from noble gas releases (mremlyr)

(X/Q) highest of 16 sectors site boundary annual average relative concentration (sec/m 3) whole body dose transfer factor for nuclide i (mrem/yr per gCVm3) [from RG 1.109]

L4-beta skin dose transfer factor for nuclide i (mrem/yr per AC~m

3) [from RG 1.109]

ml air dose transfer factor for gamma emissions of nuclide i (mrad/yr per lCVrm3) [from RG 1.109]

1.1 conversion from gamma air dose rate to tissue dose equivalent rate (mrem/mrad) qe release rate of nuclide i (pCisec) qt total release rate of all noble gas nuclides, (IiCisec)

From an evaluation of past releases, a simplification introduced in Section 2.1 can be adopted for total body dose rate calculations. If the appropriate long-term distribution of q (the total releases of noble gases) is known, then it follows that there is some weighted factor which, multiplied by q, yields the same dose rate computed by using equation G-1.

DRTB = (X/Q) Keff qt Where:

Keff

=

Weighted average of all isotopes' K factor per the following general equation:

Kef = (1/q,)

(qj ) (Ki) i=,

Leading to:

DRTB= (X/Q) Kff qt (G-3)

When this type of calculation is performed for Radiation Monitor setpoint calculations, a conservative factor (not to exceed 1.25) may be applied as a final step to reflect maximum expected radiation monitor error. Simply multiply the final Dose Rate by the chosen factor.

Kf is normally calculated with each release. For setpoint calculations, a back-calculation (similar to that of Appendix 1), is performed with an expected Keff such that uCi/cc or uCi/sec values can be obtained. Values of K1 and other noble gas dose factors are taken from Tables 2-4 through 2-7 of this section.

Indian Point 2 Page 16 Revision 9

ODCM Part II - Calculational Methodologies 2.4 Determininn the Radioiodine, 8-day Particulate and Tritium Instantaneous Dose Rates from Gaseous Releases Total dose rates for radioiodine, 8-day particulate and tritium releases are calculated for 4 age groups and each organ at the critical site boundary location. Typically, a computer code calculates and reports dose rate for each organ and age group at the highest site boundary location. Although ground plane and milk pathways are also included in the reference source (NUREG-01 33), only the inhalation pathway is applicable to IPEC. The ground plane pathway has been shown to be insignificant, and the land use census identifies no milk pathway at the site boundary. Since it is very unlikely that a milch animal will ever be identified at the site boundary, the terms in NUREG-01 33 for this pathway need not be included routinely, and simply added if the land use census should later include this pathway.

Therefore, the general equation for the single organ dose rate is:

DR

=

(X/Q) F (Pi

q1)

(inhalation only)

(G-4)

Where:

DR

=

single organ total dose rate (mrem/year)

X/Q

=

as previously defined Pi

=

dose parameters for inhalation pathway (mrem/year per pCi/m3) for nuclide i q-release rate of nuclide i (p.Ci/sec)

Computed values of Pi for all age groups, organs, and nuclides for the inhalation pathway are represented in Tables 2-2a through 2-2d in this section. X/Q values may be obtained from Appendix A or other source as allowed in Section 2.1.

Should the land use census be updated to include a the cow-milk pathway, the equation above would be updated as follows:

DRt = [Pi, * (XQ)

qt ] + [Pm, * (X/Q)5

q]

(mrem/year)

(G-5)

Where:

Pi,

=

inhalation dose parameter for all pathways for all organs except bone (bone = 0) in mrem/yr per pCi/m3 Pm,

= milk ingestion dose parameter (bone = 0) in mrem/yr per pCi/M3 X/Q

= as previously defined X/Q5

= highest of 16 sectors 5 mile annual average relative concentration, in sec/ m3 (only used when the 5-mile cow-milk pathway is utilized) q,

=

total Iodine and Particulate, H-3 release rate, in pCi/sec Indian Point 2 Page 17 Revision 9

ODCM Part II - Calculational Methodologies (x/q) = The relative concentration for the unrestricted area boundary for short term releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year or 150 hour0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months s/quarter and NOT sufficiently random as defined in NUREG 0133, Section 3.3).

Mi

= The air dose factor due to gamma emission for each identified noble gas radionuclide in mrad/yr per VCVm3.

Ni

=

The air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per pCVm3.

4i =

The total release of noble gas radionuclides in gaseous effluents, i, for short term releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year or 150 hour0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months s/quarter and NOT random as defined in NUREG 0133, Section 3.3) from all vents, in pCi, over the calendar quarter or year as appropriate.

Qi

= The total release of noble gas radionuclides in gaseous effluents, i, for long term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year or 150 hour0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months s/quarter) from all vents in pCi, 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 Reg Guide 1.109 and are listed in Table 2-6 and 2-7. The M air dose factors are finite cloud corrected.

A single effective gamma air dose rate factor of noble gases can be derived from a known mixture by weighting each isotope's factor (M) and deriving Menf in similar fashion to the earlier expression Kfn:

YMiQ,

_MiQi M

=

i

=

_i E~j Q

Which leads to:

D

=ir gamma (X/Q) * (Meff) *0 (G-9)

Monthly, quarterly, and annual gamma air doses are computed with actual release data (with an appropriately weighted M factor). Doses are also projected for the 31-day dose projection requirements to allow comparison with RECS limits.

Indian Point 2 Page 19 Revision 9

ODCM Part II - Calculational Methodologies 2.6 Beta Air Dose for Noble Gas Releases In similar fashion, the beta air dose from cumulative releases of noble gases can be calculated. The dose for any selected time (month, quarter, year) is:

beta air mrad = 3.17E -8*Ni

[(XIQ)(Q& + (x/q)(qi)]

(G-10)

Where beta air mrad is limited to 10 mrad per quarter and 20 mrad per year, with other terms defined in previous steps.

One can also determine Nef in a similar fashion to Meff:

Neff

=

N1Q1 i

Qt and also write Da. bet = (X/Q)Nff Qt (G-1 1)

Monthly, quarterly, and annual beta air doses are computed with actual release data (with an appropriately weighted N factor). Doses are also projected for the 31-day dose projection requirements to allow comparison with RECS limits.

2.7 Determining the Radioiodines. 8-Day Particulate and Tritium Cumulative Doses from Gaseous Releases 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 animals 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 a critical receptor, identified as the nearest resident with the worst meteorological data. Although the nearest resident is in the ESE direction, the worst sector and most conservative data for dose calculations is in the SSW, per Table 2-9, Appendix I, and Reference 9.

The equations for calculating the dose limitations are obtained from NUREG 0133 and reduce to the following:

During any calendar quarter (3.17E -08)*

(Ri (W Qi + w qi ) must be less than 7.5 mrem (G-12)

Indian Point 2 Page 20 Revision 9

ODCM Part II - Calculational Methodologies During any calendar year:

(3.17 E-08 )*

(Ri(WQi + wqi ) must be less than 15 mrem (G-13)

Where:

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

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

W

= The dispersion or deposition parameter for estimating the dose to an individual at the nearest resident for long term releases.

w

= The vent dispersion or deposition parameter for estimating the dose to an individual at the nearest resident for short term releases.

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 mi2 mrem/yr per giCi/sec, or mrem/yr per tpCi/M3. These dose factors are determined as described the following steps.

Utilizing the assumptions above, these equations for the nearest resident reduce to the following:

DN=(3. 1 7E-8)X[Ri(I)* fWn(in)Qi + wn(in)4i] +(Ri(G)+ Ri(V))* [Wn(dep)Qi + wn(depqiJ] (G-1 4)

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 at the controlling location, in sec/m3.

wn(in) =

The dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area at the controlling location, in sec/m 3, corrected for short term releases.

Indian Point 2 Page 21 Revision 9

ODCM Part II - Calculational Methodologies Ri (V)

=

Vegetation pathway factor for each radionuclide, i.

K'(r)_ * (DFLi)a * [(UaL)JL

e(GIfL) + (UaS)fg

e(-kith) ]

(G-1 7)

Yv(ki +kw)

Where:

K' = 1 E6 pCi/gCi r

= Dimensionless correction factor for the fraction of deposited activity retained on crops for Iodine and Particulate from Table E-15 of Reg Guide 1.109, as follows:

0 0.2 for particulates 1.0 for radioiodine DFLia =

Ingestion dose factors for each nuclide in mrem/pCi (Tables 2-3a thru 2-3d, from Reg Guide 1.109 Tables E-1 1 through E-14).

UaL

=

Consumption rate of fresh leafy vegetation by the receptor in age group (a) in kg/yr (Reg Guide 1.109, Table E-5).

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 (Reg Guide 1.109, Table E-5).

fL

=

The fraction of the annual intake of leafy vegetation grown locally (Reg Guide 1.109, Table E-15).

fg

=

The fraction of the annual intake of non-leafy vegetation grown locally (Reg Guide 1.109, Table E-15).

kw

=

Decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec 1 (corresponding to a 14 day half-life from Reg Guide 1.109, Table E-15).

tL

=

The average time between harvest of leafy vegetation and its consumption in seconds (Reg Guide 1.109, Table E-15).

th

=

The average time between harvest of stored vegetation and its consumption in seconds (Reg Guide 1.109, Table E-15).

Yv =

The vegetation area density in kg/M2 (Reg Guide 1.109, Table E-1 5).

Indian Point 2 Page 23 Revision 9

ODCM Part II - Calculational Methodologies For tritium, the concentration in vegetation is based on airborne concentration rather than deposition. Therefore, for Ri(V) is based on X/Q instead of D/Q:.

RiV (H-3) = K'K'[(UaL)fL+(UaS)fg](DFi)a (0.75)(0.5/H) (mrem/yr per IgCi/m3)

(G-18)

Where:

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

= Absolute humidity of the atmosphere in gm/M 3. This value may be considered as 8 gm/M 3 (NUREG 0133, pg 34) in lieu of site specific information.

0.75 = The fraction of total feed that is water (NUREG 0133, pg 34).

0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water (NUREG 0133, pg 34).

DFia for each age group is given in Tables 2-3a through 2-3d (from Reg Guide 1.109 Tables E-1 1 through E-14).

Ri(l), Ri(V), and Ri(G) values are listed in Tables 2-1Oa-d, 2-1 1a-c, and 2-12.

Ri(V) Parameters:

PARAMETER VALUE Reg Guide 1.109 S ource T able R (dimensionless) 1.0 for radioiodines E-1 5 0.2 for particulates (DFLi) a (mrem/pCi)

Each radionuclide E-1 1 to E-14 UaL (kg/yr) - infant 0

E-5

- child 26 E-5

- teen 42 E-5

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

E-5

- child 520 E-5

- teen 630 E-5

- adult 520 E-5 fL (dimensionless) 1.0 E-15 fg (dimensionless) 0.76 E-1 5 tL (seconds) 8.6E4 (1 day)

E-15 th (seconds) 5.18E6 (60 days)

E-15 Yv (kg/m2) 2.0 E-15 Total organ dose is the sum of all pathway doses, calculated and organ, from all applicable nuclides.

separately for each age group Indian Point 2 Page 24 Revision 9

ODCM Part II - Calculational Methodologies 2.8 Gas Storage Tank Activity Limit NUREG-0133 Section 5.6.1 provides the expression for tank activity in terms of Xe-133 equivalent, assuming no potential tank interconnections:

(500mrem)* 3.15E+7 sec/yr 29.761 Ci (lE6pCi / Ci)(294mrem - m3 / pCi - yr)(1.81E -3 sec/ M3 )

Where; 294 mrem-m 3/pCi-yr = the Xe-1 33 whole body dose factor from Reg Guide 1.109, table B-1 (K).

J 1.81 E-3 sec/M 3

= Design Basis Accident X/Q from Indian Point 2 FSAR 2.8.1 Actual Limits An actual curie limit may be calculated by substituting the actual mixture Kf into the equation above. For example, the Kff for the accident mix computed using Table 14.2-5 of the FSAR is 476 mrem-m3/4Ci-yr. Thus, the actual activity limit (for an expected mixture of radionuclides, not just Xe-1 33) is:

(500nmrem)*

3.15E+7 sec/yr

= 18.300Ci (lE6pCi / Ci)(476 mrem - M3 / pCi - yr)(1.81E-3 sec/ M3)

Similar calculations could be performed with actual Kff and X/Q data.

2.8.2 R-50 Setpoints As demonstrated above, the setpoints calculated from NUREG 0133 modeling assume Xe-1 33 equivalent and no tank interconnections (29,761 Ci of Xe-1 33 equivalent or 18,300 Ci for an expected accident mixture).

However, the tanks are, in fact, generally interconnected, requiring a more conservative approach. The unit 2 FSAR (14.2.3) has established a specific gas decay tank limit of 6000 Ci each. This value is based on the original RECS required 29,761 curies of Xe-1 33 equivalent, divided into 4 large and all 6 small gas decay tanks. Given the actual atmospheric volume of the tanks (525 ft3 for each large and 40 ft3 for each small), the total volume is approximately 4.5 tanks:

29,761 = 6000 Ci Xe -133 Equivalent 4.5 Warn setpoints are established by procedure, usually with consideration for measured tank contents and anticipated release rate.

Indian Point 2 Page 25 Revision 9

ODCM Part II - Calculational Methodologies 2.8.3 Indirect Radiation Monitoring In the event R-50 becomes inoperable, but a depressurized sample can be taken, the quantity limits can still be verified.

Compliance with the appropriate quantity limit is assured if the following inequality holds:

[A]m 14.7 (0)

(14.7 + P)V or

[Aleq 14.7 (0133)

(14.7 + P)V Where:

[Aim total measured depressurized sample concentration (JACi/cc)

[AWeq Xe-133 equivalent measured depressurized sample concentration (.LCi/cc)

V tank volume (cc)

P tank pressure (psig)

Q activity limit for selected mix (pCi)

Q133 dose equivalent Xe-133 activity limit (pCi) 2.8.4 Routine Setooint/Samoling Conservatism In accidental releases of large magnitude (tank failure) it is assumed that the entire tank contents escapes through the rupture point. In some routine releases, the tank pressure decreases to a value around 1 atmosphere (0 psig) so that the tank is never fully voided. The setpoint conservatism vary by a factor, which accounts for incomplete tank emptying, equal to 1+(14.7/P). Note that for lower tank pressures, the conservatism is higher. Procedures may account for this conservatism in establishing specific tank release setpoints.

Indian Point 2 Page 26 Revision 9

ODCM Part II - Calculational Methodologies TABLE 2-1

SUMMARY

OF GASEOUS RECS DOSE RATE RECS At or beyond the SITE BOUNDARY:

500 mrem/yr per site; noble gases, whole body.

3000 mrem/yr per site, noble gases, skin.

1500 mrem/yr per site; iodine-131, tritium, 8 day particulates; any organ.

DOSE RECS Air Dose at the SITE BOUNDARY is limited to:

5 mrad per quarter and 10 mrad per year for noble gases, gamma air dose 10 mrad per quarter and 20 mrad per year for noble gases, beta air dose Maximum Individual Dose to a Member of the Public at the nearest resident is limited to:

7.5 mrem per qtr and 15 mrem per yr for Iodine, H-3, & 8 day particulates to any organ REAL MEMBER OF THE PUBLIC 25 mrem/yr, all sources, whole body or any organ except thyroid.

75 mrem/yr, all sources, thyroid.

PROJECTIONS Projections of airborne doses shall be computed at least every 31 days as follows:

rDose Cur-rent Month Dose+ Previous months'Dose major

[Projection]

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

If projected doses would exceed the limits in the RECS:

0.2 mrad gamma air dose, or 0.4 mrad beta air dose, or 0.3 mrem to any organ at the nearest residence, clean-up treatment systems are required to be operational.

Indian Point 2 Page 27 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-2a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-ll0m Sb-122 Sb-124 Sb-125 0.OOE+00 0.OOE+00 1.28E-06 1.65E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.07E-06 1.47E-06 0.OOE+00 0.OOE+00 5.40E-05

1. 92E-10 0.OOE+00 4.05E-06 4.23E-12 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.80E-05 1.24E-02 7.74E-09 8.43E-10 2.61E-07 3.26E-11 5.78E-05 1.29E-09 1.18E-08 1.34E-05 1.21E-08 1.76E-06 0.OOE+00 1.29E-13 5.22E-15 1.91E-07 9.88E-11 8.64E-06 1.35E-06 0.OOE+00 3.90E-06 6.67E-06 1.58E-07 0.OOE+00 1.28E-06 9.64E-06

0. OOE+00 4.95E-06 1.55E-10 2.12E-06 3.47E-06

1. 98E-07 1.44E-06 3.93E-06 2.62E-11 1.83E-10 1.29E-05 8.14E-12 0.OOE+00 0.OOE+00 0.OOE+00 1.69E-05 4.84E-08 3.20E-08 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.30E-06 2.45E-09 9.77E-07 1.51E-08 3.64E-13 7.52E-15

0. OOE+00

0. OOE+00 0.OOE+00 1.25E-06

0. OOE+00 7.36E-08 7.44E-08 1.58E-07 0.OOE+00 1.28E-06 6.26E-06 1.25E-08 7.87E-07 2.29E-11

4. 93E-07 1.32E-06 2.59E-07

1. 85E-06

1. 81E-06 1.14E-11 7.69E-11 5.82E-06 5.65E-13 3.01E-08 3.91E-08 1.60E-09 7.37E-06 2.41E-08 2.12E-08 1.09E-06 7.62E-04 3.13E-10 3.64E-11

7. 01E-09 1.27E-12 1.55E-06 3.77E-l1 3.26E-10 2.91E-06 1.13E-09 5.26E-07 2.87E-09 4.63E-12 7.38E-14 8.23E-08 3.89E-11 1.09E-06 7.43E-07

0. OOE+00 1.55E-06 1.58E-06 1.58E-07 0.00E+00 1.28E-06

0. 00E+00 7.44E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00

0. 00E+00

0. 00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00

0. 00E+00 9.44E-09 6.75E-09 1.58E-07 0.00E+00 1.28E-06 0.OOE+00 2.85E-09 1.23E-06 1.63E-10 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 5.78E-10 8.62E-06 5.27E-12 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 6.77E-06 3.71E-09 9.67E-07 3.64E-08 5.52E-12 1.35E-13 7.29E-07 1.27E-10 1.67E-05 2.46E-06 0.OOE+00 0.OOE+00 0.00E+00 1.58E-07 0.OOE+00 1.28E-06 0.OOE+00 1.80E-06 1.75E-04 1.18E-06 9.01E-06 1.27E-04

1. 16E-04 7.46E-04 2.23E-05 7.00E-07 8.48E-07 1.08E-04 1.15E-07

0. 00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.75E-04 1.20E-03 4.56E-06 2.06E-06 2.12E-05 2.40E-07 2.13E-04

1. 96E-06 6.06E-06 2.21E-04 9.84E-06 6.31E-05 1.14E-05 9.55E-08 4.99E-08 6.31E-05 1.37E-06 1.17E-03 5.79E-04

0. 00E+00 3.10E-04 2.18E-04 1.58E-07

0. OOE+00 1.28E-06 1.08E-05 4.15E-07 9.67E-06 2.53E-06 7.54E-07 2.35E-05 1.33E-05 3.56E-05 1.67E-06 1.54E-06 6.12E-06 6.68E-06 2.04E-09 2.90E-08

2. 05E-13

0. 00E+00

2. 08E-06 4.18E-19 1.16E-21 4.37E-05 9.02E-05 2.39E-05 5.38E-06 6.32E-05 1.66E-10 4.81E-05 9.19E-06 5.27E-05 1.88E-05 6.54E-05 1.30E-05 3.10E-05 5.20E-07 1.36E-21 1.38E-05 6.02E-06 1.14E-04 3.78E-05 0.00E+00 5.08E-05 1.26E-05 Indian Point 2 Page 28 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-2a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 1-134 1-135 CB-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 4.27E-07 1.58E-06 1.75E-10 1.22E-06 6.22E-12 8.74E-09 1.39E-12 3.25E-08 5.72E-07 3.15E-06 1.45E-07 1.08E-06 8.05E-08 3.35E-07 4.66E-05 4.88E-06 5.98E-05 4.14E-08 1.17E-10 4.88E-06 1.25E-11 3.29E-12 4.30E-08 8.54E-11 2.49E-06 2.33E-08 4.29E-04 1.17E-06 3.76E-12 6.59E-07 1.06E-09 2.87E-08

0. OOE+00 0.OOE+00 4.OOE-06

0. OOE+00 0.OOE+00 2.78E-11

0. 00E+00 8.20E-06 9.50E-06 3.84E-12

0. OOE+00 0.OOE+00 1.98E-07 7.21E-07 8.03E-11 5.84E-07 2.99E-12 5.4SE-09 7.44E-13 2.69E-08 1.68E-06 4.47E-06 4.07E-07

1. 85E-06 2.16E-07

8. 73E-07 1.06E-04 1.83E-05 7.76E-05 7.76E-08 8.32E-14 6.13E-09 9.41E-15 3.38E-15 2.17E-08 3.88E-11 1.69E-06 1.72E-08 1.79E-04 4.69E-07 1.56E-12 7.62E-07 8.8SE-10 2.82E-09

0. OOE+00 8.65E-08

0. OOE+00

0. OOE+00 7.03E-12 4.90E-05 2.70E-07 4.20E-07 3.22E-12 0.OOE+00

0. OOE+00 5.84E-08 1.96E-07 3.87E-11 1.98E-07 1.55E-12 3.63E-09 4.49E-13 2.02E-08 6.60E-07 2.56E-06 1.45E-07 5.65E-07 7.69E-08 3.21E-07 9.10E-05 1.38E-05 5.35E-05 4.05E-08 3.42E-12 3.21E-07 4.20E-13 2.07E-13 5.73E-09 9.65E-12 1.91E-07 1.91E-09 2.3OE-05

5. 80E-08 1.91E-13 4.56E-08 3.10E-10 1.55E-09 0.OOE+00 8.39E-08 9.70E-05 0.OOE+00 0.OOE+00 2.56E-12 1.60E-06 5.60E-07 2.50E-06 1.57E-12 0.OOE+00 0.OOE+00 1.31E-07

4. 11E-07 1.32E-10 4.30E-07 4.87E-12 6.88E-09 1.17E-12 2.37E-08 1.42E-04 1.49E-03 1.43E-05 2.69E-04 3.73E-06 5.60E-05 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. 00E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 1.70E-07 0.OOE+00 3.44E-12 0.OOE+00 0.OOE+00 1.55E-06 5.72E-06 6.37E-10 4.57E-06 2.34E-11 3.86E-08 5.46E-12 1.82E-07 2.61E-06 7.66E-06 6.48E-07 3.23E-06 3.44E-07 1.39E-06 3.59E-05 1.07E-05 2.78E-05 6.OOE-08 7.78E-14 2.09E-09 8.75E-15 2.86E-15 0.OOE+00 0.OOE+00 7.83E-07 7.60E-09 1.06E-04 2.70E-07 8.81E-13 4.45E-07 0.OOE+00 8.75E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.18E-12 4.70E-05 0.OOE+00

2. lOE-09 2.18E-11 0.OOE+00 0.OOE+00 3.92E-05 1.20E-04 8.14E-07 1.45E-04 2.42E-07

1. 82E-05 1.74E-07 3.60E-05 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.22E-05 1.50E-06 9.40E-06 6.07E-09 4.70E-07 1.59E-04 2.42E-07 1.49E-07 1.70E-05 7.91E-07 4.52E-05 9.97E-06 9.72E-04 3.51E-05 1.27E-07 2.76E-05 3.63E-06 4.70E-06

0. OOE+00 4.62E-05

6. OOE-05 0.OOE+00 0.OOE+00 3.OOE-07 9.10E-05 1.20E-04 1.90E-04 4.34E-07 0.OOE+00 0.OOE+00 8.83E-06 1.87E-05 7.17E-06 4.79E-05

1. 96E-08

6. 95E-05 2.30E-09 6.37E-05 9.61E-07 7.85E-07 5.08E-08 1.1lE-06 1.26E-10 6.56E-07 1.30E-06 1.46E-06 1.05E-06 2.33E-13 1.12E-07 2.73E-05 1.45E-17 1.96E-26 5.73E-05 2.64E-07 1.50E-05 2.83E-05 1.02E-04 2.50E-05 2.69E-18 2.16E-05

1. 94E-05 1.49E-05 0.OOE+00

3. 93E-06 7.60E-06 0.OOE+00

0. OOE+00 3.02E-08 8.20E-06 1.50E-06 1.OOE-05 2.97E-11 0.OOE+00

0. OOE+00 Indian Point 2 Page 29 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-2b TEEN INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 0.OOE+00 1.72E-06 2.36E-04 0.OOE+00

0. OOE+00 0.OOE+00 4.18E-06

1. 99E-06 0.OOE+00 0.OOE+00 7.25E-05 2.73E-10 0.OOE+00 4.82E-06 6.04E-12

0. OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.43E-05 1.35E-02 1.10E-08 l.19E-09 3.73E-07 4.63E-ll 8.26E-05 1.84E-09 1.69E-08 1.82E-05 1.72E-08 2.32E-06 0.OOE+00 1.73E-13 7.40E-15 2.63E-07 1.40E-10 1.23E-05 1.73E-06 0.OOE+00 5.38E-06 9.23E-06 1.59E-07 0.OOE+00 1.72E-06 1.37E-05 0.OOE+00 6.39E-06 2.12E-10 2.98E-06 4.62E-06 2.59E-07 1.89E-06 5.43E-06 3.66E-ll 2.54E-10 1.67E-05 1.15E-1l 0.OOE+00 0.OOE+00 0.OOE+00 2.38E-05 6.82E-08 4.40E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.73E-06 3.40E-09 1.29E-06 2.11E-08 4.83E-13 1.05E-14

0. OOE+00 0.OOE+00 0.OOE+00 1.64E-06 0.OOE+00 9.92E-08 1.OlE-07 l.59E-07 0.OOE+00 1.72E-06 8.95E-06 1.69E-08 1.05E-06 3.15E-ll 6.93E-07 1.79E-06 3.47E-07 2.48E-06 2.47E-06 1.59E-ll 1.06E-10 7.80E-06 8.07E-13 4.30E-08 5.41E-08 2.29E-09 1.05E-05 3.40E-08 2.91E-08 1.56E-06 8.35E-04 4.39E-10 5.08E-ll 1.OOE-08 1.77E-12 2.21E-06 5.36E-l1 4.65E-10 3.94E-06 1.57E-09 7.08E-07 4.03E-09 6.24E-12 1.03E-13 1.12E-07 5.42E-11 1.55E-06 9.99E-07 0.OOE+00 2.1OE-06 2.15E-06 1.59E-07 0.OOE+00 1.72E-06

0. OOE+00 9.37E-09

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 1.22E-08 8.80E-09 1.59E-07 0.OOE+00 1.72E-06 0.00E+00 3.84E-09 1.59E-06 2.24E-10 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.01E-10 1.08E-05 7.53E-12

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.42E-06 5.15E-09 1.25E-06 5.14E-08 7.20E-12 1.90E-13 9.29E-07 1.76E-10 2.38E-05 3.13E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.59E-07 0.OOE+00 1.72E-06 0.OOE+00 2.62E-06 2.48E-04 1.90E-06 1.55E-05 1.91E-04 1.68E-04 1.09E-03 3.84E-05 1.17E-06 1.39E-06 1.55E-04 1.98E-07 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 3.02E-04 2.06E-03 7.59E-06 3.43E-06 3.66E-05 4.OOE-07 3.67E-04 3.35E-06 1.04E-05 3.36E-04 1.62E-05 9.39E-05 1.92E-05 1.44E-07 8.34E-08 9.79E-05 2.27E-06 2.01E-03 8.44E-04 0.OOE+00 4.81E-04 3.42E-04 1.59E-07 0.OOE+00 1.72E-06 1.16E-05 3.75E-07 8.35E-06 7.18E-06 7.99E-07 2.23E-05 l.19E-05 3.24E-05 1.77E-06 4.59E-06 7.68E-06 5.83E-06 3.56E-08

0. OOE+00

0. OOE+00 0.OOE+00 2.21E-06 3.65E-15 4.22E-17 4.64E-05 9.56E-05 3.24E-05 1.49E-05 6.99E-05 3.77E-09 5.11E-05 2.06E-05 7.24E-05 1.86E-05 7.88E-05 1.21E-05 3.36E-05 7.66E-07 1.09E-16 1.36E-05 1.13E-05 1.20E-04 3.41E-05 0.OOE+00 4.98E-05 1.24E-05 Indian Point 2 Page 30 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-2b TEEN INHALATION DOSE FACTORS t(mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 1-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 6.10E-07 2.25E-06 2.51E-10 1.74E-06 8.87E-12 1.23E-08 1.97E-12 4.50E-08 7.80E-07 4.43E-06 1.99E-07 1.52E-06 1.11E-07 4.62E-07 6.28E-05 6.44E-06 8.38E-05 5.82E-08 1.67E-10 6.84E-06 1.78E-11 4.62E-12

s. 99E-08 1.20E-10 3.55E-06 3.32E-08 6.11E-04 1.67E-06 5.37E-12 9.83E-07 1.50E-09 4.23E-08 0.OOE+00 O.OOE+00 5.OOE-06 0.OOE+00 O.OOE+00 3.93E-11 0.OOE+00 1.50E-05 4.70E-05 5.31E-12

0. OOE+00

0. OOE+00 2.80E-07 1.02E-06 1.14E-10 8.23E-07 4.22E-12 7.51E-09 1.04E-12 3.63E-08 2.24E-06 6.14E-06 5.47E-07 2.56E-06 2.90E-07 1.18E-06 1.41E-04 2.42E-05 1.06E-04 1.07E-07 1.18E-13 8.38E-09 1.32E-14 4.63E-15 2.95E-08 5.31E-ll 2.37E-06 2.42E-08 2.53E-04 6.64E-07 2.20E-12 1.07E-06 1.22E-09 3.99E-09 0.OOE+00 1.18E-07 O.OOE+00 0.OOE+00 0.OOE+00 9.72E-12 1.00E-04 4.70E-07 8.OOE-07 4.35E-12 0.OOE+00 0.OOE+00 8.34E-08 2.73E-07 5.52E-11 2.81E-07 2.20E-12 5.03E-09 6.3OE-13 2.74E-08 8.96E-07 3.30E-06 1.97E-07 7.78E-07 1.05E-07 4.36E-07 6.86E-05 1.71E-05 3.89E-05 5.58E-08 4.87E-12 4.40E-07 5.93E-13 2.84E-13 7.82E-09 1.32E-11 2.71E-07 2.70E-09 3.28E-05 8.28E-08 2.72E-13 6.41E-08 4.29E-10 2.21E-09 0.OOE+00

1. 15E-07 1.30E-06

0. OOE+00

0. OOE+00 3.55E-12 3.40E-06 9.70E-07 3.30E-06 3.64E-12 0.OOE+00 0.OOE+00 1.75E-07 5.48E-07 1.77E-10 5.72E-07 6.48E-12 9.06E-09 1.55E-12 3.07E-08 1.86E-04 1.83E-03

1. 89E-05 3.65E-04 4.94E-06 7.76E-05 O.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.90E-07 0.OOE+00 4.46E-12 0.OOE+00 0.OOE+00 0.OOE+00 8.17E-06 9.10E-10 6.49E-06 3.32E-11 5.49E-08 7.72E-12 2.44E-07 3.44E-06 1.05E-05 8.65E-07 4.49E-06 4.58E-07 1.86E-06 4.69E-05 1.38E-05 3.80E-05 8.28E-08 1.11E-13 2.85E-09 1.23E-14 3.92E-15 0.OOE+00 0.OOE+00 1.11E-06 1.08E-08 1.51E-04 3.86E-07 1.26E-12 6.28E-07 0.OOE+00 1.25E-08 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 O.OOE+00 1.14E-11 6.70E-05 0.OOE+00 2.80E-09 2.91E-11 0.OOE+00

0. OOE+00 6.70E-05 2.07E-04 1.40E-06 2.47E-04 4.12E-07 2.97E-05 2.92E-07 5.61E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.83E-05 2.22E-06 1.51E-05 9.84E-09 8.08E-07 2.54E-04 4.11E-07 2.39E-07 2.68E-05 1.27E-06 7.67E-05 1.63E-05 1.67E-03 6.04E-05 2.19E-07 4.65E-05 5.92E-06

8. 11E-06

0. OOE+00 7.33E-05 8.80E-05

0. OOE+00 0.OOE+00 4.91E-07

1. 60E-04

2. OOE-04 2.90E-04 6.75E-07

0. OOE+00

0. OOE+00 9.38E-06

1. 99E-05 1.01E-05 5.06E-05 2.02E-07 7.76E-05 1.89E-09 5.79E-05 1.14E-06

8. 11E-07 1.59E-07 1.29E-06 2.55E-09 8.69E-07 1.22E-06 1.36E-06 1.06E-06 3.38E-11 8.06E-07 2.86E-05 9.33E-14 5.99E-20 6.09E-05 1.50E-06 1.58E-05 3.19E-05 1.08E-04 2.67E-05 2.94E-14 2.28E-05 2.21E-05 1.65E-05 0.OOE+00 3.93E-06 6.90E-06 0.OOE+00 0.OOE+00 2.71E-07 8.60E-06 1.50E-06 9.70E-06 1.37E-09 0.OOE+00 0.OOE+00 Indian Point 2 Page 31 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-2c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 0.OOE+00 4.35E-06 7.04E-04

0. OOE+00 0.OOE+00 0.OOE+00 1.28E-05 5.59E-06 0.00E+00 0.OOE+00 2.22E-04 8.08E-10 0.OOE+00 1.15E-05 1.81E-11 0.OOE+00 o.OOE+00

0. OOE+00

0. 00E+00

0. OOE+00

0. OOE+00 1.62E-04 2.73E-02 3.28E-08 3.54E-09 l.11E-06 1.37E-10 2.47E-04 5.50E-09 5.04E-0o 5.13E-05 5.07E-08 6.35E-06 0.OOE+00 4.81E-13 2.19E-14 7.55E-07 4.13E-10 3.68E-05 4.56E-06

0. OOE+00 1.55E-05 2.66E-05 3.04E-07 o.OOE+00 4.35E-06 3.09E-05

0. OOE+00

1. 16E-05 4.48E-10 6.80E-06 9.04E-06 4.79E-07 3.55E-06 1.25E-05 7.99E-11 5.39E-10 3.06E-05 2.61E-11 o.OOE+00 0.OOE+00 0.OOE+00 5.36E-05 1.52E-07 9.33E-08 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. 00E+00 O. OOE+00 1.13E-05 7.34E-09 2.48E-06 4.66E-08 9.41E-13 2.30E-14 0.OOE+00 0.OOE+00 0.OOE+00 3.08E-06

0. OOE+00

2. OOE-07 2.05E-07 3.04E-07 0.OOE+00 4.35E-06 2.67E-05 4.17E-08 2.57E-06 8.43E-ll 2.10E-06 4.51E-06 8.55E-07 6.12E-06 7.56E-06 4.44E-11 2.90E-10 1.90E-05 2.41E-12 1.28E-07 1.48E-07 6.84E-09 3.09E-05 9.90E-08 7.83E-08 4.66E-06 1.74E-03 1.24E-09 1.42E-10 2.99E-08 4.98E-12 6.59E-06 1.57E-10 1.3sE-09 1.00E-05 4.32E-09 1.77E-06 1.15E-08 1.56E-11 2.91E-13 2.90E-07 1.50E-10 4.57E-06 2.47E-06

0. OOE+00 5.41E-06 5.59E-06 3.04E-07 0.OOE+00 4.35E-06 0.OOE+00 2.31E-08 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. 00E+00

0. 00E+00 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00

0. OOE+00

0. 00E+00

0. OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.00E+00 3.41E-08 2.46E-08 3.04E-07 0.OOE+00 4.35E-06 0.OOE+00 6.57E-09 2.71E-06 4.52E-10 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.63E-09 1.93E-05 1.58E-11 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.0OE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 1.61E-05 1.05E-08 2.33E-06 1.06E-07 1.37E-11 3.92E-13 1.90E-06 3.63E-10 4.97E-05 5.74E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.04E-07 0.00E+00 4.35E-06

0. OOE+00 4.59E-06 4.26E-04 3.55E-06 3.OOE-05 3.43E-04 2.99E-04

1. 91E-03 7.43E-05 2.21E-06 2.59E-06 2.69E-04 3.84E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.83E-04 3.99E-03 1.44E-05 6.49E-06 7.07E-05 7.60E-07

7. 1OE-04 6.46E-06 2.01E-05 6.03E-04 3.06E-05 1.66E-04 3.66E-05 2.57E-07 1.58E-07 1.79E-04 4.30E-06 3.87E-03 1.48E-03 0.OOE+00 8.76E-04 6.27E-04 3.04E-07

0. OOE+00 4.35E-06 1.14E-05 2.93E-07 6.19E-06 3.33E-05 7.75E-07 1.91E-05 9.29E-06 2.60E-05 1.71E-06 2.27E-05 9.92E-06 4.41E-06 2.75E-06 0.OOE+00 0.OOE+00 0.OOE+00 2.16E-06 4.66E-09

5. lIE-10 4.52E-05 9.28E-05 4.70E-05 6.55E-05 7.24E-05 4.64E-07 4.97E-05 6.46E-05 1.05E-04 1.65E-05 9.49E-05 1.OOE-05 3.42E-05 1.30E-06 4.41E-09 1.21E-05 2.69E-05 1.16E-04 2.71E-05

0. OOE+00 4.43E-05 1.09E-05 Indian Point 2 Page 32 Revision 9

ODCM Part 11-Calculational Methodologies Table 2-2c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 1.82E-06 6.72E-06 7.49E-10 5.19E-06 2.64E-11 3.63E-08 5.87E-12 1.3OE-07 2.21E-06 1.3OE-05 5.72E-07 4.48E-06 3.17E-07 1.33E-06 1.76E-04 1.76E-05 2.45E-04 1.71E-07 4.98E-10 2.00E-05 5.29E-11 1.35E-11 1.74E-07 3.50E-10 1.06E-05 9.89E-08 1.83E-03 4.99E-06 1.61E-11 2.92E-06 4.41E-09 1.26E-07 0.OOE+00 0.OOE+00 1.20E-05

0. OOE+00 0.OOE+00

1. 16E-10

0. OOE+00 3.80E-05

1. IOE-04 1.53E-11 0.OOE+00 0.OOE+00 6.29E-07 2.31E-06 2.57E-10 1.85E-06 9.45E-12 1.60E-08 2.28E-12 7.36E-08 4.43E-06 1.30E-05 1.10E-06 5.49E-06 5.84E-07 2.36E-06 2.74E-04 4.62E-05 2.23E-04 2.27E-07 2.66E-13 1.75E-08 2.95E-14 9.73E-15 6.08E-08

1. 1lE-10 5.28E-06 5.37E-08 5.72E-04 1.50E-06 4.99E-12 2.36E-06 2.61E-09 9.04E-09 0.OOE+00 2.44E-07 0.OOE+00 0.OOE+00

0. OOE+00 2.08E-11

1. 90E-04

8. 90E-07 1.10E-06 8.81E-12 0.OOE+00

0. OOE+00 2.47E-07 8.16E-07 1.65E-10 8.22E-07 6.44E-12 1.37E-08 1.78E-12 7.12E-08 2.28E-06 7.37E-06 5.07E-07 2.08E-06 2.69E-07 1.12E-06 6.07E-05 3.14E-05 3.47E-05

1. 50E-07 1.45E-11 1.17E-06 1.72E-12 7.54E-13 2.04E-08 3.49E-11 7.83E-07 7.77E-09 9.77E-05 2.47E-07 8.10E-13 1.84E-07 1.17E-09 6.35E-09 0.OOE+00 2.88E-07 3.20E-06 0.OOE+00 0.OOE+00 9.73E-12 8.OOE-06 2.30E-06 1.00E-05 9.40E-12 0.OOE+00 0.OOE+00 5.20E-07 1.64E-06 5.30E-10 1.71E-06 1.93E-l1 2.64E-08 4.59E-12 8.58E-08 4.99E-04 4.39E-03 5.23E-05 1.04E-03 1.37E-05 2.14E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.10E-07 0.00E+00 1.24E-11

0. 00E+00 0.00E+00

0. 00E+00

1. 72E-05 l.91E-09 1.36E-05 6.94E-11 1.08E-07 1.59E-11 4.79E-07 6.61E-06 2.13E-05 1.69E-06 9.13E-06 8.92E-07 3.62E-06 8.93E-05 2.58E-05 7.63E-05 1.68E-07 2.33E-13 5.71E-09 2.56E-14 7.87E-15 0.00E+00 0.00E+00 2.31E-06 2.26E-08 3.17E-04 8.11E-07 2.64E-12 1.30E-06 0.00E+00 2.63E-08

0. 00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 2.31E-11 1.70E-04 0.00E+00 5.40E-09 5.71E-11 0.00E+00 0.00E+00 1.29E-04 4.00E-04 2.71E-06 4.76E-04 7.93E-07 5.56E-05 5.55E-07 1.02E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.27E-05 3.93E-06

2. 81E-05 1.84E-08

1. 56E-06 4.71E-04 7.89E-07 4.44E-07 4.94E-05 2.35E-06 1.47E-04 3.12E-05 3.23E-03 1.17E-04 4.23E-07 8.87E-05 1.1lE-05 1.57E-05 0.00E+00 1.37E-04 1.50E-04 0.00E+00 0.OOE+00 9.24E-07 3.OOE-04 3.60E-04 5.20E-04 1.23E-06

0. 00E+00

0. 00E+00 9.13E-06 1.93E-05 1.52E-05 4.91E-05 6.89E-06 8.32E-05 3.60E-07 3.72E-05 1.38E-06 7.68E-07 8.65E-07 1.48E-06 2.58E-07 1.20E-06 1.04E-06 1.13E-06 9.78E-07 7.29E-08 1.56E-05 2.75E-05 7.44E-08 7.41E-10 6.10E-05 2.05E-05 1.53E-OS 3.44E-05 1.05E-04 2.63E-05 5.32E-08 2.22E-05 2.46E-05 1.73E-05 0.00E+00

3. 58E-06 5.50E-06 0.00E+00 0.OOE+00 7.51E-06

8. IOE-06 1.30E-06 8.30E-06 4.87E-07 0.00E+00 0.00E+00 Indian Point 2 Page 33 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-2d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-ll0m Sb-122 Sb-124 Sb-125 0.OOE+00

0. OOE+00 7.54E-06 1.45E-03 0.OOE+00

0. OOE+00 0.OOE+00 1.41E-05 9.69E-06 0.OOE+00 0.OOE+00 2.42E-04 1.71E-09 0.OOE+00 1.38E-05 3.85E-11

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.84E-04 2.92E-02 6.83E-08 7.50E-09 2.35E-06 2.91E-10 4.20E-04 1.17E-08 1.07E-07 8.24E-05 1.07E-07 1.12E-05 0.OOE+00 9.98E-13 4.65E-14 1.44E-06 8.74E-10 6.20E-05 7.13E-06 0.OOE+00 2.71E-05 3.69E-05 4.62E-07 0.OOE+00 7.54E-06 8.03E-05 0.OOE+00 1.81E-05 1.10E-09 8.39E-06 1.68E-05 8.71E-07 5.73E-06 1.46E-05 2.03E-10 1.34E-09 4.47E-05 6.91E-ll 0.OOE+00 0.OOE+00 0.OOE+00 1.36E-04 3.98E-07 2.29E-07 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 1.99E-05 1.83E-08 4.59E-06 1.18E-07 2.06E-12 S. 88E-14 0.OOE+00

0. OOE+00

0. OOE+00 5.16E-06 0.OOE+00 3.97E-07 3.41E-07 4.62E-07 0.OOE+00 7.54E-06 5.53E-05 6.39E-08 3.56E-06 1.58E-10 2.38E-06 6.77E-06 1.3OE-06 8.41E-06 8.29E-06 8.79E-11 5.53E-10 2.22E-05 5.13E-12 2.72E-07 2.86E-07 1.46E-08 6.30E-05 2.05E-07 1.47E-07 8.15E-06 1.85E-03 2.47E-09 2.79E-10 6.3OE-08 9.90E-12 1.12E-05 3.29E-10 2.91E-09 1.45E-05 8.36E-09 2.70E-06 2.31E-08 2.66E-l1 5.80E-13 4.85E-07 2.93E-10 7.77E-06 3.57E-06

0. OOE+00 8.56E-06 7.78E-06 4.62E-07 0.OOE+00 7.54E-06

0. OOE+00 4.11E-08 0.OOE+00 0.OOE+00

0. OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.18E-08 4.45E-08 4.62E-07

0. OOE+00 7.54E-06 0.OOE+00 9.45E-09 3.56E-06 7.86E-10 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 2.84E-09 2.32E-05 2.87E-11 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 2.22E-05

1. 85E-08 3.37E-06

1. 89E-07 2.22E-1l 6.99E-13 3.03E-06 6.42E-10 7.61E-05 7.80E-06 0.OOE+00

0. OOE+00

0. OOE+00 4.62E-07 0.OOE+00 7.54E-06 0.00E+00 9.17E-06 7.14E-04 8.95E-06 6.21E-05 7.25E-04 5.55E-04 3.22E-03 1.49E-04 5.80E-06 6.64E-06 4.62E-04 1.05E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.45E-03 8.03E-03 3.76E-05 1.70E-05 1.92E-04 l.99E-06 1.75E-03 1.75E-05 s.46E-05 1.25E-03 7.88E-05 3.42E-04 9.63E-05 5.79E-07 4.17E-07 3.94E-04 1.12E-05 8.26E-03 2.62E-03 0.OOE+00 1.89E-03 1.17E-03 4.62E-07

0. OOE+00 7.54E-06 1.15E-05 2.55E-07 5.04E-06 5.12E-05 7.82E-07 1.77E-05 7.95E-06 2.28E-05 1.73E-06 3.58E-05 1.07E-05 3.67E-05 9.44E-06 0.OOE+00 0.OOE+00

0. OOE+00 2.17E-06 2.42E-07 4.87E-08 4.57E-05 9.36E-05 5.24E-05 1.OOE-04 7.43E-05 1.68E-06 5.02E-05 9.04E-05 1.19E-04 1.55E-05 1.00E-04 9.05E-06 3.48E-05 1.45E-06 6.03E-07 1.15E-05 3.46E-05 1.17E-04 2.36E-05 0 OOE+00 4.22E-05 1.05E-05 Indian Point 2 Page 34 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-2d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 3.40E-06 l.19E-05 1.59E-05 1.01E-05 5.63E-11 7.62E-08 1.24E-11 2.66E-07 4.54E-06 2.71E-05 1.21E-06 9.46E-06 6.58E-07 2.76E-06 2.83E-04 3.45E-05 3.92E-04 3.61E-07 1.06E-09 4.OOE-05

1. 12E-10 2.84E-11 3.61E-07 7.36E-10 1.98E-05 2.09E-07 2.28E-03 1.OOE-05 3.42E-11 5.67E-06 9.26E-09 2.65E-07 0.OOE+00 0.OOE+00 2.70E-05 0.OOE+00 0.OOE+00 2.44E-10 0.OOE+00

6. OOE-05

1. 90E-04 3.18E-11 0.OOE+00 0.OOE+00 1.42E-06 4.93E-06 6.81E-10 4.35E-06 2.48E-l1 3.93E-08 5.87E-12 1.69E-07 9.91E-06 3.17E-05 2.53E-06 1.37E-05 1.34E-06 5.43E-06 5.02E-04 9.61E-05 4.37E-04 5.58E-07 7.03E-13 4.OOE-08 7.70E-14 2.36E-14 1.43E-07 2.69E-10 1.19E-05 1.38E-07 8.65E-04 3.74E-06 1.32E-11 5.81E-06 6.44E-09 2.37E-08 0.OOE+00 4.65E-07

0. OOE+00 0.OOE+00 0.OOE+00 5.21E-ll 2.60E-04 1.60E-06 1.70E-06 2.04E-11

0. OOE+00 0.OOE+00 4.70E-07 1.48E-06 3.49E-10 1.59E-06 1.34E-11 2.59E-08 3.57E-12 1.26E-07 3.98E-06 1.40E-05 8.99E-07 4.OOE-06 4.75E-07 1.98E-06 5.32E-05 3.78E-05 3.25E-05 2.84E-07 3.07E-11 2.07E-06 3.55E-12 1.40E-12 3.68E-08 6.46E-11 1.42E-06 1.58E-08 1.26E-04 4.99E-07 1.72E-12 3.57E-07 2.23E-09 1.34E-08 0.OOE+00 4.58E-07 5.40E-06 0.OOE+00 0.OOE+00 1.88E-11 1.OOE-05 3.60E-06 1.30E-05 1.68E-11 0.OOE+00 0.OOE+00 1.16E-06 3.48E-06 1.32E-09 3.91E-06 4.82E-ll 6.38E-08 1.13E-11 1.99E-07 1.14E-03 1.06E-02 1.21E-04 2.54E-03 3.18E-05 4.97E-04

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.00E+00 0.00E+00

0. OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00

0. 00E+00

0. OOE+00 o.00E+00 0.00E+00

0. OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.30E-06

0. 00E+00 2.91E-l1 0.00E+00

0. 00E+00 0.OOE+00 2.68E-05 3.47E-09 2.27E-05 1.25E-10 1.89E-07 2.85E-11 7.39E-07 1.09E-05 3.70E-05 2.82E-06 1.60E-05 1.49E-06 6.05E-06 1.36E-04 4.03E-05 1.23E-04 2.93E-07 4.23E-13 9.59E-09 4.64E-14 1.36E-14

0. 00E+00 0.00E+00 3.75E-06 4.03E-08 3.84E-04 1.41E-06 4.80E-12 2.25E-06 0.00E+00 4.73E-08 0.OOE+00 0.OOE+00

0. 00E+00 0.00E+00 0.000E+0 4.07E-11 2.00E-04 0.OOE+00 8.90E-09 9.59E-ll 0.OOE+00 0.OOE+00 3.19E-04 9.37E-04 7.39E-06 1.20E-03 2.14E-06 1.42E-04 1.47E-06 2.43E-04 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 5.69E-05 8.40E-06 5.09E-05 4.67E-08 4.25E-06 1.14E-03 2.12E-06

1. lIE-06 1.20E-04 5.87E-06 3.69E-04 8.30E-05 7.03E-03 3.09E-04 1.15E-06 2.30E-04 2.83E-05 4.25E-05 0.00E+00 2.71E-04 3.OOE-04 0.00E+00 0.00E+00 2.37E-06 6.20E-04

7. 80E-04 9.10E-04 2.93E-06 0.OOE+00 0.00E+00 9.22E-06 1.95E-05 1.74E-05 4.93E-05 1.88E-05 8.51E-05 5.87E-06 3.15E-05 1.42E-06 7.56E-07 1.36E-06 1.54E-06 9.21E-07 1.31E-06 9.53E-07 1.02E-06 9.53E-07 6.26E-07 3.64E-0s 2.74E-OS 3.39E-06 4.95E-07 6.06E-Os 4.25E-05 1.54E-05 3.55E-05 1.06E-04 2.66E-OS 3.06E-06 2.23E-05 2.54E-05 1.78E-os 0.OOE+00 3.47E-06 4.80E-06 0.00E+00 0.00E+00 1.92E-05 8.00E-06 1.20E-06 7.70E-06 2.53E-06 0.OOE+00 0.00E+00 Indian Point 2 Page 35 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-2e 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)

H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 12.350 53.300 15.000 14.290 27.704 312.500 2.578 2.700 44.529 70.800 5.271 96.000 2.520 12.701 243.900 0.950 2.390 0.530 0.050 18.660 0.297 0.253 50.500 29.120 9.500 2.710 2.667 0.829 58.510 3.540 10.100 63.980 16.900 35.150 2.750 6.020 0.237 39.280 4.440 368.200 249.900 2.700 60.200 2.770 y

D H

D D

D H

y D

D y

y H

H D

H H

D H

H D

Y H

H D

H H

D H

D D

H H

D H

D D

y 1.OOE-02 1.OOE-04

4. OOE-02 2.50E-02 2.20E-03 2.50E-04 2.50E-04 1.20E-03 1.20E-03 1.OOE-03 1.0OE-03 6.70E-03 6.70E-03 1.40E-02 3.90E-02 3.90E-02

5. OOE-02 5.00E-02 5.00E-02 3.OOE-02 3.OOE-02 3.OOE-02 8.OOE-04 8.OOE-04 8.OOE-04 8.OOE-04 1.OOE-05 1.OOE-05 1.OOE-05 1.OOE-05 1.OOE-05 5.00E-06 5.00E-06 2.50E-03 7.50E-03 2.50E-02 2.50E-02 1.OOE-06 1.OOE-06 1.OOE-06 S.OOE-02 1.50E-03 1.50E-03 1.50E-03

0. OOE+00

0. OOE+OO 2.50E-08

0. OOE+00 2.20E-10 5.80E-o9

1. lOE-08

0. OOE+00 8.OOE-09 7.OOE-09 1.70E-08 O.OOE+OO 3.70E-09 1.50E-09 4.OOE-09 O.OOE+00 6.40E-11 1.2OE-08 O.OOE+OO 6.30E-10 3.50E-09 1.50E-08 5.60E-13 O.OOE+0O 7.10E-09

9. OOE-09 2.20E-12 3.80E-09 2.40E-11 1.60E-09 5.70E-10 5.OOE-09

5. 50E-09 5.10E-09 1.90E-09 9.60E-10 2.70E-09 3.60E-09 4.50E-09 1.50E-o9 1.80E-08 O. OOE+00 1.30E-08

3. lOE-09 O. OOE+00 O. OOE+00 2.90E-08 O.OOE+OO

,2.60E-10 6.80E-09 1.30E-08 O.OOE+O0 9.40E-09 8.20E-09 2.OOE-08 O.OOE+00 4.30E-09 1.70E-09 4.60E-09

0. OOE+00 9.30E-l1 1.40E-08 O.OOE+OO 7.20E-10 4.OOE-09 1.80E-08 6.50E-13 O. OOE+OO 8.30E-09 1.OOE-08 2.60E-12 4.40E-09 2.70E-11 1.90E-09 7.80E-10 5.80E-09 6.40E-09 6.OOE-09 2.20E-09 1.1OE-09 3.OOE-09 4.20E-09 5.10E-09 1.80E-09

2. 1OE-08

0. OOE+0O 1.50E-08 3.50E-09 Indian Point 2 Page 36 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-2e 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)

Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 1-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 58.000 109.000 9.350 33.600 1.160 30.000 0.417 3.258 12.360 8.040 2.300 20.800 0.877 6.610 2.062 13.100 30.000 0.537 1.378 12.740 0.304 0.177 1.678 1.542 32.501 33.000 284.300 13.560 0.288 10.980 23.900 2.360 1.28E+09 270.900 64.840 106.640 2.03E+04 1.202 1.271 115.100 10.740 0.697 137.660 46.600 D

D H

H H

D H

H H

H y

D y

H H

D H

H D

D H

D y

D D

D y

H y

D y

H D

D 1.OOE-03

1. OOE-03 1.OOE-03

1. OOE-03

1. OOE-03 1.OOE-03 1.OOE-03 1.OOE-03 6.OOE-03 6.OOE-03 6.OOE-03 6.OOE-03 6.OOE-03 6.OOE-03 1.20E-02 1.20E-02 1.20E-02 1.20E-02 4.OOE-04 4.OOE-04 4.OOE-04 4.OOE-04 5.OOE-06 5.OOE-06 1.OOE-04 1.OOE-04 1.OOE-04 5.OOE-06

5. OOE-06 5.OOE-06 5.OOE-04 5.00E-06 1.OOE-02 1.OOE-03 8.OOE-04 1.OOE-05 2.50E-03 2.50E-03 1.20E-04 2.50E-03 4.OOE-04 1.OOE-03 1.OOE-04 3.80E-02 3.50E-11 1.1OE-12 1.OOE-11 7.70E-10 7.10E-10 8.40E-09 2.20E-09 1.70E-09 1.40E-08 2.80E-09 1.70E-08 3.70E-09 1.60E-08 1.20E-08 1.20E-08 1.50E-08 4.20E-09 2.10E-08 2.40E-09 2.10E-09 4.30E-09 7.90E-09 1.50E-08 1.50E-08 5.50E-10 2.20E-09 3.20E-10

0. OOE+00 2.OOE-10 1.OOE-09 3.10E-09 9.50E-10

0. OOE+00

9. 1OE-10

0. OOE+00 O.OOE+00

0. OOE+00 4.60E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.OOE-09 O.OOE+00 O.OOE+00 4.80E-11 1.30E-12 1.lOE-11 9.ODE-10 8.40E-10 9.90E-09 2.60E-06 2.OOE-09 1.70E-08 3.40E-09 2.OOE-08 4.50E-09 1.90E-08 1.40E-08 1.40E-08 1.70E-08 4.90E-09 2.40E-08 2.70E-09 2.40E-09 4.90E-09

9. OOE-09 1.70E-08 1.80E-08 6.20E-10 2.50E-09 3.70E-10 O.OOE+00 2.30E-10 1.2OE-09 3.60E-09 1.1OE-09 O.OOE+00 1.OOE-09 O.OOE+00

0. OOE+00

0. OOE+00 5.40E-09

0. OOE+00

0. OOE+O0 1.20E-09

0. OOE+00 O.OOE+O0 Indian Point 2 Page 37 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 2.77E-09 1.70E-06 1.93E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.75E-06 4.34E-06 0.OOE+00 0.OOE+00 1.30E-04 5.28E-07 0.OOE+00 4.84E-06 1.03E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 3.08E-04 7.58E-03 5.67E-06 2.15E-06 9.62E-09 9.09E-11 1.41E-07 8.45E-10

2. 68E-09 3.04E-08 1.68E-09 6.22E-09 0.OOE+00 2.47E-10 2.54E-10

1. 85E-07 1.54E-08 2.75E-06 1.60E-07

2. OOE-07 2.80E-06

1. 79E-06 1.05E-07 6.26E-09 1.70E-06 1.20E-05 0.OOE+00 4.57E-06 1.15E-07 1.90E-06 1.02E-05 7.45E-07 2.14E-06 9.01E-06 6.86E-08 8.33E-08 1.54E-05 1.97E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.11E-05 6.05E-08 4.01E-08 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 O.OOE+00 9.75E-09 3.39E-10 3.46E-09 4.31E-06 6.98E-10 3.66E-10 0.OOE+00

0. OOE+00 0.OOE+00 1.48E-07 4.60E-09 5.30E-08 2.OOE-08 1.05E-07 3.10E-09 1.70E-06 7.46E-06 2.66E-09 8.72E-07 2.04E-08 4.43E-07 3.91E-06 1.67E-06 4.72E-06 4.36E-06 3.13E-08 3.91E-08 6.96E-06 1.37E-09 4.02E-08 5.21E-08 2.14E-09 9.83E-06 3.21E-08 2.82E-08 8.84E-06 1.86E-03 2.29E-07 9.3OE-08 2.58E-10 3.52E-12 3.77E-09 2.47E-11 7.40E-11 6.60E-09 1.55E-10 1.86E-09 8.20E-07 8.89E-09 3.59E-09

7. 97E-08 6.08E-09 3.48E-07 8.79E-08 6.90E-08

1. 1OE-06 4.26E-07 1.05E-07 0.OOE+00 1.70E-06 0.OOE+00 1.59E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. 00E+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00

0. OOE+00

3. 1OE-09

6. 80E-09 1.82E-09 1.05E-07 6.58E-09 1.70E-06 0.OOE+00 5.86E-10 1.36E-06 1.46E-07 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 2.10E-07 1.03E-05 1.28E-08

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.53E-08 5.12E-10 3.42E-09 9.76E-06 1.06E-08 6.59E-09 7.06E-07

1. 99E-07 5.31E-06 2.91E-07 0.OOE+00

0. OOE+00

0. OOE+00 1.05E-07 0.00E+00 1.70E-06 0.OOE+00 3.53E-09 0.OOE+00 0.OOE+00 1.06E-06 2.85E-06

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.42E-10 1.87E-10 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.20E-07 2.18E-06 1.38E-06 1.05E-07 1.08E-06 1.70E-06 2.17E-05 6'.69E-07 1.40E-05 3.67E-06 1.09E-06 3.40E-05 1.51E-05 4.02E-05 1.88E-06 1.74E-06

7. 1OE-06 9.70E-06 2.96E-09 5.79E-08 4.09E-13 0.OOE+00 4.16E-06 8.36E-19 2.33E-21 4.94E-05 2.19E-04 2.70E-05 4.26E-05 1.02E-04 2.67E-10 7.76E-05 1.48E-05 8.50E-05 3.09E-05

1. 05E-04

2. lE-05 9.99E-06 4.13E-07

1. lOE-21 2.16E-05 9.42E-06 1.78E-04 6.04E-05 7.60E-05 7.95E-05

1. 97E-05 Indian Point 2 Page 38 Revision 9

ODCM Part 11-Calculational Methodologies Table 2-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 CB-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 2.68E-06 6.77E-06 1.10E-07 1.15E-05 3.14E-08 1.73E-06

1. 97E-08 2.52E-06 7.56E-07 4.16E-06 2.03E-07 1.42E-06 1.06E-07 4.43E-07 6.22E-05 6.51E-06 7.97E-05 5.52E-08 9.70E-08 2.03E-05 4.71E-08 2.13E-08 2.50E-09 1.28E-10 9.36E-09 1.65E-09 4.88E-07 9.20E-09 3.01E-11 6.29E-09 1.03E-07 1.19E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00 5.22E-11 0.OOE+00 0.OOE+00 0.OOE+00 3.24E-08 0.00E+00 0.OOE+00 9.71E-07 2.42E-06 3.95E-08 4.29E-06

1. 18E-08 8.46E-07 8.23E-09 1.63E-06 2.23E-06 5.95E-06 5.43E-07 2.47E-06 2.88E-07 1.16E-06 1.48E-04 2.57E-05 1.09E-04 1.09E-07 6.91E-11 2.55E-08 3.56E-11 2.19E-11 1.26E-09 5.82E-11 6.33E-09 1.22E-06 2.04E-07 3.69E-09 1.25E-11 7.27E-09 8.61E-08 1.17E-10

0. OOE+00 1.75E-07 0.00E+00

0. OOE+00 0.OOE+00 1.32E-11 0.OOE+00 0.OOE+00 0.OOE+00 2.12E-08

0. OOE+00

0. 00E+00 3.59E-07 8.25E-07 2.38E-08 1.82E-06 7.65E-09 7.05E-07 6.22E-09 1.53E-06

8. 80E-07 3.41E-06 1.90E-07 7.53E-07 1.03E-07 4.28E-07 1.21E-04 1.85E-05 7.14E-05 5.4OE-08 2.84E-09 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.45E-11 7.18E-10 1.35E-10 2.62E-08 4.56E-10 1.53E-12 4.35E-10 3.01E-08 6.45E-11 0.OOE+00 2.91E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.82E-12 0.OOE+00 0.OOE+00 0.OOE+00 1.30E-08 0.OOE+00

0. OOE+00 8.06E-07 1.73E-06 8.15E-08 3.95E-06 2.41E-08 1.34E-06 1.62E-08 1.80E-06 1.89E-04 1.95E-03 1.90E-05 3.63E-04 4.99E-06 7.65E-05

0. OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00

0. OOE+00 2.83E-08

0. OOE+00 0.OOE+00 1.09E-05 2.75E-05 4.48E-07 4.80E-05 1.32E-07 8.57E-06 8.63E-08 1.57E-05 3.48E-06 1.02E-05 8.65E-07 4.31E-06 4.58E-07 1.86E-06 4.79E-05 1.43E-05 3.70E-05 8.01E-08 6.46E-11 8.67E-09 3.31E-11 1.85E-11 0.OOE+00 0.OOE+00 2.94E-09 5.37E-10 1.21E-07 2.13E-09 7.05E-12 4.25E-09

0. OOE+00 3.65E-10 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.54E-11

0. OOE+00

0. OOE+00 2.05E-07 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 1.59E-05 1.96E-06 1.23E-05 7.91E-09 3.92E-11 1.46E-08 2.02E-11 1.24E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 o.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-08 8.40E-05 2.79E-09 7.71E-05

1. 92E-06 1.57E-06 1.02E-07 2.22E-06 2.51E-10 1.31E-06 2.59E-06 2.92E-06 2.11E-06 4.65E-13 1.72E-07 4.18E-05 2.22E-17 3.OOE-26 9.25E-05 4.25E-07 2.42E-05 4.56E-05 1.65E-04 4.03E-05 4.33E-18 3.49E-05 2.82E-05 2.40E-05

0. OOE+00 4.44E-06 0.OOE+00 0.OOE+00 0.OOE+00 4.87E-08

0. OOE+00 0.OOE+00

0. OOE+00 3.59E-11 0.OOE+00 0.OOE+00 Indian Point 2 Page 39 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 3.96E-09 2.30E-06 2.76E-04 0.OOE+00 O.OOE+00 0.OOE+00 3.78E-06

5. 87E-06

0. OOE+00 0.OOE+00 1.77E-04 7.49E-07 0.OOE+00 5.76E-06 1.47E-08 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 4.40E-04 8.30E-03 8.07E-06 3.05E-06 1.37E-08 1.29E-10 2.01E-07 1.21E-09 3.83E-09 4.12E-08 2.37E-09 8.22E-09

0. OOE+00 3.32E-10 3.60E-10 2.55E-07 2.18E-08 3.92E-06 2.05E-07 3.30E-07 3.86E-06 2.48E-06 1.06E-07 8.87E-09 2.30E-06 1.71E-05 0.OOE+00 5.90E-06 1.58E-07 2.68E-06 1.37E-05 9.72E-07 2.81E-06 1.25E-05 9.57E-08 1.15E-07

2. OOE-05 2.80E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.98E-05 8.52E-08 5.50E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.3OE-08 4.69E-10 4.56E-09 6.03E-06 9.26E-10 5.12E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.94E-07 6.42E-09 7.12E-08 2.71E-08 1.06E-07 4.43E-09 2.3OE-06 1.07E-05 3.60E-09 1.17E-06 2.81E-08 6.25E-07 5.29E-06 2.24E-06 6.33E-06

6. OOE-06 4.36E-08 5.41E-08 9.33E-06 1.96E-09 5.74E-08 7.22E-08 3.05E-09 1.40E-05 4.54E-08 3.89E-08 1.26E-05 2.05E-03 3.21E-07 1.30E-07 3.69E-10 4.93E-12 5.39E-09 3.50E-11 1.OSE-10 8.94E-09 2.16E-10 2.51E-09 1.15E-06 1.20E-08 5.03E-09

1. 09E-07 8.46E-09

4. 94E-07 1.18E-07 9.64E-08 1.51E-06

5. 79E-07 1.06E-07 O.OOE+00 2.30E-06 0.OOE+00

2. OOE-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 4.19E-09 8.79E-09 2.36E-09 1.06E-07 9.40E-09 2.30E-06 0.OOE+00 7.89E-10 1.76E-06 2.OOE-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.91E-07 1.28E-05 1.83E-08 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

1. 91E-08 7.11E-10 4.42E-09 1.38E-05 1.38E-08 9.26E-09 8.99E-07 2.75E-07 7.56E-06 3.70E-07 0.OOE+00 0.OOE+00

0. OOE+00 1.06E-07 0.OOE+00 2.30E-06 0.OOE+00 5.14E-09

0. OOE+00 0.OOE+00 1.70E-06 4.32E-06 0.OOE+00 0.OOE+00

0. OOE+00 0.0OE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.0OE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 5.14E-10 3.12E-10

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.06E-07 3.37E-06 2.16E-06 1.06E-07 1.08E-06 2.30E-06 2.32E-05

6. 05E-07 1.21E-05 1.04E-05 1.16E-06 3.24E-05 1.34E-05 3.66E-05 1.99E-06 5.19E-06 8.92E-06 8.47E-06 5.16E-08 0.OOE+00

0. OOE+00 0.OOE+00 4.41E-06 7.3OE-15 8.43E-17 5.24E-05 2.33E-04 3.66E-05 7.77E-05 1.13E-04 6.09E-09 8.24E-05 3.32E-05 1.17E-04 3.OOE-05 1.27E-04 1.95E-05 1.08E-05 6.08E-07 8.75E-17 2.13E-05

1. 76E-05 1.88E-04 5.45E-05 6.92E-05 7.81E-05 1.92E-05 Indian Point 2 Page 40 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-BS Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 3.83E-06 9.67E-06 1.58E-07 1.63E-05 4.48E-08 2.44E-06 2.79E-08 3.49E-06 1.03E-06 5.85E-06 2.79E-07 2.01E-06 1.46E-07 6.10E-07 8.37E-05 8.59E-06 1.12E-04 7.76E-08 1.39E-07 2.84E-05 6.71E-08 2.99E-08 3.48E-09 1.79E-10 1.33E-08 2.35E-09 6.96E-07 1.31E-08 4.30E-11 9.38E-09 1.46E-07 1.76E-09 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 7.37E-11 0.OOE+00

0. OOE+00 0.OOE+00 4.47E-08 0.OOE+00 0.OOE+00 1.38E-06 3.43E-06 5.60E-08 6.05E-06 1.67E-08 1.17E-06 1.15E-08 2.21E-06 2.98E-06 8.19E-06 7.30E-07 3.41E-06 3.87E-07 1.57E-06

1. 97E-04 3.38E-05 1.49E-04 1.49E-07 9.78E-11 3.48E-08

5. 01E-ll 2.99E-11 1.71E-09 7.95E-11 8.88E-09 1.71E-06 2.88E-07 5.23E-09 1.76E-11 1.02E-08 1.19E-07 1.66E-10 0.OOE+00 2.38E-07 0.OOE+00

0. OOE+00

0. OOE+00 1.83E-11

0. OOE+00 0.OOE+00 0.OOE+00 2.87E-08

0. OOE+00 0.OOE+00 5.12E-07 1.15E-06 3.40E-08 2.58E-06 1.09E-08 9.76E-07 8.72E-09 2.08E-06 1.19E-06 4.40E-06 2.62E-07 1.04E-06 1.39E-07 5.82E-07 9.14E-05 2.27E-05 5.19E-05 7.45E-08 4.05E-09 1.83E-06 2.24E-09 1.84E-09 4.55E-10 1.98E-11 1.02E-09 1.91E-10 3.74E-08 6.52E-10 2.18E-12 6.11E-10 4.17E-08 9.22E-11 0.OOE+00 3.99E-07 0.OOE+00 0.OOE+00 0.OOE+00 6.68E-12

0. OOE+00 0.OOE+00 o.OOE+00 3.OOE-08

0. OOE+00

0. OOE+00 1.07E-06 2.30E-06 1.09E-07 5.26E-06 3.20E-08 1.76E-06 2.15E-08 2.33E-06 2.43E-04 2.39E-03 2.46E-05 4.76E-04 6.45E-06 1.01E-04

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 3.67E-08 0.OOE+00

0. OOE+00 0.OOE+00 3.92E-05 6.40E-07 6.82E-05 1.88E-07 1.22E-05 1.22E-07 2.12E-05 4.59E-06 1.41E-05 1.15E-06 5.98E-06 6.10E-07 2.48E-06 6.26E-05 1.84E-05 5.07E-05 1.10E-07 9.22E-11 1.18E-08 4.65E-11 2.53E-11 0.00E+00 0.00E+00 4.18E-09 7.67E-10 1.72E-07 3.04E-09 1.01E-11 5.99E-09

0. OOE+00 5.21E-10 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.0OE+00 2.14E-11 0.OOE+00 0.OOE+00

0. OOE+00 2.74E-07

0. OOE+00

0. OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 2.39E-05 2.90E-06

1. 97E-05 1.28E-08 6.74E-11 2.34E-08 3.43E-11 1.99E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 O.OOE+00 0.0OE+00 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00

0. OOE+00 O.OOE+00

0. OOE+00 1.13E-05 2.41E-05 1.22E-05 6.12E-05 2.45E-07 9.39E-05 2.29E-09 7.OOE-05 2.29E-06 1.62E-06 3.18E-07 2.58E-06 5.10E-09 1.74E-06 2.45E-06 2.72E-06 2.12E-06 6.76E-11 1.24E-06 4.38E-05 1.43E-13 9.18E-20 9.82E-05 2.42E-06 2.54E-05 5.14E-05 1.75E-04 4.31E-05 4.74E-14 3.68E-05 3.22E-05 2.67E-05 0.OOE+00 4.44E-06 0.OOE+00 0.OOE+00 0.OOE+00 4.37E-07 0.OOE+00

0. OOE+00

0. OOE+00 1.66E-09 0.OOE+00 O.OOE+00 Indian Point 2 Page 41 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-ll0m Sb-122 Sb-124 Sb-125 0.00E+00 1.18E-08 5.80E-06 8.25E-04 0.OOE+00

0. OOE+00 0.OOE+00 1.15E-05

1. 65E-05

0. 00E+00

0. OOE+00 5.38E-04 2.22E-06 0.OOE+00 1.37E-05 4.38E-08 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00

0. 00E+00 1.32E-03 1.70E-02 2.40E-05 9.03E-06

4. lIE-08 3.82E-10 6.02E-07 3.60E-09 1.14E-08 1.16E-07 6.99E-09 2.25E-08 0.OOE+00 9.23E-10

1. 07E-09 7.31E-07 6.45E-08

1. 17E-05 5.39E-07 9.83E-07 1.11E-05

7. 15E-06 2.03E-07

2. 00E-08 5.80E-06 3.86E-05 0.OOE+00 1.07E-05 3.34E-07 6.10E-06 2.67E-05 1.80E-06 5.29E-06 2.88E-05 2.09E-07 2.45E-07 3.65E-05 6.33E-08 0.OOE+00

0. OOE+00 0.OOE+00 6.70E-05 1.90E-07 1.17E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 2.55E-08 1.01E-09 8.76E-09 1.33E-05 1.81E-09 1.12E-09 0.OOE+00 0.OOE+00 0.OOE+00 3.64E-07 1.45E-08 1.44E-07 5.51E-08 2.03E-07 1.32E-08 5.80E-06 3.18E-05 8.90E-09 2.85E-06 7.54E-08 1.89E-06 1.33E-05 5.51E-06 1.56E-05 1.83E-05 1.22E-07 1.48E-07 2.27E-05 5.85E-09 1.71E-07 1.98E-07 9.12E-09 4.12E-05 1.32E-07 1.04E-07 3.77E-05 4.31E-03 9.06E-07 3.62E-07 1.10E-09 1.39E-11 1.61E-08 1.03E-10 3.13E-10 2.27E-08 5.96E-10 6.26E-09 3.29E-06 3.OOE-08 1.42E-08 2.81E-07 2.34E-08 1.46E-06 2.91E-07 2.88E-07 3.88E-06 1.50E-06 2.03E-07 0.OOE+00 5.80E-06 0.OOE+00 4.94E-09 0.OOE+00

0. 00E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. 00E+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.26E-08 2.44E-08 6.63E-09 2.03E-07 1.97E-08 5.80E-06

0. OOE+00 1.35E-09 3.OOE-06 4.04E-07 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 5.92E-07 2.30E-05 3.84E-08 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 3.65E-08 1.45E-09 8.23E-09 2.84E-05 2.63E-08 1.91E-08 1.84E-06 5.67E-07 1.58E-05 6.78E-07 0.00E+00 0.00E+00 0.00E+00 2.03E-07

0. 00E+00 5.80E-06 0.00E+00 9.02E-09 0.00E+00 0.00E+00 3.45E-06 7.74E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00

0. 00E+00

0. OOE+00 0.OOE+00 0.00E+00 0.OOE+00

0. 00E+00 0.00E+00

0. 00E+00

0. OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00

0. OOE+00

0. 00E+00 9.19E-10 5.92E-10 0.00E+00 0.00E+00

0. OOE+00

0. 00E+00 4.00E-07 6.15E-06 3.98E-06 2.03E-07 1.12E-06 5.80E-06 2.28E-05 4'.72E-07

8. 98E-06 4.84E-05 1.13E-06 2.78E-05 1.05E-05 2.93E-05 1.94E-06 2.56E-05 1.15E-05 6.41E-06 3.99E-06 0.OOE+00 0.00E+00 0.00E+00 4.31E-06 9.32E-09 1.02E-09

5. 1IE-05 2.29E-04 5.30E-05 1.71E-04 1.17E-04 7.48E-07 8.02E-05 1.04E-04 1.70E-04 2.66E-05 1.53E-04 1.62E-05

1. IE-05

1. 03E-06 3.56E-09 1.89E-05 4.21E-05 1.82E-04 4.33E-05 7.56E-05 6.93E-05 1.71E-05 Indian Point 2 Page 42 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 1.14E-05 2.89E-05 4.71E-07 4.87E-05 1.34E-07 7.20E-06 8.30E-08 1.01E-05 2.92E-06 1.72E-05 8.00E-07 5.92E-06 4.19E-07 1.75E-06 2.34E-04 2.35E-05 3.27E-04 2.28E-07 4.14E-07 8.31E-05

2. 00E-07 8.74E-08 1.01E-08 5.24E-10 3.97E-08 6.99E-09 2.08E-06 3.93E-08 1.29E-10 2.79E-08 4.29E-07 5.25E-09 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 2.17E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.29E-07 0.OOE+00 0.00E+00 3.09E-06 7.78E-06 1.27E-07 1.36E-05 3.74E-08 2.49E-06 2.53E-08 4.47E-06

5. 90E-06 1.73E-05 1.47E-06 7.32E-06 7.78E-07 3.15E-06 3.84E-04 6.46E-05 3.13E-04 3.17E-07 2.21E-10 7.28E-08 1.12E-10 6.29E-11 3.53E-09 1.67E-10 1.98E-08 3.79E-06 6.52E-07 1.18E-08 3.99E-11 2.26E-08 2.54E-07 3.77E-10 0.00E+00 4.93E-07 0.00E+00 O.OOE+00 0.00E+00 3.92E-11 0.00E+00 0.00E+00 0.00E+00 5.80E-08

0. 00E+00 0.00E+00 1.52E-06 3.43E-06 1.01E-07 7.56E-06 3.18E-08 2.65E-06 2.47E-08 5.40E-06 3.04E-06 9.83E-06 6.76E-07 2.77E-06 3.58E-07 1.49E-06 8.10E-05 4.18E-05 4.62E-05 2.01E-07 1.20E-08 4.85E-06 6.51E-09 4.88E-09 1.19E-09 5.23E-11 2.94E-09 5.49E-10 1.11E-07 1.95E-09 6.49E-12 1.75E-09 1.14E-07 2.65E-10 0.00E+00 9.98E-07 0.00E+00 0.00E+00

0. 00E+00 1.83E-11 0.00E+00 0.00E+00 0.00E+00 7.74E-08 0.00E+00 0.00E+00 3.20E-06 6.91E-06 3.26E-07 1.57E-05 9.56E-08 5.12E-06 6.35E-08 6.51E-06 6.50E-04 5.72E-03 6.82E-05 1.36E-03 1.79E-05 2.79E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 o.OOE+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 1.02E-07 0.00E+00 0.00E+00 0.00E+00 8.24E-05 1.34E-06 1.43E-04 3.92E-07 2.41E-05 2.51E-07 4.15E-05 8.82E-06 2.84E-05 2.25E-06 1.22E-05 1.19E-06 4.83E-06 1.19E-04 3.44E-05 1.02E-04 2.23E-07 1.93E-10 2.37E-08 9.69E-11 5.09E-11 0.00E+00 0.00E+00 8.68E-09 1.59E-09 3.61E-07 6.39E-09 2.11E-11 1.24E-08 0.00E+00 1.09E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.35E-11 0.00E+00 0.00E+00 0.00E+00 5.37E-07 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.27E-05 5.13E-06 3.67E-05 2.40E-08 1.30E-10 4.34E-08 6.58E-10 3.70E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.10E-05 2.34E-05 1.84E-05 5.94E-05 8.34E-06 1.01E-04 4.36E-07 4.50E-05 2.76E-06 1.54E-06 1.73E-06 2.95E-06 5.16E-07 2.40E-06 2.07E-06 2.27E-06 1.96E-06 1.46E-07 2.39E-05 4.21E-05 1.14E-07 1.14E-09 9.84E-05 3.31E-05 2.47E-05 5.55E-05 1.70E-04 4.24E-05 8.59E-08 3.58E-05 3.57E-05 2.79E-05 0.00E+00 4.04E-06 0.00E+00 0.00E+00 0.00E+00 1.21E-05 0.00E+00

0. 00E+00 0.00E+00 5.89E-07 0.00E+00 0.00E+00 Indian Point 2 Page 43 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-llOm Sb-122 Sb-124 Sb-125 0.00E+00 2.26E-08 1.01E-05 1.70E-03 0.00E+00

0. 00E+00 0.00E+00 1.39E-05 3.08E-05 0.00E+00 0.00E+00 6.34E-04 4.70E-06 0.00E+00 1.84E-05 9.33E-08 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 2.51E-03 1.85E-02 5.00E-05 1.92E-05 8.69E-08 8.10E-10 1.13E-06 7.65E-09 2.43E-08 2.06E-07 1.48E-08 4.20E-08 0.00E+00 1.92E-09 2.27E-09 1.48E-06 1.36E-07 2.41E-05 9.96E-07

2. 10E-06 2.14E-05 1.23E-05 3.08E-07 4.72E-08 1.01E-05 1.OOE-04 0.00E+00

1. 99E-05 8.18E-07 8.98E-06 5.38E-05 3.60E-06 1.08E-05 3.92E-05 5.32E-07 6.09E-07 6.31E-05 1.68E-07 0.00E+00 0.00E+00 0.OOE+00 1.70E-04 4.98E-07 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 5.02E-08 2.54E-09 1.73E-08 3.40E-05 3.96E-09 2.86E-09 0.00E+00 0.OOE+00

0. 00E+00 7.27E-07 3.85E-08 3.15E-07 1.19E-07 3.08E-07 2.51E-08 1.01E-05 6.59E-05 1.41E-08 4.51E-06 1.41E-07 2.40E-06 2.12E-05 8.98E-06 2.55E-05 2.20E-05 2.42E-07 2.82E-07 2.91E-05 1.25E-08 3.63E-07 3.82E-07 1.94E-08 8.40E-05 2.73E-07 1.97E-07 7.20E-05 4.71E-03 1.81E-06 7.13E-07 2.33E-09 2.76E-11 3.01E-08 2.15E-10 6.62E-10 3.56E-08

1. 16E-09 1.00E-08 6.63E-06 5.10E-08 2.83E-08 4.95E-07 4.58E-08 3.01E-06 4.81E-07 6.13E-07 6.63E-06 2.53E-06 3.08E-07 0.OOE+00 1.O1E-05 0.OOE+00 9.20E-09 0.00E+00 0.OOE+00

0. OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 o.00E+00 0.OOE+00 0.00E+00 0.00E+00 3.14E-08 5.68E-08 1.54E-08 3.08E-07 3.34E-08 1.01E-05 0.00E+00 2.01E-09 4.41E-06 7.03E-07 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 1.03E-06 3.06E-05 6.98E-08 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00 0.00E+00 o.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 5.41E-08 2.56E-09 1.24E-08 5.08E-05 4.26E-08 3.40E-08 3.08E-06

1. 00E-06 2.85E-05 1.04E-06 0.00E+00 0.OOE+00

0. 00E+00 3.08E-07 0.00E+00 1.01E-05 0.OOE+00 1.79E-08 0.00E+00 0.OOE+00 4.39E-06 1.59E-05 0.00E+00

0. OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. OOE+00 0.OOE+00

0. 00E+00 0.00E+00 0.OOE+00 0.0OE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.07E-09 1.56E-09 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 1.09E-06 1.34E-05 7.72E-06 3.08E-07 1.11E-06 1.01E-05 2.3OE-05 4'.11E-07 7.31E-06 7.43E-05 1.14E-06 2.57E-05 8.97E-06 2.57E-05 1.95E-06 4.05E-05 1.25E-05 5.33E-05 1.37E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 4.85E-07 9.74E-08 5.16E-05 2.31E-04 5.92E-05 2.07E-04 1.20E-04 2.70E-06

8. lE-05 1.46E-04 1.92E-04 2.50E-05 1.62E-04 1.46E-05 1.12E-05 1.15E-06 4.86E-07 1.80E-05 5.41E-05 1.83E-04 3.77E-05 7.65E-05 6.60E-05 1.64E-05 Indian Point 2 Page 44 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 1-132 I-133 1-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 2.33E-05 5.85E-05 1.OOE-06 1.OOE-04 2.84E-07 1.52E-05 1.76E-07 2.08E-05 6.OOE-06 3.59E-05 1.66E-06 1.25E-05 8.69E-07 3.64E-06 3.77E-04 4.59E-05 5.22E-04 4.81E-07 8.81E-07 1.71E-04 4.25E-07 1.84E-07 2.11E-08 1.10E-09 7.87E-08 1.48E-08 2.98E-06 8.13E-08 2.74E-10 5.53E-08 9.03E-07 1.llE-08

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.79E-06 1.94E-05 3.35E-07 3.43E-05 9.79E-08 6.12E-06 6.50E-08

1. 03E-05 1.32E-05 4.23E-05 3.37E-06 1.82E-05 1.78E-06 7.24E-06 7.03E-04 1.35E-04 6.11E-04 7.82E-07 5.84E-10

1. 71E-07 2.91E-10 1.53E-10 8.32E-09 4.04E-10 4.80E-08 9.82E-06 1.22E-06 3.04E-08 1.06E-10 5.68E-08 6.28E-07 9.93E-10 0.OOE+00 1.15E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 3.15E-06 7.08E-06 2.15E-07 1.54E-05 6.63E-08 5.05E-06 4.94E-08 9.61E-06 5.30E-06 1.86E-05 1.20E-06 5.33E-06 6.33E-07 2.64E-06 7.10E-05 5.04E-05 4.33E-05 3.79E-07 2.55E-08

8. 81E-06 1.34E-08 9.06E-09 2.14E-09 9.67E-11 5.65E-09 1.12E-09 1.67E-07 4.03E-09 1.38E-11 3.48E-09 2.17E-07 5.61E-10 0.OOE+00 1.87E-06

0. OOE+00

0. OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 7.84E-06 1.69E-05 8.14E-07 3.84E-05 2.38E-07 1.24E-05 1.57E-07 1.52E-05 1.48E-03 1.39E-02 1.58E-04 3.31E-03 4.15E-05 6.49E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 1.44E-04 2.44E-06 2.50E-04 7.07E-07 4.21E-05 4.50E-07 6.44E-05 1.45E-05 4.94E-05 3.76E-06 2.14E-05

1. 99E-06 8.07E-06

1. 81E-04 5.38E-05 1.64E-04 3.90E-07 3.51E-10 4.06E-08

1. 75E-10 8.81E-11

0. OOE+00

0. OOE+00 1.48E-08 2.86E-09 4.93E-07 1.13E-08 3.84E-11 2.19E-08 0.OOE+00 1.98E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 7.42E-05

1. lE-05 6.64E-05 6.09E-08 3.54E-10 1.05E-07

1. 77E-10 9.26E-11

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.llE-05 2.36E-05 2.10E-05 5.97E-05 2.27E-05 1.03E-04 7.11E-06 3.81E-05 2.83E-06 1.51E-06 2.73E-06 3.08E-06 1.84E-06 2.62E-06 1.91E-06 2.05E-06 1.91E-06 1.25E-06 5.58E-05 4.20E-05 5.19E-06 7.59E-07 9.77E-05 6.86E-05 2.48E-05 5.73E-05 1.71E-04 4.29E-05 4.93E-06 3.60E-05 3.69E-05 2.87E-05

0. OOE+00 3.92E-06 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 Indian Point 2 Page 45 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-4 TOTAL BODY DOSE FACTORS Ki FROM NOBLE GASES (GAMMA)

FINITE CLOUD **

CORRECTION NUCLIDE Gamma TB*

X (pCi/uCi)

X FACTOR

=

Ki***

Kr-83m 7.56E-08 1.OOE+6 8.86E-01 6.70E-02 Kr-85m 1.17E-03 1.OOE+6 7.49E-01 8.76E+02 Kr-85 1.61E-05 1.OOE+6 6.73E-01 1.08E+01 Kr-87 5.92E-03 1.OOE+6 5.68E-01 3.36E+03 Kr-88 1.47E-02 1.OOE+6 5.40E-01 7.93E+03 Kr-89 1.66E-02 1.OOE+6 5.60E-01 9.30E+03 Kr-90 1.56E-02 1.OOE+6 5.97E-01 9.31E+03 Xe-131m 9.15E-05 1.OOE+6 8.67E-01 7.94E+01 Xe-133m 2.51E-04 1.OOE+6 8.17E-01 2.05E+02 Xe-133 2.94E-04 1.OOE+6 8.86E-01 2.60E+02 Xe-135m 3.12E-03 1.OOE+6 6.75E-01 2.11E+03 Xe-135 1.81E-03 1.OOE+6 7.60E-01 1.38E+03 Xe-137 1.42E-03 1.OOE+6 6.46E-01 9.18E+02 Xe-138 8.83E-03 1.OOE+6 5.75E-01 5.07E+03 Ar-41 8.84E-03 1.OOE+6 5.89E-01 5.21E+03 t

From Regulatory Guide 1.109, Table B-1 (mrem/yr per pCi/cu mtr)

The finite cloud correction factor is described in Section 2.1.

Ki (mrem/yr per uCi/cu mtr)

Indian Point 2 Page 46 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-5 SKIN DOSE FACTORS Li FROM NOBLE GASES (BETA)

NUCLIDE Beta Skin*

X (pCi/uCi)

=

Li**

Kr-83m O.OOE+00 1.OOE+6 O.OOE+00 Kr-85m 1.46E-03 1.OOE+6 1.46E+03 Kr-85 1.34E-03 1.00E+6 1.34E+03 Kr-87 9.73E-03 1.OOE+6 9.73E+03 Kr-88 2.37E-03 1.OOE+6 2.37E+03 Kr-89 1.01E-02 1.OOE+6 1.01E+04 Kr-90 7.29E-03 1.00E+6 7.29E+03 Xe-131m 4.76E-04 1.00E+6 4.76E+02 Xe-133m 9.94E-04 1.00E+6 9.94E+02 Xe-133 3.06E-04 1.OOE+6 3.06E+02 Xe-135m 7.11E-04 1.00E+6 7.11E+02 Xe-135 1.86E-03 1.OOE+6 1.86E+03 Xe-137 1.22E-02 1.00E+6 1.22E+04 Xe-138 4.13E-03 1.OOE+6 4.13E+03 Ar-41 2.69E-03 1.00E+6 2.69E+03 From Regulatory Guide 1.109, Table B-1 (mrem/yr per pCi/cu mtr)

Li (mrem/yr per uCi/cu mtr)

Indian Point 2 Page 47 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-6 AIR DOSE FACTORS Mi FROM NOBLE GASES (GAMMA)

FINITE CLOUD **

CORRECTION NUCLIDE Gamma*

X (pCi/uCi)

X FACTOR

=

Mi***

Kr-83m 1.93E-05 1.OOE+6 8.86E-01 1.71E+01 Kr-85m 1.23E-03 1.OOE+6 7.49E-01 9.21E+02 Kr-85 1.72E-05 1.OOE+6 6.73E-01 1.16E+01 Kr-87 6.17E-03 1.OOE+6 5.68E-01 3.50E+03 Kr-88 1.52E-02 1.OOE+6 5.40E-01 8.20E+03 Kr-89 1.73E-02 1.OOE+6 5.60E-01 9.69E+03 Kr-90 1.63E-02 1.00E+6 5.97E-01 9.73E+03 Xe-131m 1.56E-04 1.OOE+6 8.67E-01 1.35E+02 Xe-133m 3.27E-04 1.OOE+6 8.17E-01 2.67E+02 Xe-133 3.53E-04 1.OOE+6 8.86E-01 3.13E+02 Xe-135m 3.36E-03 1.00E+6 6.75E-01 2.27E+03 Xe-135 1.92E-03 1.OOE+6 7.60E-01 1.46E+03 Xe-137 1.51E-03 1.OOE+6 6.46E-01 9.76E+02 Xe-138 9.21E-03 1.OOE+6 5.75E-01 5.29E+03 Ar-41 9.30E-03 1.OOE+6 5.89E-01 5.48E+03 From Regulatory Guide 1.109, Table B-1 (mrad/yr per pCi/cu mtr)

The finite cloud correction factor is described in Section 2.1.

Mi (mrad/yr per uCi/cu mtr)

Indian Point 2 Page 48 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-7 AIR DOSE FACTORS Ni FROM NOBLE GASES (BETA)

NUCLIDE Beta*

X (pCi/uCi)

=

Ni**

Kr-83m 2.88E-04 1.OOE+6 2.88E+02 Kr-85m 1.97E-03 1.OOE+6 1.97E+03 Kr-85 1.95E-03 1.00E+6 1.95E+03 Kr-87 1.03E-02 1.OOE+6 1.03E+04 Kr-88 2.93E-03 1.00E+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 l.llE-03 1.OOE+6 l.llE+03 Xe-133m 1.48E-03 1.00E+6 1.48E+03 Xe-133 1.05E-03 1.00E+6 1.05E+03 Xe-135m 7.39E-04 1.00E+6 7.39E+02 Xe-135 2.46E-03 1.00E+6 2.46E+03 Xe-137 1.27E-02 1.00E+6 1.27E+04 Xe-138 4.75E-03 1.00E+6 4.75E+03 Ar-41 3.28E-03 1.00E+6 3.28E+03 From Regulatory Guide 1.109, Table B-1 (mrad/yr per pCi/cu mtr)

Ni (mrad/yr per uCi/cu mtr)

Indian Point 2 Page 49 Revision 9

ODCM Part II - Calculational Methodologies TABLE 2 - 8 NOBLE GAS DOSE FACTORS For Instantaneous and Time Average Mixtures at the Site Boundary Radionuclide Instantaneous Time Average Mix (%)

Mix (%)

Kr-85m 3.09 Kr-85 0

18.98 Kr-87 2.80 Kr-88 5.22 Xe-131m 0

0.162 Xe-133m 1.39 0.485 Xe-1i33 56.8 78.1 Xe-135m 1.34 Xe-135 19.2 2.21 Xe-138 2.81 Ar-41 7.43 Total 100 100 Unit 2 effective Unit 3 effective Unit 2 effective Unit 3 effective instantaneous instantaneous average average dose factors dose factors units dose factors dose factors

= 1507 K= 849 mrem/yrperuCi/m3 K =237 K = 153 L = 1310 L = 1310 mrem/yr per uCi/m3 L =540 L = 540

= 1601 M = 905 mrad/yr per uCi/m3 M =281 MF =181

= 1977 N= 1977 mrad/yr per uCi/m3

= 1254

= 1254 Instantaneous Mixture Basis:

This mix defines the shared-site noble gas limits between the two units, and is used for administrative guidelines for instantaneous releases based on an RCS noble gas mix at 1.6 yrs into a 24-month cycle, with two failed fuel rods, per Reference 21. These mixtures provide conservative application for calculating setpoints per 1 OCFR20, in terms of uCVsec before an actual sample of the release is available, per Appendix I.

Time Averaaed Release Mixture Basis:

This mix defines the routine (time-averaged) releases from either unit. It was derived from average noble-gas releases from year 2000-2003 at IPEC units 2 and 3 per Reference 21. They are used in conjunction with calculations to determine representative quarterly and annual time averaged release rates in curies/sec for administrative purposes only, per Appendix I.

Indian Point 2 Page 50 Revision 9

ODCM Part II - Calculational Methodologies TABLE 2-9 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCE Distance Distance Distance Sector to Site to Site to nearest b

Boundary Boundary

resident, by from Unit 2 from Unit 3 from Unit 1 compass Plant Vent, Plant Vent, superheater, point in meters in meters in meters N

RIVER RIVER 1788.1 NNE RIVER RIVER 3111.3 NE 550 636 1907.3 ENE 600 775 1478.2 E

662 785 1370.9 ESE 569 622 715.2 SE 553 564 1168.2 SSE 569 551 1239.7 S

700 566 1132.5 SSW 755 480 1573.5 SW 544 350 3015.9 WSW RIVER RIVER 2169.6 W

RIVER RIVER 1918.7 WNW RIVER RIVER 1752.4 NW RIVER RIVER 1692.7 NNW RIVER RIVER 1609.3 Distances are measured from the unit-specific Plant Vent to the Site Boundary. The distance to the Nearest Resident is measured from the Unit 1 Superheater Stack for both units 2 and 3.

(Reference 22)

Indian Point 2 Page 51 Revision 9

ODCM Part 11-Calculational Methodologies Table 2-10a ADULT INHALATION Ri(I) 3 (mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-5B Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-gim Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-ll0m Sb-122 Sb-124 Sb-125 0.OOE+00 0.OOE+00 1.02E+04 1.32E+06 0.OOE+00 0.OOE+00 0.OOE+00 2.46E+04 1.18E+04 0.OOE+00 0.OOE+00 4.32E+05 1.54E+00 0.OOE+00 3.24E+04 3.38E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.04E+05 9.92E+07 6.19E+01 6.74E+00 2.09E+03 2.61E-01 4.62E+05 1.03E+01 s.44E+01 1.07E+05 9.68E+01 1.41E+04 0.00E+00 1.03E-03 4.18E-05 1.53E+03 7.90E-01 6.91E+04 1.08E+04 0.00E+00 3.12E+04 5.34E+04 1.26E+03 0.00E+00 1.02E+04 7.71E+04 0.00E+00 3.96E+04 1.24E+00 1.70E+04 2.78E+04 1.58E+03 1.15E+04 3.14E+04 2.10E-01 1.46E+00 1.03E+05 6.51E-02 0.OOE+00 0.00E+00 0.OOE+00 1.35E+05 3.87E+02 2.56E+02 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 3.44E+04

1. 96E+01 7.82E+03 1.21E+02 2.91E-03 6.02E-05 0.00E+00 0.OOE+00 0.00E+00 1.00E+04 0.00E+00 5.89E+02 5.95E+02 1.26E+03 0.00E+00 1.02E+04 5.01E+04 1.OOE+02 6.30E+03 1.83E-01 3.94E+03 1.06E+04 2.07E+03 1.48E+04 1.45E+04 9.12E-02

6. 15E-01 4.66E+04 4.52E-03 2.41E+02 3.13E+02 1.28E+01 5.90E+04

1. 93E+02 1.70E+02 8.72E+03 6.10E+06 2.50E+00 2.91E-01 5.61E+01 1.02E-02 1.24E+04 3.02E-01 2.61E+00 2.33E+04 9.04E+00 4.21E+03 2.30E+0l 3.70E-02 5.90E-04 6.58E+02 3.11E-01 8.72E+03 5.94E+03

0. 00E+00 1.24E+04 1.26E+04 1.26E+03 0.00E+00 1.02E+04 0.00E+00 5.95E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.55E+01 5.4OE+01 1.26E+03 0.00E+00 1.02E+04 0.00E+00 2.28E+01 9.84E+03 1.3OE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 4.62E+00 6.90E+04 4.22E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.42E+04 2.97E+01 7.74E+03 2.91E+02 4.42E-02 1.08E-03 5.83E+03 1.02E+00 1.34E+05 1.97E+04 0.00E+00 0.00E+00 0.00E+00 1.26E+03 0.OOE+00

1. 02E+04 0.00E+00 1.44E+04 1.40E+06 9.44E+03 7.21E+04

1. 02E+06 9.28E+05 5.97E+06

1. 78E+05

5. 60E+03 6.78E+03 8.64E+05 9.20E+02 0.00E+00 0.00E+00 0.OOE+00 0.00E+00

0. 00E+00 0.00E+00 1.40E+06 9.60E+06 3.65E+04

1. 65E+04

1. 70E+05 1.92E+03 1.70E+06

1. 57E+04 4.85E+04 1.77E+06 7.87E+04 5.05E+05 9.12E+04 7.64E+02 3.99E+02 5.05E+05 1.10E+04 9.36E+06 4.63E+06 0.00E+00 2.48E+06 1.74E+06 1.26E+03 0.OOE+00 1.02E+04 8.64E+04 3.32E+03 7.74E+04 2.02E+04 6.03E+03 1.88E+05 1.06E+05 2.85E+05 1.34E+04 1.23E+04 4.90E+04 5.34E+04 1.63E+01 2.32E+02 1.64E-03 0.OOE+00 1.66E+04 3.34E-09 9.28E-12 3.50E+05 7.22E+05

1. 91E+05 4.30E+04 5.06E+05 1.33E+00 3.85E+05 7.35E+04 4.22E+05 1.50E+05 5.23E+05 1.04E+05 2.48E+05 4.16E+03 1.09E-11

1. 1OE+05 4.82E+04 9.12E+05 3.02E+05 0.00E+00 4.06E+05 1.01E+05 Indian Point 2 Page 52 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-l0a ADULT INHALATION Ri(I)

(mrem/yr per Isotope BONE LIVER TOT BODY THYROID KIDNEY 3

uci/m LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 1-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 3.42E+03 1.26E+04 1.40E+00 9.76E+03 4.98E-02 6.99E+01 1.11E-02 2.60E+02 4.58E+03 2.52E+04

1. 16E+03 8.64E+03 6.44E+02 2.68E+03 3.73E+05 3.90E+04 4.78E+05 3.31E+02 9.36E-01 3.90E+04

1. OOE-01 2.63E-02 3.44E+02 6.83E-01

1. 99E+04 1.86E+02 3.43E+06 9.36E+03 3.01E-02 5.27E+03 8.48E+00 2.3OE+02 0.OOE+00 0.OOE+00 3.20E+04

0. OOE+00 0.OOE+00 2.22E-01 0.OOE+00 6.56E+04 7.60E+04 3.07E-02 0.OOE+00 0.OOE+00

1. 58E+03 5.77E+03 6.42E-01 4.67E+03 2.39E-02 4.36E+01 5.95E-03 2.15E+02 1.34E+04 3.58E+04 3.26E+03 1.48E+04

1. 73E+03 6.98E+03 8.48E+05 1.46E+05 6.21E+05 6.21E+02 6.66E-04 4.90E+01 7.53E-05 2.70E-05

1. 74E+02 3.10E-01 1.35E+04 1.38E+02 1.43E+06

3. 75E+03 1.25E-02 6.10E+03 7.08E+00 2.26E+01

0. OOE+00 6.92E+02 0.OOE+00 0.OOE+00 0.OOE+00 5.62E-02 3.92E+05 2.16E+03 3.36E+03 2.58E-02 0.OOE+00 0.OOE+00 4.67E+02 1.57E+03 3.10E-01 1.58E+03 1.24E-02 2.90E+01 3.59E-03 1.62E+02 5.28E+03 2.05E+04 1.16E+03 4.52E+03 6.15E+02 2.57E+03 7.28E+05 1.10E+05 4.28E+05 3.24E+02 2.74E-02 2.57E+03 3.36E-03 1.66E-03 4.58E+01 7.72E-02 1.53E+03 1.53E+01 1.84E+05 4.64E+02 1.53E-03 3.65E+02 2.48E+00 1.24E+01 0.00E+00 6.71E+02 7.76E+05 0.OOE+00 0.OOE+00 2.05E-02 1.28E+04 4.48E+03 2.OOE+04 1.26E-02 0.OOE+00

0. OOE+00 1.05E+03 3.29E+03 1.06E+00 3.44E+03 3.90E-02 5.50E+01 9.36E-03

1. 90E+02 1.14E+06 1.19E+07

1. 14E+05 2.15E+06 2.98E+04 4.48E+05 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.36E+03

0. OOE+00 2.75E-02 0.OOE+00 0.OOE+00 1.24E+04 4.58E+04 5.10E+00 3.66E+04 1.87E-01 3.09E+02 4.37E-02 1.46E+03 2.09E+04 6.13E+04 5.18E+03 2.58E+04 2.75E+03 1.11E+04 2.87E+05 8.56E+04 2.22E+05 4.80E+02 6.22E-04 1.67E+01 7.OOE-05 2.29E-05 0.OOE+00

0. OOE+00 6.26E+03 6.08E+01 8.48E+05 2.16E+03 7.05E-03 3.56E+03

0. OOE+00

7. OOE+01 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 6.54E-02 3.76E+05 0.OOE+00 1.68E+01 1.74E-01 0.OOE+00

0. OOE+00 3.14E+05 9.60E+05 6.51E+03

1. 16E+06

1. 94E+03 1.46E+05 1.39E+03 2.88E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 9.76E+04 1.20E+04 7.52E+04 4.86E+01 3.76E+03 1.27E+06

1. 94E+03 1.19E+03 1.36E+05 6.33E+03 3.62E+05 7.98E+04 7.78E+06 2.81E+05

1. 02E+03 2.21E+05 2.90E+04 3.76E+04 0.OOE+00 3.70E+05 4.80E+05

0. OOE+00

0. OOE+00 2.40E+03 7.28E+05 9.60E+05

1. 52E+06 3.47E+03 0.OOE+00 0.OOE+00 7.06E+04 1.50E+05

5. 74E+04 3.83E+05 1.57E+02 5.56E+05 1.84E+01

5. 10E+05 7.69E+03 6.28E+03 4.06E+02 8.88E+03 1.01E+00 5.25E+03 1.04E+04

1. 17E+04 8.40E+03 1.86E-03 8.96E+02 2.18E+05 1.16E-07 1.57E-16 4.58E+05

2. 11E+03 1.2OE+05 2.26E+05 8.16E+05 2.OOE+05 2.15E-08

1. 73E+05 1.55E+05 1.19E+05 0.OOE+00 3.14E+04 6.08E+04 0.OOE+00 0.OOE+00 2.42E+02 6.56E+04 1.20E+04

8. OOE+04 2.38E-01 0.OOE+00 0.OOE+00 Indian Point 2 Page 53 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-lOb TEEN INHALATION Ri(I) 3 (mnrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-11Om Sb-122 Sb-124 Sb-125 O.OOE+00

0. OOE+00 1.38E+04

1. 89E+06 O.OOE+00 O.OOE+00 0.OOE+00 3.34E+04 1.59E+04 O.OOE+00 O.OOE+00 5.80E+05 2.18E+00

0. OOE+00 3.86E+04 4.83E-02 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00

0. OOE+00 O.OOE+00 4.34E+05 1.08E+08 8.80E+01 9.52E+00 2.98E+03 3.70E-0l 6.61E+05 1.47E+0l 1.35E+02 1.46E+05 1.38E+02 1.86E+04 O.OOE+00 1.38E-03 5.92E-05

2. 10E+03

1. 12E+00 9.84E+04 1.38E+04 O.OOE+00 4.30E+04 7.38E+04 1.27E+03 O.OOE+00 1.38E+04 l.lOE+05 O.OOE+00

5. 11E+04

1. 70E+00 2.38E+04 3.70E+04 2.07E+03

1. 51E+04 4.34E+04 2.93E-0l 2.03E+00 1.34E+05 9.20E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.90E+05 5.46E+02 3.52E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.58E+04 2.72E+0l 1.03E+04 1.69E+02 3.86E-03 8.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.31E+04 O.OOE+00 7.94E+02

8. 08E+02 1.27E+03

0. OOE+00 1.38E+04 7.16E+04 1.35E+02 8.4OE+03 2.52E-0l 5.54E+03 1.43E+04 2.78E+03 1.98E+04

1. 98E+04 1.27E-0l 8.48E-0l 6.24E+04 6.46E-03 3.44E+02 4.33E+02 1.83E+0l 8.40E+04 2.72E+02 2.33E+02 1.25E+04 6.68E+06 3.51E+00 4.06E-0l 8.00E+0l 1.42E-02 1.77E+04 4.29E-01 3.72E+00

3. 15E+04 1.26E+01 5.66E+03 3.22E+0l 4.99E-02 8.24E-04

8. 96E+02 4.34E-0l 1.24E+04 7.99E+03 O.OOE+00 1.68E+04

1. 72E+04 1.27E+03 O.OOE+00 1.38E+04 O.OOE+00 7.50E+0l O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00

0. OOE+00 O.OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00

0. OOE+00 O.OOE+00 9.76E+0l 7.04E+0l 1.27E+03 O.OOE+00 1.38E+04 O.OOE+00 3.07E+0l 1.27E+04 1.79E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 6.41E+00 8.64E+04 6.02E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 O.OOE+00 6.74E+04 4.12E+01

1. OOE+04 4.11E+02 5.76E-02 1.52E-03 7.43E+03 1.41E+00

1. 90E+05 2.50E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.27E+03 0.OOE+00 1.38E+04 O.OOE+00 2.10E+04

1. 98E+06

1. 52E+04 1.24E+05 1.53E+06 1.34E+06 8.72E+06 3.07E+05 9.36E+03

1. llE+04 1.24E+06 1.58E+03 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.42E+06 1.65E+07 6.07E+04 2.74E+04 2.93E+05 3.20E+03 2.94E+06 2.68E+04 8.32E+04 2.69E+06 1.30E+05 7.51E+05

1. 54E+05

1. 15E+03 6.67E+02 7.83E+05

1. 82E+04 1.61E+07 6.75E+06 O.OOE+00 3.85E+06 2.74E+06 1.27E+03 0.OOE+00 1.38E+04 9.28E+04 3.OOE+03 6.68E+04 5.74E+04 6.39E+03 1.78E+05 9.52E+04 2.59E+05 1.42E+04 3.67E+04 6.14E+04 4.66E+04 2.85E+02 O.OOE+00

0. OOE+00 O.OOE+00

1. 77E+04 2.92E-05 3.38E-07 3.71E+05 7.65E+05 2.59E+05

1. 19E+05 5.59E+05 3.02E+0l 4.09E+05 1.65E+05 5.79E+05 1.49E+05 6.3OE+05 9.68E+04 2.69E+05 6.13E+03 8.72E-07 1.09E+05 9.04E+04 9.60E+05 2.73E+05 O.OOE+00 3.98E+05 9.92E+04 Indian Point 2 Page 54 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-lOb TEEN INHALATION Ri(I) 3 (rnremlyr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 4.88E+03

1. 80E+04

2. 01E+00 1.39E+04 7.10E-02 9.84E+01 1.58E-02 3.60E+02 6.24E+03 3.54E+04 1.59E+03 1.22E+04 8.88E+02 3.70E+03 5.02E+05 5.15E+04 6.70E+05 4.66E+02 1.34E+00 5.47E+04 1.42E-01 3.70E-02 4.79E+02 9.60E-01 2.84E+04 2.66E+02 4.89E+06 1.34E+04 4.30E-02 7.86E+03 1.2OE+01 3.38E+02

0. OOE+00 0.OOE+00

4. OOE+04 0.OOE+00 0.OOE+00 3.14E-01 0.OOE+00 1.20E+05 3.76E+05 4.25E-02 0.OOE+00 0.OOE+00 2.24E+03 8.16E+03 9.12E-01 6.58E+03 3.38E-02 6.01E+01 8.32E-03 2.90E+02

1. 79E+04 4.91E+04 4.38E+03

2. 05E+04 2.32E+03 9.44E+03 1.13E+06 1.94E+05 8.48E+05 8.56E+02 9.44E-04 6.70E+01 1.06E-04 3.70E-05 2.36E+02 4.25E-01

1. 90E+04

1. 94E+02 2.02E+06 5.31E+03 1.76E-02 8.56E+03 9.76E+00 3.19E+01

0. OOE+00 9.44E+02 0.OOE+00 0.OOE+00 0.OOE+00 7.78E-02

8. OOE+05 3.76E+03 6.40E+03 3.48E-02 0.OOE+00 0.OOE+00 6.67E+02

2. 18E+03 4.42E-01 2.25E+03 1.76E-02 4.02E+01 5.04E-03 2.19E+02 7.17E+03 2.64E+04 1.58E+03 6.22E+03 8.40E+02 3.49E+03 5.49E+05 1.37E+05 3.11E+05 4.46E+02 3.90E-02 3.52E+03 4.74E-03 2.27E-03 6.26E+01 1.06E-01 2.17E+03 2.16E+01 2.62E+05 6.62E+02 2.18E-03 5.13E+02 3.43E+00 1.77E+01 0.OOE+00 9.2OE+02 1.04E+04 0.OOE+00

0. OOE+00 2.84E-02 2.72E+04 7.76E+03 2.64E+04 2.91E-02 0.OOE+00 0.OOE+00 1.4OE+03 4.38E+03 1.42E+00 4.58E+03 5.18E-02 7.25E+01 1.24E-02 2.46E+02 1.49E+06 1.46E+07 1.51E+05 2.92E+06 3.95E+04 6.21E+05 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00

0. 00E+00

0. 00E+00 0.00E+00 0.OOE+00

0. 00E+00

0. 00E+00 0.00E+00

0. OOE+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.00E+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 2.32E+03 0.00E+00 3.57E-02 0.00E+00

0. OOE+00 0.00E+00 6.54E+04 7.28E+00 5.19E+04 2.66E-01 4.39E+02 6.18E-02 1.95E+03 2.75E+04 8.4OE+04 6.92E+03 3.59E+04 3.66E+03 1.49E+04 3.75E+05

1. 10E+05 3.04E+05 6.62E+02 8.88E-04 2.28E+01 9.84E-05 3.14E-05 0.00E+00 0.00E+00

8. 88E+03 8.64E+01 1.21E+06 3.09E+03 1.01E-02

5. 02E+03 0.00E+00 1.00E+02

0. 00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 9.12E-02 5.36E+05 0.00E+00 2.24E+01 2.33E-01 0.00E+00 0.OOE+00 5.36E+05

1. 66E+06 1.12E+04 1.98E+06 3.30E+03 2.38E+05 2.34E+03 4.49E+05

0. OOE+00

0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.46E+05

1. 78E+04 1.21E+05

7. 87E+01 6.46E+03 2.03E+06 3.29E+03

1. 91E+03 2.14E+05 1.02E+04 6.14E+05 1.30E+05 1.34E+07 4.83E+05 1.75E+03 3.72E+05 4.74E+04 6.49E+04 0.00E+00 5.86E+05 7.04E+05 0.00E+00 0.00E+00 3.93E+03 1.28E+06 1.60E+06 2.32E+06 5.40E+03

0. 00E+00

0. OOE+00 7.50E+04 1.59E+05 8.08E+04 4.05E+05 1.62E+03 6.21E+05 1.51E+01 4.63E+05 9.12E+03 6.49E+03 1.27E+03 1.03E+04 2.04E+01 6.95E+03 9.76E+03 1.09E+04 8.48E+03 2.70E-01 6.45E+03 2.29E+05 7.46E-04 4.79E-10 4.87E+05 1.20E+04 1.26E+05 2.55E+05 8.64E+05 2.14E+05 2.35E-04

1. 82E+05

1. 77B+05 1.32E+05 0.00E+00 3.14E+04 5.52E+04 0.00E+00 0.OOE+00 2.17E+03 6.88E+04 1.2OE+04 7.76E+04

1. 1OE+01 0.00E+00 0.00E+00 Indian Point 2 Page 55 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-10c CHILD INHALATION Ri(I) 3 (mrem/yr per uci/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-9lm Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 0.OOE+00 1.61E+04 2.60E+06 0.OOE+00 O.OOE+00 O.OOE+00 4.74E+04 2.07E+04 O.OOE+00 0.OOE+00 8.21E+05 2.99E+00 0.OOE+00 4.26E+04 6.70E-02

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 S. 99E+05 1.01E+08 1.21E+02 1.31E+01 4.11E+03 5.07E-01 9.14E+05 2.04E+01 1.86E+02

1. 90E+05 1.88E+02 2.35E+04

0. OOE+00 1.78E-03 8.10E-05 2.79E+03 1.53E+00 1.36E+05 1.69E+04 0.OOE+00 5.74E+04 9.84E+04 1.12E+03

0. OOE+00 1.61E+04

1. 14E+05

0. OOE+00 4.29E+04 1.66E+00 2.52E+04 3.34E+04

1. 77E+03 1.31E+04 4.63E+04 2.96E-01 1.99E+00 1.13E+05 9.66E-02

0. OOE+00

1. 98E+05 5.62E+02 3.45E+02 o.OOE+00 o.OOE+00 o.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 4.18E+04 2.72E+01 9.18E+03 1.72E+02 3.48E-03 8.51E-05 0.OOE+00 0.OOE+00 0.OOE+00

1. 14E+04 0.OOE+00 7.40E+02 7.59E+02 1.12E+03 0.OOE+00 1.61E+04 9.88E+04 1.54E+02 9.51E+03 3.12E-01 7.77E+03

1. 67E+04 3.16E+03 2.26E+04 2.80E+04

1. 64E-01

1. 07E+00 7.03E+04 8.92E-03 4.74E+02 5.48E+02 2.53E+01

1. 14E+05 3.66E+02 2.90E+02

1. 72E+04 6.44E+06 4.59E+00 5.25E-01 1.11E+02 1.84E-02 2.44E+04 5.81E-01

5. 11E+00 3.70E+04

1. 60E+01 6.55E+03 4.25E+01 5.77E-02 1.08E-03 1.07E+03 5.55E-01 1.69E+04 9.14E+03 0.OOE+00 2.OOE+04 2.07E+04 1.12E+03 0.OOE+00 1.61E+04 0.OOE+00 8.55E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.26E+02 9.10E+01 1.12E+03 0.OOE+00 1.61E+04 0.OOE+00 2.43E+01 1.OOE+04 1.67E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.03E+00 7.14E+04 5.85E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+O0

0. OOE+00

0. OOE+00 5.96E+04 3.88E+01 8.62E+03 3.92E+02 5.07E-02 1.45E-03 7.03E+03 1.34E+00

1. 84E+05 2.12E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.12E+03 0.OOE+00 1.61E+04 0.OOE+00 1.70E+04 1.58E+06 1.31E+04 1.11E+05 1.27E+06 1.11E+06 7.07E+06 2.75E+05 8.18E+03 9.58E+03 9.95E+05

1. 42E+03

0. OOE+00

0. OOE+00 2.16E+06 1.48E+07 5.33E+04 2.4OE+04 2.62E+05 2.81E+03 2.63E+06 2.39E+04 7.44E+04 2.23E+06

1. 13E+05 6.14E+05 1.35E+05 9.51E+02 5.85E+02 6.62E+05 1.59E+04 1.43E+07 5.48E+06 0.OOE+00 3.24E+06 2.32E+06

1. 12E+03

0. OOE+00 1.61E+04 4.22E+04 1.08E+03 2.29E+04 1.23E+05 2'.87E+03 7.07E+04 3.44E+04 9.62E+04 6.33E+03 8.40E+04 3.67E+04 1.63E+04 1.02E+04 0.OOE+00 0.OOE+00 0.OOE+00 7.99E+03 1.72E+01 1.89E+00 1.67E+05 3.43E+05 1.74E+05 2.42E+05 2.68E+05 1.72E+03 1.84E+05 2.39E+05 3.89E+05 6.11E+04 3.51E+05 3.70E+04 1.27E+05 4.81E+03 1.63E+01 4.48E+04 9.95E+04 4.29E+05 1.OOE+05 0.OOE+00

1. 64E+05 4.03E+04 Indian Point 2 Page 56 Revision 9

ODCM Part 11 - Calculational Methodologies, Table 2-10c 3

CHILD INHALATION Ri(I)

(mrem/yr per Isotope BONE LIVER TOT BODY THYROID KIDNEY uCi/m )

LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 6.73E+03 2.49E+04 2.77E+00 1.92E+04 9.77E-02 1.34E+02 2.17E-02 4.81E+02 8.18E+03 4.81E+04 2.12E+03 1.66E+04 1.17E+03

4. 92E+03 6.51E+05 6.51E+04 9.07E+05 6.33E+02

1. 84E+00 7.40E+04 1.96E-01 4.99E-02 6.44E+02 1.29E+00 3.92E+04 3.66E+02 6.77E+06 1.85E+04 5.96E-02 1.08E+04 1.63E+01 4.66E+02

0. OOE+00 0.OOE+00 4.44E+04 0.OOE+00 0.OOE+00 4.29E-01 0.OOE+00 1.41E+05 4.07E+05 5.66E-02 0.OOE+00 0.OOE+00 2.33E+03 8.55E+03 9.51E-01 6.85E+03 3.50E-02 5.92E+01 8.44E-03 2.72E+02

1. 64E+04 4.81E+04 4.07E+03 2.03E+04 2.16E+03 8.73E+03 1.01E+06 1.71E+05 8.25E+05 8.4OE+02 9.84E-04 6.48E+01 1.09E-04 3.60E-05 2.25E+02 4.11E-01

1. 95E+04 1.99E+02 2.12E+06 5.55E+03 1.85E-02

8. 73E+03 9.66E+00 3.34E+01 0.OOE+00 9.03E+02 0.0OE+00 0.OOE+00 0.OOE+00 7.70E-02 7.03E+05 3.29E+03 4.07E+03 3.26E-02 0.OOE+00 0.OOE+00 9.14E+02 3.02E+03

6. 1OE-01 3.04E+03 2.38E-02 5.07E+01 6.59E-03 2.63E+02 8.44E+03 2.73E+04 1.88E+03 7.70E+03 9.95E+02 4.14E+03 2.25E+05 1.16E+05 1.28E+05 5.55E+02 5.36E-02 4.33E+03 6.36E-03 2.79E-03 7.55E+01 1.29E-01 2.90E+03 2.87E+01 3.61E+05 9.14E+02 3.OOE-03 6.81E+02 4.33E+00 2.35E+01

0. OOE+00 1.07E+03 1.18E+04 0.OOE+00 0.OOE+00 3.60E-02 2.96E+04 8.51E+03 3.70E+04 3.48E-02 0.OOE+00 0.OOE+00

1. 92E+03 6.07E+03

1. 96E+00 6.33E+03 7.14E-02 9.77E+01 1.70E-02 3.17E+02 1.85E+06 1.62E+07 1.94E+05 3.85E+06 5.07E+04 7.92E+05

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.0OE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.63E+03 0.OOE+00 4.59E-02 0.OOE+00 0.OOE+00 0.OOE+00 6.36E+04 7.07E+00

5. 03E+04 2.57E-01 4.0OE+02 5.88E-02 1.77E+03 2.45E+04 7.88E+04 6.25E+03 3.38E+04 3.30E+03 1.34E+04 3.30E+05 9.55E+04 2.82E+05 6.22E+02 8.62E-04

2. 11E+01 9.47E-05 2.91E-05 0.OOE+00 0.OOE+00 8.55E+03 8.36E+01 1.17E+06 3.OOE+03 9.77E-03 4.81E+03 0.OOE+00 9.73E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.55E-02 6.29E+05 0.OOE+00 2.OOE+01 2.11E-01

0. OOE+00

0. OOE+00 4.77E+05 1.48E+06 1.OOE+04 1.76E+06 2.93E+03 2.06E+05 2.05E+03 3.77E+05 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 1.21E+05 1.45E+04 1.04E+05

6. 81E+01 5.77E+03 1.74E+06 2.92E+03 1.64E+03

1. 83E+05 8.70E+03 5.44E+05

1. 15E+05 1.20E+07 4.33E+05 1.57E+03 3.28E+05

4. 11E+04 5.81E+04 0.OOE+00 5.07E+05 5.55E+05 0.OOE+00 0.OOE+00 3.42E+03 1.11E+06 1.33E+06

1. 92E+06 4.55E+03 0.OOE+00 0.OOE+00 3.38E+04 7.14E+04 5.62E+04

1. 82E+05 2.55E+04 3.08E+05 1.33E+03 1.38E+05

5. 11E+03 2.84E+03 3.20E+03 5.48E+03 9.55E+02 4.44E+03 3.85E+03 4.18E+03 3.62E+03 2.70E+02 5.77E+04

1. 02E+05 2.75E+02 2.74E+00 2.26E+05 7.59E+04 5.66E+04 1.27E+05 3.89E+05 9.73E+04

1. 97E+02 8.21E+04 9.10E+04 6.40E+04 0.OOE+00 1.32E+04 2.04E+04 0.OOE+00 0.OOE+00 2.78E+04 3.OOE+04 4.81E+03 3.07E+04 1.80E+03 0.OOE+00 0.OOE+00 Indian Point 2 Page 57 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-10d INFANT INHALATION Ri(I)

(mrem/yr per Isotope BONE LIVER TOT BODY THYROID KIDNEY 3

uci/m LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-9lm Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 0.OOE+00 1.06E+04 2.03E+06 0.OOE+00 0.OOE+00 0.OOE+00

1. 97E+04 1.36E+04 0.OOE+00 0.OOE+00 3.39E+05 2.39E+00 0.OOE+00 1.93E+04 5.39E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.98E+05 4.09E+07 9.56E+01 1.05E+01 3.29E+03 4.07E-01 5.88E+05 1.64E+01 1.50E+02

1. 15E+05 1.50E+02 1.57E+04 0.OOE+00 1.4OE-03 6.51E-05 2.02E+03 1.22E+00 8.68E+04 9.98E+03 0.OOE+00 3.79E+04 5.17E+04 6.47E+02 0.OOE+00 l1.06E+04 i1.12E+05 0.OOE+00 2.53E+04 1.54E+00

1. 17E+04 2.35E+04 1.22E+03 8.02E+03 2.04E+04 2.84E-01

1. 88E+00 6.26E+04 9.67E-02

0. OOE+00 0.OOE+00 0.OOE+00

1. 90E+05 5.57E+02 3.21E+02 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.79E+04 2.56E+01 6.43E+03

1. 65E+02 2.88E-03 8.23E-05 0.OOE+00 0.OOE+00 0.OOE+00 7.22E+03 0.OOE+00 5.56E+02 4.77E+02 6.47E+02 0.OOE+00 1.06E+04 7.74E+04 8.95E+01 4.98E+03 2.21E-01 3.33E+03 9.48E+03 1.82E+03 1.18E+04 1.16E+04 1.23E-01 7.74E-01

3. 11E+04

7. 18E-03 3.81E+02 4.OOE+02 2.04E+01 8.82E+04 2.87E+02 2.06E+02 1.14E+04 2.59E+06 3.46E+00 3.91E-01 8.82E+01 1.39E-02

1. 57E+04 4.61E-01 4.07E+00 2.03E+04 1.17E+01 3.78E+03 3.23E+01 3.72E-02 8.12E-04 6.79E+02 4.10E-01 1.09E+04 5.OOE+03 0.OOE+00 1.20E+04

1. 09E+04 6.47E+02 0.OOE+00 1.06E+04 0.OOE+00 5.75E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.01E+02 6.23E+01 6.47E+02 0.OOE+00

1. 06E+04 0.OOE+00 1.32E+01 4.98E+03 1.10E+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 3.98E+00 3.25E+04 4.02E-02 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 3.11E+04 2.59E+01 4.72E+03 2.65E+02 3.11E-02 9.79E-04 4.24E+03 8.99E-01 1.07E+05

1. 09E+04 0.OOE+00 0.OOE+00

0. OOE+00 6.47E+02

0. OOE+00 1.06E+04 0.OOE+00 1.28E+04 1.OOE+06 1.25E+04 8.69E+04 1.02E+06 7.77E+05 4.51E+06 2.09E+05 8.12E+03 9.30E+03 6.47E+05 1.47E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 2.03E+06 1.12E+07 5.26E+04 2.38E+04 2.69E+05 2.79E+03 2.45E+06 2.45E+04 7.64E+04

1. 75E+06

1. 10E+05 4.79E+05 1.35E+05

8. 11E+02 5.84E+02 5.52E+05 1.57E+04 1.16E+07 3.67E+06

0. OOE+00 2.65E+06 1.64E+06 6.47E+02 0.OOE+00 1.06E+04 1.61E+04 3.57E+02 7.06E+03 7.17E+04 1'.09E+03 2.48E+04

1. llE+04 3.19E+04 2.42E+03 5.01E+04 1.50E+04 S. 14E+04 1.32E+04 0.OOE+00 0.OOE+00

0. OOE+00 3.04E+03 3.39E+02 6.82E+01 6.40E+04 1.31E+05 7.34E+04 1.40E+05

1. 04E+05 2.35E+03 7.03E+04 1.27E+05 1.67E+05 2.17E+04 1.40E+05 1.27E+04 4.87E+04 2.03E+03 8.44E+02 1.61E+04 4.84E+04 1.64E+05 3.30E+04 0.OOE+00 5.91E+04 1.47E+04 Indian Point 2 Page 58 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-lOd 3

(mrem/yr per ucifm )

INFANT INHALATION Ri(I)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 1-133 I-134 1-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 4.76E+03 1.67E+04 2.23E+04 1.41E+04 7.88E-02 1.07E+02 1.74E-02 3.72E+02 6.36E+03 3.79E+04 1.69E+03 1.32E+04 9.21E+02 3.86E+03 3.96E+05 4.83E+04 5.49E+05 5.05E+02 1.48E+00 5.60E+04 1.57E-01

3. 98E-02 5.05E+02 1.03E+00 2.77E+04 2.93E+02 3.19E+06 1.4OE+04 4.79E-02 7.94E+03 1.3OE+01 3.71E+02

0. OOE+00 o.OOE+00 3.78E+04 0.OOE+00 0.OOE+00 3.42E-01 0.OOE+00 8.40E+04 2.66E+05 4.45E-02 0.OOE+00 0.OOE+00 1.99E+03 6.90E+03 9.53E-01 6.09E+03 3.47E-02 5.50E+01 8.22E-03 2.37E+02 1.39E+04 4.44E+04 3.54E+03

1. 92E+04 1.88E+03 7.60E+03 7.03E+05 1.35E+05 6.12E+05 7.81E+02 9.84E-04

5. 60E+01

1. 08E-04 3.30E-05 2.OOE+02 3.77E-01

1. 67E+04

1. 93E+02 1.21E+06 5.24E+03 1.85E-02

8. 13E+03 9.02E+00 3.32E+01 0.OOE+00 6.51E+02 0.OOE+00

0. OOE+00

0. OOE+00 7.29E-02 3.64E+05 2.24E+03 2.38E+03 2.86E-02

0. OOE+00

0. OOE+00 6.58E+02 2.07E+03 4.89E-01 2.23E+03 1.88E-02 3.63E+01 5.OOE-03

1. 76E+02 5.57E+03

1. 96E+04 1.26E+03 5.60E+03 6.65E+02 2.77E+03 7.45E+04 5.29E+04 4.55E+04 3.98E+02 4.30E-02 2.90E+03 4.97E-03 1.96E-03 5.15E+01 9.04E-02 1.99E+03 2.21E+01 1.76E+05 6.99E+02 2.41E-03 5.OOE+02 3.12E+00 1.88E+01 0.OOE+00 6.41E+02 7.56E+03 0.OOE+00 0.OOE+00 2.63E-02 1.40E+04 5.04E+03 1.82E+04 2.35E-02 0.OOE+00 0.OOE+00 1.62E+03 4.87E+03 1.85E+00 5.47E+03 6.75E-02 8.93E+01 1.58E-02 2.79E+02

1. 60E+06 1.48E+07 1.69E+05 3.56E+06 4.45E+04 6.96E+05

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

1. 82E+03 0.OOE+00 4.07E-02

0. OOE+00

0. OOE+00 0.OOE+00 3.75E+04 4.86E+00 3.18E+04 1.75E-01 2.65E+02 3.99E-02 1.03E+03 1.53E+04 5.18E+04 3.95E+03 2.24E+04 2.09E+03 8.47E+03

1. 90E+05 5.64E+04

1. 72E+05

4. 10E+02 5.92E-04 1.34E+01 6.50E-05 1.90E-05 0.OOE+00 0.OOE+00 5.25E+03 5.64E+01 5.38E+05

1. 97E+03 6.72E-03 3.15E+03 0.OOE+00 6.62E+01

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.70E-02 2.80E+05 0.OOE+00 1.25E+01 1.34E-01

0. OOE+00 0.OOE+00 4.47E+05 1.31E+06 1.03E+04 1.68E+06 3.OOE+03 1.99E+05 2.06E+03 3.40E+05 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.97E+04 1.18E+04 7.13E+04 6.54E+01 5.95E+03 1.60E+06 2.97E+03 1.55E+03 1.68E+05 8.22E+03 5.17E+05 1.16E+05 9.84E+06 4.33E+05 1.61E+03 3.22E+05 3.96E+04

5. 95E+04 0.OOE+00 3.79E+05 4.20E+05 0.OOE+00 0.OOE+00 3.32E+03

8. 68E+05

1. 09E+06 1.27E+06

4. 10E+03

0. OOE+00 0.OOE+00 1.29E+04 2.73E+04 2.44E+04 6.90E+04 2.63E+04 1.19E+05 8.22E+03 4.41E+04

1. 99E+03

1. 06E+03

1. 90E+03 2.16E+03 1.29E+03 1.83E+03 1.33E+03 1.43E+03 1.33E+03

8. 76E+02

5. 10E+04 3.84E+04 4.75E+03 6.93E+02 8.48E+04 5.95E+04 2.16E+04 4.97E+04 1.48E+05 3.72E+04 4.28E+03 3.12E+04 3.56E+04 2.49E+04

0. OOE+00 4.86E+03 6.72E+03 0.OOE+00 0.OOE+00 2.69E+04

1. 12E+04 1.68E+03 1.08E+04 3.54E+03

0. OOE+00

0. OOE+00 Indian Point 2 Page 59 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-lla ADULT INGESTION (Leafy Vegetable)

Ri(V) 2 M

3 (H-3:

mrem/yr per uCi/m mrem/yr per uCi/sec Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 0.OOE+00 9.36E+04 2.69E+05 1.40E+09 0.OOE+00 0.OOE+00 0.OOE+00 2.10E+08 1.26E+08 0.OOE+00 0.OOE+00 1.04E+10 6.15E+01 0.OOE+00 3.17E+08 8.73E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 9.96E+09 6.05E+l1 3.05E+05 4.27E+02 1.33E+04 5.22E-09

5. 11E+06 9.15E-01

1. 70E+02

1. 17E+06 3.37E+02 1.43E+05 0.OOE+00 3.10E+00 8.22E-31 4.76E+06 5.39E+01

1. 93E+08 1.05E+07 2.80E+05 1.04E+08 1.37E+08 2.26E+03 2.11E+05 2.69E+05 8.73E+07

0. OOE+00 3.13E+08 1.59E+01 1.45E+08 2.96E+08 3.07E+07 1.67E+08 7.21E+08 7.99E+00 9.20E+03 1.01E+09 1.67E-05 0.OOE+00

0. OOE+00

0. OOE+00 2.19E+08 3.43E-22 1.39E-26 0.OOE+00 0.00E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.00E+00 0.OOE+00 3.77E+05 6.81E+01

7. 94E+04 6.15E+06 8.77E+00 1.18E-30 0.OOE+00 0.OOE+00

0. OOE+00 9.75E+06 6.43E+03

1. 96E+06

1. 53E+06 2.26E+03

1. 05E+05 2.69E+05 5.43E+07 4.64E+04

5. 97E+07 2.82E+00 3.38E+07 1.13E+08 6.89E+07 3.69E+08 3.49E+08 3.64E+00 4.32E+03 4.56E+08 1.16E-06

3. 11E+00 2.48E-11

0. OOE+00 1.02E+08 1.82E-22 9.74E-27 2.86E+08 1.48E+11 1.23E+04 1.85E+01 3.56E+02 2.02E-10 1.37E+05 2.68E-02 4.68E+00 2.55E+05 3.11E+01 4.27E+04 1.17E+06 1.12E+02 1.16E-29 2.05E+06 2.13E+01 2.44E+07 5.79E+06 9.65E+04 4.07E+07 3.25E+07 2.26E+03 0.00E+00 2.69E+05 0.00E+00 2.78E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.34E+03 2.52E+05 1.39E+05 2.26E+03 2.22E+05 2.69E+05 0.00E+00 1.02E+04 9.31E+07 2.02E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 2.32E+04 6.75E+08 1.09E-05 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

5. 91E+05

1. 03E+02

7. 85E+04 1.39E+07 1.33E+02 2.13E-29

1. 82E+07 6.96E+02 3.72E+08 1.92E+07 0.00E+00 0.00E+00 0.00E+00 2.26E+03 0.OOE+00 2.69E+05 0.00E+00 6.16E+04 0.00E+00 0.00E+00 8.08E+07 8.27E+07 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00

0. OOE+00 0.00E+00 0.00E+00

0. 00E+00

0. 00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 4.30E+00 6.05E-31 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.68E+05

8. 07E+07 1.05E+08 2.26E+03 3.65E+07 2.69E+05 1.58E+08 1.17E+07 9.58E+08 5.07E+02 8.31E+07 9.86E+08 6.23E+08 3.14E+09 1.50E+08 2.03E+02 7.84E+05 6.36E+08 2.51E-06 4.47E+00 1.94E-16 0.OOE+00 4.33E+07 4.74E-33 8.05E-40 1.60E+09 1.75E+10 1.45E+06 8.45E+03 1.41E+08 1.53E-08 2.81E+09 1.60E+04 5.38E+06 1.19E+09 2.11E+07 4.82E+08 1.43E+07 5.19E+03 3.56E-42 5.56E+08 3.29E+04 1.25E+10 3.98E+09 1.06E+08 2.94E+09 1.50E+09 Indian Point 2 Page 60 Revision 9

ODCM Part 11-Calculational Methodologies Table 2-lla 2

m ADULT INGESTION (Leafy Vegetable)

Ri(V) mrem/yr per uCi/sec (H-3:

mrem/yr 3

per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 1-132 1-133 I-134 1-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 9.66E+07 3.49E+08 5.66E+03 2.51E+08 7.62E-04 9.12E+05 1.50E-15 4.30E+06 3.92E+05 8.08E+07

5. 76E+01 2.09E+06 9.65E-05 3.90E+04 4.67E+09 4.24E+07 6.36E+09 3.91E-11 2.68E-02 1.28E+08

1. 15E-21 2.46E-39 1.98E+03 1.41E-04 1.97E+05 9.98E+02 3.29E+07 6.26E+04 3.09E-26 3.33E+04 3.82E+04 1.43E+03 O. OOE+O0

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 2.15E-06 0.OOE+00 0.OOE+00

0. OOE+00 3.56E-08

0. OOE+00 0.OOE+00 3.50E+07 1.25E+08 2.03E+03 9.38E+07 2.87E-04 4.46E+05 6.27E-16 2.78E+06 1.16E+06 1.16E+08 1.54E+02 3.63E+06 2.62E-04

1. 02E+05

1. 11E+10 1.68E+08 8.70E+09 7.73E-11 1.91E-05 1.61E+05 8.70E-25 2.53E-42 9.98E+02 6.43E-05 1.33E+05 7.38E+05 1.38E+07 2.51E+04 1.28E-26 3.85E+04 3.19E+04 1.41E+02 O. OOE+00 1.17E+07

0. OOE+00

0. OOE+00 0.OOE+00 5.45E-07

0. OOE+00

0. OOE+00 2.33E-08 0.OOE+00 0.OOE+00 1.29E+07 4.26E+07 1.22E+03 3.98E+07 1.86E-04 3.72E+05 4.74E-16 2.61E+06 4.57E+05 6.62E+07 5.39E+01

1. 11E+06 9.38E-05 3.77E+04 9.08E+09 1.21E+08 5.70E+09 3.83E-11 7.86E-04 8.38E+06 3.89E-23 1.55E-40 2.64E+02 1.60E-05 1.51E+04 8.16E+01

1. 77E+06

3. 10E+03 1.57E-27 2.31E+03

1. 12E+04 7.76E+01 O. OOE+00

1. 95E+07 0.OOE+00 0.OOE+00 0.OOE+00 1.99E-07 0.OOE+00 0.OOE+00

0. OOE+00 1.43E-08 0.OOE+00 0.OOE+00 2.90E+07 8.92E+07 4.19E+03 8.63E+07

5. 85E-04 7.06E+05 1.23E-15 3.07E+06 9.81E+07 3.79E+10 5.39E+03 5.33E+08 4.54E-03 6.73E+06

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 3.11E-08 0.OOE+00

0. OOE+00 3.93E+08 1.42E+09 2.31E+04 1.05E+09 3.20E-03 4.52E+06 6.57E-15 2.68E+07 1.81E+06

1. 98E+08 2.45E+02 6.33E+06 4.17E-04 1.64E+05 3.59E+09 9.32E+07 2.95E+09 5.68E-11 1.79E-05 5.46E+04

8. 09E-25 2.14E-42 0.OOE+00 0.OOE+00 6.19E+04 3.25E+02

8. 16E+06 1.45E+04 7.23E-27 2.25E+04 0.OOE+00 4.39E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.35E-07 0.OOE+00 0.OOE+00 0.OOE+00 2.25E-07 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

1. 19E+09 1.28E+07 9.81E+08 5.61E-12 1.08E-05 9.2OE+04 4.94E-25 1.43E-42 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.86E+08 1.17E+09 4.47E+05 1.27E+09 5.75E-04 4.43E+07 2.13E-16 1.32E+08 9.96E+05 3.05E+07 2.89E+01 3.26E+06 2.29E-07 1.15E+05 1.94E+08 1.90E+07 1.68E+08 3.30E-16 4.76E-02 2.63E+08 5.43E-31 0.OOE+00 7.33E+07 4.69E-01 5.10E+08 2.76E+07

1. 11E+10 2.74E+08 4.44E-33 1.85E+08 1.05E+07 2.89E+07 0.OOE+00 2.97E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.01E-03 0.OOE+00 0.OOE+00 0.OOE+00 3.95E-11 0.00E+00 0.OOE+00 Indian Point 2 Page 61 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-llb 2

m

mrem/y TEEN INGESTION (Leafy Vegetable)

Ri(V) yr per uCi/sec (H-3:

mrem/yr 3

per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-9lm Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-ll0m Sb-122 Sb-124 Sb-125 0.OOE+00 1.43E+05 2.39E+05 1.61E+09 0.OOE+00 0.OOE+00 0.OOE+00 3.26E+08 1.79E+08 0.OOE+00 0.OOE+00 1.61E+10 5.72E+01 0.OOE+00 4.24E+08 8.18E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.51E+10 7.51E+11 2.85E+05 3.97E+02 1.24E+04 4.86E-09 7.84E+06 8.60E-01 1.59E+02 1.72E+06 3.12E+02 1.93E+05 0.OOE+00 2.74E+00 7.64E-31 6.81E+06 5.OOE+01 3.10E+08

1. 52E+07 3.03E+05 1.54E+08 2.14E+08 2.59E+03 3.20E+05 2.39E+05 9.97E+07

0. OOE+00 4.54E+08 1.43E+01 2.31E+08 4.18E+08 4.36E+07 2.49E+08 1.13E+09 7.31E+00 8.34E+03 1.47E+09 1.56E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.74E+08 3.17E-22 1.25E-26

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 5.43E+05

6. 18E+01

1. 07E+05 5.65E+06 7.63E+00 1.09E-30

0. OOE+00 0.OOE+00 0.OOE+00 1.43E+07 5.89E+03 2.84E+06 2.34E+06 2.59E+03 1.60E+05 2.39E+05 6.24E+07 6.17E+04

9. 01E+07 2.55E+00 5.39E+07 1.61E+08

1. OOE+08 5.60E+08 5.45E+08 3.33E+00 3.92E+03 6.86E+08 1.09E-06 2.91E+00 2.25E-11

0. OOE+00 1.29E+08 1.69E-22 8.82E-27 4.33E+08

1. 85E+11 1.13E+04 1.69E+01 3.34E+02 1.86E-10 2.10E+05 2.49E-02 4.36E+00 3.73E+05 2.85E+01 5.89E+04 1.08E+06 9.89E+01 1.07E-29 2.91E+06 1.94E+01 3.90E+07 8.72E+06 8.85E+04 6.02E+07

5. OOE+07 2.59E+03 0.OOE+00 2.39E+05 0.OOE+00 3.43E+04

'0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. 00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00

0. OOE+00 0.00E+00 3.85E+03 3.50E+05 2.04E+05 2.59E+03 3.39E+05 2.39E+05 0.00E+00 1.3SE+04 1.36E+08 1.81E+01 0.00E+00 0.00E+00

0. OOE+00 0.00E+00 0.00E+00 0.00E+00 2.11E+04 9.42E+08 1.02E-05 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 7.98E+05 9.37E+01 1.04E+05 1.29E+07 1.14E+02 1.97E-29 2.40E+07 6.31E+02 5.97E+08 2.74E+07 0.00E+00 0.00E+00 0.00E+00 2.59E+03 0.00E+00 2.39E+05 0.00E+00 8.81E+04 0.00E+00 0.00E+00 1.47E+08 1.32E+08 0.OOE+00

0. OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00

0. 00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00

0. OOE+00 0.00E+00 0.OOE+00 0.00E+00 4.24E+00 6.62E-31 0.OOE+00 0.00E+00

0. OOE+00 0.00E+00 1.89E+05 1.34E+08

1. 86E+08 2.59E+03 3.90E+07 2.39E+05 1.35E+08

1. 04E+07 9.32E+08 9.44E+02 1.00E+08 9.88E+08 6.01E+08 3.24E+09 1.81E+08 3.97E+02 6.47E+05 6.23E+08 2.87E-05 0.00E+00 0.OOE+00

0. 00E+00 4.05E+07 2.71E-29 1.91E-35 1.80E+09 2.11E+10 1.29E+06 1.01E+04

1. 02E+08 2.29E-07 3.21E+09 2.36E+04 4.86E+06 1.25E+09

1. 67E+07 4.57E+08 1.01E+07 5.01E+03 1.86E-37 5.69E+08 4.04E+04 1.48E+10 4.03E+09 6.35E+07 3.11E+09 1.66E+09 Indian Point 2 Page 62 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-llb TEEN INGESTION (Leafy Vegetable)

Ri(V) 2 m

mrem/yr per uCi/sec 3

(H-3:

mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 1-133 1-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 1.48E+08 5.51E+08 5.34E+03 3.62E+08 7.14E-04 8.44E+05 1.39E-15 3.91E+06 3.51E+05 7.69E+07 5.19E+01

1. 94E+06 8.73E-05 3.52E+04 7.10E+09 4.34E+07 1.01E+10 3.61E-1l 2.52E-02 1.37E+08 1.08E-21 2.27E-39

1. 81E+03 1.30E-04 2.83E+05 9.33E+02 5.27E+07 7.OOE+04 2.89E-26 3.62E+04 3.55E+04 1.39E+03 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.OOE-06 0.OOE+00

0. OOE+00 0.OOE+00 3.23E-08 0.OOE+00 0.OOE+00

5. 34E+07

1. 96E+08 1.89E+03 1.34E+08 2.66E-04

4. 05E+05 5.75E-16 2.47E+06 1.01E+06 1.08E+08 1.36E+02 3.29E+06 2.31E-04 9.07E+04 1.67E+10

1. 71E+08 1.35E+10 6.93E-11 1.78E-05 1.68E+05 8.04E-25 2.27E-42 8.89E+02 5.76E-05 1.89E+05 6.79E+05 2.18E+07 2.80E+04 1.18E-26 3.94E+04 2.90E+04 1.31E+02 0.OOE+00

1. 79E+07

0. OOE+00

0. OOE+00 4.95E-07 0.OOE+00

0. OOE+00

0. OOE+00 2.07E-08 0.OOE+00 0.OOE+00 1.98E+07 6.56E+07 1.15E+03

5. 73E+07 1.74E-04 3.38E+05 4.36E-16 2.33E+06 4.05E+05 5.78E+07 4.88E+01 1.00E+06 8.31E-05 3.36E+04 7.75E+09 1.15E+08 4.69E+09 3.47E-11 7.35E-04 8.85E+06 3.59E-23 1.40E-40 2.37E+02 1.43E-05 2.17E+04 7.58E+01 2.83E+06 3.49E+03 1.47E-27 2.36E+03 1.02E+04 7.28E+01 O.OOE+00 3.OOE+07 0.OOE+00

0. OOE+00 0.OOE+00 1.81E-07 0.OOE+00

0. OOE+00 0.OOE+00 2.17E-08

0. OOE+00

0. OOE+00 4.14E+07 1.31E+08 3.68E+03

1. 17E+08

5. 10E-04 6.09E+05 1.07E-15 2.61E+06 8.28E+07 3.14E+10 4.58E+03 4.59E+08 3.85E-03 5.83E+06 0.OOE+00 0.OOE+00 0.00E+00

0. 00E+00

0. 00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

0. OOE+00

0. OOE+00 0.OOE+00 0.00E+00 0.00E+00

0. OOE+00 0.00E+00

0. 00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 2.65E-08

0. OOE+00

0. 00E+00

0. OOE+00 2.24E+09 2.16E+04 1.51E+09 3.00E-03 4.22E+06 6.10E-15 2.37E+07 1.56E+06 1.85E+08 2.14E+02 S. 76E+06 3.65E-04 1.43E+05 5.3lE+09 9.30E+07 4.59E+09 5.12E-11 1.67E-05 5.70E+04 7.46E-25

1. 92E-42

0. 00E+00 0.OOE+00 8.89E+04 3.04E+02 1.3OE+07 1.63E+04 6.80E-27 2.31E+04 0.OOE+00

4. 11E+02

0. 00E+00

0. 00E+00 0.OOE+00 0.OOE+00 0.OOE+00 5.79E-07 0.OOE+00

0. OOE+00

0. OOE+00 1.98E-07 0.00E+00 0.00E+00

0. 00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

0. OOE+00

0. 00E+00

0. 00E+00 0.00E+00 2.03E+09 1.47E+07 1.78E+09 5.96E-12 1.22E-05

1. 13E+05 5.50E-25 1.51E-42 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

0. OOE+00

0. 00E+00 0.00E+00

0. 00E+00

0. OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.0OE+00

0. OOE+00

0. 00E+00 0.00E+00 4.37E+08 1.37E+09 4.12E+05 1.36E+09 3.90E-03 3.25E+07 1.14E-16 7.84E+07 7.80E+05 2.13E+07 5.92E+01 2.49E+06 3.05E-06 1.00E+05 2.08E+08 1.37E+07

1. 92E+08 3.15E-14 2.25E-01 2.12E+08 2.29E-27

0. 00E+00 5.11E+07 1.75E+00 5.40E+08 2.04E+07 1.33E+10 2.30E+08 3.19E-29 1.42E+08 7.84E+06 2.11E+07 0.00E+00 3.33E+08 0.OOE+00

0. 00E+00 0.00E+00 1.18E-02 0.OOE+00 0.00E+00 0.OOE+00 1.20E-09 0.OOE+00 0.OOE+00 Indian Point 2 Page 63 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-llc CHILD INGESTION (Leafy Vegetable)

Ri(V) 2 m

mrem/yr per uCi/sec (H-3:

mrem/yr per uCi/m3)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-ll0m Sb-122 Sb-124 Sb-125 0.OOE+00 3.37E+05 3.73E+05 3.37E+09

0. OOE+00

0. OOE+00 0.OOE+00 8.01E+08 3.97E+08 0.OOE+00 0.OOE+00 3.95E+10 1.05E+02 0.OOE+00 8.12E+08

1. 51E-05 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 3.59E+10 1.24E+12 5.24E+05 7.28E+02 2.30E+04 8.91E-09

1. 86E+07 1.58E+00 2.93E+02

3. 86E+06 5.70E+02 4.12E+05 0.00E+00 4.71E+00 1.41E-30 1.53E+07 9.16E+01 7.45E+08 3.21E+07 5.58E+05 3.52E+08

4. 99E+08 4.01E+03 5.72E+05 3.73E+05 1.58E+08 0.OOE+00 6.65E+08

1. 88E+01 4.25E+08 6.42E+08 6.44E+07 3.78E+08 2.11E+09 9.89E+00 1.10E+04 2.16E+09 2.18E-05

0. OOE+00

0. OOE+00 4.52E+08 4.37E-22 1.64E-26 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 8.48E+05 8.24E+01 1.60E+05 7.71E+06 9.24E+00 1.47E-30 0.OOE+00

0. OOE+00

0. OOE+00 2.17E+07 8.24E+03 4.56E+06 3.84E+06

4. 01E+03 3.77E+05 3.73E+05 1.3OE+08

1. 17E+05 1.77E+08 4.24E+00 1.32E+08 3.20E+08

1. 97E+08 1.12E+09 1.34E+09 5.77E+00 6.64E+03 1.35E+09 2.02E-06 5.37E+00 3.82E-11 0.OOE+00 2.78E+08 3.04E-22 1.46E-26

1. 03E+09 3.15E+1l

1. 98E+04 2.92E+01 6.17E+02 3.24E-10 4.99E+05 4.53E-02 8.04E+00 7.55Ei05 4.86E+01 1.15E+05 1.91E+06 1.53E+02 1.87E-29 5.88E+06 3.32E+01 9.3OE+07 1.73E+07 1.64E+05 1.23E+08 1.05E+08

4. 01E+03 0.OOE+00 3.73E+05 0.OOE+00 6.50E+04 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 o.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

7. 16E+03 7.73E+05 4.63E+05

4. 01E+03 5.63E+05 3.73E+05

0. OOE+00

1. 78E+04

1. 86E+08 2.27E+01

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 2.66E+04 1.36E+09 1.32E-05 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.21E+06

1. 18E+02 1.51E+05 1.65E+07 1.34E+02 2.51E-29 3.85E+07 8.05E+02 1.01E+09 4.04E+07 0.OOE+00

0. OOE+00

0. OOE+00 4.01E+03 0.OOE+00 3.73E+05 0.OOE+00 1.19E+05 0.OOE+00 0.OOE+00 2.40E+08 1.86E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 4.69E+00 7.78E-31 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.27E+05 1.95E+08 2.78E+08 4.01E+03 3.20E+07 3.73E+05 9.31E+07 6.21E+06

5. 58E+08 2.72E+03 7.87E+07 6.68E+08 3.76E+08 2.10E+09 1.42E+08 1.21E+03 5.16E+05 3.80E+08 1.37E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.91E+07 2.15E-23 1.43E-28 1.39E+09 1.67E+10

1. 16E+06 1.38E+04 6.56E+07 1.74E-05 2.48E+09 4.58E+04 4.37E+06 8.84E+08 1.25E+07 2.97E+08 6.38E+06 5.26E+03 4.68E-30 3.96E+08

5. 98E+04 1.16E+10 2.58E+09 4.30E+07 2.20E+09 1.19E+09 Indian Point 2 Page 64 Revision 9

ODCM Part 11 - Calculational Methodologies.

Table 2-llc CHILD INGESTION (Leafy Vegetable)

Ri(V) 2 mn

mrem/yr per uCi/sec 3

(H-3:

miremfyr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 3.51E+08 1.32E+09 9.85E+03 8.41E+08 1.32E-03 1.54E+06 2.57E-15 7.OOE+06 6.16E+05 1.43E+08 9.22E+01 3.53E+06 1.55E-04 6.26E+04 1.60E+10 8.17E+07 2.39E+10 6.57E-11 4.65E-02 2.75E+08

1. 99E-21

4. 11E-39 3.25E+03 2.35E-04 6.56E+05 1.72E+03

1. 27E+08 1.46E+05 5.37E-26 7.15E+04 6.47E+04 2.57E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.64E-06 0.OOE+00 0.OOE+00 0.OOE+00 5.76E-08 0.OOE+00

0. OOE+00 9.50E+07 3.56E+08 2.65E+03 2.35E+08 3.69E-04 5.33E+05 7.83E-16

3. 10E+06 1.24E+06 1.44E+08 1.69E+02 4.37E+06 2.88E-04 1.13E+05 2.63E+10 2.25E+08 2.29E+10 9.13E-11 2.48E-05 2.41E+05 1.11E-24 2.96E-42

1. 14E+03 7.49E-05 3.27E+05 9.31E+05 3.98E+07 4.37E+04 1.66E-26 5.79E+04 3.83E+04 1.84E+02 0.OOE+00 2.99E+07 0.OOE+00 0.OOE+00 0.00E+00 6.57E-07 0.OOE+00 0.OOE+00

0. OOE+00 2.59E-08 0.OOE+00

0. OOE+00 4.67E+07 1.57E+08 2.11E+03 1.31E+08 3.14E-04 5.68E+05 7.64E-16 3.74E+06 6.41E+05 8.17E+07 7.79E+01 1.65E+06 1.32E-04 5.33E+04 5.55E+09 1.45E+08 3.38E+09 5.79E-11 1.35E-03

1. 60E+07 6.47E-23 2.29E-40 3.83E+02 2.35E-05 4.86E+04 1.35E+02 6.78E+06 7.23E+03 2.70E-27 4.48E+03

1. 72E+04 1.29E+02 O.OOE+00 6.04E+07 0.OOE+00

0. OOE+00

0. OOE+00 3.07E-07

0. OOE+00

0. OOE+00 0.OOE+00 3.46E-08

0. OOE+00 0.OOE+00 9.84E+07 3.16E+08 6.81E+03 2.71E+08 9.43E-04 1.10E+06 1.97E-15 4.51E+06 1.37E+08 4.75E+10 7.86E+03

8. 11E+08 6.62E-03 9.97E+06 0.OOE+00 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.56E-08 0.OOE+00

0. OOE+00 0.OOE+00 3.77E+09 2.80E+04 2.47E+09 3.87E-03

5. 16E+06 7.77E-15 2.88E+07 1.86E+06 2.36E+08 2.59E+02 7.28E+06 4.40E-04 1.73E+05 8.15E+09 1.20E+08 7.46E+09 6.43E-11 2.17E-05 7.84E+04 9.62E-25 2.39E-42 0.OOE+00 0.OOE+00 1.43E+05 3.91E+02 2.21E+07 2.37E+04 8.79E-27 3.18E+04 0.OOE+00 5.33E+02

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 7.29E-07 0.OOE+00 0.OOE+00

0. OOE+00 2.40E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 2.93E+09 1.78E+07 2.68E+09 6.91E-12 1.46E-05 1.44E+05 6.53E-24

1. 74E-42 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.38E+08 1.07E+09

.3. 85E+05 1.03E+09 8.23E-02 2.16E+07 1.35E-14 3.12E+07 5.82E+05 1.28E+07 1.99E+02 1.76E+06

1. 91E-04 8.58E+04 1.42E+08 7.90E+06 1.43E+08 4.21E-11 2.69E+00 1.39E+08

1. 13E-21 5.36E-41 3.17E+07 1.48E+01 4.08E+08 1.36E+07 1.04E+10 1.57E+08 3.58E-23 9.17E+07 5.38E+06 1.36E+07 0.OOE+00 2.45E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.03E-01 0.OOE+00 0.OOE+00

0. OOE+00 2.63E-07 0.OOE+00 0.00E+00 Indian Point 2 Page 65 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-12 Total Body & Skin Ground Plane Dose Factors Ri(G) and Ri(S) 2 (m

mrem/yr per uCi/sec)

-1 (sec)

Isotope Decay Constant Ri(G)

Ri(S)

H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-lOrm Sb-122 Sb-124 Sb-125 1.780E-09 1.505E-07 1.284E-05 5.614E-07 2.896E-07 2.567E-08 7.467E-05 8.141E-09 1.802E-07 1.133E-07 4.170E-09 2.290E-10 7.641E-05 1.516E-05 3.289E-08 2.027E-04 8.056E-05 3.633E-04 3.851E-03 4.299E-07 6.490E-04 7.600E-04 1.589E-07 7.548E-10 2.027E-05 7.105E-05 3.008E-06 2.324E-04 1.371E-07 5.439E-05 1.906E-05 1.254E-07 1.139E-05 2.282E-07 2.917E-06 3.198E-05 8.136E-04 2.042E-07 4.337E-05 2.179E-08 3.210E-08 2.971E-06 1.333E-07 7.935E-09 O.OOE+O0 O.OOE+O0

1. 19E+07 O.OOE+00 4.66E+06 1.39E+09 9.03E+05 O. OOE+0O 2.72E+08 3.79E+08 2.15E+10 O.OOE+OO 2.97E+05 6.07E+05 7.46E+08

0. OOE+00 4.87E+03 2.03E+05 O.OOE+0O 8.99E+06 3.31E+04 1.21E+05 2.16E+04 O.OOE+00 2.15E+06 7.77E+05 4.48E+03

1. OOE+05

1. 07E+06 1.80E+05 1.83E+05 2.45E+08 2.96E+06

1. 37E+08 3.99E+06 1.84E+05 2.04E+04 1.08E+08 6.36E+05 4.22E+08 3.44E+09

0. OOE+O0

5. 98E+08 2.34E+09 O. OOE+00 O. OOE+00 1.39E*07

0. OOE+O0 5.51E+06 1.62E+09 1.07E+06

0. OOE+OO 3.20E+08 4.44E+08 2.53E+10 O.OOE+00 3.45E+05 6.88E+05 8.58E+08 O. OOE+00 7.08E+03 2.36E+05 O.OOE+O0 1.03E+07 3.78E+04 1.45E+05 2.51E+04 O. OOE+O0 2.51E+06 8.63E+05 5.3OE+03

1. 16E+05 1.21E+06 2.14E+05 2.51E+05 2.84E+08 3.44E+06

1. 61E+08 4.62E+06

2. 11E+05 2.26E+04 1.26E+08 7.21E+05 5.07E+08 4.01E+09 O. OOE+0O 6.90E+08 2.64E+09 Indian Point 2 Page 66 Revision 9

ODCM Part 11 - Calculational Methodologies Table 2-12 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 6.418E-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 I-131 9.978E-07 1.72E+07 2.09E+07 I-132 8.371E-05 1.25E+06 1.46E+06 I-133 9.257E-06 2.45E+06 2.98E+06 I-134 2.196E-04 4.47E+05 5.30E+05 I-135 2.913E-05 2.53E+06 2.95E+06 Cs-134 1.066E-08 6.86E+09 8.OOE+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 l.090E-03 4.44E+04 5.06E+04 La-140 4.781E-06 1.92E+07 2.18E+07 La-142 1.249E-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 O.OOE+00 O.OOE+00 Pr-144 6.685E-04 1.83E+03 2.11E+03 Nd-147 7.306E-07 8.39E+06 l.O1E+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 O.OOE+00 O.OOE+00 Co-57 2.961E-08 1.88E+08 2.07E+08 Sr-85 1.237E-07 O.OOE+00 O.OOE+00 Y-88 7.523E-08 O.OOE+00 O.OOE+00 Nb-94 1.083E-12 O.OOE+00 O.OOE+00 Nb-97 1.602E-04 1.76E+05 2.07E+05 Cd-109 1.729E-08 O.OOE+00 O.OOE+00 Sn-113 6.970E-08 O.OOE+00 O.OOE+00 Ba-133 2.047E-09 O.OOE+00 O.OOE+00 Te-134 2.764E-04 2.22E+04 2.66E+04 Ce-139 5.828E-08 O.OOE+00 O.OOE+00 Hg-203 1.722E-07 O.OOE+00 O.OOE+00 Indian Point 2 Page 67 Revision 9

ODCM Part II - Calculational Methodologies 3.0 TOTAL DOSE DETERMINATIONS 3.1 10CFR190 Dose Evaluation RECS require that the impact of uranium fuel cycle activities be limited to 25 mrem to the whole body or any organ and 75 mrem to the thyroid of real identifiable individual in any twelve month period. Direct radiation effects are added to the effects of liquid and gaseous effluents. NUREG-133 section 3.8 may be used to show compliance. Site and environmental TLD results may be incorporated along with projected doses to show compliance. 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 2.5, 2.6, and 2.7, due the application of multiplicative occupancy factors. These factors are determined by comparing the expected hours on site to 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months (the number of hours in a year, which is used in the calculations demonstrated in 2.5, 2.6, 2.7. 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 2.5 through 2.7, demonstrate that dose to these MEMBERS OF THE PUBLIC is negligible, despite any potential reduction in the atmospheric dispersion.

3.2 Doses From Liquid Releases If doses for real individuals are desired, the same calculational method for cumulative liquid dose can be used. However, more realistic assumptions regarding dilution, diet and occupancy can be employed. Actual levels of radionuclides in consumed foodstuffs, as shown in the Radiological Environmental Monitoring Program (REMP), can provide more meaningful information, in lieu of projected intakes using models only.

3.3 Doses From Atmospheric Releases Similarly, real individual methodology can be substituted for maximum individual modeling for airborne releases. Specific dose transfer factors can be used in lieu of weighted dose transfer factors. Information on the location and occupancy of real individuals, as well as more precise meteorological information and the consumption of foodstuffs, can be employed to show actual doses.

Data from the land use census can be used to either extend times from food production to consumption or otherwise show that the exposure of the critical receptors is reduced. Also, estimates of direct exposure through calculation may be supplanted by REMP results since these are often more indicative of the true impact at specific locations. Default values used in NUREG-01 33 and Reg Guide 1.109 methodology can be supplanted by more specific values.

Indian Point 2 Page 68 Revision 9

ODCM Part II - Calculational Methodologies 4.0 SETPOINT CALCULATIONS The RECS require alarm/trip setpoints for effluent monitors. Setpoints assure that alarm and trip actions occur such that limits of 1 OCFR20 at the release point in the unrestricted area are not instantaneously exceeded.

4.1 Liquid Effluent Monitor Setooirlts 4.1.1 Liquid Effluent Monitors have setpoints based on limiting the concentrations in the discharge canal to the MPCW identified in RECS D1.1 Monitor setpoints are inherently conservative due to the routine use of Circulating Water Pumps for liquid waste releases, and Service Water for continuous releases. In actuality, both Circulating and Service Water systems contribute to site dilution.

Alarm setpoints are calculated as follows:

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

F = Available discharge canal dilution flow for this release in gal/min f = calculated allowable release rate in gal/min ADC = Allowed Diluted Concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (beta and gamma emitters). This 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. This parameter is further clarified in Attachment E.

4.1.2 The basis for the WARN setpoint for Liquid Waste Effluent monitors (batch releases) is to ensure the contents of the batch tank have not changed since sampling. The warn setpoint for this type of monitor is calculated as follows:

WS

=

(C) * (M) where:

WS

=

Warn setpoint in uCVml 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%).

Liquid Effluent Radiation Monitor WARN setpoints do not control any auto functions but simply provide indication to operators. WARN setpoints for other monitors are typically set at approximately 75% of the ALARM value.

Indian Point 2 Page 69 Revision 9

ODCM Part II - Calculational Methodologies 4.1.3 Methods of determining a valid conversion factor (CF) for liquid effluent monitors are shown in Appendix F. These methods include direct measurement of process fluid with radiochemical analyses, as well as determining the CF from a NIST traceable mixture during primary calibration.

4.1.4 Additional conservatism is required for compliance with 10CFR20 if continuous (blowdown) releases are coincident with batch releases (distillate tanks).

Typically, at least 10,000 gpm from Service Water is apportioned to continuous releases to ensure sufficient dilution. However, if there is identified gamma activity in these continuous releases, the required dilution factor may need to be re-evaluated, apportioning circulator flow as necessary.

4.2 Gaseous Monitor Setpoints 1

4.2.1 Setpoints for gaseous monitors are based on the permissible discharge rates identified in Section 2.1 and demonstrated in Appendix I. These setpoints are inherently conservative due to the assumed mixture (Table 2-8) and the use of the most restrictive setpoints (annual average dose limit), which are used whenever practical. Higher release rates (for alarm setpoint considerations) may be authorized with the proper concurrence, as delineated in Section 2.1.

Permissible Discharge Rates (uCilsecl at Indian Point Unit 2 Basis of Limit Iodine/Particulate*

Noble Gases Annual Average 4.01 E-2 7.20E+3 Quarterly Average 8.02E-2 1.44E+4 Instantaneous 1.38E+1 7.OOE+4 Half-lives greater than 8 days These limits are not part of the RECS, but are included for information, as these limits are used for operational control of releases.

Derived in Appendix I for purposes of assurance of compliance with 1 OCFR20.

4.2.2 The Plant Vent radiation monitor (R-44), as well as most others, reads out in uCi/cc, so the maximum alarm set point is calculated as follows:

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

where:

S = Maximum alarm setpoint in ACi/cc D = Permissible discharge rate in ACisec F = Vent duct flow in ft3/min 4.72E+2 = unit conversion factor (28317 cc.min/ft3*60sec) 4.2.3 If the monitor reads and alarms in cpm, the conversion factor must be applied to convert the reading to uCi/cc.

Indian Point 2 Page 70 Revision 9

ODCM Part II - Calculational Methodologies 4.2.4 Normally, maximum allowable limits are calculated using a standard nuclide mix (Table 2-8). 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 partitioning (for all release points) to ensure site dose rate limits are not approached.

4.2.5 During normal operation, the unit 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 instantaneous limit.

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

4.3 Warn Alarms Warn alarms are set at the discretion of the CRS, generally 75% of the ALARM. They can be based on an application of 10CFR50 Appendix I limits, or a portion of the expected monitor response from preliminary grab sample results.

Indian Point 2 Page 71 Revision 9

ODCM Part II - Calculational Methodologies 5.0 LOWER LIMIT OF DETECTION 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):

2.71 +3.29s LLD=

T, T

E*V*k*Y*e-A' 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 giCi)

Y =

The fractional radiochemical yield (when applicable)

X =

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 Radiological Environmental Monitoring Program (REMP), uses an LLD formula that assumes equal background and sample count times (per the RECS). For the effluents program, the constants above are more appropriate. 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 DeterminationN. (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)

Indian Point 2 Page 72 Revision 9

ODCM Part 11 - Calculational Methodologies 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 priori (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 Critical Level concept is defined below. Following an experimental observation, one must decide whether or not a real signal was, in fact, detected. This type of binary qualitative decision is subject to two kinds of error:

1) deciding that radioactive material is present when it is not (a: Type I error), and the converse,

2) failing to decide that it is present when it is (b: Type 11 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.

L = ksb(1+Tb/Ts)5 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 RECS.

This calculation, if necessary, will be performed on a case by case basis.

Indian Point 2 Page 73 Revision 9

ODCM Part II - Calculational Methodologies REFERENCES

1.

Indian Point Unit 2 Technical Specifications.

2.

Indian Point Unit 2 Final Safety Analysis Report.

3.

1 OCFR20, "Standards for Protection Against Radiation."

4.

40CFR1 90, "Environmental Rad Protection Standards for Nuclear Power Operations."

5.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I."

6.

Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants."

1

7.

NUREG-0133, "Guidance Manual for Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."

8.

NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors."

9.

NYPA IP3-CALC-RAD-00001, Rev. 0, "IP3 - Revised ODCM Atmospheric Dispersion Parameters (Multi-Year Hourly Data, Mixed-Mode Releases and Valley Effects, 1994)" and the updated work from Entech Engineering: Reports P1 15-196-ECI, EC2, and EC3 (2004).

10.

G. Knoll, "Radiation Detection and Measurement," (1979)

11.

IPI-91-015N, "Commitments from March 26t Meeting on Shared Site Noble Gas Limits."

12.

IPI-91-019N, "Corrections to Memo IPI-91-015N."

13.

IPI-91-019, "IP2 and IP3 Isotope-Specific Site Boundary Atmospheric Dispersion Parameters (Mixed-Mode Releases)."

14.

JNH-91-020, "IP3 - Dispersion Parameters at the Nearest Residences and at 5 Miles."

15.

TS (RS) 92-24, "Ingestion Dose Factor Methodology."

16.

NPG (RS) 92-88, "Process and Effluent Monitor Energy Calibration."

17.

NPG (RS) 92-97, "Effective Stack Height for Blowdown Flash Tank Vent."

18.

New York University Medical Center, "Radiological Studies of the Hudson River Progress Report (1987-1988)" (1988).

19.

IP-CHM-96-050, "Updated IP3 ODCM and Unit 2 Impact."

20.

M.E. Wrenn and J.W. Lentsch, "The Fate of Gamma-Emitting Radionuclides Released into the Hudson River Estuary and an Evaluation of Their Environmental Significance", New York University Medical Center, Institute of Environmental Medicine, 1974.

21.

IPEC CHM-04-035, "Nuclide Mixtures for Instantaneous and Time Average Releases".

22.

IPEC CHM-05-003, "Site Specific Distances to Site Boundary and Nearest Resident".

23.

IPEC-CHM-05-022, "Altemative Methods for Liquid Rad Monitor Setpoints/ Conv Factors."

Indian Point 2 Page 74 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX A DISPERSION and DEPOSITION FACTORS X/Q highest of 16 sectors site boundary annual average relative concentration (sec/M3) [SSW]

(X/Q)r highest of 16 sectors nearest residence annual average relative concentration (sec/rn3) [SSW]

(X/Q)5 highest of 16 sectors at 5 miles annual average relative concentration (sec/rn3) [S] (used only when activated)

D/Q highest of 16 sectors site boundary annual average relative deposition (1/M2) [SSW]

(D/Q)r highest of 16 sectors nearest residence annual relative deposition (1/M2) [S]

(DIQ)5 highest of 16 sectors at 5 miles annual average relative deposition (1/rM2) [S] (used only when activated) 2.22E-6 (2.87E-5) 1.03E-6 (5.16E-6) 7.22E-7 1.41 E-8 (8.76E-8) 7.52E-9 (1.88E-8) 1.34E-9 Notes:

1) Ground-level values are shown parenthetically with each parameter, when applicable.

2) Ground-level deposition factors (DIQ) are provided, but not routinely utilized.

3) The bases information for these meteorological factors is provided in Reference 9.

Indian Point 2 Page 75 Revision 9

ODCM Part 11 - Calculational Methodologies APPENDIX B LIQUID EFFLUENT SIMPLIFIED FLOW DIAGRAM I canal

. canal canal LII

e.g.:

House Service Boilers Blowdown; Steam Condensate; Service Water Return; Utility Tunnel Sump (expectedly <LLD for gamma emitters in effluents).

Indian Point 2 Page 76 Revision 9

ODCM Part 11 - Calculational Methodologies APPENDIX C (Page 2 of 2)

GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM PlessM Rdef PRT Eductor Purr es

-e}

Unit2Vent --

t atmosphere Fuel S&oage Building F;-aatmosphee containment MOB

[Exbusatmosphere Blowoowr Fl.h B/D Flash Tank atmosphere Tant (llnit 2)

Vent (Unit 2)

B B/D Flash Tank atmosphere Tank (n Vent (Unit 1, for SBBPS)

from or unht B ExhaustUnit I Stack -

atmosphere Indian Point 2 Page 77 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX D STEAM PARTITION FACTOR CALCULATION (f)

The Steam Partition Factor f for the Unit 2 flash tank vent is given by:

f = hBD-180 970 For the secondary boiler blowdown purification system flash tank, the factor f is palculated by:

f =hBD -291 895 Where; hBD is the enthalpy of blowdown liquid, as taken from SOP 15.1, "Calorimetric Thermal Power Calculation," in BTU/Ibm. A typical value = 500 BTU/Ibm.

180 or 291 is the enthalpy of condensed water in each flash tank, in BTU/lbm 970 or 895 is the enthalpy of associated with the latent heat of vaporization in each tank, in BTU/lbm f

= A multiplicative factor used to determine the curies of H-3 escaping the flash tank vent, as follows:

f

SGBD activity (uCVml)

SGBD flowrate (gpm)

3785 ml/gal

min = uCi released from vent (1-f)

SGBD activity (uCVml)

SGBD flowrate (gpm)

3785 mIl/gal

min = Liquid uCi released Indian Point 2 Page 78 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX E ALLOWED DILUTED CONCENTRATION (ADC)

The Allowed Diluted Concentration (ADC) is derived and calculated as follows:

MPCWt

CG or ADC= MPCWt

CG or ADC= MPCWt Total activity CG+CB 1+C7CG Where; ADC

= Allowed diluted concentration in plCiml MPCWt = Maximum permissible concentration in water for all isotopes (beta &

gamma), in uCVml, as defined in RECS D3.1.1, as follows:

Zci MPCWt =

C Y-r(cyipw Where; Ci and MPCWi = Concentration and MPCW for each isotope CB = The concentration of the non gamma emitters, in gCVcc CG = The concentration of the gamma emitters in uCVml Applications of ADC:

If simultaneous liquid radioactive discharges are being performed from one unit, dilution flows may need to be re-apportioned. This may be performed by allocation or by calculation. The required dilution flow is calculated as follows:

E Dr

CG ADC where; Dr = Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm The permissible discharge rate is then calculated as follows:

ADC *B CG Where:

D = Permissible discharge rate in gal/min B

= Adjusted dilution flow (Available - E, above), in gpm Note that when there is no other releases (E=O), B simply becomes the available dilution flowrate.

Indian Point 2 Page 79 Revision 9

ODCM Part 11 - Calculational Methodologies APPENDIX F CONVERSION FACTORS FOR LIQUID EFFLUENT MONITORS Monitor conversion factors are derived from circulating a representative sample (or NIST traceable fluid) through the monitor until a stable reading is obtained. The conversion factor is then determined by quantifying the uCi/cc (by gamma spectroscopy or known activity) and dividing this value by the net cpm displayed on the monitor.

Fluid may be recirculated within the monitoring system, or introduced into a closed loop, to provide elevated, stable readings on the monitor. This fluid should be representative of the expected nuclide mixture in the system, as the conversion factor is energy-dependent.

When the process fluid itself is of sufficient activity to provide this function, it is this fluid that is measured and applied to develop a typical conversion factor.

When the process fluid is usually free of contamination, NIST traceable fluid must be injected into the sample chamber to accomplish this task.

Once the sample chamber is providing a stable reading, an alequate of the fluid is measured by gamma spectroscopy to determine the average energy and the monitor's conversion factor.

Conversion Factors for effluent monitors are maintained by Chemistry and updated when standard mixtures change which would warrant an improved average energy representation.

If desired, a more robust method can be applied per Reference 23.

Indian Point 2 Page 80 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX G (Page 1 of 7)

ENVIRONMENTAL SAMPLING POINTS RECS SAMPLE DESIGNATION/

STATION LOCATION DISTANCE DR1/57 DR2/59 DR3/90 DR4/28 DR5/35 DR6/88 DR7/14 DR8/03 DR9134 DR1 0/05 DR1 1/53 DR12/74 DR13/76 DR14/78 DR1 5/80 DR1 6/82 DR1 7/58 DR1 8/60 DR1 9/62 DR20164 DR21/66 DR22/67 DR23/69 DR24/92 DR25/71 DR26/72 DR27/73 DR28/81 DR29/77 DR30/79 DR31/75 DR32/83 DR33/33 DR34138 DR35189 DR36/61 DR37/56 DR38/20 DR39129 DR40/23 DR41/27

Control Station Roa Hook Old Pemart Avenue Charles Point Lents Cove Broadway and Bleakley Avenue Reuter-Stokes Pole #6 Water Meter House Service Center Building South East Corner of Site NYU Tower White Beach West Shore Drive - South West Shore Drive - North Rt. 9W, across from R/S #14 Rt. 9W - South of Ayers Road Ayers Road Rt. 9D - Garrison Gallows Hill Road and Sprout Brook Road West Brook Drive (near the Community Center)

Lincoln Road - Cortlandt (School Parking Lot)

Croton Ave. - Cortlandt Colabaugh Pond Rd. - Cortlandt Mt. Airy & Windsor Road Warren Rd. - Cortlandt Warren Ave. - Haverstraw Railroad Ave. & 9W Haverstraw Willow Grove Rd. & Captain Faldermeyer Drive Palisades Parkway, Lake Welch Exit Palisades Parkway Anthony Wayne Park Palisades Parkway Rt. 9W Fort Montgomery Hamilton Street (Substation)

Furnace Dock (Substation)

Highland Ave. & Sprout Brook Rd. (near Rock Cut)

Lower South Street and Franklin Street Verplanck - Broadway & 6" St.

Cortlandt Yacht Club (aka Montrose Marina)

Grassy Point

Roseton Croton Point 2.0 mi-N 1.8 mi - NNE 0.88 mi - NE 0.45 mi - ENE 0.37 mi - E 0.32 mi - ESE 0.3 mi - SE 0.35 mi - SSE 0.52 mi-S 0.88 mi - SSW 0.92 mi - SW 1.59 mi - WSW 1.21 mi-W 1.2 mi -WNW 1.02 mi-NW 1.01 mi - NNW 5.41 mi - N 5.02 ml - NNE 5.03 mi-NE 4.6 mi-ENE 4.87 mi-E 4.5 mi-ESE 4.97 mi - SE 3.84 mi - SSE 4.83 mi - S 4.53 mi - SSW 4.97 mi - SW 4.96 mi - WSW 4.15 mi-W 4.57 mi - WNW 4.65 ml - NW 4.82 mi-NNW 2.88 mi - NE 3.43 mi - SE 2.89 mi - NNE 1.3 mi - NE 1.25 mi - SSW 1.5 mi - S 3.37 mi - SSW 20.7 mi-N 6.36 mi - SSE Indian Point 2 Page 81 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX G (Page 2 of 7)

ENVIRONMENTAL RECS SAMPLING POINTS RECS SAMPLE SAMPLE DESIGNATION/

SAMPLE STATION LOCATION Airborne DISTANCE A1/4 A2/94 A3/95 A415 A5/23 Algonquin Gas Line IPEC Training Center Meteorological Tower NYU Tower

Roseton 0.28 mi - SW 0.39 mi - S 0.46 mi - SSW 0.88 mi - SSW 20.7 mi - N Wal/9 Wa2/1 0 Waterbome - Surface (Hudson River Water)

Plant Inlet (Hudson River Intake)0.16 mi -W Discharge Canal (Mixing Zone)0.3 mi - WSW Waterbome - Drinking Wb1/7 Camp Field Reservoir 3.4 mi - NE Soil From Shoreline Wc1153 Wc2/50 Exposure Pathway/Sample: Milk White Beach

Manitou Inlet 0.92 mi - SW 4.48 mi - NNW There are no milch animals whose milk is used for human consumption within 8 km distance of Indian Point; therefore, no milk samples are taken.

Exposure Pathway/Sample: Ingestion-Fish and Invertebrates The RECS designate two required sample locations labeled lbl/25 and lb2/23. The downstream IbI location and samples will be chosen where it is likely to be affected by plant discharge. Ib2 will be a location upstream that is not likely to be affected by plant discharge. The following species along with other commercially/recreationally important species are considered acceptable:

Striped Bass Bluegill Sunfish White Perch Pumpkin Seed White Catfish Blueback Herring American Eel Crabs Exposure Pathway/Sample: Ingestion-Food Products (Broad Leaf Vegetation)

Ic1/95 lc2/94 Ic3/23 Meteorological Tower IPEC Training Center

Roseton 0.46 mi-SSW 0.39 mi - S 20.7 mi-N

Control Station Indian Point 2 Page 82 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX G (Page 3 of 7)

ENVIRONMENTAL SAMPLING POINTS RECS SAMPLE DESIGNATION/

STATION LOCATION DISTANCE SAMPLE TYPES DR8/3 A1/4 A4, DR10/5 Wb1/7

-/8 Wa1/9 Wa2/1 0 DR7/14

-/17 DR38/20

-/22 Ib2,A5,DR40,1c3/23 Ibl/25 DR41/27 DR4/28 DR39/29 DR33/33

'v DR9134 DR5/35 DR34/38

-'44 Wc2/50 Wc1, DRI1/53 DR37/56 DRI/57 DR1 7/58 DR2/59 DR1 8/60 DR36/61 DR1 9/62 DR20/64 DR21/66 DR22/67 DR23/69 Service Center Building Algonquin Gas Line NYU Tower Camp Field Reservoir Croton Reservoir

Plant Inlet (Hudson River Intake)

Discharge Canal (Mixing Zone)

Water Meter House Off Verplanck Cortlandt Yacht Club (AKA Montrose Marina)

Lovett Power Plant

Roseton where available, downstream Croton Point Lents Cove Grassy Point Hamilton Street (Substation)

South East Corner of Site Broadway & Bleakley Avenue Furnace Dock (Substation)

Peekskill Gas Holder Building

Manitou Inlet White Beach Verplanck - Broadway & 6h Street Roa Hook Rt. 9D Garrison Old Pemart Ave.

Gallows Hill Road and Sprout Brook Road Lower South Street and Franklin Street West Brook Drive (near the Community Center)

Lincoln Road - Cortlandt (School Parking Lot)

Croton Ave. - Cortlandt Colabaugh Pond Rd. - Cortlandt Mt. Airy & Windsor Road 0.35 mi - SSE 0.28 mi - SW 0.88 mi - SSW 3.4 mi - NE 6.3 mi - SE 0.16 mi -W 0.3 mi - WSW 0.3 mi - SE 1.5 mi - SSW 1.5 mi-S 3

1,2 1,2,3 6

6 7

7,8 3

8,9,10 3

1.6 mi - WSW 20.7 mi - N N/A 6.36 mi - SSE 0.45 mi - ENE 3.37 mi - SSW 2.88 mi - NE 0.52 mi-S 0.37 mi - E 3.43 mi - SE 1.84 mi-NE 4.48 mi - NNW 0.92 mi - SW 1.25 mi - SSW 2.0 mi-N 5.41 mi - N 1.8 mi-NNE 5.02 ml - NNE 1,2 1,2,3,4,5,11,12 12 1,2,3 3,8,9,10 1,2,3

.3 3

3 3

1,2,11 10 3,10 3

3 3

1.3 mi-NE 3

5.03 mi - NE 3

4.6 mi - ENE 3

4.87 mi - E 4.5 mi - ESE 4.97 mi - SE 3

3 3

Control Station Indian Point 2 Page 83 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX G (Page 4 of 7)

ENVIRONMENTAL SAMPLING POINTS RECS SAMPLE DESIGNATION/

STATION SAMPLE TYPES LOCATION DISTANCE DR25/71 DR26/72 DR27/73 DR12/74 DR31/75 DR13/76 DR29/77 DR14/78 DR30/79 DR1 5/80 DR28181 DR16/82 DR32/83

-484

-/85 DR6188 DR35189 DR3/90 DR24192 A2, Ic2194 A3, lc1/95

-'99

-/100

-4101

-102

-/103 Warren Avenue - Haverstraw Railroad Ave. & 9W - Haverstraw Willow Grove Rd. & Captain Faldermeyer Drive West Shore Drive - South Palisades Parkway West Shore Drive - North Palisades Parkway Rte. 9W, across from RIS #14 Anthony Wayne Park Rte. 9W - South of Ayers Road Palisades Parkway, Lake Welch Exit Ayers Road Rte. 9W - Fort Montgomery Cold Spring Quality Control Reuter-Stokes Pole #6 Highland Ave. & Sprout Brook Road (near rock cut)

Charles Point Warren Rd. - Cortlandt IPEC Training Center Meteorological Tower Algonquin outfall Gypsum Plant Stream 5u Street Well - Verplanck Trap Rock Quarry IP3 Trailer Well 4.83 mi - S 4.53 mi - SSW 4.97 mi-SW 1.59 mi - WSW 4.65 mi - NW 1.21 mi-W 4.15 mi -W 1.2 mi - WNW 4.57 mi - WNW 1.02 mi - NW 4.96 ml -WSW 1.01 mi - NNW 4.82 mi - NNW 10.88 mi - N 0.32 mi - ESE 2.89 ml-NNE 0.88 mi-NE 3.84 mi - SSE 0.39 mi - S 0.46 mi - SSW 0.34 mi-SW 0.34 mi-SW 1.3 mi-S 0.7 mi - SSW 0.4 mi -S 3

3 3

8,9,10 6

3 3

1,2,4,5 1,2,4,5 13 13 13 13 13 Some sampling and some locations are in excess of RECS.

Sample types are:

1.

2.

3.

4.

5.

6.

7.

Air particulates Radioiodine Direct gamma Broadleaf vegetation Soil Drinking water Hudson River (H.R.) water 8.

9.

10.

11.

12.

13.

H.R. bottom sediment-silt H.R. aquatic vegetation H.R. shoreline soil Fallout Fish and invertebrates Special water, sample outfall spring Indian Point 2 Page 84 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX G (Page 5 of 7)

ENVIRONMENTAL SAMPLING POINTS RECS SAMPLING LOCATIONS Within Two Miles of Indian Point N

Peekskill Rockland County

)

14 Indian Hudson 1II River Ic2

~[D Bucd Vrplanck Key:

A - Waterborne: Surface (HR) Wa#

o - Direct Radiation Sample Location DR#

o

- Air Particulate & Radiolodine A#

- HR Shoreline Sediment Wc#

Westchester County I

1 mile an Ic# - Broadleaf Vegetation Ibl - Fish and Invertebrates (where available downstream)

Indian Point 2 Page 85 Revision 9

ODCM Part 11-Calculational Methodologies APPENDIX G (Page 6 of 7)

ENVIRONMENTAL SAMPLING POINTS RECS SAMtLIG LOCATIONS Within Ten Miles of Indian Point N

Roseton (20.7 mi. N): j51 i Ic3 Upstream:

1b2 Orange County Bear Mountain Bridge Rockland County AA Y3 0

I

Putnam County

© 3

1 5 miles Westchester County Key: 0 - Direct Radiation Sample Location DR#

o - Air Particulate & Radioiodine A#

.0

- HR Shoreline Sediment Wc#

o -Waterborne: Drinking Wb#

Ic3 - Broadleaf Vegetation 1b2 - Fish and Invertebrates (where available upstream)

Indian Point 2 Page 86 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX G (Page 7 of 7)

ENVIRONMENTAL SAMPLING POINTS NON RECS SAMPLING LOCATIONS N

Roseton (20.7 mi. N): 23: p.

Orange County Bear Mountain Bridge 10: *.,

99: sp Putnam County Cold Spring (10.88 mi. N) : 84 :Y I a 28: V fian Point

_1 03:sp Westchester County

%>101 :sp

)nI 27: E

8: dw r

/

l l 5 miles 17:

v

_4.

22:.

29 Rockland County 3:

Key:

- Air Particulate & Radioiodine o-HR Shoreline Sediment V - Aquatic Vegetation

- Soil

- HR Bottom Sediment sp - Special Water p - Precipitation dw - Drinking Water Indian Point 2 Page 87 Revision 9

ODCM Part 11 - Calculational Methodologies APPENDIX H INTERLABORATORY COMPARISON PROGRAM The New York Power Authority, as part of its share of REMP tasks, performs environmental analysis of samples obtained in the Indian Point plants environs. The New York Power Authority's James A. Fitzpatrick NPP Environmental Laboratory participates in the EPA Interlaboratory Comparison program or comparable program with a certified vendor. Samples of various media containing known activities of radionuclides were sent to participating laboratories for analyses. Results of the analyses are compared to the known values.

Results are reported in term of normalized deviations from a known value. Interlaboratory results are considered acceptable if the laboratory's normalized deviation for a s'ample is less than 3 or greater than minus 3.

Annual results of participation are summarized in the Annual Environmental Operating Report.

Indian Point 2 Page 88 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX I Page 4 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Primary Assumptions:

1. Units 2 and 3 effective dose factors (KLMN) are equivalent, except for site-specific finite cloud correction, as required.

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

Therefore, Q 3 = Q 2 for instantaneous releases.

Given the following long-term meteorological data:

Unit 1/2:

Concentration Finite-Cloud Deposition Unit i or 2 Receptor XIQ Gamma XIQ DIQ Release Points (seclm3)

(secim3) -Xe133 (11m2)

Site Boundary 2.219E-06 1.974E-06 1.407E-08 SiteBoundary_[SSW, 755 ml

[SSW, 755 ml

[SSW, 755 ml Primary Vent 1.030E-06 9.714E-07 7.517E-09 Releases Nearest Residence [SSW, 1574 ml

[SSW, 1574 ml

[S, 1133 m]

2.873E-05 1.215E-05 8.759E-08 Ground Level Site Boundary

[SSW, 440 ml

[55W, 440 ml Releases 5.158E-06 3.068E-06 1.878E-08 Nearest Residence

[SSW, 1374 ml

[SSW, 1374 ml IS, 933 m]

Concentration Finite-Cloud Deposition Unit 3 Receptor X/Q Gamma YJQ D/Q Release Point (secIm3)

(sec/r 3) - Xe133 (1l/ 2) 4.473E-06 3.171E-06 2.599E-08 Site Boundary

[SW, 350 ml

[SSW, 480 ml

[SSW, 480 ml Primary Vent 1.016E-06 9.606E-07 7.451E-09 Releases Nearest Residence JSSW, 1574 ml

[SSW, 1574 ml

[S, 1133 ml 6.980E-05 2.350E-05 2.012E-07 Ground Level Site Boundary

[SSW, 250 ml

[SSW, 250 m 5SW, 250 m Releases 5.158E-06 3.068E-06 1.878E-08 Nearest Residence

[SSW, 1374 ml

[SSW, 1374 ml JS, 933 m]

Unit 3:

Indian Point 2 Page 89 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX I Page 2 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Instantaneous Release Rates vs Dose Rates Indian Point units 2 and 3 share a common site boundary limit of 500 mrem/yr. This 500 mrem/yr limit was divided between the units based upon a 50-50 split of the release rate in lCi/sec. Because each unit has its own X/Q and K-bar, equal pCi/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, IPEC units 2 and 3 must base the dose split on the mixture presented in Table 2-8.

Dose Split Between IP2 and 1P3 A. Instantaneous Dose Rates and Calculation of Allowable Release Rate in uCi/sec:

i.

Whole Body Dose Rate Calculations:

Given:

a) site limit is 500 mrem/yr b) IP3 worst sector X/Q = 4.47E-6 sec/M 3 c) IP3 K-bar for instantaneous mixture = 849 Xieme m

,uCi

yr d) IP2 worst sector X/Q = 2.22E-6 sec/M 3 e) IP2 K-bar for instantaneous mixture = 1507 mreme m

,uCi

yr f) 9 = pCi/sec Solve for Q:

Q [(X/Q3) (K bar3) + (X/Q2) (K bar2)] = 500 mrem/yr Q [(4.47E-6) (849) + (2.22E-6) (1507) ] = 500 mrem/yr Solving for Q a default back-calculated instantaneous release rate for either unit:

Q = 7.OOE+4 gCi/sec In other words, if both units were releasing at this rate, with the default instantaneous mixture identified in Table 2-8, IPEC would be releasing at 500 mrem/yr (the RECS and 10CFR20 release rate limit).

Since this value assumes ALL releases are included (per unit), a partitioning factor should be applied for each applicable release point when this limit is used. Should it become necessary to "borrow" from the other unit, isotopic mixtures from specific sample results should replace the dose factors used in this default calculation. Without specific sample data, the default SITE release rate limit is then:

1.40E5 uCi/sec.

Indian Point 2 Page 90 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX I Page,3 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ii. Skin Dose Rate Calculations:

Given:

a) site limit is 3,000 mrem/yr b) 1P3 worst sector X/Q = 4.47E-6 sec/m 3 c) IP3 (Li + 1.1 Mi) = 2306 mrem-my

,uCi

yr d) IP2 X/Q for SSW sector = 2.22E-6 sec/m 3 mrem m 3 e) IP2 (Li + 1.1 Mi) = 3071 Cie

yr f) Q = uCi/sec Solve for Q:

Q [(X/Q)3 (Li + 1.1 Mi)3 + (X/Q)2 (Li + 1.1 Mi)2] = 3,000 mrem/yr Q [(4.47E-6) (2306) + (2.22E-6) (3071)] = 3,000 mrem/yr Q = 1.75E+5,Ci/sec (less restrictive than Whole Body) iii. Solve for WB dose rate commitments per site (with Q = 7.OOE+4 uCi/sec)

Indian Point 2:

(7.OOE+4 0Ci/sec) (2.22E-6 sec/r 3) (1507 mrem *m 3 )

234 mrem/yr

/iCi

yr Indian Point 3:

(7.OOE+4 piCi/sec) (4.47E-6 sec/m 3) (849 mrem m

= 266 3rem/yr

,pCi

yr The less restrictive skin dose rate limit for each unit (information only):

Unit 2:

(1.75E+5 uCi/sec) (2.22E-6 sec/m 3) (3071 MreM m ) = 1194 mrem/yr Unit

yr Unit 3:

(1.75E+5 uCi/sec) (4.47E-6 sec/rn3) (2306 m)m

= 1806 mrem/yr jiCi

y Indian Point 2 Page 91 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX I Page 4 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 RELEASE RATE LIMITS FOR QUARTERLY AND ANNUAL AVERAGE NOBLE GAS RELEASES Gamma air dose Beta air dose For a Calendar Quarter 5 mrad limit 10 mrad limit For a Calendar Year 10 mrad limit 20 mrad limit

1. Assumptions:

1. Doses are delivered to the air at the site boundary.

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

3. X/Q for Unit 2 = 2.22E-6 sec/M3, (Q = release rate uCi/sec)

4. X/Q for Unit 3 = 4.47E-6 sec/M3, (Q = release rate uCi/sec)

5. Gamma and Beta air dose factors (M and N), Corrected for finite cloud geometry (as described on Table 2-8) are as follows:

Unit 2 effective Unit 3 effective average dose factors average dose factors Units M- =281 M

= 181 mrad/yr per uCi/m3 N = 1254 N = 1254 mrad/yr per uCi/m3 II. Calculation of Quarterly Release Rates:

a) for gamma dose: (Q )*[(M)(X/Q)] less than or equal to 5 mrad/qtr b) for beta dose: (Q )*[(N)(X/Q)] less than or equal to 10 mrad/qtr gamma dose rate beta dose rate unit 2 0 =

5mrad Iqtr

3.21E+4 pCi/sec (1 / 4yr)(M)(X / Q) 0

l0mrad /qtr

= 1.44E+4 jCi/sec (1 / 4yr)(N)(X / Q) unit 3 2.47E+4 gCi/sec 7.14E+3 gCi/sec Based on the above analysis, the beta dose is limiting for time average doses.

Therefore, the allowable quarterly average release rates are 1.44E+4 j.Ci/sec for unit 2 and 7.14E+3 ItCi/sec for unit 3.

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 annual average release rates are 7.20E+3,Ci/sec for unit 2 and 3.57E+3,uCi/sec for unit 3.

Indian Point 2 Page 92 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX I Page,5of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE INSTANTANEOUS RELEASE RATE for 1-131 & Particulates w/ T1/2> 8 DAYS)

Given:

Wv(in): X/Q at the Site Boundary for IP3 = 4.47E-6 sec/m 3 Wv(in): X/Q at the Site Boundary for IP2 = 2.22E-6 sec/m 3 Pl(c) = 1.62 E7 mrem / yr Assumed Pathway: Child Inhalation at Unrestricted Area Boundary Solve the following equation for Q:

[(O )Pl(c)(Wv(in)) Unit 3] + [( Q)PI(c)(Wv(in)) Unit 2] = 1500 mrem/yr IP3: (Q )Pl(c)(Wv(in))3 = Q

1.62E7 mrem / yr 4 47E6 S3

=

,uCI mlm IP2: (Q)PI(c)(Wv(in))2 = Q

1.62E7 mrem lyr 2.22E-6 s/m3

=

p"Ci/M3 Q

72.4 mrem / yr

,uCi / sec Q

36.0 mrem l yr

,uCi/sec The sum equals: (108) ( Q) mrem/yr per uCi/sec Limit is 1500 mrem/yr per site:

Therefore:

mrem / yr = 1500 mrem/yr

,uCi / sec Q = 1.38E+1,uCi/sec (for each unit)

IP3 Dose Contribution:

IP2 Dose Contribution:

1.38E+1 1C*1.62E7E7-*4.47E-6--e

= 1003 mrem/yr sec yr,uCi mr3 1.38E+1

1.62E7 E*

2.22E

= 497 mrem/yr sec yr pCi m3 Sum = 1500 mrem/yr Approximately a 67 / 33 % dose split for IP3 and IP2 respectively.

Indian Point 2 Page 93 Revision 9

ODCM Part II - Calculational Methodologies APPENDIX I Page 6 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE RELEASE RATES FOR IODINE / PARTICULATE TIME AVERAGE QUARTERLY AND ANNUAL DOSE LIMITS AT THE NEAREST RESIDENT Dose factors for the child, thyroid (for Iodine 131) are used for this category as a conservative assumption since this nuclide has the highest thyroid dose factor of all iodines and particulates, and its most significant effect in on the child age group. The H-3 dose factor is about 4 orders of magnitude less significant and its contribution to the total dose is considered negligible. The back-calculated release rate for Iodine and Particulate is as follows:

Given:

Unit 2 Unit 3 X/Q (in sec/M 3 at the nearest resident) 1.03E-6

'.02E-6 D/Q (in m2 at the nearest resident) 7.52E-9 7.45E-9 RlI(c) = 1.62E+7 rei/lY, child thyroid inhalation dose factor for 1-131 (for both units) 2rmremn yr

-3 RG = 1.72E+7m 2 irsec ground plane dose factor for-131 (for both units) pxCi / e RV(c) = 4.75E+10 m2 mre/yr, child thyroid vegetation dose factor for -131 (for both units)

,uC/sec Calculating the allowable time average release rate by solving the following equation for Q:

Q [(Rlc)(X/Q) + (RGXD/Q) + (RVcXD/Q)] = limit in mrem/yr Unit 2 Unit 3 Q (Rlc)(X/Q) in mrem/yr per uCi/sec 16.7

Q 16.5

Q Q (RG) (D/Q) in mrem/yr per uCi/sec =

0.129

Q 0.128

Q Q (RVcXD/Q) in mrem/yr per uCi/sec =

357

Q 354

Q The sum for each unit ( X

Q ) in mrem/yr per uCi/sec. 374

Q 371' Q Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr).

Solving for Q yields:

(IP2)

Q

374 mrem /yr = 30 mrem/yr Q = 8.02E-2 gCi/sec (Quarterly Limit) pCi/sec Annual limit is t/2 quarterly limit, or 15 mrem to any organ/yr = 4.01 E-2 pCi/sec (Annual Limit)

(IP3)

Q '371 'remr/yr = 30 mrem/yr Q = 8.1OE-2 pCi/sec (Quarterly Limit) pCi/sec Annual limit is 'A quarterly limit, or 15 mrem to any organ/yr = 4.05E-2 pCi/sec (Annual Limit)

Indian Point 2 Page 94 Revision 9

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