Text

Annual Radioactive Effluent Release Report
	ML21168A024
Person / Time
Site:	Indian Point
Issue date:	04/30/2021
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	NL-21-029
	Download: ML21168A024 (66)
	v • d • e

ENCLOSURE TO NL-21-029 Annual Radioactive Effluent Release Report ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 1, 2, and 3 NUCLEAR POWER PLANTS DOCKET Nos. 50-03, 50-247, and 50-286

Student ID: tjones2 Student Name: Jones, Terry R Root Curriculum ID Root Curriculum Title Complete Expires F-TECH-GET-PAT-U Entergy Plant Access Training - Utility y 5/31/2021 F-TECH-GET-RWT-U Entergy Radiation Worker Training - Utility y 6/18/2021 IPEC-SEC-CSGI IPEC Security Safeguards Curriculum y 6/25/2021 F-TECH-GET-BTR Baseline Training Requirements y 7/5/2021 F-ADM-ENTERGY-ORIENT- Entergy Orientation and Awareness y 8/8/2021 AWARE F-ACCESS-REOUIREMENTS Access Requirements for Critical Group y 9/20/2021 I0-ESP-CON FIG MA NAG EM ENT Configuration Management y 10/19/2021 F-ADM-PRIVACY-PPI Protection of Personal Information y 10/26/2021 F-ADM-SCREEN ER PAD Screener y 10/29/2021 F-ADM-5059 EVALUATOR 50.59 Evaluator Qualification y 12/4/2021 F-ADM-NEM Nuclear Excellence Model y 12/31/2021 F-EP-EOF-OFFSITE-LIAISON EOF OffSite Liaison y 12/31/2021 F-ERTD-FLEX-INITIAL Basic Diverse and Flexible Coping y 12/31 /2021 Strategies IPEC-ERO-EOF-15 IPEC ERO - Offsite Liaison y 12/31 /2021 F-SAF-COMBUSTIBLES Fleet Controls of Combustibles Training y 1/10/2022 F-ACCESS-REINVEST Reinvestigation for Non-Critical Group y 9/20/2023 F-TECH-GET-IP-GGNS GGNS Site Specific In-Processing Curricula y 12/31/2023 F-ADM-ADMFW Admin Fire Watch y F-ADM-CONAPR Fleet Contract Approver y F-MAINT-FME Monitor FM E Monitor y F-SAF-CONFINED SPACE Entergy Confined Space Training y F-TECH-GET FATIGUE PROGRAM Fleet Fatigue Rule Maintenance Program

Page 1 of 63 Facility: Indian Point Energy Center YEAR: 2020 Indian Point Units 1, 2 and 3 Docket Nos.: 50-3, 50-247, & 50-286

t Entergy Nuclear Operations, Inc. (Entergy)

Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 I Year: 2020 I Page 2 of 63 Annual Radioactive Effluent Release Report TABLE OF CONTENTS

1.0 INTRODUCTION

.. ....... ..... ... ...... ... ........ .... ... .. .... .. ... ........ .. .......................... ..... ... ......... .............. .4 2.0 SUPPLEMENTAL INFORMATION .. ...... .... ....... ........ ... ............... ..... .......... .. .... ............ .. .......... ... .4 3.0 GASEOUS EFFLUENTS ................................ ...... .... .... ... ... ... ..... .... ... .. .. .............. ..... .. ...... ....... .. 12 4.0 LIQUID EFFLUENTS ... ..... .. ... .... ........ ...... .... .... .. ..... .... .... ... ... ... ........ ... ... ..... ...... ... ....... ... ...... .. ... 18 5.0 SOLID WASTE

SUMMARY

..... .. ............... .......... .... .............. ... .. .......... ... ... .... ..... ........... .. ... .. .. .. 23 6.0 RADIOLOGICAL IMPACT TO MAN .... ..... .. .... .... .... .. .. .. ... .. ...... .... ........ .. ... .. ...... ........................ .42 7.0 METEOROLOGICAL DATA ..... ..... ...... .... .... .. ........ ....... ... .. ..... ... ...... ......... .. .......... ... ...... ... ..... ... .46 LIST OF TABLES ......... ... ............. .. .. .... ....... ...... ..... .. ............ ... .... ... ... ....... ........ ..... ..... ......... ..... ... ... .... . 3 ATTACHMENTS - Carbon 14 Discussion ... ... ....... ... .. ....... ................. .. ....... ..... .. .... .. ................. ................. .4 7 - Groundwater Monitoring Program Results ............... .......... ... .... ......... ........................... 48 - 2020 Laboratory Analytical Results .... ....... .......... ..... .. ...... ..... .. .. ...... .. .. .... .. ...... ............ .. 51 - ODCM Revision 5 Summary of Changes .................................................. ............ ...... ..62

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 3 of 63 Annual Radioactive Effluent Release Report List of Tables Table 2.5 Airborne Batch Releases Table 2.5 Liquid Batch Releases Table 3 ~aseous Effluents - Summation of All Releases - Units 1 and 2 Table 3 Gaseous Effluents - Batch Mode - Units 1 and 2 Table 3 Gaseous Effluents - Continuous Mode - Units 1 and 2 Table 3 Gaseous Effluents - Summation of All Releases - Unit 3 Table 3 Gaseous Effluents - Batch Mode - Unit 3 Table 3 Gaseous Effluents - Continuous Mode - Unit 3 Table 4 Liquid Effluents - Summation of All Releases - Units 1 and 2 Table 4 Liquid Effluents - Batch Mode - Units 1 and 2 Table 4 Liquid Effluents - Continuous Mode - Units 1 and 2 Table 4 Liquid Effluents - Summation of All Releases - Unit 3 Table 4 Liquid Effluents - Batch and Continuous Modes - Unit 3 Table 6 Summary of Dose Assessments Table 6 Unit 2 Appendix I Dose Assessment Table 6 Unit 3 Appendix I Dose Assessment

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 4 of 63 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

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

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

1. Fission and activation gases:

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

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

Less than or equal to 3000 mrem/year to the skin

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

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

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

2. Iodine, tritium , and all radionuclides in particulate form (with half-lives > 8 days) .

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

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

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

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

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 5 of 63 Annual Radioactive Effluent Release Report

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

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

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

4. Total Dose (40CFR190)

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:

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

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

1. Airborne Effluents Maximum concentrations and compliance with 10CFR20 release rate limits are controlled by the application of Radiation Monitor setpoints, preliminary grab sampling , and conservative procedural guidance for batch and continuous releases. These measures, in conjunction with plant design, preclude approaching release rate limits, per the ODCM.

2. Liquid Effluents Proximity to release rate and total release limits is controlled through the application of a calculated Allowed Diluted Concentration (ADC) and ALARA guidance with regard to dilution flow and maximum tank concentration. The ADC is used to determine a Radiation Monitor setpoint associated with an estimated amount of non-gamma activity (H-3, Ni-63, Fe-55, Sr-89/90 etc.) , as well as the measured gamma activity. ADC is defined in the station ODCM as a means of assuring compliance with the release rate limits of 10CFR20, as defined by the application of ten times the Effluent Concentrations of the new 10CFR20.

Liquid effluents are further controlled by the application of proceduralized ALARA limits such as a MINIMUM dilution flow of 100,000 gpm required for batch discharges, a maximum gamma concentration of 5E-5 uCi/ml (without gas) for routine effluents, and procedural guidance for optimizing decay and treatment of liquid waste.

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 6 of 63 Annual Radioactive Effluent Release Report 2.4 Measurements & Approximations of Total Radioactivity The following provides the methods used to measure or approximate the total radioactivity in effluents and how radionuclide composition is determ ined .

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

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

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

At least one complete isotopic concentration analysis of containment air is performed monthly and compared to a process monitor's reading . Pressure reliefs are quantified by scaling subsequent releases with the monitor's reading , applying the mixture from the grab sample. In this fashion , the base grab sample defines the mixture and the activity released . The monitor scales the release up or down and provides continuous indication of potential leaks.

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

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

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

If 1-131 is identified in any routine weekly sample, it is added to the table and other iodine isotopic concentrations (1-133, 1-135) are then determined on a 24-hour sample at least once per month.

The concentration of each isotope is analytically determined by ratioing the activities with weekly media for 1-131 . This activity is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged. A compositing method of analyzing for gross alpha, Sr-89 , and Sr-90 is used per the station ODCM . Absence of any positive activity is identified as "-".

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 7 of 63 Annual Radioactive Effluent Release Report

3. Tritium Airborne tritium is collected by passing a known volume of the sample stream through a silica gel column . The collected samples are distilled and analyzed by liquid scintillation. The tritium released was calculated for each release point from the measured tritium concentration , the volume of the sample, the tritium collection efficiency, and the respective ventilation exhaust flow rates. As a check on the silica gel sampling, Chem istry performs a comparison of total curies evaporated from the spent fuel pool (the major H-3 source term) and adjusts the silica gel measurements, as necessary.

4. Carbon-14 Airborne Carbon-14 release values were estimated using the methodology included in the EPRI Technical Report 1021106, using the normalized Carbon-14 production rate of 3.48 Ci/GW1h-EFPyear for Unit 2 and 3.47 Ci/GW1h-EFPyear for Unit 3, a gaseous release fraction of 100%, a Carbon-14 carbon dioxide fraction of 26% , a reactor power rating 3216 MW1h for Unit 2 and 3188 MW1h for Unit 3 and equ ivalent full power (EFP) operation of 113.492 days for Unit 2 and 365.784 days for Unit 3 for calendar year 2020. See Section 6 and Attachment 1 for more details concerning the Carbon 14 calculations.

5. Liquid Effluents A sample of each batch discharge is taken and an isotopic analysis is performed in compliance with requirements specified in the ODCM . Proportional composite samples of continuous discharges are taken and analyzed per the ODCM , as well. Isotopic concentration data are combined with the information on volume discharged to determine the amount of each isotope discharged .

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

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

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

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

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 8 of 63 Annual Radioactive Effluent Release Re ort 2.5 Batch Rele ases:

1. Airborne Table 2.5 Airborne Batch Releases Unit 1 and 2 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2020 Number of Batch Releases 53 30 6 7 96 Total Time Period (min) 2493 2169 235 253 5150 Maximum Ti me Period (min) 78 720 45 42 720 Average Ti me Period (min) 47 72 39 36 54 Minimum Ti me Period (min) 4 18 22 25 4 Unit 3 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2020 Number of Batch Releases 20 26 24 16 86 Total Time Period (min) 1747 23821 2582 1815 29965 Maximum Ti me Period (min) 175 21600 276 225 21600 Average Ti me Period (min) 87 916 108 113 348 Minimum Ti me Period (min) 1 1 1 3 1

2. Liquid Table 2.5 Liquid Batch Releases Unit 1 and 2 Li uid Releases Qtr 1 Qtr 2 Qtr 3 Qtr4 2020 Number of Batch Releases 17 10 8 3 38 Total Time Period min 1614 922 706 287 3529 Maximum Time Period min 104 108 98 100 108 Averaqe Ti me Period min 95 92 88 96 93 Minimum Time Period min 88 51 66 90 51 Unit 3 Li uid Releases Qtr 1 Qtr 2 Qtr 3 Qtr4 2020 Number of Batch Releases 19 5 16 15 55 Total Time Period min 2149 553 1712 1569 5983 Maximum Time Period (min) 178 112 114 117 178 Averaqe Ti me Period min 113 111 107 105 109 Minimum Time Period (min) 78 109 85 67 67 Average Strearn Flow:

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

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

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

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 9 of 63 t-------

Annual Radioactive Effluent Release Re ort 2.6 Abnormal Releases

1. Liquid None

2. Gaseous During review of CR-IP3-2020-1191 and CR-IP3-2020-1213 it was noted that there was leak-by valve SP-906 (relief valve stuck open) . This effectively caused a bypass of the normal containment isolation by pumping Vapor Containment air into the PAB Ventilation System on a continuous basis. Although the PAB ventilation system is continuously monitored via R-14 and R-27, this is essentially a very minor abnormal situation of a continuous Vapor Containment pressure relief that is difficult to account for since it is below the detectability of R-14 and R-27. Conservatively assuming that SP-906 was fully open , a design flow rate of 3 SCFM and a release period of 20 days (per Operations tracking of this issue), the resulting release was 783 uCi of Ar-41 and 489 uCi of Xe-133, for a total of 1,272 uCi of noble gases. This is equivalent of one additional Vapor Containment pressure relief (which typically occurs on a weekly basis at Unit 3). The resulting dose consequence was 3.5 e-7 mRad gamma air dose and 4.4 e-7 beta air dose, well below the allowable quarterly limits of 5 mRad gamma air dose and 1O mRad beta air dose.

2.7 Non-routine, Planned Discharges Recovery Well - 1 (RW-1) was installed as a contingency for mitigation of spills affecting the area near the Unit 2 Fuel Storage Building . Due to the two abnormal releases that were discussed in the 2016 Radioactive Effluent Release Report it was determined necessary to operate this well to enhance the reduction of H-3 levels in groundwater. This was necessary to reduce the H-3 to levels that would enable the Site to detect any new leaks or spills of contaminated waters. Operation of this well is a continuous monitored release pathway for liquid effluents from Unit 2. Therefore, this well is sampled per procedure and monthly permits are performed for this liquid discharge pathway. For ease of tracking , the releases from this pathway are documented as non-routine batch releases that are discharged from Unit 2. The batch totals listed in Section 2.5.2 do not include these in the totals since this discharge pathway is a continuous release pathway. Note that only H-3 has been detected in the RW-1 releases and the levels are very low compared to the typical batch releases. This does not present a problem with the dose calculations since the dose assessment modeling does not differentiate between continuous and batch releases.

Another non-routine release is one that occurs when routine ventilation is out of service (OOS) .

Typically, this is only for a very short amount of time per procedure, such that these releases are insignificant. Typically, the most significant of these releases occurs when the Fuel Storage Building (FSB) ventilation is OOS . The use of H-3 curie balance for the Spent Fuel Pool (SFP) can be used to account for these releases (also see Section 2.4 -Tritium) since the major airborne source term from the FSB is the evaporation of the SFP water. Another method is to evaluate the SFP H-3 airborne activity and estimate the airborne release rate .

2.8 Radioactive Waste Treatment System Changes There were no changes to the Radioactive Waste Treatment System .

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 10 of 63 Annual Radioactive Effluent Release Re ort 2.9 Land Use Census Changes No changes or modifications affecting receptors , receptor location or new (or changed) routes of exposure were identified as a result of the last Land Use Census.

2.10 Effluent Monitor Instrument lnoperability

1. Effluent Monitoring Equipment Inoperable> 30 Days During this reporting period , there were no instances of effluent monitoring equipment out of service for greater than 30 consecutive days.

2. Effluent Monitoring Equipment Sample Deviation None 2.11 Offsite Dose Calculation Manual Changes During this report period there was an ODCM change. Revision 5 of the ODCM was implemented in October 2020. Attachment 4 contains the ODCM Revision 5, summary of changes. A complete copy of Revision 5 of the IPEC ODCM is being submitted with this report.

2.12 Process Control Program (PCP) Changes There were no PCP changes during 2020.

2.13 Groundwater Monitoring and Program (NEI 07-07)

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

No abnormal releases occurred in 2020 and conservative assessments of legacy events have determined that the doses resulting from these events were negligible. The groundwater monitoring program provides additional confirmation of these assessments. The groundwater monitoring program also includes a storm water monitoring program . Together these programs provide data for offsite dose evaluation . The subsurface water flow directions and rates are used to estimate the transport of abnormal releases of liquid effluents in groundwater.

The offsite dose associated with the groundwater pathway remains extremely small. The 2020 effluent dose was slightly lower than in 2019. The total routine liquid effluent dose inclusive of the groundwater pathway contributes < 0.1 % of the annual limit. Groundwater and storm water effluent flow rates and source term data are further described in Attachment 2 of this report. A breakdown of the total dose from the groundwater and storm water pathways and detailed results from the samples obtained as part of this program are also provided in Attachment 2. Section 6 (Radiological Impact on Man) of this report provides a comparison of the groundwater and storm water doses to the other dose pathways.

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 11 of 63 Annual Radioactive Effluent Release Report 2.14 Outside Tanks During this period there were no curie limits exceeded in the outdoor tanks.

2.15 Errata/Corrections to Previous ARERRs None

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 12 of 63 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS Table 3-1 Gaseous Effluents - Summation of All Releases - Units 1 and 2 Total A Fission & Activation Gase U .

nits Qtr 1 Qtr 2 Qtr 3 Qtr4 Year % Error

1. Total Release Ci 7. 98E-02 2.35E-01 - - 3.15E-01 +/- 25 2 . Average release rate uCi/sec 1.03E-02 2.99E-02 - - 9.99E-03 B. Iodines

1. Total lod ine-13 1 Ci - - - - 0 .00E+00 +/- 25 2 . Average release rate uCi/sec - - - - 0 .00E+00 C Particulates

1. Total Release , with h::ilf-lifP > Fl rl<:>IIC Ci - - - - 0 .00E+00 +/- 25

2. Average re lease rate uCi/sec - - - - 0 .00E+00 3 . Gross Alpha Ci - - - - 0.00E+00 +/- 25 D Tritium

1. Total release Ci 7 .98E-01 2.1 3E+00 1.34E+00 7.45E-01 5 .01 E+00 +/- 25 2 . Average release rate uCi/sec 1.03E-01 2 .70E-01 1.69E-01 9.38E-02 1.59E-01 E. Carbon-14

1. Total release Ci 2. 78E+00 6.88E-01 - - 3.47 E+00 2 . Average release rate uCi/sec 3.58E-01 8.75E-02 - - 1.10E-01

- Indicates < MDA

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 13 of 63 Annual Radioactive Effluent Release Report Table 3-2 Gaseous Effluents -- Batch Mode - Units 1 and 2 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year Ar-41 Ci 3.75E-02 4.83E-03 - - 4 .23E-02 Kr-85 Ci - - - - 0.00E+00 Kr-85m Ci 1.59E-04 - - - 1.59E-04 Kr-87 Ci 1.46E-04 - - - 1.46E-04 Kr-88 Ci 2.89E-04 - - - 2.89E-04 Xe-131 m Ci - - - - 0.00E+00 Xe-133 Ci 3.90E-02 1.84E-01 - - 2.23E-01 Xe-133m Ci - 1.93E-02 - - 1.93E-02 Xe-135 Ci 2.46E-03 2.77E-02 - - 3.01E-02 Xe-135m Ci 2.47E-04 - - - 2.47E-04 Xe-138 Ci - - - - 0.00E+00 I Total for Period Ci 7.98E-02 2.35E-01 0.00E+00 0.00E+00 3.15E-01

- indicates <MDA

2) Iodines Not Applicable for Batch Releases

3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 14 of 63 Annual Radioactive Effluent Release Re ort Table 3-3 Gaseous Effluents -- Continuous Mode - Units 1 and 2 Nuclides Released

1) F iss ion Gases Units Qtr 1 Qtr 2 Qt r 3 Qtr 4 Year Xe-133 Ci . 0 .00E+OO Total for Period Ci O.OOE+OO O. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2 ) Iod ines 1-131 Ci O.OOE+OO 1-133 Ci O.OOE+OO 1-135 Ci O.OOE+OO Total for Period Ci O.OOE+OO O.OOE+OO O.OOE +O 0 O.OOE+OO O.OOE+OO

3) Particulates Cs-137 Ci 9 .29E-06 - 9 .29E-06 Ci O.OOE+OO 9 .29E-06 O.OO E +O 0 O.OOE+OO 9 .29E-06

- Indicates < MDA

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 15 of 63 Annual Radioactive Effluent Release Report Table 3-4 Gaseous Effluents - Summation of All Releases - Unit 3 Est. Total A. Fission & Activation Gase Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year % Error

1. Total Release Ci 1.48E-02 2. 12E-02 2.46E-02 1.99E-02 8.04E-02 +/- 25

2. Average release rate uCi/sec 1.90E-03 2.69E-03 3.09E-03 2.51E-03 2.55E-03 B. Iodines

1. Total lodine-131 Ci - - - - 0.00E+00 +/- 25

2. Average release rate uCi/sec - - - - 0.00E+00 C. Particulates

1. Total Release , with Ci - - - - 0.00E+00 +/- 25 half-life > 8 davs

2. Average release rate uCi/sec - - - - 0.00E+00

3. Gross Alpha Ci - - - - 0.00E+00 +/- 25 D. Tritium

1. Total release Ci 3.01E+00 4.11E+00 4.23E+00 2.40E+00 1.37E+01 +/- 25

2. Average release rate uCi/sec 3.86E-01 5.23E-01 5.33E-01 3.02E-01 4.36E-01 E. Carbon-14

1. Total release Ci 2.75E+00 2.75E+00 2.75E+00 2.75E+00 1.10E+01

2. Average release rate uCi/sec 3.54E-01 3.50E-01 3.46E-01 3.46E-01 3.49E-01

- Indicates < MDA

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 16 of 63 Annual Radioactive Effluent Release Report Table 3-5 Gaseous Effluents - Batch Mode - Unit 3 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ar-41 Ci 9.91 E-03 1.25E-02 1.14E-02 1.22E-02 4.60E-02 Kr-85 Ci - - - - 0.00E+00 Kr-85m Ci - - - - 0.00E+00 Kr-87 Ci - - - - 0.00E+00 Kr-88 Ci - - - - 0.00E+00 Xe-131m Ci - - - - 0.00E+00 Xe-133 Ci 4.86E-03 8.31 E-03 1.32E-02 7.63E-03 3.40E-02 Xe-133m Ci - 3.92E-04 - - 3.92E-04 Xe-135 Ci - 2.14E-06 2.68E-05 7.21E-05 1.01E-04 Xe-135m Ci - - - - 0.00E+00 I Total for Period Ci 1.48E-02 2.12E-02 2.46E-02 1.99E-02 8.04E-02

- Indicates< MDA

2) Iodines Not Applicable for Batch Releases

3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 17 of 63 Annual Radioactive Effluent Release Report Table 3-6 Gaseous Effluents - Continuous Mode - Unit 3 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ar-41 Ci - - - - O. OOE+OO Xe- 133 Ci - - - - O. OOE+OO Xe- 135 Ci - - - - O.OOE+OO I Total for Period Ci O. OOE+OO O. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

2) Iodines 1-131 Ci - - - - O. OOE+OO 1-133 Ci - - - - O. OOE+OO 1-135 Ci - - - - O. OOE+OO I Total for Period Ci O. OOE+OO O.OOE+OO O. OOE+OO 0 . 00E+OO O. OOE+OO

3) Particulates Total for Period Ci 0.00E+OO O. OOE+OO O.OOE+OO O. OOE+OO O. OOE+OO

- indicates < MDA

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 18 of 63 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS Table 4-1 Liquid Effluents - Summation of All Releases - Units 1 and 2 Est. Total A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year % Error

1. Total Release (not including Ci 3.61E-03 2.64E-03 2 03E-03 1.86E-03 1.01E-02 +/-25 Tritium Gr Aloha & Gases)

2. Average Diluted Cone uCi/ml 4.89E-12 5.71E-12 4.96E- 12 4 . 72E-12 5.06E-12 B. Tritium

1. Total Release Ci 6.31E+02 1.91E+02 4.66E+01 7.95E+00 8.76E+02 +/- 25 2 . Average Diluted Cone uCi/ml 8.55E-07 4 .12E-07 1.14E-07 2.02E-08 4.37E-07 C. Dissolved & Entrained Gases

1. Total Release Ci 9.62E-05 - - - 9.62E-05 +/- 25

2. AverageDiluted Cone uCi/ml 1.30E- 13 - - - 4.80E-14 D. Gross Alpha

1. Total Release Ci I0.00E+00 I +/- 25 E. Volume of Waste Released

1. Processed Fluids (Mon Tanks) liters 1.90E+06 1.57E+06 1.05E+06 1.70E+06 6.22E+06 +/- 10

2. Unprocessed Fluids (SGs and liters 4 .28E+07 2.08E+07 7.78E+06 9.86E+06 8.13E+07 +/- 10 RW -1)

F. Volume of Diluti on Water liters 7.38E+11 4 .63E+ 11 4.09E+11 3 .94E+11 2.00E+12 +/- 10

- indicates < MDA

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 19 of 63 Annual Radioactive Effluent Release Report Table 4-2 Liquid Effluents - Batch Mode - Units 1 and 2 Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ag - 11 Om Ci - - 4 .BBE-05 - 4 .BBE-05 Co-58 Ci - 2 .69E-04 2 .20E-04 2 .70E-05 ... 5.16E-04 Co- 60 Ci 2.21 E-05 4.47E-05 1.30E-05 - 7 .98E-05 Cr-51 Ci - - - - .,. O.OOE+OO Cs-137 Ci 1.22E-04 2 .98E-05 3.03E-06 1.57E-05 1.71 E-04 Fe- 55 Ci 1.94E- 04 5.02E- 04 - - 6.96E-04 Fe-59 - - - - O.OOE+OO Mn-54 Ci - - - - O.OOE+OO Nb-95 Ci - - - - O.OOE+OO Ni-63 Ci 6 .88E- 04 9.31E-04 - - 1.62E- 03 Sb- 125 Ci 7 .74E-04 2 .81E-04 - - 1.06E-03 Te-123m Ci - - 1.38E- 05 - 1.38E- 05 Te- 125m Ci - - 6.87E-04 - 6 .87E-04 Total for Period Ci 1.80E-03 2 .06E-03 9.86E-04 4 .28E-05 4 .89E-03 Dissolved & Entrained Gas Xe-133m Ci 2 .88E-05 - - - 2 .88E-05 Xe-133 Ci 6 .74E- 05 - - - 6 .74E-05 Total for Period Ci 9 .62E-05 O.OOE+OO O.OOE+OO O.OOE+OO 9.62E-05

- Indicates < MDA

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 20 of 63 Annual Radioactive Effluent Release Report Table 4-3 Liquid Effluents - Continuous Mode - Units 1 and 2 Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Cs-137 Ci 1.B0E-03 5.65E-04 1.03E-03 1.79E-03 5.18E-03 Ni-63 Ci - - - - 0.00E+00 Sr-89 Ci - - - - 0.00E+00 Sr-90 Ci 1.39E-05 2.14E-05 9.20E-06 3.01 E-05 7.47E-05 I Total for Period Ci 1.81E-03 5.86E-04 1.04E-03 1.82E-03 5.26E-03 H-3 (only) Ci 1.37E-02 8.25E-03 1.32E-02 1.26E-02 4. 78E-02

- Indicates< MDA

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 21 of 63 Annual Radioactive Effluent Release Report Table 4-4 Liquid Effluents -Summation of All Releases - Unit 3 Est. Total A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year % Error

1. Total Release (not including Ci 5 .22E-03 9.79E-04 1.43E-02 1.18E-02 3.22E-02 +/- 25 Tritium Gr Alpha & Gases)

2. Average Diluted Cone uCi/ml 7 .08E-12 2 .11E-12 3.49E-11 2 .98E-11 1.61E-11 B . Tritium

1. Total Release Ci 1.23E+02 2.67E+01 3.03E+01 3.34E+02 5.13E+02 +/- 25

2. Average Diluted Cone uCi/ml 1.66E- 07 5.76E-08 7.41 E-08 8 .47E-07 2 .56E-07 C . Dissolved & Entrained Gases

1. Total Release Ci 7.24E-05 - - - 7.24E-05 +/- 25

2. AverageDiluted Cone uCi/ml 9 .81 E- 14 - - - 3.61E-14 D . Gross Alpha

1. Total Release Ci I 0.00E+00 I +/- 25 E . Volume of Waste Released

1. Processed Fluids (Mon Tanks) liters 4 .90E+05 1.30E+05 4 .00E+05 3 .65 E+05 1.38E+06 +/- 10 2 . Unprocessed Fluids (SGs ) liters 1.62E+06 1.62E+06 3.51 E+06 1.64E+06 8.40E+06 +/- 10 F. Volume of Dilution Water liters 7.38E+11 4.63E+11 4 .09E+11 3 .94E+11 2 .00E+12 +/- 10

- indicates < MDA

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 22 of 63 Annual Radioactive Effluent Release Report Table 4-5 Liquid Effluents - Batch and Continuous Modes - Unit 3 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ag-110m Ci 1.80E-04 4 .39E-05 - 8 .20E-05 3 .06E-04 Co-57 Ci - - 7 .13E-05 7.92E-06 7 .92E-05 Co-58 Ci 3.79E-04 4 .14E-05 1.14E-03 2 .65E-04 1.82E Co-60 Ci 1.28E-03 2 .83E-04 1.33E-03 2 .14E-03 5 .04E-03 Cr-51 Ci - - - - 0 .00E+00 Cs-134 Ci - - - - 0 .00E+00 Cs- 137 Ci - - 7 .71E-04 8.60E-04 1.63E-03 Fe-55 Ci 6 .34E-04 2 .12E-04 2 .92E-03 1.02E-03 4 .79E-03 1- 132 Ci - - - - 0.00E+00 Mn-54 Ci 3.41 E-05 5.17E-06 1.33E-04 7.21E-05 2.44E-04 Nb-95 Ci 2 .34E-06 - - - 2 .34E-06 Ni-63 Ci 7.10E-04 2.72E-04 7.10E-03 6 .86E-03 1.49E-02 Sb-124 Ci - - 6 .67E-06 - 6 .67E-06 Sb-125 Ci 2 .00E-03 1.21 E-04 6 .99E-04 4 .54E-04 3.27E-03 Tc-99m Ci - - - - 0 .00E+00 Te-123m Ci 1.66E-06 - - - 1.66E-06 Te- 125m Ci - - - - 0 .00E+00 Te-132 Ci - - - - 0.00E+00 Zr-95 Ci - - - - 0 .00E+00 I Total for Period Ci 5.22E-03 9 .79E-04 1.42E-02 1.18E-02 3.21E-02 Dissolved and Entrained Gas (Batch)

Xe- 133 Ci 7 .24E-05 - - - 7.24E-05 Xe-135 Ci - - - - 0.00E+00 I Total for Period Ci 7 .24E-05 0 .00E+00 0 .00E+00 0 .00E+00 7 .24E-05 Continuous Releases (SG Blowdown)

H-3 (only) Ci

- indicates < mda

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 23 of 63 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Units 1 & 2 T)lE!es of Solid Waste - Summa!:)£ Waste Stream: Resins , Filters , and Evap Bottoms Waste Volume Curies % .Error (Ci)

Class ft3 m3 Shipped A 2 .61E+02 7 .39E+00 3.84E+00 +/- 25%

B 7 .39E+02 2 .09E+01 1.52E+02 +/- 25%

C 2 .20E+01 6 .22E-01 1.49E+01 +/- 25%

All 1 .02E+03 2 .89E+01 1.71E+02 +/- 25 %

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

Class ft3 m3 Shipped A 9.59E+03 2 .72E+02 2.32E+00 +/-25%

B 3 .50E+01 9.91 E-01 2 .15E-01 +/-25%

C 0 .O0E+00 0 .00E+00 0 .00E+00 +/-25%

All 9.63E+03 2.73E+02 2 .54E+00 +/-25%

Waste Stream Irradiated Components Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 0.O0E+00 0 .00E+00 0 .00E+00 +/-25%

B 0 .00E+00 0 .00E+00 0 .00E+00 +/-25 %

C 0 .00E+00 0.00E+00 0 .00E+00 +/-25%

All 0 .00E+00 0.00E+00 0 .00E+00 +/-25%

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

Class ft3 m3 Shipped A 0 .00E+00 0 .00E+00 0 .O0E+00 +/-25%

B 0 .00E+00 0.00E+00 0 .00E+00 +/-25%

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

All 0 .00E+00 0 .00E+00 0 .00E+00 +/-25%

Waste Stream : Sum of All 4 Categories Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 9 .85E+03 2 .79E+02 6 .17E+00 +/-25%

B 7.74E+02 2 .19E+01 1 .52E+02 +/-25%

C 2 .20E+01 6 .22E-01 1.49E+01 +/-25 %

All 1.07E+04 3.02E+02 1 .73E+02 +/-25%

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 24 of 63 Annual Radioactive Effluent Release Report 5.2 Units 1 & 2 Solid Waste - Destination by Carrier Number of Shipments Mode of Transportations Destination 17 Hittman Transport Energy Solutions - Bear Creek 1 Hittman Transport Energy Solutions - GRF

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 25 of 63 Annual Radioactive Effluent Release Report 5.3 Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Abundance Activity (Ci)

H-3 8.45% 3.25E-01 C-14 14.39% 5.53E-01 Mn-54 0.28% 1.0BE-02 Fe-55 10.51% 4.04E-01 Co-57 0.06% 2.35E-03 Co-58 0.08% 2.94E-03 Co-60 34.86% 1.34E+OO Ni-59 0.12% 4.57E-03 Ni-63 25.86% 9.94E-01 Sr-90 0.02% 7.16E-04 Nb-94 0.10% 3.77E-03 Ag-110m 0.50% 1.94E-02 Sb-125 0.96% 3.68E-02 Cs-137 3.59% 1.38E-01 Ce-144 0.22% 8.59E-03 Total 100.00% 3 .84E+OO Note: For radionuclides H-3, C-14, Tc-99 and l-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 26 of 63 Annual Radioactive Effluent Release Report Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Abundance Activity (Ci)

H-3 0.02% 3.20E-02 C-14 1.57% 2.38E+OO Cr-51 0.04% 5.53E-02 Mn-54 0.45% 6.86E-01 Fe-55 2.10% 3.19E+OO Co-57 0.15% 2.31 E-01 Co-58 0.22% 3.40E-01 Co-60 9.94% 1.51 E+01 Ni-59 0.49% 7.48E-01 Ni-63 68.43% 1.04E+02 Zn-65 0.06% 9.82E-02 Sr-89 0.00% 6.19E-06 Sr-90 0.28% 4.24E-01 Nb-94 0.02% 2.41 E-02 Tc-99 0.00% 1.35E-03 Ag-110m 0.04% 6.11 E-02 Sb-125 1.08% 1.64E+OO Cs-134 0.03% 4.25E-02 Cs-137 15.00% 2.28E+01 Ce-144 0.00% 3.48E-03 Pu-238 0.00% 4.98E-03 Pu-239 0.00% 6.18E-03 Pu-241 0.07% 1.02E-01 Am-241 0.01% 1.28E-02 Cm-242 0.00% 6.74E-06 Cm-243 0.00% 1.28E-03 Total 100.00% 1.52E+02 Note: For radionuclides H-3, C-14, Tc-99 and l-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 27 of 63 Annual Radioactive Effluent Release Report Resins, Filters and Evaporator Bottoms Waste Class C Nuclide Name Abundance Activity (Ci)

H-3 0.10% 1.52E-02 C-14 1.97% 2.95E-01 Cr-51 0.00% 3.02E-05 Mn-54 2.14% 3.20E-01 Fe-55 36.08% 5.39E+OO Fe-59 0.00% 2.11E-04 Co-57 0.12% 1.81 E-02 Co-58 0.92% 1.37E-01 Co-60 42.98% 6.42E+OO Ni-59 0.10% 1.49E-02 Ni-63 11 .58% 1.73E+OO Zn-65 0.35% 5.25E-02 Sr-90 0.02% 3.35E-03 Nb-94 0.07% 1.05E-02 Tc-99 0.00% 5.62E-04 Ag-110m 0.05% 7.57E-03 Sn-113 0.25% 3.74E-02 Sb-124 0.00% 5.88E-04 Sb-125 2.45% 3.66E-01 Cs-137 0.70% 1.05E-01 Ce-144 0.02% 3.67E-03 Pu-238 0.00% 4.46E-04 Pu-239 0.00% 1.41E-04 Pu-241 0.05% 7.91 E-03 Am-241 0.01% 1.17E-03 Cm-242 0.00% 1.63E-04 Cm-243 0.01% 1.48E-03 Total 100.00% 1.49E+01 Note: For radionuclides H-3, C-14, Tc-99 and l -129 if valu e is <MDA th en MDA is used to r eport Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 28 of 63 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Total Combined Nuclide Name Percent Abundance Curies H-3 0.22% 3.72E-01 C-14 1.89% 3.23E+OO Cr-51 0.03% 5.53E-02 Mn-54 0.60% 1.02E+OO Fe-55 5.25% 8.98E+OO Fe-59 0.00% 2.11 E-04 Co-57 0.15% 2.51 E-01 Co-58 0.28% 4.81 E-01 Co-60 13.33% 2.28E+01 Ni-59 0.45% 7.68E-01 Ni-63 62.55% 1.07E+02 Zn-65 0.09% 1.51 E-01 Sr-89 0.00% 6.19E-06 Sr-90 0.25% 4.28E-01 Nb-94 0.02% 3.84E-02 Tc-99 0.00% 1.91 E-03 Ag-110m 0.05% 8.81E-02 Sn-113 0.02% 3.74E-02 Sb-124 0.00% 5.88E-04 Sb-125 1.20% 2.05E+OO Cs-134 0.02% 4.25E-02 Cs-137 13.50% 2.31 E+01 Ce-144 0.01% 1.57E-02 Pu-238 0.00% 5.43E-03 Pu-239 0.00% 6.32E-03 Pu-241 0.06% 1.10E-01 Am-241 0.01% 1.39E-02 Cm-242 0.00% 1.?0E-04 Cm-243 0.00% 2.76E-03 Total 100.00% 1.71E+02 Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 29 of 63 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.04% 9.54E-04 C-14 3.32% 7.71E-02 Mn-54 0.07% 1.52E-03 Fe-55 13.66% 3.17E-01 Co-57 0.00% 1.16E-04 Co-60 8.32% 1.93E-01 Ni-59 0.38% 8.87E-03 Ni-63 47.39% 1.10E+OO Sr-89 0.00% 1.85E-07 Sr-90 0.53% 1.23E-02 Nb-94 0.03% 7.93E-04 Sb-125 0.06% 1.30E-03 Cs-134 0.01 % 2.65E-04 Cs-137 26 .02% 6.04E-01 Ce-144 0.01 % 1.71E-04 Pu-238 0.01 % 1.56E-04 Pu-239 0.01% 2.02E-04 Pu-241 0.11 % 2.61 E-03 Am-241 0.02% 5.09E-04 Cm-242 0.00% 1.17E-06 Cm-243 0.01 % 2.30E-04 Total 100.00% 2 .32E+OO Note: For radionuc/ides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 30 of 63 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class B Nuclide Name Percent Abundance Curies H-3 0.05% 1.17E-04 C-14 4.39% 9.45E-03 Co-60 2.87% 6.18E-03 Ni-59 0.51% 1.09E-03 Ni-63 59.45% 1.28E-01 Sr-89 0.00% 2.33E-08 Sr-90 0.68% 1.47E-03 Nb-94 0.05% 9.73E-05 Cs-137 31 .81% 6.85E-02 Ce-144 0.01% 1.30E-05 Pu-238 0.01% 1.85E-05 Pu-239 0.01% 2.46E-05 Pu-241 0.14% 3 05E-04 Am-241 0.02% 5.08E-05 Cm-243 0.00% 4.02E-06 Total 100.00% 2.15E-01 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 31 of 63 Annual Radioactive Effluent Release Re ort Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Total Combined Nuclide Name Percent Abundance Curies H-3 0.04% 1.0?E-03 C-14 3.41% 8.66E-02 Mn-54 0.06% 1.52E-03 Fe-55 12.49% 3.17E-01 Co-57 0.00% 1.16E-04 Co-60 7.84% 1.99E-01 Ni-59 0.39% 9.96E-03 Ni-63 48.47% 1.23E+00 Sr-89 0.00% 2.08E-07 Sr-90 0.54% 1.37E-02 Nb-94 0.04% 8.91 E-04 Sb-125 0.05% 1.30E-03 Cs-134 0.01% 2.65E-04 Cs-137 26.48% 6.72E-01 Ce-144 0.01% 1.84E-04 Pu-238 0.01% 1.74E-04 Pu-239 0.01% 2.26E-04 Pu-241 0.12% 2.92E-03 Am-241 0.02% 5.60E-04 Cm-242 0.00% 1.17E-06 Cm-243 0.01% 2.34E-04 Total 100.00% 2.54E+00 Note: For radionuc/ides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 32 of 63 Annual Radioactive Effluent Release Re ort Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 5.27% 3.25E-01 C-14 10.22% 6.30E-01 Mn-54 0.20% 1.23E-02 Fe-55 11 .69% 7.21 E-01 Co-57 0.04% 2.46E-03 Co-58 0.05% 2.94E-03 Co-60 24.81% 1.53E+OO Ni-59 0.22% 1.34E-02 Ni-63 34.05% 2.10E+OO Sr-89 0.00% 1.85E-07 Sr-90 0.21% 1.30E-02 Nb-94 0.07% 4.56E-03 Ag-110m 0.31% 1.94E-02 Sb-125 0.62% 3.81E-02 Cs-134 0.00% 2.65E-04 Cs-137 12.03% 7.42E-01 Ce-144 0.14% 8.76E-03 Pu-238 0.00% 1.56E-04 Pu-239 0.00% 2.02E-04 Pu-241 0.04% 2.61 E-03 Am-241 0.01% 5.09E-04 Cm-242 0.00% 1.17E-06 Cm-243 0.00% 2.30E-04 Total 100.00% 6.17E+OO Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 33 of 63 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.02% 3.21 E-02 C-14 1.57% 2.39E+OO Cr-51 0.04% 5.53E-02 Mn-54 0.45% 6.86E-01 Fe-55 2.10% 3.19E+OO Co-57 0.15% 2.31 E-01 Co-58 0.22% 3.40E-01 Co-60 9.93% 1.51 E+01 Ni-59 0.49% 7.49E-01 Ni-63 68.38% 1.04E+02 Zn-65 0.06% 9.82E-02 Sr-89 0.00% 6.22E-06 Sr-90 0.28% 4.25E-01 Nb-94 0.02% 2.42E-02 Tc-99 0.00% 1.35E-03 Ag-110m 0.04% 6.11E-02 Sb-125 1.08% 1.64E+OO Cs-134 0.03% 4.25E-02 Cs-137 15.06% 2.29E+01 Ce-144 0.00% 3.50E-03 Pu-238 0.00% 5.00E-03 Pu-239 0.00% 6.20E-03 Pu-241 0.07% 1.03E-01 Am-241 0.01% 1.28E-02 Cm-242 0.00% 6.74E-06 Cm-243 0.00% 1.28E-03 Total 100.00% 1.52E+02 Note: For radionuclides H-3, C-14, Tc-99 and /-1 29 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 34 of 63 Annual Radioactive Effluent Release Report Sum All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies H-3 0.10% 1.52E-02 C-14 1.97% 2.95E-01 Cr-51 0.00% 3.02E-05 Mn-54 2.14% 3.20E-01 Fe-55 36.08% 5.39E+OO Fe-59 0.00% 2.11E-04 Co-57 0.12% 1.81 E-02 Co-58 0.92% 1.37E-01 Co-60 42 .98% 6.42E+OO Ni-59 0.10% 1.49E-02 Ni-63 11 .58% 1.73E+OO Zn-65 0.35% 5.25E-02 Sr-90 0.02% 3.35E-03 Nb-94 0.07% 1.05E-02 Tc-99 0.00% 5.62E-04 Ag-110m 0.05% 7.57E-03 Sn-113 0.25% 3.74E-02 Sb-124 0.00% 5.88E-04 Sb-125 2.45% 3.66E-01 Cs-137 0.70% 1.05E-01 Ce-144 0.02% 3.67E-03 Pu-238 0.00% 4.46E-04 Pu-239 0.00% 1.41 E-04 Pu-241 0.05% 7.91 E-03 Am-241 0.01% 1.17E-03 Cm-242 0.00% 1.63E-04 Cm-243 0.01% 1.48E-03 Total 100.00% 1.49E+01 Note: For radionuclides H-3, C-14, Tc -99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 35 of 63 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories All Waste Classes Nuclide Name Percent Abundance Curies H-3 0.22% 3.73E-01 C-14 1.91% 3.31 E+OO Cr-51 0.03% 5.53E-02 Mn-54 0.59% 1.02E+OO Fe-55 5.37% 9.30E+OO Fe-59 0.00% 2.11E-04 Co-57 0.14% 2.51 E-01 Co-58 0.28% 4.81 E-01 Co-60 13.27% 2.30E+01 Ni-59 0.45% 7.78E-01 Ni-63 62.33% 1.08E+02 Zn-65 0.09% 1.51 E-01 Sr-89 0.00% 6.40E-06 Sr-90 0.25% 4.41 E-01 Nb-94 0.02% 3.93E-02 Tc-99 0.00% 1.91 E-03 Ag-110m 0.05% 8.81 E-02 Sn-113 0.02% 3.74E-02 Sb-124 0.00% 5.88E-04 Sb-125 1.18% 2.05E+OO Cs-134 0.02% 4.28E-02 Cs-137 13.68% 2.37E+01 Ce-144 0.01% 1.59E-02 Pu-238 0.00% 5.61E-03 Pu-239 0.00% 6.55E-03 Pu-241 0.07% 1.13E-01 Am-241 0.01% 1.45E-02 Cm-242 0.00% 1.71 E-04 Cm-243 0.00% 2.99E-03 Total 100.00% 1.73E+02 Note: For radionuclides H-3, C-14, Tc-99 and l -129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 36 of 63 Annual Radioactive Effluent Release Report 5.4 Unit 3 T~12es of Solid Waste - Summarv Waste Stream : Resins, Filters , and Evap Bottoms Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 1 .56E+02 4.42E+00 2 .14E+00 +/-25%

B 0 .00E+00 0 .00E+00 0 .00E+00 +/-25%

C 0 .00E+00 0 .00E+00 0 .00E+00 +/-25%

All 1 .56E+02 4.42E+00 2 .14E+00 +/- 25%

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

Class ft3 m3 Shipped A 1.48E+03 4 .19E+01 2.33E-02 +/-25%

B 0.00E+00 0 .00E+00 0 .00E+00 +/-25%

C 0.00E+00 0 .00E+0O 0 .00E+00 +/-25%

All 1.48E+03 4.19E+01 2 .33E-02 +/-25%

Waste Stream Irradiated Components Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 0 .O0E+00 0 .00E+00 O.00E+00 +/-25%

B 0.00E+00 0 .00E+00 0 .00E+00 +/-25%

C 0.O0E+00 0.00E+00 O.00E+00 +/-25%

All 0 .O0E+00 0 .00E+00 O.00E+00 +/-25%

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

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

B O.00E+00 0 .00E+00 O.00E+00 +/-25%

C O.00E+00 0 .00E+00 O.00E+00 +/-25%

All O.00E+00 0.00E+00 0 .00E+00 +/-25%

Waste Stream : Sum of All 4 Categories Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 1.64E+03 4 .63E+01 2 .16E+00 +/-25%

B O.00E+00 0.00E+00 O.00E+0O +/-25%

C 0 .00E+00 0 .00E+00 O.00E+00 +/-25%

All 1 .64E+03 4.63E+01 2 . 16E+00 +/-25%

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 37 of 63 Annual Radioactive Effluent Release Report 5.5 Unit 3 Solid Waste - Destination by Carrier Number of Mode of Transportations Destination Shipments 1 Hittman Transport Energy Solutions - Bear Creek 1 Hittman Transport Erwin Resin Solutions LLC 5.6 Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Abundance Activity (C i)

H-3 27.87% 5.96E-01 C-14 5.05% 1.08E-01 Cr-51 7.48% 1.60E-01 Mn-54 0.79% 1.70E-02 Fe-55 1.30% 2.79E-02 Co-57 0.09% 1.82E-03 Co-58 21 .27% 4.55E-01 Co-60 3.24% 6.93E-02 Ni-59 0.44% 9.40E-03 Ni-63 22.82% 4.88E-01 Sr-89 0.04% 7.94E-04 Nb-95 0.10% 2.14E-03 Ag-110m 0.24% 5.12E-03 Sb-124 0.94% 2.02E-02 Sb-125 6.41% 1.37E-01 Te-123m 0.14% 3.04E-03 Cs-137 1.65% 3.52E-02 Ce-144 0.06% 1.36E-03 Pu-238 0.00% 3.25E-05 Pu-239 0.00% 7.68E-06 Pu-241 0.07% 1.51 E-03 Am-241 0.00% 2.91 E-05 Total 100.00% 2.14E+00 Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 38 of 63 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Total Combined Nuclide Name Percent Abundance Curies H-3 27.87% 5.96E-01 C-1 4 5.05% 1.0BE-01 Cr-51 7.48% 1.60E-01 Mn-54 0.79% 1.?0E-02 Fe-55 1.30% 2.79E-02 Co-57 0.09% 1.82E-03 Co-58 21.27% 4.55E-01 Co-60 3.24% 6.93E-02 Ni-59 0.44% 9.40E-03 Ni-63 22.82% 4.88E-01 Sr-89 0.04% 7.94E-04 Nb-95 0.10% 2.14E-03 Ag-110m 0.24% 5.12E-03 Sb-124 0.94% 2.02E-02 Sb-125 6.41% 1.37E-01 Te-123m 0.14% 3.04E-03 Cs-137 1.65% 3.52E-02 Ce-144 0.06% 1.36E-03 Pu-238 0.00% 3.25E-05 Pu-239 0.00% 7.68E-06 Pu-241 0.07% 1.51 E-03 Am-241 0.00% 2.91 E-05 Total 100.00% 2.14E+00 Note: For radionuc/ides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 39 of 63 Annual Radioactive Effluent Release Report Units 3 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 5.62% 1.31 E-03 Mn-54 0.44% 1.03E-04 Fe-55 12.82% 2.99E-03 Co-57 0.07% 1.61 E-05 Co-58 1.63% 3.80E-04 Co-60 10.63% 2.48E-03 Ni-63 57.87% 1.35E-02 Zr-95 0.14% 3.29E-05 Nb-94 0.06% 1.35E-05 Nb-95 0.26% 5.99E-05 Sb-125 1.25% 2.91 E-04 Cs-137 9.22% 2.15E-03 Total 100.00% 2.33E-02 Note: For radionuc/ides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped Units 3 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Total Combined Nuclide Name Percent Abundance Curies H-3 5.62% 1.31 E-03 Mn-54 0.44% 1.03E-04 Fe-55 12.82% 2.99E-03 Co-57 0.07% 1.61 E-05 Co-58 1.63% 3.S0E-04 Co-60 10.63% 2.48E-03 Ni-63 57 .87% 1.35E-02 Zr-95 0.14% 3.29E-05 Nb-94 0.06% 1.35E-05 Nb-95 0.26% 5.99E-05 Sb-125 1.25% 2.91 E-04 Cs-137 9.22% 2.15E-03 Total 100.00% 2.33E-02 Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 40 of 63 Annual Radioactive Effluent Release Re ort Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 27.65% 5.98E-01 C-14 4.99% 1.0BE-01 Cr-51 7.40% 1.60E-01 Mn-54 0.79% 1.71 E-02 Fe-55 1.43% 3.09E-02 Co-57 0.09% 1.84E-03 Co-58 21.04% 4.55E-01 Co-60 3.32% 7.17E-02 Ni-59 0.43% 9.40E-03 Ni-63 23 .21% 5.02E-01 Sr-89 0.04% 7.94E-04 Zr-95 0.00% 3.29E-05 Nb-94 0.00% 1.35E-05 Nb-95 0.10% 2.20E-03 Ag-110m 0.24% 5.12E-03 Sb-124 0.93% 2.02E-02 Sb-125 6.33% 1.37E-01 Te-123m 0.14% 3.04E-03 Cs-137 1.73% 3.74E-02 Ce-144 0.06% 1.36E-03 Pu-238 0.00% 3.25E-05 Pu-239 0.00% 7.68E-06 Pu-241 0.07% 1.51 E-03 Am-241 0.00% 2.91 E-05 Total 100.00% 2.16E+00 Note: For radionu clides H-3, C-14, Tc-99 an d l -129 if value is <MDA th en MDA is used to r eport Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 41 of 63 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories All Waste Classes Nuclide Name Percent Abundance Curies H-3 27.65% 5.98E-0 1 C-14 4.99% 1.08E-01 Cr-51 7.40% 1.60E-01 Mn-54 0. 79% 1.71 E-02 Fe-55 1.43% 3.09E-02 Co-57 0.09% 1.84E-03 Co-58 21 .04% 4.55E-01 Co-60 3.32% 7.17E-02 Ni-59 0.43% 9.40E-03 Ni-63 23.21 % 5.02E-01 Sr-89 0.04% 7.94E-04 Zr-95 0.00% 3.29E-05 Nb-94 0.00% 1.35E-05 Nb-95 0.10% 2.20E-03 Ag-110m 0.24% 5.12E-03 Sb-124 0.93% 2.02E-02 Sb-125 6.33% 1.37E-01 Te-123m 0.14% 3.04E-03 Cs-137 1.73% 3.74E-02 Ce-144 0.06% 1.36E-03 Pu-238 0.00% 3.25E-05 Pu-239 0.00% 7.68E-06 Pu-241 0.07% 1.51 E-03 Am-241 0.00% 2.91E-05 Total 100.00% 2.16E+00 Note: For radionuclides H-3, C-14, Tc-99 and /-129 if valu e is <MDA th en MDA is used t o report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 42 of 63 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN The Radiological Impact on Man due to radioactive effluent from the site is determined from NRC approved modeling , per Regulatory Guide 1.109 and NUREG 0133. Calculations are divided into 3 categories: Noble Gases, Particulates and Iodine, and Liquid Releases (fish and invertebrate consumption) . This modeling involves conservative dose calculations to Adult, Teen , Child , and Infant age groups. Furthermore, dose modeling is performed for six separate organs as well as the total body dose. This well-established industry model provides doses (as a result of plant effluent) to a hypothetical maximally exposed individual offsite. While all age groups and organs are considered , it is this maximum value that is provided in the tables that follow.

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

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

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

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

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

2 min/day

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

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 43 of 63 Annual Radioactive Effluent Release Re ort 6.3 40CFR Part 190 Dose to Individual in the Unrestricted Area Unit and pathway-specific dose data can be found on the Radiological Impact on Man tables following this discussion. For simplicity and to demonstrate compliance with 40CFR 190, the following table indicates the maximum hypothetical Total Dose to an individual from operation of the facility , including any measured direct shine component from the site property.

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

Routine Airborne Effluents Units 1 and 2 8.96E-04 8.63E-04 9.14E-04 Routine Liquid Effluents Units 1 and 2 4.07E-04 1.66E-04 5.24E-04 14 Liquid Releases of C Units 1 and 2 1.17E-03 1.17E-03 5.83E-03 14 Airborne Releases of C Units 1 and 2 2.14E-02 2.14E-02 1.0?E-01 1

Routine Airborne Effluents Unit 3 2.29E-03 2.27E-03 2.27E-03 Routine Liquid Effluents Unit 3 3.02E-04 1.44E-04 1.48E-03 14 Liquid Releases of C Unit 3 1.17E-03 1.1?E-03 5.83E-03 14 Airborne Releases of C Unit 3 6.75E-02 6.75E-02 3.38E-01 2

Ground Water & Storm Drain Totals IPEC 3.15E-05 2.22E-07 1.27E-04 Direct Shine from areas such as dry cask storage, radwaste storage, SG IPEC 3 3.00E-01 3.00E-01 3.00E-01 Mausoleum. etc.

Indian Point Energy Center IPEC 3.95E-01 3.95E-01 7.62E-01 Total Dose oer 40 CFR 190 Note 1: Routine airborne dose in this table is conservatively represented as a sum of Iodine, Particu late , and Tritium dose (exclud ing C-14, in mrem) with a mrem term added from noble gas gamma air energy (mrad ,

expressed as mrem). This 'addition ' does not represent a real dose and is listed here solely to help demonstrate compliance with 40CFR 190. (Doses by type of release and comparison to the specific limits of 10CFR50 Appendix I are summarized on the following pages. )

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

Note 3: 40CFR 190 requires the reporting of total dose, including that of direct shine. Direct shine dose from sources other than dry cask are indistinguishable from background . Direct shine dose is determined from TLDs near the dry cask area and site boundary, compared with REMP TLDs and historical values , and corrected with occupancy factors to determine a bounding , worst case assessment of direct shine dose to a real individual. Details of each year's dose evaluation are available on site .

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 44 of 63 Annual Radioactive Effluent Release Re ort Table 6-2 Unit 2 Appendix I Dose Assessment A LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Or an Dose (mrem) 1 :92E-04 1.01 E-04 9 .57E-05 1.60E-04 5.24E-04 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit 3.83E-03 2.03E-03 1.91 E-03 3 .19E-03 5.24E-03 Adult Child Adult Child Adult Liver Bone Liver Bone Liver Adult Total Bod (mrem) 1.62E-04 7.32E-05 6.93E-05 1.03E-04 4.07E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit 1.08E-02 4 .88E-03 4.62E-03 6 .84E-03 1.36E-02 Note: Liquid Annual dose is the Dose Analysis for the year, it is not a sum of the quarters 8 . Al RBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 1.58E-05 9 .10E-06 0 .00E+00 0 .00E+00 2.49E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit 3 .16E-04 1.82E-04 0 .00E+00 0 .00E+00 2.49E-04 Beta Air (mrad) 1.22E-05 2.15E-05 0 .00E+00 0.00E+00 3 .36E-05 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 1.22E-04 2.15E-04 0.00E+00 0 .00E+00 1.68E-04 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excludin C-14, for info onl )

Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 1.34E-04 4.30E-04 2.25E-04 1.25E-04 9 . 14E-04 A licable Limit (mrem) 7.5 7 .5 7 .5 7.5 15 Percent of Limit 1. 78E-03 5. 7 4E-03 3. 00E-03 1. 67E-03 6 . 09E-03 Child Child Child Child Child Liver Liver Liver Liver Liver D . AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Child TB Dose (mrem) 5.48E-03 5.74E-03 5.58E-03 5.47E-03 2 .23E-02 Applicable Limit mrem) 7 .5 7 .5 7 .5 7 .5 15 Percent of Limit (%) 7 .31E-02 7.65E-02 7.43E-02 7.30E-02 1.48E-01 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Child Bone Dose (mrem) 2 .68E-02 2.68E-02 2 .68E- 02 2 .68E-02 1.07E-01 Applicable Limit (mrem) 7 .5 7.5 7.5 7 .5 15 Percent of Limit (%) 3 .57E-01 3 .58E-01 3 .57E-01 3.57E-01 7.14E-01

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 45 of 63 Annual Radioactive Effluent Release Report Table 6-3 Unit 3 Appendix I Dose Assessment A LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Orqan Dose (mrem) 7 .25E-05 3.73E-05 7 .35E-04 6 .55E-04 1.48E-03 Aoolicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 1.45E-03 7.46E-04 1.47E-02 1.31 E-02 1.48E- 02 Age Group Adult Child Child Child Child Critical Organ GI-LLI Bone Bone Bone Bone Adult Total Body (mrem) 2.59E-05 1.33E- 05 8.50E-05 1.78E-04 3.02E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3 .0 Percent of Limit (%) 1.73E-03 8 .84E-04 5 .67E-03 1.19E-02 1.01 E-02 Note: Liquid Annual dose is the Dose Analysis for the year, it is not a sum of the quarters B . Al RBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 4 .34E-06 5 .54E-06 5 . 19E-06 5.41E-06 2 .05E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 8 .67E-05 1.11 E-04 1.04E-04 1.08E-04 2 .05E-04 Beta Air (mrad) 5 .33E-06 7 . 13E-06 7 .26E-06 6 .85E-06 2.66E-05 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 5 .33E-05 7.13E-05 7 .26E-05 6 .85E-05 1.33E-04 C . AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excludinq C-14, for info only)

Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 4 .97E-04 6 .80E-04 7 .00E-04 3 .97E-04 2 .27E-03 Applicable Limit (mrem) 7 .5 7 .5 7 .5 7 .5 15 Percent of Limit (%) 6 .63E-03 9 .06E-03 9 .33E-03 5 .29E-03 1.52E-02 Aqe Group Child Child Child Child Child Critical Organ Liver Liver Liver Liver Liver D . AIRBORNE IODINE, PARTICULATE , TRITIUM, and CARBON-14 DOSES Child TB Dose (mrem) 1.74E-02 1.76E-02 1.76E-02 1.73E-02 6 .98E-02 Applicable Limit (mrem) 7 .5 7.5 7 .5 7 .5 15 Percent of Limit (%) 2 .32E-01 2 .34E-01 2 .34E-01 2 .30E-01 4 .65E-01 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Child Bone Dose (mrem) 8.45E-02 8.45E-02 8.45E-02 8.45E-02 3.38E-01 Applicable Limit (mrem) 7 .5 7 .5 7 .5 7 .5 15 Percent of Limit (%) 1. 13E+00 1.13E+00 1.13E+00 1. 13E+00 2 .25E+O0

Indian Point Units 1, 2 & 3 YEAR: 2020 Page 46 of 63 Annual Radioactive Effluent Release Re ort 7.0 METEOROLOGICAL DATA The site meteorological data is maintained on-site and available for review.

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 47 of 63 Annual Radioactive Effluent Release Report - Carbon-14 Discussion Concentrations and offsite dose from C-14 were determined from sampling at Indian Point #3 from August 1980 to June 1982, during a study conducted by the NY State Department of Health (C. Kunz, later published and incorporated into NCRP 81) . The annual C-14 curies released , as determined from this study,.were consistent with NUREG 0017, Rev. 1. Data was then normalized to a maximum expected annual total, based on rated electrical capacity, (approximately 1000 MW(e) maintained for the entire year) . Once the curies released were established , dose calculations were performed per the station ODCM , which uses all C-14 released to determine inhalation doses, and 26% of the total (determined to be Carbon Dioxide form), to determine the ingestion doses, in accordance with Regulatory Guide 1.109.

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

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

Maximum (Bounding ) Annual C-14 releases from IPEC Unit 2 Unit 3 Liquid Effluent C14 Released Curies 0.07 0.07 Total Airborne C 14 Released Curies 11 .19 11.05 Airborne C 14 as CO2 Curies 2.91 2.87 Airborne Effluent Child TB Dose , C 14 mrem 0.0690 0.0675 Airborne Effluent Child Bone Dose , C 14 mrem 0.346 0.338 Liquid Effluent Child TB Dose , C 14 mrem 0.00117 0.00116 Liquid Effluent Child Bone Dose , C14 mrem 0.00583 0.00577 The bounding values were then normalized with actual effective full power days (EFFD) to yield more accurate year to year annual airborne curies and mrem for each unit. A small liquid effluent component is maintained at IPEC as a result of data accumulated in the 1983 study (Kunz). Tables 3-1 and 3-4 (shown earlier) include the airborne curie data for the current year. Section 6.0 (Radiological Impact on Man) includes the dose information.

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

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

Calculated Annual C-14 releases from IPEC , 2020 Unit 2 Unit 3 14 Airborne Effluent Child TB Dose, C mrem 0.0214 .0675 14 Airborne Effluent Child Bone Dose, C mrem 0.107 0.338 The airborne effluent dose from C-14 is distributed evenly over the year and applied to a total Iodine and Particulate dose in Tables 6-1 , 6-2 and 6-3.

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 48 of 63 Annual Radioactive Effluent Release Report - Groundwater Monitoring Program Results Summary of IPEC Groundwater and Storm Water Activity, 2020 The precipitation mass balance model applied in previous years was applied for offsite dose calculations in 2020, with some minor calibration updates performed in 2009 by the contractor with regard to the distribution of groundwater flow through the site. Groundwater elevation readings continued to validate the model throughout the year.

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

Historical average precipitation at IPEC has been approximately 3 feet per year. In 2011 , precipitation was unusually high (over 6 feet) . In 2020, precipitation was measured at 3.45 feet per year (or inches per month, as an average). Doses from Groundwater/Storm water are dependent on two factors:

source term and precipitation during the effected year.

Results of 2020 Groundwater and Storm water offsite dose evaluation The results of the assessment are shown below. These dose values are a small portion of the annual limits (<0.1%) and were added to the Total Dose table in the opening summary of the Radiological Impact to Man section of this report (Section 6).

Groundwater (GW) and storm water tritium released from IPEC in 2020 totaled approximately 0.04 curies, resulting in a total body dose of significantly less than 0.1 mrem. It is evident that tritium alone, whether from ground water or routine effluents, does not arithmetically contribute to integrated offsite dose.

Sampling near the effluent points identified only trace levels of Tritium and Strontium-90. These data, as part of the Monitored Natural Attenuation analyses , show a continuation of the decreasing trends established with the termination of the identified Unit 2 SFP leaks (tritium plume) and the defueling and draining of Unit 1 SFPs (strontium plume). Strontium-90, a legacy isotope from Unit 1, contributed approximately 0.000017 curies to site effluent from the groundwater pathway. Combined GW releases from IPEC in 2020 (all radionuclides) resulted in a calculated annual dose of less than 0.002 % of the annual limits for whole body and critical organ :

IPEC Groundwater and Storm Water Effluent Dose, 2020 0.0000315 mrem to the total body (0.0011 % limit) 0.000127 mrem to the critical organ , adult bone (0.0013% limit)

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

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 49 of 63 Annual Radioactive Effluent Release Report IPEC Summary for Storm & Ground Water Releases 2020 Northern Clean Zone Adult Doses, in mrem ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 4.54E-09 4.54E-09 4 .54E-09 4.54E-09 4.54E-09 4.54E-09 4.06E+02 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Ni-63 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+OO Sr-90 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Cs-137 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sb-125 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO totals 0.O0E+00 4.54E-09 4.54E-09 4 .54E-09 4.54E-09 4.54E-09 4.54E-09 4.06E+02 Unit 2 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 2.27E-08 2.27E-08 2.27E-08 2.27E-08 2.27E-08 2.27E-08 2.03E+03 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sb-125 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO totals 0.O0E+00 2.27E-08 2.27E-08 2.27E-08 2.27E-08 2.27E-08 2.27E-08 2.03E+03 Unit 1/2 ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 9.93E-08 9.93E-08 9.93E-08 9.93E-08 9.93E-08 9.93E-08 1.52E+04 Co-60 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Ni-63 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sr-90 1.27E-04 0.00E+00 3.12E-05 0.00E+00 0.00E+00 0.00E+00 3.67E-06 1.68E+01 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO totals 1.27E-04 9.93E-08 3.13E-05 9.93E-08 9.93E-08 9.93E-08 3.77E-06 1.52E+04 Unit 3 North ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 7.16E-08 7.16E-08 7.16E-08 7.16E-08 7.16E-08 7.16E-08 6.40E+03 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO totals 0.00E+00 7.16E-08 7.16E-08 7.16E-08 7.16E-08 7.16E-08 7.16E-08 6.40E+03 Unit 3 South ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI uCi H-3 0.00E+00 2.34E-08 2.34E-08 2.34E-08 2.34E-08 2.34E-08 2.34E-08 1.93E+04 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+OO totals 0.00E+00 2.34E-08 2.34E-08 2 .34E-08 2.34E-08 2.34E-08 2.34E-08 1.93E+04

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 50 of 63 Annual Radioactive Effluent Release Report Southern Clean Zone ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LU uCi H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E.+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 totals 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals: Adult Doses, in mrem Total H-3 only 0.00E+00 2.22E-07 2.22E-07 2 .22E-07 2.22E-07 2.22E-07 2.22E-07 uCis BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LU 4.33E+04 H3 all isotopes 1.27E-04 2.22E-07 3.15E-05 2.22E-07 2.22E-07 2.22E-07 3.89E-06 0.00E+00 Co 0.00E+00 Ni Adult Doses 1.6BE+01 Sr

% Annual Limit 0.00127 I 0.000 I 0.00105 I 0.000 I 0.000 I 0.000 I 0.000 I 0.00E+00 Cs 0.00E+00 Sb

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 51 of 63 Annual Radioactive Effluent Release Report - Laboratory Analytical Results The following pages list the results of the 2020 groundwater samples. Note that the positive results are shown in bold print.

2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

1-2 6/26/2020 2.22E+Ol 3.45E+02 0.5 1.6 -3.3 5.8 0.0 8.2 2.2 16.7 MH-5VCFD 1/14/2020 7.12E+02 4.08E+02 0.1 1.4 1.9 4.9 1.4 5.8 2.5 13.4 MH-5VCFD 2/10/2020 4.25E+02 3.15E+02 -0.2 1.2 1.9 7.1 3.7 7.3 -6.3 18.6 MH-5VCFD 3/10/2020 -3.07E-01 3.03E+02 -0.8 0.9 -0.6 5.0 0.2 5.2 -1.2 12.3 MH-5VCFD 6/3/2020 -l.38E+02 3.69E+02 0.2 1.7 0. 8 5.1 -3.2 5.5 1.3 13.7 MH-5VCFD 7/ 1/2020 <MDA MH-5VCFD 7/ 29/ 2020 3.08E+0l 3.75E+02 1.3 1.7 2.3 6.0 0.5 6.1 -5.6 14.9 MH-5VCFD 8/ 20/2020 2.30E+02 3.27E+02 -0.4 1.5 1.5 7.1 4.6 7.1 -1.0 16.5 MH-5VCFD 9/22/2020 <MDA MH-5VCFD 10/20/2020 <MDA MH-5VCFD 11/16/2020 5.39E+02 4.23E+02 -0.1 0.8 2.4 6.1 0.4 6.2 2.4 19.7 -7.5 15.4 MH-5VCFD 12/14/2020 6.00E+02 MW-107 5/ 21/2020 2.13E+02 3.72E+02 1.1 1.4 4.3 6.0 -2.9 6.3 12.1 16.2 MW- 111 1/13/2020 2.50E+03 MW-111 2/10/2020 2.30E+03 MW-111 3/9/2020 2.48E+03 4.95E+02 -0.2 1.4 - 1.0 4.7 -1.0 5.2 2.7 10.3 MW-111 5/ 26/2020 l .11E+04 9. 42E+02 0.8 1.0 1.3 5.9 -0.4 4.2 1.2 16.4 MW-111 6/30/2020 l.35E+04 MW-111 7/27/ 2020 4.10E+03 MW-111 8/24/2020 2.02E+03 4. 86E+02 -0.3 1.5 0.0 11.7 0.2 5.2 -5.6 16.8 MW-111 9/ 21/2020 2.30E+03 MW-111 10/19/2020 8.00E+02 MW-111 11/16/ 2020 8.22E+02 4.08E+02 0.5 1.6 0.3 5.3 -1.1 5.3 10.4 14.6 MW-111 12/14/2020 <MDA MW-30-71 3/13/ 2020 1.09E+05 MW-30-71 8/27/2020 4.45E+04 MW-30-71 11/6/2020 3.44E+04 MW-30-71 12/16/2020 6.56E+04 MW-30-84 1/15/2020 7.0SE+04 2.32E+03 0.8 1.7 3.4 4.0 0.8 5.3 0.1 12.9 MW-30-84 2/ 17/2020 7.65E+04 l .91E+03 0.0 1.6 -0.7 6.2 -0.8 6.8 1.8 15.7 MW-30-84 3/13/2020 6.80E+04 2.07E+03 1.4 1.4 -0.1 6.2 0.6 6.7 4.0 13.7 MW-30-84 6/10/2020 7.95E+04 2.42E+03 0.4 1.5 1.4 5.7 2.0 5.4 -0.8 12.7 MW-30-84 7/2/ 2020 7.76E+04 2.17E+03 -0.5 1.5 0.7 6.8 -2.9 6.1 -4.4 15.3 MW-30-84 7/30/ 2020 7.22E+04 2.11E+03 0.8 1.8 1.8 5.6 -1.3 7.4 -10.5 12.4 MW-30-84 8/ 27/2020 7.53E+04 2.03E+03 1.1 1.7 -0.4 3.6 1.9 4.5 -1.8 10.7 MW-30-84 11/6/ 2020 7.86E+04 3.15E+03 0.4 1.6 0.0 6. 4 -0.1 4. 8 -3.1 13.5 MW-30-84 12/ 16/2020 7.07E+04 2.63E+03 -0.1 1.6 -1.5 5.6 4.8 6.3 -3.1 14.2 MW-31-49 3/ 9/ 2020 3.20E+03 5.37E+02 0.8 1.5 -1.7 6.9 -2.7 6.2 -0.8 19.5 MW-31-49 6/3/ 2020 l.80E+03 4.86E+02 0.7 1.5 5.1 9.4 -0.2 6.1 10.3 16.1 MW-31-49 8/31/2020 5.42E+03 6.12E+02 -1.1 1.3 1.6 6.5 0.5 7.4 0.1 15.9

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 52 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb- 125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-31-49 11/13/ 2020 9.70E+03 8.46E+02 -0.4 1.5 2.6 6.6 -2.0 6.7 0.1 16.3 MW-31-63 1/13/2020 2.24E+04 l.07E+03 -0.6 1.2 -0.8 5.8 1.2 7.6 37.9 25.9 MW-31-63 2/10/2020 3.30E+04 l .30E+03 0.5 1.3 3.2 5.3 -1.4 5.0 30.6 27.1 MW-31-63 3/9/2020 3.51E+04 1.49E+03 0.5 1.4 -0.7 5.9 -1.8 7.0 28.9 31.8 MW-31-63 6/3/2020 2.63E+04 l .39E+03 1.5 1.8 2.7 5.3 -3.7 7.1 0.0 28.7 MW-31-63 7/2/2020 2.96E+04 1.38E+03 0.3 1.5 -0.7 5.8 -0.3 4.7 0.0 32.4 MW-31-63 7/30/2020 2.88E+04 l.34E+03 0.2 1.6 5.7 9.4 12.2 10.8 14.4 30.6 MW-31-63 8/31/2020 4.12E+04 l.93E+03 0.2 1.6 -1.5 4.3 0.4 4.6 19.4 25.1 MW-31-63 9/25/2020 4 .15E+04 1.71E+03 0.1 1.6 4.1 8.0 -3.5 8.2 15.3 18.4 MW-31-63 10/20/2020 3.83E+04 l.79E+03 0.2 1.6 -0.4 3.5 0.0 4.1 0.0 19.4 MW-31-63 11/13/2020 3.37E+04 l.50E+03 -0.1 1.5 1.4 4.8 2.5 6.2 30.1 27.0 MW-31-63 12/15/2020 2.78E+04 1.67E+03 -0.6 1.5 0.0 17.3 -2.2 6.3 18.1 36.0 MW-31-85 3/9/ 2020 8.55E+03 7.77E+02 0.4 1.4 -0.3 5.4 3.8 5.1 -0.5 14.6 MW-31-85 6/3/2020 6.07E+03 7.44E+02 -0.3 1.4 4.3 11.8 0.7 6.2 8.4 13.8 MW-31-85 8/31/2020 9.03E+03 9.78E+02 1.2 1.7 -0.2 4.9 -1.9 4.4 8.7 13.7 MW-31-85 11/13/ 2020 l.01E+04 8.76E+02 0.4 1.4 -1.1 4.2 -5.0 6.8 12.6 13.4 MW 149 3/13/ 2020 3.50E+02 2.88E+02 0.8 1.5 0.2 5.8 2.7 6.5 -0.4 14.6 MW-32-149 6/1/2020 -2.04E+02 4.08E+02 -0.2 1.5 0.8 4.4 -0.7 4.4 - 1.0 11.9 MW-32-149 8/26/2020 6.87E+02 3.75E+02 0.5 1.6 0.8 5.7 3.1 5.8 -3.4 14.0 MW-32-149 11/13/2020 1.12E+04 MW-32-173 3/13/ 2020 2.63E+02 3.09E+02 0.9 1.3 -2.8 7.0 -1.2 6.0 4.6 15.7 MW-32-173 6/1/2020 -1.73E+0l 4.29E+02 -0.6 1.4 0.1 6.1 -4.8 6.6 -0.3 12.2 MW-32-173 8/26/2020 l .04E+02 3.30E+02 0.3 1.7 0.1 4.9 -0.7 5.6 -0.8 11.2 MW-32-173 11/13/2020 6.55E+03 4.05E+02 1.7 1.9 1.9 5.7 2.3 7.5 7.5 15.2 MW 173 12/29/2020 3.67E+02 3.45E+02 1.6 1.6 -1.4 5.9 1.8 6.9 -7.0 14.4 MW-32-190 3/13/2020 4.84E+02 2.99E+02 -0.5 1.5 0.0 5.6 -1.0 6.1 3.8 12.6 MW-32-190 6/1/2020 l .83E+02 3.72E+02 -0.6 1.6 2.1 5.6 2.9 7.1 -2.8 13.7 MW-32-190 8/26/2020 3.37E+02 3.39E+02 0.8 1.7 -2.3 4.9 2.2 5.3 -0.1 13.0 MW-32-190 11/13/2020 2.99E+02 4.14E+02 0.2 1.4 -0.6 5.6 0.2 6.3 5.6 14.5 MW-32-59 1/14/2020 2.63E+04 l.43E+03 1.1 1.8 1.2 7.6 3.3 5.6 0.0 26.3 MW-32-59 2/11/2020 2.99E+04 l.22E+03 0.5 1.6 -1.4 5.6 1.7 5.6 47.2 28.4 MW-32-59 3/12/2020 3.99E+04 l.60E+03 -0.8 1.0 -2.4 5.4 0.0 5.4 65.5 25.9 MW-32-59 6/1/2020 4.39E+04 l .89E+03 -0.1 1.4 0.0 10.3 3.1 7.5 0.0 29.7 MW-32-59 7/2/2020 5.04E+04 l.79E+03 -0.9 1.6 -1.0 4.8 2.4 4.1 56.3 30.3 MW-32-59 7/30/ 2020 4.09E+04 l.56E+03 0.1 1.7 1.0 5.9 3.7 8.2 0.0 34.8 MW-32-59 8/26/2020 3.94E+04 1.54E+03 0.0 1.7 -1.5 5.5 - 1.1 5.0 30.9 27.4 MW-32-59 9/25/2020 4 .43E+04 l.76E+03 -0.5 1.5 0.7 5.2 3.2 6.6 43.0 25.4 MW-32-59 10/20/2020 3.57E+04 1.68E+03 -0.3 0.9 1.8 5.3 -1.2 5.3 31.1 25.4 MW-32-59 11/13/2020 4.73E+04 1.85E+03 1.0 1.8 2.8 5.1 -0.3 4.5 43.8 27.7 MW-32-59 12/29/2020 2.29E+03 4.89E+02 -0.2 1.6 -0.7 5.1 -1.1 4.7 29.1 21.8 MW-32-85 1/14/2020 2.44E+04 l .40E+03 -0.4 1.1 -2.1 5.6 1.3 6.0 0.0 13.9 MW-32-85 2/11/2020 2.47E+04 l.14E+03 0.7 1.8 -0.7 6.9 1.6 7.4 5.6 15.2

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 53 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-32-85 3/11/2020 2.37E+04 l.25E+03 -0.8 1.1 -2.0 6.3 0.2 6.5 -1.4 17.6 MW-32-85 6/1/2020 3.21E+04 l.64E+03 0.6 1.7 2.4 4.5 -1.4 6.5 -0.2 11.6 MW-32-85 7/2/2020 2.42E+04 l .26E+03 0.7 1.7 -1.3 5.9 5.7 5.5 -3.7 16.5 MW-32-85 7/30/2020 2.38E+04 1.22E+03 -0.3 1.6 3.1 5.1 1.0 6.6 0.6 17.5 MW-32-85 8/26/2020 2.51E+04 l.19E+03 0.6 1.7 1.0 5.0 -1.6 5.1 -1.8 14.3 MW-32-85 9/25/2020 2.49E+04 l.35E+03 -0.4 1.5 1.4 4.8 -0.2 5.6 5.6 14.9 MW-32-85 10/20/2020 2.66E+04 l.48E+03 -0.3 1.6 -0.9 4.4 4.8 5.7 -3.9 10.3 MW-32-85 11/13/2020 2.59E+04 l .43E+03 0.8 1.5 2.9 6.3 -3.4 12.6 -1.0 17.5 MW-32-85 12/29/2020 2.76E+04 l .73E+03 -0.8 1.4 -1.8 6.8 2.2 5.8 -5.7 13.1 MW-33 1/13/2020 7.93E+03 6.54E+02 1.4 1.9 3.5 7.4 0.3 6.3 -10.6 13.6 MW-33 2/10/2020 l.25E+04 8.22E+02 -0.5 1.1 0.9 4.5 1.2 5.1 2.1 12.3 MW-33 3/9/2020 8.60E+03 7.68E+02 0.4 1.5 -2.5 6.8 -2.1 5.8 5.6 16.4 MW-33 5/26/2020 2.18E+04 l.25E+03 0.0 1.2 2.2 4.8 -1.8 6.7 -3.9 12.7 MW-33 6/30/2020 l.51E+04 MW-33 7/27/2020 1.50E+04 MW-33 8/24/2020 l.05E+04 8.37E+02 -0.3 1.6 -1. 3 5.4 -0.3 5.4 -4.5 12.3 MW-33 9/21/2020 8.90E+03 MW-33 10/19/2020 9.40E+03 MW-33 11/16/2020 4.08E+03 6.09E+02 1.2 1.8 -2.3 6.2 -1.1 5.0 2.6 13.9 MW-33 12/14/2020 5.20E+03 MW-35 1/13/2020 l.20E+03 3.57E+02 0.9 1.8 0.5 7.7 -0.2 5.9 6.3 18.4 MW-35 2/10/2020 l.13E+03 3.63E+02 0.5 1.5 -0.1 7.2 0.3 6.5 12.8 16.9 MW-35 3/9/2020 5.42E+02 3.57E+02 -0.5 1.2 -1.2 5.0 -3.6 6.9 8.8 13.4 MW-35 5/26/2020 l.38E+03 4.59E+02 0.6 1.1 4.9 8.2 4.1 10.8 3.7 14.1 MW-35 6/30/2020 1.22E+03 4.65E+02 -0.3 1.6 -4.0 7.8 3.4 6.7 -0.4 16.7 MW-35 7/27/2020 6.96E+02 4.32E+02 -0.3 1.6 -1.1 5.5 1.5 7.5 -6.6 17.2 MW-35 8/24/2020 6.76E+02 3.84E+02 0.7 1.7 -1.4 4.2 0.2 4.8 0.8 11.6 MW-35 9/21/2020 6.50E+02 3.90E+02 0.6 1.7 2.2 6.5 0.5 7.0 -4.7 13.4 MW-35 10/19/2020 3.12E+02 4.47E+02 -0.2 1.2 3.3 6.6 5.6 5.2 -5.2 16.5 MW-35 11/16/2020 2.86E+02 3.45E+02 -0.3 1.3 -1.6 5.5 0.7 5.6 3.3 12.0 MW-35 12/14/2020 5.03E+02 2.95E+02 0.2 1.5 0.0 12.3 -1.7 6.4 10.0 14.7 MW-36-24 3/4/2020 3.29E+02 3.21E+02 0.9 1.3 -0.2 5.9 -2.3 5.3 -7.4 14.2 MW-36-24 6/18/2020 8.45E+02 4.38E+02 1.4 1.7 2.0 5.7 -0.9 6.5 0.1 15.8 MW-36-24 8/27/2020 1.40E+03 4.29E+02 -0.6 1.4 -1.1 4.7 0.9 6.0 0.6 14.4 MW-36-24 11/11/2020 2.40E+03 7.11E+02 0.6 1.7 0.6 4.2 2.4 3.6 0.9 10.9 MW-36-41 3/4/2020 4.14E+03 5.76E+02 2.8 1.4 1.1 5.6 2.9 6.6 -9.2 15.9 MW-36-41 6/18/2020 7.28E+03 7.77E+02 4.1 2.0 -1.0 7.7 -0.5 6.9 5.2 11.7 MW-36-41 8/27/2020 5.67E+03 6.69E+02 2.0 1.9 0.2 5.9 -2.6 6.4 1.0 12.7 MW-36-41 11/11/2020 5.30E+03 9.30E+02 4.2 2.2 0.5 5.5 1.3 6.8 -3. 6 16.9 MW-36-52 3/4/2020 3.60E+03 7.32E+02 2.5 1.4 -0.7 7.1 2.4 7.2 -1.8 16.7 MW-36-52 6/18/2020 6.44E+03 7.47E+02 4.6 2.1 -1.3 6.3 1.1 5.6 7.3 14.1 MW-36-52 8/27/2020 6.67E+03 6.84E+02 3.0 2.1 -2.3 6.5 2.3 7.6 -2.8 14.6

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 54 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Sample Date 3 Well ID 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-36--52 11/11/2020 6.0SE+03 9.81E+02 3.0 2.0 -4.1 6.3 -0.2 5.6 1.4 13.3 MW-37-22 6/5/2020 3.71E+03 7.56E+02 4.0 2.2 0.0 9.5 0.4 6.9 -8.4 16.8 MW-37-22 11/11/2020 3.94E+03 8.49E+02 5.6 2.1 5.1 8.1 2.4 7.4 -7.1 11.8 MW-37-32 6/5/2020 5.08E+03 8.58E+02 7.2 2.5 5.5 6.8 1.9 6.4 0.7 17.5 MW-37-32 11/11/2020 5.29E+03 9.69E+02 7.6 2.8 0.7 5.1 -0.1 4.4 1.8 11.9 MW-37-40 6/5/2020 4.79E+03 8.40E+02 10.2 2.9 0.0 5.7 -1.1 7.1 -3.1 14.9 MW-37-40 11/11/2020 5.06E+03 9.06E+02 8.2 2.7 0.6 4.3 0.4 4.8 -5.8 10.9 MW-37-57 6/5/2020 4.79E+03 8.28E+02 10.3 3.0 1.9 7.9 -4.7 6.7 3.5 13.1 MW-37-57 11/11/2020 4.71E+03 9.03E+02 7.1 2.7 -0.9 5.9 -0.7 4.7 -2.5 13.5 MW-39-102 6/23/2020 1.77E+02 3.81E+02 0.1 1.4 - 1.0 5.9 1.6 6.3 -0.9 19.0 MW-39-102 11/17/2020 2.13E+02 3.51E+02 0.8 1.7 2.3 5.2 2.0 6.8 -0.7 15.1 MW-39-183 6/23/2020 l .99E+02 3.90E+02 1.1 1.3 -6.9 8.2 -0.5 7.7 6.6 15.4 MW-39-183 11/17/2020 8.45E+Ol 3.36E+02 0.2 1.4 0.0 8.2 0.9 4.1 -0.2 11.9 MW-39-195 6/23/2020 5.32E+Ol 3.93E+02 0.4 1.6 2.5 5.9 5.1 6.0 7.9 13.8 MW-39-195 11/17/2020 -l.36E+0l 3.18E+02 0.5 1.7 0.5 7.2 -1.0 6.6 -1.0 16.5 MW-39-67 6/23/2020 2.92E+02 4.08E+02 0.5 1.2 -1.0 5.6 -0.9 6.4 -2.0 15.1 MW-39-67 11/17/2020 7.75E+0l 3.36E+02 1.2 1.7 -0.3 6.8 1.8 7.3 -1.2 18.5 MW-39-84 6/23/2020 2.71E+02 3.84E+02 0.6 1.5 0.5 5.6 -3.1 5.2 -2.0 12.2 MW-39-84 11/17/2020 l .40E+02 3.45E+02 1.6 1.8 -4.3 6.7 1.5 6.3 5.8 16.6 MW-40-100 5/22/2020 -2.95E+0l 3.33E+02 0.0 1.1 -0.2 5.5 -1.5 5.3 -9.6 14.0 MW-40-100 8/20/2020 -l.78E+02 3.09E+02 1.4 1.8 0.0 6.5 -0.9 7.0 1.4 15.3 MW-40-100 11/19/2020 -1.07E+0l 3.33E+02 0.7 1.7 -3.0 7.5 -1.2 8.2 3.2 16.1 MW-40-127 5/22/2020 1.85E+0l 3.48E+02 0.3 1.0 -2.1 6.5 -2.1 7.0 7.5 18.0 MW-40-127 8/20/2020 -5.14E+0l 3.09E+02 1.2 1.8 3.1 6.3 4.3 7.0 -0.9 20.0 MW-40-127 11/19/2020 l .06E+02 3.39E+02 -1.3 1.4 0.7 5.1 -2.0 5.0 11.6 21.5 MW-40-162 5/22/2020 7.37E+0l 3.36E+02 -0.2 1.3 4.4 6.5 0.9 7.4 3.2 16.5 MW-40-162 8/20/2020 -2.18E+02 3.21E+02 0.5 1.7 -3.0 7.3 2.4 5.9 5.6 13.4 MW-40-162 11/19/2020 - l.02E+0l 3.33E+02 -0.8 1.5 2.7 5.3 0.8 4.8 -2.8 11.5 MW-40-27 5/22/2020 l .38E+02 3.57E+02 -0.5 0.8 2.5 4.7 2.7 6.2 1.9 15.2 MW-40-27 8/20/2020 -l.21E+02 3.48E+02 1.1 1.8 -1.4 5.8 0.0 6.3 -2.0 14.8 MW-40-27 11/19/2020 l .05E+Ol 3.24E+02 1.3 1.8 - 2.0 6.3 1.4 6.3 -6.0 13.3 MW-40-46 5/22/2020 3.68E+0l 3.54E+02 0.5 1.3 3.1 5.7 -0.5 5.6 1.3 15.8 MW-40-46 8/20/2020 1.67E+02 3.57E+02 1.3 1.8 0.1 6.1 3.0 6.9 -1.1 13.7 MW-40-46 11/19/2020 8.82E+OO 3.06E+02 0.4 1.6 -0.9 6.9 -1.0 5.1 -6.6 17.6 MW-40-81 5/22/2020 1.21E+02 3.63E+02 0.0 0.8 -3.0 5.9 -7.2 11.0 5.4 34.2 MW-40-81 8/20/2020 -8.35E+0l 3.21E+02 -0.8 1.4 0.2 6.4 1.1 5.8 -4.8 14.9 MW-40-81 11/19/2020 5.04E+0l 3.39E+02 0.1 1.6 1.4 5.6 -2.6 6.4 5.3 15.5 MW-41-40 3/2/2020 2.00E+02 2.85E+02 0.9 1.4 0.7 7.7 1.3 5.2 1.9 12.4 MW-41-40 4/6/2020 3.55E+02 3.84E+02 0.4 1.2 -2.0 6.7 -1.7 5.6 3.3 12.4 MW-41-40 5/28/2020 -4.28E+OO 3.87E+02 -0.5 1.6 4.2 5.1 -3.0 6.4 -1.9 12.4 MW-41-40 8/17/2020 8.27E+02 4.23E+02 0.8 1.8 -3.4 6.9 -0.1 5.9 -0.9 14.3 MW-41-40 11/9/2020 3.73E+02 3.75E+02 -0.3 1.5 -1.2 5.4 0.0 5.1 6.8 23.7 -1.1 13.2

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 55 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-41-63 3/3/2020 l .32E+02 4.14E+02 1.6 1.8 0.8 5.8 -0.3 7.3 1.4 16.4 -2.4 12.7 MW-41-63 4/7/2020 2.33E+02 3.60E+02 -0.7 1. 7 -0.3 6.2 -0.5 5.8 -4.5 19.7 -0.9 16.6 MW-41-63 5/28/2020 6.50E+0l 3.93E+02 0.6 1.7 -1.0 6.8 -0.8 6.4 5.3 20.9 -0.5 16.4 MW-41-63 8/17/2020 l.19E+0l 3.75E+02 0.7 1.7 2.1 5.9 -0.9 5.0 1.0 19.7 0.5 15.1 MW-41-63 12/23/2020 4.01E+02 4.26E+02 -0.5 1.5 3.3 4.9 1.2 4.1 5.3 18.4 2.1 13.1 MW-42-49 1/14/ 2020 l.90E+02 3.45E+02 26.0 3.0 39300 336 -3.6 6.7 667 40 -12.5 144.3 MW-42-49 2/ 11/2020 l.12E+02 3.30E+02 35.5 5.0 61100 384 3.0 9.2 921 51 -16.4 162.0 MW-42-49 3/10/2020 l.85E+02 3.39E+02 35.5 5.6 54800 345 1.6 4.5 687 47 5.2 126.9 MW-42-49 5/27/2020 4.54E+02 3.90E+02 21.7 3.6 39400 309 -1.3 5.4 586 45 -71.9 134.1 MW-42-49 6/30/2020 7.19E+02 4.23E+02 41.1 4.3 69250 393 3.0 6.3 1185 68 67.6 162.9 MW-42-49 7/29/2020 5.62E+02 4.17E+02 20.4 4.1 43000 306 1.1 3.8 539 48 -33.5 113.7 MW-42-49 8/28/2020 4.54E+02 4.05E+02 13.6 2.8 38100 287 0.7 4.6 558 51 -9.7 109.8 MW-42-49 9/21/2020 6.68E+02 3.87E+02 27.4 3.0 63000 366 1.1 4.7 996 51 8.3 135.6 MW-42-49 10/19/2020 3.35E+02 4.38E+02 10.6 2.7 50500 363 2.9 5.7 682 45 32.9 143.4 MW-42-49 11/10/2020 5.22E+02 4.20E+02 9.9 2.0 44700 357 -0.2 6.2 643 41 -17.5 139.8 MW-42-49 12/15/2020 3.76E+02 4.05E+02 8.5 2.8 35400 272 0.6 4.4 417 38 8.9 103.5 MW-42-78 3/ 10/ 2020 6.63E+02 3.66E+02 -0.8 1.0 -2.1 6.3 -2. 5 5.2 -1.5 16.4 7.6 17.5 MW-42-78 5/27/2020 4.96E+02 3.87E+02 0.7 1.7 2.9 5.6 1.1 6.2 1.6 21.2 0.1 13.5 MW-42-78 8/28/2020 3.06E+02 4.05E+02 0.9 1.3 -1.3 4.6 1.9 5.2 -2.3 17.3 4.5 11.0 MW-42-78 11/10/2020 l.13E+03 5.82E+02 0.3 1.6 -0.3 6.5 -1. 2 5.5 12.9 20.3 -7.7 13.9 MW-43-28 3/2/2020 1.65E+02 3.06E+02 0.2 1.5 -1.1 5.5 -1.1 5.1 -2.0 13.1 MW-43-28 4/6/ 2020 1.53E+02 3.75E+02 0.1 0.5 1.4 5.4 1.6 5.3 -4. 2 11.4 MW-43-28 6/2/2020 3.32E+02 4.62E+02 -0.2 1.5 2.4 6.4 5.1 5.7 -0.7 13.7 MW-43-62 3/ 2/2020 4.63E+Ol 3.03E+02 -0.1 1.2 -1.4 6.3 0.6 5.4 1.3 14.8 MW-43-62 4/6/2020 3.l0E+0l 3.60E+02 0.1 0.6 -0.3 5.2 -1.6 5.0 -8.1 15.4 MW-43-62 6/2/2020 1.33E+02 4.35E+02 -0.9 1.2 -1.4 6.5 0.0 4.7 5.3 17.4 MW-44-102 6/19/2020 2.40E+02 3.66E+02 -0.2 1.3 1.8 5.7 2.4 7.7 2.8 15.5 MW-44-102 11/23/ 2020 1.87E+02 3.36E+02 -0.1 1.6 1.6 5.0 -1.8 4.8 0.8 11.9 MW-44-66 6/19/2020 3.25E+02 3.57E+02 0.8 1.6 0.8 4.8 -2.7 5.7 - 1.8 13.3 MW-44-66 11/23/2020 l.32E+02 3.45E+02 1.1 1.8 3.0 5.6 -1.8 6.4 -1.1 13.5 MW-45-42 3/2/2020 l.05E+03 3.78E+02 1.3 1.5 2.8 6.9 3.9 7.2 6.0 18.9 MW-45-42 4/6/2020 3.48E+03 5.79E+02 0.4 0.6 2.2 7.5 1.7 7.9 6.1 14. 8 MW-45-42 5/28/2020 2.22E+03 6.24E+02 0.8 1.7 0.0 15.0 -0.1 4.5 -1.5 13.2 MW-45-42 8/17/2020 2.64E+03 5.31E+02 -1.2 1.2 0.4 5.3 5.0 5.6 -6.9 17.6 MW-45-42 11/9/2020 3.07E+03 7.71E+02 0.9 1.7 -1.6 6.2 0.3 5.4 0.6 14.5 MW-45-61 3/2/2020 6.98E+02 3.60E+02 0.6 1.3 -1.9 5.6 2.9 4.5 -2.5 11.5 MW-45-61 4/6/2020 1.21E+03 4.65E+02 0.4 1.3 -4.0 6.0 5.3 5.5 3.3 13.0 MW-45-61 5/28/2020 9.26E+02 4.95E+02 1.2 1.6 -0.1 5.6 -0.3 8.0 -5.0 14.8 MW-45-61 8/17/2020 1.31E+03 4.71E+02 -0.5 1.4 -0.3 5.0 -0.6 4.9 10.0 12.3 MW-45-61 11/9/2020 1.25E+03 4.29E+02 -0.2 0.9 1.5 8.0 -2.0 7.4 1.7 20.9 MW-46 1/28/2020 7.19E+0l 3.06E+02 0.0 1.3 -1.2 5.1 -0.1 5.9 -4.4 11.7 MW-46 4/7/2020 2.11E+02 3.57E+02 0.3 1.4 -0.2 4.9 2.9 5.3 1.7 13.1

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 56 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L} Sr-90 (pCi/L} Cs-137 (pCi/L} Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std . (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-46 5/29/2020 -1.37E+02 3.60E+0i 0.0 1.4 -1.7 5.4 -2.2 5.4 1.5 15.0 MW-46 8/18/2020 4.18E+02 3.99E+02 0.3 1.6 1.7 5.3 -0.2 7.2 -1.9 17.3 MW-46 11/5/2020 7.33E+02 4.17E+02 0.7 1.3 1.3 6.7 1.2 6.2 -2.4 15.5 MW-49-26 6/15/2020 4.80E+03 7.11E+02 8.4 2.5 -0.3 5.9 1.3 7.1 1.7 21.8 4.8 16.2 MW-49-26 10/27/2020 3.73E+03 6.99E+02 8.2 2.3 -3.6 6.8 1.9 5.2 6.3 19.3 -6.7 16.2 MW-49-42 6/15/2020 4.00E+03 6.81E+02 8.7 2.4 -1.4 6.9 3.6 8.1 9.2 22.0 12.4 17.5 MW-49-42 10/27/2020 2.68E+03 6.30E+02 9.7 2.6 -1.0 4.7 -3.6 4.7 -3.4 18.8 4.4 11.5 MW-49-65 6/15/2020 3.49E+03 6.33E+02 5.5 2.1 2.8 10.5 1.3 7.4 5.3 21.4 -2.4 15.9 MW-49-65 10/27/2020 2.36E+03 6.12E+02 5.2 1.7 -2.1 5.9 0.5 5.3 -10.9 20.9 -3.1 16.4 MW-50-42 3/4/2020 5.22E+02 3.63E+02 1.1 1.1 -3.5 7.5 -1.2 5.8 6.0 22.1 -4.3 12.0 MW-50-42 6/16/2020 1.55E+03 4.74E+02 5.1 2.3 2.5 6.4 -0.6 5.4 -16.6 26.2 5.4 18.3 MW-50-42 9/2/2020 l .75E+03 5.07E+02 3.8 2.3 0.0 5.6 3.9 6.5 3.2 17.1 -7.2 13.9 MW-50-42 11/11/2020 1.53E+03 6.09E+02 3.4 2.1 -1.6 5.8 -0.2 4.8 6.8 22.2 -4. 2 18.1 I

MW-50-66 3/4/2020 4.25E+03 7.47E+02 13.0 2.8 2.3 5.7 1.3 5.0 -3.6 20.2 -2.4 13.4 MW-50-66 6/16/2020 3.89E+03 6.00E+02 13.8 3.2 0.8 6.6 -1.7 5.0 -7.0 15.3 -6.2 18.3 MW-50-66 9/2/2020 2.90E+03 8.13E+02 9.4 2.8 -3.0 4.8 0.4 5.6 3.1 18.0 0.3 11.4 MW-50-66 11/11/2020 3.01E+03 7.62E+02 12.7 3.3 1.1 4.2 2.2 5.0 8.3 21.1 -3.7 10.1 MW-51-104 3/6/2020 1.31E+02 3.12E+02 -0.8 1.2 4.6 9.3 -2.5 5.8 0.0 14.4 MW-51-104 5/21/2020 1.96E+02 3.69E+02 -0.7 1.1 1.0 5.4 0.9 6.7 2.6 14.1 MW-51-104 8/21/2020 -1.10E+02 3.72E+02 0.6 1.5 -1.3 5.1 -1.3 4.4 -1.6 11.9 MW-51-104 11/19/2020 1.02E+02 3.42E+02 1. 7 1.9 0.4 4.1 1.9 4.2 3.8 12.8 MW-51-135 3/6/2020 3.23E-03 3.06E+02 -0.8 1.4 3.8 7.3 4.7 8.4 4.6 20.4 MW-51-135 5/21/2020 4.97E+0l 3.51E+02 0.4 1.6 3.8 6.4 1.7 5.7 4.9 17.0 MW-51-135 8/21/2020 -3.03E+02 3.51E+02 0.6 0.9 1.4 5.7 1.8 7.5 4.5 16.5 MW-51-135 11/19/2020 1.39E+02 3.48E+02 0.1 1.6 -0.8 6.2 2.0 6.2 -2.5 14.2 MW-51-163 3/6/2020 8.07E+0l 3.18E+02 -0.9 1.3 0.3 6.8 1.5 6.3 0.7 16.7 MW-51-163 5/21/2020 -3.03E+0l 3.51E+02 0.4 1.3 2.5 8.5 1.9 7.0 3.2 12.8 MW-51-163 8/21/2020 -3.57E+0l 2.76E+02 1.2 1.8 -0.2 7.5 2.1 7.6 -2.9 18.6 MW-51-163 11/19/2020 l.07E+02 3.45E+02 0.5 1.7 -0.1 5.4 -3.3 11.3 0.1 10.9 MW-51-189 3/6/2020 - l.99E+0l 2.99E+02 -0.5 1.4 -0.7 4.7 4.5 5.6 2.8 12.2 MW-51-189 5/21/2020 -1.07E+02 3.36E+02 -0.5 1.1 -0.6 6.2 -4.4 7.5 2.0 14.0 MW-51-189 8/21/2020 8.47E+0l 3.15E+02 0.6 1.7 -0.3 5.7 5.1 4.9 -8.3 17.1 MW-51-189 11/19/2020 3.38E+Ol 3.39E+02 0.4 1.7 -1.3 7.1 1.6 5.6 -7.1 17.5 MW-51-40 3/6/2020 -4.56E+0l 3.00E+02 0.0 1.5 3.3 5.1 0.3 5.0 -5.0 13.0 MW-51-40 5/21/2020 2.04E+02 3.60E+02 0.8 1.3 4.3 5.0 3.9 8.0 0.2 13.4 MW-51-40 8/21/2020 -3.29E+02 3.69E+02 -0.9 1.4 1.5 6.3 -0.9 7.4 -8.5 17.2 MW-51-40 11/19/2020 2.58E+02 3.57E+02 0.2 1.6 -0.4 5.7 3.4 8.0 8.7 17.1 MW-51-79 3/6/2020 8.87E+Ol 3.03E+02 -0.1 1.5 0.0 7.9 2.7 5.6 -2.7 13.8 MW-51-79 5/21/2020 4.27E+0l 3.54E+02 0.3 1.2 -0.3 6.1 0.9 4.6 -1.4 15.6 MW-51-79 8/21/ 2020 -6.61E+0l 2.83E+02 0.8 1.7 4.3 6.7 1.1 7.1 -7.4 14.8 MW-51-79 11/19/2020 9.30E+0l 3.36E+02 -0.1 1.6 -3.3 6.9 -1.1 6.2 2.5 16.3 MW-52-122 6/17/2020 l.05E+02 3.81E+02 0.5 1.3 0.3 6.4 -0.9 8.0 2.6 12.7

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 57 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-52-162 6/17/2020 3.61E+02 3.93E+02 0.3 1.1 -0.7 6.2 -1.8 6.8 1.6 15.0 MW-52-18 6/17/2020 1.47E+0l 3.81E+02 -0.3 1.0 -0.9 4.4 -3.4 7.0 -5.5 11.4 MW-52-181 6/17/2020 2.17E+02 3.66E+02 0.1 1.3 -1.6 5.7 -0.3 6.8 3.6 15.2 MW-52-48 6/17/2020 5.74E+0l 4.29E+02 1.4 1.8 -2.1 5.6 0.0 6.4 0.0 12.9 MW-52-64 6/17/2020 1.72E+02 3.57E+02 -0.7 0.9 -1.2 4.4 -0.8 5.8 6.1 10.5 MW-53-120 1/14/2020 9.82E+03 8.67E+02 29.4 4.5 -4.3 7.1 -1.7 6.3 -6.6 17.9 1.2 14.0 MW-53-120 2/11/2020 1.07E+04 7.74E+02 17.9 4.0 0.3 6.2 2.3 7.2 3.2 16.2 MW-53-120 3/10/2020 9.75E+03 8.19E+02 14.8 2.6 2.0 6.3 3.8 10.8 4.0 16.6 -6.9 17.9 MW 120 5/27/2020 9.96E+03 8.88E+02 16.0 3.7 -1.7 6.7 -0.3 6.1 14.7 22.2 -1.5 19.1 MW-53-120 6/30/2020 9.19E+03 8.37E+02 16.9 3.4 -1.6 5.6 0.0 4.3 3.8 15.1 -1.6 10.8 MW-53-120 7/29/2020 9.06E+03 8.10E+02 15.2 3.2 -0.6 6.5 3.3 7.3 4.5 16.2 -5.5 16.2 MW-53-120 8/28/2020 1.05E+04 1.04E+03 19.0 3.7 1.4 6.7 0.3 7.5 1.4 17.1 -13.8 15.7 MW-53-120 9/21/2020 8.77E+03 8.19E+02 17.6 3.6 4.9 11.1 - 2.1 5.8 5.0 19.6 3.0 17.4 MW-53-120 10/19/2020 9.19E+03 9.54E+02 26.4 4.6 -2.1 5.4 4.8 7.9 15.0 20.8 -3.4 13.3 MW-53-120 11/10/2020 l .02E+04 1.23E+03 20.4 4.2 1.9 5.9 - 2.9 8.2 5.7 19.8 2.9 16.8 MW-53-120 12/15/2020 8.60E+03 9.96E+02 23.1 4.2 0.7 4.7 2.2 5.1 11.8 20.1 0.6 12.7 MW-53-82 3/10/ 2020 5.93E+02 3.66E+02 0.1 1.0 -0.6 5.9 1.4 6.1 -4.6 20.5 -0.7 12.1 MW-53-82 5/27/2020 3.57E+02 4.11E+02 -0.5 1.6 0.3 5.2 2.4 9.8 -8.9 20.0 3.9 13.6 MW-53-82 8/28/2020 -3.27E+0l 3.66E+02 -0.3 0.9 -0.6 6.8 3.7 7.1 0.9 14.9 0.8 14.8 MW-53-82 11/10/2020 3.98E+02 3.63E+02 0.5 1.6 -0.9 6.5 2.2 5.9 -5.2 18.5 2.6 16.4 MW-54-123 3/11/2020 l .72E+03 4.62E+02 0.4 1.4 3.1 5.8 0.2 5.3 3.7 17.7 0.4 13.4 MW-54-123 6/11/2020 1.62E+03 5.76E+02 -0.3 1.5 -1.9 6.1 2.7 7.7 -7.2 22.3 0.4 12.9 MW-54-123 9/1/2020 2.01E+03 7.74E+02 -1.0 1.4 0.1 4.5 0.7 4.0 12.9 24.3 11.4 16.3 MW-54-123 11/2/2020 1.33E+03 5.19E+02 0.3 1.1 -0.2 5.2 0.2 5.3 -6.4 17.6 -1.1 11.1 MW-54-144 3/11/2020 l.69E+03 4.50E+02 7.6 2.7 0.2 12.0 1.2 5.5 3.6 16.4 -0.8 13.4 MW-54-144 6/11/2020 l.90E+03 6.15E+02 5.0 2.3 0.4 5.0 -3.0 5.8 1.3 22.1 -6.0 14.5 MW-54-144 9/1/2020 8.73E+02 6.54E+02 3.7 2.1 -2.4 5.9 -0.1 6.7 10.0 23.8 -7.8 15.5 MW-54-144 11/2/2020 1.27E+03 5.46E+02 3.8 1.9 -0.3 4.5 -0.6 4.7 -0.4 18.4 2.0 11.5 MW-54-173 3/11/2020 4.10E+03 6.03E+02 5.0 1.8 2.2 8.2 0.0 11.2 -4. 9 17.0 1.1 14.7 MW-54-173 6/11/2020 4.23E+03 7.80E+02 4.0 2.2 1.0 5.8 0.9 6.0 5.6 21.6 0.0 13.8 MW-54-173 9/1/2020 3.27E+03 8.46E+02 1.1 1.2 2.3 5.1 2.2 6.6 1.8 23.2 -7.8 14.5 MW-54-173 11/2/2020 3.38E+03 6.78E+02 -0.3 1.6 -0.6 5.5 -0.8 5.4 -2.5 17.9 1.3 12.3 MW-54-190 3/11/2020 2.11E+03 4.77E+02 10.6 2.4 0.7 6.0 1.0 5.3 -2.9 16.9 1.1 13.3 MW-54-190 6/11/2020 2.11E+03 6.39E+02 10.5 3.0 0.1 6.4 2.1 5.4 -0.4 23.1 -3.1 18.5 MW-54-190 9/1/2020 1.54E+03 7.14E+02 6.8 2.4 2.2 9.2 - 2.9 5.4 -6.5 22.5 8.0 14.9 MW-54-190 11/2/ 2020 1.36E+03 5.25E+02 5.7 2.3 0.0 8.9 1.8 4.7 -2.5 19.1 4.6 12.2 MW-54-37 3/11/2020 8.03E+02 3.81E+02 2.3 1.9 1.5 5.2 0.3 5.8 -1.1 17.3 7.0 12.7 MW-54-37 6/11/2020 7.11E+02 4.92E+02 1.7 1.9 -0.6 4.7 3.7 4.8 -0.6 24.6 0.1 12.8 MW-54-37 9/1/2020 3.49E+02 4.29E+02 0.6 1.7 1.6 5.8 -0.6 5.8 -1.2 23.3 -1.9 12.9 MW-54-37 11/2/2020 5.30E+02 4.50E+02 0.7 1.7 0.7 4.9 2.5 5.4 1.0 23.3 5.6 12.8 MW-54-58 3/11/2020 l.79E+03 4.47E+02 0.8 1.7 -0.3 7.8 -1.8 6.6 1.5 19.5 -9.3 19.3 MW-54-58 6/11/2020 l.27E+03 4.68E+02 0.9 1.7 -2.4 6.2 -0.6 5.6 7.4 20.9 -0.6 17.2

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 58 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-54-58 9/1/2020 l.08E+03 6.72E+02 0.4 1.7 5.8 5.9 1.8 5.0 -3.8 23.3 1.5 13.8 MW-54-58 11/2/2020 1.13E+03 5.19E+02 0.5 1.2 -0.9 5.2 0.4 6.9 0.0 19.0 -10.4 13.1 MW-55-24 3/10/2020 1.01[+03 3.60E+02 5.6 2.3 -1.1 4.8 0.9 4.3 -4.5 16.1 7.5 13.3 MW-55-24 5/26/2020 l.10E+03 4.53E+02 6.4 2.0 -0.6 5.1 1.8 5.1 -8.7 20.5 1.6 11.7 MW-55-24 9/2/2020 6.55E+02 4.14E+02 4.1 2.1 -0.4 4.6 0.3 4.7 4.6 23.9 4.2 11.6 MW-55-24 11/16/2020 5.14E+02 3.69E+02 1.1 1.7 0.1 5.0 -1.2 4.8 -4.7 20.6 4.9 12.5 MW-55-35 3/10/2020 2.23[+03 4.53E+02 11.4 3.1 1.5 7.1 1.7 8.3 -5.0 16.5 -0.7 21.5 MW-55-35 5/26/2020 2.32E+03 5.34E+02 9.5 2.4 0.3 4.5 3.6 7.1 2.8 20.3 -0.2 10.4 MW-55-35 9/2/2020 1.89E+03 5.40E+02 7.6 2.8 -0.5 4.4 2.9 4.3 8.7 24.8 2.3 12.7 MW-55-35 11/16/2020 1.16[+03 4.23E+02 7.4 2.6 0.1 5.9 0.9 5.4 -1.7 18.1 -7.6 13.0 MW-55-54 3/10/2020 4.51[+03 6.12E+02 8.4 2.4 4.8 8.6 1.9 5.8 -0.8 16.6 2.7 16.5 MW-55-54 5/26/2020 5.05E+03 6.66E+02 9.7 2.6 -0.6 7.5 0.4 5.8 0.4 19.8 3.3 18.1 MW-55-54 9/2/2020 3.84[+03 8.67E+02 7.8 2.5 -0.7 6.5 1.4 7.3 3.1 23.3 4.5 14.6 MW-55-54 11/16/2020 3.31[+03 5.49E+02 4.2 2.0 -1.2 5.2 -1.4 5.9 -0.2 20.6 -2.3 13.0 MW-56-53 6/19/2020 5.91E+02 3.93E+02 0.3 1.3 -0.3 5.0 0.6 4.4 6.0 13.2 MW-56-53 11/6/2020 2.11E+02 3.54E+02 0.2 1.6 -0.9 5.0 0.8 3.7 -4.8 13.4 MW-56-83 6/19/2020 1.63[+03 4.80E+02 1.4 1.8 2.6 8.0 -0.4 5.3 1.1 12.3 MW-56-83 11/6/2020 2.56[+03 5.43E+02 0.0 0.9 0.3 5.5 1.5 6.1 5.5 12.6 MW-57-11 6/18/2020 2.00E+03 5.58E+02 4.7 2.1 2.1 6.2 3.9 9.7 10.7 22.0 0.2 13.9 MW-57-20 6/18/2020 1.00E+03 4.83E+02 0.3 1.5 -0.9 6.5 1.8 8.3 13.3 21.6 8.4 17.0 MW-57-45 6/18/2020 8.19[+02 4.62E+02 1.5 1.7 0.1 6.2 1.9 6.8 3.7 21.9 2.1 13.0 MW-58-26 6/10/2020 2.64E+02 3.81E+02 0.5 1.7 -0.3 6.7 2.3 5.9 -0.6 16.7 MW-58-26 11/18/2020 l.15E+0l 3.36E+02 1.1 1.8 -2.6 6.0 -1.2 4.9 7.7 13.5 MW-58-65 6/10/2020 2.66E+02 3.66E+02 0.5 1.3 -1.5 4.6 -0.8 5.6 2.6 12.1 MW-58-65 11/18/2020 l.88E+02 3.54E+02 0.9 1.7 0.0 7.1 0.7 8.3 21.2 27.6 MW-60-135 6/12/2020 1.27[+03 4.50E+02 0.4 1.7 0.0 6.7 5.4 7.7 1.4 16.9 MW-60-154 6/12/2020 9.37E+02 4.20E+02 -1.0 1.3 -1.1 5.3 4.4 10.9 4.3 14.6 MW-60-176 6/12/2020 1.19[+03 5.52E+02 0.6 1.7 -2.2 7.2 1.1 7.7 16.3 26.4 MW-60-35 6/12/2020 l.84E+02 4.44E+02 -0.8 1.4 -0.4 5.6 0.6 4.4 3.3 13.6 MW-60-53 6/12/2020 l.91E+02 4.41E+02 -0.8 1.2 -0.4 5.8 1.0 6.2 -1.6 14.2 MW-60-72 6/12/2020 2.19E+02 3.75E+02 -0.4 1.4 1.8 6.7 -3.5 6.5 0.9 14.2 MW-62-138 3/5/2020 8.56[+02 3.81E+02 0.9 1.5 -4.1 6.5 -1.9 5.6 4.9 14.9 MW-62-138 6/8/2020 5.61E+02 4.29E+02 -0.8 1.6 -0.2 8.4 -0.5 5.3 0.0 24.7 MW-62-138 9/3/2020 3.23E+02 4.32E+02 0.0 1.6 -0.8 4.7 4.6 5.8 -4.6 13.5 MW-62-138 11/4/2020 7.15[+02 3.84E+02 -0.7 1.0 0.4 4.6 0.3 4.3 0.7 10.8 MW-62-18 3/5/2020 l.75E+02 3.18E+02 1.4 1.8 0.8 4.4 2.0 4.2 -5.2 9.7 MW-62-18 6/8/2020 3.91E+0l 3.78E+02 0.4 1.1 1.0 6.9 0.6 6.1 6.1 16.8 MW-62-18 9/3/2020 -2.73E+02 3.81E+02 -1.1 1.3 2.2 5.0 -0.4 4.8 -1.5 10.8 MW-62-18 11/4/2020 3.76E+02 3.63E+02 0.6 1.0 0.0 5.8 1.7 5.0 -0.7 11.3 MW-62-182 3/5/2020 1.21[+03 4.05E+02 -0.7 1.1 -2.4 7.4 -1.5 5.7 -4.3 11.0 MW-62-182 6/8/2020 7.14[+02 5.07E+02 1.6 1.7 0.8 6.9 -0.6 7.9 -4.4 16.9 MW-62-182 9/3/2020 6.03E+02 4.41E+02 0.3 1.6 - 2.2 7.8 2.5 4.9 2.8 14.3

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 59 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L) 3 Well ID Sample Date 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Re sult Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-62-182 11/4/2020 7.02E+02 3.81E+02 -0.5 0.7 1.9 6.1 -2.0 5.6 -0.8 13.5 MW-62-37 3/5/ 2020 7.71E+02 3.78E+02 -0.4 1.2 -4.5 6.4 1.8 6.2 -6.3 15.8 MW-62-37 6/8/2020 4.60E+02 4.14E+02 0.7 1.4 3.1 6.3 1.6 6.4 0.9 15.1 MW-62-37 9/3/2020 2.36E+02 4.26E+02 0.0 1.5 -1.1 4.7 -1.2 4.9 0.4 10.6 MW-62-37 11/4/2020 7.92E+02 4.23E+02 0.9 1.0 -1.4 5.6 0.4 4.3 4.5 13.0 MW-62-53 3/5/2020 9.47E+02 3.84E+02 0.2 0.9 -0. 5 5.7 -1.3 5.5 2.2 11.9 MW-62-53 6/8/2020 7.82E+02 4.32E+02 0.2 1.2 -2.1 5.0 2.8 6.2 3.0 12.3 MW-62-53 9/3/ 2020 5.88E+02 4.32E+02 -0.8 1.4 0.6 6.7 9.1 6.6 6.3 15.4 MW-62-53 11/4/2020 9.36E+02 3.90E+02 0.7 1.0 -0.4 5.9 0.8 6.2 2.8 13.8 MW-62-71 3/5/2020 8.26E+02 3.75E+02 0.1 1.4 0.6 6.2 2.8 7.0 -7.9 15.8 MW-62-71 6/8/ 2020 7.39E+02 5.04E+02 -0.3 1.4 0.5 5.6 -1.7 7.3 6.3 12.5 MW-62-71 9/ 3/ 2020 6.32E+02 4.32E+02 -0.1 0.9 1.2 6.4 5.5 7.8 1.1 14.9 MW-62-71 11/4/2020 7.83E+02 3.93E+02 0.5 0.9 -0.5 6.3 -0.2 8.0 1.9 18.6 MW-62-92 3/5/2020 9.44E+02 3.84E+02 -0.5 1.1 -4.4 6.2 -1.0 5.0 -6.2 11.6 MW-62-92 6/8/2020 8.81E+02 5.04E+02 0.1 1.4 3.7 6.9 0.4 6.0 1.9 16.0 MW-62-92 9/3/2020 8.00E+02 6.48E+02 0.9 1.7 -0.5 6.2 -1.8 6.8 -5.4 16.6 MW-62-92 11/4/2020 8.86E+02 3.99E+02 0.4 0.9 2.1 5.9 -0.9 6.0 -6.3 14.7 MW-63-112 6/ 9/2020 4.08E+02 3.84E+02 -0.6 1.3 0.0 4.6 1.1 5.5 -1.5 12.5 MW-63-112 11/18/2020 5.14E+02 3.75E+02 1.8 1.8 -0.8 4.5 -0.3 4.9 -3.7 11.7 MW-63-121 6/9/2020 4.39E+02 4.17E+02 -0.6 l. 7 -2.6 5.4 -2.6 6.8 2.4 16.0 MW 121 11/18/2020 5.21E+02 3.81E+02 l. 7 1.8 -0.6 4.9 -3.0 5.3 2.9 13.0 MW-63-163 6/9/2020 5.21E+02 4.29E+02 -0.2 1.2 0.4 4.7 -4.5 6.7 -0.1 12.4 MW-63-163 11/18/2020 5.94E+02 3.81E+02 1.8 1.9 1.5 4.5 -2.9 5.7 7.2 16.7 MW-63-174 6/9/2020 4.36E+02 4.26E+02 0.4 1.7 2.7 6.8 2.5 8.1 4.2 17.4 MW-63-174 11/18/2020 6.01E+02 3.81E+02 0.6 1.7 -1. 6 5.3 1.1 4.9 -6. 7 13.8 MW-63-18 6/9/2020 2.69E+02 3.99E+02 -1.2 1.4 -1.1 6.5 -1.1 5.8 3.2 17.2 MW-63-18 11/18/2020 3.27E+02 3.69E+02 -0.1 1.5 3.9 10.7 -1.3 7.4 0.6 15.0 MW-63-34 6/9/2020 6.04E+02 4.08E+02 0.1 1.2 -3.7 7.9 0.8 5.9 -0.2 12.4 MW-63-34 11/18/2020 1.68E+02 3.60E+02 0.1 1.6 0.8 5.1 -0.1 4.3 2.6 11.8 MW-63-50 6/9/2020 4.12E+02 3.87E+02 0.0 1.6 0.1 5.4 -1.7 5.9 -2.1 11.1 MW-63-50 11/18/2020 4.44E+02 3.57E+02 1.2 1.8 -2.2 5.5 -0.9 6.4 -1.5 16.6 MW-63-93 6/9/2020 2.85E+02 3.66E+02 -0.3 1.1 0.9 7.2 1.7 7.9 -2.2 17.5 MW-63-93 11/18/2020 l.28E+02 3.63E+02 0.6 1.7 2.9 6.8 -2.1 8.4 -4.9 15.9 MW-66--21 3/3/2020 6.86E+02 3.51E+02 0.4 1.1 2.1 5.0 -0.5 4.5 -3.6 18.7 2.9 11.5 MW-66--21 6/2/2020 9.35E+02 5.16E+02 1.5 1.8 2.4 4.1 2.0 5.3 3.5 22.1 -2.5 12.2 MW-66-21 9/4/2020 1.01E+03 4.53E+02 0.2 1.6 1.3 4.4 0.3 4.7 -0.1 24.0 -1.9 11.7 MW-66--21 11/3/ 2020 1.09E+03 4.17E+02 0.2 0.8 -2.9 5.6 1.3 5.1 2.1 14.2 10.3 20.4 MW-66--36 3/3/2020 3.95E+03 5.61E+02 4.4 2.0 2.8 6.5 0.5 4.7 0.2 19.1 -2.4 15.7 MW-66--36 6/2/2020 4.48E+03 8.10E+02 6.2 2.4 -4. 9 4.5 0.6 5.7 -1.9 20.9 3.1 11.9 MW-66--36 7/1/2020 4.10E+03 MW-66--36 9/4/2020 4.55E+03 7.05E+02 4.2 2.1 0.1 4.8 0.3 3.9 12.7 24.1 2.6 9.7 MW-66--36 9/22/2020 4.70E+03

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 60 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-12S (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW-66-36 11/3/2020 3.71E+03 6.69E+02 5.4 1.9 -2.5 8.7 -1.1 7.8 2.9 18.5 -4. 3 17.1 MW-66-36 12/14/2020 3.70E+03 MW-67-105 3/4/2020 1.57E+03 4.32E+02 1.1 1.7 -0.8 6.7 -1.3 6.0 2.6 19.2 -4.2 13.6 MW-67-105 6/4/2020 l .59E+03 5.46E+02 -0.3 1.5 0.3 4.8 0.6 3.8 -4.4 19.7 0.0 12.4 MW-67-105 7/1/2020 l.50E+03 MW-67-105 8/25/2020 1.74E+03 5.94E+02 0.9 1.7 -1.5 6.7 -1.1 6.2 5.6 17.3 1.7 16.4 MW-67-105 9/22/2020 1.70E+03 MW-67-105 11/3/2020 l.25E+03 4.38E+02 1.1 1.2 -1.9 6.1 -2.2 7.8 -3.8 12.9 -7.3 16.1 MW-67-105 12/ 14/2020 l.20E+03 MW-67-173 3/4/2020 7.13E+02 3.72E+02 0.4 1.2 1.9 4.8 -1. 5 4.0 -11.2 25.4 -0.6 12.8 MW-67-173 6/4/2020 5.88E+02 4.29E+02 0.0 1.6 4.8 6.0 -1. 9 6.4 0.1 24.6 -0.8 11.6 MW-67-173 8/25/2020 7.26E+02 5.01E+02 -0.6 1.5 -1.4 4.8 2.9 3.9 -9. 7 22.4 3.6 12.1 MW-67-173 11/3/2020 7.50E+02 3.99E+02 0.0 0.7 0.9 5.1 -1.4 5.3 3.0 22.4 -1.7 12.6 MW-67-219 3/ 4/2020 1.00E+03 3.69E+02 0.0 1.0 -0.8 6.5 3.7 7.2 4.9 20.6 8.9 28.4 MW-67-219 6/4/2020 1.00E+03 4.89E+02 -0.4 1.4 -0.7 4.6 2.7 7.7 0.4 21.2 -0.4 13.1 MW-67-219 8/25/2020 l.04E+03 5.25E+02 0.2 1.6 -1.3 4.8 2.6 6.0 -3. 1 16.1 -0.9 12.8 MW-67-219 11/3/ 2020 7.40E+02 4.92E+02 -0.1 1.1 0.6 6.6 3.7 6.8 9.2 19.4 4.4 15.2 MW-67-276 3/4/ 2020 6.30E+02 3.54E+02 0.1 0.9 0.6 6.0 -3.5 6.0 5.3 19.8 5.0 18.1 MW-67-276 6/4/2020 6.88E+02 4.86E+02 -0.5 1.3 3.8 5.7 -3.0 7.2 2.0 19.3 -1.7 13.7 MW-67-276 7/1/2020 <MDA MW-67-276 8/25/2020 7.10E+02 5.16E+02 -0.4 1.5 1.6 8.0 -1.0 9.5 5.4 18.1 5.1 15.4 MW-67-276 9/22/2020 l.20E+03 MW-67-276 11/3/2020 5.46E+02 4.71E+02 0.5 0.9 4.0 6.1 -0.5 5.8 5.2 18.7 -4.9 14.3 MW-67-276 12/14/2020 6.00E+02 MW-67-340 3/4/2020 2.04E+02 3.30E+02 0.5 0.8 -1.4 7.4 -0.8 6.3 -0.2 20.5 -4.9 20.7 MW-67-340 6/4/2020 l.99E+02 3.90E+02 -0.1 1.6 -2.0 5.3 -3.2 6.9 -0.5 18.4 -1.3 13.1 MW-67-340 8/25/2020 3.55E+02 3.87E+02 0.6 1.7 3.1 6.7 1.9 8.2 -1.1 18.1 -3.1 15.1 MW-67-340 11/3/2020 3.39E+02 3.66E+02 0.8 1.2 1.5 6.1 0.5 7.9 4.3 15.7 4.5 15.5 MW-67-39 3/4/2020 3.69E+03 7.35E+02 3.2 2.0 1.2 5.4 -0.1 5.4 -1. 6 20.0 - 2.1 13.2 MW-67-39 6/4/2020 3.71E+03 6.75E+02 6.5 2.7 -0.1 7.0 -1.1 7.9 -5.2 19.3 -1.9 15.1 MW-67-39 7/1/2020 4.00E+03 MW-67-39 8/25/2020 4.28E+03 7.53E+02 5.6 2.1 1.0 4.9 0.7 5.0 -13.9 16.3 -0.1 9.8 MW-67-39 9/22/2020 4.00E+03 MW-67-39 11/3/2020 3.85E+03 6.99E+02 3.6 1.7 -0.4 7.1 0.9 7.2 -12.5 17.1 -1.3 17.9 MW-67-39 12/14/2020 4.10E+03 MW-68-103 1/28/2020 3.40E+02 3.36E+02 0.9 1.6 2.2 8.1 -4.5 6.9 -4.1 15.3 MW-68-103 4/7/2020 4.57E+02 3.78E+02 0.3 0.6 0.2 6.0 - 2.3 6.4 -2.5 16.7 MW-68-103 8/18/2020 4.19E+02 4.02E+02 -0.2 1.6 3.4 5.1 -1.0 5.3 -6.8 12.6 MW-68-103 11/5/2020 3.24E+02 3.72E+02 0.3 0.8 -2.0 5.5 0.2 6.0 -1.6 14.0 MW-68-132 1/28/2020 9.29E+0l 3.00E+02 -0.6 1.3 -1.6 6.4 2.3 7.1 -7.6 14.5 MW-68-132 4/7/2020 l.70E+02 3.63E+02 0.0 0.7 -1.6 6.2 -0.5 6.6 17.8 27.6 MW-68-132 8/18/2020 5.45E+Ol 3.66E+02 0.4 1.6 -1.6 6.4 1.0 7.4 6.6 16.6

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 61 of 63 Annual Radioactive Effluent Release Report 2020 Laboratory Analytical Results H3 (pCi/L) Sr-90 (pCi/L) Cs-137 (pCi/L) Co-60 (pCi/L) Ni-63 (pCi/L) Sb-125 (pCi/L)

Well ID Sample Date 3 3 Sigma 3 Sigma 3 Sigma 3 Sigma Sigma 3 Sigma Result Result Result Result Result Result (Std. (Std. (Std. (Std. (Std. (Std.

Dev.) Dev.) Dev.) Dev.) Dev.) Dev.)

MW 132 11/5/2020 3.28E+02 3.48E+02 0.6 0.8 -2.2 5.6 -1.3 7.3 0.0 51.0 MW-68-19 1/ 28/ 2020 4.32E+02 3.48E+02 0.8 1.5 3.4 6. 8 -0.8 7.1 -14.5 17.1 MW-68-19 4/7/2020 3.94E+02 3.78E+02 0.2 0.9 0.0 5.9 3.1 4.8 -2.8 15.7 MW-68-19 5/ 29/2020 5.53E+02 4.08E+02 0.5 1.5 0.0 5.2 0.0 6.6 -6.4 14.8 MW-68-19 8/ 18/ 2020 6.15E+02 5.07E+02 -0.2 1.6 1.5 4.7 -0.1 4.8 0.0 26.6 MW-68-19 11/5/2020 8.21E+02 4.02E+02 0.4 0.9 - 2.0 6.8 1.1 6.7 2.3 15.1 MW-68-29 1/ 28/2020 7.08E+02 3.75E+02 0.6 1.4 1.1 7.4 -1.0 7.1 4.4 21.2 MW-68-29 4/ 7/2020 6.53E+02 4.17E+02 0.4 0.6 -0.3 4.8 -1.2 4.2 0.8 13.9 MW-68-29 5/ 29/2020 4.45E+02 4.23E+02 0.7 1.7 2.4 6.6 0.7 6.9 5.4 17.9 MW-68-29 8/18/ 2020 5.97E+02 4.92E+02 -0.7 1.6 -0.7 5.8 0.9 7.2 1.0 15.0 MW-68-29 11/5/ 2020 4.67E+02 3.87E+02 1.0 1.0 -1. 7 6.4 0.8 6.2 -1.3 15.0 MW-68-57 1/ 28/2020 5.56E+02 3.54E+02 1.6 1.8 -0.5 5.3 1.9 5.3 -7.6 13.2 MW-68-57 4/ 7/2020 4.76E+02 3.81E+02 0.2 0.5 -0.1 5.7 1.6 5.0 0.5 11.2 MW-68-57 5/ 29/ 2020 3.87E+02 3. 84E+02 0.4 1.4 -1.2 5.0 0.0 6.1 -6.8 16.5 MW-68-57 8/18/ 2020 3.99E+02 4.02E+02 0.8 1.7 0.1 6.5 5.1 7.3 4.0 15.2 MW-68-57 11/ 5/2020 3.88E+02 3.72E+02 1.0 1.0 -4.5 6.2 1.6 4.4 -4.1 12.2 MW-73 1/ 27/2020 1.43E+02 3.54E+02 -0.1 1.4 1.1 5.4 1.9 4.3 3.8 13.1 MW-73 4/ 7/2020 3.41E+02 4.02E+02 1.3 1.6 0.5 3.9 0.7 3.6 -3.9 10.5 Ul-CSS 6/24/2020 2.16E+03 5.04E+02 2.0 1.9 -0.6 6.4 -3.6 5.6 4.0 20.9 -1.6 13.1 Ul-CSS 10/ 27/2020 l.27E+03 5.43E+02 0.9 1.6 6.3 9.2 -0.7 6.1 -6.1 18.4 0.0 28.5 Ul- NCD 3/2/2020 2.80E+03 4.65E+02 27.0 1.8 26800 265 0.9 5.6 535 39 29.4 105.6 Ul- NCD 5/25/2020 3.56E+03 6.15E+02 23.6 3.9 19300 207 2.7 6.8 397 41 18.4 85.5 Ul- NCD 8/ 17/ 2020 3.59E+03 6.27E+02 25.3 3.5 18500 210 2.2 6.8 434 43 42.6 88. 5 Ul- NCD 11/10/ 2020 2.83E+03 6.15E+02 18.4 3.5 16300 197 2.5 5.6 465 35 -25.9 78.9 Ul-SFDS 3/ 4/2020 1.96E+02 3.33E+02 2.0 2.0 7.9 10.5 -0.3 5.0 0.2 16.4 1.8 12.8 Ul-SFDS 5/27/2020 2.89E+02 3.81E+02 5.8 2.2 3.3 7.0 -2.3 6.7 -1.8 22.1 -6.6 11.7 Ul-SFDS 8/19/2020 4.58E+02 4.14E+02 5.0 2.1 0.0 11.4 1.3 5.0 0.1 24.5 9.5 11.9 Ul-SFDS 11/11/2020 3.67E+02 4.05E+02 3.6 1.9 5.6 9.9 1.3 7.7 0.9 19.0 -2.0 14.0 U3-40 3/3/2020 1.66E+02 2.99E+02 0.4 0.9 2.0 4.2 0.5 5.5 6.8 11.0 U3-40 5/29/2020 4.04E+02 3.99E+02 0.7 1.4 0.0 7.9 -2.4 6.8 -4.9 17.4 U3-40 8/19/2020 1.54E+02 3.90E+02 0.7 1.7 2.6 6.0 1.0 5.9 0.9 13.7 U3-40 11/12/2020 3.40E+02 3.72E+02 -0.5 1.5 3.3 5.2 0.4 4.9 -2.7 19.8 5.1 13.9 U3-4S 5/ 29/2020 2.02E+02 3.96E+02 1.2 1.8 -0.3 5.4 8.3 7.9 1.1 12.7 U3-4S 11/12/2020 4.96E+02 3.96E+02 0.0 0.9 3.1 6.7 2.1 5.8 0.2 19.0 2.7 15.3 U3-Tl 1/27/2020 l.OOE+03 3.87E+02 0.5 1.4 -2.3 6.9 0.9 6.5 3.0 19.1 U3-Tl 6/16/2020 7.29E+02 4.05E+02 0.3 1.6 1.2 5.4 5.3 5.6 -1.1 11.0 U3-Tl 8/19/2020 7.35E+02 5.13E+02 0.9 1.7 0.0 7.9 0.3 4.6 0.9 10.6 U3-Tl 11/12/2020 5.66E+02 3.54E+02 -0.7 1.4 4.3 7.8 0.1 5.4 7.2 15.5 U3-T2 1/27/2020 7.58E+02 3.75E+02 -0.3 0.9 0.5 5.1 -3.4 7.0 3.5 11.5 U3-T2 6/16/2020 1.08E+03 4.29E+02 1.6 1.9 -0.4 6.4 3.7 8.0 2.6 13.1 U3-T2 8/19/2020 l.14E+03 5.10E+02 0.0 1.6 -0.8 6.1 5.4 8.6 0.4 15.9 U3-T2 11/12/2020 1.42E+03 4.26E+02 -1.3 1.6 1.1 6.2 2.0 6.8 -1.9 16.1

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 62 of 63 Annual Radioactive Effluent Release Report Attachment 4 - ODCM Revision 5 Summary of Changes ODCM Part I 1 Added "Foundation Drain Line (k)" to Table D 3.1.1-1 , Continuous Releases section.

2 Add "(k)" to Table D 3.1.1-1 , (page 2 of 2) , to indicate that all the Foundation Drain Line samples are grab samples (at least once per month).

3 Corrected error on Table D 3.1.1-1 , (page 2 of 2), Item (b) , changed Section 1.4 to Section 2.1.4.

4 Modified Table D 3.3.1-1 , Section 2, item a, deleted Secondary Boiler Slowdown Purification System, SBBPS HX (R-52) , per EC 75435, piping and equipment are interim abandoned .

5 Modified Table D 3.3.1-1 , Section 2, deleted item b, Unit 1 Secondary Boiler Slowdown Effluent Line (R-51) , per EC 73608 , piping and equipment are interim abandoned .

6 Modified Table D 3.3.1-1 , Section 3 and Section 4 to eliminate the actual component IDs.

7 Corrected wording in D 3.5.1, Required Action B.1 Note to more clearly indicate that a Special Report is not required when the radioactivity detected is not the result of plant effluents.

8 Deleted Note 2 in Section D 3.5.1, Required Action B.2.

9 Revised wording in Table D 3.5.1-1 and table notes to be more consistent with NU REG 1301 and added a fish and invertebrates sampling location downstream of the Site to satisfy another regulatory commitment.

10 Corrected spelling in Table D 3.5.1-2 and Table D 3.5.1-3, changed Partiuclate to Particulate.

Corrected typo for the Sr-90 LLD in Soil or Sediment from 5000 to 50 pCi/kg on Table D 3.5.1-3.

11 Added word "general" in Section 5.1 , third bullet prior to "format of the Radiological Assessment Branch Technical Position".

ODCM Part II 12 Deleted R-51 and R-52 on Table 1-1 (Unit 2 Effluent Radiation Monitor System Data) , page 4 of 144 per EC 75435 and EC 73608.

13 Corrected units of the AiT Factors in Table 2-1 from mR/hr to mrem/hr.

14 Corrected the second equation listed in Step 3.1 .12 (page 27) to indicate the quantity being calculated is actually Om ixture instead of Q 133.

15 Corrected typo on page 32 of 144, Revision 4 last paragraph . Changed factgors to factors.

16 Added wording to Section 3.5.2, 2 nd and 3 rd paragraph to include 2006 to 2015 meteorology, Document No. 32-9256934-001 .

17 Added wording to Section 3.5.2, 3rd paragraph to include the selection of the higher dispersion values (most restrictive) of the last two ten-year periods.

18 Corrected wording in section 3.5.3 and 3.5.4 (page 47) , changed Attachment I to Appendix I 19 Modified wording and slope data in section 3.5 .6.f to use the most restrictive deposition and dispersion slope.

20 Correct typo in table 3-5 and table 3-7 , Skin Dose Factors, changed Nucline to Nuclide.

21 Added Reference 50 to references on page 106, Document No. 32-9256934-001 , "Updated

Indian Point Units 1, 2 & 3 I YEAR: 2020 I Page 63 of 63 Annual Radioactive Effluent Release Report Valley Recirculation Effects and Revised Atmospheric Dispersion and Deposition Factors for Indian Point Units 2 and 3 Offsite Dose Calculation Manual (2006-2015 Site Meteorology)",

March 2017.

22 Modified Appendix B, Page 1 of 2, Units 1 and 2 Liquid Effluent Simplified Flow Diagram to remove SBBPS HX (R-52) , per EC 75435 and Unit 1 Secondary Boiler Slowdown Effluent Line (R-51 ), per EC 73608.

23 Modified Appendix G, Environmental Sample Points. Deleted sample points that are in excess of the RECS requirements.

24 Changed the control location from Plant Inlet (Hudson River Intake) 0.16 miles Wto Roseton 20.7 miles N. Added Fish and Invertebrate sampling at Vicinity of Haverstraw Bay (2 .5 miles SSW) .

25 Updated Appendix I Ground Level release dispersion and deposition data as a result of updated (2006-2015) Site Meteorology.

The following are editorial changes and do not need to be justified:

Items 3, 10, 11 , 13, 14, 15, 18, and 20.

ENCLOSURE TO NL-21-029 Offsite Dose Calculation Manual ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 1, 2, and 3 NUCLEAR POWER PLANTS DOCKET Nos. 50-03, 50-247, and 50-286

ML21168A024

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