ML22182A076

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Resubmittal of the 2021 Annual Radioactive Effluent Release Report
ML22182A076
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 07/01/2022
From: Fleming J
Holtec Decommissioning International
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
HDI-IPEC-22-052
Download: ML22182A076 (301)
v • d • e


Text

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-IPEC-22-052 10 CFR 50.36a (a)(2) 10 CFR 72.44 (d)(3)

July 1, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Indian Point Energy Center Facility License No. DPR-05, DPR-26 and DPR-64 NRC Docket Nos. 50-03, 50-247, and 50-286

Subject:

Resubmittal of the 2021 Annual Radioactive Effluent Release Report Reference 1: Holtec Decommissioning International, LLC (HDI) Letter to US NRC, 2021 Annual Radioactive Effluent Release Report, (HDI-IPEC-22-034) (ADAMS Accession Number ML22118A493), dated April 28, 2022 Enclosed is a resubmittal of the Indian Point Units 1, 2, and 3 Annual Radioactive Effluent Release Report for 2021 and the updated Offsite Dose Calculation Manual (ODCM). Reference 1 inadvertently included a copy of the Annual Radiological Environmental Operating Report rather than the Annual Radioactive Effluent Release Report as Enclosure 1 in the submittal.

This letter contains no new regulatory commitments.

If you have any questions or need further information, please contact Mr. Walter Wittich, IPEC Licensing at 914-254-7212, or me at (856) 797-0900, ext. 3578.

Sincerely, Jean A. Digitally signed by Jean A. Fleming Fleming Date: 2022.07.01 07:20:26 -04'00' Jean A. Fleming Vice President, Licensing, Regulatory Affairs and PSA Holtec Decommissioning International, LLC

Enclosures:

1) 2021 Annual Radioactive Effluent Release Report
2) Offsite Dose Calculation Manual (ODCM) cc: NRC Senior Project Manager, NRC NMSS NRC Region l Regional Administrator NRC Senior Regional Inspector, Indian Point Energy Center New York State Liaison Officer Designee, NYSERDA New York State (NYS) Public Service Commission

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 ENCLOSURE 1 TO HDI-IPEC-22-052 2021 Annual Radioactive Effluent Release Report (55 pages not including this cover sheet)

Page 1 of 55 Facility: Indian Point Energy Center YEAR: 2021 Indian Point Units 1, 2 and 3 Docket Nos.: 50-3, 50-247, & 50-286 Holtec Decommissioning International Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 Year: 2021 Page 2 of 55 Annual Radioactive Effluent Release Report TABLE OF CONTENTS

1.0 INTRODUCTION

........................................................................................................................4 2.0 SUPPLEMENTAL INFORMATION..............................................................................................4 3.0 GASEOUS EFFLUENTS...........................................................................................................11 4.0 LIQUID EFFLUENTS ................................................................................................................17 5.0 SOLID WASTE

SUMMARY

......................................................................................................22 6.0 RADIOLOGICAL IMPACT TO MAN ..........................................................................................36 7.0 METEOROLOGICAL DATA ......................................................................................................40 LIST OF TABLES ........................................................................................................................... .. 3 ATTACHMENTS - Carbon 14 Discussion ...................................................................................................41 - Groundwater Monitoring Program Results ....................................................................42 - 2021 Laboratory Analytical Results ...............................................................................45 - ODCM Revision 6 Summary of Changes ......................................................................54

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 3 of 55 Annual Radioactive Effluent Release Report List of Tables Table 2.5 Airborne Batch Releases Table 2.5 Liquid Batch Releases Table 3 Gaseous Effluents - Summation of All Releases - Units 1 and 2 Table 3 Gaseous Effluents - Batch Mode - Units 1 and 2 Table 3 Gaseous Effluents - Continuous Mode - Units 1 and 2 Table 3 Gaseous Effluents - Summation of All Releases - Unit 3 Table 3 Gaseous Effluents - Batch Mode - Unit 3 Table 3 Gaseous Effluents - Continuous Mode - Unit 3 Table 4 Liquid Effluents - Summation of All Releases - Units 1 and 2 Table 4 Liquid Effluents - Batch Mode - Units 1 and 2 Table 4 Liquid Effluents - Continuous Mode - Units 1 and 2 Table 4 Liquid Effluents - Summation of All Releases - Unit 3 Table 4 Liquid Effluents - Batch and Continuous Modes - Unit 3 Table 6 Summary of Dose Assessments Table 6 Unit 2 Appendix I Dose Assessment Table 6 Unit 3 Appendix I Dose Assessment

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 4 of 55 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

This information is provided in accordance with the requirements of Regulatory Guide 1.21. This report includes effluent information from Indian Point Units 1, 2, and 3. Units 1 and 2 share effluent processing equipment and Technical Specifications. In this site report, releases from Unit 1 are included with Unit 2, while Unit 3 releases are calculated and shown separately. Liquid and gaseous effluents are released in accordance with the Offsite Dose Calculation Manual (ODCM). This report is a summary of the effluent data in accordance with Unit 2 Technical Specification (TS) 5.6.3 and Unit 3 TS 5.6.3. Unit 2 was permanently shutdown on April 30th, 2020. Unit 3 ceased operation April 30th, 2021.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits Indian Point Energy Center is subject to limits on radioactive waste releases that are set forth in the Offsite Dose Calculation Manual (ODCM), Parts I and II, as defined in the Technical Specifications. ODCM Part I, also known as the Radiological Effluent Controls (or RECS) contains the specific requirements and controls, while ODCM Part II (calculation methodologies) contains the details necessary to perform offsite dose calculations from the sampling and monitoring outlined in the RECS. The following are the limits required by the ODCM:

1. Fission and activation gases:
a. Noble gases dose rate due to radioactive materials released in gaseous effluents from the areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin

b. Noble gas air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

Quarterly: Less than or equal to 5 mrads gamma Less than or equal to 10 mrads beta Yearly: Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta

2. Iodine, tritium, and all radionuclides in particulate form (with half-lives > 8 days).
a. The dose rate for Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 1500 mrem/yr to any organ

b. The dose to a MEMBER OF THE PUBLIC from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Quarterly: Less than or equal to 7.5 mrem to any organ Yearly: Less than or equal to 15 mrem to any organ

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 5 of 55 Annual Radioactive Effluent Release Report

3. Liquid Effluents Dose The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

Quarterly: Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ Yearly: Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ

4. Total Dose (40CFR190)

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 the following:

Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.

Less than or equal to 75 mrem, Thyroid 2.2 Maximum Permissible Concentrations

1. Airborne Effluents Maximum concentrations and compliance with 10CFR20 release rate limits are controlled by the application of Radiation Monitor setpoints, preliminary grab sampling, and conservative procedural guidance for batch and continuous releases. These measures, in conjunction with plant design, preclude approaching release rate limits, per the ODCM.
2. Liquid Effluents Proximity to release rate and total release limits is controlled through the application of a calculated Allowed Diluted Concentration (ADC) and ALARA guidance with regard to dilution flow and maximum tank concentration. The ADC is used to determine a Radiation Monitor setpoint associated with an estimated amount of non-gamma activity (H-3, Ni-63, Fe-55, Sr-89/90 etc.), as well as the measured gamma activity. ADC is defined in the station ODCM as a means of assuring compliance with the release rate limits of 10CFR20, as defined by the application of ten times the Effluent Concentrations of the new 10CFR20.

Liquid effluents are further controlled by the application of proceduralized ALARA limits such as a MINIMUM dilution flow of 80,000 gpm required for batch discharges, a maximum gamma concentration of 5E-5 uCi/ml (without gas) for routine effluents, and procedural guidance for optimizing decay and treatment of liquid waste.

2.3 Average Energy This information is no longer used. It is available onsite if required.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 6 of 55 Annual Radioactive Effluent Release Report 2.4 Measurements & Approximations of Total Radioactivity The following provides the methods used to measure or approximate the total radioactivity in effluents and how radionuclide composition is determined.

1. Fission & activation gases Analyses of effluent gases are performed in compliance with the requirements of the RECS (ODCM Part I). In the case of isolated tanks (batch releases), the total activity discharged is based on an isotopic analysis of each batch with the volume of gas in the batch corrected to standard temperature and pressure.

Vapor containment purge and pressure relief (vent) discharges, which routinely total less than 150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />s/quarter in duration, have been treated as batch releases. However, both types of releases from the Vapor Containment are performed randomly with regard to time of day and duration (release periods were not dependent solely on time of day or atmospheric condition).

Therefore, determination of doses due to Vapor Containment releases includes the use of annual average dispersion data, as defined in NUREG 0133, Section 3.3.

During operation, at least one complete isotopic concentration analysis of containment air is performed monthly and compared to a process monitors reading. Pressure reliefs are quantified by scaling subsequent releases with the monitors reading, applying the mixture from the grab sample. In this fashion, the base grab sample defines the mixture and the activity released. The monitor scales the release up or down and provides continuous indication of potential leaks. Unit 2 shutdown April 2020 and not longer requires this analysis. Unit 3 shutdown April 2021 and no longer performs this analysis.

Isotopic analyses for each vapor containment purge are taken prior to and during the purge. This information is combined with the volume of air in each discharge to calculate the quantity of activity released from these discharges.

2. Iodines and Particulates Unit 3 airborne iodine and particulate releases are quantified by collecting a continuous sample of ventilation air on a Triethylenediamine (TEDA) impregnated, activated charcoal cartridge and a glass-fiber filter paper. These samples are changed weekly as required in the RECS. The concentration of isotopes found by analysis of these samples is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged. Unit 2 performs particulate analysis only.

If no I-131 is identified in weekly vent samples, - is entered in Table 3-1 and Table 3-4. A typical Minimum Detectable Activity (MDA) for weekly I-131 analyses is 1.0E-13 uCi/cc, which is 100 times lower than ODCM requirements.

If I-131 is identified in any routine weekly sample, it is added to the table and other iodine isotopic concentrations (I-133, I-135) are then determined on a 24-hour sample at least once per month.

The concentration of each isotope is analytically determined by ratioing the activities with weekly media for I-131. This activity is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged. A compositing method of analyzing for gross alpha, Sr-89, and Sr-90 is used per the station ODCM. Absence of any positive activity is identified as -.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 7 of 55 Annual Radioactive Effluent Release Report

3. Tritium Airborne tritium is collected by passing a known volume of the sample stream through a silica gel column. The collected samples are distilled and analyzed by liquid scintillation. The tritium released was calculated for each release point from the measured tritium concentration, the volume of the sample, the tritium collection efficiency, and the respective ventilation exhaust flow rates. As a check on the silica gel sampling, Chemistry performs a comparison of total curies evaporated from the spent fuel pool (the major H-3 source term) and adjusts the silica gel measurements, as necessary.
4. Carbon-14 Unit 3 Airborne Carbon-14 release values were estimated using the methodology included in the EPRI Technical Report 1021106, using the normalized Carbon-14 production rate of 3.47 Ci/GWth-EFPyear for Unit 3, a gaseous release fraction of 100%, a Carbon-14 carbon dioxide fraction of 26%, a reactor power rating 3188 MWth for Unit 3 and equivalent full power (EFP) operation of 113.512 days for Unit 3 for calendar year 2021. See Section 6 and Attachment 1 for more details concerning the Carbon 14 calculations.
5. Liquid Effluents A sample of each batch discharge is taken and an isotopic analysis is performed in compliance with requirements specified in the ODCM. Proportional composite samples of continuous discharges are taken and analyzed per the ODCM, as well. Isotopic concentration data are combined with the information on volume discharged to determine the amount of each isotope discharged.

A compositing method of analyzing for non-gamma emitters is used per the station ODCM (Gross Alpha, Sr-89, Sr-90, Fe-55 and Ni-63). When there has been no positive activity, - is entered.

Liquid Effluent volumes of waste released on Tables 4-1 and 4-4 (Section 4) are differentiated between processed fluids (routine liquid waste and Unit 1s North Curtain Drain), and water discharged through monitored pathways identified in the ODCM, but NOT processed (SG Blowdown and Unit 1s Sphere Foundation Drain Sump). The unprocessed water may still contain trace levels of contamination (generally only tritium) and as such, is identified as liquid waste. Curie and dose data from unprocessed fluid is included in the following tables, along with all other liquid effluent, continuous or batch, processed or not. Processed and unprocessed water is differentiated only to prevent confusion with regard to measures undertaken to convert liquid to solid waste (resin cleanup). Therefore, volumes of processed and unprocessed liquid waste are reported separately on Tables 4-1 and 4-4.

6. Estimated Total Error Present Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:

= + +. . .

Where: ET = total percent error E1 ... En = percent error due to calibration standards, Laboratory analysis, instruments, sample flow, etc.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 8 of 55 Annual Radioactive Effluent Release Report 2.5 Batch Releases:

1. Airborne Table 2.5 Airborne Batch Releases Unit 1 and 2 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2021 Number of Batch Releases 12 6 2 0 20 Total Time Period (min) 362 151 110 0 623 Maximum Time Period (min) 79 40 65 0 79 Average Time Period (min) 30 25 55 0 31 Minimum Time Period (min) 20 20 45 0 20 Unit 3 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2021 Number of Batch Releases 22 7 1 0 30 Total Time Period (min) 2060 1160 8 0 3240 Maximum Time Period (min) 162 600 8 0 600 Average Time Period (min) 94 166 8 0 108 Minimum Time Period (min) 2 15 8 0 2
2. Liquid Table 2.5 Liquid Batch Releases Unit 1 and 2 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2021 Number of Batch Releases 0 0 0 4 4 Total Time Period (min) 0 0 0 770 770 Maximum Time Period (min) 0 0 0 226 226 Average Time Period (min) 0 0 0 193 193 Minimum Time Period (min) 0 0 0 175 175 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2021 Number of Batch Releases 42 26 31 1 100 Total Time Period (min) 4650 2960 3740 64 11400 Maximum Time Period (min) 122 131 240 64 240 Average Time Period (min) 111 114 121 64 114 Minimum Time Period (min) 85 105 107 64 64 Average Stream Flow:

Regulatory Guide 1.21 includes a section to report average stream flows. This data, for some plants, is used to determine dilution volume. However, at IPEC, the Hudson River stream flow is not applied to dilution calculations, in favor of the more conservative method of using only the dilution in the discharge canal, running north to south, parallel to the river, and servicing the plant.

This conservative dilution volume is determined quarterly, applied to liquid offsite dose calculations (and all other determinations of diluted effluent), and reported on Tables 4-1 and 4-4, in Section 4 of this report. Hudson River flow information remains available, however, from the Department of the Interior, United States Geological Survey (USGS), or from web sites such as:

https://www.usgs.gov/centers/ny-water/data-tools

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 9 of 55 Annual Radioactive Effluent Release Report 2.6 Abnormal Releases

1. Liquid None
2. Gaseous None 2.7 Non-routine, Planned Discharges None 2.8 Radioactive Waste Treatment System Changes To accommodate the Holtec Hi-Lift Crane in the Unit 3 Fuel Storage Building (FSB), the existing Liquid Radwaste Processing System (LRPS) skid will be removed from the FSB Truck Bay. An alternate means of liquid radwaste processing is therefore needed to support Unit 3 during decommissioning. The liquid radwaste stream normally sent to the LRPS will be diverted to the Unit 3 Radioactive Machine Shop (RAMS). A truck filling station will be installed that will fill a tanker truck. The truck will be driven to the Unit 1 Fuel Handling Building (FHB) where it will be connected to the Unit 1/2 Integrated Liquid Waste Processing (ILWS) System and its contents processed (EC IPC-2021-002).

2.9 Land Use Census Changes No changes or modifications affecting receptors, receptor location or new (or changed) routes of exposure were identified as a result of the last Land Use Census.

2.10 Effluent Monitor Instrument Inoperability

1. Effluent Monitoring Equipment Inoperable > 30 Days During this reporting period, there were no instances of effluent monitoring equipment out of service for greater than 30 consecutive days.
2. Effluent Monitoring Equipment Sample Deviation None 2.11 Offsite Dose Calculation Manual Changes During this report period there was an ODCM change. Revision 6 of the ODCM was implemented in April 2021. Attachment 4 contains the ODCM Revision 6, summary of changes. A complete copy of Revision 6 of the IPEC ODCM is being submitted with this report.

2.12 Process Control Program (PCP) Changes There were no PCP changes during 2021.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 10 of 55 Annual Radioactive Effluent Release Report 2.13 Groundwater Monitoring and Program (NEI 07-07)

The Groundwater Monitoring Program is a voluntary program set up to assure timely effective management of situations involving inadvertent releases of licensed material to ground water. A major part of the IPECs program is a groundwater quantification model that involves verification/calibration such that the annual release to the environment remains a function of the annual precipitation and source term.

No abnormal releases occurred in 2021 and conservative assessments of legacy events have determined that the doses resulting from these events were negligible. The groundwater monitoring program provides additional confirmation of these assessments. The groundwater monitoring program also includes a storm water monitoring program. Together these programs provide data for offsite dose evaluation. The subsurface water flow directions and rates are used to estimate the transport of abnormal releases of liquid effluents in groundwater.

The offsite dose associated with the groundwater pathway remains extremely small. The 2021 effluent dose was slightly higher than in 2020. The total routine liquid effluent dose inclusive of the groundwater pathway contributes < 0.1 % of the annual limit. Groundwater and storm water effluent flow rates and source term data are further described in Attachment 2 of this report. A breakdown of the total dose from the groundwater and storm water pathways and detailed results from the samples obtained as part of this program are also provided in Attachment 2. Section 6 (Radiological Impact on Man) of this report provides a comparison of the groundwater and storm water doses to the other dose pathways.

2.14 Outside Tanks During this period there were no curie limits exceeded in the outdoor tanks.

2.15 Errata/Corrections to Previous ARERRs None

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 11 of 55 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS Table 3-1 Gaseous Effluents - Summation of All Releases - Units 1 and 2 Total A. Fission & Activation Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year  % Error

1. Total Release Ci - 1.59E-05 - - 1.59E-05 +/- 25
2. Average release rate uCi/sec - 2.02E-06 - - 5.04E-07 B. Iodines
1. Total Iodine-131 Ci - - - - 0.00E+00 +/- 25
2. Average release rate uCi/sec - - - - 0.00E+00 C. Particulates
1. Total Release, with Ci 1.33E-06 - - 1.29E-06 2.62E-06 +/- 25 half-life > 8 days
2. Average release rate uCi/sec 1.71E-07 - - 1.62E-07 8.30E-08
3. Gross Alpha Ci - - - - 0.00E+00 +/- 25 D. Tritium
1. Total release Ci 1.98E-01 7.37E-01 1.41E+00 8.90E-01 3.23E+00 +/- 25
2. Average release rate uCi/sec 2.55E-02 9.37E-02 1.77E-01 1.12E-01 1.02E-01 E. Carbon-14
1. Total release Ci - - - - 0.00E+00
2. Average release rate uCi/sec - - - - 0.00E+00

- Indicates < MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 12 of 55 Annual Radioactive Effluent Release Report Table 3-2 Gaseous Effluents -- Batch Mode - Units 1 and 2 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ar-41 Ci - - - - 0.00E+00 Kr-85 Ci - - - - 0.00E+00 Kr-85m Ci - - - - 0.00E+00 Kr-87 Ci - - - - 0.00E+00 Kr-88 Ci - - - - 0.00E+00 Xe-131m Ci - - - - 0.00E+00 Xe-133 Ci - 1.59E-05 - - 1.59E-05 Xe-133m Ci - - - - 0.00E+00 Xe-135 Ci - - - - 0.00E+00 Xe-135m Ci - - - - 0.00E+00 Xe-138 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 1.59E-05 0.00E+00 0.00E+00 1.59E-05

- indicates <MDA

2) Iodines Not Applicable for Batch Releases
3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 13 of 55 Annual Radioactive Effluent Release Report Table 3-3 Gaseous Effluents -- Continuous Mode - Units 1 and 2 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Xe-133 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
2) Iodines I-131 Ci - - - - 0.00E+00 I-133 Ci - - - - 0.00E+00 I-135 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
3) Particulates Cs-137 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

- Indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 14 of 55 Annual Radioactive Effluent Release Report Table 3-4 Gaseous Effluents - Summation of All Releases - Unit 3 Est. Total A. Fission & Activation Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year  % Error

1. Total Release Ci 2.80E-02 4.99E-02 - - 7.79E-02 +/- 25
2. Average release rate uCi/sec 3.59E-03 6.35E-03 - - 2.47E-03 B. Iodines
1. Total Iodine-131 Ci - - - - 0.00E+00 +/- 25
2. Average release rate uCi/sec - - - - 0.00E+00 C. Particulates
1. Total Release, with Ci - - - - 0.00E+00 +/- 25 half-life > 8 days
2. Average release rate uCi/sec - - - - 0.00E+00
3. Gross Alpha Ci - - - - 0.00E+00 +/- 25 D. Tritium
1. Total release Ci 2.22E+00 2.51E+00 4.19E+00 5.79E+00 1.47E+01 +/- 25
2. Average release rate uCi/sec 2.85E-01 3.19E-01 5.27E-01 7.29E-01 4.66E-01 E. Carbon-14
1. Total release Ci 2.72E+00 7.10E-01 - - 3.43E+00
2. Average release rate uCi/sec 3.50E-01 9.03E-02 0.00E+00 0.00E+00 1.09E-01

- Indicates < MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 15 of 55 Annual Radioactive Effluent Release Report Table 3-5 Gaseous Effluents - Batch Mode - Unit 3 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ar-41 Ci 1.30E-02 2.94E-03 - - 1.59E-02 Kr-85 Ci - - - - 0.00E+00 Kr-85m Ci - - - - 0.00E+00 Kr-87 Ci - - - - 0.00E+00 Kr-88 Ci - - - - 0.00E+00 Xe-131m Ci - - - - 0.00E+00 Xe-133 Ci 1.48E-02 4.61E-02 - - 6.09E-02 Xe-133m Ci - 8.51E-04 - - 8.51E-04 Xe-135 Ci 1.27E-04 8.51E-05 - - 2.12E-04 Xe-135m Ci - - - - 0.00E+00 Total for Period Ci 2.79E-02 4.99E-02 0.00E+00 0.00E+00 7.79E-02

- Indicates < MDA

2) Iodines Not Applicable for Batch Releases
3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 16 of 55 Annual Radioactive Effluent Release Report Table 3-6 Gaseous Effluents - Continuous Mode - Unit 3 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ar-41 Ci - - - - 0.00E+00 Xe-133 Ci - - - - 0.00E+00 Xe-135 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
2) Iodines I-131 Ci - - - - 0.00E+00 I-133 Ci - - - - 0.00E+00 I-135 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
3) Particulates Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

- indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 17 of 55 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS Table 4-1 Liquid Effluents - Summation of All Releases - Units 1 and 2 Est. Total A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year  % Error

1. Total Release (not including Ci 5.53E-03 4.05E-02 1.17E-02 2.17E-03 5.99E-02 +/- 25 Tritium, Gr Alpha, & Gases)
2. Average Diluted Conc uCi/ml 3.75E-12 4.92E-11 1.08E-10 5.64E-11 2.45E-11 B. Tritium
1. Total Release Ci 1.33E-02 1.08E-02 1.08E-02 6.52E+00 6.55E+00 +/- 25
2. Average Diluted Conc uCi/ml 9.02E-12 1.31E-11 1.00E-10 1.69E-07 2.68E-09 C. Dissolved & Entrained Gases
1. Total Release Ci - - - - 0.00E+00 +/- 25
2. AverageDiluted Conc uCi/ml - - - - 0.00E+00 D. Gross Alpha
1. Total Release Ci - - - 8.29E-05 8.29E-05 +/- 25
2. AverageDiluted Conc uCi/ml - - - 2.15E-12 3.39E-14 E. Volume of Waste Released
1. Processed Fluids (Mon Tanks) liters 2.04E+06 1.56E+06 2.85E+06 1.52E+06 7.97E+06 +/- 10
2. Unprocessed Fluids (SGs and RW-1) liters 8.20E+06 9.52E+06 6.23E+06 4.79E+06 2.87E+07 +/- 10 F. Volume of Dilution Water liters 1.47E+12 8.24E+11 1.08E+11 3.85E+10 2.44E+12 +/- 10

- indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 18 of 55 Annual Radioactive Effluent Release Report Table 4-2 Liquid Effluents - Batch Mode - Units 1 and 2 Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ag-110m Ci - - - - 0.00E+00 Co-58 Ci - - - - 0.00E+00 Co-60 Ci - - - - 0.00E+00 Cr-51 Ci - - - - 0.00E+00 Cs-137 Ci - - - 2.31E-05 2.31E-05 Fe-55 Ci - - - - 0.00E+00 Fe-59 Ci - - - - 0.00E+00 Mn-54 Ci - - - - 0.00E+00 Nb-95 Ci - - - - 0.00E+00 Ni-63 Ci - - - - 0.00E+00 Sb-125 Ci - - - - 0.00E+00 Te-123m Ci - - - - 0.00E+00 Te-125m Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 2.31E-05 2.31E-05 Dissolved & Entrained Gas Xe-133m Ci - - - - 0.00E+00 Xe-133 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

- Indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 19 of 55 Annual Radioactive Effluent Release Report Table 4-3 Liquid Effluents - Continuous Mode - Units 1 and 2 Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Cs-137 Ci 2.87E-03 3.96E-02 6.11E-03 6.68E-04 4.92E-02 Ni-63 Ci - - - - 0.00E+00 Sr-89 Ci - - - - 0.00E+00 Sr-90 Ci 7.30E-05 2.55E-05 4.12E-05 5.84E-05 1.98E-04 Total for Period Ci 2.94E-03 3.96E-02 6.15E-03 7.26E-04 4.94E-02 H-3 (only) Ci 1.33E-02 1.08E-02 1.08E-02 6.81E-03 4.17E-02

- Indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 20 of 55 Annual Radioactive Effluent Release Report Table 4-4 Liquid Effluents -Summation of All Releases - Unit 3 Est. Total A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year  % Error

1. Total Release (not including Ci 2.33E-02 1.11E-02 1.06E-02 1.47E-05 4.50E-02 +/- 25 Tritium, Gr Alpha, & Gases)
2. Average Diluted Conc uCi/ml 1.74E-13 1.29E-10 1.30E-09 4.32E-10 3.35E-13 B. Tritium
1. Total Release Ci 6.71E+02 1.05E+02 8.55E+01 1.85E-01 8.61E+02 +/- 25
2. Average Diluted Conc uCi/ml 5.00E-09 1.22E-06 1.05E-05 5.46E-06 6.42E-09 C. Dissolved & Entrained Gases
1. Total Release Ci 4.31E-03 8.42E-04 - - 5.15E-03 +/- 25
2. AverageDiluted Conc uCi/ml 3.21E-14 9.80E-12 - - 3.84E-14 D. Gross Alpha
1. Total Release Ci - - - - 0.00E+00 +/- 25 E. Volume of Waste Released
1. Processed Fluids (Mon Tanks) liters 1.07E+06 6.76E+05 8.45E+05 5.12E+03 2.60E+06 +/- 10
2. Unprocessed Fluids (SGs) liters 1.60E+06 5.35E+05 0.00E+00 0.00E+00 2.14E+06 +/- 10 F. Volume of Dilution Water liters 1.34E+14 8.59E+10 8.11E+09 3.39E+07 1.34E+14 +/- 10

- indicates < MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 21 of 55 Annual Radioactive Effluent Release Report Table 4-5 Liquid Effluents - Batch and Continuous Modes - Unit 3 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Te-123m Ci - 1.36E-04 3.44E-04 7.32E-07 4.81E-04 Cr-51 Ci 2.47E-05 1.06E-03 2.79E-04 - 1.36E-03 Mn-54 Ci 1.63E-04 4.64E-06 1.53E-05 - 1.83E-04 Fe-55 Ci 1.93E-03 4.55E-04 1.22E-03 - 3.61E-03 Co-58 Ci 5.33E-04 1.07E-04 8.64E-04 4.62E-07 1.50E-03 Co-60 Ci 3.56E-03 6.29E-04 2.25E-03 1.63E-06 6.44E-03 Ni-63 Ci 7.81E-03 2.06E-03 3.52E-04 - 1.02E-02 Zr-95 Ci 1.26E-05 - 3.03E-05 - 4.29E-05 Nb-95 Ci 5.19E-05 2.70E-05 1.64E-04 - 2.43E-04 Ru-103 Ci 7.75E-05 - - - 7.75E-05 Ag-110m Ci 3.25E-04 - 1.08E-05 - 3.36E-04 Sb-124 Ci - 7.18E-05 8.14E-05 - 1.53E-04 Sb-125 Ci 9.91E-04 4.55E-04 6.68E-04 - 2.11E-03 Te-125m Ci - 8.74E-04 1.65E-03 - 2.52E-03 Cs-137 Ci 6.62E-04 6.35E-04 3.36E-06 2.18E-07 1.30E-03 Ce-144 Ci - 2.20E-04 - - 2.20E-04 Pr-144 Ci - 1.72E-03 - - 1.72E-03 Total for Period Ci 1.61E-02 8.45E-03 7.93E-03 3.04E-06 3.25E-02 Dissolved and Entrained Gas (Batch)

Xe-133 Ci 4.24E-03 8.39E-04 - - 5.08E-03 Xe-135 Ci 6.96E-05 2.80E-06 - - 7.24E-05 Total for Period Ci 4.31E-03 8.42E-04 0.00E+00 0.00E+00 5.15E-03 Continuous Releases (SG Blowdown)

H-3 (only) Ci 4.86E-04 - - - 4.86E-04

- indicates < mda

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 22 of 55 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Units 1 & 2 Types of Solid Waste - Summary Waste Stream: Resins, Filters, and Evap Bottoms Waste Volume Curies % Error (Ci) 3 3 Class ft m Shipped A 1.74E+02 4.93E+00 5.01E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 1.74E+02 4.93E+00 5.01E+00 +/- 25%

Waste Stream  : Dry Active Waste Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 2.68E+04 7.58E+02 6.66E-01 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 2.68E+04 7.58E+02 6.66E-01 +/-25%

Waste Stream  : Irradiated Components Waste Volume Curies % Error (Ci) 3 3 Class ft m Shipped A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Waste Stream: Other Waste Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Waste Stream: Sum of All 4 Categories Waste Volume Curies % Error (Ci) 3 3 Class ft m Shipped A 2.69E+04 7.63E+02 5.67E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 2.69E+04 7.63E+02 5.67E+00 +/-25%

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 23 of 55 Annual Radioactive Effluent Release Report 5.2 Units 1 & 2 Solid Waste - Destination by Carrier Number of Mode of Transportations Destination Shipments 5 Interstate Ventures Waste Control Specialist, LLC (TSDF) 21 S & J Transportation Company, Inc. Waste Control Specialist, LLC (TSDF)

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 24 of 55 Annual Radioactive Effluent Release Report 5.3 Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Abundance Activity (Ci)

H-3 7.52% 3.77E-01 C-14 11.13% 5.57E-01 Cr-51 1.39% 6.96E-02 Mn-54 0.76% 3.78E-02 Fe-55 2.87% 1.44E-01 Co-57 0.12% 5.82E-03 Co-58 10.83% 5.42E-01 Co-60 7.13% 3.57E-01 Ni-59 0.97% 4.86E-02 Ni-63 50.36% 2.52E+00 Zn-65 0.12% 5.86E-03 Sr-89 0.01% 4.69E-04 Nb-94 0.03% 1.59E-03 Nb-95 0.38% 1.90E-02 Ag-110m 0.36% 1.81E-02 Sn-113 0.04% 1.98E-03 Sb-124 0.86% 4.30E-02 Sb-125 4.6% 2.30E-01 Te-123m 0.02% 8.40E-04 Cs-137 0.44% 2.23E-02 Ce-144 0.02% 8.46E-04 Hg-203 0.03% 1.70E-03 Pu-238 0% 2.06E-05 Pu-239 0% 4.86E-06 Pu-241 0.02% 9.55E-04 Am-241 0% 1.84E-05 Total 100.00% 5.01E+00 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 25 of 55 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Total Combined Nuclide Name Percent Abundance Curies H-3 7.52% 3.77E-01 C-14 11.13% 5.57E-01 Cr-51 1.39% 6.96E-02 Mn-54 0.76% 3.78E-02 Fe-55 2.87% 1.44E-01 Co-57 0.12% 5.82E-03 Co-58 10.83% 5.42E-01 Co-60 7.13% 3.57E-01 Ni-59 0.97% 4.86E-02 Ni-63 50.36% 2.52E+00 Zn-65 0.12% 5.86E-03 Sr-89 0.01% 4.69E-04 Nb-94 0.03% 1.59E-03 Nb-95 0.38% 1.90E-02 Ag-110m 0.36% 1.81E-02 Sn-113 0.04% 1.98E-03 Sb-124 0.86% 4.30E-02 Sb-125 4.6% 2.30E-01 Te-123m 0.02% 8.40E-04 Cs-137 0.44% 2.23E-02 Ce-144 0.02% 8.46E-04 Hg-203 0.03% 1.70E-03 Pu-238 0% 2.06E-05 Pu-239 0% 4.86E-06 Pu-241 0.02% 9.55E-04 Am-241 0% 1.84E-05 Total 100.00% 5.01E+00 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 26 of 55 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies C-14 0% 2.04E-05 Cr-51 1.2% 7.99E-03 Mn-54 1.22% 8.10E-03 Fe-55 26.16% 1.74E-01 Co-57 0.01% 5.44E-05 Co-58 2.57% 1.71E-02 Co-60 43.32% 2.88E-01 Ni-63 9.72% 6.47E-02 Sr-90 0.01% 9.98E-05 Zr-95 1.45% 9.68E-03 Nb-94 0.03% 2.26E-04 Nb-95 2.94% 1.96E-02 Tc-99 0.96% 6.39E-03 Sn-113 0.06% 4.18E-04 Sb-125 3.14% 2.09E-02 Cs-134 0.02% 1.15E-04 Cs-137 4.35% 2.89E-02 Ce-144 1.41% 9.39E-03 Pu-238 0.01% 9.88E-05 Pu-239 0% 5.25E-07 Pu-241 1.34% 8.91E-03 Am-241 0.03% 1.76E-04 Cm-242 0% 3.17E-05 Cm-243 0.02% 1.47E-04 Total 100.00% 6.66E-01 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 27 of 55 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Total Combined Nuclide Name Percent Abundance Curies C-14 0% 2.04E-05 Cr-51 1.2% 7.99E-03 Mn-54 1.22% 8.10E-03 Fe-55 26.16% 1.74E-01 Co-57 0.01% 5.44E-05 Co-58 2.57% 1.71E-02 Co-60 43.32% 2.88E-01 Ni-63 9.72% 6.47E-02 Sr-90 0.01% 9.98E-05 Zr-95 1.45% 9.68E-03 Nb-94 0.03% 2.26E-04 Nb-95 2.94% 1.96E-02 Tc-99 0.96% 6.39E-03 Sn-113 0.06% 4.18E-04 Sb-125 3.14% 2.09E-02 Cs-134 0.02% 1.15E-04 Cs-137 4.35% 2.89E-02 Ce-144 1.41% 9.39E-03 Pu-238 0.01% 9.88E-05 Pu-239 0% 5.25E-07 Pu-241 1.34% 8.91E-03 Am-241 0.03% 1.76E-04 Cm-242 0% 3.17E-05 Cm-243 0.02% 1.47E-04 Total 100.00% 6.66E-01 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 28 of 55 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 6.64% 3.77E-01 C-14 9.83% 5.58E-01 Cr-51 1.37% 7.76E-02 Mn-54 0.81% 4.59E-02 Fe-55 5.6% 3.18E-01 Co-57 0.1% 5.87E-03 Co-58 9.86% 5.60E-01 Co-60 11.38% 6.46E-01 Ni-59 0.86% 4.86E-02 Ni-63 45.59% 2.59E+00 Zn-65 0.1% 5.86E-03 Sr-89 0.01% 4.69E-04 Sr-90 0% 9.98E-05 Zr-95 0.17% 9.68E-03 Nb-94 0.03% 1.82E-03 Nb-95 0.68% 3.86E-02 Tc-99 0.11% 6.39E-03 Ag-110m 0.32% 1.81E-02 Sn-113 0.04% 2.40E-03 Sb-124 0.76% 4.30E-02 Sb-125 4.42% 2.51E-01 Te-123m 0.01% 8.40E-04 Cs-134 0% 1.15E-04 Cs-137 0.9% 5.12E-02 Ce-144 0.18% 1.02E-02 Hg-203 0.03% 1.70E-03 Pu-238 0% 1.19E-04 Pu-239 0% 5.38E-06 Pu-241 0.17% 9.87E-03 Am-241 0% 1.94E-04 Cm-242 0% 3.17E-05 Cm-243 0% 1.47E-04 Total 100.00% 5.67E+00 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 29 of 55 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories All Waste Classes Nuclide Name Percent Abundance Curies H-3 6.64% 3.77E-01 C-14 9.83% 5.58E-01 Cr-51 1.37% 7.76E-02 Mn-54 0.81% 4.59E-02 Fe-55 5.6% 3.18E-01 Co-57 0.1% 5.87E-03 Co-58 9.86% 5.60E-01 Co-60 11.38% 6.46E-01 Ni-59 0.86% 4.86E-02 Ni-63 45.59% 2.59E+00 Zn-65 0.1% 5.86E-03 Sr-89 0.01% 4.69E-04 Sr-90 0% 9.98E-05 Zr-95 0.17% 9.68E-03 Nb-94 0.03% 1.82E-03 Nb-95 0.68% 3.86E-02 Tc-99 0.11% 6.39E-03 Ag-110m 0.32% 1.81E-02 Sn-113 0.04% 2.40E-03 Sb-124 0.76% 4.30E-02 Sb-125 4.42% 2.51E-01 Te-123m 0.01% 8.40E-04 Cs-134 0% 1.15E-04 Cs-137 0.9% 5.12E-02 Ce-144 0.18% 1.02E-02 Hg-203 0.03% 1.70E-03 Pu-238 0% 1.19E-04 Pu-239 0% 5.38E-06 Pu-241 0.17% 9.87E-03 Am-241 0% 1.94E-04 Cm-242 0% 3.17E-05 Cm-243 0% 1.47E-04 Total 100.00% 5.67E+00 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 30 of 55 Annual Radioactive Effluent Release Report 5.4 Unit 3 Types of Solid Waste - Summary Waste Stream: Resins, Filters, and Evap Bottoms Waste Volume Curies  % Error (Ci) 3 3 Class ft m Shipped A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 9.50E+01 2.69E+00 2.47E+01 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 9.50E+01 2.69E+00 2.47E+01 +/- 25%

Waste Stream  : Dry Active Waste Waste Volume Curies  % Error (Ci) 3 3 Class ft m Shipped A 4.00E+03 1.13E+02 1.14E-02 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 4.00E+03 1.13E+02 1.14E-02 +/-25%

Waste Stream  : Irradiated Components Waste Volume Curies  % Error (Ci) 3 3 Class ft m Shipped A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Waste Stream: Other Waste Waste Volume Curies  % Error (Ci) 3 3 Class ft m Shipped A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Waste Stream: Sum of All 4 Categories Waste Volume Curies  % Error (Ci) 3 3 Class ft m Shipped A 4.00E+03 1.13E+02 1.14E-02 +/-25%

B 9.50E+01 2.69E+00 2.47E+01 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 4.10E+03 1.16E+02 2.47E+01 +/-25%

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 31 of 55 Annual Radioactive Effluent Release Report 5.5 Unit 3 Solid Waste - Destination by Carrier Number of Mode of Transportations Destination Shipments 2 Hittman Transport Energy Solutions - Bear Creek 1 Hittman Transport Erwin Resin Solutions LLC 5.6 Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Abundance Activity (Ci)

H-3 0.01% 1.32E-03 C-14 0.05% 1.12E-02 Mn-54 0.35% 8.76E-02 Fe-55 3.49% 8.62E-01 Co-57 0.07% 1.66E-02 Co-58 0.15% 3.61E-02 Co-60 5.86% 1.45E+00 Ni-59 0.62% 1.54E-01 Ni-63 82.88% 2.05E+01 Sr-90 0.05% 1.34E-02 Nb-94 0.02% 3.86E-03 Sb-125 2.01% 4.97E-01 Cs-137 4.32% 1.07E+00 Ce-144 0% 8.23E-04 Pu-238 0% 5.10E-05 Pu-241 0.11% 2.80E-02 Am-241 0% 7.24E-05 Total 100.00% 2.47E+01 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 32 of 55 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Total Combined Nuclide Name Percent Abundance Curies H-3 0.01% 1.32E-03 C-14 0.05% 1.12E-02 Mn-54 0.35% 8.76E-02 Fe-55 3.49% 8.62E-01 Co-57 0.07% 1.66E-02 Co-58 0.15% 3.61E-02 Co-60 5.86% 1.45E+00 Ni-59 0.62% 1.54E-01 Ni-63 82.88% 2.05E+01 Sr-90 0.05% 1.34E-02 Nb-94 0.02% 3.86E-03 Sb-125 2.01% 4.97E-01 Cs-137 4.32% 1.07E+00 Ce-144 0% 8.23E-04 Pu-238 0% 5.10E-05 Pu-241 0.11% 2.80E-02 Am-241 0% 7.24E-05 Total 100.00% 2.47E+01 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 33 of 55 Annual Radioactive Effluent Release Report Units 3 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies C-14 0.02% 2.16E-06 Mn-54 0.66% 7.44E-05 Fe-55 7.56% 8.58E-04 Co-60 49.41% 5.61E-03 Ni-63 36.66% 4.16E-03 Nb-94 0.28% 3.17E-05 Tc-99 0.09% 9.73E-06 Sb-125 4.3% 4.88E-04 Cs-137 1.03% 1.17E-04 Total 100.00% 1.14E-02 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped Units 3 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Total Combined Nuclide Name Percent Abundance Curies C-14 0.02% 2.16E-06 Mn-54 0.66% 7.44E-05 Fe-55 7.56% 8.58E-04 Co-60 49.41% 5.61E-03 Ni-63 36.66% 4.16E-03 Nb-94 0.28% 3.17E-05 Tc-99 0.09% 9.73E-06 Sb-125 4.3% 4.88E-04 Cs-137 1.03% 1.17E-04 Total 100.00% 1.14E-02 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 34 of 55 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies C-14 0.02% 2.16E-06 Mn-54 0.66% 7.44E-05 Fe-55 7.56% 8.58E-04 Co-60 49.41% 5.61E-03 Ni-63 36.66% 4.16E-03 Nb-94 0.28% 3.17E-05 Tc-99 0.09% 9.73E-06 Sb-125 4.3% 4.88E-04 Cs-137 1.03% 1.17E-04 Total 100.00% 1.14E-02 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped Sum All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.01% 1.32E-03 C-14 0.05% 1.12E-02 Mn-54 0.35% 8.76E-02 Fe-55 3.49% 8.62E-01 Co-57 0.07% 1.66E-02 Co-58 0.15% 3.61E-02 Co-60 5.86% 1.45E+00 Ni-59 0.62% 1.54E-01 Ni-63 82.88% 2.05E+01 Sr-90 0.05% 1.34E-02 Nb-94 0.02% 3.86E-03 Sb-125 2.01% 4.97E-01 Cs-137 4.32% 1.07E+00 Ce-144 0% 8.23E-04 Pu-238 0% 5.10E-05 Pu-241 0.11% 2.80E-02 Am-241 0% 7.24E-05 Total 100.00% 2.47E+01

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 35 of 55 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories All Waste Classes Nuclide Name Percent Abundance Curies H-3 0.01% 1.32E-03 C-14 0.05% 1.12E-02 Mn-54 0.36% 8.77E-02 Fe-55 3.49% 8.63E-01 Co-57 0.07% 1.66E-02 Co-58 0.15% 3.61E-02 Co-60 5.88% 1.45E+00 Ni-59 0.62% 1.54E-01 Ni-63 82.86% 2.05E+01 Sr-90 0.05% 1.34E-02 Nb-94 0.02% 3.89E-03 Tc-99 0% 9.73E-06 Sb-125 2.02% 4.98E-01 Cs-137 4.32% 1.07E+00 Ce-144 0% 8.23E-04 Pu-238 0% 5.10E-05 Pu-241 0.11% 2.80E-02 Am-241 0% 7.24E-05 Total 100.00% 2.47E+01 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 36 of 55 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN The Radiological Impact on Man due to radioactive effluent from the site is determined from NRC approved modeling, per Regulatory Guide 1.109 and NUREG 0133. Calculations are divided into 3 categories: Noble Gases, Particulates and Iodine, and Liquid Releases (fish and invertebrate consumption). This modeling involves conservative dose calculations to Adult, Teen, Child, and Infant age groups. Furthermore, dose modeling is performed for six separate organs as well as the total body dose. This well-established industry model provides doses (as a result of plant effluent) to a hypothetical maximally exposed individual offsite. While all age groups and organs are considered, it is this maximum value that is provided in the tables that follow.

An approved computer code is used to perform liquid and gaseous dose calculations according to the models and parameters presented in the Indian Point Offsite Dose Calculation Manual (ODCM). This information is stored in a database on site to enhance dose tracking and information management. Site airborne effluent dose calculations include annual average dispersion and deposition factors, averaged from data collected over approximately ten-year periods. When new data is averaged (approximately every ten years) the modeling is updated and used in subsequent airborne effluent calculations. Liquid offsite dose calculations involve fish and invertebrate consumption pathways only, as determined appropriate in the ODCM.

While the ODCM identified some site-specific dose factors, the bulk of this information is obtained directly from Regulatory Guide 1.109 and NUREG 0133. Details of the calculations, site-specific data, and their bases are presented in the ODCM. See the tables at the end of this section for the 10CFR50 Appendix I Dose Assessments.

6.1 Dose to Members of the Public Inside the Site Boundary Members of the public visiting the site receive minimal dose as a result of onsite releases because of the relatively insignificant total amount of time they are on site, as well as the immeasurably low levels of dose at the critical receptors. Their doses can be calculated from standard ODCM methodology, with typical occupancy factors employed. These factors are determined by comparing a conservative assumption for their expected hours on site, to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> (the number of hours in a year, used in calculations in the ODCM).

Example 1: Several students visit the site for 8-hour tour.

Their occupancy factor is: 8 / 8760 or 0.0009 Example 2: A man drives his wife to work and drops her off at the security gate each morning, with a stay time of 2 minutes per day. His occupancy factor is calculated as follows:

2 min/day

  • 250 days/year / 60 min/hr / 8760 hr/year = 0.0010 6.2 Dose to a Member of the Public due to Release of Radioactive Material in Groundwater Curies and dose contribution from activity discovered in onsite groundwater and storm drain pathways during the year are discussed in more detail in Attachment 2. The offsite dose calculation involves multiple source term measurements, as well as computations for release and dilution flow. A summary of the quantification methodology, and the resulting calculated doses, is also provided in Attachment 2. The Summation of Dose Assessments (Table 6-1) below provides a means to compare ground water doses with those of other components making up the total offsite dose.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 37 of 55 Annual Radioactive Effluent Release Report 6.3 40CFR Part 190 Dose to Individual in the Unrestricted Area Unit and pathway-specific dose data can be found on the Radiological Impact on Man tables following this discussion. For simplicity and to demonstrate compliance with 40CFR190, the following table indicates the maximum hypothetical Total Dose to an individual from operation of the facility, including any measured direct shine component from the site property.

Table 6-1 Summation of Dose Assessments Year: 2020 Total Body Thyroid Max Organ 40 CFR 190 limit === IPEC 25 mrem 75 mrem 25 mrem 1

Routine Airborne Effluents Units 1 and 2 5.42E-04 5.42E-04 5.42E-04 Routine Liquid Effluents Units 1 and 2 1.12E-02 1.17E-05 1.82E-02 14 Liquid Releases of C Units 1 and 2 0.00E+00 0.00E+00 0.00E+00 14 Airborne Releases of C Units 1 and 2 0.00E+00 0.00E+00 0.00E+00 Routine Airborne Effluents1 Unit 3 2.44E-03 2.43E-03 2.43E-03 Routine Liquid Effluents Unit 3 7.66E-04 5.32E-04 1.81E-03 14 Liquid Releases of C Unit 3 1.17E-03 1.17E-03 5.83E-03 14 Airborne Releases of C Unit 3 2.09E-02 2.09E-02 1.05E-01 Ground Water & Storm Drain Totals IPEC2 4.91E-05 3.49E-07 1.99E-04 Direct Shine from areas such as dry cask storage, radwaste storage, SG IPEC3 3.00E-01 3.00E-01 3.00E-01 Mausoleum, etc.

Indian Point Energy Center IPEC 3.37E-01 3.26E-01 4.34E-01 Total Dose, per 40 CFR 190 Note 1: Routine airborne dose in this table is conservatively represented as a sum of Iodine, Particulate, and Tritium dose (excluding C-14, in mrem) with a mrem term added from noble gas gamma air energy (mrad, expressed as mrem). This addition does not represent a real dose and is listed here solely to help demonstrate compliance with 40CFR190. (Doses by type of release and comparison to the specific limits of 10CFR50 Appendix I are summarized on the following pages.)

Note 2: Groundwater curie and dose calculations are provided in Attachment 2.

Note 3: 40CFR190 requires the reporting of total dose, including that of direct shine. Direct shine dose from sources other than dry cask are indistinguishable from background. Direct shine dose is determined from TLDs near the dry cask area and site boundary, compared with REMP TLDs and historical values, and corrected with occupancy factors to determine a bounding, worst case assessment of direct shine dose to a real individual. Details of each years dose evaluation are available on site.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 38 of 55 Annual Radioactive Effluent Release Report Table 6-2 Unit 2 Appendix I Dose Assessment A. LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 3.57E-04 3.45E-03 1.03E-02 4.08E-03 1.82E-02 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 7.14E-03 6.90E-02 2.06E-01 8.16E-02 1.82E-01 Age Group Child Child Child Child Child Critical Organ Bone Bone Bone Bone Bone Adult Total Body (mrem) 2.22E-04 2.22E-03 6.40E-03 2.40E-03 1.12E-02 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 1.48E-02 1.48E-01 4.27E-01 1.60E-01 3.73E-01 Note: Liquid Annual dose is the Dose Analysis for the year, it is not a sum of the quarters B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 0.00E+00 3.49E-10 0.00E+00 0.00E+00 3.49E-10 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 0.00E+00 6.98E-09 0.00E+00 0.00E+00 3.49E-09 Beta Air (mrad) 0.00E+00 1.17E-09 0.00E+00 0.00E+00 1.17E-09 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 0.00E+00 1.17E-08 0.00E+00 0.00E+00 5.85E-09 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excluding C-14, for info only)

Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 3.33E-05 1.24E-04 2.36E-04 1.49E-04 5.42E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 4.44E-04 1.65E-03 3.15E-03 1.99E-03 3.62E-03 Age Group Child Child Child Child Child Critical Organ Liver Liver Liver Liver Liver C-14 only--> Child Bone 0 0 Child TB 0 0 D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Child TB Dose (mrem) 3.33E-05 1.24E-04 2.36E-04 1.49E-04 5.42E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 4.44E-04 1.65E-03 3.14E-03 1.99E-03 3.61E-03 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Child Bone Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 no C-14 Child TB Dose 3.33E-05 1.24E-04 2.36E-04 1.49E-04 5.42E-04 no C-14 Child Bone Dose 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 39 of 55 Annual Radioactive Effluent Release Report Table 6-3 Unit 3 Appendix I Dose Assessment A. LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 8.81E-04 3.73E-04 9.12E-04 7.51E-07 1.81E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 1.76E-02 7.46E-03 1.82E-02 1.50E-05 1.81E-02 Age Group Child Child Adult Adult Child Critical Organ Bone Bone GI-Lii GI-Lii Bone Adult Total Body (mrem) 3.35E-04 1.80E-04 2.51E-04 4.34E-07 7.66E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 2.23E-02 1.20E-02 1.67E-02 2.89E-05 2.55E-02 Note: Liquid Annual dose is the Dose Analysis for the year, it is not a sum of the quarters B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 5.94E-06 2.61E-06 0.00E+00 0.00E+00 8.55E-06 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 1.19E-04 5.22E-05 0.00E+00 0.00E+00 8.55E-05 Beta Air (mrad) 8.30E-06 8.43E-06 0.00E+00 0.00E+00 1.67E-05 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 8.30E-05 8.43E-05 0.00E+00 0.00E+00 8.37E-05 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excluding C-14, for info only)

Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 3.66E-04 4.15E-04 6.93E-04 9.58E-04 2.43E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 4.89E-03 5.54E-03 9.24E-03 1.28E-02 1.62E-02 Age Group Child Child Child Child Child Critical Organ Liver Liver Liver Liver Liver C-14 only--> Child Bone 8.32E-02 2.17E-02 0.00E+00 0.00E+00 1.05E-01 Child TB 1.66E-02 4.34E-03 0.00E+00 0.00E+00 2.09E-02 D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Child TB Dose (mrem) 1.70E-02 4.75E-03 6.93E-04 9.58E-04 2.34E-02 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 2.26E-01 6.34E-02 9.24E-03 1.28E-02 1.56E-01 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Child Bone Dose (mrem) 8.32E-02 2.17E-02 0.00E+00 0.00E+00 1.05E-01 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 1.11E+00 2.90E-01 0.00E+00 0.00E+00 7.00E-01 no C-14 Child TB Dose 3.66E-04 4.15E-04 6.93E-04 9.58E-04 2.43E-03 no C-14 Child Bone Dose 0 0 0 0

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 40 of 55 Annual Radioactive Effluent Release Report 7.0 METEOROLOGICAL DATA The site meteorological data is maintained on-site and available for review.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 41 of 55 Annual Radioactive Effluent Release Report - Carbon-14 Discussion Concentrations and offsite dose from C-14 were determined from sampling at Indian Point #3 from August 1980 to June 1982, during a study conducted by the NY State Department of Health (C. Kunz, later published and incorporated into NCRP 81). The annual C-14 curies released, as determined from this study, were consistent with NUREG 0017, Rev. 1. Data was then normalized to a maximum expected annual total, based on rated electrical capacity, (approximately 1000 MW(e) maintained for the entire year). Once the curies released were established, dose calculations were performed per the station ODCM, which uses all C-14 released to determine inhalation doses, and 26% of the total (determined to be Carbon Dioxide form), to determine the ingestion doses, in accordance with Regulatory Guide 1.109.

In 2010, IPEC and other facilities combined historical data with the application of an EPRI model designed to estimate C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc.). The estimates from this model, for IPEC, closely match the measured observations of 1982.

The maximum annual C-14 release information is as follows:

Maximum (Bounding) Annual C-14 releases from IPEC Unit 2 Unit 3 Liquid Effluent C14 Released Curies 0.07 0.07 Total Airborne C14 Released Curies 11.19 11.05 Airborne C14 as CO2 Curies 2.91 2.87 Airborne Effluent Child TB Dose, C14 mrem 0.0690 0.0675 Airborne Effluent Child Bone Dose, C14 mrem 0.346 0.338 Liquid Effluent Child TB Dose, C14 mrem 0.00117 0.00116 Liquid Effluent Child Bone Dose, C14 mrem 0.00583 0.00577 The bounding values were then normalized with actual effective full power days (EFFD) to yield more accurate year to year annual airborne curies and mrem for each unit. A small liquid effluent component is maintained at IPEC as a result of data accumulated in the 1983 study (Kunz). Tables 3-1 and 3-4 (shown earlier) include the airborne curie data for the current year. Section 6.0 (Radiological Impact on Man) includes the dose information.

C-14 doses are grouped with Iodine and Particulate and reported in Section D of Tables 6-2 and 6-

3. Section C of these tables provides doses from this category excluding C-14, to facilitate historical comparisons. However, since C-14 is grouped as a particulate, the total dose for this isotope needs to be added to the doses from iodine, particulate and H-3 doses for comparison to the singular dose limit for this category. Therefore, Tables 6-2 and 6-3 include dose from all categories of this group (Iodine, Particulate, Tritium, and Carbon-14), for appropriate comparison of the dose limits. C-14 doses (alone) for the current year are provided (for information) in the following table:

Calculated Annual C-14 releases from IPEC, 2021 Unit 2 Unit 3 Airborne Effluent Child TB Dose, C14 mrem 0.000 .0209 Airborne Effluent Child Bone Dose, C14 mrem 0.000 0.105 The airborne effluent dose from C-14 was distributed between 1st and 2nd quarter for Unit 3 and applied to a total Iodine and Particulate dose in Tables 6-1, 6-2 and 6-3. Unit 2 C-14 dose was set to zero because it was shutdown in 2020.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 42 of 55 Annual Radioactive Effluent Release Report - Groundwater Monitoring Program Results Summary of IPEC Groundwater and Storm Water Activity, 2021 The precipitation mass balance model applied in previous years was applied for offsite dose calculations in 2021, with some minor calibration updates performed in 2009 by the contractor with regard to the distribution of groundwater flow through the site. Groundwater elevation readings continued to validate the model throughout the year.

As defined in the ODCM, a conservative method of source term selection is used for determining offsite dose from Groundwater and Storm Water. If a result is below MDC (whether positive or negative) it is not included in the computed average. This computed average is therefore biased high (more conservative from a dose computation perspective) relative to an average computed using all of the data (many of which indicate no activity). In cases where all the sampling locations assigned to a given stream tube provided results below the MDC, then an average activity value of zero was assigned to the effected portion of the stream tube. (This mathematically allows the calculation to proceed in the absence of positive detections).

Historical average precipitation at IPEC has been approximately 3 feet per year. In 2011, precipitation was unusually high (over 6 feet). In 2021, precipitation was measured at 4.04 feet per year (or inches per month, as an average). Doses from Groundwater/Storm water are dependent on two factors:

source term and precipitation during the effected year.

Results of 2021 Groundwater and Storm water offsite dose evaluation The results of the assessment are shown below. These dose values are a small portion of the annual limits (<0.1%) and were added to the Total Dose table in the opening summary of the Radiological Impact to Man section of this report (Section 6).

Groundwater (GW) and storm water tritium released from IPEC in 2021 totaled approximately 0.05 curies, resulting in a total body dose of significantly less than 0.1 mrem. It is evident that tritium alone, whether from ground water or routine effluents, does not arithmetically contribute to integrated offsite dose.

Sampling near the effluent points identified only trace levels of Tritium and Strontium-90. These data, as part of the Monitored Natural Attenuation analyses, show a continuation of the decreasing trends established with the termination of the identified Unit 2 SFP leaks (tritium plume) and the defueling and draining of Unit 1 SFPs (strontium plume). Strontium-90, a legacy isotope from Unit 1, contributed approximately 0.000025 curies to site effluent from the groundwater pathway. Combined GW releases from IPEC in 2021 (all radionuclides) resulted in a calculated annual dose of less than 0.002 % of the annual limits for whole body and critical organ:

IPEC Groundwater and Storm Water Effluent Dose, 2021 0.0000491 mrem to the total body (0.0016% limit) 0.000199 mrem to the critical organ, adult bone (0.002% limit)

The annual dose from combined groundwater and storm water pathways remains well below applicable limits. When combined with routine liquid effluents (Section 6), the total dose also remains significantly below ALARA limits of 3 mrem total body, and 10 mrem to the critical organ.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 43 of 55 Annual Radioactive Effluent Release Report IPEC Summary for Storm & Ground Water Releases 2021 Northern Clean Zone Adult Doses, in mrem ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 5.31E-09 5.31E-09 5.31E-09 5.31E-09 5.31E-09 5.31E-09 4.75E+02 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 0.00E+00 5.31E-09 5.31E-09 5.31E-09 5.31E-09 5.31E-09 5.31E-09 4.75E+02 Unit 2 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 4.25E-08 4.25E-08 4.25E-08 4.25E-08 4.25E-08 4.25E-08 1.20E+04 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 0.00E+00 4.25E-08 4.25E-08 4.25E-08 4.25E-08 4.25E-08 4.25E-08 1.20E+04 Unit 1/2 ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 1.46E-07 1.46E-07 1.46E-07 1.46E-07 1.46E-07 1.46E-07 1.87E+04 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 1.99E-04 0.00E+00 4.87E-05 0.00E+00 0.00E+00 0.00E+00 5.72E-06 2.45E+01 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 1.99E-04 1.46E-07 4.89E-05 1.46E-07 1.46E-07 1.46E-07 5.87E-06 1.87E+04 Unit 3 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 1.19E-07 1.19E-07 1.19E-07 1.19E-07 1.19E-07 1.19E-07 1.07E+04 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 0.00E+00 1.19E-07 1.19E-07 1.19E-07 1.19E-07 1.19E-07 1.19E-07 1.07E+04 Unit 3 South ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 3.57E-08 3.57E-08 3.57E-08 3.57E-08 3.57E-08 3.57E-08 9.59E+03 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 0.00E+00 3.57E-08 3.57E-08 3.57E-08 3.57E-08 3.57E-08 3.57E-08 9.59E+03

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 44 of 55 Annual Radioactive Effluent Release Report Southern Clean Zone ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals: Adult Doses, in mrem Total H-3 only 0.00E+00 3.49E-07 3.49E-07 3.49E-07 3.49E-07 3.49E-07 3.49E-07 uCis BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI 5.14E+04 H3 all isotopes 1.99E-04 3.49E-07 4.91E-05 3.49E-07 3.49E-07 3.49E-07 6.07E-06 0.00E+00 Co 0.00E+00 Ni Adult Doses 2.45E+01 Sr

% Annual Limit 0.00199 0.000 0.00164 0.000 0.000 0.000 0.000 0.00E+00 Cs 0.00E+00 Sb

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 45 of 55 Annual Radioactive Effluent Release Report - Laboratory Analytical Results The following pages list the results of the 2021 groundwater samples. Note that the positive results are shown in bold print.

2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

I-2 6/17/2021 -6.19E+01 4.11E+02 1.0 1.6 -0.8 4.3 2.2 5.2 -0.6 10.7 MH-5 VCFD 1/13/2021 4.47E+02 MH-5 VCFD 2/22/2021 1.69E+03 4.47E+02 1.7 1.8 -7.8 8.2 3.3 6.1 1.5 13.2 MH-5 VCFD 3/17/2021 4.53E+02 MH-5 VCFD 4/12/2021 7.34E+02 MH-5 VCFD 5/17/2021 5.98E+02 4.80E+02 0.9 1.6 -1.8 7.1 2.5 5.9 0.1 14.0 MH-5 VCFD 6/14/2021 7.48E+02 MH-5 VCFD 7/13/2021 5.00E+02 MH-5 VCFD 8/9/2021 1.90E+03 4.92E+02 1.6 1.8 2.6 5.6 1.0 5.6 1.2 14.0 MH-5 VCFD 9/20/2021 1.20E+03 MH-5 VCFD 10/11/2021 8.00E+02 MH-5 VCFD 11/9/2021 7.24E+02 4.47E+02 0.2 1.6 1.2 5.9 1.3 6.9 -3.6 11.6 MH-5 VCFD 12/7/2021 7.56E+02 MW-107 4/27/2021 1.26E+02 3.81E+02 0.1 0.7 1.0 4.6 -0.5 5.3 1.7 10.3 MW-111 1/11/2021 4.48E+02 MW-111 2/23/2021 7.56E+02 5.07E+02 0.8 1.7 -2.2 6.7 -2.0 6.5 2.6 14.9 MW-111 4/28/2021 1.54E+03 5.04E+02 0.2 1.1 -0.8 6.5 5.0 6.9 2.3 16.0 MW-111 8/9/2021 9.22E+02 4.32E+02 -0.5 1.2 0.4 5.1 -0.8 6.4 2.1 14.4 MW-111 11/9/2021 6.54E+03 6.75E+02 0.7 1.7 0.8 7.3 -2.3 6.8 -2.1 17.0 MW-30-71 1/12/2021 6.56E+04 MW-30-71 2/15/2021 7.69E+04 MW-30-71 9/21/2021 2.20E+04 MW-30-71 11/17/2021 3.89E+04 MW-30-84 1/12/2021 7.30E+04 2.69E+03 -0.1 1.4 4.5 4.9 -0.6 4.7 -1.5 11.9 MW-30-84 2/15/2021 7.89E+04 2.84E+03 1.4 1.9 -1.0 3.9 0.7 4.9 -10.0 12.8 MW-30-84 3/18/2021 7.10E+04 2.29E+03 0.7 1.7 1.0 6.6 0.3 6.2 -1.5 17.7 MW-30-84 4/30/2021 6.39E+04 2.14E+03 -0.6 0.7 2.0 4.5 7.1 7.6 -4.4 12.3 MW-30-84 5/25/2021 7.13E+04 2.22E+03 -0.2 1.5 -0.4 7.1 -1.8 4.6 5.1 19.4 MW-30-84 7/15/2021 7.01E+04 1.83E+03 0.7 1.6 -1.0 5.5 1.4 6.6 -4.1 15.4 MW-30-84 8/18/2021 6.58E+04 2.08E+03 0.4 1.7 1.4 4.9 -0.5 6.5 -4.4 13.4 MW-30-84 9/21/2021 6.28E+04 1.71E+03 0.4 1.0 -0.5 5.8 2.6 5.6 6.8 14.8 MW-30-84 11/17/2021 5.65E+04 1.61E+03 0.4 1.6 2.2 6.4 0.0 6.6 5.9 17.0 MW-30-84 12/7/2021 5.26E+04 2.12E+03 0.3 1.7 2.1 5.6 0.0 4.4 -2.9 15.4 MW-31-49 2/16/2021 1.04E+03 3.96E+02 1.5 1.9 2.0 5.1 -0.7 5.5 1.9 13.4 MW-31-49 4/30/2021 1.79E+03 5.16E+02 0.2 0.8 -0.2 5.2 2.7 4.6 -0.3 11.2 MW-31-49 6/17/2021 2.30E+02 3.72E+02 1.1 1.5 0.5 5.6 0.1 6.5 -0.5 14.9 MW-31-49 7/12/2021 2.77E+02 3.99E+02 0.7 1.7 1.7 5.8 1.4 6.0 0.5 14.6 MW-31-49 8/18/2021 2.54E+03 5.34E+02 0.5 1.6 -0.3 4.5 2.8 6.1 15.3 20.5 MW-31-49 9/20/2021 1.86E+02 4.08E+02 0.2 1.6 1.8 5.4 2.1 6.2 -4.9 16.2 MW-31-49 11/16/2021 2.11E+03 5.01E+02 0.7 1.2 -1.1 4.8 -1.5 4.6 3.0 11.1 MW-31-63 1/12/2021 2.42E+04 1.54E+03 -0.3 1.4 0.4 3.8 1.2 5.5 37.6 29.6 MW-31-63 2/16/2021 2.85E+04 1.34E+03 -0.1 1.4 0.5 4.6 -2.3 5.1 36.7 27.9 MW-31-63 4/1/2021 1.73E+04 1.16E+03 0.7 1.7 2.9 5.2 1.3 4.2 29.7 20.3 MW-31-63 4/30/2021 2.02E+04 1.27E+03 0.6 1.3 3.0 6.7 -1.0 7.6 9.3 19.5 MW-31-63 5/25/2021 2.33E+04 1.91E+03 0.8 1.6 -1.1 8.1 3.0 5.8 26.8 37.8 MW-31-63 9/20/2021 1.71E+04 9.60E+02 1.2 1.4 0.6 6.1 -2.6 7.1 -4.3 17.4 MW-31-63 11/16/2021 1.51E+04 9.15E+02 1.2 1.4 1.6 15.5 1.6 6.2 1.7 20.0 MW-31-63 12/6/2021 1.82E+04 1.29E+03 0.7 1.7 4.5 6.5 4.4 5.8 17.4 18.6

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 46 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-31-85 2/16/2021 6.33E+03 6.90E+02 0.4 1.4 -3.0 5.8 -0.5 6.5 11.1 14.4 MW-31-85 4/30/2021 6.13E+03 7.62E+02 1.0 1.1 0.1 4.1 -0.3 5.0 8.5 18.4 MW-31-85 9/20/2021 9.85E+02 4.56E+02 0.6 1.6 1.4 5.2 -0.9 5.2 10.5 15.1 MW-31-85 11/16/2021 1.54E+03 4.80E+02 1.0 1.7 -1.3 7.3 1.7 5.9 3.6 12.3 MW-32-149 4/30/2021 3.41E+02 3.87E+02 -0.3 1.1 1.9 5.4 2.2 4.6 -0.7 14.1 MW-32-173 2/26/2021 1.85E+02 2.87E+02 -1.2 1.4 0.6 5.3 2.4 4.8 5.6 11.2 MW-32-173 8/27/2021 2.98E+02 3.21E+02 0.1 1.2 -1.0 6.0 2.1 7.1 -1.5 17.8 MW-32-173 11/17/2021 3.31E+02 4.17E+02 0.5 1.6 1.6 5.9 -1.7 4.9 -2.9 16.2 MW-32-190 2/26/2021 5.47E+02 3.57E+02 1.1 1.8 1.1 4.8 -1.0 5.0 1.6 11.4 MW-32-190 4/30/2021 4.73E+02 3.90E+02 0.3 0.9 2.6 5.3 0.3 5.6 -6.8 12.4 MW-32-190 8/27/2021 3.20E+02 3.18E+02 -0.6 1.3 0.0 13.7 -1.7 4.0 6.0 13.4 MW-32-59 1/12/2021 2.91E+04 1.71E+03 0.7 1.6 1.1 5.0 1.3 6.6 30.5 28.6 MW-32-59 2/26/2021 2.06E+04 1.62E+03 1.8 1.9 2.4 4.7 -1.0 6.8 26.4 30.3 MW-32-59 3/18/2021 2.50E+04 1.40E+03 0.0 1.6 0.4 4.8 0.9 5.6 24.8 20.8 MW-32-59 4/30/2021 2.27E+04 1.34E+03 1.6 1.7 -1.3 5.3 3.9 5.9 0.0 26.0 MW-32-59 5/24/2021 2.55E+04 1.35E+03 1.6 1.8 2.1 7.4 -5.6 8.6 6.2 29.9 MW-32-59 6/18/2021 2.69E+04 1.73E+03 0.3 1.6 1.7 8.8 0.6 5.5 0.0 27.7 MW-32-59 7/15/2021 4.88E+03 7.17E+02 -0.5 1.6 1.6 8.0 0.8 7.6 19.0 20.0 MW-32-59 8/27/2021 1.03E+03 4.59E+02 1.4 1.8 -0.4 5.4 -0.2 4.8 5.8 15.3 MW-32-59 9/21/2021 9.92E+03 7.80E+02 0.0 0.7 -1.1 6.5 3.3 6.8 12.0 17.9 MW-32-59 11/17/2021 1.58E+04 9.33E+02 1.2 1.8 0.8 8.7 8.3 13.1 6.5 22.1 MW-32-59 12/7/2021 1.84E+04 1.29E+03 1.7 1.8 2.9 5.1 3.4 5.0 0.0 35.1 MW-32-85 2/26/2021 2.40E+04 1.71E+03 -1.2 1.6 2.9 6.4 -2.2 4.5 10.8 14.5 MW-32-85 3/18/2021 2.01E+04 1.27E+03 0.5 1.7 -1.8 6.5 0.4 7.7 3.6 15.9 MW-32-85 4/30/2021 2.01E+04 1.27E+03 -0.7 0.9 -1.2 4.7 0.9 5.6 0.7 15.0 MW-32-85 5/24/2021 2.03E+04 1.22E+03 0.9 1.1 1.3 5.0 0.0 4.9 3.1 16.8 MW-32-85 6/18/2021 1.90E+04 1.47E+03 1.3 1.7 1.8 5.9 3.2 6.4 1.8 12.3 MW-32-85 7/15/2021 1.83E+04 9.96E+02 -0.6 1.4 1.9 6.1 1.3 5.8 4.9 15.5 MW-32-85 8/27/2021 1.91E+04 7.71E+02 1.3 1.3 0.6 5.0 5.7 5.3 -1.5 13.7 MW-32-85 9/21/2021 1.61E+04 9.48E+02 -0.7 0.9 -1.5 7.6 -4.3 8.6 -2.6 17.5 MW-32-85 11/17/2021 1.37E+04 8.76E+02 0.2 1.4 -0.4 5.9 -1.7 5.4 -2.2 14.5 MW-32-85 12/7/2021 1.38E+04 1.14E+03 1.4 1.8 0.6 4.7 -0.3 5.0 -2.7 10.8 MW-33 1/11/2021 2.90E+03 MW-33 2/23/2021 2.56E+03 5.85E+02 1.1 1.8 1.1 4.5 6.4 6.9 11.1 21.3 MW-33 4/28/2021 1.62E+03 4.92E+02 0.5 1.2 -2.7 5.9 -0.3 4.5 0.6 13.9 MW-33 8/9/2021 1.99E+03 4.83E+02 1.2 1.7 1.3 5.1 0.9 5.1 0.1 12.0 MW-33 11/9/2021 1.73E+03 4.68E+02 -0.4 1.5 3.3 7.6 -1.5 8.5 20.8 19.2 MW-35 1/11/2021 8.93E+02 3.84E+02 0.1 1.5 -2.4 7.0 -0.7 5.2 5.5 13.1 MW-35 2/23/2021 2.27E+02 3.36E+02 0.8 1.8 2.3 6.4 -0.4 4.3 -5.3 12.5 MW-35 4/1/2021 1.39E+02 3.90E+02 1.1 1.8 -0.1 6.0 0.7 7.5 1.2 15.2 MW-35 4/28/2021 4.37E+02 3.96E+02 0.6 1.7 -0.4 7.7 1.7 10.1 -2.5 20.7 MW-35 5/25/2021 5.94E+02 4.05E+02 1.2 1.7 0.2 6.3 1.1 5.1 2.1 18.0 MW-35 6/15/2021 6.53E+02 5.16E+02 1.3 1.8 -0.1 6.8 0.3 5.9 -5.4 14.2 MW-35 7/14/2021 8.67E+02 4.32E+02 -0.5 1.1 4.8 7.3 1.2 5.3 2.0 13.6 MW-35 8/9/2021 7.09E+02 4.17E+02 0.5 1.7 1.0 5.3 1.4 6.3 -9.7 14.7 MW-35 9/17/2021 3.30E+03 5.55E+02 0.0 0.7 0.5 5.4 1.8 5.5 5.7 12.1 MW-35 10/11/2021 8.29E+02 4.62E+02 0.9 1.7 -2.5 5.4 -5.9 9.9 0.0 14.9 MW-35 11/9/2021 1.87E+03 4.92E+02 1.2 1.7 3.5 7.7 -1.2 8.0 3.8 15.8 MW-35 12/6/2021 1.79E+03 5.49E+02 -0.8 1.1 -5.2 9.0 -3.2 6.8 -2.0 13.7 MW-36-24 2/8/2021 2.74E+02 3.33E+02 -0.2 1.5 1.8 6.7 1.2 7.7 0.1 15.7 MW-36-24 5/14/2021 8.69E+01 3.54E+02 1.0 1.8 -1.8 4.9 1.9 6.7 1.5 14.7 MW-36-24 8/11/2021 1.06E+02 3.90E+02 -0.2 1.5 7.8 10.0 0.6 6.2 7.4 16.8

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 47 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-36-24 11/12/2021 4.84E+03 1.05E+03 1.6 1.8 -3.0 6.8 0.2 4.2 0.8 13.7 MW-36-41 2/8/2021 4.65E+03 7.86E+02 6.3 2.0 -3.8 6.0 0.6 6.3 -3.0 14.5 MW-36-41 5/14/2021 2.33E+03 5.46E+02 4.0 2.1 -1.1 6.5 2.7 6.2 -0.8 15.8 MW-36-41 8/11/2021 3.46E+03 5.43E+02 2.6 1.2 -1.8 7.3 2.2 7.1 -6.8 18.7 MW-36-41 11/12/2021 4.88E+03 6.15E+02 5.3 1.9 -0.1 5.6 -6.1 10.5 -1.0 13.2 MW-36-52 2/8/2021 1.09E+03 4.02E+02 2.1 1.0 1.1 5.2 -3.8 6.3 -3.3 12.0 MW-36-52 5/14/2021 9.80E+01 3.57E+02 1.4 1.6 1.1 7.0 4.9 9.2 -0.9 16.1 MW-36-52 8/11/2021 5.21E+02 3.99E+02 -0.6 1.5 1.3 7.4 1.1 5.7 -3.5 15.5 MW-36-52 11/12/2021 6.93E+02 4.53E+02 1.1 1.3 -11.9 13.8 9.0 12.3 -3.1 20.1 MW-37-22 5/14/2021 1.05E+03 4.47E+02 3.8 2.2 -4.7 8.5 -3.5 8.3 0.8 18.9 MW-37-22 11/18/2021 3.13E+03 5.52E+02 2.6 1.9 0.3 6.8 -0.4 6.5 4.8 19.3 MW-37-32 5/14/2021 2.24E+03 5.43E+02 5.6 2.2 -2.4 4.5 1.1 5.7 4.3 10.3 MW-37-32 11/18/2021 4.38E+03 5.91E+02 6.7 2.5 -1.2 5.3 1.6 4.6 -0.2 12.6 MW-37-40 5/14/2021 3.06E+03 5.97E+02 15.6 3.5 -0.8 5.6 2.7 8.1 -1.4 14.6 MW-37-40 11/18/2021 2.75E+03 5.52E+02 10.0 3.2 0.8 4.5 -1.4 4.9 -1.6 11.1 MW-37-57 5/14/2021 3.22E+03 6.09E+02 4.5 2.2 1.1 5.4 1.3 5.3 -2.5 11.5 MW-37-57 11/18/2021 2.94E+03 5.58E+02 7.6 2.6 1.0 4.8 -1.1 6.3 -0.4 15.6 MW-39-102 5/20/2021 5.12E+01 3.60E+02 1.8 1.9 1.2 5.4 3.0 7.1 9.2 15.2 MW-39-102 11/17/2021 3.42E+02 4.20E+02 0.8 1.2 -3.2 7.1 -0.1 7.5 4.5 16.9 MW-39-183 5/20/2021 1.74E+01 3.63E+02 1.6 1.9 -3.9 9.1 0.1 6.2 23.3 26.9 MW-39-183 11/17/2021 2.49E+02 4.17E+02 0.3 1.2 -1.1 7.3 -0.6 7.9 3.6 17.9 MW-39-195 5/20/2021 2.10E+01 3.57E+02 0.7 1.0 -4.0 8.6 -2.0 8.5 12.0 16.5 MW-39-195 11/17/2021 2.30E+02 4.20E+02 1.2 1.4 0.3 5.9 0.4 5.8 1.7 16.5 MW-39-67 5/20/2021 2.90E+02 3.81E+02 0.6 1.7 -0.3 6.7 2.8 8.0 7.1 17.0 MW-39-67 11/17/2021 1.80E+02 4.11E+02 1.2 1.3 -1.4 5.3 2.8 6.3 -8.7 14.8 MW-39-84 5/20/2021 1.52E+02 3.66E+02 1.4 1.8 2.5 5.3 -0.7 6.6 4.4 14.1 MW-39-84 11/17/2021 7.27E+00 4.02E+02 1.0 1.2 1.0 6.1 0.5 5.5 -5.0 18.3 MW-40-100 2/12/2021 1.43E+02 3.12E+02 1.0 1.7 0.4 5.6 0.6 5.7 -2.5 14.7 MW-40-100 4/26/2021 1.84E+02 3.69E+02 0.2 0.7 -1.1 5.7 0.7 4.1 -4.3 11.6 MW-40-100 8/30/2021 -1.50E+02 3.54E+02 0.1 1.1 0.2 6.8 -1.5 7.3 -4.4 14.6 MW-40-100 11/23/2021 -3.02E+01 2.78E+02 0.8 1.0 -0.5 6.2 -5.1 10.1 1.3 13.5 MW-40-127 2/12/2021 1.28E+01 3.09E+02 1.4 1.8 1.6 6.0 -3.1 5.7 8.5 13.5 MW-40-127 4/26/2021 1.89E+02 3.63E+02 -0.3 0.7 2.0 5.4 -3.0 5.7 12.8 24.2 MW-40-127 8/30/2021 -1.53E+02 3.63E+02 0.3 1.1 -0.2 5.6 1.9 6.0 8.1 13.8 MW-40-127 11/23/2021 6.51E+01 2.98E+02 0.5 1.4 -2.1 12.7 0.1 8.6 1.9 21.7 MW-40-162 2/12/2021 -2.90E+01 3.03E+02 1.4 1.7 -3.7 5.3 1.5 6.3 -4.8 13.7 MW-40-162 4/26/2021 1.61E+02 3.66E+02 -0.1 1.5 -0.3 4.2 1.5 4.5 1.6 12.1 MW-40-162 8/30/2021 1.76E+01 3.81E+02 0.8 1.3 -0.1 5.1 0.1 3.7 -0.5 13.3 MW-40-162 11/23/2021 -1.13E+02 2.65E+02 1.0 1.2 0.0 6.2 0.9 5.4 1.0 15.4 MW-40-27 2/12/2021 2.33E+02 3.30E+02 1.1 1.7 1.0 4.4 3.3 5.6 -3.6 11.4 MW-40-27 4/26/2021 1.82E+02 3.63E+02 -0.2 0.7 2.7 5.0 1.8 6.0 8.6 15.2 MW-40-27 8/30/2021 -1.75E+02 3.96E+02 0.1 1.1 -2.7 7.1 0.0 8.1 -4.0 17.2 MW-40-27 11/23/2021 -3.05E+00 4.05E+02 0.2 1.2 -0.2 5.0 0.6 4.6 -2.3 10.7 MW-40-46 2/12/2021 4.79E+00 3.06E+02 0.9 1.7 -3.6 6.9 0.5 6.7 -1.0 16.8 MW-40-46 4/26/2021 3.20E+02 3.78E+02 0.4 1.0 7.1 8.0 -2.7 7.3 -8.8 15.8 MW-40-46 8/30/2021 3.63E+01 3.90E+02 0.9 1.4 3.1 5.8 -0.5 7.1 6.7 18.1 MW-40-46 11/23/2021 5.45E+01 4.08E+02 1.1 1.6 0.0 7.9 0.5 7.5 -9.0 16.3 MW-40-81 2/12/2021 1.90E+01 3.09E+02 0.5 1.5 -2.2 6.4 -0.3 4.1 6.6 11.9 MW-40-81 4/26/2021 3.01E+02 3.78E+02 0.4 0.7 2.5 5.2 2.6 4.3 5.4 14.3 MW-40-81 8/30/2021 -1.88E+02 3.84E+02 0.2 1.4 1.3 4.6 -0.9 5.0 3.0 12.4 MW-40-81 11/23/2021 -1.92E+00 2.90E+02 0.8 1.3 8.7 14.6 -2.9 7.9 3.1 20.5 MW-41-40 1/21/2021 1.20E+03 3.78E+02 0.7 1.7 -0.4 4.6 1.0 5.0 -3.3 19.2 -1.1 12.0 MW-41-40 2/17/2021 2.39E+02 3.30E+02 0.3 1.6 -0.6 5.9 3.4 11.8 -4.9 14.1

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 48 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-41-40 3/11/2021 6.00E+02 4.32E+02 0.4 1.7 -0.6 5.6 0.5 5.6 1.5 14.9 -3.1 10.7 MW-41-40 4/14/2021 3.03E+02 3.66E+02 MW-41-40 5/5/2021 1.46E+02 3.66E+02 1.2 1.7 1.1 5.2 0.5 6.1 6.4 17.7 -1.0 13.8 MW-41-40 9/20/2021 7.90E+01 4.08E+02 0.3 1.2 -1.0 6.0 -2.1 8.4 -3.4 17.8 MW-41-40 11/22/2021 2.73E+02 4.20E+02 0.7 1.7 1.4 6.1 2.0 6.1 2.6 11.3 11.9 23.3 MW-41-63 1/21/2021 5.00E+02 4.02E+02 -0.1 1.6 -1.9 5.1 -3.9 4.8 9.9 19.8 0.5 12.2 MW-41-63 2/24/2021 1.11E+03 4.59E+02 -1.2 1.5 1.3 5.4 4.0 8.7 -0.4 13.0 MW-41-63 3/12/2021 1.00E+03 4.62E+02 0.1 0.9 1.9 7.3 -2.7 7.5 3.6 15.2 2.8 17.7 MW-41-63 4/16/2021 1.98E+01 3.30E+02 MW-41-63 5/5/2021 2.74E+02 3.75E+02 -0.1 1.5 -2.5 7.8 1.7 10.5 -7.0 16.7 -26.3 20.9 MW-41-63 9/20/2021 3.39E+02 4.17E+02 1.5 1.6 -1.8 5.6 -0.8 5.8 1.8 12.6 MW-41-63 11/22/2021 1.70E+02 4.17E+02 1.3 1.7 0.8 5.2 0.6 5.5 4.1 14.0 7.0 17.3 MW-42-49 1/11/2021 3.69E+02 4.14E+02 15.0 3.5 43500.0 372.0 0.9 7.1 523.0 39.0 53.9 153.0 MW-42-49 2/24/2021 3.22E+02 3.75E+02 42.6 4.7 98400.0 444.0 -0.9 5.8 996.0 35.1 34.4 173.7 MW-42-49 3/17/2021 2.98E+02 3.63E+02 38.7 4.1 62100.0 408.0 1.4 6.5 839.0 41.1 -40.1 183.0 MW-42-49 4/29/2021 2.84E+02 3.69E+02 29.1 4.1 55700.0 333.0 0.8 6.2 696.0 38.1 -87.6 135.3 MW-42-49 5/26/2021 3.15E+02 4.02E+02 35.8 4.4 52900.0 402.0 2.8 6.5 671.0 33.6 -29.2 179.1 MW-42-49 6/15/2021 2.47E+02 3.87E+02 23.9 4.0 42400.0 318.0 -1.3 5.9 922.0 38.4 83.9 171.9 MW-42-49 7/14/2021 4.76E+02 4.44E+02 6.9 1.5 33700.0 306.0 5.8 10.4 -2.6 146.4 MW-42-49 8/10/2021 5.38E+02 4.08E+02 6.1 6.9 27900.0 266.4 -1.1 6.2 290.0 25.2 11.0 110.4 MW-42-49 9/16/2021 5.15E+02 3.72E+02 -1.5 7.3 1.2 5.2 -0.4 5.9 -8.9 24.5 -0.1 15.2 MW-42-49 10/12/2021 5.04E+02 3.72E+02 9.7 2.9 21900.0 220.2 0.4 5.1 255.0 27.2 -9.6 92.1 MW-42-49 11/11/2021 3.16E+02 3.06E+02 8.4 2.2 18700.0 201.6 2.3 5.0 261.0 27.8 -9.9 78.9 MW-42-49 12/6/2021 2.74E+02 4.26E+02 31.7 2.7 24900.0 256.5 3.7 7.1 482.0 41.7 11.1 98.1 MW-42-78 2/24/2021 5.71E+02 3.66E+02 -0.9 1.6 4.3 5.8 2.3 5.8 10.2 15.0 5.7 15.8 MW-42-78 4/29/2021 3.11E+02 4.02E+02 -0.4 1.0 -1.0 6.2 0.5 6.9 -0.9 14.6 0.7 14.2 MW-42-78 8/10/2021 5.68E+02 4.32E+02 0.5 1.4 0.5 6.9 -0.8 5.4 5.3 14.8 -9.8 16.8 MW-42-78 11/11/2021 1.62E+02 3.21E+02 0.5 1.7 -0.1 4.8 0.7 4.7 -3.2 11.3 -3.2 11.8 MW-43-28 1/14/2021 1.95E+02 4.17E+02 0.7 1.6 1.7 4.6 1.0 5.0 1.7 12.7 MW-43-28 2/16/2021 3.22E+02 3.24E+02 0.9 1.3 -0.8 6.3 3.7 6.5 -0.1 16.5 MW-43-28 3/12/2021 9.79E+01 2.96E+02 0.0 1.1 0.0 8.7 0.6 7.0 2.2 14.9 MW-43-28 4/12/2021 1.36E+02 3.45E+02 MW-43-28 5/6/2021 2.73E+02 3.75E+02 -1.1 1.2 0.6 5.4 3.5 5.2 0.3 13.9 MW-43-62 1/14/2021 1.88E+01 3.84E+02 0.1 1.5 -4.1 5.5 -0.9 7.9 -3.5 14.3 MW-43-62 2/16/2021 3.01E+02 3.24E+02 0.1 1.1 -1.3 6.5 -3.0 8.0 -1.9 15.1 MW-43-62 3/12/2021 1.44E+02 4.41E+02 0.2 1.6 0.8 5.1 0.2 3.6 -0.2 14.1 MW-43-62 4/12/2021 6.20E+01 3.48E+02 MW-43-62 5/6/2021 2.09E+02 3.72E+02 0.8 1.6 1.1 5.1 4.2 7.7 -2.6 12.4 MW-45-42 1/21/2021 3.51E+03 6.84E+02 -0.8 1.6 -2.9 5.0 2.1 5.7 -0.4 11.6 MW-45-42 2/17/2021 2.70E+03 4.98E+02 1.4 1.9 -3.7 6.3 0.9 5.0 0.6 10.5 MW-45-42 3/11/2021 7.17E+03 9.33E+02 0.0 1.6 0.4 6.2 3.7 7.6 -10.8 15.1 MW-45-42 4/14/2021 8.77E+03 7.74E+02 -0.1 1.3 1.5 7.7 2.2 7.4 5.6 20.2 MW-45-42 5/5/2021 1.03E+04 8.97E+02 -0.3 1.4 -0.9 5.6 0.4 4.9 -2.7 11.6 MW-45-42 6/17/2021 9.96E+03 1.11E+03 1.0 1.7 3.2 5.6 -1.1 5.8 3.4 12.8 MW-45-42 7/12/2021 2.14E+03 4.98E+02 -0.4 1.4 2.2 5.9 -0.6 6.8 -4.0 17.9 MW-45-42 8/23/2021 8.56E+02 4.26E+02 -0.7 1.4 3.2 5.2 2.3 6.3 -6.9 12.3 MW-45-42 9/16/2021 1.95E+03 4.98E+02 0.3 1.5 4.0 9.1 3.2 7.9 -6.9 19.2 MW-45-42 10/12/2021 3.54E+03 8.94E+02 1.3 1.6 1.6 5.4 3.3 3.6 2.6 13.5 MW-45-42 11/11/2021 1.46E+03 5.25E+02 0.5 1.7 1.0 5.0 -0.5 5.0 0.7 12.6 MW-45-61 1/21/2021 1.40E+03 5.10E+02 1.8 1.9 3.8 4.7 1.0 4.7 -2.5 11.2 MW-45-61 2/17/2021 1.49E+03 4.56E+02 0.3 1.6 -2.1 6.2 0.5 4.9 -6.4 13.2 MW-45-61 3/11/2021 2.87E+03 6.75E+02 0.1 1.7 1.7 5.0 1.9 5.2 -2.2 14.4 MW-45-61 4/14/2021 2.35E+03 4.68E+02 <MDC 3.1 2 6 0.5 4.6 14.3 16.4 MW-45-61 5/5/2021 2.67E+03 5.43E+02 -0.3 1.3 1 6 1.6 5.3 -7.2 12.0 MW-45-61 6/17/2021 2.89E+03 7.11E+02 <MDC 2.3 1 5 -3.6 6.8 -4.0 13.1 MW-45-61 7/12/2021 2.78E+03 5.22E+02 -0.4 1.4 3.9 6.2 -2.2 4.9 10.5 19.8 MW-45-61 8/23/2021 1.85E+03 4.98E+02 1.0 1.7 -0.6 6.1 -1.2 6.3 5.7 15.6 MW-45-61 9/16/2021 1.31E+03 4.74E+02 0.3 1.7 1.0 4.6 0.4 4.5 3.2 13.9

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 49 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-45-61 10/12/2021 1.12E+03 4.83E+02 0.5 1.3 4.6 10.5 0.3 6.8 0.0 14.1 MW-45-61 11/11/2021 8.92E+02 4.35E+02 0.6 1.5 1.0 6.1 -1.3 4.4 -11.2 18.0 MW-46 4/12/2021 2.46E+02 3.72E+02 MW-46 5/10/2021 2.79E+02 3.69E+02 -0.8 1.5 -4 6 -2.1 8.5 -2.2 13.2 MW-46 6/14/2021 6.88E+02 4.11E+02 <MDC 2.1 -1 6 5.1 8.6 -6 17 7.7 15.5 MW-46 7/13/2021 7.94E+02 4.29E+02 MW-46 8/24/2021 8.97E+02 4.41E+02 1.9 1.9 2.3 5.4 -1.7 5.8 -1.2 12.6 MW-46 9/17/2021 5.88E+02 4.32E+02 0.8 1.2 -4.3 7.0 -1.1 6.3 5.6 14.5 MW-46 10/11/2021 6.02E+02 4.56E+02 0.6 1.7 9.2 16.3 5.0 9.5 7.9 21.9 MW-46 11/10/2021 8.81E+02 4.44E+02 0.7 1.7 -1.4 4.6 5.4 7.0 4.7 13.3 MW-49-26 5/7/2021 3.00E+03 5.76E+02 9.2 1.9 7 12 0.4 9.2 8 15 -5.6 21.7 MW-49-26 11/8/2021 3.06E+03 5.31E+02 8.6 2.9 1.1 4.8 -0.1 5.0 6.3 18.2 2.3 14.3 MW-49-42 5/7/2021 2.89E+03 5.76E+02 6.2 1.5 -1 7 0.9 7.2 -3 15 2.5 19.1 MW-49-42 11/8/2021 2.88E+03 5.37E+02 10.5 2.7 -2.6 7.4 2.5 6.3 5.1 18.4 2.6 16.3 MW-49-65 5/7/2021 2.09E+03 5.04E+02 5.7 1.4 -1 5 0.2 5.4 2 15 2.5 12.5 MW-49-65 11/8/2021 2.45E+03 5.13E+02 8.0 2.5 -1.3 5.0 0.5 6.0 6.5 18.7 -2.4 14.8 MW-50-42 2/8/2021 6.48E+02 3.69E+02 3.3 2.1 -3.8 8.8 -0.5 5.2 -10.7 20.2 1.2 12.0 MW-50-42 4/29/2021 8.15E+02 4.23E+02 1.9 1.9 -1.7 5.4 0.7 5.5 -2.7 14.7 -7.8 12.1 MW-50-42 8/11/2021 9.71E+02 4.35E+02 2.1 2.0 2.3 8.2 2.7 8.5 2.7 18.3 MW-50-42 11/12/2021 6.96E+02 4.14E+02 5.7 2.4 -2.9 7.1 -0.1 6.8 3.0 11.2 -0.1 15.2 MW-50-66 2/8/2021 3.20E+03 6.78E+02 9.9 2.6 0.6 6.7 0.0 6.3 -4.6 21.7 4.0 15.1 MW-50-66 4/29/2021 2.51E+03 5.49E+02 9.7 2.8 -0.8 7.7 -3.9 6.5 -4.0 14.7 0.3 14.0 MW-50-66 8/11/2021 2.51E+03 5.07E+02 10.3 2.5 0.2 4.1 -1.2 4.3 13.6 21.8 MW-50-66 11/12/2021 1.86E+03 5.52E+02 16.0 3.4 3.2 5.3 1.7 5.0 1.8 12.1 0.4 12.9 MW-51-104 3/16/2021 1.62E+02 3.72E+02 -0.8 1.6 5.1 6.7 -1.5 5.3 -5.1 11.4 MW-51-104 4/26/2021 7.54E+01 3.54E+02 0.4 0.8 1.4 4.2 2.6 5.9 -6.4 16.6 MW-51-104 8/31/2021 -4.58E+01 3.57E+02 -0.1 1.1 3.9 7.3 2.9 6.5 5.8 14.4 MW-51-104 11/23/2021 2.99E-01 3.90E+02 0.0 1.5 -2.1 5.7 6.3 6.3 2.9 16.4 MW-51-135 3/16/2021 3.10E+00 3.69E+02 0.0 1.6 1.5 6.5 0.3 5.3 0.1 11.8 MW-51-135 4/26/2021 -5.79E+01 3.42E+02 -0.1 0.8 4.1 6.1 4.5 6.4 4.7 15.0 MW-51-135 8/31/2021 5.30E+01 3.81E+02 0.9 1.1 -2.0 8.0 -0.2 9.4 4.0 21.8 MW-51-135 11/23/2021 1.03E+02 4.14E+02 -0.3 1.5 0.0 9.1 -2.8 7.7 -9.4 17.5 MW-51-163 3/16/2021 -4.07E+00 3.51E+02 0.0 1.6 -0.3 6.7 1.1 5.2 -1.9 17.9 MW-51-163 4/26/2021 2.53E+02 3.72E+02 0.6 0.9 3.6 6.4 4.0 8.1 2.4 16.4 MW-51-163 8/31/2021 -1.68E+02 3.39E+02 1.5 1.7 -0.7 5.9 3.0 5.7 7.1 16.5 MW-51-163 11/23/2021 2.01E+02 4.14E+02 0.6 1.6 0.0 5.3 2.4 6.5 1.8 18.1 MW-51-189 3/16/2021 3.90E+01 3.78E+02 -1.2 1.4 -0.8 6.7 3.1 5.8 -0.8 17.2 MW-51-189 4/26/2021 -8.95E+01 3.45E+02 1.8 1.9 1.2 6.5 -1.9 6.5 5.7 16.6 MW-51-189 8/31/2021 3.64E+01 3.21E+02 -0.1 0.9 -0.1 5.4 0.5 6.2 5.6 14.9 MW-51-189 11/23/2021 2.21E+02 4.23E+02 1.5 1.5 0.1 7.5 -0.7 9.2 4.4 16.1 MW-51-40 3/16/2021 6.09E+01 3.75E+02 0.0 1.6 1.3 10.3 0.0 4.8 -3.3 12.3 MW-51-40 4/26/2021 2.64E+02 3.69E+02 0.6 0.9 -0.1 5.5 0.9 5.9 2.6 15.2 MW-51-40 8/31/2021 -9.06E+01 3.96E+02 1.2 1.8 1.2 4.1 1.9 4.2 -3.8 11.7 MW-51-40 11/23/2021 1.84E+02 4.17E+02 0.9 1.7 3.4 5.3 1.0 5.0 7.1 12.3 MW-51-79 3/16/2021 -2.07E+01 3.75E+02 1.0 1.7 -0.4 6.3 -3.9 5.7 -0.4 13.9 MW-51-79 4/26/2021 1.31E+02 3.60E+02 0.7 1.0 -0.8 5.3 -2.4 6.2 -1.4 16.4 MW-51-79 8/31/2021 -1.50E+02 3.75E+02 0.7 1.3 0.7 5.7 2.5 7.2 2.2 15.7 MW-51-79 11/23/2021 7.96E+01 3.93E+02 0.5 1.7 -0.5 7.9 4.3 7.6 2.2 21.2 MW-52-122 5/13/2021 -1.02E+02 3.42E+02 -0.2 1.5 0.5 10.0 -6.7 6.5 -0.3 13.8 MW-52-162 5/13/2021 1.77E+02 3.72E+02 -1.0 1.3 0.8 5.9 0.8 5.7 3.1 13.9 MW-52-18 5/13/2021 2.12E+02 3.66E+02 -1.2 1.2 5.9 6.8 -0.2 6.0 4.6 15.6 MW-52-181 5/13/2021 3.25E+02 3.84E+02 -1.0 1.3 1.9 4.7 -0.9 5.1 -1.1 15.8 MW-52-48 5/13/2021 -5.43E+01 3.45E+02 -1.2 1.3 0.0 20.2 -3.2 5.6 -6.7 13.5 MW-52-64 5/13/2021 5.98E+01 3.51E+02 1.0 1.7 3.2 6.7 -0.4 7.6 4.3 15.9 MW-53-120 1/11/2021 1.01E+04 1.07E+03 19.6 3.9 -1.1 7.0 -2.4 6.1 4.0 18.8 -2.8 15.8 MW-53-120 2/24/2021 8.59E+03 1.04E+03 17.7 3.1 1.2 5.5 3.2 5.1 17.3 20.8 4.4 13.7 MW-53-120 3/17/2021 8.00E+03 8.31E+02 16.4 3.4 -2.4 5.6 1.6 5.0 15.9 15.5 -1.3 14.4 MW-53-120 4/27/2021 8.50E+03 8.67E+02 14.3 2.3 5.9 9.8 3.0 8.9 1.6 15.1 2.6 16.3

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 50 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-53-120 5/26/2021 7.81E+03 1.00E+03 20.5 4.1 6.2 11.1 0.9 5.9 4.2 17.0 -0.6 14.4 MW-53-120 6/15/2021 7.74E+03 9.81E+02 19.1 4.1 0.0 15.6 1.7 6.4 2.0 17.3 -2.4 15.3 MW-53-120 7/14/2021 7.86E+03 7.23E+02 23.0 3.7 1.2 7.2 3.4 11.0 -0.2 18.6 MW-53-120 8/10/2021 7.45E+03 7.08E+02 13.0 3.3 -0.6 4.8 -3.3 7.5 13.3 15.5 -1.5 12.9 MW-53-120 9/16/2021 6.46E+03 6.66E+02 16.7 2.4 0.0 7.0 -3.2 8.3 12.9 19.5 -6.2 16.8 MW-53-120 10/12/2021 6.44E+03 6.78E+02 26.6 3.6 0.1 6.9 1.7 6.8 6.3 17.0 -2.7 20.4 MW-53-120 11/11/2021 5.84E+03 9.21E+02 21.5 3.4 2.7 5.4 3.7 3.6 4.0 12.7 -2.8 14.1 MW-53-120 12/6/2021 6.24E+03 8.19E+02 26.1 1.9 2.6 6.0 0.7 5.1 7.8 19.7 5.9 13.5 MW-53-82 1/11/2021 3.23E+02 4.14E+02 0.9 1.8 -2.7 5.1 0.9 6.2 2.8 17.9 -4.3 13.6 MW-53-82 2/24/2021 1.98E+02 2.90E+02 -0.2 1.6 0.9 4.6 0.3 6.2 1.4 13.1 3.8 13.1 MW-53-82 3/17/2021 3.97E+02 4.08E+02 1.3 1.8 1.8 4.9 0.9 5.1 6.8 14.5 -1.5 10.1 MW-53-82 4/27/2021 9.56E+01 3.84E+02 0.7 1.5 2.8 6.1 2.2 6.5 3.0 14.9 -4.3 13.6 MW-53-82 8/10/2021 1.05E+02 4.14E+02 0.8 1.7 5.7 5.4 0.7 5.9 8.5 14.5 -2.3 15.8 MW-53-82 11/11/2021 2.14E+02 3.42E+02 1.5 1.6 2.3 11.0 -1.8 5.8 2.7 11.9 6.5 13.6 MW-54-123 2/9/2021 1.72E+03 4.32E+02 1.3 1.4 5.2 11.8 -0.4 6.4 5.6 16.7 -1.0 17.3 MW-54-123 5/12/2021 1.57E+03 4.74E+02 0.5 1.6 2.7 4.9 1.3 5.4 -1.9 17.0 -1.5 14.1 MW-54-123 8/13/2021 8.54E+02 4.35E+02 0.8 1.3 2.2 4.7 -0.5 4.9 -0.9 16.4 -7.0 14.7 MW-54-123 11/12/2021 1.44E+03 4.80E+02 1.3 1.4 1.3 5.2 5.8 5.5 -3.3 17.8 2.9 25.1 MW-54-144 2/9/2021 1.66E+03 4.35E+02 5.2 1.9 -2.9 6.3 2.8 7.3 10.2 16.7 -0.1 12.8 MW-54-144 5/12/2021 1.35E+03 4.56E+02 5.2 2.3 0.3 4.4 0.0 5.0 -4.4 16.3 1.8 10.2 MW-54-144 8/13/2021 1.01E+03 4.89E+02 5.8 1.8 -1.2 5.0 -4.7 8.6 5.8 16.2 -2.8 14.5 MW-54-144 11/12/2021 1.34E+03 4.77E+02 5.0 1.9 0.1 5.1 -1.0 5.0 1.7 16.9 2.4 12.4 MW-54-173 2/9/2021 3.22E+03 5.25E+02 4.0 1.8 -2.5 5.5 0.2 4.1 9.6 17.8 -3.3 12.8 MW-54-173 5/12/2021 2.83E+03 5.52E+02 1.8 1.9 1.0 5.1 -0.8 5.5 2.7 17.1 7.4 13.3 MW-54-173 8/13/2021 1.94E+03 5.22E+02 3.0 1.6 2.4 6.5 -0.1 6.1 5.9 16.7 9.3 15.6 MW-54-173 11/12/2021 2.40E+03 5.31E+02 4.6 1.9 1.9 6.3 -6.3 7.7 -4.0 15.9 6.7 17.2 MW-54-190 2/9/2021 1.63E+03 4.32E+02 8.1 2.1 -2.2 6.0 0.8 5.9 1.8 16.5 3.7 12.0 MW-54-190 5/12/2021 1.50E+03 4.62E+02 6.8 2.7 0.4 7.3 -4.7 7.5 -4.6 16.1 0.4 16.0 MW-54-190 8/13/2021 9.72E+02 4.62E+02 8.9 1.8 0.1 5.7 -0.9 5.0 -1.8 16.4 -6.8 18.2 MW-54-190 11/12/2021 1.57E+03 4.95E+02 9.2 2.4 0.8 6.2 -2.2 6.6 -4.0 16.4 -0.9 17.1 MW-54-37 2/9/2021 9.98E+02 3.84E+02 0.2 1.4 -1.2 5.8 1.0 4.9 14.4 17.6 -3.6 13.6 MW-54-37 5/12/2021 9.31E+02 4.20E+02 2.3 1.4 0.3 5.7 -0.1 6.7 0.7 23.9 6.8 13.3 MW-54-37 8/13/2021 5.92E+02 4.32E+02 2.3 1.8 2.4 11.4 -1.3 5.5 2.4 16.4 -0.7 14.7 MW-54-37 11/12/2021 7.54E+02 4.62E+02 2.7 1.6 4.9 8.7 -2.8 4.9 4.4 17.9 -0.4 18.7 MW-54-58 2/9/2021 1.30E+03 4.02E+02 1.1 1.0 0.1 10.5 0.6 5.0 4.1 16.5 -1.8 12.9 MW-54-58 5/12/2021 1.26E+03 4.53E+02 0.5 1.6 0.4 6.1 0.1 5.0 2.0 17.6 -2.5 12.1 MW-54-58 8/13/2021 8.12E+02 5.01E+02 1.4 0.9 0.1 6.6 0.5 6.7 0.6 16.3 1.9 17.4 MW-54-58 11/12/2021 1.22E+03 4.68E+02 1.7 1.8 3.3 8.5 -0.7 6.1 0.6 17.3 -2.0 12.5 MW-55-24 2/23/2021 5.05E+02 3.99E+02 4.2 2.2 -2.1 6.2 3.4 6.2 0.9 14.5 1.2 11.9 MW-55-24 4/28/2021 7.70E+02 4.41E+02 3.5 1.4 -2.5 5.6 0.4 6.5 -12.4 14.7 -4.3 15.8 MW-55-24 8/9/2021 7.60E+02 4.26E+02 6.1 2.5 1.5 6.5 3.7 5.2 1.4 17.4 -7.4 15.9 MW-55-24 11/9/2021 1.13E+03 4.68E+02 6.5 2.7 2 6 0.4 4.7 6 18 6.0 14.9 MW-55-35 2/23/2021 6.71E+02 4.11E+02 7.1 2.1 -1.5 5.6 3.2 5.9 11.2 15.5 -2.2 13.7 MW-55-35 4/28/2021 9.71E+02 4.53E+02 5.9 2.2 -2.9 5.1 -1.4 5.6 -0.4 15.8 0.5 13.9 MW-55-35 8/9/2021 1.04E+03 4.35E+02 8.0 2.7 0.7 5.0 0.1 5.9 6.5 18.4 0.4 13.8 MW-55-35 11/9/2021 1.08E+03 4.53E+02 10.0 2.8 1 5 -0.3 5.2 14 18 0.5 12.9 MW-55-54 2/23/2021 3.95E+03 6.33E+02 4.2 1.4 0.3 5.3 3.7 6.3 10.6 14.4 -3.9 15.8 MW-55-54 4/28/2021 3.11E+03 6.06E+02 5.4 2.0 1.2 10.4 -2.7 6.9 -3.7 19.8 5.5 12.3 MW-55-54 8/9/2021 3.11E+03 5.31E+02 5.1 2.3 0.5 4.4 1.1 5.3 5.7 23.3 -0.2 12.9 MW-55-54 11/9/2021 2.94E+03 5.55E+02 7.2 2.6 -7 9 -2.2 6.0 3 18 -0.1 13.7 MW-56-53 5/17/2021 6.28E+02 4.68E+02 0.2 1.5 1.1 6.0 -1.2 5.0 0.2 13.8 MW-56-53 11/11/2021 1.26E+02 3.24E+02 0.4 1.5 4 15 -6.6 6.8 2.3 15.9 MW-56-83 5/17/2021 3.51E+03 7.35E+02 -0.6 1.4 -1.9 6.5 -1.4 7.1 -5.1 15.9 MW-56-83 11/11/2021 1.90E+03 5.73E+02 0.8 1.6 -4 7 -1.5 5.2 6.4 13.0 MW-57-11 5/6/2021 1.85E+03 4.92E+02 7.0 1.6 5.5 6.3 2.1 4.9 -4.8 14.6 -5.0 14.1 MW-57-20 5/6/2021 8.60E+02 4.23E+02 0.4 0.8 0.0 7.0 2.0 4.8 -4.0 14.2 1.1 12.4 MW-57-45 5/6/2021 1.14E+03 4.47E+02 0.2 0.6 2.3 5.6 3.1 6.0 -5.2 22.3 -0.9 14.0 MW-58-26 5/6/2021 2.72E+02 3.72E+02 0.1 0.7 0.4 5.5 -2.1 6.8 1.1 13.3

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 51 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-58-26 11/18/2021 1.28E+02 4.11E+02 1.2 1.4 2.0 6.1 -0.3 6.6 2.0 15.6 MW-58-65 5/6/2021 1.95E+02 3.66E+02 -1.0 1.3 0.2 6.4 2.2 7.7 6.8 13.7 MW-58-65 11/18/2021 3.18E+02 3.75E+02 1.8 1.9 0.8 8.3 -1.2 8.0 -6.1 21.4 MW-60-135 5/4/2021 1.05E+03 4.26E+02 -0.7 1.1 2.7 4.8 -0.5 6.0 4.8 13.3 MW-60-154 5/4/2021 1.08E+03 4.35E+02 0.0 1.6 -0.8 4.0 3.2 4.9 -1.8 11.9 MW-60-176 5/4/2021 1.00E+03 4.29E+02 0.4 1.6 1.9 5.6 -0.2 5.2 5.9 14.2 MW-60-35 5/4/2021 -1.60E+01 3.51E+02 0.2 1.6 -0.1 4.0 2.1 4.2 -7.5 11.3 MW-60-53 5/4/2021 2.38E+02 3.81E+02 -0.8 1.4 -2.0 6.2 -0.5 5.6 -5.3 14.7 MW-60-72 5/4/2021 5.31E+00 3.54E+02 0.5 1.7 1.3 5.6 2.1 6.9 1.9 14.7 MW-62-138 2/11/2021 7.99E+02 4.59E+02 1.6 1.8 4.4 13.8 -0.7 8.2 1.0 17.7 MW-62-138 5/27/2021 5.91E+02 4.05E+02 1.4 1.8 2.3 8.6 -0.1 8.8 -7.3 19.3 MW-62-138 8/26/2021 5.14E+02 3.24E+02 1.1 1.3 2.2 8.0 -1.7 8.9 -12.7 21.9 MW-62-138 11/8/2021 4.46E+02 4.23E+02 0.3 1.7 0.8 4.9 0.7 6.0 -1.8 12.8 MW-62-18 2/11/2021 2.40E+02 3.15E+02 1.0 1.3 -1.9 7.4 0.8 6.1 6.0 15.1 MW-62-18 5/27/2021 6.65E+02 4.08E+02 0.4 1.6 0.4 6.3 2.9 5.6 -7.5 14.6 MW-62-18 8/26/2021 1.55E+02 3.15E+02 -0.4 1.2 -1.5 6.8 -1.8 6.2 0.2 15.0 MW-62-18 11/8/2021 1.91E+02 4.08E+02 0.1 1.5 1.3 5.8 -1.3 8.9 1.5 16.9 MW-62-182 2/11/2021 1.20E+03 4.08E+02 1.3 1.8 0.9 6.3 7.2 7.6 -0.4 15.4 MW-62-182 5/27/2021 9.84E+02 4.38E+02 1.1 1.7 2.5 5.7 -0.6 5.0 5.2 16.7 MW-62-182 8/26/2021 8.87E+02 3.36E+02 -0.5 1.0 3.2 5.3 -3.7 7.3 1.7 11.9 MW-62-182 11/8/2021 9.62E+02 4.38E+02 -0.1 1.4 -1.0 6.1 0.2 5.1 -0.6 15.9 MW-62-37 2/11/2021 1.04E+03 3.90E+02 0.3 1.1 1.5 5.0 -1.5 6.2 5.6 12.7 MW-62-37 5/27/2021 1.65E+02 3.66E+02 1.3 1.6 1.3 7.9 -1.8 7.5 1.5 16.8 MW-62-37 8/26/2021 5.69E+02 3.21E+02 1.0 1.2 0.5 8.7 -1.9 8.9 3.9 21.8 MW-62-37 11/8/2021 8.99E+02 4.47E+02 -1.1 1.3 4.3 7.7 2.8 8.2 -1.1 20.7 MW-62-53 2/11/2021 9.92E+02 3.84E+02 0.3 1.1 -1.0 4.3 1.7 5.1 -0.6 10.7 MW-62-53 5/27/2021 7.51E+02 4.20E+02 1.0 1.8 5.5 8.0 -0.5 6.3 -3.0 14.3 MW-62-53 8/26/2021 8.94E+02 3.42E+02 0.8 1.8 -2.5 5.2 2.7 5.3 4.3 12.5 MW-62-53 11/8/2021 8.77E+02 4.62E+02 2.1 1.9 1.0 4.7 3.9 7.8 -3.5 13.3 MW-62-71 2/11/2021 1.05E+03 3.87E+02 0.8 1.3 0.9 4.5 -1.9 6.2 1.1 13.6 MW-62-71 5/27/2021 6.10E+02 4.02E+02 1.1 1.8 3.1 7.1 2.3 6.6 -1.7 15.2 MW-62-71 8/26/2021 8.01E+02 3.39E+02 1.2 1.2 -2.0 7.1 9.5 8.9 5.2 16.0 MW-62-71 11/8/2021 9.77E+02 4.44E+02 -0.7 1.5 0.7 4.7 1.2 4.4 -4.9 11.8 MW-62-92 2/11/2021 1.11E+03 3.93E+02 1.1 1.2 0.3 7.2 -4.8 8.7 -7.4 17.6 MW-62-92 5/27/2021 9.22E+02 4.32E+02 0.8 1.7 -0.8 5.8 0.0 7.1 6.3 14.2 MW-62-92 8/26/2021 1.10E+03 3.51E+02 0.4 1.2 0.9 10.1 2.5 9.3 -4.9 21.2 MW-62-92 11/8/2021 1.16E+03 4.56E+02 0.6 1.7 0.7 6.4 0.8 6.1 -1.7 16.1 MW-63-112 5/11/2021 2.42E+02 3.66E+02 -0.6 1.5 1.8 5.5 0.5 4.5 -2.4 13.1 MW-63-112 11/16/2021 7.10E+02 4.41E+02 1.2 1.4 -0.7 5.7 5.4 5.6 -6.7 17.3 MW-63-121 5/11/2021 4.28E+02 3.90E+02 0.1 0.8 -4.3 7.3 -1.4 4.9 0.8 14.2 MW-63-121 11/16/2021 6.52E+02 4.32E+02 0.7 0.8 -2.7 7.5 4.9 6.1 9.0 16.2 MW-63-163 5/11/2021 5.92E+02 4.05E+02 0.5 1.1 1.3 4.8 -3.8 7.1 0.7 11.6 MW-63-163 11/16/2021 6.64E+02 4.56E+02 0.0 1.5 0.0 5.9 1.1 5.5 5.5 15.5 MW-63-174 5/11/2021 4.96E+02 3.99E+02 0.1 1.1 -1.9 4.8 -1.3 6.0 1.1 14.5 MW-63-174 11/16/2021 7.19E+02 4.02E+02 1.4 1.6 1.6 5.9 3.6 8.4 -5.5 17.8 MW-63-18 5/11/2021 4.94E+01 3.45E+02 -0.2 1.5 -2.0 5.9 2.2 6.5 0.7 14.3 MW-63-18 11/16/2021 2.10E+02 4.14E+02 0.4 1.2 0.0 14.8 1.1 6.8 6.1 23.0 MW-63-34 5/11/2021 1.88E+02 3.54E+02 -1.0 1.3 -1.8 6.5 -0.4 4.4 -3.0 15.8 MW-63-34 11/16/2021 3.55E+02 4.23E+02 1.3 1.4 -0.7 5.7 2.2 5.6 5.0 16.5 MW-63-50 5/11/2021 3.01E+02 3.72E+02 0.2 1.4 -2.4 4.8 2.6 6.3 1.5 13.9 MW-63-50 11/16/2021 3.17E+02 4.17E+02 0.4 1.6 -3.1 7.4 1.6 5.9 0.4 13.4 MW-63-93 5/11/2021 3.34E+02 3.57E+02 0.4 1.5 -1.1 5.8 2.0 6.6 -0.6 12.0 MW-63-93 11/16/2021 4.89E+02 4.32E+02 1.3 1.3 2.8 4.9 -0.5 5.1 3.6 14.5 MW-66-21 2/15/2021 3.69E+02 3.45E+02 0.9 0.9 -1.2 4.7 1.6 4.4 -12.8 20.4 3.8 11.0 MW-66-21 5/7/2021 3.08E+02 4.08E+02 0.8 1.2 0.5 9.4 -5.7 7.6 -4.3 15.4 -2.5 12.1 MW-66-21 8/23/2021 1.08E+02 3.93E+02 0.7 1.6 0.0 5.6 1.9 6.9 6.3 16.3 -0.1 15.2 MW-66-21 11/15/2021 3.16E+02 3.51E+02 1.4 1.7 0.5 6.8 -0.4 5.9 4.9 11.3 7.0 21.1 MW-66-36 1/13/2021 4.20E+03

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 52 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-66-36 2/15/2021 4.02E+03 7.26E+02 6.6 2.5 1.8 11.9 1.2 4.9 -5.1 21.8 0.0 12.2 MW-66-36 5/7/2021 3.49E+03 6.12E+02 3.8 1.4 -2.3 8.0 3.9 9.3 -1.4 15.3 1.4 15.0 MW-66-36 8/23/2021 3.76E+03 6.33E+02 6.4 2.5 -1.1 5.3 0.8 5.0 -1.2 16.5 4.6 13.1 MW-66-36 11/15/2021 3.73E+03 7.44E+02 5.0 2.1 1.5 6.2 -1.1 8.6 -1.0 11.5 0.7 17.3 MW-67-105 1/13/2021 1.50E+03 MW-67-105 2/10/2021 1.71E+03 4.38E+02 0.4 1.2 -0.8 5.2 1.7 5.6 -15.4 18.8 -3.7 12.3 MW-67-105 5/19/2021 1.50E+03 4.77E+02 1.7 1.8 -0.5 5.7 3.2 5.0 -13.7 22.7 8.0 14.2 MW-67-105 8/25/2021 1.66E+03 3.69E+02 0.2 1.1 0.0 7.8 1.4 8.0 -3.9 16.1 8.4 18.8 MW-67-105 11/15/2021 1.25E+03 4.98E+02 0.9 1.7 -1.3 7.0 1.9 5.3 1.4 11.6 -2.7 13.8 MW-67-173 2/10/2021 6.62E+02 3.54E+02 -0.1 1.0 -0.9 4.8 -1.7 4.5 19.3 22.4 7.9 17.3 MW-67-173 5/19/2021 5.91E+02 4.05E+02 <MDC 2.0 -3.4 7.5 4.7 5.6 -0.9 17.8 1.7 14.1 MW-67-173 8/25/2021 6.63E+02 3.78E+02 1.0 1.6 3.0 6.8 1.4 6.3 12.9 18.5 -9.0 16.7 MW-67-173 11/15/2021 9.07E+02 4.38E+02 1.1 1.8 1.0 12.9 0.6 9.6 -1.8 14.7 6.3 20.0 MW-67-219 2/10/2021 1.14E+03 3.93E+02 -0.1 1.0 -0.3 5.6 1.8 4.7 2.7 22.5 -5.6 12.7 MW-67-219 5/19/2021 1.08E+03 4.47E+02 1.0 1.1 3.3 7.0 -7.7 8.9 -12.1 17.6 4.7 18.7 MW-67-219 8/25/2021 1.46E+03 4.35E+02 2.5 2.4 -0.3 6.8 1.1 6.2 6.6 16.4 -5.7 18.4 MW-67-219 11/15/2021 1.22E+03 4.56E+02 0.7 1.3 0.9 5.5 -0.9 5.3 3.7 11.9 -5.7 16.4 MW-67-276 1/13/2021 9.00E+02 MW-67-276 2/10/2021 8.35E+02 3.69E+02 0.6 1.3 0.4 5.5 -0.5 8.1 -12.9 22.5 -5.4 16.6 MW-67-276 5/19/2021 6.85E+02 3.93E+02 -0.6 1.6 0.2 4.4 2.2 5.4 -2.1 17.7 2.9 11.6 MW-67-276 8/25/2021 5.35E+02 3.87E+02 0.1 1.5 -1.5 5.1 0.0 4.3 7.3 16.8 3.0 13.9 MW-67-276 11/15/2021 8.53E+02 4.38E+02 1.3 1.6 -1.3 7.5 0.1 4.9 6.4 12.0 3.3 14.1 MW-67-340 2/10/2021 2.31E+02 3.09E+02 -0.2 1.1 1.9 5.3 -4.7 8.7 -12.4 18.0 3.5 17.2 MW-67-340 5/19/2021 3.82E+02 3.87E+02 1.2 1.6 3.4 8.1 0.0 7.4 -4.4 15.7 -5.1 18.5 MW-67-340 8/25/2021 1.90E+02 3.66E+02 1.1 1.4 5.2 8.0 -5.5 9.9 2.5 16.2 1.6 17.7 MW-67-340 11/15/2021 2.85E+02 4.20E+02 1.3 1.8 -3.2 12.3 1.5 9.5 3.0 11.3 13.4 21.5 MW-67-39 1/13/2021 3.90E+03 MW-67-39 2/10/2021 4.09E+03 5.82E+02 5.5 2.0 0.0 4.2 -1.6 5.5 0.0 16.7 4.9 11.7 MW-67-39 5/19/2021 3.52E+03 6.03E+02 7.1 2.7 0.9 4.6 -1.8 5.1 -3.2 17.0 2.9 12.3 MW-67-39 8/25/2021 3.31E+03 4.20E+02 6.6 3.2 -1.4 6.9 -4.5 9.8 4.8 16.1 2.2 17.2 MW-67-39 11/15/2021 3.20E+03 7.02E+02 5.3 1.9 2.6 6.7 1.5 6.9 2.3 11.2 -1.2 16.9 MW-68-103 1/14/2021 8.94E+01 3.93E+02 0.8 1.3 0.0 4.5 -1.5 3.4 1.1 11.0 MW-68-103 2/22/2021 3.33E+02 3.39E+02 0.3 1.5 8.0 6.9 2.0 6.9 -1.6 16.4 MW-68-103 3/15/2021 7.76E+02 3.60E+02 0.5 1.7 -1.3 6.1 -1.0 8.3 9.5 18.3 MW-68-103 4/12/2021 8.24E+01 3.57E+02 MW-68-103 5/10/2021 2.57E+02 3.66E+02 1.1 1.7 -1.3 5.3 0.8 3.9 4.7 11.6 MW-68-103 6/14/2021 4.57E+02 4.53E+02 <MDC 1.9 0.5 7.7 -1.1 5.9 -4.3 16.7 -3.6 16.3 MW-68-103 8/24/2021 2.01E+02 4.02E+02 -0.4 1.5 -1.7 4.3 0.2 4.7 5.4 11.7 MW-68-103 11/10/2021 4.49E+02 4.35E+02 0.9 1.7 -4.5 5.8 1.8 6.4 -2.0 16.5 MW-68-132 1/14/2021 2.28E+02 4.05E+02 1.0 1.4 3.0 5.0 4.1 5.9 2.9 14.9 MW-68-132 2/22/2021 1.89E+02 3.06E+02 0.1 1.6 0.5 6.2 1.5 5.9 8.5 15.0 MW-68-132 3/15/2021 9.53E+01 3.18E+02 -0.4 1.6 -1.2 5.4 1.4 5.3 0.6 12.9 MW-68-132 4/12/2021 -3.58E+01 3.36E+02 MW-68-132 5/10/2021 1.06E+02 3.51E+02 -0.4 1.6 1.1 5.0 -2.4 5.3 9.1 14.0 MW-68-132 6/14/2021 3.60E+02 4.44E+02 1.5 1.7 1.8 6.2 -1.3 6.8 1.7 22.5 10.3 16.1 MW-68-132 8/24/2021 1.41E+02 3.81E+02 -0.1 1.6 -1.4 5.8 0.4 7.8 6.2 14.9 MW-68-132 11/10/2021 2.62E+01 4.05E+02 0.6 1.6 1.0 7.4 -3.6 5.7 8.6 17.6 MW-68-19 1/14/2021 5.73E+02 3.36E+02 1.8 1.9 2.3 6.8 2.5 8.5 -3.7 16.9 MW-68-19 2/22/2021 1.04E+03 3.63E+02 -0.6 1.3 -0.2 4.7 -3.2 6.5 -2.8 14.5 MW-68-19 3/15/2021 9.53E+02 3.36E+02 0.8 1.7 1.7 5.8 0.9 5.3 0.3 15.3 MW-68-19 4/12/2021 7.58E+02 4.20E+02 MW-68-19 5/10/2021 6.85E+02 3.90E+02 1.3 1.8 0.4 5.3 2.2 4.8 -0.9 12.2 MW-68-19 6/14/2021 1.25E+03 5.64E+02 <MDC 2.1 -3.5 7.7 -2.7 7.8 -4.0 17.6 -5.2 13.5 MW-68-19 7/13/2021 1.15E+03 4.56E+02 MW-68-19 8/24/2021 1.17E+03 4.62E+02 1.0 1.8 0.8 4.7 -0.2 5.4 -1.5 14.0 MW-68-19 9/17/2021 1.24E+03 4.71E+02 1.0 1.3 -1.2 3.6 0.6 4.8 -7.0 12.5 MW-68-19 10/11/2021 1.21E+03 4.77E+02 1.8 1.9 0.7 5.2 2.7 5.0 3.6 15.8 MW-68-19 11/10/2021 9.67E+02 4.50E+02 0.3 1.5 -0.9 6.2 1.5 5.8 5.2 16.7

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 53 of 55 Annual Radioactive Effluent Release Report 2021 Laboratory Analytical Results Well ID Sample Date H-3 H-3 Sr-90 Sr-90 Cs-137 Cs-137 Co-60 Co-60 Ni-63 Ni-63 Sb-125 Sb-125 Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma Result 3 Sigma (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.) (pCi/L) (Std. Dev.)

MW-68-29 1/14/2021 5.19E+02 4.44E+02 -1.0 1.4 2.2 5.7 0.4 6.3 2.7 13.2 MW-68-29 2/22/2021 7.14E+02 3.54E+02 0.2 1.6 -2.8 5.9 -0.1 6.8 0.1 15.4 MW-68-29 3/15/2021 8.74E+02 4.14E+02 1.0 1.7 -0.3 4.6 -0.6 4.8 0.9 11.0 MW-68-29 4/12/2021 8.20E+02 4.17E+02 MW-68-29 5/10/2021 7.46E+02 3.96E+02 1.1 1.8 0.9 4.5 -0.9 5.1 -0.1 14.0 MW-68-29 6/14/2021 8.53E+02 4.98E+02 <MDC 2.0 -0.1 6.4 0.0 7.6 -1.9 17.1 -7.0 16.9 MW-68-29 7/13/2021 8.86E+02 4.35E+02 MW-68-29 8/24/2021 1.16E+03 4.26E+02 1.4 1.3 0.2 4.9 -2.8 6.5 6.3 14.0 MW-68-29 9/17/2021 6.67E+02 4.35E+02 -0.4 1.3 -1.8 6.4 0.4 6.5 -0.5 16.1 MW-68-29 10/11/2021 7.22E+02 4.59E+02 1.5 1.5 -1.7 7.2 3.2 8.2 -0.7 16.9 MW-68-29 11/10/2021 9.81E+02 4.50E+02 1.7 1.8 -1.1 6.5 7.3 9.6 -7.1 15.4 MW-68-57 1/14/2021 7.33E+02 3.54E+02 0.6 1.3 2.5 4.8 -3.0 3.9 9.2 13.2 MW-68-57 2/22/2021 4.08E+02 3.48E+02 1.4 1.8 1.5 6.2 -1.4 6.8 1.5 14.0 MW-68-57 3/15/2021 5.81E+02 3.66E+02 0.7 1.7 -1.3 5.6 1.1 5.6 8.2 13.9 MW-68-57 4/12/2021 3.64E+02 3.81E+02 MW-68-57 5/10/2021 3.42E+02 3.72E+02 1.0 1.7 0.4 5.0 0.9 4.4 -1.3 11.5 MW-68-57 6/14/2021 5.16E+02 4.59E+02 1.1 1.5 -0.9 4.4 -0.9 5.0 -5.4 16.5 3.6 11.7 MW-68-57 7/13/2021 5.13E+02 4.05E+02 MW-68-57 8/24/2021 4.86E+02 4.29E+02 1.3 1.6 -3.5 5.1 -0.4 5.9 -1.4 10.4 MW-68-57 9/17/2021 6.20E+02 4.41E+02 -0.8 1.1 4.7 9.8 -0.4 4.3 -1.6 15.5 MW-68-57 10/11/2021 4.96E+02 4.44E+02 0.3 0.9 1.4 7.1 0.0 6.4 -2.1 16.4 MW-68-57 11/10/2021 6.79E+02 4.35E+02 0.7 1.6 2.1 5.9 -0.4 6.2 1.8 15.9 U1-CSS 1/21/2021 1.12E+03 4.95E+02 1.1 1.8 -1.5 5.5 0.3 5.8 -9.2 19.2 -3.4 16.4 U1-CSS 2/9/2021 1.18E+03 3.93E+02 1.0 1.3 3.0 4.7 2.0 5.3 9.9 16.8 -1.8 15.1 U1-CSS 3/12/2021 1.56E+03 4.92E+02 -0.3 1.7 0.7 7.0 -2.4 7.4 8.4 14.7 -4.7 16.4 U1-CSS 4/29/2021 1.07E+03 4.62E+02 0.1 0.8 4.5 7.1 2.4 4.7 -2.7 15.4 5.6 11.5 U1-CSS 11/12/2021 3.42E+02 4.23E+02 0.8 1.2 -1.6 5.6 0.7 8.6 -4.9 15.8 -2.2 14.2 U1-NCD 2/4/2021 2.60E+03 5.43E+02 33.5 6.2 22100.0 228.6 1.6 5.6 632.0 40.5 2.8 87.9 U1-NCD 4/26/2021 1.91E+03 5.01E+02 34.6 4.4 25700.0 236.7 1.2 5.6 560.0 34.8 -15.7 90.0 U1-NCD 7/19/2021 1.58E+03 5.46E+02 23.0 2.1 15700.0 196.5 -1.1 5.9 349.0 37.8 -23.0 85.5 U1-NCD 10/12/2021 1.33E+03 5.22E+02 22.4 1.8 17600.0 211.5 3.4 6.2 533.0 46.5 32.4 91.5 U1-SFDS 2/3/2021 2.72E+02 3.24E+02 1.0 1.7 0.0 8.6 1.1 5.2 1.6 17.0 -4.4 12.9 U1-SFDS 4/28/2021 1.38E+02 3.81E+02 3.7 2.2 1.6 4.7 3.7 5.4 -0.3 14.3 2.0 10.3 U1-SFDS 7/21/2021 4.47E+02 4.11E+02 3.4 2.1 5.2 11.4 0.2 3.9 10.6 18.2 -0.4 13.6 U1-SFDS 10/13/2021 4.24E+02 4.41E+02 5.5 1.6 0.0 11.0 2.5 5.9 -0.1 17.3 -6.2 16.9 U3-4D 2/25/2021 1.39E+02 4.38E+02 0.2 1.3 0.0 11.0 -2.0 4.7 0.1 12.8 U3-4D 5/18/2021 3.12E+02 3.78E+02 1.3 1.4 3.9 7.8 7.6 6.7 7.2 15.2 U3-4D 8/26/2021 2.38E+02 3.81E+02 1.1 1.2 -0.6 6.4 0.1 6.6 3.6 14.7 U3-4D 11/19/2021 1.85E+02 3.21E+02 0.5 1.1 1.7 6.0 3.2 6.1 -4.9 17.8 U3-4S 5/18/2021 4.50E+02 4.53E+02 0.6 1.5 4.8 10.4 3.4 6.2 6.2 15.5 U3-4S 11/19/2021 8.29E+01 3.12E+02 1.2 1.3 -0.9 6.0 -0.6 5.0 -3.2 12.5 U3-T1 2/25/2021 5.99E+02 4.05E+02 1.5 1.8 1.0 5.7 0.6 5.3 8.5 13.3 U3-T1 5/18/2021 3.94E+02 4.50E+02 1.7 1.7 5.3 9.2 -3.4 9.7 7.1 19.0 U3-T1 8/24/2021 4.68E+01 3.57E+02 0.5 1.7 0.5 9.5 0.4 5.2 -2.6 14.3 U3-T1 11/19/2021 4.76E+02 4.26E+02 0.0 1.5 -2.3 6.4 -1.1 6.8 -17.8 18.4 U3-T2 2/25/2021 8.22E+02 4.17E+02 -1.1 1.4 0.0 4.6 6.7 5.4 4.0 12.5 U3-T2 5/18/2021 4.18E+02 3.93E+02 1.7 1.8 1.4 6.2 -0.2 6.7 7.9 15.6 U3-T2 8/24/2021 1.54E+03 4.68E+02 1.1 1.7 -0.3 6.3 3.1 7.4 0.3 14.8 U3-T2 11/19/2021 1.52E+03 4.95E+02 1.4 1.8 -1.0 4.1 1.6 2.8 0.3 11.8

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 54 of 55 Annual Radioactive Effluent Release Report Attachment 4 - ODCM Revision 6 Summary of Changes ODCM Part I 1 Added note (j) to Table D 3.2.1-1 Section 4, Charcoal Sample. Note (j) Charcoal sample not required for Unit 1 and Unit 2. ODCM page D 3.2.1 - 2 and page D 3.2.1 - 3.

2 Removed instrument 2.a, Condenser Air Evacuation System, Unit 2 Noble Gas Activity, (R-45) from Table D 3.3.2-1. ODCM page D 3.3.2 - 5.

3 Removed instrument 3.a, Vapor Containment Atmosphere, Unit 2 Noble Gas Activity Monitor, providing ALARM and automatic termination of release (R-42) from Table D 3.3.2-1. ODCM page D 3.3.2 - 5.

4 Removed equipment 4.b, Unit 2 Main Plant Vent, Iodine Sampler from Table D 3.3.2-1. ODCM page D 3.3.2 - 6.

5 Removed equipment 6.b, Unit 1 Stack Vent, Iodine Sampler from Table D 3.3.2-1. ODCM page D 3.3.2 - 7.

6 Delete 3.d, Ground Water, from Table D 3.5.1-1. ODCM page D 3.5.1-7 and corrected Notation (f) on Table D 3.5.1-7, ODCM page 3.5.1-8.

ODCM Part II 7 Deleted R-42 (Containment Gas Monitor), R-45 (Condenser Air Ejector Monitor) and R-49 (SG Blowdown Monitor) on Table 1-1 (Unit 2 Effluent Radiation Monitor System Data), ODCM page 4 of 144.

8 Changed recirculated for at least two tank volumes to recirculated for at least three tank volumes in ODCM Part II section 2.1.4. ODCM page 6 of 144.

9 ODCM section 2.1.6, page 6 of 144.

a) Change minimum dilution flow from 100,000 gpm to 80,000 gpm.

b) Change routine use of unit-specific dilution flow for each permitted release to limiting to only one unit discharging at a time.

c) Delete second paragraph on section 2.1.6.

10 Delete second sentence on section 2.1.9, Actual monthly average flow rates and total gallons of dilution are determined by Programs and Components and delivered to Chemistry on a monthly basis. ODCM page 6 of 144.

11 Delete time-average in section 2.2.1. ODCM page 9 of 144.

12 Change section 2.2.2 wording and formula. ODCM page 9 of 144.

a) two tank volumes to three tank volumes b) )recirculation time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to recirculation time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> c) Formula - 2 Tank Volumes to 3 Tank Volumes, 3.9 Hours to 5.9 Hours and 4 Hours to 6 Hours.

13 Section 2.4.2 last paragraph, clarify wording for Fk to use a conservative dilution flow for permitting releases and update the permit with best estimate of total dilution after the release.

ODCM page 14 of 144.

14 Added Reference 50 to section 3.5.5 (next to last paragraph). ODCM page 49 of 144.

Indian Point Units 1, 2 & 3 YEAR: 2021 Page 55 of 55 Annual Radioactive Effluent Release Report 15 Appendix B (Page 1 of 2), move U1 Found Drain from 80-10 to between WDST and Sphere Foundation Drain Sump. ODCM page 108 of 144.

16 Appendix C (Page 1 of 2) delete Containment Pressure Relief, Containment Purge, Condenser Air Ejector, and both R-49 and R-51 Blowdown. ODCM page 110 of 144.

17 Delete the Steam Partition Factor f for the Unit 2 flash tank vent, ODCM Appendix D page 112 of 144. Also deleted the remaining information on the steam generator blowdown purification system listed in APPENDIX D.

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 ENCLOSURE 2 TO HDI-IPEC-22-052 Offsite Dose Calculation Manual (ODCM)

(242 pages not including this cover sheet)

PAGE Table of Contents ii List of Tables and Figures vi Introduction viii PART I - RADIOLOGICAL EFFLUENT CONTROLS D 1.0 USE AND APPLICATION D 1.1 Definitions D 1.1-1 D 1.2 Logical Connectors D 1.2-1 D 1.3 Completion Times D 1.2-1 D 1.4 Frequency D 1.2-1 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 IPEC ODCM ii Revision 6

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 (PCP) D 5.5-1 D 5.6 Radiological Ground Water Monitoring Program (RGWMP) D 5.6-1 IPEC ODCM iii Revision 6

BASES PAGE B D 3.0 APPLICABILITY B D 3.0 ODCM Limiting Condition for Operation (DLCO) B D 3.0-1 B D 3.0 ODCM Surveillance Requirement (DSR) B D 3.0-1 B D 3.1 RADIOACTIVE LIQUID EFFLUENTS B D 3.1.1 Liquid Effluents Concentration B D 3.1.1-1 B D 3.1.2 Liquid Effluents Dose B D 3.1.2-1 B D 3.1.3 Liquid Radwaste Treatment System B D 3.1.3-1 B D 3.1.4 Liquid Holdup Tanks B D 3.1.4-1 B D 3.2 RADIOACTIVE GASEOUS EFFLUENTS B D 3.2.1 Gaseous Effluents Dose Rate B D 3.2.1-1 B D 3.2.2 Gaseous Effluents Dose - Noble Gas B D 3.2.2-1 B D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate B D 3.2.3-1 B D 3.2.4 Gaseous Radwaste Treatment System B D 3.2.4-1 B D 3.2.5 Ventilation Exhaust Treatment System B D 3.2.5-1 B D 3.2.6 Gas Storage Tanks B D 3.2.6-1 B D 3.3 INSTRUMENTATION B D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation B D 3.3.1-1 B D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation B D 3.3.2-1 B D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE B D 3.4.1 Radioactive Effluents Total Dose B D 3.4.1-1 B D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B D 3.5.1 Radiological Environmental Monitoring Program B D 3.5.1-1 B D 3.5.2 Land Use Census B D 3.5.2-1 B D 3.5.3 Interlaboratory Comparison Program B D 3.5.3-1 B D 3.6 SOLID RADIOACTIVE WASTE B D 3.6.1 Solid Radwaste Treatment System B D 3.6.1-1 IPEC ODCM iv Revision 6

PART II CALCULATIONAL METHODOLOGIES PAGE 1.0 RADIATION MONITORS AND SETPOINTS 1.1 Effluent Monitoring System Description 1 1.2 Setpoints for Airborne Effluent Monitors 1 1.3 Setpoints for Liquid Effluent Monitors 2 2.0 LIQUID EFFLUENT METHODOLOGY 2.1 Liquid Effluent Releases - General Information 6 2.2 Liquid Effluent Concentrations 9 2.3 Liquid Effluent Dose Calculation Requirements 12 2.4 Dose Methodology (Computer Calculation) 13 2.5 Backup Simplified Dose Methodology 16 2.6 Site-Specific Bio-Accumulation and Dose Factors 16 3.0 GASEOUS EFFLUENT METHODOLOGY 3.1 Gaseous Effluent Releases - General Information 25 3.2 Gaseous Effluent Dose Calculation Requirements 30 3.3 Dose Methodology (Computer Calculation) 31 3.4 Backup Simplified Dose Methodology 43 3.5 Calculation of Meteorological Dispersion Factors 46 3.6 Justification and Use of Finite Cloud Assumptions for Assessing SB Dose 51 4.0 TOTAL DOSE DETERMINATIONS 4.1 10CFR190 Dose Evaluation 100 4.2 Doses from Liquid Releases 100 4.3 Doses from Atmospheric Releases 100 4.4 Doses to MEMBERS OF THE PUBLIC Visiting the Site 101 5.0 LOWER LIMIT OF DETECTION 102 REFERENCES 104 APPENDICES Appendix A: Summary of Radiological Effluent Controls 107 Appendix B: Liquid Effluent Simplified Flow Diagram 108 Appendix C: Gaseous Effluent Simplified Flow Diagram 110 Appendix D: Steam Partition Factor Calculation ( ) 112 Appendix E: Allowed Diluted Concentration (ADC) 113 Appendix F: Conversion Factors for Liquid Effluent Monitors 114 Appendix G: Environmental Sampling Points 115 Appendix H: Interlaboratory Comparison Program 122 Appendix I: Calculation of Allowable Release Rates for Indian Point Units 2 and 3 123 Appendix J: Groundwater & Stormwater Flow and Offsite Dose Calculation Details 130 Appendix K: Quantification and Reporting of C-14 in IPEC Releases 139 IPEC ODCM v Revision 6

LIST OF TABLES AND FIGURES PAGE PART I - RADIOLOGICAL EFFLUENT CONTROLS Tables:

D 3.1.1-1 Radioactive Liquid Waste Sampling and Analysis D 3.1.1-2 D 3.2.1-1 Radioactive Gaseous Waste Sampling and Analysis D 3.2.1-2 D 3.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1-6 D 3.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2-5 D 3.5.1-1 Radiological Environmental Monitoring Program D 3.5.1-6 D 3.5.1-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples D 3.5.1-9 D 3.5.1-3 Detection Capabilities for Environmental Sample Analysis D 3.5.1-10 Figures:

4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE D 4.1-2 GASEOUS AND LIQUID EFFLUENTS 4.1-2 MAP DEFINING RELEASE POINTS D 4.1-3 IPEC ODCM vi Revision 6

LIST OF TABLES AND FIGURES PAGE PART II - CALCULATIONAL METHODOLOGIES 1-1 Unit 2 Effluent Radiation Monitor System Data 4 1-2 Unit 3 Effluent Radiation Monitor System Data 5 2-1 Site Related Adult Ingestion Dose Commitment Factors 18 2-2 Site Related Teen Ingestion Dose Commitment Factors 20 2-3 Site Related Child Ingestion Dose Commitment Factors 22 2-4 Bio-Accumulation Factors for Liquid Effluent Isotopes 24 3-1a Adult Inhalation Dose Factors 52 3-1b Teen Inhalation Dose Factors 54 3-1c Child Inhalation Dose Factors 56 3-1d Infant Inhalation Dose Factors 58 3-2 TB/Skin GP Dose Factors, w/ Half Life & Stable Element Transfer Data 60 3-3a Adult Ingestion Dose Factors 62 3-3b Teen Ingestion Dose Factors 64 3-3c Child Ingestion Dose Factors 66 3-3d Infant Ingestion Dose Factors 68 3-4 Total Body Dose Factors, Ki, from Noble Gas (Gamma) 70 3-5 Skin Dose Factors, Li, from Noble Gas (Beta) 71 3-6 Air Dose Factors, Mi, from Noble Gas (Gamma) 72 3-7 Air Dose Factors, Ni, from Noble Gas (Beta) 73 3-8 NG Dose Factors for Instantaneous and Time Average Mixtures at the SB 74 3-9 Locations of Site Boundary and Nearest Residence 75 3-10a Adult Inhalation Ri(I) 76 3-10b Teen Inhalation Ri(I) 78 3-10c Child Inhalation Ri(I) 80 3-10d Infant Inhalation Ri(I) 82 3-11a Adult Ingestion (Leafy Vegetable) Ri(V) 84 3-11b Teen Ingestion (Leafy Vegetable) Ri(V) 86 3-11c Child Ingestion (Leafy Vegetable) Ri(V) 88 3-12a Adult Grass-Cow-Milk Pathway Ri(C) 90 3-12b Teen Grass-Cow-Milk Pathway Ri(C) 92 3-12c Child Grass-Cow-Milk Pathway Ri(C) 94 3-12d Infant Grass-Cow-Milk Pathway Ri(C) 96 3-13 Total Body and Skin Ground Plane Dose Factors Ri(G) and Ri(S) 98 IPEC ODCM vii Revision 6

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5. for both IPEC units 2 and 3. Previous revisions of each units ODCM have been combined to form a station ODCM. The IPEC ODCM consists of two parts:

1) Part I, Radiological Effluent Controls, (RECS) - previously, often referred to as the Radiological Effluent Technical Specifications, or RETS (Section 3.9 of original Unit 2 Technical Specifications, and Appendix B or original Unit 3 Technical Specifications).
2) Part II, Calculational Methodologies (previously often referred to as simply the ODCM)

Part I, Radiological Effluent Controls, includes the Radiological Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5. It also includes descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by each units Technical Specifications.

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. At IPEC, this method includes the use of ten-year averaged 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.

The sources for criteria found in the ODCM and the Radiological Effluent Control Specifications include the following:

Liquid Effluent Release Rate: Diluted concentrations in the discharge canal are limited to ten times the EFFLUENT CONCENTRATIONS identified in 10CFR20 Appendix B.

Airborne Effluent Release Rate: Release rates are limited to corresponding dose rate limits from NUREG 0133 and 0472.

Integrated Radiological Effluent Dose: The design objectives of 10CFR50 Appendix I.

The ODCM and associated tracking software implements the methodology of

1) 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
2) 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. In some cases, site-specific data or reasonable simplifying assumptions are used and justified to permit formulation of more workable methodologies for implementing RECS dose calculation requirements.

IPEC ODCM viii Revision 6

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

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 A GASEOUS RADWASTE TREATMENT SYSTEM is any system RADWASTE designed and installed to reduce radioactive gaseous effluents by TREATMENT collecting primary coolant system offgases from the primary system and SYSTEM providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF MEMBER(S) OF THE PUBLIC includes all persons who are not THE PUBLIC 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.

MAXIMUM MPCW is that concentration of a radionuclide equal to ten times the PERMISSIBLE EFFLUENT CONCENTRATIONS specified in 10CFR20, Appendix B, CONCENTRATION Table 2, Column 2.

WATER (MPCW)

OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL shall contain the CALCULATION current methodology and parameters used in the calculation of offsite MANUAL 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.

PRIMARY TO A PRIMARY TO SECONDARY LEAK is defined by a quantifiable leak SECONDARY rate equal to or greater than 0.5 gpd, AND LEAK a) The presence of fission or activation products in the secondary fluid, verified as Steam Generator U-tube leaks (and not from other known contamination, such as IVSWS leaks), OR b) Tritium activity in the secondary fluid indicating an increase above historical baseline (normal diffusion) of 5.00E-6 uCi/ml or greater.

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

IPEC ODCM D 1.1 - 1 Revision 6

Definitions D 1.1 D 1.1 Definitions PURGE - PURGING 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.

SITE BOUNDARY The SITE BOUNDARY is that line beyond which the land is neither owned, leased, nor otherwise controlled by the licensee(s).

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

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

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

VENTILATION A VENTILATION EXHAUST TREATMENT SYSTEM is any system EXHAUST designed and installed to reduce gaseous radioiodine or radioactive TREATMENT material in particulate form in effluents by passing ventilation or vent SYSTEM 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 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.

IPEC ODCM D 1.1 - 2 Revision 6

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.

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.

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 IPEC ODCM D 1.2-1 Revision 6

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

IPEC ODCM D 3.0-1 Revision 6

APPLICABILITY D 3.0 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.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

IPEC ODCM D 3.0-2 Revision 6

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. 2E-4 uCi/ml total activity concentration for dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTIONS 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.

IPEC ODCM Page 3.1.1 - 1 Revision 6

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

Radioactive Liquid Waste Sampling and Analysis LOWER LIMIT LIQUID MINIMUM OF DETECTION RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS (LLD) in uCi/ml, TYPE TYPE FREQUENCY FREQUENCY (a),(g),(c)

1. Batch Waste Principal Release Tanks Gamma Emitters 5E-7 (b) Grab Sample Each Batch (h) Each Batch (h)

Mo-99, Ce-144 5E-6 eg, Waste Tanks, I-131 1E-6 SG Dissolved and One batch per Draindowns, Grab Sample 31 days Entrained Gases 1E-5 31 days (h) etc (gamma emitters)

H-3 1E-5 Composite (d) Each batch (h) 31 days Gross Alpha 1E-7 Sr-89, Sr-90 5E-8 Composite (d) Each batch (h) 92 days Fe-55 1E-6

2. Continuous Releases (e) eg, SG Principal Gamma Composite (d) Composite 7 days Blowdown, Emitters (c) 5E-7 U1 NCD, Mo-99, Ce-144 5E-6 U1 SFDS, I-131 1E-6 Foundation Drain Line (k) Dissolved and Grab Sample 31 days 31 days Entrained Gases 1E-5 etc (gamma emitters)

H-3 1E-5 31 days Gross Alpha 1E-7 Composite (d) Composite Sr-89, Sr-90 5E-8 92 days Fe-55 1E-6

3. Service Water Gamma and Beta Per liquid batch Grab Sample 31 days 31 days (in Radiologically emitters (j) releases, above.

Controlled Areas)

4. Turbine Hall Gamma and Beta Per liquid batch Drains, SG Composite (d) Composite 7 days emitters (j) releases, above.

Feedwater (i)

IPEC ODCM Page 3.1.1 - 2 Revision 6

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 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 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 2.1.4 to assure representative sampling.

(c) The principal gamma emitters for which the LLD (of 5E-7 uCi/ml) applies include the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, and Ce-141. Mo-99 and Ce-144 shall also be measured, but with an LLD of 5E-6 uCi/ml, per Reference 49. 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 circumstances, the LLD may be increased in inverse proportion to the magnitude of the gamma yield (i.e., 5 x 10-7/I where I is the photon abundance expressed as a decimal fraction).

(h) Complete prior to each release.

(i) Steam Generator Feedwater and Turbine Hall Drains are adequately monitored from Steam Generator Blowdown Composites. Increased monitoring need only be performed when a Primary to Secondary leak exists, as defined in RECS Section D.1.1.

(j) Beta emitters need only be analyzed if gamma emitters have been positively identified.

(k) Foundation Drain Line samples are grab samples (at least once per month).

IPEC ODCM Page 3.1.1 - 3 Revision 6

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.

IPEC ODCM D 3.1.2 - 1 Revision 6

Liquid Effluents Dose D 3.1.2 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.

IPEC ODCM D 3.1.2 - 2 Revision 6

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.

IPEC ODCM D 3.1.2 - 3 Revision 6

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.

IPEC ODCM D 3.1.3 - 1 Revision 6

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 U2 & U3 PWSTs A.2 Initiate measures to reduce 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> U2 & U3 RWSTs content to within the limits.

U1 Waste Dist Storage Tanks AND U3 Monitor Tanks A.3 Describe the events leading to Prior to submittal of U3 CPF High/Low TDS Tanks the condition in the next Radioactive Outdoor Temporary Tanks Radioactive Effluent Release Effluent Release Report. Report SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.4.1 Determine that the quantity of radioactivity in 31 days, during periods outdoor liquid unprotected tanks (listed above) where radioactive liquid does not exceed the limit. is being added to the tanks, in accordance with the methodology and parameters of the ODCM IPEC ODCM D 3.1.4 - 1 Revision 6

Gaseous Effluents Dose Rate D 3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 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 I-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 I-131, H-3 and all In accordance with Table D 3.2.1-1 radionuclides in particulate form with half-lives 8 days in gaseous effluents shall be determined to be within the limits of DLCO 3.2.1.b.

IPEC ODCM D 3.2.1 - 1 Revision 6

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 LOWER GASEOUS SAMPLE SAMPLE ANALYSIS SAMPLE LIMIT OF RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION TYPE (LLD) (a)

Principal Noble 1E-4

1. Waste Gas Grab Each Tank (h) Each Tank (h) Gas (NG)

Storage Tank Sample Ci/cc Gamma Emitters (b)

Principal NG Grab 1E-4 Purge Each Purge (h) Each Purge (h) Gamma Sample

2. Emitters (b) Ci/cc Vapor Containment Principal NG Press Grab 1E-4 31 days (i) 31 days (i) Gamma Relief Sample Ci/cc Emitters (b)

Principal NG 1E-4

3. Condenser Air Grab 31 days 31 days Gamma Ejector Sample Ci/cc Emitters (b)

Principal NG 1E-4

4. Continuous Grab 31 days (c) 31 days (c) Gamma Ventilation: Sample Ci/cc Emitters (b)
a. Main Plant H-3 1E-6 Continuous 31 days (e) H-3 Vent (unit 2) Specific Ci/cc (e)
b. Stack Vent Charcoal 1E-12 (unit 1) Continuous (f) 7 days (c), (g) I-131 4/21 Sample (j) Ci/cc
c. Main Plant Principal Vent (unit 3) Gamma Particulate 1E-11 Continuous (f) 7 days (c), (g) Emitters (b)
d. Radioactive Sample Ci/cc (I-131, Machine Shop Others)

Vent (unit 3)

Composite 1E-11

e. Admin Bldg Particulate Continuous (f) 31 days Gross Alpha Sample Ci/cc Vent (unit 3)

Composite 1E-11 Particulate Continuous (f) 92 days Sr-89 / Sr-90 Sample Ci/cc Noble Gases 1E-6 Noble Gas Continuous (f) Continuous (f) Gross Beta Monitor Ci/cc (d) or Gamma IPEC ODCM D 3.2.1 - 2 Revision 6

Gaseous Effluents Dose Rate D 3.2.1 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 Specifications, 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 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.

(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-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. Other identifiable gamma peaks (I-131 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 I-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 for Noble Gases within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, AND
2) Sample the main Plant Vent for Iodine and Particulate once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days with analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 alternative to continuous sampling, provided the periodicity of these grab samples is increased from monthly to once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded, or at least once per 7 days when spent fuel is in the Spent Fuel Pool. The LLD value of 1E-6 uCi/cc applies to the liquid distillate from the selected sample (or approximately 1E-10 uCi/cc in the exhaust vent air stream).

(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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Additionally, IF routine Iodine sampling indicates I-131 in any of the listed continuous streams, THEN collect a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample from the applicable vent (within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the Pressure Relief. Should BOTH the containment noble gas and particulate monitors be inoperable, two independent samples of the VC are required prior to a Pressure Relief.

4/21 (j) Charcoal sample not required for Unit 1 and Unit 2.

IPEC ODCM D 3.2.1 - 3 Revision 6

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 BOUNDARY due to noble Special Report that gases released in gaseous (1) Identifies the cause(s) effluents exceeds limits. 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.

IPEC ODCM D 3.2.2 - 1 Revision 6

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 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.

IPEC ODCM D 3.2.2 - 2 Revision 6

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.

IPEC ODCM D 3.2.2 - 3 Revision 6

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 I-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 I-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 SITE BOUNDARY 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 3.2.3.

IPEC ODCM D 3.2.3 - 1 Revision 6

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.

IPEC ODCM D 3.2.3 - 2 Revision 6

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.3.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year for I-131, tritium, and radioactive material in particulate form with half-lives 8 days.

IPEC ODCM D 3.2.3 - 3 Revision 6

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 the following:

AND (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.

IPEC ODCM D 3.2.4 - 1 Revision 6

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.5.1 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.

IPEC ODCM D 3.2.5 - 1 Revision 6

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 the following unit-specific curie levels of noble gas (considered as Xe-133):

Unit 2: 29,761 Curies Unit 3: 50,000 Curies 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.6.1 The quantity of radioactive material contained in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during each gas storage tank shall be determined to be addition of within the limits above, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radioactive when radioactive materials are being added to the material to the tank in accordance with the methodology and tank parameters in the ODCM.

IPEC ODCM D 3.2.6 - 1 Revision 6

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 unit-specific 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 for the applicable unit.

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.

IPEC ODCM D 3.3.1 - 1 Revision 6

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 10-7 Ci/ml.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter IPEC ODCM D 3.3.1 - 2 Revision 6

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 10-7 Ci/ml, when specific activity is Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

> 0.01 Ci/gm DOSE thereafter EQUIVALENT I-131.

OR E.2 Collect and analyze grab 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> samples for radioactivity at a limit of detection of at AND least 5 x 10-7 Ci/ml, when specific activity is Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.01 Ci/gm DOSE thereafter EQUIVALENT I-131.

F. As required by Required F.1 ---------------NOTE------------

Action B.1 and Pump performance curves 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> referenced in generated in place may be Table D 3.3.1-1. used to estimate flow. AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Estimate the flow rate during thereafter actual releases.

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.

IPEC ODCM D 3.3.1 - 3 Revision 6

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. Required Action and I.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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DSR 3.3.1.2 Perform CHANNEL CHECK by verifying indication of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 IPEC ODCM D 3.3.1 - 4 Revision 6

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 OPERATIONAL TEST 24 months DSR 3.3.1.9 Perform CHANNEL CALIBRATION 24 months IPEC ODCM D 3.3.1 - 5 Revision 6

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 1 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS SURVEILLANCE INSTRUMENT FROM SPECIFIED PER REQUIREMENTS REQUIRED CONDITIONS INSTRUMENT ACTION B.1

1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release DSR 3.3.1.1 (a) 1 C DSR 3.3.1.3
a. Unit 2 Liquid Radioactive DSR 3.3.1.6 (e)

Waste Effluent Line (R-54) DSR 3.3.1.9 (d)

DSR 3.3.1.1

b. Unit 2 Steam Generator Effluent (a) (i) 1 E DSR 3.3.1.4 Blowdown Line (R-49) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

c. Unit 3 Liquid Radioactive (a) 1 C DSR 3.3.1.3 Waste Effluent Line (R-18) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1 (h)

d. Unit 3 Condensate Polisher Facility (a) 1 C DSR 3.3.1.4 (h)

(CPF) Waste Line (R-61) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

e. Unit 3 Steam Generator Effluent (a) (i) 1 E DSR 3.3.1.4 Blowdown Line (R-19) 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. Unit 1 or 2 Service Water or River Water Effluent Lines DSR 3.3.1.1

- VC FCU (R-46 or R-53) (a) 1 (g) D DSR 3.3.1.4 DSR 3.3.1.7 (e)

- 21 CCW HX (R-39) DSR 3.3.1.9 (d)

- 22 CCW HX (R-40)

b. Unit 1 Sphere Foundation DSR 3.3.1.1 Drain Sump Effluent Line (R-62) (a) 1 D DSR 3.3.1.4 DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

c. Unit 3 Service Water Effluent Lines DSR 3.3.1.1

- SW for VC FCU return (a) 1 (g) D DSR 3.3.1.4 (R-16A or R-16B) DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

- SW for CCW Heat DSR 3.3.1.1 Exchanger (R-23) (a) 1 D DSR 3.3.1.4 DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

IPEC ODCM D 3.3.1 - 6 Revision 6

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 2 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SURVEILLANCE INSTRUMENT SPECIFIED PER FROM REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

3. Flow Rate Measurement Devices DSR 3.3.1.2
a. Unit 2 Liquid Radwaste (a) 1 F DSR 3.3.1.5 Effluent Line DSR 3.3.1.9
b. Unit 2 Steam Generator DSR 3.3.1.2 Blowdown Effluent Line (a) (i) 1 F DSR 3.3.1.5 DSR 3.3.1.9
c. Unit 1 North Curtain Drain Effluent Line (f) (a) 1 F DSR 3.3.1.2 DSR 3.3.1.9
d. Unit 1 Sphere Foundation (a) 1 F DSR 3.3.1.2 Drain Sump (f) DSR 3.3.1.9
e. Unit 3 Liquid Radwaste DSR 3.3.1.2 Effluent Line (a) 1 F DSR 3.3.1.5 DSR 3.3.1.9
f. Unit 3 Cond Polisher (CPF)

Effluent Line DSR 3.3.1.2 (a) 1 F DSR 3.3.1.5 DSR 3.3.1.9 (h)

g. Unit 3 Steam Generator DSR 3.3.1.2 Blowdown Effluent Line (a) (i) 1 F DSR 3.3.1.5 DSR 3.3.1.9
4. Tank Level Indicating Devices (c)
a. Unit 1 Waste Distillate (a) 1 G DSR 3.3.1.1 (b)

Storage Tank #13 DSR 3.3.1.5 DSR 3.3.1.9

b. Unit 1 Waste Distillate DSR 3.3.1.1 (b)

Storage Tank #14 (a) 1 G DSR 3.3.1.5 DSR 3.3.1.9

c. Unit 2 Primary Water DSR 3.3.1.1 (b)

Storage Tank (a) 1 G DSR 3.3.1.5 DSR 3.3.1.9

d. Unit 2 Refueling Water (a) 1 Storage Tank G DSR 3.3.1.1 (b)

(j)

e. Unit 3 Refueling Water (a) 1 Storage Tank G DSR 3.3.1.1 (b)

(j)

IPEC ODCM D 3.3.1 - 7 Revision 6

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 3 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SURVEILLANCE INSTRUMENT SPECIFIED PER FROM REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

4. Tank Level Indicating Devices (c) (continued)

DSR 3.3.1.1 (b)

f. Unit 3 Primary Water Storage (a) 1 G DSR 3.3.1.8 Tank DSR 3.3.1.9 DSR 3.3.1.1 (b)
g. Unit 3 Monitor Tank #31 (a) 1 G DSR 3.3.1.8 DSR 3.3.1.9 DSR 3.3.1.1 (b)
h. Unit 3 Monitor Tank #32 (a) 1 G DSR 3.3.1.8 DSR 3.3.1.9
i. Unit 3 CPF High Total DSR 3.3.1.1 (b)

Dissolved Solids Tank (a) 1 G DSR 3.3.1.8 DSR 3.3.1.9 (h)

j. Unit 3 CPF Low Total DSR 3.3.1.1 (b)

Dissolved Solids Tank (a) 1 G DSR 3.3.1.8 DSR 3.3.1.9 (h)

NOTES (a) Applicability is defined as anytime releases are being performed via this pathway. During periods of release, 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, as specified in RECS Section D 3.1.4.

(d) Radioactive calibration standards used for CHANNEL CALIBRATIONS shall be analyzed with instrumentation which is calibrated NIST traceable standards. Standards from suppliers who participate in approved measurement assurance activities with NIST are acceptable.

(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, nor the performance of any 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.

(g) One instrument per operating Service Water system is required. For example, unit-specific VC FCU monitors are redundant and compensatory actions are only required when BOTH monitors are OOS for any one unit. However, for Unit 2s CCW HXs (R-39 and R-40), the appropriate SW monitor is required to be in service anytime the effected loop is in service.

(h) Channel and Source Checks for effluent instrumentation/indication in Unit 3s Condensate Polisher Facility (CPF) are required only during or after a primary to secondary leak, as defined in RECS Section 1. Surveillances on these items are performed to be prepared for this type of leak. The level instrument calibration is also required by the SPDES permit.

(i) Applicable for Continuous Steam Generator Blowdown to the environment only. These requirements are not applicable for Batch Steam Generator Draindowns.

(j) Surveillance requirements for the RWST level instruments (CHECKS and CALIBRATIONS) are prescribed in Technical Specifications (Sections 3.3.3 and 3.5.4 for Unit 2 and Section 3.5.4 for Unit 3). However, the requirement for a daily channel check (when making additions to the tank, per earlier footnote b) is maintained in the ODCM per the original licensing bases (NUREG 0472) and the 10 curie rule.

IPEC ODCM D 3.3.1 - 8 Revision 6

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.

IPEC ODCM D 3.3.2 - 1 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required Action B.1 and referenced C.1 Take grab samples. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in Table D 3.3.2-1.

AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2 Analyze samples for gross 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of activity. sampling completion D. As required by Required D.1 Estimate the flow rate for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action B.1 and referenced the inoperable channel(s).

in Table D 3.3.2-1. AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter E. As required by Required E.1 Continuously collect 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action B.1 and referenced samples using auxiliary in Table D 3.3.2-1. sampling equipment as required in Table D 3.2.1-1.

F. As required by Required F.1 Determine the radioactive 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action B.1 and referenced content of the receiving in Table D 3.3.2-1. gas decay tank is in AND compliance with DLCO 3.2.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter IPEC ODCM D 3.3.2 - 2 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in gas decay tank in Table D 3.3.2-1, for gas accordance with release decay tank releases. 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 gas decay tank discharge line valving. release 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 I.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.

K. As required by Required K.1 Take Noble Gas grab Prior to venting Action B.1 and referenced samples and analyze for Vapor Containment in Table D 3.3.2-1 (in gross activity. (VC)

MODES 1-4 only).

K.2 Immediately suspend PURGING the VC.

IPEC ODCM D 3.3.2 - 3 Revision 6

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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. 92 days The test shall include 1) low sample flow, 2) no counts per minute failure, 3) a demonstration of 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.

This test does NOT include testing of troubleshooting and equipment diagnostic capabilities provided with the monitor installation.

DSR 3.3.2.6 Perform CHANNEL OPERATIONAL TEST. 92 days The test shall include 1) low sample flow (except for Condenser Air Ejector monitors), 2) no counts per minute failure, 3) a demonstration that control room alarm annunciation (or control panel indications or display) occurs if the instrument indicates measured levels above the alarm setpoint, or the instrument controls are not set in operate mode.

This test does NOT include testing of troubleshooting and equipment diagnostic capabilities provided with the monitor installation.

DSR 3.3.2.7 Perform CHANNEL CALIBRATION. 24 months IPEC ODCM D 3.3.2 - 4 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 1 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1, 2, or 3) CONDITIONS INSTRUMENT ACTION B.1

1. Waste Gas Holdup System
a. Unit 2 Noble Gas DSR 3.3.2.1 Monitor, providing (b) 1 F DSR 3.3.2.4 Alarm, (R-50) DSR 3.3.2.6 DSR 3.3.2.7 (c)
b. Unit 3 Noble Gas DSR 3.3.2.1 (b) 1 F DSR 3.3.2.4 Monitor, providing DSR 3.3.2.6 Alarm, (R-20) DSR 3.3.2.7 (c)
2. Condenser Air Evacuation System
a. Unit 3 Noble Gas 4/21 (a) DSR 3.3.2.1 Activity, (R-15) 1 DSR 3.3.2.4 C

DSR 3.3.2.6 (d)

DSR 3.3.2.7 (c)

3. Vapor Containment Atmosphere 4/21
a. Unit 3 Noble Gas Activity Monitor, providing (a) 1 K DSR 3.3.2.4 ALARM and automatic (g) termination of release (R-12)

IPEC ODCM D 3.3.2 - 5 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 2 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1, 2, or 3) CONDITIONS INSTRUMENT ACTION B.1

4. Unit 2 Main Plant Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor (R-44) (a) & (b) 1 C&G DSR 3.3.2.4 DSR 3.3.2.5 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

4/21

b. Particulate Sampler (a) 1 E DSR 3.3.2.2
c. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (SV2-DPT, SV2-1-DPT, SV2-DPI) DSR 3.3.2.7
d. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chem Totalizer) DSR 3.3.2.7
5. Unit 3 Main Plant Vent Radiation Monitor:
a. Noble Gas Monitor(s) DSR 3.3.2.1 (a) & (b) 1 C&G DSR 3.3.2.4 (R-14 or R-27)

DSR 3.3.2.5 Other Monitoring Equipment: DSR 3.3.2.7 (c)

b. Iodine Sampler (a) 1 E DSR 3.3.2.2
c. Particulate Sampler (a) 1 E DSR 3.3.2.2
d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (from R-27s Kurz probes and DSR 3.3.2.7 RM80 processing computer)

(a) 1 D DSR 3.3.2.1

e. Sample Flow-Rate Monitor DSR 3.3.2.7 (Chem Totalizer)

IPEC ODCM D 3.3.2 - 6 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 3 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1, 2, or 3) CONDITIONS INSTRUMENT ACTION B.1

6. Unit 1 Stack Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor (R-60) (a) 1 C DSR 3.3.2.4 DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Particulate Sampler (a) 1 E DSR 3.3.2.2 4/21
c. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (SV1-DPT, SV1-FR) DSR 3.3.2.7
d. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chem Totalizer) DSR 3.3.2.7
7. Unit 3 Radioactive Machine Shop (RAMS) Vent Radiation Monitor: DSR 3.3.2.1 DSR 3.3.2.4
a. Noble Gas Monitor (R-59) (a) 1 C DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2
c. Particulate Sampler (a) 1 E DSR 3.3.2.2
d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (from R-59s RM80 processor) DSR 3.3.2.7
e. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chem Totalizer) DSR 3.3.2.7 IPEC ODCM D 3.3.2 - 7 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 4 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1, 2, or 3) CONDITIONS INSTRUMENT ACTION B.1

8. Unit 3 Admin Bldg Vent (f)

Radiation Monitor: DSR 3.3.2.1 DSR 3.3.2.4

a. Noble Gas Monitor (R-46) (a) 1 C DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2
c. Particulate Sampler (a) 1 E DSR 3.3.2.2
d. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chem Totalizer) DSR 3.3.2.7 NOTES (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 Institute of Standards and Technology (NIST) or an aliquot of calibration gas shall be analyzed with instrumentation which is calibrated with NIST traceable standards. Standards from suppliers who participate in measurement assurance activities with NIST are acceptable.

(d) The CHANNEL OPERATIONAL TEST for the Condenser Air Ejector monitors does NOT require a loss of sample flow test.

(e) The main Plant Vents for Units 2 and 3 monitors the Fuel Storage Building vents, in addition to ventilation from the Primary Auxiliary Buildings.

(f) The Unit 3 Admin Bldg Controlled Area ventilation system does NOT have an installed process flow meter.

Default fan flow is used in lieu of a measurement , per ODCM Part II, Section 3.1.11.

(g) Most surveillance requirements for Vapor Containment monitors are located in Technical Specifications, Section 3.3.6. Source checks, however, are NOT required per Technical Specifications. Since these checks are valuable to ensure accurate quantification of VC Pressure Reliefs (as described below), a monthly source check requirement is listed here, in addition to the requirements of Technical Specifications.

Grab samples of the Vapor Containment atmosphere are routinely collected at least monthly and compared to the gas monitor for use in quantification of VC Pressure Reliefs (by scaling the monitor reading for each release to the reading obtained at time of grab sample). If the noble gas monitor is inoperable, a grab samples shall be taken and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to performing a Pressure Relief. During containment building ventilation in Modes 5 or 6, continuous monitoring and automatic termination of release is not required. In this condition, one continuous monitor at the Plant Vent is sufficient.

IPEC ODCM D 3.3.2 - 8 Revision 6

Radioactive Effluents Total Dose D 3.4.1 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.

IPEC ODCM D 3.4.1 - 1 Revision 6

Radioactive Effluents Total Dose D 3.4.1 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.

IPEC ODCM D 3.4.1 - 2 Revision 6

Radiological Environmental Monitoring Program D 3.5.1 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Monitoring Program DLCO 3.5.1 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. If the radioactivity medium at a specified (radionuclides) detected is location exceeds the not the result of plant reporting levels of effluents no report is Table D 3.5.1-2 when necessary, however this averaged over any condition needs to be calendar quarter. described in the Annual Radiological OR Environmental Operating Report.

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.

IPEC ODCM D 3.5.1 - 1 Revision 6

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME More than one of the Prepare and submit to the 30 days radionuclides in Table NRC, pursuant to D 5.3, a D 3.5.1-2 are detected in Special Report that the environmental (1) Identifies the cause(s) for sampling medium and exceeding the limit(s) and Concentration 1 + (2) Defines the corrective reporting level 1 actions to be taken to reduce radioactive concentration 2 + 1.0. effluents so that the reporting level 2 potential annual dose to a MEMBER OF THE OR PUBLIC is less than the calendar year limits of Radionuclides other than Specifications D 3.1.2, those in Table D 3.5.1-2 D 3.2.2, or D 3.2.3.

are detected in an (3) For radionuclides other environmental sampling than those listed in Table medium at a specified D 3.5.1-2, this report location which are the shall indicate the result of plant effluents and methodology and the potential annual dose parameters used to to a MEMBER OF THE estimate the potential PUBLIC from all annual dose to a radionuclides is the MEMBER OF THE calendar year limits of PUBLIC.

Specifications D 3.1.2, D 3.2.2 or D 3.2.3.

IPEC ODCM D 3.5.1 - 2 Revision 6

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or fresh leafy 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 IPEC ODCM D 3.5.1 - 3 Revision 6

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.

IPEC ODCM D 3.5.1 - 4 Revision 6

Radiological Environmental Monitoring Program D 3.5.1 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.

IPEC ODCM D 3.5.1 - 5 Revision 6

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

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

1. Direct 41 routine (1) An inner ring of stations Quarterly Gamma dose quarterly Radiation monitoring (DR1-DR16), one in each stations (b) meteorological sector in (DR1-DR41) 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-DR41), 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 4 locations (1) 3 locations (A1-A3) close Continuous sampler Radioiodine canister:

Radioiodine (A1-A5) to the site boundary in operation with sample Analyze weekly for I-131 and different sectors, of the collection weekly or Particulates highest calculated annual more frequently if Particulate sampler:

average ground level D/Q (1) Analyze for gross beta required by dust loading radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (2) 1 location (A4) from the vicinity of an established following filter change year-round community (d).

having the highest (2) Perform gamma isotopic calculated annual average analysis on each sample ground level D/Q (e) in which gross beta activity is 10 times the (3) 1 control location (A5) previous yearly mean of located approximately 15- control samples.

30 km distant, and in the least prevalent wind (3) Gamma isotopic analysis direction (c) of composite sample (e)

(by location) once per 3 months.

3. Waterborne
a. Surface (f) 1 location Upstream (Wa1) Composite sample (1) Gamma isotopic (used as a Control Station) over a one month analysis of each sample period (g) (e) once per month.

1 location Downstream (Wa2)

(2) Composite and analyze for H-3 quarterly.

b. Drinking 1 location Nearest water supply (Wb1) Grab sample: Monthly (1) Gamma isotopic analyses(e) of each sample monthly.

(2) Composite and analyze for H-3 quarterly.

IPEC ODCM D 3.5.1 - 6 Revision 6

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

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

3. Waterborne (continued)
c. Soil 2 locations Downstream area (Wc1) Twice per year at least 90 Gamma isotopic (e) from with existing or potential days apart and Sr-90 analyses Shoreline recreational value of each sample, semi-annually.

Upstream area (Wc2) control sample 4/21

4. Ingestion
a. Milk (i) 3 milk animal In 3 locations (Ia1-Ia3) locations within 5 km having the highest dose potential (human consumption).

If there are none within 5 Twice per month when km, then a milk location in animals are on pasture; each of 3 areas (Ia1-Ia3) 5 monthly at other times Gamma isotopic (e) and to 8 km distance, if I-131 analyses of each available, where doses are sample.

calculated to be > 1mrem per year (h) 1 control milk At a control location (Ia4), Concurrently, with animal location approximately 15 to 30 km indicator locations distant, and in the least prevalent wind direction

b. Fish and 2 indicator location One In the vicinity of the Samples from edible Invertebrates plant discharge area (Ib1) portions of each and one further commercially or downstream (Ib3) recreationally important Gamma isotopic, species when in season, Ni-63, and Sr-90 analyses of each or sample (e) 1 control location If available, 1 location of same species as the above Semiannually if species is location, in an area not not seasonal influenced by plant discharge (Ib2)

IPEC ODCM D 3.5.1 - 7 Revision 6

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

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

4. Ingestion Vegetation grown (continued) 2 locations nearest to each of 2 different offsite locations
c. Food of highest predicted Monthly Products annual average ground when available level D/Q if milk Gamma isotopic (e) sampling is not Samples of 3 different and I-131 analyses performed (Ic1-Ic2) kinds of broad leaf vegetation (edible or Vegetation grown 15 to inedible) (j) 30 km distant in the 1control location least prevalent wind direction if milk sampling is not performed (Ic3)

(a) The code letters in parenthesis, e.g., DR1, A1 refer to sample locations specified in ODCM, Part II. 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 due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to D5.1.

(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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 sample(s) should be from a Control Location. The downstream sample shall be taken from the 4/21 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.

(i) The requirement to obtain and analyze samples from milch animals within 8 km of the site is intended to ensure monitoring of the cow-milk and vegetation pathways. Thus, only milch animals whose milk is used for human consumption are considered in the pathway and sample evaluation.

(j) Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different sectors with the highest predicted D/Q in lieu of the garden census. Similar species should be obtained at both locations.

IPEC ODCM D 3.5.1 - 8 Revision 6

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

Reporting Levels for Radioactivity in Environmental Samples **

AIRBORNE FOOD RADIONUCLIDE WATER FISH MILK PARTICULATE OR PRODUCTS ANALYSIS (pCi/L) (pCi/kg, wet) (pCi/L)

GASES (pCi/m3) (pCi/kg, wet)

H-3 20,000

  • Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Ni-63 *** 300 1,000 Zn-65 300 20,000 Sr-90 *** 8* 40 Zr-95 400 Nb-95 400 I-131 2* 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300
  • Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCi/L (This is a 40 CFR 141 value)

Sr-90 12 pCi/L I-131 20 pCi/L

    • These reporting levels are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.
      • Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment, per References 45 and 46.

IPEC ODCM D 3.5.1 - 9 Revision 6

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

Detection Capabilities for Environmental Sample Analysis (a) (e)

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

FOOD SOIL or AIRBORNE FISH RADIONUCLIDE WATER MILK PRODUCTS SEDIMENT PARTICULATE OR (pCi/kg, ANALYSIS (pCi/L) (pCi/L) (pCi/kg, wet) (pCi/kg, dry)

GASES (pCi/m3) wet)

Gross Beta 4 0.01 H-3 2,000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Ni-63 (f) 30 100 Zn-65 30 260 Sr-90 (f) 1 5 50 Zr-95 30 Nb-95 15 I-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 60 60 La-140 15 15 IPEC ODCM D 3.5.1 - 10 Revision 6

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

Detection Capabilities for Environmental Sample Analysis Table Notation (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.

For the purposes of defining the LLD as described above the t is the elapsed time between environmental collection, or end of the sample collection period, and time of counting (sec).

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. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to RECS D 5.1.

(d) These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 for H-3 and 15 for I-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

(f) Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment, per References 45 and 46.

IPEC ODCM D 3.5.1 - 11 Revision 6

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, the nearest residence, and the nearest garden of 50 m2 (500 ft2) producing broad leaf vegetation. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of a garden census, per Table D 3.5.1-1, part 4.c.

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 greater than the values currently being calculated in DSR 3.2.3.1.

IPEC ODCM D 3.5.2 - 1 Revision 6

Land Use Census D 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Land use census identifies B.1 Add the new location(s) to 30 days location(s) that yields a the Radiological calculated dose, or dose Environmental Monitoring commitment (via the same Program.

exposure pathway) a factor greater than 2 than at a AND location from which samples are currently B.2 Delete the sampling After October 31 of being obtained in location(s), excluding the the year in which the accordance with control station location, land use census was Table D 3.5.1-1. having the lowest conducted 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 In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a change Report 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.

IPEC ODCM D 3.5.2 - 2 Revision 6

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 IPEC ODCM D 3.5.2 - 3 Revision 6

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 IPEC ODCM D 3.5.3 - 1 Revision 6

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.

IPEC ODCM D 3.6.1 - 1 Revision 6

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).

IPEC ODCM D 3.6.1 - 2 Revision 6

UNRESTRICTED AREA D 4.1 D 4.0 DESIGN FEATURES D 4.1 UNRESTRICTED AREA 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.

A map representing the UNRESTRICTED AREA is shown in Figure 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 4.1-2.

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 the FSARs.

IPEC ODCM D 4.1 - 1 Revision 6

UNRESTRICTED AREA D 4.1 Figure D 4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS IPEC ODCM D 4.1 - 2 Revision 6

UNRESTRICTED AREA D 4.1 Figure D 4.1-2 MAP DEFINING RELEASE POINTS IPEC ODCM D 4.1 - 3 Revision 5

Annual Radiological Environmental Operating Report D 5.1 D 5.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report An annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15th of each year. Per the Technical Specification Reporting Requirements, a single submittal may be made for a multiple unit station.

The Annual Radiological Environmental Operating Report shall include:

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

At least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary and the second shall include the more distant stations.

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

A summary description of the Radiological Environmental Monitoring Program.

A discussion of the reasons for not conducting the Radiological Environmental Monitoring Program as specified by D 3.5.1 and the plans for preventing recurrence.

A discussion of environmental sample measurements that exceed the reporting levels of Table D 3.5.1-2 but are not the result of plant effluents.

A discussion of all deviations from the sampling schedule of Table D 3.5.1-1.

A discussion of the contributing factors for cases in which the LLD required by Table D 3.5.1-3 was not achievable.

A discussion of identifiable nuclide peaks, including those of nuclides specified in Table D 3.5.1-3.

The results of the land use census.

The corrective actions taken to prevent a recurrence if the Interlaboratory Comparison Program is not being performed as required.

The results of licensee participation in the Interlaboratory Comparison Program.

IPEC ODCM D 5.1 - 1 Revision 6

Radioactive Effluent Release Report D 5.2 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.
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 offsite radiation doses due to the radioactive liquid and gaseous effluent releases from the unit or station during the previous calendar year. This assessment shall include potential offsite dose determined with data collected from the Radiological Ground Water Monitoring Program (RGWMP).
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.

IPEC ODCM D 5.2 - 1 Revision 6

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

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),
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.
g. A summary of data collected for the RGWMP, per D5.6 and NEI 07 Industry Ground Water Protection Initiative.
h. 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.

IPEC ODCM D 5.2 - 2 Revision 6

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)

IPEC ODCM D 5.3 - 1 Revision 6

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;
g. 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.

IPEC ODCM D 5.4 - 1 Revision 6

Process Control Program D 5.5 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:
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.

D 5.6 Radiological Ground Water Monitoring Program (RGWMP)

The purpose of the RGWMP is to monitor, investigate, and characterize any contamination of groundwater from licensed radioactive material at Indian Point Energy Center (IPEC).

a. The program is also required in order to meet the following objectives:

The Nuclear Energy Institute Groundwater Protection Initiative (NEI-07-07),

American Nuclear Insurers Guideline for unmonitored releases (ANI 07-01),

EPRI Groundwater Protection Guidelines, (report #1015118, Nov 2007),

NRC Information Notice 2006-13, Groundwater Contamination Due to Undetected Leakage of Radioactive Water, IPEC commitments to the NRC, Entergy Letter NL-06-033, Current Status/Future Plans Regarding Onsite Groundwater Contamination at IPEC, IPEC commitments to the NRC, Entergy Letter NL-08-079, Remediation and Long Term Monitoring of Site Groundwater.

b. Specific monitoring objectives of the program include:

Monitoring the status of any known radiological groundwater plumes, Detecting and quantifying previously unidentified sources of groundwater contamination, such as spills or leaks from a radioactively contaminated system, structure, or component, Providing data to calculate potential offsite doses to a member of the public, Monitoring and evaluating the long term effectiveness of remediation or intervention.

IPEC ODCM D 5.5 - 1 Revision 6

Radiological Ground Water Monitoring Program D 5.5 D 5.0 ADMINISTRATIVE CONTROLS D 5.6 Radiological Ground Water Monitoring Program (RGWMP) (continued)

c. Investigation and characterization activities are performed to evaluate and understand any groundwater contamination once it has been identified, or an event (such as a spill or leak) with the potential to contaminate the groundwater to levels above the investigation levels has occurred. Specific investigation and characterization objectives of the program include:

Determining the source(s) of groundwater contamination (eg, leaking radioactive components or systems, radioactive spills, or legacy soil/bedrock contamination),

Determining the locations, extent, and concentrations of groundwater contamination (eg, plume definition),

Evaluating necessary corrective or investigative actions, utilizing the Corrective Action Program.

d. Station procedures shall include detailed information regarding the following:

The purpose and scope of the program, as defined above, Location and periodicities of samples, Required radionuclides for analysis, including limits of detection, Guidance for communication of abnormal results, Guidance regarding the generation of periodic summary reports.

e. Elements of the RGWMP program that intersect the REMP shall be included in the Annual Radiological Environmental Operating Report, per D 5.1.
f. An evaluation of the EFFLUENT impact, and a summary of the sample data from the RGWMP shall be included in the annual Radiological Effluent Release Report, as identified in ODCM D 5.2.

IPEC ODCM D 5.5 - 2 Revision 6

Indian Point Energy Center Offsite Dose Calculation Manual Part I (RECS)

BASES

Applicability B D 3.0 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 Specifications, 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.

IPEC ODCM B D 3.0-1 Revision 6

Liquid Effluent Concentrations B D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS 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 a small fraction of 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 less than ten times the effluent concentration limits (ECs) 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 ten times the EFFLUENT CONCENTRATIONS 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-135 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.

IPEC ODCM B D 3.1.1 - 1 Revision 6

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 II.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 I", 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.

IPEC ODCM B D 3.1.2 - 1 Revision 6

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 II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I to 10 CFR Part 50 for liquid effluents.

IPEC ODCM B D 3.1.3 - 1 Revision 6

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 Tanks
b. Primary Water Storage Tanks
c. 13 Waste Distillate Storage Tank
d. 14 Waste Distillate Storage Tank
e. 31 Monitor Tank
f. 32 Monitor Tank
g. Unit 3 CPF High Total Dissolved Solids Tank
h. Unit 3 CPF Low Total Dissolved Solids Tank
i. Any 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.

IPEC ODCM B D 3.1.4 - 1 Revision 6

Gaseous Effluents Dose Rate D 3.2.1 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.

IPEC ODCM B D 3.2.1 - 1 Revision 6

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 II.B, III.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 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 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 I," Revision 1, October 1977 and Regulatory Guide 1.111, "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 each unit on site.

IPEC ODCM B D 3.2.2 - 1 Revision 6

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 II.C of Appendix I.

The action statements provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as 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 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man (applied where applicable), and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.3 - 1 Revision 6

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

This Specification applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.4 - 1 Revision 6

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

This Specification applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.5 - 1 Revision 6

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration.

Restricting the quantity of radioactivity contained in each gas storage tank provides 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, and NUREG 0133.

IPEC ODCM B D 3.2.6 - 1 Revision 6

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 ten times the EFFLUENT CONCENTRATION values specified in 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.

IPEC ODCM B D 3.3.1 - 1 Revision 6

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 release rates corresponding to effluent dose rates of 0.5 Rem/yr whole body, and 3.0 Rem/yr to the skin.

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.

IPEC ODCM B D 3.3.2 - 1 Revision 6

Radioactive Effluents Total Dose D 3.4.1 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.

IPEC ODCM B D 3.4.1 - 1 Revision 6

Radiological Environmental Monitoring Program D 3.5.1 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 implements Section 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.

IPEC ODCM B D 3.5.1 - 1 Revision 6

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.

IPEC ODCM B D 3.5.2 - 1 Revision 6

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.

IPEC ODCM B D 3.5.3 - 1 Revision 6

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.

IPEC ODCM B D 3.6.1 - 1 Revision 6

ODCM Part II - Calculational Methodologies 1.0 RADIATION MONITORS AND SETPOINTS 1.1 Effluent Monitoring System Description Information regarding effluent radiation monitor function and setpoint bases is provided in Tables 1-1 and 1-2. Additionally, Appendices B and C show a schematic of release pathways, including the relative position and application of these monitors.

1.2 Setpoints for Airborne Effluent Monitors Setpoints for airborne (gaseous) monitors are based on the permissible discharge rate as calculated in Section 3 of the ODCM, Part II, and shown in Appendix I. These setpoints are inherently conservative due to the assumed mixture (Table 3-8). They are tiered in such a way as to ensure proper (higher) authentication is obtained as the selected limit (and expected release rate) increases.

The Annual Limit is used to conservatively establish initial setpoints for routine operation.

For releases associated with unit shutdown, etc, additional permission may be obtained to apply the quarterly or instantaneous values, per Section 3.1.8. This method ensures operational control of releases, while precluding approaching the limits of D3.2.1.

The methodology identified in Section 3 and Appendix I is used to generate the following release rate limits. Default radiation monitor setpoints are calculated from these values:

Conservative Permissible Discharge Rates (Ci/sec)

Iodine/Particulate* Noble Gases Type of Limit Basis Unit 2 Unit 3 Unit 2 Unit 3 Annual Average ODCM, Part II, App I 4.01E-2 4.05E-2 7.20E+3 3.57E+3 Quarterly Average ODCM, Part II, App I 8.02E-2 8.10E-2 1.44E+4 7.14E+3 Instantaneous RECS D3.2.1 and App I 1.38E+1 1.38E+1 7.00E+4 7.00E+4

  • Half-lives greater than 8 days 1.2.1 The Plant Vent Wide Range Gas Monitor (R-27) reads in Ci/sec. Therefore, at unit 3, the alarm setpoints are set directly in Ci/sec. (Unit 2 does not apply alarm setpoints to R-27).

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

S = D / [(F) * (4.72E+2)] where; S = Maximum alarm setpoint in Ci/cc D = Permissible discharge rate in Ci/sec F = Vent duct flow in ft3/min 4.72E+2 = unit conversion factor (28317 ccmin/ft360sec)

For example, A plant vent flow of 60,000 cfm for noble gas: 70,000/(60,000

  • 472) = 2.47E-3 uCi/cc A containment purge of 28,000 cfm for particulates: 13.8/(28,000
  • 472) = 1.04E-6 uCi/cc IPEC ODCM Page 1 of 145 Revision 6

ODCM Part II - Calculational Methodologies 1.2.3 If the monitor reads and alarms in cpm, then the maximum alarm setpoint is calculated as follows:

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

where:

S, D, F, and 4.72E+2 are defined in the previous step CF = Rad Monitor Conversion Factor (Ci/cc per net cpm) 1.2.4 Normally, maximum allowable limits are calculated using a standard nuclide mix. However, setpoints may be determined based on the actual mix, on a case by case basis. This method is usually performed when the instantaneous release rate is applied. Should this method be applied, extra care should be applied to setpoint partitioning (for all release points) to ensure site dose rate limits are not approached.

1.2.5 During normal operation, the main plant vent is the only significant release point at either unit. 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 pathways 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.

If necessary, release rates may be apportioned (per 10CFR20 applicability to a site, rather than any one unit) for maximum operational flexibility such that one unit borrows routine apportionment from the other unit. This evolution is controlled by station procedures, which require direct communication with the Shift Managers and the Chemistry Department.

1.3 Setpoints for Liquid Effluent Monitors 1.3.1 Liquid Effluent Monitors have setpoints based on limiting the concentrations in the discharge canal to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20 in accordance with 10CFR20.1302(2)(i).

1.3.2 Monitor setpoints are inherently conservative due to the routine use of determining dilution from Circulating Water Pumps at the applicable unit only.

In actuality, both Circulating and Service Water systems for the entire site contribute to site dilution.

IPEC ODCM Page 2 of 145 Revision 6

ODCM Part II - Calculational Methodologies 1.3.3 For monitors that read and alarm in Ci/ml, setpoints are calculated as follows:

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

F = Available discharge canal dilution flow for this release, in gpm f= calculated allowable release rate in gpm (Section 2.2.6)

ADC = The Allowed Diluted Concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (both gamma and beta emitters). This term is necessary to correct the MPCW due to the relatively insignificant effect of beta emitters on the radiation monitor, as described in Section 2.2.6 and ODCM Appendix E.

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

AS = (C) * (M) where:

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

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

Alert or Warn setpoints for other monitors are typically initially established at approximately 75% of the Alarm value.

IPEC ODCM Page 3 of 145 Revision 6

ODCM Part II - Calculational Methodologies TABLE 1 - 1 Unit 2 Effluent Radiation Monitor System Data CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS TYPICAL RANGE 1 EFFLUENT CONTROL FUNCTIONS 4.6E-7 to 4.6E-1 Shuts RCV-014 (isolating gas tanks), stops VC Plant Vent Radiogas R-44 88 Fan Bldg release fans and shuts VC vent/purge valves.

Monitor Ci/cc (The charcoal bank remains in service at all times).

Waste Gas Disposal 0.1 to 1E5 None. RECS D3.2.6 is assured by setpoint R-50 98 PAB 4/21 System Monitor Curies basis per ODCM Part II, Sec 3.1.12.

Plant Vent Wide-Range Drawn from inside Plant Vent, Ch1-3) E-7 to E+6 R-27 Ci/cc None. PV Concentration and release rate (Accident) Monitor to 85 BAB Ch4) 10 to E+13 Ci/sec information only, for accident applications.

Unit 1 Stack Vent Unit 1 Nuclear Services Bldg 4.6E-7 to 4.6E-2 R-60 None Radiogas Monitor 100 Elevation Ci/cc Adjacent to service water return Fan Cooler Unit Service 1E-7 to 1E-1 R-46 / 53 line from V.C. fan cooler units None Water Return Ci/ml and motor coolers Component Cooling Adjacent to line monitors on 1E-7 to 1E-1 None. Setpoints are not based on effluent.

R-47 System pump outlet each pump outlet Ci/ml They are for ALARA and information only.

Component Cooling Heat 1E-7 to 1E-1 R-39 / 40 Exchanger Service Water 80 PAB None Ci/ml Monitors Waste Disposal Liquid 4.3E-8 to 4.3E-2 R-54 In-line monitor on 70 CSB Terminates Distillate Tank releases on alarm Effluent Monitor Ci/ml 4/21 1

Actual Ranges of Rad Monitors (in Engineering Units) are a function of the selection of isotopes (average energy) and other factors.

IPEC ODCM Page 4 of 145 Revision 6

ODCM Part II - Calculational Methodologies TABLE 1 - 2 Unit 3 Effluent Radiation Monitor System Data 1

CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS TYPICAL RANGE EFFLUENT CONTROL FUNCTIONS Samples drawn from 32 and 35 9.2E-8 to 9.2E-2 R-12 Containment Gas Monitor Containment Ventilation Isolation Containment Fan Coolers Ci/cc Plant Vent (PV) Installed within the plenum of the 1.6E-7 to 1.6E-1 Secures waste gas tank release, isolates R-14 Radiogas Monitor Plant Vent, 105 elevation Ci/cc containment, aligns PV charcoal On alarm, diverts air ejector exhaust to Condenser Air Ejector Adjecent-to-line detector, on the 2.8E-7 to 2.8E-1 R-15 VC and secures steam to priming air Monitor exhaust header, 53 Turbine Hall Ci/cc ejectors re-heaters Waste Gas Disposal Adjacent to line, on suction to 1E-2 to 1E+3 None. This setpoint is based on limiting R-20 System Monitor waste gas compressors Ci/cc 50,000 Ci per tank, per RECS D3.2.6.

Plant Vent Wide-Range Drawn from inside Plant Vent to Ch1-3) E-7 to E+5 Ci/cc R-27 (Same functions as R-14)

(Accident) Monitor fan house near 80 airlock Ch4) 10 to E+13 Ci/sec 4th Floor Administration Building Administration Building 1E+1 to 1E+6 cpm R-46 Monitor Exhaust Plenum for None Vent Radiogas Monitor (approx 5.0E-8 to 5.0E-2 Ci/cc)

Controlled Areas RAMS Building Vent 55 RAMS Building Monitor 1E-6 to 1E+2 R-59 None Radiogas Monitor Exhaust Plenum Ci/cc Fan Cooler and Motor Adjacent to service water return 7.1E-7 to 7.1E-1 R-16 A/B Cooler Service Water line from V.C. fan cooler units and None Ci/ml Return motor coolers Component Cooling Adjacent to line monitors on each 2.3E-6 to 2.3E-1 None. These setpoints are based on R-17 A/B System pump outlet pump outlet Ci/ml early indication of RCS leak into CCW.

Component Cooling Heat Adjacent to line, mounted on SW 1.3E-6 to 1.3E-2 R-23 Exchanger Service Water return from Component Cooling None Ci/ml Monitor Heat Exchanger Waste Disposal Liquid In-line monitor on monitor tank 4.0E-8 to 4.0E-2 R-18 Terminates monitor tank release on alarm Effluent Monitor recirc pump discharge Ci/ml R-19 SG Blowdown Monitor PAB blowdown room monitors 7.0E-8 to 8.2E+2 Ci/ml Closes blowdown isolation valves and SG steam generator blown (using 2 ranges, per RG 1.97) sample valves Condensate Polisher Recirc line of HTDS/LTDS tanks in Terminates HTDS or LTDS tank release.

1E-7 to 1E-1 R-61 Facility (CPF) Regen Waste CPF (used during a primary to Applicable only in a primary to secondary Ci/ml Release Monitor secondary leak). leak, as defined in RECS D1.1.

1 Actual Ranges of Rad Monitors (in Engineering Units) are a function of the selction of isotopes (average energy) and other factors.

IPEC ODCM Page 5 of 145 Revision 6

ODCM Part II - Calculational Methodologies 2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Information 2.1.1 A completed and properly authorized Liquid Radioactive Waste Permit is required prior to performing any BATCH release (a release of known volume and activity from an isolated source).

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

2.1.3 The radioactivity in liquid waste tanks shall be continuously monitored during release except as allowed by RECS D3.3.1. If the flowmeter is inoperable, the flow shall be estimated every four hours by difference in tank level or by discharge pump curves.

2.1.4 Prior to discharge, the radioactive waste tank contents shall be recirculated for at least three tank volumes. After this recirculation, and prior to discharge, a sample 4/21 shall be taken and analyzed for activity with a portion of the sample set aside for composite analysis. The measured activity shall be used for calculating allowable discharge rate and the alarm setpoint for the liquid waste discharge monitor.

2.1.5 Steam Generators or other CONTINUOUS releases shall be quantified and included in effluent reports, but do not require a pre-release permit. Continuous releases are typically quantified from periodic sampling and the use of radiation monitoring. In Modes 4-6, however, SG Draindowns are typically quantified in BATCH mode.

2.1.6 Assurance that the combined liquid releases from Units 2 and 3 maintain compliance with 10CFR20 is provided by administrative controls which include an administrative minimum dilution of 80,000 gpm for any batch release, and limiting to only one unit discharging at a time. 4/21 2.1.7 Steam Generator Blowdown activity is determined by composite samples collected in a manner to be proportional to the rate of flow of individual steam generator to total steam generator blowdown. These samples are then analyzed for the various radionuclides at frequencies specified in the RECS. Due to appropriate compositing, total blowdown flow is then routinely multiplied by average concentrations to determine the actual effluent contribution from Steam Generator Blowdown.

2.1.8 Time average dose calculations (10CFR50) may use total site dilution flow for both units, with the determined dose contributions additive for a site report over any specified period.

2.1.9 The discharge canal flow rate is determined by the use of pump flow characteristics curves. Unit 2 circulator pumps are operated at either low or high speed 4/21 (approximately 88,000 to 140,000 gpm). Unit 3 circulator pumps have a variable speed capacity, and can produce a range from 65,000 to 140,000 gpm.

IPEC ODCM Page 6 of 145 Revision 6

ODCM Part II - Calculational Methodologies 2.1.10 Radioactivity content in outdoor tanks is to be limited to less than 10 curies, excluding tritium and noble gas, as per RECS D3.1.4. Compliance with this requirement is demonstrated by limiting the radioactive concentration in these tanks to the value which results in 10 curies when the tank is at full liquid capacity, except as modified below. The radioactive concentration limits for these tanks are:

10 curies 106 Ci / curie RWST: 7.3 10 3 Ci / ml 358,500 gal 3785ml / gal 10 curies 106 Ci / curie PWST: 1.6 10 2 Ci / ml 165,000 gals 3785ml / gal 31 & 32 Monitor Tanks (Unit 3):

10 curies 106 Ci / curie 2.2 101 Ci / ml 11,750gals 3785ml / gal 13 & 14 Waste Distillate Storage Tanks (Units 1/2):

10 curies 10 6 Ci / curie 1.1 10 1 Ci / ml 23,577gals 3785ml / gal Unit 3s Condensate Polisher High and Low Total Dissolved Solids Tanks:

10 curies 106 Ci / curie 4.4 10 2 Ci / ml 60,000 gals 3785ml / gal Outside Temporary Tanks:

10 curies 106 Ci / curie Ci / ml Volume ( gal ) 3785ml / gal Integrated curies in a tank can similarly be determined by calculating the curies added from known inlet concentrations and volumes, which would then be combined with previously determined tank curie levels.

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

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

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ODCM Part II - Calculational Methodologies 2.1.11 Turbine hall drains (from sumps in the five foot elevation for units 2 and 3) receive drains from areas containing secondary plant components at sub-atmospheric pressures. These sumps do not meet the intent of a turbine hall drain system as defined in NUREG 0472, however their effluent contribution should be evaluated.

Quantification of effluents is performed on this pathway during a Primary to Secondary Leak , as defined by RECS D1.1. In these cases, releases from this pathway would be quantified by periodic sampling multiplying the source term by a determination of the release rate to the river, generally bounded by secondary system loss or make-up rate.

At elevated Steam Generator activity levels (approximately 1.0E-4 or above), turbine hall drains may require temporary processing, should effluents via this pathway approach the 31-day dose projection limits per RECS D3.1.3. In this case, water at Unit 3 can be directed to the Condensate Polishing Facility prior to release. At Unit 2, a temporary processing skid will need to be applied, or other installed cleanup system.

Activity released via this pathway is determined as follows:

Turbine Hall Feedwater Steam Plant SG Blowdown Drain Effluent Activity Specific

  • Makeup Activity Rate Rate to the River 2.1.12 Studies performed by the NY State Department of Health (1981-82) determined that waterborne Carbon 14 is released at IPEC, at a conservative estimate of .07 curies per year. The curies released and offsite dose from liquid C-14 effluent is reported separately from other, more common isotopes, to prevent confusion, loss of relevance of the more common isotopes, and to preserve historical trends.

Carbon-14 effluent is discussed in detail in Appendix K. Annual curies released and offsite dose are summarized in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report.

2.1.13 Several normally non-radioactive systems are periodically analyzed for radioactivity.

Examples include Unit 3s Condensate Polisher regenerant waste tank, the Spent Fuel Pool Auxiliary Heat Exchanger Secondary Cooling Systems (when in use), and Site Storm Drains, etc. The monitoring program for these type of release points is consistent with the direction set forth in NRC IE Bulletin 80-10 "Contamination of Non-radioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment". Should a system become contaminated, releases will be evaluated and quantified (as either batch or continuous) in accordance with the requirements listed in the RECS and the IPEC 80-10 program.

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

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ODCM Part II - Calculational Methodologies 2.1.15 Due to the addition of Hafnium control rods at Unit 3, an offsite dose may need to be calculated for Hafnium isotopes in waste pathways. In the absence of site-specific bioaccumulation and dose factors for Hafnium, factors for Zirconium are used, as suggested in ICRP 30. Should these calculations become necessary, they will be performed per the following sections, and manually added to other totals.

2.1.16 Investigations from the Radiological Ground Water Monitoring Program (RGWMP) have resulted in a determination of liquid effluent. A quantification and dose assessment of radioactive groundwater and storm water leaving the site shall be performed at least annually. This quantification shall include, as a minimum, the source term from samples obtained near the effluent points of each applicable pathway (eg, ground water wells nearest the site boundary), and a determination of release rate and dilution flow.

Release rates to the river from both the bedrock pathways and collective storm drain pathways are provided from modeling by hydrologists. Initially, a general precipitation mass balance model was applied to assess groundwater flow rates (Reference 32). During calendar year 2007, and again in 2010, this model was calibrated using an independent Darcys Law model. The precipitation mass balance model, as modified through the final calibration in 2010, will continue to be used going forward, as discussed in Appendix J, Groundwater and Stormwater Flow and Offsite Dose Calculation Details.

Dilution flow is directly measured in the Discharge Canal, for any water directed there. For storm or groundwater reaching the Hudson via a direct path under the canal, a dilution factor equivalent to a 6-hour half-tidal surge in the effected area of the Hudson is applied. As discussed in Reference 33, this dilution is equivalent to 5.83E10 gallons per year, or 1.11E5 gallons per minute.

Dose calculations are otherwise then completed per the following sections.

2.2 Liquid Effluent Concentrations This section provides a description of the means that will be used to demonstrate compliance with the RECS D3.1.1.

2.2.1 Compliance with the instantaneous limits of 10CFR20 is achieved by allocating dilution flow on a per unit basis, as described in Section 2.1.6. Compliance with 10CFR50 (quarterly and annual limitations) is assured by completing a monthly report which summarizes the releases from the site.

2.2.2 Each isolated liquid waste tank must be recirculated for at least three tank volumes prior to sampling in order to ensure a representative sample is obtained. At Unit 2, this duration is determined from station procedures with every batch release. At Unit 4/21 3, a default minimum recirculation time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> may be used for 31 and 32 monitor tanks in lieu of the actual calculation:

11750 3

= 5.9 6 100 /

Note: Nominal monitor tank pump flow rate is approximately 135 gpm. For conservativism however, 100 gpm is used for the recirculation flow rate, while 150 gpm is used for the discharge flow rate in all release calculations.

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ODCM Part II - Calculational Methodologies 2.2.3 For batch releases, the concentration in liquid effluents prior to dilution in the discharge canal is determined by sampling prior to release. For continuous releases, the concentrations can be determined by either grab sampling, or by direct reading radiation monitor. If the process radiation monitor is utilized, the conversion factor should be verified as appropriate for the mixture being released.

For non-direct reading monitors, the following calculation is used:

C CF CR C= Concentration of liquid effluent (uCi/ml) prior to dilution CF = Conversion factor of monitor (uCi/ml per net cpm)

CR = Count rate of monitor (in net cpm) 2.2.4 The final diluted concentration in the canal is determined as follows:

CD (C ) ( f ) /( F )

Where: CD = Diluted concentration in the discharge canal in uCi/ml C = Pre-dilution liquid concentration in uCi/ml F = Dilution flow in the discharge canal in gal/min f = Release rate of liquid effluent in gal/min 2.2.5 Calculation of Maximum Permissible Concentration in Liquid Effluents

a. This section describes the methodology used to ensure compliance with RECS D3.1.1. The discharge canal concentration of radionuclides must be maintained less than those identified as limits (10 times the ECs of 10CFR20). The noble gas limit has been specified as 2E-4 uCi/ml.

These criteria are normally assured by using an Allowed Diluted Concentration (ADC) on each discrete release. This differs from the ECs given in 10CFR20 Appendix B in that, for radioisotopes that do not have gammas greater than 60 kev emitted during decay, default values are included to estimate their contribution.

The Allowed Diluted Concentration is derived and calculated as follows:

MPCW t

  • CG MPCW t
  • CG MPCW t ADC or ADC or ADC Total activity CG CB 1 CB CG where:

ADC = Allowed diluted concentration in uCi/ml as defined in ODCM Appendix E.

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ODCM Part II - Calculational Methodologies MPCWt = Maximum permissible concentration in water for all isotopes (beta & gamma), in uCi/ml, as defined in RECS, D1.1, as follows:

Ci MPCWt i i

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

b. A representative sample must be obtained. For batch releases, at least two tank volumes are recirculated after the tank has been isolated to meet these requirements. The minimum recirculation time is determined as follows:

T = 2 (V) / (G) where; T = Minimum recirculation time in min V = Volumes in the tank to be discharged, in gal G = Recirculation rate in gal/min

c. After the tank has been sampled, the Allowed Diluted Concentration is determined, per the equations above.
d. A determination of other liquid radioactive discharges is evaluated. If other releases are in progress at an affected unit, the radioactive concentrations and discharge rates are included to determine a potentially new required dilution factor.
e. Available dilution flow may be adjusted by physically using more pumps or altering an allocation fraction. Additionally, if required, release rate can be adjusted to comply with diluted concentration limits with existing dilution flow. Typically, however, these measures are not required.
f. The required dilution flow is calculated as follows:

Dr CG E where; ADC Dr = Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm CG and ADC are defined in Section 2.2.6.a IPEC ODCM Page 11 of 145 Revision 6

ODCM Part II - Calculational Methodologies

g. The permissible discharge rate is calculated as follows:

ADC

  • B D Where:

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

Available Dilution Required Dilution Flow B Flow , gpm from Other Releases, gpm Note: With no other releases, B simply becomes the Available Dilution Flow.

2.3 Liquid Effluent Dose Calculation Requirements RECS D3.1.2 requires that the dose or dose commitment above background to an individual in an unrestricted area from radioactive materials in liquid effluents released from each reactor unit shall be limited:

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

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

c) If either of the above limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per RECS D3.4.1.

2.3.1 RECS D3.1.3 requires that appropriate portions of the radwaste treatment system be used to reduce the radioactive material in liquid waste prior to their discharge when the projected dose due to liquid effluent from each reactor unit when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses due to liquid release shall be projected at least once per 31 days. These doses are projected based on the dose methodology in Section 2.4. or 2.5. The average of previous months' doses is used to project future dose, as follows:

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

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

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

Due to the absence of a potable water pathway, RECS D3.1.2 reporting regulations for a 3 mile downstream limit do not apply. There is no exposures from ingestion of drinking water.

Thus, at IPEC, the cumulative dose considers only the dose contributions from the maximum exposed individuals consumption of fish and invertebrates. Tables of dose factors for three age groups were developed as per Section 2.4.3 and are included as Tables 2-1, 2-2, and 2-3. (Infant dose factors are 0 and are not included).

2.4.2 The relationships and methods that form the calculational base for dose accounting for the liquid effluent pathway are described in this section. These relationships can be used to meet the calculational requirements of Section 2.3.1. The cumulative dose factors (Ait) are calculated in Section 2.4.3. The following equation is generally applicable and can be used for any number of isotopes released over a time period:

m n D (T ) [A i 1 iT ( dt k )( C ik )( Fk ) ]

k 1 Where:

m = The total number of isotopes released.

D(T) = The liquid effluent cumulative dose commitment from nuclides to the total body or any organ, T, for the time period k, in mrem.

dtk = The length of the time period, k over which Cik and Fk are averaged for all liquid releases, in hours. (This can be individual release durations summed, or an entire period duration, defined with each application of this equation.)

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

n = The total number of releases considered.

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ODCM Part II - Calculational Methodologies AiT = The site related ingestion dose commitment factor to the total body or any organ for each identified principal gamma and beta emitter listed in Table 2-1, 2-2, and 2-3, in mrem-ml per hr-uCi.

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

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

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

Liquid Radioact ive Waste Flow Fk Discharge Structure Exit Flow Applicable Factor The liquid radioactive waste flow is the flow from all continuous and batch radioactive effluent releases specified in the RECS from all liquid radioactive waste management systems. The discharge structure exit flow is the average flow during disposal from the discharge structure release point into the receiving body of water. Based on studies by New York University Medical Center (ref. 14 page 7), the appropriate "Applicable Factor" (a mixing factor in the near field), is 5.0.

For permitting of liquid effluent releases, Fk is typically determined with a conservative dilution flow concurrent with the applicable release. (see Section 2.2). Initial doses are later calculated for each permit based upon the best estimate of the total dilution flow. If necessary doses are later recalculated with a more accurate estimate of the 4/21 total dilution flow. This method allows both 1) an immediate assessment of proximity to 10CFR20 (release rate) limits, and 2) a more accurate long-term assessment of doses per 10CFR50.

2.4.3 Dose Factor for Liquid Effluent Calculations The equation for dose from liquid effluents requires the use of a dose factor A iT for each nuclide, i, which embodies the dose factors, pathway transfer factor, pathway usage factors, and dilution factors for the points of pathway origin.

IPEC follows the guidance of NUREG 0133 and has calculated A iT for the total body and critical organ of the maximum exposed individual for Adult, Teen and Child doses.

Most factors needed in the equation were obtained from Regulatory Guide 1.109 with the following exceptions (see Section 2.6 and Ref 2, 12, 13, 14, and 25):

The fish and invertebrate bioaccumulation factors (BFi and BIi) for Cesium, Niobium, Silver, and Antimony, were determined locally.

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ODCM Part II - Calculational Methodologies For Cesium, a site specific factor of 224 was used instead of the 2,000 presented in Table A-1 of the Regulatory Guide for fish. Similarly, a factor of 224 was used for invertebrates instead of the Regulatory Guide value of 1000.

For Silver, the fish and invertebrate factors are 2.3 and 3300, respectively.

For Niobium, the fish and invertebrate factors are 300 and 100 respectively.

For Antimony, the fish and invertebrate factors are 1 and 300 respectively.

The summary dose factor is as follows:

AiT K [(UF ) BFi (UI ) BI i ]Df Where:

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

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

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

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

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

DFi = 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.

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

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ODCM Part II - Calculational Methodologies 2.5 Backup Simplified Dose Methodology 2.5.1 An alternate computer method which completely complies with Section 2.4 is available should the primary computer system be inoperable.

2.5.2 Hand Calculations which completely comply with Section 2.4 can be employed if the primary and secondary computer codes are inoperable. Because they are time consuming and subject to calculational errors, procedural guidance in the actual flow of calculations should be used to maintain a standard format. These procedures are also used for benchmark tests of the computer codes.

2.6 Site Specific Bio-Accumulation & Dose Factors 2.6.1 As stated in Section 2.4.3 the bioaccumulation factor (BF i) for Cesium in fish is assumed to be 224 instead of the 2000 listed in Regulatory Guide 1.109 (Ref. 3).

Similarly, the bioaccumulation factor for invertebrates is 224. This is based on three facts; 1) the Hudson River at IPEC is not completely fresh, 2) the Bioaccumulation Factor for salt water is 40 (Ref. 2), and 3) the behavior of Cesium in the Hudson is a complex phenomenon, as discussed below.

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

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

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

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

Similarly for invertebrates, the site specific bioaccumulation factor of 224 is used.

This is larger than the value of 25 given in Reg Guide 1.109 for salt water invertebrates.

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ODCM Part II - Calculational Methodologies A second conservatism in the NRC model concerns the location at which the concentrations in the river of the discharged Cesium are evaluated. Use of this model implies that these fish have grown directly in such a location prior to being caught, which is unrealistic and adds about a factor of five in conservation. This conservatism remains in the calculation, thus the use of the NYU (Ref. 12) bioaccumulation factor is justifiable.

2.6.2 No bioaccumulation factor for Silver is listed in Rev. 1 of Regulatory Guide 1.109, Table A-1. The values of 2.3 and 5000 for fish and invertebrates were obtained from ORNL-4992 (sponsored by ERDA 660, Ref. 25) and are included in the ODCM in the interests of increased accuracy since Ag-110m is a potential component of IPEC liquid releases.

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

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

2.6.5 Te-123m dose factors are not listed in Reg. Guide 1.109. Since this isotope is identified from potentially failed secondary startup sources and previously identified at IPEC, ingestion dose factors were derived from ICRP 30 and calculated per Ref 34.

2.6.6 In summary, with the exception of the bioaccumulation and dose factors discussed above, all remaining factors applied at IPEC are defined in Reg Guide 1.109 for a combination of fresh water fish and salt water invertebrates.

IPEC ODCM Page 17 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 2 - 1 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mrem/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 BE-7 3.29E-01 7.45E-01 3.69E-01 0.00E+00 7.83E-01 0.00E+00 1.28E+02 NA-24 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 P-32 4.96E+07 3.08E+06 1.92E+06 0.00E+00 0.00E+00 0.00E+00 5.57E+06 CR-51 0.00E+00 0.00E+00 4.31E+00 2.58E+00 9.50E-01 5.72E+00 1.08E+03 MN-54 0.00E+00 5.43E+03 1.04E+03 0.00E+00 1.61E+03 0.00E+00 1.66E+04 MN-56 0.00E+00 1.37E+02 2.42E+01 0.00E+00 1.73E+02 0.00E+00 4.36E+03 FE-55 3.21E+04 2.21E+04 5.16E+03 0.00E+00 0.00E+00 1.24E+04 1.27E+04 FE-59 5.06E+04 1.19E+05 4.56E+04 0.00E+00 0.00E+00 3.32E+04 3.96E+05 CO-58 0.00E+00 5.15E+02 1.15E+03 0.00E+00 0.00E+00 0.00E+00 1.04E+04 CO-60 0.00E+00 1.48E+03 3.26E+03 0.00E+00 0.00E+00 0.00E+00 2.78E+04 NI-63 4.97E+04 3.45E+03 1.67E+03 0.00E+00 0.00E+00 0.00E+00 7.19E+02 NI-65 2.02E+02 2.62E+01 1.20E+01 0.00E+00 0.00E+00 0.00E+00 6.65E+02 CU-64 0.00E+00 9.08E+01 4.26E+01 0.00E+00 2.29E+02 0.00E+00 7.74E+03 ZN-65 1.61E+05 5.13E+05 2.32E+05 0.00E+00 3.43E+05 0.00E+00 3.23E+05 ZN-69 3.43E+02 6.57E+02 4.57E+01 0.00E+00 4.27E+02 0.00E+00 9.87E+01 BR-83 0.00E+00 0.00E+00 4.05E+01 0.00E+00 0.00E+00 0.00E+00 5.84E+01 BR-84 0.00E+00 0.00E+00 5.25E+01 0.00E+00 0.00E+00 0.00E+00 4.13E-04 BR-85 0.00E+00 0.00E+00 2.16E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 1.01E+05 4.72E+04 0.00E+00 0.00E+00 0.00E+00 2.00E+04 RB-88 0.00E+00 2.91E+02 1.54E+02 0.00E+00 0.00E+00 0.00E+00 4.02E-09 RB-89 0.00E+00 1.93E+02 1.35E+02 0.00E+00 0.00E+00 0.00E+00 1.12E-11 SR-89 2.57E+04 0.00E+00 7.37E+02 0.00E+00 0.00E+00 0.00E+00 4.12E+03 SR-90 6.32E+05 0.00E+00 1.55E+05 0.00E+00 0.00E+00 0.00E+00 1.82E+04 SR-91 4.72E+02 0.00E+00 1.91E+01 0.00E+00 0.00E+00 0.00E+00 2.25E+03 SR-92 1.79E+02 0.00E+00 7.75E+00 0.00E+00 0.00E+00 0.00E+00 3.55E+03 Y-90 6.07E+00 0.00E+00 1.63E-01 0.00E+00 0.00E+00 0.00E+00 6.43E+04 Y-91M 5.73E-02 0.00E+00 2.22E-03 0.00E+00 0.00E+00 0.00E+00 1.68E-01 Y-91 8.89E+01 0.00E+00 2.38E+00 0.00E+00 0.00E+00 0.00E+00 4.89E+04 Y-92 5.33E-01 0.00E+00 1.56E-02 0.00E+00 0.00E+00 0.00E+00 9.33E+03 Y-93 1.69E+00 0.00E+00 4.67E-02 0.00E+00 0.00E+00 0.00E+00 5.36E+04 ZR-95 1.63E+00 5.22E-01 3.54E-01 0.00E+00 8.20E-01 0.00E+00 1.66E+03 ZR-97 9.00E-02 1.82E-02 8.30E-03 0.00E+00 2.74E-02 0.00E+00 5.63E+03 NB-95 4.83E+00 2.69E+00 1.44E+00 0.00E+00 2.65E+00 0.00E+00 1.63E+04 MO-99 0.00E+00 1.28E+02 2.43E+01 0.00E+00 2.90E+02 0.00E+00 2.97E+02 TC-99M 1.59E-02 4.50E-02 5.73E-01 0.00E+00 6.84E-01 2.21E-02 2.66E+01 TC-101 1.64E-02 2.36E-02 2.32E-01 0.00E+00 4.25E-01 1.21E-02 7.09E-14 RU-103 1.10E+02 0.00E+00 4.74E+01 0.00E+00 4.20E+02 0.00E+00 1.28E+04 RU-105 9.16E+00 0.00E+00 3.62E+00 0.00E+00 1.18E+02 0.00E+00 5.60E+03 RU-106 1.64E+03 0.00E+00 2.07E+02 0.00E+00 3.16E+03 0.00E+00 1.06E+05 AG-110M 4.58E+02 4.23E+02 2.51E+02 0.00E+00 8.32E+02 0.00E+00 1.73E+05 SB-122 3.47E+01 7.99E-01 1.20E+01 5.38E-01 0.00E+00 2.08E+01 1.32E+04 SB-124 4.86E+02 9.20E+00 1.91E+02 1.18E+00 0.00E+00 3.79E+02 1.38E+04 SB-125 3.11E+02 3.47E+00 7.40E+01 3.16E-01 0.00E+00 2.40E+02 3.42E+03 IPEC ODCM Page 18 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 2 - 1 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mrem/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.72E+03 9.87E+02 3.65E+02 8.19E+02 1.11E+04 0.00E+00 1.09E+04 TE-127M 6.88E+03 2.46E+03 8.38E+02 1.76E+03 2.79E+04 0.00E+00 2.31E+04 TE-127 1.12E+02 4.01E+01 2.42E+01 8.28E+01 4.55E+02 0.00E+00 8.82E+03 TE-129M 1.17E+04 4.36E+03 1.85E+03 4.01E+03 4.88E+04 0.00E+00 5.88E+04 TE-129 3.19E+01 1.20E+01 7.77E+00 2.45E+01 1.34E+02 0.00E+00 2.41E+01 TE-131M 1.76E+03 8.60E+02 7.16E+02 1.36E+03 8.71E+03 0.00E+00 8.53E+04 TE-131 2.00E+01 8.36E+00 6.32E+00 1.65E+01 8.77E+01 0.00E+00 2.83E+00 TE-132 2.56E+03 1.66E+03 1.55E+03 1.83E+03 1.60E+04 0.00E+00 7.83E+04 I-130 4.88E+01 1.44E+02 5.68E+01 1.22E+04 2.24E+02 0.00E+00 1.24E+02 I-131 2.68E+02 3.84E+02 2.20E+02 1.26E+05 6.58E+02 0.00E+00 1.01E+02 I-132 1.31E+01 3.50E+01 1.23E+01 1.23E+03 5.58E+01 0.00E+00 6.58E+00 I-133 9.16E+01 1.59E+02 4.86E+01 2.34E+04 2.78E+02 0.00E+00 1.43E+02 I-134 6.84E+00 1.86E+01 6.64E+00 3.22E+02 2.95E+01 0.00E+00 1.62E-02 I-135 2.86E+01 7.48E+01 2.76E+01 4.93E+03 1.20E+02 0.00E+00 8.45E+01 CS-134 4.14E+04 9.84E+04 8.04E+04 0.00E+00 3.18E+04 1.06E+04 1.72E+03 CS-136 4.33E+03 1.71E+04 1.23E+04 0.00E+00 9.51E+03 1.30E+03 1.94E+03 CS-137 5.30E+04 7.25E+04 4.75E+04 0.00E+00 2.46E+04 8.18E+03 1.40E+03 CS-138 3.67E+01 7.25E+01 3.59E+01 0.00E+00 5.33E+01 5.26E+00 3.09E-04 BA-139 6.47E+00 4.61E-03 1.89E-01 0.00E+00 4.31E-03 2.61E-03 1.15E+01 BA-140 1.35E+03 1.70E+00 8.87E+01 0.00E+00 5.78E-01 9.73E-01 2.79E+03 BA-141 3.14E+00 2.37E-03 1.06E-01 0.00E+00 2.21E-03 1.35E-03 1.48E-09 BA-142 1.42E+00 1.46E-03 8.93E-02 0.00E+00 1.23E-03 8.27E-04 2.00E-18 LA-140 1.58E+00 7.95E-01 2.10E-01 0.00E+00 0.00E+00 0.00E+00 5.83E+04 LA-142 8.07E-02 3.67E-02 9.15E-03 0.00E+00 0.00E+00 0.00E+00 2.68E+02 CE-141 3.23E+00 2.18E+00 2.48E-01 0.00E+00 1.01E+00 0.00E+00 8.35E+03 CE-143 5.69E-01 4.21E+02 4.66E-02 0.00E+00 1.85E-01 0.00E+00 1.57E+04 CE-144 1.68E+02 7.04E+01 9.04E+00 0.00E+00 4.17E+01 0.00E+00 5.69E+04 PR-143 5.80E+00 2.33E+00 2.88E-01 0.00E+00 1.34E+00 0.00E+00 2.54E+04 PR-144 1.90E-02 7.88E-03 9.65E-04 0.00E+00 4.45E-03 0.00E+00 2.73E-09 ND-147 3.97E+00 4.59E+00 2.74E-01 0.00E+00 2.68E+00 0.00E+00 2.20E+04 W-187 2.98E+02 2.49E+02 8.71E+01 0.00E+00 0.00E+00 0.00E+00 8.16E+04 NP-239 3.53E-02 3.47E-03 1.91E-03 0.00E+00 1.08E-02 0.00E+00 7.12E+02 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-57 0.00E+00 1.21E+02 2.01E+02 0.00E+00 0.00E+00 0.00E+00 3.07E+03 SR-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-97 4.05E-02 1.02E-02 3.74E-03 0.00E+00 1.20E-02 0.00E+00 3.78E+01 CD-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SN-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-134 3.29E+01 2.15E+01 1.32E+01 2.88E+01 2.08E+02 0.00E+00 3.65E-02 CE-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HG-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 19 of 145 Revision 6

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

(AiT) mrem/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 BE-7 3.58E-01 8.02E-01 4.01E-01 0.00E+00 8.50E-01 0.00E+00 9.76E+01 NA-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 P-32 5.40E+07 3.35E+06 2.09E+06 0.00E+00 0.00E+00 0.00E+00 4.54E+06 CR-51 0.00E+00 0.00E+00 4.44E+00 2.47E+00 9.73E-01 6.34E+00 7.46E+02 MN-54 0.00E+00 5.33E+03 1.06E+03 0.00E+00 1.59E+03 0.00E+00 1.09E+04 MN-56 0.00E+00 1.43E+02 2.54E+01 0.00E+00 1.81E+02 0.00E+00 9.40E+03 FE-55 3.35E+04 2.37E+04 5.54E+03 0.00E+00 0.00E+00 1.51E+04 1.03E+04 FE-59 5.20E+04 1.21E+05 4.69E+04 0.00E+00 0.00E+00 3.83E+04 2.87E+05 CO-58 0.00E+00 5.10E+02 1.18E+03 0.00E+00 0.00E+00 0.00E+00 7.04E+03 CO-60 0.00E+00 1.48E+03 3.32E+03 0.00E+00 0.00E+00 0.00E+00 1.92E+04 NI-63 5.15E+04 3.64E+03 1.75E+03 0.00E+00 0.00E+00 0.00E+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 0.00E+00 2.15E+05 ZN-69 3.73E+02 7.10E+02 4.97E+01 0.00E+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 0.00E+00 0.00E+00 BR-84 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 1.09E+05 5.12E+04 0.00E+00 0.00E+00 0.00E+00 1.61E+04 RB-88 0.00E+00 3.12E+02 1.66E+02 0.00E+00 0.00E+00 0.00E+00 2.67E-05 RB-89 0.00E+00 2.01E+02 1.42E+02 0.00E+00 0.00E+00 0.00E+00 3.09E-07 SR-89 2.79E+04 0.00E+00 8.00E+02 0.00E+00 0.00E+00 0.00E+00 3.33E+03 SR-90 5.27E+05 0.00E+00 1.30E+05 0.00E+00 0.00E+00 0.00E+00 1.48E+04 SR-91 5.12E+02 0.00E+00 2.04E+01 0.00E+00 0.00E+00 0.00E+00 2.32E+03 SR-92 1.94E+02 0.00E+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 0.00E+00 0.00E+00 5.42E+04 Y-91M 6.18E-02 0.00E+00 2.36E-03 0.00E+00 0.00E+00 0.00E+00 2.92E+00 Y-91 9.64E+01 0.00E+00 2.58E+00 0.00E+00 0.00E+00 0.00E+00 3.95E+04 Y-92 5.80E-01 0.00E+00 1.68E-02 0.00E+00 0.00E+00 0.00E+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 0.00E+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 0.00E+00 4.93E+01 0.00E+00 4.06E+02 0.00E+00 9.63E+03 RU-105 9.85E+00 0.00E+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 0.00E+00 3.42E+03 0.00E+00 8.50E+04 AG-110M 4.45E+02 4.22E+02 2.56E+02 0.00E+00 8.04E+02 0.00E+00 1.18E+05 SB-122 4.35E+01 8.47E-01 1.27E+01 5.53E-01 0.00E+00 2.72E+01 9.13E+03 SB-124 5.09E+02 9.40E+00 1.99E+02 1.16E+00 0.00E+00 4.45E+02 1.03E+04 SB-125 3.27E+02 3.58E+00 7.64E+01 3.11E-01 0.00E+00 2.85E+02 2.53E+03 IPEC ODCM Page 20 of 145 Revision 6

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

(AiT) mrem/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.96E+03 1.07E+03 3.96E+02 8.28E+02 0.00E+00 0.00E+00 8.75E+03 TE-127M 7.48E+03 2.65E+03 8.90E+02 1.78E+03 3.03E+04 0.00E+00 1.87E+04 TE-127 1.22E+02 4.33E+01 2.63E+01 8.44E+01 4.95E+02 0.00E+00 9.44E+03 TE-129M 1.26E+04 4.68E+03 2.00E+03 4.07E+03 5.28E+04 0.00E+00 4.74E+04 TE-129 3.47E+01 1.29E+01 8.44E+00 2.48E+01 1.46E+02 0.00E+00 1.90E+02 TE-131M 1.89E+03 9.06E+02 7.55E+02 1.36E+03 9.44E+03 0.00E+00 7.27E+04 TE-131 2.16E+01 8.90E+00 6.75E+00 1.66E+01 9.44E+01 0.00E+00 1.77E+00 TE-132 2.70E+03 1.71E+03 1.61E+03 1.80E+03 1.64E+04 0.00E+00 5.42E+04 I-130 5.06E+01 1.46E+02 5.84E+01 1.19E+04 2.25E+02 0.00E+00 1.12E+02 I-131 2.87E+02 4.02E+02 2.16E+02 1.17E+05 6.92E+02 0.00E+00 7.95E+01 I-132 1.37E+01 3.58E+01 1.29E+01 1.21E+03 5.64E+01 0.00E+00 1.56E+01 I-133 9.87E+01 1.67E+02 5.11E+01 2.34E+04 2.94E+02 0.00E+00 1.27E+02 I-134 7.17E+00 1.90E+01 6.82E+00 3.17E+02 2.99E+01 0.00E+00 2.50E-01 I-135 2.99E+01 7.71E+01 2.86E+01 4.96E+03 1.22E+02 0.00E+00 8.54E+01 CS-134 4.24E+04 9.97E+04 4.63E+04 0.00E+00 3.17E+04 1.21E+04 1.24E+03 CS-136 4.35E+03 1.71E+04 1.15E+04 0.00E+00 9.32E+03 1.47E+03 1.38E+03 CS-137 5.67E+04 7.54E+04 2.63E+04 0.00E+00 2.57E+04 9.97E+03 1.07E+03 CS-138 3.93E+01 7.54E+01 3.77E+01 0.00E+00 5.57E+01 6.48E+00 3.42E-02 BA-139 7.05E+00 4.96E-03 2.05E-01 0.00E+00 4.67E-03 3.42E-03 6.28E+01 BA-140 1.44E+03 1.76E+00 9.28E+01 0.00E+00 5.98E-01 1.19E+00 2.22E+03 BA-141 3.40E+00 2.54E-03 1.14E-01 0.00E+00 2.36E-03 1.74E-03 7.25E-06 BA-142 1.52E+00 1.52E-03 9.33E-02 0.00E+00 1.28E-03 1.01E-03 4.65E-12 LA-140 1.67E+00 8.20E-01 2.18E-01 0.00E+00 0.00E+00 0.00E+00 4.71E+04 LA-142 8.58E-02 3.81E-02 9.49E-03 0.00E+00 0.00E+00 0.00E+00 1.16E+03 CE-141 3.49E+00 2.33E+00 2.67E-01 0.00E+00 1.10E+00 0.00E+00 6.66E+03 CE-143 6.16E-01 4.48E+02 5.01E-02 0.00E+00 2.01E-01 0.00E+00 1.35E+04 CE-144 1.82E+02 7.55E+01 9.80E+00 0.00E+00 4.51E+01 0.00E+00 4.59E+04 PR-143 6.28E+00 2.51E+00 3.13E-01 0.00E+00 1.46E+00 0.00E+00 2.07E+04 PR-144 2.06E-02 8.44E-03 1.05E-03 0.00E+00 4.84E-03 0.00E+00 2.27E-05 ND-147 4.50E+00 4.89E+00 2.93E-01 0.00E+00 2.87E+00 0.00E+00 1.76E+04 W-187 3.22E+02 2.62E+02 9.19E+01 0.00E+00 0.00E+00 0.00E+00 7.10E+04 NP-239 3.98E-02 3.75E-03 2.08E-03 0.00E+00 1.18E-02 0.00E+00 6.03E+02 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-57 0.00E+00 1.25E+02 2.10E+02 0.00E+00 0.00E+00 0.00E+00 2.33E+03 SR-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-97 4.36E-02 1.08E-02 3.95E-03 0.00E+00 1.27E-02 0.00E+00 2.58E+02 CD-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SN-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-134 3.46E+01 2.22E+01 2.32E+01 2.84E+01 2.12E+02 0.00E+00 1.28E+00 CE-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HG-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 21 of 145 Revision 6

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

(AiT) mrem/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.81E-01 1.81E-01 1.81E-01 1.81E-01 1.81E-01 1.81E-01 BE-7 4.77E-01 8.08E-01 5.33E-01 0.00E+00 7.96E-01 0.00E+00 4.52E+01 NA-24 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 P-32 6.98E+07 3.27E+06 2.69E+06 0.00E+00 0.00E+00 0.00E+00 1.93E+06 CR-51 0.00E+00 0.00E+00 4.86E+00 2.70E+00 7.37E-01 4.92E+00 2.58E+02 MN-54 0.00E+00 4.20E+03 1.12E+03 0.00E+00 1.18E+03 0.00E+00 3.53E+03 MN-56 0.00E+00 1.31E+02 2.96E+01 0.00E+00 1.59E+02 0.00E+00 1.90E+04 FE-55 4.55E+04 2.42E+04 7.48E+03 0.00E+00 0.00E+00 1.37E+04 4.47E+03 FE-59 6.53E+04 1.06E+05 5.27E+04 0.00E+00 0.00E+00 3.07E+04 1.10E+05 CO-58 0.00E+00 4.20E+02 1.29E+03 0.00E+00 0.00E+00 0.00E+00 2.45E+03 CO-60 0.00E+00 1.23E+03 3.64E+03 0.00E+00 0.00E+00 0.00E+00 6.84E+03 NI-63 6.85E+04 3.67E+03 2.33E+03 0.00E+00 0.00E+00 0.00E+00 2.47E+02 NI-65 2.83E+02 2.66E+01 1.55E+01 0.00E+00 0.00E+00 0.00E+00 3.26E+03 CU-64 0.00E+00 9.05E+01 5.47E+01 0.00E+00 2.19E+02 0.00E+00 4.25E+03 ZN-65 1.55E+05 4.12E+05 2.56E+05 0.00E+00 2.59E+05 0.00E+00 7.23E+04 ZN-69 4.94E+02 7.14E+02 6.60E+01 0.00E+00 4.33E+02 0.00E+00 4.50E+04 BR-83 0.00E+00 0.00E+00 5.67E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-84 0.00E+00 0.00E+00 6.56E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-85 0.00E+00 0.00E+00 3.02E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 1.06E+05 6.50E+04 0.00E+00 0.00E+00 0.00E+00 6.80E+03 RB-88 0.00E+00 3.00E+02 2.08E+02 0.00E+00 0.00E+00 0.00E+00 1.47E+01 RB-89 0.00E+00 1.85E+02 1.64E+02 0.00E+00 0.00E+00 0.00E+00 1.61E+00 SR-89 3.63E+04 0.00E+00 1.04E+03 0.00E+00 0.00E+00 0.00E+00 1.41E+03 SR-90 4.68E+05 0.00E+00 1.19E+05 0.00E+00 0.00E+00 0.00E+00 6.30E+03 SR-91 6.60E+02 0.00E+00 2.49E+01 0.00E+00 0.00E+00 0.00E+00 1.46E+03 SR-92 2.48E+02 0.00E+00 9.96E+00 0.00E+00 0.00E+00 0.00E+00 4.70E+03 Y-90 8.79E+00 0.00E+00 2.35E-01 0.00E+00 0.00E+00 0.00E+00 2.50E+04 Y-91M 8.17E-02 0.00E+00 2.97E-03 0.00E+00 0.00E+00 0.00E+00 1.60E+02 Y-91 1.29E+02 0.00E+00 3.44E+00 0.00E+00 0.00E+00 0.00E+00 1.71E+04 Y-92 7.70E-01 0.00E+00 2.20E-02 0.00E+00 0.00E+00 0.00E+00 2.22E+04 Y-93 2.44E+00 0.00E+00 6.69E-02 0.00E+00 0.00E+00 0.00E+00 3.63E+04 ZR-95 2.10E+00 4.62E-01 4.11E-01 0.00E+00 6.62E-01 0.00E+00 4.82E+02 ZR-97 1.27E-01 1.83E-02 1.08E-02 0.00E+00 2.63E-02 0.00E+00 2.77E+03 NB-95 5.75E+00 2.24E+00 1.60E+00 0.00E+00 2.10E+00 0.00E+00 4.14E+03 MO-99 0.00E+00 1.31E+02 3.23E+01 0.00E+00 2.79E+02 0.00E+00 1.08E+02 TC-99M 1.99E-02 3.89E-02 6.46E-01 0.00E+00 5.66E-01 1.98E-02 2.22E+01 TC-101 2.30E-02 2.41E-02 3.06E-01 0.00E+00 4.11E-01 1.27E-02 7.66E-02 RU-103 1.48E+02 0.00E+00 5.67E+01 0.00E+00 3.72E+02 0.00E+00 3.82E+03 RU-105 1.30E+01 0.00E+00 4.73E+00 0.00E+00 1.15E+02 0.00E+00 8.50E+03 RU-106 2.36E+03 0.00E+00 2.95E+02 0.00E+00 3.19E+03 0.00E+00 3.68E+04 AG-110M 5.24E+02 3.54E+02 2.83E+02 0.00E+00 6.59E+02 0.00E+00 4.21E+04 SB-122 5.80E+01 8.56E-01 1.70E+01 7.43E-01 0.00E+00 2.36E+01 4.46E+03 SB-124 6.55E+02 8.50E+00 2.29E+02 1.44E+00 0.00E+00 3.63E+02 4.09E+03 SB-125 4.22E+02 3.25E+00 8.85E+01 3.91E-01 0.00E+00 2.35E+02 1.01E+03 IPEC ODCM Page 22 of 145 Revision 6

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

(AiT) mrem/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 3.81E+03 1.03E+03 5.08E+02 1.07E+03 0.00E+00 0.00E+00 3.68E+03 TE-127M 9.67E+03 2.60E+03 1.15E+03 2.31E+03 2.76E+04 0.00E+00 7.83E+03 TE-127 1.58E+02 4.25E+01 3.38E+01 1.09E+02 4.48E+02 0.00E+00 6.15E+03 TE-129M 1.63E+04 4.55E+03 2.53E+03 5.25E+03 4.78E+04 0.00E+00 1.99E+04 TE-129 4.48E+01 1.25E+01 1.06E+01 3.20E+01 1.31E+02 0.00E+00 2.79E+03 TE-131M 2.41E+03 8.33E+02 8.86E+02 1.71E+03 8.06E+03 0.00E+00 3.38E+04 TE-131 2.78E+01 8.46E+00 8.26E+00 2.12E+01 8.40E+01 0.00E+00 1.46E+02 TE-132 3.38E+03 1.50E+03 1.81E+03 2.18E+03 1.39E+04 0.00E+00 1.51E+04 I-130 6.28E+01 1.27E+02 6.54E+01 1.40E+04 1.90E+02 0.00E+00 5.94E+01 I-131 3.70E+02 3.72E+02 2.12E+02 1.23E+05 6.11E+02 0.00E+00 3.31E+01 I-132 1.72E+01 3.16E+01 1.45E+01 1.47E+03 4.84E+01 0.00E+00 3.72E+01 I-133 1.27E+02 1.58E+02 5.96E+01 2.93E+04 2.63E+02 0.00E+00 6.35E+01 I-134 9.02E+00 1.67E+01 7.70E+00 3.85E+02 2.56E+01 0.00E+00 1.11E+01 I-135 3.77E+01 6.78E+01 3.21E+01 6.00E+03 1.04E+02 0.00E+00 5.16E+01 CS-134 5.15E+04 8.44E+04 1.78E+04 0.00E+00 2.62E+04 9.39E+03 4.55E+02 CS-136 5.17E+03 1.42E+04 9.19E+03 0.00E+00 7.56E+03 1.13E+03 4.99E+02 CS-137 7.19E+04 6.88E+04 1.02E+04 0.00E+00 2.24E+04 8.07E+03 4.31E+02 CS-138 5.01E+01 6.97E+01 4.42E+01 0.00E+00 4.90E+01 5.28E+00 3.21E+01 BA-139 9.34E+00 4.99E-03 2.71E-01 0.00E+00 4.35E-03 2.93E-03 5.39E+02 BA-140 1.87E+03 1.64E+00 1.09E+02 0.00E+00 5.35E-01 9.79E-01 9.50E+02 BA-141 4.51E+00 2.53E-03 1.47E-01 0.00E+00 2.19E-03 1.48E-02 2.57E+00 BA-142 1.97E+00 1.42E-03 1.10E-01 0.00E+00 1.15E-03 8.35E-04 2.57E-02 LA-140 2.16E+00 7.55E-01 2.54E-01 0.00E+00 0.00E+00 0.00E+00 2.10E+04 LA-142 1.12E-01 3.57E-02 1.12E-02 0.00E+00 0.00E+00 0.00E+00 7.08E+03 CE-141 4.65E+00 2.32E+00 3.45E-01 0.00E+00 1.02E+00 0.00E+00 2.90E+03 CE-143 8.19E-01 4.44E+02 6.44E-02 0.00E+00 1.86E-01 0.00E+00 6.51E+03 CE-144 2.44E+02 7.64E+01 1.30E+01 0.00E+00 4.23E+01 0.00E+00 1.99E+04 PR-143 8.40E+00 2.52E+00 4.17E-01 0.00E+00 1.37E+00 0.00E+00 9.06E+03 PR-144 2.76E-02 8.53E-03 1.39E-03 0.00E+00 4.51E-03 0.00E+00 1.84E+01 ND-147 5.96E+00 4.83E+00 3.74E-01 0.00E+00 2.65E+00 0.00E+00 7.65E+03 W-187 4.08E+02 2.42E+02 1.08E+02 0.00E+00 0.00E+00 0.00E+00 3.40E+04 NP-239 5.15E-02 3.70E-03 2.60E-03 0.00E+00 1.07E-02 0.00E+00 2.74E+02 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-57 0.00E+00 1.15E+02 2.33E+02 0.00E+00 0.00E+00 0.00E+00 9.43E+02 SR-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-97 5.55E-02 1.00E-02 4.68E-03 0.00E+00 1.11E-02 0.00E+00 3.09E+03 CD-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SN-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-134 4.31E+01 1.94E+01 2.59E+01 3.41E+01 1.80E+02 0.00E+00 1.97E+02 CE-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HG-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 23 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 2-4 Bio-Accumulation Factors for Liquid Effluent Isotopes (pCi/kg per pCi/liter)

Freshwater Saltwater l Freshwater Saltwater ISOTOPE Fish Invertebratesl ISOTOPE Fish Invertebrates BFi BIi l BFi BIi

l------------------------------------

H-3 9.000E-01 9.300E-01 l TE-125M 4.000E+02 1.000E+02 BE-7 2.000E+00 2.000E+02 l TE-127M 4.000E+02 1.000E+02 NA-24 1.000E+02 1.900E-01 l TE-127 4.000E+02 1.000E+02 P-32 1.000E+05 3.000E+04 l TE-129M 4.000E+02 1.000E+02 CR-51 2.000E+02 2.000E+03 l TE-129 4.000E+02 1.000E+02 MN-54 4.000E+02 4.000E+02 l TE-131M 4.000E+02 1.000E+02 MN-56 4.000E+02 4.000E+02 l TE-131 4.000E+02 1.000E+02 FE-55 1.000E+02 2.000E+04 l TE-132 4.000E+02 1.000E+02 FE-59 1.000E+02 2.000E+04 l I-130 1.500E+01 5.000E+01 CO-58 5.000E+01 1.000E+03 l I-131 1.500E+01 5.000E+01 CO-60 5.000E+01 1.000E+03 l I-132 1.500E+01 5.000E+01 NI-63 1.000E+02 2.500E+02 l I-133 1.500E+01 5.000E+01 NI-65 1.000E+02 2.500E+02 l I-134 1.500E+01 5.000E+01 CU-64 5.000E+01 1.700E+03 l I-135 1.500E+01 5.000E+01 ZN-65 2.000E+03 5.000E+04 l CS-134 2.240E+02 2.240E+02 ZN-69 2.000E+03 5.000E+04 l CS-136 2.240E+02 2.240E+02 BR-83 4.200E+02 3.100E+00 l CS-137 2.240E+02 2.240E+02 BR-84 4.200E+02 3.100E+00 l CS-138 2.240E+02 2.240E+02 BR-85 4.200E+02 3.100E+00 l BA-139 4.000E+00 1.000E+02 RB-86 2.000E+03 1.700E+01 l BA-140 4.000E+00 1.000E+02 RB-88 2.000E+03 1.700E+01 l BA-141 4.000E+00 1.000E+02 RB-89 2.000E+03 1.700E+01 l BA-142 4.000E+00 1.000E+02 SR-89 3.000E+01 2.000E+01 l LA-140 2.500E+01 1.000E+03 SR-90 3.000E+01 2.000E+01 l LA-142 2.500E+01 1.000E+03 SR-91 3.000E+01 2.000E+01 l CE-141 1.000E+00 6.000E+02 SR-92 3.000E+01 2.000E+01 l CE-143 1.000E+00 6.000E+02 Y-90 2.500E+01 1.000E+03 l CE-144 1.000E+00 6.000E+02 Y-91M 2.500E+01 1.000E+03 l PR-143 2.500E+01 1.000E+03 Y-91 2.500E+01 1.000E+03 l PR-144 2.500E+01 1.000E+03 Y-92 2.500E+01 1.000E+03 l ND-147 2.500E+01 1.000E+03 Y-93 2.500E+01 1.000E+03 l W-187 1.200E+03 3.000E+01 ZR-95 3.300E+00 8.000E+01 l NP-239 1.000E+01 1.000E+01 ZR-97 3.300E+00 8.000E+01 l K-40 0.000E+00 0.000E+00 NB-95 3.000E+02 1.000E+02 l CO-57 5.000E+01 1.000E+03 MO-99 1.000E+01 1.000E+01 l SR-85 0.000E+00 0.000E+00 TC-99M 1.500E+01 5.000E+01 l Y-88 0.000E+00 0.000E+00 TC-101 1.500E+01 5.000E+01 l NB-94 3.000E+02 1.000E+02 RU-103 1.000E+01 1.000E+03 l NB-97 3.000E+02 1.000E+02 RU-105 1.000E+01 1.000E+03 l CD-109 0.000E+00 0.000E+00 RU-106 1.000E+01 1.000E+03 l SN-113 0.000E+00 0.000E+00 AG-110M 2.300E+00 5.000E+03 l BA-133 0.000E+00 0.000E+00 SB-122 1.000E+00 3.000E+02 l TE-134 4.000E+02 1.000E+02 SB-124 1.000E+00 3.000E+02 l CE-139 0.000E+00 0.000E+00 SB-125 1.000E+00 3.000E+02 l HG-203 0.000E+00 0.000E+00 Bio-Accumulation Factors and DFi's for Noble Gases = 0 IPEC ODCM Page 24 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Releases - General Information 3.1.1 A completed and properly authorized Airborne Radioactive Waste Release Permit shall be issued prior to the release of airborne activity from the waste gas holding system, containment purge, or any other batch release.

3.1.2 Since Indian Point is a two unit site, the derived instantaneous Ci/sec limits for each unit, (Section 3.2) were derived from an actual site limit (Appendix I). The time-average limits are "per reactor", and applicable to each unit.

3.1.3 During Modes 4 through 6, there is no flowpath for a release from the Condenser Air Ejector. During these intervals, when there is no actual release pathway, the monthly grab sample described in RECS D3.2.1 is not required.

3.1.4 During normal plant operation (without a primary to secondary leak), almost all gaseous releases are through the main Plant Vent. A negligible amount may be identified in other pathways (see Appendix C).

In the event of extended operation with a primary to secondary leak, low level releases are expected from both the blowdown flash tank vent and condenser air ejector. However, the limits on steam generator leakage are much more restrictive than those for effluent releases. Therefore, allocation of portions of the allowable release rate to these various release points during routine operation is not warranted.

If, on the other hand, the instantaneous release rate is being considered for the Plant Vent, then ALL release points should be considered when establishing alarm setpoints, per ODCM Part II, Section 1.

3.1.5 For releases that are expected to continue for periods over two days, a new release permit will normally be issued each day.

A containment purge permit may be closed, with the release reclassified as continuous building ventilation, when activity in containment is sufficiently reduced to that level which, if released for 31-days, would remain BELOW the dose projection limits.

However, when plant conditions change, such that releases to containment are likely, a new permit should be evaluated.

3.1.6 Assurance that the combined gaseous releases from Units 2 and 3 do not exceed limits of Section 3.2.1 is provided by administrative controls for both units. These controls include apportionment of the 10CFR20 limitations and back-calculating radiation monitor setpoints accordingly. These calculations are discussed in Appendix I.

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ODCM Part II - Calculational Methodologies 3.1.7 By mutual agreement with units 2 and 3 Shift Supervisors, one unit can reduce or eliminate discharges for a period of time to allow the other unit to use the full site permissible discharge rate, or a specific portion thereof, for unique releases that may require the site limit for release rate. To better control these evolutions, written agreement to the apportionment is generally kept with each units CRS and included on applicable permits for the duration.

3.1.8 Conservative release rate limitations have been established to ensure compliance with 10CFR20, and to aid in controlling time average dose limits. The annual average release rate limit (Appendix I) shall normally be used for calculating limitations on discharge. If this limitation is unduly restrictive, other release rates may be allowed, per Appendix I, and summarized below:

Release Rate (Ci/sec) Permission Required Quarterly Average Site Operations Manager / designee Default Instantaneous General Manager Plant Operations (GMPO) / designee ODCM Instantaneous GMPO and Chemistry Manager / designee As described in Appendix I, the ODCM instantaneous limit provides a maximum release rate with an actual or suspected isotopic mixture, back-calculated from the actual 10CFR20 limit (500 mrem/yr for the site). The calculations for the use of this limit should be verified within the Chemistry department. The default interval in which to determine the proximity to this limit (uCi/sec or mrem/yr) is one hour or less.

3.1.9 Containment Pressure Reliefs Containment pressure reliefs occur frequently enough to be considered continuous releases. Grab samples of containment atmosphere are obtained periodically to ensure the use of accurate mixtures in effluent calculations. The containment noble gas monitors (R-42 for Unit 2 and R-12 for Unit 3) are used in conjuction with expected flow rates to determine a release rate. The effluent noble gas monitor in the plant vent is also used to verify total unit release rate remains below the current authorized limit.

3.1.10 Composite Particulate Samples Continuous building ventilation exhaust points are sampled continuously for Iodine and Particulate. Media is replaced weekly, with composite filters prepared for vendor lab analyses monthly.

3.1.11 Flow rate measurement for the Continuous Building Ventilation systems is typically obtained from the installed process monitor or nearby instrument. When the process flow rate instrument is OOS, estimates are performed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per the RECS, to allow appropriate quantification of continuous airborne effluent. The estimates are typically performed by summing the exhaust flow rates (or design flow rate) from any operable fans. Unit 3s PV flow may be estimated from a backup instrument.

Unit 3s Admin Bldg does NOT have a flow rate instrument (design flow of 12500 cfm is used). The process flow rate monitor surveillance requirements specified in the RECS are not applicable for the Unit 3 Admin Building.

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ODCM Part II - Calculational Methodologies 3.1.12 Gas Storage Tank Activity Limits The quantity of radioactivity in each gas storage tank is limited to 50,000 Ci of noble gas, Xenon-133 equivalent, per RECS D3.2.6. The source of this requirement is NUREG 0133 (Section 5.6.1) for both units. However, the parameters used in the given equation are applied differently at each unit, as defined in the FSARs and summarized in the following discussion:

Unit 2:

(500mrem)

  • 3.15 E 7 sec/ yr Q133= = 29,761 Ci (1E 6 Ci / Ci )(294mrem m 3 / Ci yr )(1.81E 3 sec/ m 3 )

Where; 294 mrem-m3/Ci-yr = the Xe-133 WB dose factor, RG 1.109, table B-1 (K).

1.81E-3 sec/m3 = Design Basis Accident X/Q from Indian Point 2 FSAR An actual curie limit is calculated by substituting the actual mixture K eff into the equation above. For example, the Keff for the accident mix computed using Table 14.2-5 of the FSAR is 476 mrem-m3/Ci-yr. Thus, the actual activity limit (for an expected mixture of radionuclides, not just Xe-133) is:

(500mrem)

  • 3.15 E 7 sec/ yr Qmixture= = 18,300 Ci (1E 6 Ci / Ci )(476 mrem m 3 / Ci yr )(1.81E 3 sec/ m 3 )

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

As demonstrated above, the setpoints calculated from NUREG 0133 modeling assume Xe-133 equivalent and no tank interconnections (29,761 Ci of Xe-133 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 6,000 Ci each. This value is based on the original RECS required 29,761 curies of Xe-133 equivalent, divided into 4 large and all 6 small gas decay tanks. Given the actual atmospheric volume of the tanks (525 ft 3 for each large and 40 ft3 for each small), the total volume is approximately 4.5 tanks:

29,761 6,000 Ci Xe-133 Equivalent 4 .5 The RECS required gas storage tank radiation monitor (R-50), is therefore set to alarm at 6,000 curies. Warn setpoints are established by procedure, usually with consideration for measured tank contents and anticipated release rate.

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ODCM Part II - Calculational Methodologies 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 curie limit in a tank is assured if the following inequality holds:

[A]m 14.7 (Q) or [A]eq 14.7 (Q133)

(14.7 + P)V (14.7 + P)V Where:

[A]m total measured depressurized sample concentration (Ci/cc)

[A]eq Xe-133 equivalent measured depressurized sample concentration (Ci/cc)

V tank volume (cc) P tank pressure (psig)

Q activity limit for selected mix (Ci) Q133 dose equivalent Xe133 limit(Ci)

Unit 3:

(500mrem)

  • 3.15E 7 sec/ yr Qit= = 50,000 Ci (1E 6Ci / Ci )(294mrem m3 / Ci yr )(1.03E 3 sec/ m3 )

Where; Ki = 294 mrem-m3/Ci-yr, Xe-133 equivalent Table B-1 (RG 1.109)

X/Q = 1.03 x 10-3 sec/m3, Indian Point 3 FSAR This limit assumes 100% Xe-133 as per NUREG 0133. Utilizing the Ki from an expected mixture during RCS degasification (787 mrem-m3 per uCi-yr), the gas tank conservative administrative limit should becomes:

(500mrem)

  • 3.15E 7 sec/ yr Qit= = 19,400 Ci (1E 6Ci / Ci)(787 mrem m 3 / Ci yr )(1.03E 3 sec/ m 3 )

There are two methods available to ensure that the activity in the gas storage tank is within the conservative administrative limit:

1.94E 4 1E 6Ci / Ci 1.17 E 2 Ci / cc 3 164.7 psia 525 ft 2.83E 4 cc / ft 3 14.7 psia

1. The total gaseous activity will normally be limited to less than 117 Ci/cc. If this concentration limit is exceeded, then the contents of the tank will be monitored and actions taken to ensure the 19,400 curie per tank limit is not exceeded.
2. The waste gas line monitor (R-20) reads in Ci/cc. It allows for control of waste gas tank curie content by limiting the input concentration to 117 Ci/cc, thereby limiting the curies to 19,400.

IPEC ODCM Page 28 of 145 Revision 6

ODCM Part II - Calculational Methodologies Large gas decay tanks on fill and CVCS tanks (which are indicative of the gas mixture in or from the reuse system) are continuously monitored for H2 and O2 through in-line instrumentation. With either in-line instrument out of service, a grab sample of the tank on receipt shall be taken daily, unless in degassing operation, when the periodicity is every four hours.Other primary system tank cover gases can be manually directed through these instruments for individual samples.

Gas releases may also occur from the gas space atop liquid holdup tanks. The basis for assuring these tanks comply with the curie limits for noble gas is Technical Specification 3.4.16, which limits Reactor Coolant to 1 Ci/gm Dose Equivalent Iodine-131. Using the assumptions discussed in each units FSAR, the potential total curies of noble gas in the liquid holdup tanks is limited to less than the conservative limit for the Gas Storage Tanks.

3.1.13 The activity released via the blowdown flash tank vent is determined by obtaining the steam generator blowdown activity (tritium, noble gas, and iodine), partitioned per Regulatory Guide 1.42 Interim Licensing Policy On As Low As Practicable for Gaseous Radioiodine Releases from Light Water Cooled Nuclear Power Reactors (from NUREG 0472, Rev3, DRAFT 6, TABLE 3.3-13), or Reference 4, An Evaluation to Demonstrate the Compliance of the Indian Point Reactors with the Design Objectives of 10CFR50, Appendix I.

3.1.14 Studies and measurements performed by the NY State Department of Health (1981 to 1982) determined that approximately 9.6 curies of Carbon-14 were released from IPEC annually. Recent EPRI studies have resulted in a model to apply plant-specific data to better calculate a curie value for airborne C-14 effluent. Using this updated model, IPECs airborne C-14 releases are projected to be 10.5 Curies per year, with 26% as CO2. Offsite dose resulting from these releases are calculated in accordance with the methodology in Reg. Guide 1.109, and discussed in detail in Appendix K.

Curies released and offsite dose from airborne C-14 effluent is reported separately from other, more common isotopes, to prevent confusion, loss of relevance of the more common isotopes, and to preserve historical trends.

3.1.15 The Unit 3 Liquid Waste Monitor Tanks have an airborne release pathway. The original plant design limited the gases through this pathway by reducing the entrained gases to less than 2E-3 Ci/ml. The removal of the CVCS gas stripper under modification 86-3-122 CVCS requires the quantification of these gases when the entrained gaseous activity in the Monitor Tank inlet exceeds 2E-3 Ci/ml. No action is required if the inlet noble gas concentration is less than 2E-3 Ci/ml. This gas release will be quantified by calculating the difference (in Ci's) between the gaseous activity added to the tank and the gaseous activity present in the effluent release sample. This difference will be quantified as an airborne ground level batch release, using a specifically determined ground level dispersion constant (Section 3.5.3).

A separate release permit evaluating this release is not required prior to release.

Calculation of this rate of release is not required, however the time average dose contribution shall be calculated and controlled per Sections 3.3 and 3.4 of the ODCM.

Section 3.6 provides additional detail relative to the finite cloud correction assumptions for this pathway.

Unit 2s Waste Distillate Storage Tanks are vented inside the Unit 1 facility, so there is no similar airborne release pathway from these tanks.

IPEC ODCM Page 29 of 145 Revision 6

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

3.1.17 Airborne releases from the Steam Generator Safety or Atmospheric Dump Valves can occur during a Primary to Secondary leak. Tritium, Noble Gas, and Iodine effluent doses are determined using a source term activity (Main Steam or Steam Generator Blowdown), an Iodine partition factor (per Section 3.1.13), and a release rate, determined from Engineering Design Calculation 187 (Steam Generator Atmospherics), or design flowrate (from Steam Generator Safeties) at specific pressures in the Steam Generator.

3.1.18 Other release pathways resulting from Primary to Secondary leakage include the steam driven auxiliary feed pump vent, the gland seal exhaust vent, the air ejector vent, and the Feed Water heater flash tank vent. Offsite doses from these or other abnormal airborne release points are calculated by obtaining the release rate (from system descriptions and/or steam tables corrected for system pressure, as applicable) and source term activity (eg. Main Steam , Reactor Coolant, or best estimate) for Tritium, Noble Gas, and Iodine, partitioned as per Section 3.1.13.

3.1.19 The Unit 3 Monitor Tank vents, both unit Condenser Air Ejector, and the Gland Seal Exhaust points are ground level releases. Unless otherwise designated, other release points are considered mixed mode, per Section 3.6.

3.2 Gaseous Effluent Dose Calculation Requirements 3.2.1 RECS D3.2.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site at or beyond the site boundary shall be limited to:

a) For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin; and b) For Iodine 131, H-3, and radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

These are SITE limits and normally apportioned appropriately between the units to simplify assurance of compliance with the RECS. The methodologies for performing these calculations are discussed in Sections 3.3.1 and 3.3.2, respectively.

3.2.2 RECS Section D3.2.2 requires that the air dose due to noble gas released in gaseous effluents from each reactor unit at or beyond the site boundary shall be limited to:

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

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

The methodology for calculating these doses is discussed in Section 3.3.3.

IPEC ODCM Page 30 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.2.3 RECS Section D3.2.3 requires that the dose to a member of the general public from Iodine 131, Tritium, and radionuclides in particulate form (half-lives > 8 days) in gaseous effluents released from each reactor unit shall be limited to:

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

Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined at least once every 31 days.

The methodology for calculating these doses is discussed in Section 3.3.4.

If either of the air dose or iodine/particulate dose cumulative limits is exceeded by a factor of two or more, then a cumulative dose evaluation is required from all contributions of direct radiation at the site boundary per RECS D3.4.1.

3.2.4 RECS D3.2.4 requires that for each reactor unit, the appropriate portions of the gaseous radwaste treatment system shall be used to reduce radioactive effluents in gaseous waste prior to their discharge when projected gaseous effluent air dose at the site boundary when averaged over 31 days, would exceed 0.2 mrad for gamma radiation or 0.4 mrad for beta radiation.

RECS D3.2.4 requires that for each reactor unit, the appropriate portions of the The appropriate portions of the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous releases when the projected doses averaged over 31 days, would exceed 0.3 mrem to any organ (at nearest residence).

Dose due to gaseous releases from the site shall be calculated at least once every 31 days.

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

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

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

3.3.1.1 The equations developed in this section are used to meet the calculational requirements of paragraph 3.2.1. The magnitude of this pathway is the same for all age groups so there is no critical group. The site release rate is split to 50% per each unit, in terms of uCi/sec. Converted to actual mrem/yr dose rate, Unit 2s portion is 44.6%, with Unit 3 being allocated 55.4% (Unit 3 is slightly closer to the site boundary where dose rates are calculated).

IPEC ODCM Page 31 of 145 Revision 6

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

A calculation showing the relationship between Ci/sec and dose rates from Units 2 and 3 is shown in Appendix I. The equations for calculating the dose rate limitations are obtained from NUREG 0133 (Ref. 1, Section 5.2.1). Utilizing the above assumptions, these equations reduce to the following which are to be summed for each nuclide, i. (Note that these are default unit portions of a site release rate limit. The entire site limit can be applied to any one site, when required, per Section 3.1 and Appendix I).

() < unit specific mrem/yr whole body limit

( + 1.1) < unit specific skin limit, mrem/yr Where:

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per Ci/m3 (unit-specific finite cloud correction included, per Table 3-4).

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per Ci/m3, per Table 3-5.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per Ci/m3 (unit-specific finite cloud correction included, per Table 3-6).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per Ci/m3, per Table 3-7.

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

(X/Q) = For all vent releases, the highest calculated annual averaged relative concentration at the critical receptor (at a unit-specific distance and direction, in sec/m3, as shown on Page 1 of Appendix I).

The Ki, Li, Mi, and Ni factors were obtained from Table B-1 of Regulatory Guide 1.109 and are included in this document as Tables 3-4, 3-5, 3-6, and 3-7 respectively. The gamma dose factors (Ki and Mi) have a unit-specific finite cloud correction factor included, as discussed in Sections 3.5 and 3.6.

Unit specific dose rate limits, as stated in Appendix I are as follows:

Unit 2: mrem/yr whole body = 234, skin limit = 1194 mrem/yr Unit 3: mrem/yr whole body = 266, skin limit = 1806 mrem/yr IPEC ODCM Page 32 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.3.1.2 These equations can also be expressed in the following manner:

()( )(/) = mrem/yr dose to whole body

( + 1.1)(/)( ) = mrem/yr dose to skin Where:

t = The release rate of all noble gases summed together in Ci/sec, i.e., the sum of all i.

K (1/ ) ( ) ()

L (1/ ) ()

M (1/ ) ()

N (1/ ) ()

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

3.3.2 Instantaneous Dose Rates - I-131, Part w/>8 day t1/2 , and H-3 The equation developed in this section is used to meet the calculational requirements of RECS D3.2.1. The critical organ is considered to be the child thyroid as stated in the RECS bases (BD3.2.1). Different dispersion factors are applied to the critical sector of the unrestricted area boundary for units 2 and 3. Therefore, while 50% of the site release limit (in Ci/sec) is applied to each unit, 32.8% of the limit is applied to Unit 2 and 67.2% to Unit 3 (per Appendix I). The equation for calculating the dose rate limitation is abbreviated from that shown in NUREG 0133 (Ref. 1, Section 5.2.1, Pg. 25) in that ground plane and milk pathways are not considered for this dose rate determination, due to insignificant contribution compared to the inhalation pathway.

Utilizing the above assumptions, the dose rate equation reduces to the following:

( * (X/Q) *Q) must be less than the unit-specific mrem/yr limit Where:

Unit-specific limits are 497 mrem/yr for Unit 2 and 1003 mrem/yr for Unit 3.

Pi = The dose parameter for radionuclides other than noble gases for the inhalation pathway in mrem/yr per Ci/m3. These parameters (per Section 3.3.2.1) are calculated separately for each isotope, age group, and organ.

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ODCM Part II - Calculational Methodologies i = The release rate of radionuclide 131 and particulates, i, in gaseous effluents for all release points in Ci/sec.

X/Q = The unit-specific annual average dispersion parameter for the inhalation pathway at the controlling location due to all vent releases, per Section 3.5 and Appendix I.

3.3.2.1 Calculation of Pi(in): Inhalation Dose Factor Pi (inhalation) = K' (BR) DFAi (mrem/yr per Ci/m3)

Where:

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

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

3.3.3 Time Average Dose - Noble Gas Release 3.3.3.1 The equations in this section are used to meet the calculational requirements of RECS D3.2.2. All noble gas releases at IPEC are assumed to be mixed mode unless indicated otherwise. Because the limits are in measured air dose (mrad), the magnitude of a measured effect is the same for all age groups.

Dispersion parameters are discussed in Section 3.5.

3.3.3.2 Equations for calculating the air dose limitations are obtained from NUREG 0133 (Ref. 1, Section 5.3). The doses are evaluated at the unrestricted area boundary in the worst meteorological sector (a unit-specific location identified in Appendix I). These equations reduce to the following:

~

gamma air mrad 3.17 E 8* Mi [(X/Q) (Qi) (x/q) ( ~ q i) (x/q mt ) ( ~

q i mt )]

i

~

beta air mrad 3.17 E 8

  • Ni [(X/Q) (Qi) (x/q) ( ~

q i) (x/q mt ) ( ~

q i mt )]

i Where:

Air dose limits are as follows:

Any Calendar Quarter Any Calendar Year Gamma Air 5 mrad 10 mrad Beta Air 10 mrad 20 mrad IPEC ODCM Page 34 of 145 Revision 6

ODCM Part II - Calculational Methodologies (X/Q) =The highest calculated annual average relative concentration for the unrestricted area boundary at the controlling sector for long term releases (greater than 500 hrs/yr or 150 hrs/qtr or as noted in 3.1.16), per Appendix I.

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

(x/qmt)=The relative concentration for the unrestricted area boundary for ground level releases from Unit 3 Monitor Tanks at the critical receptor, in sec/m3, per Section 3.5.3.

Mi = The weighted air dose factor due to gamma emission for each identified noble gas radionuclide in mrad/yr per Ci/m3.

This factor is unit-specific, per Table 3-6.

Ni = The weighted air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per Ci/m3.

q~i mt = The total releases of noble gas radionuclides in Monitor Tank vents in Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.

q~i = The total release of noble gas radionuclides in gaseous effluents, i, for short term releases (equal to or less than 500 hrs/yr or 150 hrs/qtr and not random as defined in NUREG 0133, Section 3.3) from all vents, in Ci. Releases shall be cumulative 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 hrs/yr or 150 hrs/qtr or as noted in 3.1.16) from all vents in Ci.

Releases shall be cumulative over the calendar quarter or year as appropriate.

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

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

3.3.4 Time Averaged Dose - Radioiodine 131, Part w/t1/2 >8 days, and Tritium 3.3.4.1 The equations in this section are used to meet the calculational requirements of RECS D3.2.3.

IPEC ODCM Page 35 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.3.4.2 The pathways considered in this analysis are as follows:

Pathway Receptor Inhalation, Ground Plane, Primary, Nearest Resident, per App I Vegetative Ingestion Inhalation, Ground Plane, Secondary Receptor at 5 mile, Vegatative, Cow-Milk applied per the annual Land Use Census Ingestion The land use census identifies a high degree of commercial, industrial, and residential land usage in the area, and as such, the meat ingestion pathway is not considered.

Doses from the cow-milk pathway are included only if the applicable annual census has defined the pathway applicable. The methodology in nonetheless included here.

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

~

(3.17 E - 08 ) * (Ri (W Qi w ~ qi ) 7.5 mrem in a calendar quarter i

~

(3.17 E - 08 ) * (Ri (W Qi w ~ qi ) 15 mrem in a calendar year i

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 as defined in Section 3.1.16, in Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.

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

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

w = The vent dispersion or deposition parameter for estimating the dose to an individual at the applicable receptor for short term releases as calculated as in Section 3.5 and defined in Section 3.1.16 and Appendix I.

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

Ri = The dose factor for each identified pathway, organ, and radionuclide, i, in m2 mrem/yr per Ci/sec or mrem/yr per Ci/m3. These dose factors are determined as described in Sections 3.3.4.5a-d.

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ODCM Part II - Calculational Methodologies 3.3.4.4 Utilizing the assumptions contained in Section 3.3.4.3, these equations for the nearest resident and the 5-mile cow secondary receptor reduce to the following:

~ ~

DN (3.17E- 8) [Ri (I) * [Wn (in) Qi wn (in) ~ qi] (Ri (G) Ri (V)) * [Wn (dep)Qi wn (dep) ~ qi))

i

~ ~

DS (3.17E - 8) [Ri (I) * [Ws (in) Qi ws (in) ~

qi] (Ri (G) Ri(c) Ri (V)) * [Ws (dep)Qi ws (dep) ~

qi))

i Where:

DN = total dose at the nearest residence, in mrem DS = total dose at the 5-mile cow secondary receptor, in mrem.

Wn(in) = The highest calculated annual average dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area, as defined in Appendix I.

wn(in) = The dispersion parameter Wn(in), corrected for short term releases, as defined in Appendix I.

Wn(dep)= The highest calculated annual average deposition parameter for the nearest residence in the unrestricted area, as defined in Appendix I, for all isotopes except Tritium, which uses the X/Q value instead (Wn(in)).

wn(dep)= The deposition parameter Wn(dep), corrected for short term releases, as defined in Appendix I.

Ws(in) = The highest calculated annual average dispersion parameter for the inhalation pathway at the 5-mile cow secondary receptor per Appendix I.

ws(in) = The dispersion parameter Ws(in), at the 5-mile cow secondary receptor, corrected for short term releases, as defined in Appendix I.

Ws(dep)= The highest calculated annual average deposition parameter for the 5-mile cow secondary receptor, as defined in Appendix I, for all isotopes except Tritium, which uses the X/Q value instead (Ws(in)).

ws(dep)= The deposition parameter Ws(dep), at the 5-mile cow secondary receptor, corrected for short term releases, as defined in Appendix I.

~

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

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

Ri (I): Inhalation pathway factor for each radionuclide, i, defined in Section 3.3.4.5.

Ri (G): Ground plane pathway factor for each radionuclide, i, defined in Section 3.3.4.5.

Ri (V): Vegetation pathway factor for each radionuclide, i, defined in Section 3.3.4.5.

Ri (C): Cow-Milk pathway factor for each radionuclide, i, defined in Section 3.3.4.5.

IPEC ODCM Page 37 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.3.4.5 Calculation of Dose Factors 3.3.4.5.a Calculation of Ri (I) (X/Q) Inhalation Pathway Factor Ri (I) (X/Q) = K'[(BR) a] [(DFAi) a] (mrem/yr per Ci/m3)

Where:

K' = Constant of unit conversion, 106 pCi/uCi (BR) a = Breathing rate of the receptor of age group (a) in m 3/yr.

(from Regulatory Guide 1.109, Table E-5)

Infant = 1400 (m3/yr) Child = 3700 (m3/yr) Adult/Teen = 8000 (m3/yr)

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

Child and infant inhalation dose factors are generally more restrictive, however, doses from each age group are calculated separately. The (DFAi)a values are listed in Tables 3-1a through 3-1d. The Ri values for the inhalation pathway are listed in Table 3-10a through 3-10d.

3.3.4.5.b Calculation of Ri(G)(D/Q) Ground Plane Pathway Factor K ' K ' ' (SF)(DFGi)(1 e ( kit ) ) m 2 mrem / yr Ri(G) ( D / Q )

Ki uCi / sec Where:

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

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

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

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

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

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

The values of DFGi were obtained from Table E-6 of Regulatory Guide 1.109 and are listed in Table 3-2. These values were used to calculate Ri(G), which is the same for all age groups and organs and is listed in Table 3-13.

IPEC ODCM Page 38 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.3.4.5.c Calculation of Ri(V)(D/Q) - Vegetation Pathway Factor For non-Tritium isotopes:

m 2 mrem / yr K ' (r )

Ri(V) ( D / Q ) (DFLi)a [(UaL)fL e ( kitL ) ( UaS)fg e ( kith ) ]

uCi / sec Yv(ki kw )

Where:

K' = Constant of conversion, 106 pCi/Ci r = Dimensionless correction factor for Iodine and Particulate from Table E-15 of Reg Guide 1.109: 0.2 for particulates, 1.0 for radioiodine DFLia = Reg Guide 1.109 dose factor for each nuclide, in mrem/pCi, for each age group.

UaL = Consumption rate of fresh leafy vegetation by the receptor in age group (a) in kg/yr.

-1 ki = Decay constant for the radionuclide, in sec UaS = Consumption rate of non-leafy vegetables by the receptor in age group (a) in kg/yr.

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

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

kw = Decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec -1 (corresponding to a 14 day half-life).

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

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

Yv = The vegetation area density in kg/m2.

The concentration of Tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri(V) is based on X/Q:

(RiV) (X/Q) = K'K"[(UaL)fL+(UaS)fg](DFLi)a (0.75)(0.5/H) (mrem/yr per Ci/m3)

Where:

K = A constant of unit conversion, 1000 gm/kg IPEC ODCM Page 39 of 145 Revision 6

ODCM Part II - Calculational Methodologies H = Absolute humidity of the atmosphere in gm/m 3 . This value may be considered as 8 gm/m3 (NUREG 0133, pg 27) in lieu of site specific information.

0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water DFLia for each age group is given in Tables 3-3a through 3-3d and Ri(V) values are listed in Table 3-11a through 3-11c.

Ri(V) Parameters Are From The Following Sources:

PARAMETER VALUE Reg Guide 1.109 Table R (dimensionless) 1.0 for iodines & 0.2 for part. E-15 (DFLi) a (mrem/pCi)

Each radionuclide E-11 to E-14 UaL (kg/yr) - infant 0 E-5

- child 26 E-5

- teen 42 E-5

- adult 64 E-5 UaS (kg/yr) - 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-15 tL (seconds) 8.6E4 (1 day) E-15 th (seconds) 5.18E6 (60 days) E-15 Yv (kg/m2) 2.0 E-15 IPEC ODCM Page 40 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.3.4.5.d Calculation of Ri(c)(D/Q) - Grass-Cow-Milk Pathway Factor (applied only as required by the Land Use Census) m 2 mrem / yr K (QF)( Uap)(Fm)(r )(DFLi)a fpfs (1 fpfs) (e ( kith ) )

Ri(c) (D/Q) e ( kitf )

uCi / sec ki kw Yp Ys Where:

K' = Constant of conversion, 106 pCi/Ci QF = Cow's consumption rate in kg/day (wet weight)

Uap= Receptor's milk consumption rate for age (a) in liters/yr.

Yp = Agricultural productivity by unit area of pasture grass in kg/m 2.

Ys = Agricultural productivity by unit area of stored feed in kg/m 2.

Fm = Stable element transfer coefficients in days/liters, Table 2-2.

r = Fraction of deposited activity retained on cow's feed grass.

(DFLi)a= The maximum organ ingestion dose for the radionuclide, I, for the receptor in age group (a) in mrem/pCi. Values are from Tables E-11 through E-14 of Regulatory Guide 1.109 and are listed in Tables 3-3a through 3-3d.

ki = Decay constant for the radionuclide in sec-1.

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).

tf = The transport time from pasture, to cow, to milk, to receptor in sec.

th = The transport time from pasture, to harvest, to cow, to milk, to receptor, in sec.

fp = Fraction of the year that the cow is on pasture.

fs = Fraction of the cow feed that is pasture grass while the cow is on pasture.

Note: The values of Ri (c) are listed in Table 3-12a-d.

The concentration of Tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Ri (c) is based on X/Q:

Ri (c) (X/Q) = K'K" (Fm) (QF) (Uap) (DFLi) a 0.75 (0.5/H) (mrem/yr per Ci/m3)

Where:

K" = A constant of unit conversion, 103 m/kg; IPEC ODCM Page 41 of 145 Revision 6

ODCM Part II - Calculational Methodologies H = Absolute humidity of the atmosphere in gm/m3; 0.75 = The fraction of total feed that is water; 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water; Other parameters and values are given above. The value of H may be considered as 8 grams/meter3 (NUREG 0133, PAGE 27) in lieu of site specific information.

Ri(c) Parameters Are Taken From The Following Sources:

PARAMETER VALUE TABLE R.G. 1.109 R (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Fm (days/liter) Each stable element E-1 Uap (liters/year) - infant 330 E-5

- child 330 E-5

- teen 400 E-5

- adult 310 E-5 (Dfli) a (mrem/pCi) Each radionuclide E-11 to E-14 Yp (kg/m2) 0.7 E-15 Ys (kg/m2) 2.0 E-15 tf (seconds) 1.73E5 (2 days) E-15 th (seconds) 7.78E6 (90 days) E-15 Qf (kg/day) 50 E-15 fs Assumed to be unity fp Assumed to be unity Stable Element Transfer data is listed in Table 3-2 (Reg Guide 1.109, Table E-1).

The (DFLi)a values for 4 age groups are given in Tables 3-3a through 3-3d.

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

3.4.1 Instantaneous Dose Rates - Noble Gas Releases Note: While true instantaneous rates and limits generally apply, a one hour average can be chosen as the defining interval for determining process radiation monitor response or release rate determinations.

3.4.1.1 This section describes the alternative calculational methods to meet the requirements of Section 3.2.1 and the calculational results per Section 3.3.1.

3.4.1.2 To determine an acceptable noble gas instantaneous release rate in Ci/sec, a standard isotopic mixture of noble gas is assumed. This isotopic mixture was measured for a mixture of isotopes typical of reactor coolant with exposed fuel.

This requirement is evaluated at the worst sector of the unrestricted area boundary. Based on this isotopic mixture, standard weighted values of K, L, M, and N is determined using the technique presented in paragraph 3.3.1.2, and the Ki, Li, Mi, and Ni values from Tables 3-4 through 3-7. The data and results of this calculation are shown in Table 3-8.

3.4.1.3 Utilizing the equations from Paragraph 3.3.1.2 and the values from Table 3-8, conservative IPEC maximum (site) release limits for all noble gases in Ci/sec are calculated in Appendix I, page 2.

The resulting calculations establish a default instantaneous noble gas release rate limit of 140,000 Ci/sec for the site, split equally between the units for conservativism. While both Units 2 and 3 originally apply the instantaneous limit at 70,000 Ci/sec, any one unit can use up to nearly 100% of the site limit, should it become necessary.

Generally, as these limits begin to apply, actual sample data is used to determine the true instantaneous limit associated with 10CFR20 requirements, for both whole body and skin dose rate, as shown in Appendix I.

3.4.1.4 For individual release rate determinations, alternate computer codes and/or a procedurally driven hand calculation template serve as back up methodologies should the primary computer method be inoperable. These methods comply with calculations in Section 3.3.

3.4.2 Instantaneous Dose Rates-I-131, Particulates w/t1/2 >8 days, & H-3 3.4.2.1 This section describes the alternative calculational method to meet the requirements of Section 3.2.1. The purposes of this method is to provide backup calculational techniques, both computer aided and hand calculated, which approximate section 3.3.2.

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ODCM Part II - Calculational Methodologies 3.4.2.2 To determine an acceptable iodine and particulate release rate, it is assumed that the limit on these releases shall be met if a) the total noble gas concentration in the VC is at least a factor of 20,000 more than the concentration of radioiodine and long lived particulates, or b) VC iodines and long lived particulates are less than 1E-7 Ci/cc.

Both these conditions have historically been the case, assuring that noble gas activity continues to be more limiting.

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

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

3.4.3.2 The values of Ki , Li , M i , and Ni for either units Plant Vent (PV) mixed mode releases, and the potential Unit 3 Monitor Tank (MT) ground plane releases are determined for each release using the dispersion parameter for the site boundary in the worst sector. The calculations are as follows:

PV Ki = Ki ( X / Q) PV and MT Ki = ( Ki ) ( X / Q ) MT PV Li = ( Li ) ( X / Q ) PV and MTLi = ( Li ) ( X / Q ) MT PV M i = ( Mi ) ( X / Q ) PV and MTMi = ( M i ) ( X / Q ) MT PV Ni = ( Ni ) ( X / Q ) MT and MTNi = ( Ni ) ( X / Q ) MT Where:

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per Ci/m3 (unit-specific finite cloud correction used).

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide in mrem/yr per Ci/m3.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per Ci/m3 (unit-specific finite cloud correction used).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per Ci/m3.

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ODCM Part II - Calculational Methodologies (X/Q)PV = The highest calculated annual average dispersion parameter for the noble gas pathway at the unrestricted area boundary, applicable to plant vent mixed mode releases, per Appendix I.

(X/Q)MT = The highest calculated annual average X/Q for ground level monitor tank noble gas release pathway, 5.00E-5 sec/m3.

3.4.3.3 Determine weighted average dose factors as follows:

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

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

PV Kt = [ Ki (Ci / Ct )]

PV Lt = [ Li (Ci / Ct )]

PV Mt = [Mi (Ci / Ct )]

PV Nt = [ Ni (Ci / Ct )]

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

Where:

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

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

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

3.4.3.4 Resultant doses are compared with limits as per 3.3.3. The sum of all releases in a calendar quarter or calendar year should be compared to the limits of Section 3.2.2 and 3.2.4 as appropriate for gamma air dose and beta air dose.

3.4.4 Time Averaged Dose-Iodine 131 and Particulates w/t1/2 days& H-3 3.4.4.1 This section describes the alternate methods of meeting the requirements of Paragraphs 3.2.3 and 3.2.4 and of implementing the calculational techniques presented in Section 3.3.4.

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ODCM Part II - Calculational Methodologies 3.4.4.2 If the primary computer method is inoperable, dose calculations can be performed by 1) an alternate computer code which complies with Section 3.3.4, using all identified Iodine and Particulate isotopes; or 2) hand calculations (via a formalized departmental procedure) which comply with Section 3.3.4.

3.4.4.3 Quarterly and annual Iodine, Particulate, and Tritium dose contributions are summed and compared to limits described in Section 3.2.3.

3.5 Calculation of Meteorological Dispersion Factors 3.5.1 For the purpose of these calculations, the site boundary was taken to be the unrestricted area boundary. The distances to the site boundary and nearest residents are shown in Table 3-9 for each of the 16 major compass sectors. Site boundary distances at IPEC are measured from the applicable units Plant Vent, while distances to the nearest resident in each of these sectors is measured from a common point, the Unit 1 superheater stack.

In the sectors where the Hudson River forms the site or exclusion area boundary, the near shore is assumed as the boundary of the unrestricted area, because, in general, IPEC does not attempt to control population on the river. Potential confusion regarding the near or far shore for this application is effectively removed per the definition of unrestricted area in NUREG 0133 (Ref. 1, Section 2.2, Page 6). This section states that these criteria do not include areas over water bodies and the river is therefore not applicable for evaluating the maximum unrestricted area boundary concentrations.

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

The analyses were carried out using the AEOLUS-3 computer code (Ref. 16) and are documented in detail in Ref. 17 and Ref. 50. Hourly meteorological data was collected from 1981 through 1990, initially updated with data from 1992 to 2002 and updated again with data from 2006 to 2015, in accordance with the accuracy requirements of Safety (Draft Regulatory) Guide 1.23 (Ref. 18). The data recovery index for these periods was in excess of 99%.

Comparison of the new meteorological data (2006-2015) with previous data (1992 to 2002 and 1981 to 1990) continues to show little difference in the overall dispersion conditions at the site. The meteorological parameters selected were the higher values of the last two 10 year periods. In the analyses, wind-speed coefficients in Regulatory Guide 1.111 were used to extrapolate the measured wind speeds to the height of the main vent (on top of the primary containment).

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ODCM Part II - Calculational Methodologies Also, the regulatory plume entrainment model was used to determine plume partitioning between ground-level and elevated releases, and no credit was taken for decay and depletion in transit.

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

3.5.3 To meet the calculational requirements of Paragraphs 3.2.1, 3.2.2, and 3.2.4 the annual average dispersion factors are calculated approximately once every ten years, for each compass sector at the site unrestricted area boundary. The most restrictive meteorological dispersion and deposition factors determined from this accumulation of data is currently presented in Appendix I.

The distances to the site boundary and nearest resident in each sector were determined from the land use census and global positioning technology, and are listed in Table 3-9.

For the monitor tank release pathway, ground level dispersion values (X/Q) were assessed using the methodology discussed in Section 3.5.2. The most restrictive X/Q was determined to be in the SW sector at 350m with a value of 5.00E-5 sec/m 3 (concentration X/Q per Ref. 21). This value is specific only to the Unit 3 Monitor Tank pathway for noble gas dose at the site boundary.

3.5.4 To meet the calculational requirements of Paragraph 3.2.3 (Iodines and Particulates),

the annual average deposition and dispersion parameters were calculated for the nearest residents in each of the compass sectors. Because no real dairy exists within 5 miles of the power plant, a hypothetical grass-cow-milk pathway and its dispersion and deposition factors are included, but turned on or off according to the applicable annual Land Use Census. Dispersion and deposition parameters for these locations were calculated using the models and data described in Sec. 3.5.2, and are represented as:

Wn(in) = The highest calculated annual average dispersion parameters for the inhalation pathway for the nearest residence in the unrestricted area, per Appendix I.

Wn(dep)= The highest calculated annual average deposition parameters for the ground plane and vegetation pathways for the nearest residence in the unrestricted area, per Appendix I. For Tritium in the vegetation pathway, Wn(in) is used.

Ws(in) = The highest calculated annual average dispersion parameters for the inhalation pathway at the 5-mile cow secondary receptor, per Appendix I.

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ODCM Part II - Calculational Methodologies Ws(dep)= The highest calculated annual average deposition parameters for the cow-milk, vegetation, and ground plane pathways at the 5-mile secondary receptor, per Appendix I. For Tritium at this location, Ws(in) is used.

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

3.5.5 To meet the calculational requirements of Paragraphs 3.2.2, 3.2.3 and 3.2.4, and the calculation methodologies described in Sections 3.3.4 and 3.3.3, short term release dispersion and deposition factors may need to be calculated.

Short term release dispersion and deposition factors are determined from the long term annual average parameters and a method presented by Sagendorf in NUREG 0324 (Ref. 5) as recommended by NUREG 0133 (Ref. 1, Section 3.3, Page 8). This method makes use of a factor (F), developed for a particular compass sector and distance, which is simply multiplied by the annual average dispersion or deposition parameter for the same sector and distance to develop the corresponding short-term parameter.

This factor is defined as: F = [NTOTAL/8760] m Where:

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

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

log( ANMX / F15MX )

m =

log(8760) 8760 = The total number of hours in a year.

ANMX = The calculated historical average dispersion (sec/m3) or deposition (m-2) factor for the compass sector and distance of interest.

F15MX = The short term dispersion (sec/m3) or deposition (m-2) factor for the compass sector and distance of interest. This is the 15th percentile value such that worse weather conditions can only exist 15% of the time and better conditions 85% of the time.

The atmospheric transport and diffusion model used in the evaluation of short-term dispersion and deposition parameters (F15MX) is the Gaussian plume-centerline model in Regulatory Guide 1.145 (Ref. 19), adapted for mixed-mode releases with plume-rise effects, downwash, building-wake correction and plume meander considerations.

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ODCM Part II - Calculational Methodologies As was the case with the annual average parameters, the analyses were carried out using the AEOLUS-3 computer code (Ref. 16) and the most recent 10-year hourly meteorological data. They are documented in detail in Reference 17 and Reference 50. 4/21 Note that in line with the guidance in NUREG-0133, Sec. 5.3.1, page 29, short-term releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year) are considered to be cumulative over the calendar quarter or year, as appropriate. However, from Sec. 3.1.16 of the ODCM Part II, and in line with Sec. 3.3, page 8 of NUREG-0133, gas-decay tank releases and containment purges have been determined to be sufficiently random so as to permit use of the long-term dispersion and deposition parameters for assessment of their radiological impact.

3.5.6 The short term 15th percentile dispersion or deposition factor for use in the equation of the preceding paragraphs and the simplified F factor equation for mixed-mode releases to critical locations of each IPEC unit are as follows:

a) Site Boundary Noble Gas:

Unit 2 Unit 3 F15MX = 7.724E-5 sec/m3 1.590E-4 sec/m3 ANMX = 2.219E-6 sec/m3 4.470E-6 sec/m3 log( ANMX / F15MX )

m= 0.391 0.393 log(8760)

F= [NTOTAL/8760]-0.391 [NTOTAL/8760]-0.393 b) Nearest Residence Inhalation:

Unit 2 Unit 3 F15MX = 4.992E-5 sec/m3 4.888E-5 sec/m3 ANMX = 1.030E-6 sec/m3 1.016E-6 sec/m3 log( ANMX / F15MX )

m= 0.428 0.427 log(8760)

F= [NTOTAL/8760]-0.428 [NTOTAL/8760]-0.427 IPEC ODCM Page 49 of 145 Revision 6

ODCM Part II - Calculational Methodologies c) Nearest Residence Deposition:

Unit 2 Unit 3 F15MX = 3.995E-7 m-2 4.019E-7 m-2 ANMX = 7.517E-9 m-2 7.451E-9 m-2 log( ANMX / F15MX )

m= 0.438 0.439 log(8760)

F= [NTOTAL/8760]-0.438 [NTOTAL/8760]-0.439 d) 5-mile Inhalation:

Same for both Units 2 and 3 F15MX = 6.192E-6 sec/m3 ANMX = 7.223E-7 sec/m3 log(ANMX / F15MX) m= 0.237 log(8760)

F = [NTOTAL/8760]-0.237 e) 5-mile Deposition:

Same for both Units 2 and 3 F15MX = 9.501E-9 m-2 ANMX = 1.350E-9 m-2 log(ANMX / F15MX) m= 0.215 log(8760)

F = [NTOTAL/8760]-0.215 f) The slopes (m) for ground level short term correction factors can be calculated in a similar fashion, use the most restrictive value from ground level data found in Reference 17 and Reference 50. For example:

Unit 2 Unit 3 Site Boundary Noble Gas: -0.399 -0.407 Nearest Resident Inhalation: -0.427 -0.427 Nearest Resident Deposition: -0.455 -0.455 5-mile Inhalation: -0.235 -0.235 5-mile Deposition: -0.212 -0.212 IPEC ODCM Page 50 of 145 Revision 6

ODCM Part II - Calculational Methodologies 3.6 Justification for and Use of Finite Cloud Assumption for Assessing Site Boundary Dose Two models are available for the computation of doses from external gamma radiation:

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

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

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

1. It could be overly conservative for receptors close to the release point (particularly for ground-level releases under stable conditions with limited plume dispersion) due to the basis that the high concentration at the receptor is assumed to exist everywhere, and;
2. It is not suitable for elevated releases since gamma radiation emanating from the radioactive cloud could still reach a receptor on the ground even though the plume is still aloft (the concentration at ground level is equal to zero).

For practical applications, it is possible to define isotope-dependent finite-cloud correction factors to express the difference in external radiation exposures between a finite cloud (which may be either at ground level or elevated) and a semi-finite cloud. Physically, when such a correction factor is applied to the calculated ground-level concentration resulting from a given plume, it will define the equivalent concentration in a semi-infinite cloud which would yield the same external exposure as the finite cloud. Such a correction factor is a function of both the airborne radionuclide energy and of plume dispersion under the prevailing conditions. At distant receptors, where the plume dimensions reach limiting conditions, such correction factors reduce to unity.

The AEOLUS-3 code (which was used for the determination of the annual average dispersion and deposition parameters listed in Section 3.5), also has the capability of providing a basis for computation of isotope-specific finite-cloud correction factors based on the models in "Meteorology and Atomic Energy" (Ref. 20, Sec. 7.5.2). The code was used (along with the mixed-mode release option and the 10-year hourly meteorological data base) for the determination of the correction factors as would be applicable at the IPEC site boundary. Note that the correction factors can be viewed as adjustment factors to the dose conversion factors in Regulatory Guide 1.109 (Ref. 3) for immersion in semi-infinite clouds. The nuclide specific correction factors and adjusted dose factors are presented in Tables 3-4 and 3-6 for the IPEC site boundary.

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

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ODCM Part II - Calculational Methodologies Table 3-1a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30E-05 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E+00 2.46E-06 5.79E-04 3.78E-05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 IPEC ODCM Page 52 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Sr-85 4.00E-06 0.00E+00 9.70E-05 0.00E+00 0.00E+00 6.00E-05 7.60E-06 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Cd-109 0.00E+00 4.90E-05 1.60E-06 0.00E+00 4.70E-05 9.10E-05 8.20E-06 Sn-113 8.20E-06 2.70E-07 5.60E-07 1.70E-07 0.00E+00 1.20E-04 1.50E-06 Ba-133 9.50E-06 4.20E-07 2.50E-06 0.00E+00 2.10E-09 1.90E-04 1.00E-05 Te-134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.34E-07 2.97E-11 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 53 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1b TEEN INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 IPEC ODCM Page 54 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1b TEEN INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Sr-85 5.00E-06 0.00E+00 1.30E-06 0.00E+00 0.00E+00 8.80E-05 6.90E-06 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 3.93E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Cd-109 0.00E+00 1.00E-04 3.40E-06 0.00E+00 6.70E-05 1.60E-04 8.60E-06 Sn-113 1.50E-05 4.70E-07 9.70E-07 2.90E-07 0.00E+00 2.00E-04 1.50E-06 Ba-133 4.70E-05 8.00E-07 3.30E-06 0.00E+00 2.80E-09 2.90E-04 9.70E-06 Te-134 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-11 6.75E-07 1.37E-09 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 55 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 IPEC ODCM Page 56 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Sr-85 1.20E-05 0.00E+00 3.20E-06 0.00E+00 0.00E+00 1.50E-04 5.50E-06 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 1.16E-10 2.08E-11 9.73E-12 0.00E+00 2.31E-11 9.24E-07 7.51E-06 Cd-109 0.00E+00 1.90E-04 8.00E-06 0.00E+00 1.70E-04 3.00E-04 8.10E-06 Sn-113 3.80E-05 8.90E-07 2.30E-06 7.10E-07 0.00E+00 3.60E-04 1.30E-06 Ba-133 1.10E-04 1.10E-06 1.00E-05 0.00E+00 5.40E-09 5.20E-04 8.30E-06 Te-134 1.53E-11 8.81E-12 9.40E-12 1.24E-11 5.71E-11 1.23E-06 4.87E-07 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 57 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 IPEC ODCM Page 58 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-1d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-05 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Sr-85 2.70E-05 0.00E+00 5.40E-06 0.00E+00 0.00E+00 3.00E-04 4.80E-06 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Cd-109 0.00E+00 2.60E-04 1.00E-05 0.00E+00 2.00E-04 6.20E-04 8.00E-06 Sn-113 6.00E-05 1.60E-06 3.60E-06 1.30E-06 0.00E+00 7.80E-04 1.20E-06 Ba-133 1.90E-04 1.70E-06 1.30E-05 0.00E+00 8.90E-09 9.10E-04 7.70E-06 Te-134 3.18E-11 2.04E-11 1.68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 59 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-2 2

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

with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody(DFg) Skin(DFs)

H-3 12.350 Y 1.00E-02 0.00E+00 0.00E+00 Be-7 53.300 D 1.00E-04 0.00E+00 0.00E+00 Na-24 15.000 H 4.00E-02 2.50E-08 2.90E-08 P-32 14.290 D 2.50E-02 0.00E+00 0.00E+00 Cr-51 27.704 D 2.20E-03 2.20E-10 2.60E-10 Mn-54 312.500 D 2.50E-04 5.80E-09 6.80E-09 Mn-56 2.578 H 2.50E-04 1.10E-08 1.30E-08 Fe-55 2.700 Y 1.20E-03 0.00E+00 0.00E+00 Fe-59 44.529 D 1.20E-03 8.00E-09 9.40E-09 Co-58 70.800 D 1.00E-03 7.00E-09 8.20E-09 Co-60 5.271 Y 1.00E-03 1.70E-08 2.00E-08 Ni-63 96.000 Y 6.70E-03 0.00E+00 0.00E+00 Ni-65 2.520 H 6.70E-03 3.70E-09 4.30E-09 Cu-64 12.701 H 1.40E-02 1.50E-09 1.70E-09 Zn-65 243.900 D 3.90E-02 4.00E-09 4.60E-09 Zn-69 0.950 H 3.90E-02 0.00E+00 0.00E+00 Br-83 2.390 H 5.00E-02 6.40E-11 9.30E-11 Br-84 0.530 H 5.00E-02 1.20E-08 1.40E-08 Br-85 0.050 H 5.00E-02 0.00E+00 0.00E+00 Rb-86 18.660 D 3.00E-02 6.30E-10 7.20E-10 Rb-88 0.297 H 3.00E-02 3.50E-09 4.00E-09 Rb-89 0.253 H 3.00E-02 1.50E-08 1.80E-08 Sr-89 50.500 D 8.00E-04 5.60E-13 6.50E-13 Sr-90 29.120 Y 8.00E-04 0.00E+00 0.00E+00 Sr-91 9.500 H 8.00E-04 7.10E-09 8.30E-09 Sr-92 2.710 H 8.00E-04 9.00E-09 1.00E-08 Y-90 2.667 D 1.00E-05 2.20E-12 2.60E-12 Y-91m 0.829 H 1.00E-05 3.80E-09 4.40E-09 Y-91 58.510 D 1.00E-05 2.40E-11 2.70E-11 Y-92 3.540 H 1.00E-05 1.60E-09 1.90E-09 Y-93 10.100 H 1.00E-05 5.70E-10 7.80E-10 Zr-95 63.980 D 5.00E-06 5.00E-09 5.80E-09 Zr-97 16.900 H 5.00E-06 5.50E-09 6.40E-09 Nb-95 35.150 D 2.50E-03 5.10E-09 6.00E-09 Mo-99 2.750 D 7.50E-03 1.90E-09 2.20E-09 Tc-99m 6.020 H 2.50E-02 9.60E-10 1.10E-09 Tc-101 0.237 H 2.50E-02 2.70E-09 3.00E-09 Ru-103 39.280 D 1.00E-06 3.60E-09 4.20E-09 Ru-105 4.440 H 1.00E-06 4.50E-09 5.10E-09 Ru-106 368.200 D 1.00E-06 1.50E-09 1.80E-09 Ag-110m 249.900 D 5.00E-02 1.80E-08 2.10E-08 Sb-122 2.700 D 1.50E-03 0.00E+00 0.00E+00 Sb-124 60.200 D 1.50E-03 1.30E-08 1.50E-08 Sb-125 2.770 Y 1.50E-03 3.10E-09 3.50E-09 IPEC ODCM Page 60 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-2 2

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

with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody(DFg) Skin(DFs)

Te-125m 58.000 D 1.00E-03 3.50E-11 4.80E-11 Te-127m 109.000 D 1.00E-03 1.10E-12 1.30E-12 Te-127 9.350 H 1.00E-03 1.00E-11 1.10E-11 Te-129m 33.600 D 1.00E-03 7.70E-10 9.00E-10 Te-129 1.160 H 1.00E-03 7.10E-10 8.40E-10 Te-131m 30.000 H 1.00E-03 8.40E-09 9.90E-09 Te-131 0.417 H 1.00E-03 2.20E-09 2.60E-06 Te-132 3.258 D 1.00E-03 1.70E-09 2.00E-09 I-130 12.360 H 6.00E-03 1.40E-08 1.70E-08 I-131 8.040 D 6.00E-03 2.80E-09 3.40E-09 I-132 2.300 H 6.00E-03 1.70E-08 2.00E-08 I-133 20.800 H 6.00E-03 3.70E-09 4.50E-09 I-134 0.877 H 6.00E-03 1.60E-08 1.90E-08 I-135 6.610 H 6.00E-03 1.20E-08 1.40E-08 Cs-134 2.062 Y 1.20E-02 1.20E-08 1.40E-08 Cs-136 13.100 D 1.20E-02 1.50E-08 1.70E-08 Cs-137 30.000 Y 1.20E-02 4.20E-09 4.90E-09 Cs-138 0.537 H 1.20E-02 2.10E-08 2.40E-08 Ba-139 1.378 H 4.00E-04 2.40E-09 2.70E-09 Ba-140 12.740 D 4.00E-04 2.10E-09 2.40E-09 Ba-141 0.304 H 4.00E-04 4.30E-09 4.90E-09 Ba-142 0.177 H 4.00E-04 7.90E-09 9.00E-09 La-140 1.678 D 5.00E-06 1.50E-08 1.70E-08 La-142 1.542 H 5.00E-06 1.50E-08 1.80E-08 Ce-141 32.501 D 1.00E-04 5.50E-10 6.20E-10 Ce-143 33.000 H 1.00E-04 2.20E-09 2.50E-09 Ce-144 284.300 D 1.00E-04 3.20E-10 3.70E-10 Pr-143 13.560 D 5.00E-06 0.00E+00 0.00E+00 Pr-144 0.288 H 5.00E-06 2.00E-10 2.30E-10 Nd-147 10.980 D 5.00E-06 1.00E-09 1.20E-09 W-187 23.900 H 5.00E-04 3.10E-09 3.60E-09 Np-239 2.360 D 5.00E-06 9.50E-10 1.10E-09 K-40 1.28E+09 Y 1.00E-02 0.00E+00 0.00E+00 Co-57 270.900 D 1.00E-03 9.10E-10 1.00E-09 Sr-85 64.840 D 8.00E-04 0.00E+00 0.00E+00 Y-88 106.640 D 1.00E-05 0.00E+00 0.00E+00 Nb-94 2.03E+04 Y 2.50E-03 0.00E+00 0.00E+00 Nb-97 1.202 H 2.50E-03 4.60E-09 5.40E-09 Cd-109 1.271 Y 1.20E-04 0.00E+00 0.00E+00 Sn-113 115.100 D 2.50E-03 0.00E+00 0.00E+00 Ba-133 10.740 Y 4.00E-04 0.00E+00 0.00E+00 Te-134 0.697 H 1.00E-03 1.00E-09 1.20E-09 Ce-139 137.660 D 1.00E-04 0.00E+00 0.00E+00 Hg-203 46.600 D 3.80E-02 0.00E+00 0.00E+00 IPEC ODCM Page 61 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 Be-7 2.77E-09 6.26E-09 3.10E-09 0.00E+00 6.58E-09 0.00E+00 1.08E-06 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 Sb-122 2.00E-07 4.60E-09 6.90E-08 3.10E-09 0.00E+00 1.20E-07 7.60E-05 Sb-124 2.80E-06 5.30E-08 1.10E-06 6.80E-09 0.00E+00 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E+00 1.38E-06 1.97E-05 IPEC ODCM Page 62 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 1.75E-07 2.91E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0.00E+00 3.59E-11 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 63 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 Be-7 3.96E-09 8.87E-09 4.43E-09 0.00E+00 9.40E-09 0.00E+00 1.08E-06 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-122 3.30E-07 6.42E-09 9.64E-08 4.19E-09 0.00E+00 2.06E-07 6.92E-05 Sb-124 3.86E-06 7.12E-08 1.51E-06 8.79E-09 0.00E+00 3.37E-06 7.81E-05 Sb-125 2.48E-06 2.71E-08 5.79E-07 2.36E-09 0.00E+00 2.16E-06 1.92E-05 IPEC ODCM Page 64 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0.00E+00 1.66E-09 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 65 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 Be-7 1.18E-08 2.00E-08 1.32E-08 0.00E+00 1.97E-08 0.00E+00 1.12E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-122 9.83E-07 1.45E-08 2.88E-07 1.26E-08 0.00E+00 4.00E-07 7.56E-05 Sb-124 1.11E-05 1.44E-07 3.88E-06 2.44E-08 0.00E+00 6.15E-06 6.93E-05 Sb-125 7.15E-06 5.51E-08 1.50E-06 6.63E-09 0.00E+00 3.98E-06 1.71E-05 IPEC ODCM Page 66 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0.00E+00 5.89E-07 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 67 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 Be-7 2.26E-08 4.72E-08 2.51E-08 0.00E+00 3.34E-08 0.00E+00 1.11E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-122 2.10E-06 3.85E-08 6.13E-07 3.14E-08 0.00E+00 1.09E-06 7.65E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 IPEC ODCM Page 68 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 69 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-4 Total Body Dose Factors Ki From Noble Gases (gamma)

Gamma Finite Cloud Correction Factor**

Nuclide TB factor

  • x (pCi/uCi) x Unit 2 Unit 3 = U2 Ki *** U3 Ki ***

Kr-83m 7.56E-08 1E+6 8.86E-01 5.78E-01 6.70E-02 4.37E-02 Kr-85m 1.17E-03 1E+6 7.49E-01 4.46E-01 8.76E+02 5.22E+02 Kr-85 1.61E-05 1E+6 6.73E-01 3.85E-01 1.08E+01 6.19E+00 Kr-87 5.92E-03 1E+6 5.68E-01 3.09E-01 3.36E+03 1.83E+03 Kr-88 1.47E-02 1E+6 5.40E-01 2.88E-01 7.93E+03 4.23E+03 Kr-89 1.66E-02 1E+6 5.60E-01 3.03E-01 9.30E+03 5.03E+03 Kr-90 1.56E-02 1E+6 5.97E-01 3.29E-01 9.31E+03 5.13E+03 Xe-131m 9.15E-05 1E+6 8.67E-01 5.62E-01 7.94E+01 5.14E+01 Xe-133m 2.51E-04 1E+6 8.17E-01 5.12E-01 2.05E+02 1.29E+02 Xe-133 2.94E-04 1E+6 8.86E-01 5.78E-01 2.60E+02 1.70E+02 Xe-135m 3.12E-03 1E+6 6.75E-01 3.87E-01 2.11E+03 1.21E+03 Xe-135 1.81E-03 1E+6 7.60E-01 4.55E-01 1.38E+03 8.24E+02 Xe-137 1.42E-03 1E+6 6.46E-01 3.65E-01 9.18E+02 5.18E+02 Xe-138 8.83E-03 1E+6 5.75E-01 3.14E-01 5.07E+03 2.77E+03 Ar-41 8.84E-03 1E+6 5.89E-01 3.21E-01 5.21E+03 2.84E+03

    • The finite cloud correction factor is described in Section 3.6
      • Ki (mrem/yr per uCi/m3)

IPEC ODCM Page 70 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-5 Skin Dose Factors Li From Noble Gases (beta)

Beta Skin*

Nuclide x (pCi/uCi) = Li**

Dose Factor Kr-83m 0.00E+00 1E+6 0.00E+00 Kr-85m 1.46E-03 1E+6 1.46E+03 Kr-85 1.34E-03 1E+6 1.34E+03 Kr-87 9.73E-03 1E+6 9.73E+03 Kr-88 2.37E-03 1E+6 2.37E+03 Kr-89 1.01E-02 1E+6 1.01E+04 Kr-90 7.29E-03 1E+6 7.29E+03 Xe-131m 4.76E-04 1E+6 4.76E+02 Xe-133m 9.94E-04 1E+6 9.94E+02 Xe-133 3.06E-04 1E+6 3.06E+02 Xe-135m 7.11E-04 1E+6 7.11E+02 Xe-135 1.86E-03 1E+6 1.86E+03 Xe-137 1.22E-02 1E+6 1.22E+04 Xe-138 4.13E-03 1E+6 4.13E+03 Ar-41 2.69E-03 1E+6 2.69E+03

    • Li (mrem/yr per uCi/m3)

IPEC ODCM Page 71 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-6 Air Dose Factors Mi From Noble Gases (gamma)

Gamma Finite Cloud Correction Factor**

Nuclide factor

  • x (pCi/uCi) x Unit 2 Unit 3 = U2 Mi *** U3 Mi ***

Kr-83m 1.93E-05 1E+6 8.86E-01 5.78E-01 1.71E+01 1.12E+01 Kr-85m 1.23E-03 1E+6 7.49E-01 4.46E-01 9.21E+02 5.49E+02 Kr-85 1.72E-05 1E+6 6.73E-01 3.85E-01 1.16E+01 6.62E+00 Kr-87 6.17E-03 1E+6 5.68E-01 3.09E-01 3.50E+03 1.91E+03 Kr-88 1.52E-02 1E+6 5.40E-01 2.88E-01 8.20E+03 4.37E+03 Kr-89 1.73E-02 1E+6 5.60E-01 3.03E-01 9.69E+03 5.24E+03 Kr-90 1.63E-02 1E+6 5.97E-01 3.29E-01 9.73E+03 5.36E+03 Xe-131m 1.56E-04 1E+6 8.67E-01 5.62E-01 1.35E+02 8.77E+01 Xe-133m 3.27E-04 1E+6 8.17E-01 5.12E-01 2.67E+02 1.68E+02 Xe-133 3.53E-04 1E+6 8.86E-01 5.78E-01 3.13E+02 2.04E+02 Xe-135m 3.36E-03 1E+6 6.75E-01 3.87E-01 2.27E+03 1.30E+03 Xe-135 1.92E-03 1E+6 7.60E-01 4.55E-01 1.46E+03 8.74E+02 Xe-137 1.51E-03 1E+6 6.46E-01 3.65E-01 9.76E+02 5.51E+02 Xe-138 9.21E-03 1E+6 5.75E-01 3.14E-01 5.29E+03 2.89E+03 Ar-41 9.30E-03 1E+6 5.89E-01 3.21E-01 5.48E+03 2.99E+03

    • The finite cloud correction factor is described in Section 3.6
      • Mi (mrad/yr per uCi/m3)

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ODCM Part II - Calculational Methodologies Table 3-7 Air Dose Factors Ni From Noble Gases (beta)

Beta

  • Nuclide Factor x (pCi/uCi) = Ni**

Kr-83m 2.88E-04 1E+6 2.88E+02 Kr-85m 1.97E-03 1E+6 1.97E+03 Kr-85 1.95E-03 1E+6 1.95E+03 Kr-87 1.03E-02 1E+6 1.03E+04 Kr-88 2.93E-03 1E+6 2.93E+03 Kr-89 1.06E-02 1E+6 1.06E+04 Kr-90 7.83E-03 1E+6 7.83E+03 Xe-131m 1.11E-03 1E+6 1.11E+03 Xe-133m 1.48E-03 1E+6 1.48E+03 Xe-133 1.05E-03 1E+6 1.05E+03 Xe-135m 7.39E-04 1E+6 7.39E+02 Xe-135 2.46E-03 1E+6 2.46E+03 Xe-137 1.27E-02 1E+6 1.27E+04 Xe-138 4.75E-03 1E+6 4.75E+03 Ar-41 3.28E-03 1E+6 3.28E+03

    • Ni (mrad/yr per uCi/m3)

IPEC ODCM Page 73 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3 - 8 NOBLE GAS DOSE FACTORS For Instantaneous and Time Average Mixtures at the Site Boundary, Units 2 and 3 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-133 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 K = 1507 K = 849 mrem/yr per uCi/m3 K = 237 K = 153 L = 1310 L = 1310 mrem/yr per uCi/m3 L = 540 L = 540 M = 1601 M = 905 mrad/yr per uCi/m3 M = 281 M = 181 N = 1977 N = 1977 mrad/yr per uCi/m3 N = 1254 N = 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 30. These mixtures provide conservative application for calculating setpoints per 10CFR20, in terms of uCi/sec before an actual sample of the release is available, per Appendix I.

Time Averaged 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 30. They are used in conjunction with calculations to determine representative quarterly and annual time averaged release rates in curies per second for administrative purposes only, per Appendix I.

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ODCM Part II - Calculational Methodologies TABLE 3 - 9 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCE Distance Distance Distance Sector to Site to Site to nearest Boundary Boundary residence, 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 to the Site Boundary are unit-specific and measured from the applicable units Plant Vent release point. Distances to the Nearest Residence are measured from the Unit 1 Superheater Stack for both Units 2 and 3, per Reference 31.

IPEC ODCM Page 75 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10a 3

ADULT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 P-32 1.32E+06 7.71E+04 5.01E+04 0.00E+00 0.00E+00 0.00E+00 8.64E+04 Cr-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 Mn-56 0.00E+00 1.24E+00 1.83E-01 0.00E+00 1.30E+00 9.44E+03 2.02E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 Co-58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 Co-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 1.34E+04 Ni-65 1.54E+00 2.10E-01 9.12E-02 0.00E+00 0.00E+00 5.60E+03 1.23E+04 Cu-64 0.00E+00 1.46E+00 6.15E-01 0.00E+00 4.62E+00 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51E-02 4.52E-03 0.00E+00 4.22E-02 9.20E+02 1.63E+01 Br-83 0.00E+00 0.00E+00 2.41E+02 0.00E+00 0.00E+00 0.00E+00 2.32E+02 Br-84 0.00E+00 0.00E+00 3.13E+02 0.00E+00 0.00E+00 0.00E+00 1.64E-03 Br-85 0.00E+00 0.00E+00 1.28E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 Rb-88 0.00E+00 3.87E+02 1.93E+02 0.00E+00 0.00E+00 0.00E+00 3.34E-09 Rb-89 0.00E+00 2.56E+02 1.70E+02 0.00E+00 0.00E+00 0.00E+00 9.28E-12 Sr-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 Sr-90 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 Sr-91 6.19E+01 0.00E+00 2.50E+00 0.00E+00 0.00E+00 3.65E+04 1.91E+05 Sr-92 6.74E+00 0.00E+00 2.91E-01 0.00E+00 0.00E+00 1.65E+04 4.30E+04 Y-90 2.09E+03 0.00E+00 5.61E+01 0.00E+00 0.00E+00 1.70E+05 5.06E+05 Y-91m 2.61E-01 0.00E+00 1.02E-02 0.00E+00 0.00E+00 1.92E+03 1.33E+00 Y-91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 Y-92 1.03E+01 0.00E+00 3.02E-01 0.00E+00 0.00E+00 1.57E+04 7.35E+04 Y-93 9.44E+01 0.00E+00 2.61E+00 0.00E+00 0.00E+00 4.85E+04 4.22E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+00 0.00E+00 2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 Mo-99 0.00E+00 1.21E+02 2.30E+01 0.00E+00 2.91E+02 9.12E+04 2.48E+05 Tc-99m 1.03E-03 2.91E-03 3.70E-02 0.00E+00 4.42E-02 7.64E+02 4.16E+03 Tc-101 4.18E-05 6.02E-05 5.90E-04 0.00E+00 1.08E-03 3.99E+02 1.09E-11 Ru-103 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 0.00E+00 3.11E-01 0.00E+00 1.02E+00 1.10E+04 4.82E+04 Ru-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 Ag-110m 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 0.00E+00 2.48E+06 4.06E+05 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 0.00E+00 1.74E+06 1.01E+05 IPEC ODCM Page 76 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10a 3

ADULT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127m 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1.40E+00 6.42E-01 3.10E-01 1.06E+00 5.10E+00 6.51E+03 5.74E+04 Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 Te-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 Te-131m 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 Te-131 1.11E-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 I-130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 0.00E+00 7.69E+03 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 I-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 0.00E+00 4.06E+02 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 I-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 0.00E+00 1.01E+00 I-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.11E+04 0.00E+00 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 0.00E+00 4.80E+02 4.86E+01 1.86E-03 Ba-139 9.36E-01 6.66E-04 2.74E-02 0.00E+00 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 Ba-141 1.00E-01 7.53E-05 3.36E-03 0.00E+00 7.00E-05 1.94E+03 1.16E-07 Ba-142 2.63E-02 2.70E-05 1.66E-03 0.00E+00 2.29E-05 1.19E+03 1.57E-16 La-140 3.44E+02 1.74E+02 4.58E+01 0.00E+00 0.00E+00 1.36E+05 4.58E+05 La-142 6.83E-01 3.10E-01 7.72E-02 0.00E+00 0.00E+00 6.33E+03 2.11E+03 Ce-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 Ce-143 1.86E+02 1.38E+02 1.53E+01 0.00E+00 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 Pr-144 3.01E-02 1.25E-02 1.53E-03 0.00E+00 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 W-187 8.48E+00 7.08E+00 2.48E+00 0.00E+00 0.00E+00 2.90E+04 1.55E+05 Np-239 2.30E+02 2.26E+01 1.24E+01 0.00E+00 7.00E+01 3.76E+04 1.19E+05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 6.92E+02 6.71E+02 0.00E+00 0.00E+00 3.70E+05 3.14E+04 Sr-85 3.20E+04 0.00E+00 7.76E+05 0.00E+00 0.00E+00 4.80E+05 6.08E+04 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 2.22E-01 5.62E-02 2.05E-02 0.00E+00 6.54E-02 2.40E+03 2.42E+02 Cd-109 0.00E+00 3.92E+05 1.28E+04 0.00E+00 3.76E+05 7.28E+05 6.56E+04 Sn-113 6.56E+04 2.16E+03 4.48E+03 1.36E+03 0.00E+00 9.60E+05 1.20E+04 Ba-133 7.60E+04 3.36E+03 2.00E+04 0.00E+00 1.68E+01 1.52E+06 8.00E+04 Te-134 3.07E-02 2.58E-02 1.26E-02 2.75E-02 1.74E-01 3.47E+03 2.38E-01 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 77 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10b 3

TEEN INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 P-32 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.28E+04 Cr-51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 Mn-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 Mn-56 0.00E+00 1.70E+00 2.52E-01 0.00E+00 1.79E+00 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 Co-58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 Co-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 Ni-65 2.18E+00 2.93E-01 1.27E-01 0.00E+00 0.00E+00 9.36E+03 3.67E+04 Cu-64 0.00E+00 2.03E+00 8.48E-01 0.00E+00 6.41E+00 1.11E+04 6.14E+04 Zn-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 Zn-69 4.83E-02 9.20E-02 6.46E-03 0.00E+00 6.02E-02 1.58E+03 2.85E+02 Br-83 0.00E+00 0.00E+00 3.44E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 4.33E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.83E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 Rb-88 0.00E+00 5.46E+02 2.72E+02 0.00E+00 0.00E+00 0.00E+00 2.92E-05 Rb-89 0.00E+00 3.52E+02 2.33E+02 0.00E+00 0.00E+00 0.00E+00 3.38E-07 Sr-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 Sr-90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Sr-91 8.80E+01 0.00E+00 3.51E+00 0.00E+00 0.00E+00 6.07E+04 2.59E+05 Sr-92 9.52E+00 0.00E+00 4.06E-01 0.00E+00 0.00E+00 2.74E+04 1.19E+05 Y-90 2.98E+03 0.00E+00 8.00E+01 0.00E+00 0.00E+00 2.93E+05 5.59E+05 Y-91m 3.70E-01 0.00E+00 1.42E-02 0.00E+00 0.00E+00 3.20E+03 3.02E+01 Y-91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 Y-92 1.47E+01 0.00E+00 4.29E-01 0.00E+00 0.00E+00 2.68E+04 1.65E+05 Y-93 1.35E+02 0.00E+00 3.72E+00 0.00E+00 0.00E+00 8.32E+04 5.79E+05 Zr-95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 0.00E+00 4.12E+01 1.30E+05 6.30E+05 Nb-95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 Mo-99 0.00E+00 1.69E+02 3.22E+01 0.00E+00 4.11E+02 1.54E+05 2.69E+05 Tc-99m 1.38E-03 3.86E-03 4.99E-02 0.00E+00 5.76E-02 1.15E+03 6.13E+03 Tc-101 5.92E-05 8.40E-05 8.24E-04 0.00E+00 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+00 0.00E+00 4.34E-01 0.00E+00 1.41E+00 1.82E+04 9.04E+04 Ru-106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 Ag-110m 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 0.00E+00 3.85E+06 3.98E+05 Sb-125 7.38E+04 8.08E+02 1.72E+04 7.04E+01 0.00E+00 2.74E+06 9.92E+04 IPEC ODCM Page 78 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10b 3

TEEN INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 Te-127m 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 Te-127 2.01E+00 9.12E-01 4.42E-01 1.42E+00 7.28E+00 1.12E+04 8.08E+04 Te-129m 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131m 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1.51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 I-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 0.00E+00 9.12E+03 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 0.00E+00 1.27E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 I-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 0.00E+00 2.04E+01 I-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 0.00E+00 6.95E+03 Cs-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 Cs-137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 0.00E+00 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+00 9.44E-04 3.90E-02 0.00E+00 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 Ba-141 1.42E-01 1.06E-04 4.74E-03 0.00E+00 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 0.00E+00 3.14E-05 1.91E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6.26E+01 0.00E+00 0.00E+00 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-01 1.06E-01 0.00E+00 0.00E+00 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+01 0.00E+00 8.64E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 0.00E+00 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 W-187 1.20E+01 9.76E+00 3.43E+00 0.00E+00 0.00E+00 4.74E+04 1.77E+05 Np-239 3.38E+02 3.19E+01 1.77E+01 0.00E+00 1.00E+02 6.49E+04 1.32E+05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 9.44E+02 9.20E+02 0.00E+00 0.00E+00 5.86E+05 3.14E+04 Sr-85 4.00E+04 0.00E+00 1.04E+04 0.00E+00 0.00E+00 7.04E+05 5.52E+04 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 3.14E-01 7.78E-02 2.84E-02 0.00E+00 9.12E-02 3.93E+03 2.17E+03 Cd-109 0.00E+00 8.00E+05 2.72E+04 0.00E+00 5.36E+05 1.28E+06 6.88E+04 Sn-113 1.20E+05 3.76E+03 7.76E+03 2.32E+03 0.00E+00 1.60E+06 1.20E+04 Ba-133 3.76E+05 6.40E+03 2.64E+04 0.00E+00 2.24E+01 2.32E+06 7.76E+04 Te-134 4.25E-02 3.48E-02 2.91E-02 3.57E-02 2.33E-01 5.40E+03 1.10E+01 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 79 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 P-32 2.60E+06 1.14E+05 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 Cr-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 Mn-56 0.00E+00 1.66E+00 3.12E-01 0.00E+00 1.67E+00 1.31E+04 1.23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 Co-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 Co-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 Ni-65 2.99E+00 2.96E-01 1.64E-01 0.00E+00 0.00E+00 8.18E+03 8.40E+04 Cu-64 0.00E+00 1.99E+00 1.07E+00 0.00E+00 6.03E+00 9.58E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 Zn-69 6.70E-02 9.66E-02 8.92E-03 0.00E+00 5.85E-02 1.42E+03 1.02E+04 Br-83 0.00E+00 0.00E+00 4.74E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 5.48E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.53E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 Rb-88 0.00E+00 5.62E+02 3.66E+02 0.00E+00 0.00E+00 0.00E+00 1.72E+01 Rb-89 0.00E+00 3.45E+02 2.90E+02 0.00E+00 0.00E+00 0.00E+00 1.89E+00 Sr-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 Sr-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Sr-91 1.21E+02 0.00E+00 4.59E+00 0.00E+00 0.00E+00 5.33E+04 1.74E+05 Sr-92 1.31E+01 0.00E+00 5.25E-01 0.00E+00 0.00E+00 2.40E+04 2.42E+05 Y-90 4.11E+03 0.00E+00 1.11E+02 0.00E+00 0.00E+00 2.62E+05 2.68E+05 Y-91m 5.07E-01 0.00E+00 1.84E-02 0.00E+00 0.00E+00 2.81E+03 1.72E+03 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 Y-92 2.04E+01 0.00E+00 5.81E-01 0.00E+00 0.00E+00 2.39E+04 2.39E+05 Y-93 1.86E+02 0.00E+00 5.11E+00 0.00E+00 0.00E+00 7.44E+04 3.89E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 0.00E+00 3.88E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 Mo-99 0.00E+00 1.72E+02 4.25E+01 0.00E+00 3.92E+02 1.35E+05 1.27E+05 Tc-99m 1.78E-03 3.48E-03 5.77E-02 0.00E+00 5.07E-02 9.51E+02 4.81E+03 Tc-101 8.10E-05 8.51E-05 1.08E-03 0.00E+00 1.45E-03 5.85E+02 1.63E+01 Ru-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+00 0.00E+00 5.55E-01 0.00E+00 1.34E+00 1.59E+04 9.95E+04 Ru-106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 Ag-110m 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 0.00E+00 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 0.00E+00 2.32E+06 4.03E+04 IPEC ODCM Page 80 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+00 9.51E-01 6.10E-01 1.96E+00 7.07E+00 1.00E+04 5.62E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-131m 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 I-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 0.00E+00 5.11E+03 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 0.00E+00 3.20E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 I-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 0.00E+00 9.55E+02 I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0.00E+00 4.44E+03 Cs-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 0.00E+00 6.22E+02 6.81E+01 2.70E+02 Ba-139 1.84E+00 9.84E-04 5.36E-02 0.00E+00 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 Ba-141 1.96E-01 1.09E-04 6.36E-03 0.00E+00 9.47E-05 2.92E+03 2.75E+02 Ba-142 4.99E-02 3.60E-05 2.79E-03 0.00E+00 2.91E-05 1.64E+03 2.74E+00 La-140 6.44E+02 2.25E+02 7.55E+01 0.00E+00 0.00E+00 1.83E+05 2.26E+05 La-142 1.29E+00 4.11E-01 1.29E-01 0.00E+00 0.00E+00 8.70E+03 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+01 0.00E+00 8.36E+01 1.15E+05 1.27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.00E-03 0.00E+00 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 W-187 1.63E+01 9.66E+00 4.33E+00 0.00E+00 0.00E+00 4.11E+04 9.10E+04 Np-239 4.66E+02 3.34E+01 2.35E+01 0.00E+00 9.73E+01 5.81E+04 6.40E+04 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 9.03E+02 1.07E+03 0.00E+00 0.00E+00 5.07E+05 1.32E+04 Sr-85 4.44E+04 0.00E+00 1.18E+04 0.00E+00 0.00E+00 5.55E+05 2.04E+04 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 4.29E-01 7.70E-02 3.60E-02 0.00E+00 8.55E-02 3.42E+03 2.78E+04 Cd-109 0.00E+00 7.03E+05 2.96E+04 0.00E+00 6.29E+05 1.11E+06 3.00E+04 Sn-113 1.41E+05 3.29E+03 8.51E+03 2.63E+03 0.00E+00 1.33E+06 4.81E+03 Ba-133 4.07E+05 4.07E+03 3.70E+04 0.00E+00 2.00E+01 1.92E+06 3.07E+04 Te-134 5.66E-02 3.26E-02 3.48E-02 4.59E-02 2.11E-01 4.55E+03 1.80E+03 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 81 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10d 3

INFANT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 Be-7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 P-32 2.03E+06 1.12E+05 7.74E+04 0.00E+00 0.00E+00 0.00E+00 1.61E+04 Cr-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 Mn-54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 Mn-56 0.00E+00 1.54E+00 2.21E-01 0.00E+00 1.10E+00 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 Fe-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 Co-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 Co-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 Ni-65 2.39E+00 2.84E-01 1.23E-01 0.00E+00 0.00E+00 8.12E+03 5.01E+04 Cu-64 0.00E+00 1.88E+00 7.74E-01 0.00E+00 3.98E+00 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 0.00E+00 4.02E-02 1.47E+03 1.32E+04 Br-83 0.00E+00 0.00E+00 3.81E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 4.00E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.04E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03 Rb-88 0.00E+00 5.57E+02 2.87E+02 0.00E+00 0.00E+00 0.00E+00 3.39E+02 Rb-89 0.00E+00 3.21E+02 2.06E+02 0.00E+00 0.00E+00 0.00E+00 6.82E+01 Sr-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 Sr-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Sr-91 9.56E+01 0.00E+00 3.46E+00 0.00E+00 0.00E+00 5.26E+04 7.34E+04 Sr-92 1.05E+01 0.00E+00 3.91E-01 0.00E+00 0.00E+00 2.38E+04 1.40E+05 Y-90 3.29E+03 0.00E+00 8.82E+01 0.00E+00 0.00E+00 2.69E+05 1.04E+05 Y-91m 4.07E-01 0.00E+00 1.39E-02 0.00E+00 0.00E+00 2.79E+03 2.35E+03 Y-91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 Y-92 1.64E+01 0.00E+00 4.61E-01 0.00E+00 0.00E+00 2.45E+04 1.27E+05 Y-93 1.50E+02 0.00E+00 4.07E+00 0.00E+00 0.00E+00 7.64E+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+01 1.17E+01 0.00E+00 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 Mo-99 0.00E+00 1.65E+02 3.23E+01 0.00E+00 2.65E+02 1.35E+05 4.87E+04 Tc-99m 1.40E-03 2.88E-03 3.72E-02 0.00E+00 3.11E-02 8.11E+02 2.03E+03 Tc-101 6.51E-05 8.23E-05 8.12E-04 0.00E+00 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 Ru-105 1.22E+00 0.00E+00 4.10E-01 0.00E+00 8.99E-01 1.57E+04 4.84E+04 Ru-106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 Ag-110m 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 3.79E+04 5.56E+02 1.20E+04 1.01E+02 0.00E+00 2.65E+06 5.91E+04 Sb-125 5.17E+04 4.77E+02 1.09E+04 6.23E+01 0.00E+00 1.64E+06 1.47E+04 IPEC ODCM Page 82 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-10d 3

INFANT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 Te-127m 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+04 9.53E-01 4.89E-01 1.85E+00 4.86E+00 1.03E+04 2.44E+04 Te-129m 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 Te-131m 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 I-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 0.00E+00 1.99E+03 I-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 0.00E+00 1.90E+03 I-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 I-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 0.00E+00 1.29E+03 I-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 0.00E+00 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 0.00E+00 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+00 9.84E-04 4.30E-02 0.00E+00 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-01 1.08E-04 4.97E-03 0.00E+00 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 0.00E+00 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.00E+02 5.15E+01 0.00E+00 0.00E+00 1.68E+05 8.48E+04 La-142 1.03E+00 3.77E-01 9.04E-02 0.00E+00 0.00E+00 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E+02 1.93E+02 2.21E+01 0.00E+00 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 0.00E+00 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 W-187 1.30E+01 9.02E+00 3.12E+00 0.00E+00 0.00E+00 3.96E+04 3.56E+04 Np-239 3.71E+02 3.32E+01 1.88E+01 0.00E+00 6.62E+01 5.95E+04 2.49E+04 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 6.51E+02 6.41E+02 0.00E+00 0.00E+00 3.79E+05 4.86E+03 Sr-85 3.78E+04 0.00E+00 7.56E+03 0.00E+00 0.00E+00 4.20E+05 6.72E+03 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 3.42E-01 7.29E-02 2.63E-02 0.00E+00 5.70E-02 3.32E+03 2.69E+04 Cd-109 0.00E+00 3.64E+05 1.40E+04 0.00E+00 2.80E+05 8.68E+05 1.12E+04 Sn-113 8.40E+04 2.24E+03 5.04E+03 1.82E+03 0.00E+00 1.09E+06 1.68E+03 Ba-133 2.66E+05 2.38E+03 1.82E+04 0.00E+00 1.25E+01 1.27E+06 1.08E+04 Te-134 4.45E-02 2.86E-02 2.35E-02 4.07E-02 1.34E-01 4.10E+03 3.54E+03 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 83 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-11a ADULT INGESTION (Leafy Vegetable) Ri(V) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 Be-7 9.36E+04 2.11E+05 1.05E+05 0.00E+00 2.22E+05 0.00E+00 3.65E+07 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 P-32 1.40E+09 8.73E+07 5.43E+07 0.00E+00 0.00E+00 0.00E+00 1.58E+08 Cr-51 0.00E+00 0.00E+00 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 Mn-54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 9.58E+08 Mn-56 0.00E+00 1.59E+01 2.82E+00 0.00E+00 2.02E+01 0.00E+00 5.07E+02 Fe-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.13E+08 0.00E+00 0.00E+00 8.27E+07 9.86E+08 Co-58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 Co-60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 Ni-63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 Ni-65 6.15E+01 7.99E+00 3.64E+00 0.00E+00 0.00E+00 0.00E+00 2.03E+02 Cu-64 0.00E+00 9.20E+03 4.32E+03 0.00E+00 2.32E+04 0.00E+00 7.84E+05 Zn-65 3.17E+08 1.01E+09 4.56E+08 0.00E+00 6.75E+08 0.00E+00 6.36E+08 Zn-69 8.73E-06 1.67E-05 1.16E-06 0.00E+00 1.09E-05 0.00E+00 2.51E-06 Br-83 0.00E+00 0.00E+00 3.11E+00 0.00E+00 0.00E+00 0.00E+00 4.47E+00 Br-84 0.00E+00 0.00E+00 2.48E-11 0.00E+00 0.00E+00 0.00E+00 1.94E-16 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.33E+07 Rb-88 0.00E+00 3.43E-22 1.82E-22 0.00E+00 0.00E+00 0.00E+00 4.74E-33 Rb-89 0.00E+00 1.39E-26 9.74E-27 0.00E+00 0.00E+00 0.00E+00 8.05E-40 Sr-89 9.96E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 Sr-90 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 Sr-91 3.05E+05 0.00E+00 1.23E+04 0.00E+00 0.00E+00 0.00E+00 1.45E+06 Sr-92 4.27E+02 0.00E+00 1.85E+01 0.00E+00 0.00E+00 0.00E+00 8.45E+03 Y-90 1.33E+04 0.00E+00 3.56E+02 0.00E+00 0.00E+00 0.00E+00 1.41E+08 Y-91m 5.22E-09 0.00E+00 2.02E-10 0.00E+00 0.00E+00 0.00E+00 1.53E-08 Y-91 5.11E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.81E+09 Y-92 9.15E-01 0.00E+00 2.68E-02 0.00E+00 0.00E+00 0.00E+00 1.60E+04 Y-93 1.70E+02 0.00E+00 4.68E+00 0.00E+00 0.00E+00 0.00E+00 5.38E+06 Zr-95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+05 0.00E+00 1.19E+09 Zr-97 3.37E+02 6.81E+01 3.11E+01 0.00E+00 1.03E+02 0.00E+00 2.11E+07 Nb-95 1.43E+05 7.94E+04 4.27E+04 0.00E+00 7.85E+04 0.00E+00 4.82E+08 Mo-99 0.00E+00 6.15E+06 1.17E+06 0.00E+00 1.39E+07 0.00E+00 1.43E+07 Tc-99m 3.10E+00 8.77E+00 1.12E+02 0.00E+00 1.33E+02 4.30E+00 5.19E+03 Tc-101 8.22E-31 1.18E-30 1.16E-29 0.00E+00 2.13E-29 6.05E-31 3.56E-42 Ru-103 4.76E+06 0.00E+00 2.05E+06 0.00E+00 1.82E+07 0.00E+00 5.56E+08 Ru-105 5.39E+01 0.00E+00 2.13E+01 0.00E+00 6.96E+02 0.00E+00 3.29E+04 Ru-106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 Ag-110m 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 Sb-122 2.80E+05 6.43E+03 9.65E+04 4.34E+03 0.00E+00 1.68E+05 1.06E+08 Sb-124 1.04E+08 1.96E+06 4.07E+07 2.52E+05 0.00E+00 8.07E+07 2.94E+09 Sb-125 1.37E+08 1.53E+06 3.25E+07 1.39E+05 0.00E+00 1.05E+08 1.50E+09 IPEC ODCM Page 84 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-11a ADULT INGESTION (Leafy Vegetable) Ri(V) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 Te-127m 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 0.00E+00 1.17E+09 Te-127 5.66E+03 2.03E+03 1.22E+03 4.19E+03 2.31E+04 0.00E+00 4.47E+05 Te-129m 2.51E+08 9.38E+07 3.98E+07 8.63E+07 1.05E+09 0.00E+00 1.27E+09 Te-129 7.62E-04 2.87E-04 1.86E-04 5.85E-04 3.20E-03 0.00E+00 5.75E-04 Te-131m 9.12E+05 4.46E+05 3.72E+05 7.06E+05 4.52E+06 0.00E+00 4.43E+07 Te-131 1.50E-15 6.27E-16 4.74E-16 1.23E-15 6.57E-15 0.00E+00 2.13E-16 Te-132 4.30E+06 2.78E+06 2.61E+06 3.07E+06 2.68E+07 0.00E+00 1.32E+08 I-130 3.92E+05 1.16E+06 4.57E+05 9.81E+07 1.81E+06 0.00E+00 9.96E+05 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07 I-132 5.76E+01 1.54E+02 5.39E+01 5.39E+03 2.45E+02 0.00E+00 2.89E+01 I-133 2.09E+06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 0.00E+00 3.26E+06 I-134 9.65E-05 2.62E-04 9.38E-05 4.54E-03 4.17E-04 0.00E+00 2.29E-07 I-135 3.90E+04 1.02E+05 3.77E+04 6.73E+06 1.64E+05 0.00E+00 1.15E+05 Cs-134 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.24E+07 1.68E+08 1.21E+08 0.00E+00 9.32E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 Cs-138 3.91E-11 7.73E-11 3.83E-11 0.00E+00 5.68E-11 5.61E-12 3.30E-16 Ba-139 2.68E-02 1.91E-05 7.86E-04 0.00E+00 1.79E-05 1.08E-05 4.76E-02 Ba-140 1.28E+08 1.61E+05 8.38E+06 0.00E+00 5.46E+04 9.20E+04 2.63E+08 Ba-141 1.15E-21 8.70E-25 3.89E-23 0.00E+00 8.09E-25 4.94E-25 5.43E-31 Ba-142 2.46E-39 2.53E-42 1.55E-40 0.00E+00 2.14E-42 1.43E-42 0.00E+00 La-140 1.98E+03 9.98E+02 2.64E+02 0.00E+00 0.00E+00 0.00E+00 7.33E+07 La-142 1.41E-04 6.43E-05 1.60E-05 0.00E+00 0.00E+00 0.00E+00 4.69E-01 Ce-141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.19E+04 0.00E+00 5.10E+08 Ce-143 9.98E+02 7.38E+05 8.16E+01 0.00E+00 3.25E+02 0.00E+00 2.76E+07 Ce-144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+10 Pr-143 6.26E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08 Pr-144 3.09E-26 1.28E-26 1.57E-27 0.00E+00 7.23E-27 0.00E+00 4.44E-33 Nd-147 3.33E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 W-187 3.82E+04 3.19E+04 1.12E+04 0.00E+00 0.00E+00 0.00E+00 1.05E+07 Np-239 1.43E+03 1.41E+02 7.76E+01 0.00E+00 4.39E+02 0.00E+00 2.89E+07 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 1.17E+07 1.95E+07 0.00E+00 0.00E+00 0.00E+00 2.97E+08 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 2.15E-06 5.45E-07 1.99E-07 0.00E+00 6.35E-07 0.00E+00 2.01E-03 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 3.56E-08 2.33E-08 1.43E-08 3.11E-08 2.25E-07 0.00E+00 3.95E-11 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 85 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-11b TEEN INGESTION (Leafy Vegetable) Ri(V) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 Be-7 1.43E+05 3.20E+05 1.60E+05 0.00E+00 3.39E+05 0.00E+00 3.90E+07 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 P-32 1.61E+09 9.97E+07 6.24E+07 0.00E+00 0.00E+00 0.00E+00 1.35E+08 Cr-51 0.00E+00 0.00E+00 6.17E+04 3.43E+04 1.35E+04 8.81E+04 1.04E+07 Mn-54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 Mn-56 0.00E+00 1.43E+01 2.55E+00 0.00E+00 1.81E+01 0.00E+00 9.44E+02 Fe-55 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 Fe-59 1.79E+08 4.18E+08 1.61E+08 0.00E+00 0.00E+00 1.32E+08 9.88E+08 Co-58 0.00E+00 4.36E+07 1.00E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 Co-60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 Ni-63 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 Ni-65 5.72E+01 7.31E+00 3.33E+00 0.00E+00 0.00E+00 0.00E+00 3.97E+02 Cu-64 0.00E+00 8.34E+03 3.92E+03 0.00E+00 2.11E+04 0.00E+00 6.47E+05 Zn-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 Zn-69 8.18E-06 1.56E-05 1.09E-06 0.00E+00 1.02E-05 0.00E+00 2.87E-05 Br-83 0.00E+00 0.00E+00 2.91E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.25E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.74E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 4.05E+07 Rb-88 0.00E+00 3.17E-22 1.69E-22 0.00E+00 0.00E+00 0.00E+00 2.71E-29 Rb-89 0.00E+00 1.25E-26 8.82E-27 0.00E+00 0.00E+00 0.00E+00 1.91E-35 Sr-89 1.51E+10 0.00E+00 4.33E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 Sr-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 Sr-91 2.85E+05 0.00E+00 1.13E+04 0.00E+00 0.00E+00 0.00E+00 1.29E+06 Sr-92 3.97E+02 0.00E+00 1.69E+01 0.00E+00 0.00E+00 0.00E+00 1.01E+04 Y-90 1.24E+04 0.00E+00 3.34E+02 0.00E+00 0.00E+00 0.00E+00 1.02E+08 Y-91m 4.86E-09 0.00E+00 1.86E-10 0.00E+00 0.00E+00 0.00E+00 2.29E-07 Y-91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.21E+09 Y-92 8.60E-01 0.00E+00 2.49E-02 0.00E+00 0.00E+00 0.00E+00 2.36E+04 Y-93 1.59E+02 0.00E+00 4.36E+00 0.00E+00 0.00E+00 0.00E+00 4.86E+06 Zr-95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 Zr-97 3.12E+02 6.18E+01 2.85E+01 0.00E+00 9.37E+01 0.00E+00 1.67E+07 Nb-95 1.93E+05 1.07E+05 5.89E+04 0.00E+00 1.04E+05 0.00E+00 4.57E+08 Mo-99 0.00E+00 5.65E+06 1.08E+06 0.00E+00 1.29E+07 0.00E+00 1.01E+07 Tc-99m 2.74E+00 7.63E+00 9.89E+01 0.00E+00 1.14E+02 4.24E+00 5.01E+03 Tc-101 7.64E-31 1.09E-30 1.07E-29 0.00E+00 1.97E-29 6.62E-31 1.86E-37 Ru-103 6.81E+06 0.00E+00 2.91E+06 0.00E+00 2.40E+07 0.00E+00 5.69E+08 Ru-105 5.00E+01 0.00E+00 1.94E+01 0.00E+00 6.31E+02 0.00E+00 4.04E+04 Ru-106 3.10E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 Ag-110m 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 Sb-122 3.03E+05 5.89E+03 8.85E+04 3.85E+03 0.00E+00 1.89E+05 6.35E+07 Sb-124 1.54E+08 2.84E+06 6.02E+07 3.50E+05 0.00E+00 1.34E+08 3.11E+09 Sb-125 2.14E+08 2.34E+06 5.00E+07 2.04E+05 0.00E+00 1.86E+08 1.66E+09 IPEC ODCM Page 86 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-11b TEEN INGESTION (Leafy Vegetable) Ri(V) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 Te-127m 5.51E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 Te-127 5.34E+03 1.89E+03 1.15E+03 3.68E+03 2.16E+04 0.00E+00 4.12E+05 Te-129m 3.62E+08 1.34E+08 5.73E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 Te-129 7.14E-04 2.66E-04 1.74E-04 5.10E-04 3.00E-03 0.00E+00 3.90E-03 Te-131m 8.44E+05 4.05E+05 3.38E+05 6.09E+05 4.22E+06 0.00E+00 3.25E+07 Te-131 1.39E-15 5.75E-16 4.36E-16 1.07E-15 6.10E-15 0.00E+00 1.14E-16 Te-132 3.91E+06 2.47E+06 2.33E+06 2.61E+06 2.37E+07 0.00E+00 7.84E+07 I-130 3.51E+05 1.01E+06 4.05E+05 8.28E+07 1.56E+06 0.00E+00 7.80E+05 I-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I-132 5.19E+01 1.36E+02 4.88E+01 4.58E+03 2.14E+02 0.00E+00 5.92E+01 I-133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.76E+06 0.00E+00 2.49E+06 I-134 8.73E-05 2.31E-04 8.31E-05 3.85E-03 3.65E-04 0.00E+00 3.05E-06 I-135 3.52E+04 9.07E+04 3.36E+04 5.83E+06 1.43E+05 0.00E+00 1.00E+05 Cs-134 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.34E+07 1.71E+08 1.15E+08 0.00E+00 9.30E+07 1.47E+07 1.37E+07 Cs-137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 Cs-138 3.61E-11 6.93E-11 3.47E-11 0.00E+00 5.12E-11 5.96E-12 3.15E-14 Ba-139 2.52E-02 1.78E-05 7.35E-04 0.00E+00 1.67E-05 1.22E-05 2.25E-01 Ba-140 1.37E+08 1.68E+05 8.85E+06 0.00E+00 5.70E+04 1.13E+05 2.12E+08 Ba-141 1.08E-21 8.04E-25 3.59E-23 0.00E+00 7.46E-25 5.50E-25 2.29E-27 Ba-142 2.27E-39 2.27E-42 1.40E-40 0.00E+00 1.92E-42 1.51E-42 0.00E+00 La-140 1.81E+03 8.89E+02 2.37E+02 0.00E+00 0.00E+00 0.00E+00 5.11E+07 La-142 1.30E-04 5.76E-05 1.43E-05 0.00E+00 0.00E+00 0.00E+00 1.75E+00 Ce-141 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.89E+04 0.00E+00 5.40E+08 Ce-143 9.33E+02 6.79E+05 7.58E+01 0.00E+00 3.04E+02 0.00E+00 2.04E+07 Ce-144 5.27E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 Pr-143 7.00E+04 2.80E+04 3.49E+03 0.00E+00 1.63E+04 0.00E+00 2.30E+08 Pr-144 2.89E-26 1.18E-26 1.47E-27 0.00E+00 6.80E-27 0.00E+00 3.19E-29 Nd-147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 W-187 3.55E+04 2.90E+04 1.02E+04 0.00E+00 0.00E+00 0.00E+00 7.84E+06 Np-239 1.39E+03 1.31E+02 7.28E+01 0.00E+00 4.11E+02 0.00E+00 2.11E+07 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 1.79E+07 3.00E+07 0.00E+00 0.00E+00 0.00E+00 3.33E+08 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 2.00E-06 4.95E-07 1.81E-07 0.00E+00 5.79E-07 0.00E+00 1.18E-02 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 3.23E-08 2.07E-08 2.17E-08 2.65E-08 1.98E-07 0.00E+00 1.20E-09 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 87 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-11c CHILD INGESTION (Leafy Vegetable) Ri(V) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 Be-7 3.37E+05 5.72E+05 3.77E+05 0.00E+00 5.63E+05 0.00E+00 3.20E+07 Na-24 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 P-32 3.37E+09 1.58E+08 1.30E+08 0.00E+00 0.00E+00 0.00E+00 9.31E+07 Cr-51 0.00E+00 0.00E+00 1.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06 Mn-54 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 Mn-56 0.00E+00 1.88E+01 4.24E+00 0.00E+00 2.27E+01 0.00E+00 2.72E+03 Fe-55 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 0.00E+00 0.00E+00 1.86E+08 6.68E+08 Co-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 Co-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 Ni-63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 Ni-65 1.05E+02 9.89E+00 5.77E+00 0.00E+00 0.00E+00 0.00E+00 1.21E+03 Cu-64 0.00E+00 1.10E+04 6.64E+03 0.00E+00 2.66E+04 0.00E+00 5.16E+05 Zn-65 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 Zn-69 1.51E-05 2.18E-05 2.02E-06 0.00E+00 1.32E-05 0.00E+00 1.37E-03 Br-83 0.00E+00 0.00E+00 5.37E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 4.52E+08 2.78E+08 0.00E+00 0.00E+00 0.00E+00 2.91E+07 Rb-88 0.00E+00 4.37E-22 3.04E-22 0.00E+00 0.00E+00 0.00E+00 2.15E-23 Rb-89 0.00E+00 1.64E-26 1.46E-26 0.00E+00 0.00E+00 0.00E+00 1.43E-28 Sr-89 3.59E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 Sr-90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Sr-91 5.24E+05 0.00E+00 1.98E+04 0.00E+00 0.00E+00 0.00E+00 1.16E+06 Sr-92 7.28E+02 0.00E+00 2.92E+01 0.00E+00 0.00E+00 0.00E+00 1.38E+04 Y-90 2.30E+04 0.00E+00 6.17E+02 0.00E+00 0.00E+00 0.00E+00 6.56E+07 Y-91m 8.91E-09 0.00E+00 3.24E-10 0.00E+00 0.00E+00 0.00E+00 1.74E-05 Y-91 1.86E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.48E+09 Y-92 1.58E+00 0.00E+00 4.53E-02 0.00E+00 0.00E+00 0.00E+00 4.58E+04 Y-93 2.93E+02 0.00E+00 8.04E+00 0.00E+00 0.00E+00 0.00E+00 4.37E+06 Zr-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.84E+08 Zr-97 5.70E+02 8.24E+01 4.86E+01 0.00E+00 1.18E+02 0.00E+00 1.25E+07 Nb-95 4.12E+05 1.60E+05 1.15E+05 0.00E+00 1.51E+05 0.00E+00 2.97E+08 Mo-99 0.00E+00 7.71E+06 1.91E+06 0.00E+00 1.65E+07 0.00E+00 6.38E+06 Tc-99m 4.71E+00 9.24E+00 1.53E+02 0.00E+00 1.34E+02 4.69E+00 5.26E+03 Tc-101 1.41E-30 1.47E-30 1.87E-29 0.00E+00 2.51E-29 7.78E-31 4.68E-30 Ru-103 1.53E+07 0.00E+00 5.88E+06 0.00E+00 3.85E+07 0.00E+00 3.96E+08 Ru-105 9.16E+01 0.00E+00 3.32E+01 0.00E+00 8.05E+02 0.00E+00 5.98E+04 Ru-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 Ag-110m 3.21E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2.58E+09 Sb-122 5.58E+05 8.24E+03 1.64E+05 7.16E+03 0.00E+00 2.27E+05 4.30E+07 Sb-124 3.52E+08 4.56E+06 1.23E+08 7.73E+05 0.00E+00 1.95E+08 2.20E+09 Sb-125 4.99E+08 3.84E+06 1.05E+08 4.63E+05 0.00E+00 2.78E+08 1.19E+09 IPEC ODCM Page 88 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-11c CHILD INGESTION (Leafy Vegetable) Ri(V) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 Te-127 9.85E+03 2.65E+03 2.11E+03 6.81E+03 2.80E+04 0.00E+00 3.85E+05 Te-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00E+00 1.03E+09 Te-129 1.32E-03 3.69E-04 3.14E-04 9.43E-04 3.87E-03 0.00E+00 8.23E-02 Te-131m 1.54E+06 5.33E+05 5.68E+05 1.10E+06 5.16E+06 0.00E+00 2.16E+07 Te-131 2.57E-15 7.83E-16 7.64E-16 1.97E-15 7.77E-15 0.00E+00 1.35E-14 Te-132 7.00E+06 3.10E+06 3.74E+06 4.51E+06 2.88E+07 0.00E+00 3.12E+07 I-130 6.16E+05 1.24E+06 6.41E+05 1.37E+08 1.86E+06 0.00E+00 5.82E+05 I-131 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 0.00E+00 1.28E+07 I-132 9.22E+01 1.69E+02 7.79E+01 7.86E+03 2.59E+02 0.00E+00 1.99E+02 I-133 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.28E+06 0.00E+00 1.76E+06 I-134 1.55E-04 2.88E-04 1.32E-04 6.62E-03 4.40E-04 0.00E+00 1.91E-04 I-135 6.26E+04 1.13E+05 5.33E+04 9.97E+06 1.73E+05 0.00E+00 8.58E+04 Cs-134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 Cs-136 8.17E+07 2.25E+08 1.45E+08 0.00E+00 1.20E+08 1.78E+07 7.90E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 Cs-138 6.57E-11 9.13E-11 5.79E-11 0.00E+00 6.43E-11 6.91E-12 4.21E-11 Ba-139 4.65E-02 2.48E-05 1.35E-03 0.00E+00 2.17E-05 1.46E-05 2.69E+00 Ba-140 2.75E+08 2.41E+05 1.60E+07 0.00E+00 7.84E+04 1.44E+05 1.39E+08 Ba-141 1.99E-21 1.11E-24 6.47E-23 0.00E+00 9.62E-25 6.53E-24 1.13E-21 Ba-142 4.11E-39 2.96E-42 2.29E-40 0.00E+00 2.39E-42 1.74E-42 5.36E-41 La-140 3.25E+03 1.14E+03 3.83E+02 0.00E+00 0.00E+00 0.00E+00 3.17E+07 La-142 2.35E-04 7.49E-05 2.35E-05 0.00E+00 0.00E+00 0.00E+00 1.48E+01 Ce-141 6.56E+05 3.27E+05 4.86E+04 0.00E+00 1.43E+05 0.00E+00 4.08E+08 Ce-143 1.72E+03 9.31E+05 1.35E+02 0.00E+00 3.91E+02 0.00E+00 1.36E+07 Ce-144 1.27E+08 3.98E+07 6.78E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 0.00E+00 2.37E+04 0.00E+00 1.57E+08 Pr-144 5.37E-26 1.66E-26 2.70E-27 0.00E+00 8.79E-27 0.00E+00 3.58E-23 Nd-147 7.15E+04 5.79E+04 4.48E+03 0.00E+00 3.18E+04 0.00E+00 9.17E+07 W-187 6.47E+04 3.83E+04 1.72E+04 0.00E+00 0.00E+00 0.00E+00 5.38E+06 Np-239 2.57E+03 1.84E+02 1.29E+02 0.00E+00 5.33E+02 0.00E+00 1.36E+07 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 2.99E+07 6.04E+07 0.00E+00 0.00E+00 0.00E+00 2.45E+08 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 3.64E-06 6.57E-07 3.07E-07 0.00E+00 7.29E-07 0.00E+00 2.03E-01 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 5.76E-08 2.59E-08 3.46E-08 4.56E-08 2.40E-07 0.00E+00 2.63E-07 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 89 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12a ADULT GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 Be-7 1.65E+03 3.73E+03 1.85E+03 0.00E+00 3.92E+03 0.00E+00 6.44E+05 Na-24 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 P-32 1.71E+10 1.06E+09 6.61E+08 0.00E+00 0.00E+00 0.00E+00 1.92E+09 Cr-51 0.00E+00 0.00E+00 2.86E+04 1.71E+04 6.30E+03 3.79E+04 7.19E+06 Mn-54 0.00E+00 8.41E+06 1.61E+06 0.00E+00 2.50E+06 0.00E+00 2.58E+07 Mn-56 0.00E+00 4.15E-03 7.36E-04 0.00E+00 5.27E-03 0.00E+00 1.32E-01 Fe-55 2.51E+07 1.74E+07 4.05E+06 0.00E+00 0.00E+00 9.68E+06 9.95E+06 Fe-59 2.97E+07 6.98E+07 2.67E+07 0.00E+00 0.00E+00 1.95E+07 2.33E+08 Co-58 0.00E+00 4.71E+06 1.06E+07 0.00E+00 0.00E+00 0.00E+00 9.55E+07 Co-60 0.00E+00 1.64E+07 3.62E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 Ni-63 6.73E+09 4.66E+08 2.26E+08 0.00E+00 0.00E+00 0.00E+00 9.73E+07 Ni-65 3.70E-01 4.81E-02 2.19E-02 0.00E+00 0.00E+00 0.00E+00 1.22E+00 Cu-64 0.00E+00 2.38E+04 1.12E+04 0.00E+00 6.01E+04 0.00E+00 2.03E+06 Zn-65 1.37E+09 4.36E+09 1.97E+09 0.00E+00 2.92E+09 0.00E+00 2.75E+09 Zn-69 5.18E-12 9.91E-12 6.89E-13 0.00E+00 6.44E-12 0.00E+00 1.49E-12 Br-83 0.00E+00 0.00E+00 9.72E-02 0.00E+00 0.00E+00 0.00E+00 1.40E-01 Br-84 0.00E+00 0.00E+00 1.61E-23 0.00E+00 0.00E+00 0.00E+00 1.26E-28 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.12E+08 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.33E+08 Sr-90 4.68E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1.35E+09 Sr-91 2.89E+04 0.00E+00 1.17E+03 0.00E+00 0.00E+00 0.00E+00 1.38E+05 Sr-92 4.88E-01 0.00E+00 2.11E-02 0.00E+00 0.00E+00 0.00E+00 9.68E+00 Y-90 7.07E+01 0.00E+00 1.90E+00 0.00E+00 0.00E+00 0.00E+00 7.49E+05 Y-91m 5.98E-20 0.00E+00 2.32E-21 0.00E+00 0.00E+00 0.00E+00 1.76E-19 Y-91 8.59E+03 0.00E+00 2.30E+02 0.00E+00 0.00E+00 0.00E+00 4.73E+06 Y-92 5.58E-05 0.00E+00 1.63E-06 0.00E+00 0.00E+00 0.00E+00 9.77E-01 Y-93 2.23E-01 0.00E+00 6.17E-03 0.00E+00 0.00E+00 0.00E+00 7.08E+03 Zr-95 9.43E+02 3.02E+02 2.05E+02 0.00E+00 4.75E+02 0.00E+00 9.59E+05 Zr-97 4.33E-01 8.74E-02 4.00E-02 0.00E+00 1.32E-01 0.00E+00 2.71E+04 Nb-95 8.26E+04 4.60E+04 2.47E+04 0.00E+00 4.54E+04 0.00E+00 2.79E+08 Mo-99 0.00E+00 2.48E+07 4.71E+06 0.00E+00 5.61E+07 0.00E+00 5.74E+07 Tc-99m 3.32E+00 9.38E+00 1.20E+02 0.00E+00 1.43E+02 4.60E+00 5.55E+03 Tc-101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 1.02E+03 0.00E+00 4.38E+02 0.00E+00 3.88E+03 0.00E+00 1.19E+05 Ru-105 8.57E-04 0.00E+00 3.38E-04 0.00E+00 1.11E-02 0.00E+00 5.24E-01 Ru-106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.94E+04 0.00E+00 1.32E+06 Ag-110m 5.82E+07 5.39E+07 3.20E+07 0.00E+00 1.06E+08 0.00E+00 2.20E+10 Sb-122 2.24E+05 5.16E+03 7.73E+04 3.47E+03 0.00E+00 1.35E+05 8.52E+07 Sb-124 2.57E+07 4.87E+05 1.01E+07 6.25E+04 0.00E+00 2.00E+07 7.31E+08 Sb-125 2.04E+07 2.28E+05 4.86E+06 2.08E+04 0.00E+00 1.58E+07 2.25E+08 IPEC ODCM Page 90 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12a ADULT GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.63E+07 5.90E+06 2.18E+06 4.90E+06 6.63E+07 0.00E+00 6.50E+07 Te-127m 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 0.00E+00 1.54E+08 Te-127 6.53E+02 2.34E+02 1.41E+02 4.84E+02 2.66E+03 0.00E+00 5.15E+04 Te-129m 6.02E+07 2.25E+07 9.53E+06 2.07E+07 2.51E+08 0.00E+00 3.03E+08 Te-129 2.82E-10 1.06E-10 6.88E-11 2.17E-10 1.19E-09 0.00E+00 2.13E-10 Te-131m 3.61E+05 1.77E+05 1.47E+05 2.80E+05 1.79E+06 0.00E+00 1.75E+07 Te-131 3.60E-33 1.51E-33 1.14E-33 2.96E-33 1.58E-32 0.00E+00 5.10E-34 Te-132 2.40E+06 1.55E+06 1.46E+06 1.72E+06 1.50E+07 0.00E+00 7.35E+07 I-130 4.20E+05 1.24E+06 4.89E+05 1.05E+08 1.93E+06 0.00E+00 1.07E+06 I-131 2.96E+08 4.23E+08 2.43E+08 1.39E+11 7.26E+08 0.00E+00 1.12E+08 I-132 1.64E-01 4.39E-01 1.54E-01 1.54E+01 7.00E-01 0.00E+00 8.25E-02 I-133 3.87E+06 6.73E+06 2.05E+06 9.89E+08 1.17E+07 0.00E+00 6.05E+06 I-134 2.02E-12 5.48E-12 1.96E-12 9.49E-11 8.71E-12 0.00E+00 4.77E-15 I-135 1.28E+04 3.36E+04 1.24E+04 2.22E+06 5.39E+04 0.00E+00 3.80E+04 Cs-134 5.65E+09 1.35E+10 1.10E+10 0.00E+00 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.46E+08 0.00E+00 5.77E+08 7.90E+07 1.18E+08 Cs-137 7.38E+09 1.01E+10 6.61E+09 0.00E+00 3.43E+09 1.14E+09 1.95E+08 Cs-138 9.04E-24 1.79E-23 8.85E-24 0.00E+00 1.31E-23 1.30E-24 7.62E-29 Ba-139 3.92E-08 2.79E-11 1.15E-09 0.00E+00 2.61E-11 1.58E-11 6.94E-08 Ba-140 2.68E+07 3.37E+04 1.76E+06 0.00E+00 1.15E+04 1.93E+04 5.52E+07 Ba-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 4.52E+00 2.28E+00 6.02E-01 0.00E+00 0.00E+00 0.00E+00 1.67E+05 La-142 9.34E-12 4.25E-12 1.06E-12 0.00E+00 0.00E+00 0.00E+00 3.10E-08 Ce-141 4.84E+03 3.28E+03 3.72E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 Ce-143 4.16E+01 3.07E+04 3.40E+00 0.00E+00 1.35E+01 0.00E+00 1.15E+06 Ce-144 3.58E+05 1.50E+05 1.92E+04 0.00E+00 8.87E+04 0.00E+00 1.21E+08 Pr-143 1.58E+02 6.33E+01 7.83E+00 0.00E+00 3.66E+01 0.00E+00 6.92E+05 Pr-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd-147 9.42E+01 1.09E+02 6.51E+00 0.00E+00 6.36E+01 0.00E+00 5.22E+05 W-187 6.56E+03 5.48E+03 1.92E+03 0.00E+00 0.00E+00 0.00E+00 1.80E+06 Np-239 3.68E+00 3.62E-01 2.00E-01 0.00E+00 1.13E+00 0.00E+00 7.43E+04 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 1.28E+06 2.13E+06 0.00E+00 0.00E+00 0.00E+00 3.25E+07 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 3.29E-12 8.32E-13 3.04E-13 0.00E+00 9.71E-13 0.00E+00 3.07E-09 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 8.90E-19 5.83E-19 3.57E-19 7.78E-19 5.63E-18 0.00E+00 9.87E-22 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 91 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12b TEEN GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 Be-7 3.05E+03 6.83E+03 3.41E+03 0.00E+00 7.23E+03 0.00E+00 8.31E+05 Na-24 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 P-32 3.15E+10 1.95E+09 1.22E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09 Cr-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 Mn-54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.18E+06 0.00E+00 2.87E+07 Mn-56 0.00E+00 7.36E-03 1.31E-03 0.00E+00 9.31E-03 0.00E+00 4.84E-01 Fe-55 4.45E+07 3.16E+07 7.36E+06 0.00E+00 0.00E+00 2.00E+07 1.37E+07 Fe-59 5.18E+07 1.21E+08 4.67E+07 0.00E+00 0.00E+00 3.81E+07 2.86E+08 Co-58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.09E+08 Co-60 0.00E+00 2.78E+07 6.26E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 Ni-63 1.18E+10 8.35E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 Ni-65 6.77E-01 8.65E-02 3.94E-02 0.00E+00 0.00E+00 0.00E+00 4.69E+00 Cu-64 0.00E+00 4.25E+04 2.00E+04 0.00E+00 1.07E+05 0.00E+00 3.29E+06 Zn-65 2.11E+09 7.31E+09 3.41E+09 0.00E+00 4.68E+09 0.00E+00 3.10E+09 Zn-69 9.55E-12 1.82E-11 1.27E-12 0.00E+00 1.19E-11 0.00E+00 3.35E-11 Br-83 0.00E+00 0.00E+00 1.79E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.88E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 2.67E+09 0.00E+00 7.66E+07 0.00E+00 0.00E+00 0.00E+00 3.18E+08 Sr-90 6.61E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 Sr-91 5.31E+04 0.00E+00 2.11E+03 0.00E+00 0.00E+00 0.00E+00 2.41E+05 Sr-92 8.94E-01 0.00E+00 3.81E-02 0.00E+00 0.00E+00 0.00E+00 2.28E+01 Y-90 1.30E+02 0.00E+00 3.50E+00 0.00E+00 0.00E+00 0.00E+00 1.07E+06 Y-91m 1.10E-19 0.00E+00 4.19E-21 0.00E+00 0.00E+00 0.00E+00 5.17E-18 Y-91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 Y-92 1.03E-04 0.00E+00 2.98E-06 0.00E+00 0.00E+00 0.00E+00 2.83E+00 Y-93 4.12E-01 0.00E+00 1.13E-02 0.00E+00 0.00E+00 0.00E+00 1.26E+04 Zr-95 1.65E+03 5.20E+02 3.58E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 Zr-97 7.88E-01 1.56E-01 7.19E-02 0.00E+00 2.37E-01 0.00E+00 4.22E+04 Nb-95 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 Mo-99 0.00E+00 4.47E+07 8.52E+06 0.00E+00 1.02E+08 0.00E+00 8.01E+07 Tc-99m 5.76E+00 1.61E+01 2.08E+02 0.00E+00 2.39E+02 8.92E+00 1.05E+04 Tc-101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 1.81E+03 0.00E+00 7.74E+02 0.00E+00 6.38E+03 0.00E+00 1.51E+05 Ru-105 1.56E-03 0.00E+00 6.07E-04 0.00E+00 1.97E-02 0.00E+00 1.26E+00 Ru-106 3.75E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 Ag-110m 9.63E+07 9.11E+07 5.54E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 Sb-122 4.77E+05 9.29E+03 1.39E+05 6.06E+03 0.00E+00 2.98E+05 1.00E+08 Sb-124 4.58E+07 8.44E+05 1.79E+07 1.04E+05 0.00E+00 4.00E+07 9.26E+08 Sb-125 3.65E+07 3.99E+05 8.53E+06 3.48E+04 0.00E+00 3.18E+07 2.83E+08 IPEC ODCM Page 92 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12b TEEN GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.00E+07 1.08E+07 4.02E+06 8.39E+06 0.00E+00 0.00E+00 8.86E+07 Te-127m 8.44E+07 2.99E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.10E+08 Te-127 1.21E+03 4.29E+02 2.60E+02 8.35E+02 4.90E+03 0.00E+00 9.34E+04 Te-129m 1.10E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 0.00E+00 4.13E+08 Te-129 5.20E-10 1.94E-10 1.26E-10 3.71E-10 2.18E-09 0.00E+00 2.84E-09 Te-131m 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.29E+06 0.00E+00 2.53E+07 Te-131 6.58E-33 2.71E-33 2.06E-33 5.07E-33 2.88E-32 0.00E+00 5.40E-34 Te-132 4.29E+06 2.72E+06 2.56E+06 2.87E+06 2.61E+07 0.00E+00 8.61E+07 I-130 7.38E+05 2.14E+06 8.53E+05 1.74E+08 3.29E+06 0.00E+00 1.64E+06 I-131 5.37E+08 7.52E+08 4.04E+08 2.19E+11 1.29E+09 0.00E+00 1.49E+08 I-132 2.91E-01 7.62E-01 2.74E-01 2.57E+01 1.20E+00 0.00E+00 3.32E-01 I-133 7.07E+06 1.20E+07 3.66E+06 1.67E+09 2.10E+07 0.00E+00 9.07E+06 I-134 3.58E-12 9.50E-12 3.41E-12 1.58E-10 1.50E-11 0.00E+00 1.25E-13 I-135 2.28E+04 5.87E+04 2.18E+04 3.78E+06 9.27E+04 0.00E+00 6.51E+04 Cs-134 9.82E+09 2.31E+10 1.07E+10 0.00E+00 7.34E+09 2.80E+09 2.87E+08 Cs-136 4.47E+08 1.76E+09 1.18E+09 0.00E+00 9.57E+08 1.51E+08 1.42E+08 Cs-137 1.34E+10 1.78E+10 6.20E+09 0.00E+00 6.06E+09 2.35E+09 2.53E+08 Cs-138 1.64E-23 3.15E-23 1.57E-23 0.00E+00 2.33E-23 2.71E-24 1.43E-26 Ba-139 7.24E-08 5.09E-11 2.11E-09 0.00E+00 4.80E-11 3.51E-11 6.46E-07 Ba-140 4.84E+07 5.93E+04 3.12E+06 0.00E+00 2.01E+04 3.99E+04 7.46E+07 Ba-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 8.12E+00 3.99E+00 1.06E+00 0.00E+00 0.00E+00 0.00E+00 2.29E+05 La-142 1.69E-11 7.49E-12 1.86E-12 0.00E+00 0.00E+00 0.00E+00 2.28E-07 Ce-141 8.88E+03 5.93E+03 6.81E+02 0.00E+00 2.79E+03 0.00E+00 1.70E+07 Ce-143 7.64E+01 5.56E+04 6.21E+00 0.00E+00 2.49E+01 0.00E+00 1.67E+06 Ce-144 6.58E+05 2.72E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 Pr-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.54E+05 Pr-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd-147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.11E+05 W-187 1.20E+04 9.78E+03 3.43E+03 0.00E+00 0.00E+00 0.00E+00 2.65E+06 Np-239 7.03E+00 6.63E-01 3.68E-01 0.00E+00 2.08E+00 0.00E+00 1.07E+05 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 2.25E+06 3.76E+06 0.00E+00 0.00E+00 0.00E+00 4.19E+07 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 5.99E-12 1.49E-12 5.43E-13 0.00E+00 1.74E-12 0.00E+00 3.55E-08 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 1.59E-18 1.02E-18 1.06E-18 1.30E-18 9.72E-18 0.00E+00 5.89E-20 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 93 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12c CHILD GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 Be-7 7.49E+03 1.27E+04 8.38E+03 0.00E+00 1.25E+04 0.00E+00 7.11E+05 Na-24 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 P-32 7.78E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 Cr-51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 Mn-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.88E+06 0.00E+00 1.76E+07 Mn-56 0.00E+00 1.28E-02 2.90E-03 0.00E+00 1.55E-02 0.00E+00 1.86E+00 Fe-55 1.12E+08 5.93E+07 1.84E+07 0.00E+00 0.00E+00 3.35E+07 1.10E+07 Fe-59 1.20E+08 1.94E+08 9.68E+07 0.00E+00 0.00E+00 5.64E+07 2.02E+08 Co-58 0.00E+00 1.21E+07 3.71E+07 0.00E+00 0.00E+00 0.00E+00 7.07E+07 Co-60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 Ni-63 2.96E+10 1.59E+09 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 Ni-65 1.66E+00 1.56E-01 9.10E-02 0.00E+00 0.00E+00 0.00E+00 1.91E+01 Cu-64 0.00E+00 7.46E+04 4.51E+04 0.00E+00 1.80E+05 0.00E+00 3.50E+06 Zn-65 4.13E+09 1.10E+10 6.85E+09 0.00E+00 6.94E+09 0.00E+00 1.93E+09 Zn-69 2.35E-11 3.39E-11 3.13E-12 0.00E+00 2.06E-11 0.00E+00 2.14E-09 Br-83 0.00E+00 0.00E+00 4.40E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 6.51E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 8.77E+09 5.39E+09 0.00E+00 0.00E+00 0.00E+00 5.64E+08 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 6.62E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.56E+08 Sr-90 1.12E+11 0.00E+00 2.83E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 Sr-91 1.30E+05 0.00E+00 4.92E+03 0.00E+00 0.00E+00 0.00E+00 2.88E+05 Sr-92 2.18E+00 0.00E+00 8.75E-02 0.00E+00 0.00E+00 0.00E+00 4.13E+01 Y-90 3.21E+02 0.00E+00 8.60E+00 0.00E+00 0.00E+00 0.00E+00 9.15E+05 Y-91m 2.68E-19 0.00E+00 9.74E-21 0.00E+00 0.00E+00 0.00E+00 5.24E-16 Y-91 3.90E+04 0.00E+00 1.04E+03 0.00E+00 0.00E+00 0.00E+00 5.20E+06 Y-92 2.53E-04 0.00E+00 7.24E-06 0.00E+00 0.00E+00 0.00E+00 7.31E+00 Y-93 1.01E+00 0.00E+00 2.78E-02 0.00E+00 0.00E+00 0.00E+00 1.51E+04 Zr-95 3.83E+03 8.42E+02 7.50E+02 0.00E+00 1.21E+03 0.00E+00 8.79E+05 Zr-97 1.92E+00 2.77E-01 1.64E-01 0.00E+00 3.98E-01 0.00E+00 4.20E+04 Nb-95 3.18E+05 1.24E+05 8.85E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+08 Mo-99 0.00E+00 8.13E+07 2.01E+07 0.00E+00 1.74E+08 0.00E+00 6.73E+07 Tc-99m 1.32E+01 2.59E+01 4.29E+02 0.00E+00 3.76E+02 1.32E+01 1.47E+04 Tc-101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 4.28E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 0.00E+00 1.11E+05 Ru-105 3.82E-03 0.00E+00 1.39E-03 0.00E+00 3.36E-02 0.00E+00 2.49E+00 Ru-106 9.24E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 Ag-110m 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 Sb-122 1.17E+06 1.73E+04 3.44E+05 1.50E+04 0.00E+00 4.77E+05 9.02E+07 Sb-124 1.09E+08 1.41E+06 3.80E+07 2.39E+05 0.00E+00 6.02E+07 6.78E+08 Sb-125 8.69E+07 6.70E+05 1.82E+07 8.06E+04 0.00E+00 4.84E+07 2.08E+08 IPEC ODCM Page 94 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12c CHILD GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 7.38E+07 2.00E+07 9.84E+06 2.07E+07 0.00E+00 0.00E+00 7.12E+07 Te-127m 2.08E+08 5.60E+07 2.47E+07 4.97E+07 5.93E+08 0.00E+00 1.68E+08 Te-127 2.98E+03 8.02E+02 6.38E+02 2.06E+03 8.47E+03 0.00E+00 1.16E+05 Te-129m 2.71E+08 7.58E+07 4.21E+07 8.75E+07 7.97E+08 0.00E+00 3.31E+08 Te-129 1.28E-09 3.58E-10 3.04E-10 9.15E-10 3.75E-09 0.00E+00 7.98E-08 Te-131m 1.60E+06 5.53E+05 5.89E+05 1.14E+06 5.35E+06 0.00E+00 2.24E+07 Te-131 1.62E-32 4.93E-33 4.81E-33 1.24E-32 4.89E-32 0.00E+00 8.49E-32 Te-132 1.02E+07 4.53E+06 5.48E+06 6.60E+06 4.21E+07 0.00E+00 4.57E+07 I-130 1.73E+06 3.49E+06 1.80E+06 3.84E+08 5.22E+06 0.00E+00 1.63E+06 I-131 1.30E+09 1.31E+09 7.45E+08 4.33E+11 2.15E+09 0.00E+00 1.17E+08 I-132 6.89E-01 1.27E+00 5.82E-01 5.87E+01 1.94E+00 0.00E+00 1.49E+00 I-133 1.72E+07 2.12E+07 8.03E+06 3.94E+09 3.54E+07 0.00E+00 8.56E+06 I-134 8.48E-12 1.58E-11 7.25E-12 3.62E-10 2.41E-11 0.00E+00 1.04E-11 I-135 5.40E+04 9.72E+04 4.60E+04 8.61E+06 1.49E+05 0.00E+00 7.40E+04 Cs-134 2.26E+10 3.72E+10 7.84E+09 0.00E+00 1.15E+10 4.13E+09 2.00E+08 Cs-136 1.01E+09 2.77E+09 1.79E+09 0.00E+00 1.48E+09 2.20E+08 9.74E+07 Cs-137 3.22E+10 3.09E+10 4.55E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08 Cs-138 3.98E-23 5.53E-23 3.51E-23 0.00E+00 3.89E-23 4.19E-24 2.55E-23 Ba-139 1.78E-07 9.50E-11 5.16E-09 0.00E+00 8.29E-11 5.59E-11 1.03E-05 Ba-140 1.17E+08 1.02E+05 6.82E+06 0.00E+00 3.33E+04 6.10E+04 5.92E+07 Ba-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 1.94E+01 6.80E+00 2.29E+00 0.00E+00 0.00E+00 0.00E+00 1.89E+05 La-142 4.07E-11 1.30E-11 4.06E-12 0.00E+00 0.00E+00 0.00E+00 2.57E-06 Ce-141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.78E+03 0.00E+00 1.36E+07 Ce-143 1.87E+02 1.02E+05 1.47E+01 0.00E+00 4.26E+01 0.00E+00 1.49E+06 Ce-144 1.62E+06 5.09E+05 8.66E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 Pr-143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 Pr-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd-147 4.45E+02 3.60E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5.70E+05 W-187 2.91E+04 1.72E+04 7.73E+03 0.00E+00 0.00E+00 0.00E+00 2.42E+06 Np-239 1.73E+01 1.24E+00 8.73E-01 0.00E+00 3.59E+00 0.00E+00 9.19E+04 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 3.84E+06 7.77E+06 0.00E+00 0.00E+00 0.00E+00 3.14E+07 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 1.46E-11 2.63E-12 1.23E-12 0.00E+00 2.92E-12 0.00E+00 8.12E-07 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 3.77E-18 1.70E-18 2.26E-18 2.98E-18 1.57E-17 0.00E+00 1.72E-17 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 95 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12d INFANT GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 Be-7 1.43E+04 3.00E+04 1.59E+04 0.00E+00 2.12E+04 0.00E+00 7.05E+05 Na-24 1.54E+07 1.54E+07 1.54E+07 1.54E+07 1.54E+07 1.54E+07 1.54E+07 P-32 1.60E+11 9.43E+09 6.21E+09 0.00E+00 0.00E+00 0.00E+00 2.17E+09 Cr-51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 Mn-54 0.00E+00 3.90E+07 8.84E+06 0.00E+00 8.64E+06 0.00E+00 1.43E+07 Mn-56 0.00E+00 3.14E-02 5.42E-03 0.00E+00 2.70E-02 0.00E+00 2.85E+00 Fe-55 1.35E+08 8.73E+07 2.33E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 Fe-59 2.24E+08 3.92E+08 1.54E+08 0.00E+00 0.00E+00 1.16E+08 1.87E+08 Co-58 0.00E+00 2.42E+07 6.05E+07 0.00E+00 0.00E+00 0.00E+00 6.04E+07 Co-60 0.00E+00 8.82E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 Ni-63 3.49E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 Ni-65 3.50E+00 3.97E-01 1.80E-01 0.00E+00 0.00E+00 0.00E+00 3.02E+01 Cu-64 0.00E+00 1.86E+05 8.59E+04 0.00E+00 3.14E+05 0.00E+00 3.81E+06 Zn-65 5.55E+09 1.90E+10 8.78E+09 0.00E+00 9.23E+09 0.00E+00 1.61E+10 Zn-69 5.00E-11 9.00E-11 6.70E-12 0.00E+00 3.74E-11 0.00E+00 7.34E-09 Br-83 0.00E+00 0.00E+00 9.34E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.26E-22 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.69E+08 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 1.26E+10 0.00E+00 3.61E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+08 Sr-90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 Sr-91 2.72E+05 0.00E+00 9.83E+03 0.00E+00 0.00E+00 0.00E+00 3.21E+05 Sr-92 4.64E+00 0.00E+00 1.72E-01 0.00E+00 0.00E+00 0.00E+00 5.00E+01 Y-90 6.80E+02 0.00E+00 1.82E+01 0.00E+00 0.00E+00 0.00E+00 9.39E+05 Y-91m 5.67E-19 0.00E+00 1.93E-20 0.00E+00 0.00E+00 0.00E+00 1.89E-15 Y-91 7.33E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.25E+06 Y-92 5.38E-04 0.00E+00 1.51E-05 0.00E+00 0.00E+00 0.00E+00 1.03E+01 Y-93 2.16E+00 0.00E+00 5.87E-02 0.00E+00 0.00E+00 0.00E+00 1.70E+04 Zr-95 6.80E+03 1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.26E+05 Zr-97 4.06E+00 6.97E-01 3.18E-01 0.00E+00 7.03E-01 0.00E+00 4.45E+04 Nb-95 5.94E+05 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.06E+08 Mo-99 0.00E+00 2.08E+08 4.05E+07 0.00E+00 3.11E+08 0.00E+00 6.85E+07 Tc-99m 2.75E+01 5.67E+01 7.30E+02 0.00E+00 6.10E+02 2.96E+01 1.65E+04 Tc-101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 8.67E+03 0.00E+00 2.90E+03 0.00E+00 1.80E+04 0.00E+00 1.05E+05 Ru-105 8.05E-03 0.00E+00 2.71E-03 0.00E+00 5.92E-02 0.00E+00 3.20E+00 Ru-106 1.90E+05 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 1.44E+06 Ag-110m 3.86E+08 2.82E+08 1.86E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 Sb-122 2.51E+06 4.59E+04 7.31E+05 3.75E+04 0.00E+00 1.30E+06 9.13E+07 Sb-124 2.09E+08 3.08E+06 6.49E+07 5.56E+05 0.00E+00 1.31E+08 6.46E+08 Sb-125 1.50E+08 1.45E+06 3.08E+07 1.87E+05 0.00E+00 9.38E+07 1.99E+08 IPEC ODCM Page 96 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-12d INFANT GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

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

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.51E+08 5.04E+07 2.04E+07 5.07E+07 0.00E+00 0.00E+00 7.18E+07 Te-127m 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 Te-127 6.32E+03 2.12E+03 1.36E+03 5.14E+03 1.54E+04 0.00E+00 1.33E+05 Te-129m 5.57E+08 1.91E+08 8.58E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 Te-129 2.72E-09 9.37E-10 6.35E-10 2.28E-09 6.77E-09 0.00E+00 2.17E-07 Te-131m 3.38E+06 1.36E+06 1.12E+06 2.75E+06 9.35E+06 0.00E+00 2.29E+07 Te-131 3.43E-32 1.27E-32 9.62E-33 3.06E-32 8.76E-32 0.00E+00 1.38E-30 Te-132 2.11E+07 1.04E+07 9.75E+06 1.54E+07 6.53E+07 0.00E+00 3.87E+07 I-130 3.55E+06 7.81E+06 3.13E+06 8.75E+08 8.58E+06 0.00E+00 1.67E+06 I-131 2.72E+09 3.20E+09 1.41E+09 1.05E+12 3.74E+09 0.00E+00 1.14E+08 I-132 1.43E+00 2.90E+00 1.03E+00 1.36E+02 3.24E+00 0.00E+00 2.35E+00 I-133 3.63E+07 5.28E+07 1.55E+07 9.60E+09 6.21E+07 0.00E+00 8.93E+06 I-134 1.76E-11 3.60E-11 1.28E-11 8.40E-10 4.03E-11 0.00E+00 3.73E-11 I-135 1.12E+05 2.23E+05 8.14E+04 2.00E+07 2.49E+05 0.00E+00 8.08E+04 Cs-134 3.65E+10 6.80E+10 6.87E+09 0.00E+00 1.75E+10 7.18E+09 1.85E+08 Cs-136 1.97E+09 5.79E+09 2.16E+09 0.00E+00 2.31E+09 4.72E+08 8.80E+07 Cs-137 5.15E+10 6.02E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.88E+08 Cs-138 8.39E-23 1.36E-22 6.61E-23 0.00E+00 6.80E-23 1.06E-23 2.18E-22 Ba-139 3.79E-07 2.51E-10 1.10E-08 0.00E+00 1.51E-10 1.52E-10 2.40E-05 Ba-140 2.40E+08 2.40E+05 1.24E+07 0.00E+00 5.71E+04 1.48E+05 5.91E+07 Ba-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 4.06E+01 1.60E+01 4.12E+00 0.00E+00 0.00E+00 0.00E+00 1.88E+05 La-142 8.55E-11 3.14E-11 7.51E-12 0.00E+00 0.00E+00 0.00E+00 5.33E-06 Ce-141 4.34E+04 2.64E+04 3.11E+03 0.00E+00 8.15E+03 0.00E+00 1.37E+07 Ce-143 3.97E+02 2.63E+05 3.00E+01 0.00E+00 7.67E+01 0.00E+00 1.54E+06 Ce-144 2.33E+06 9.52E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.33E+08 Pr-143 1.49E+03 5.55E+02 7.36E+01 0.00E+00 2.06E+02 0.00E+00 7.84E+05 Pr-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd-147 8.81E+02 9.05E+02 5.55E+01 0.00E+00 3.49E+02 0.00E+00 5.74E+05 W-187 6.12E+04 4.26E+04 1.47E+04 0.00E+00 0.00E+00 0.00E+00 2.50E+06 Np-239 3.66E+01 3.27E+00 1.85E+00 0.00E+00 6.53E+00 0.00E+00 9.46E+04 K-40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 0.00E+00 8.95E+06 1.46E+07 0.00E+00 0.00E+00 0.00E+00 3.05E+07 Sr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cd-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hg-203 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IPEC ODCM Page 97 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-13 Total Body & Skin Ground Plane Dose Factors Ri(G) and Ri(S) 2 (m

  • mrem/yr per uCi/sec)

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

H-3 1.780E-09 0.00E+00 0.00E+00 Be-7 1.505E-07 0.00E+00 0.00E+00 Na-24 1.284E-05 1.19E+07 1.39E+07 P-32 5.614E-07 0.00E+00 0.00E+00 Cr-51 2.896E-07 4.66E+06 5.51E+06 Mn-54 2.567E-08 1.39E+09 1.62E+09 Mn-56 7.467E-05 9.03E+05 1.07E+06 Fe-55 8.141E-09 0.00E+00 0.00E+00 Fe-59 1.802E-07 2.72E+08 3.20E+08 Co-58 1.133E-07 3.79E+08 4.44E+08 Co-60 4.170E-09 2.15E+10 2.53E+10 Ni-63 2.290E-10 0.00E+00 0.00E+00 Ni-65 7.641E-05 2.97E+05 3.45E+05 Cu-64 1.516E-05 6.07E+05 6.88E+05 Zn-65 3.289E-08 7.46E+08 8.58E+08 Zn-69 2.027E-04 0.00E+00 0.00E+00 Br-83 8.056E-05 4.87E+03 7.08E+03 Br-84 3.633E-04 2.03E+05 2.36E+05 Br-85 3.851E-03 0.00E+00 0.00E+00 Rb-86 4.299E-07 8.99E+06 1.03E+07 Rb-88 6.490E-04 3.31E+04 3.78E+04 Rb-89 7.600E-04 1.21E+05 1.45E+05 Sr-89 1.589E-07 2.16E+04 2.51E+04 Sr-90 7.548E-10 0.00E+00 0.00E+00 Sr-91 2.027E-05 2.15E+06 2.51E+06 Sr-92 7.105E-05 7.77E+05 8.63E+05 Y-90 3.008E-06 4.48E+03 5.30E+03 Y-91m 2.324E-04 1.00E+05 1.16E+05 Y-91 1.371E-07 1.07E+06 1.21E+06 Y-92 5.439E-05 1.80E+05 2.14E+05 Y-93 1.906E-05 1.83E+05 2.51E+05 Zr-95 1.254E-07 2.45E+08 2.84E+08 Zr-97 1.139E-05 2.96E+06 3.44E+06 Nb-95 2.282E-07 1.37E+08 1.61E+08 Mo-99 2.917E-06 3.99E+06 4.62E+06 Tc-99m 3.198E-05 1.84E+05 2.11E+05 Tc-101 8.136E-04 2.04E+04 2.26E+04 Ru-103 2.042E-07 1.08E+08 1.26E+08 Ru-105 4.337E-05 6.36E+05 7.21E+05 Ru-106 2.179E-08 4.22E+08 5.07E+08 Ag-110m 3.210E-08 3.44E+09 4.01E+09 Sb-122 2.971E-06 0.00E+00 0.00E+00 Sb-124 1.333E-07 5.98E+08 6.90E+08 Sb-125 7.935E-09 2.34E+09 2.64E+09 IPEC ODCM Page 98 of 145 Revision 6

ODCM Part II - Calculational Methodologies Table 3-13 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 I-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 8.00E+09 Cs-136 6.124E-07 1.50E+08 1.70E+08 Cs-137 7.327E-10 1.03E+10 1.20E+10 Cs-138 3.588E-04 3.59E+05 4.10E+05 Ba-139 1.397E-04 1.05E+05 1.19E+05 Ba-140 6.297E-07 2.04E+07 2.34E+07 Ba-141 6.323E-04 4.17E+04 4.75E+04 Ba-142 1.090E-03 4.44E+04 5.06E+04 La-140 4.781E-06 1.92E+07 2.18E+07 La-142 1.249E-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 0.00E+00 0.00E+00 Pr-144 6.685E-04 1.83E+03 2.11E+03 Nd-147 7.306E-07 8.39E+06 1.01E+07 W-187 8.056E-06 2.36E+06 2.74E+06 Np-239 3.399E-06 1.71E+06 1.98E+06 K-40 1.717E-17 0.00E+00 0.00E+00 Co-57 2.961E-08 1.88E+08 2.07E+08 Sr-85 1.237E-07 0.00E+00 0.00E+00 Y-88 7.523E-08 0.00E+00 0.00E+00 Nb-94 1.083E-12 0.00E+00 0.00E+00 Nb-97 1.602E-04 1.76E+05 2.07E+05 Cd-109 1.729E-08 0.00E+00 0.00E+00 Sn-113 6.970E-08 0.00E+00 0.00E+00 Ba-133 2.047E-09 0.00E+00 0.00E+00 Te-134 2.764E-04 2.22E+04 2.66E+04 Ce-139 5.828E-08 0.00E+00 0.00E+00 Hg-203 1.722E-07 0.00E+00 0.00E+00 IPEC ODCM Page 99 of 145 Revision 6

ODCM Part II - Calculational Methodologies 4.0 TOTAL DOSE DETERMINATIONS 4.1 40CFR190 Dose Evaluation Per RECS D3.4, the direct radiation component for potential offsite dose is routinely determined and reported, along with doses from effluent. Radiological Support has determined bounding calculations (using References 26 through 29) as follows:

Direct Radiation Dose = VC + IRWSF + SGM + ISFSI + RMHAs where; VC = The Vapor Containment structures IRWSF = The Interim Radioactive Waste Storage Facility SGM = The Steam Generator Mausoleums (both units)

ISFSI = The Dry Cask Storage Facility, once active RMHA = Radioactive Material Handling Areas, as posted, summed Other structures or tanks are included as determined by Rad Support. The calculations in References 26 through 29 were performed in order to meet the requirements of the annual effluent report, and NRC Generic Letter 81-38, 11/10/1981, Storage of Low-Level Radioactive Wastes at Power Reactor Sites.

Offsite doses from onsite storage must be sufficiently low to account for other uranium fuel cycle sources (e.g., an additional dose of <1 mrem/year is not likely to cause the limits of 40 CFR 190 to be exceeded). On site dose limits will be controlled per 10CFR20 The IRWSF, SGM, and RMHAs fence line dose rates are limited by department procedures to keep dose rates at the SITE BOUNDARY fence < 1 mrem/yr based on calculations performed in References 26 through 29. These calculations contain realistic occupancy factors for the SITE BOUNDARY fence and the nearest neighbor.

ISFSI dose rate calculations and specification are bounded by a conservatively applied maximum annual dose of 17 mrem at the site boundary. This special bounding criteria ensure that combined offsite doses (effluent and direct shine) are in compliance with 40CFR190.

4.2 Doses From Liquid Releases Doses to real individuals can be determined with the same (maximum individual) methodology described in the ODCM, but with more realistic assumptions with regard to dilution, diet, and occupenncy. Actual radionuclide concentrations in foodstuffs can be applied per the Radiological Environmental Monitoring Program (REMP), such that more accurate doses are determined from actual intakes, rather than models only.

4.3 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 re-calculate more accurate doses. The REMP can also provide actual concentrations to apply for a more accurate determination than modeling alone.

IPEC ODCM Page 100 of 145 Revision 6

ODCM Part II - Calculational Methodologies 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-0133 and Reg Guide 1.109 methodology can be supplanted by more specific values if there has been sufficient science and pedigree involved in their determination.

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

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

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

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

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

IPEC ODCM Page 101 of 145 Revision 6

ODCM Part II - Calculational Methodologies 5.0 LOWER LIMIT OF DETECTION (LLD)

The LLD is the smallest concentration of radioactive material in a sample that will yield a net count above system background, and be detected with 95% probability, with a 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

+ 3.29 sb

  • 1 + ( T b )

T Ts LLD = s - t E*V

  • k* Y
  • e where:

LLD = The lower limit of detection as defined above (as picocurie per unit mass or volume)

Ts = The sample counting time in minutes sb = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

Tb = The background count time in minutes E= The counting efficiency (as counts per transformation)

V= The sample size (in units of mass or volume) k= A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per Ci)

Y= The fractional radiochemical yield (when applicable)

= The radioactive decay constant for the particular radionuclide t= The elapsed time between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times.

The Radiological Environmental Monitoring Program, REMP, uses an LLD formula that assumes equal background and sample count times, in accordance with the RECS.

When the above LLD formula is more appropriate for the effluents program, it may be used.

IPEC ODCM Page 102 of 145 Revision 6

ODCM Part II - Calculational Methodologies The constants 2.71 and 3.29 and the general LLD equation were derived from the following two sources:

1) Currie, L.A. "Limits for Qualitative Detection of Quantitative Determination". (Anal. Chem.

40:586-593, 1968); and,

2) Mayer, Dauer "Application of Systematic Error Bounds to Detection Limits for Practical Counting".

(HP Journal 65(1): 89-91, 1993)

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that the LLD is defined as an a 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, which has been identified as the Critical Level. 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:

deciding that the radioactive material is present when it is not (a: Type I error), and the converse, failing to decide that it is present when it is (b: Type II error). The maximum acceptable Type I error (a), together with the standard deviation, Snet, of the net signal when the net signal equals zero, establish the Critical Level, Lc, upon which decisions may be based.

Operationally, an observed signal, S, must exceed Lc to yield the decision, detected.

Lc = kasb(1+Tb/Ts)0.5 where:

ka 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 Lc 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.

IPEC ODCM Page 103 of 145 Revision 6

ODCM Part II - Calculational Methodologies REFERENCES

1. U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", USNRC Report NUREG-0133, Washington D.C.

20555, October 1978.

2. 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.
3. 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, Revisions 1 and 0 (original draft for information only), USNRC Washington D.C. 20555, October 1977.
4. "An Evaluation to Demonstrate the Compliance of the Indian Point Reactors with the Design Objectives of 10CFR50, Appendix I", Consolidated Edison Company of New York, Inc. and Power Authority of the State of New York, February 1977.
5. U.S. Nuclear Regulatory Commission, "XOQDOQ Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC Report NUREG-0324, Washington D.C. 10555, September 1977. (Later updated by NUREG CR 2919).
6. "Semi-Annual Report of Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents for Indian Point Three", Power Authority of the State of New York, January 1, 1978 to June 30, 1980.
7. "Environmental Technical Specification Requirements for Indian Point Nuclear Generating Unit Number 3", Power Authority of the State of New York, December 12, 1975 (original ETSR).
8. U.S. Nuclear Regulatory Commission, "Radiological Effluent Technical Specification for PWR's",

USNRC Report NUREG-0472, Washington D.C. 20555.

9. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix ", Revision 1, USNRC, Washington D.C. 10555, October 1977.
10. IP-SMM-CY-001, "Radioactive Effluents Control Program" (formerly AP-11 for unit 3).
11. NUREG/CR-4007, 1984, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements".
12. New York University Medical Center, "Radioecological Studies of the Hudson River Progress Report (1986-1987)", N.Y.U. New York, New York 10016, March 1988.
13. IPI-DM-153, "Antimony Dose Factors", IPS Memorandum to M. Kerns from D. Mayer, August 8, 1988.
14. New York University Medical Center, "Radiological Studies of the Hudson River Progress Report (1987-1988)", N.Y.U. New York, New York 10016, September 1988.

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ODCM Part II - Calculational Methodologies

15. USNRC Regulatory Guide 1.111, "Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. Nuclear Regulatory Commission (October 1977, Rev. 1).
16. CRE Computer Code AEOLUS-3, "A Computer Code for the Determination of Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents During Continuous, Intermittent and Accident Conditions in Open-Terrain Sites, Coastal Sites and Deep-River Valleys," RAD-004, Version 1, Level 2 (June 1991).
17. CRE Engineering Calculation IP3-CALC-RAD-00001, "IP3 - Revised ODCM Atmospheric Dispersion Parameters (Multi-Year Hourly Data, Mixed-Mode Releases and Valley Effects, July 1991)," and updated reports from Entech Engineering (March 2005), by John N. Hamawi.
18. USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs," U.S. Nuclear Regulatory Commission (2/17/72) (Safety Guide 23 and and proposed revision 1 to the Reg Guide).
19. USNRC Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants," U.S. Nuclear Regulatory Commission (August 1979).
20. D. H. Slade, Ed., "Meteorology and Atomic Energy - 1968," USAEC, TID-24190 (1968).
21. WCRE-93-157, "IP3-Annual Average Atmospheric Dispersion and Deposition factors for Ground-Level Release, December , 1993 Memorandum Hamawi to Mayer.

22 NRC Generic Letter 89-01 (Technical Specification Amendment 199) with NUREG 1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors.

23. Improved Technical Specifications from NUREG 1431, Amendment 205, Feb 2001.
24. ERDA 660 (ORNL-4992), A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment .
25. International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases: Exposures of Critical Groups, Safety Series No. 57, IAEA, Vienna (1978).
26. IP3-CALC-RAD-00013, Radiological Analysis of Site Boundary Gamma Dose from Onsite Radioactive Material Holding Areas.
27. MicroShield Manual and Calculations, Grove Engineering.
28. M020.02, Calculations for Steam Generator Storage Facility Site Boundary Dose.
29. NYPA 3899.001, Calculations for Direct Shine Dose from the Interim Radioactive Waste Storage Facility.
30. IPEC CHM-04-035, Nuclide Mixtures for Instantaneous and Time Average Releases.
31. IPEC CHM-05-003, Site Specific Distances to Site Boundary and Nearest Resident.

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ODCM Part II - Calculational Methodologies

32. IPEC CHM-06-012, Updated Ground Water Dose Evaluations, Apr 2006.
33. IPEC CHM-05-042, Update to Initial Monitoring Well Offsite Dose Calculation, Dec 2005.
34. Indian Point Technical Specifications (all units).
35. Indian Point Final Safety Analysis Reports (all units).
36. 10CFR20, Standards for Protection Against Radiation.
37. 40CFR190, Environmental Rad Protection Standards for Nuclear Power Operations.
38. 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.
39. G. Knoll, Radiation Detection and Measurement, (1979)
40. TS (RS) 92-24, Ingestion Dose Factor Methodology.
41. NPG (RS) 92-88, Process and Effluent Monitor Energy Calibration.
42. NPG (RS) 92-97, Effective Stack Height for Blowdown Flash Tank Vent.
43. IPEC-CHM-05-022, Alternative Methods for Liq Rad Monitor Setpoints / Conv Factors.
44. IPEC Chemistry Department Procedures 0-CY-2730 and 0-CY-2740, Airborne and Liquid Radioactive Effluents.
45. IPEC-CHM-06-026, Reporting Levels and Lower Limits of Detection for Sr-90 in REMP.
46. IPEC-CHM-08-008, Reporting Levels and Lower Limits of Detection for Ni-63 in REMP.
47. Estimation of Carbon-14 in Nuclear Power Gaseous Effluents, EPRI, Nov 2010.
48. IPEC-CHM-10-014, Calculated C-14 Releases From IPEC.
49. IPEC-CHM-10-019, Liquid Effluent LLDs.
50. Document No. 32-9256934-001, Updated Valley Recirculation Effects and Revised Atmospheric Dispersion and Deposition Factors for Indian Point Units 2 and 3 Offsite Dose Calculation Manual (2006-2015 Site Meteorology), March 2017.

IPEC ODCM Page 106 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX A

SUMMARY

of RADIOLOGICAL EFFLUENT CONTROLS (RECS)

LIQUID: AIRBORNE:

Dose The diluted concentration of each Rate isotope in UNRESTRICTED AREAS Dose rate is limited at or beyond the SITE BOUNDARY to:

is limited to ten times the ECs of 10CFR20, defined as the Maximum 500 mrem/yr whole body, per site, for noble gases; Permissible Concentrations (MPCw) 3000 mrem/yr to the skin, per site, for noble gases; identified per Section D1.1. The 1500 mrem/yr to any organ, per site for iodine-131, diluted concentration of dissolved or tritium, or 8 day particulates.

entrained noble gases is limited to 2E-4 uCi/ml.

Cumulative Dose Dose commitment to any member Air Dose at the SITE BOUNDARY is limited to:

of public in UNRESTRICTED 5 mrad per quarter and 10 mrad per year for noble AREAS is limited to:

gases, gamma air dose;

1) In any calendar quarter, 1.5 10 mrad per quarter and 20 mrad per year for noble mrem to the total body and 5 gases, beta air dose.

mrem to any organ.

2) In a calendar year, 3 mrem to Maximum Individual Dose to a Member of the Public at the total body and 10 mrem to the nearest resident is limited to 7.5 mrem per qtr and any organ. 15 mrem per yr for Iodine, H-3, & 8 day particulates to any organ.

Dose Projection Projection of liquid effluent doses Projection of airborne effluent doses shall be computed shall be computed at least every 31 at least every 31 days. If projected doses exceed days. If projected doses exceed:

0.2 mrad gamma air dose, 0.06 mrem total body, or 0.4 mrad beta air dose, or 0.2 mrem critical organ, 0.3 mrem to any organ at the nearest residence, clean-up treatment systems are clean-up treatment systems are required to be required to be operational and operational.

applied to future releases.

TOTAL DOSE:

(includes all effluents, plus direct shine from holding pens, or ISFSI, etc) 25 mrem/yr, all sources, whole body or any organ except thyroid, 75 mrem/yr, all sources, thyroid.

IPEC ODCM Page 107 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX B (Page 1 of 2)

UNITS 1 and 2 LIQUID EFFLUENT SIMPLIFIED FLOW DIAGRAM Flash Tank Vent Discharge See App C Canal 21 22 23 24 SG SG SG SG R-49 SGBD Flash Tank Secondary Plant Turbine Hall Drains Secondary Boiler Blowdown Purification System (SBBPS).

Interim abandoned, EC 73608 Unit 1 North Curtain Compositor Drain System & Totalizer 4/21 R-62 FCU SW Sphere Foundation w/ totalizer Drain Sump R-46 U1 Foundation Drain R-53 13 WDST R-54 Processed Liq Waste Service Water 14 WDST R-39 21 CCW HX SW Service R-47 Water 22 CCW HX SW R-40 IE Bulletin 80-10 Includes Storm Drains, GW, Condensate, roof drains, Utility Tunnel Sumps, etc Hudson River Any other identified effluent is evaluated for inclusion in integrated totals.

IPEC ODCM Page 108 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX B (Page 2 or 2)

UNIT 3 LIQUID EFFLUENT SIMPLIFIED FLOW DIAGRAM Flash Tank Vent See Appendix C Monitor Tank Vent See Appendix C IPEC ODCM Page 109 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX C (Page 1 of 2)

UNITS 1 and 2 GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM R-27 Primary Aux Bldg (PAB) Unit 2 Vent R-44 atmosphere o

Waste Gas System RCV-014 R-50 Fuel Storage Fan Building MOB Exhaust R-5976 atmosphere 4/21 CSB Exhaust NSB Exhaust R-60 Unit 1 Stack atmosphere Unit 1 Annulus Exhaust House Service Boilers IPEC ODCM Page 110 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX C (Page 2 of 2)

UNIT 3 GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM Batch Release Points Vents Cont.

Main Release Point Monitor Condenser Tanks Liquid Waste Cont.

R15 Release R18 Point Condenser Air-eject To the river, per See Recirc Appendix B River Appendix B (on high alarm)

R14 R11 R12 Vapor PV Containment R27 Primary Primary Aux Auxiliary Bldg (PAB)

Building R20 Fill RCV-014 Waste Gas Cont.

Tanks Fill Release Point Fuel Storage fan Building R59 Cont.

Release Radioactive Point Machine Shop Trubine R46 Cont.

Administration Release Building Points

  1. 32 Aux Feed Pump Excess Steam Vent Main Steam Atmospherics and Safeties S/G B/D Flash Tank R19 STEAM Steam Vent
  1. 32 Aux GEN Generator Feed Pump Blow-down FlashTank to to BDR River IPEC ODCM Page 111 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX D Appendix D information deleted in Revision 6.

4/21 IPEC ODCM Page 112 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX E ALLOWED DILUTED CONCENTRATION (ADC)

The Allowed Diluted Concentration (ADC) is derived and calculated as follows:

MPCWt

  • CG MPCWt
  • CG MPCWt ADC or ADC or ADC Total activity CGCB 1CB CG Where; ADC = Allowed diluted concentration in Ci/ml MPCWt = Maximum permissible concentration in water for all isotopes (beta &

gamma), in uCi/ml, as defined in RECS D3.1.1, as follows:

Ci MPCWt i i

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

Dr CG E

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 D

CG Where:

D = Permissible discharge rate in gal/min B = Adjusted dilution flow (Available - E, above), in gpm Note that when there are no other releases (E=0), B simply becomes the available dilution flow.

IPEC ODCM Page 113 of 145 Revision 6

ODCM Part II - 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 monitors 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 43.

IPEC ODCM Page 114 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX G (Page 1 of 7)

ENVIRONMENTAL SAMPLING POINTS IPEC Sample Designation Station Location Distance Direction Number from U1 Stack DR1 57 Roa Hook 2.0 mi N DR2 59 Old Pemart Avenue 1.8 mi NNE DR3 90 Charles Point 0.88 mi NE DR4 28 Lents Cove 0.45 mi ENE DR5 35 Broadway and Bleakley Avenue 0.37 mi E DR6 88 Reuter-Stokes Pole #6 0.32 mi ESE DR7 14 Water Meter House 0.3 mi SE DR8 03 Service Center Building 0.35 mi SSE DR9 34 South East Corner of Site 0.52 mi S DR10 05 NYU Tower 0.88 mi SSW DR11 53 White Beach 0.92 mi SW DR12 74 West Shore Drive - South 1.59 mi WSW DR13 76 West Shore Drive - North 1.21 mi W DR14 78 Rt. 9W, across from R/S #14 1.2 mi WNW DR15 80 Rt. 9W - South of Ayers Road 1.02 mi NW DR16 82 Ayers Road 1.01 mi NNW DR17 58 Rt. 9D - Garrison 5.41 mi N DR18 60 Gallows Hill Road and Sprout Brook Road 5.02 mi NNE DR19 62 West Brook Drive (near the Community Center) 5.03 mi NE DR20 64 Lincoln Road - Cortlandt (School Parking Lot) 4.6 mi ENE DR21 66 Croton Ave. - Cortlandt 4.87 mi E DR22 67 Colabaugh Pond Rd. - Cortlandt 4.5 mi ESE DR23 69 Mt. Airy & Windsor Road 4.97 mi SE DR24 92 Warren Rd. - Cortlandt 3.84 mi SSE DR25 71 Warren Ave. - Haverstraw 4.83 mi S DR26 72 Railroad Ave. & 9W Haverstraw 4.53 mi SSW DR27 73 Willow Grove Rd. & Captain Faldermeyer Drive 4.97 mi SW DR28 81 Palisades Parkway, Lake Welch Exit 4.96 mi WSW DR29 77 Palisades Parkway 4.15 mi W DR30 79 Anthony Wayne Park 4.57 mi WNW DR31 75 Palisades Parkway 4.65 mi NW DR32 83 Rt. 9W Fort Montgomery 4.82 mi NNW DR33 33 Hamilton Street (Substation) 2.88 mi NE DR34 38 Furnace Dock (Substation) 3.43 mi SE DR35 89 Highland Ave. & Sprout Brook Rd. (near Rock Cut) 2.89 mi NNE DR36 61 Lower South Street and Franklin Street 1.3 mi NE DR37 56 Verplanck - Broadway & 6th St. 1.25 mi SSW DR38 20 Cortlandt Yacht Club (aka Montrose Marina) 1.5 mi S DR39 29 Grassy Point 3.37 mi SSW DR40 23 *Roseton 20.7 mi N DR41 27 Croton Point 6.36 mi SSE

  • Control Station IPEC ODCM Page 115 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX G (Page 2 of 7)

ENVIRONMENTAL SAMPLING POINTS IPEC Sample Designation Station Location Distance Direction Number from U1 Stack Airborne A1 4 Algonquin Gas Line 0.28 mi SW A2 94 IPEC Training Center 0.38 mi S A3 95 Meteorological Tower 0.46 mi SSW A4 5 NYU Tower 0.88 mi SSW A5 23 *Roseton 20.7 mi N Waterborne - Surface (Hudson River Water)

Wa1 9 *Roseton 20.7 miles N Wa2 10 Discharge Canal (Mixing Zone) 0.3 mi - WSW Waterborne - Drinking Wb1 7 Camp Field Reservoir 3.4 mi NE Soil From Shoreline Wc1 53 White Beach 0.92 mi SW Wc2 50 *Manitou Inlet 4.48 mi NNW Ingestion-Food Products (Broad Leaf Vegetation)

Ic1 95 Meteorological Tower 0.46 mi SSW Ic2 94 IPEC Training Center 0.39 mi S Ic3 23 *Roseton 20.7 mi N Exposure Pathway/Sample Designation: Milk 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 (la1 - la4).

Exposure Pathway/Sample Designation: Ingestion-Fish and Invertebrates The RECS designate three required sample locations labeled Ib1/25, Ib2/23 and Ib3/107. The downstream Ib1 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 Pumpkin Seed American Eel Bluegill Sunfish White Catfish Crabs White Perch Blueback Herring

  • Control Station IPEC ODCM Page 116 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX G (Page 3 of 7)

ENVIRONMENTAL SAMPLING POINTS IPEC Sample Sample Designation Station Location Distance Direction Types Number from U1 Stack DR8 3 Service Center Building 0.35 mi SSE 3 A1 4 Algonquin Gas Line 0.28 mi SW 1,2 A4, DR10 5 NYU Tower 0.88 mi SSW 1,2,3 Wb1 7 Camp Field Reservoir 3.4 mi NE 6 Wa1 9 *Roseton 20.7 mi N 7 Wa2 10 Discharge Canal (Mixing Zone) 0.3 mi WSW 7 DR7 14 Water Meter House 0.3 mi SE 3 DR38 20 Cortlandt Yacht Club (AKA Montrose Marina) 1.5 mi S 3 Ib2,A5,DR40,Ic3 23 *Roseton 20.7 mi N 1,2,3,4,12 Ib1 25 where available, downstream N/A N/A 12 DR41 27 Croton Point 6.36 mi SSE 1,2,3 DR4 28 Lents Cove 0.45 mi ENE 3 DR39 29 Grassy Point 3.37 mi SSW 1,2,3 DR33 33 Hamilton Street (Substation) 2.88 mi NE 3 DR9 34 South East Corner of Site 0.52 mi S 3 DR5 35 Broadway & Bleakley Avenue 0.37 mi E 3 DR34 38 Furnace Dock (Substation) 3.43 mi SE 3 Wc2 50 *Manitou Inlet 4.48 mi NNW 10 Wc1, DR11 53 White Beach 0.92 mi SW 3,10 DR37 56 Verplanck - Broadway & 6th Street 1.25 mi SSW 3 DR1 57 Roa Hook 2.0 mi N 3 DR17 58 Rt. 9D Garrison 5.41 mi N 3 DR2 59 Old Pemart Ave. 1.8 mi NNE 3 DR18 60 Gallows Hill Road and Sprout Brook Road 5.02 mi NNE 3 DR36 61 Lower South Street and Franklin Street 1.3 mi NE 3 DR19 62 West Brook Drive (near the Community Center) 5.03 mi NE 3 DR20 64 Lincoln Road - Cortlandt (School Parking Lot) 4.6 mi ENE 3 DR21 66 Croton Ave. - Cortlandt 4.87 mi E 3 DR22 67 Colabaugh Pond Rd. - Cortlandt 4.5 mi ESE 3 DR23 69 Mt. Airy & Windsor Road 4.97 mi SE 3

  • Control Station IPEC ODCM Page 117 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX G (Page 4 of 7)

ENVIRONMENTAL SAMPLING POINTS Sample IPEC Direction Sample Designation Station # Location Distance from U1 Stack Types DR25 71 Warren Avenue - Haverstraw 4.83 mi S 3 DR26 72 Railroad Ave. & 9W - Haverstraw 4.53 mi SSW 3 DR27 73 Willow Grove Rd. & Captain Faldermeyer Dr 4.97 mi SW 3 DR12 74 West Shore Drive - South 1.59 mi WSW 3 DR31 75 Palisades Parkway 4.65 mi NW 3 DR13 76 West Shore Drive - North 1.21 mi W 3 DR29 77 Palisades Parkway 4.15 mi W 3 DR14 78 Rte. 9W, across from R/S #14 1.2 mi WNW 3 DR30 79 Anthony Wayne Park 4.57 mi WNW 3 DR15 80 Rte. 9W - South of Ayers Road 1.02 mi NW 3 DR28 81 Palisades Parkway, Lake Welch Exit 4.96 mi WSW 3 DR16 82 Ayers Road 1.01 mi NNW 3 DR32 83 Rte. 9W - Fort Montgomery 4.82 mi NNW 3 DR6 88 Reuter-Stokes Pole #6 0.32 mi ESE 3 DR35 89 Highland Ave. & Sprout Brook Road (near rock cut) 2.89 mi NNE 3 DR3 90 Charles Point 0.88 mi NE 3 DR24 92 Warren Rd. - Cortlandt 3.84 mi SSE 3 A2, Ic2 94 IPEC Training Center 0.39 mi S 1,2,4 A3, Ic1 95 Meteorological Tower 0.46 mi SSW 1,2,4 Ib3 107 Vicinity of Haverstraw Bay 2.50 mi SSW 12

  • Control Station Sample types are:

1 Air particulates 9 H.R. aquatic vegetation 2 Radioiodine 10 H.R. shoreline soil 3 Direct gamma 12 Fish and invertebrates 4 Broadleaf vegetation 13 Groundwater well 6 Drinking water 7 Hudson River (H.R.) water IPEC ODCM Page 118 of 145 Revision 6

ODCM Part II - Calculational Methodologies IPEC ODCM Page 119 of 145 Revision 6

ODCM Part II - Calculational Methodologies IPEC ODCM Page 120 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX G (Page 7 of 7)

ENVIRONMENTAL SAMPLING POINTS ADDITIONAL SAMPLING LOCATIONS, by IPEC Station Number Deleted IPEC ODCM Page 121 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX H INTERLABORATORY COMPARISON PROGRAM Laboratories used for analysis of samples to support the Radiological Environmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program or comparable program with an approved vendor (EPA, NIST, etc).

Samples of various media containing known activities of radionuclides are sent to participating laboratories for analyses. Results of the analyses are compared to the known values.

While laboratory results may be reported in terms of normalized deviations from a known value (generally + 3 sigma), the results are evaluated for acceptance criteria using the NRCs standardized comparison requirements for agreement found in the site quality control procedures (as a function of resolution).

Annual results of the interlab participation, along with resolution and agreement criteria, are summarized in the Annual Environmental Operating Report.

IPEC ODCM Page 122 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 1 of 7 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Primary Assumptions:

Units 2 and 3 effective dose factors (KLMN) are equivalent, except for unit-specific finite cloud correction factors, which represent different recirculation contribution, as required.

For instantaneous release calculations, the default (initial) condition is for each unit to share (50-50) in the application of the sites 10CFR20 limit (converted to uCi/sec from mrem/yr).

The following data represent long-term meteorological factors. Short term correction, if applicable, should be applied to these values, as discussed in Section 3.5, and Reference 17.

5-miles Unit 1 or 2 Site Nearest Receptor Down Valley, Release Points Boundary Resident Haverstraw Concentration 2.219E-06 1.030E-06 7.22E-07 X/Q (sec/m3) [SSW, 755 m] [SSW, 1574 m]

Primary Vent Releases Deposition 1.407E-08 7.517E-09 1.35E-09 D/Q (m-2) [SSW, 755 m [S, 1133 m]

Concentration 4.585E-05* 1.448E-05*

7.22E-07 X/Q (sec/m3) [SSW, 440 m] [ESE, 515 m]

Ground Level Releases Deposition 8.759E-08 3.439E-08*

1.35E-09 D/Q (m-2) [SSW, 440 m [ESE, 515 m]

5-miles Unit 3 Site Nearest Receptor Down Valley, Release Point Boundary Resident Haverstraw Concentration 4.473E-06 1.016E-06 7.22E-07 X/Q (sec/m3) [SW, 350 m] [SSW, 1574 m]

Primary Vent Deposition 2.599E-08 7.451E-09 Releases 1.35E-09 D/Q (m-2) [SSW, 480 m] [S, 1133 m]

Concentration 1.114E-4* 1.448E-05*

7.22E-07 X/Q (sec/m3) [SSW, 250 m] [ESE, 515 m]

Ground Level Releases Deposition 2.012E-07 3.439E-08*

1.35E-09 D/Q (m-2) [SSW, 250 m] [ESE, 515 m]

  • Data from Reference 50, 2006 to 2015 Site Meterology IPEC ODCM Page 123 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 2 of 7 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 Ci/sec. Because each unit has its own X/Q and K-bar, equal Ci/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 3-8.

Dose Split Between IP2 and IP3 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 Note:

b) IP3 worst sector X/Q = 4.47E-6 sec/m3 mrem m 3 Units 2 and 3 effective c) IP3 K-bar for instantaneous mixture = 849 dose factors (KLMN)

Ci yr are equivalent, except d) IP2 worst sector X/Q = 2.22E-6 sec/m3 for site-specific finite cloud correction, as mrem m 3 defined in Table 3-8.

e) IP2 K-bar for instantaneous mixture = 1507 Ci yr f) = Ci/sec Solve for  :

[ (X/Q3) (K bar3) + (X/Q2) (K bar2) ] = 500 mrem/yr

[ (4.47E-6) (849) + (2.22E-6) (1507) ] = 500 mrem/yr Therefore, without performing any specific calculations for an actual release, the default back-calculated instantaneous release rate ( ) for either unit = 7.00E+4 Ci/sec.

In other words, if both units were releasing at this rate, with the default instantaneous mixture identified in Table 3-8, 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.

IPEC ODCM Page 124 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 3 of 7 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) IP3 worst sector X/Q = 4.47E-6 sec/m3 mrem m 3 c) IP3 (Li + 1.1 Mi) = 2306 Ci yr d) IP2 X/Q for SSW sector = 2.22E-6 sec/m3 mrem m 3 e) IP2 (Li + 1.1 Mi) = 3071 Ci yr f) = uCi/sec Solve for  :

[(X/Q)3 (Li + 1.1 Mi)3 + (X/Q)2 (Li + 1.1 Mi)2] = 3,000 mrem/yr

[(4.47E-6) (2306) + (2.22E-6) (3071)] = 3,000 mrem/yr

= 1.75E+5 Ci/sec (less restrictive than Whole Body) iii. Solve for WB dose rate commitments per site (with = 7.00E+4 uCi/sec)

Indian Point 2:

mrem m 3 (7.00E+4 Ci/sec) (2.22E-6 sec/m ) (1507 3

) = 234 mrem/yr Ci yr Indian Point 3:

mrem m 3 (7.00E+4 Ci/sec) (4.47E-6 sec/m3) (849 ) = 266 mrem/yr Ci yr The less restrictive skin dose rate limit for each unit (information only):

mrem m 3 Unit 2: (1.75E+5 uCi/sec) (2.22E-6 sec/m3) (3071 ) = 1194 mrem/yr Ci yr mrem m 3 Unit 3: (1.75E+5 uCi/sec) (4.47E-6 sec/m3) (2306 ) = 1806 mrem/yr Ci yr IPEC ODCM Page 125 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 4 of 7 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 RELEASE RATE LIMITS FOR QUARTERLY AND ANNUAL AVERAGE NOBLE GAS RELEASES For a Calendar Quarter For a Calendar Year Gamma air dose 5 mrad limit 10 mrad limit Beta air dose 10 mrad limit 20 mrad limit I. 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 3-8) are as follows:

Unit 2 effective Unit 3 effective Units average dose factors average dose factors 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: ( )*[(M)(X/Q)] less than or equal to 5 mrad/qtr b) for beta dose: ( )*[(N)(X/Q)] less than or equal to 10 mrad/qtr unit 2 unit 3 5 mrad / qtr gamma dose rate = = 3.21E+4 Ci/sec 2.47E+4 Ci/sec (1 / 4 yr )( M )( X / Q )

10 mrad / qtr beta dose rate = = 1.44E+4 Ci/sec 7.14E+3 Ci/sec (1 / 4 yr )( N )( X / Q )

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 Ci/sec for unit 2 and 7.14E+3 Ci/sec for unit 3.

III. 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 Ci/sec for unit 3.

IPEC ODCM Page 126 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 5 of 7 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE INSTANTANEOUS RELEASE RATE for I-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 mrem / yr PI(c) = 1.62 E7 Ci / m3 Assumed Pathway: Child Inhalation at Unrestricted Area Boundary Solve the following equation for  :

[( )PI(c)(Wv(in)) Unit 3] + [( )PI(c)(Wv(in)) Unit 2] = 1500 mrem/yr mrem / yr mrem / yr IP3: ( )PI(c)(Wv(in))3 =

  • 1.62E7 4.47E-6 s/m3 =
  • 72.4 Ci / m 3 Ci / sec mrem / yr mrem / yr IP2: ( )PI(c)(Wv(in))2 =
  • 1.62E7 2.22E-6 s/m3 =
  • 36.0 Ci / m 3 Ci / sec The sum equals : (108) ( ) mrem/yr per uCi/sec Limit is 1500 mrem/yr per site:

mrem / yr Therefore: 108 * = 1500 mrem/yr Ci / sec

= 1.38E+1 Ci/sec (for each unit)

Ci mrem m 3 sec IP3 Dose Contribution: 1.38E+1 1.62 E 7 4.47 E 6 3 = 1003 mrem/yr sec yr Ci m Ci mrem m 3 sec IP2 Dose Contribution: 1.38E+1 1.62 E 7 2.22 E 6 3 = 497 mrem/yr sec yr Ci m Sum = 1500 mrem/yr (Approximately a 67 / 33 percent dose split for IP3 and IP2 respectively).

IPEC ODCM Page 127 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 6 of 7 ALLOWABLE QUARTERLY and ANNUAL IODINE/PARTICULATE RELEASE RATES 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:

Unit 2 Unit 3 X/Q (in sec/m3 at the nearest resident) 1.03E-6 1.02E-6 D/Q (in m-2 at the nearest resident) 7.52E-9 7.45E-9 mrem / yr RI(c) = 1.62E+7 , child thyroid inhalation dose factor for I-131 (for both units)

Ci / m3 mrem / yr RG = 1.72E+7 m2 , ground plane dose factor for I-131 (for both units)

Ci / sec mrem / yr RV(c) = 4.75E+10 m2 , child thyroid vegetation dose factor for I-131 (for both units)

Ci / sec Calculating the allowable time average release rate by solving the following equation for  :

[(RIc)(X/Q) + (RG)(D/Q) + (RVc)(D/Q)] = limit in mrem/yr Unit 2 Unit 3 (RIc)(X/Q) in mrem/yr per uCi/sec = 16.7

  • 16.5 *

(RG) (D/Q) in mrem/yr per uCi/sec = 0.129

  • 0.128 *

(RVc)(D/Q) in mrem/yr per uCi/sec = 357

  • 354
  • The sum for each unit ( X * ) in mrem/yr per uCi/sec. 374
  • 371
  • Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr). Solving for yields:

(Quarterly Limit) (Annual Limit) mrem / yr (IP2)

  • 374 = 30 mrem/yr; 8.02E-2 Ci/sec 4.01E-2 Ci/sec Ci / sec mrem / yr (IP3)
  • 371 = 30 mrem/yr; 8.10E-2 Ci/sec 4.05E-2 Ci/sec Ci / sec (Annual limits are 1/2 quarterly limits, or 15 mrem to any organ/yr)

IPEC ODCM Page 128 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX I Page 7 of 7 ALLOWABLE QUARTERLY and ANNUAL IODINE/PARTICULATE RELEASE RATES DOSE LIMITS AT THE 5-MILE SECONDARY RECEPTOR (when applied)

Dose factors for the infant, 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 is on the infant age group at this location. When applied (as required by the applicable current Land Use Census), this pathway may be approximately four times more limiting than the Primary Receptor. The back-calculated release rate for Iodine and Particulate are as follows:

Units 2 or 3 X/Q (in sec/m3 at 5-miles down valley) 7.22E-7 D/Q (in m-2 at 5-miles down valley) 1.35E-9 mrem / yr RI(i) = 1.48E+7 , infant thyroid inhalation dose factor for I-131 (for both units)

Ci / m3 mrem / yr RG = 2.10E+7 m2 , ground plane dose factor for I-131 (for both units)

Ci / sec mrem / yr RC(i) = 1.05E+12 m2 , infant thyroid cow-milk dose factor for I-131 (for both units)

Ci / sec (there is no vegetative pathway for the infant)

Calculating the allowable time average release rate by solving the following equation for  :

[(RIi)(X/Q) + (RG)(D/Q) + (RCi)(D/Q)] = limit in mrem/yr Units 2 or 3 (RIi)(X/Q) in mrem/yr per uCi/sec = 10.7 *

(RG) (D/Q) in mrem/yr per uCi/sec = 0.028 *

(RCi)(D/Q) in mrem/yr per uCi/sec = 1412

  • The sum for each unit ( X * ) in mrem/yr per uCi/sec. 1428
  • Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr).

Solving for yields the following limits, at either unit:

(Quarterly Limit) (Annual Limit) mrem / yr

  • 1428 = 30 mrem/yr; 2.10E-2 Ci/sec 1.05E-2 Ci/sec Ci / sec (Annual limits are 1/2 quarterly limits, or 15 mrem to any organ/yr)

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ODCM Part II - Calculational Methodologies APPENDIX J Page 1 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Overview:

Site hydrologists have verified the overall direction of groundwater flow at IPEC to be ultimately into the Hudson River. From this established understanding, two independent models have been applied to determine groundwater flowrates from the site into the river, the precipitation mass balance and the Darcys Law models.

The precipitation mass balance model, exclusively relied upon prior to 2007, was enhanced and further validated for 2007 and beyond using a calibration process involving Darcys Law. A total of six zones on site (described below) were evaluated to better partition the distribution of flow across the site. Each zone was also further subdivided into a shallow flow regime and a deeper flow regime based on the depth-specific differences in formation hydraulic conductivity. In addition, the groundwater flow values before and after the Discharge Canal were computed and compared to estimate the amount of groundwater flowing into the canal as well as that discharging directly to the river. This flow discretization was conducted using a 3-dimensional numerical model based on Darys Law (Darcys Law model). The overall flow values generated by the precipitation mass balance model were also validated through calibration against the Darcys Law model.

The evaluation method for radionuclide activities at groundwater to surface water discharge points was updated using wells specifically drilled proximate to these points, thus allowing more accurate assessment of these activities at these plume boundaries. Average activities are used, and based on multiple samples, generally four, but at least one, per quarter per elevation per well. The additional wells, and the instrumentation installed therein, also provides further definition of groundwater elevations to enhance the Darcys Law calibration of the precipitation mass balance model. The hydrogeology portion of the model was produced by IPECs consultant, GZA GeoEnvironmental, Inc.

The specific processes for release and dilution flow evaluation are defined in the following text.

The precipitation mass balance model partitions the precipitation falling on the watershed catchment area (i.e., that portion of the Facility area where the surface topography is sloped towards the river) into water that: 1) infiltrates through the ground surface to become groundwater (GW); 2) water which infiltrates but then moves back into the atmosphere via evaporation / transpiration and other processes; and 3) water that flows off the surface as storm water (SW).

There are five primary parameters required by the precipitation mass balance method of computing radionuclide release rate to the Hudson River via the groundwater pathway.

1. Overall direction of groundwater flow - The surface topography shows that the IPEC facility is located in a significant depression in the eastern bank of the Hudson River. Given that groundwater elevations generally mirror ground surface topography and groundwater flow is from high elevations to lower elevations, the groundwater flows from the north, east and south towards the facility, with ultimate discharge to the Hudson River to the west (as generally confirmed for the IPEC site by the monitoring network).

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ODCM Part II - Calculational Methodologies APPENDIX J Page 2 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS

2. Facility-specific groundwater flow paths - To establish facility-specific groundwater flow paths relative to on-site release areas, facility ground surface topography mapping was used. These flow paths were refined based on groundwater contours developed from the groundwater elevations measured with transducers installed in groundwater monitoring installations. The groundwater flow in each zone was then proportioned into shallow flow and deeper flow regimes based on relative hydraulic conductivities measured for the geologic deposits in each zone.
3. Rate of groundwater flow - The groundwater flow rates through the individual zones were computed using mass-balance relationships that begin with the overall average yearly precipitation for the watershed area and then subtract out precipitation volumes reflecting removal mechanisms such as:

Direct evaporation; Vegetative transpiration; Paved and roof surfaces - transport precipitation directly to the river via storm drains; Footing drains.

Prior to 2007, the net precipitation infiltration rates resulting in groundwater flow were adopted directly from a USGS study performed specifically for the Westchester County area, the location in which the facility is sited (USGS report: Water Use, Groundwater Recharge and Availability, and Quality in the Greenwich Area, Fairfield County, CT and Westchester County, NY, 2000 - 2002). The total groundwater flow rate was initially proportioned relative to the catchment areas associated with general groundwater flow areas.

These groundwater flow values were subsequently refined in 2007 and 2010 using the relative flow values computed with the Darcys Law model. The gradients (changes in hydraulic pressure with distance) throughout the site were computed from the groundwater elevation contours. For this computation, each flow zone was segregated into two depth regimes; a higher hydraulic conductivity shallow regime and a lower conductivity deeper regime. Finally, the zone-specific flow rates before the Discharge Canal were compared to those after the canal to evaluate the groundwater flux to the river via the Discharge Canal as compared to that discharging directly to the river.

4. Groundwater radionuclideactivity - A number of multi-level groundwater monitoring installations are in place up-gradient of the Discharge Canal and along the waterfront, thus allowing the radionuclide activities to be measured for groundwater flowing into the canal as well as proximate totthe groundwater/river interface.
5. Radionuclide release rate to river - Once the groundwater flow rates were established, the zone-specific radionuclide release rates to the Hudson River were computed by multiplying the area/depth-specific groundwater flow rates times the associated radionuclide activities; these individual zone-specific values were then summed to arrive at the total radionuclide release rate to the river.

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ODCM Part II - Calculational Methodologies APPENDIX J Page 3 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Over the entire watershed catchment area of 3.2 million ft2, the GW and SW has been segmented relative to areas of the facility through which it flows (primarily established based on the relative activities and types of contaminants in the various facility areas). The bulk of the GW activity has been identified down gradient of the Unit 2 transformer yard. While tritium is suspected to have originated at both Unit 2 and Unit 1 leaks, most of the offsite dose has been demonstrated to originate from Unit 1 contamination from Sr-90 and other radionuclides (tritium has little dose effect). Stream tubes have been drawn through the boundaries of these areas to define six individual groundwater flow zones:

Northern Clean Zone, the area north of Unit 2; Unit 2 North Zone, the northern areas of Unit 2, including some low levels of tritium; Unit 1 / 2 Zone, the area encompassing most of the known plume, between units 1 and 2; Unit 3 North Zone, the area between Unit 1 and Unit 3; Unit 3 South Zone, the area that primarily includes operating areas of Unit 3; Southern Clean Zone, south of Unit 3 to the edge of the property line.

Overall, the partitioning is established for groundwater and storm water, including recharge rates where storm drains and ground water communicate. In each zone, the groundwater flow is further subdivided into a shallow flow regime and a deeper flow regime based on the depth-specific differences in formation hydraulic conductivity. In addition, the groundwater flow values, determined from hydraulic pressure differences before and after the Discharge Canal, were computed and compared to estimate the amount of groundwater flowing into the canal as well as that discharging directly to the river.

Source Terms:

Activities of identified radionuclides for all Zones (from quarterly groundwater sampling data from Monitoring Wells and the accumulated Storm Drain sample data) are then applied for routine offsite dose cacluations per ODCM Part II, Section 2. All wells and storm drains are analyzed for gamma spectroscopy and tritium by liquid scintillation. Additionally, groundwater analyses are completed for beta emitters, such as Ni-63 and Sr-90. Four sets of quarterly results for each year from effected wells in the effluent locations are evaluated to compute a spatial and temporal average source term for each area or zone.

If a result is below MDC (whether positive or negative) it was not included in the computed average. This computed average is therefore biased high (more conservative from a dose computation perspective) relative to an average computed using all of the data, which would be more representative of actual conditions (values below MDC and non-detected zero values are equally valid results for the groundwater activity levels at certain locations/times).

In cases where all the sampling locations assigned to a given stream tube provided results below the MDC, then an average activity value of zero was assigned to the effected portion of the stream tube. (This mathematically allows the calculation to proceed in the absence of positive detections).

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ODCM Part II - Calculational Methodologies APPENDIX J Page 4 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Ground Water and Storm Drain Source Term selection for flow to the canal is as follows:

Manholes Monitoring Wells, Monitoring Wells, Streamtube (Storm Drains) upper zone lower zone Northern NA Background Background Clean Zone Unit 2 MW-52-11 MW-52-18 MW-52-64 MW-52-122 None MW-52-48 MW-52-162 MW-52-181 North MW-36-24 MW-36-41 MW-32-85 MW-32-149 Units MW-36-52 MW-50-42 MW-32-173 MW-32-190 MH-4A MW-50-66 MW-54-37 MW-53-120 MW-54-58 1/ 2 MW-57-11 MW-57-20 MW-54-123 MW-54-144 MW-57-45 MW-54-173 MW-54-190 Unit 3 MW-58-26 MW-54-58 MW-54-123 CB-14, CB-34 MW-58-65 MW-54-144 MW-54-173 North MW-54-190 Unit 3 U3-T2 U3-T1 B8 U3-4S MW-68-19 MW-44-102 U3-4D South MW-68-29 MW-68-57 MW-68-103 MW-68-132 MW-40-81 MW-40-100 Southern C1, D1, MW-40-27 MW-40-46 MW-40-127 MW-40-162 Clean Zone E6, E10 MW-51-40 MW-51-79 MW-51-104 MW-51-135 MW-51-163 MW-51-189 Ground Water and Storm Drain Source Term selection for flow directly to the river is as follows:

Manholes Monitoring Wells, Monitoring Wells, Streamtube (Storm Drains) upper zone lower zone Northern NA Background Background Clean Zone Unit 2 MH-1 MW-60-35 MW-60-53 MW-60-72 MW-60-135 MW-60-154 North MH-12 MW-60-176 MW-37-22 MW-37-32 Units MW-67-105 MW-67-173 MW-49-26 MW-49-42 MH-14 MW-49-65 MW-66-21 MW-67-219 MW-67-276 1and 2 MW-67-323 MW-67-340 MW-66-36 MW-67-39 MW-62-18 MW-62-37 MW-62-92 MW-62-138 Unit 3 MW-62-53 MW-62-71 MW-62-182 MW-63-112 CB-15 MW-63-18 MW-63-34 North MW-63-121 MW-63-163 MW-63-50 MW-63-93 MW-63-174 Unit 3 U3-T1 U3-T2 MW-68-103 none U3-4S MW-68-19 MW-68-132 MW-44-102 South MW-68-29 MW-68-57 U3-4D MW-40-81 MW-40-100 Southern MW-40-127 MW-40-162 C2, E13 MW-40-27 MW-40-46 MW-51-104 MW-51-135 Clean Zone MW-51-40 MW-51-79 MW-51-163 MW-51-189 IPEC ODCM Page 133 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX J Page 5 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Flow Rates:

Determination of groundwater flow rates to the canal and the river through each zone depend on infiltration rates as well as rainfall and measured hydraulic pressure differences. The infiltration rate in non-paved areas (or building areas) was computed as approximately 25 percent of the total precipitation for the previous year, as is consistent with the final Darcys law calibration of the Precipitation Mass Balance Model (as described below).

The precipitation rate for the IPEC area is recorded each year, and averages approximately 3 feet per year. All precipitation falling on paved/building areas is assumed to result in stormwater flow. Although some of this water actually evaporates directly to atmosphere from pavement and building roofs, no credit for this evaporation is taken to enhance conservativism in the model. Model conservatism relative to stormwater dose computation is further enhanced through the use of activities which are inherently baised high due to the typical timing of sample collection which favors low flow conditions1. Finally, it is noted that a portion of the Stormwater also ultimately recharges the groundwater.

The following values are currently applied in the flow model:

Percent of Stormwater Flow Streamtube Recharging Groundwater Northern Clean Zone 0%

Unit 2 North 50%

Unit 1/2 30%

Unit 3 North 60%

Unit 3 South 10%

Southern Clean Zone 40%

Known subsurface drain extration rates from existing groundwater pathways need to be subtracted from the zones applicable to these specific pathways, as follows:

Five gallons per minute (gpm) from the Unit 2 Footing Drain is removed from the Unit 2 North streamtube.

Five gpm from the Unit 1 North Curtain Drain and 2.5 gpm from the Unit 1 Chemical Systems Building Foundation Drain are removed from the Unit 1/2 streamtube.

Seven and a half gpm from the Unit 1 Chemical Systems Building Foundation Drain are removed from the Unit 3 North streamtube.

1 Samples are typically obtained from the storm drain manholes when its not raining so as to facilitate field work. As such, there is generally little to no stormwater flow during sampling, with the majority of the flow then contributed by groundwater infiltration. Therefore, the activities are biased high relative to those which would be obtained during precipitation events when the storm drains are carrying much higher flow rates, and thus the majority of their flow contribution to the dose computation. These relatively high activities are then applied to the full yearly average stormwater flow, resulting in: 1) a substantial overstatement of the dose to the river; and 2) high computed variability in the dose due to stormwater flow induced variability in the measured activity.

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ODCM Part II - Calculational Methodologies APPENDIX J Page 6 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Beyond the known extraction rates, the Precipitation Mass Balance Model was calibrated using Darcys Law with the groundwater elevation contours for each of the six zones. The contours and measurements of hydraulic conductivity were developed from the wells on site, recognizing that flow is perpendicular to the contours. This effort also provides knowledge of facility-specific flow paths.

Measurments of pressure differential were then applied (per Darcys Law) to determine flow rate for use in the calibration process:

Q K i A Where:

Q is groundwater flow (cubic feet/day). This value is calculated.

K is the hydraulic conductivity (ft/day). This value is a log normal average of hydraulic conductivity values measured within the appropriate portion of the streamtube. In other words, the ease of which flow can be forced through sub-surface media.

A is the cross sectional area through which groundwater is moving (ft 2).

i is the change in head over a distance (ft/ft), or a measure of the pressure driving the flow. This value is calculated for the shallow and deep zones both upgradient and downgradient of the canal.

The parameters above were originally developed from the Quarter 2 2007 data set and applied to calibrate the precipitation mass balance model; subsequent data was used to verify the applicability of this calibration on a quarterly basis. After collection of nine quarterly rounds of data, a final recalibration of the model was performed using the quarterly data set yielding the most conservative groundwater flow values (Quarter 4 2008).

The calibration routine generally consisted of the following steps:

1) Groundwater elevation data was downloaded from transducers and/or recorded manually with an electronic water level indicator or equivalent. Following download, the data was reduced and evaluated by the site Hydrologists.
2) A period of time was selected to evaluate the groundwater at key elevations and positions along all three axes, such that the maximum number of working transducers were included.

Flow evaluations were biased high (overstates dose) by selecting readings during low tide on the targeted day, and targeting a day when the tides are particularly low.

3) Two sets of groundwater contours were prepared. Shallow groundwater contours were drawn based on groundwater elevation data collected generally at elevations higher than 40 feet below top of bedrock. Deep groundwater contours were drawn based on groundwater elevation data from sampling locations deeper than 40 feet below the top of rock, although preference was given to data from the upper portion of that zone.
4) Using the groundwater contours within each streamtube, the shallow and deep groundwater flux was calculated within each zone using Darcys Law as described above.
5) The total flow, both upgradient and downgradient of the Discharge Canal, was summed separately. The difference between these flows yields the groundwater flow which is recharging the Discharge Canal.

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ODCM Part II - Calculational Methodologies APPENDIX J Page 7 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS

6) The total flow downgradient of the Discharge Canal discharges into the Hudson river.
7) The percentage of groundwater flow in the upper and lower zones of each streamtube was calculated for proportioning of groundwater flow in the upper and lower zones in the Precipitation Mass Balance Model.

NOTE:

The groundwater contours used for the Darcys Law calibration of the Precipitation Mass Balance Model had originally been based on data collected during Quarter 2 of calendar year 2007; this calibration was used for dose computations through 2009.

Given that seasonal and yearly variations in precipitation and runoff cause changes in the groundwater contours for individual quarterly monitoring rounds, quarterly groundwater elevation data was collected for nine quarters between Q2 2007 to Q2 2009. These data were reviewed to evaluate the magnitude of variation in the computed groundwater flows due to precipitation variability. It was concluded that sufficient seasonal data had been collected to encompass the majority of the precipitation variability observed over the last fourteen years (fifty-six quarters); see analysis in Section 3.1.2 of the Quarter 2 2009 monitoring report. The Precipitation Mass Balance Model was therefore recalibrated in Quarter 2 of 2009 (shown on the following 2 pages).

To be conservative, the model was recalibrated to the quarterly data set that yielded the largest total and/or Unit 1/2 Zone2 groundwater flows from the Darcys Law Model. Based on these analyses, the model was recalibrated to the groundwater fluxes from Quarter 4 2008.

While this quarter did not yield the highest total flow through the entire site, it did provide a high total flow and the highest flow through the Unit 1/2 Zone, and thus the highest computed dose. This calibration to Quarter 4 2008 groundwater elevations has therefore been used from 2010 going forward.

8) A final determination of offsite dose can be performed with the previously compiled data (dilution flow, effluent flow rates, and source terms) using an integrated dose calculation model (electronic Excel spreadsheet) identified in Reference 44. This spreadsheet, called the Master Groundwater Dose Calculator, is available from Chemistry Management.

The distribution of flow rates to the canal and the river, from each zone, is determined within this asset as a result of calibrations of the rainfall model with Darcys Law and transducer data. Its purpose is to bound the effluent flow rate in a conservative fashion.

Averaged or conservative assessments of source term are entered for each zone from a list of required input locations (wells or drains in each effected area).

Dose calculations are performed with this information per ODCM Part II, Section 2.4, in the same fashion as other liquid effluents.

2 In order to approach the recalibration conservatively, GZA not only reviewed the groundwater flux across the entire site but also the flux in the Unit 1/2 Zone because the majority of the radionuclide dose is located within this Zone.

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ODCM Part II - Calculational Methodologies APPENDIX J Page 8 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Facility Groundwater Flux Calculation Example of the Precipitation Mass Balance Calibration 2009, Q2 Site Indian Point Prepared By: JAS Job No. 17869.91 Reviewed By: mjb Parameter Values:

Totals Total Catchment Total Improved Zone (ft^2) Zone (ft^2) Recharge (ft/yr) Precipitation (ft/yr) 3,969,765 1,432,972 0.70 2.69 year Surface Area 2009 Unit 3 North Unit 3 South Northern Clean Zone Unit 2 North Improved Unit 1/2 Improved Improved Zone Improved Zone Southern Clean Improved (ft^2) Zone (ft^2) Zone (ft^2) (ft^2) (ft^2) Improved Zone (ft^2) 0 148,214 433,904 316,210 321,290 213,354 Northern Clean Unit 1/2 Unit 3 North Unit 3 South Unimproved Zone Unit 2 North Unimproved Unimproved Zone Unimproved Zone Unimproved Southern Clean Zone (ft^2) Zone (ft^2) (ft^2) (ft^2) Zone (ft^2) Unimproved (ft^2) 106,429 204,317 438,221 323,116 268,862 585,600 Discounted Area Discounted Area Within Discounted Area Discounted Area Discounted Area Discounted Area Within Within Zone Zone Within Zone Within Zone Within Zone Zone 50,265 0 291,186 106,718 17,730 144,347 Unit 3 North Northern Clean Zone Unit 2 North Catchment Unit 1/2 Catchment Catchment Zone Unit 3 South Southern Clean Zone Catchment (ft^2) Zone (ft^2) Zone (ft^2) (ft^2) Zone (ft^2) (ft^2) 156,694 352,531 1,163,311 746,044 607,882 943,302 Activity (pCi/L)

Groundwater Northern Clean Zone Unit 3 South Catchment Unit 2 North Unit 1/2 Unit 3 North Zone Southern Clean Zone Upper Zone Before Canal 150 297 3,031 327 778 227 Lower Zone Before Canal 150 251 2,750 1,143 480 210 Unit 3 South Northern Clean Zone Unit 2 North Unit 1/2 Unit 3 North Zone Southern Clean Zone Upper Zone After Canal 150 198 3,121 376 778 227 Lower Zone After Canal 150 575 1,061 511 480 210 Stormwater Discharging to Canal (pCi/L)

Storm Water for Storm Water for Unit 2 Storm Water for Storm Water for Storm Water for Storm Water for Northern Clean Zone North Unit 1/2 Unit 3 North Unit 3 South Southern Clean Zone 1,276 0 0 0 NA Avg MH-4a NA Avg CB-14 and CB-34 Avg U3-CB-B8 Avg D1, C3, E6, & E10 Stormwater Discharging to River (pCi/L)

Storm Water for Storm Water for Unit 2 Storm Water for Storm Water for Storm Water for Storm Water for Northern Clean Zone North Unit 1/2 Unit 3 North Unit 3 South Southern Clean Zone 613 0 683 251 NA Avg. MH-1 and MH-12 Avg MH-14 Avg CB-15 NA Avg E13,CB-C2 Potential Water Received by Storm Drain System

=(Improved Area) x Precipitation Northern Clean Area Unit 2 North Unit 1/2 Unit 3 North Unit 3 South Southern Clean Zone Units 0 398,572 1,166,841 850,342 864,001 573,746 ft^3/yr 0 1,092 3,197 2,330 2,367 1,572 ft^3/day 0.00 5.67 16.61 12.10 12.30 8.17 GPM 0 11,286,298 33,041,245 24,079,009 24,465,788 16,246,670 L/Yr The total amount of water available to be received by the storm sys tem is computed as the combined area of buildings and paved areas in the catchment multiplied by the annual precipitation rate. Note this conservatively assumes that the amount of water lost to the atmosphere or other s inks after precipitation has fallen on paved or built up surfaces is zero.

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ODCM Part II - Calculational Methodologies APPENDIX J Page 9 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS IPEC ODCM Page 138 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX J Page 10 of 10 GROUNDWATER AND STORMWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS IPEC ODCM Page 139 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX K QUANTIFICATION AND REPORTING of C-14 in IPEC RELEASES Page 1 of 6 Effluent Curie Determination:

In the early 1980s, the NYSDOH conducted experiments at IP3 to quantify C-14 releases (Ref.

48). This data was summarized and incorporated into station procedures and annual effluent reports after 1983. In 2009, EPRI began working with licensees to develop a modern model to generate a good estimate of C-14 curies released from American nuclear power plants.

EPRIs project Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents was completed and published in December 2010 as document # 1021106.

Applying the EPRI model (Ref. 47) at IPEC resulted in closely matched values from those of the earlier work by NYSDOH. EPRIs calculation involves using the unit-specific average neutron flux (averaged values for beginning and end of core life), and the active core coolant mass in the reactor vessel area. From this data, the C-14 production rates from both the Oxygen and Nitrogen generation methods were computed ( 17O(n,)14C and14N(n,p)14C).

The Nitrogen generation model requires the additional input of the average Nitrogen content in the reactor coolant, as described in References 47 and 48. Old and new values for C-14 released via airborne pathways annually is summarized below:

Curies C-14 released Curies C-14 released CO2 Annual Curies per NYSDOH, 1983 per EPRI, 2010 fraction causing dose IP 2 N/A 10.5 N/A 2.73 IP 3 9.6 10.4 26% 2.72 Liquid effluent C-14 was evaluated in 1982 and determined to be insignificant. However, since it has been reported since 1983, all liquid effluent data will continue to be reported for comparison purposes in the annual effluent report to the NRC. Annual curie and dose values for liquid C-14 releases are unchanged from Reference 48 and will continue:

0.07 Ci, 1.17E-3 mrem Child Total Body, and 5.83E-3 mrem Child Bone dose, per unit.

For 2010 and beyond, the curies of airborne effluent C-14 are determined from the EPRI model and used in conjunction with the defined fraction of CO2 from the NYSDOH studies (Ref. 48), to establish the source term for offsite dose calculations from C-14.

Determination of Curies, Appendix D of the EPRI model (Unit 2, 2009-2010 data shown)

Note: Details of this calculation are provided in References 47 and 48 and are only summarized below:

Indian Point Unit-2 is a Westinghouse 4 loop PWR rated at 3216 MWth with a net electrical rating of 1032 MWe. Active core mass and core average neutron flux data is supplied by Reactor Engineering (and may be modified from cycle to cycle). However the following calculation serves as a template for an annual assessment of C-14 at either IPEC unit:

Core Average Neutron Flux, n/cm2-sec 0.625 eV >0.625 eV BOC 3.18E13 2.78E14 EOC 3.96E13 2.90E14 Reaction Effective Cross-Section, b 17O(n,)14C 0.119 0.0482 14N(n,p)14C 0.951 0.0393 IPEC ODCM Page 140 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX K QUANTIFICATION AND REPORTING of C-14 in IPEC RELEASES Page 2 of 6 The following equation was used to calculate the production rate in units of µCi/sec-kg for the 17 O(n,)14C reaction.

N * [th

  • th + f
  • f ]
  • 1.0E-24
  • Production Rate (µCi/sec-kg ) =

3.7E4 where:

N = 1.27E22 atoms 17O/kg H2O th = effective thermal cross-section, b Indian Point Unit 2 Cycle 20 Average Production Rates for Oxygen Reaction Production Rate, µCi/sec-kg BOC 2.261E-5 EOC 2.459E-5 Average: 2.36E-5 th = thermal neutron flux (0.625 eV), n/cm2-sec f = effective fast cross-section, b f = fast neutron flux (>0.625 eV), n/cm 2-sec 1.0E-24 = Conversion factor, 1.0E-24 cm2/b 14

= C decay constant, 3.833E-12/sec 3.7E4 = Conversion factor, 3.7E4 d/sec-µCi The effective cross section data were obtained from site Reactor Engineering, from Westinghouse documents.

BOC calculation:

1.27E22* [0.119

  • 3.18E13 + 0.0482
  • 2.78E14]
  • 1.0E-24
  • 3.833E-12 PR = = 2.261E-5 µCi/sec-kg 3.7E4 EOC calculation:

1.27E22* [0.119

  • 3.96E13 + 0.0482
  • 2.90E14]
  • 1.0E-24
  • 3.833E-12 PR = = 2.459E-5 µCi/sec-kg 3.7E4 IPEC ODCM Page 141 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX K QUANTIFICATION AND REPORTING of C-14 in IPEC RELEASES Page 3 of 6 The cycle average 14C production rates for the 17O(n,)14C reaction were as follows:

14 Given an active core mass of 13,498 kg (from site Reactor Engineering), the total C produced by the 17O(n,)14C reaction is:

2.36E-5 µCi/sec-kg

  • 13,498 kg
  • 3.156E7 sec/yr = 1.01E7 µCi/yr (10.1 Ci/yr) or 2.36E-5 µCi/sec-kg
  • 13,498 kg
  • 3.6E3 sec/hr]/3216 MWth = 0.357 µCi/MWth-h 14 To calculate the production rate in units of µCi/sec-kg-ppm N for the N(n,p)14C reaction, the following equation is employed:

N * [th

  • th + f
  • f ]
  • 1.0E-24
  • Production Rate (µCi/sec-kg-ppm N ) =

3.7E4 where:

N = 4.284E19 atoms 14N/kg-ppm N th = effective thermal cross-section, b th = thermal neutron flux, n/cm2-sec f = effective fast cross-section, b f = fast neutron flux, n/cm2-sec 1.0E-24 = conversion factor, 1.0E-24 cm2/b 14

= C decay constant, 3.833E-12/sec 3.7E4 = conversion factor, 3.7E4 d/sec-µCi The effective cross section data were obtained from site Reactor Engineering, from Westinghouse documents.

BOC calculation:

4.284E19* [0.951

  • 3.18E13 + 0.0393
  • 2.78E14]
  • 1.0E-24
  • 3.833E-12 PR = = 1.827E-7 µCi/sec-kg-ppm N 2 3.7E4 EOC calculation:

4.284E19* [0.951

  • 3.96E13 + 0.0393
  • 2.90E14]
  • 1.0E-24
  • 3.833E-12 PR = = 2.177E-7 µCi/sec-kg-ppm N 2 3.7E4 IPEC ODCM Page 142 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX K QUANTIFICATION AND REPORTING of C-14 in IPEC RELEASES Page 4 of 6 The production rates are summarized below:

Indian Point Unit 2 Cycle 20 Average Production Rates for Nitrogen Reaction Production Rate, µCi/sec-kg-ppm N2 BOC 1.827E-7 EOC 2.177E-7 Average: 2.00E-7 14 Given an active core mass of 13,498 kg (from site Reactor Engineering), the total C produced by the 14N(n,p)14C reaction is:

2.00E-7 µCi/sec-kg-ppm N

  • 13,498 kg
  • 3.156E7 sec/yr = 8.52E4 µCi/yr-ppm N = 0.0852 Ci/yr-ppm-N2 or

[2.00E-7 µCi/sec-kg-ppm N

  • 13,498 kg
  • 3.6E3 sec/hr]/3216 MWth = 3.02E-3 µCi/MWth-h-ppm N2 The ppm N2 in the coolant is determined from VCT conditions per EPRIs model, Appendix E.

Indian Point Unit 2 averages approximately 90% Hydrogen, and conservatively 30 psig pressure in the VCT. Accounting for a slight reduction in pressure due to the water vapor, the partial pressure of Nitrogen is then:

P (N2) = 0.10

  • 29.7 = 0.302 atm Assuming 9.88E4 atm/mole-fraction at average operating temperature (from Appendix E), the mole fraction of N2 in the VCT liquid phase is:

0.302 atm / 9.88E4 atm/mole fraction = 3.06E-6 Converting to ppm N2:

3.06E-6 moles N2 mole H20 28.01 g N2

* ------------------ * ----------------- = 4.76E-6 g N 2 /g H20 = 4.76 ppm mole H20 18.02 g H20 mole N2 The resulting curies from the N2 reaction would then be:

0.0852 Ci/yr-ppm N2

  • 4.76 ppm = 0.405 Ci/yr Adding the curies determined from theO2 reaction, earlier (10.1 Ci/yr):

Total Curies of C-14 released from a single IPEC unit = 10.5 Ci/full power year Applying a correction factor for effective full power days (EFPD, obtained from Programs and Components) provides actual curies for each year. For example, if a units EFPD for a given year was 299, the factor would be 299/365 or 0.819. In the above example, this would result in actual curies of C-14 for the given year to be: 0.819

  • 10.5, or 8.60 Curies total C-14.

IPEC ODCM Page 143 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX K QUANTIFICATION AND REPORTING of C-14 in IPEC RELEASES Page 5 of 6 Effluent Dose Determination:

Comparing the EPRI model curie calculations with the work compiled at IP3 in 1982:

Measurements at EPRI model, Percent IP3, 1982 2010 Difference Curies of C-14 released, per unit 9.6 10.5 8.57% increase The EPRI model compares favorably (slightly in the conservative direction) with sample data results obtained at IP3 in the 1980s. For conservativism and industry standardization, IPEC uses the EPRI model for determining curies released, as of 2010.

Offsite doses from C-14 emissions are calculated in the same manner as all other isotopes at IPEC, using Reg Guide 1.109 and associated dose factors, with details identified in Ref 48.

As the release is in the form of CO2, the X/Q dispersion constant is used. Whole Body and Critical Organ doses are calculated for the critical age group (child) at the Primary Receptor, from ingestion (vegetative) and inhalation pathways.

Adding the liquid effluent data, and attributing dose to each unit (as is required by 10CFR50),

results in annual totals that can be used as a bounding calculation from maximum rated output and core size. See the summary table at the end of this section.

Liquid:

Liquid effluent curies and doses from C-14 were determined to be relatively insignificant in the 1982 study. The EPRI model in 2010 also identified liquid pathways to be insignificant, and specifically mentions only airborne pathways need to be evaluated. However, since liquid effluent values were determined from actual sampling in 1982, the historical curies and doses (determined from standard Reg Guide 1.109 modeling) will continue to be reported in annual reports, as shown in the table at the end of this section. Details of both liquid and airborne dose calculations are provided in Reference 48.

Airborne:

1. Assumptions
a. 21 Ci/yr released from IPEC, per EPRI model (10.5 Ci/yr per operating unit)
b. Q=5.46 Ci/yr (26% as CO2, the only dose contributor, 2.73 Ci/yr per unit)
c. p= ratio of C-14 releases to total release time = 1 (very conservative)
d. X/Q @ Primary Receptor (U2 = 1.03E-6 sec/m 3 , U3 = 1.02E-6 sec/m3 )
e. Fraction of total plant mass that is natural carbon = 0.11 (RG 1.109, C-8)
f. Concentration (g/m3) of natural carbon in atmosphere = 0.16 (RG 1.109, C-8)
g. Child dose at the Primary Receptor is most limiting
h. Dose Factors used from Reg Guide 1.109 Note: Values for c, e, and f are conservative and offered by RG 1.109. Better (site-specific) data is being evaluated at IPEC and throughout the industry for application in the future.
2. Vegetative Pathway Calculation from Reg Guide (see RG 1.109, equation C-8)

C14 pCi/kg = 3.17E7

  • p
  • Q
  • X/Q * (0.11/0.16) [3.17E7 = (pCi-g-yr)/(Ci-kg-sec)]

C14 pCi/kg = 122.6 pCi/kg ingested (veg) (conservatively using U2s X/Q)

IPEC ODCM Page 144 of 145 Revision 6

ODCM Part II - Calculational Methodologies APPENDIX K QUANTIFICATION AND REPORTING of C-14 in IPEC RELEASES Page 6 of 6

3. Child Ingestion (uses 26% of total C-14 released, or just the CO2 portion)

Dose = DF * [ uv*fg + uL]

  • 122.6 pCi/kg DF = 1.21E-5 mrem/pCi Bone Child [RG 1.109, E-13]

2.42E-6 mrem/pCi TB Child [RG 1.109, E-13]

uv=520 kg/yr (child ; uL=26 kg/yr [usage factors, RG 1.109, E-5]

fg = 0.76 [ fraction of produce ingested in garden of interest, E-15]

Annual Child Bone Dose = 1.21E-5

  • 51639 = 0.625 mrem Annual Child TB Dose = 2.42E-6
  • 51639 = 0.125 mrem
4. Child Inhalation (uses all released C-14, not just CO2)

C14 pCi/m3 = 3.17E+4 * (Q) * (X/Q) [3.17E+4 = (pCi-yr) / (Ci-sec)]

C14 pCi/m3 = 3.17E+4 pCi-yr/Ci-sec

  • 21 Ci
  • 1.03E-6 sec/m 3 = 0.686 pCi/m3 C14 Dose = BR
  • pCi/m3
  • DFi BRchild = 3700 m3/yr ; Conc = 0.686 pCi/m3 ; DFI = 9.70E-6 mrem/pCi Child Bone

= 1.82E-6 mrem/pCi Child TB Annual Child Inh Bone Dose = 3700

  • 0.686
  • 9.70E-6 = 2.46E-3 mrem Annual Child Inh Tot Body Dose = 3700
  • 0.686
  • 1.82E-6 = 4.62E-3 mrem
5. The doses above apply to IPEC. Individual unit doses are half the total, as follows:

One IPEC Unit Child Bone Dose = (0.625 + 2.46E-3) / 2 = 0.325 mrem One IPEC Unit Child Tot Body Dose = (0.125 + 4.62E-3) / 2 = 0.0648 mrem

6. The Annual Radioactive Effluent Release Report (ARERR, per RG 1.21), includes data similar to the following table, as determined for each year, corrected for effective full power days. The percentage of total C-14 that is CO2 should also be identified.
7. C-14 curies and doses should be reported separately from other isotopes because:

C-14s measurement and quantification methods are unique, Trending/representation of C-14 and other isotopes will remain unchanged, and, This method precludes any confusion or inappropriate comparison between C-14 and isotopes that are categorized as Noble Gas, Iodine, or Particulate (as C-14 cannot be accurately grouped with any of these).

Typical Annual C-14 reporting from IPEC Unit 2 Unit 3 Liquid Effluent C14 Released Curies 0.07 0.07 Total Airborne C14 Released Curies 10.5 10.5 Airborne C14 as CO2 Curies 2.73 2.73 Airborne Eff Child TB Dose, C14 mrem 0.0648 0.0648 Airborne Eff Child Bone Dose, C14 mrem 0.325 0.325 Liquid Eff Child TB Dose, C14 mrem 0.00117 0.00117 Liquid Eff Child Bone Dose, C14 mrem 0.00583 0.00583 IPEC ODCM Page 145 of 145 Revision 6

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