Text

Unit 1 - 2024 Annual Radioactive Effluent Release Report
	ML25106A287
Person / Time
Site:	River Bend
Issue date:	04/16/2025
From:	Giddens J; Entergy Operations
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	RBG-48333
	Download: ML25106A287 (1)
	v • d • e

) entergy RBG-48333 April 16, 2025 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

2024 Annual Radioactive Effluent Release Report River Bend Station - Unit 1 NRC Docket Nos. 50-458 Renewed Facility Operating License No. NPF-47 John Giddens Senior Manager - Regulatory Compliance (Acting Regulatory Assurance Manager)

River Bend Station 601-368-5756 10 CFR 50.36a Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for the period of January 1, 2024, through December 31, 2024. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.3.

This letter contains no new regulatory commitments.

Should you have any questions, please contact Mr. Titus Folds, Sr. Specialist, Regulatory Assurance, at 225-381-5602.

Respectfully, JMG/twf

Enclosure:

cc:

Digitally signed by John Giddens DN: cn=John Giddens, o=Entergy, ou=Regulatory Compliance, email=jgidden@entergy.com Date: 2025.04.16 11 :29:14 -05'00' 2024 Annual Radioactive Effluent Release Report NRC Region IV Regional Administrator - Region IV NRC Senior Resident Inspector - River Bend Station Entergy Nuclear Operations, Inc., River Bend Station, 5485 U.S. Highway 61, St. Francisville, LA 70775

Enclosure 2024 Annual Radioactive Effluent Release Report

) entergy River Bend Nuclear Station 2024 Annual Radioactive Effluent Release Report Document Number: RBG-48333

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 1 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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 Miscellaneous Limits..................................................................................................... 16 4.6 Effluent Concentration Limits........................................................................................ 17 4.7 Measurements & Approximations of Total Radioactivity............................................... 17 4.8 Onsite Doses (Within Site Boundary)............................................................................ 19 5.0 SUPPLEMENTAL INFORMATION........................................................................................... 20 5.1 Gaseous Batch Releases............................................................................................. 20 5.2 Liquid Batch Releases.................................................................................................. 20 5.3 Abnormal Releases...................................................................................................... 20 5.4 Land Use Census Changes.......................................................................................... 21 5.5 Meteorological Data...................................................................................................... 21 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days................................ 21 5.7 Offsite Dose Calculation Manual (ODCM) Changes...................................................... 22 5.8 Process Control Program (PCP) Changes.................................................................... 22 5.9 Radioactive Waste Treatment System Changes........................................................... 22 5.10 Other Supplemental Information................................................................................... 22 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM............... 24 6.1 Voluntary Notification.................................................................................................... 27 7.0 BIBLIOGRAPHY...................................................................................................................... 28 TABLES Table 1, River Bend Nuclear Station Dose Summary............................................................................. 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for RBS..................................... 7 Table 3, Onsite Doses (Within Site Boundary)..................................................................................... 19 Table 4, Groundwater Protection Program Monitoring Well Sample Schedule..................................... 24 Table 5, Gaseous Effluents Summation of All Releases..................................................................... 29 Table 6, Gaseous Effluents - Ground Level Release Continuous Mode............................................ 30 Table 7, Gaseous Effluents - Mixed Level Release Continuous Mode.............................................. 31 Table 8, Radioactive Gaseous Waste Sampling and Analysis Program............................................... 32

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 2 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 9, Liquid Effluents - Summation of All Releases...................................................................... 33 Table 10, Batch Mode Liquid Effluents................................................................................................. 34 Table 11, Radioactive Liquid Waste Sampling and Analysis Program.................................................. 35 Table 12, Types of Solid Waste Summary........................................................................................... 36 Table 13, Major Nuclides..................................................................................................................... 36 Table 14, Solid Waste Disposition....................................................................................................... 37 Table 15, Irradiated Fuel Shipments Disposition.................................................................................. 38 Table 16, 30 Ft Elevation: All Stability Classes.................................................................................... 39 Table 17, 30 Ft Elevation: Stability Class A.......................................................................................... 40 Table 18, 30 Ft Elevation: Stability Class B.......................................................................................... 41 Table 19, 30 Ft Elevation: Stability Class C......................................................................................... 42 Table 20, 30 Ft Elevation: Stability Class D......................................................................................... 43 Table 21, 30 Ft Elevation: Stability Class E.......................................................................................... 44 Table 22, 30 Ft Elevation: Stability Class F.......................................................................................... 45 Table 23, 30 Ft Elevation: Stability Class G......................................................................................... 46 Table 24, 150 Ft Elevation: All Stability Classes.................................................................................. 47 Table 25, 150 Ft Elevation: Stability Class A........................................................................................ 48 Table 26, 150 Ft Elevation: Stability Class 8........................................................................................ 49 Table 27, 150 Ft Elevation: Stability Class C....................................................................................... 50 Table 28, 150 Ft Elevation: Stability Class D....................................................................................... 51 Table 29, 150 Ft Elevation: Stability Class E........................................................................................ 52 Table 30, 150 Ft Elevation: Stability Class F........................................................................................ 53 Table 31, 150 Ft Elevation: Stability Class G....................................................................................... 54 Table 32, Classification of Atmospheric Stability.................................................................................. 55 Table 33, Gamma Isotopic Results...................................................................................................... 56 Table 34, Hard to Detect Nuclides....................................................................................................... 70 Table 35, Tritium Analysis Results....................................................................................................... 71 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)................................................... 29, Solid Waste Information................................................................................................ 36, Meteorological Data...................................................................................................... 39, Groundwater Monitoring Well Sampling Results........................................................... 56

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 3 of 78 Company: Enterav I Plant: River Bend Nuclear Station 1.0 LIST OF ACRONYMS AND DEFINITIONS

1.

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.

2.

BWR: Boiling Water Reactor

3.

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.

4.

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.

5.

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

6.

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

7.

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.

8.

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

9.

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

10.

Ingestion Pathway: The ingestion pathway includes milk, fish, drinking water and garden produce. Also sampled (under special circumstances) are other media such as vegetation or animal products when additional information about particular radionuclides is needed.

11.

ISFSI: Independent Spent Fuel Storage Installation

12.

LLD: Lower Limit of Detection. An a priori measure of the detection capability of a radiochemistry measurement based on instrument setup, calibration, background, decay time, and sample volume. An LLD is expressed as an activity concentration. The MDA is used for reporting results. LLD are specified by a regulator, such as the NRC and are typically listed in the ODCM.

13.

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 5% probability of falsely concluding that a blank observation represents a true signal.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 4 of 78 Company: Enterav I Plant: River Bend Nuclear Station

14.

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

15.

Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.

16.

Microcurie (µCi): 3. 7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.

17.

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

18.

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

19.

N/A: Not Applicable

20.

NEI: Nuclear Energy Institute

21.

NRC: Nuclear Regulatory Commission

22.

ODCM: Offsite Dose Calculation Manual

23.

OSLO: Optically Stimulated Luminescence Dosimeter

24.

Protected Area: A 10 CFR 73 security term is an area encompassed by physical barriers and to which access is controlled for security purposes. The fenced area immediately surrounding the plant and around ISFSI are commonly classified by the licensee as "Protected areas." Access to the protected area requires a security badge or escort.

25.

PWR: Pressurized Water Reactor

26.

REC: Radiological Effluent Control

27.

REMP: Radiological Environmental Monitoring Program

28.

Restricted Area: A 10 CFRR 20 defined term where access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.

29.

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).

30.

TLD: Thermoluminescent Dosimeter

31.

TRM: Technical Requirements Manual

32.

TS: Technical Specification

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 5 of 78 Company: Enterav I Plant: River Bend Nuclear Station

33.

Unrestricted Area: An area, access to which is neither limited nor controlled by the licensee.

2.0 EXECUTIVE

SUMMARY

River Bend Nuclear Station (RBS) 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 Technical Specifications, 10 CFR 20, and by 40 CFR 190. Operational doses to the public during 2024 were calculated to be within 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 processing or direct disposal; and other information as required by site licensing documents.

In 2024, the gaseous effluent dose assessments for locations from the Land Use Census showed that the critical receptor for River Bend Nuclear Station is Child, due to Fresh Leafy Vegetation, at 994m WNW. The maximum Annual Organ Dose calculated for this receptor was 1.23e+00 mrem, to the Thyroid.

The maximum dose calculated to any organ due to radioactive liquid effluents was 8.43E-04 mrem, for Adult GI Tract due to ingestion.

Solid radioactive waste shipped offsite for processing or direct disposal included 6.17E+01 Curies and 4.20E+02 m3, shipped in 27 shipments.

In addition to monitoring radioactive effluents, RBS has a Radiological Environmental Monitoring Program (REMP) that monitors for levels of radiation and radioactive materials in the local environment. Data from the REMP is published in the Annual Radiological Environmental Operating Report (AREOR).

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 6 of 78 Company: Enterav I Plant: River Bend Nuclear Station 2.1 Comparison to Regulatory Limits During 2024 all solid, liquid, and gaseous radioactive effluents from River Bend Nuclear Station were well below regulatory limits, as summarized in Table 1 and Table 2.

Table 1, River Bend Nuclear Station 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 5.42E-07 3.81 E-06 8.26E-05 3.91 E-05 Total Body

% of Limit 3.61 E-05 2.54E-04 5.51 E-03 2.60E-03 Liquid Effluent Limit 5 mrem 5 mrem 5 mrem 5 mrem Dose Limit, Max Organ Dose 4.64E-06 2.15E-05 5.36E-04 2.80E-04 Any Organ

% of Limit 9.27E-05 4.30E-04 1.07E-02 5.61 E-03 Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad Dose Limit, Gamma Air Dose 3.40E-02 1.14E-02 4.06E-03 2.94E-03 Gamma Air (Noble Gas)

% of Limit 6.80E-01 2.29E-01 8.11 E-02 5.88E-02 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad Dose Limit, Beta Air Dose 2.55E-02 5.43E-03 2.08E-03 1.84E-03 Beta Air (Noble Gas)

% of Limit 2.55E-01 5.43E-02 2.08E-02 1.84E-02 Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem Organ Dose Limit Max Organ Dose 1.67E-01 1.60E-01 7.92E-01 1.10E-01 (Iodine, Tritium, Particulates with

% of Limit 2.23E+00 2.13E+00 1.06E+01 1.46E+00

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

Annual 3 mrem 1.26E-04 4.20E-03 10 mrem 8.43E-04 8.43E-03 10 mrad 5.24E-02 5.24E-01 20 mrad 3.49E-02 1.74E-01 15 mrem 1.23E+00 8.19E+00

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 7 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for RBS2 Whole Body Thyroid Max Other Organ Gaseous3 6.60E-02 1.28E+00 7.01E-02 Carbon-14 9.37E-01 9.37E-01 4.69E+00 Liquid 1.26E-04 2.65E-05 8.43E-04 Direct Shine 0.00E+00 0.00E+00 0.00E+00 Total Site Dose 1.00E+00 2.22E+00 4.76E+00 Total w/Other Nearby Facility4 N/A N/A N/A Limit 25 mrem 75 mrem 25 mrem

% of Limit 4.01%

2.96%

19.04%

2 Table 2 is a summation of Units to show compliance with 40 CFR Part 190 Limits.

3 Gaseous dose values in Table 2 include organ dose from Noble Gas, Iodine, Tritium, and particulates.

4 Other fuel cycle sources within 5 miles of the site are considered in this analysis.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 8 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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. 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: 2024 I Page 9 of 78 Company: Enterav I Plant: River Bend Nuclear Station 3.1 (Continued)

Containment Structure Control Rods 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 powered 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 producing 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: 2024 I Page 10 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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 fluoroscopy (medical)

(7%)

Radon & thoron (background)

(37%)

Industrial

(<0.1%)

Occupational

(<0.1%)

Consumer Conventional radiography/fluoroscopy (medical)

(5%)

(2%)

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

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 11 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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% of total mrem per year) 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: 2024 I

Page 12 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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 products Gaseous cffiucnts

- - - - Inge t' 0

~

I

\ Inhalation

\ ~cpo ition I **::... ':::~.. t:~~-*********

1[

~ /

Public 11

- ** lngcsuon \

0

Radionuclides

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

Each plant has an Offsite Dose Calculation Manual (ODCM) that specifies the methodology used to obtain the doses in the Dose Assessment section of this report.

The dose assessment 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: 2024 I Page 13 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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 (e.g., taken from wells, rivers, or lakes). 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.

Every two years 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 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 maximum exposed individual due to plant operation are a very small fraction of the annual dose that is received due to other sources. The calculated doses due to plant effluents, along with REMP results, serve to provide assurance that radioactive effluents releases are not exceeding safety standards for the environment or people living near the plant.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 14 of 78 Company: Enterav I Plant: River Bend Nuclear Station 4.0 4.1 4.2 DOSE ASSESSMENT FOR PLANT OPERATIONS Regulatory Limits Regulatory limits are detailed in station licensing documents such as the plant Technical Specifications and the Offsite Dose Calculation Manual (ODCM). These documents contain the limits to which RBS must adhere. RBS drives to maintain the philosophy to keep dose "as low as is 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 RBS is well below the ODCM limits.

The instantaneous 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 microcuries/ml.

The annual whole body, skin and organ dose was computed using the 2024 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents are used to demonstrate compliance with offsite dose limits are presented in Table 1, River Bend Nuclear Station Dose Summary and Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for RBS.

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 10 mrads gamma b)

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

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 15 of 78 Company: Enterav I Plant: River Bend Nuclear Station 4.3

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 10 mrem critical organ

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 16 of 78 Company: Enterav I Plant: River Bend Nuclear Station 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public

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.

4.5 Miscellaneous Limits

1.

Technical Requirement 3.11.2.1 - Fission and Activation Gases

a.

In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be:

Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin

2.

Technical Requirement 3.11.2.1 - Radioiodine (1-131 & 1-133) and Particulate

a.

In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioiodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to:

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

3.

Technical Requirement 3.11.1.1 - Liquid Effluent

a.

In accordance with Technical Requirement 3.11.1.1, the concentration of radioactive material released in liquid effluent to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 1 0CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/milliliter total concentration.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 17 of 78 Company: Enterav I Plant: River Bend Nuclear Station

4.

Technical Requirement 3.11.2.5 - Ventilation Exhaust Treatment

a.

In accordance with Technical Requirement 3.11.2.5, the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31-day period.

5.

Technical Requirement 3.11.1.3 - Liquid Radwaste Treatment System

a.

In accordance with Technical Requirement 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.

4.6 Effluent Concentration Limits 4.7 1.

Gaseous Releases

a.

The concentrations of radioactive gaseous releases are based on the dose rate restrictions in RBS Technical Requirements, rather than the Effluent Concentration Limits (ECL) listed in 1 0CFR20 Appendix B, Table 2, Column 1.

2.

Liquid Releases

a.

The Effluent Concentration Limits of radioactive materials in liquid effluents are limited to ten times 1 0CFR20, Appendix B, Table 2, Column

2.

Measurements & Approximations of Total Radioactivity

1.

Gaseous Effluent

a.

Fission & activation gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent. These samples are analyzed using high purity germanium detectors coupled to computerized pulse height analyzers. The sampling and analysis frequencies are described in Table 8.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 18 of 78 Company: Enterav I Plant: River Bend Nuclear Station Sampling and analysis of these effluent streams provide noble gas radionuclide relative abundance that can then be applied to the noble gas gross activity and gross activity release rate to obtain nuclide specific activities and release rates. The noble gas gross activity released within a specific time period is determined by integrating the stack monitor release rate over the considered time period. If no activity was detected between the stack grab sample and a significant increase in hourly averages was recorded, the nuclide relative abundance of the last sample (or the last similar event), which indicated the presence of activity, was used to obtain nuclide specific activities. Correction factors for the monitors are derived and applied for each sampling period whenever noble gas radionuclides are detected in the effluent stream.

b.

Particulate and Radioiodine (I 131 & I 133)

Particulates, lodine-131 and lodine-133 are continuously sampled from the three release points using a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 8. Analysis is performed to identify and quantify radionuclides using high purity germanium detectors coupled to computerized pulse height analyzers. Given the nuclide specific activity concentrations, process flow rate, and duration of the sample, the nuclide specific activity released to the environment can be obtained. Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Strontium-89, Strontium-90, and Gross alpha are quantitatively analyzed by counting by gas flow proportional counting.

c.

Tritium Tritium grab samples are obtained from the three gaseous release points at the specified frequencies listed in Table 8 using an ice bath condensation collection method. The collected sample is then analyzed using a liquid scintillation counter. Given the tritium concentration, process flow rate, and time period for which the sample is obtained, the tritium activity released to the environment can be determined. Due to the frequency of sampling, it is assumed that the tritium is released to the environment at a constant rate within the time period for which the sample is obtained.

d.

Nickel-63 No Nickel 63 was quantified in 2024

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 19 of 78 Company: Enterav I Plant: River Bend Nuclear Station 4.8 Location Bow Hunting Club RV Park WFPS0

2.

Liquid Effluents

a.

a. Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 11. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high purity germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined using a liquid scintillation counter. Strontium-89, Strontium-90, and Gross alpha analysis are performed using a gas flow proportional counter. lron-55 is counted with a liquid scintillation counter after digestion of the iron. The activity of each nuclide released to the environment is determined from the nuclide specific concentration and total tank volume released.

Onsite Doses {Within Site Boundary)

RBS classifies individuals within the site boundary as either occupationally exposed individuals or members of the public. 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 10 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 occupants of the West Feliciana Sherif's Office building (WFPSO), temporary occupants of the on-site RV park, and RBS Bow Hunting Club members. While occupancy times vary greatly between these groups, using of a conservative assumption of 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />s/year spent inside the site boundary by the WFPSO represents the most-exposed individual.

Table 3, Onsite Doses (Within Site Boundary)

Total Body Dose External Approx.

(mrem)

Dose Sector Distance X/Q D/Q Occupancy (Meters) s/m/\3 1/m/\2 (Hours/Year)

Noble

Iodine, TLD or Gas Particulate, OSLO C-14 & H-3 WNW 2500 4.21 E-05 5.03E-08 2.56E+02 7.26E-04 2.13E-03 O.OOE+OO WNW 994 4.21 E-05 5.03E-08 5.97E+02 1.69E-03 4.96E-03 O.OOE+OO NNE 1630 4.21 E-05 5.03E-08 2.00E+03 5.67E-03 1.66E-02 O.OOE+OO Total 2.85E-03 6.66E-03 2.23E-02

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 20 of 78 Company: Enterav I Plant: River Bend Nuclear Station 5.0 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 RBS There were no routine batch releases of gaseous effluents from River Bend Nuclear Station during the reporting period of January 1, 2024, through December 31, 2024.

5.2 Liquid Batch Releases 5.2.1 RBS Number of batch releases 115 Total time period for a batch release 3.92E+04 minutes Maximum time period for a batch release 1.45E+03 minutes Average time period for a batch release 3.41 E+02 minutes Minimum time period for a batch release 2.35E+02 minutes Average total flow during period of release 2.04E+08 gpm 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases There were no abnormal releases of gaseous effluents from River Bend Nuclear Station during the reporting period of January 1, 2024, through December 31 2024 5.3.2 Liquid Abnormal Releases There were no abnormal releases of liquid effluents from River Bend Nuclear Station during the reporting period of January 1, 2024, through December 31 2024

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 21 of 78 Company: Enterav I Plant: River Bend Nuclear Station 5.4 5.5 5.6 5.6.1 Land Use Census Changes The Land Use Census for 2024 was conducted as required by the Technical Requirements Manual (TRM) (TR 3.12.2). The results of the Land Use Census will be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

A garden census is not conducted pursuant to the note in the TRM 3.12.2 that allows the sampling of broadleaf vegetation in the highest calculated average ground-level D/Q sector near site boundary in lieu of the garden census.

The milk animal census identified no milk animals within 8 km (5 miles) of River Bend site. This information was verified by the County Agents from West Feliciana, East Feliciana, and Pointe Coupee parishes.

No locations were identified this period that would yield a calculated dose or dose commitment greater than those currently calculated in Requirement TSR 3.11.2.3.1.

The County Agents confirmed that there was no commercial harvesting of crawfish within the five-mile radius downstream of RBS. RBS conservatively uses the invertebrate pathway although not required by NUREG-0133 liquid dose factor methodology for fresh water nuclear power plants.

Meteorological Data Cumulative joint frequency distributions and annual average data for continuous releases are listed in Attachment 3, Meteorological Data. The meteorological data recovery for 2024 was 97.6%.

Effluent Radiation Monitors Out of Service Greater Than 30 Days Radioactive Liquid Effluent Monitoring Instrumentation Operability The minimum number of channels required to be OPERABLE as described in Table 3.3.11.2-1 of Technical Requirement 3.3.11.2 were, if inoperable at any time in the period January 1, 2024, through December 31, 2024, restored to operable status within the required time.

5.6.2 Radioactive Gaseous Effluent Monitoring Instrumentation Operability The minimum number of channels required to be OPERABLE as described in Table 3.3.11.3-1 of Technical Requirement 3.3.11.3 were, if inoperable at any time in the period January 1, 2024, through December 31, 2024, restored to operable status within the required time.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 22 of 78 Company: Enterav I Plant: River Bend Nuclear Station 5.7 5.8 5.9 Offsite Dose Calculation Manual (ODCM) Changes There were no changes to the Offsite Dose Calculation Manual in 2024 Process Control Program (PCP) Changes There were no changes to the Process Control Program (PCP) in 2024 Radioactive Waste Treatment System Changes Engineering performed a review of the Maximo database to evaluate non-administrative design changes completed or partially completed during 2024 involving the subject systems (i.e. changes classified as evaluations or nuclear changes).

These design changes were then reviewed to determine if there have been any major changes to the subject systems. The review was based on a major change being defined as a modification which affected the method of processing or the effluent from the system. Also, to be a "major change" the change must have affected the Updated Safety Analysis Report (USAR).

No EC was identified as being completed during this time period that modified any radioactive waste system major component such that the processing method or effluent was changed. Also, no changes were identified affecting the method of processing solid, liquid or gaseous waste or the isotopic composition or the quantity of liquid, solid, or gaseous waste as described in the USAR.

5.10 Other Supplemental Information 5.10.1 Outside Tanks The maximum quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected outdoor tank during the period of January 1, 2024, through December 31,2024 was less than or equal to the 10 curie limit as required by Technical Specification 5.5.8.b

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 23 of 78 Company: Enterav I Plant: River Bend Nuclear Station 5.10.2 Independent Spent Fuel Storage Installation {ISFSI) Monitoring Program The HI-STORM 100 Cask System at River Bend Nuclear Station does not create any radioactive materials or have any radioactive waste treatment systems. There is no gaseous or liquid pathway attributed to the spent fuel stored in the independent spent fuel storage installation (ISFSI). Therefore, there were no radionuclides released to the environment in liquid or gaseous effluents during the reporting period of January 1 2024 to December 31, 2024. Dose due to direct radiation from ISFSI operations and from other uranium fuel cycle operations in the area was also reviewed. In 2024, no additional dry fuel storage casks were placed in service at the Independent Spent Fuel Storage Installation (ISFSI), for a total of 37 casks. Radiation Protection radiological surveys (RBS-2405-0096, RBS-2411-00114), Environmental TLD surveillance data (REMP-2 per EN-CY-130-03, Radiological Environmental Monitoring Program (REMP) - River Bend Station), Area Optically Stimulated Luminescent Dosimetry (OSLO) results per EN-RP-210, Area Monitoring Program, and current radiological postings were reviewed and demonstrate that there was no impact to members of the public from the dry fuel storage in 2024 and the limits of 10 CFR 72.104 were met.

5.10.3 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide with a 5,730-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.

The annual dose from C-14 was calculated using guidance from Regulatory Guide 1.21, Revision 2, NUREG-0016, and the methodology in Regulatory Guide 1.109.

The results of this calculation are listed in Table 2. The C-14 source term of 11 curies was taken from the site calculation PR(C)-359-3A, Gaseous Releases per NUREG-0016 Revision 1. Carbon-14 does not have dose factors associated with standing on contaminated ground; therefore, no ground plane dose was calculated. There is no milk pathway within five miles of River Bend Station, so this pathway is not evaluated.

RBS does not take credit for decay in the X/Q. This calculation assumes the inhalation, meat and vegetation pathways are at the site boundary in the sector with the highest X/Q. The dose from liquid effluents is not calculated as the dose contribution from C-14 is considered to be insignificant as indicated in Regulatory Guide 1.21, Revision 2. According to EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, 95% of the carbon released is in the form of carbon dioxide and this contributes the highest dose to man. The ingestion pathway, specifically vegetation, is the most likely route of intake for man. An assumption has been made for gaseous releases that plants obtain all of their C-14 from carbon dioxide. The estimated generation for River Bend Nuclear Station during 2024 was 11 Curies.

Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 24 of 78 Company: Enterav I Plant: River Bend Nuclear Station 5.10.4 Errata/Corrections to Previous ARERRs There were no Errata issued or corrections to previous ARERRs for the 2024 reporting period.

6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM River Bend Nuclear Station 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 2024, RBS collected and analyzed groundwater samples in accordance with the requirements of EN-CY-111.

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 as summarized in Table 4, Groundwater Protection Program Monitoring Well Sample Schedule. In addition to reporting results from NEI 07-07 monitoring wells, voluntary communications to offsite governmental agencies 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 ARERR.

Table 4, Groundwater Protection Program Monitoring Well Sample Schedule Well Name Tritium Gamma HTD Sulfate and Chloride5 MW-04 Annually Annually MW-05 Annually Annually MW-08 Annually Annually MW-14 Annually Annually MW-18 Annually Annually MW-100 Quarterly Quarterly Quinquennially MW-103 Annually Annually MW-104 Annually Annually MW-106 Semi-Annually Semi-Annually MW-107 Annually Annually 5 Last sampled in November 2022. Sulfate and Chloride are monitored in support of the Buried Piping Integrity Monitoring Program

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 25 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 4, Groundwater Protection Program Monitoring Well Sample Schedule Well Name Tritium Gamma HTD Sulfate and Chloride5 MW-108 Annually Annually MW-110 Quarterly Quarterly MW-111 Annually Annually MW-112 Quarterly Quarterly MW-114 Quarterly Quarterly MW-116 Quarterly Quarterly MW-118 Quarterly Quarterly MW-120 Semi-Annually Semi-Annually MW-122 Semi-Annually Semi-Annually MW-124 Quarterly Quarterly MW-125 Quarterly Quarterly Annually MW-126 Quarterly Quarterly MW-128 Semi-Annually Semi-Annually MW-130 Semi-Annually Semi-Annually MW-131 Semi-Annually Semi-Annually MW-132 Semi-Annually Semi-Annually MW-134 Semi-Annually Semi-Annually MW-137 Quarterly Quarterly MW-139 Quarterly Quarterly MW-141 Quarterly Quarterly MW-142 Quarterly Quarterly MW-144 Quarterly Quarterly MW-146 Quarterly Quarterly MW-147 Quarterly Quarterly MW-148 Quarterly Quarterly MW-151 Quarterly Quarterly MW-153 Quarterly Quarterly

Annual Radioactive Effluent Release Report I YEAR: 2024 I

Page 26 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 4, Groundwater Protection Program Monitoring Well Sample Schedule Well Name Tritium Gamma HTD Sulfate and Chloride5 MW-155 Quarterly Quarterly MW-156 Quarterly Quarterly MW-157 Quarterly Quarterly MW-158 Quarterly Quarterly MW-159 Quarterly Quarterly MW-161 Quarterly Quarterly MW-162 Quarterly Quarterly MW-164 Quarterly Quarterly Quinquennially MW-165 Quarterly Quarterly MW-167 Semi-Annually Semi-Annually MW-169 Semi-Annually Semi-Annually MW-170 Quarterly Quarterly MW-172 Annually Annually Quinquennially MW-174 Annually Annually Quinquennially MW-178 Quarterly Quarterly MW-179 Quarterly Quarterly MW-180 Semi-Annually Semi-Annually MW-182 Quarterly Quarterly MW-185 Quarterly Quarterly Quinquennially MW-186 Quarterly Quarterly MW-187 Quarterly Quarterly Quinquennially MW-188 Quarterly Quarterly MW-201 Semi-Annually Semi-Annually MW-203 Annually Annually MW-205 Semi-Annually Semi-Annually MW-207 Semi-Annually Semi-Annually MW-209 Quarterly Quarterly

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 27 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 4, Groundwater Protection Program Monitoring Well Sample Schedule Well Name Tritium Gamma HTD Sulfate and Chloride5 MW-211 Quarterly Quarterly MW-213 Semi-Annually Semi-Annually MW-215 Semi-Annually Semi-Annually MW-217 Semi-Annually Semi-Annually MW-219 Semi-Annually Semi-Annually MW-221 Quarterly Quarterly MW-223 Quarterly Quarterly MW-225 Semi-Annually Semi-Annually MW-227 Semi-Annually Semi-Annually MW-229 Semi-Annually Semi-Annually MW-231 Semi-Annually Semi-Annually MW-233 Semi-Annually Semi-Annually MW-235 Semi-Annually Semi-Annually PZ-01 Quarterly Quarterly PZ-03 Semi-Annually Semi-Annually SW-101 Quarterly Quarterly SW-102 Quarterly Quarterly SW-103 Quarterly Quarterly SW-104 Quarterly Quarterly T-14 Annually Annually All Radiological Groundwater Monitoring Program sample results are provided in, Groundwater Monitoring Well Sampling Results 6.1 Voluntary Notification During 2024, River Bend Nuclear Station 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: 2024 I Page 28 of 78 Company: Enterav I Plant: River Bend Nuclear Station 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] Health Physics Society, [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.

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

[11] "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.

[12] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

[13] "40 CFR 141 - National Primary Drinking Water Regulations," US Environmental Protection Agency, Washington, DC..

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

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

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

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

[18] "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.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 29 of 78 Company: Enterav I Plant: River Bend Nuclear Station, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 5, Gaseous Effluents Summation of All Releases 6 A.

Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Est. Total Error%

1.

Total Release Ci 2.08E+01 3.39E+00 2.65E+00 1.79E+00 37.0%

2.

Average release rate for the period

µCi/sec 2.64E+00 4.32E-01 3.33E-01 2.26E-01 B.

Iodine

1.

Total Iodine - 131 Ci 4.47E-03 4.00E-03 2.40E-02 2.77E-03 18.6% I

2.

Average release rate for the period

µCi/sec 5.75E-04 5.09E-04 3.01 E-03 3.48E-04 C.

Particulates

1.

Particulates with half-lives > 8 days Ci 7.74E-05 1.30E-04 1.38E-04 1.08E-04 18.6% I

2.

Average release rate for the period

µCi/sec 9.85E-06 1.65E-05 1.73E-05 1.36E-05 D.

Tritium

1.

Total Release Ci 1.77E+00 1.82E+00 1.39E+00 1.33E+00 18.2% I

2.

Average release rate for the period

µCi/sec 2.25E-01 2.31 E-01 1.74E-01 1.67E-01 E.

Gross Alpha

1.

Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2.

Average release rate for the period

µCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6 % of limit is provided in Table 1, River Bend Nuclear Station Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 30 of 78 Company: Enterav I Plant: River Bend Nuclear Station F.

Carbon-14

1.

Total Release Ci 2.73E+00 2.74E+00 2.76E+00 2.76E+00

2.

Average release rate for the period

µCi/sec 3.48E-01 3.48E-01 3.47E-01 3.47E-01 Table 6, Gaseous Effluents - Ground Level Release Continuous Mode Radionuclide Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Total for year Released Fission Gases Xe-135m Ci 3.87E+00 1.94E+00 6.55E-01 4.03E-01 6.87E+00 Xe-135 Ci 6.06E+00 1.04E+00 3.04E-01 3.60E-01 7.76E+00 Total for Period Ci 9.94E+00 2.98E+00 9.58E-01 7.63E-01 1.46E+01 Iodines 1-131 Ci 1.09E-05 7.92E-06 1.41 E-05 3.66E-06 3.66E-05 1-133 Ci 6.64E-06 9.83E-06 7.99E-06 2.12E-05 4.57E-05 Total for Period Ci 1.76E-05 1.78E-05 2.20E-05 2.49E-05 8.23E-05 Particulates Co-60 Ci 1.85E-06 5.62E-07 0.00E+00 0.00E+00 2.41 E-06 Total for Period Ci 1.85E-06 5.62E-07 0.00E+00 0.00E+00 2.41 E-06 Tritium H-3 Ci 3.51 E-01 9.25E-01 8.22E-01 3.76E-01 2.47E+00 Gross Alpha Alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Carbon-14 C-14 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 31 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 7, Gaseous Effluents - Mixed Level Release Continuous Mode Radionuclide Units Quarter 1 Quarter 2 Quarter3 Quarter4 Total for year Released Fission Gases Xe-131m Ci 6.28E+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.28E+OO Xe-133 Ci 1.23E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.23E+OO Xe-135 Ci 3.01 E+OO 4.16E-01 1.69E+OO 1.03E+OO 6.15E+OO Xe-138 Ci 3.14E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E-01 Total for Period Ci 1.08E+01 4.16E-01 1.69E+OO 1.03E+OO 1.40E+01 Iodines 1-131 Ci 4.46E-03 4.00E-03 2.39E-02 2.76E-03 3.52E-02 1-133 Ci 2.43E-02 3.00E-02 2.31 E-02 2.13E-02 9.87E-02 Total for Period Ci 2.88E-02 3.40E-02 4.71 E-02 2.40E-02 1.34E-01 Particulates Co-60 Ci 1.39E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E-06 Sr-89 Ci 4.56E-05 6.22E-05 9.25E-05 7.34E-05 2.74E-04 Ag-11 Om Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.00E-06 2.00E-06 Ba-140 Ci 2.86E-05 6.68E-05 4.50E-05 3.30E-05 1.73E-04 Total for Period Ci 7.56E-05 1.29E-04 1.38E-04 1.0SE-04 4.51 E-04 Tritium H-3 Ci 1.42E+OO 8.95E-01 5.63E-01 9.49E-01 3.83E+OO Gross Alpha Alpha Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Carbon-14 C-14 Ci 2.73E+OO 2.74E+OO 2.76E+OO 2.76E+OO 1.10E+01

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 32 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 8, Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Sampling Release Type Frequency Main Plant M

Exhaust Duct Grab Sample Fuel Building Ventilation M

Exhaust Duct Grab Sample Radwaste Building M

Ventilation Grab Sample Exhaust Duct All Release Types as listed Continuous above Continuous Continuous Continuous Continuous W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days Minimum Analysis Frequency M

M M

w Charcoal Sample w

Particulate Sample M

Composite Particulate Sample Q

Composite Particulate Sample Noble Gas Monitor Type of Activity Lower Limit of Detection (LLD)

Analysis uC/ml Principle Gamma 1.00E-04 Emitters H-3 1.00E-06 Principle Gamma 1.00E-04 Emitters H-3 1.00E-06 Principle Gamma 1.00E-04 Emitters H-3 1.00E-06 1-131 1.00E-12 1-133 1.00E-10 Principle Gamma 1.00E-11 Emitters (1-131, Others)

Gross Alpha 1.00E-11 Sr-89, Sr-90 1.00E-11 Noble Gases Gross Beta or 1.00E-6 Gamma

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 33 of 78 Company: Enterav I Plant: River Bend Nuclear Station 2.0 LIQUID EFFLUENTS Table 9, Liquid Effluents - Summation of All Releases 7 A.

Fission & Activation Products Units Quarter 1 Quarter2 Quarter 3 Quarter 4 Est. Total Error%

1.

Total Release Ci 1.44E-03 7.87E-03 2.46E-03 1.12E-03 14.2%

2.

Average diluted concentration

µCi/ml 1.09E-09 5.95E-09 2.26E-09 9.76E-10 B.

Tritium

1.

Total Release Ci 1.35E-01 4.30E+00 6.23E+00 2.96E+00 14.2%

I

2.

Average diluted concentration

µCi/ml 1.03E-07 3.25E-06 5.73E-06 2.59E-06 C.

Dissolved & Entrained Gases

1.

Total Release Ci 1.94E-04 1.09E-02 1.57E-02 1.66E-03 14.2%

I

2.

Average diluted concentration

µCi/ml 1.48E-10 8.27E-09 1.44E-08 1.45E-09 D.

Gross Alpha Activity

1.

Total Release Ci I 0.00E+00 I 0.00E+00 I 0.00E+00 I 0.0OE+00 I 14.2% I E.

Volume of Waste Released (prior Liters 5.64E+05 1.99E+06 3.65E+06 1.48E+06 to dilution)

F.

Volume of Dilution Water Used Liters 1.32E+09 1.32E+09 1.09E+09 1.15E+09 During Period 7 % of limit is provided in Table 1, River Bend Nuclear Station Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 34 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 10, Batch Mode Liquid Effluents Radionuclide Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Total for year Released Fission and Activation Products Mn-54 Ci 1.57E-06 6.91 E-05 4.58E-05 1.64E-05 1.33E-04 Co-58 Ci 8.06E-07 4.22E-06 8.15E-07 0.00E+0O 5.84E-06 Co-60 Ci 1.44E-03 1.23E-03 2.17E-03 1.0SE-03 5.92E-03 Ni-65 Ci 0.00E+00 3.83E-05 1.21 E-05 7.00E-06 5.75E-05 Zn-65 Ci 0.00E+00 2.39E-05 2.37E-05 7.65E-06 5.53E-05 Br-82 Ci 0.00E+00 0.00E+00 7.36E-07 1.78E-06 2.52E-06 Y-92 Ci 0.00E+00 0.00E+00 5.36E-06 0.00E+0O 5.36E-06 Zr-95 Ci 0.00E+00 7.25E-07 0.00E+00 0.00E+0O 7.25E-07 Nb-97 Ci 0.00E+00 0.00E+00 1.44E-06 0.00E+0O 1.44E-06 Mo-99 Ci 0.00E+00 0.00E+00 4.46E-06 0.00E+0O 4.46E-06 Tc-99m Ci 0.00E+00 0.00E+00 6.55E-07 0.00E+0O 6.55E-07 Ag-110m Ci 0.00E+00 1.23E-06 3.22E-06 0.00E+0O 4.44E-06 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 4.35E-07 4.35E-07 Sb-125 Ci 0.00E+00 0.00E+00 3.96E-06 0.00E+0O 3.96E-06 1-132 Ci 0.00E+00 0.00E+00 1.88E-06 0.00E+0O 1.88E-06 1-133 Ci 0.00E+00 0.00E+00 1.09E-06 0.00E+0O 1.09E-06 1-134 Ci 0.00E+00 0.00E+00 3.93E-06 0.00E+0O 3.93E-06 Cs-134 Ci 0.00E+00 0.00E+00 5.61 E-07 0.00E+0O 5.61 E-07 Ba-142 Ci 0.00E+00 6.50E-03 1.69E-04 0.00E+0O 6.66E-03 La-140 Ci 0.00E+00 7.43E-06 0.00E+00 2.03E-06 9.46E-06 Am-241 Ci 0.00E+00 0.00E+00 7.03E-06 0.00E+0O 7.03E-06 Total for Period Ci 1.44E-03 7.87E-03 2.46E-03 1.12E-03 1.29E-02 Tritium H-3 Ci 1.35E-01 4.30E+00 6.23E+00 2.96E+0O 1.36E+01 Gross Alpha Alpha Ci II

" -ini=+nn 0.00E+00 0.00E+00 o.onF+nn n nnF+nn Entrained Gases Kr-88 Ci 0.00E+00 1.92E-05 0.00E+00 0.00E+0O 1.92E-05 Xe-133m Ci 0.00E+00 1.09E-04 1.66E-04 2.11 E-05 2.97E-04 Xe-133 Ci 9.18E-05 4.52E-03 7.24E-03 8.48E-04 1.27E-02 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 3.63E-06 3.63E-06 Xe-135 Ci 1.03E-04 6.30E-03 8.31 E-03 7.86E-04 1.55E-02 Total for Period Ci 1.94E-04 1.09E-02 1.57E-02 1.66E-03 2.85E-02

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 35 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 11, Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sampling Type Frequency Batch Waste Release (Liquid Radwaste p

Recovery Each Batch Sample Tanks) p Each Batch / M p

Each Batch p

Each Batch P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days Minimum Analysis Frequency p

Each Batch M

M Composite Q

Composite Type of Activity Lower Limit of Detection (LLD)

Analysis uC/ml Principle Gamma 5.00E-07 Emitters; except 5.00E-06 Ce-144 1-131 1.00E-06 Dissolved and Entrained Gases (Gamma 1.00E-05 Emitters)

H-3 1.00E-05 Gross Alpha 1.00E-07 Sr-89, Sr-90 5.00E-8 Fe-55 1.00E-06

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 36 of 78 Company: Enterav I Plant: River Bend Nuclear Station, Solid Waste Information 3.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Solid waste volumes and activity were determined by measurement and correlation. All solid waste was packaged in strong, tight liners. No solidification agent or absorbents were used. "Major" radionuclide is equivalent to a "principle" radionuclide, i.e. greater than 1 percent of total activity.

Table 12, Types of Solid Waste Summary Total Volume Total Activity Est. Total Types of Waste Error (m3)

(Ci)

(%)

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

8.13E+01 6.16E+01 25

b. Dry compressible waste, contaminated equip, etc.

3.31 E+02 1.09E-01 25

c. Irradiated components, control rods, etc.

O.OOE+OO O.OOE+OO 25

d. Other 8.33E+OO 3.19E-03 25 4.0 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY WASTE TYPE) ONLY >1 %

ARE REPORTED.

Table 13, Major Nuclides Major Nuclide Composition Curies

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

Mn-54 4.41%

2.72E+OO Fe-55 1.49%

9.16E-01 Co-60 65.28%

4.02E+01 Zn-65 26.21%

1.62E+01 Cs-137 1.57%

9.66E-01

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 37 of 78 Company: Enterav I Plant: River Bend Nuclear Station Table 13, Major Nuclides

b. Dry compressible waste, contaminated equip, etc.

Fe-55 41.47%

4.42E-02 Co-60 53.05%

5.65E-02 Ni-63 1.7%

1.81 E-03 Zn-65 1.03%

1.10E-03

c. Irradiated components, control rods, etc.

N/A N/A N/A

d. Other Mn-54 5.21%

1.67E-04 Fe-55 1.36%

4.36E-05 Co-60 56.17%

1.79E-03 Zn-65 33.94%

1.0SE-03 Cs-137 1.27%

4.06E-05 5.0 SOLID WASTE DISPOSITION Table 14, Solid Waste Disposition Number of Mode of Transportation Destination Shipments 27 Hittman Transport Services, Inc.

EnergySolutions Services (Bear Creek)

Bear Creek Processing Facility

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 38 of 78 Company: Enterav I Plant: River Bend Nuclear Station 6.0 IRRADIATED FUEL DISPOSITION Table 15, Irradiated Fuel Shipments Disposition Number of Mode of Transportation Destination Shipments N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 39 of 78 Company: Enterav I Plant: River Bend Nuclear Station, Meteorological Data 1.0 METEOROLOGICAL DATA

SUMMARY

1.1 Joint Frequency Distributions

1.

Period of Record: 2024

2.

Tower Height: 30 Ft

a.

Stability Class: All

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 199

3)

Number of Valid Hours: 8585

4)

Total hours for the Period: 8784 Table 16, 30 Ft Elevation: All Stability Classes Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

68 43 88 114 107 92 50 0

0 0

562 NNE 64 40 81 173 142 106 16 0

0 0

622 NE 85 45 62 134 163 96 3

0 0

0 588 ENE 58 53 71 136 89 54 5

0 0

0 466 E

53 69 57 109 89 20 1

0 0

0 398 ESE 33 64 81 131 146 56 7

0 0

0 518 SE 24 54 109 273 295 251 41 0

0 0

1047 SSE 26 45 54 187 170 224 108 2

0 0

816 s

19 46 85 110 105 191 47 0

0 0

603 SSW 20 44 40 57 53 72 19 0

0 0

305 SW 15 42 27 40 44 44 13 0

0 0

225 WSW 32 70 22 37 82 60 8

0 0

0 311 w

72 111 41 54 81 67 10 0

0 0

436 WNW 92 139 55 87 62 68 39 1

0 0

543 NW 109 100 50 69 94 130 62 3

0 0

617 NNW 82 65 84 78 66 90 63 0

0 0

528 Total 852 1030 1007 1789 1788 1621 492 6

0 0

8585

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 40 of 78 Company: Enterav I Plant: River Bend Nuclear Station

b.

Stability Class: A

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 1944

4)

Total hours for the Period: 1944 Table 17, 30 Ft Elevation: Stability Class A Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

2 13 37 53 26 0

0 0

131 NNE 0

0 2

14 43 58 6

0 0

0 123 NE 0

0 0

19 58 46 0

0 0

0 123 ENE 0

2 5

22 40 22 3

0 0

0 94 E

0 2

2 18 28 9

0 0

59 ESE 0

1 2

23 44 17 2

0 0

0 89 SE 0

2 1

16 68 94 18 0

0 0

199 SSE 0

0 0

25 42 74 53 0

0 0

194 s

0 0

1 9

37 86 28 0

0 0

161 SSW 0

0 5

15 26 37 15 0

0 0

98 SW 1

0 0

15 26 31 4

0 0

0 77 WSW 0

2 0

14 60 46 3

0 0

0 125 w

0 1

3 14 54 48 6

0 0

0 126 WNW 0

1 0

20 25 28 27 1

0 0

102 NW 1

0 2

17 46 50 21 1

0 0

138 NNW 0

1 3

13 23 37 28 0

0 0

105 Total 2

12 28 267 657 736 240 2

0 0

1944

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 41 of 78 Company: Enterav I Plant: River Bend Nuclear Station C.

Stability Class: B

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 219

4)

Total hours for the Period: 219 Table 18, 30 Ft Elevation: Stability Class B Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 0

4 6

2 0

0 0

13 NNE 0

0 1

3 6

5 0

0 0

0 15 NE 0

0 1

2 7

4 0

0 0

0 14 ENE 0

0 0

5 1

3 0

0 0

0 9

E 0

0 0

5 2

1 0

0 0

0 8

ESE 0

0 1

4 0

2 0

0 0

0 7

SE 0

0 1

5 8

8 3

0 0

0 25 SSE 0

0 0

2 4

11 10 0

0 0

27 s

0 0

0 2

1 14 5

0 0

0 22 SSW 0

0 0

0 1

5 1

0 0

0 7

SW 0

0 0

1 1

4 2

0 0

0 8

WSW 0

0 2

2 2

0 0

0 8

w 0

0 1

1 2

2 0

0 0

0 6

WNW 0

0 0

4 0

4 2

0 0

0 10 NW 0

0 0

5 0

8 11 1

0 0

25 NNW 0

0 1

0 2

7 5

0 0

0 15 Total 0

0 9

39 41 86 43 1

0 0

219

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 42 of 78 Company: Enterav I Plant: River Bend Nuclear Station

d.

Stability Class: C

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 210

4)

Total hours for the Period: 210 Table 19, 30 Ft Elevation: Stability Class C Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 5

4 4

5 0

0 0

19 NNE 0

0 0

4 2

7 1

0 0

0 14 NE 0

0 0

5 7

3 0

0 0

0 15 ENE 0

1 0

5 1

1 0

0 0

0 8

E 0

0 1

3 0

1 0

0 0

0 5

ESE 0

0 1

4 1

4 0

0 0

0 10 SE 0

0 1

5 7

6 5

0 0

0 24 SSE 0

0 0

3 4

10 7

0 0

0 24 s

0 0

0 1

1 12 2

0 0

0 16 SSW 0

0 0

0 4

3 1

0 0

0 8

SW 0

0 0

2 3

1 3

0 0

0 9

WSW 0

0 1

3 0

1 0

0 0

0 5

w 0

0 0

2 3

3 1

0 0

0 9

WNW 0

0 0

2 2

6 1

0 0

0 11 NW 0

0 0

2 4

4 6

0 0

0 16 NNW 0

0 0

1 3

7 6

0 0

0 17 Total 0

1 5

47 46 73 38 0

0 0

210

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 43 of 78 Company: Enterav I Plant: River Bend Nuclear Station

e.

Stability Class: D

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 1705

4)

Total hours for the Period: 1705 Table 20, 30 Ft Elevation: Stability Class D Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 1

7 18 35 27 15 0

0 0

103 NNE 0

2 8

39 40 24 8

0 0

0 121 NE 1

3 8

30 46 32 3

0 0

0 123 ENE 0

3 18 30 27 25 2

0 0

0 105 E

0 2

10 32 30 3

0 0

77 ESE 0

6 11 53 61 19 5

0 0

0 155 SE 0

3 13 61 98 85 14 0

0 0

274 SSE 0

0 11 24 40 88 34 2

0 0

199 s

0 2

6 26 23 60 11 0

0 0

128 SSW 0

2 9

13 12 21 2

0 0

0 59 SW 0

1 3

12 8

8 3

0 0

0 35 WSW 0

1 1

10 11 8

1 0

0 0

32 w

0 2

6 12 14 11 2

0 0

0 47 WNW 0

0 3

17 18 20 7

0 0

0 65 NW 0

1 7

8 19 43 20 1

0 0

99 NNW 0

1 4

7 19 32 20 0

0 0

83 Total 1

30 125 392 501 506 147 3

0 0

1705

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 44 of 78 Company: Enterav I Plant: River Bend Nuclear Station

f.

Stability Class: E

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 2422

4)

Total hours for the Period: 2422 Table 21, 30 Ft Elevation: Stability Class E Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

2 7

29 57 26 2

2 0

0 0

125 NNE 2

11 43 102 50 12 1

0 0

0 221 NE 5

15 35 71 45 11 0

0 0

0 182 ENE 6

9 31 58 19 3

0 0

126 E

11 13 23 44 29 5

1 0

0 0

126 ESE 8

19 47 41 36 13 0

0 0

0 164 SE 2

23 65 166 108 55 1

0 0

0 420 SSE 5

13 31 116 73 41 4

0 0

0 283 s

3 19 52 56 40 19 1

0 0

0 190 SSW 5

28 22 24 10 6

0 0

95 SW 4

21 21 7

4 0

1 0

0 0

58 WSW 7

18 11 4

9 3

2 0

0 0

54 w

3 18 12 23 7

3 1

0 0

0 67 WNW 10 25 18 33 16 5

2 0

0 0

109 NW 2

13 11 26 20 20 4

0 0

0 96 NNW 3

10 26 38 19 7

3 0

0 0

106 Total 78 262 477 866 511 205 23 0

0 0

2422

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 45 of 78 Company: Enterav I Plant: River Bend Nuclear Station

g.

Stability Class: F

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 966

4)

Total hours for the Period: 966 Table 22, 30 Ft Elevation: Stability Class F Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

13 24 43 19 1

0 0

0 100 NNE 10 14 25 9

1 0

0 0

59 NE 7

13 14 4

0 0

38 ENE 9

13 15 13 1

0 0

0 51 E

12 20 16 7

0 0

55 ESE 10 27 16 6

2 1

0 0

62 SE 8

20 23 18 2

2 0

0 0

0 73 SSE 6

24 11 15 5

0 0

0 61 s

10 17 20 12 0

0 0

0 59 SSW 5

9 4

2 0

0 0

0 20 SW 4

12 1

2 0

0 0

0 19 WSW 15 22 3

4 0

0 0

0 44 w

30 30 14 1

0 0

75 WNW 28 45 17 8

1 2

0 0

101 NW 24 27 16 8

1 3

0 0

79 NNW 20 10 22 17 0

0 1

0 0

0 70 Total 211 327 260 145 14 8

1 0

0 0

966

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 46 of 78 Company: Enterav I Plant: River Bend Nuclear Station

h.

Stability Class: G

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 1119

4)

Total hours for the Period: 1119 Table 23, 30 Ft Elevation: Stability Class G Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

53 11 5

2 0

0 0

0 71 NNE 52 13 2

2 0

0 0

0 69 NE 72 14 4

3 0

0 0

0 93 ENE 43 25 2

3 0

0 0

0 73 E

30 32 5

0 0

1 0

0 0

0 68 ESE 15 11 3

0 2

0 0

0 31 SE 14 6

5 2

4 1

0 0

32 SSE 15 8

1 2

2 0

0 0

28 s

6 8

6 4

3 0

0 0

27 SSW 10 5

0 3

0 0

18 SW 6

8 2

1 2

0 0

0 19 WSW 10 27 4

2 0

0 0

0 43 w

39 60 5

1 1

0 0

0 106 WNW 54 68 17 3

0 3

0 0

145 NW 82 59 14 3

4 2

0 0

164 NNW 59 43 28 2

0 0

132 Total 560 398 103 33 18 7

0 0

1119

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 4 7 of 78 Company: Enterav I Plant: River Bend Nuclear Station

3.

Tower Height: 150 Ft

a.

Stability Class: All

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 217

3)

Number of Valid Hours: 8567

4)

Total hours for the Period: 8784 Table 24, 150 Ft Elevation: All Stability Classes Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 2

8 13 37 161 195 28 1

0 0

0 446 NNE 0

2 3

30 63 278 238 8

2 0

0 0

624 NE 0

2 5

31 73 273 323 6

4 0

0 0

717 ENE 0

1 6

43 86 181 271 61 3

0 0

0 652 E

0 4

14 42 77 147 160 46 4

0 0

0 494 ESE 0

1 3

22 54 225 652 143 27 0

0 0

1127 SE 1

2 3

31 58 228 252 62 5

0 0

0 642 SSE 0

2 6

26 52 179 260 56 6

0 0

0 587 s

0 2

5 29 64 220 258 23 2

0 0

0 603 SSW 1

1 3

31 74 198 129 15 1

0 0

0 453 SW 0

0 7

28 73 130 39 5

3 0

0 0

285 WSW 0

6 7

30 107 173 45 4

0 0

372 w

0 5

7 39 68 193 83 13 3

0 0

0 411 WNW 0

2 5

22 50 137 113 37 4

0 0

0 370 NW 0

0 6

17 39 147 159 22 4

0 0

0 394 NNW 1

1 4

15 33 157 133 43 3

0 0

0 390 Total 4

33 92 449 1008 3027 3310 572 72 0

0 0

8567

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 48 of 78 Company: Enterav I Plant: River Bend Nuclear Station

b.

Stability Class: A

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 1821

4)

Total hours for the Period: 1821 Table 25, 150 Ft Elevation: Stability Class A Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 1

2 3

10 40 51 15 0

0 0

0 122 NNE 0

0 0

9 13 43 44 2

0 0

111 NE 0

0 0

7 15 55 58 2

1 0

0 0

138 ENE 0

0 3

4 13 40 55 7

0 0

122 E

0 0

1 7

18 23 21 4

0 0

74 ESE 0

0 0

4 11 41 96 22 0

0 0

0 174 SE 0

1 0

7 16 43 38 17 1

0 0

0 123 SSE 0

0 0

6 10 29 58 22 0

0 0

0 125 s

0 0

0 4

10 37 71 9

0 0

131 SSW 0

0 0

4 15 35 29 10 1

0 0

0 94 SW 0

0 0

2 14 31 14 1

0 0

62 WSW 0

0 2

4 35 65 17 1

0 0

124 w

0 1

0 7

15 72 38 5

1 0

0 0

139 WNW 0

0 0

9 12 29 31 16 3

0 0

0 100 NW 0

0 0

5 12 47 29 5

1 0

0 0

99 NNW 0

0 4

3 11 28 16 18 3

0 0

0 83 Total 0

3 12 85 230 658 666 156 11 0

0 0

1821

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 49 of 78 Company: Enterav I Plant: River Bend Nuclear Station C.

Stability Class: B

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 287

4)

Total hours for the Period: 287 Table 26, 150 Ft Elevation: Stability Class B Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 1

1 4

6 3

0 0

16 NNE 0

0 0

4 1

8 6

0 0

0 19 NE 0

0 0

0 2

3 3

0 0

0 8

ENE 0

0 0

1 2

3 9

1 0

0 0

0 16 E

0 0

1 0

1 5

0 0

7 ESE 0

0 0

1 4

4 8

5 0

0 0

0 22 SE 0

0 0

1 1

6 11 5

1 0

0 0

25 SSE 0

0 0

1 0

6 17 6

0 0

30 s

0 0

0 3

0 7

23 4

0 0

37 SSW 0

0 0

0 1

3 12 2

0 0

18 SW 0

0 1

1 1

2 4

1 0

0 0

0 10 WSW 0

0 0

0 1

8 4

0 0

0 13 w

0 0

1 2

2 4

3 3

1 0

0 0

16 WNW 0

0 0

2 12 2

1 0

0 0

17 NW 0

0 0

1 0

2 8

3 1

0 0

0 15 NNW 0

0 0

1 3

2 10 2

0 0

18 Total 0

0 4

17 20 69 136 37 4

0 0

0 287

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 50 of 78 Company: Enterav I Plant: River Bend Nuclear Station

d.

Stability Class: C

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 246

4)

Total hours for the Period: 246 Table 27, 150 Ft Elevation: Stability Class C Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 1

3 1

6 2

0 0

13 NNE 0

0 1

1 1

6 7

0 0

0 16 NE 0

0 0

0 1

5 9

0 0

0 15 ENE 0

0 0

2 1

5 4

1 0

0 0

0 13 E

0 0

0 2

2 0

0 0

4 ESE 0

0 0

0 4

6 14 3

2 0

0 0

29 SE 0

0 0

1 0

5 7

6 1

0 0

0 20 SSE 0

1 0

1 1

4 9

8 0

0 0

0 24 s

0 0

0 7

13 3

0 0

23 SSW 0

0 0

5 5

1 0

0 0

0 11 SW 0

0 0

7 1

0 0

0 8

WSW 0

0 0

0 5

2 1

0 0

0 8

w 0

0 0

1 2

6 3

0 1

0 0

0 13 WNW 0

0 0

7 8

4 0

0 0

0 19 NW 0

0 0

1 1

2 9

2 0

0 0

0 15 NNW 0

0 0

4 6

5 0

0 0

0 15 Total 0

1 1

8 19 74 104 35 4

0 0

0 246

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 51 of 78 Company: Enterav I Plant: River Bend Nuclear Station

e.

Stability Class: D

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 1768

4)

Total hours for the Period: 1768 Table 28, 150 Ft Elevation: Stability Class D Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

2 2

4 25 47 5

0 0

85 NNE 0

0 0

4 6

51 51 6

0 0

118 NE 0

0 4

2 18 36 64 3

3 0

0 0

130 ENE 0

0 2

5 21 27 79 27 1

0 0

0 162 E

0 1

3 5

7 35 53 12 2

0 0

0 118 ESE 0

0 0

2 6

38 171 60 20 0

0 0

297 SE 0

0 0

4 5

28 60 24 2

0 0

0 123 SSE 0

0 0

3 6

28 93 20 5

0 0

0 155 s

0 0

1 4

7 31 73 7

1 0

0 0

124 SSW 0

0 1

6 6

23 47 2

0 0

85 SW 0

0 0

4 6

9 12 2

3 0

0 0

36 WSW 0

0 1

2 7

10 14 2

0 0

36 w

0 0

1 5

10 24 24 4

0 0

68 WNW 0

0 0

2 9

17 30 12 0

0 0

0 70 NW 0

0 2

2 4

15 47 9

2 0

0 0

81 NNW 0

1 0

1 3

21 40 14 0

0 0

0 80 Total 0

2 17 53 125 418 905 209 39 0

0 0

1768

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 52 of 78 Company: Enterav I Plant: River Bend Nuclear Station

f.

Stability Class: E

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 2437

4)

Total hours for the Period: 2437 Table 29, 150 Ft Elevation: Stability Class E Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 1

0 3

12 41 36 3

1 0

0 0

98 NNE 0

1 1

3 12 88 94 0

2 0

0 0

201 NE 0

0 0

9 22 98 122 1

0 0

252 ENE 0

1 0

15 20 47 99 24 2

0 0

0 208 E

0 0

3 14 21 45 71 29 2

0 0

0 185 ESE 0

1 2

6 15 82 276 51 5

0 0

0 438 SE 0

0 1

6 20 82 87 10 0

0 0

0 206 SSE 0

1 1

7 14 56 72 0

1 0

0 0

152 s

0 1

0 4

18 85 64 0

1 0

0 0

173 SSW 0

0 1

7 21 77 31 0

0 0

137 SW 0

0 3

4 13 29 5

1 0

0 0

0 55 WSW 0

2 1

7 19 29 4

1 0

0 0

0 63 w

0 1

0 7

14 25 12 1

0 0

60 WNW 0

0 2

7 11 25 15 3

0 0

63 NW 0

0 0

2 5

21 36 3

0 0

67 NNW 1

0 0

6 4

34 31 3

0 0

79 Total 2

9 15 107 241 864 1055 130 14 0

0 0

2437

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 53 of 78 Company: Enterav I Plant: River Bend Nuclear Station

g.

Stability Class: F

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 954

4)

Total hours for the Period: 954 Table 30, 150 Ft Elevation: Stability Class F Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 2

2 10 35 0

0 0

50 NNE 0

1 0

4 10 48 31 0

0 0

94 NE 0

2 1

6 8

44 46 0

0 0

107 ENE 0

0 1

6 17 27 15 1

0 0

67 E

0 0

4 10 12 18 11 1

0 0

56 ESE 0

0 0

6 10 30 52 2

0 0

100 SE 1

0 1

6 7

32 31 0

0 0

78 SSE 0

0 1

4 8

29 10 0

0 0

52 s

0 1

2 6

15 35 13 0

0 0

72 SSW 0

0 0

5 11 23 2

0 0

0 41 SW 0

0 2

7 18 23 1

0 0

0 51 WSW 0

0 2

8 19 22 1

0 0

0 52 w

0 1

2 5

12 13 0

0 0

0 33 WNW 0

1 3

0 7

16 6

0 0

0 33 NW 0

0 2

2 7

11 9

0 0

0 31 NNW 0

0 0

2 6

18 10 1

0 0

37 Total 1

6 22 79 169 399 273 5

0 0

954

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 54 of 78 Company: Enterav I Plant: River Bend Nuclear Station

h.

Stability Class: G

1)

Periods of calm (hours): 0

2)

Number of Invalid Hours: 0

3)

Number of Valid Hours: 1054

4)

Total hours for the Period: 1054 Table 31, 150 Ft Elevation: Stability Class G Wind Speed (Meters/Second)

Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

2 1

5 40 14 0

0 0

62 NNE 0

0 1

5 20 34 5

0 0

0 65 NE 0

0 0

7 7

32 21 0

0 0

67 ENE 0

0 0

10 12 32 10 0

0 0

64 E

0 3

2 6

18 19 2

0 0

0 50 ESE 0

0 1

3 4

24 35 0

0 0

67 SE 0

1 1

6 9

32 18 0

0 0

67 SSE 0

0 4

4 13 27 1

0 0

0 49 s

0 0

2 8

14 18 1

0 0

0 43 SSW 1

1 1

9 20 32 3

0 0

0 67 SW 0

0 1

10 21 29 2

0 0

0 63 WSW 0

4 1

9 21 37 4

0 0

0 76 w

0 2

3 12 13 49 3

0 0

0 82 WNW 0

1 0

4 11 41 11 0

0 0

68 NW 0

0 2

4 10 49 21 0

0 0

86 NNW 0

0 0

2 6

50 20 0

0 0

78 Total 1

12 21 100 204 545 171 0

0 0

1054

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 55 of 78 Company: Enterav I Plant: River Bend Nuclear Station 1.2 Stability class Table 32, Classification of Atmospheric Stability Stability Condition Pasquill Categories Percentage Extremely Unstable A

22%

Moderately Stable B

3%

Slightly Unstable C

3%

Neutral D

20%

Slightly Stable E

28%

Moderately Stable F

11%

Extremely Stable G

13%

Station ID Sample Date MW-04 11/14/2024 MW-05 11/13/2024 MW-08 11/13/2024 MW-100 2/13/2024 MW-100 6/19/2024 MW-100 9/17/2024 MW-100 11/13/2024 MW-100 11/13/2024 MW-102 9/18/2024 MW-103 11/14/2024 MW-104 11/14/2024 MW-106 6/19/2024 MW-106 11/13/2024 MW-107 11/12/2024 MW-107 11/12/2024 MW-108 11/12/2024 MW-110 2/14/2024 MW-110 6/19/2024 Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 56 of 78 Company: Entergy I Plant: River Bend Nuclear Station Units MN-54 pCi/L

< 7.6E+00 pCi/L

< 5.5E+00 pCi/L

< 6.7E+00 pCi/L

< 5.1E+00 pCi/L

< 6.4E+00 pCi/L

< 5.6E+00 pCi/L

< 4.7E+00 pCi/L

< 5.9E+00 pCi/L

< 5.3E+00 pCi/L

< 6.8E+00 pCi/L

< 5.3E+00 pCi/L

< 5.2E+00 pCi/L

< 7.7E+00 pCi/L

< 6.5E+00 pCi/L

< 4.2E+00 pCi/L

< 7.2E+00 pCi/L

< 4.4E+00 pCi/L

< 1.9E+00, Groundwater Monitoring Well Sampling Results Table 33, Gamma Isotopic Results CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131

< 7.5E+00

< 1.2E+01

< 7.7E+00

< 1.1E+01

< 8.1E+00

< 1.2E+01

< 1.3E+01

< 6.3E+00

< 1.5E+01

< 6.4E+00

< 1.4E+01

< 6.7E+00

< 1.4E+01

< 1.3E+01

< 6.1E+00

< 1.4E+01

< 5.6E+00

< 1.4E+01

< 6.1E+00

< 1.1E+01

< 5.0E+00

< 1.3E+01

< 4.8E+00

< 1.1E+01

< 5.8E+00

< 9.1E+00

< 1.5E+01

< 6.7E+00

< 1.2E+01

< 7.8E+00

< 1.6E+01

< 8.0E+00

< 9.7E+00

< 1.4E+01

< 6.3E+00

< 9.1E+00

< 7.3E+00

< 1.2E+01

< 8.8E+00

< 1.1E+01

< 1.2E+01

< 6.4E+00

< 1.3E+01

< 6.3E+00

< 1.3E+01

< 6.0E+00

< 8.1E+00

< 9.4E+00

< 5.9E+00

< 1.3E+01

< 5.8E+00

< 1.1E+01

< 5.9E+00

< 9.7E+00

< 1.1E+01

< 6.1E+00

< 1.2E+01

< 8.1E+00

< 1.5E+01

< 6.3E+00

< 1.0E+01

< 1.1E+01

< 6.9E+00

< 1.6E+01

< 8.9E+00

< 7.1E+00

< 4.4E+00

< 1.5E+01

< 1.1E+01

< 7.2E+00

< 1.2E+01

< 7.2E+00

< 1.1E+01

< 7.2E+00

< 1.0E+01

< 1.1E+01

< 7.2E+00

< 1.1E+01

< 6.5E+00

< 1.5E+01

< 7.5E+00

< 1.3E+01

< 1.4E+01

< 7.4E+00

< 1.8E+01

< 8.3E+00

< 1.5E+01

< 9.7E+00

< 1.1E+01

< 1.4E+01

< 5.9E+00

< 8.9E+00

< 5.4E+00

< 1.2E+01

< 6.9E+00

< 1.1E+01

< 1.3E+01

< 5.9E+00

< 1.4E+01

< 7.3E+00

< 1.0E+01

< 6.4E+00

< 1.0E+01

< 9.4E+00

< 7.9E+00

< 1.7E+01

< 7.9E+00

< 1.4E+01

< 7.7E+00

< 1.0E+01

< 1.5E+01

< 4.0E+00

< 9.4E+00

< 4.0E+00

< 9.0E+00

< 4.7E+00

< 7.6E+00

< 1.4E+01

< 2.3E+00

< 4.9E+00

< 2.2E+00

< 4.0E+00

< 2.4E+00

< 4.0E+00

< 1.0E+01 CS-134

< 8.7E+00

< 6.7E+00

< 6.1E+00

< 5.6E+00

< 8.0E+00

< 7.8E+00

< 7.0E+00

< 5.6E+00

< 5.4E+00

< 7.7E+00

< 4.5E+00

< 6.2E+00

< 6.9E+00

< 8.2E+00

< 4.5E+00

< 2.2E+00 CS-137

< 6.9E+00

< 6.7E+00

< 6.1E+00

< 4.8E+00

< 5.8E+00

< 7.3E+00

< 4.6E+00

< 5.7E+00

< 6.2E+00

< 6.3E+00

< 7.5E+00

< 6.9E+00

< 9.4E+00

< 5.8E+00

< 5.7E+00

< 7.2E+00

< 4.1E+00

< 2.0E+00 BA-140 LA-140

< 3.9E+01

< 1.4E+01

< 2.9E+01

< 1.2E+01

< 3.0E+01

< 1.0E+01

< 3.0E+01

< 1.2E+01

< 3.4E+01

< 1.2E+01

< 3.5E+01

< 7.5E+00

< 2.7E+01

< 1.1E+01

< 3.0E+01

< 9.6E+00

< 3.6E+01

< 1.0E+01

< 3.8E+01

< 1.4E+01

< 2.4E+01

< 1.2E+01

< 3.8E+01

< 1.4E+01

< 3.8E+01

< 1.4E+01

< 3.3E+01

< 7.0E+00

< 2.9E+01

< 1.2E+01

< 3.8E+01

< 1.2E+01

< 2.9E+01

< 1.0E+01

< 1.9E+01

< 6.2E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 57 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-110 9/18/2024 pCi/L

< 4.7E+00

< 4.6E+00

< 1.2E+01

< 4.8E+00

< 9.3E+00

< 5.7E+00

< 8.2E+00

< 1.3E+01

< 5.1E+00

< 4.7E+00

< 2.7E+01

< 1.1E+01 MW-110 11/14/2024 pCi/L

< 1.6E+00

< 2.0E+00

< 4.7E+00

< 1.9E+00

< 3.7E+00

< 2.1E+00

< 3.4E+00

< 1.0E+01

< 1.8E+00

< 1.8E+01

< 5.6E+00 MW-111 11/14/2024 pCi/L

< 7.7E+00

< 1.2E+01

< 7.0E+00

< 1.1E+01

< 6.8E+00

< 1.3E+01

< 1.1E+01

< 5.5E+00

< 7.9E+00

< 3.4E+01

< 1.2E+01 MW-112 2/14/2024 pCi/L

< 3.5E+00

< 4.5E+00

< 7.6E+00

< 4.9E+00

< 6.6E+00

< 4.0E+00

< 6.8E+00

< 1.5E+01

< 5.0E+00

< 4.7E+00

< 2.6E+01

< 9.9E+00 MW-112 6/19/2024 pCi/L

< 1.8E+00

< 2.1E+00

< 4.8E+00

< 2.1E+00

< 4.2E+00

< 2.0E+00

< 4.1E+00

< 9.9E+00

< 2.2E+00

< 2.0E+00

< 1.9E+01

< 7.1E+00 MW-112 9/18/2024 pCi/L

< 4.8E+00

< 4.5E+00

< 1.2E+01

< 4.9E+00

< 1.0E+01

< 5.2E+00

< 7.9E+00

< 1.4E+01

< 5.0E+00

< 4.8E+00

< 3.3E+01

< 9.9E+00 MW-112 11/14/2024 pCi/L

< 1.9E+00

< 2.1E+00

< 4.7E+00

< 2.2E+00

< 4.1E+00

< 2.4E+00

< 3.9E+00

< 1.1E+01

< 2.0E+00

< 1.8E+00

< 2.0E+01

< 7.3E+00 MW-114 2/14/2024 pCi/L

< 3.0E+00

< 3.2E+00

< 7.5E+00

< 3.6E+00

< 7.2E+00

< 4.1E+00

< 6.1E+00

< 1.1E+01

< 3.2E+00

< 3.0E+00

< 2.3E+01

< 7.9E+00 MW-114 6/19/2024 pCi/L

< 1.9E+00

< 2.0E+00

< 4.8E+00

< 2.2E+00

< 4.0E+00

< 2.2E+00

< 3.7E+00

< 1.0E+01

< 1.9E+00

< 1.7E+01

< 6.5E+00 MW-114 9/18/2024 pCi/L

< 4.5E+00

< 4.8E+00

< 1.1E+01

< 5.8E+00

< 8.9E+00

< 4.9E+00

< 8.6E+00

< 1.4E+01

< 5.0E+00

< 5.2E+00

< 2.6E+01

< 1.2E+01 MW-114 11/14/2024 pCi/L

< 1.9E+00

< 2.3E+00

< 4.9E+00

< 2.1E+00

< 4.5E+00

< 2.2E+00

< 4.0E+00

< 1.2E+01

< 2.2E+00

< 2.0E+00

< 2.0E+01

< 7.0E+00 MW-116 2/14/2024 pCi/L

< 4.6E+00

< 5.4E+00

< 1.2E+01

< 5.5E+00

< 9.9E+00

< 5.5E+00

< 9.1E+00

< 1.5E+01

< 5.4E+00

< 5.1E+00

< 3.4E+01

< 1.4E+01 MW-116 6/19/2024 pCi/L

< 2.1E+00

< 2.4E+00

< 5.5E+00

< 2.4E+00

< 4.6E+00

< 2.5E+00

< 4.2E+00

< 1.1E+01

< 2.4E+00

< 2.1E+00

< 2.1E+01

< 6.4E+00 MW-116 9/18/2024 pCi/L

< 5.2E+00

< 1.2E+01

< 6.0E+00

< 1.4E+01

< 6.0E+00

< 9.0E+00

< 1.4E+01

< 5.6E+00

< 5.2E+00

< 3.5E+01

< 1.3E+01 MW-116 11/14/2024 pCi/L

< 1.9E+00

< 2.1E+00

< 4.7E+00

< 2.2E+00

< 4.2E+00

< 2.5E+00

< 3.9E+00

< 1.3E+01

< 2.0E+00

< 2.1E+00

< 2.2E+01

< 9.2E+00 MW-118 2/14/2024 pCi/L

< 4.1E+00

< 4.7E+00

< 9.6E+00

< 5.2E+00

< 7.2E+00

< 3.8E+00

< 8.2E+00

< 1.3E+01

< 4.9E+00

< 3.8E+00

< 2.5E+01

< 9.4E+00 MW-118 6/19/2024 pCi/L

< 2.2E+00

< 2.3E+00

< 6.0E+00

< 2.3E+00

< 4.8E+00

< 2.6E+00

< 4.5E+00

< 1.2E+01

< 2.6E+00

< 2.2E+00

< 2.0E+01

< 7.2E+00 MW-118 9/18/2024 pCi/L

< 4.7E+00

< 1.1E+01

< 5.4E+00

< 1.0E+01

< 5.3E+00

< 8.4E+00

< 1.3E+01

< 4.7E+00

< 4.6E+00

< 3.2E+01

< 8.1E+00 MW-118 11/14/2024 pCi/L

< 1.7E+00

< 4.4E+00

< 1.7E+00

< 3.5E+00

< 1.9E+00

< 3.4E+00

< 1.2E+01

< 1.8E+00

< 1.6E+00

< 2.0E+01

< 7.0E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 58 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-120 6/19/2024 pCi/L

< 6.4E+00

< 8.9E+00

< 1.4E+01

< 8.5E+00

< 1.7E+01

< 7.7E+00

< 1.2E+01

< 1.4E+01

< 9.0E+00

< 8.3E+00

< 4.5E+01

< 1.3E+01 MW-120 11/13/2024 pCi/L

< 5.9E+00

< 6.3E+00

< 1.1E+01

< 7.3E+00

< 1.5E+01

< 7.1E+00

< 1.3E+01

< 7.0E+00

< 6.8E+00

< 3.1E+01

< 1.2E+01 MW-122 6/19/2024 pCi/L

< 4.4E+00

< 7.0E+00

< 1.2E+01

< 7.5E+00

< 1.2E+01

< 7.2E+00

< 1.2E+01

< 1.3E+01

< 5.8E+00

< 7.4E+00

< 3.4E+01

< 8.2E+00 MW-122 11/14/2024 pCi/L

< 7.4E+00

< 7.7E+00

< 1.6E+01

< 9.4E+00

< 2.0E+01

< 9.4E+00

< 1.2E+01

< 1.1E+01

< 7.6E+00

< 6.8E+00

< 3.8E+01

< 1.1E+01 MW-124 2/13/2024 pCi/L

< 2.1E+00

< 2.3E+00

< 4.8E+00

< 2.5E+00

< 4.5E+00

< 2.5E+00

< 4.0E+00

< 7.0E+00

< 2.1E+00

< 1.5E+01

< 5.3E+00 MW-124 2/13/2024 pCi/L

< 4.2E+00

< 4.9E+00

< 9.8E+00

< 4.9E+00

< 8.3E+00

< 5.0E+00

< 9.1E+00

< 1.5E+01

< 4.9E+00

< 4.4E+00

< 3.2E+01

< 1.2E+01 MW-124 6/18/2024 pCi/L

< 2.0E+00

< 2.3E+00

< 5.0E+00

< 2.2E+00

< 4.0E+00

< 2.4E+00

< 4.1E+00

< 8.2E+00

< 2.1E+00

< 1.7E+01

< 6.0E+00 MW-124 9/17/2024 pCi/L

< 6.1E+00

< 5.8E+00

< 1.2E+01

< 6.0E+00

< 1.0E+01

< 4.8E+00

< 9.9E+00

< 1.4E+01

< 5.6E+00

< 5.4E+00

< 3.7E+01

< 9.1E+00 MW-124 9/17/2024 pCi/L

< 4.1E+00

< 4.2E+00

< 1.1E+01

< 3.5E+00

< 1.1E+01

< 5.5E+00

< 7.0E+00

< 1.4E+01

< 4.0E+00

< 3.4E+00

< 2.9E+01

< 1.1E+01 MW-124 11/12/2024 pCi/L

< 1.2E+00

< 1.4E+00

< 3.1E+00

< 1.5E+00

< 2.7E+00

< 1.5E+00

< 2.4E+00

< 8.6E+00

< 1.3E+00

< 1.2E+00

< 1.3E+01

< 4.8E+00 MW-125 2/13/2024 pCi/L

< 4.1E+00

< 4.4E+00

< 1.0E+01

< 4.0E+00

< 8.3E+00

< 4.1E+00

< 7.3E+00

< 1.5E+01

< 4.8E+00

< 3.9E+00

< 2.8E+01

< 1.0E+01 MW-125 6/18/2024 pCi/L

< 1.7E+00

< 2.0E+00

< 4.5E+00

< 2.1E+00

< 3.8E+00

< 2.1E+00

< 3.4E+00

< 7.3E+00

< 2.1E+00

< 1.9E+00

< 1.5E+01

< 4.9E+00 MW-125 9/17/2024 pCi/L

< 4.5E+00

< 4.8E+00

< 1.2E+01

< 3.6E+00

< 9.6E+00

< 4.9E+00

< 8.0E+00

< 1.4E+01

< 5.2E+00

< 4.3E+00

< 3.1E+01

< 1.2E+01 MW-125 11/12/2024 pCi/L

< 1.8E+00

< 2.1E+00

< 5.3E+00

< 1.9E+00

< 4.0E+00

< 2.3E+00

< 3.8E+00

< 1.2E+01

< 2.2E+00

< 1.9E+00

< 2.1E+01

< 8.5E+00 MW-125 11/12/2024 pCi/L

< 1.8E+00

< 2.1E+00

< 4.5E+00

< 1.9E+00

< 4.2E+00

< 2.3E+00

< 3.9E+00

< 1.4E+01

< 2.0E+00

< 2.2E+01

< 7.1E+00 MW-126 2/13/2024 pCi/L

< 3.6E+00

< 3.8E+00

< 1.0E+01

< 4.0E+00

< 8.3E+00

< 5.1E+00

< 8.1E+00

< 1.3E+01

< 4.9E+00

< 4.0E+00

< 3.2E+01

< 9.1E+00 MW-126 2/13/2024 pCi/L

< 3.5E+00

< 4.0E+00

< 8.2E+00

< 3.6E+00

< 7.4E+00

< 3.9E+00

< 6.2E+00

< 1.4E+01

< 3.8E+00

< 3.7E+00

< 2.7E+01

< 8.0E+00 MW-126 6/19/2024 pCi/L

< 2.0E+00

< 2.2E+00

< 5.1E+00

< 2.0E+00

< 4.0E+00

< 2.2E+00

< 4.0E+00

< 9.4E+00

< 2.1E+00

< 2.0E+00

< 1.8E+01

< 6.0E+00 MW-126 9/17/2024 pCi/L

< 7.0E+00

< 6.7E+00

< 1.6E+01

< 1.0E+01

< 1.3E+01

< 8.1E+00

< 1.4E+01

< 1.2E+01

< 8.5E+00

< 7.6E+00

< 3.0E+01

< 1.1E+01

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 59 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-126 9/17/2024 pCi/L

< 5.8E+00

< 6.9E+00

< 1.4E+01

< 7.5E+00

< 1.4E+01

< 6.8E+00

< 1.0E+01

< 6.9E+00

< 5.7E+00

< 3.2E+01

< 1.4E+01 MW-126 11/14/2024 pCi/L

< 5.8E+00

< 7.6E+00

< 1.5E+01

< 7.6E+00

< 1.5E+01

< 7.4E+00

< 1.2E+01

< 1.4E+01

< 7.5E+00

< 7.0E+00

< 3.4E+01

< 1.2E+01 MW-128 6/19/2024 pCi/L

< 4.4E+00

< 5.4E+00

< 1.3E+01

< 6.5E+00

< 8.6E+00

< 4.8E+00

< 1.0E+01

< 1.2E+01

< 5.7E+00

< 5.1E+00

< 3.2E+01

< 1.3E+01 MW-128 11/13/2024 pCi/L

< 5.9E+00

< 6.3E+00

< 1.5E+01

< 1.0E+01

< 1.1E+01

< 6.5E+00

< 1.5E+01

< 1.3E+01

< 8.3E+00

< 5.5E+00

< 3.2E+01

< 1.4E+01 MW-130 6/19/2024 pCi/L

< 6.0E+00

< 5.2E+00

< 1.1E+01

< 6.6E+00

< 1.1E+01

< 5.6E+00

< 9.3E+00

< 1.1E+01

< 5.6E+00

< 5.8E+00

< 2.8E+01

< 1.0E+01 MW-130 11/14/2024 pCi/L

< 6.4E+00

< 8.5E+00

< 1.9E+01

< 1.1E+01

< 1.4E+01

< 9.7E+00

< 1.6E+01

< 1.4E+01

< 7.2E+00

< 1.1E+01

< 3.8E+01

< 1.3E+01 MW-131 6/19/2024 pCi/L

< 4.9E+00

< 6.4E+00

< 1.7E+01

< 7.4E+00

< 1.3E+01

< 6.3E+00

< 1.0E+01

< 1.4E+01

< 4.7E+00

< 5.1E+00

< 3.6E+01

< 1.4E+01 MW-131 11/14/2024 pCi/L

< 7.8E+00

< 7.4E+00

< 1.4E+01

< 9.0E+00

< 1.3E+01

< 9.4E+00

< 1.3E+01

< 1.1E+01

< 7.3E+00

< 6.0E+00

< 3.2E+01

< 1.2E+01 MW-132 6/19/2024 pCi/L

< 6.5E+00

< 7.7E+00

< 1.4E+01

< 6.2E+00

< 1.4E+01

< 8.1E+00

< 1.0E+01

< 1.4E+01

< 7.1E+00

< 7.3E+00

< 4.0E+01

< 1.3E+01 MW-132 6/19/2024 pCi/L

< 6.0E+00

< 1.6E+01

< 7.9E+00

< 1.4E+01

< 8.1E+00

< 1.3E+01

< 8.2E+00

< 5.9E+00

< 2.6E+01

< 1.2E+01 MW-132 11/14/2024 pCi/L

< 6.4E+00

< 5.6E+00

< 7.3E+00

< 5.4E+00

< 1.1E+01

< 6.1E+00

< 1.1E+01

< 8.5E+00

< 7.5E+00

< 4.4E+00

< 2.4E+01

< 1.4E+01 MW-134 6/20/2024 pCi/L

< 7.4E+00

< 6.3E+00

< 1.5E+01

< 7.2E+00

< 1.3E+01

< 7.6E+00

< 1.2E+01

< 1.5E+01

< 7.3E+00

< 6.7E+00

< 4.0E+01

< 1.1E+01 MW-134 11/14/2024 pCi/L

< 7.6E+00

< 7.9E+00

< 1.6E+01

< 8.3E+00

< 1.1E+01

< 7.3E+00

< 1.3E+01

< 8.5E+00

< 9.1E+00

< 4.2E+01

< 1.4E+01 MW-137 2/14/2024 pCi/L

< 3.4E+00

< 3.9E+00

< 9.0E+00

< 3.9E+00

< 8.0E+00

< 3.7E+00

< 6.6E+00

< 1.4E+01

< 3.9E+00

< 4.0E+00

< 2.7E+01

< 8.1E+00 MW-137 6/19/2024 pCi/L

< 2.0E+00

< 2.4E+00

< 5.4E+00

< 2.3E+00

< 4.4E+00

< 2.3E+00

< 4.3E+00

< 9.4E+00

< 2.3E+00

< 2.2E+00

< 2.0E+01

< 7.2E+00 MW-137 9/18/2024 pCi/L

< 5.3E+00

< 6.9E+00

< 1.6E+01

< 5.9E+00

< 1.2E+01

< 7.5E+00

< 1.2E+01

< 9.6E+00

< 6.4E+00

< 4.1E+00

< 2.6E+01

< 1.0E+01 MW-137 9/18/2024 pCi/L

< 7.3E+00

< 7.0E+00

< 1.5E+01

< 7.8E+00

< 1.6E+01

< 7.0E+00

< 1.5E+01

< 1.2E+01

< 7.6E+00

< 7.3E+00

< 2.9E+01

< 1.1E+01 MW-137 11/14/2024 pCi/L

< 1.7E+00

< 2.1E+00

< 4.7E+00

< 1.9E+00

< 3.7E+00

< 2.2E+00

< 3.6E+00

< 1.3E+01

< 1.9E+00

< 1.8E+00

< 2.0E+01

< 7.0E+00 MW-139 2/14/2024 pCi/L

< 6.5E+00

< 6.0E+00

< 2.0E+01

< 5.3E+00

< 1.4E+01

< 7.3E+00

< 9.8E+00

< 1.4E+01

< 9.2E+00

< 7.5E+00

< 4.2E+01

< 1.4E+01

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 60 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-139 6/19/2024 pCi/L

< 6.2E+00

< 7.9E+00

< 1.8E+01

< 8.3E+00

< 1.3E+01

< 7.1E+00

< 1.2E+01

< 1.4E+01

< 7.5E+00

< 9.0E+00

< 3.9E+01

< 1.1E+01 MW-139 9/18/2024 pCi/L

< 9.0E+00

< 8.3E+00

< 1.6E+01

< 5.9E+00

< 1.6E+01

< 7.2E+00

< 1.4E+01

< 1.1E+01

< 7.5E+00

< 8.1E+00

< 3.7E+01

< 1.2E+01 MW-139 11/14/2024 pCi/L

< 5.4E+00

< 4.6E+00

< 6.7E+00

< 6.4E+00

< 1.4E+01

< 5.9E+00

< 8.9E+00

< 1.2E+01

< 6.5E+00

< 5.1E+00

< 2.4E+01

< 8.3E+00 MW-14 11/12/2024 pCi/L

< 6.9E+00

< 5.6E+00

< 1.4E+01

< 6.2E+00

< 1.5E+01

< 7.8E+00

< 9.3E+00

< 1.3E+01

< 8.6E+00

< 7.3E+00

< 3.8E+01

< 1.3E+01 MW-141 2/14/2024 pCi/L

< 4.5E+00

< 5.1E+00

< 9.5E+00

< 5.2E+00

< 9.4E+00

< 4.5E+00

< 7.6E+00

< 1.4E+01

< 4.0E+00

< 3.6E+00

< 2.7E+01

< 1.2E+01 MW-141 6/19/2024 pCi/L

< 1.8E+00

< 1.9E+00

< 4.6E+00

< 2.0E+00

< 3.9E+00

< 2.0E+00

< 3.5E+00

< 9.8E+00

< 1.9E+00

< 1.7E+00

< 1.8E+01

< 6.2E+00 MW-141 9/18/2024 pCi/L

< 4.6E+00

< 4.7E+00

< 1.0E+01

< 5.3E+00

< 9.0E+00

< 5.8E+00

< 8.7E+00

< 1.5E+01

< 5.8E+00

< 5.2E+00

< 3.2E+01

< 1.3E+01 MW-141 11/14/2024 pCi/L

< 1.8E+00

< 2.1E+00

< 4.8E+00

< 2.2E+00

< 3.5E+00

< 2.3E+00

< 3.6E+00

< 1.5E+01

< 2.0E+00

< 2.2E+01

< 7.2E+00 MW-141 11/14/2024 pCi/L

< 1.9E+00

< 2.3E+00

< 5.1E+00

< 1.7E+00

< 4.0E+00

< 2.3E+00

< 4.2E+00

< 1.5E+01

< 2.1E+00

< 1.8E+00

< 2.4E+01

< 7.5E+00 MW-142 2/13/2024 pCi/L

< 4.4E+00

< 4.9E+00

< 9.5E+00

< 5.2E+00

< 1.1E+01

< 5.4E+00

< 9.5E+00

< 1.4E+01

< 6.7E+00

< 4.6E+00

< 2.9E+01

< 7.7E+00 MW-142 6/18/2024 pCi/L

< 2.0E+00

< 2.2E+00

< 5.3E+00

< 2.3E+00

< 4.2E+00

< 2.4E+00

< 4.0E+00

< 8.6E+00

< 2.3E+00

< 2.2E+00

< 1.7E+01

< 5.9E+00 MW-142 9/17/2024 pCi/L

< 2.0E+00

< 1.9E+00

< 4.7E+00

< 2.1E+00

< 4.4E+00

< 2.3E+00

< 3.9E+00

< 6.2E+00

< 2.1E+00

< 1.4E+01

< 5.1E+00 MW-142 11/12/2024 pCi/L

< 1.7E+00

< 1.9E+00

< 4.8E+00

< 1.8E+00

< 3.5E+00

< 2.2E+00

< 3.4E+00

< 1.2E+01

< 1.9E+00

< 1.7E+00

< 1.9E+01

< 6.8E+00 MW-144 2/13/2024 pCi/L

< 4.5E+00

< 4.6E+00

< 1.1E+01

< 4.3E+00

< 7.8E+00

< 5.1E+00

< 7.4E+00

< 1.4E+01

< 4.9E+00

< 3.9E+00

< 3.5E+01

< 1.1E+01 MW-144 6/18/2024 pCi/L

< 5.9E+00

< 5.2E+00

< 1.4E+01

< 5.2E+00

< 1.2E+01

< 5.4E+00

< 1.2E+01

< 1.1E+01

< 5.0E+00

< 6.1E+00

< 3.8E+01

< 1.2E+01 MW-144 9/17/2024 pCi/L

< 6.8E+00

< 5.6E+00

< 1.1E+01

< 7.3E+00

< 1.4E+01

< 5.2E+00

< 7.5E+00

< 1.1E+01

< 4.7E+00

< 6.8E+00

< 2.5E+01

< 8.1E+00 MW-144 11/12/2024 pCi/L

< 6.3E+00

< 6.5E+00

< 1.2E+01

< 7.1E+00

< 1.4E+01

< 5.3E+00

< 1.1E+01

< 1.4E+01

< 7.9E+00

< 6.6E+00

< 3.2E+01

< 9.3E+00 MW-146 2/13/2024 pCi/L

< 4.0E+00

< 4.3E+00

< 1.0E+01

< 4.9E+00

< 9.5E+00

< 4.9E+00

< 8.0E+00

< 1.5E+01

< 3.8E+00

< 4.3E+00

< 3.0E+01

< 1.1E+01 MW-146 6/18/2024 pCi/L

< 1.3E+00

< 1.6E+00

< 3.4E+00

< 1.4E+00

< 2.7E+00

< 1.5E+00

< 2.5E+00

< 7.0E+00

< 1.3E+00

< 1.2E+01

< 4.8E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 61 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-146 9/17/2024 pCi/L

< 3.8E+00

< 4.0E+00

< 8.3E+00

< 4.4E+00

< 7.7E+00

< 3.1E+00

< 7.0E+00

< 1.2E+01

< 4.6E+00

< 4.3E+00

< 2.8E+01

< 1.0E+01 MW-146 11/12/2024 pCi/L

< 1.6E+00

< 1.8E+00

< 4.1E+00

< 1.8E+00

< 3.3E+00

< 1.9E+00

< 3.3E+00

< 1.1E+01

< 1.8E+00

< 1.6E+00

< 1.9E+01

< 6.0E+00 MW-147 2/13/2024 pCi/L

< 4.0E+00

< 4.7E+00

< 9.4E+00

< 5.8E+00

< 8.2E+00

< 4.8E+00

< 6.9E+00

< 1.4E+01

< 4.8E+00

< 3.5E+00

< 3.2E+01

< 1.4E+01 MW-147 6/18/2024 pCi/L

< 1.7E+00

< 2.1E+00

< 4.3E+00

< 2.2E+00

< 3.6E+00

< 2.0E+00

< 3.2E+00

< 6.9E+00

< 2.1E+00

< 1.9E+00

< 1.6E+01

< 5.5E+00 MW-147 6/18/2024 pCi/L

< 2.3E+00

< 2.6E+00

< 5.7E+00

< 2.5E+00

< 4.8E+00

< 2.7E+00

< 4.5E+00

< 9.4E+00

< 2.6E+00

< 2.4E+00

< 1.9E+01

< 6.7E+00 MW-147 9/17/2024 pCi/L

< 2.5E+00

< 6.2E+00

< 2.3E+00

< 5.0E+00

< 2.3E+00

< 4.4E+00

< 7.5E+00

< 2.9E+00

< 2.5E+00

< 1.6E+01

< 5.7E+00 MW-147 11/12/2024 pCi/L

< 1.8E+00

< 2.1E+00

< 4.8E+00

< 2.1E+00

< 3.8E+00

< 2.1E+00

< 3.8E+00

< 1.4E+01

< 1.9E+00

< 2.1E+01

< 6.4E+00 MW-148 2/13/2024 pCi/L

< 4.7E+00

< 4.5E+00

< 1.2E+01

< 3.5E+00

< 8.7E+00

< 4.6E+00

< 8.6E+00

< 1.4E+01

< 5.9E+00

< 4.0E+00

< 3.2E+01

< 1.1E+01 MW-148 6/18/2024 pCi/L

< 6.1E+00

< 5.2E+00

< 1.3E+01

< 6.4E+00

< 1.3E+01

< 5.3E+00

< 1.2E+01

< 1.4E+01

< 7.0E+00

< 6.8E+00

< 2.6E+01

< 1.0E+01 MW-148 9/17/2024 pCi/L

< 4.9E+00

< 5.4E+00

< 1.2E+01

< 7.5E+00

< 1.5E+01

< 5.4E+00

< 1.1E+01

< 1.0E+01

< 5.7E+00

< 5.2E+00

< 2.5E+01

< 1.2E+01 MW-148 11/12/2024 pCi/L

< 6.2E+00

< 5.8E+00

< 1.2E+01

< 6.2E+00

< 1.1E+01

< 6.2E+00

< 1.1E+01

< 1.3E+01

< 6.3E+00

< 5.8E+00

< 3.2E+01

< 1.2E+01 MW-151 2/14/2024 pCi/L

< 5.3E+00

< 5.1E+00

< 1.6E+01

< 7.2E+00

< 1.5E+01

< 7.3E+00

< 9.5E+00

< 1.4E+01

< 7.0E+00

< 6.4E+00

< 4.0E+01

< 1.3E+01 MW-151 6/19/2024 pCi/L

< 6.1E+00

< 6.3E+00

< 1.1E+01

< 7.8E+00

< 1.4E+01

< 6.5E+00

< 1.3E+01

< 1.4E+01

< 6.4E+00

< 7.7E+00

< 3.8E+01

< 1.4E+01 MW-151 9/17/2024 pCi/L

< 7.2E+00

< 5.7E+00

< 1.4E+01

< 7.5E+00

< 1.3E+01

< 9.3E+00

< 1.3E+01

< 7.6E+00

< 9.5E+00

< 3.6E+01

< 8.2E+00 MW-151 11/13/2024 pCi/L

< 5.9E+00

< 6.7E+00

< 1.5E+01

< 8.2E+00

< 1.6E+01

< 6.1E+00

< 1.3E+01

< 7.8E+00

< 6.8E+00

< 3.7E+01

< 1.4E+01 MW-153 2/14/2024 pCi/L

< 3.9E+00

< 4.7E+00

< 1.0E+01

< 4.4E+00

< 7.6E+00

< 5.1E+00

< 9.8E+00

< 1.4E+01

< 4.3E+00

< 4.7E+00

< 2.9E+01

< 1.1E+01 MW-153 6/18/2024 pCi/L

< 2.3E+00

< 5.5E+00

< 2.4E+00

< 4.3E+00

< 2.7E+00

< 3.9E+00

< 8.4E+00

< 2.6E+00

< 2.2E+00

< 1.7E+01

< 6.9E+00 MW-153 9/18/2024 pCi/L

< 3.3E+00

< 3.4E+00

< 7.6E+00

< 3.3E+00

< 6.4E+00

< 3.7E+00

< 6.6E+00

< 9.8E+00

< 3.6E+00

< 3.2E+00

< 2.3E+01

< 6.8E+00 MW-153 11/14/2024 pCi/L

< 1.7E+00

< 1.9E+00

< 4.3E+00

< 1.8E+00

< 3.5E+00

< 2.0E+00

< 3.5E+00

< 1.0E+01

< 1.9E+00

< 1.8E+00

< 1.9E+01

< 6.4E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 62 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-155 2/13/2024 pCi/L

< 4.4E+00

< 8.0E+00

< 4.3E+00

< 8.3E+00

< 4.2E+00

< 8.2E+00

< 1.4E+01

< 4.4E+00

< 3.9E+00

< 3.2E+01

< 1.1E+01 MW-155 6/18/2024 pCi/L

< 1.6E+00

< 1.8E+00

< 4.7E+00

< 1.9E+00

< 3.2E+00

< 2.1E+00

< 3.9E+00

< 9.1E+00

< 1.8E+00

< 1.8E+01

< 5.8E+00 MW-155 9/17/2024 pCi/L

< 4.9E+00

< 5.6E+00

< 1.2E+01

< 4.6E+00

< 1.2E+01

< 5.6E+00

< 1.0E+01

< 1.5E+01

< 6.2E+00

< 5.8E+00

< 3.6E+01

< 1.2E+01 MW-155 11/12/2024 pCi/L

< 1.8E+00

< 1.9E+00

< 5.0E+00

< 1.8E+00

< 3.7E+00

< 2.2E+00

< 3.5E+00

< 1.1E+01

< 1.9E+00

< 1.6E+00

< 2.0E+01

< 6.3E+00 MW-156 2/13/2024 pCi/L

< 3.2E+00

< 3.4E+00

< 8.4E+00

< 3.3E+00

< 7.3E+00

< 4.0E+00

< 6.3E+00

< 1.3E+01

< 4.0E+00

< 3.8E+00

< 2.4E+01

< 9.8E+00 MW-156 2/13/2024 pCi/L

< 2.6E+00

< 3.0E+00

< 5.8E+00

< 3.2E+00

< 5.1E+00

< 3.1E+00

< 5.2E+00

< 8.7E+00

< 2.9E+00

< 2.7E+00

< 2.0E+01

< 6.3E+00 MW-156 6/19/2024 pCi/L

< 2.1E+00

< 2.3E+00

< 5.4E+00

< 2.2E+00

< 4.3E+00

< 2.4E+00

< 4.0E+00

< 1.0E+01

< 2.2E+00

< 2.1E+00

< 1.8E+01

< 6.4E+00 MW-156 9/17/2024 pCi/L

< 2.3E+00

< 2.6E+00

< 6.0E+00

< 2.7E+00

< 4.8E+00

< 2.3E+00

< 4.4E+00

< 7.3E+00

< 2.5E+00

< 2.4E+00

< 1.6E+01

< 5.3E+00 MW-156 11/12/2024 pCi/L

< 2.1E+00

< 2.2E+00

< 5.2E+00

< 2.1E+00

< 3.9E+00

< 2.5E+00

< 4.0E+00

< 1.4E+01

< 2.3E+00

< 2.0E+00

< 2.4E+01

< 7.7E+00 MW-157 2/13/2024 pCi/L

< 3.6E+00

< 4.0E+00

< 7.4E+00

< 4.5E+00

< 7.3E+00

< 3.2E+00

< 5.6E+00

< 1.2E+01

< 3.8E+00

< 3.7E+00

< 2.3E+01

< 9.2E+00 MW-157 6/19/2024 pCi/L

< 2.0E+00

< 2.2E+00

< 5.5E+00

< 2.2E+00

< 4.0E+00

< 2.3E+00

< 4.0E+00

< 1.0E+01

< 2.3E+00

< 2.2E+00

< 2.0E+01

< 6.6E+00 MW-157 9/17/2024 pCi/L

< 2.8E+00

< 6.3E+00

< 3.1E+00

< 5.1E+00

< 3.0E+00

< 4.9E+00

< 8.2E+00

< 3.1E+00

< 2.8E+00

< 1.9E+01

< 6.5E+00 MW-157 11/13/2024 pCi/L

< 1.1E+00

< 1.4E+00

< 3.4E+00

< 1.3E+00

< 2.6E+00

< 1.4E+00

< 2.4E+00

< 8.3E+00

< 1.3E+00

< 1.2E+00

< 1.3E+01

< 4.7E+00 MW-158 2/13/2024 pCi/L

< 2.0E+00

< 4.4E+00

< 2.2E+00

< 4.1E+00

< 2.3E+00

< 3.3E+00

< 7.6E+00

< 2.2E+00

< 2.0E+00

< 1.6E+01

< 4.6E+00 MW-158 6/18/2024 pCi/L

< 1.3E+00

< 1.6E+00

< 3.7E+00

< 1.6E+00

< 2.9E+00

< 1.5E+00

< 2.6E+00

< 5.9E+00

< 1.4E+00

< 1.1E+01

< 4.1E+00 MW-158 9/17/2024 pCi/L

< 4.4E+00

< 4.8E+00

< 1.1E+01

< 4.1E+00

< 1.1E+01

< 5.5E+00

< 8.8E+00

< 1.3E+01

< 5.4E+00

< 3.9E+00

< 3.2E+01

< 1.1E+01 MW-158 11/12/2024 pCi/L

< 1.3E+00

< 1.5E+00

< 3.6E+00

< 1.7E+00

< 3.0E+00

< 1.7E+00

< 2.7E+00

< 9.3E+00

< 1.5E+00

< 1.3E+00

< 1.6E+01

< 5.4E+00 MW-159 2/13/2024 pCi/L

< 2.2E+00

< 2.3E+00

< 5.3E+00

< 2.3E+00

< 4.2E+00

< 2.4E+00

< 4.1E+00

< 6.9E+00

< 2.3E+00

< 2.2E+00

< 1.5E+01

< 5.3E+00 MW-159 6/18/2024 pCi/L

< 2.2E+00

< 2.4E+00

< 5.3E+00

< 2.4E+00

< 4.4E+00

< 2.5E+00

< 4.3E+00

< 9.8E+00

< 2.4E+00

< 2.3E+00

< 1.8E+01

< 6.2E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 63 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-159 9/17/2024 pCi/L

< 4.5E+00

< 4.1E+00

< 9.8E+00

< 5.1E+00

< 8.9E+00

< 5.0E+00

< 8.8E+00

< 1.4E+01

< 5.0E+00

< 4.5E+00

< 3.0E+01

< 1.1E+01 MW-159 11/12/2024 pCi/L

< 2.0E+00

< 2.3E+00

< 5.2E+00

< 2.2E+00

< 4.2E+00

< 2.4E+00

< 4.6E+00

< 1.5E+01

< 2.2E+00

< 2.0E+00

< 2.4E+01

< 8.4E+00 MW-161 2/14/2024 pCi/L

< 4.7E+00

< 3.9E+00

< 9.8E+00

< 3.8E+00

< 9.0E+00

< 4.6E+00

< 7.7E+00

< 1.3E+01

< 4.3E+00

< 4.0E+00

< 3.0E+01

< 1.2E+01 MW-161 6/18/2024 pCi/L

< 2.1E+00

< 2.2E+00

< 5.2E+00

< 2.2E+00

< 4.2E+00

< 2.3E+00

< 4.0E+00

< 7.8E+00

< 2.2E+00

< 2.0E+00

< 1.7E+01

< 5.7E+00 MW-161 9/18/2024 pCi/L

< 5.4E+00

< 5.2E+00

< 1.0E+01

< 6.1E+00

< 1.1E+01

< 5.9E+00

< 9.3E+00

< 1.3E+01

< 5.1E+00

< 4.9E+00

< 3.1E+01

< 1.4E+01 MW-161 11/14/2024 pCi/L

< 1.8E+00

< 1.9E+00

< 4.5E+00

< 1.7E+00

< 4.0E+00

< 2.2E+00

< 3.8E+00

< 1.4E+01

< 2.0E+00

< 1.8E+00

< 2.2E+01

< 7.2E+00 MW-161 11/14/2024 pCi/L

< 1.5E+00

< 1.8E+00

< 4.0E+00

< 1.8E+00

< 3.5E+00

< 1.9E+00

< 3.3E+00

< 1.0E+01

< 1.7E+00

< 1.7E+01

< 5.8E+00 MW-162 2/13/2024 pCi/L

< 4.5E+00

< 4.3E+00

< 1.1E+01

< 4.9E+00

< 1.1E+01

< 5.2E+00

< 1.0E+01

< 1.4E+01

< 4.8E+00

< 4.9E+00

< 3.5E+01

< 1.1E+01 MW-162 6/18/2024 pCi/L

< 7.2E+00

< 6.8E+00

< 1.2E+01

< 7.1E+00

< 1.6E+01

< 6.5E+00

< 1.1E+01

< 1.5E+01

< 6.3E+00

< 5.9E+00

< 3.8E+01

< 9.9E+00 MW-162 9/17/2024 pCi/L

< 7.8E+00

< 1.5E+01

< 7.2E+00

< 2.0E+01

< 8.6E+00

< 1.4E+01

< 1.2E+01

< 7.3E+00

< 7.2E+00

< 4.2E+01

< 1.3E+01 MW-162 11/12/2024 pCi/L

< 4.5E+00

< 5.0E+00

< 1.1E+01

< 6.8E+00

< 1.1E+01

< 5.3E+00

< 1.1E+01

< 1.2E+01

< 5.1E+00

< 5.5E+00

< 3.1E+01

< 1.4E+01 MW-164 2/14/2024 pCi/L

< 5.4E+00

< 6.0E+00

< 1.4E+01

< 7.9E+00

< 1.1E+01

< 6.3E+00

< 1.2E+01

< 1.4E+01

< 8.4E+00

< 6.3E+00

< 4.3E+01

< 1.4E+01 MW-164 6/19/2024 pCi/L

< 5.8E+00

< 6.3E+00

< 1.1E+01

< 6.5E+00

< 1.1E+01

< 6.4E+00

< 8.9E+00

< 1.0E+01

< 7.2E+00

< 6.8E+00

< 3.7E+01

< 1.1E+01 MW-164 9/17/2024 pCi/L

< 8.8E+00

< 5.7E+00

< 1.8E+01

< 8.0E+00

< 1.9E+01

< 9.9E+00

< 1.4E+01

< 1.3E+01

< 5.7E+00

< 8.6E+00

< 3.5E+01

< 1.1E+01 MW-164 11/13/2024 pCi/L

< 7.8E+00

< 6.9E+00

< 1.4E+01

< 8.4E+00

< 1.4E+01

< 7.8E+00

< 1.2E+01

< 1.4E+01

< 6.7E+00

< 6.9E+00

< 3.5E+01

< 8.7E+00 MW-165 2/14/2024 pCi/L

< 4.6E+00

< 4.4E+00

< 1.0E+01

< 5.2E+00

< 1.0E+01

< 4.7E+00

< 8.8E+00

< 1.4E+01

< 5.0E+00

< 4.6E+00

< 2.9E+01

< 7.8E+00 MW-165 6/19/2024 pCi/L

< 7.2E+00

< 5.7E+00

< 9.9E+00

< 7.2E+00

< 1.8E+01

< 5.9E+00

< 1.0E+01

< 1.3E+01

< 6.1E+00

< 8.3E+00

< 3.8E+01

< 1.3E+01 MW-165 9/17/2024 pCi/L

< 5.6E+00

< 5.0E+00

< 1.2E+01

< 6.4E+00

< 1.3E+01

< 6.2E+00

< 9.7E+00

< 1.1E+01

< 7.2E+00

< 6.1E+00

< 3.0E+01

< 1.2E+01 MW-165 11/13/2024 pCi/L

< 6.8E+00

< 6.2E+00

< 1.6E+01

< 9.6E+00

< 1.3E+01

< 7.4E+00

< 1.1E+01

< 7.5E+00

< 6.9E+00

< 3.6E+01

< 1.4E+01

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 64 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-167 6/19/2024 pCi/L

< 4.9E+00

< 4.5E+00

< 1.1E+01

< 4.5E+00

< 9.9E+00

< 6.2E+00

< 9.6E+00

< 1.3E+01

< 5.2E+00

< 4.6E+00

< 3.0E+01

< 9.1E+00 MW-167 11/14/2024 pCi/L

< 8.6E+00

< 5.6E+00

< 1.5E+01

< 7.5E+00

< 1.9E+01

< 6.1E+00

< 1.2E+01

< 5.6E+00

< 8.9E+00

< 3.3E+01

< 1.4E+01 MW-169 6/20/2024 pCi/L

< 5.2E+00

< 4.8E+00

< 8.5E+00

< 5.6E+00

< 1.2E+01

< 6.2E+00

< 9.1E+00

< 1.2E+01

< 4.9E+00

< 4.6E+00

< 3.0E+01

< 1.1E+01 MW-169 11/14/2024 pCi/L

< 7.8E+00

< 8.3E+00

< 1.3E+01

< 6.1E+00

< 1.8E+01

< 9.5E+00

< 1.5E+01

< 1.3E+01

< 7.8E+00

< 6.9E+00

< 3.7E+01

< 1.3E+01 MW-170 2/14/2024 pCi/L

< 5.3E+00

< 5.1E+00

< 1.2E+01

< 6.5E+00

< 1.1E+01

< 7.7E+00

< 1.0E+01

< 1.4E+01

< 6.2E+00

< 4.6E+00

< 3.1E+01

< 9.5E+00 MW-170 6/19/2024 pCi/L

< 5.8E+00

< 7.5E+00

< 1.7E+01

< 8.3E+00

< 1.7E+01

< 7.6E+00

< 1.4E+01

< 7.1E+00

< 7.0E+00

< 3.9E+01

< 1.4E+01 MW-170 9/18/2024 pCi/L

< 7.4E+00

< 8.8E+00

< 1.9E+01

< 9.7E+00

< 1.5E+01

< 6.5E+00

< 1.3E+01

< 1.2E+01

< 5.5E+00

< 8.8E+00

< 3.2E+01

< 1.1E+01 MW-170 11/12/2024 pCi/L

< 6.9E+00

< 6.8E+00

< 1.4E+01

< 7.6E+00

< 1.6E+01

< 6.8E+00

< 1.1E+01

< 1.3E+01

< 7.4E+00

< 6.1E+00

< 3.4E+01

< 1.1E+01 MW-172 11/14/2024 pCi/L

< 8.3E+00

< 7.9E+00

< 2.1E+01

< 9.9E+00

< 1.3E+01

< 1.0E+01

< 1.3E+01

< 1.4E+01

< 8.5E+00

< 9.7E+00

< 3.9E+01

< 1.2E+01 MW-174 11/12/2024 pCi/L

< 7.1E+00

< 4.4E+00

< 1.3E+01

< 4.9E+00

< 8.7E+00

< 4.4E+00

< 9.8E+00

< 1.0E+01

< 4.6E+00

< 5.5E+00

< 2.6E+01

< 8.4E+00 MW-178 2/14/2024 pCi/L

< 3.7E+00

< 4.4E+00

< 7.7E+00

< 3.8E+00

< 7.7E+00

< 4.4E+00

< 8.1E+00

< 1.4E+01

< 4.3E+00

< 4.1E+00

< 3.0E+01

< 7.8E+00 MW-178 6/19/2024 pCi/L

< 1.9E+00

< 2.1E+00

< 4.9E+00

< 2.0E+00

< 3.8E+00

< 2.0E+00

< 3.8E+00

< 9.2E+00

< 2.0E+00

< 1.9E+00

< 1.6E+01

< 6.4E+00 MW-178 6/19/2024 pCi/L

< 1.7E+00

< 1.9E+00

< 4.7E+00

< 1.8E+00

< 3.7E+00

< 2.0E+00

< 3.4E+00

< 9.4E+00

< 1.9E+00

< 1.8E+00

< 1.6E+01

< 5.6E+00 MW-178 9/17/2024 pCi/L

< 2.7E+00

< 2.8E+00

< 6.0E+00

< 2.9E+00

< 5.8E+00

< 2.9E+00

< 4.5E+00

< 8.1E+00

< 2.8E+00

< 2.6E+00

< 1.7E+01

< 5.8E+00 MW-178 11/14/2024 pCi/L

< 1.9E+00

< 2.3E+00

< 5.0E+00

< 2.0E+00

< 4.3E+00

< 2.4E+00

< 4.2E+00

< 1.3E+01

< 2.2E+00

< 2.1E+00

< 2.3E+01

< 7.5E+00 MW-178 11/14/2024 pCi/L

< 1.8E+00

< 2.1E+00

< 4.6E+00

< 1.8E+00

< 4.1E+00

< 2.2E+00

< 3.9E+00

< 1.3E+01

< 1.9E+00

< 1.8E+00

< 2.1E+01

< 6.4E+00 MW-179 2/14/2024 pCi/L

< 4.2E+00

< 5.6E+00

< 1.1E+01

< 4.3E+00

< 8.7E+00

< 4.8E+00

< 8.8E+00

< 1.4E+01

< 5.1E+00

< 5.0E+00

< 3.1E+01

< 9.8E+00 MW-179 6/19/2024 pCi/L

< 1.9E+00

< 2.1E+00

< 4.7E+00

< 2.0E+00

< 3.9E+00

< 2.2E+00

< 3.9E+00

< 1.0E+01

< 2.0E+00

< 1.9E+01

< 6.4E+00 MW-179 9/17/2024 pCi/L

< 2.4E+00

< 5.9E+00

< 2.6E+00

< 5.0E+00

< 2.6E+00

< 4.5E+00

< 7.7E+00

< 2.6E+00

< 2.3E+00

< 1.6E+01

< 6.7E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 65 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-179 11/14/2024 pCi/L

< 2.4E+00

< 2.5E+00

< 5.3E+00

< 2.4E+00

< 4.8E+00

< 2.8E+00

< 4.7E+00

< 1.4E+01

< 2.4E+00

< 2.3E+00

< 2.5E+01

< 7.7E+00 MW-180 6/19/2024 pCi/L

< 4.0E+00

< 4.7E+00

< 1.1E+01

< 6.1E+00

< 1.1E+01

< 4.6E+00

< 8.4E+00

< 1.3E+01

< 4.9E+00

< 5.1E+00

< 2.3E+01

< 1.0E+01 MW-180 11/14/2024 pCi/L

< 6.1E+00

< 5.6E+00

< 1.2E+01

< 7.1E+00

< 1.2E+01

< 7.0E+00

< 1.0E+01

< 1.1E+01

< 6.5E+00

< 5.6E+00

< 2.7E+01

< 1.1E+01 MW-182 2/14/2024 pCi/L

< 7.4E+00

< 6.7E+00

< 9.1E+00

< 6.8E+00

< 1.1E+01

< 6.5E+00

< 1.2E+01

< 1.3E+01

< 5.8E+00

< 6.1E+00

< 3.1E+01

< 1.4E+01 MW-182 6/19/2024 pCi/L

< 7.8E+00

< 8.4E+00

< 1.1E+01

< 8.4E+00

< 1.6E+01

< 7.3E+00

< 1.6E+01

< 1.4E+01

< 8.7E+00

< 4.9E+00

< 2.9E+01

< 6.9E+00 MW-182 6/19/2024 pCi/L

< 7.6E+00

< 7.8E+00

< 1.5E+01

< 8.4E+00

< 1.4E+01

< 7.3E+00

< 1.3E+01

< 1.5E+01

< 8.0E+00

< 7.4E+00

< 3.3E+01

< 1.4E+01 MW-182 9/18/2024 pCi/L

< 4.7E+00

< 7.1E+00

< 1.5E+01

< 1.0E+01

< 1.4E+01

< 9.6E+00

< 1.4E+01

< 1.2E+01

< 9.3E+00

< 7.0E+00

< 3.6E+01

< 1.4E+01 MW-182 9/18/2024 pCi/L

< 6.4E+00

< 7.1E+00

< 1.1E+01

< 6.5E+00

< 1.4E+01

< 7.4E+00

< 1.2E+01

< 1.1E+01

< 5.5E+00

< 7.4E+00

< 3.3E+01

< 1.0E+01 MW-182 11/12/2024 pCi/L

< 7.4E+00

< 5.9E+00

< 1.3E+01

< 6.5E+00

< 1.4E+01

< 8.0E+00

< 1.1E+01

< 1.5E+01

< 7.4E+00

< 6.0E+00

< 3.4E+01

< 9.9E+00 MW-182 11/12/2024 pCi/L

< 5.4E+00

< 1.1E+01

< 7.1E+00

< 1.3E+01

< 7.7E+00

< 1.1E+01

< 5.4E+00

< 5.9E+00

< 3.2E+01

< 1.2E+01 MW-185 2/13/2024 pCi/L

< 4.4E+00

< 5.0E+00

< 1.1E+01

< 5.3E+00

< 1.1E+01

< 5.7E+00

< 7.7E+00

< 1.5E+01

< 4.6E+00

< 5.2E+00

< 3.2E+01

< 1.0E+01 MW-185 2/13/2024 pCi/L

< 5.4E+00

< 6.1E+00

< 1.0E+01

< 5.3E+00

< 1.4E+01

< 6.4E+00

< 9.5E+00

< 1.5E+01

< 6.5E+00

< 5.6E+00

< 3.2E+01

< 1.2E+01 MW-185 6/18/2024 pCi/L

< 6.2E+00

< 4.8E+00

< 9.4E+00

< 1.3E+01

< 6.9E+00

< 1.2E+01

< 1.4E+01

< 7.5E+00

< 5.7E+00

< 3.0E+01

< 1.3E+01 MW-185 9/17/2024 pCi/L

< 6.3E+00

< 5.9E+00

< 1.5E+01

< 1.0E+01

< 1.4E+01

< 6.1E+00

< 1.2E+01

< 9.9E+00

< 8.3E+00

< 7.2E+00

< 3.0E+01

< 1.0E+01 MW-185 11/12/2024 pCi/L

< 6.5E+00

< 6.7E+00

< 1.3E+01

< 6.7E+00

< 9.6E+00

< 5.9E+00

< 8.9E+00

< 1.2E+01

< 6.6E+00

< 6.3E+00

< 2.9E+01

< 1.1E+01 MW-186 2/14/2024 pCi/L

< 4.6E+00

< 5.2E+00

< 1.1E+01

< 4.9E+00

< 9.1E+00

< 5.2E+00

< 9.2E+00

< 1.5E+01

< 5.7E+00

< 4.7E+00

< 3.1E+01

< 1.1E+01 MW-186 6/19/2024 pCi/L

< 6.5E+00

< 6.6E+00

< 1.3E+01

< 9.0E+00

< 1.7E+01

< 5.2E+00

< 1.1E+01

< 1.3E+01

< 7.0E+00

< 5.0E+00

< 3.7E+01

< 8.8E+00 MW-186 9/17/2024 pCi/L

< 9.1E+00

< 7.7E+00

< 1.8E+01

< 1.1E+01

< 1.7E+01

< 7.3E+00

< 1.5E+01

< 1.3E+01

< 9.9E+00

< 7.7E+00

< 4.6E+01

< 1.4E+01 MW-186 11/13/2024 pCi/L

< 6.3E+00

< 7.2E+00

< 1.2E+01

< 7.2E+00

< 1.4E+01

< 8.6E+00

< 1.2E+01

< 8.7E+00

< 8.2E+00

< 3.8E+01

< 8.5E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 66 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-187 2/14/2024 pCi/L

< 4.8E+00

< 5.2E+00

< 9.6E+00

< 4.8E+00

< 8.8E+00

< 5.4E+00

< 8.9E+00

< 1.4E+01

< 5.4E+00

< 5.5E+00

< 3.5E+01

< 9.7E+00 MW-187 6/19/2024 pCi/L

< 3.0E+00

< 3.5E+00

< 7.3E+00

< 4.0E+00

< 7.2E+00

< 3.7E+00

< 5.9E+00

< 7.5E+00

< 3.9E+00

< 3.7E+00

< 1.7E+01

< 5.3E+00 MW-187 9/17/2024 pCi/L

< 7.5E+00

< 6.8E+00

< 1.5E+01

< 7.5E+00

< 1.8E+01

< 8.3E+00

< 1.3E+01

< 1.2E+01

< 9.7E+00

< 8.2E+00

< 3.7E+01

< 1.2E+01 MW-187 11/13/2024 pCi/L

< 6.5E+00

< 7.2E+00

< 1.4E+01

< 6.7E+00

< 1.7E+01

< 6.8E+00

< 9.5E+00

< 1.1E+01

< 6.5E+00

< 6.6E+00

< 3.0E+01

< 8.1E+00 MW-188 2/13/2024 pCi/L

< 4.5E+00

< 4.9E+00

< 1.2E+01

< 4.6E+00

< 9.9E+00

< 5.4E+00

< 9.5E+00

< 1.4E+01

< 4.7E+00

< 4.BE+00

< 3.1E+01

< 1.0E+01 MW-188 6/18/2024 pCi/L

< 5.5E+00

< 7.4E+00

< 1.0E+01

< 7.3E+00

< 1.0E+01

< 7.4E+00

< 1.2E+01

< 1.4E+01

< 5.5E+00

< 5.9E+00

< 3.8E+01

< 1.5E+01 MW-188 6/18/2024 pCi/L

< 6.1E+00

< 5.5E+00

< 1.4E+01

< 5.9E+00

< 1.1E+01

< 5.4E+00

< 1.1E+01

< 1.4E+01

< 7.0E+00

< 5.BE+00

< 2.9E+01

< 1.4E+01 MW-188 9/17/2024 pCi/L

< 6.9E+00

< 7.1E+00

< 1.5E+01

< 7.1E+00

< 1.2E+01

< 6.5E+00

< 1.5E+01

< 1.4E+01

< 7.6E+00

< 6.7E+00

< 3.6E+01

< 1.2E+01 MW-188 11/12/2024 pCi/L

< 5.6E+00

< 6.7E+00

< 1.4E+01

< 6.5E+00

< 1.6E+01

< 8.5E+00

< 1.3E+01

< 8.2E+00

< 5.9E+00

< 3.3E+01

< 1.3E+01 MW-201 6/19/2024 pCi/L

< 6.6E+00

< 6.4E+00

< 1.4E+01

< 7.3E+00

< 1.1E+01

< 7.0E+00

< 9.6E+00

< 1.4E+01

< 7.BE+00

< 7.9E+00

< 4.3E+01

< 1.3E+01 MW-201 11/13/2024 pCi/L

< 7.9E+00

< 7.0E+00

< 1.5E+01

< 7.6E+00

< 1.4E+01

< 7.3E+00

< 1.2E+01

< 1.4E+01

< 7.0E+00

< 7.9E+00

< 3.6E+01

< 1.3E+01 MW-205 6/18/2024 pCi/L

< 2.5E+00

< 2.7E+00

< 6.1E+00

< 2.8E+00

< 5.1E+00

< 2.7E+00

< 4.9E+00

< 7.4E+00

< 3.0E+00

< 2.6E+00

< 1.6E+01

< 5.6E+00 MW-205 11/12/2024 pCi/L

< 5.3E+00

< 6.0E+00

< 1.5E+01

< 4.7E+00

< 1.1E+01

< 6.4E+00

< 8.6E+00

< 1.2E+01

< 7.3E+00

< 6.6E+00

< 2.7E+01

< 1.1E+01 MW-207 6/18/2024 pCi/L

< 4.6E+00

< 5.5E+00

< 9.6E+00

< 4.9E+00

< 1.1E+01

< 4.3E+00

< 8.6E+00

< 9.8E+00

< 5.1E+00

< 5.9E+00

< 2.5E+01

< 8.6E+00 MW-207 11/14/2024 pCi/L

< 6.5E+00

< 6.1E+00

< 1.8E+01

< 9.BE+00

< 1.7E+01

< 7.0E+00

< 1.6E+01

< 1.3E+01

< 9.6E+00

< 1.1E+01

< 4.2E+01

< 1.2E+01 MW-209 2/14/2024 pCi/L

< 4.7E+00

< 4.9E+00

< 1.4E+01

< 5.0E+00

< 7.BE+00

< 6.0E+00

< 1.1E+01

< 1.4E+01

< 4.BE+00

< 5.6E+00

< 3.0E+01

< 1.2E+01 MW-209 2/14/2024 pCi/L

< 6.0E+00

< 5.2E+00

< 1.1E+01

< 5.4E+00

< 8.5E+00

< 5.5E+00

< 1.1E+01

< 1.4E+01

< 5.4E+00

< 5.5E+00

< 3.4E+01

< 1.2E+01 MW-209 6/19/2024 pCi/L

< 7.0E+00

< 6.5E+00

< 1.4E+01

< 6.4E+00

< 1.3E+01

< 7.1E+00

< 1.1E+01

< 1.4E+01

< 6.1E+00

< 7.0E+00

< 4.0E+01

< 1.2E+01 MW-209 6/19/2024 pCi/L

< 3.3E+00

< 3.5E+00

< 8.1E+00

< 4.0E+00

< 7.3E+00

< 4.2E+00

< 6.6E+00

< 8.4E+00

< 4.2E+00

< 3.7E+00

< 2.1E+01

< 6.1E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 67 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-209 9/18/2024 pCi/L

< 7.7E+00

< 6.7E+00

< 1.5E+01

< 1.0E+01

< 1.5E+01

< 6.5E+00

< 1.2E+01

< 7.4E+00

< 8.5E+00

< 3.4E+01

< 9.7E+00 MW-209 11/14/2024 pCi/L

< 6.9E+00

< 7.0E+00

< 1.2E+01

< 6.9E+00

< 1.4E+01

< 8.2E+00

< 1.3E+01

< 6.7E+00

< 6.8E+00

< 4.1E+01

< 1.2E+01 MW-211 2/13/2024 pCi/L

< 3.6E+00

< 3.3E+00

< 8.2E+00

< 3.6E+00

< 7.3E+00

< 3.9E+00

< 5.7E+00

< 1.2E+01

< 3.8E+00

< 3.9E+00

< 2.7E+01

< 7.1E+00 MW-211 6/19/2024 pCi/L

< 5.4E+00

< 5.1E+00

< 1.4E+01

< 5.1E+00

< 1.2E+01

< 5.1E+00

< 1.0E+01

< 1.3E+01

< 6.3E+00

< 4.4E+00

< 2.9E+01

< 1.0E+01 MW-211 9/17/2024 pCi/L

< 8.1E+00

< 7.8E+00

< 1.3E+01

< 6.4E+00

< 1.5E+01

< 6.8E+00

< 1.2E+01

< 8.5E+00

< 7.1E+00

< 3.2E+01

< 1.1E+01 MW-211 11/13/2024 pCi/L

< 5.9E+00

< 6.8E+00

< 1.3E+01

< 5.8E+00

< 1.3E+01

< 5.8E+00

< 1.1E+01

< 1.2E+01

< 5.4E+00

< 6.1E+00

< 3.6E+01

< 1.1E+01 MW-213 6/19/2024 pCi/L

< 5.2E+00

< 5.8E+00

< 7.1E+00

< 6.3E+00

< 1.0E+01

< 5.6E+00

< 7.9E+00

< 1.3E+01

< 5.8E+00

< 5.9E+00

< 3.5E+01

< 1.2E+01 MW-213 11/13/2024 pCi/L

< 6.4E+00

< 6.0E+00

< 1.8E+01

< 8.4E+00

< 1.2E+01

< 7.5E+00

< 8.8E+00

< 1.4E+01

< 7.5E+00

< 7.1E+00

< 4.0E+01

< 9.5E+00 MW-215 6/19/2024 pCi/L

< 4.9E+00

< 4.5E+00

< 1.2E+01

< 4.4E+00

< 1.0E+01

< 5.1E+00

< 9.1E+00

< 1.2E+01

< 5.0E+00

< 5.2E+00

< 2.8E+01

< 1.0E+01 MW-215 11/14/2024 pCi/L

< 6.8E+00

< 7.8E+00

< 1.2E+01

< 8.9E+00

< 1.8E+01

< 7.6E+00

< 1.4E+01

< 7.5E+00

< 8.1E+00

< 3.5E+01

< 7.1E+00 MW-217 6/19/2024 pCi/L

< 3.5E+00

< 4.9E+00

< 9.8E+00

< 4.9E+00

< 8.1E+00

< 4.1E+00

< 8.4E+00

< 1.2E+01

< 4.3E+00

< 2.9E+01

< 1.1E+01 MW-217 11/14/2024 pCi/L

< 4.3E+00

< 4.8E+00

< 1.2E+01

< 6.9E+00

< 1.2E+01

< 5.3E+00

< 9.3E+00

< 7.6E+00

< 5.2E+00

< 6.2E+00

< 2.1E+01

< 1.0E+01 MW-219 6/19/2024 pCi/L

< 6.3E+00

< 6.6E+00

< 1.2E+01

< 7.3E+00

< 1.2E+01

< 6.0E+00

< 1.1E+01

< 1.3E+01

< 6.4E+00

< 7.7E+00

< 2.9E+01

< 1.4E+01 MW-219 11/14/2024 pCi/L

< 7.9E+00

< 8.2E+00

< 1.8E+01

< 6.7E+00

< 1.5E+01

< 7.7E+00

< 1.1E+01

< 1.4E+01

< 7.2E+00

< 3.5E+01

< 1.2E+01 MW-221 2/14/2024 pCi/L

< 6.0E+00

< 5.7E+00

< 1.4E+01

< 6.3E+00

< 1.2E+01

< 5.9E+00

< 1.1E+01

< 1.4E+01

< 6.8E+00

< 5.3E+00

< 3.4E+01

< 1.4E+01 MW-221 6/19/2024 pCi/L

< 3.9E+00

< 4.2E+00

< 8.4E+00

< 5.0E+00

< 7.7E+00

< 4.1E+00

< 6.0E+00

< 7.2E+00

< 4.3E+00

< 3.7E+00

< 1.9E+01

< 5.9E+00 MW-221 9/18/2024 pCi/L

< 5.9E+00

< 6.2E+00

< 1.3E+01

< 7.9E+00

< 1.6E+01

< 7.0E+00

< 1.0E+01

< 1.1E+01

< 7.2E+00

< 6.4E+00

< 2.8E+01

< 1.2E+01 MW-221 11/12/2024 pCi/L

< 7.2E+00

< 6.5E+00

< 1.5E+01

< 7.0E+00

< 1.4E+01

< 9.0E+00

< 1.4E+01

< 7.7E+00

< 7.2E+00

< 3.5E+01

< 1.1E+01 MW-223 2/14/2024 pCi/L

< 5.2E+00

< 6.0E+00

< 1.3E+01

< 6.5E+00

< 1.3E+01

< 6.0E+00

< 8.9E+00

< 1.4E+01

< 5.3E+00

< 5.5E+00

< 3.0E+01

< 9.9E+00

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 68 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-223 6/19/2024 pCi/L

< 6.9E+00

< 6.7E+00

< 1.4E+01

< 6.1E+00

< 1.4E+01

< 7.1E+00

< 1.1E+01

< 1.4E+01

< 6.8E+00

< 7.1E+00

< 3.5E+01

< 1.5E+01 MW-223 9/18/2024 pCi/L

< 6.8E+00

< 6.4E+00

< 1.3E+01

< 7.2E+00

< 1.8E+01

< 7.8E+00

< 1.3E+01

< 1.0E+01

< 7.3E+00

< 7.7E+00

< 2.9E+01

< 1.0E+01 MW-223 11/14/2024 pCi/L

< 6.7E+00

< 7.1E+00

< 1.8E+01

< 9.6E+00

< 1.5E+01

< 9.3E+00

< 1.5E+01

< 1.3E+01

< 7.8E+00

< 9.2E+00

< 3.9E+01

< 1.3E+01 MW-225 6/19/2024 pCi/L

< 8.3E+00

< 7.9E+00

< 1.8E+01

< 7.1E+00

< 1.3E+01

< 7.5E+00

< 1.1E+01

< 1.5E+01

< 8.6E+00

< 6.8E+00

< 3.6E+01

< 1.1E+01 MW-225 11/14/2024 pCi/L

< 4.8E+00

< 6.3E+00

< 1.0E+01

< 7.9E+00

< 1.6E+01

< 7.5E+00

< 1.0E+01

< 9.4E+00

< 6.5E+00

< 7.3E+00

< 2.7E+01

< 1.1E+01 MW-227 6/18/2024 pCi/L

< 2.4E+00

< 2.7E+00

< 5.9E+00

< 2.8E+00

< 5.2E+00

< 2.8E+00

< 4.8E+00

< 8.2E+00

< 2.7E+00

< 1.7E+01

< 5.1E+00 MW-227 11/12/2024 pCi/L

< 6.2E+00

< 6.8E+00

< 1.4E+01

< 5.8E+00

< 1.2E+01

< 6.6E+00

< 1.1E+01

< 1.2E+01

< 6.9E+00

< 5.1E+00

< 2.6E+01

< 8.5E+00 MW-229 6/19/2024 pCi/L

< 5.3E+00

< 5.5E+00

< 1.2E+01

< 7.4E+00

< 1.1E+01

< 7.1E+00

< 1.0E+01

< 1.1E+01

< 4.3E+00

< 5.4E+00

< 2.5E+01

< 9.1E+00 MW-229 11/14/2024 pCi/L

< 6.2E+00

< 7.1E+00

< 1.5E+01

< 8.3E+00

< 1.4E+01

< 6.8E+00

< 1.4E+01

< 1.3E+01

< 6.9E+00

< 7.1E+00

< 3.8E+01

< 1.1E+01 MW-231 6/19/2024 pCi/L

< 7.4E+00

< 7.3E+00

< 1.7E+01

< 7.1E+00

< 1.7E+01

< 8.6E+00

< 1.2E+01

< 1.4E+01

< 7.4E+00

< 6.1E+00

< 3.7E+01

< 1.3E+01 MW-231 11/14/2024 pCi/L

< 3.3E+00

< 7.4E+00

< 1.7E+01

< 8.1E+00

< 1.2E+01

< 8.3E+00

< 1.1E+01

< 9.6E+00

< 6.6E+00

< 5.3E+00

< 3.1E+01

< 1.0E+01 MW-233 6/19/2024 pCi/L

< 7.6E+00

< 9.5E+00

< 1.6E+01

< 9.5E+00

< 1.1E+01

< 6.7E+00

< 1.3E+01

< 1.2E+01

< 9.8E+00

< 7.2E+00

< 4.5E+01

< 1.0E+01 MW-233 11/13/2024 pCi/L

< 7.1E+00

< 7.8E+00

< 1.4E+01

< 7.9E+00

< 1.4E+01

< 7.1E+00

< 1.1E+01

< 1.2E+01

< 7.3E+00

< 6.8E+00

< 3.6E+01

< 6.8E+00 MW-235 6/19/2024 pCi/L

< 3.7E+00

< 8.3E+00

< 3.4E+00

< 7.8E+00

< 3.7E+00

< 6.5E+00

< 7.2E+00

< 3.8E+00

< 1.8E+01

< 6.7E+00 MW-235 11/12/2024 pCi/L

< 6.4E+00

< 5.8E+00

< 1.2E+01

< 4.9E+00

< 1.5E+01

< 6.3E+00

< 1.4E+01

< 1.2E+01

< 6.2E+00

< 6.4E+00

< 3.4E+01

< 1.1E+01 PZ-01 2/14/2024 pCi/L

< 4.4E+00

< 5.0E+00

< 1.1E+01

< 4.3E+00

< 7.4E+00

< 4.7E+00

< 8.2E+00

< 1.4E+01

< 4.6E+00

< 4.7E+00

< 3.3E+01

< 1.0E+01 PZ-01 6/18/2024 pCi/L

< 1.5E+00

< 1.8E+00

< 4.0E+00

< 1.6E+00

< 3.1E+00

< 1.9E+00

< 3.3E+00

< 9.3E+00

< 1.7E+00

< 1.6E+01

< 5.4E+00 PZ-01 6/18/2024 pCi/L

< 1.2E+00

< 1.3E+00

< 3.0E+00

< 1.2E+00

< 2.6E+00

< 1.3E+00

< 2.3E+00

< 7.2E+00

< 1.3E+00

< 1.2E+00

< 1.2E+01

< 4.4E+00 PZ-01 9/18/2024 pCi/L

< 5.6E+00

< 5.3E+00

< 1.1E+01

< 6.2E+00

< 1.0E+01

< 6.6E+00

< 1.0E+01

< 1.4E+01

< 5.2E+00

< 3.6E+01

< 1.1E+01

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 69 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 33, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 PZ-01 11/14/2024 pCi/L

< 1.9E+00

< 2.3E+00

< 5.0E+00

< 2.3E+00

< 4.1E+00

< 2.4E+00

< 4.0E+00

< 1.3E+01

< 2.2E+00

< 2.2E+01

< 6.8E+00 PZ-03 6/19/2024 pCi/L

< 7.1E+00

< 7.6E+00

< 1.7E+01

< 6.1E+00

< 1.7E+01

< 7.0E+00

< 1.5E+01

< 8.9E+00

< 7.2E+00

< 4.4E+01

< 1.2E+01 PZ-03 11/14/2024 pCi/L

< 8.1E+00

< 7.2E+00

< 1.6E+01

< 8.3E+00

< 1.7E+01

< 7.2E+00

< 8.3E+00

< 1.2E+01

< 9.0E+00

< 7.1E+00

< 3.9E+01

< 1.2E+01 SW-101 2/15/2024 pCi/L

< 4.9E+00

< 5.9E+00

< 1.3E+01

< 7.4E+00

< 1.2E+01

< 5.2E+00

< 1.0E+01

< 1.3E+01

< 5.3E+00

< 6.3E+00

< 3.4E+01

< 1.2E+01 SW-101 6/20/2024 pCi/L

< 5.3E+00

< 6.6E+00

< 1.1E+01

< 6.1E+00

< 1.1E+01

< 6.3E+00

< 1.3E+01

< 1.5E+01

< 6.3E+00

< 7.0E+00

< 3.5E+01

< 1.3E+01 SW-101 9/18/2024 pCi/L

< 6.6E+00

< 7.0E+00

< 1.5E+01

< 9.8E+00

< 1.5E+01

< 8.4E+00

< 1.3E+01

< 1.0E+01

< 9.4E+00

< 3.6E+01

< 1.1E+01 SW-101 11/14/2024 pCi/L

< 8.1E+00

< 7.3E+00

< 1.8E+01

< 7.3E+00

< 1.4E+01

< 8.6E+00

< 9.9E+00

< 1.3E+01

< 6.7E+00

< 9.5E+00

< 3.6E+01

< 1.1E+01 SW-102 2/15/2024 pCi/L

< 6.2E+00

< 5.7E+00

< 1.4E+01

< 7.1E+00

< 1.1E+01

< 5.3E+00

< 7.9E+00

< 1.4E+01

< 6.4E+00

< 5.8E+00

< 3.6E+01

< 1.1E+01 SW-102 6/20/2024 pCi/L

< 7.0E+00

< 6.7E+00

< 1.2E+01

< 8.1E+00

< 1.7E+01

< 8.5E+00

< 1.3E+01

< 1.2E+01

< 7.7E+00

< 5.3E+00

< 3.7E+01

< 1.5E+01 SW-103 2/15/2024 pCi/L

< 5.8E+00

< 5.9E+00

< 8.8E+00

< 6.1E+00

< 1.1E+01

< 6.5E+00

< 8.6E+00

< 1.3E+01

< 5.9E+00

< 5.3E+00

< 3.0E+01

< 1.0E+01 SW-103 6/19/2024 pCi/L

< 6.3E+00

< 1.3E+01

< 5.4E+00

< 1.5E+01

< 5.9E+00

< 1.2E+01

< 1.3E+01

< 7.3E+00

< 7.0E+00

< 3.3E+01

< 1.1E+01 SW-103 9/18/2024 pCi/L

< 6.4E+00

< 7.0E+00

< 1.6E+01

< 5.9E+00

< 1.7E+01

< 7.2E+00

< 1.2E+01

< 8.4E+00

< 7.8E+00

< 3.2E+01

< 1.1E+01 SW-103 11/14/2024 pCi/L

< 6.6E+00

< 7.2E+00

< 1.4E+01

< 7.4E+00

< 1.8E+01

< 6.2E+00

< 1.2E+01

< 1.3E+01

< 9.0E+00

< 8.9E+00

< 4.4E+01

< 1.3E+01 SW-104 2/15/2024 pCi/L

< 6.4E+00

< 6.1E+00

< 1.6E+01

< 7.3E+00

< 1.2E+01

< 6.8E+00

< 9.8E+00

< 1.4E+01

< 7.0E+00

< 7.2E+00

< 4.0E+01

< 1.2E+01 SW-104 6/20/2024 pCi/L

< 9.0E+00

< 8.9E+00

< 1.5E+01

< 7.8E+00

< 1.4E+01

< 8.4E+00

< 1.5E+01

< 1.4E+01

< 7.4E+00

< 9.4E+00

< 3.8E+01

< 1.3E+01 SW-104 9/18/2024 pCi/L

< 8.0E+00

< 7.3E+00

< 1.0E+01

< 8.1E+00

< 1.7E+01

< 8.3E+00

< 1.6E+01

< 1.4E+01

< 7.8E+00

< 8.4E+00

< 3.4E+01

< 1.4E+01 SW-104 11/14/2024 pCi/L

< 6.4E+00

< 6.5E+00

< 1.6E+01

< 8.3E+00

< 1.5E+01

< 7.2E+00

< 1.2E+01

< 1.0E+01

< 8.9E+00

< 7.6E+00

< 3.6E+01

< 1.1E+01 T-14 11/13/2024 pCi/L

< 8.6E+00

< 7.0E+00

< 1.6E+01

< 7.9E+00

< 1.4E+01

< 8.2E+00

< 1.5E+01

< 1.4E+01

< 8.7E+00

< 7.8E+00

< 3.3E+01

< 1.1E+01

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 70 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 34, Hard to Detect Nuclides Station ID Sample Date Units FE-55 Nl-63 SR-89 SR-90 AM-241 CM-242 CM-243/244 PU-238 MW-125 02/13/2024 pCi/L

< 5.1E+01

< 3.8E+01

< 4.9E+00

< 1.6E+00

< 2.0E-01

< 7.4E-02

< 2.8E-02

< 2.7E-01

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 71 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-04 11/14/2024 pCi/L

< 5.2E+02 MW-110 9/18/2024 pCi/L 7.60E+03 MW-05 11/13/2024 pCi/L

< 5.8E+02 MW-110 11/14/2024 pCi/L 6.80E+03 MW-08 11/13/2024 pCi/L

< 5.8E+02 MW-111 11/14/2024 pCi/L

< 5.4E+02 MW-100 2/13/2024 pCi/L

< 6.3E+02 MW-112 2/14/2024 pCi/L 2.60E+03 MW-100 6/19/2024 pCi/L

< 6.1E+02 MW-112 6/19/2024 pCi/L 2.10E+03 MW-100 9/17/2024 pCi/L

< 6.1E+02 MW-112 9/18/2024 pCi/L 1.90E+03 MW-100 11/13/2024 pCi/L

< 5.3E+02 MW-112 11/14/2024 pCi/L 1.30E+03 MW-100 11/13/2024 pCi/L

< 5.4E+02 MW-114 2/14/2024 pCi/L 1.80E+03 MW-102 9/18/2024 pCi/L

< 5.7E+02 MW-114 6/19/2024 pCi/L 1.20E+03 MW-103 11/14/2024 pCi/L

< 5.3E+02 MW-114 9/18/2024 pCi/L 7.40E+02 MW-104 11/14/2024 pCi/L

< 5.3E+02 MW-114 11/14/2024 pCi/L

< 5.4E+02 MW-106 6/19/2024 pCi/L

< 6.1E+02 MW-116 2/14/2024 pCi/L 5.30E+03 MW-106 11/13/2024 pCi/L

< 5.8E+02 MW-116 6/19/2024 pCi/L 2.00E+03 MW-107 11/12/2024 pCi/L

< 5.8E+02 MW-116 9/18/2024 pCi/L 3.70E+03 MW-107 11/12/2024 pCi/L

< 5.8E+02 MW-116 11/14/2024 pCi/L 1.50E+03 MW-108 11/12/2024 pCi/L

< 6.0E+02 MW-118 2/14/2024 pCi/L 2.50E+03 MW-110 2/14/2024 pCi/L 1.00E+04 MW-118 6/19/2024 pCi/L 2.10E+03 MW-110 6/19/2024 pCi/L 7.40E+03 MW-118 9/18/2024 pCi/L 2.00E+03 MW-110 9/18/2024 pCi/L 7.30E+03 MW-118 11/14/2024 pCi/L 1.40E+03

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 72 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-120 6/19/2024 pCi/L

< 6.1E+02 MW-126 9/17/2024 pCi/L

< 5.8E+02 MW-120 11/13/2024 pCi/L

< 5.9E+02 MW-126 11/14/2024 pCi/L 1.00E+03 MW-122R 6/19/2024 pCi/L

< 6.1E+02 MW-128 6/19/2024 pCi/L

< 6.4E+02 MW-122R 11/14/2024 pCi/L

< 5.2E+02 MW-128 11/13/2024 pCi/L

< 5.3E+02 MW-124 2/13/2024 pCi/L 8.70E+04 MW-130 6/19/2024 pCi/L

< 6.3E+02 MW-124 2/13/2024 pCi/L 9.30E+04 MW-130 11/14/2024 pCi/L

< 5.3E+02 MW-124 6/18/2024 pCi/L 1.00E+05 MW-131 6/19/2024 pCi/L

< 6.2E+02 MW-124 9/17/2024 pCi/L 8.90E+04 MW-131 11/14/2024 pCi/L

< 5.4E+02 MW-124 9/17/2024 pCi/L 7.60E+04 MW-132 6/19/2024 pCi/L

< 6.3E+02 MW-124 11/12/2024 pCi/L 7.90E+04 MW-132 6/19/2024 pCi/L

< 6.2E+02 MW-125 2/13/2024 pCi/L 1.80E+05 MW-132 11/14/2024 pCi/L

< 5.3E+02 MW-125 6/18/2024 pCi/L 1.40E+05 MW-134 6/20/2024 pCi/L

< 6.1E+02 MW-125 9/17/2024 pCi/L 1.50E+05 MW-134 11/14/2024 pCi/L

< 5.4E+02 MW-125 11/12/2024 pCi/L 1.30E+05 MW-137 2/14/2024 pCi/L 3.40E+03 MW-125 11/12/2024 pCi/L 1.30E+05 MW-137 6/19/2024 pCi/L 4.60E+03 MW-126 2/13/2024 pCi/L 6.70E+02 MW-137 9/18/2024 pCi/L 7.40E+03 MW-126 2/13/2024 pCi/L 9.20E+02 MW-137 9/18/2024 pCi/L 7.20E+03 MW-126 6/19/2024 pCi/L

< 6.2E+02 MW-137 11/14/2024 pCi/L 4.60E+03 MW-126 9/17/2024 pCi/L

< 5.9E+02 MW-139 2/14/2024 pCi/L

< 6.2E+02

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 73 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-139 6/19/2024 pCi/L

< 6.4E+02 MW-146 6/18/2024 pCi/L 2.40E+03 MW-139 9/18/2024 pCi/L

< 5.7E+02 MW-146 9/17/2024 pCi/L 2.60E+03 MW-139 11/14/2024 pCi/L

< 5.3E+02 MW-146 11/12/2024 pCi/L 4.20E+03 MW-14 11/12/2024 pCi/L

< 5.9E+02 MW-147 2/13/2024 pCi/L 1.90E+03 MW-141 2/14/2024 pCi/L 1.40E+03 MW-147 6/18/2024 pCi/L 8.70E+02 MW-141 6/19/2024 pCi/L 1.20E+03 MW-147 6/18/2024 pCi/L 7.50E+02 MW-141 9/18/2024 pCi/L 1.30E+03 MW-147 9/17/2024 pCi/L 1.30E+03 MW-141 11/14/2024 pCi/L 7.20E+02 MW-147 11/12/2024 pCi/L 2.40E+03 MW-141 11/14/2024 pCi/L 9.70E+02 MW-148 2/13/2024 pCi/L

< 5.6E+02 MW-142 2/13/2024 pCi/L 9.10E+02 MW-148 6/18/2024 pCi/L

< 6.2E+02 MW-142 2/13/2024 pCi/L 1.20E+03 MW-148 9/17/2024 pCi/L

< 5.7E+02 MW-142 6/18/2024 pCi/L 8.30E+02 MW-148 11/12/2024 pCi/L

< 5.8E+02 MW-142 9/17/2024 pCi/L 1.40E+03 MW-151 2/14/2024 pCi/L

< 6.4E+02 MW-142 11/12/2024 pCi/L 6.80E+02 MW-151 6/19/2024 pCi/L

< 5.9E+02 MW-144 2/13/2024 pCi/L

< 6.1E+02 MW-151 9/17/2024 pCi/L

< 5.8E+02 MW-144 6/18/2024 pCi/L

< 6.3E+02 MW-151 11/13/2024 pCi/L

< 5.8E+02 MW-144 9/17/2024 pCi/L

< 5.9E+02 MW-153 2/14/2024 pCi/L 9.50E+02 MW-144 11/12/2024 pCi/L

< 5.9E+02 MW-153 6/18/2024 pCi/L 1.30E+03 MW-146 2/13/2024 pCi/L 1.30E+04 MW-153 9/18/2024 pCi/L 8.40E+02

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 74 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-153 11/14/2024 pCi/L 9.70E+02 MW-159 2/13/2024 pCi/L 1.40E+04 MW-155 2/13/2024 pCi/L 1.20E+05 MW-159 6/18/2024 pCi/L 1.30E+04 MW-155 6/18/2024 pCi/L 4.10E+04 MW-159 9/17/2024 pCi/L 1.50E+04 MW-155 9/17/2024 pCi/L 5.30E+04 MW-159 11/12/2024 pCi/L 1.20E+04 MW-155 11/12/2024 pCi/L 4.80E+04 MW-161 2/14/2024 pCi/L 7.40E+02 MW-156 2/13/2024 pCi/L 5.20E+04 MW-161 6/18/2024 pCi/L 9.80E+02 MW-156 2/13/2024 pCi/L 6.00E+04 MW-161 9/18/2024 pCi/L 1.70E+03 MW-156 6/19/2024 pCi/L 9.70E+04 MW-161 11/14/2024 pCi/L 1.20E+03 MW-156 6/19/2024 pCi/L 8.90E+04 MW-161 11/14/2024 pCi/L 1.10E+03 MW-156 9/17/2024 pCi/L 9.80E+04 MW-162 2/13/2024 pCi/L

< 6.3E+02 MW-156 11/12/2024 pCi/L 8.80E+04 MW-162 6/18/2024 pCi/L

< 6.4E+02 MW-157 2/13/2024 pCi/L 2.00E+05 MW-162 9/17/2024 pCi/L

< 6.1E+02 MW-157 6/19/2024 pCi/L 1.70E+05 MW-162 11/12/2024 pCi/L

< 5.2E+02 MW-157 9/17/2024 pCi/L 1.80E+05 MW-164 2/14/2024 pCi/L

< 6.3E+02 MW-157 11/13/2024 pCi/L 1.70E+05 MW-164 6/19/2024 pCi/L

< 6.0E+02 MW-158 2/13/2024 pCi/L 1.80E+04 MW-164 9/17/2024 pCi/L

< 5.8E+02 MW-158 6/18/2024 pCi/L 3.80E+04 MW-164 11/13/2024 pCi/L

< 5.8E+02 MW-158 9/17/2024 pCi/L 5.70E+04 MW-165 2/14/2024 pCi/L

< 6.2E+02 MW-158 11/12/2024 pCi/L 4.50E+04 MW-165 6/19/2024 pCi/L

< 6.2E+02

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 75 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-165 9/17/2024 pCi/L

< 5.8E+02 MW-179 6/19/2024 pCi/L 6.70E+04 MW-165 11/13/2024 pCi/L

< 5.9E+02 MW-179 9/17/2024 pCi/L 7.00E+04 MW-167 6/19/2024 pCi/L

< 6.3E+02 MW-179 11/14/2024 pCi/L 1.90E+04 MW-167 11/14/2024 pCi/L

< 5.3E+02 MW-180 6/19/2024 pCi/L

< 6.2E+02 MW-169 6/20/2024 pCi/L

< 6.6E+02 MW-180 11/14/2024 pCi/L

< 5.9E+02 MW-169 11/14/2024 pCi/L

< 5.2E+02 MW-182 2/14/2024 pCi/L

< 6.3E+02 MW-170 2/14/2024 pCi/L

< 6.3E+02 MW-182 6/19/2024 pCi/L

< 6.1E+02 MW-170 6/19/2024 pCi/L

< 6.1E+02 MW-182 6/19/2024 pCi/L

< 6.0E+02 MW-170 9/18/2024 pCi/L

< 5.7E+02 MW-182 9/18/2024 pCi/L

< 5.7E+02 MW-170 11/12/2024 pCi/L

< 5.9E+02 MW-182 9/18/2024 pCi/L

< 5.8E+02 MW-172 11/14/2024 pCi/L

< 5.8E+02 MW-182 11/12/2024 pCi/L

< 5.8E+02 MW-174 11/12/2024 pCi/L

< 5.8E+02 MW-182 11/12/2024 pCi/L

< 6.0E+02 MW-178 2/14/2024 pCi/L 4.50E+03 MW-185 2/13/2024 pCi/L

< 6.3E+02 MW-178 6/19/2024 pCi/L 2.30E+03 MW-185 2/13/2024 pCi/L

< 6.4E+02 MW-178 6/19/2024 pCi/L 2.30E+03 MW-185 6/18/2024 pCi/L

< 6.2E+02 MW-178 9/17/2024 pCi/L 1.50E+03 MW-185 9/17/2024 pCi/L

< 6.0E+02 MW-178 11/14/2024 pCi/L 1.40E+03 MW-185 11/12/2024 pCi/L

< 5.8E+02 MW-178 11/14/2024 pCi/L 1.40E+03 MW-186 2/14/2024 pCi/L

< 6.4E+02 MW-179 2/14/2024 pCi/L 1.20E+05 MW-186 6/19/2024 pCi/L

< 6.0E+02

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 76 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-186 9/17/2024 pCi/L

< 6.0E+02 MW-209 6/19/2024 pCi/L

< 6.1E+02 MW-186 11/13/2024 pCi/L

< 5.9E+02 MW-209 6/19/2024 pCi/L

< 6.2E+02 MW-187 2/14/2024 pCi/L

< 6.3E+02 MW-209 9/18/2024 pCi/L

< 5.8E+02 MW-187 6/19/2024 pCi/L

< 6.1E+02 MW-209 11/14/2024 pCi/L

< 5.2E+02 MW-187 9/17/2024 pCi/L

< 6.0E+02 MW-211 2/13/2024 pCi/L

< 5.4E+02 MW-187 11/13/2024 pCi/L

< 5.9E+02 MW-211 6/19/2024 pCi/L

< 6.5E+02 MW-188 2/13/2024 pCi/L

< 6.5E+02 MW-211 9/17/2024 pCi/L

< 6.0E+02 MW-188 6/18/2024 pCi/L

< 6.4E+02 MW-211 11/13/2024 pCi/L

< 5.3E+02 MW-188 6/18/2024 pCi/L

< 6.3E+02 MW-213 6/19/2024 pCi/L

< 6.2E+02 MW-188 9/17/2024 pCi/L

< 5.8E+02 MW-213 11/13/2024 pCi/L

< 5.2E+02 MW-188 11/12/2024 pCi/L

< 6.2E+02 MW-215 6/19/2024 pCi/L

< 6.2E+02 MW-201 6/19/2024 pCi/L

< 6.1E+02 MW-215 11/14/2024 pCi/L 1.10E+03 MW-201 11/13/2024 pCi/L

< 5.9E+02 MW-215 11/14/2024 pCi/L 1.10E+03 MW-205 6/18/2024 pCi/L

< 6.4E+02 MW-217 6/19/2024 pCi/L

< 6.4E+02 MW-205 11/12/2024 pCi/L

< 5.9E+02 MW-217 11/14/2024 pCi/L

< 5.3E+02 MW-207 6/18/2024 pCi/L

< 6.0E+02 MW-219 6/19/2024 pCi/L

< 6.0E+02 MW-207 11/14/2024 pCi/L

< 5.3E+02 MW-219 11/14/2024 pCi/L

< 5.3E+02 MW-209 2/14/2024 pCi/L

< 5.7E+02 MW-221 2/14/2024 pCi/L

< 6.3E+02 MW-209 2/14/2024 pCi/L

< 6.0E+02 MW-221 6/19/2024 pCi/L

< 6.0E+02

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 77 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-221 9/18/2024 pCi/L

< 5.7E+02 PZ-01 6/18/2024 pCi/L 1.90E+04 MW-221 11/12/2024 pCi/L

< 5.9E+02 PZ-01 6/18/2024 pCi/L 2.10E+04 MW-223 2/14/2024 pCi/L

< 6.4E+02 PZ-01 9/18/2024 pCi/L 1.40E+04 MW-223 6/19/2024 pCi/L

< 6.1E+02 PZ-01 11/14/2024 pCi/L 1.20E+04 MW-223 9/18/2024 pCi/L

< 6.0E+02 PZ-03 6/19/2024 pCi/L

< 6.1E+02 MW-223 11/14/2024 pCi/L

< 5.3E+02 PZ-03 11/14/2024 pCi/L

< 5.3E+02 MW-225 6/19/2024 pCi/L

< 6.0E+02 SW-101 2/15/2024 pCi/L

< 6.0E+02 MW-225 11/14/2024 pCi/L

< 5.2E+02 SW-101 6/20/2024 pCi/L

< 6.3E+02 MW-227 6/18/2024 pCi/L

< 6.5E+02 SW-101 9/18/2024 pCi/L

< 5.6E+02 MW-227 11/12/2024 pCi/L

< 5.8E+02 SW-101 11/14/2024 pCi/L

< 5.2E+02 MW-229 6/19/2024 pCi/L

< 6.0E+02 SW-102 2/15/2024 pCi/L

< 6.0E+02 MW-229 11/14/2024 pCi/L

< 5.3E+02 SW-102 6/20/2024 pCi/L

< 6.2E+02 MW-231 6/19/2024 pCi/L

< 6.1E+02 SW-102 11/13/2024 pCi/L

< 5.7E+02 MW-231 11/14/2024 pCi/L

< 5.4E+02 SW-103 2/15/2024 pCi/L

< 5.7E+02 MW-233 6/19/2024 pCi/L

< 6.1E+02 SW-103 6/19/2024 pCi/L

< 6.0E+02 MW-233 11/13/2024 pCi/L

< 5.9E+02 SW-103 9/18/2024 pCi/L

< 5.6E+02 MW-235 6/19/2024 pCi/L

< 6.3E+02 SW-103 11/14/2024 pCi/L

< 5.3E+02 MW-235 11/12/2024 pCi/L

< 5.8E+02 SW-104 2/15/2024 pCi/L

< 5.9E+02 PZ-01 2/14/2024 pCi/L 1.90E+04 SW-104 6/20/2024 pCi/L

< 6.5E+02

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 78 of 78 Company: Entergy I Plant: River Bend Nuclear Station Table 35, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 SW-104 9/18/2024 pCi/L

< 5.6E+02 T-14 11 /13/2024 pCi/L

< 5.8E+02 SW-104 11/14/2024 pCi/L

< 5.3E+02

RBG-48333, Unit 1 - 2024 Annual Radioactive Effluent Release Report

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RBG-48333, Unit 1 - 2024 Annual Radioactive Effluent Release Report

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