BW240019, Annual Radioactive Effluent Release Report
| ML24122A653 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/01/2024 |
| From: | Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24122A651 | List: |
| References | |
| BW240019 | |
| Download: ML24122A653 (1) | |
Text
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~' Constellation Braidwood Nuclear Power Station 2023 Annual Radioactive Effluent Release Report UNIT 1 AND UNIT 2 (Docket Numbers 50-456 and 50-457)
ISFSI (Docket Number 72-73)
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................ 3 2.0 EXECUTIVE
SUMMARY
............................................................................................................ 5 2.1 Comparison to Regulatory Limits.................................................................................... 7
3.0 INTRODUCTION
........................................................................................................................ 9 3.1 About Nuclear Power...................................................................................................... 9 3.2 About Radiation Dose................................................................................................... 11 3.3 About Dose Calculation................................................................................................ 13 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................. 15 4.1 Regulatory Limits.......................................................................................................... 15 4.2 Regulatory Limits for Gaseous Effluent Doses:............................................................. 15 4.3 Regulatory Limits for Liquid Effluent Doses................................................................... 16 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. 17 4.5 Onsite Doses (Within Site Boundary)............................................................................ 17 5.0 SUPPLEMENTAL INFORMATION........................................................................................... 18 5.1 Gaseous Batch Releases............................................................................................. 18 5.2 Liquid Batch Releases.................................................................................................. 18 5.3 Abnormal Releases...................................................................................................... 18 5.4 Land Use Census Changes.......................................................................................... 19 5.5 Meteorological Data...................................................................................................... 19 5.6 Effluent Radiation Monitors Out of Service Greater Than ODCM Requirements............................................................................................................... 19 5.7 Offsite Dose Calculation Manual (ODCM) Changes...................................................... 20 5.8 Process Control Program (PCP) Changes.................................................................... 20 5.9 Radioactive Waste Treatment System Changes........................................................... 20 5.10 Other Supplemental Information................................................................................... 20 6.0 BIBLIOGRAPHY...................................................................................................................... 22 TABLES Table 1, Braidwood Nuclear Power Station Unit 1 and Unit 2 Dose Summary....................................... 7 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for BNPS.................................. 8 Table 3, Gaseous Effluents Summation of All Releases Unit 1 and Unit 2.......................................... 23 Table 4, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1 and 2................................... 24 Table 5, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1 and 2.......................... 25 Table 6, Liquid Effluents - Summation of All Releases Unit 1 and 2................................................... 26 Table 7, Batch Mode Liquid Effluents Unit 1 and 2............................................................................... 27 Table 8, Continuous Mode Liquid Effluents Unit 1 and 2...................................................................... 28 Table 9, Resins, Filters, and Evaporator Bottoms Summary Shipped from the BNPS Site................... 29 Table 10, Dry Active Waste (DAW) Summary Shipped from the BNPS Site........................................ 30
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 2 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station Table 11, Irradiated Components Summary Shipped from the BNPS Site........................................... 31 Table 12, Other Waste Summary Shipped from the BNPS Site........................................................... 32 Table 13, Sum of All Low-Level Waste Shipped from the BNPS Site................................................... 33 Table 14, Solid Waste Disposition from the BNPS Site........................................................................ 34 Table 15, Classification of Atmospheric Stability.................................................................................. 36 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]..................................................................................... 9 Figure 2, Boiling Water Reactor (BWR) [2]........................................................................................... 10 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3].................................................. 11 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]............. 13 ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)................................................... 23, Solid Waste Information................................................................................................ 29, Meteorological Data Summary...................................................................................... 35
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 3 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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.
- 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.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 4 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station
- 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.
NRG: 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
- 33.
Unrestricted Area: An area, access to which is neither limited nor controlled by the licensee.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 5 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 2.0 EXECUTIVE
SUMMARY
Braidwood Nuclear Power Station (BNPS) 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 2023 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 quantity of radioactive material released from Braidwood Nuclear Power Plant was determined from in-house and vendor laboratory analysis of continuous inline sampling media and batch sample media from all ODCM specified effluent pathways.
These pathways include continuous releases from the Unit 1 and Unit 2 Station Vent Stack, Condensate Polisher Sump, Waste Water Treatment, and Circulating Water Slowdown. The ODCM specified effluent pathways also include batch releases from the Unit 1 and Unit 2 Primary Containments, Waste Gas Decay Tanks, and Liquid Radwaste Batch Release Tanks.
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 2023, the gaseous effluent dose assessments for locations from the Land Use Census showed that the critical receptor for Braidwood Nuclear Power Station is a Child due to Inhalation, at the Nearest Residence. The maximum Annual Organ Dose calculated for this receptor was 1.05E-02 mrem, to the thyroid. This represents 3.51 E-02 percent of the ODCM Annual Dose Limit of 30 mrem.
The maximum annual dose calculated to any organ due to radioactive liquid effluents was 2.74E-01 mrem, for a Child to the GI-LLI due to ingestion of potable water and fish. This represents 1.37 percent of the ODCM Annual Dose Limit of 20 mrem.
Solid radioactive waste shipped offsite for processing or direct disposal included 6.83E+02 Curies and 3.59E+02 m3, shipped in 21 shipments.
In addition to monitoring radioactive effluents, BNPS 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: 2023 I Page 6 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station An Independent Spent Fuel Storage Installation (ISFSI) was placed in service at Braidwood Station in 2011. The ISFSI is a closed system, and the only exposure would be due to direct radiation, which is measured by Optically Stimulated Luminescent Dosimetry (OSLO). In 2023 the dose to the nearest resident from the ISFSI was calculated to be not detectable. This estimate was determined using environmental dosimeters from the Radiological Environmental Monitoring Program and extrapolating the dose from the ISFSI environmental dosimeters.
The volume and quantity of radioactive waste shipped offsite from Braidwood Nuclear Power Plant for processing and disposal was determined from data maintained in the radwaste shipping database. Radwaste processed for shipment was in accordance with Exelon procedure RW-AA-100, "PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES" and consistent with the UFSAR.
Meteorological data was obtained from the 320-foot meteorological tower located on the Braidwood Station premises. During 2023, the Braidwood site joint met data recovery was 99.3% which exceeded the goal of 90%.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 7 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 2.1 Comparison to Regulatory Limits During 2023 all solid, liquid, and gaseous radioactive effluents from Braidwood Nuclear Power Station were well below regulatory limits, as summarized in Table 1 and Table 2.
Table 1, Braidwood Nuclear Power Station Unit 1 and Unit 2 Dose Summary1 Summary of Gaseous and Liquid Effluent Doses to Members of the Public Highest Dose Receptor to the Nearest Resident is the Child Quarter 1 Quarter 2 Quarter 3 Quarter 4 Liquid Effluent Limit 3.0 mrem 3.0 mrem 3.0 mrem 3.0 mrem Dose Limit, Total Body Dose 1.41E-01 6.43E-02 2.78E-02 3.95E-02 Total Body
% of Limit 4.69E+00 2.14E+00 9.28E-01 1.32E+00 Liquid Effluent Limit 10 mrem 10 mrem 10 mrem 10 mrem Dose Limit, Max Organ Dose 1.41 E-01 6.50E-02 2.78E-02 4.03E-02 Any Organ
% of Limit 1.41 E+00 6.50E-01 2.78E-01 4.03E-01 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad Dose Limit, Gamma Air Dose 3.45E-05 2.30E-05 2.60E-05 5.55E-05 Gamma Air (Noble Gas)
% of Limit 3.45E-04 2.30E-04 2.60E-04 5.55E-04 Gaseous Effluent Limit 20 mrad 20 mrad 20 mrad 20 mrad Dose Limit, Beta Air Dose 1.23E-05 9.13E-06 9.19E-06 1.97E-05 Beta Air (Noble Gas)
% of Limit 6.16E-05 4.56E-05 4.59E-05 9.83E-05 Gaseous Effluent Limit 15 mrem 15 mrem 15 mrem 15 mrem Organ Dose Limit Max Organ Dose 1.71 E-03 5.53E-03 2.79E-03 4.95E-04 (Iodine, Tritium, 1.14E-02 3.69E-02 1.86E-02 3.30E-03 Particulates with
% of Limit
> 8-day half-life)
Annual 6.0 mrem 2.72E-01 4.54E+00 20 mrem 2.74E-01 1.37E+00 20 mrad 1.39E-04 6.95E-04 40 mrad 5.03E-05 1.26E-04 30 mrem 1.05E-02 3.51 E-02 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits. C-14 was not included in organ dose calculations from airborne effluents conforming to 10 CFR 50, Appendix I.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 8 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for BNPS1 Whole Body Thyroid Max Other Organ Gaseous2 1.03E-02 1.05E-02 1.03E-02 Carbon-14 2.24E-01 2.24E-01 1.12E+00 Liquid 2.72E-01 2.72E-01 2.74E-01 Direct Shine Not Detectable Not Detectable Not Detectable Total Site Dose 5.06E-01 5.0?E-01 1.40E+00 Total w/Other Nearby Facility3 N/A N/A N/A Limit 25 mrem 75 mrem 25 mrem
% of Limit 2.02E+00 6.75E-01 5.60E+00 1 Table 2 is a summation of Units to show compliance with 40 CFR Part 190 Limits.
2 Gaseous dose values in Table 2 include organ dose from Noble Gas, Iodine, Tritium, and Particulates.
3 Other fuel cycle sources within 5 miles of the site are considered in this analysis.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 9 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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 Structu-e Figure 1, Pressurized Water Reactor (PWR) [1]
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 10 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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: 2023 I Page 11 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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 tomography (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 (2%)
Conventional radiography/fluoroscopy (medical)
{5%)
Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 12 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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: 2023 I Page 13 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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.
Ga:-eous cffiuents
~I 0
- * * ** : 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 NRG 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: 2023 I Page 14 of 36 Company: Constellation I Plant: Braidwood Nuclear Power 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.
Each year a Land Use Census is performed to determine what potential dose pathways currently exist within a five-mile radius around the plant, the area most affected by plant operations. The Annual Land Use Census identifies the locations of vegetable gardens, nearest residences, milk animals and meat animals. The data from the census is used to determine who is the most likely to be 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: 2023 I Page 15 of 36 Company: Constellation
/ Plant: Braidwood Nuclear Power Station 4.0 4.1 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 BNPS must adhere. BNPS 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 BNPS 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 104 microcuries/ml.
The annual whole body, skin and organ dose was computed using the 2023 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 and Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for BNPS.
4.2 Regulatory Limits for Gaseous Effluent Doses:
- 1.
Fission and activation gases:
- a.
Noble gases dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
- 1)
Less than or equal to 500 mrem/year to the total body
- 2)
Less than or equal to 3000 mrem/year to the skin
- b.
Noble gas air dose due to noble gases released in gaseous effluents, from the site, to areas at and beyond the site boundary shall be limited to the following:
- 1)
Quarterly a)
Less than or equal to 10 mrads gamma b)
Less than or equal to 20 mrads beta
- 2)
Yearly a)
Less than or equal to 20 mrads gamma b)
Less than or equal to 40 mrads beta
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 16 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 4.2 (Continued) 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 the site to areas at and beyond the site boundary shall be limited to the following:
- 1)
Quarterly a)
Less than or equal to 15 mrem to any organ
- 2)
Yearly a)
Less than or equal to 30 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 the site to unrestricted areas shall be limited to the following:
- a.
Quarterly
- 1)
Less than or equal to 3 mrem total body
- 2)
Less than or equal to 10 mrem critical organ
- b.
Yearly
- 1)
Less than or equal to 6 mrem total body
- 2)
Less than or equal to 20 mrem critical organ
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 17 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public 4.5
- 1.
Total Dose (40 CFR 190)
- a.
The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC in the unrestricted area due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:
- 1)
Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.
- 2)
Less than or equal to 75 mrem, Thyroid.
Onsite Doses (Within Site Boundary)
BNPS 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. Braidwood had no non-occupational or members of the public on-site during 2023.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 18 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 5.0 5.1 5.1.1 SUPPLEMENTAL INFORMATION Gaseous Batch Releases BNPS Unit 1 and Unit 2 1. Number of Batch Releases
- 2. Total duration of batch releases
- 3. Maximum batch release duration
- 4. Averaqe batch release duration
- 5. Minimum batch release duration 5.2 5.2.1 Liquid Batch Releases BNPS Unit 1 and Unit 2
- 1. Number of Batch Releases
- 2. Total duration of batch releases
- 3. Maximum batch release duration
- 4. Average batch release duration
- 5. Minimum batch release duration
- 6. Avg stream flow during periods of release of liquid effluent into a flowinq stream Units minutes minutes minutes minutes Units minutes minutes minutes minutes m3/sec 5.3 5.3.1 Abnormal Releases Gaseous Abnormal Releases Quarter 1
9.60E+01 3.99E+03 1.28E+02 4.15E+01 6.00E+00 Quarter 1
2.90E+01 5.00E+04 3.06E+03 1.72E+03 9.90E+01 2.16E02 Quarter Quarter Quarter 2
3 4
Annual 9.10E+01 9.30E+01 9.20E+01 3.72E+02 9.52E+03 4.37E+03 6.25E+03 2.41 E+04 1.85E+03 3.51E+02 1.67E+03 1.85E+03 1.05E+02 4.70E+01 6.79E+01 6.49E+01 1.10E+01 1.70E+01 2.70E+01 6.00E+00 Quarter Quarter Quarter 2
3 4
Annual 2.80E+01 1.30E+01 1.00E+01 8.00E+01 7.00E+04 2.63E+04 2.18E+04 1.68E+05 4.71E+03 3.97E+03 4.20E+03 4.71 E+03 2.50E+03 2.02E+03 2.18E+03 2.10E+03 2.85E+02 6.78E+02 1.27E+03 9.90E+01 1.14E02 5.20E01 8.26E01 1.16E02 No abnormal (unplanned) gaseous releases or discharges from the site were made during the report period.
5.3.2 Liquid Abnormal Releases No abnormal (unplanned) liquid releases or discharges from the site were made during the report period.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 19 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 5.4 5.5 5.6 Land Use Census Changes There were no changes to the Land Use Census during the report period.
Meteorological Data In accordance with ODCM Control 5.2, the ARERR should include a summary of meteorological data collected over the reporting year. During 2023, Braidwood site joint met data recovery was 99.3% which exceeded the goal of 90%. Joint Frequency Distribution (JFD) and meteorological data collected during 2023 is retained onsite.
This data is available for review by the NRG upon request.
During 2023, the goal of 90% joint data recovery was met. The Braidwood Station meteorological monitoring program produced 52,209 hours0.00242 days <br />0.0581 hours <br />3.455688e-4 weeks <br />7.95245e-5 months <br /> of valid data out of a possible 52,560 parameter hours during 2023, which represents an overall data recovery rate of 99.3%. Priority parameters are all parameters except dew point temperature and precipitation. For the year, winds measured at 34 ft. most frequently came from the West-Northwest (8.75%) and fell into the 3.6 - 7.5 mph wind speed class (41.83%). Calms (wind speeds at or below the sensor threshold) were measured 0.00% of the time and speeds greater than 24.5 mph were measured 0.04% of the time. Stability based on the 199 - 30 ft. differential temperature most frequently fell into the neutral classification (40.52%).
Effluent Radiation Monitors Out of Service Greater Than ODCM Requirements Three effluent radiation monitors were declared out of service for greater than ODCM requirements during the report period:
- 1.
The Condensate Polisher Sump Discharge Radiation Monitor, 0RE-PR041, was declared out of service on 12/13/22 due to a failed calibration. Multiple equipment issues were discovered, and repairs were tracked under Work Order 5146362. On 1/12/23, 0RE-PR041 exceeded the 30 day action statement in accordance with ODCM Table 12.2-1, Action 34. The radiation monitor flow indicator was repaired, and the radiation monitor was returned to service on 1/17/23 and was out of service for 35 days. (AR 4542783)
- 2.
The Containment Purge System Noble Gas Radiation Monitor, RE-1 PR001 B, was declared out of service on 4/29/23 due to loss of communications with Loop #1, 3, and 5. On 5/6/23, 1 PR001 B exceeded the 7 day action statement in accordance with ODCM Table 12.2-3, Action 37. Communication was restored, and the radiation monitor returned to service on 5/28/23. The radiation monitor was out of service for 30 days. (AR 4675996)
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 20 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 5.7 5.8 5.9
- 3.
Liquid Radwaste Effluent Line Radiation Monitors, 0RE-PR001 and 0RE-PR090, were declared out of service on 10/26/23 due to a clearance order for circulating water blowdown line inspections. On 11/9/23, both radiation monitors exceeded the 14 day action statement in accordance with ODCM Table 12.2-1, Action 31 due to robot equipment issues which extended the inspection period.
Both radiation monitors were returned to service on 11/14/23 and were out of service for 19 days. (AR 4 716089)
Offsite Dose Calculation Manual (ODCM) Changes There were no changes to the ODCM during the report period.
Process Control Program (PCP) Changes There were no changes to the PCP during the report period.
Radioactive Waste Treatment System Changes There were no changes or modifications to the gaseous radioactive waste, liquid radioactive waste, or ventilation exhaust treatment systems during the report period.
5.10 Other Supplemental Information 5.10.1 Outside Tanks No outside tanks exceeded ODCM or Technical Specification Limits.
5.10.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program An Independent Spent Fuel Storage Installation (ISFSI) was placed in service at Braidwood Station in 2011. The ISFSI is a closed system, and the only exposure would be due to direct radiation, which is measured by Optically Stimulated Luminescent Dosimetry (OSLO). In 2023 the dose to the nearest resident from the ISFSI was estimated to be non-detectable. This estimate was determined using environmental dosimeters from the Radiological Environmental Monitoring Program and extrapolating the dose from the ISFSI environmental dosimeters.
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.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 21 of 36 Company: Constellation
/ Plant: Braidwood Nuclear Power Station In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRG recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for Braidwood Nuclear Power Station during 2023 was 8.66 Curies.
Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. C-14 dose is included in dose calculation results in Table 2.
5.10.4 Errata/Corrections to Previous ARERRs One typographical error was discovered in the 2020 BNPS ARERR Report. The exponent for Table D. Tritium Releases was cut off in four instances and was corrected from "E+0" to "E+00".
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 22 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station 6.0 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] "10 CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.
[1 OJ "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.
[11) "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.
[12) "NEI 07 Industry Ground Water Protection Initiative -
Final Guidance Document, Rev. 1,"
Nuclear Energy Institute, Washington, D.C., 2019.
[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: 2023 I Page 23 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 3, Gaseous Effluents Summation of All Releases Unit 1 and Unit 2 1 A. Fission &
Units Quarter 1 Quarter Quarter Quarter Total Est. Total Activation Gases 2
3 4
Error%
- 1. Total Release Ci 1.11E-01 9.79E-02 8.09E-02 1.74E-01 4.63E-01 7.59E+00
- 2. Average Release
µCi/sec 1.43E-02 1.25E-02 1.02E-02 2.18E-02 1.47E-02 Rate for Period B. Iodine
- 1. Total Iodine - 131 Ci
<LLD 1.79E-06 7.77E-09 3.71E-09 1.80E-06 3.32E+01
- 2. Average Release
µCi/sec N/A 1.16E-06 3.35E-06 4.66E-06 3.88E-06 Rate for Period C. Particulates
- 1. Particulates with Ci
<LLD
<LLD
<LLD
<LLD
<LLD 1.98E+01 half-lives > 8 days.
- 2. Average Release
µCi/sec N/A N/A N/A N/A N/A Rate for Period D. Tritium 1. Total Release Ci 1.90E+01 5.94E+01 3.10E+01 5.50E+O0 1.15E+02 8.07E+00
- 2. Average Release
µCi/sec 2.45E+00 7.56E+00 3.90E+00 6.92E-01 3.65E+00 Rate for Period E. Gross Alpha
- 1. Total Release Ci
<LLD
<LLD
<LLD
<LLD
<LLD 1.98E+01
- 2. Average Release
µCi/sec N/A N/A N/A N/A N/A Rate for Period F. Carbon-14
- 1. Total Release Ci 2.22E+00 2.01E+00 2.22E+00 2.22E+00 8.66E+00
- 2. Average Release
µCi/sec 2.85E-01 2.55E-01 2.79E-01 2.79E-01 2.75E-01 Rate for Period 1 % of limit is provided in Table 1, Braidwood Nuclear Power Station Unit 1 and Unit 2 Dose Summary.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 24 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables)
Table 4, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1 and 2 Radionuclide Units I Quarter 1 I
Quarter 2 I
Quarter 3 I
Quarter 4 I
Total for year Released Fission Gases Ar-41 Ci 1.06E-01 6.91 E-02 8.00E-02 1.71E-01 4.27E-01 Xe-133 Ci 4.66E-03 2.55E-02 8.30E-04 2.37E-03 3.34E-02 Xe-135 Ci
<LLD 3.34E-03
<LLD
<LLD 3.34E-03 Total for Period Ci 1.11 E-01 9.79E-02 8.09E-02 1.74E-01 4.63E-01 Iodines Br-80 Ci 3.93E-05 0.O0E+00 1.43E-05 1.90E-05 7.26E-05 Br-82 Ci 9.78E-06 7.22E-06 8.SOE-06 1.74E-05 4.32E-05 1-131 Ci
<LLD
<LLD 7.77E-09 3.71 E-09 1.15E-08 1-132 Ci 2.47E-08 4.97E-08 3.22E-08
<LLD 1.07E-07 1-133 Ci
<LLD 2.57E-08 1.66E-07 6.40E-07 8.32E-07 Total for Period Ci 4.91 E-05 7.30E-06 2.33E-05 3.71 E-05 1.17E-04 Particulates None Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 I Ci II 5.23E-01 I
2.96E-01 I
4.11 E-01 I
1.78E+00 II 3.01 E+00 I
Gross Alpha I
Alpha I Ci II
<LLD I
<LLD I
<LLD I
<LLD II
<LLD I
C-14 I Ci II
<LLD I
<LLD I
<LLD I
<LLD II
<LLD I
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 25 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables}
Table 5, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1 and 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases None Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines Br-82 Ci 4.86E-07
<LLD 3.27E-06
<LLD 3.76E-06 1-131 Ci
<LLD 1.79E-06
<LLD
<LLD 1.79E-06 1-132 Ci
<LLD
<LLD
<LLD
<LLD
<LLD 1-133 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period Ci 4.86E-07 1.79E-06 3.27E-06
<LLD 5.55E-06 Particulates None Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci 1.85E+01 5.92E+01 3.06E+01 3.72E+00 1.12E+02 Gross Alpha Alpha Ci
<LLD
<LLD
<LLD
<LLD
<LLD Carbon-14 C-14 Ci 2.22E+00 2.0lE+00 2.22E+00 2.22E+00 8.66E+00
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 26 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, ARERR Release Summary Tables {RG-1.21 Tables) 2.0 LIQUID EFFLUENTS Table 6, Liquid Effluents - Summation of All Releases Unit 1 and 2 1 Quarter Quarter Quarter Quarter Annual Est. Total A. Fission & Activation Products Unit 1
2 3
4 Error%
- 1. Total Release Ci 1.41 E-02 5.95E-03 5.91 E-04 1.25E-02 3.32E-02 2.64E+00
- 2. Average diluted concentration
µCi/ml 9.76E-10 5.15E-10 4.53E-11 1.17E-09 6.66E-10 B. Tritium
- 1. Total Release Ci 8.84E+02 6.06E+02 1.21 E+02 2.69E+02 1.88E+03 5.85E+00
- 2. Average diluted concentration
µCi/ml 6.12E-05 5.24E-05 9.29E-06 2.51 E-05 3.78E-05 C. Dissolved & Entrained Gases
- 1. Total Release Ci
<LLD
<LLD
<LLD
<LLD
<LLD 2.64E+00
- 2. Average diluted concentration
µCi/ml N/A N/A N/A N/A N/A D. Gross Alpha Activity
- 1.
Total Release Ci
<LLD
<LLD
<LLD
<LLD
<LLD 1.47E+01
- 2.
Average diluted concentration uCi/mL N/A N/A N/A N/A N/A E. Volume of Waste Released (prior Liters 1.02E+10 7.86E+09 1.09E+10 9.09E+09 3.81 E+10 to dilution)
F. Volume of Dilution Water Used Liters 4.27E+09 3.70E+09 2.14E+09 1.62E+09 1.17E+10 Durinq Period 1 % of limit is provided in Table 1, Braidwood Nuclear Power Station Unit 1 and Unit 2 Dose Summary.
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 27 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables)
Table 7, Batch Mode Liquid Effluents Unit 1 and 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci 3.57E-03 5.0SE-04
<LLD
<LLD 4.07E-03 Mn-54 Ci 1.32E-05 1.08E-05
<LLD 3.85E-06 2.78E-05 Fe-55 Ci 4.25E-03 2.19E-03
<LLD
<LLD 6.45E-03 Fe-59 Ci
<LLD 4.97E-05
<LLD
<LLD 4.97E-05 Co-57 Ci 1.09E-05
<LLD
<LLD
<LLD 1.09E-05 Co-58 Ci 1.65E-03 1.69E-03 3.61 E-04 1.03E-04 3.80E-03 Co-60 Ci 4.21E-03 9.72E-04 1.63E-04 3.47E-04 5.69E-03 Sr-92 Ci
<LLD 1.76E-06
<LLD
<LLD 1.76E-06 Nb-95 Ci 6.47E-06 4.46E-05
<LLD
<LLD 5.10E-05 Ag-110m Ci 2.96E-04 1.41 E-04
<LLD 4.79E-05 4.86E-04 Sb-125 Ci 8.12E-05 4.63E-05 2.43E-05 1.70E-05 1.69E-04 Te-123m Ci
<LLD 2.71 E-04 4.29E-05 4.17E-06 3.18E-04 Te-125m Ci
<LLD
<LLD
<LLD 1.20E-02 1.20E-02 Te-132 Ci
<LLD 3.97E-06
<LLD
<LLD 3.97E-06 1-132 Ci
<LLD 3.87E-06
<LLD
<LLD 3.87E-06 1-134 Ci 1.71 E-05 1.85E-05
<LLD
<LLD 3.56E-05 Total for Period Ci 1.41 E-02 5.95E-03 5.91 E-04 1.25E-02 3.32E-02 Tritium H-3 Ci 8.83E+02 5.71E+02 1.14E+02 2.6'-r-(Vl E+03 Gross Alpha I
Alpha I Ci II
<LLD I
<LLD I
<LLD I
<LLD II
<LLD I
Entrained Gases None Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A
Annual Radioactive Effluent Release Report I
YEAR: 2023 l Page 28 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables)
Table 8, Continuous Mode Liquid Effluents Unit 1 and 2 Radionuclide Units I Quarter 1 I
Quarter 2 I
Quarter 3 I
Quarter 4 Released I Fission and Activation Products None Ci I
N/A I
N/A I
N/A I
N/A Total for Period Ci N/A N/A N/A N/A jTritium H-3 I Ci II 8.0?E-01 I 3.48E+01 I 7.54E+00 I 3.37E+00 Gross Alpha Alpha I Ci II
<LLD I
<LLD I
<LLD I
<LLD Entrained Gases None Ci I
N/A I
N/A I
N/A I
N/A Total for Period Ci N/A N/A N/A N/A Total for year i
N/A N/A II 4.65E+01 II
<LLD I
N/A N/A I
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 29 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Solid Waste Information Solid Waste Shipped Offsite For disposal and estimates of major nuclides by waste class and stream FROM 01/01/2023 to 12/31/2023 Table 9, Resins, Filters, and Evaporator Bottoms Summary Shipped from the BNPS Site Waste Volume Curies Class ft3 ml Shipped A
3.90E+03 1.11 E+02 6.64E+01 B
0.00E+00 0.00E+O0 0.O0E+00 C
1.20E+02 3.40E+O0 6.16E+02 Unclassified 0.O0E+00 0.00E+O0 0.00E+00 All 4.02E+03 1.14E+02 6.82E+02 Major Nuclides for Above Table: H-3, C-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-95, Tc-99, Sn-117m, Sb-124, Sb-125, 1-129, Cs-137, Ce-144, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-244 Waste Class A
> 1% Abundance Nuclide Name Abundance Curies H-3 14.35%
9.53E+00 C-14 1.4%
9.33E-01 Mn-54 2.01%
1.33E+00 Fe-55 11.85%
7.87E+00 Co-60 28.84%
1.92E+01 Ni-63 36.2%
2.40E+01 Sb-125 2.82%
1.88E+00 Waste Class B
> 1 % Abundance Nuclide Name Abundance Curies None N/A N/A Waste Class C
> 1 % Abundance Nuclide Name Abundance Curies Co-60 3.4%
2.10E+01 Ni-59 1.35%
8.30E+00 Ni-63 93.14%
5.74E+02 Total Combined
> 1 % Abundance Nuclide Name Abundance Curies H-3 1.69%
1.15E+01 Fe-55 1.98%
1.35E+01 Co-60 5.88%
4.01 E+01 Ni-59 1.26%
8.60E+00 Ni-63 87.6%
5.98E+02
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 30 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Solid Waste Information Table 10, Dry Active Waste (DAW) Summary Shipped from the BNPS Site Waste Volume Curies Class ft3 ml Shipped A
7.84E+03 2.22E+02 6.23E-01 B
0.00E+0O 0.O0E+00 0.00E+00 C
0.00E+00 0.O0E+00 0.00E+00 Unclassified 0.0OE+00 0.00E+0O 0.00E+00 All 7.84E+03 2.22E+02 6.23E-01 Major Nuclides for Above Table: H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-95, Tc-99, Sb-125, 1-129, Cs-137, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-244 Waste Class A
> 1 % Abundance Nuclide Name Abundance Curies H-3 8.04%
5.02E-02 Cr-51 1.5%
9.38E-03 Mn-54 1.61%
1.01 E-02 Fe-55 32.27%
2.02E-01 Co-58 9.7%
6.06E-02 Co-60 28.18%
1.76E-01 Ni-63 10.67%
6.67E-02 Zr-95 1.47%
9.21 E-03 Nb-95 2.34%
1.46E-02 Sb-125 1.29%
8.06E-03 Waste Class B
> 1 % Abundance Nuclide Name Abundance Curies None N/A N/A Waste Class C
> 1 % Abundance Nuclide Name Abundance Curies None N/A N/A Total Combined
> 1 % Abundance Nuclide Name Abundance Curies H-3 8.04%
5.02E-02 Cr-51 1.5%
9.38E-03 Mn-54 1.61%
1.01 E-02 Fe-55 32.27%
2.02E-01 Co-58 9.7%
6.06E-02 Co-60 28.18%
1.76E-01 Ni-63 10.67%
6.67E-02 Zr-95 1.47%
9.21 E-03 Nb-95 2.34%
1.46E-02 Sb-125 1.29%
8.06E-03
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 31 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Solid Waste Information Table 11, Irradiated Components Summary Shipped from the BNPS Site Waste Volume Curies Class ft3 m3 Shipped A
O.OOE+OO O.OOE+OO O.OOE+OO 8
O.OOE+OO O.OOE+OO O.OOE+OO C
O.OOE+OO O.OOE+OO O.OOE+OO Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides for Above Table: NIA Waste Class A
~ 1 % Abundance Nuclide Name Abundance Curies None NIA NIA Waste Class B
~ 1 % Abundance Nuclide Name Abundance Curies None NIA NIA Waste Class C
~ 1% Abundance Nuclide Name Abundance Curies None NIA NIA Total Combined
~ 1 % Abundance Nuclide Name Abundance Curies None NIA NIA
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 32 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Solid Waste Information Table 12, Other Waste Summary Shipped from the BNPS Site Waste Volume Curies Class ft3 m3 Shipped A
8.34E+02 2.36E+01 1.21 E-02 B
0.00E+00 0.00E+O0 0.O0E+00 C
0.00E+00 0.0OE+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 8.34E+02 2.36E+01 1.21 E-02 Major Nuclides for Above Table: H-3, C-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-95, Tc-99, Sb-125, 1-129, Cs-137, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-244 Waste Class A
~ 1 % Abundance Nuclide Name Abundance Curies Cr-51 13.82%
1.68E-03 Mn-54 1.43%
1.73E-04 Fe-55 22.78%
2.76E-03 Co-58 24.31%
2.95E-03 Co-60 18.88%
2.29E-03 Ni-63 6.78%
8.23E-04 Zr-95 4.19%
5.09E-04 Nb-95 3.09%
3.75E-04 Waste Class B
~ 1 % Abundance Nuclide Name Abundance Curies None N/A N/A Waste Class C
~ 1 % Abundance Nuclide Name Abundance Curies None N/A N/A Total Combined
~ 1 % Abundance Nuclide Name Abundance Curies Cr-51 13.82%
1.68E-03 Mn-54 1.43%
1.73E-04 Fe-55 22.78%
2.76E-03 Co-58 24.31%
2.95E-03 Co-60 18.88%
2.29E-03 Ni-63 6.78%
8.23E-04 Zr-95 4.19%
5.09E-04 Nb-95 3.09%
3.75E-04
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 33 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Solid Waste Information Table 13, Sum of All Low-Level Waste Shipped from the BNPS Site Waste Volume Curies Class ft3 m3 Shipped A
1.26E+04 3.56E+02 6.70E+01 B
0.00E+00 0.00E+00 0.00E+00 C
1.20E+02 3.40E+00 6.16E+02 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 1.27E+04 3.59E+02 6.83E+02 Major Nuclides for Above Table: H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-95, Tc-99, Sn-117m, Sb-124, Sb-125, 1-129, Cs-137, Ce-144, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-244 Waste Class A
> 1 % Abundance Nuclide Name Abundance Curies H-3 14.29%
9.58E+00 C-14 1.39%
9.33E-01 Mn-54 2.01%
1.34E+00 Fe-55 12.04%
8.07E+00 Co-60 28.83%
1.93E+01 Ni-63 35.96%
2.41 E+01 Sb-125 2.81%
1.88E+00 Waste Class B
> 1 % Abundance Nuclide Name Abundance Curies None N/A N/A Waste Class C
> 1 % Abundance Nuclide Name Abundance Curies Co-60 3.4%
2.10E+01 Ni-63 93.14%
5.74E+02 Total Combined
> 1 % Abundance Nuclide Name Abundance Curies H-3 1.7%
1.16E+01 Fe-55 2.01%
1.37E+01 Co-60 5.9%
4.03E+01 Ni-59 1.26%
8.60E+00 Ni-63 87.53%
5.98E+02
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 34 of 36 Company: Constellation
\\ Plant: Braidwood Nuclear Power Station, Solid Waste Information Table 14, Solid Waste Disposition from the BNPS Site Number of Mode of Transportation Destination Shipments 6
Hittman Transportation Energy Solutions - Memphis 1790 Dock St. Memphis, TN 8
Hittman Transportation Energy Solutions-Bear Creek Facility 1560 Bear Creek Road, Oak Ridge, TN 6
Hittman Transportation Energy Solutions LLC., Clive, UT Clive Disposal Site - Containerized Waste Facility Clive, UT 1
Hittman Transportation Waste Control Specialists LLC Compact Waste Disposal Facility, Andrews, TX 21 Total
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 35 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Meteorological Data Summary 2.2 Joint Frequency Distributions
- 1.
Period of Record: 2023
- 2.
Stability Class: All
- a.
Periods of calm (hours): 0 Hours
- b.
Hours of Valid Data: 52,209 of 52,496
- c.
Meteorological data are reported in percentage of total for all stability classes.
- 3.
Elevation: 320 ft Wind Speed (mph)
Wind Direction
< 3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5
>24.5 N
0.85 1.97 1.35 0.01 0.00 0.00 NNE 1.16 2.12 1.07 0.04 0.00 0.00 NE 1.38 3.27 1.88 0.05 0.00 0.00 ENE 2.79 4.17 1.23 0.02 0.00 0.00 E
3.45 1.76 0.27 0.00 0.00 0.00 ESE 1.57 3.03 0.45 0.05 0.00 0.00 SE 0.51 3.29 0.95 0.06 0.00 0.00 SSE 0.49 3.37 2.16 0.41 0.02 0.00 s
0.16 1.99 3.42 1.25 0.13 0.00 SSW 0.13 1.41 2.49 1.56 0.43 0.02 SW 0.32 2.10 4.01 1.00 0.10 0.01 WSW 0.60 3.01 2.09 0.47 0.08 0.00 w
1.66 2.95 2.49 1.44 0.20 0.00 WNW 1.66 2.54 3.15 1.36 0.05 0.00 NW 1.45 2.30 1.24 0.10 0.00 0.00 NNW 1.07 2.55 1.69 0.11 0.00 0.00 Total 19.25 41.84 29.95 7.92 1.01 0.03 Total 4.18 4.39 6.58 8.21 5.48 5.1 4.81 6.45 6.95 6.04 7.54 6.25 8.75 8.76 5.09 5.42 100
Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 36 of 36 Company: Constellation I Plant: Braidwood Nuclear Power Station, Meteorological Data Summary 2.3 Stability class Table 15, Classification of Atmospheric Stability Stability Condition Pasquill Categories Percentage Extremely Unstable A
4.73%
Moderately Unstable B
5.57%
Slightly Unstable C
6.46%
Neutral D
40.52%
Slightly Stable E
28.26%
Moderately Stable F
10.20%
Extremely Stable G
4.26%