Latest revision as of 06:33, 21 February 2026

Text

Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report
	ML23125A073
Person / Time
Site:	Nine Mile Point
Issue date:	04/30/2023
From:	Alexander Sterio; Constellation Energy Generation
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	NMP1L3522
	Download: ML23125A073 (1)
	v • d • e

1 Constellation NMP1L3522 April 30, 2023 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 Alexander D. Sterio Plant Manager Nine Mile Point P.O. Box 63 Lycoming, NY 13093 (315) 349-5205 Alexander.Sterio@Constellation.com 10 CFR 50.36a 10 CFR 72.44(d)(3)

Technical Specifications Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410 Independent Spent Fuel Storage Installation (ISFSI)

ISFSI Docket No. 72-1036

Subject:

2022 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 In accordance with 10 CFR 50.36a, and the Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2) Technical Specifications, enclosed are the Radioactive Effluent Release Reports for NMP1 and NMP2 for the period of January through December 2022. This letter also satisfies the annual effluent reporting requirements for the ISFSI required by 10 CFR 72.44(d)(3).

The format used for the effluent data is outlined in Append ix B of Regulatory Guide 1.21, Revision

1. During the reporting period, NMP1, NMP2, and the ISFSI did not exceed any 10 CFR 20, 10 CFR 50, 10 CFR 72, Technical Specification, or ODCM limits for gaseous or liquid effluents.

Should you have questions regarding the information in this submittal, please contact Jeremy Kerling, Manager, Site Chemistry and Radwaste, at (315) 349-1683.

Sincerely, Alexander D. Sterio Plant Manager, Nine Mile Point Nuclear Station Constellation Generation Company, LLC ADS/KES f ~4-CZ NrY1SS 26 N f'L((__

N(Y)SS j

2022 RERR April 30, 2022 Page2

Enclosures:

(1)

Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2022 (2)

Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2022 Cc:

NRC Regional Administrator, Region 1 NRC Project Manager NRC Resident Inspector S.Veunephechan,NRC

ENCLOSURE 1 Nine Mile Point Nuclear Station, Unit 1 Radiological Effluent Release Report, January - December 2022

Nine Mile Point Annual Radioactive Effluent Release Report 2022 Document Number: NMP1 L3522

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 1 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS.................................................................................. 3 2.0 EXECUTIVE

SUMMARY

.............................................................................................................. 5 2.1 Comparison to Regulatory Limits...................................................................................... 6

3.0 INTRODUCTION

........................................................................................................................... 8 3.1

_ About Nuclear Power........................................................................................................ 8 3.2 About Radiation Dose..................................................................................................... 10 3.3 About Dose Calculation..................................................................................... \............. 12 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................... 14 4.1 Regulatory Limits................................................................................................. *............ 14 4.2 Regulatory Limits for Gaseous Effluent Doses:................................................................ 14 4.3 Regulatory Limits for Liquid Effluent Doses.................................................................... 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. *.. 16 4.5 Onsite Doses (Within Site Boundary).............................................................................. 16 5.0 SUPPLEMENTAL INFORMATION.........................,................................................................... 17 5.1 Gaseous Batch Releases.............................................. :................................................. 17 5.2 Liquid Batch Releases.................................................-.................................................... 17 5.3 Abnormal Releases..........-................................................................................................ 17 5.4 Land Use Census Changes*******************************************************************************:************ 18 5.5 Meteorological Data**********************************************************************.********************************** 18 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days-................................. 18 5.7 Offsite Dose Calculation Manual (ODCM) Changes....................................................... 18 5.8 Process Control Program (PCP) Changes...,.................................................................. 18 5.9 Radioactive Waste Treatment System Changes..................................,........................ :.18 5.1 O Other Supplemental Information ********************:**************************************************************** 18 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM................ 20 6.1 Voluntary Notification *******************************:*******************************;********:............................. 21 7.0 BIBLIOGRAPHY......................................................................................................................... 22 TABLES Table 1, Nine Mile Point Units 1 Dose Summary..................................................................................... 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for NMP..................................... 7 Table 3, Onsite Doses (Within Site Boundary)....................................................................................... 16 Table 4, Groundwater Protection Program Monitoring Well Results...................................................... 20 Table 5, Gaseous Effluents Summation of All Releases NMP 1........,.................................................. 23 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP 1........................................... 24 Table 7, Gaseous Effluents - Ground Level Release Continuous Mod.e NMP 1.................................. 25 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP 1......................................... 26 Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP 1.................................. 27 Table 10, Liquid Effluents - Summation of All Releases NMP 1............................................................ 28 Table 11, Batch Mode Liquid Effluents NMP 1....................................................................................... 29

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 2 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 12, Continuous Mode Liquid Effluents NMP 1.............................................................................. 30 Table 13, Types of Solid Waste Summary NMP 1.................................................................................. 31 Table 14, Major Nuclides NMP 1............................................................................................................ 31 Table 15, Solid Waste Disposition NMP 1.............................................................................................. 32 Table 16, Irradiated Fuel Shipments Disposition NMP 1........................................................................ 32 Table 17, Classification of Atmospheric Stability.................................................................................... 34 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]....................................................................................... 8 Figure 2, Boiling Water Reactor (BWR) [2]............................................................................................... 9 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]................................................... 10 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6].............. 12 ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)..................................................... 23, Solid Waste lnformation................................................................................................... 31, Meteorological Data......................................................................................................... 33

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 3 of 34 Com I Plant: Nine Mile Point Unit 1 1.0 LIST OF ACRONYMS AND DEFINITIONS 1...

.Airborne Activity Sampling: Sampling of air through the collection of particulates and radionuclides on filter media, collection of noble gases in a container, and collection of water vapor containing tritium.

2:

Alpha Particle (a): A charged particle emitted from the nucleus of an atom having a mass and charge equal in magnitude of a helium nucleus.

3.

BWR: Boiling Water Reactor

4.

Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.

5.

Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the Plant.

6.

Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on total counts accumulated.

7.

Curie (Ci): A measure of radioactivity; equal to 3.7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.

8.

Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.

9.

Grab Sample: A single discrete sample drawn at one point in time.

10.

Indicator: A sampling location that is likely to be affected by plant effluents due to its proximity and/or direction from the plant.

11.

Ingestion Pathway: The ingestion pathway includes milk, fish, and garden produce. Meat or other food products may also be included.

12.

ISFSI: Independent Spent Fuel Storage Installation

13.

Lower Limit of Detection (LLD): The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with a 5% probability of a false conclusion that a blank observation represents "real" signal.

14.

MDA: Minimum Detectable Activity. - For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95%

probability, with only five% probability of falsely concluding that a blank observation represents a true signal.

_________ ~

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 4 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1

15.

MDC: Minimum Detectable Concentration, essentially synonymous with MDA for the purposes of radiological monitoring.

16.

Mean: The average, i.e., the sum of results divided by the number of results.

17.

Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.

18.

millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.

19.

Milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X-or gamma radiation.

20.

MWe: Megawatts Electric

21.

MWTh: Megawatts Thermal

22.

NA: Not Applicable

23.

NEI: Nuclear Energy Institute

24.

NRG: Nuclear Regulatory Commission

25.

ODCM: Offsite Dose Calculation Manual

26.

OSLO: Optically Stimulated Luminescence Dosimeter

27.

Protected Area: The fenced area immediately surrounding the Plant. Access to the protected area requires a security badge or escort.

28.

PWR: Pressurized Water Reactor

29.

REC: Radiological Effluent Control

30.

REMP: Radiological Environmental Monitoring Program

31.

Restricted Area: Any area where access is controlled for the purpose of protecting individuals from exposure to radiation or radioactive materials.

32.

SLCs: Selected Licensee Commitments

33.

TEDE: Total Effective Dose Equivalent (TEDE) means the sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).

34.

TLD: Thermoluminescent Dosimeter

35.

TRM: Technical Requirements Manual

36.

TS: Technical Specification

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 5 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 2.0 EXECUTIVE

SUMMARY

Nine Mile Point Unit 1 (NMP1) Radiological Effluent Control (REC) Program was established to limit the quantities of radioactive material that may be released based on calculated radiatio'n doses or dose rates. Dose to Members of the Public due to radioactive materials released from the plant is limited by Appendix I of 1 O CFR 50 and by 40 CFR 190. Operational doses to the public during 2022 were calculated to be very small compared to the limits required by regulation and compared to other sources of radiation dose and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1, Comparison to Regulatory Limits, below.

The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements and provides data related to plant operation, including: quantities of radioactive materials released in liquid and gaseous effluents; radiation doses to members of the public; solid radioactive waste shipped offsite for disposal; and other information as required by site licensing documents.

In 2022 the Land Use Census dose assessments due to radioactive gaseous effluents showed that the critical receptor for Nine Mile Point Unit 1 is child, due to C-14, at the nearest resident. The maximum Annual Organ Dose calculated for this receptor was 3.67E-01 mrem to the bone. This annual dose is a small fraction of the 10 CFR 50, Appendix I guideline of 15 mrem to the Maximum Organ per reactor unit.

Solid radioactive waste shipped offsite for disposal included 3.47E+02 Curies and 3.30E+01 m3, shipped in eight shipments.

In addition to monitoring radioactive effluents, NMP has a Radiological Environmental Monitoring Program (REMP) that monitors for buildup of radioactivity in the offsite environment. Data from the REMP is published in the John A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Environmental Operating Report (AREOR).

Annual Radioactive Effluent Release Report YEAR: 2022 Page 6 of 34 Compan : Constellation Plant: Nine Mile Point Unit 1 2.1 Comparison to Regulatory Limits During 2022 all solid, liquid, and gaseous radioactive effluents from Nine Mile Point Unit 1 were well below regulatory limits, as summarized in Table 1 and Table 2.

Table 1, Nine Mile Point Unit 1 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Liquid Effluent Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem Dose Limit, Total Body Dose 00E+00 00E+00 00E+00 00E+00 Total Body

% of Yearly Limit Liquid Effluent Limit 5 mrem 5 mrem 5 mrem 5 mrem Dose Limit, Max Organ Dose 00E+00 00E+00 00E+00 00E+00 Any Organ

% of Yearly Limit Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad Dose Limit, Gamma Air Dose 00E+00 00E+00 00E+00 00E+00 Gamma Air (Noble Gas)

% of Yearly Limit Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad Dose Limit, Beta Air Dose 00E+00 00E+00 00E+00 00E+00 Beta Air (Noble Gas)

% of Yearly Limit Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem Organ Dose Limit Max Organ Dose 7.36E-03 8.57E-03 7.60E-03 1.10E-02 (Iodine, Tritium, 4.91E-02 1.06E-01 1.57E-01 2.30E-01 Particulates with

% of Yearly Limit

> 8-day half-life) 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual 3 mrem 00E+00 10 mrem 00E+00 10 mrad 00E+00 20 mrad 00E+00 15 mrem 3.45E-02 5.42E-01

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page7 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 2, Dose Potentially Received. by the Likely Most Exposed Member ofthe Public Outside the Site Boundary During 2022 Exposure Pathway Dose Type Dose (mrem)

Fish and Vegetation Consumption Total Whole Body No Dose Total Maxium Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin of Whole No Dose Body Gaseous Effluents Total Whole Body 1.47E-01 (excluding C-14)

Thyroid 1.59E-01 Maximum Organ Skin: 1.60E-01 Bone 1.40E-01 Gaseous Effluent Total Whole Body 4.52E-02 (C-14 only)

Maximum Organ Bone: 2.27E-01 Direct Radiation Total Whole Body 0.66E+00

Annual Radioactive Effluent Release Report YEAR: 2022 Page 8 of 34

3.0 INTRODUCTION

3.1 About Nuclear Power Commercial nuclear power plants are generally classified as either Boiling Water Reactors (BWRs) or Pressurized Water Reactors (PWRs), based on their design.

Nine Mile Point Units 1 and 2 are BWRs. A BWR includes a single coolant system where water used as reactor coolant boils as it passes through the core and the steam generated is used to turn the turbine generator for power production. A PWR, in contrast, includes two separate water systems: radioactive reactor coolant and a secondary system. Reactor coolant is maintained under high pressure, preventing boiling. The high-pressure coolant is passed through a heat exchanger called a steam generator where the secondary system water is boiled, and the steam is used to turn the turbine generator for power production.

Containment Struct1re Figure 1, Pressurized Water Reactor (PWR) [1]

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 9 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 3.1 (Continued)

Containment Structure Figure 2, Boiling Water Reactor (BWR) [2]

Electricity is generated by a nuclear power plant similarly to the way that electricity is generated at other conventional types of power plants, such as those driven by coal or natural gas. Water is boiled to generate steam; the steam turns a turbine that is attached to a generator and the steam is condensed back into water to be returned to the boiler. What makes nuclear power different from these other types of power plants is that the heat is generated by fission and decay reactions occurring within and around the core containing fissionable uranium (U-235).

Nuclear fission occurs when certain nuclides (primarily U-233, U-235, or Pu-239) absorb a neutron and break into several smaller nuclides (called fission products) as well as some additional neutrons.

Fission results in production of radioactive materials including gases and solids that must be contained to prevent release or treated prior to release. These effluents are generally treated by filtration and/or hold-up prior to release. Releases are generally monitored by sampling and by continuously indicating radiation monitors. The effluent release data is used to calculate doses in order to ensure that dose to the public due to plant operation remains within required limits.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 10 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 3.2 About Radiation Dose Ionizing radiation, including alpha, beta, and gamma radiation from radioactive decay, has enough energy to break chemical bonds in tissues and result in damage to tissue or genetic material. The amount of ionization that will be generated by a given exposure to ionizing radiation is quantified as dose. Radiation dose is generally reported in units of millirem (mrem) in the US.

Computed tomograpliy (medical)

(24%)

Terrestrial (background )

(3%)

Nuclear medicine _

(medical)

(12%)

Space (background)

(5%)

lnterventional ftuoroscopy (medical)

(7%)

/

Rai;lon & thoron (background)

(371/o)

Industrial

(<0.1%)

Occupational

(<0.1%)

Consumer (2%)

Conventional radiography/fluoroscopy (medical)

(5o/o)

Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 11 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 3.2 (Continued)

The National Council on Radiation Protection (NCRP) has evaluated the population dose for the US and determined that the average individual is exposed to approximately 620 mrem per year [3]. There are many sources for radiation dose, ranging from natural background sources to medical procedures, air travel, and industrial processes. Approximately half (310 mrem) of the average exposure is due to natural sources of radiation including exposure to Radon, cosmic radiation, and internal radiation and terrestrial due to naturally occurring radionuclides. The remaining 310 mrem of exposure is due to man-made sources of exposure, with the most significant contributors being medical (48%) due to radiation used in various types of medical scans and treatments. Of the remaining 2% of dose, most is due to consumer activities such as air travel, smoking cigarettes, and building materials. A small fraction of this 2% is due to industrial activities including generation of nuclear power.

Readers that are curious about common sources and effects of radiation dose that they may encounter can find excellent sources of information from the Health Physics Society, including the Radiation Fact Sheets [4], and from the US Nuclear Regulatory Commission website [5].

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 12 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 3.3 About Dose Calculation Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples. To overcome this, Dose Calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public, including: Ingestion of radionuclides in food or water; Inhalation of radionuclides in air; Immersion in a plume of noble gases; and Direct Radiation from the ground, the plant or from an elevated plume.

.... : Behaviot of radionuelidea Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]

The Offsite Dose Calculation Manual (ODCM) specifies the methodology used to obtain the doses in the Dose Assessment section of this report. The methodology in the ODCM is based on NRC Regulatory Guide 1.109 [7] and NUREG-0133 [8].

Doses are calculated by determining what the nuclide concentration will be in air, water, on the ground, or in food products based on plant effluent releases. Release points are continuously monitored to quantify what concentrations of nuclides are being released. For gaseous releases meteorological data is used to determine how much of the released activity will be present at a given location outside of the plant either deposited onto the ground or in gaseous form. Intake patterns and nuclide bio-concentration factors are used to determine how much activity will be transferred into animal milk or meat. Finally, human ingestion factors and dose factors are used to determine how much activity will be consumed and how much dose the consumer will receive. Inhalation dose is calculated by determining the concentration of nuclides and how much air is breathed by the individual.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 13 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 3.3 (Continued)

For liquid releases, dilution and mixing factors are used to model the environmental concentrations in water. Drinking water pathways are modeled by determining the concentration of nuclides in the water at the point where the drinking water is sourced. Fish and invertebrate pathways are determined by using concentration at the release point, bioaccumulation factors for the fish or invertebrate and an estimate of the quantity of fish consumed.

Each year a Land Use Census is performed to determine what potential dose pathways currently exist within a five-mile radius around the plant, the area most affected by plant operations. The Annual Land Use Census identifies the locations of vegetable gardens, nearest residences, milk animals and meat animals. The data from the census is used to determine who is the likely to be most exposed to radiation dose as a result of plant operation.

There is significant uncertainty in dose calculation results, due to modeling dispersion of material released and bioaccumulation factors, as well as assumptions associated with consumption and land-use patterns. Even with these sources of uncertainty, the calculations do provide a reasonable estimate of the order of magnitude of the exposure. Conservative assumptions are made in the calculation inputs such as the number of various foods and water consumed, the amount of air inhaled, and the amount of direct radiation exposure from the ground or plume, such that the actual dose received are likely lower than the calculated dose. Even with the built-in conservatism, doses calculated for the highest hypothetical exposed individual due to plant operation are a very small fraction of the annual dose that is received due to other sources. The low calculated doses due to plant effluents, along with REMP results, serve to provide assurance that the site is not having a negative impact on the environment or people living near the plant.

Annual Radioactive Effluent Release Report I YEAR: 2022 I

Page 14 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS 4.1 Regulatory Limits Regulatory limits are detailed in Station Licensing documents such as the Offsite Dose Calculation Manual (ODCM). The ODCM document contains the limits to which NMP unit 1 and 2 must adhere. NMP drives to maintain the philosophy to keep dose "as low as reasonably achievable" (ALARA) and actions are taken to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from NMP is well below the ODCM limits. The concentration of liquid radioactive material released shall be limited to ten times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0 x 10-4 (µCi/ml). These data reveals that the radioactive effluents have an overall minimal dose contribution to the surrounding environment.

The annual whole body, skin and organ dose was computed using the 2022 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents to demonstrate compliance with offsite dose limits are presented in Table 1, Nine Mile Point Unit 1 Dose Summary and Table 2.

4.2

. Regulatory Limits for Gaseous Effluent Doses:

1.

Fission and activation gases:

a.

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

1)

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

2)

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

b.

Noble gas air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly a)

Less than or equal to 5 mrads gamma b)

Less than or equal to 10 mrads beta

2)

Yearly a)

Less than or equal to 1 O mrads gamma b)

Less than or equal to 20 mrads beta 4.2 (Continued)

Annual Radioactive Effluent Release Report, I YEAR: 2022 I Page 15 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1

2.

Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.

a.

The dose rate for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents rel.eased from the site to areas at and beyond the site boundary shall be limited to the following:

1)

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

b.

The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, -and all radionuclides in particulate form with half-lives greater than 8 DAYS in gaseous effluents released, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly a)

Less than or equal to 7.5 mrem to any organ

2)

Yearly a)

Less than or equal to 15 mrem to any organ 4.3 Regulatory Limits for Liquid Effluent Doses

1.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to unrestricted areas shall be limited to the following:

a.

Quarterly

1)

Less than or equal to 1.5 mrem total body

2)

Less than or equal to 5 mrem critical organ

b.

Yearly

1)

Less than or equal to 3 mrem total body

2)

Less than or equal to 1 O mrem critical organ

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 16 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 4.4.

40 CFR 190 Regulatory Dose Limits for a Member of the Public 4.5

1.

Total Dose (40 CFR 190)

2.

a.

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

1)

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

2)

Less than or equal to 75 mrem, Thyroid.

In accordance with NRC memorandum19 HPPOS-140 PDR-9111210378, Guidance on Reporting Dose to Members of the Public from Normal Operations, updated October 17, 2017, NMP1 dose to the public is less than(<)

2.25 mrem dose to any organ or the total body and less than (<) 1. 75 mrem dose to the thyroid. Memorandum can be found on the NRC website:

https://www.nrc.gov/about-nrc/radiation/protects-you/h ppos/hppos 140. html.

Onsite Doses (Within Site Boundary)

This section evaluates dose to non-occupationally exposed workers and members of the public that may be onsite for various reasons. The report must include any other information as may be required by the Commi~sion to estimate maximum potential annual radiation doses to the public resulting from effluent releases as required by 1 O CFR 50.36a(a)(2). While within controlled or restricted areas, the limits from Sections 4.1 through 4.4 do not apply; however, 10 CFR 20.1301 dose limit of 100 mrem per year TEDE and dose rate limit of 2 mrem per hour from external sources continue to apply. Occupancy times within the controlled areas are generally sufficiently low to compensate for increase in the atmospheric dispersion factor above the site boundary. Groups of concern include fishermen, visitors, and daily contractors. Use of a conservative assumption for fishermen is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39-weeks spent inside the site boundary by these groups conservatively represents the most-exposed individual.

Table 3, Onsite Doses (Within Site Boundary)

Total Body Dose External Release Approx.

X/Q XIQ (mrem)

Dose Source Sector Distance s/mA3 s/mA3 Noble

Iodine, TLD and Total (Meters)

(EC)

(Stack)

Gas Particulate, Gamma C-14 & H-3 Combined w

805 6.63E-06 8.90E-06 1.92E-01 6.60E-01 8.52E-01 Note: Combined refers to the combined dose from the stack and reactor building and radwaste.

EC - Emergency Condenser

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 17 of 34 Com I Plant: Nine Mile Point Unit 1 5.0 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 NMP Unit 1 Number of batch releases 0

Total time period for a batch release 0 minutes Maximum time period for a batch release 0 minutes Average time period for a batch release 0 minutes Minimum time period for a batch release 0 minutes 5.2 Liquid Batch Releases 5.2.1 NMP Unit 1 Number of batch releases 0

Total time period for a batch release 0 minutes Maximum time period for a batch release 0 minutes Average time period for a batch release 0 minutes Minimum time period for a batch release 0 minutes Average total flow during period of release 0 gpm 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases Number of releases 0

Total activity released 0 Ci 5.3.2 Liquid Abnormal Releases Number of releases

o.

Total activity released 0 Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 18 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 5.4 5.5 5.6 5.7 5.8 Land Use Census Changes There were no significant changes to the Land Use Census in 2022. On site gardens were not operational for routine sampling in 2022.

Meteorological Data Meteorology data provided via Murray and Trettel, Inc. report. The Nine Mile Point meteorology tower is primarily used to collect meteorology for both the JAF and NMP power plants. Accordingly, the NMP meteorological monitoring program produced 77,447 hours0.00517 days 0.124 hours 7.390873e-4 weeks 1.700835e-4 months of valid data out of 78,840 parameter hours during 2022. Data recovery was 98.2%. Calibrations were performed in May, August, and October. Specific sensor and data errors are available upon request.

Effluent Radiation Monitors Out of Service Greater Than 30 Days Radiation effluent monitoring equipment was operational throughout the year and there were no periods where radiation monitoring equipment was not operational for longer than 30-days.

Offsite Dose Calculation Manual (ODCM) Changes NMP Unit 1 ODCM, CY-NM-170-301 Revision 38 was valid January to December 2022 with no changes required.

Process Control Program (PCP) Changes There were no changes to PCP in 2022.

5.9 Radioactive Waste Treatment System Changes 5.10 There were no changes to the radioactive waste treatment system in 2022.

Other Supplemental Information During 2022, Nine Mile Point Units 1 and 2 had two non-emergency notifications to the NRG:

1. Event 55821 was completed on April 5, 2022.

2. Event 56089 was completed on September 4, 2022.

5.10.1 Outside Tanks During 2022, there were no external water storage tanks containing radioactive material that leaked onto the ground or storm drain.

Annual Radioactive Effluent Release Report YEAR: 2022 Page 19 of 34

___ 5_,1_D.2 _ Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program Information concerning the ISFSI monitoring program and 2022 annual dose can be found in the 2022 John A. FitzPatrick Nuclear Power Plant and Nine Mile Point

Nuclear Station Annual Radiological Environmental Operating Report published on the Nuclear Regulatory Commission website:

https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific-reports/nmp1-2.html.

5.10.3 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide with a 5730-year half-life.

Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.

In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using EPRI Report 1021106, "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents".

This calculation uses active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for NMP Unit 1 during 2022 was 8.84E+00 curies.

Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. Carbon dioxide is assumed to make up 20-30% of the Carbon-14 gaseous emissions from the station based upon available references and on-site testing.

5.10.4 Errata/Corrections to Previous ARERRs There are no corrections to prior ARERRs.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 20 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Nine Mile Point~has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. During 2021, NMP Unit 1 and 2 collected and analyzed groundwater samples in accordance with the site requirements.

This section is included in this report to communicate results of NEI 07-07 Radiological Groundwater Monitoring Program. Monitoring wells installed as part of GPI program are sampled and analyzed annually and quarterly. In addition to reporting results from NEl 07-07 monitoring wells, new voluntary communications made for onsite leaks or spills per NEI 07-07 Objective 2.2, are also reported as part of this report. It is important to note, samples and results taken in support of NEI 07-07 groundwater monitoring program are not part of the Radiological Environmental Monitoring Program (REMP) but should be reported as part of AREOR or ARERR.

Number of positive detections for Tritium: 6 Number of analyses: 49 Number of samples below lower level of detection: 43 Maximum concentration identified: 381 pCi/L Table 4, Groundwater Protection Program Monitoring Well Results Number of Average Maximum Type of Number of Well Name Positive

Concentration 2 Concentration Analysis Analyses Detections (pCi/L)

(pCi/L)

GMX-MW1 (control)

Tritium 0

1

<191

<191 MW-1 Tritium 0

1

<173

<173 MW-5 Tritum 0

4

<182

. <194 MW-6 Tritium 0

1

<188

<188 MW-7 Tritium 0

1

<185

<185 MW-8 Tritium 0

4

<184

<184 MW-9 (sentinel well)

Tritium 0

4

<182

<182 MW-10 (sentinel well)

Tritium 1

1 227 227 MW-11 Tritium 0

1

<194

<194 MW-12 Tritium 0

1

<191

<191 MW-13 Tritium 0

1

<189

<189 MW-14 (control)

Tritium 0

1

<181

<181 MW-15 Tritium 1

4

<176 204 MW-16 Tritium 1

1 264 264 2 Results <MDA should not be included in the average concentration calculation.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 21 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 4, Groundwater Protection Program Monitoring Well Results Type Qf Number of Number of Average Maximum Well Name Analysis Positive Analyses Concentration 2 Concentration Detections (pCi/L)

(pCi/L)

MW-17 Tritium 0

4

<176

<194 MW-18 Tritium 0

4

<180

<197 MW-19 Tritium 0

1

<179

<179 MW-20 Tritium 0

1

<194

<194 MW-21 Tritium 0

1

<189

<189 NMP2 MAT1 Tritium 3

4

<184 381 PZ-7 Tritium 0

4

<177

<203 PZ-8 Tritium 0

4

<180

<191 Note 1: NMP2 MAT is the groundwater depression cone. Samples collected from storm drain system, which includes precipitation; likely atmospheric recapture.

6.1 Voluntary Notification During 2022, Nine Mile Point Units 1 and 2 did not make a voluntary NEI 07-07 notification to State/Local officials, NRG, and to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 22 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 7.0 BIBLIOGRAPHY

[1] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].

[2] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].

[3] "NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States","

National Council on Radiation Protection and Measurements, Bethesda, MD, 2009.

[4] [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020].

[5] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 1 O November 2020].

[6] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:

https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.

[7] "Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 1 O CFR Part 50, Appendix I,,"

Nuclear Regulatory Commission, Ocotober, 1977.

[8] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants,"

Nuclear Regulatory Commission, 1987.

[9] "NEI 07 Industry Ground Water Protection Initiative -

Final Guidance Document, Rev. 1,"

Nuclear Energy Institute, Washington, D.C., 2019.

[10] "Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revisio_n 2," Nuclear Regulatory Commision, June, 2019.

[11] "Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"

Nuclear Regulatory Commission, July, 2007.

[12] "10 CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.

[13] "NUREG-0324, "XOQDOQ, Program for the Meteorqlogical Evaluation of Routine Effluent Releases at Nuclear Power Stations,"," Nuclear Regulatory Commission, September, 1977.

[14] "NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,".," Nuclear Regulatory Commission, April 1991.

[15] "NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors,"," Nuclear Regulatory Commission, April 1991.

[16] "40 CFR Part 141, "National Primary Drinking Water Regulations,"," US Environmental Protection Agency, Washington, DC..

[17] "40 CFR 190 - Environmental Radiation Protection Standards fqr Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.

[18] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

[19] HPPOS-140 PDR-9111210378, NRC memorandum from D.R. Muller to T.M. Novak and G.C.

Lain as dated March 10, 1983.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 23 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 5, Gaseous Effluents Summation of All Releases NMP1 A.

Fission & Activation Gases Units Quarter Quarter Quarter Quarter Est. Total 1

2 3

4 Error%

1.

Total Release Ci 5.00E+01

2.

Average release rate for the period

µCi/sec B.

Iodine

1.

Total Iodine -131 Ci 8.05E-05 1.04E-04 4.96E-05 8.33E-05 3.00E+01

2.

Average release rate for the period

µCi/sec 1.04E-05 1.32E-05 6.23E-06 1.05E-05 C.

Particulates

1.

Particulates with half-lives > 8 days Ci 2.?0E-03 3.11 E-03 3.92E-03 5.95E-03 3.00E+01

2.

Average release rate for the period

~LCilsec 3.47E-04 3.95E-04 4.94E-04 7.49E-04 D.

Tritium

1.

Total Release Ci 5.80E+00 1.61 E+01 8.35E+00 5.86E+00 5.00E+01

2.

Average release rate for the period

µCi/sec 7.46E-01 2.05E+00 1.05E+00 7.38E-01 E.

Gross Alpha

1.

Total Release Ci 5.00E+01

2.

Average release rate for the period

~LCi/sec F.

Carbon-14

1.

Total Release Ci 2.18E+00 2.20E+00 2.23E+00 2.23E+0O 5.00E+01

2.

Average release rate for the period

µCi/sec 4.41E-02 4.46E-02 4.51E-02 4.50E-02

% of limit is on Table 1, Nine Mile Point Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 24 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci (List Others)

Ci Total for Period Ci Iodines 1-131 Ci 1-133 Ci 1-135 Ci (List Others)

Ci Total for Period Ci Particulates Co-58 Ci Co-60 Ci Sr-89 Ci Sr-90 Ci Cs-134 Ci (List Others)

Ci Total for Period Ci Tritium H-3 Ci Gross Alpha Alpha Ci I

I Carbon-14 C-14 Ci I

I

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 25 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 7, Gaseous Effluents - Ground Level Release Continuous Mode NMP1 Quarter 1 Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci (List Others)

Ci Total for Period Ci 1-131 Ci 1-133 Ci 1-135 Ci Total forPeriod Ci Co-58 Ci Co..SO Ci Sr-89 Ci Sr-90 Ci Cs-134 Ci (List Others)

Ci Total for Period Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 26 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released I Fission Gases I

Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci (List Others)

Ci Total for Period Ci I10.dines

. I 1-131 Ci 1-133 Ci 1-135 Ci (List Others)

Ci Total for Period Ci Particulates Co-58 Ci Co-60 Ci Sr-89 Ci Sr-90 Ci Cs-134 Ci (List others)

Ci Total for Period Ci II llllll;IIII H-3 Ci G~6ss* Alph~**i:

fr,

~

,_. :,:,.. r:: '.

','1: :,

.. ~/:!<..

)S" ~ C I

Alpha Ci Carbon-14

I C-14 Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 27 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for Period Ci Iodines 1-131 Ci 8.05E-05 1.04E-04 4.96E-05 8.33E-05 3.18E-04 1-133 Ci 2.83E-03 2.31E-03 1.0SE-03 2.26E-03 8.50E-03 1-135 Ci Total for Period Ci 2.91E-03 2.41 E-03 1.13E-03 2.34E-03 8.82E-03 I Particulates*

I

,,;":}*';/

Co-58 Ci 8.82E-04 7.76E-04 9.20E-04 1.26E-03 3.84E-03 Co-60 Ci 1.17E-03 1.33E-03 1.57E-03 2.23E-03 6.30E-03 Sr-89 Ci Sr-90 Ci Cs-134 Ci Mn-54 Ci 1.05E-04 2.01E-04 2.23E-04 2.54E-04 7.83E-04 Fe-55 Ci 3.27E-04 5.23E-04 6.67E-04 4.06E-04 1.92E-03 Zn-65 Ci 1.84E-04 2.59E-04 5.18E-04 7.46E-04 1.71 E-03 Cs-137 Ci 3.12E-05 1.47E-05 3.01E-05 1.07E-05 8.67E-05 Ni-63 Ci 1.05E-03 1.05E-03 Ag-11 Om Ci 4.69E-06 4.69E-06 Total for Period Ci 2.70E-03 3.11 E-03 3.93E-03 5.96E-03 1.57E-02 Tritium**

.. ;' __ }c,.:

~' **'"

r::*,~;..~t'," "

H-3 Ci 4.91 E+OO 1.52E+01 6.93E+OO 5.09E+OO I

3.21E+01 I

Gross Alpha t~lpha Ci I

I

~4

.:-\

,~<' '> 1 >

1,

\ ~,, "*,

Ci I 2.18E+OO I 2.20E+OO I 2.23E+OO I

2.23E+OO II 8.84E+00 I

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 28 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 2.0 LIQUID EFFLUENTS Table 10, Liquid Effluents - Summation of All Releases NMP1 Quarter Quarter Quarter Quarter Est.

A.

Fission & Activation Products Units Total 1

2 3

4 Error%

1.

Total Release Ci 5.00E+01

2.

Average diluted concentration

µCi/ml

8.

Tritium

1.

Total Release Ci 5.00E+01 I

2.

Average diluted concentration

µCi/ml C.

Dissolved & Entrained Gases

1.

Total Release Ci 5.00E+01 2

Average diluted concentration

µCi/ml D.

Gross Alpha Activity

1.

Total Release Ci 5.00E+01 E.

Volume of Waste Released (prior Liters to dilution)

F.

Volume of Dilution Water Used During Liters 1.39E+11 1.36E+11 1.39E+11 1.30E+11 Period

% of li.mit is on the Table 1, Nine Mile Point Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 29 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 11, Batch Mode Liquid Effluents NMP1 Radionuclide Released Units :

Quarter 1 Fissidnan*d.Activation;P(oducts.*

Cr-51 Ci Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-60 Ci Sr-89 Ci Ci Nb-95 Ci Zn-65 Ci Ag-110111 Ci 1-131 Ci 1-133 Ci Cs-134 Ci Cs-137 Ci (List Others)

Ci Total for Period Ci Xe-135 Ci (List Others)

Ci Total for Period Ci Quarter 2 Quarter 3 Quarter 4 Total for year

Annual Radioactive Effluent Release Report I YEAR: 2022 I

Page 30 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 12, Continuous Mode Liquid Effluents NMP1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activatio11 Products Cr-51 Ci Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-60 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zn-65 Ci Ag-110m Ci 1-131 Ci 1-133 Ci Cs-134 Ci Cs-137 Ci (List Others)

Ci Total for Period Ci Tritium H-3 Ci Gross Alpha*>_

"',t I

Alpha I Ci I Entrained Gases'.

Xe-133 Ci Xe-135 Ci (List Others)

Ci Total for Period Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 31 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1, Solid Waste Information

.1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Table 13, Types of Solid Waste Summary NMP Unit 1 Total Volume Total Activity Types of Waste (m3)

(Ci)

a. Spent resins, filter sludges, evaporator b9ttoms, etc.

3.30E+01 3.47E+02

b. Dry compressible waste, contaminated equip, etc.

O.OOE+OO O.OOE+OO

c. Irradiated components, control rods, etc.

O.OOE+OO O.OOE+OO

d. Other (None reported)

O.OOE+OO O.OOE+OO Est. Total Error

(%)

25 25 25 25 2.0 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY WASTE TYPE) ONLY >1 %

ARE REPORTED. [NOTE 1]

. Table 14, Major Nuclides NMP Unit 1 Major Nuclide Composition Isotope Curies

a. Spent resins, filter sludges, evaporator bottoms, etc.

Co-60 79.39 2.75E+02 C-14 <1 % (3.33E-01 curies)

Fe-55 13.2 4.58E+01 Zn-65 <1 % 93.02E-01 curies)

Cs-137 3.09 1.07E+01 Mn-54 2.31 8.00E+00

b. Dry compressible waste, contaminated equip, etc.

0 00E+00

c. Irradiated components, control rods, etc.

0 00E+00

d. Other (describe) 0 00E+00

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 32 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 3.0 SOLID WASTE DISPOSITION Table 15, Solid Waste Disposition NMP Unit 1 Number of Mode of Transportation Destination Shipments 5

NRG Class: A; DOT Type: A LSA-11 Energy Solutions Clive (CWF Containerized Waste Facility) 3 NRG Class: B, DOT Type: B Waste Control Specialists LLC (CWF Facility) 4.0 IRRADIATED FUEL DISPOSITION Table 16, Irradiated Fuel Shipments Disposition NMP Unit 1 Number of Mode of Transportation Destination Shipments 0

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 33 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1, Meteorological Data 1.0 METEOROLOGICAL DATA

SUMMARY

1.1 Joint Frequency Distributions

1.

Period of Record: 2022

2.

Stability Class: All

a.

Periods of calm (hours): 12

b.

Hours of missing data: 155 hours0.00179 days 0.0431 hours 2.562831e-4 weeks 5.89775e-5 months

c.

Meteorological data quality 98.2% for all stability classes and parameters.

d.

Total annual precipitation: 27.32 inches

3.

Elevation: 200 ft.

Wind Speed Range (m/s)

Wind

<0.5 0.5 1.1 1.6 2.1 3.1 4.1 5.1 6.1 8.1

>10.0 Total Direction 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 N

0 4

12 17 40 58 43 27 54 19 44 318 NNE 1

2 8

9 38 67 34 47 99 50 116 471 NE 0

4 12 20 50 51 46 44 40 25 12 304 ENE 0

3 10 21 39 47 10 4

6 0

0 140 E

0 2

10 11 58 65 22 12 17 0

0 197 ESE 1

4 3

13 37 65 55 42 48 17 7

292 SE 0

3 9

10 35 96 103 113 303 116 38 826 SSE 0

1 6

10 27 114 80 132 355 125 44 894 s

0 5

3 11 25 95 109 132 344 108 45 877 SSW 1

3 6

6 31 76 109 133 210 21 1

597 SW 1

4 6

15 26 74 68 86 163 48 20 510 WSW 0

4 9

11 38 104 82 106 206 110 150 820 w

0 4

7 18 37 103 63 70 143 123 288 856 WNW 1

3 9

12 34 67 34 23 101 82 221 587 NW 1

5 4

9 38 42 40 41 116 84 141 521 NNW 1

3 12 13 43 44 34 26 82 45 46 349 Total 7

54 126 206 595 1168 932 1038 2287 973 1173 8559

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 34 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 1.2 Stability class Table 17, Classification of Atmospheric Stability Stability Condition Pasquill Categories Hours Percentage Extremely Unstable A

969 11.3%

Moderately Stable 8

568 6.6%

Slightly Unstable C

722 8.4%

Neutral D

3306 38.6%

Slightly Stable E

1865 21.8%

Moderately Stable F

610 7.1%

Extremely Stable G

519 6.1%

Note: Percentage is calculated based on the 200ft winds and 200ft-30ft stability hourly data for the year (8559 hours0.0991 days 2.378 hours 0.0142 weeks 0.00326 months of valid data).

ENCLOSURE 2 Nine Mile Point Nuclear Station, Unit 2 Radiological Effluent Release Report, January - December 2022

Constellation Nine Mile Point Annual Radioactive Effluent Release Report 2022 Document Number: NMP1 L3522

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 1 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS.................................................................................. 3 2.0 EXECUTIVE

SUMMARY

...........................................................................,.................................. 5 2.1 Comparison to Regulatory Limits...................................................................................... 6

3.0 INTRODUCTION

........................................................................................................................... 8 3.1 About Nuclear Power........................................................................................................ 8 3.2 About Radiation Dose..................................................................................................... 1 O 3.3 About Dose Calculation................................................................................................... 12 4.0 DOSE ASSESSMEN:r FOR PLANT OPERATIONS................................................................... 14 4.1 Regulatory Limits............................................................................................................. 14 4.2 Regulatory Limits for Gaseous Effluent Doses:............................................................... 14 4.3 Regulatory Limits for Liquid Effluent Doses.................................................................... 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................... 16 4.5 Onsite Doses (Within Site Boundary).............................................................................. 16 5.0 SUPPLEMENTAL INFORMATION............................................................................................. 17 5.1 Gaseous Batch Releases................................................................................................ 17 5.2 Liquid Batch Releases..................................................................................................... 17 5.3 Abnormal Releases......................................................................................................... 17 5.4 Land Use Census Changes............................................................................................ 18 5.5 Meteorological Data........................................................................................................ 18 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days................................. 18

5. 7 Offsite Dose Calculation Manual (ODCM) Changes....................................................... 18 5.8 Process Control Program (PCP) Changes...................................................................... 18 5.9 Radioactive Waste Treatment System Changes............................................................. 18 5.10 Other Supplemental Information..................................................................................... 18 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM................ 20 6.1 Voluntary Notification...................................................... :............................................... 21 7.0 BIBLIOGRAPHY......................................................................................................................... 22 TABLES Table 1, Nine Mile Point Units 2 Dose Summary..................................................................................... 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for NMP..................................... 7 Table 3, Onsite Doses (Within Site Boundary)....................................................................................... 16 Table 4, Groundwater Protection Program Monitoring Well Results...................................................... 20 Table 5, Gaseous Effluents Summation of All Releases NMP 2........................................................... 23 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP 2........................................... 24 Table 7, Gaseous Effluents - Ground Level Release Continuous Mode NMP 2.................................. 25 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP 2......................................... 26 Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP 2.................................. 27 Table 10, Liquid Effluents - Summation of All Releases NMP 2............................................................ 28 Table 11, Batch Mode Liquid Effluents NMP 2....................................................................................... 29

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 2 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 12, Continuous Mode Liquid Effluents NMP 2.............................................................................. 30 Table 13, Types of Solid Waste Summary NMP 2.......................................................................,,:......... 31 Table 14, Major Nuclides NMP 2............................................................................................................ 31 Table 15, Solid Waste Disposition NMP 2.............................................................................................. 32 Table 16, Irradiated Fuel Shipments Disposition NMP 2........................................................................ 32 Table 17, Classification of Atmospheric Stability.................................................................................... 34 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]....................................................................................... 8 Figure 2, Boiling Water Reactor (BWR) [2].............................................. :................................................ 9 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]................................................... 1 O Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6].............. 12 ATTACHMENTS Attachm~nt 1, ARERR Release Summary Tables (RG-1.21 Tables)..................................................... 23, Solid Waste lnformation.............,...................................................................................... 31, Meteorological Data......................................................................................................... 33

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 3 of 34 Com an : Constellation Plant: Nine Mile Point Unit 2 1.0 LIST OF ACRONYMS AND DEFINITIONS

1.

Airborne Activity Sampling: Sampling of air through the collection of particulates and radionuclides on filter media, collection of noble gases in a container, and collection of water vapor containing tritium.

2.

Alpha Particle (a): A charged particle emitted from the nucleus of an atom having a mass and charge equal in magnitude of a helium nucleus.

3.

BWR: Boiling Water Reactor

4.

Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.

5.

Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the Plant.

6.

Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on total counts accumulated.

7.

Curie (Ci): A measure of radioactivity; equal to 3.7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.

8.

Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.

9.

Grab Sample: A single discrete sample drawn at one point in time.

10.

Indicator: A sampling location that is likely to be affected by plant effluents due to its proximity and/or direction from the plant.

11.

Ingestion Pathway: The ingestion pathway includes milk, fish, and garden produce. Meat or other food products may also be included.

12.

ISFSI: Independent Spent Fuel Storage Installation

13.

Lower Limit of Detection (LLD): The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with a 5% probability of a false conclusion that a blank observation represents "real" signal.

14.

MDA: Minimum Detectable Activity. - For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95%

probability, with only five% probability of falsely concluding that a blank observation represents a true signal.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 4 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2

15.

MDC: Minimum Detectable Concentration, essentially synonymous with MDA for the purposes of radiological monitoring.

16.

Mean: The average, i.e., the sum of results divided by the number of results.

17.

Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.

18.

millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.

19.

Milliroentgen (mR): 1/1000 Roentgen; a unitof exposure to X-or gamma radiation.

20.

MWe: Megawatts Electric

21.

MWTh: Megawatts Thermal

22.

NA: Not Applicable

23.

NEI: Nuclear Energy Institute

24.

NRG: Nuclear Regulatory Commission

25.

ODCM: Offsite Dose Calculation Manual

26.

OSLO: Optically Stimulated Luminescence Dosimeter

27.

Protected Area: The fenced area immediately surrounding the Plant. Access to the protected area requires a security badge or escort.

28.

PWR: Pressurized Water Reactor

29.

REC: Radiological Effluent Control

30.

REMP: Radiological Environmental Monitoring Program

31.

Restricted Area: Any area where access is controlled for the purpose of prptecting individuals from exposure to radiation or radioactive materials.

32.

SLCs: Selected Licensee Commitments

33.

TEDE: Total Effective Dose Equivalent (TEDE) means the sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for intern*aI exposures).

34.

TLD: Thermoluminescent Dosimeter

35.

TRM: Technical Requirements Manual

36.

TS: Technical Specification

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 5 of 34 Com

I Plant: Nine Mile Point Unit 2 2.0 EXECUTIVE

SUMMARY

Nine Mile Point Unit 2 (NMP2) Radiological Effluent Control (REC) Program was established to limit the quantities of radioactive material that may be released based on calculated radiation doses or dose rates. Dose to Members of the Public due to radioactive materials released from the plant is limited by Appendix I of 1 O CFR 50 and by 40 CFR 190. Operational doses to the public during 2022 were calculated to be very small compared to the limits required by regulation and compared to other sources of radiation dose and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1, Comparison to Regulatory Limits, below.

The Annual Radioactive Effluent Release Report (ARERR) is published per NMP requirements and provides data related to plant operation, including: quantities of radioactive materials released in liquid and gaseous effluents; radiation doses to members of the public; solid radioactive waste shipped offsite for disposal; and other information as required by site licensing documents.

In 2022 the Land Use Census dose assessments due to radioactive gaseous effluents showed that the critical receptor for Nine Mile Point Unit 2 is child, due to C-14, at the nearest resident. The maximum Annual Organ Dose calculated for this receptor was 3.67E-01 mrem to the bone. This annual dose is a small fraction of the 10 CFR 50, Appendix I guideline of 15 mrem to the Maximum Organ per reactor unit Solid radioactive waste shipped offsite for disposal included 1.89E+01 Curies and 5.73E+02 m3, shipped in twenty-one shipments.

In addition to monitoring radioactive effluents, NMP has a Radiological Environmental Monitoring Program (REMP) that monitors for buildup of radioactivity in the offsite environment. Data from the REMP is published in the John A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Statiof"'! Annual Radiological Environmental Operating Report (AREOR).

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 6 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 2.1 Comparison to Regulatory Limits During 2022 all solid, liquid, and gaseous radioactive effluents from Nine Mile Point Unit 2 were well below regulatory limits, as summarized in Table 1 and Table 2.

Table 1, Nine Mile Point Unit 2 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Liquid Effluent Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem Dose Limit, Total Body Dose 00E+00 00E+00 00E+00 00E+00 Total Body

% of Yearly Limit Liquid Effluent Limit 5 mrem 5 mrem 5 mrem 5 mrem Dose Limit, Max Organ Dose 00E+00 00E+00 00E+00 00E+00 Any Organ

% of Yearly Limit Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad Dose Limit, Gamma Air Dose 00E+00 00E+00 3.65E-04 00E+00 Gamma Air (Noble Gas)

% of Yearly Limit

<1.0E-02 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad Dose Limit, Beta Air Dose 00E+00 00E+00 1.13E-05 00E+00 Beta Air (Noble Gas)

% of Yearly Limit

<1.0E-02 Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem Organ Dose Limit Max Organ Dose 1.34E-02 9.79E-03 9.23E-01 8.43E-01 (Iodine, Tritium, Particulates with

% of Yearly Limit 6.68E-03 1.03E-02 4.67E-01 8.89E-01

> 8-day half-life) 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual 3 mrem 00E+00 10 mrem 00E+00 10 mrad 5.55E-04 5.55E-03 20 mrad 5.15E-05 2.58E-04 15 mrem 1.79E+00 1.37E+00

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 7 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 2, Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2022 Exposure Pathway Dose Type Dose (mrem)

Fish and Vegetation Consumption Total Whole Body No Dose Total Maxium Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin of Whole No Dose Body Gaseous Effluents Total Whole Body 1.47E-01 (excluding C-14)

Thyroid 1.59E-01 Maximum Organ Skin: 1.60E-01 Bone 1.40E-01 Gaseous Effluent Total Whole Body 4.52E-02 (C-14 only)

Maximum Organ Bone: 2.27E-01 Direct Radiation Total Whole Body 0.66E+00

Annual Radioactive Effluent Release Report YEAR: 2022 Page 8 of 34

3.0 INTRODUCTION

3.1 About Nuclear Power Commercial nuclear power plants are generally classified as either Boiling Water Reactors (BWRs) or Pressurized Water Reactors (PWRs), based on their design.

Nine Mile Point Units 1 and 2 are BWRs. A BWR includes a single coolant system where water used as reactor coolant boils as it passes through the core and the steam generated is used to turn the turbine generator for power production. A PWR, in contrast, includes two separate water systems: radioactive reactor coolant and a secondary system. Reactor coolant is maintained under high pressure, preventing boiling. The high-pressure coolant is passed through a heat exchanger called a steam generator where the secondary system water is boiled, and the steam is used to turn the turbine generator for power production.

Containment Structire Figure 1, Pressurized Water Reactor (PWR) [1]

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 9 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 3.1 (Continued)

Containment Structure Figure 2, Boiling Water Reactor (BWR) [2]

Electricity is generated by a nuclear power plant similarly to the way that electricity is generated at other conventional types of power plants, such as those driven by coal or natural gas. Water is boiled to generate steam; the steam turns a turbine that is attached to a generator and the steam is condensed back into water to be returned to the boiler. What makes nuclear power different from these other types of power plants is that the heat is generated by fission and decay reactions occurring within and around the core containing fissionable uranium (U-235).

Nuclear fission occurs when certain nuclides (primarily U-233, U-235, or Pu-239) absorb a neutron and break into several smaller nuclides (called fission products) as well as some additional neutrons.

Fission results in production of radioactive materials including gases and solids that must be contained to prevent release or treated prior to release. These effluents are generally treated by filtration and/or hold-up prior to release. Releases are generally monitored by sampling and by continuously indicating radiation monitors. The effluent release data is used to calculate doses in order to ensure that dose to the public due to plant operation remains within required limits.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 10 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 3.2 About Radiation Dose Ionizing radiation, including alpha, beta, and gamma radiation from radioactive decay, has enough energy to break chemical bonds in tissues and result in damage to tissue or genetic material. The amount of ionization that will be generated by a given exposure to ionizing radiation is quantified as dose. Radiation dose is generally reported in units of millirem (mrem) in the US.

Computed (omogr plly (madleal)

(24%)

Terrestrial (background)

(3%)

Nuclear medicine (medical)

(12%)

Space (bacilligrou ridl (S%)

lnterventional nuoroscopy -----------

(medicel)

~

(7%)

Radon & thoron (background)

(37%)

Industrial

(<0.1%)

Occupational

(<0.1','o}

Consumer (2%)

Conventional radiography/ftuoroscopy (medical)

(5%)

Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 11 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 3.2 (Continued)

The National Council on Radiation Protection (NCRP) has evaluated the population dose for the US and determined that the average individual is exposed to approximately 620 mrem per year [3]. There are many sources for radiation dose, ranging from natural background sources to medical procedures, air travel, and industrial processes. Approximately half (310 mrem) of the average exposure is due to natural sources of radiation including exposure to Radon, cosmic radiation, and internal radiation and terrestrial due to naturally occurring radionuclides. The remaining 310 mrem of exposure is due to man-made sources of exposure, with the most significant contributors being medical (48%) due to radiation used in various types of medical scans and treatments. Of the remaining 2% of dose, most is due to consumer activities such as air travel, smoking cigarettes, and building materials. A small fraction of this 2% is due to industrial activities including generation of nuclear power.

Readers that are curious about common sources and effects of radiation dose that they may encounter can find excellent sources of information from the Health Physics Society, including the Radiation Fact Sheets [4], and from the US Nuclear Regulatory Commission website [5].

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 12 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 3.3 About Dose Calculation Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples. To overcome this, Dose Calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public, including: Ingestion of radionuclides in food or water; Inhalation of radionuclides in air; Immersion in a plume of noble gases; and Direct Radiation from the ground, the plant or from an elevated plume.

Deposition Livestock producta Gaseous emuenta

~

- - - - lnges i

- . Inhalation

~

\ DeJ)Ollition t **:**..

1

.:~~~.

1

~~..........

~

+ ******

0 Public 11

- I ngeatton \

... : Radiation o

Radionuclides

.... : Behavior of radionuclidea Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]

The Offsite Dose Calculation Manual (ODCM) specifies the methodology used to obtain the doses in the Dose Assessment section of this report. The methodology in the ODCM is based on NRC Regulatory Guide 1.109 [7] and NUREG-0133 [8].

Doses are calculated by determining what the nuclide concentration will be in air, water, on the ground, or in food products based on plant effluent releases. Release points are continuously monitored to quantify what concentrations of nuclides are being released. For gaseous releases meteorological data is used to determine how much of the released activity will be present at a given location outside of the plant either deposited onto the ground or in gaseous form. Intake patterns and nuclide bio-concentration factors are used to determine how much activity will be transferred into animal milk or meat. Finally, human ingestion factors and dose factors are used to determine how much activity will be consumed and how much dose the consumer will receive. Inhalation dose is calculated by determining the concentration of nuclides and how much air is breathed by the individual.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 13 of 34

_Com I Plant: Nine Mile Point Unit 2 3.3 (Continued)

For liquid releases, dilution and mixing factors are used to model the environmental concentrations in water. Drinking water pathways are modeled by determining the concentration of nuclides in the water at the point where the drinking water is sourced. Fish and invertebrate pathways are determined by using concentration at the release point, bioaccumulation factors for the fish or invertebrate and an estimate of the quantity of fish consumed.

Each year a Land Use Census is performed to determine what potential dose pathways currently exist within a five-mile radius around the plant, the area most affected by plant operations. The Annual Land Use Census identifies the locations of vegetable gardens, nearest residences, milk animals and meat animals. The data from the census is used to determine who is the likely to be most exposed to radiation dose as a result of plant operation.

There is significant uncertainty in dose calculation results, due to modeling dispersion of material released and bioaccumulation factors, as well as assumptions associated_

with consumption and land-use patterns. Even with these sources of uncertainty, the calculations do provide a reasonable estimate of the order of magnitude of the exposure. Conservative assumptions are made in the calculation inputs such as the number of various foods and water consumed, the amount of air inhaled, and the amount of direct radiation exposure from the ground or plunJe, such that the actual dose received are likely lower than the calculated dose. Even with the built-in conservatism, doses calculated for the highest hypothetical exposed individual due to plant operation are a very small fraction of the annual dose that is received due to other sources. The low calculated doses due to plant effluents, along with REMP results, serve to provide assurance that the site is not having a negative impact on

the environment or people living near the plant.

Com 4.0 4.1 4.2 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 14 of 34 I Plant: Nine Mile Point Unit 2 DOSE ASSESSMENT FOR PLANT OPERATIONS Regulatory Limits Regulatory limits are detailed in Station Licensing documents such as the Offsite Dose Calculation Manual (ODCM). The ODCM document contains the limits to which NMP unit 1 and 2 must adhere. NMP drives to maintain the philosophy to keep dose "as low as reasonably achievable" (ALARA) and actions are taken to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from NMP is well below the ODCM limits. The concentration of liquid radioactive material released shall be limited to ten times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0 x 10-4 µCi/ml. These data reveals that the radioactive effluents have an overall minimal dose contribution to the surrounding environment.

The annual whole body, skin and organ dose was computed using the 2022 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents to demonstrate compliance with offsite dose limits are presented in Table 1, Nine Mile Point Unit 1 Dose Summary and Table 2.

Regulatory Limits for Gaseous Effluent Doses:

1.

Fission and activation gases:

a.

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

1)

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

2)

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

b.

Noble gas air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly a)

Less than or equal to 5 mrads gamma b)

Less than or equal to 1 O mrads beta

2)

Yearly a)

Less than or equal to 10 mrads gamma b)

Less than or equal to 20 mrads beta 4.2 (Continued)

Com 4.3 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 15 of 34 I Plant: Nine Mile Point Unit 2

2.

Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.

a.

The dose rate for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary shall be limited to the following:

1)

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

b.

The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 DAYS in gaseous effluents released, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly a)

Less than or equal to 7.5 mrem to any organ

2)

Yearly a)

Less than or equal to 15 mrem to any organ Regulatory Limits for Liquid Effluent Doses

1.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to unrestricted areas shall be limited to the following:

a.

Quarterly

1)

Less than or equal to 1.5 mrem total body

2)

Less than or equal to 5 mrem critical organ

b.

Yearly

1)

Less than or equal to 3 mrem total body

2)

Less than or equal to 1 O mrem critical organ

Annual Radioactive Effluent Release Report

\ YEAR: 2022

\

Page 16 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public 4.5

1.

Total Dose (40 CFR 190)

a.

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

1)

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

2)

Less than or equal to 75 mrem, Thyroid.

2.

In accordance with NRC memorandum19 HPPOS-140 PDR-9111210378, Guidance on Reporting Dose to Members of the Public from Normal Operations, updated October 17, 2017, NMP2 dose to the public is less than(<)

2.25 mrem dose to any organ or the total body and less than(<) 1.75 mrem dose to the thyroid. Memorandum can be found on the NRC website:

https://www.nrc.gov/about-nrc/radiation/protects-you/hppos/hppos140.html.

Onsite Doses (Within Site Boundary)

This section evaluates dose to non-occupationally exposed workers and members of the public that may be onsite for various reasons. The report must include any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases as required by 1 O CFR 50,36a(a)(2). While within controlled or restricted areas, the limits from Sections 4.1 through 4.4 do not apply; however, 10 CFR 20.1301 dose limit of 100 mrem per year TEDE and dose rate limit of 2 mrem per hour from external sources continue to apply. Occupancy times within the controlled areas are generally sufficiently low to compensate for increase in the atmospheric dispersion factor above the site boundary. Groups of concern include fishermen, visitors, and daily contractors. Use of a conservative assumption for fishermen is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39-weeks spent inside the site boundary by these groups conservatively represents the most-exposed individual.

Table 3, Onsite Doses (Within Site Boundary)

Total Body Dose External Dose Effluent Approx.

X/Q X/Q

Iodine, Sector Distance s/mA3 s/mA3 Noble Total Source (Meters)

(Vent)

(Stack)

Gas Particulate, TLD and C-14 & H-3 Gamm~

(mrem)

Combined w

805 2.80e-06 9.60E-07 4.21 E-04 1.81E+00 6.60E-01 2.47E+00 Note: combined refers to the combined dose from the stack and reactor buildinQ and radwaste.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 17 of 34 Combany: Constellation I Plant: Nine Mile Point Unit 2 5.0 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 NMP Unit 2 Number of batch releases 4

Total time period for a batch release 354 minutes Maximum time period for a batch release 127 minutes Average time period for a batch release 89 minutes Minimum time period for a batch release 50 minutes 5.2 Liquid Batch Releases 5.2.1 NMP Unit 2 Number of batch releases 0

Total time period for a batch release 0 minutes Maximum time period for a batch release 0 minutes Average time period for a batch release 0 minutes Minimum time period for a batch release 0 minutes Average total flow during period ofrelease 0 gpm 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases Number of releases 0

Total activity released 0 Ci 5.3.2 Liquid Abnormal Releases Number of releases 0

Total activity released 0 Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 18 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 5.4 5.5 Land Use Census Changes There were no significant changes to the Land Use Census in 2022. On site gardens were not operational for routine sampling in 2022.

Meteorological Data Meteorology data provided via Murray and Trettel, Inc. report. The Nine Mile Point meteorology tower was used to collect meteorology for both the JAF and NMP power plants. Accordingly, NMP meteorological monitoring program produced 77,447 hours0.00517 days 0.124 hours 7.390873e-4 weeks 1.700835e-4 months of valid data out of 78,840 parameter hours during 2022. Data recovery was 98.2%.

Calibrations were performed in May, August, and October. Specific sensor and data collection errors are available upon request.

5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days Radiation effluent monitoring equipment was operational throughout the year and there were no periods where radiation monitoring equipment was not operational for longer than 30-days.

5.7 Offsite Dose Calculation Manual (ODCM) Changes 5.8 5.9 5.10 NMP Unit 2 ODCM, CY-AA-170-3100 Revision 37 was valid January to December 2022 with no changes required.

Process Control Program (PCP) Changes There were no changes to PCP in 2022.

Radioactive Waste Treatment System Changes There were no changes to the radioactive waste treatment system in 2022.

Other Supplemental Information

a. During 2022, Nine Mile Point Units 1 and 2 had two non-emergency notifications to the NRC:

1. Event 55821 was completed on April 5, 2022.

2. Event 56089 was completed on September 4, 2022.

b. At the time of this report development, an anomaly was identified with gaseous effluent results for isotopes Sr-89, Sr-90, and Fe-55 from ground and elevated releases and integration with dose calculation software. NMP acknowledges these results and conservatively reports these isotopes. Future amendments to the 2022 NMP Unit 2 ARERR may occur, if the results for these three isotopes were identified as errors in accordance with RG 1.21 rev 3, section 7.0.

Annual Radioactive Effluent Release Report

\ YEAR: 2022 I Page 19 of 34 Com an : Constellation Plant: Nine Mile Point Unit 2 5.10.1 Outside Tanks During 2022, there were no external water storage tanks containing radioactive material that leaked onto the ground or storm drain.

5.10_,2. Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program Information concerning the ISFSI monitoring program and 2022 annual dose can be found in the 2022 John A. FitzPafrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Environmental Operating Report published on the Nuclear Regulatory Commission website:

https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific-reports/nmp1-2.html.

5.10.3 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide with a 5730-year half-life.

Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.

In accordance with Regulatory Guide 1.21, "Measuririg, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRG recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using EPRI Report 1021106, "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents".

This calculation uses active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrati.ons to determine Carbon-14 generation based upon an effective full power year. The estimated generation for unit 2 during 2022 was 1.68E+01 curies.

Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. Carbon dioxide is assumed to make up 20-30% of the Carbon-14 gaseous emissions from the station based upon available references and on-site testing.

5.10.4 Errata/Corrections to Previous ARERRs There are no corrections to prior ARERRs.

Annual Radioactive Effluent Release Report YEAR: 2022 Page 20 of 34 Compan : Constellation Plant: Nine Mile Point Unit 2 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Nine Mile Point has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. During 2022, NMP Unit 1 and 2 collected and analyzed groundwater samples in accordance with the site requirements.

This section is included in this report to communicate results of NEI 07-07 Radiological Groundwater Monitoring Program. Monitoring wells installed as part of GPI program are sampled and analyzed annually and quarterly. In addition to reporting results from NEI 07-07 monitoring wells, new voluntary communications made for onsite leaks or spills per NEI 07-07 Objective 2.2, are also reported as part of this report. It is important to note, samples and results taken in support of NEI 07-07 groundwater monitoring program are not part of the Radiological Environmental Monitoring Program (REMP) but should be reported as part of AREOR or ARERR.

Number of positive detections for Tritium: 6 Number of analyses: 49 Number of samples below lower level of detection: 43 Maximum concentration identified: 381 pCi/L Table 4, Groundwater Protection Program Monitoring Well Results Number of Average Maximum Type of Number of Well Name Positive Concentration 2 Concentration Analysis Analyses Detections (pCi/L)

(pCi/L)

GMX-MW1 (control)

Tritium 0

1

<191

<191 MW-1 Tritium 0

1

<173

<173 MW-5 Tritum 0

4

<182

<194 MW-6 Tritium 0

1

<188

<188 MW-7 Tritium 0

1

<185

<185 MW-8 Tritium 0

4

<184

<184 MW-9 (sentinel well)

Tritium 0

4

<182

<182 MW-10 (sentinel well)

Tritium 1

1 227 227 MW-11 Tritium 0

1

<194

<194 MW-12 Tritium 0

1

<191

<191 MW-13 Tritium 0

1

<189

<189 MW-14 (control)

Tritium 0

1

<181

<181 MW-15 Tritium 1

4

<176 204 MW-16 Tritium 1

1 264 264 2 Results <MDA should not be included in the average concentration calculation.

Annual Radioactive Effluent Release Report YEAR: 2022 Page 21 of 34 Compan : Constellation Plant: Nine Mile Point Unit 2 Table 4, Groundwater Protection Program Monitoring Well Results Type of Number of Number of Average Maximum Well Name Analysis Positive Analyses Concentration 2 Concentration Detections (pCi/L)

(pCi/L)

MW-17 Tritium 0

4

<176

<194 MW-18 Tritium 0

4

<180

<197 MW-19 Tritium 0

1

<179

<179 MVV-20 Tritium 0

1

<194

<194 MW-21 Tritium 0

1

<189

<189 NMP2 MAT1 Tritium 3

4

<184 381 PZ-7 Tritium 0

4

<177

<203 PZ-8 Tritium 0

4

<180

<191 Note 1: NMP2 MAT is the groundwater depression cone. Samples collected from storm drain system, which includes precipitation; likely atmospheric recapture.

6.1 Voluntary Notification During 2022, Nine Mile Point Units 1 and 2 did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, and to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report YEAR: 2022 Page 22 of 34 7.0 BIBLIOGRAPHY

[1] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].

[2] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].

[3] "NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States","

National Council on Radiation Protection and Measurements, Bethesda, MD, 2009.

[4] [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020].

[5] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November 2020].

[6] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:

https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.

[7] "Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I;,"

Nuclear Regulatory Commission, Ocotober, 1977.

[8] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants,"

Nuclear Regulatory Commission, 1987.

[9] "NEI 07 Industry Ground Water Protection Initiative -

Final Guidance Document, Rev. 1,"

Nuclear Energy Institute, Washington, D.C., 2019.

[1 O] "Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019.

[11] "Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"

Nuclear Regulatory Commission, July, 2007.

[12] "10 CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.

[13] "NUREG-0324, "XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,"," Nuclear Regulatory Commission, September, 1977.

[14] "NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,".," Nuclear Regulatory Commission, April 1991.

[15] "NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors,"," Nuclear Regulatory Commission, April 1991.

[16] "40 CFR Part 141, "National Primary Drinking Water Regulations,"," US Environmental Protection Agency, Washington, DC..

[17] "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.

[18] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

[19] HPPOS-140 PDR-9111210378, NRC memorandum from D.R. Muller to T.M. Novak and G.C.

Lainas dated March 10, 1983.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 23 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 5, Gaseous Effluents Summation of All Releases NMP2 A.

Fission & Activation Gases Units Quarter Quarter Quarter Quarter Est. Total 1

2 3

4 Error%

1.

Total Release Ci 2.82E+00 5.00E+01

2.

Average release rate for the period

µCi/sec 3.55E-01 B.

Iodine

1.

Total Iodine -131 Ci 1.61 E-06 2.61E-06 3.00E+01 I

2.

Average release rate for the period

µCi/sec 2.07E-07 3.32E-07 C.

Particulates

1.

Particulates with half-lives > 8 days Ci 2.00E-04 2.59E-04 6.44E-02 5.87E-02 3.00E+01 I

2.

Average release rate for the period

~tCi/sec 2.57E-05 3.29E-05 8.11 E-03 7.39E-03 D.

Tritium

1.

Total Release Ci 1.80E+01 2.08E+01 1.93E+01 1.93E+01 5.00E+01 I

2.

Average release rate for the period

~tCi/sec 2.32E+00 2.64E+00 2.42E+00 2.43E+00 E.

Gross Alpha

1.

Total Release Ci 2.50E+01 I

2.

Average release rate for the period

µCi/sec F.

Carbon-14

1.

Total Release Ci 3.34E+00 4.52E+O0 4,15E+00 4.82E+00 5.00E+01 I

2.

Average release rate for the period

~tCi/sec 3.18E-03 4.30E-03 3.95E-03 4.59E-03

% of limit is on Table 1, Nine Mile Point Unit 2 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2022 I

Page 24 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fissiori Gases: *

\

Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for Period Ci Iodines,

'*e' 1-131 Ci 1-133 Ci 1-135 Ci Total for Period Ci Partic;~lates C'

Co-58 Ci Co-60 Ci Sr-89 Ci Sr-90 Ci Cs-134 Ci Total for Period Ci Tritium H-3 Ci 7.62E-02 II 7.62E-02

!~Alpha,*

I" Alpha Ci Carbon-14

,, ~.

"ii C-14 Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 l Page 25 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2

-Table 7, Gaseous Effluents - Ground Level Release Continuous Mode NMP2 Quarter 1 Quarter 2 Quarter 3 Quarter4 Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for Period Ci 1-131 Ci 1-133 Ci 1-135 Ci Total for Period Ci Co-58 Ci 4.24E-06 9.79E-06 1.40E-05 Co-60 Ci 1.21E-04 1.75E-04 2.90E-04 3.12E.:04 8.98E-04 Sr-89 Ci 6.37E-06 s:37E-06 Sr-90 Ci 6.37E-06 6.37E-06 Cs-137 Ci 6.27E-06 6.27E-06 Fe-55 Ci 6.37E-06 6.37E-06 Mri-54 Ci 7.01E-06 7.01E-06 Total for Period Ci 1.47E-04 1.88E-04 3.00E-04 3.12E-04 9.47E-04

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 26 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases

"\'

Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for Period Ci

i1

~"

Iodines.

J,,

'c 1-131 Ci 1-133 Ci 1-135 Ci Total for Period Ci Particulates Co-58 Ci Co-60 Ci 2.72E-12 2.72E-12 Sr-89 Ci Sr-90 Ci Cs-137 Ci 1.20E-11 1.20E-11 Total for Period Ci 1.47E-11 Tritium H-3 Ci 7.62E-02 3.00E-02 1.06E-01 Gross Alpha Alpha Ci Carbon-14

~

I C-14 Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 27 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP2 Rionuclide eleased Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission Gases Ar-41 Ci 2.40E+00 2.40E+00 Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci 4.20E-01 4.20E-01 Total for Period Ci 2.82E+00 2.82E+00 1-131 Ci 1.61E-06 2.61E-06 4.22E-06 1-133 Ci 8.70E-05 1.41E-04 2.28E-04 1-135 Ci Total for Period Ci 8.86E-05 1.44E-04 2.32E-04 tes Co-58 Ci Co-60 Ci 3.38E-05 5.93E-05 6.41E-02 5.84E-02 1.23E-01 Sr-89 Ci 7.34E-06 2.73E-06 1.01E-05 Sr-90 Ci 7.34E-06 2.73E-06 1.01 E-05 Cs-134 Ci Mn-54 Ci 1.93E-06 2.35E-06 4.28E-06 Fe-55 Ci 7.34E-06 4.03E-06 4.24E-05 5.38E-05 Zn-65 Ci Cs-137 Ci 1.84E-09 Ni-63 Ci Ag-110m Ci Total for Period Ci 5.58E-05 7.07E-05 6.41E-02 5.84E-02 =

1.23E-01 Triti(i'm H-3 1.19E+01 1.61E+01 Alpha Alpha Ci Carbon-1*f

.I:

1..,-14 3.34E+O0 4.52E+00 4.15E+0O 4.82E+00 1.68E+01

Annual Radioactive Effluent Release Report YEAR: 2022 Page 28 of 34 2.0 LIQUID EFFLUENTS Table 10, Liquid Effluents - Summation of All Releases NMP2 Quarter Quarter Quarter Quarter Est.

A.

Fission & Activation Products Units Total 1

2 3

4 Error%

1.

Total Release Ci 5.00E+01

2.

Average diluted concentration

µCi/ml B.

Tritium

1.

Total Release Ci 5.00E+01

2.

Average diluted concentration

µCi/ml C.

Dissolved & Entrained Gases

1.

Total Release Ci 5.00E+01

2.

Average diluted concentration

µCi/ml D.

Gross Alpha Activity

1.

Total Release Ci 5.00E+01 E.

Volume of Waste Released (prior Liters to dilution)

F.

Volume of Dilution Water Used During Liters 1.08E+10 1.16E+10 1.27E+10 1.00E+10 Period

% of limit is on the Table 1, Nine Mile Point Unit 2 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 29 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 11, Batch Mode Liquid Effluents NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Activati~n-~toij_ucts.

*.f

.. \ -~

Cr-51 Ci Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-6O Ci Sr-89 Ci Sr-9O Ci Nb-95 Ci Zn-65 Ci Ag-11Om Ci 1-131 Ci 1-133 Ci Cs-134 Ci Cs-137 Ci Total for Period Ci

tritiuin

.,h'*

. *l" '~

H-3 Ci t

".. :,\

0rossAlpha Alpha Ci

~ined ~ases.

Xe-133 Ci Xe-135 Ci Total for Period Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 30 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 12, Continuous Mode Liquid Effluents NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released "Fi&sion:and Actiyation ProdUGtS.

/

,*'4" '", *:,

Cr-51 Ci Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-60 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zn-65 Ci Ag-110m Ci 1-131 Ci 1-133 Ci Cs-134 Ci Cs-137 Ci Total for Period Ci "FrifiurQ;s

";)

':s t

H-3 Ci

.t rpss ~lpha

. **,,>-,.::, y /

"t,j

,~

Alpha Ci

,/

. \:.,'

, ?,../*.,. **:**

!;ntra.irifip:Gases*.,:

..,).

'°'

Xe-133 Ci Xe-135 Ci (List Others)

Ci Total for Period Ci

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 31 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2, Solid Waste Information 1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Table 13, Types of Solid Waste Summary NMP2 Total Volume Total Activity Types of Waste (m3)

(Ci)

a. Spent resins, filter sludges, evaporator bottoms, etc.

3.03E+01 1.45E+01

b. Dry compressible waste, contaminated equip, etc.

4.91E+02 1.95E-01

c. Irradiated components, control rods, etc.

0.00E+00 0.00E+00

d. Other 5.17E+01 4.17E+00 Total 5.73E+02 1.89E+01 Est. Total Error

(%)

25 25 25 25 25 2.0 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY WASTE TYPE) ONLY >1%

ARE REPORTED. [NOTE 1]

Table 14, Major Nuclides NMP2 Major Nuclide Composition Isotope Curies

a. Spent resins, filter sludges, evaporator bottoms, etc.

Co-60 78.1 1.13E+01 Fe-55 18.0 2.61E+00 Mn-54 2.25 3.26E-01

b. Dry compressible waste, contaminated equip, etc.

Co-60 86.48 1.68E-01 Fe-55 8.96 1.75E-02 Mn-54 2.66 5.17E-03 Zn-65 1.17 2.28E-03

c. Other waste Co-60 89.51 3.73E+00 Fe-55 6.22 2.59E-01 Mn-54 2.87 1.20E-01

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 32 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 14, Major Nuclides NMP2 Zn-65 1.02 4.23E-02

d. Irradiated components, control rods, etc.

0 00E+00 3.0 SOLID WASTE DISPOSITION Table 15, Solid Waste Disposition NMP2 Number of Mode of Transportation Di:stination Shipments 7

NRC Class: A; DOT Type: A LSA-II Energy Solutions Clive (CWF Containerized Waste Facility) 14 NRC Class: A; DOT Type: A LSA-II Energy Solutions Bear Cr~ek (CVRF) 4.0 IRRADIATED FUEL DISPOSITION Table 16, Irradiated Fuel Shipments Disposition NMP2 Number of Mode of Transportation Destination Shipments 0

I Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 33 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 1.0 1.1 Wind Direction N

NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

WNW NW NNW Total, Meteorological Data METEOROLOGICAL DATA

SUMMARY

Joint Frequency Distributions

1.

Period of Record: 2022

2.

Stability Class: All

a.

Periods of calm (hours): 12

b.

Hours of missing data: 155 hours0.00179 days 0.0431 hours 2.562831e-4 weeks 5.89775e-5 months

c.

Meteorological data quality 98.2% for all stability classes and parameters.

d.

Total annual precipitation: 27.32 inches

3.

Elevation: 200 ft.

Wind Speed Range (m/s)

<0.5 0.5 1.1 1.6 2.1 3.1 4.1 5.1 6.1 8.1

>10.0 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 0

4 12 17 40 58 43 27 54 19 44 1

2 8

9 38 67 34 47 99 50 116 0

4 12 20 50 51 46 44 40 25 12 0

3 10 21 39 47 10 4

6 0

0 0

2 10 11 58 65 22 12 17 0

0 1

4 3

13 37 65 55 42 48 17 7

0 3

9 10 35 96 103 113 303 116 38 0

1 6

10 27 114 80 132 355 125 44 0

5 3

11 25 95 109 132 344 108 45 1

3 6

6 31 76 109 133 210 21 1

1 4

6 15 26 74 68 86 163 48 20 0

4 9

11 38 104 82 106 206 110 150 0

4 7

18 37 103 63 70 143 123 288 1

3 9

12 34 67 34 23 101 82 221 1

5 4

9 38 42 40 41 116 84 141 1

3 12 13 43 44 34 26 82 45 46 I

7 I 54 I 126 I 206 I 595 I 1168 I 932 I 1038 I 2287 I 973 I 1173 I Total 318 471 304 140 197 292 826 894 877 597 510 820 856 587 521 349 8559 I

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 34 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 1.2 Stability class Table 17, Classification of Atmospheric Stability Stability Condition Pasquill Categories Hours Percentage Extremely Unstable A

969 11.3%

Moderately Stable B

568 6.6%

Slightly Unstable C

722 8.4%

Neutral D

3306 38.6%

Slightly Stable E

1865 21.8%

Moderately Stable F

610 7.1%

Extremely Stable G

519 6.1%

Note: Percentage is calculated based on the 200ft winds and 200ft-30ft stability hourly data for the year (8559 hours0.0991 days 2.378 hours 0.0142 weeks 0.00326 months of valid data).

NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report: Difference between revisions

Latest revision as of 06:33, 21 February 2026

Contents

Text

Subject:

Enclosures:

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

Navigation menu

@@ Line 47: / Line 47: @@
 ==3.0 INTRODUCTION==
 ........................................................................................................................... 8 3.1
-_ About Nuclear Power........................................................................................................ 8 3.2 About Radiation Dose..................................................................................................... 10 3.3 About Dose Calculation..................................................................................... \\............. 12 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................... 14 4.1 Regulatory Limits................................................................................................. *............ 14 4.2 Regulatory Limits for Gaseous Effluent Doses:................................................................ 14 4.3 Regulatory Limits for Liquid Effluent Doses.................................................................... 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. *.. 16 4.5 Onsite Doses (Within Site Boundary).............................................................................. 16 5.0 SUPPLEMENTAL INFORMATION.........................,................................................................... 17 5.1 Gaseous Batch Releases.............................................. :................................................. 17 5.2 Liquid Batch Releases.................................................-.................................................... 17 5.3 Abnormal Releases..........-................................................................................................ 17 5.4 Land Use Census Changes*******************************************************************************:************ 18 5.5 Meteorological Data**********************************************************************.********************************** 18 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days-................................. 18 5.7 Offsite Dose Calculation Manual (ODCM) Changes....................................................... 18 5.8 Process Control Program (PCP) Changes...,.................................................................. 18 5.9 Radioactive Waste Treatment System Changes..................................,........................ :.18 5.1 O Other Supplemental Information ********************:**************************************************************** 18 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM................ 20 6.1 Voluntary Notification *******************************:*******************************;********:............................. 21 7.0 BIBLIOGRAPHY......................................................................................................................... 22 TABLES Table 1, Nine Mile Point Units 1 Dose Summary..................................................................................... 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for NMP..................................... 7 Table 3, Onsite Doses (Within Site Boundary)....................................................................................... 16 Table 4, Groundwater Protection Program Monitoring Well Results...................................................... 20 Table 5, Gaseous Effluents Summation of All Releases NMP 1........,.................................................. 23 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP 1........................................... 24 Table 7, Gaseous Effluents - Ground Level Release Continuous Mod.e NMP 1.................................. 25 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP 1......................................... 26 Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP 1.................................. 27 Table 10, Liquid Effluents - Summation of All Releases NMP 1............................................................ 28 Table 11, Batch Mode Liquid Effluents NMP 1....................................................................................... 29
+_ About Nuclear Power........................................................................................................ 8 3.2 About Radiation Dose..................................................................................................... 10 3.3 About Dose Calculation..................................................................................... \............. 12 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................... 14 4.1 Regulatory Limits................................................................................................. *............ 14 4.2 Regulatory Limits for Gaseous Effluent Doses:................................................................ 14 4.3 Regulatory Limits for Liquid Effluent Doses.................................................................... 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. *.. 16 4.5 Onsite Doses (Within Site Boundary).............................................................................. 16 5.0 SUPPLEMENTAL INFORMATION.........................,................................................................... 17 5.1 Gaseous Batch Releases.............................................. :................................................. 17 5.2 Liquid Batch Releases.................................................-.................................................... 17 5.3 Abnormal Releases..........-................................................................................................ 17 5.4 Land Use Census Changes*******************************************************************************:************ 18 5.5 Meteorological Data**********************************************************************.********************************** 18 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days-................................. 18 5.7 Offsite Dose Calculation Manual (ODCM) Changes....................................................... 18 5.8 Process Control Program (PCP) Changes...,.................................................................. 18 5.9 Radioactive Waste Treatment System Changes..................................,........................ :.18 5.1 O Other Supplemental Information ********************:**************************************************************** 18 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM................ 20 6.1 Voluntary Notification *******************************:*******************************;********:............................. 21 7.0 BIBLIOGRAPHY......................................................................................................................... 22 TABLES Table 1, Nine Mile Point Units 1 Dose Summary..................................................................................... 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for NMP..................................... 7 Table 3, Onsite Doses (Within Site Boundary)....................................................................................... 16 Table 4, Groundwater Protection Program Monitoring Well Results...................................................... 20 Table 5, Gaseous Effluents Summation of All Releases NMP 1........,.................................................. 23 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP 1........................................... 24 Table 7, Gaseous Effluents - Ground Level Release Continuous Mod.e NMP 1.................................. 25 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP 1......................................... 26 Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP 1.................................. 27 Table 10, Liquid Effluents - Summation of All Releases NMP 1............................................................ 28 Table 11, Batch Mode Liquid Effluents NMP 1....................................................................................... 29
 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 2 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1 Table 12, Continuous Mode Liquid Effluents NMP 1.............................................................................. 30 Table 13, Types of Solid Waste Summary NMP 1.................................................................................. 31 Table 14, Major Nuclides NMP 1............................................................................................................ 31 Table 15, Solid Waste Disposition NMP 1.............................................................................................. 32 Table 16, Irradiated Fuel Shipments Disposition NMP 1........................................................................ 32 Table 17, Classification of Atmospheric Stability.................................................................................... 34 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]....................................................................................... 8 Figure 2, Boiling Water Reactor (BWR) [2]............................................................................................... 9 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]................................................... 10 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6].............. 12 ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)..................................................... 23, Solid Waste lnformation................................................................................................... 31, Meteorological Data......................................................................................................... 33
@@ Line 497: / Line 497: @@
 I
 ~4
-.:-\\
+.:-\
 ,~<' '> 1 >
 ,
-\\ ~,, "*,
+\ ~,, "*,
 Ci I 2.18E+OO I 2.20E+OO I 2.23E+OO I
 .23E+OO II 8.84E+00 I
@@ Line 816: / Line 816: @@
 ~
 ~
-\\ DeJ)Ollition t **:**..
+\ DeJ)Ollition t **:**..
 .:~~~.
@@ Line 824: / Line 824: @@
 + ******
 Public 11
-** I ngeatton \\
+** I ngeatton \
 ... : Radiation o
 :Radionuclides
@@ Line 892: / Line 892: @@
 Annual Radioactive Effluent Release Report
-\\ YEAR: 2022
+\ YEAR: 2022
-\\
+\
 Page 16 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public 4.5
 : 1.
@@ Line 941: / Line 941: @@
 Annual Radioactive Effluent Release Report
-\\ YEAR: 2022 I Page 19 of 34 Com an : Constellation Plant: Nine Mile Point Unit 2 5.10.1 Outside Tanks During 2022, there were no external water storage tanks containing radioactive material that leaked onto the ground or storm drain.
+\ YEAR: 2022 I Page 19 of 34 Com an : Constellation Plant: Nine Mile Point Unit 2 5.10.1 Outside Tanks During 2022, there were no external water storage tanks containing radioactive material that leaked onto the ground or storm drain.
 .10_,2. Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program Information concerning the ISFSI monitoring program and 2022 annual dose can be found in the 2022 John A. FitzPafrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Environmental Operating Report published on the Nuclear Regulatory Commission website:
 https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific-reports/nmp1-2.html.
@@ Line 1,098: / Line 1,098: @@
 Annual Radioactive Effluent Release Report I YEAR: 2022 I
 Page 24 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 6, Gaseous Effluents - Ground Level Release Batch Mode NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fissiori Gases: *
-\\''
+\''
 Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for Period Ci Iodines,
 '*e' 1-131 Ci 1-133 Ci 1-135 Ci Total for Period Ci Partic;~lates C'
@@ Line 1,111: / Line 1,111: @@
 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 26 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases
-"\\'
+"\'
 Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for Period Ci
 *i1
@@ Line 1,158: / Line 1,158: @@
 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 29 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2 Table 11, Batch Mode Liquid Effluents NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Activati~n-~toij_ucts.
 ; *.f
-*.. \\ -~
+*.. \ -~
 Cr-51 Ci Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-6O Ci Sr-89 Ci Sr-9O Ci Nb-95 Ci Zn-65 Ci Ag-11Om Ci 1-131 Ci 1-133 Ci Cs-134 Ci Cs-137 Ci Total for Period Ci
 :tritiuin
@@ Line 1,164: / Line 1,164: @@
 . *l" '~
 H-3 Ci t
-".. :,\\
+".. :,\
 rossAlpha Alpha Ci
 ~ined ~ases.
@@ Line 1,182: / Line 1,182: @@
 Alpha Ci
 ,/
-. \\:.,'
+. \:.,'
 , ?,../''*.,. **:**
 !;ntra.irifip:Gases*.,:

NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report: Difference between revisions

Latest revision as of 06:33, 21 February 2026

Text

Subject:

Enclosures:

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

Navigation menu

Search