ML25125A131
| ML25125A131 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/05/2025 |
| 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-25-019 | |
| Download: ML25125A131 (1) | |
Text
Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-IPEC-25-019 10 CFR 50 Appendix I May 5, 2025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Indian Point Energy Center Provisional Operating License No. DPR-05 Renewed Facility License No. DPR-26 and DPR-64 NRC Docket Nos.50-003, 50-247, and 50-286
Subject:
2024 Annual Radiological Environmental Operating Report In accordance with the Indian Point 2 and the Indian Point 3 Defueled Safety Analysis Report Section 5.13, Administrative Controls, Holtec Decommissioning International, LLC (HDI) is submitting the 2024 Radiological Environmental Operating Report.
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
Enclosure:
2024 Annual Radiological Environmental Operating 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 HOLTE C ------------------------
0EcoM M 1ss 10N 1Nc I NT
- R NAT I NAL Digitally signed by William Noval DN: cn=William Noval, o=HDI, ou=Regulatory Affairs, email=w.noval@holtec.com Date: 2025.05.05 10:54:03 -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-25-019 ENCLOSURE TO HDI-IPEC-25-019 2024 Annual Radiological Environmental Operating Report HOLTE C ------------------------
0EcoM M 1ss 10N 1Nc I NT
- R NAT I NAL
Plant: Indian Point Energy Center Page 1 of 122 YEAR: 2024 Docket Number: 50-003 (IP1), 50-247 (IP2), 50-286 (IP3)
Annual Radiological Environmental Operating Report
Plant: Indian Point Energy Center Year: 2024 Page 2 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS Page 1.0 EXECUTIVE
SUMMARY
7 1.1 Introduction 8
1.2 Sampling and Analysis 8
1.3 Land Use Census 8
1.4 Summary of Results 9
1.5 Conclusions 9
2.0 INTRODUCTION
10 2.1 Overview 11 2.2 Site Description 11 2.3 Program Background 12 2.4 Program Objectives 12 3.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM REQUIREMENTS 13 3.1 Sample Collection 14 3.2 Sample Analysis 14 3.3 Sample Collection and Analysis Methodology 14 3.3.1 Direct Radiation 14 3.3.2 Airborne Particulates and Radioiodine 15 3.3.3 Drinking Water 15 3.3.4 Soil 15 3.3.5 Broad Leaf Vegetation 15 3.3.6 Hudson River Water 15 3.3.7 Hudson River Bottom Sediment 15 3.3.8 Hudson River Shoreline Soil 16 3.3.9 Hudson River Aquatic Vegetation 16 3.3.10 Fish and Invertebrates 16 3.3.11 Land Use Census 16 3.4 Statistical Methodology 17 3.4.1 Lower Limit of Detection (LLD) 17 3.4.2 Table Statistics 18
Plant: Indian Point Energy Center Year: 2024 Page 3 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS (continued)
Page 4.0 INTERPRETATION AND TRENDS OF RESULTS 28 4.1 Direct Radiation 30 4.2 Airborne Particulates and Radioiodine 31 4.3 Drinking Water 32 4.4 Soil 32 4.5 Broad Leaf Vegetation 32 4.6 Hudson River Water 32 4.7 Hudson River Bottom Sediment 32 4.8 Hudson River Shoreline Soil 33 4.9 Hudson River Aquatic Vegetation 33 4.10 Fish and Invertebrates 33 4.11 Land Use Census 33 4.12 Conclusion 34 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 35
SUMMARY
5.1 2024 Annual Radiological Monitoring Program Summary 36 5.2 Land Use Census 36 5.3 Sampling Deviations 36 5.4 Analytical Deviations 36 5.5 Special Reports 36 6.0 HISTORICAL TRENDS 90 7.0 INTERLABORATORY COMPARISON PROGRAM 109 7.1 Program Description - Teledyne Brown Engineering 110 Environmental Services Comparison Programs 7.2 Acceptance Criteria 110 7.2.1 Analytics Sample Results Evaluation 110 7.2.2 ERA and MAPEP Sample Result Evaluation 111 7.3 Program Results Summary 111 7.4 Environmental TLD Quality Assurance 117
8.0 REFERENCES
119
Plant: Indian Point Energy Center Year: 2024 Page 4 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles) 22 A-2 Sampling Locations (Greater Than Two Miles) 23 A-3 Additional Sampling Locations 24 C-1 Direct Radiation, Annual Summary, 2014 to 2024 93 C-2 Radionuclides in Air - Gross Beta, 2014 to 2024 95 C-3 Radionuclides in Hudson River Water - Tritium 97 2014 to 2024 C-4 Radionuclides in Drinking Water, 99 2014 to 2024 C-5 Radionuclides in Shoreline Soil, 2014 to 2024 101 C-6 Radionuclides in Broad Leaf Vegetation, 2014 to 2024 103 C-7 Radionuclides in Fish & Invertebrates, 2014 to 2024 105 C-9 Radionuclides in Bottom Sediment, 2014 to 2024 108
Plant: Indian Point Energy Center Year: 2024 Page 5 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES TABLE TITLE Page A-1 Indian Point REMP Sampling Station Locations 19 A-2 Lower Limit of Detection (LLD) Requirements for 25 Environmental Samples A-3 Reporting Levels for Radioactivity Concentrations in 27 Environmental Samples B-1 Summary of Sampling Deviations - 2024 37 B-1a 2024 Air Sampling Deviations 38 B-1b 2024 Other Media Deviations 38 B-1c 2024 Changes to the REMP Program 39 B-2 Radiological Environmental Monitoring Program Summary 40 Indian Point Energy Center - 2024 B-3 Direct Radiation, Quarterly Data - 2024 45 B-4 Direct Radiation, 2014 through 2024 Data 46 B-4A Direct Radiation, REMP Dose per Standard 91-day Quarter 47 (mrem)
B-5 Direct Radiation, Inner and Outer Rings - 2024 48 B-6 Gross Beta Activity in Airborne Particulate Samples - 2024 49 B-7 Iodine-131 Activity in Airborne Charcoal Samples - 2024 51 B-8 Gamma Emitters in Airborne Particulate Samples - 2024 52 B-9 Radionuclides in Drinking Water Samples - 2024 56 B-10 Gamma Emitters in Soil Samples - 2024 60 B-11 Gamma Emitters in Broad Leaf Vegetation Samples - 2024 61 B-12 Radionuclides in River Water Samples - 2024 70 B-13 Gamma Emitters in Bottom Sediment Samples - 2024 74 B-14 Radionuclides in Shoreline Soil Samples - 2024 76 B-15 Gamma Emitters in Aquatic Vegetation Samples - 2024 79 B-16 Radionuclides in Fish / Invertebrates - 2024 82 B-17 Land Use Census, Residence & Milch Animal Results 2024 88 B-18 Land Use Census - 2024 - Unrestricted Area Boundary 89 and Nearest Residences
Plant: Indian Point Energy Center Year: 2024 Page 6 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES (Continued)
TABLE TITLE Page C-1 Direct Radiation Annual Summary, 2014 - 2024 92 C-2 Radionuclides in Air, 2014 - 2024 94 C-3 Radionuclides in Hudson River Water - Tritium 96 2014 to 2024 C-4 Radionuclides in Drinking Water, 2014 to 2024 98 C-5 Radionuclides in Shoreline Soil, 2014 to 2024 100 C-6 Radionuclides in Broad Leaf Vegetation, 2014 to 2024 102 C-7 Radionuclides in Fish & Invertebrates, 2014 to 2024 104 C-8 River Water Discharge Area Tritium, REMP vs Effluent 106 C-9 Radionuclides in Bottom Sediment, 2014 to 2024 107 D-2.1 Ratio of Agreement 111 D-3.1 Analytics Interlaboratory Comparison Program 112 and Ratio of Agreement D-3.2 DOE Interlaboratory Comparison Program 114 and Ratio of Agreement D-3.3 ERA Interlaboratory Comparison Program 115 and Ratio of Agreement D-4.1 Percentage of Individual Dosimeters That Passed EDC 117 Internal Criteria, 2024 D-4.2 Mean Dosimeter Analysis (N=6), 2024 118 D-4.3 Summary of Independent Dosimeter Testing, 2024 118
Plant: Indian Point Energy Center Year: 2024 Page 7 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION 1.0 EXECUTIVE
SUMMARY
Plant: Indian Point Energy Center Year: 2024 Page 8 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1.0 EXECUTIVE
SUMMARY
1.1 INTRODUCTION
This report summarizes the results of the Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Indian Point Energy Center (IPEC) during the period from January 1 to December 31, 2024. The Indian Point site consists of Units 1, 2 and 3, which are operated by Holtec Decommissioning International. Unit 1 was retired as a generating facility in 1974, and its reactor is no longer operated. Unit 2 was permanently shutdown on April 30th 2020. Unit 3 ceased operation April 30th 2021.
The REMP has been established to monitor/measure the radiation and radioactivity detectable in the environment that may be attributable to the operation of IPEC. This program, initiated in 1958, includes the collection, analysis, and evaluation of radiological data in order to assess the impact of IPEC on the environment.
1.2 SAMPLING AND ANALYSIS The environmental sampling media collected in the vicinity of IPEC and at distant locations included air particulate filters and charcoal cartridges, soil, drinking water, broad leaf vegetation, river water, shoreline sediment, bottom sediment, aquatic vegetation, fish, and invertebrates.
During 2024 there were 766 samples collected from the atmospheric, aquatic, and terrestrial environments. This includes 161 exposure measurements which were obtained using environmental thermoluminescent dosimeters (TLDs).
In March of 2024 the collection of air samples (charcoal cartridges) for I-131 ended due to the short half-life of the isotope and the time elapsed since final plant shutdown in 2021.
A small number of issues were encountered in 2024 in the collection of environmental samples in accordance with the IPEC Offsite Dose Calculation Manual (ODCM). Equipment failures and electrical outages resulted in a small number of instances in which lower than normal sampling volumes were collected at the airborne monitoring stations. A full description of all discrepancies encountered with the environmental monitoring program is presented in the Table B-1 of this report.
There were 905 analyses performed on the environmental media samples. The analyses of the 2024 Indian Point environmental samples were performed by several laboratories.
Thermoluminescent dosimeters were analyzed by Environmental Dosimetry Company (formerly Stanford Associates) of Sterling, MA. Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the remaining analyses for 2024. Samples were analyzed as required by the IPEC ODCM.
1.3 LAND USE CENSUS The annual land use census in the vicinity of IPEC was conducted as required by the IPEC ODCM in June through October. No dairy animals whose milk is used for human consumption were identified within 5 miles of the Station during the census. Due to the difficulty of locating individual gardens and determining those having an area greater than
Plant: Indian Point Energy Center Year: 2024 Page 9 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 500 square feet, broad leaf sampling was performed from two onsite locations in the highest downwind sectors. As allowed for in the ODCM, monthly broad leaf sampling may be used in lieu of a garden census.
1.4
SUMMARY
OF RESULTS Samples collected as part of the IPEC REMP continued to contain detectable amounts of naturally-occurring and some man-made radioactive materials. Offsite ambient radiation measurements using environmental TLDs beyond the site boundary ranged between 46 and 64 milli-Roentgens (mR) per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for New York.
Monitoring of the aquatic environment in the area of the station indicated the presence of cesium-137 as a potential station related radioactivity indicator. Low-levels of cesium-137 were detected in one Hudson River bottom sediment sample downstream of the discharge canal as well as one detection at the Cold Spring location. The levels detected were consistent with historical findings. No other plant related activity was detected in any offsite samples. The predominant radioactivity for all samples was from non-plant related sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.
1.5 CONCLUSION
S The 2024 Radiological Environmental Monitoring Program for IPEC resulted in the collection and analysis of over a thousand environmental samples and measurements. The data obtained were used to determine the impact of IPECs operation on the environment and on the general public.
An evaluation of direct radiation measurements, environmental sample analyses, and dose calculations demonstrates that all applicable federal criteria were met. Furthermore, radiation levels and resulting doses from station operation were a small fraction of those attributed to natural and man-made background radiation.
In summary, the levels of radionuclides in the environment surrounding Indian Point were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, IPEC decommissioning activities in 2024 did not result in exposure to the public greater than the variability of environmental background levels.
Plant: Indian Point Energy Center Year: 2024 Page 10 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION
2.0 INTRODUCTION
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Plant: Indian Point Energy Center Year: 2024 Page 11 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
2.0 INTRODUCTION
2.1 Overview The Radiological Environmental Monitoring Program (REMP) for 2024 performed by Holtec for the Indian Point Energy Center (IPEC) is discussed in this report. Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be established to monitor radiation and radioactivity in the environment (Reference 1). This report, which is submitted to the NRC annually per Indian Point Offsite Dose Calculation Manual, summarizes the results of measurements of radiation and radioactivity in the envi-ronment in the vicinity of the IPEC and at distant locations during the period January 1 to December 31, 2024.
The REMP is used to measure the direct radiation and the airborne and waterborne pathway activity in the vicinity of the Indian Point site. Direct radiation pathways include radiation from buildings and plant structures, airborne and liquid material that might be released from the plant, cosmic radiation, and the naturally occurring radioactive materials in the ground. Analysis of thermoluminescent dosimeters (TLDs), used to measure direct radiation, indicated that there were no increased radiation levels attributable to plant operations.
The airborne pathway includes measurements of air, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations.
The waterborne pathway consists of Hudson River water, fish and invertebrates, aquatic vegetation, bottom sediment, and shoreline sediment. Measurements of the media comprising the waterborne pathway indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station activities.
These results are reviewed by IPEC's staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others for over 50 years.
This report contains a description of the REMP for IPEC and the conduct of that program in 2024 as required by the IPEC ODCM. Also included are summaries and discussions of the results of the 2024 program, trend analyses (where appropriate), comparison to historical results and evaluation of any potential impact on the environment. Results of the annual land use census, as well as the inter-laboratory comparison program are included, per the ODCM requirements.
2.2 Site Description The Indian Point site occupies 239 acres on the east bank of the Hudson River on a point of land at Mile Point 42.6. The site is located in the Village of Buchanan, Westchester County, New York. Three nuclear reactors, Indian Point Unit Nos. 1, 2 and 3, and associated buildings occupy approximately 35 acres. Unit 1 began operation in 1962 and was retired as a generating facility in 1974. Units 2 and 3 began operation 1974 and 1978. Indian Point I
I
Plant: Indian Point Energy Center Year: 2024 Page 12 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Units 1 and 2 are owned by Holtec Decommissioning International Indian Point 2, LLC and Unit 3 is owned by Holtec Decommissioning International Indian Point 3 LLC. All three units are no longer in operation.
2.3 Program Background Environmental monitoring and surveillance have been conducted at Indian Point since 1958, four years prior to the start-up of Unit 1. The pre-operational program was designed and implemented to determine the background radioactivity and to measure the variations in activity levels from natural and other sources in the vicinity, as well as fallout from atmospheric nuclear weapons tests. Thus, as used in this report, background levels consist of those resulting from both natural and anthropogenic sources of environmental radioactivity. Accumulation of this background data permits the detection and assessment of environmental activity attributable to plant operations.
2.4 Program Objectives The current environmental monitoring program is designed to meet two primary objectives:
1.
To enable the identification and quantification of changes in the radioactivity of the area.
2.
To measure radionuclide concentrations in the environment attributable to past operation and/or decommissioning activities of the Indian Point site.
To identify changes in activity, the environmental sampling schedule requires that analyses be conducted for specific environmental media on a regular basis. The radioactivity profile of the environment is established and monitored through routine evaluation of the analytical results obtained.
The REMP designates sampling locations for the collection of environmental media for analysis. These sample locations are divided into indicator and control locations. Indicator locations are established near the site, where the presence of environmental radioactivity of plant origin is most likely to be detected. Control locations are established farther away (and upwind/upstream, where applicable) from the site, where the level would not generally be affected by plant discharges. The use of indicator and control locations enables the identification of potential sources of detected radioactivity, thus meeting one of the program objectives.
Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is another objective of the REMP, which is met by meeting the two primary program objectives described above. Verifying projected concentrations through evaluating REMP data can be difficult since the environmental concentrations resulting from plant releases are typically too small to be detected. Plant related radionuclides were detected in 2024 in very low levels; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2024 REMP sample results confirms that environmental concentrations which could be attributed to radiological effluents were well below regulatory limits.
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Plant: Indian Point Energy Center Year: 2024 Page 13 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM REQUIREMENTS I
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Plant: Indian Point Energy Center Year: 2024 Page 14 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM REQUIREMENTS To achieve the objectives of the REMP and ensure compliance with the ODCM, sampling and analysis of environmental media are performed as outlined in Table A-1 and described in section 3.3.
3.1 Sample Collection A contracted environmental vendor, Normandeau Associates, Inc (NAI), perform collection of environmental samples for the Indian Point site, with the exception of environmental dosimetry. Environmental dosimetry collection is performed by Holtec personnel.
Environmental media are sampled at the locations specified in Table A-1 and shown in Figures A-1, A-2, and A-3. The samples are analyzed according to criteria established in the ODCM. These requirements include: methods of sample collection; types of sample analysis; minimum sample size required; lower limit of detection, which must be attained for each medium, sample, or analysis type, and environmental concentrations requiring special reports.
Table A-1 provides the sampling station number, location, sector, and distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2024 REMP.
Three maps are provided to show the locations of REMP sampling. Figure A-1 shows the sampling locations within two miles of Indian Point. Figures A-2 and A-3 show the sampling locations within ten miles of Indian Point.
3.2 Sample Analysis The analysis of the 2024 Indian Point environmental samples was performed by two laboratories. Thermoluminescent dosimeters were analyzed by Environmental Dosimetry Company (formerly Stanford Associates) of Sterling, MA. Teledyne Brown Engineering, Inc.
of Knoxville, TN performed all the remaining analyses.
3.3 Sample Collection and Analysis Methodology 3.3.1 Direct Radiation Direct gamma radiation is measured using integrating calcium sulfate thermoluminescent dosimeters (TLDs), which provide cumulative measurements of radiation exposure (i.e., total integrated exposures in milli-roentgen, mR) for a given period. The area surrounding the Indian Point site is divided into 16 compass sectors. Each sector has two TLD sample locations. The inner ring is located near the site boundary at approximately 1 mile (1.6 km).
The outer ring is located at approximately 5 miles (8 km) from the site (6.7-8.0 km), see Figures A-1 and A-2. Additional TLD locations include a control location at Roseton (20.7 miles north) and eight locations of special interest. In total, there are 41 TLD sample sites, designated DR-1 through DR-41, with two TLDs placed at each site. TLDs are collected and processed on a quarterly basis. The results are reported as mR per standard quarter (91 days). The data reported is the average of the two TLDs from each sample site.
Plant: Indian Point Energy Center Year: 2024 Page 15 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.3.2 Airborne Particulates and Radioiodine Air samples were taken at eight locations varying in distance from 0.28 to 20.7 miles (0.5 to 33 km) from the plant. These locations represent one control at sampling station 23 (A5) and seven indicator locations. These indicator locations are at sampling stations 4 (A1), 5 (A4),
27, 29, 94 (A2), 95 (A3), and 108. The locations are shown on Figures A-1, A-2, and A-3.
The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges. Both filters and cartridges are changed on a weekly basis with the exception of location 108 where the exchange occurs bi-weekly. The filters are analyzed for gross beta. Radioiodine analyses ended in March 2024. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters.
3.3.3 Drinking Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, sample station 7, sample designation Wb1) and Croton Reservoir (6.3 miles SE, sample station 8); see Figure A-2 and Figure A-3. Each monthly sample is approximately 4 liters and is analyzed for gross beta and gamma-emitting radionuclides. Monthly samples are composited quarterly and analyzed for tritium.
3.3.4 Soil Soil samples are collected from two indicator locations (sampling stations 94 and 95), and one control location (23) on an annual basis; see Figure A-3. They are approximately 2 kg in size and consist of about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.
3.3.5 Broad Leaf Vegetation Broad Leaf vegetation samples are collected from three locations during the growing season.
The indicator locations are sampling stations 94 (Ic2) and 95 (Ic1), and the control location is at sampling station 23 (Ic3). See Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.
3.3.6 Hudson River Water Hudson River water sampling is performed continuously at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, Wa2); see Figure A-1. Samples were also collected continuously at a control station 23 Roseton (Figure A-2 and A-3). An automatic composite sampler is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis and quarterly for tritium analysis.
3.3.7 Hudson River Bottom Sediment Bottom sediment and benthos are sampled at four locations: three indicator locations (sampling stations 10, 17, and 28) and one control location (84), along the Hudson River, once each spring and summer; see Figure A-3. These samples are obtained using a
Plant: Indian Point Energy Center Year: 2024 Page 16 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Peterson grab sampler or similar instrument. The bottom sediment samples are analyzed by gamma spectroscopy.
3.3.8 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The indicator locations are at sampling stations 53 (Wc1), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-1, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90.
3.3.9 Hudson River Aquatic Vegetation During the spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations (sampling stations 17 and 28) and one control location (84);
see Figure A-3. Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.
3.3.10 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The indicator location (downstream sample point) is designated as sampling station 25 (Ib1), and a second sampling station 107 is located further downstream. The control location (upstream) is at sampling station 23 (Ib2). See Figures A-1 and A-2. These samples are collected in season or semiannually if they are not seasonal.
The fish and invertebrates sampled are analyzed by gamma spectroscopy as well as for strontium-90 and for nickel-63.
3.3.11 Land Use Census In addition to the sampling outlined in Table A-1, there is an environmental surveillance requirement that an annual land use census be performed. Each year a land use census consisting of milch animal and residence surveys is conducted during the growing season to determine the current utilization of land within 5 miles (8 km) of the site. These surveys are used to determine whether there are changes in existing conditions that warrant changing the sampling program. The results of the census are discussed in Section 4.11.
For example, the milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. This census consists of visual field surveys of the areas where a high probability of milch animals exists and confirmation through New York State records or with personnel such as feed suppliers who deal with farm animals and dairy associations.
Visual inspections are made of the 5-mile area around the Indian Point Site during routine sample collections in the area throughout the year. An extensive land survey is conducted of the 5-mile area in an attempt to identify new residential areas, commercial developments and to identify milch animals in pasture.
Plant: Indian Point Energy Center Year: 2024 Page 17 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A garden census is not required, since the ODCM allows sampling of vegetation in two sectors near the site boundary in lieu of a garden census. The sectors are chosen to be in the pre-dominant wind directions with the highest predicted deposition rates.
3.4 Statistical Methodology There are several statistical calculation methodologies used in evaluating the data from the Indian Point REMP. These methods include determination of Lower Limits of Detection (LLD) and the Minimum Detectable Concentration (MDC), and estimation of the mean and associated propagated error.
3.4.1 Lower Limit of Detection (LLD)
The LLD is the smallest concentration of radioactive material in a sample that will yield a net count above system background, and be detected with 95% probability, with a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
Where:
LLD =
The lower limit of detection as defined above (as picocurie per unit mass or volume)
Ts =
The sample counting time in minutes sb =
The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
Tb =
The background count time in minutes E =
The counting efficiency (as counts per transformation)
V =
The sample size (in units of mass or volume) k =
A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per uCi)
Y =
The fractional radiochemical yield (when applicable)
=
The radioactive decay constant for the particular radionuclide t =
The elapsed time between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times.
The Radiological Environmental Monitoring Program, REMP, may use an LLD formula that assumes equal background and sample count times, when appropriate.
The constants 2.71 and 3.29 and the general LLD equation were derived from References 2 and 3.
The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the e
Y k
V E
)
T T
(
+
1 s
3.29
+
T 2.71
=
LLD t
s b
b s
1 I---
Plant: Indian Point Energy Center Year: 2024 Page 18 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined by a separate background count or in the case of gamma ray spectroscopy, from adjacent channels of the energy band of the gamma ray peak used for the quantitative analysis for that radionuclide.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement process and not as an a posteriori (after the fact) limit for a particular measurement. To document the a posteriori (after the fact) measurement statistics, the MDC is calculated using the same equation as above with actual values for parameters such as Tb and Ts.
To handle the a posteriori problem, a decision level must be defined. To minimize the number of false positives, a value is not considered positive unless it is greater than the MDC and 3 times the total standard deviation of the post priori measurement, where MDC is the post priori (after the fact) measurement statistic calculated similar to the LLD equation listed above (for Tb = Ts, the term 3.29 sb * [(1 + ( Tb / Ts ))1/2] = 4.66 sb).
The ODCM required lower limits of detection (LLD) for Indian Point sample analyses are presented in Table A-2. These required lower limits of detection are not the same as the lower limits of detection or critical levels actually achieved by the laboratory. The laboratory's lower limits of detection and critical levels must be equal to or lower than the required levels presented in Table A-2.
Table A-3 provides the reporting level for radioactivity in various media. Sample results that exceed these levels and are due to plant operations require that a special report be submitted to the NRC.
3.4.2 Table Statistics The averages shown in the summary table (Table B-2) are the averages of the positive values in accordance with the NRC's Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference 4). Samples with "<" values are not included in the averages.
It should be noted that this statistic for the mean using only positive values tends to strongly bias the average high, particularly when only a few of the data are measurably positive. The REMP data show few positive values; thus the corresponding means are biased high.
Exceptions to this include direct radiation measured by TLDs and gross beta radioactivity in air, which show positive monitoring results throughout the year.
The historical data tables contain the annual averages of the positive values for each year for 2014 through 2024. The historical averages are calculated using only the positive values presented for 2014 through 2023. The 2024 average values are included in these historic tables for purposes of comparison.
Plant: Indian Point Energy Center Year: 2024 Page 19 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- = Control location
- = In 2020 Air sampler station 44 Peekskill was relocated to 108 Telcom. Bldg.
- = In 2020 River water station 9 Plant Inlet (Hudson River Intake) was moved to Roseton.
TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING STATION SAMPLE DESIGNATION LOCATION DISTANCE SAMPLE TYPES 3
DR8 Service Center Building Onsite - 0.35 Mi (SSE) at 158° Direct Gamma 4
A1 Algonquin Gas Line Onsite - 0.28 Mi (SW) at 234° Air Particulate A1 Radioiodine 5
A4 NYU Tower Onsite - 0.88 Mi (SSW) at 208° Air Particulate A4 Radioiodine DR10 Direct Gamma 7
Wb1 Camp Field Reservoir 3.4 Mi (NE) at 51° Drinking Water 8
Croton Reservoir 6.3 Mi (SE) at 124° Drinking Water 10 Wa2 Discharge Canal (Mixing Zone)
Onsite - 0.3 Mi (WSW) at 249° HR Water HR Bottom Sediment 14 DR7 Water Meter House Onsite - 0.3 Mi (SE) at 133° Direct Gamma 17 Verplanck Area 1.5 Mi (SSW) at 202.5° HR Aquatic Vegetation HR Shoreline Soil HR Bottom Sediment 20 DR38 Cortlandt Yacht Club (AKA Montrose Marina) 1.5 Mi (S) at 180° Direct Gamma 23 23****
Roseton*
20.7 Mi (N) at 357° HR Water A5 Air Particulate A5 Radioiodine DR40 Direct Gamma Ic3 Broad Leaf Vegetation Soil Ib2 Fish & Invertebrates 25 Ib1 Downstream Downstream Fish & Invertebrates 27 Croton Point 6.36 Mi (SSE) at 156° Air Particulate Radioiodine DR41 Direct Gamma 28 Lent's Cove 0.45 Mi (ENE) at 069° HR Shoreline Soil DR4 Direct Gamma HR Bottom Sediment HR Aquatic Vegetation 29 Grassy Point 3.37 Mi (SSW) at 196° Air Particulate Radioiodine DR39 Direct Gamma 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053° Direct Gamma 34 DR9 South East Corner of Site Onsite - 0.52 Mi (S) at 179° Direct Gamma 35 DR5 Broadway & Bleakley Avenue Onsite - 0.37 Mi (E) at 092° Direct Gamma 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141° Direct Gamma
Plant: Indian Point Energy Center Year: 2024 Page 20 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- = Control location
- = In 2020 Air sampler station 44 Peekskill was relocated to 108 Telcom. Bldg.
- = In 2020 River water station 9 Plant Inlet (Hudson River Intake) was moved to Roseton.
TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING STATION SAMPLE DESIGNATION LOCATION DISTANCE SAMPLE TYPES 50 Wc2 Manitou Inlet*
4.48 Mi (NNW) at 347° HR Shoreline Soil 53 Wc1 White Beach 0.92 Mi (SW) at 226° HR Shoreline Soil DR11 Direct Gamma 56 DR37 Verplanck - Broadway & 6th Street 1.25 Mi (SSW) at 202° Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 358° Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 032° Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook Road 5.02 Mi (NNE) at 029° Direct Gamma 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 052° Direct Gamma 62 DR19 Westbrook Drive (near the Community Center) 5.03 Mi (NE) at 062° Direct Gamma 64 DR20 Lincoln Road - Cortlandt (School Parking Lot) 4.6 Mi (ENE) at 067° Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 083° Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 114° Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 127° Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 188° Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 203° Direct Gamma 73 DR27 Willow Grove Road & Captain Faldermeyer Drive 4.97 Mi (SW) at 226° Direct Gamma 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 252° Direct Gamma 75 DR31 Palisades Parkway 4.65 Mi (NW) at 225° Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 276° Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 272° Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 295° Direct Gamma 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 296° Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 317° Direct Gamma 81 DR-28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 310° Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 334° Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 339° Direct Gamma 84 Cold Spring
- 10.88 Mi (N) at 356° HR Aquatic Vegetation HR Shoreline Soil HR Bottom Sediment 88 DR6 Reuter Stokes Pole #6 0.32 Mi (ESE) at 118° Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road (near rock cut) 2.89 Mi (NNE) at 025° Direct Gamma
Plant: Indian Point Energy Center Year: 2024 Page 21 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- = Control location
- = In 2020 Air sampler station 44 Peekskill was relocated to 108 Telcom. Bldg.
- = In 2020 River water station 9 Plant Inlet (Hudson River Intake) was moved to Roseton.
TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING STATION SAMPLE DESIGNATION LOCATION DISTANCE SAMPLE TYPES 90 DR3 Charles Point 0.88 Mi (NE) at 047° Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 149° Direct Gamma 94 A2 IPEC Training Center Onsite- 0.39 Mi (S) at 193° Air Particulate A2 Radioiodine Ic2 Broad Leaf Vegetation Soil 95 A3 Meteorological Tower Onsite - 0.46 Mi (SSW) at 208° Air Particulate A3 Radioiodine Ic1 Broad Leaf Vegetation Soil 107 Vicinity of Haverstraw Bay 2.5 mi SSW (downstream)
Fish & Invertebrates 108***
Telecomm Bldg.
0.36 mi ESE Air Particulate Radioiodine
Plant: Indian Point Energy Center Year: 2024 Page 22 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point N
t 1 mile
~
Hudson River Shoreline V
Soil Sampling Location.
Fis~ and fm;;eriebntes Jb# (~ available),
d!ownstream. Bud.son River
~
Buds.on Rirver Sample
\\.:::_/ Upstre11m & Downstream
~ Ah-borne Iodine/Part D
Sample* Location Du-ed' :Radiation Sl!Dlple Location DR#
., IM I Boc!ltman
- BrniadleafV,egeta 'on Sa.mp e Location
Plant: Indian Point Energy Center Year: 2024 Page 23 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FIGURE A-2 SAMPLING LOCATIONS Greater than Two Miles from Indian Point I-00 Broa.d!fea:f V,eg,e.tatioo S1mplle
-..:':..II!
Lo.......,
- d" ti.oil!
,e.d'Rlli u DR pie Loce:tio.11.
.~ =-tiome: foilin.-e. &
~.....,,
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Pu,firn1ate rintiD.g Water
,c-.\\n *. L ti.on
~
ample tieline S.oil
- dsoa-:R:n't!£ s~
, g l.bOl.tlDll.
l\\
Plant: Indian Point Energy Center Year: 2024 Page 24 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations
~
20,. 7 miles north g\\Y,11,lu Sample, Location
~
Airtior:a_e Iodi.a.e, &
L.:J.!Padirnlate SanfJl!e
~
Hu:dsa~ Rinr: S~r,~
Soi.I V
Sampling Laai.tlOll Soil Sampling Loa.tib.n Cro 27:,0
- llmaitorill~Wrill,.
S\\l of Site Bonndaey V
Aqnafic l, @!!;et:&.tioDI
Plant: Indian Point Energy Center Year: 2024 Page 25 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES RADIONUCLIDE ANALYSIS WATER (pCi/L)
AIRBORNE PARTIUCLATE OR GASES (pCi/m3)
FISH (pCi/kg, wet)
MILK (pCi/L)
FOOD PRODUCTS (pCi/kg, wet)
SOIL or SEDIMENT (pCi/kg, dry)
Gross Beta 4
0.01 H-3 2,000 (d)
Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Ni-63 (f) 30 100 Zn-65 30 260 Sr-90 (f) 1 5
50 Zr-95 30 Nb-95 15 I-131 1 (d) 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15
Plant: Indian Point Energy Center Year: 2024 Page 26 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES Table Notation (a)
This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to the ODCM.
(b)
Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
(c)
The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to the ODCM.
(d)
These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 pCi/liter for H-3 and 15 pCi/liter for I-131.
(e)
These required lower limits of detection are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.
(f)
Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment.
Plant: Indian Point Energy Center Year: 2024 Page 27 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES RADIONUCLIDE ANALYSIS WATER (pCi/L)
AIRBORNE PARTIUCLATE OR GASES (pCi/m3)
FISH (pCi/kg, wet)
MILK (pCi/L)
FOOD PRODUCTS (pCi/kg, wet)
H-3 20,000
300 1,000 Zn-65 300 20,000 Sr-90 ***
8*
40 Zr-95 400 Nb-95 400 I-131 2
- 0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:
H-3 30,000 pCi/L (This is a 40 CFR 141 value)
Sr-90 12 pCi/L I-131 20 pCi/L These reporting levels are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.
Plant: Indian Point Energy Center Year: 2024 Page 28 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION 4.0 INTERPRETATION AND TRENDS OF RESULTS
Plant: Indian Point Energy Center Year: 2024 Page 29 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4.0 INTERPRETATION AND TRENDS OF RESULTS The 2024 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manual ODCM. The ODCM contains requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity.
The REMP at Indian Point includes measurements of radioactivity levels in the following environmental pathways.
Direct Gamma Radiation Drinking Water Broad Leaf Vegetation Hudson River Water Bottom Sediment Shoreline Soil Aquatic Vegetation Fish and Invertebrates Airborne Particulates and Radioiodine Soil An annual land use and milch animal census is also part of the REMP.
To evaluate the contribution of past plant operations or decommissioning activities to environmental radioactivity levels, other man-made and natural sources of environmental radioactivity, as well as the aggregate of past monitoring data, must be considered. It is not merely the detection of a radionuclide, but the evaluation of the location, magnitude, source, and history of its detection that determines its significance. Therefore, we have reported the data collected in 2024 and assessed the significance of the findings.
A summary of the results of the 2024 REMP is presented in Table B-2. This Table lists the mean and range of all positive results obtained for each of the media sampled at ODCM indicator and control locations. Discussions of these results and their evaluations are provided below.
The radionuclides detected in the environment can be grouped into three categories: (1) naturally occurring radionuclides; (2) radionuclides resulting from weapons testing and other non-plant related, anthropogenic sources; and (3) radionuclides that could be related to past plant operations or decommissioning activities.
The environment contains a broad inventory of naturally occurring radionuclides which can be classified as, cosmic ray induced (e.g., Be-7) or geologically derived (e.g., Ra-226 and progeny, Th-228 and progeny, and K-40.) These radionuclides constitute the majority of the background radiation source and thus account for a majority of the annual background dose detected. Since the detected concentrations of these radionuclides were consistent at indicator and control locations, and unrelated to plant operations, their presence is noted only in the data tables and will not be discussed further.
The second group of radionuclides detected in 2024 consists of those resulting from past weapons testing in the earth's atmosphere. The more recent contamination events resulting from the Chernobyl and Fukushima accidents only indicated detectable activity shortly after their occurrences (Reference 5). However, weapons testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, still contributes to the
Plant: Indian Point Energy Center Year: 2024 Page 30 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT concentrations in the ecological systems. Although reduced in frequency, atmospheric weapons testing continued into the 1980's. The resultant radionuclide inventory of some radionuclides, although diminishing with time (e.g., through radioactive decay and natural dispersion processes), remains detectable.
In 2024, the detected radionuclides that may be attributable to past atmospheric weapons testing consisted of Cs-137 in several media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years.
The final group of radionuclides detected by the 2024 REMP comprises those that may be attributable to past plant operations. During 2024, Cs-137 was the only potentially plant-related radionuclide detected in any environmental samples.
H-3 may be present in the local environment due to either natural occurrence, other manmade sources including nuclear weapons fallout, or as a result of nuclear plant operations. Other sources include weapons production and industrial uses where levels are highly dependent on the release rates and distance from the source term. In 2024, H-3 was not detected in any water samples.
Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2024, Cs-137 was detected in two bottom sediment samples.
In all cases, the Cs-137 concentrations, when detected, were consistent with historical values.
Strontium-90 (Sr-90) may also be present in the environment from atmospheric testing debris. Sr-90 was not detected in any of the fish, invertebrate, or shoreline soil.
I-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as has been noted in previous years. There is no longer any production of I-131 at the plant, and due to its short half-life there is no source of I-131. I-131 was not detected in 2024 in aquatic or terrestrial vegetation indicator and control locations.
Co-58 and Co-60 are activation/corrosion products also related to plant operations. They are produced by neutron activation in the reactor core. Co-58 has a much shorter half-life than Co-60. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is more likely the result of recent releases. When significant concentrations of Co-60 are detected but no Co-58, there is an increased likelihood that the Co-60 is due to residual Co-60 from past operations. There was no Co-58 or Co-60 detected in the 2024 REMP, although they were observed in historical data.
In the following sections, a summary of the results of the 2024 REMP is presented by sample medium and the significance of any positive findings discussed. As previously mentioned, Table B-2 provides an annual summary of the following media.
4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by Environmental Dosimetry Company. In 2024, the TLD program produced a
Plant: Indian Point Energy Center Year: 2024 Page 31 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table B-2 and all the TLD data are presented in Tables B-3, B-4, B4A and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.
Table B-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. Table B-4 provides the mean, standard deviation, minimum and maximum values in mR per year for the years 2015 through 2023. The 2024 means are also presented in Table B-4. Table B-4A presents TLD data in the new NISP format based on ANSI N13.37. Table B-5 presents the 2024 TLD data for the inner ring and outer ring of TLDs. The table also provides the sector for each of the DR sample points.
The 2024 mean value for the indicator direct radiation sample points was 14.0 mR per standard quarter - which is consistent with historical values. At those locations where the 2024 mean value was higher than historical means, they are within historical bounds for the respective locations.
The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-16) is close to the site boundary. The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units.
The results of the annual totals for these two rings of TLDs are provided in Table B-5. The annual average for the inner ring was 14.0 mR per standard quarter and the average for the outer ring was 14.3 mR per standard quarter. The control location average for 2024 was 15.4 mR per standard quarter.
Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDs. The 2024 averages are consistent with the historical data. The 2024 and previous years' data show that there is no measurable direct radiation in the environment due to the operation of the Indian Point site.
4.2 Airborne Particulates and Radioiodine The results of the analyses of weekly air particulate filter samples for gross beta activity are presented in Table B-6 and the weekly charcoal cartridge analytical results are presented in Table B-7.
Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the seven indicator air sample locations was 0.013 pCi/m3 and the average for the control location was 0.014 pCi/m3 as shown in Table B-2. The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location.
The results of the gamma spectral analyses (GSA) of the quarterly composites of these samples are shown in Table B-8. These quarterly composite air samples indicate that no reactor-related radionuclides were detected and that only Be-7, a naturally-occurring radionuclide was present at detectable levels.
Plant: Indian Point Energy Center Year: 2024 Page 32 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The mean annual gross beta concentrations and Cs-137 concentrations in air for the past 10 years are presented in Table C-2. From this table and Figure C-2, it can be seen that the average 2024 gross beta concentration was consistent with historical levels. Cs-137 has not been detected since 1987. This is consistent with the trend of decreasing ambient Cs-137 concentrations in recent years.
From the data, it can be seen that no airborne radioactivity attributable to the decommissioning of Indian Point was detected in 2024.
4.3 Drinking Water Results of the gross beta, tritium and gamma spectroscopy analyses of the monthly drinking water samples are in Table B-9. Other than Gross Beta activity consistent with historical values, no radioactivity was detected in drinking water samples. This has historically been the case for the radionuclide results for this media. Past operation of the Indian Point units had no detectable radiological impact on drinking water.
4.4 Soil Table B-10 contains the results of the soil samples for 2024. Other than naturally occurring radionuclides, there were no plant related nuclides detected in the 2024 samples.
4.5 Broad Leaf Vegetation Data from analysis of the 2024 samples are presented in Table B-11. Table C-6 contains an historical summary and Figure C-6 is an illustration of the broad leaf vegetation analysis results. There were no plant related nuclides detected in the 2024 samples. The detection of low levels of Cs-137 has occurred sporadically at indicator locations at relatively low concentrations most likely the result of previous atmospheric weapons testing, but Cs-137 has not been detected in any sample in the last 10 years.
4.6 Hudson River Water Data resulting from analysis of monthly Hudson River water samples for gamma emitters and quarterly composites of H-3 are presented in Tables B-12.
There were no plant related nuclides detected in the 2024 samples. Tritium could be detected at levels that are consistent with occasional historical detection of H-3 related to plant operation. Table C-3 shows historical H-3 concentrations at the plant inlet and discharge points. Table C-8 contains a comparison of H-3 detected at the plant discharge (Hudson River Water mixing point) versus calculated quarterly average effluents concentrations. The data in table C-8 provides assurance that the REMP is indeed providing verification of the calculated radionuclide concentrations resulting from effluent releases attributable to the site.
4.7 Hudson River Bottom Sediment Table B-13 contains the results of the analysis of bottom sediment samples for 2024.
Cesium-137 was detected in one of the six indicator samples and one of the two control station samples. Detection of positive levels of Cs-137 in river bottom sediment is not unusual. The primary source of Cs-137 has been from prior historical releases over the years
Plant: Indian Point Energy Center Year: 2024 Page 33 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT and from residual weapons testing fallout. Historical levels of Cs-137 in bottom sediment samples are shown in table C-9 and figure C-9. This data shows the continued detection of Cs-137 in bottom sediment samples at varying levels, in both indicator and control locations, and demonstrates that the levels observed during 2024 sampling are within the range of levels identified in historical samples.
4.8 Hudson River Shoreline Soil Table B-14 contains the results of the gamma spectroscopic and strontium-90 analyses of the shoreline soil samples. Naturally occurring radionuclides were detected in the shoreline soil samples. There were no plant related nuclides detected in the 2024 samples.
Cs-137 was not detected in any of the six indicator location samples or any of the control location samples. A historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table C-5 and Figure C-5. Cesium-137 has been present in this media, both at indicator and occasionally at the control location, at a consistent level over the past ten years.
Strontium-90 (Sr-90) was not detected in any of the six indicator location samples or any of the control location samples.
4.9 Hudson River Aquatic Vegetation Table B-15 results show no plant related radionuclides were detected in any indicator or control aquatic vegetation samples in 2024. This is consistent with historical findings.
4.10 Fish and Invertebrates Table B-16 contains the results of the analysis of fish and invertebrate samples for 2024.
No plant related radionuclides were detected. This is consistent with historical results which are shown in Table C-7 and Figure C-7.
4.11 Land Use Census A census was performed in the vicinity of Indian Point in 2024. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables B-17 and B-18.
The results of the 2024 census were generally same as the 2023 census results. In 2021 the presence of goats was noted on a property located less than 5.0 miles of IPEC, discussions with the owner of the property indicated that the goats were male and did not produce milk.
In 2022, the owner of the property confirmed they no longer owned the goats. Similar to 2022 and 2023, it was noted in 2024 that no animals were producing milk for human consumption at this location or any other location within 5 miles to IPEC.
The 2024 land use census indicated there were no new residences that were closer in proximity to IPEC.
Plant: Indian Point Energy Center Year: 2024 Page 34 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The ODCM allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis results for these two sectors are discussed in Section 4.5 and presented in Table B-11, Table C-6 and Figure C-6.
4.12 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2024 REMP reveal that operations at the station did not result in a radiological impact on the environment.
The 2024 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. The results indicate that the fallout from previous atmospheric weapons testing continues to contribute to detection of Cs-137 in some environmental samples. There are infrequent detections of plant related activity in the environs; however, the radiological levels are very low and are significantly less than those from natural background and other anthropogenic sources.
Plant: Indian Point Energy Center Year: 2024 Page 35 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Plant: Indian Point Energy Center Year: 2024 Page 36 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
5.1 2024 Annual Radiological Environmental Monitoring Program Summary The results of the 2024 radiological environmental sampling program are presented in Tables B-2 through B-16. Table B-2 is a summary table of the sample results for 2024.
The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8, and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 4). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-16.
REMP samples were analyzed by various counting methods as appropriate. The methods are gross beta, gamma spectroscopy analysis, liquid scintillation, radiochemical analysis, and TLD processing. Gamma spectroscopy analysis was performed for gamma emitting nuclides, including the following: Be-7, K-40, Mn-54, Co-58, Co-60, Fe-59, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, I-131, Cs-134, Cs-137, Ba/La-140, Ce-141, Ce-144, Ra-226 and Ac/Th-228. Radiochemical analyses were performed for H-3, Ni-63, Sr-90 and I-131 for specific media and locations as required in the ODCM.
5.2 Land Use Census In accordance with Section D 3.5.2 of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use census are presented in Tables B-17 and B-18, respectively. In lieu of identifying and sampling the nearest garden of greater than 50 m2, at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-11).
5.3 Sampling Deviations During 2024, environmental sampling was performed for 10 unique media types addressed in the ODCM and for direct radiation. A total of 766 samples of 780 scheduled were obtained. Of the scheduled samples, 98.2% were collected and analyzed for the program. Sampling deviations are summarized in Table B-1.
Discussions of the reasons for the deviations are provided in Table B-1a for the air samples, Table B-1b for other media, and Table B-1c for changes to the REMP program. Analytical deviations noted in Table B-6 and B-7 due to insufficient sample volumes as noted in Table B-1a.
5.4 Analytical Deviations No analytical deviations were found in 2024.
5.5 Special Reports No special reports were required under the REMP.
Plant: Indian Point Energy Center Year: 2024 Page 37 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE B-1 Summary of Sampling Deviations - 2024 MEDIA TOTAL SCHEDULED SAMPLES NUMBER OF DEVIATIONS*
SAMPLING EFFICIENCY %
NUMBER OF ANALYSES**
REASON FOR DEVIATION MEDIA TLD 164 3
98%
161 See Table B-1b PARTICULATES IN AIR 387 2
99.5%
416 See Table B-1a CHARCOAL FILTER 64 0
100%
64 See Table B-1c DRINKING WATER 24 0
100%
56 N/A SOIL 3
0 100%
3 N/A BROAD LEAF VEGETATION 54 0
100%
54 N/A HUDSON RIVER WATER 24 0
100%
32 N/A SHORELINE SOIL 10 0
100%
20 N/A HUDSON RIVER BOTTOM SEDIMENT 8
0 100%
8 N/A AQUATIC VEGETATION 6
2 67%
4 See Table B-1b FISH & INVERTEBRATES 36 7
81%
87 See Table B-1b TOTALS 780 14 98.2%
905 TOTAL NUMBER OF SAMPLES COLLECTED =
766
- Samples not collected or unable to be analyzed.
- Several sample types require more than one analysis
Plant: Indian Point Energy Center Year: 2024 Page 38 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE B-1a 2024 Air Sampling Deviations LOCATION DATE PROBLEM / ACTIONS TO PREVENT RECURRENCE
- 29 4/15/2024 The air sample pump at Grassy point was found unplugged during routine sample media changeout. Lost sample time of approximately 139 hours0.00161 days <br />0.0386 hours <br />2.29828e-4 weeks <br />5.28895e-5 months <br />. Condition corrected. Refer to IR IP3-01656. Not an ODCM designated location.
- 27 5/20/2024 The air sampler at Croton Point was found off due to a tripped power receptacle.
The sample pump was off for approximately 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />. Power was restored. No impact to REMP. Refer to IR IP3-01673. Not an ODCM required location.
- 27 6/4/2024 The air sample pump at Croton Point tripped off after 75 hrs in service time for the week. It was found during weekly changeout and restored to operation. Refer to IP3-01688 for corrective actions. Not an ODCM location.
- 4 (ODCM A1) 6/10/2024 The air sample station near the Algonquin gas line did not collect a sample due the filter holder coming loose from the sample line. It was found during weekly changeout and restored to operation. Refer to IP3-01690 for corrective actions.
- 29 7/08/2024 The air sample pump at Grassy point was found off during routine sample media changeout. Lost sample time of approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. It was confirmed that the loss of power was due to a power outage. Power could not be restored. Refer to IR IP3-01710 for corrective actions. Not an ODCM designated location.
- 5 (ODCM A4) 11/4/2024 The air sample pump was found off during routine sample collection. The pump failed shortly after the sample media change out, no sample was collected for the week. The pump was replaced and restored to operation. Refer to IR IP3-01772 for actions.
TABLE B-1b 2024 Other Media Deviations LOCATION DATE PROBLEM / ACTIONS TO PREVENT RECURRENCE DR-14 4/17/2024 TLD missing and cup holder broken. No apparent cause. TLD replaced. IR IP3-01672 DR-34 07/17/2024 TLD missing and cup holder broken. No apparent cause. TLD replaced. IR IP3-01721 DR-39 01/15/2025 TLD missing during 4th Qtr collection. TLD inadvertently removed on 12/2 during removal of air sampling equipment. New TLD located near original location. Refer to IR IP3-01808.
ALL Spring Season No blue crabs available, out of season Croton/Haverstraw Summer Season No stripers or sunfish available, stripers out of season Verplank Summer Season Aquatic vegetation not available in all locations
Plant: Indian Point Energy Center Year: 2024 Page 39 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE B-1c 2024 Changes to the REMP Program LOCATION DATE Discussion of REMP Change All air sample locations March 20, 2024 Removed requirement for collection of charcoal cartridges and analysis of I-131 due to it's short half-life.
TABLE B-2 RADIOLOGICIAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIAN POINT ENERGY CENTER - 2024 Dockets50-003, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*
Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **
Location Distance Mean**
Mean**
Reported (Units)
(Range)
Number Direction (Range)
(Range)
Measurements Direct Radiation TLD-Quarterly 161 14.0 (157157)
DR-13 1.21 Mi.
16.2 (4/4) 15.4 (4/4) 0 (mR/Standard Quarter)
(9.8/16.7)
W (15.9/16.7)
(14.8/16.3)
Air Particulate Gr-B 385 0.01
.013 (333/333) 4 0.28 Mi.
.014 (51/51)
.014 (52/52) 0 (pCi/m3)
(.005/.024)
(.007/.024)
(.007/.025)
Air Iodine GAMMA 64 (pCi/m3)
I-131 0.07
<LLD
<LLD 0
Air Particulate GAMMA 31 (10-3 pCi/m3)
Be-7 NA 81.8 (26/27) 29 3.37 Mi.
85.1 (2/3) 81.4 (4/4) 0 (53.3/105.5)
SSW (64.7/105.5)
(61.7/95.7)
K-40 NA
<LLD
<LLD 0
Cs-134 0.05
<LLD
<LLD 0
Cs-137 0.06
<LLD
<LLD 0
Th-228 NA
<LLD
<LLD 0
Drinking Water Gr-B 24 4
2.83 (9/24) 08 6.3 Mi.
3.06 (5/12)
NA 0
(pCi/L)
(2.27/3.39)
SE (2.61/3.39)
H-3 8
200
<LLD NA 0
GAMMA 24 Mn-54 15
<LLD NA 0
Co-58 15
<LLD NA 0
Fe-59 30
<LLD NA 0
Co-60 15
<LLD NA 0
Zn-65 30
<LLD NA 0
Nb-95 15
<LLD NA 0
Zr-95 30
<LLD NA 0
I-131 15
<LLD NA 0
Cs-134 15
<LLD NA 0
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Page 40 of 122 Year: 2024 Plant: Indian Point Energy Center I
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TABLE B-2 RADIOLOGICIAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIAN POINT ENERGY CENTER - 2024 Dockets50-003, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*
Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **
Location Distance Mean**
Mean**
Reported (Units)
(Range)
Number Direction (Range)
(Range)
Measurements Drinking Water (cont'd)
Cs-137 18
<LLD NA 0
(pCi/L)
Ba-140 60
<LLD NA 0
La-140 15
<LLD NA 0
Soil GAMMA 3
(pCi/kg dry)
Be-7 NA
<LLD
<LLD 0
K-40 NA 9532 (2/2) 23 20.7 Mi.
14090 (1/1) 14090 (1/1) 0 (8764/10300)
N Co-60 NA
<LLD
<LLD 0
Cs-134 150
<LLD
<LLD 0
Cs-137 180
<LLD
<LLD 0
Ra-226 NA
<LLD
<LLD 0
Th-228 NA 238.2 (2/2) 23 20.7 Mi.
671.8 (1/1) 671.8 (1/1) 0 (163.9/312.4)
N Broad leaf Vegetation GAMMA 54 (pCi/kg wet)
Be-7 NA 1796 (33/36) 95 0.46 Mi.
2047 (17/18) 1056 (17/18) 0 (366.8/4453)
SSW (431.6/4453)
(398.5/2312)
K-40 NA 4324 (36/36) 94 0.39 Mi.
4501 (18/18) 3979 (18/18) 0 (1013/7422)
S (2941/6134)
(2528/5522)
Co-60 NA
<LLD
<LLD 0
I-131 60
<LLD
<LLD 0
Cs-134 60
<LLD
<LLD 0
Cs-137 80
<LLD
<LLD 0
Th-228 NA 71.75 (4/36) 95 0.46 Mi.
80.19 (2/18)
<LLD 0
(54.72/89.68)
SSW (70.7/89.68)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Plant: Indian Point Energy Center Year: 2024 Page 41 of 122 I
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TABLE B-2 RADIOLOGICIAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIAN POINT ENERGY CENTER - 2024 Dockets50-003, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*
Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **
Location Distance Mean**
Mean**
Reported (Units)
(Range)
Number Direction (Range)
(Range)
Measurements River Water H-3 8
200
<LLD
<LLD 0
(pCi/L)
GAMMA 24 Mn-54 15
<LLD
<LLD 0
Co-58 15
<LLD
<LLD 0
Fe-59 30
<LLD
<LLD 0
Co-60 15
<LLD
<LLD 0
Zn-65 30
<LLD
<LLD 0
Nb-95 15
<LLD
<LLD 0
Zr-95 30
<LLD
<LLD 0
Cs-134 15
<LLD
<LLD 0
I-131 15
<LLD
<LLD 0
Cs-137 18
<LLD
<LLD 0
Ba-140 60
<LLD
<LLD 0
La-140 15
<LLD
<LLD 0
Th-228 NA
<LLD
<LLD 0
Bottom Sediment GAMMA 8
(pCi/kg dry)
K-40 NA 18923 (6/6) 84 10.88 Mi.
20390 (2/2) 20390 (2/2) 0 (14630/22420)
N (20280/20500)
(20280/20500)
Co-60 NA
<LLD
<LLD 0
Cs-134 150
<LLD
<LLD 0
Cs-137 180 199 (1/6) 10 0.3 Mi.
199 (1/2) 154.5 (1/2) 0 WSW Year: 2024 Page 42 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Plant: Indian Point Energy Center I
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TABLE B-2 RADIOLOGICIAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIAN POINT ENERGY CENTER - 2024 Dockets50-003, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*
Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **
Location Distance Mean**
Mean**
Reported (Units)
(Range)
Number Direction (Range)
(Range)
Measurements Bottom Sediment (cont'd)
Ra-226 NA 3530 (2/6) 17 1.5 Mi.
4064 (1/2) 3160 (1/2) 0 (pCi/kg dry)
(2996/4064)
SSW Th-228 NA 932.4 (6/6) 17 1.5 Mi.
984 (2/2) 852.7 (2/2) 0 (655.6/1110)
SSW (898/1070)
(837.8/867.6)
Shoreline Soil Sr-90 10 50
<LLD
<LLD 0
(pCi/kg dry)
GAMMA 10 K-40 NA 13921 (6/6) 53 0.92 Mi.
17033 (2/2) 11866 (4/4) 0 (9159/24100)
SW (9965/24100)
(7444/15020)
Cs-134 150
<LLD
<LLD 0
Cs-137 180
<LLD
<LLD 0
Ra-226 NA
<LLD
<LLD 0
Ac-228 NA
<LLD 50 4.48 Mi.
1066 (1/2) 1066 (1/4) 0 NNW Th-228 NA 612.3 (6/6) 28 0.45 Mi.
781.9 (2/2) 496.8 (3/4) 0 (311.8/1142)
ENE (421.7/1142)
(450.1/523.3)
Aquatic Vegetation GAMMA 4
(pCi/kg wet)
Be-7 NA 565 (1/2) 28 0.45 Mi.
565 (1/2) 487.9 (1/2) 0 ENE K-40 NA 2450 (2/2) 84 10.88 Mi.
3086 (2/2) 3086 (2/2) 0 (2309/2591)
N (2994/3177)
(2994/3177)
Co-60 NA
<LLD
<LLD 0
I-131 60
<LLD
<LLD 0
Cs-134 60
<LLD
<LLD 0
Cs-137 80
<LLD
<LLD 0
Ra-226 NA
<LLD
<LLD 0
Ac-228 NA
<LLD
<LLD 0
Th-228 NA
<LLD
<LLD 0
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Plant: Indian Point Energy Center Year: 2024 Page 43 of 122 I
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TABLE B-2 RADIOLOGICIAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIAN POINT ENERGY CENTER - 2024 Dockets50-003, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*
Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **
Location Distance Mean**
Mean**
Reported (Units)
(Range)
Number Direction (Range)
(Range)
Measurements Fish Ni-63 29 100
<LLD
<LLD 0
(pCi/kg wet)
Sr-90 29 5
<LLD
<LLD 0
GAMMA 29 K-40 NA 2853 (19/19) 107 2.5 Mi.
3002 (9/9) 2735 (9/10) 0 (1811/3636)
SSW (1886/3571)
(1935/4381)
Mn-54 130
<LLD
<LLD 0
Co-58 130
<LLD
<LLD 0
Fe-59 260
<LLD
<LLD 0
Co-60 130
<LLD
<LLD 0
Zn-65 260
<LLD
<LLD 0
Cs-134 130
<LLD
<LLD 0
Cs-137 150
<LLD
<LLD 0
Th-228 NA
<LLD
<LLD 0
Environment Samples 766 Analysis 905
- LLD IS THE LOWER LIMIT OF DETECTION
- THE MEAN VALUES ARE CALCULATED USING THE POSITIVE VALUES ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Plant: Indian Point Energy Center Year: 2024 Page 44 of 122 I
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INDIAN POINT ENERGY CENTER TABLE B-3 DIRECT RADIATION, QUARTERLY DATA - 2024 mR/Quarter +/- 1 sigma Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Annual Annual Nuclide Number 01/01-03/31 04/01-06/30 07/01-09/30 10/01-01/01 Average Total TLD DR-01 16.2 +/- 0.8 15.4 +/- 0.8 15.0 +/- 0.7 16.0 +/- 0.6 15.7 +/- 0.5 62.7 DR-02 15.5 +/- 0.6 14.6 +/- 0.6 14.0 +/- 0.7 15.0 +/- 0.6 14.8 +/- 0.6 59.1 DR-03 12.9 +/- 0.5 12.4 +/- 0.9 11.9 +/- 0.5 12.7 +/- 0.6 12.5 +/- 0.4 50.0 DR-04 14.2 +/- 0.5 13.8 +/- 0.6 13.1 +/- 0.9 13.6 +/- 0.5 13.7 +/- 0.4 54.8 DR-05 14.0 +/- 0.7 13.7 +/- 0.6 13.4 +/- 0.8 14.0 +/- 0.5 13.8 +/- 0.3 55.1 DR-06 14.5 +/- 0.7 13.7 +/- 0.6 14.6 +/- 0.7 14.4 +/- 0.5 14.3 +/- 0.4 57.2 DR-07 16.0 +/- 0.7 15.3 +/- 0.8 15.2 +/- 1.0 15.6 +/- 0.7 15.6 +/- 0.4 62.2 DR-08 13.0 +/- 0.5 12.2 +/- 0.6 12.4 +/- 0.7 12.1 +/- 0.5 12.4 +/- 0.4 49.7 DR-09 13.5 +/- 0.6 13.3 +/- 0.5 12.7 +/- 0.6 13.9 +/- 0.5 13.4 +/- 0.5 53.4 DR-10 13.7 +/- 0.7 13.2 +/- 0.7 13.1 +/- 0.5 13.6 +/- 0.5 13.4 +/- 0.3 53.5 DR-11 10.6 +/- 0.5 9.8 +/- 0.4 10.8 +/- 0.7 10.7 +/- 0.5 10.5 +/- 0.5 42.0 DR-12 16.1 +/- 0.8 15.4 +/- 0.8 15.7 +/- 0.7 15.6 +/- 0.5 15.7 +/- 0.3 62.8 DR-13 16.7 +/- 0.8 15.9 +/- 0.8 16.0 +/- 0.6 16.0 +/- 0.5 16.2 +/- 0.3 64.7 DR-14 (a) 12.8 +/- 0.8 13.3 +/- 0.6 13.1 +/- 0.5 13.1 +/- 0.2 52.3 DR-15 13.6 +/- 0.6 13.2 +/- 0.8 13.6 +/- 0.9 13.5 +/- 0.7 13.5 +/- 0.2 54.0 DR-16 15.3 +/- 0.5 14.3 +/- 0.5 14.4 +/- 0.6 14.8 +/- 0.6 14.7 +/- 0.5 58.8 DR-17 15.5 +/- 0.7 14.5 +/- 0.7 14.5 +/- 0.6 14.3 +/- 0.6 14.7 +/- 0.6 58.8 DR-18 14.6 +/- 0.7 14.9 +/- 0.8 14.4 +/- 0.7 14.7 +/- 0.4 14.6 +/- 0.2 58.5 DR-19 14.6 +/- 0.7 14.8 +/- 0.9 14.5 +/- 0.8 14.6 +/- 0.5 14.6 +/- 0.1 58.5 DR-20 13.7 +/- 0.4 14.0 +/- 0.6 13.7 +/- 0.7 14.4 +/- 0.5 13.9 +/- 0.3 55.8 DR-21 14.4 +/- 0.6 14.5 +/- 0.6 14.1 +/- 0.8 14.1 +/- 0.4 14.3 +/- 0.2 57.1 DR-22 11.6 +/- 0.5 11.5 +/- 0.5 11.2 +/- 0.7 11.6 +/- 0.8 11.5 +/- 0.2 45.9 DR-23 14.1 +/- 0.7 15.4 +/- 0.9 14.3 +/- 0.9 14.1 +/- 0.5 14.5 +/- 0.6 57.9 DR-24 14.7 +/- 1.0 16.2 +/- 0.8 14.8 +/- 0.6 14.7 +/- 0.6 15.1 +/- 0.7 60.4 DR-25 12.4 +/- 0.7 12.2 +/- 0.7 12.8 +/- 0.5 12.1 +/- 0.4 12.4 +/- 0.3 49.5 DR-26 14.0 +/- 0.6 14.1 +/- 0.8 14.0 +/- 0.5 13.4 +/- 0.4 13.9 +/- 0.3 55.6 DR-27 13.7 +/- 0.4 13.2 +/- 0.7 13.8 +/- 0.8 13.3 +/- 0.5 13.5 +/- 0.3 54.0 DR-28 15.3 +/- 0.7 15.2 +/- 0.9 15.5 +/- 0.6 14.8 +/- 0.5 15.2 +/- 0.3 60.9 DR-29 13.9 +/- 0.8 13.8 +/- 0.5 14.2 +/- 0.6 13.9 +/- 0.7 14.0 +/- 0.2 55.8 DR-30 14.0 +/- 0.5 13.9 +/- 0.6 13.9 +/- 0.5 13.9 +/- 0.5 13.9 +/- 0.0 55.7 DR-31 16.1 +/- 0.6 15.9 +/- 0.6 16.5 +/- 0.6 15.7 +/- 0.8 16.1 +/- 0.3 64.2 DR-32 16.6 +/- 0.7 15.8 +/- 0.7 15.7 +/- 0.9 15.7 +/- 0.6 15.9 +/- 0.4 63.8 DR-33 13.5 +/- 0.6 13.7 +/- 0.6 13.3 +/- 0.5 13.6 +/- 0.5 13.5 +/- 0.2 54.1 DR-34 13.4 +/- 0.5 (a) 13.3 +/- 0.8 13.2 +/- 0.5 13.3 +/- 0.1 53.2 DR-35 15.2 +/- 0.5 14.4 +/- 0.5 14.0 +/- 0.7 13.8 +/- 0.5 14.3 +/- 0.6 57.3 DR-36 15.2 +/- 0.8 14.7 +/- 0.8 14.5 +/- 0.7 15.1 +/- 0.5 14.8 +/- 0.3 59.4 DR-37 14.2 +/- 0.6 14.1 +/- 0.6 13.4 +/- 0.5 13.8 +/- 0.7 13.9 +/- 0.3 55.5 DR-38 12.5 +/- 0.6 12.4 +/- 0.8 12.5 +/- 0.6 12.4 +/- 0.5 12.4 +/- 0.04 49.7 DR-39 15.9 +/- 0.8 14.2 +/- 0.8 14.4 +/- 0.6 (a) 14.8 +/- 0.9 59.3 DR-40*
16.3 +/- 0.8 14.8 +/- 0.6 15.1 +/- 0.8 15.2 +/- 0.6 15.4 +/- 0.7 61.4 DR-41 13.6 +/- 0.5 12.9 +/- 0.5 12.8 +/- 0.5 13.3 +/- 0.6 13.2 +/- 0.4 52.7 AVERAGE 14.3 + 1.3 14.0 + 1.3 13.9 + 1.2 14.0 + 1.2 14.1 +/- 1.2 56.1 (Indicator Locations)
- Control location Annual Radiological Environmental Operating Report Page 45 of 122 Year: 2024 Plant: Indian Point Energy Center (a) Refer to deviation table B-1b. Data was not available for the quarter listed, and the net dose was not calculated. For those locations with missing data, the annual dose is based on the average of the remaining quarterly data.
Year: 2024 Page 46 of 122 INDIAN POINT ENERGY CENTER TABLE B-4 DIRECT RADIATION, 2014 THROUGH 2024 DATA mR per Year Station Mean Standard Deviation Minimum Value Maximum Value 2024 Annual Number (2015-2023)
(2015-2023)
(2015-2023)
(2015-2023)
Total DR-01 63.1 1.8 60.6 65.6 62.7 DR-02 58.9 1.3 57.3 60.4 59.1 DR-03 49.5 1.4 46.8 50.9 50.0 DR-04 53.5 1.0 52.1 54.8 54.8 DR-05 55.1 1.9 52.3 58.2 55.1 DR-06 56.4 1.5 54.4 58.0 57.2 DR-07 62.5 2.0 59.3 64.6 62.2 DR-08 47.9 1.3 45.9 49.5 49.7 DR-09 54.2 1.7 50.9 55.8 53.4 DR-10 56.8 5.9 50.1 67.7 53.5 DR-11 43.2 1.5 40.4 44.6 42.0 DR-12 60.2 5.2 49.2 64.8 62.8 DR-13 64.5 2.2 62.0 67.6 64.7 DR-14 52.0 1.6 49.5 54.0 52.3 (a)
DR-15 51.7 1.7 49.0 53.8 54.0 DR-16 57.3 2.0 54.3 59.3 58.8 DR-17 57.4 2.4 53.5 60.1 58.8 DR-18 56.5 1.7 53.8 58.2 58.5 DR-19 58.1 2.1 54.3 60.4 58.5 DR-20 55.6 1.6 52.8 57.5 55.8 DR-21 56.0 2.1 53.0 58.4 57.1 DR-22 45.5 1.7 42.5 47.7 45.9 DR-23 55.7 1.9 52.3 57.4 57.9 DR-24 58.5 1.9 54.9 60.2 60.4 DR-25 48.3 1.4 46.1 50.0 49.5 DR-26 54.7 1.8 51.2 56.5 55.6 DR-27 54.1 1.9 51.3 56.5 54.0 DR-28 67.3 12.1 51.3 80.6 60.9 DR-29 56.1 1.9 52.6 58.3 55.8 DR-30 56.7 2.0 53.1 59.3 55.7 DR-31 64.8 2.2 60.7 67.4 64.2 DR-32 57.3 4.7 51.3 63.3 63.8 DR-33 53.6 1.6 50.7 55.6 54.1 DR-34 52.9 1.9 49.5 55.0 53.2 (a)
DR-35 54.4 1.9 50.7 56.3 57.3 DR-36 57.9 1.4 55.8 59.6 59.4 DR-37 54.8 2.0 50.8 56.8 55.5 DR-38 47.6 4.3 38.5 50.9 49.7 DR-39 58.3 1.5 55.8 59.4 59.3 (a)
DR-40*
60.1 2.4 56.3 62.4 61.4 DR-41 52.4 1.8 49.1 53.9 52.7 AVERAGE 55.5 56.1 (Indicator Locations)
- Control location Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report (a) Data was not available for the quarter listed, and the net dose was not calculated. For those locations with missing data, the annual dose is based on the average of the remaining quarterly data.
Plant: Indian Point Energy Center Year: 2024 Page 47 of 122 Annual Radiological Environmental Operating Report Table B-4A NISP ANSI 13.37 Monitoring Location Quarterly
- Baseline, BQ (mrem)
BQ +
MDDQ (mrem)
Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual
- Baseline, BA (mrem)
BA +
MDDA (mrem)
Annual Monitoring Data, MA (mrem)
Annual Facility Dose, FA=MA-BA (mrem, or ND if FA MDDA)
(mrem)
(mrem, or ND if FQ MDDQ) 1 2
3 4
1 2
3 4
DR-1 15.3 18.3 16.2 15.4 15.0 16.0 ND ND ND ND 61.1 67.1 62.7 ND DR-2 14.5 17.5 15.5 14.6 14.0 15.0 ND ND ND ND 58.1 64.1 59.1 ND DR-3 12.5 15.5 12.9 12.4 11.9 12.7 ND ND ND ND 49.9 55.9 50.0 ND DR-4 13.3 16.3 14.2 13.8 13.1 13.6 ND ND ND ND 53.2 59.2 54.8 ND DR-5 13.5 16.5 14.0 13.7 13.4 14.0 ND ND ND ND 54.0 60.0 55.1 ND DR-6 14.1 17.1 14.5 13.7 14.6 14.4 ND ND ND ND 56.3 62.3 57.2 ND DR-7 15.4 18.4 16.0 15.3 15.2 15.6 ND ND ND ND 61.4 67.4 62.2 ND DR-8 12.0 15.0 13.0 12.2 12.4 12.1 ND ND ND ND 48.2 54.2 49.7 ND DR-9 13.3 16.3 13.5 13.3 12.7 13.9 ND ND ND ND 53.3 59.3 53.4 ND DR-10 13.3 16.3 13.7 13.2 13.1 13.6 ND ND ND ND 53.0 59.0 53.5 ND DR-11 10.7 13.7 10.6 9.8 10.8 10.7 ND ND ND ND 42.8 48.8 42.0 ND DR-12 15.4 18.4 16.1 15.4 15.7 15.6 ND ND ND ND 61.4 67.4 62.8 ND DR-13 15.8 18.8 16.7 15.9 16.0 16.0 ND ND ND ND 63.2 69.2 64.7 ND DR-14 12.7 15.7 NA*
12.8 13.3 13.1 ND ND ND 51.0 57.0 52.3 ND DR-15 12.8 15.8 13.6 13.2 13.6 13.5 ND ND ND ND 51.3 57.3 54.0 ND DR-16 14.3 17.3 15.3 14.3 14.4 14.8 ND ND ND ND 57.1 63.1 58.8 ND DR-17 14.1 17.1 15.5 14.5 14.5 14.3 ND ND ND ND 56.2 62.2 58.8 ND DR-18 14.1 17.1 14.6 14.9 14.4 14.7 ND ND ND ND 56.3 62.3 58.5 ND DR-19 14.2 17.2 14.6 14.8 14.5 14.6 ND ND ND ND 57.0 63.0 58.5 ND DR-20 13.7 16.7 13.7 14.0 13.7 14.4 ND ND ND ND 54.9 60.9 55.8 ND DR-21 14.1 17.1 14.4 14.5 14.1 14.1 ND ND ND ND 56.2 62.2 57.1 ND DR-22 11.1 14.1 11.6 11.5 11.2 11.6 ND ND ND ND 44.3 50.3 45.9 ND DR-23 13.7 16.7 14.1 15.4 14.3 14.1 ND ND ND ND 54.9 60.9 57.9 ND DR-24 14.3 17.3 14.7 16.2 14.8 14.7 ND ND ND ND 57.1 63.1 60.4 ND DR-25 11.9 14.9 12.4 12.2 12.8 12.1 ND ND ND ND 47.6 53.6 49.5 ND DR-26 13.4 16.4 14.0 14.1 14.0 13.4 ND ND ND ND 53.6 59.6 55.6 ND DR-27 13.2 16.2 13.7 13.2 13.8 13.3 ND ND ND ND 52.9 58.9 54.0 ND DR-28 15.0 18.0 15.3 15.2 15.5 14.8 ND ND ND ND 60.1 66.1 60.9 ND DR-29 13.7 16.7 13.9 13.8 14.2 13.9 ND ND ND ND 54.7 60.7 55.8 ND DR-30 13.8 16.8 14.0 13.9 13.9 13.9 ND ND ND ND 55.3 61.3 55.7 ND DR-31 15.8 18.8 16.1 15.9 16.5 15.7 ND ND ND ND 63.3 69.3 64.2 ND DR-32 15.6 18.6 16.6 15.8 15.7 15.7 ND ND ND ND 62.3 68.3 63.8 ND DR-33 13.2 16.2 13.5 13.7 13.3 13.6 ND ND ND ND 52.6 58.6 54.1 ND DR-34 12.9 15.9 13.4 NA*
13.3 13.2 ND ND ND 51.7 57.7 53.2 ND DR-35 13.9 16.9 15.2 14.4 14.0 13.8 ND ND ND ND 55.5 61.5 57.3 ND DR-36 14.3 17.3 15.2 14.7 14.5 15.1 ND ND ND ND 57.2 63.2 59.4 ND DR-37 13.4 16.4 14.2 14.1 13.4 13.8 ND ND ND ND 53.8 59.8 55.5 ND DR-38 12.2 15.2 12.5 12.4 12.5 12.4 ND ND ND ND 48.9 54.9 49.7 ND DR-39 14.6 17.6 15.9 14.2 14.4 NA*
ND ND ND 58.5 64.5 59.3 ND DR-40 14.8 17.8 16.3 14.8 15.1 15.2 ND ND ND ND 59.3 65.3 61.4 ND DR-41 12.9 15.9 13.6 12.9 12.8 13.3 ND ND ND ND 51.7 57.7 52.7 ND MDDQ = Quarterly Minimum Differential Dose = 3 mrem MDDA = Annual Minimum Differential Dose = 6 mrem ND = Not Detected, where MQ (BQ+MDDQ) or MA (BA+MDDA)
Year: 2024 Page 48 of 122 INDIAN POINT ENERGY CENTER TABLE B-5 DIRECT RADIATION, INNER AND OUTER RINGS - 2024 (mR per Year)
Inner Ring Outer Ring Sector Inner Ring Outer Ring ID ID Annual Total Annual Total DR-01 DR-17 N
62.66 58.83 DR-02 DR-18 NNE 59.12 58.46 DR-03 DR-19 NE 50.00 58.50 DR-04 DR-20 ENE 54.76 55.76 DR-05 DR-21 E
55.13 57.08 DR-06 DR-22 ESE 57.19 45.88 DR-07 DR-23 SE 62.21 57.86 DR-08 DR-24 SSE 49.70 60.36 DR-09 DR-25 S
53.44 49.46 DR-10 DR-26 SSW 53.46 55.57 DR-11 DR-27 SW 41.99 53.96 DR-12 DR-28 WSW 62.83 60.90 DR-13 DR-29 W
64.71 55.83 DR-14 DR-30 WNW 52.27 55.68 DR-15 DR-31 NW 53.97 64.25 DR-16 DR-32 NNW 58.81 63.79 Average 55.77 57.01 Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report
INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2024 pCi/m3 +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Training Building Met Tower Telcom Bldg.
ENDING 4
5 23*
27 29 94 95 01/08/24 0.014 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 01/16/24 0.016 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 01/22/24 0.021 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 01/29/24 0.012 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.002 02/05/24 0.012 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 02/12/24 0.012 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 02/20/24 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 02/26/24 0.013 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.003 0.014 +/- 0.003 03/04/24 0.014 +/- 0.002 0.016 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 03/11/24 0.007 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 03/18/24 0.019 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 03/25/24 0.010 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 04/01/24 0.014 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.003 04/08/24 0.008 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 04/15/24 0.012 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.022 +/- 0.008 0.011 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 04/22/24 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 04/29/24 0.015 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.018 +/- 0.003 05/06/24 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 05/13/24 0.009 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 05/20/24 0.011 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.007 +/- 0.002 0.010 +/- 0.002 05/28/24 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 06/03/24 0.012 +/- 0.002 0.013 +/- 0.003 0.014 +/- 0.003 0.008 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0.012 +/- 0.003 0.012 +/- 0.003 06/10/24 (a) 0.013 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 06/17/24 0.010 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 06/24/24 0.014 +/- 0.003 0.015 +/- 0.002 0.016 +/- 0.003 0.014 +/- 0.002 0.016 +/- 0.003 0.013 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.003
- Control Location (a) Refer to deviation table B-1a 108 Page 49 of 122 Year: 2024 Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report I
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INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2024 pCi/m3 +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Training Building Met Tower Telcom Bldg.
ENDING 4
5 23*
27 29 94 95 07/01/24 0.012 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 07/08/24 0.013 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 07/15/24 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 (a) 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 07/22/24 0.015 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 (a) 0.016 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 07/29/24 0.015 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 (a) 0.015 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 08/05/24 0.018 +/- 0.002 0.018 +/- 0.002 0.020 +/- 0.003 0.018 +/- 0.003 (a) 0.017 +/- 0.002 0.017 +/- 0.002 0.020 +/- 0.003 08/12/24 0.010 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 (a) 0.011 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 08/19/24 0.016 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 (a) 0.014 +/- 0.002 0.017 +/- 0.003 0.013 +/- 0.002 08/26/24 0.015 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 (a) 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 09/03/24 0.017 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 0.015 +/- 0.002 (a) 0.014 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 09/09/24 0.010 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.003 0.011 +/- 0.002 (a) 0.012 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 09/16/24 0.024 +/- 0.003 0.018 +/- 0.002 0.025 +/- 0.003 0.021 +/- 0.003 (a) 0.021 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 09/23/24 0.021 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.003 (a) 0.021 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 09/30/24 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 (a) 0.009 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 10/07/24 0.018 +/- 0.003 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 (a) 0.013 +/- 0.002 0.016 +/- 0.003 0.014 +/- 0.002 10/14/24 0.013 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 (a) 0.013 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 10/21/24 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 (a) 0.012 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 10/28/24 0.024 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 (a) 0.024 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003 11/04/24 0.017 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.003 0.020 +/- 0.003 (a) 0.014 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 11/11/24 0.013 +/- 0.002 (a) 0.014 +/- 0.002 0.016 +/- 0.002 (a) 0.012 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 11/18/24 0.015 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 (a) 0.012 +/- 0.002 0.011 +/- 0.002 (b) 11/25/24 0.015 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 (a) 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.001 12/02/24 0.015 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.003 0.019 +/- 0.003 (a) 0.017 +/- 0.003 0.017 +/- 0.002 (b) 12/09/24 0.014 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 (a) 0.013 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 12/16/24 0.012 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 (a) 0.012 +/- 0.002 0.013 +/- 0.002 (b) 12/23/24 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.024 +/- 0.004 (a) 0.012 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 12/30/24 0.017 +/- 0.003 0.016 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.004 (a) 0.014 +/- 0.002 0.014 +/- 0.002 (b)
- Control Location (a) Refer to deviation table B-1a (b) Sample collection frequency changed to every 2 weeks.
Annual Radiological Environmental Operating Report 108 Plant: Indian Point Energy Center Year: 2024 Page 50 of 122 I
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INDIAN POINT ENERGY CENTER TABLE B-7 IODINE-131 ACTIVITY IN AIRBORNE CHARCOAL SAMPLES - 2024 pCi/m3 +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Training Building Met Tower Telcom Bldg.
ENDING 4
5 23*
27 29 94 95 108 01/08/24
< 0.028
< 0.030
< 0.030
< 0.028
< 0.031
< 0.028
< 0.030
< 0.032 02/05/24
< 0.030
< 0.032
< 0.022
< 0.030
< 0.023
< 0.030
< 0.022
< 0.024 02/12/24
< 0.035
< 0.037
< 0.021
< 0.036
< 0.020
< 0.035
< 0.021
< 0.022 02/20/24
< 0.018
< 0.017
< 0.019
< 0.018
< 0.018
< 0.018
< 0.018
< 0.019 02/26/24
< 0.024
< 0.023
< 0.024
< 0.025
< 0.015
< 0.024
< 0.024
< 0.024 03/04/24
< 0.018
< 0.008
< 0.020
< 0.019
< 0.019
< 0.018
< 0.019
< 0.020 03/11/24
< 0.024
< 0.023
< 0.026
< 0.024
< 0.025
< 0.024
< 0.025
< 0.027 03/18/24
< 0.021
< 0.020
< 0.021
< 0.021
< 0.020
< 0.021
< 0.021
< 0.021
- Control Location (a) Refer to deviation table B-1c Annual Radiological Environmental Operating Report Page 51 of 122 Year: 2024 Plant: Indian Point Energy Center (a)
I I
INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2024 10-3 pCi/m3 +/- 2 Sigma Algonquin NYU Tower 4
5 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 75 +/- 18 85 +/- 22 103 +/- 18 62 +/- 16 88 +/- 18 103 +/- 23 92 +/- 20 53 +/- 20 K-40
< 26
< 23
< 14
< 22
< 21
< 20
< 23
< 22 Mn-54
< 2
< 1
< 1
< 1
< 1
< 1
< 1
< 2 Co-58
< 3
< 2
< 2
< 1
< 2
< 2
< 3
< 2 Fe-59
< 8
< 6
< 3
< 6
< 4
< 7
< 5
< 7 Co-60
< 2
< 2
< 1
< 2
< 1
< 2
< 2
< 2 Zn-65
< 5
< 3
< 2
< 3
< 3
< 3
< 2
< 4 Nb-95
< 3
< 3
< 2
< 2
< 2
< 2
< 3
< 2 Zr-95
< 4
< 4
< 3
< 4
< 3
< 3
< 4
< 5 Ru-103
< 3
< 4
< 2
< 3
< 2
< 3
< 4
< 4 Ru-106
< 15
< 14
< 7
< 11
< 8
< 9
< 11
< 12 I-131
< 213
< 413
< 437
< 193
< 167
< 304
< 627
< 227 Cs-134
< 2
< 2
< 1
< 1
< 1
< 1
< 1
< 2 Cs-137
< 2
< 1
< 1
< 1
< 1
< 1
< 1
< 1 Ba-140
< 135
< 166
< 145
< 91
< 62
< 169
< 173
< 116 La-140
< 34
< 70
< 82
< 50
< 32
< 67
< 109
< 51 Ce-141
< 5
< 6
< 4
< 4
< 3
< 5
< 5
< 4 Ce-144
< 6
< 6
< 4
< 5
< 5
< 4
< 5
< 6 Ra-226
< 25
< 20
< 15
< 18
< 18
< 16
< 20
< 22 Ac-228
< 5
< 3
< 3
< 4
< 4
< 4
< 5
< 5 Th-228
< 2
< 2
< 1
< 2
< 2
< 2
< 2
< 2 Page 52 of 122 Year: 2024 Plant: Indian Point Energy Center Annual Radiological Environmental Operating ReportI I
INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2024 10-3 pCi/m3 +/- 2 Sigma Roseton Croton Point 23*
27 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 73 +/- 17 96 +/- 27 96 +/- 22 62 +/- 20 64 +/- 13 87 +/- 22 89 +/- 22 63 +/- 17 K-40
< 22
< 26
< 25
< 21
< 17
< 25
< 18
< 28 Mn-54
< 1
< 2
< 1
< 1
< 1
< 1
< 1
< 1 Co-58
< 2
< 3
< 3
< 2
< 1
< 2
< 1
< 2 Fe-59
< 6
< 8
< 8
< 6
< 5
< 6
< 8
< 7 Co-60
< 2
< 2
< 2
< 2
< 1
< 2
< 1
< 1 Zn-65
< 4
< 5
< 4
< 4
< 2
< 4
< 4
< 3 Nb-95
< 2
< 3
< 3
< 2
< 2
< 3
< 2
< 2 Zr-95
< 4
< 5
< 5
< 4
< 3
< 5
< 4
< 3 Ru-103
< 3
< 4
< 5
< 3
< 2
< 3
< 3
< 2 Ru-106
< 12
< 17
< 14
< 13
< 8
< 12
< 10
< 12 I-131
< 163
< 525
< 667
< 213
< 107
< 439
< 493
< 229 Cs-134
< 2
< 2
< 2
< 1
< 1
< 1
< 1
< 1 Cs-137
< 1
< 2
< 1
< 1
< 1
< 1
< 1
< 1 Ba-140
< 95
< 236
< 204
< 124
< 67
< 171
< 158
< 93 La-140
< 20
< 98
< 74
< 42
< 30
< 53
< 72
< 29 Ce-141
< 5
< 5
< 6
< 5
< 3
< 7
< 5
< 4 Ce-144
< 6
< 7
< 6
< 6
< 4
< 7
< 5
< 5 Ra-226
< 23
< 22
< 22
< 21
< 17
< 25
< 16
< 19 Ac-228
< 5
< 6
< 5
< 4
< 4
< 6
< 4
< 4 Th-228
< 2
< 2
< 2
< 2
< 2
< 2
< 2
< 2
- Control Location Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center Year: 2024 Page 53 of 121 I
I
INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2024 10-3 pCi/m3 +/- 2 Sigma Grassy Point Training Building 29 94 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 65 +/- 14 106 +/- 22
< 74 (a) 67 +/- 14 85 +/- 18 101 +/- 25 79 +/- 20 K-40
< 14
< 17
< 25 (a)
< 21
< 13
< 25
< 22 Mn-54
< 1
< 1
< 3 (a)
< 1
< 1
< 1
< 1 Co-58
< 1
< 2
< 7 (a)
< 1
< 2
< 2
< 2 Fe-59
< 6
< 7
< 27 (a)
< 5
< 5
< 6
< 6 Co-60
< 1
< 1
< 3 (a)
< 1
< 1
< 1
< 1 Zn-65
< 2
< 3
< 8 (a)
< 3
< 3
< 4
< 4 Nb-95
< 1
< 2
< 8 (a)
< 2
< 2
< 2
< 2 Zr-95
< 1
< 4
< 13 (a)
< 3
< 3
< 4
< 4 Ru-103
< 2
< 3
< 15 (a)
< 3
< 2
< 3
< 3 Ru-106
< 10
< 11
< 25 (a)
< 10
< 9
< 12
< 12 I-131
< 93
< 326
< 43480 (a)
< 119
< 325
< 650
< 240 Cs-134
< 1
< 1
< 3 (a)
< 1
< 1
< 1
< 2 Cs-137
< 1
< 1
< 2 (a)
< 1
< 1
< 1
< 1 Ba-140
< 67
< 102
< 3815 (a)
< 63
< 109
< 211
< 109 La-140
< 31
< 79
< 1489 (a)
< 30
< 59
< 96
< 29 Ce-141
< 2
< 4
< 23 (a)
< 3
< 4
< 6
< 5 Ce-144
< 3
< 4
< 11 (a)
< 4
< 4
< 6
< 6 Ra-226
< 14
< 17
< 37 (a)
< 16
< 16
< 23
< 24 Ac-228
< 3
< 4
< 10 (a)
< 4
< 4
< 5
< 3 Th-228
< 1
< 1
< 4 (a)
< 1
< 1
< 2
< 2 Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center Year: 2024 Page 54 of 121 I
I
INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2024 10-3 pCi/m3 +/- 2 Sigma Met Tower Telecomm Bldg 95 108 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 67 +/- 17 95 +/- 22 94 +/- 26 65 +/- 19 75 +/- 16 103 +/- 19 97 +/- 24 62 +/- 16 K-40
< 21
< 13
< 21
< 22
< 21
< 15
< 14
< 18 Mn-54
< 1
< 1
< 1
< 1
< 1
< 1
< 1
< 2 Co-58
< 1
< 2
< 2
< 2
< 1
< 2
< 2
< 2 Fe-59
< 5
< 6
< 7
< 5
< 4
< 4
< 6
< 5 Co-60
< 1
< 1
< 1
< 2
< 1
< 1
< 1
< 2 Zn-65
< 3
< 3
< 4
< 3
< 3
< 3
< 3
< 5 Nb-95
< 2
< 2
< 2
< 2
< 2
< 2
< 2
< 2 Zr-95
< 3
< 4
< 4
< 3
< 4
< 2
< 3
< 3 Ru-103
< 3
< 3
< 4
< 2
< 2
< 2
< 3
< 2 Ru-106
< 11
< 11
< 11
< 9
< 8
< 8
< 11
< 13 I-131
< 127
< 403
< 501
< 187
< 152
< 254
< 488
< 285 Cs-134
< 2
< 1
< 1
< 1
< 1
< 1
< 1
< 1 Cs-137
< 1
< 1
< 1
< 1
< 1
< 1
< 1
< 2 Ba-140
< 75
< 173
< 170
< 89
< 79
< 117
< 178
< 119 La-140
< 40
< 60
< 49
< 37
< 41
< 48
< 65
< 37 Ce-141
< 4
< 5
< 4
< 3
< 3
< 4
< 4
< 4 Ce-144
< 5
< 5
< 5
< 4
< 3
< 3
< 4
< 5 Ra-226
< 17
< 18
< 17
< 17
< 16
< 14
< 16
< 19 Ac-228
< 4
< 4
< 4
< 5
< 4
< 4
< 3
< 5 Th-228
< 2
< 2
< 1
< 1
< 1
< 1
< 1
< 2 Plant: Indian Point Energy Center Year: 2024 Page 55 of 121 Annual Radiological Environmental Operating ReportI I
INDIAN POINT ENERGY CENTER TABLE B-9 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Camp Field 7
DATE RADIOCHEMICAL Gr-B
< 2 2 +/- 1
< 2
< 2
< 2
< 2 H-3 (a)
< 191
< 190 GAMMA Be-7
< 55
< 57
< 54
< 42
< 40
< 27 K-40
< 106
< 104
< 140
< 121
< 71
< 65 Mn-54
< 6
< 5
< 6
< 5
< 6
< 3 Co-58
< 7
< 5
< 9
< 6
< 4
< 4 Fe-59
< 11
< 16
< 14
< 10
< 9
< 8 Co-60
< 6
< 9
< 11
< 7
< 6
< 5 Zn-65
< 13
< 16
< 18
< 12
< 11
< 7 Nb-95
< 7
< 7
< 6
< 5
< 5
< 4 Zr-95
< 12
< 10
< 12
< 8
< 8
< 6 Ru-103
< 6
< 7
< 7
< 5
< 4
< 4 Ru-106
< 49
< 44
< 68
< 52
< 43
< 31 I-131
< 7
< 7
< 6
< 6
< 6
< 4 Cs-134
< 6
< 6
< 8
< 7
< 5
< 4 Cs-137
< 7
< 6
< 8
< 6
< 5
< 3 Ba-140
< 21
< 19
< 27
< 18
< 17
< 12 La-140
< 10
< 7
< 7
< 8
< 6
< 5 Ce-141
< 10
< 10
< 9
< 8
< 8
< 6 Ce-144
< 43
< 44
< 44
< 41
< 33
< 23 Ra-226
< 175
< 148
< 160
< 133
< 134
< 101 Ac-228
< 28
< 22
< 28
< 21
< 20
< 15 Th-228
< 10
< 12
< 12
< 10
< 9
< 8 (a) Quarterly Composite 5/14/2024 Annual Radiological Environmental Operating Report Page 56 of 122 Year: 2024 Plant: Indian Point Energy Center 01/09/24 02/14/24 03/12/24 04/09/24 06/11/24
INDIAN POINT ENERGY CENTER TABLE B-9 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Camp Field 7
DATE RADIOCHEMICAL Gr-B
< 2 3 +/- 1 3 +/- 2
< 2
< 2 2 +/- 1 H-3 (a)
< 190
< 178 GAMMA Be-7
< 56
< 31
< 51
< 13
< 40
< 35 K-40
< 116
< 115
< 122
< 32
< 92
< 62 Mn-54
< 7
< 7
< 6
< 2
< 4
< 4 Co-58
< 6
< 6
< 7
< 2
< 3
< 5 Fe-59
< 14
< 12
< 12
< 3
< 9
< 11 Co-60
< 7
< 8
< 8
< 2
< 7
< 5 Zn-65
< 11
< 15
< 14
< 3
< 12
< 11 Nb-95
< 4
< 4
< 6
< 2
< 4
< 4 Zr-95
< 11
< 10
< 10
< 3
< 5
< 7 Ru-103
< 6
< 7
< 7
< 2
< 4
< 4 Ru-106
< 57
< 65
< 52
< 15
< 45
< 51 I-131
< 7
< 7
< 7
< 2
< 5
< 5 Cs-134
< 8
< 8
< 7
< 2
< 5
< 5 Cs-137
< 7
< 8
< 6
< 2
< 5
< 4 Ba-140
< 27
< 21
< 23
< 6
< 17
< 14 La-140
< 4
< 9
< 9
< 2
< 6
< 8 Ce-141
< 10
< 10
< 10
< 3
< 7
< 6 Ce-144
< 43
< 39
< 41
< 12
< 37
< 32 Ra-226
< 160
< 143
< 152
< 34
< 141
< 116 Ac-228
< 22
< 25
< 31
< 7
< 19
< 18 Th-228
< 12
< 13
< 14
< 3
< 11
< 10 (a) Quarterly Composite Year: 2024 Page 57 of 122 Annual Radiological Environmental Operating Report 12/10/24 07/09/24 08/13/24 09/10/24 10/08/24 11/12/24 Plant: Indian Point Energy Center
INDIAN POINT ENERGY CENTER TABLE B-9 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Croton 8
DATE RADIOCHEMICAL Gr-B 3 +/- 2
< 2 3 +/- 2
< 2
< 2 3 +/- 2 H-3 (a)
< 190
< 194 GAMMA Be-7
< 44
< 41
< 57
< 48
< 44
< 50 K-40
< 91
< 75
< 112
< 105
< 92
< 105 Mn-54
< 6
< 5
< 7
< 5
< 4
< 5 Co-58
< 7
< 5
< 7
< 4
< 6
< 6 Fe-59
< 16
< 10
< 12
< 12
< 8
< 13 Co-60
< 8
< 7
< 9
< 6
< 8
< 8 Zn-65
< 14
< 13
< 16
< 13
< 14
< 11 Nb-95
< 14
< 5
< 7
< 7
< 5
< 7 Zr-95
< 7
< 11
< 12
< 12
< 10
< 8 Ru-103
< 49
< 5
< 7
< 4
< 5
< 6 Ru-106
< 8
< 49
< 63
< 56
< 52
< 51 I-131
< 6
< 6
< 6
< 6
< 6
< 6 Cs-134
< 7
< 7
< 8
< 5
< 7
< 7 Cs-137
< 30
< 7
< 9
< 7
< 6
< 6 Ba-140
< 8
< 21
< 23
< 18
< 14
< 19 La-140
< 11
< 8
< 10
< 8
< 6
< 11 Ce-141
< 44
< 8
< 10
< 9
< 8
< 8 Ce-144
< 182
< 37
< 39
< 41
< 34
< 34 Ra-226
< 11
< 143
< 163
< 136
< 130
< 139 Ac-228
< 26
< 21
< 26
< 22
< 18
< 20 Th-228
< 11
< 10
< 11
< 10
< 10
< 11 (a) Quarterly Composite Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center Year: 2024 Page 58 of 122 06/11/24 01/09/24 02/14/24 03/12/24 04/09/24 05/14/24
INDIAN POINT ENERGY CENTER TABLE B-9 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Croton 8
DATE RADIOCHEMICAL Gr-B
< 2 3 +/- 1 3 +/- 1
< 2
< 2
< 2 H-3 (a)
< 188
< 180 GAMMA Be-7
< 52
< 50
< 57
< 44
< 48
< 48 K-40
< 134
< 107
< 130
< 121
< 98
< 111 Mn-54
< 7
< 5
< 6
< 7
< 6
< 6 Co-58
< 8
< 7
< 6
< 5
< 6
< 5 Fe-59
< 12
< 10
< 15
< 12
< 12
< 13 Co-60
< 8
< 6
< 8
< 5
< 7
< 7 Zn-65
< 14
< 9
< 10
< 14
< 10
< 12 Nb-95
< 6
< 6
< 8
< 7
< 7
< 7 Zr-95
< 11
< 10
< 12
< 10
< 9
< 11 Ru-103
< 7
< 5
< 6
< 7
< 6
< 5 Ru-106
< 60
< 54
< 55
< 70
< 57
< 57 I-131
< 6
< 6
< 6
< 7
< 6
< 6 Cs-134
< 7
< 6
< 7
< 7
< 7
< 7 Cs-137
< 8
< 6
< 8
< 6
< 4
< 6 Ba-140
< 26
< 23
< 21
< 25
< 21
< 23 La-140
< 8
< 9
< 9
< 7
< 7
< 7 Ce-141
< 9
< 10
< 9
< 10
< 11
< 9 Ce-144
< 41
< 37
< 43
< 40
< 42
< 38 Ra-226
< 154
< 132
< 151
< 155
< 168
< 147 Ac-228
< 27
< 25
< 21
< 32
< 22
< 26 Th-228
< 12
< 10
< 13
< 12
< 10
< 12 (a) Quarterly Composite Plant: Indian Point Energy Center Year: 2024 Page 59 of 122 07/09/24 12/10/24 08/13/24 09/10/24 10/08/24 11/12/24 Annual Radiological Environmental Operating Report
INDIAN POINT ENERGY CENTER TABLE B-10 GAMMA EMITTERS IN SOIL SAMPLES - 2024 pCi/kg dry +/- 2 Sigma Roseton Training Building Met Tower 23*
94 95 DATE Be-7
< 718
< 575
< 414 K-40 14090 +/- 1837 8764 +/- 1285 10300 +/- 1513 Mn-54
< 96
< 74
< 58 Co-58
< 82
< 62
< 59 Fe-59
< 183
< 140
< 132 Co-60
< 94
< 94
< 60 Zn-65
< 220
< 201
< 139 Nb-95
< 97
< 77
< 63 Zr-95
< 148
< 137
< 95 Ru-103
< 79
< 67
< 42 Ru-106
< 686
< 639
< 485 I-131
< 92
< 63
< 54 Cs-134
< 125
< 85
< 59 Cs-137
< 90
< 89
< 64 Ba-140
< 325
< 284
< 167 La-140
< 89
< 81
< 60 Ce-141
< 114
< 85
< 59 Ce-144
< 449
< 355
< 259 Ra-226
< 1985
< 1508
< 1191 Th-228 672 +/- 218 312 +/- 103 164 +/- 66
- Control Location 09/03/24 09/04/24 09/04/24 Plant: Indian Point Energy Center Year: 2024 Page 60 of 122 Annual Radiological Environmental Operating Report
DATE GAMMA Be-7 467 +/- 217 708 +/- 201
< 229 437 +/- 168 1072 +/- 263 761 +/- 210 K-40 5522 +/- 555 5381 +/- 573 2894 +/- 584 4636 +/- 516 3503 +/- 509 4601 +/- 698 Mn-54
< 20
< 20
< 34
< 17
< 29
< 30 Co-58
< 21
< 21
< 24
< 14
< 27
< 19 Fe-59
< 42
< 40
< 48
< 34
< 60
< 67 Co-60
< 26
< 27
< 37
< 29
< 29
< 37 Zn-65
< 48
< 46
< 58
< 53
< 70
< 68 Nb-95
< 20
< 22
< 20
< 18
< 29
< 29 Zr-95
< 39
< 37
< 48
< 33
< 48
< 45 Ru-103
< 20
< 21
< 25
< 16
< 31
< 28 Ru-106
< 175
< 158
< 274
< 174
< 252
< 226 I-131
< 25
< 22
< 24
< 21
< 27
< 36 Cs-134
< 21
< 23
< 31
< 26
< 26
< 33 Cs-137
< 23
< 21
< 26
< 19
< 32
< 25 Ba-140
< 84
< 75
< 83
< 78
< 88
< 115 La-140
< 18
< 21
< 22
< 17
< 39
< 40 Ce-141
< 31
< 28
< 28
< 24
< 37
< 37 Ce-144
< 121
< 138
< 124
< 99
< 141
< 161 Ra-226
< 530
< 502
< 530
< 455
< 649
< 566 Th-228
< 47
< 38
< 47
< 29
< 46
< 52
- Control Location Page 61 of 122 Year: 2024 Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report 06/17/24 05/20/24 05/20/24 05/20/24 INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma Roseton 23*
06/17/24 06/17/24
DATE GAMMA Be-7 1199 +/- 283 1490 +/- 368 413 +/- 160 399 +/- 195 1749 +/- 298 685 +/- 292 K-40 4509 +/- 609 2765 +/- 545 4744 +/- 596 4067 +/- 478 2528 +/- 463 4204 +/- 758 Mn-54
< 22
< 31
< 26
< 22
< 24
< 32 Co-58
< 23
< 24
< 26
< 17
< 21
< 31 Fe-59
< 54
< 56
< 61
< 40
< 44
< 53 Co-60
< 34
< 34
< 30
< 26
< 18
< 27 Zn-65
< 64
< 78
< 63
< 49
< 48
< 74 Nb-95
< 26
< 29
< 32
< 19
< 20
< 32 Zr-95
< 43
< 56
< 53
< 33
< 39
< 61 Ru-103
< 26
< 25
< 26
< 18
< 23
< 31 Ru-106
< 221
< 258
< 257
< 180
< 170
< 327 I-131
< 47
< 49
< 46
< 24
< 25
< 39 Cs-134
< 33
< 32
< 29
< 23
< 26
< 36 Cs-137
< 23
< 25
< 30
< 21
< 24
< 37 Ba-140
< 138
< 140
< 144
< 74
< 81
< 128 La-140
< 43
< 44
< 45
< 28
< 16
< 40 Ce-141
< 41
< 41
< 41
< 33
< 33
< 47 Ce-144
< 166
< 179
< 146
< 142
< 138
< 184 Ra-226
< 632
< 666
< 634
< 507
< 550
< 901 Th-228
< 44
< 53
< 55
< 38
< 41
< 70
- Control Location 08/19/24 08/19/24 08/19/24 07/22/24 07/22/24 Page 62 of 122 07/22/24 Plant: Indian Point Energy Center INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 Year: 2024 Annual Radiological Environmental Operating Report pCi/kg wet +/- 2 Sigma Roseton 23*
DATE GAMMA Be-7 2312 +/- 332 1670 +/- 309 966 +/- 240 1884 +/- 261 1188 +/- 183 551 +/- 138 K-40 4142 +/- 523 2808 +/- 509 5137 +/- 633 2763 +/- 463 3857 +/- 372 3566 +/- 358 Mn-54
< 32
< 29
< 22
< 23
< 17
< 19 Co-58
< 27
< 19
< 25
< 18
< 15
< 16 Fe-59
< 66
< 51
< 53
< 49
< 32
< 35 Co-60
< 45
< 31
< 33
< 27
< 20
< 20 Zn-65
< 68
< 68
< 67
< 49
< 37
< 40 Nb-95
< 32
< 31
< 26
< 23
< 17
< 19 Zr-95
< 58
< 44
< 49
< 36
< 28
< 31 Ru-103
< 27
< 28
< 23
< 20
< 17
< 17 Ru-106
< 282
< 220
< 231
< 189
< 157
< 164 I-131
< 38
< 34
< 28
< 26
< 21
< 21 Cs-134
< 31
< 27
< 26
< 26
< 18
< 19 Cs-137
< 30
< 37
< 26
< 22
< 17
< 19 Ba-140
< 107
< 86
< 100
< 83
< 66
< 73 La-140
< 40
< 17
< 26
< 29
< 22
< 19 Ce-141
< 45
< 39
< 35
< 32
< 24
< 26 Ce-144
< 179
< 169
< 125
< 147
< 92
< 114 Ra-226
< 788
< 648
< 599
< 516
< 357
< 419 Th-228
< 55
< 53
< 48
< 44
< 28
< 33
- Control Location pCi/kg wet +/- 2 Sigma Roseton 23*
10/14/24 10/14/24 10/14/24 Year: 2024 Page 63 of 122 Annual Radiological Environmental Operating Report GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 INDIAN POINT ENERGY CENTER TABLE B-11 09/16/24 09/16/24 09/16/24 Plant: Indian Point Energy Center
DATE GAMMA Be-7 399 +/- 193 702 +/- 153
< 138 1449 +/- 354
< 256 674 +/- 306 K-40 4217 +/- 587 5191 +/- 473 2941 +/- 535 6134 +/- 838 4132 +/- 570 4401 +/- 735 Mn-54
< 20
< 19
< 22
< 36
< 20
< 49 Co-58
< 22
< 20
< 20
< 31
< 21
< 46 Fe-59
< 58
< 38
< 45
< 88
< 51
< 98 Co-60
< 24
< 25
< 42
< 38
< 26
< 40 Zn-65
< 56
< 51
< 38
< 90
< 55
< 107 Nb-95
< 27
< 17
< 14
< 37
< 24
< 57 Zr-95
< 38
< 33
< 33
< 62
< 33
< 73 Ru-103
< 21
< 18
< 18
< 33
< 23
< 45 Ru-106
< 214
< 172
< 154
< 294
< 196
< 366 I-131
< 21
< 22
< 20
< 31
< 26
< 45 Cs-134
< 30
< 22
< 24
< 34
< 28
< 48 Cs-137
< 25
< 22
< 18
< 37
< 26
< 53 Ba-140
< 85
< 66
< 73
< 111
< 90
< 156 La-140
< 23
< 13
< 21
< 30
< 13
< 63 Ce-141
< 33
< 28
< 24
< 43
< 37
< 56 Ce-144
< 134
< 111
< 114
< 179
< 153
< 267 Ra-226
< 473
< 482
< 425
< 771
< 560
< 884 Th-228
< 39
< 39
< 30
< 62
< 45
< 82 05/21/24 06/18/24 06/18/24 INDIAN POINT ENERGY CENTER 05/21/24 05/21/24 TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma Training Center 94 Annual Radiological Environmental Operating Report 06/18/24 Plant: Indian Point Energy Center Year: 2024 Page 64 of 122
DATE GAMMA Be-7 2233 +/- 368 367 +/- 208 886 +/- 221 2894 +/- 308 1134 +/- 286 4364 +/- 463 K-40 3927 +/- 638 5004 +/- 538 3863 +/- 530 3577 +/- 506 5172 +/- 594 5886 +/- 675 Mn-54
< 28
< 20
< 25
< 24
< 25
< 29 Co-58
< 24
< 24
< 26
< 18
< 31
< 24 Fe-59
< 57
< 51
< 55
< 42
< 49
< 60 Co-60
< 31
< 27
< 27
< 22
< 28
< 33 Zn-65
< 62
< 48
< 61
< 44
< 60
< 72 Nb-95
< 33
< 22
< 26
< 22
< 32
< 28 Zr-95
< 55
< 39
< 45
< 40
< 39
< 52 Ru-103
< 28
< 20
< 28
< 20
< 27
< 28 Ru-106
< 235
< 183
< 249
< 205
< 236
< 248 I-131
< 40
< 30
< 37
< 24
< 28
< 29 Cs-134
< 36
< 26
< 29
< 26
< 32
< 32 Cs-137
< 29
< 25
< 24
< 22
< 23
< 30 Ba-140
< 104
< 93
< 115
< 65
< 97
< 107 La-140
< 37
< 16
< 32
< 26
< 25
< 29 Ce-141
< 42
< 35
< 45
< 32
< 36
< 41 Ce-144
< 162
< 139
< 162
< 135
< 162
< 186 Ra-226
< 592
< 473
< 655
< 498
< 583
< 673 Th-228
< 59 72 +/- 42
< 53
< 49
< 50
< 56 94 Plant: Indian Point Energy Center Year: 2024 Page 65 of 122 pCi/kg wet +/- 2 Sigma Training Center 08/20/24 07/24/24 07/24/24 07/24/24 08/20/24 08/20/24 Annual Radiological Environmental Operating Report INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024
DATE GAMMA Be-7 1602 +/- 324 780 +/- 323 1059 +/- 292 928 +/- 235 2878 +/- 230 2108 +/- 219 K-40 4263 +/- 529 5115 +/- 714 5639 +/- 642 4554 +/- 496 3194 +/- 406 3812 +/- 341 Mn-54
< 29
< 31
< 29
< 22
< 17
< 17 Co-58
< 31
< 26
< 27
< 22
< 17
< 18 Fe-59
< 62
< 54
< 59
< 43
< 43
< 43 Co-60
< 31
< 39
< 24
< 26
< 22
< 22 Zn-65
< 73
< 71
< 75
< 56
< 41
< 44 Nb-95
< 26
< 27
< 29
< 23
< 19
< 19 Zr-95
< 50
< 60
< 37
< 36
< 29
< 34 Ru-103
< 25
< 24
< 28
< 21
< 17
< 17 Ru-106
< 238
< 247
< 283
< 203
< 149
< 162 I-131
< 32
< 30
< 32
< 26
< 18
< 21 Cs-134
< 33
< 39
< 33
< 26
< 20
< 22 Cs-137
< 31
< 33
< 32
< 26
< 17
< 19 Ba-140
< 103
< 92
< 84
< 89
< 65
< 70 La-140
< 34
< 38
< 30
< 23
< 18
< 22 Ce-141
< 37
< 43
< 43
< 32
< 24
< 26 Ce-144
< 167
< 182
< 200
< 139
< 104
< 109 Ra-226
< 614
< 597
< 722
< 532
< 436
< 420 Th-228
< 56
< 60
< 58
< 37
< 37 55 +/- 33 09/17/24 09/17/24 Training Center 94 09/17/24 Plant: Indian Point Energy Center Year: 2024 Page 66 of 122 Annual Radiological Environmental Operating Report INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma 10/15/24 10/15/24 10/15/24
DATE GAMMA Be-7 863 +/- 246
< 221 621 +/- 228 1150 +/- 266 1118 +/- 370 1249 +/- 380 K-40 3962 +/- 550 2609 +/- 519 5860 +/- 639 3590 +/- 577 3983 +/- 622 4729 +/- 721 Mn-54
< 24
< 25
< 26
< 27
< 32
< 30 Co-58
< 25
< 26
< 28
< 26
< 27
< 33 Fe-59
< 59
< 55
< 62
< 52
< 57
< 80 Co-60
< 24
< 28
< 32
< 27
< 31
< 38 Zn-65
< 57
< 60
< 65
< 61
< 60
< 78 Nb-95
< 24
< 26
< 28
< 27
< 28
< 34 Zr-95
< 44
< 36
< 50
< 46
< 54
< 53 Ru-103
< 25
< 24
< 25
< 22
< 29
< 25 Ru-106
< 223
< 183
< 238
< 214
< 281
< 306 I-131
< 35
< 24
< 30
< 22
< 37
< 35 Cs-134
< 31
< 22
< 28
< 27
< 29
< 36 Cs-137
< 28
< 30
< 32
< 22
< 33
< 30 Ba-140
< 117
< 100
< 91
< 79
< 120
< 118 La-140
< 27
< 27
< 26
< 30
< 27
< 35 Ce-141
< 43
< 33
< 35
< 37
< 47
< 42 Ce-144
< 167
< 149
< 130
< 134
< 184
< 165 Ra-226 962 +/- 588
< 522
< 523
< 603
< 813
< 650 Th-228
< 55
< 45
< 46
< 43
< 61 90 +/- 44 Annual Radiological Environmental Operating Report 06/18/24 06/18/24 06/18/24 INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma Met Tower 95 05/21/24 05/21/24 Plant: Indian Point Energy Center Year: 2024 05/20/24 Page 67 of 122
DATE GAMMA Be-7 3309 +/- 408 432 +/- 169 2325 +/- 385 3575 +/- 414 3444 +/- 440 4453 +/- 526 K-40 4485 +/- 662 3736 +/- 529 6852 +/- 767 3806 +/- 605 5027 +/- 684 7422 +/- 966 Mn-54
< 29
< 17
< 32
< 29
< 29
< 44 Co-58
< 25
< 23
< 33
< 28
< 29
< 41 Fe-59
< 65
< 45
< 70
< 56
< 64
< 79 Co-60
< 34
< 25
< 34
< 30
< 44
< 56 Zn-65
< 88
< 40
< 72
< 70
< 73
< 108 Nb-95
< 31
< 23
< 32
< 27
< 28
< 47 Zr-95
< 59
< 38
< 58
< 46
< 44
< 73 Ru-103
< 26
< 21
< 31
< 24
< 26
< 39 Ru-106
< 261
< 168
< 279
< 262
< 299
< 401 I-131
< 36
< 31
< 33
< 33
< 35
< 46 Cs-134
< 30
< 22
< 32
< 33
< 31
< 48 Cs-137
< 33
< 20
< 34
< 29
< 34
< 38 Ba-140
< 117
< 74
< 97
< 92
< 105
< 161 La-140
< 40
< 18
< 35
< 27
< 24
< 37 Ce-141
< 41
< 27
< 45
< 51
< 51
< 58 Ce-144
< 158
< 110
< 191
< 214
< 218
< 269 Ra-226
< 655
< 376
< 699
< 821
< 825
< 1090 Th-228 71 +/- 40
< 31
< 53
< 64
< 59
< 80 Plant: Indian Point Energy Center Year: 2024 Page 68 of 122 Annual Radiological Environmental Operating Report 08/20/24 07/24/24 07/24/24 08/06/24 Met Tower 95 INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma 08/20/24 08/20/24
DATE GAMMA Be-7 1205 +/- 302 2524 +/- 301 1604 +/- 400 2491 +/- 249 2707 +/- 221 1726 +/- 266 K-40 4353 +/- 673 3691 +/- 545 3305 +/- 566 1013 +/- 281 4116 +/- 352 2103 +/- 412 Mn-54
< 27
< 33
< 33
< 18
< 16
< 24 Co-58
< 32
< 30
< 29
< 17
< 14
< 24 Fe-59
< 79
< 54
< 69
< 40
< 31
< 51 Co-60
< 35
< 36
< 38
< 27
< 15
< 29 Zn-65
< 84
< 73
< 75
< 37
< 39
< 56 Nb-95
< 27
< 26
< 33
< 18
< 16
< 23 Zr-95
< 49
< 46
< 57
< 31
< 26
< 43 Ru-103
< 28
< 26
< 30
< 19
< 15
< 24 Ru-106
< 240
< 243
< 293
< 161
< 139
< 234 I-131
< 34
< 34
< 39
< 23
< 18
< 29 Cs-134
< 33
< 28
< 34
< 20
< 17
< 28 Cs-137
< 30
< 30
< 31
< 20
< 16
< 28 Ba-140
< 119
< 96
< 114
< 70
< 60
< 96 La-140
< 22
< 22
< 31
< 23
< 16
< 29 Ce-141
< 45
< 42
< 44
< 32
< 26
< 35 Ce-144
< 167
< 183
< 204
< 132
< 106
< 149 Ra-226
< 683
< 660
< 707
< 486
< 427
< 510 Th-228
< 61
< 63
< 58
< 35
< 34
< 41 Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center Year: 2024 Page 69 of 122 09/17/24 09/17/24 09/17/24 INDIAN POINT ENERGY CENTER TABLE B-11 GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma 95 Met Tower 10/15/24 10/15/24 10/15/24
INDIAN POINT ENERGY CENTER TABLE B-12 RADIONUCLIDES IN RIVER WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Discharge Canal 10 DATE RADIOCHEMICAL H-3 (a)
< 194
< 189 GAMMA K-40
< 21
< 19
< 67
< 48
< 27
< 35 Mn-54
< 2
< 2
< 4
< 3
< 2
< 2 Co-58
< 2
< 3
< 5
< 3
< 2
< 2 Fe-59
< 5
< 5
< 9
< 7
< 4
< 5 Co-60
< 2
< 2
< 4
< 3
< 2
< 2 Zn-65
< 5
< 5
< 8
< 6
< 3
< 4 Nb-95
< 2
< 3
< 5
< 3
< 2
< 2 Zr-95
< 4
< 5
< 7
< 6
< 3
< 4 Ru-103
< 3
< 3
< 5
< 4
< 2
< 2 Ru-106
< 20
< 24
< 36
< 25
< 15
< 19 I-131
< 10
< 9
< 14
< 13
< 11
< 7 Cs-134
< 3
< 3
< 4
< 3
< 2
< 2 Cs-137
< 2
< 3
< 4
< 3
< 2
< 2 Ba-140
< 20
< 20
< 30
< 25
< 18
< 14 La-140
< 6
< 6
< 12
< 9
< 6
< 5 Ce-141
< 5
< 6
< 9
< 6
< 4
< 4 Ce-144
< 15
< 21
< 31
< 21
< 11
< 12 Ra-226
< 46
< 73
< 108
< 73
< 34
< 46 Ac-228
< 9
< 9
< 15
< 10
< 6
< 8 Th-228
< 4
< 5
< 8
< 5
< 3
< 4 (a) Quarterly Composite Plant: Indian Point Energy Center Year: 2024 Page 70 of 121 Annual Radiological Environmental Operating Report 01/30/24 02/27/24 03/26/24 04/30/24 06/25/24 05/29/24
INDIAN POINT ENERGY CENTER TABLE B-12 RADIONUCLIDES IN RIVER WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Discharge Canal 10 DATE RADIOCHEMICAL H-3 (a)
< 190
< 182 GAMMA K-40 59 +/- 28
< 40 52 +/- 23 35 +/- 22 61 +/- 30
< 19 Mn-54
< 2
< 2
< 2
< 2
< 2
< 2 Co-58
< 3
< 2
< 2
< 2
< 2
< 2 Fe-59
< 5
< 5
< 4
< 4
< 5
< 5 Co-60
< 2
< 2
< 2
< 2
< 2
< 2 Zn-65
< 4
< 4
< 4
< 3
< 4
< 4 Nb-95
< 2
< 2
< 2
< 2
< 3
< 2 Zr-95
< 4
< 4
< 3
< 3
< 4
< 4 Ru-103
< 3
< 2
< 2
< 2
< 3
< 3 Ru-106
< 18
< 18
< 15
< 15
< 17
< 17 I-131
< 10
< 7
< 6
< 8
< 11
< 10 Cs-134
< 2
< 2
< 2
< 2
< 2
< 2 Cs-137
< 2
< 2
< 2
< 2
< 2
< 2 Ba-140
< 18
< 15
< 13
< 15
< 20
< 18 La-140
< 6
< 5
< 5
< 5
< 6
< 6 Ce-141
< 5
< 5
< 4
< 4
< 4
< 4 Ce-144
< 15
< 16
< 12
< 12
< 13
< 13 Ra-226
< 45
< 57
< 39
< 43
< 42
< 39 Ac-228
< 8
< 8
< 7
< 6
< 8
< 7 Th-228
< 3
< 4
< 4
< 3
< 4
< 3 (a) Quarterly Composite Plant: Indian Point Energy Center Year: 2024 Page 71 of 121 12/31/24 07/30/24 08/27/24 09/24/24 10/29/24 11/26/24 Annual Radiological Environmental Operating Report
INDIAN POINT ENERGY CENTER TABLE B-12 RADIONUCLIDES IN RIVER WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Roseton 23*
DATE RADIOCHEMICAL H-3 (a)
< 195
< 190 GAMMA K-40
< 48
< 36
< 34
< 40
< 37
< 17 Mn-54
< 2
< 2
< 3
< 2
< 2
< 2 Co-58
< 3
< 2
< 4
< 2
< 2
< 2 Fe-59
< 6
< 5
< 8
< 5
< 5
< 5 Co-60
< 2
< 2
< 4
< 2
< 2
< 2 Zn-65
< 5
< 4
< 7
< 5
< 4
< 4 Nb-95
< 3
< 2
< 4
< 3
< 2
< 2 Zr-95
< 5
< 4
< 7
< 5
< 4
< 4 Ru-103
< 3
< 2
< 4
< 3
< 2
< 3 Ru-106
< 22
< 18
< 31
< 18
< 18
< 18 I-131
< 10
< 7
< 14
< 12
< 8
< 8 Cs-134
< 3
< 2
< 3
< 3
< 2
< 2 Cs-137
< 2
< 2
< 3
< 2
< 2
< 2 Ba-140
< 20
< 15
< 23
< 21
< 16
< 15 La-140
< 7
< 6
< 9
< 7
< 5
< 5 Ce-141
< 5
< 4
< 7
< 5
< 4
< 5 Ce-144
< 15
< 13
< 23
< 17
< 14
< 16 Ra-226
< 54
< 46
< 88
< 63
< 54
< 57 Ac-228
< 10
< 8
< 14
< 9
< 7
< 8 Th-228
< 4
< 3
< 6
< 4
< 4
< 4
- Control Location (a) Quarterly Composite Plant: Indian Point Energy Center Year: 2024 Page 72 of 122 Annual Radiological Environmental Operating Report 06/24/24 01/29/24 02/26/24 03/25/24 04/29/24 05/28/24
INDIAN POINT ENERGY CENTER TABLE B-12 RADIONUCLIDES IN RIVER WATER SAMPLES - 2024 pCi/L +/- 2 Sigma Roseton 23*
DATE RADIOCHEMICAL H-3 (a)
< 186
< 177 GAMMA K-40
< 13
< 19
< 13
< 11
< 19
< 16 Mn-54
< 1
< 2
< 2
< 1
< 2
< 2 Co-58
< 1
< 2
< 2
< 1
< 2
< 2 Fe-59
< 3
< 4
< 4
< 3
< 5
< 4 Co-60
< 1
< 2
< 2
< 1
< 2
< 2 Zn-65
< 3
< 4
< 3
< 2
< 4
< 4 Nb-95
< 1
< 2
< 2
< 1
< 2
< 2 Zr-95
< 3
< 4
< 3
< 2
< 4
< 3 Ru-103
< 2
< 2
< 2
< 1
< 3
< 2 Ru-106
< 11
< 17
< 16
< 10
< 18
< 14 I-131
< 7
< 7
< 7
< 6
< 12
< 10 Cs-134
< 1
< 2
< 2
< 1
< 2
< 2 Cs-137
< 1
< 2
< 2
< 1
< 2
< 2 Ba-140
< 11
< 15
< 13
< 10
< 20
< 18 La-140
< 5
< 4
< 4
< 4
< 6
< 6 Ce-141
< 3
< 4
< 4
< 3
< 5
< 4 Ce-144
< 9
< 11
< 12
< 8
< 16
< 12 Ra-226
< 28
< 37
< 37
< 31
< 55
< 33 Ac-228
< 5
< 7
< 6
< 4
< 8
< 7 Th-228
< 2
< 3
< 3
< 3
< 4
< 3
- Control Location (a) Quarterly Composite 10/28/24 11/25/24 12/30/24 Plant: Indian Point Energy Center Year: 2024 Page 73 of 122 Annual Radiological Environmental Operating Report 07/29/24 08/26/24 09/23/24
INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2024 pCi/kg dry +/- 2 Sigma Discharge Canal Verplanck Area 10 17 DATE GAMMA Be-7
< 1024
< 735
< 880
< 631 K-40 22420 +/- 2544 16980 +/- 2074 20000 +/- 2049 14630 +/- 2074 Mn-54
< 115
< 80
< 111
< 85 Co-58
< 95
< 94
< 99
< 78 Fe-59
< 207
< 185
< 252
< 197 Co-60
< 107
< 98
< 102
< 99 Zn-65
< 241
< 207
< 220
< 199 Nb-95
< 94
< 95
< 119
< 88 Zr-95
< 205
< 162
< 201
< 155 Ru-103
< 73
< 68
< 99
< 73 Ru-106
< 971
< 717
< 892
< 737 I-131
< 112
< 86
< 107
< 90 Cs-134
< 125
< 104
< 144
< 105 Cs-137
< 100 199 +/- 95
< 142
< 129 Ba-140
< 312
< 320
< 356
< 299 Ce-141
< 116
< 115
< 132
< 109 Ce-144
< 522
< 411
< 512
< 423 Ra-226
< 1840
< 1576 4064
+/- 1896
< 1927 Th-228 1110 +/- 198 656 +/- 174 1070 +/- 177 898 +/- 175 Annual Radiological Environmental Operating Report 06/03/24 08/21/24 06/03/24 08/21/24 Plant: Indian Point Energy Center Year: 2024 Page 74 of 122
INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2024 pCi/kg dry +/- 2 Sigma Lent's Cove Cold Spring 28 84*
DATE GAMMA Be-7
< 1113
< 616 2396
+/- 860
< 602 K-40 21610 +/- 2586 17900 +/- 1962 20280 +/- 2859 20500 +/- 1898 Mn-54
< 87
< 75
< 113
< 78 Co-58
< 120
< 70
< 111
< 65 Fe-59
< 237
< 154
< 229
< 163 Co-60
< 118
< 102
< 123
< 68 Zn-65
< 259
< 148
< 261
< 156 Nb-95
< 112
< 87
< 135
< 71 Zr-95
< 186
< 107
< 228
< 122 Ru-103
< 97
< 64
< 110
< 68 Ru-106
< 1090
< 583
< 877
< 651 I-131
< 120
< 71
< 112
< 77 Cs-134
< 142
< 99
< 139
< 94 Cs-137
< 167
< 124
< 165 155 +/- 74 Ba-140
< 391
< 297
< 454
< 253 Ce-141
< 138
< 97
< 142
< 87 Ce-144
< 573
< 414
< 636
< 361 Ra-226 2996 +/- 1730
< 1932
< 3015 3160 +/- 1499 Th-228 1020 +/- 186 841 +/- 146 838 +/- 219 868 +/- 141
- Control Location Annual Radiological Environmental Operating Report 06/03/24 06/03/24 08/21/24 08/21/24 Plant: Indian Point Energy Center Year: 2024 Page 75 of 122
INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2024 pCi/kg dry +/- 2 Sigma Verplanck Area Lent's Cove 17 28 DATE RADIOCHEMICAL Sr-90
< 43
< 44
< 44
< 45 GAMMA Be-7
< 612
< 617
< 661
< 716 K-40 13020 +/- 1526 12600 +/- 1370 14680 +/- 1758 9159 +/- 1506 Mn-54
< 69
< 59
< 85
< 74 Co-58
< 64
< 56
< 73
< 72 Fe-59
< 103
< 137
< 166
< 151 Co-60
< 65
< 51
< 85
< 84 Zn-65
< 136
< 118
< 192
< 167 Nb-95
< 64
< 66
< 85
< 97 Zr-95
< 109
< 99
< 114
< 123 Ru-103
< 58
< 51
< 76
< 63 Ru-106
< 497
< 509
< 741
< 619 I-131
< 54
< 54
< 89
< 84 Cs-134
< 76
< 67
< 107
< 85 Cs-137
< 79
< 71
< 123
< 87 Ba-140
< 241
< 192
< 279
< 247 La-140
< 35
< 71
< 100
< 89 Ce-141
< 86
< 81
< 97
< 98 Ce-144
< 313
< 300
< 418
< 393 Ra-226
< 1488
< 1379
< 1579
< 1725 Ac-228
< 434
< 373
< 633
< 337 Th-228 410 +/- 111 365 +/- 131 1142 +/- 138 422 +/- 91 Plant: Indian Point Energy Center Year: 2024 Page 76 of 122 Annual Radiological Environmental Operating Report 06/03/24 09/04/24 06/03/24 09/04/24
INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2024 pCi/kg dry +/- 2 Sigma Manitou Inlet White Beach 50*
53 DATE RADIOCHEMICAL Sr-90
< 38
< 43
< 37
< 39 GAMMA Be-7
< 559
< 651
< 534
< 592 K-40 11790 +/- 1647 13210 +/- 1566 24100 +/- 1911 9965 +/- 1459 Mn-54
< 70
< 74
< 77
< 56 Co-58
< 75
< 64
< 64
< 62 Fe-59
< 135
< 175
< 157
< 154 Co-60
< 77
< 95
< 85
< 73 Zn-65
< 163
< 172
< 188
< 182 Nb-95
< 73
< 94
< 70
< 74 Zr-95
< 132
< 130
< 118
< 121 Ru-103
< 67
< 80
< 68
< 56 Ru-106
< 604
< 660
< 630
< 561 I-131
< 64
< 91
< 87
< 75 Cs-134
< 100
< 101
< 74
< 76 Cs-137
< 81
< 93
< 77
< 80 Ba-140
< 258
< 288
< 255
< 227 La-140
< 89
< 89
< 63
< 104 Ce-141
< 88
< 116
< 104
< 79 Ce-144
< 343
< 501
< 414
< 291 Ra-226
< 1357
< 2099
< 1742
< 1260 Ac-228 1066 +/- 207
< 483
< 432
< 357 Th-228 523 +/- 112 517 +/- 119 1023 +/- 170 312 +/- 89
- Control Location Plant: Indian Point Energy Center Year: 2024 Page 77 of 122 06/03/24 09/04/24 06/03/24 09/03/24 Annual Radiological Environmental Operating Report
INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2024 pCi/kg dry +/- 2 Sigma Cold Spring 84*
DATE RADIOCHEMICAL Sr-90
< 38
< 39 GAMMA Be-7
< 419
< 806 K-40 7444 +/- 1101 15020 +/- 1784 Mn-54
< 53
< 85 Co-58
< 34
< 76 Fe-59
< 94
< 152 Co-60
< 38
< 80 Zn-65
< 83
< 247 Nb-95
< 45
< 87 Zr-95
< 72
< 121 Ru-103
< 35
< 71 Ru-106
< 421
< 716 I-131
< 47
< 87 Cs-134
< 54
< 103 Cs-137
< 52
< 92 Ba-140
< 163
< 300 La-140
< 32
< 107 Ce-141
< 60
< 97 Ce-144
< 238
< 378 Ra-226
< 1018
< 1618 Ac-228
< 220
< 512 Th-228
< 91 450 +/- 117
- Control Location 09/04/24 06/03/24 Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center Year: 2024 Page 78 of 122
INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma DATE Be-7
< 320 565 +/- 234 K-40 2591 +/- 587 2309 +/- 407 Mn-54
< 25
< 18 Co-58
< 27
< 19 Fe-59
< 54
< 37 Co-60
< 39
< 24 Zn-65
< 70
< 51 Nb-95
< 33
< 17 Zr-95
< 54
< 34 Ru-103
< 32
< 20 Ru-106
< 317
< 184 I-131
< 38
< 19 Cs-134
< 36
< 20 Cs-137
< 41
< 17 Ba-140
< 114
< 76 La-140
< 30
< 21 Ce-141
< 52
< 29 Ce-144
< 193
< 120 Ra-226
< 733
< 543 Ac-228
< 118
< 92 Th-228
< 59
< 38 Plant: Indian Point Energy Center Year: 2024 Page 79 of 122 Annual Radiological Environmental Operating Report Peltandra Virginica Lent's Cove 28 08/20/24 Peltandra Virginica 06/03/24
INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma DATE Be-7 (a)
(a)
K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 I-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 (a) Refer to deviation table B-1b Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center Year: 2024 Page 80 of 122 06/03/24 08/20/24 Verplanck Area 17
INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2024 pCi/kg wet +/- 2 Sigma DATE Be-7
< 192 488 +/- 248 K-40 3177 +/- 456 2994 +/- 542 Mn-54
< 23
< 23 Co-58
< 20
< 24 Fe-59
< 38
< 56 Co-60
< 25
< 27 Zn-65
< 48
< 68 Nb-95
< 19
< 29 Zr-95
< 36
< 39 Ru-103
< 19
< 21 Ru-106
< 148
< 239 I-131
< 22
< 29 Cs-134
< 24
< 28 Cs-137
< 27
< 25 Ba-140
< 89
< 89 La-140
< 24
< 22 Ce-141
< 31
< 30 Ce-144
< 134
< 144 Ra-226
< 515
< 514 Ac-228
< 105
< 124 Th-228
< 42
< 46
- Control Location Plant: Indian Point Energy Center Year: 2024 Page 81 of 122 08/20/24 84*
Peltandra Virginica Peltandra Virginica Cold Spring 06/03/04 Annual Radiological Environmental Operating Report
INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN FISH / INVERTEBRATES - 2024 pCi/kg wet +/- 2 Sigma DATE RADIOCHEMICAL Ni-63
< 72
< 50
< 60
< 67
< 69 (a)
< 3
< 4
< 4
< 4
< 4 GAMMA Be-7
< 699
< 381
< 459
< 641
< 505 K-40 3233 +/- 1563 2975 +/- 942 3518 +/- 842 3359 +/- 819 3571 +/- 899 Mn-54
< 94
< 67
< 61
< 77
< 52 Co-58
< 77
< 72
< 55
< 78
< 58 Fe-59
< 162
< 132
< 130
< 162
< 123 Co-60
< 108
< 74
< 62
< 75
< 66 Zn-65
< 209
< 113
< 122
< 154
< 146 Nb-95
< 95
< 84
< 57
< 81
< 68 Zr-95
< 135
< 107
< 90
< 132
< 121 Ru-103
< 95
< 70
< 61
< 72
< 67 Ru-106
< 815
< 509
< 476
< 644
< 536 I-131
< 154
< 105
< 79
< 111
< 101 Cs-134
< 103
< 86
< 54
< 83
< 68 Cs-137
< 101
< 56
< 51
< 69
< 63 Ba-140
< 431
< 288
< 243
< 319
< 265 La-140
< 84
< 64
< 75
< 112
< 94 Ce-141
< 120
< 85
< 66
< 83
< 82 Ce-144
< 496
< 323
< 241
< 363
< 336 Ra-226
< 1845
< 1390
< 1173
< 1529
< 1230 Th-228
< 153
< 82
< 105
< 116
< 107 (a) Refer to deviation table B-1b.
Plant: Indian Point Energy Center Year: 2024 Page 82 of 122 Sunfish Catfish Striped Bass Eel Perch 05/28/24 05/28/24 05/29/24 05/29/24 05/29/24 Annual Radiological Environmental Operating Report Downstream 107 05/29/24 Blue Crab
INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN FISH / INVERTEBRATES - 2024 pCi/kg wet +/- 2 Sigma 107 DATE RADIOCHEMICAL Ni-63
< 57
< 53
< 44
< 85 (a)
(a)
< 5
< 3
< 3
< 3 GAMMA Be-7
< 589
< 684
< 671
< 433 K-40 3104 +/- 1003 1886 +/- 830 2926 +/- 1041 2447 +/- 668 Mn-54
< 75
< 75
< 63
< 43 Co-58
< 90
< 104
< 76
< 57 Fe-59
< 200
< 185
< 174
< 105 Co-60
< 84
< 90
< 70
< 64 Zn-65
< 203
< 155
< 154
< 105 Nb-95
< 85
< 103
< 69
< 57 Zr-95
< 145
< 120
< 135
< 87 Ru-103
< 80
< 84
< 77
< 62 Ru-106
< 787
< 724
< 651
< 536 I-131
< 129
< 134
< 118
< 84 Cs-134
< 104
< 111
< 76
< 48 Cs-137
< 74
< 95
< 82
< 50 Ba-140
< 359
< 315
< 369
< 227 La-140
< 110
< 105
< 144
< 85 Ce-141
< 94
< 114
< 104
< 72 Ce-144
< 343
< 393
< 350
< 273 Ra-226
< 1399
< 1714
< 1395
< 968 Th-228
< 130
< 140
< 131
< 86 (a) Refer to deviation table B-1b Plant: Indian Point Energy Center Year: 2024 Page 83 of 122 Downstream Catfish Sunfish Striped Bass Annual Radiological Environmental Operating Report 09/18/24 09/18/24 Eel Perch Blue Crab 09/18/24 09/18/24 09/18/24 09/19/24
INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN FISH / INVERTEBRATES - 2024 pCi/kg wet +/- 2 Sigma 23*
DATE RADIOCHEMICAL Ni-63
< 81
< 40
< 59
< 62
< 75 (a)
< 4
< 4
< 4
< 4
< 0.3 GAMMA Be-7
< 479
< 607
< 354
< 490
< 439 K-40 2927 +/- 1073 4381 +/- 1191 2531 +/- 930 2312 +/- 820 2985 +/- 932 Mn-54
< 61
< 55
< 46
< 62
< 60 Co-58
< 60
< 68
< 46
< 59
< 45 Fe-59
< 96
< 149
< 93
< 148
< 94 Co-60
< 43
< 68
< 59
< 63
< 65 Zn-65
< 136
< 139
< 117
< 152
< 96 Nb-95
< 56
< 73
< 59
< 72
< 54 Zr-95
< 77
< 104
< 88
< 114
< 96 Ru-103
< 55
< 65
< 44
< 64
< 51 Ru-106
< 491
< 632
< 469
< 562
< 440 I-131
< 70
< 81
< 71
< 100
< 77 Cs-134
< 65
< 70
< 58
< 76
< 66 Cs-137
< 66
< 66
< 45
< 78
< 61 Ba-140
< 257
< 279
< 203
< 320
< 233 La-140
< 105
< 96
< 81
< 104
< 73 Ce-141
< 68
< 86
< 58
< 87
< 68 Ce-144
< 264
< 326
< 236
< 353
< 256 Ra-226
< 1167
< 1228
< 1001
< 1365
< 1011 Th-228
< 97
< 116
< 83
< 112
< 92
- Control Location (a) Refer to deviation table B-1b Plant: Indian Point Energy Center Year: 2024 Page 84 of 122 Blue Crab Perch Sunfish 05/29/24 05/29/24 05/29/24 05/29/24 05/29/24 05/29/24 Roseton Annual Radiological Environmental Operating Report Striped Bass Catfish Eel
INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN FISH / INVERTEBRATES - 2024 pCi/kg wet +/- 2 Sigma 23*
DATE RADIOCHEMICAL Ni-63
< 53
< 63
< 41
< 66
< 32 (a)
< 4
< 3
< 4
< 4
< 3 GAMMA Be-7
< 752
< 577
< 352
< 467
< 684 K-40 1935 +/- 1145 2610 +/- 1285 2193 +/- 836 2739 +/- 911
< 732 Mn-54
< 93
< 77
< 54
< 49
< 70 Co-58
< 87
< 72
< 49
< 46
< 68 Fe-59
< 161
< 161
< 128
< 137
< 180 Co-60
< 107
< 75
< 55
< 52
< 59 Zn-65
< 142
< 172
< 134
< 115
< 183 Nb-95
< 92
< 70
< 65
< 59
< 90 Zr-95
< 166
< 116
< 97
< 95
< 152 Ru-103
< 93
< 85
< 51
< 64
< 79 Ru-106
< 883
< 681
< 563
< 576
< 644 I-131
< 138
< 136
< 98
< 115
< 119 Cs-134
< 99
< 92
< 67
< 59
< 73 Cs-137
< 84
< 78
< 44
< 55
< 83 Ba-140
< 452
< 347
< 290
< 297
< 346 La-140
< 134
< 74
< 136
< 95
< 105 Ce-141
< 130
< 112
< 63
< 96
< 88 Ce-144
< 542
< 386
< 262
< 338
< 377 Ra-226
< 1902
< 1772
< 1185
< 1497
< 1424 Th-228
< 153
< 149
< 97
< 115
< 123
- Control Location (a) Refer to deviation table B-1b Striped Bass 09/19/24 09/18/24 Blue Crab Roseton Sunfish Catfish Eel Perch 09/18/24 09/18/24 09/18/24 09/18/24 Plant: Indian Point Energy Center Year: 2024 Page 85 of 122 Annual Radiological Environmental Operating Report
INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN FISH / INVERTEBRATES - 2024 pCi/kg wet +/- 2 Sigma DATE RADIOCHEMICAL Ni-63
< 84
< 79
< 90
< 92
< 98 (a)
< 2
< 4
< 4
< 3
< 4 GAMMA Be-7
< 624
< 729
< 538
< 560
< 405 K-40 3636 +/- 1253 3545 +/- 1032 3303 +/- 971 2475 +/- 1223 3020 +/- 935 Mn-54
< 78
< 78
< 75
< 48
< 46 Co-58
< 94
< 91
< 71
< 57
< 46 Fe-59
< 161
< 180
< 126
< 131
< 84 Co-60
< 71
< 91
< 69
< 76
< 61 Zn-65
< 168
< 197
< 131
< 91
< 106 Nb-95
< 80
< 91
< 57
< 65
< 42 Zr-95
< 136
< 159
< 118
< 106
< 86 Ru-103
< 84
< 92
< 63
< 62
< 54 Ru-106
< 750
< 908
< 596
< 502
< 366 I-131
< 116
< 136
< 98
< 107
< 75 Cs-134
< 80
< 97
< 84
< 72
< 49 Cs-137
< 76
< 85
< 84
< 59
< 51 Ba-140
< 324
< 380
< 288
< 292
< 227 La-140
< 96
< 141
< 92
< 102
< 63 Ce-141
< 121
< 114
< 89
< 98
< 59 Ce-144
< 446
< 425
< 310
< 362
< 250 Ra-226
< 1888
< 1840
< 1400
< 1617
< 1150 Th-228
< 150
< 146
< 116
< 114
< 85 (a) Refer to deviation table B-1b Eel Year: 2024 05/29/24 05/29/24 Blue Crab Annual Radiological Environmental Operating Report Page 86 of 122 Plant: Indian Point Energy Center Downstream 25 Sunfish Catfish Striped Bass Perch 05/29/24 05/29/24 05/29/24 05/29/24
INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN FISH / INVERTEBRATES - 2024 pCi/kg wet +/- 2 Sigma 25 DATE RADIOCHEMICAL Ni-63
< 52
< 68
< 56
< 47
< 38 (a)
< 4
< 4
< 5
< 4
< 3 GAMMA Be-7
< 618
< 518
< 624
< 408
< 517 K-40 1861 +/- 923 2589 +/- 891 1811 +/- 809 2512 +/- 651 2436 +/- 823 Mn-54
< 81
< 62
< 62
< 39
< 58 Co-58
< 68
< 76
< 69
< 50
< 50 Fe-59
< 161
< 153
< 140
< 115
< 137 Co-60
< 79
< 55
< 66
< 69
< 79 Zn-65
< 165
< 172
< 130
< 105
< 120 Nb-95
< 76
< 68
< 67
< 58
< 54 Zr-95
< 131
< 103
< 117
< 80
< 107 Ru-103
< 65
< 60
< 78
< 51
< 63 Ru-106
< 664
< 510
< 716
< 431
< 539 I-131
< 103
< 106
< 139
< 89
< 100 Cs-134
< 81
< 60
< 75
< 54
< 68 Cs-137
< 76
< 71
< 70
< 46
< 64 Ba-140
< 337
< 280
< 374
< 248
< 258 La-140
< 113
< 77
< 79
< 90
< 83 Ce-141
< 81
< 79
< 113
< 65
< 91 Ce-144
< 366
< 291
< 326
< 246
< 367 Ra-226
< 1322
< 1302
< 1655
< 930
< 1288 Th-228
< 103
< 97
< 132
< 71
< 100 (a) Refer to deviation table B1-b Striped Bass Catfish Eel 09/18/24 09/18/24 09/18/24 09/18/24 Annual Radiological Environmental Operating Report 09/18/24 09/19/24 Perch Sunfish Blue Crab Year: 2024 Page 87 of 122 Downstream Plant: Indian Point Energy Center
Plant: Indian Point Energy Center Year: 2024 Page 88 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE B-17 LAND USE CENSUS - RESIDENCE AND MILCH ANIMAL RESULTS 2024 The 2024 land use census indicated there were no new residences that were closer in proximity to IPEC.
IPEC maintains a complete nearest residence survey with updated distances.
No milch animals were observed during this reporting period within the 5-mile zone. There are no animals producing milk for human consumption within five miles of Indian Point.
Plant: Indian Point Energy Center Year: 2024 Page 89 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE B-18 LAND USE CENSUS 2024 UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES Sector Compass Point Distance to site Boundary from Unit 2 Plant Vent (meters)
Distance to site Boundary from Unit 3 Plant Vent (meters)
Distance to nearest resident, from Unit 1 superheater (meters)
Address of nearest resident, Last Census 1
N RIVER RIVER 1788 41 River Road Tomkins Cove 2
NNE RIVER RIVER 3111 Chateau Rive Apts. John St. Peekskill 3
NE 550 636 1907 211 Viewpoint Terrace, Peekskill 4
ENE 600 775 1478 1018 Lower South St. Peekskill 5
E 662 785 1371 1103 Lower South St. Peekskill 6
ESE 569 622 715 461 Broadway Buchanan 7
SE 553 564 1168 223 First St. Buchanan 8
SSE 569 551 1240 5 Pheasant's Run Buchanan 9
S 700 566 1133 320 Broadway Verplanck 10 SSW 755 480 1574 240 Eleventh St. Verplanck 11 SW 544 350 3016 8 Spring St. Tomkins Cove 12 WSW RIVER RIVER 2170 9 West Shore Dr. Tomkins Cove 13 W
RIVER RIVER 1919 712 Rt. 9W Tomkins Cove 14 WNW RIVER RIVER 1752 770 Rt. 9W Tomkins Cove 15 NW RIVER RIVER 1693 807 Rt. 9W Tomkins Cove 16 NNW RIVER RIVER 1609 4 River Rd. Tomkins Cove
Plant: Indian Point Energy Center Year: 2024 Page 90 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION 6.0 HISTORICAL TRENDS
Plant: Indian Point Energy Center Year: 2024 Page 91 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT HISTORICAL TRENDS The past ten years of historical data for various radionuclides and media are presented both in tabular form and graphical form to facilitate the comparison of 2024 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.
Averaging the positive values in these tables can result in a biased high value, especially, when the radionuclide is detected in only one or two quarters for the year.
Year Inner Ring Outer Ring Control Location 2014 13.7 13.6 14.2 2015 13.8 14.0 14.3 2016 14.3 14.2 15.6 2017 14.3 14.7 15.6 2018 14.0 14.4 15.3 2019 13.7 13.9 15.0 2020 14.0 14.2 15.4 2021 13.2 13.3 14.1 2022 13.5 13.8 14.9 2023 13.9 14.1 15.2 2024 13.9 14.3 15.4 Historical Average 2014-2023 13.8 14.0 15.0 Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report Page 92 of 122 Year: 2024 Average Quarterly Dose (mR/Quarter)
TABLE C-1 DIRECT RADIATION, ANNUAL
SUMMARY
2014-2024
Page 93 of 122 Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report Figure C-1 DIRECT RADIATION, ANNUAL
SUMMARY
2014-2024 Year: 2024 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 (Mean) mR / Quarter Inner Ring Outer Ring Control Location
Year: 2024 Gross Beta Cs-137 Year All Indicator Locations Control Location All Indicator Locations Control Location 2014 0.013 0.013
< Lc
< Lc 2015 0.016 0.015
< Lc
< Lc 2016 0.015 0.015
< Lc
< Lc 2017 0.013 0.012
< Lc
< Lc 2018 0.013 0.012
< Lc
< Lc 2019 0.012 0.012
< Lc
< Lc 2020 0.013 0.013
< Lc
< Lc 2021 0.014 0.014
< Lc
< Lc 2022 0.015 0.015
< Lc
< Lc 2023 0.015 0.015
< Lc
< Lc 2024 0.013 0.014
< Lc
< Lc Historical Average 2014-2023 0.014 0.014
< Lc
< Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
Page 94 of 122 Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center TABLE C-2 RADIONUCLIDES IN AIR 2014-2024 (pCi/m3)
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2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 95 of 122 Annual Radiological Environmental Operating Report Figure C-2 RADIONUCLIDES IN AIR - GROSS BETA 0
0.01 0.02 0.03 0.04 0.05 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 pCi/m3 All Indicator Locations Control Location
Year: 2024 Year Inlet Discharge Inlet Discharge 2014 224 253
< Lc
< Lc 2015 188 341
< Lc
< Lc 2016
< Lc 415
< Lc
< Lc 2017
< Lc 299
< Lc
< Lc 2018 236 266
< Lc
< Lc 2019 273 295
< Lc
< Lc 2020 (b)
< Lc 288
< Lc
< Lc 2021
< Lc 380
< Lc
< Lc 2022
< Lc 249
< Lc
< Lc 2023
< Lc
< Lc
< Lc
< Lc 2024
< Lc
< Lc
< Lc
< Lc Historical Average 2014-2023 230 310
< Lc
< Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
(b) Refer to REMP changes Table B-1c report year 2020, change in sample location.
Cs-137 Plant: Indian Point Energy Center Page 96 of 122 Annual Radiological Environmental Operating Report TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER-TRITIUM 2014-2024 (pCi/L)
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2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 97 of 122 Annual Radiological Environmental Operating Report Figure C-3 RADIONUCLIDES IN HUDSON RIVER WATER - TRITIUM 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2014 2015 2016 2017 2018 2019 2020 (b) 2021 2022 2023 2024 pCi/L Inlet (H-3)
Discharge (H-3)
Cs-137 2014
< Lc
< Lc 2015
< Lc
< Lc 2016
< Lc
< Lc 2017
< Lc
< Lc 2018
< Lc
< Lc 2019
< Lc
< Lc 2020
< Lc
< Lc 2021
< Lc
< Lc 2022
< Lc
< Lc 2023
< Lc
< Lc 2024
< Lc
< Lc Historical Average 2014-2023
< Lc
< Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
Page 98 of 122 Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report TABLE C-4 RADIONUCLIDES IN DRINKING WATER 2014-2024 (pCi/L)
2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 99 of 122 Annual Radiological Environmental Operating Report Figure C-4 RADIONUCLIDES IN DRINKING WATER 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 pCi/L NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEARS HISTORY
Cs-134 Cs-137 Year Indicator Control Indicator Control 2014
< Lc
< Lc 327
< Lc 2015
< Lc
< Lc 110
< Lc 2016
< Lc
< Lc
< Lc
< Lc 2017
< Lc
< Lc 151
< Lc 2018
< Lc
< Lc 129
< Lc 2019
< Lc
< Lc 104
< Lc 2020
< Lc
< Lc 96
< Lc 2021
< Lc
< Lc
< Lc
< Lc 2022
< Lc
< Lc
< Lc
< Lc 2023
< Lc
< Lc
< Lc
< Lc 2024
< Lc
< Lc
< Lc
< Lc Historical Average 2014-2023
< Lc
< Lc 153
< Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
Plant: Indian Point Energy Center Annual Radiological Environmental Operating Report TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 2014-2024 (pCi/Kg, dry)
Year: 2024 Page 100 of 122 I
I
2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 101 of 122 Annual Radiological Environmental Operating Report Figure C-5 RADIONUCLIDES IN SHORELINE SOIL 0
100 200 300 400 500 600 700 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 pCi/Kg, dry The picture can't be displayed.Indicator (Cs-134)
The picture can't be displayed.Control (Cs-134)
Indicator (Cs-137)
Control (Cs-137)
Year: 2024 Year Indicator Control 2014
< Lc
< Lc 2015
< Lc
< Lc 2016
< Lc
< Lc 2017
< Lc
< Lc 2018
< Lc
< Lc 2019
< Lc
< Lc 2020
< Lc
< Lc 2021
< Lc
< Lc 2022
< Lc
< Lc 2023
< Lc
< Lc 2024
< Lc
< Lc Historical Average 2014-2023
< Lc
< Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
Cs-137 Plant: Indian Point Energy Center Page 102 of 122 Annual Radiological Environmental Operating Report TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 2014-2024 (pCi/Kg, wet)
2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 103 of 122 Annual Radiological Environmental Operating Report Figure C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 0
20 40 60 80 100 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 pCi/Kg, wet Indicator (Cs-137)
Control (Cs-137)
NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEARS HISTORY
Year: 2024 Page 104 of 122 Year Indicator Control 2014
< Lc
< Lc 2015
< Lc
< Lc 2016
< Lc
< Lc 2017
< Lc
< Lc 2018
< Lc
< Lc 2019
< Lc
< Lc 2020
< Lc
< Lc 2021
< Lc
< Lc 2022
< Lc
< Lc 2023
< Lc
< Lc 2024
< Lc
< Lc Historical Average 2014-2023
< Lc
< Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
Annual Radiological Environmental Operating Report Plant: Indian Point Energy Center TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 2014-2024 (pCi/Kg, Wet)
2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 105 of 122 Annual Radiological Environmental Operating Report Figure C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 0
20 40 60 80 100 120 140 160 180 200 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 pCi/Kg, wet Indicator (Cs-137)
Control (Cs-137)
NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEARS HISTORY
Year: 2024 Year REMP*
EFFLUENT **
1Q 2021 483 4.95 2Q 2021 214 115 3Q 2021 442 737 4Q 2021
<170 174 1Q 2022
<182 0.21 2Q 2022
<182 0.37 3Q 2022 249 344 4Q 2022
<179 114 1Q 2023
<189 370 2Q 2023
<196 125 3Q 2023
<189 83.9 4Q 2023
<196 1.11 1Q 2024
<195 266 2Q 2024
<190 708 3Q 2024
<188 613 4Q 2024
<180 382 Four Year Average, by Quarter, 2021-2024 347 252
- Sample from mixing zone, expected to be less than average activity in the discharge canal.
- Based upon Effluent Report data, average activity in the discharge canal calculated from the total H-3 discharged divided by the total dilution volume for the quarter.
Plant: Indian Point Energy Center Page 106 of 122 Annual Radiological Environmental Operating Report TABLE C-8 RIVER WATER - Discharge Area - Tritium REMP vs. EFFLUENT (pCi/L)
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Year: 2024 Year Indicator Control 2014 327
< Lc 2015 876
< Lc 2016 224
< Lc 2017 350
< Lc 2018 741 198 2019 190 176 2020 167 207 2021 183 257 2022 255
< Lc 2023
< Lc
< Lc 2024 199 155 Historical Average 2014-2023 368 210 Critical Level (Lc) is less than the RETS required LLD.
<Lc indicates no positive values above sample critical level.
Cs-137 Plant: Indian Point Energy Center Page 107 of 122 Annual Radiological Environmental Operating Report TABLE C-9 RADIONUCLIDES IN BOTTOM SEDIMENT 2014-2024 (pCi/Kg, dry)
2014-2024 Plant: Indian Point Energy Center Year: 2024 Page 108 of 122 Annual Radiological Environmental Operating Report Figure C-9 RADIONUCLIDES IN BOTTOM SEDIMENT 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 pCi/Kg, dry Indicator Control
Plant: Indian Point Energy Center Year: 2024 Page 109 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION 7.0 INTERLABORATORY COMPARISON PROGRAM
Plant: Indian Point Energy Center Year: 2024 Page 110 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT INTERLABORATORY COMPARISON PROGRAM This section presents the results of the interlaboratory comparison program for the Teledyne Brown Engineering Environmental Services and Environmental Dosimetry Company.
7.1 Program Description - Teledyne Brown Engineering Environmental Services Comparison Programs The Teledyne Brown Engineering Environmental Services participates in several interlaboratory comparison programs. These programs include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in these interlaboratory comparison programs ensure that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, Teledyne Brown Engineering Environmental Services has engaged the following programs:
Eckert & Ziegler Analytics Environmental Radioactivity Cross Check Program Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP)
Environmental Resource Associates (ERA) Cross Check Program These programs supply sample media as blind samples (typically spikes), which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the Teledyne Brown Engineering Environmental Services using standard laboratory procedures. Each program issues a statistical summary report of the results. Teledyne Brown Engineering Environmental Services uses predetermined acceptance criteria methodology for evaluating its laboratory performance.
Teledyne Brown Engineering Environmental Services also analyzes laboratory blanks. The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples. The analysis of analytical blanks also provides information on the adequacy of background subtraction. Laboratory blank results are analyzed using control charts.
7.2 Acceptance Criteria Each sample result is evaluated to determine the accuracy and precision of the laboratorys analysis result. The sample evaluation method is discussed below.
7.2.1 Analytics Sample Results Evaluation Samples provided by Analytics are evaluated using what is specified as the NRC method.
This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).
Plant: Indian Point Energy Center Year: 2024 Page 111 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT An Environmental Laboratory analytical result is evaluated using the following calculation:
The value for the error resolution is calculated.
Error Resolution =
Reference Result_______
Reference Results Error (1 sigma)
Using the appropriate row under the Error Resolution column in Table D-2.1, a corresponding Ratio of Agreement interval is given for use in Tables D-3.1, D-3.2, and D-3.3 The value for the ratio is then calculated.
Ratio of agreement =
QC Result Reference Result If the value falls within the agreement interval, the result is acceptable.
TABLE D-2.1 Ratio of Agreement ERROR RESOLUTION RATIO OF AGREEMENT
< 4 No Comparison 4 to 7 0.5-2.0 8 to 15 0.6-1.66 16 to 50 0.75-1.33 51 to 200 0.8-1.25
>200 0.85-1.18 This acceptance test is generally referred to as the NRC method. The acceptance criteria are contained in Procedure EN-CY-102-01. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.
7.2.2 ERA and MAPEP Sample Result Evaluation Both these programs supply an acceptance range for evaluating the results.
7.3 Program Results Summary The Interlaboratory Comparison Program numerical results are summarized in the following tables.
Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)
Ratio of TBE to Analytics Result Evaluation (b)
March 2024 E14089 Milk Sr-89 pCi/L 79.6 78.2 1.02 A
Sr-90 pCi/L 12.6 11.9 1.06 A
E14090 Milk Ce-141 pCi/L 75.6 85.0 0.89 A
Co-58 pCi/L
-0.069 Not Measured Co-60 pCi/L 139 158 0.88 A
Cr-51 pCi/L 212 230 0.92 A
Cs-134 pCi/L 167 198 0.84 A
Cs-137 pCi/L 158 171 0.93 A
Fe-59 pCi/L 81.1 86.5 0.94 A
I-131 pCi/L 80.9 90.8 0.89 A
Mn-54 pCi/L 173 183 0.95 A
Zn-65 pCi/L 165 176 0.93 A
E14091 Charcoal I-131 pCi 90.1 90.3 1.00 A
E14092 AP Ce-141 pCi 68.1 67.5 1.01 A
Co-58 pCi 1.73 Not Measured Co-60 pCi 168 126 1.34 N(1)
Cr-51 pCi 182 183 0.99 A
Cs-134 pCi 157 157 1.00 A
Cs-137 pCi 132 136.0 0.97 A
Fe-59 pCi 70.3 68.6 1.02 A
Mn-54 pCi 144 145 0.99 A
Zn-65 pCi 125 140 0.89 A
E14093 Soil Ce-141 pCi/g 0.106 0.071 1.48 N(1)
Co-58 pCi/g
-0.005 Not Measured Co-60 pCi/g 0.121 0.133 0.91 A
Cr-51 pCi/g 0.198 0.194 1.02 A
Cs-134 pCi/g 0.206 0.166 1.24 W
Cs-137 pCi/g 0.207 0.209 0.99 A
Fe-59 pCi/g 0.063 0.073 0.87 A
Mn-54 pCi/g 0.140 0.153 0.91 A
Zn-65 pCi/g 0.149 0.148 1.01 A
E14094 AP Sr-89 pCi 83.9 90.6 0.93 A
Sr-90 pCi 11.7 13.8 0.85 A
Teledyne Brown Engineering Environmental Services TABLE D-3.1 Analytics Environmental Radioactivity Cross Check Program Plant: Indian Point Energy Center Year: 2024 Page 112 of 122 Annual Radiological Environmental Operating Report (Page 1 of 5)
Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)
Ratio of TBE to Analytics Result Evaluation (b)
September 2024 E14095 Milk Sr-89 pCi/L 88.0 92.3 0.95 A
Sr-90 pCi/L 12.4 15.2 0.82 A
E14096 Milk Ce-141 pCi/L 124 124 1.00 A
Co-58 pCi/L 154 150 1.03 A
Co-60 pCi/L 232 236 0.98 A
Cr-51 pCi/L 284 274 1.04 A
Cs-134 pCi/L 180.0 187 0.96 A
Cs-137 pCi/L 126 127 0.99 A
Fe-59 pCi/L 127.0 113 1.12 A
I-131 pCi/L 85.3 89.0 0.96 A
Mn-54 pCi/L 162 162 1.00 A
Zn-65 pCi/L 294 275 1.07 A
E14097 Charcoal I-131 pCi 98.8 92.6 1.07 A
E14098 AP Ce-141 pCi 82.0 76.7 1.07 A
Co-58 pCi 91.0 92.6 0.98 A
Co-60 pCi 180 146 1.23 W
Cr-51 pCi 208 170 1.22 W
Cs-134 pCi 116 116 1.00 A
Cs-137 pCi 83.1 78.9 1.05 A
Fe-59 pCi 75.6 70.2 1.08 A
Mn-54 pCi 101 100 1.01 A
Zn-65 pCi 167 170 0.98 A
E14099 Soil Ce-141 pCi/g 0.224 0.222 1.01 A
Co-58 pCi/g 0.249 0.268 0.93 A
Co-60 pCi/g 0.420 0.423 0.99 A
Cr-51 pCi/g 0.492 0.492 1.00 A
Cs-134 pCi/g 0.278 0.336 0.83 A
Cs-137 pCi/g 0.276 0.295 0.94 A
Fe-59 pCi/g 0.233 0.204 1.14 A
Mn-54 pCi/g 0.279 0.290 0.96 A
Zn-65 pCi/g 0.538 0.494 1.09 A
E14100 AP Sr-89 pCi 79.8 82.7 0.96 A
Sr-90 pCi 12.0 13.6 0.88 A
E14197 Liquid Gr-A (Am241) pCi/L 47.6 50.1 0.95 A
Gr-B (Cs137) pCi/L 248 270 0.92 A
(a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:
A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) See NCR 24-06 Teledyne Brown Engineering Environmental Services Plant: Indian Point Energy Center Year: 2024 Page 113 of 122 Annual Radiological Environmental Operating Report TABLE D-3.1 Analytics Environmental Radioactivity Cross Check Program (Page 2 of 5)
I I
Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)
Acceptance Range Evaluation (b)
February 2024 24-MaS50 Soil Fe-55 Bq/kg 297 650 455 - 845 N(3)
Ni-63 Bq/kg 1070 1530 1071 - 1989 N(4)
Tc-99 Bq/kg 325 336 235 - 437 A
Th-228 Bq/kg 34.6 48.8 34.2 - 63.4 W
Th-230 Bq/kg 49.7 54.0 38.0 - 70.0 A
Th-232 Bq/kg 36.4 45.1 31.6 - 58.6 A
24-MaSU50 Urine Cs-134 Bq/L 1.12 1.36 0.95-1.77 A
Cs-137 Bq/L 2.00 2.23 1.56-2.90 A
Co-57 Bq/L 1.06 1.26 0.88 - 1.64 A
Co-60 Bq/L 2.26 2.38 1.67 - 3.09 A
K-40 Bq/L
-1.80 NR Mn-54 Bq/L 1.44 1.51 1.06 - 1.96 A
U-234 Bq/L 0.00101 (1)
A U-238 Bq/L 0.00228 (1)
A Zn-65 Bq/L
-0.42 0.84 0.59-1.09 NE(5) 24-MaW50 Water Ni-63 Bq/L 0.338 0.80 (2)
A Tc-99 Bq/L 9.95 7.47 5.23 - 9.71 N(6) 24-RdV50 Vegetation Cs-134 Bq/sample 2.80 3.67 2.57 - 4.77 W
Cs-137 Bq/sample 2.21 2.57 1.80 - 3.34 A
Co-57 Bq/sample 2.23 2.53 1.77 - 3.29 A
Co-60 Bq/sample 2.42 2.96 2.07 - 3.85 A
Mn-54 Bq/sample 0.033 (1)
A Sr-90 Bq/sample 0.276 0.529 0.370 - 0.688 N(7)
Zn-65 Bq/sample 6.83 8.02 5.61 - 10.43 A
August 2024 24-MaS51 Soil Fe-55 Bq/kg (8) 780 546-1014 N(9)
Ni-63 Bq/kg 1140.00 1450.00 1015 - 1885 W
Tc-99 Bq/kg 155.00 171.00 120 - 222 A
Th-228 Bq/kg 38.00 43.30 30.3 - 56.3 A
Th-230 Bq/kg 46.10 44.00 30.8 - 57.2 A
Th-232 Bq/kg 38.90 42.60 29.8 - 55.4 A
24-MaW51 Water Ni-63 Bq/L 0.60 (1)
A Tc-99 Bq/L 11.90 11.20 7.8 - 14.6 A
24-RdV51 Vegetation Cs-134 Bq/sample 3.12 2.89 2.02 - 3.76 A
Cs-137 Bq/sample 2.18 1.91 1.34 - 2.48 A
Co-57 Bq/sample 0.00 (1)
A Co-60 Bq/sample 2.24 2.01 1.41 - 2.61 A
Mn-54 Bq/sample 3.76 3.53 2.47 - 4.59 A
Sr-90 Bq/sample 0.95 2.39 1.67 - 3.11 N(10)
Zn-65 Bq/sample 10.30 9.13 6.39 - 11.87 A
(a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOE/MAPEP evaluation:
A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) False positive test (2) Sensitivity evaluation (3) See CAR 23-31 (4) See NCR 24-08 (5) Not Evaluated, re-reported as Falst Pos by MAPEP (6) See NCR 24-10 (7) See NCR 24-11 (8) Not Reported (9) See NCR 24-16 (10) See NCR 24-17 Teledyne Brown Engineering Environmental Services TABLE D-3.2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Plant: Indian Point Energy Center Year: 2024 Page 114 of 122 Annual Radiological Environmental Operating Report I
I
Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)
Acceptance Limits Evaluation (b)
March 2024 MRAD-40 Water Am-241 pCi/L 101 139 95.4 - 178 A
Fe-55 pCi/L 2185 2480 1460- 3610 A
Pu-238 pCi/L 62.0 70.4 42.3 - 91.2 A
Pu-239 pCi/L 61.2 76.5 47.3 - 94.3 A
Soil Am-241 pCi/kg NR 1880 1020 - 2660 Pu-238 pCi/kg 667 512 255 - 778 A
Pu-239 pCi/kg 562.0 545 297 - 784 A
Sr-90 pCi/kg 4050.0 3630 1130 - 5650 A
U-234 pCi/kg 3040.0 4360.0 2040 - 5710 A
U-238 pCi/kg 3270.0 4320 2370 - 5800 A
AP Am-241 pCi/filter 38.8 55 39.3 - 73.3 N(1)
Fe-55 pCi/filter 387 386 141 - 616 A
Pu-238 pCi/filter 45.9 41 31.0 - 50.5 A
Pu-239 pCi/filter 54.9 56.1 41.9 - 67.7 A
U-234 pCi/filter 11.1 11.6 8.60 - 13.6 A
U-238 pCi/filter 12.8 11.5 8.68 - 13.7 A
GR-A pCi/filter 116 96 50.1 - 158 A
GR-B pCi/filter 42.1 22.2 13.5 - 33.5 N(2)
April 2024 RAD-137 Water Ba-133 pCi/L 62.8 65.9 50.1 - 81.7 A
Cs-134 pCi/L 51 57.8 42.8 - 72.8 A
Cs-137 pCi/L 153.0 186.0 149 - 223 A
Co-60 pCi/L 92.1 98.8 79.7 - 118 A
Zn-65 pCi/L 208 240 188 - 292 A
GR-A pCi/L 35 52.6 39.6 - 65.6 N(3)
GR-B pCi/L 49 46.5 33.9 - 59.1 A
U-Nat pCi/L 56 59.3 52.8-65.8 A
H-3 pCi/L 19000 21300 18,200 - 24,400 A
Sr-89 pCi/L 48.9 52.2 37.8 - 66.6 A
Sr-90 pCi/L 32.6 37.6 32.0 - 43.2 A
I-131 pCi/L 21.8 25.1 21.7 - 28.5 A
Cs-134 pCi/L 38.4 41.2 27.9 - 54.5 A
Cs-137 pCi/L 194 199 161 - 237 A
Co-60 pCi/L 49.5 47.8 33.8 - 61.8 A
Zn-65 pCi/L 59.7 57.0 23.7 - 90.3 A
GR-A pCi/L 53.2 70.6 54.0 - 87.2 N(2)
GR-B pCi/L 46.9 42.2 30.5 - 53.9 A
U-Nat pCi/L 51.26 51.7 45.9-57.5 A
H-3 pCi/L 20,100 22,900 19,700 - 26,100 A
Sr-89 pCi/L 51.1 38.2 25.2 - 51.2 A
Sr-90 pCi/L 31.7 35.7 30.3 - 41.1 A
I-131 pCi/L 23.5 29.7 25.8 - 33.6 N(3)
Teledyne Brown Engineering Environmental Services Plant: Indian Point Energy Center Year: 2024 Page 115 of 122 Annual Radiological Environmental Operating Report TABLE D-3.3 ERA Environmental Radioactivity Cross Check Program (Page 4 of 5)
Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)
Acceptance Limits Evaluation (b)
September 2024 MRAD-41 Water Am-241 pCi/L 108 117 80.3-150 A
Fe-55 pCi/L 615 1230 723-1790 N(4)
Pu-238 pCi/L 99.3 103 61.9-133 A
Pu-239 pCi/L 123.0 133 82.3-164 A
Soil Am-241 pCi/kg 1320 1110 599-1570 A
Pu-238 pCi/kg 1380 1860 928-2830 A
Pu-239 pCi/kg 796.0 1030 561-1480 A
Sr-90 pCi/kg 3240.0 4730 1470-7370 A
U-234 pCi/kg 2540.0 2860.0 1340-3750 A
U-238 pCi/kg 2390.0 2840 1560-3810 A
AP Am-241 pCi/filter 27 29.1 20.8-38.8 A
Fe-55 pCi/filter 644 800 292-1280 A
Pu-238 pCi/filter 22.3 22 16.2-26.4 A
Pu-239 pCi/filter 30.6 32.4 24.2-39.1 A
U-234 pCi/filter 14 31.1 23.1-36.4 N(5)
U-238 pCi/filter 14.2 30.9 23.3-36.9 N(5)
GR-A pCi/filter 80 72 37.8-119 A
GR-B pCi/filter 57.5 47.9 29.0-72.4 A
October 2024 RAD-139 Water Ba-133 pCi/L 30.3 27.4 15.5-39.3 A
Cs-134 pCi/L 73.3 80.2 63.0-97.4 A
Cs-137 pCi/L 46.6 46.3 23.3-69.3 A
Co-60 pCi/L 44.2 45.3 31.6-59.0 A
Zn-65 pCi/L 104 114 75.0-153 A
GR-A pCi/L 48 51.7 38.9-64.5 A
GR-B pCi/L 44 48.1 35.2-61.0 A
U-Nat pCi/L 28 26.9 23.6-30.2 A
H-3 pCi/L 4690 5320 3870-6770 A
Sr-89 pCi/L 57.5 44.2 30.6-57.8 A
Sr-90 pCi/L 37.3 35.6 30.2-41.0 A
I-131 pCi/L 28.3 26.3 22.7-29.9 A
Cs-134 pCi/L 38.4 41.2 27.9 - 54.5 A
Cs-137 pCi/L 194 199 161 - 237 A
Co-60 pCi/L 49.5 47.8 33.8 - 61.8 A
Zn-65 pCi/L 59.7 57.0 23.7 - 90.3 A
GR-A pCi/L 53.2 70.6 54.0 - 87.2 N(2)
GR-B pCi/L 46.9 42.2 30.5 - 53.9 A
U-Nat pCi/L 51.26 51.7 45.9-57.5 A
H-3 pCi/L 20,100 22,900 19,700 - 26,100 A
Sr-89 pCi/L 51.1 38.2 25.2 - 51.2 A
Sr-90 pCi/L 31.7 35.7 30.3 - 41.1 A
I-131 pCi/L 23.5 29.7 25.8 - 33.6 N(3)
(a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(b) ERA evaluation:
A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 24-02 (2) See NCR 24-03 (3) See NCR 24-05 (4) See NCR 24-15 (5) See NCR 24-14 Teledyne Brown Engineering Environmental Services Plant: Indian Point Energy Center Year: 2024 Page 116 of 122 Annual Radiological Environmental Operating Report TABLE D-3.3 ERA Environmental Radioactivity Cross Check Program (Page 5 of 5)
Plant: Indian Point Energy Center Year: 2024 Page 117 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 7.4 Environmental TLD Quality Assurance Environmental dosimetry services for the reporting period of January - December, 2024 were provided by the Environmental Dosimetry Company (EDC),
- Sterling, Massachusetts. The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in house performance testing and independent performance testing by EDC clients and both internal and client directed program assessments.
The purpose of the dosimetry quality assurance program is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes.
Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in-house testing program conducted by the EDC QA Officer and (2) independent test perform by EDC clients.
Excluded from this report are instrumentation checks. Although instrumentation checks represent an important aspect of the quality assurance program, they are not included as process checks in this report. Instrumentation checks represent between 5-10% of the TLDs processed.
Table D-4.1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons only. The internal acceptance (tolerance) criteria for the Panasonic Environmental dosimeters are: +/- 15% for bias and
+/- 12.8% for precision. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (72/72) met the criterion for precision.
Table D-4.2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall, 100% (12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria.
Table D-4.3 presents the independent blind spike results for irradiated dosimeters provided by client utilities during this annual period. All results passed the performance acceptance criterion.
TABLE D-4.1 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2024 (1), (2)
Dosimeter Type Number Tested
% Passed Bias Criteria
% Passed Precision Criteria Panasonic Environmental 72 100 100 (1)This table summarizes results of tests conducted by EDC.
(2)Environmental dosimeter results are free in air.
Plant: Indian Point Energy Center Year: 2024 Page 118 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE D-4.2 MEAN DOSIMETER ANALYSES (N=6)
JANUARY - DECEMBER 2024 (1), (2)
Process Date Mean Bias %
Standard Deviation %
Tolerance Limit +/-15%
5/05/2024 37
-0.3 2.2 5/08/2024 51 2.2 1.5 5/15/2024 83 2.5 2.2 7/30/2024 27 1.1 1.8 8/06/2024 63 6.6 1.2 9/25/2024 95
-3.1 1.8 10/24/2024 42 4.9 2.6 10/30/2024 73 6.8 1.6 11/27/2024 107
-6.7 1.6 01/20/2025 32 1.9 1.0 01/26/2025 47 2.8 1.5 01/29/2025 117 2.6 2.1 (1)This table summarizes results of tests conducted by EDC for TLDs issued in 2024.
(2)Environmental dosimeter results are free in air.
TABLE D-4.3
SUMMARY
OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2024 (1), (2)
Issuance Period Client Mean Bias %
Standard Deviation %
Pass / Fail 1st Qtr. 2024 Millstone
-.1 0.2 Pass 2nd Qtr.2024 Seabrook 1.7 2.8 Pass 2nd Qtr. 2024 Millstone
-4.3 0.9 Pass 3rd Qtr. 2024 SONGS
-9.7 1.4 Pass 3rd Qtr. 2024 Millstone
-1.4 2.5 Pass 4th Qtr.2024 Millstone 1.5 1.4 Pass 4th Qtr.2024 Seabrook 3.8 1.5 Pass (1)Performance criteria are +/- 15%.
(2)Blind spike irradiations using Cs-137
Plant: Indian Point Energy Center Year: 2024 Page 119 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SECTION
8.0 REFERENCES
Plant: Indian Point Energy Center Year: 2024 Page 120 of 122 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
8.0 REFERENCES
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A Review of the Available Literature, Applied Physical Technology, Inc., report to NYPA, September 1977.
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