ML25120A328
| ML25120A328 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/30/2025 |
| From: | Noval W Holtec Decommissioning International |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| HDI-IPEC-25-016 | |
| Download: ML25120A328 (1) | |
Text
Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-IPEC-25-016 10 CFR 50.36a (a)(2) 10 CFR 72.44 (d)(3)
April 30, 2025 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:
2024 Annual Radioactive Effluent Release Report In accordance with the requirements of Title 10 of the Code of Federal Regulations (CFR),
Part 50 Section 36a (a)(2) and Part 72 Section 44 (d)(3), Holtec Decommissioning International, LLC (HDI), on behalf of Indian Point Nuclear Generating Station Units 1, 2, and 3 (IPEC), hereby submits the Annual Radioactive Effluent Release Report for 2024. The report includes effluent information from Indian Point Units 1, 2, and 3 and dose from the Independent Spent Fuel Storage Facility.
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, William Noval Director, Regulatory Affairs Holtec Decommissioning International, LLC
Enclosures:
2024 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 Digitally signed by William Noval DN: cn=William Noval, o=HDI, ou=Regulatory Affairs, email=w.noval@holtec.com Date: 2025.04.30 13:48:26 -04'00' William Noval
Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-IPEC-25-016 ENCLOSURE TO HDI-IPEC-25-016 2024 Annual Radioactive Effluent Release Report
Facility: Indian Point Energy Center Page 1 of 41 YEAR: 2024 Indian Point Units 1, 2 and 3 Docket Nos.: 50-3, 50-247, & 50-286 Holtec Decommissioning International Annual Radioactive Effluent Release Report HEEEN HOLTEC DECOMMISSIONING INTERNATIONAL
Indian Point Units 1, 2 & 3 Year: 2024 Page 2 of 41 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.......................................................................................... 25 7.0 METEOROLOGICAL DATA...................................................................................................... 29 LIST OF TABLES............................................................................................................................. 3 ATTACHMENTS - Groundwater Monitoring Program Results.................................................................... 30 - 2021 Laboratory Analytical Results............................................................................... 33 - 2023 ARERR corrected pages............... 40
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 3 of 41 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: 2024 Page 4 of 41 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). 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 (IPEC) 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 Defueled Safety Analysis Report (DSAR). ODCM Part I, also known as 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: With Units 2 and 3 permanently shut down, defueled, and all the spent fuel in dry casks on the Independent Spent Fuel Storage Installation (ISFSI),
the generation of fission and activation gases is no longer possible. The limits for fission and activation gases were removed from the ODCM.
- 2. Tritium and all radionuclides in particulate form (with half-lives > 8 days).
- a.
The dose rate for 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 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: 2024 Page 5 of 41 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 plant design, preliminary grab sampling, and conservative procedural guidance for continuous releases. These measures 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, Sr-90),
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.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 6 of 41 Annual Radioactive Effluent Release Report 2.3 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 Both units are permanently shut down and the respective Spent Fuel Pools are empty of spent fuel. All spent fuel assemblies are now stored in dry casks in the Independent Spent Fuel Storage Installation (ISFSI).
Sampling for fission and activation gases is no longer required based on the above statement.
- 2. Particulates Unit 2 and Unit 3 airborne particulate releases are quantified by collecting a continuous sample of ventilation air on 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. A compositing method of analyzing gross alpha, Sr-89, and Sr-90, is used per station ODCM. Absence of any positive activity is identified as -.
Iodine is no longer sampled at the site. All spent fuel was moved to the ISFSI, and any remaining iodine in plant systems has decayed away.
- 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 release 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.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 7 of 41 Annual Radioactive Effluent Release Report
- 4. 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.
Fission and activation products identified in the liquid effluents are listed in the Liquid Effluent Tables in Section 4. In addition, the gross beta results are added to the identified radionuclides to determine the total activity released. Although this will overestimate the curies and result in additional conservatism in the calculated dose to the public, the increase is minimal when compared to the overall dose to the public from the site.
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 (Unit 1s Sphere Foundation Drain Sump). 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.
- 5. 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: 2024 Page 8 of 41 Annual Radioactive Effluent Release Report 2.4 Batch Releases:
- 1. Airborne Table 2.5 Airborne Batch Releases Batch Airborne Releases are no longer performed at IPEC.
- 2. Liquid Table 2.5 Liquid Batch Releases Unit 1 and 2 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2024 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 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2024 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 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 2.5 Abnormal Releases
- 1. Liquid None
- 2. Gaseous None 2.6 Non-routine, Planned Discharges None
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 9 of 41 Annual Radioactive Effluent Release Report 2.7 Radioactive Waste Treatment System Changes None 2.8 Land Use Census Changes No changes or modifications affecting receptors, receptor location or new (or changed) routes of exposure were identified.
2.9 Effluent Monitor Instrument Inoperability
- 1. Effluent Monitoring Equipment Inoperable > 30 Days None.
- 2. Effluent Monitoring Equipment Sample Deviation None.
2.10 Offsite Dose Calculation Manual Changes There were no ODCM changes in 2024.
2.11 Process Control Program (PCP) Changes There were no PCP changes during 2024.
2.12 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 2024, 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 2024 total routine liquid effluent dose inclusive of the groundwater pathway contributes < 1 % of the annual limit. Groundwater and storm water effluent flow rates and source term data are further described in Attachment 1 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 1. Section 6 (Radiological Impact on Man) of this report provides a comparison of the groundwater and storm water doses to the other dose pathways.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 10 of 41 Annual Radioactive Effluent Release Report 2.13 Outside Tanks During this period, no curie limits in outdoor tanks were exceeded.
2.14 Errata/Corrections to Previous ARERRs 2023 ARERR, Attachment 7 - While correcting the Unit 3 Radiological Impact on Man Table, a new transposition error was introduced under Section A, Liquid Doses section of the table. The Percent of Limit could not be calculated due to the double negative sign inadvertently applied to the exponent in the Organ Dose value. Verified values from RETDAS printouts. Report tables were corrected.
The correction did not change the reported 40CFR190 Total Dose for Indian Point Energy Center. The original and corrected pages are in Attachment 3 of this report.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 11 of 41 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS Table 3-1 Gaseous Effluents - Summation of All Releases - Units 1 and 2 A. Fission & Activation Gases Units
- 1. Total Release Ci No longer produced on site Pp
- 2. Average release rate uCifsec B. lodines
- 1. Total lodine-131 Ci No longer produced on site
- 2. Average release rate uCifsec C. Particulates Qtrl Qir 2 Qir3 Qir 4 Year
- 1. Total Release, with Ci 1.56E-06 l 1.3905 l 5.47E-06 l 4.95E-06 l 2.59E-05 half-life >8 days
- 2. Average release rate uCifsec l 1.99E-07 l 1.77E-06G l 6.88E-07 l 6.22E-07 l 8.20E07
- 3. Gross Alpha Ci l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 D. Tritium Qri Qir2 Qir3 Qir 4 Year
- 1. Total release Ci l 4.70E-01 l 3.80E-01 l 1.42E+00 l 1.82E+00 l 4.09E+00
- 2. Average release rate uCifsec l 5.98E-02 l 4.83E02 l 1.78601 l 2.29E-01 l 1.29E-01
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 12 of 41 Annual Radioactive Effluent Release Report Table 3-2 Gaseous Effluents - Batch Mode - Units 1 and 2 Nuclides Released
- 1) Fission & Aclivalion Gases Fission and Activation Gases are no longer produced on site.
- 2) lodines lodine 15 no longer produced on site.
- 3) Particulates Batch releases are no longer performed on site.
- 4) Tritium Batch releases are no longer performed on site.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 13 of 41 Annual Radioactive Effluent Release Report Table 3-3 Gaseous Effluents - Continuous Mode - Units 1 and 2
- 1) Fission & Activation Gases Fission and Activation Gases are no longer produced on site.
- 2) lodines lodine is no longer produced on site.
- 3) Particulates Units Qir1 Qir 2 Qtr 3 Qir 4 Year Cs-137 Ci 4.50E-11 l 9.76E-11 l 1.25E-10 l 1.90E-10 l 4.58E-10 Gross Beta Ci 1.56E-06 l 1.39E-05 l 5.47E-06 l 4.95E-06 l 2.589E-05 Total far Period Ci 1.56E-06 l 1.39E05 l 5.47E-06 l 4.95E-06 l 2.50E-05
- 4) Tritinm Units Qir1 Qir 2 Qtr 3 Qtr 4 Year H-3 Ci 4.70E-01 l 3.80E01 l 1.42E+00 l 1.82E+00 l 4.08E+00
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 14 of 41 Annual Radioactive Effluent Release Report Table 3-4 Gaseous Effluents - Summation of All Releases - Unit 3 A. Fission & Activation Gases Units
- 1. Total Release Ci No longer produced on site Pp
- 2. Average release rate uCirsec BE. lodines
- 1. Total lodine-131 Ci No longer produced on site
- 2. Average release rate uCifsec C. Particulates Qir1l Qir2 Qir3 Qir 4 Year
- 1. Total Release, with Ci 0.00E+00 l 0.00E+00 l 6.58E-07 l 2.19E-06 l 285E-06 half-life >8 days
- 2. Average release rate uCifsec { 0.00E+00 l 0.00EHD0 l 8.28E-08 l 2.75E-07 l 8.95E08
- 3. Grass Alpha Ci l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 D. Tritium Qtr Qir2 Qir3 Qtr 4 Year
- 1. Total release Ci l 6.34601 l 9.56E-01 l 2.16E+00 l 1.46E+00 l 5.21E+00
- 2. Average release rate uCifsec l 8.06E-02 l 1.22E-01 l 2.71E-01 l 1.84E-01 l 1.64E)1
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 15 of 41 Annual Radioactive Effluent Release Report Table 3-5 Gaseous Effluents - Batch Mode - Unit 3 Huclides Released
- 1) Fission & Activation Gases Fission and Activation Gases are no longer produced on site.
- 2) lodines ladine is no longer produced on site.
- 3) Particulates Batch releases are no longer performed on site.
- 4) Tritium Batch releases are no longer performed on site.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 16 of 41 Annual Radioactive Effluent Release Report Table 3-6 Gaseous Effluents - Continuous Mode - Unit 3
- 1) Fission & Activation Gases Fission and Activation Gases are no longer produced on site.
- 2) lodines iodine is no longer produced on site.
- 3) Particulates Units Qir1l Qir 2 Qir3 Qtr 4 Year Gross Beta Ci l 0.00E+00 l 0.00E+00 l 6.58E-07 l 2.19E-06 l 2.85E-06 Total for Period Ci l 0.00E+00 l 0.00E+00 l 6.58E-07 l 2.19E-06 l 2.85E-06
- 4) Tritium Units Qtr Qir2 Qir3 Qtr 4 Year H-3 Ci l 6.34601 l 9.56E-01 l 2.16E+00 l 1.46E-+00 l 5.21E+00 Total for Period Ci l 6.34601 l 9.56E-01 l 2.16E+00 l 1.46E+00 l 5.21E+00
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 17 of 41 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS Table 4-1 Liquid Effluents - Summation of All Releases - Units 1 and 2 A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year
- 1. Total Release (not including Tritium, Gr Alpha, & Gases)
Ci 2.98E-03 3.22E-03 4.74E-03 5.81E-04 1.15E-02
- 2. Average Diluted Conc uCi/ml 5.44E-10 6.46E-10 9.95E-10 1.41E-10 5.96E-10 B. Tritium
- 1. Total Release Ci 4.43E-03 7.04E-03 5.78E-03 2.40E-03 1.97E-02
- 2. Average Diluted Conc uCi/ml 8.09E-10 1.41E-09 1.21E-09 5.83E-10 1.02E-09 C. Dissolved & Entrained Gases
- 1. Total Release Ci
- 2. AverageDiluted Conc uCi/ml D. Gross Alpha
- 1. Total Release Ci
- 2. AverageDiluted Conc uCi/ml E. Volume of Waste Released
- 1. Processed Fluids liters 4.33E+06 1.34E+06 1.39E+06 5.79E+05 7.64E+06
- 2. Unprocessed Fluids liters 1.24E+07 7.99E+06 7.29E+06 5.16E+06 3.28E+07 F. Volume of Dilution Water liters 5.47E+09 4.98E+09 4.77E+09 4.12E+09 1.93E+10
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 18 of 41 Annual Radioactive Effluent Release Report Table 4-2 Liquid Effluents - Batch Mode - Units 1 and 2 There were no Batch liquid releases this reporting period.
There were no Batch liquid releases this reporting period.
- 3) Dissolved and Entrained Gases There were no Batch liquid releases this reporting period.
There were no Batch liquid releases this reporting period.
Nuclides Released
- 1) Fission and Activation Products
- 2) Tritium
- 4) Gross Alpha Activity
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 19 of 41 Annual Radioactive Effluent Release Report Table 4-3 Liquid Effluents - Continuous Mode - Units 1 and 2 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Sr-90 Ci 4.75E-05 0.00E+00 3.23E-05 0.00E+00 7.98E-05 Cs-137 Ci 1.59E-03 1.86E-03 2.66E-03 3.35E-04 6.45E-03 Gross Beta Ci 1.34E-03 1.36E-03 2.05E-03 2.46E-04 5.00E-03 Total for Period Ci 2.98E-03 3.22E-03 4.74E-03 5.81E-04 1.15E-02 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year H-3 (only)
Ci 4.43E-03 7.04E-03 5.78E-03 2.40E-03 1.97E-02 No Nuclides Found No Nuclides Found Nuclides Released
- 1) Fission and Activation Products
- 2) Tritium
- 3) Dissolved and Entrained Gases
- 4) Gross Alpha Activity
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 20 of 41 Annual Radioactive Effluent Release Report Table 4-4 Liquid Effluents -Summation of All Releases - Unit 3 A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year
- 1. Total Release (not including Tritium, Gr Alpha, & Gases)
Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Average Diluted Conc uCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Tritium
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Average Diluted Conc uCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Dissolved & Entrained Gases
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. AverageDiluted Conc uCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Gross Alpha
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Waste Released
- 1. Processed Fluids (Mon Tanks) liters 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Unprocessed Fluids liters 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F. Volume of Dilution Water liters 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 There were no liquid releases from Unit 3 in 2024.
% limit is located in Section 6, Tables 6-2 and 6-3
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 21 of 41 Annual Radioactive Effluent Release Report Table 4-5 Liquid Effluents - Batch and Continuous Modes - Unit 3 There were no liquid releases, Batch or Continuous, in 2024 from Unit 3.
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 22 of 41 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 Curies Class ft3 m3 Shipped A
3.54E+02 1.00E+01 1.45E+02 B
1.77E+02 5.00E+00 2.12E+02 C
0.00E+00 0.00E+00 0.00E+00 All 5.31E+02 1.50E+01 3.57E+02 Waste Stream : Dry Active Waste Waste Curies Class ft3 m3 Shipped A
8.07E+04 2.29E+03 4.07E+01 B
0.00E+00 0.00E+00 0.00E+00 C
0.00E+00 0.00E+00 0.00E+00 All 8.07E+04 2.29E+03 4.07E+01 Waste Stream : Irradiated Components Waste Curies Class ft3 m3 Shipped A
1.16E+03 3.29E+01 3.52E+01 B
0.00E+00 0.00E+00 0.00E+00 C
0.00E+00 0.00E+00 0.00E+00 All 1.16E+03 3.29E+01 3.52E+01 Waste Stream: Other Waste Waste Curies Class ft3 m3 Shipped A
0.00E+00 0.00E+00 0.00E+00 B
0.00E+00 0.00E+00 0.00E+00 C
0.00E+00 0.00E+00 0.00E+00 All 0.00E+00 0.00E+00 0.00E+00 Waste Stream: Sum of All 4 Categories Waste Volume Curies Class ft3 m3 Shipped A
8.22E+04 2.33E+03 2.21E+02 B
1.77E+02 5.00E+00 2.12E+02 C
0.00E+00 0.00E+00 0.00E+00 All 8.24E+04 2.33E+03 4.33E+02 Volume Volume Volume Volume
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 23 of 41 Annual Radioactive Effluent Release Report 5.2 Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream NRC Regulatory Guide 1.21 Activity Report Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Shipment, Package, and Category During Period From: 01/01/2024 to 12/31/2024 Percent Cutoff: 1.0%
10.36%
12.92%
12.49%
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 24 of 41 Annual Radioactive Effluent Release Report Units 1 & 2 and Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream NRC Regulatory Guide 1.2% Activity Report Solid Wasle Shipped Offsite for Disposal and Estimates of Major Nuclides by Shipment,Package, and Category During Period From: 01/01/2024 to 12/31/2024 Percent Cultodt: 1.0%
Ni-63 17.51%
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 25 of 41 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 in 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. 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 1. 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 1. 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: 2024 Page 26 of 41 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: 2024 Total Body Thyroid Max Organ 40 CFR 190 limit===
IPEC 25 mrem 75 mrem 25 mrem Routine Airborne Effluents 1
Units 1 and 2 6.84E-04 6.84E-04 6.84E-04 Routine Liquid Effluents Units 1 and 2 2.66E-02 4.65E-07 4.18E-02 Routine Airborne Effluents 1
Unit 3 8.61E-04 8.61E-04 8.61E-04 Routine Liquid Effluents Unit 3 0.00E+00 0.00E+00 0.00E+00 Ground Water & Storm Drain Totals IPEC 2
1.07E-04 3.67E-07 4.35E-04 Direct Shine from areas such as dry cask storage, radwaste storage, SG Mausoleum, etc.
IPEC 3
2.00E-01 2.00E-01 2.00E-01 Indian Point Energy Center Total Dose, per 40 CFR 190 IPEC 2.28E-01 2.44E-01 2.02E-01 Note 1: Routine airborne dose in this table is conservatively represented as a sum of Particulate and Tritium dose from site releases. 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 1.
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: 2024 Page 27 of 41 Annual Radioactive Effluent Release Report Table 6-2 Unit 2 Appendix I Dose Assessment Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 1.09E-02 1.12E-02 1.65E-02 3.90E-03 4.18E-02 Applicable Limit (mrem) 5 5
5 5
10 Percent of Limit
(%)
0.22 0.22 0.33 0.08 0.42 Age Group Child Teenager Child Teenager Child Critical Organ Bone Liver Bone Liver Bone Adult Total Body (mrem) 6.62E-03 7.05E-03 1.05E-02 2.45E-03 2.66E-02 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit
(%)
0.44 0.47 0.70 0.16 0.89 Note: Liquid Annual dose is the Dose Analysis for the year, it is not a sum of the quarters 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
(%)
0.00 0.00 0.00 0.00 0.00 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
(%)
0.00 0.00 0.00 0.00 0.00 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Particulate (mrem) 7.88E-05 6.36E-05 2.37E-04 2.89E-04 6.84E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit
(%)
0.0011 0.0008 0.0032 0.0038 0.0046 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 Child TB Dose (mrem) 7.88E-05 6.36E-05 2.37E-04 2.89E-04 6.84E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit
(%)
0.0011 0.0008 0.0032 0.0038 0.0046 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Child Bone Dose (mrem) 3.68E-10 7.99E-10 7.99E-10 3.65E-05 3.74E-09 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit
(%)
0.00 0.00 0.00 0.00 0.00 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 A. LIQUID DOSES B. AIRBORNE NOBLE GAS DOSES C. AIRBORNE PARTICULATE and TRITIUM DOSES D. AIRBORNE PARTICULATE and TRITIUM DOSES
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 28 of 41 Annual Radioactive Effluent Release Report Table 6-3 Unit 3 Appendix I Dose Assessment 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
(%)
0.00 0.00 0.00 0.00 0.00 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
(%)
0.00 0.00 0.00 0.00 0.00 Note: Liquid Annual dose is the Dose Analysis for the year, it is not a sum of the quarters 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
(%)
0.00 0.00 0.00 0.00 0.00 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
(%)
0.00 0.00 0.00 0.00 0.00 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Particulate (mrem) 1.05E-04 1.58E-04 3.56E-04 1.70E-04 8.61E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit
(%)
0.0014 0.0021 0.0048 0.0023 0.0057 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 Child TB Dose (mrem) 1.05E-04 1.58E-04 3.56E-05 1.70E-04 8.61E-04 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit
(%)
0.0014 0.0021 0.0005 0.0023 0.0057 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
(%)
0.00 0.00 0.00 0.00 0.00 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 A. LIQUID DOSES B. AIRBORNE NOBLE GAS DOSES C. AIRBORNE PARTICULATE and TRITIUM DOSES D. AIRBORNE PARTICULATE and TRITIUM DOSES
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 29 of 41 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: 2024 Page 30 of 41 Annual Radioactive Effluent Release Report - Groundwater Monitoring Program Results Summary of IPEC Groundwater and Storm Water Activity, 2024 The precipitation mass balance model applied in previous years was applied for offsite dose calculations in 2024, 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 2024, precipitation was measured at 4.27 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 2024 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 2024 totaled approximately 0.04 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 0.000036 curies to site effluent from the groundwater pathway. Combined GW releases from IPEC in 2024 (all radionuclides) resulted in a calculated annual dose of less than 0.0044 % of the annual limits for whole body and critical organ:
IPEC Groundwater and Storm Water Effluent Dose, 2024 0.000107 mrem to the total body (0.0036% limit) 0.000435 mrem to the critical organ, adult bone (0.0044% 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: 2024 Page 31 of 41 Annual Radioactive Effluent Release Report IPEC Summary for Storm & Ground Water Releases 2024 Northern Clean Zone Adult Doses, in mrem ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 5.61E-09 5.61E-09 5.61E-09 5.61E-09 5.61E-09 5.61E-09 5.02E+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 5.61E-09 5.61E-09 5.61E-09 5.61E-09 5.61E-09 5.61E-09 5.02E+02 Unit 2 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.99E+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 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.99E+03 Unit 1/2 ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 1.47E-07 1.47E-07 1.47E-07 1.47E-07 1.47E-07 1.47E-07 1.66E+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 2.95E-04 0.00E+00 7.22E-05 0.00E+00 0.00E+00 0.00E+00 8.48E-06 2.30E+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 2.95E-04 1.47E-07 7.24E-05 1.47E-07 1.47E-07 1.47E-07 8.63E-06 1.66E+04 Unit 3 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.03E+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 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.03E+04 Unit 3 South ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 6.40E-08 6.40E-08 6.40E-08 6.40E-08 6.40E-08 6.40E-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 1.41E-04 0.00E+00 3.45E-05 0.00E+00 0.00E+00 0.00E+00 4.05E-06 1.29E+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 1.41E-04 6.40E-08 3.46E-05 6.40E-08 6.40E-08 6.40E-08 4.11E-06 1.20E+04
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 32 of 41 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 H-3 only 0.00E+00 1.92E-07 1.92E-07 1.92E-07 1.92E-07 1.92E-07 1.92E-07 Total uCis BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI 4.43E+04 H3 all isotopes 4.35E-04 3.67E-07 1.07E-04 3.67E-07 3.67E-07 3.67E-07 1.29E-05 0.00E+00 Co 0.00E+00 Ni Adult Doses 3.59E+01 Sr
% Annual Limit 0.00435 0.000 0.00357 0.000 0.000 0.000 0.000 0.00E+00 Cs 0.00E+00 Sb
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 33 of 41 Annual Radioactive Effluent Release Report - Laboratory Analytical Results The following pages list the results of the 2024 groundwater samples. Note that the positive results are shown in bold print.
V 2024 Laboratory Analytical Results Vell ID Sample H-3 H-3 Sr-90 sod Cs137 =
B71 cogo icine Ni-63 Roni Date Result 3 Sigma Result (Sed Result (Sod, Result (Se, Result (Sel, pCi)
(sed. Dev l pei) l BV l peiay l ER fein l BE l pci l EEL BE H523%2024 l 1.04E+03 304E +02
-0.6 14 0.0 13.0 0.8 3.3 MH-5 VCFD
¥82024 l 3.66E+02l 3R7E+02 0.0 09 0.7 4.4
-18 5.5 MHA VCFD l 342024 l 1.12E+03 l 552E+02 0.3 1.0 1.9 6.1 1.4 7.0 MHS VCFD l 52002024 l 263E+02 l 4.05E+02
-0.5 0.9 0.0 5.3 20 0.2 MH-5 YCFD l 8122024 l 1.06E+03 MH-5 VCFD l ¥2¥2024
<4B4 0.6 15
-10 41
-0.6 51 hel -107 ain2024
<483 0.2 09 0.5 6.4
-1.3 9.4
-0.2 16.4 kev -111 9132024 l B817E+02 l 456E+02
-1.0 14 0.0 13.2 47 7.5 hAW-1T1 o2a2024 l 8.94E+02 hAaf-30-69 42024 12.07E+D4 Mwi-30-69 H2002024 l 266E+04 hA\\wf-30-69 22002024 l 4.51E+D04 hAWf-30-82 42024 l 1L.0E+DS hAW-30-82 82024 l 1.00E+05 Mwi-30-84 A42024 l 2.6G0E+D4l 194E+03
-0.3 1.2
-2.4 6.8 4.2 3.8 Mw-30-84 H2002024 l 2.62E+D4l 170E+03
-0.6 049 2.3 5.0
-18 5.2 hA\\w-30-84 22002024 l 2.26E+D4
-12 G2
-09 9.0 relif-31-49 AM2024 l -50E+00 l 3.49E+02
-0.2 11 5.0 9.9 3.5 6.2 hedf-31-49 5212024 l 1.12E+03 l 456E+02 0.0 0.7
-0.9 6.0 1.0 7.1 hived-31-49 192024 433 27 FA a7 7.0 flWw/-31-49 l 22024
<484 0.7 13
-0.2 7
06 5.5 Pelbf-31-49 TWRI2024
<<452 hef-31-63 AM2024 13.09E+03l 7.99E+02 0.8 0.9 0.2 4.7
-0.3 4.4 hAWf-31-63 5212024 l 4.55E+032l 6.51E+02 0.1 11 13 12.1 4.1 5.2 mlvad-31-63
- 192024 l 1.93E+03 23 6.4 21 73 kWw/-31-53 l 232024 l 2.97E+03
-0.3 12
-12 hE 19 5.0 helf-31-53 WR2024 l 2.1IE+03 hAf-31-85 F2024 119E+02 l 3.75E+02
-0.4 12 17 4.5
-1.5 5.4 hived-31-85 5212024 l 8.70E+02l 456E+02 0.0 11 2.2 5.0 0.9 10.2 mivf-31-85 192024
<4B3 0.5 44 40 5.2 kWw/-31-85 l 232024
<484
-0.3 12 0.7 5
0.0 45 hWw-32-149 FIH2024 1568E+02 l 4.32E+02 0.2 15
-4.8 10.3 31 6.5 kW 149 l S2002024 l 2.23E+02 l 4.35E+02
-0.9 0.9 5.9 10.3
-0.3 3.3 Mw-32-149 l S2002024
<4B63
-2
[3]
-0.3 5.4 Mw-32-149 l 1T02V2024
<464
-0.5 11 0.6 55 16 7.4 MW 173 AH2024 1.78E+02 l 4.35E+02 11 11 31 6.4 20 5.5 kW 173 l 2002024 l -5.12E+01 l 3.72E+02 0.7 13 0.0 8.9 5.3 3.5 M-32-173 l B2002024
<463
-1 5
-0.3 5.6 Mw-32-173 l 12¥2024 464
-0.5 11
-0.6 47 0.1 51 Mf-32-190 FIH2024
-193E+01 l 3.99E+02 0.7 14
-8.9 8.2 46 75 kW 190 l 20/2024 l -6.26E+00 l 3.66E+02
-0.2 0.6 0.2 4.2 11 42 hW-32-190 l S2002024
<463 47 13.2
-0.1 71 Mw-32-190 l 1N2¥2024
<4B4 ny 16 1.3 6.7
-09 9.0 Mw-32-59
¥82024 l 5.64E+02l 38IE+D2
-0.7 11 1.0 55
-1.0 5.4 kAWw-32-59 292024 187E+02 l 4.17E+02 0.9 13
-0.8 5.0 0.3 47 hAWw-32-59 AN2024 l 7.94E+02 l 5.07E+02 0.4 0.9
-2.1 5.3 14 5.0 hf-32-59 H2A42024 l5.93E+03 l 5.26E+02 0.1 12
-1.4 5.6 16 2.5 Mw/-32-53 S224 417E+03 l 7.41E+02
-0.2 11
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Indian Point Units 1, 2 & 3 YEAR: 2024 Page 34 of 41 Annual Radioactive Effluent Release Report 2024 Laboratory Analytical Results Vell ID Sample h-2 H-3 Sr-90 2 rama Cs-137 ll Co-60 2 rama Ni-63 2 Sigma esult 2 Sigma Result (Std.
Result (Std.
Result (Std.
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Indian Point Units 1, 2 & 3 YEAR: 2024 Page 35 of 41 Annual Radioactive Effluent Release Report 4
2024 Laboratory Analytical Results Sample H-3 H-3 sr90 l 5790 l poqar CSB pogo l BO80 ll pigs l MSI vellio Date Result 3 Sigma Result 3 oa Result 3 oo Result 3 oo Result 3 fo
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Indian Point Units 1, 2 & 3 YEAR: 2024 Page 36 of 41 Annual Radioactive Effluent Release Report 2024 Laboratory Analytical Results Vell ID Sample h2 H-3 Sr-90 2 gma Cs-137 ell Co-60 2 Sian Ni-62 2 9iama esult 3 Sigma Result (Std.
Result (Std.
Result (Std.
Result (Std.
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Indian Point Units 1, 2 & 3 YEAR: 2024 Page 37 of 41 Annual Radioactive Effluent Release Report 2024 Laboratory Analytical Results Sample H-3 H-3 sr90 l S790 l poqar ESB pogo l COBO ll pigs l M63 Veni Date Result 3 Sigma Result 3 oa Result 3 oo Result 3 oa Result 3 on (pCi) l (Std. Dev) l (pCit) l pon ll teCitt) l pon ll Cin) l pon l ecitn) l pn Mw-h4-144 l HI52024 l B.0ME+D2 l 450E+02 2.0 16
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Indian Point Units 1, 2 & 3 YEAR: 2024 Page 38 of 41 Annual Radioactive Effluent Release Report 2024 Laboratory Analytical Results Sample H-3 H-3 seo l S190 fl po qap lCSBT l op gp l COD ll pgp l M63 velo Date Result 3 Sigma Result 3 a Result 3 on Result 3 a Result 3 oo
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-4.5 E.2 0.2 53 2.0 18.5 Mw-EB-21 l 8132024
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<467 0.3 0.8 Mw-BB-36 l F204 l 2 21E+03 l 6.78E+02 l 3.6 15
-0.4 5.7
-0.2 5.7 2.3 14.0 MW-B6-36 l SN132024 12 23E+03l A.73E+02 ll 3.0 17 0.8 E.2 17 9.3
-3.3 18.9 Mw-B6-36 l 8132024 l 1.63E+03 1h 12 Mw-EB-36 l 100292024 l 2.24E+03 3.0 2.1 11
£2
-0.2 b.5 0.3 20.6 Mw-67-100 l FAH2024 l9.78E+02( 5.34E+02 ll 13 15 26 E.5
-0.4 5.0 13 16.0 MW-E7-105 l S142024 l] 1.09E+03 l 3.54E+02 0.8 1.0 0.7 4.4 1.0 5.6
-10 16.4 Mw-67-100 l S132024 l 6.07E+02
-0.9 13 PAw-67-105 l TH42024 l 1.08E+03
-0.1 12 Mw-67-173 l FA2024 l5.93E+02l 5.13E+02 ll -0.3 10 25 125
-2.1 6.8 1.1 17.0 MW-E7-173 l S4H2024 l 7.31E+D2 l 312E+02
-0.4 1.0
-0.5 E.1
-2.9 73
-17 16.6 Mw-67-173 l 132024 l5.60E+02
-0.2 11 PW-EF-173 l TH42024 l5.84E+D2 13 16 Mw-67-219 l 32024 19.43E+02l 5.34E+02 l 0.2 15
-13 E.3
-13 48 15.6 18.4 MW-67-219 l S142024 11.07E+03 l 3.54E+02 0.0 1.0 15 14.2
-12 1.4 41 16.9 Mw-67-219 l 132024 l5.65E+02 11 16 PW-E7-219 l TH42024 l 1.32E+03 0.3 12 MW-B7-276 l 3122024 l17.29E+02 l 5.25E+02 11 17
-10 4.9
-2.3 4.4 12.4 18.0 MWwW-67-276 l 542024 l 7.BIE+D2 l 309E+02 0.4 11 13 8.4 18 7.5 0.0 16.2 Mw-67-276 l 1¥2024 l 8.52E+02
-0.5 15 PAW-67-276 l TH42024 l 8.76E+02 0.6 12 Mw-67-340 l 1X2024 l 255E+02 l 450E+02 [l 13 15 293 9.8
-0.9 5.4 17 17.1 Miw-67-340 l 5142024 14. 3E+02 l 290E+02 l 0A 0.9 16 71 0.1 7.2 38 17.1 Mw-67-340 l 81¥2024
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-0.6 14 Mw-67-340 l TH42024 l 2.3BE+03
-0.7 12 MW-E7-29 l 22024
§1.92E+03 l 563E+02 l 10 16
-0.5 6.1
-0.3 5.2 4.9 17.0 Mw-E7-39 l S42024
§1197E+03 l 444E+02 l 2.5 14 4.0 2.0 12 95
-2.1 16.9 hwW-67-39 l 8132024 l 1.92E+03 2.2 16 MW-E7-39 l TH42024 l 1.97E+03 2.8 19 Mw-63-103 l F52024 l 432E+02 l 432E+02 l 0.9 12 0.0 5.2 0.8 39 Mwi-63-103 l BA2024 l5.00E+02l 426E+02 l 0.1 1.0 0.2 49 0.41 5.8 Mw-68-103 l S212024 l 5.87E+02 Mw-63-103 l 107312024
<467 Mw-63-132 l FIN2024 l 465E+02 l 441E+02 l 0.9 13
-0.2 E.4 23 5.7
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 39 of 41 Annual Radioactive Effluent Release Report 2024 Laboratory Analytical Results well ID Sample H-3 H-3 srao l S70 ff oo gap
[CSB pogo l CO80 [1 piggy l M63 Date Result 2 Sigma Result i
Result do Result on Result
? on pci)
(sed. Dev l pein) l BU l poi) l EN cin l GE l pci l EEL Mw 68-132 NA2024 2B84E+02 l 4.20E+02 0.4 12 26 5.0 0.5 5.1 MwW-68-132 l 9212024 l 5.18E+02 Mw-68-132 l 10312024 l 5.10E+02 hiv/-68-19 IN2024
§7.99E+02l 4.74E+02 16 14 0.1 6.5 3.0 5.9 hw 19 HA2024 l 5.81E+02 l 4 29E+02 0.2 12
-0.8 B.S 26 72 h\\W/-68-13 9272024
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<451 mA -B3-57 IN2024 l6.62E+02l 47E+02 11 0.9
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<4k1 miW/-B63-57 l 1372024
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-8.7 17.5 UI-WNCD I2024
-5.50E+01 l 3.72E+02 8.5 25 6000.0 136.5 0.4 7.4 271.0 28.6 LH-MCD R2A2024 l 304E+02 l 327E+02 T.¥ 24 5890.0 114.3 0.5 46 196.0 27.6 LH-WCD HR2024 l 3.52E+02 l 363E+02 87 21 160.0 g1.0
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-6.7 16.0 L1-SFDS A024 l 192E+01 l 247E+02 0.7 16 1.7 49 0.4 46
-B.1 19.7 LN-SFDS AA2024 171E+02 l 357E+02 28 18 f1 47 12 28 1.4 16.1 LH-SFDS 1NY2024 18 139 11 9.3 0k 6.5 5.3 16.8 LN-SFDS 1AM52024
¢<452 LN-SFDS 12312024 12 17 85 98 24 6.2
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-11 49 Us-4D 9272024
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-0.7 36 19 3.9 U3-T1 0302024 l 5.39E+02 u3-t2 He¥2024 l 203E+02 l 299E+02 0.0 11 2.8 42 0.8 2.6 L3-T2 1302024
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Indian Point Units 1, 2 & 3 YEAR: 2024 Page 40 of 41 Annual Radioactive Effluent Release Report - 2023 ARERR original page.
Page 1 of 2 Indian Point Units 1,2 & 3 YEAR: 2023 Page 60 of 66 Annual Radioactive Effluent Release Report - 2016 ARERR corrected pages.
Page 4 of 4 2016 ARERR Revision 1 Docket No. 50-3, 50-247, & 50-288 Page 48 of 92 INDIANPOINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ONMAN JANUARY -DECEMBER 2016 OLD DOSES 4
Ctr9 Qtr 2 ofr 3 Qtr4 l ANNUAL Rav1 Organ Dose (rmeem) [l 1.23604 l B.20E-04 l 7.07E-05 l 1.26E-04 l 4.98E04 wa l_{rryem) 5 3
3 I
TE Sm l I Pavcert of Limit 9%
ALl 6 58E-03 l 141E-03 l 2526-03 l 498E-03 Group Adull Child Child Chit Crifical l
Bone GHLI Bone Bone Bone Adult Tota Body l (mwem) l 2666-05 1116-04 l 112605 l 350605 l 1.55604
[Applicable Lim l (nwem) 1.5 1.5 15 1.5 ag Percent of Limit
{%) l 1776-03]
7.40E-03 l 7.47E-04 l 233E-03 l 517E-03
- 8. AIRBORNE NOBLE GAS DOSES 1
Qir2 Qtr 3 Qtr 4 ANNUAL Gamma Air
{mrad}
164E-05l 1876-05 l 178E-05 l S.7DE-05 5
5 Umkt_l (md) 5 5
5 10 Percent of Limit
{%)
300-04 l 328604 l 3ITAEDS l 3566-04 l 6.79E04 Bota Air
{mrad}
1.77E-05 l 1.96E-05 l 2 38F-05 l 225F-05
[A
[Applicable Limit_l (mrad) 10 10 10 10 20 lParcent of Limit
{%)
1.77E-04 l 1.95E-04 l 2386-04 l 2266-04 l 4.18E-04 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (exchxiing C-14, for info only)
Qtr vy Or 2 otr3 or 4 ANNUALl lndine/Part (mem) 596E-04 l 7596-04 l 7 76E-04 l 496E-04 l 2.63E-0
[Appicable Limt l (mrem) 7.5 75 7.5 7.5 15 Percent of Limit
{%)
7.85603 1 1.01602 l 1.03602 l 66103 1.7502 LAQS Croup Chid 1 _Chid 1__Chid l __Chid i Critical Organ Liver Liver Liver Liver D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES ChikdTH Dose
{mrem) l 1746-02 l 1766-02 l 1766-02 l 1736-02 l 7.00602
[(Appicatie Limit l (mmm) 75 75 75 75 15 Peycent of Limit
{%)
2 336-01 l 235601 l 235601 l
2 31E-O01 4 67E-01 ofr 1 ofr 2 ors ord l ANNUAL Child Bona Dose l
{mrem)
B.ASE-02 l B.45SE-02 l B456-02 l B4SE-D2 JI38E-(1 Applicable Limk_l _(mrem) 75 75 7.5 7.5 15 Percent of Limit
(%)
l 1.13E+00] 1.13E+00 l 1.93E+00 l 1.93E+00 l 2256+00
Indian Point Units 1, 2 & 3 YEAR: 2024 Page 41 of 41 Annual Radioactive Effluent Release Report - 2023 ARERR corrected pages.
Page 2 of 2 Indian Point Units 1,2 & 3 YEAR: 2023 l Page 60 of 66 Annual Radioactive Effluent Release Report Revision 1 - 2016 ARERR corrected pages.
Page4of4 2016 ARERR Revision 1 Docket No. 50-3, 50-247,
& 50-286 Page 48 of 92 INDIANPOINT 3NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ONMAN JANUARY - DECEMBER 2016 D DOSES
/]
ars Or 2 Cir 3 Qir 4 ANNUAL Rev 1 res 1.23E-04 l 3
-04 l 7O7E-05 l 1.26E-04 A, 98E-04 PTY) mrem)
[3
[3 S
5 10 a
2 46E-03 SBE-03 l
__l Bone GeLL)
Bone Bone Bone l Adul Total
[rwem) 266E-051 1.11E-04 l
1.12E-05 l
3S0E-OS5 1.55E-04 L(meom])
Percent of Limit
(%)
1.77E-03 l 740E-03 l 747E-04 l 2336-03 l 5.17E-03 B. AIRBORNE NOBLE GAS DOSES m=
Te ox 1 an 2 or 3 Ord l ANNUAL v
l_(mwad)l 1.5005) 1.64E05 l 1676.05 l 1.78C 00 l &.79C 06 l Umit l (nwad) 5 5
5 5
10 Percent of Limit
(%)
l 300E04]l 328E04 l 374E04 l 3SEE04 l 6796.04 C. AIRBORNE IODINE, PARTICIA ATE, & TRITIUM DOSES (suciuding C-14, for info only) ory loz lacu3 ars l annuall bodine/Part (rower)
S.96E-04 l 7.55E-04 l 7.76E-D4 l 4 96E-04 2.63E-03
[ (nwem) 75 75 75 75 15 Percent of Lanit
(%}
T95F-03 l 1.0E-02 l
1.03E-02 l 6681E-03 1.756-02 Child Chik Child Child Child Critical uver l Liver Liver Liver Liver D__AIRBORNE HOOINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES l_(meem)11 74F-00 1 1.76602 l 1766-02 l 1 7I.00 l 7.006-02 l (we) 7.5 7.5 7.5 75 15 Percent of Limit
(%)
2.33.01 l 2356-01 l 23SE-01 l 2 ME-01 l 4.67E-01 owl l} O32 oud Child Bone Dose}
(nwem) l 8.45E02 l 8.45602 l BASE0Z l Ba5E02 l 3.38601 7s 15 75 75 1s Percent of Limit
(%)
l%.13E+00]1.136+00 l 1.43E+00 l 1.13E+00 l 2256400 Rev1 0524