ML23118A070

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2022 Annual Radioactive Effluent Release Report
ML23118A070
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 04/28/2023
From: Fleming J
Holtec
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
HDI-IPEC-23-020
Download: ML23118A070 (1)
v • d • e


Text

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

April 28, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Indian Point Energy Center Provisional Operating License No. DPR-05 Facility License No. DPR-26 and DPR-64 NRC Docket Nos. 50-03, 50-247, and 50-286

Subject:

2022 Annual Radioactive Effluent Release Report Enclosed with this cover letter is the Indian Point Units 1, 2, and 3 Annual Radioactive Effluent Release Report for 2022. The report is submitted in accordance with Technical Specification 5.6.2 and Regulatory Guide 1.21 and includes dose from the Independent Spent Fuel Storage Facility. There were no changes to report for the Offsite Dose Calculation Manual (ODCM) in 2022.

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.

Sincerely, Digitally signed by Jean A.

Jean A. Fleming Fleming Date: 2023.04.28 08:03:16 -04'00' Jean A. Fleming Vice President, Licensing, Regulatory Affairs and PSA Holtec International

Enclosures:

2022 Annual Radioactive Effluent Release Report 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 HDI-IPEC-23-020

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 ENCLOSURE TO HDI-IPEC-23-020 2022 Annual Radioactive Effluent Release Report HDI-IPEC-23-020

Page 1 of 49 Facility: Indian Point Energy Center YEAR: 2022 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: 2022 Page 2 of 49 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 ..........................................................................................34 7.0 METEOROLOGICAL DATA ......................................................................................................38 LIST OF TABLES ........................................................................................................................... .. 3 ATTACHMENTS - Carbon 14 Discussion - DELETED ...............................................................................39 - Groundwater Monitoring Program Results ....................................................................40 - 2021 Laboratory Analytical Results...............................................................................43

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 3 of 49 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: 2022 Page 4 of 49 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 Permanently Defueled Technical Specification (PDTS) 5.6.3 and Unit 3 PDTS 5.6.3. Unit 2 permanently shut down on April 30th, 2020. Unit 3 permanently shut down on 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 Permanently Defueled 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: 2022 Page 5 of 49 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. Gaseous 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 regarding 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 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 5.0E-05 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: 2022 Page 6 of 49 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 are no longer performed at the site. Both units are permanently shut down and defueled with their respective vapor containments open for general access. Both vapor containment buildings are now part of their respective units auxiliary building ventilation system, which is continuously monitored for radioactivity.

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 I-131 is not identified in weekly vent samples, then - 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, then 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 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: 2022 Page 7 of 49 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 was permanently shut down in April 2021. Unit 2 was permanently shut down in April 2020. Both units were permanently defueled. Both units ceased producing airborne Carbon-14, and the subsequent dose to the public from airborne Carbon-14, for calendar year 2022, is zero.
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 regarding 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:

= [(1 )2 + (2 )2 +. . . ( )2 ]

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: 2022 Page 8 of 49 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 2022 Number of Batch Releases 0 0 0 0 0 Total Time Period (min) 0 0 0 0 0 Maximum Time Period (min) 0 0 0 0 0 Average Time Period (min) 0 0 0 0 0 Minimum Time Period (min) 0 0 0 0 0 Unit 3 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2022 Number of Batch Releases 0 0 0 0 0 Total Time Period (min) 0 0 0 0 0 Maximum Time Period (min) 0 0 0 0 0 Average Time Period (min) 0 0 0 0 0 Minimum Time Period (min) 0 0 0 0 0
2. Liquid Table 2.5 Liquid Batch Releases Unit 1 and 2 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2022 Number of Batch Releases 4 3 9 1 17 Total Time Period (min) 1920 272 960 170 3320 Maximum Time Period (min) 480 99 145 170 480 Average Time Period (min) 480 90.67 106.67 170 195 Minimum Time Period (min) 480 85 88 170 85 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2022 Number of Batch Releases 4 0 0 0 4 Total Time Period (min) 1920 0 0 0 1920 Maximum Time Period (min) 480 0 0 0 480 Average Time Period (min) 480 0 0 0 480 Minimum Time Period (min) 480 0 0 0 480 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: 2022 Page 9 of 49 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 Device in the Unit 3 Fuel Storage Building (FSB), the existing Liquid Radwaste Processing System (LRPS) skid was removed from the FSB Truck Bay. An alternate means of liquid radwaste processing was established to support Unit 3 during decommissioning. The liquid radwaste stream normally sent to the Unit 3 LRPS was diverted to the Unit 3 Radioactive Machine Shop (RAMS). A truck filling station was installed that fills a tanker truck. The truck is driven to the Unit 1 Fuel Handling Building (FHB) where the trailer is 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 because 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 No changes were made to the ODCM during this reporting period.

2.12 Process Control Program (PCP) Changes There were no PCP changes during 2022.

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 10 of 49 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 2022 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 2022 effluent dose was slightly higher than in 2021. 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: 2022 Page 11 of 49 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS Table 3-1 Gaseous Effluents - Summation of All Releases - Units 1 and 2 Est. Total A. Fission & Activation Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year  % Error

1. Total Release Ci - - - - 0.00E+00 +/- 25
2. Average release rate uCi/sec - - - - 0.00E+00 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 2.58E-01 2.33E-01 4.92E-01 2.62E-01 1.25E+00
2. Average release rate uCi/sec 3.32E-02 2.96E-02 6.19E-02 3.30E-02 3.95E-02 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: 2022 Page 12 of 49 Annual Radioactive Effluent Release Report Table 3-2 Gaseous Effluents -- Batch Mode - Units 1 and 2 Nuclides Released

1) Fission Gases There were no Batch Releases of Gaseous Effluents for Unit 2
2) Iodines Not Applicable for Batch Releases
3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 13 of 49 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

4) Tritium H-3 Ci 2.58E-01 2.33E-01 4.92E-01 2.62E-01 1.25E+00 Total for Period Ci 2.58E-01 2.33E-01 4.92E-01 2.62E-01 1.25E+00

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 14 of 49 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 - - - - 0.00E+00 +/- 25
2. Average release rate uCi/sec - - - - 0.00E+00 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 1.55E+00 2.14E+00 2.10E+00 4.43E+00 1.02E+01
2. Average release rate uCi/sec 1.99E-01 2.72E-01 2.64E-01 5.57E-01 3.24E-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: 2022 Page 15 of 49 Annual Radioactive Effluent Release Report Table 3-5 Gaseous Effluents - Batch Mode - Unit 3 Nuclides Released

1) Fission Gases There were no Batch Releases of Gaseous Effluents for Unit 3
2) Iodines Not Applicable for Batch Releases
3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 16 of 49 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
4) Tritium H-3 Ci 1.55E+00 2.14E+00 2.10E+00 4.43E+00 1.02E+01 Total for Period Ci 1.55E+00 2.14E+00 2.10E+00 4.43E+00 1.02E+01

- indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 17 of 49 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 7.34E-03 1.36E-02 4.54E-02 7.56E-03 7.39E-02 +/- 25 Tritium, Gr Alpha, & Gases)
2. Average Diluted Conc uCi/ml 1.49E-09 1.75E-09 2.85E-09 1.34E-09 5.34E-10 B. Tritium
1. Total Release Ci 4.06E-03 3.21E+00 2.19E+01 2.85E+00 2.80E+01 +/- 25
2. Average Diluted Conc uCi/ml 8.23E-10 4.11E-07 1.38E-06 4.57E-07 2.02E-07 C. Dissolved & Entrained Gases
1. Total Release Ci - - - - - +/- 25
2. AverageDiluted Conc uCi/ml - - - - -

D. Gross Alpha

1. Total Release Ci - - - - - +/- 25
2. AverageDiluted Conc uCi/ml - - - - -

E. Volume of Waste Released

1. Processed Fluids liters 9.59E+05 1.80E+06 1.48E+06 1.39E+06 5.63E+06 +/- 10
2. Unprocessed Fluids liters 1.24E+07 1.20E+07 4.41E+06 4.62E+06 3.34E+07 +/- 10 F. Volume of Dilution Water liters 1.97E+10 3.11E+10 6.50E+10 2.26E+10 1.38E+11 +/- 10

- indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 18 of 49 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 - 4.42E-05 3.76E-04 4.37E-05 4.64E-04 Cr-51 Ci - - - - 0.00E+00 Cs-137 Ci - 1.89E-05 7.88E-06 0.00E+00 2.68E-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 - 3.43E-03 3.40E-02 2.43E-03 3.99E-02 Sb-125 Ci - 2.92E-03 1.98E-03 1.19E-03 6.09E-03 Te-123m Ci - - - - 0.00E+00 Te-125m Ci - - - - 0.00E+00 Gross Beta Ci - 1.18E-03 3.64E-03 4.65E-04 5.29E-03 Total for Period Ci 0.00E+00 7.59E-03 4.00E-02 4.13E-03 5.17E-02 Tritium H-3 Ci 0.00E+00 3.20E+00 2.18E+01 2.57E+00 2.76E+01 Total for Period Ci 0.00E+00 3.20E+00 2.18E+01 2.57E+00 2.76E+01 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: 2022 Page 19 of 49 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 Sr-90 Ci 2.59E-05 5.20E-05 4.64E-06 4.38E-05 1.26E-04 Cs-137 Ci 3.75E-03 3.29E-03 2.74E-03 1.73E-03 1.15E-02 Gross Beta Ci 3.56E-03 2.68E-03 2.57E-03 1.66E-03 1.05E-02 Total for Period Ci 7.34E-03 6.02E-03 5.31E-03 3.43E-03 2.21E-02 H-3 (only) Ci 4.06E-03 8.16E-03 1.52E-01 6.58E-03 1.71E-01

- Indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 20 of 49 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 - - - - 0.00E+00 +/- 25 Tritium, Gr Alpha, & Gases)
2. Average Diluted Conc uCi/ml - - - - 0.00E+00 B. Tritium
1. Total Release Ci - - - - 0.00E+00 +/- 25
2. Average Diluted Conc uCi/ml - - - - 0.00E+00 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 - - - - 0.00E+00 +/- 25 E. Volume of Waste Released
1. Processed Fluids (Mon Tanks) liters - - - - 0.00E+00 +/- 10
2. Unprocessed Fluids (SGs) liters 1.28E+05 - - - 1.28E+05 +/- 10 F. Volume of Dilution Water liters 9.58E+09 - - - 9.58E+09 +/- 10

- indicates < MDA

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

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 21 of 49 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 - - - - 0.00E+00 Cr-51 Ci - - - - 0.00E+00 Mn-54 Ci - - - - 0.00E+00 Fe-55 Ci - - - - 0.00E+00 Co-58 Ci - - - - 0.00E+00 Co-60 Ci - - - - 0.00E+00 Ni-63 Ci - - - - 0.00E+00 Zr-95 Ci - - - - 0.00E+00 Nb-95 Ci - - - - 0.00E+00 Ru-103 Ci - - - - 0.00E+00 Ag-110m Ci - - - - 0.00E+00 Sb-124 Ci - - - - 0.00E+00 Sb-125 Ci - - - - 0.00E+00 Te-125m Ci - - - - 0.00E+00 Cs-137 Ci - - - - 0.00E+00 Ce-144 Ci - - - - 0.00E+00 Pr-144 Ci - - - - 0.00E+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved and Entrained Gas (Batch)

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 Continuous Releases (SG Blowdown)

H-3 (only) Ci - - - - 0.00E+00

- indicates < mda

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 22 of 49 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Units 1 & 2 and 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 3.95E+02 1.12E+01 1.10E+01 +/-25%

B 4.46E+02 1.26E+01 3.82E+02 +/-25%

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

All 8.41E+02 2.38E+01 3.93E+02 +/- 25%

Waste Stream  : Dry Active Waste Waste Volume Curies % Error (Ci) 3 3 Class ft m Shipped A 1.15E+05 3.25E+03 7.07E+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 1.15E+05 3.25E+03 7.07E+00 +/-25%

Waste Stream  : Irradiated Components Waste Volume Curies % Error (Ci) 3 3 Class ft m Shipped A 2.32E+02 6.57E+00 4.07E+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 2.32E+02 6.57E+00 4.07E+00 +/-25%

Waste Stream: Other Waste Waste Volume Curies % Error (Ci) 3 Class ft m3 Shipped A 5.64E+02 1.60E+01 8.87E-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 5.64E+02 1.60E+01 8.87E-02 +/-25%

Waste Stream: Sum of All 4 Categories Waste Volume Curies % Error (Ci) 3 3 Class ft m Shipped A 1.16E+05 3.28E+03 2.22E+01 +/-25%

B 4.46E+02 1.26E+01 3.82E+02 +/-25%

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

All 1.16E+05 3.29E+03 4.04E+02 +/-25%

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 23 of 49 Annual Radioactive Effluent Release Report 5.2 Units 1 & 2 and Unit 3 Solid Waste - Destination by Carrier Number of Mode of Transportations Destination Shipments Waste Control Specialist, LLC (CWF) 7 Interstate Ventures Compact Waste Disposal Facility Waste Control Specialist, LLC (TSDF) 3 Interstate Ventures TSD Facility Waste Control Specialist, LLC (CWF) 1 Landstar Ranger Compact Waste Disposal Facility Waste Control Specialist, LLC (TSDF) 7 Landstar Ranger TSD Facility Waste Control Specialist, LLC (TSDF) 146 S & J Transportation Company, Inc.

TSD Facility

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 24 of 49 Annual Radioactive Effluent Release Report 5.3 Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Abundance Activity (Ci)

H-3 2.08% 2.29E-01 C-14 1.49% 1.64E-01 Cr-51 0% 1.12E-08 Mn-54 0.77% 8.49E-02 Fe-55 20.47% 2.26E+00 Fe-59 0% 9.36E-07 Co-57 0.10% 1.15E-02 Co-58 0.27% 2.99E-02 Co-60 46.20% 5.09E+00 Ni-59 0.20% 2.24E-02 Ni-63 22.28% 2.46E+00 Zn-65 0.08% 8.71E-03 Sr-89 0% 7.41E-05 Sr-90 0.03% 3.74E-03 Nb-94 0.04% 4.27E-03 Nb-95 0% 1.36E-13 Tc-99 0.02% 2.22E-03 Ag-108m 0.14% 1.50E-02 Ag-110m 0.49% 5.37E-02 Sn-113 0.02% 2.37E-03 Sb-124 0% 7.77E-06 Sb-125 2.42% 2.67E-01 Te-123m 0% 1.68E-06 Cs-137 2.71% 2.99E-01 Ce-144 0.03% 3.33E-03 Pu-238 0.01% 6.90E-04 Pu-239 0% 1.50E-04 Pu-241 0.12% 1.29E-02 Am-241 0.01% 1.07E-03 Cm-242 0% 3.09E-05 Cm-243 0.01% 1.36E-03 Total 100.00% 1.10E+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: 2022 Page 25 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and 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% 1.16E-02 C-14 0.04% 1.48E-01 Cr-51 0.03% 1.05E-01 Mn-54 0.9% 3.42E+00 Fe-55 3.31% 1.27E+01 Co-57 0.14% 5.50E-01 Co-58 0.59% 2.24E+00 Co-60 9.88% 3.78E+01 Ni-59 0.54% 2.06E+00 Ni-63 76.26% 2.92E+2 Zn-65 0.16% 5.99E-01 Sr-90 0.05% 1.95E-01 Nb-94 0.01% 2.16E-02 Tc-99 0% 3.78E-03 Ag-110m 0.06% 2.45E-01 Sb-125 3.03% 1.16E+01 Cs-134 0.03% 1.05E-01 Cs-137 4.94% 1.89E+01 Ce-144 0% 2.93E-03 Pu-238 0% 1.26E-03 Pu-239 0% 2.37E-04 Pu-241 0.04% 1.45E-01 Am-241 0% 6.61E-04 Cm-242 0% 1.64E-05 Cm-243 0% 7.85E-04

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 26 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and 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 0.06% 2.41E-01 C-14 0.08% 3.13e-01 Cr-51 0.03% 1.05E-01 Mn-54 0.89% 3.51E+00 Fe-55 3.79% 1.49E+01 Fe-59 0% 9.36E-07 Co-57 0.14% 5.61E-01 Co-58 0.58% 2.27E+00 Co-60 10.9% 4.29E+01 Ni-59 0.53% 2.09E+00 Ni-63 74.75% 2.94E+02 Zn-65 0.15% 6.08E-01 Sr-89 0% 7.41E-05 Sr-90 0.05% 1.99E-01 Nb-94 0.01% 2.59E-02 Nb-95 0% 1.36E-13 Tc-99 0% 6.00E-03 Ag-108m 0% 1.50E-02 Ag-110m 0.08% 2.99E-01 Sn-113 0% 2.37E-03 Sb-124 0% 7.77E-06 Sb-125 3.01% 1.19E+01 Te-123m 0% 1.68E-06 Cs-134 0.03% 1.05E-01 Cs-137 4.88% 1.90E+01 Ce-144 0% 6.25E-03 Pu-238 0% 1.95E-03 Pu-239 0% 3.88E-04 Pu-241 0.04% 1.58E-01 Am-241 0% 1.74E-03 Cm-242 0% 4.72E-05 Cm-243 0% 2.14E-03 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: 2022 Page 27 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.51% 3.62E-02 C-14 1.19% 8.40E-02 Mn-54 0.54% 3.79E-02 Fe-55 14.28% 1.01E+00 Co-57 0.01% 7.37E-04 Co-58 0.25% 1.74E-02 Co-60 31.8% 2.25E+00 Ni-59 0% 1.60E-07 Ni-63 44.29% 3.13E+00 Zn-65 0% 2.26E-07 Sr-90 0.11% 7.69E-03 Zr-95 0.02% 1.59E-03 Nb-94 0.1% 7.32E-03 Nb-95 0.04% 2.52E-03 Tc-99 0.03% 2.13E-03 Ag-110m 0.03% 2.33E-03 Sn-113 0% 2.36E-07 Sb-125 1.66% 1.17E-01 Cs-134 0.14% 1.02E-02 Cs-137 4.99% 3.52E-01 Ce-144 0% 1.29E-04 U-235 0% 2.02E-05 U-238 0% 1.02E-06 Pu-238 0% 9.38E-06 Pu-239 0% 2.22E-06 Pu-241 0% 2.19E-04 Am-241 0% 1.68E-04 Cm-242 0% 2.53E-06 Cm-243 0% 3.49E-04 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: 2022 Page 28 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Total Combined Nuclide Name Percent Abundance Curies H-3 0.51% 3.62E-02 C-14 1.19% 8.40E-02 Mn-54 0.54% 3.79E-02 Fe-55 14.28% 1.01E+00 Co-57 0.01% 7.37E-04 Co-58 0.25% 1.74E-02 Co-60 31.8% 2.25E+00 Ni-59 0% 1.60E-07 Ni-63 44.29% 3.13E+00 Zn-65 0% 2.26E-07 Sr-90 0.11% 7.69E-03 Zr-95 0.02% 1.59E-03 Nb-94 0.1% 7.32E-03 Nb-95 0.04% 2.52E-03 Tc-99 0.03% 2.13E-03 Ag-110m 0.03% 2.33E-03 Sn-113 0% 2.36E-07 Sb-125 1.66% 1.17E-01 Cs-134 0.14% 1.02E-02 Cs-137 4.99% 3.52E-01 Ce-144 0% 1.29E-04 U-235 0% 2.02E-05 U-238 0% 1.02E-06 Pu-238 0% 9.38E-06 Pu-239 0% 2.22E-06 Pu-241 0% 2.19E-04 Am-241 0% 1.68E-04 Cm-242 0% 2.53E-06 Cm-243 0% 3.49E-04 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: 2022 Page 29 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Irradiated Components Waste Class A Nuclide Name Percent Abundance Curies H-3 0.05% 1.98E-03 C-14 0.01% 4.85E-04 Mn-54 1.19% 4.84E-02 Fe-55 36.18% 1.47E+00 Co-57 0.03% 1.34E-03 Co-58 0.45% 1.83E-02 Co-60 44.03% 1.79E+00 Ni-59 0.03% 1.26E-03 Ni-63 14.58% 5.93E-01 Zr-95 0.33% 1.35E-02 Nb-94 0.15% 6.21E-03 Nb-95 0.75% 3.06E-02 Tc-99 0.02% 6.59E-04 Sn-113 0.08% 3.18E-03 Sb-125 1.74% 7.10E-02 Cs-137 0.25% 9.99E-03 Ce-144 0.02% 9.38E-04 Pu-238 0% 7.93E-06 Pu-241 0.11% 4.38E-03 Am-241 0% 2.16E-05 Cm-243 0% 1.44E-05

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 30 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Irradiated Components Total Combined Nuclide Name Percent Abundance Curies H-3 0.05% 1.98E-03 C-14 0.01% 4.85E-04 Mn-54 1.19% 4.84E-02 Fe-55 36.18% 1.47E+00 Co-57 0.03% 1.34E-03 Co-58 0.45% 1.83E-02 Co-60 44.03% 1.79E+00 Ni-59 0.03% 1.26E-03 Ni-63 14.58% 5.93E-01 Zr-95 0.33% 1.35E-02 Nb-94 0.15% 6.21E-03 Nb-95 0.75% 3.06E-02 Tc-99 0.02% 6.59E-04 Sn-113 0.08% 3.18E-03 Sb-125 1.74% 7.10E-02 Cs-137 0.25% 9.99E-03 Ce-144 0.02% 9.38E-04 Pu-238 0% 7.93E-06 Pu-241 0.11% 4.38E-03 Am-241 0% 2.16E-05 Cm-243 0% 1.44E-05 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 98.94% 8.78E-02 Co-60 0.57% 5.02E-04 Cs-137 0.5% 4.40E-04 Other Waste Total Combined Nuclide Name Percent Abundance Curies H-3 98.94% 8.78E-02 Co-60 0.57% 5.02E-04 Cs-137 0.5% 4.40E-04

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 31 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 1.6% 3.55E-01 C-14 1.12% 2.49E-01 Cr-51 0% 1.12E-08 Mn-54 0.77% 1.71E-01 Fe-55 21.29% 4.74E+00 Fe-59 0% 9.36E-07 Co-57 0.06% 1.35E-02 Co-58 0.3% 6.56E-02 Co-60 41.05% 9.13E+00 Ni-59 0.11% 2.37E-02 Ni-63 27.78% 6.18E+00 Zn-65 0.04% 8.71E-03 Sr-89 0% 7.41E-05 Sr-90 0.05% 1.14E-02 Zr-95 0.07% 1.51E-02 Nb-94 0.08% 1.78E-02 Nb-95 0.15% 3.31E-02 Tc-99 0.02% 5.01E-03 Ag-108m 0.07% 1.50E-02 Ag-110m 0.25% 5.60E-02 Sn-113 0.02% 5.55E-03 Sb-124 0% 7.77E-06 Sb-125 2.05% 4.55E-01 Te-123m 0% 1.68E-06 Cs-134 0.05% 1.02E-02 Cs-137 2.98% 6.62E-01 Ce-144 0.02% 4.39E-03 U-235 0% 2.02E-05 U-238 0% 1.02E-06 Pu-238 0% 7.07E-04 Pu-239 0% 1.52E-06 Pu-241 0.08% 1.75E-02 Am-241 0.01% 1.26E-03 Cm-242 0% 3.34E-05 Cm-243 0.01% 1.72E-03 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: 2022 Page 32 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0% 1.16E-02 C-14 0.04% 1.48E-01 Cr-51 0.03% 1.05E-01 Mn-54 0.9% 3.42E+00 Fe-55 3.31% 1.27E+01 Co-57 0.14% 5.50E-01 Co-58 0.59% 2.24E+00 Co-60 9.88% 3.78E+01 Ni-59 0.54% 2.06E+00 Ni-63 76.26% 2.92E+02 Zn-65 0.16% 5.99E-01 Sr-90 0.05% 1.95E-01 Nb-94 0.01% 2.16E-02 Tc-99 0% 3.78E-03 Ag-110m 0.06% 2.45E-01 Sb-125 3.03% 1.16E+01 Cs-134 0.03% 1.05E-01 Cs-137 4.94% 1.89E+01 Ce-144 0% 2.93E-03 Pu-238 0% 1.26E-03 Pu-239 0% 2.37E-04 Pu-241 0.04% 1.45E-01 Am-241 0% 6.61E-04 Cm-242 0% 1.64E-05 Cm-243 0% 7.85E-04

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 33 of 49 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Total Combined Nuclide Name Percent Abundance Curies H-3 0.09% 3.67E-01 C-14 0.1% 3.97E-01 Cr-51 0.03% 1.05E-01 Mn-54 0.89% 3.60E+00 Fe-55 4.3% 1.74E+01 Fe-59 0% 9.36E-07 Co-57 0.14% 5.63E-01 Co-58 0.57% 2.30E+00 Co-60 11.59% 4.69E+01 Ni-59 0.52% 2.09E+00 Ni-63 73.59% 2.98E+02 Zn-65 0.15% 6.08E-01 Sr-89 0% 7.41E-05 Sr-90 0.05% 2.06E-01 Zr-95 0% 1.51E-02 Nb-94 0.01% 3.94E-02 Nb-95 0.01% 3.31E-02 Tc-99 0% 8.78E-03 Ag-108m 0% 1.50E-02 Ag-110m 0.07% 3.01E-01 Sn-113 0% 5.55E-03 Sb-124 0% 7.77E-06 Sb-125 2.98% 1.21E+01 Te-123m 0% 1.68E-06 Cs-134 0.03% 1.15E-01 Cs-137 4.83% 1.96E-01 Ce-144 0% 7.32E-03 U-235 0% 2.02E-05 U-238 0% 1.02E-06 Pu-238 0% 1.97E-03 Pu-239 0% 3.90E-04 Pu-241 0.04% 1.62E-01 Am-241 0% 1.93E-03 Cm-242 0% 4.98E-05 Cm-243 0% 2.51E-03 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: 2022 Page 34 of 49 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 (because 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 gathered (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 because of onsite releases due to 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: 2022 Page 35 of 49 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: 2022 Total Body Thyroid Max Organ 40 CFR 190 limit === IPEC 25 mrem 75 mrem 25 mrem 1

Routine Airborne Effluents Units 1 and 2 2.09E-04 2.09E-04 2.09E-04 Routine Liquid Effluents Units 1 and 2 3.53E-02 5.09E-05 7.19E-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 1

Routine Airborne Effluents Unit 3 1.69E-03 1.69E-03 1.69E-03 Routine Liquid Effluents Unit 3 0.00E+00 0.00E+00 0.00E+00 14 Liquid Releases of C Unit 3 0.00E+00 0.00E+00 0.00E+00 14 Airborne Releases of C Unit 3 0.00E+00 0.00E+00 0.00E+00 2

Ground Water & Storm Drain Totals IPEC 8.48E-05 2.85E-07 3.45E-04 Direct Shine from areas such as dry 3

cask storage, radwaste storage, SG IPEC 3.00E-01 3.00E-01 3.00E-01 Mausoleum, etc.

Indian Point Energy Center IPEC 3.37E-01 3.02E-01 3.74E-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: 2022 Page 36 of 49 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) 2.26E-02 1.73E-02 2.02E-02 1.21E-02 7.19E-02 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 4.51E-01 3.45E-01 4.03E-01 2.41E-01 7.19E-01 Age Group Teenager Child Child Child Child Critical Organ Liver Bone Bone Bone Bone Adult Total Body (mrem) 1.45E-02 1.01E-02 4.16E-03 6.60E-03 3.53E-02 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 9.67E-01 6.71E-01 2.77E-01 4.40E-01 1.18E+00 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta Air (mrad) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excluding C-14, for info only)

Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 4.33E-05 3.90E-05 8.25E-05 4.39E-05 2.09E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 5.77E-04 5.20E-04 1.10E-03 5.86E-04 1.39E-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) 4.33E-05 3.90E-05 8.25E-05 4.39E-05 2.09E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 5.77E-04 5.20E-04 1.10E-03 5.86E-04 1.39E-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: 2022 Page 37 of 49 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) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Age Group - - - - -

Critical Organ - - - - -

Adult Total Body (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta Air (mrad) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excluding C-14, for info only)

Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 2.57E-04 3.55E-04 3.47E-04 7.33E-04 1.69E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 3.43E-03 4.73E-03 4.62E-03 9.77E-03 1.13E-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) 2.57E-04 3.55E-04 3.47E-04 7.33E-04 1.69E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 3.43E-03 4.73E-03 4.62E-03 9.77E-03 1.13E-02 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 Child TB Dose 3.66E-04 4.15E-04 6.93E-04 9.58E-04 2.43E-03 Child Bone Dose 0 0 0 0

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 38 of 49 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: 2022 Page 39 of 49 Annual Radioactive Effluent Release Report - Carbon-14 (C-14) Discussion - Deleted The airborne and liquid effluent doses from C-14, for both units were set to zero because both units were permanently shut down and defueled in 2022. Unit 2 was permanently shut down in April 2020, and Unit 3 was permanently shut down in April 2021.

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 40 of 49 Annual Radioactive Effluent Release Report - Groundwater Monitoring Program Results Summary of IPEC Groundwater and Storm Water Activity, 2022 The precipitation mass balance model applied in previous years was applied for offsite dose calculations in 2022, with some minor calibration updates performed in 2009 by the contractor regarding 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 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 2022, precipitation was measured at 3.15 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 2022 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 2022 totaled approximately 0.06 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 0.000029 curies to site effluent from the groundwater pathway. Combined GW releases from IPEC in 2022 (all radionuclides) resulted in a calculated annual dose of less than 0.004 % of the annual limits for whole body and critical organ:

IPEC Groundwater and Storm Water Effluent Dose, 2022 0.0000848 mrem to the total body (0.0028% limit) 0.000345 mrem to the critical organ, adult bone (0.0035% 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: 2022 Page 41 of 49 Annual Radioactive Effluent Release Report IPEC Summary for Storm & Ground Water Releases 2022 Northern Clean Zone Adult Doses, in mrem ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 4.93E-09 4.93E-09 4.93E-09 4.93E-09 4.93E-09 4.93E-09 4.41E+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 4.93E-09 4.93E-09 4.93E-09 4.93E-09 4.93E-09 4.93E-09 4.41E+02 Unit 2 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 3.18E-08 3.18E-08 3.18E-08 3.18E-08 3.18E-08 3.18E-08 1.00E+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 3.18E-08 3.18E-08 3.18E-08 3.18E-08 3.18E-08 3.18E-08 1.00E+04 Unit 1/2 ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 1.20E-07 1.20E-07 1.20E-07 1.20E-07 1.20E-07 1.20E-07 1.49E+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 1.80E-04 0.00E+00 4.41E-05 0.00E+00 0.00E+00 0.00E+00 5.18E-06 2.21E+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 1.80E-04 1.20E-07 4.42E-05 1.20E-07 1.20E-07 1.20E-07 5.30E-06 1.49E+04 Unit 3 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 9.28E-08 9.28E-08 9.28E-08 9.28E-08 9.28E-08 9.28E-08 9.56E+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 1.65E-04 0.00E+00 4.05E-5 0.00E+00 0.00E+00 0.00E+00 4.75E-06 6.58E+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 1.65E-04 9.28E-08 4.06E-05 9.28E-08 9.28E-08 9.28E-08 4.84E-06 9.57E+03 Unit 3 South ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 3.52E-08 3.52E-08 3.52E-08 3.52E-08 3.52E-08 3.52E-08 2.32E+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 3.52E-08 3.52E-08 3.52E-08 3.52E-08 3.52E-08 3.52E-08 2.32E+4

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 42 of 49 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 2.85E-07 2.85E-07 2.85E-07 2.85E-07 2.85E-07 2.85E-07 uCis BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI 5.81E+04 H3 all isotopes 3.45E-04 2.85E-07 8.48E-05 2.85E-07 2.85E-07 2.85E-07 1.02E-05 0.00E+00 Co 0.00E+00 Ni Adult Doses 2.86E+01 Sr

% Annual Limit 0.00345 0.000 0.00283 0.000 0.000 0.000 0.000 0.00E+00 Cs 0.00E+00 Sb

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 43 of 49 Annual Radioactive Effluent Release Report - Laboratory Analytical Results The following pages list the results of the 2022 groundwater samples. Note that the positive results are shown in bold print.

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 44 of 49 Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 45 of 49 Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 46 of 49 Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 47 of 49 Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 48 of 49 Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 YEAR: 2022 Page 49 of 49 Annual Radioactive Effluent Release Report

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