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| =Text= | | =Text= |
| {{#Wiki_filter:Carl Crawford Plant Manager Nine Mile Point 348 Lake Rd. | | {{#Wiki_filter:}} |
| Oswego, NY 13126 (315) 349-5205 Constellatione Carl.Crawforde-Constellation.com
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| 10 CFR 50.36a 10 CFR 72.44 (d )( 3 )
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| Technical Specifications NMP1L3581 April 30, 2024
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| U.S. Nuclear Regulatory Commission Attn: Document Contro l Desk Washington, DC 20555-0001
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| Nine Mile Point Nuclear Station , Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos . 50-220 and 50-410
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| Independent Spent Fuel Storage Ins tallation (ISFS I)
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| ISFSI Docket No . 72-1036
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| ==Subject:==
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| 2023 Radioactive Effluent Release Report for Nine Mile Point Un its 1 and 2
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| In accordance with 10 CFR 50.36a, and the Nine Mile Point Un it 1 (NMP1) and Nine Mile Point Unit 2 (NMP2 ) Technica l Specifications, enclosed are the Radioactive Effluent Release Reports for NMP1 and NMP2 for the period of January through December 2023. This letter also satisfies the annual efflu e nt reporting requirements for the ISFSI required by 10 CFR 72.44 (d)(3 ).
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| The format used for the effluent data is out lined in Appendix B of Regulatory Guide 1.21, Revision
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| : 1. Du ring the reporting period, NMP1, NMP2, and the ISFSI did not exceed any 10 CFR 20, 10 CFR 50, 10 CFR 72 , Technica l Specification, or ODCM limits for gaseous or liquid effluents.
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| Sho uld yo u h ave questions regarding the information in this submittal, please contact Jeremy Kerling, Manager, Site Chemistry and Radwaste , at (315 ) 349-5226.
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| Sincerely,
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| Nicholas A. Tryt Director Site Operations
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| For Carl Crawford Plant Manager, Nine Mile Point Nu clear Station Constellation Generation Company, LLC
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| NAT/ EEK 2023 RERR April 30, 2024 Page 2
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| ==Enclosures:==
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| (1) Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2023 (2) Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2023
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| Cc: NRC Regional Administrator, Region 1 NRC Project Manager NRC Resident Inspector R. Rolph, NRC Constellation w PRIDE - IN THE POINT
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| Nine Mile Point Clean Energy Center
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| Unit 1
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| 2023 Radioactive Effluent Release Report Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 of 40
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| * Company: Constellation
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| * I Plant: Nine Mile Point Unit 1
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| Page intentionally left blank Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 2 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS ................................................................................. 4 2.0 EXECUTIV*E
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| ==SUMMARY==
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| ............................................................................................................ 6 2.1 Comparison to. Regulatory Limits .................................................................................... 7
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| ==3.0 INTRODUCTION==
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| .......................................................................................................................... 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 for Gaseous and Liquid Effluent Doses ............................................ _. 15 4.2 40 CFR 190 Regulatory Dose Limits for a Member of the Public ................... _ ............... 16 4.3 Measurements and Approximations of Total Radioactivity ................................. , ........... 17 4.4 Onsite Doses (Within Site Boundary) ............................................................................. 19 5.0 SUPPLEMENTAL INFORMATION ....................................................... , .................... , .............. 20 5.1 Land Use Census Changes .............. * ............................................................................. 20 5.2 Meteorological Data ......................................................................................................... 20 5.3 Effluent Monitoring System lnoperability ....................................................................... 20 5.4 Offsite Dose Calculation Manual (ODCM) Changes ........................................................ 20 5.5 Process Control Program (PCP) Changes .................................................................... 20 5.6 Radioactive Waste Treatment System Changes ........................................................... 20 5.7 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program .................... 20 5.8 Carbon-14 ................................................................... : .................................................. 21 5.9 Errata/Corrections to Previous ARERRs ....................................................................... 22
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| : 5. to Other Information ........................................................................................... * ................ 22 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM ................ 23 7.0 BIBLIOGRAPHY ...................................................................................................................... 24 TABLES Table 1; Nine Mile Point Unit 1. Dose Comparison to 1 O CFR 50 Appendix I Limits ................................. 7 Table 2, Maximum Dose Received by a Member of the Public in an Unrestricted Area During 2023 Compared to EPA 40 CFR 190 Limits ..................................................................................................... 8 Table 3, Onsite Doses (Within Site Boundary) ...................................................................................... 19 Table 4, Estimated C-14 Activity Released From NMP1, NMP2, and JAF in ~023 ............................... 21 Table 5, Groundwater Protection Program Monitoring Well Results ..................................................... 23 Table 6, Average. Energies, Batch & Abnormal Releases .................................................................... 25 Table 7, Gaseous Effluents - Summation of All Releases, Elevated and Ground Level. ...................... 26 Table 8, Gaseous Effluents - Elevated Release Continuous Mode ..................................................... 27 Table 9, Gaseous Effluents - Elevated Release :Batch Mode .............................................................. 28 Table 10, Gaseous Effluents - Ground_Release Continuous Mode ........ : ............................................. 29 Table 11, Gaseous Effluents - Ground Release Batch Mode .............................................................. 30 Table 12, Liquid Effluents - Summation of All Releases ...................................................................... 31 Table 13, Liquid Effluents Released Batch Mode ................................................................................. 32 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 3 of40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| Table 14, Liquid Effluents Released Continuous Mode ......................................................................... 33 FIGURES Figure 1, Pressurized Water Reactor (~WR) [1] ....................... '. .............................................................. 9 Figure 2, Boilin,g 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 , Effluent Summary Tables ..... , ............................ : ........... :**** .. ***** .. ******* ........................... 25 , Solid Waste Information ................................................................................................ 34 ATTACHMENTS FOLLOWING BOTH SUBMITTALS , Classification of Atmospheric Stability and Joint Frequency Tables for 2023 ERRATA/CORRECTIONS TO PREVIOUS ARERRS , Errata and Corrections to the 2021 NMP1 and NMP2 ARERRs , Errata and Corrections to the 2022 NMP1 ARERR , Errata and Corrections to the 2022 NMP2 ARERR , Classification of Atmospheric Stability and Joint Frequency Tables for 2022 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 4 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 1.0 LIST OF ACRONYMS AND DEFINITIONS
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| : 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.
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| : 2. BWR: Boiling Water Reactor
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| : 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.
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| : 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.
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| : 5. Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on total counts accumulated.
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| : 6. Critical Organ (Max Organ): That part of the body that is most susceptible to radiation damage under the specific conditions under consideration.
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| : 7. Curie (Ci): A measure of radioactivity; equal to 3.7 x 10 10 disintegrations per second, or 2.22 x 1012 disintegrations per minute.
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| : 8. Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.
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| : 9. Grab Sample: A single discrete sample drawn at one point in time.
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| : 10. Indicator: A sampling location that is potentially affected by plant effluents due to its proximity and/or direction from the plant.
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| : 11. 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.
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| : 12. ISFSI: Independent Spent Fuel Storage Installation
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| : 13. Lower Limit of Detection (LLD): 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. LLDs are specified by a regulator, such as the NRG, and are typically listed in the ODCM.
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| : 14. Minimum Detectable Activity (MDA): 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%
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| probability of falsely concluding that a blank observation represents a true signal.
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| : 15. Minimum Detectable Concentration (MDC): Essentially synonymous with MDA for the purposes of radiological monitoring.
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 5 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| : 16. Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.
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| : 17. Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x10 6 disintegrations per minute.
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| : 18. millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.
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| : 19. milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X- or gamma radiation.
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| : 20. N/A: Not Applicable
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| : 21. NEI: Nuclear Energy Institute
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| : 22. NRC: Nuclear Regulatory Commission
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| : 23. ODCM: Offsite Dose Calculation Manual
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| : 24. OSLO: Optically Stimulated Luminescence Dosimeter
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| : 25. Protected Area: The fenced area immediately surrounding the Plant. Access to the protected area requires a security badge or escort.
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| : 26. PWR: Pressurized Water Reactor
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| : 27. REC: Radiological Effluent Control
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| : 28. REMP: Radiological Environmental Monitoring Program
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| : 29. Restricted Area: Any area to which access is limited by the licensee for the protection of individuals from exposure to radiation and radioactive materials.
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| : 30. Total Effective Dose Equivalent (TEDE): The sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
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| : 31. TLD: Thermoluminescent Dosimeter
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| : 32. TRM: Technical Requirements Manual
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| : 33. Technical Specifications (TS): Part of an NRC license authorizing the operation of a nuclear production or utilization facility. A Technical Specification establishes requirements for items such as safety limits, limiting safety system settings, limiting control settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls.
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| : 34. Unrestricted Area: Any area to which access is neither limited nor controlled by the licensee.
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 6 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 2.0 EXECUTIVE
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| ==SUMMARY==
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| The Nine Mile Point (NMP) Radiological Effluent Control (REC) Program was established to ensure compliance with NMP Technical Specifications, 10 CFR 20, 10 CFR 50, and 40 CFR 190, and to assure that the release of radioactive materials in plant effluents and the resultant dose to members of the public is kept "as low as reasonably achievable" (ALARA). The dose calculation methodology implemented by the station as described in the Offsite Dose Calculation Manual(s) (ODCMs) is consistent with the methodology provided in the following US NRG Regulatory Guidance for Power Reactors:
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| * Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1
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| * Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1
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| * Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1
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| Doses to members of the public as a result of plant operation during 2023 were calculated to be a fraction of the applicable regulatory limits and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1, Comparison to Regulatory Limits.
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| The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements, NMP Technical Specifications, and 10 CFR 50.36(a). The ARERR 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.
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| In addition to monitoring radioactive effluents, Nine Mile Point and James A.
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| FitzPatrick Clean Energy Center (JAF) share a Radiological Environmental Monitoring Program (REMP). The REMP is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 1 O CFR 20, 40 CFR 190, and 1 O CFR 72. Samples are collected from the aquatic and terrestrial pathways applicable to the JAF/NMP site. Aquatic pathways include fish from Lake Ontario, surface water, and lakeshore sediment.
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| Terrestrial pathways include airborne particulate and radioiodine, milk, food products, and direct radiation.
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| Data from the REMP is published in the JAF/NMP Annual Radiological Environmental Operating Report (AREOR), which can be found on the NRC's website:
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| https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific reports/nmp1-2.html Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 7 of 40 Companv: Constellation I Plant: Nine Mile Point Unit 1
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| 2.1 Comparison to Regulatory Limits
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| Table 1 provides a summary of the maximum dose received by a member of the public in an unrestricted area in 2023 from all gaseous and liquid effluents from Nine Mile Point Unit 1 in comparison with 10 CFR 50 Appendix I limits.
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| Table 1, Nine Mile Point Unit 1 Dose Comparison to 1 0 CFR 50 Appendix I Limits1
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| Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual2
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| % of Limit * * * *
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| * Liquid Effluent Dose Limit, :,:~jrriit;{ '*\\. ,>/ i/ c* ~ \\~Jnr,~'.rr( . '~;:.~*:tfirernr:
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| Any Organ Max Organ Dose 2 * * * * *
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| % of Limit * * * *
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| * Gaseous Effluent Dose Limit, Gamma Air Dose * *
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| * Gamma Air % of Limit * * * * *
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| (Noble Gas)
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| Gaseous Effluent Dose Limit, Beta Air Dose * * * *
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| * Beta Air (Noble Gas) % ofUmit * * * *
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| * Gaseous Effluent Organ Dose Limit (lodine-131, Max Organ Dose 2 6.586-02 2.52E-02 4.44E-02 4.87E-02 1.84E-01 lodine-133, Tritium, Particulates with % of Limit 8. 78E-01 3.36E-01 5.92E-01 6.50E:-01 1.23E+00
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| > 8-day half-life)
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| 1 Doses based on quarterly and annual limits, on a per reactor basis.
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| 2 The sum of quarterly max organ doses may not equal the annual max organ dose if the quarterly max organ differs from the annual max organ.
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| 3 If activity was not detected for the period in question, (*) indicates no dose.
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 8 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| Table 2 provides a summary of the maximum dose received by a member of the public in an unrestricted area in 2023 as a result of operations at NMP1, NMP2, and JAF, evaluated against 40 CFR 190 limits ..
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| Table 2, Maximum Dose Received by a Member of the Public in an Unrestricted Area During 2023 Compared to EPA 40 CFR 190 Limits
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| Dose Limit 6.89E-06 9.0SE-02 2.29E-01 2.29E-01 4.16E-02. 2.0SE-01 2.0SE-01 2._69E-01 2.69E-01 2.69E-01 4.01 E-01 7.06E-01 7.06E-01 1.61E+00 9.41E-01 2.82E+00 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 9 of 40 Companv: Constellation I Plant: Nine Mile Point Unit 1
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| : 3. 0 INTRODUCTION
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| 3.1 About Nuclear Power
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| 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 gene rated 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 bo iled, and the steam is used to turn the turbine generator for power production.
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| Conto inmcnt Struct1re
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| Figure 1, Pressurized Water Reactor ( PWR ) [1]
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| Annual Radioactive Effluent Release Report I YEAR : 2023 I Page 10 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 3.1 (Continued)
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| Con tainment Stru cture
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| Figure 2 , Boiling Water Reactor (BWR) [2]
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| 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).
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| Nuclear fission occurs when certain nuclides (primarily U-233 , U-235 , or Pu-239 )
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| absorb a neutron and break into several smaller nuclides (called fission products ) as well as producing some additional neutrons.
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| 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 /o r 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.
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 1 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 3.2 About Radiation Dose
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| Ionizing radiation , including alpha , beta , and gamma rad iation from radioac tive deca y, has enough energy to b reak 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 .
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| Space (background)
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| (5%)
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| Terrestrial (background)
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| (3%)
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| Radon & thoron (background)
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| (37%)
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| Computed tomograptiy (medica l)
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| (24%)
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| Industrial
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| (<0.1o/,)
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| Nuclear medicine Occupational (medical) (<0. 1%)
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| (12 %) Consumer Conventional (2%)
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| lnterventional fluoroscopy radiography / fluoroscopy (medical)
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| (medical) (5%)
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| (7%)
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| Figure 3 , Sources of Radiation Exposure (NCRP Report No . 160) [3]
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 12 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 3.2 (Continued)
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| 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 (31 O 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%
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| 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.
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| 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].
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 13 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 3.3 About Dose Calculation
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| Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possib le 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 , includ ing : Ingestion of radionuclides in food or water ; Inhalation of radionuclides in air; Im mersion in a plume of noble gases ; and Direct Radiation from the ground , the plant or from an elevated plume .
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| . Liv est ock products
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| C)
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| : Ra diation
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| ... 0 ~ o : Radionuclide s Mar in e produc?s * "' : Beh,vior of radionu<:li dos
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| Figure 4 , Potential e x posure pathways to Members of the Publ ic due to Plant Operations [6]
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| 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.
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| 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 nucl ide concentration will be in air, water , on the ground , or in food products based on plant effluent releases. Release points are continuously monitored to quant ify what concentrations of nuclides are being released. For gaseous releases meteorological data is used to determine how much of the released activity w ill be present at a given location outside of the plant either deposited onto the ground or in gaseous form .
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| 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 rece ive . Inhalat ion dose is calculated by determining the concentration of nuclides and how much a ir is breathed by the individual.
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 14 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 3.3 (Continued)
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| 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.
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| Each year a Land Use Census is performed to determine what potential dose pathways currently exist within a five-mile radius around the plant, the area most affected by plant operations. The Annual Land Use Census identifies the locations of vegetable gardens, nearest residences, milk animals and meat animals. The data from the census is used to determine who is the likely to be most exposed to radiation dose as a result of plant operation.
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| 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.
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| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 15 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS
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| 4.1 Regulatory Limits for Gaseous and Liquid Effluent Doses
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| : 1. Fission and Activation gases:
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| : a. The dose rate limit of noble gases released in gaseous effluents fron:i the site to areas at and beyond the site boundary shall be:
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| : 1) Less than or equal to 500 mrem/year to the total body
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| : 2) Less than or equal to 3000 mrem/year to the skin
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| : b. The 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:
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| : 1) Quarterly
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| a) Less than or equal to 5 mrads gamma
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| b) Less than or equal to 10 mrads beta
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| : 2) Yearly
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| a) Less than or equal to 1 0 mrads gamma
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| b) Less than or equal to 20 mrads beta
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| : 2. Tritium, Iodines, and Particulates with Half Lives > 8 Days
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| a" The dose rate for lodine-131, lodine-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:
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| : 1) Less than or equal to 1500 mrem/yr to any organ
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| : b. The ddse to a member of the public from lodine-131, lodine-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:
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| : 1) Quarterly
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| a) Less than or equal to 7.5 mrem to any organ
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| : 2) Yearly
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| a) Less than or equal to 15 mrem to any organ Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 16 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| * 3. Liquid Effluents
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| : a. The concentration of radioactive.material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 1 0 CFR Part 20, 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 2E-04 microcuries/ml total activity.
| |
| : b. 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:
| |
| : 1) Quarterly
| |
| | |
| a) Less than or equal to 1.5 mrem total body
| |
| | |
| b) Less than or equal to 5 mrem to any organ
| |
| : 2) Yearly
| |
| | |
| a) Less than or equal to 3 mrem total body
| |
| | |
| b) Less than or equal to 10 mrem to any organ
| |
| | |
| 4.2 40 CFR 190 Regulatory Dose Limits for a Member of the Public
| |
| : 1. For any member of the. public as the result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium fuel cycle operations and to radiation from these operations, the annual dose equivalent shall not exceed:
| |
| : a. 25 millirems to the Whole Body
| |
| : b. 75 millirems to the Thyroid
| |
| : c. 25 millirems to any other organ Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 17 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| | |
| 4.3 Measurements and Approximations of Total Radioactivity
| |
| | |
| Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
| |
| : 1. Fission and Activation Gases Noble gas effluent activity is determined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.
| |
| : 2. Iodines Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.
| |
| : 3. Particulates Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample .stream and composite analysis of the filters for non-gamma emitters.
| |
| : 4. Tritium Tritium effluent activity is measured by liquid scintillation of monthly samples taken with an air spargirig/water trap apparatus. Tritium effluent activity is measured during purge and weekly when fuel is offloaded until stable tritium release rates are demonstrated.
| |
| : 5. Emergency Condenser Vent Effluents The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water. Actual isotopic concentrations are found via gamma .spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates .of gamma emitters and actual release rates are determined from post offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.
| |
| : 6. Liquid Effluents Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters. Tritium activity is estimated on the most recent analysis of the Condensate Storage Tank water. Initial release rates of Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 18 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| : 7. Solid Effluents Isotopic contents of waste shipments are determined by gamma spectroscopy analysis of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
| |
| : 8. C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code).
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 19 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| | |
| 4.4 Onsite Doses {Within Site Boundary)
| |
| | |
| Prior to September 11, 2001, the public had access to the Nine Mile Point Nuclear Learning Center (NLC; formerly known as the Energy Information Center) for purposes of obseNing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose received by a member of the public.
| |
| | |
| Following September 11, 2001, public access to the NLC has been restricted and fishing by members of the public at locations on site was prohibited. Although fishing was not conducted onsite by members of the public during 2023, the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location.
| |
| | |
| It is conseNatively assumed that the maximum exposed individual spends an average of 8 hours per week from April to December fishing from the shoreline at a location between the NLC and NMP1.
| |
| | |
| 4.4.1 Dose Pathways for Evaluation of Doses to Members of the Public Within the Site Boundary
| |
| | |
| The pathways considered for the evaluation include the inhalation pathway, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated whole body dose. The direct radiation dose pathway includes gamma plume shine, gamma plume submersion, direct shine from the NMP1, NMP2, and JAF facilities, and ground plane deposition, and is evaluated by average environmental TLD readings at the shoreline fishing location between the NLC and NMP1.
| |
| | |
| Other pathways, such as the *ingestion pathway, are not applicable since these doses are included under calculations for doses to members of the public outside of the site boundary. In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here. These include swimming, boating and wading which are prohibited at the facility.
| |
| | |
| Table 3, Onsite Doses (Within Site Boundary)
| |
| Exposure Pathway Dose (mrem)
| |
| | |
| Ground Inhalation Direct (Max Organ: Thyroid) Radiation Total (mrem)
| |
| | |
| 0.00E+00 5.66E-03 4.03E-01 4.09E-01 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 20 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 5.0 SUPPLEMENTAL INFORMATION
| |
| | |
| 5.1 Land Use Census Changes
| |
| | |
| In 2022, three new gardens were planted in the E, ESE, and SE sectors of the JAF owner-controlled area (OCA) which have since served as indicator locations for broad-leaf vegetation sampling. The gardens were planted due to a decline in local personal gardens in recent years and less sample availability.
| |
| | |
| Based on the 2023 annual land use census, there were no changes to critical receptors and no new sampling locations were required.
| |
| * 5.2 Meteorological Data
| |
| | |
| NMP and JAF share a joint meteorological monitoring program. During 2023, 74,574 hours of data were captured out of a possible 78,840 parameter hours, which represents an overall data recovery rate of 94.6%. Atmospheric stability classes as ,
| |
| measured by 200'-30' vertical temperature difference (liT) and joint frequency tables of wind speed and wind direction for each stability class are provided' in Attachment 3.
| |
| | |
| 5.3 Effluent Monitoring System lnoperability
| |
| | |
| Liquid radwaste discharge radiation monitors 11 and 12 are retired in place and were inoperable for all of 2023, as liquid batch discharges are no longer expected to occur and were not performed at NMP1 during 2023. No other effluent radiation monitors or equipment required by the ODCM were inoperable for more than 30 days in 2023.
| |
| | |
| 5.4 Offsite Dose Calculation Manual CODCM) Changes
| |
| | |
| No changes to the NMP1 ODCM were made in 2023.
| |
| | |
| 5.5 Process Control Program {PCP) Changes
| |
| | |
| There were no changes to the PCP in 2023.
| |
| | |
| 5.6 Radioactive Waste Treatment System Changes
| |
| | |
| There were no changes or modifications to the gaseous rad,ioactive waste treatment system or the liquid radioactive waste treatment system in 2023.
| |
| | |
| 5.7 Independent Spent Fuel Storage Installation (ISFSI} Monitoring Program
| |
| | |
| Information concerning the ISFSI monitoring program and 2023 annual dose can be found in the 2023 JAF/NMP Annual Radiological Environmental Operating Report, which is published on the NRC's website:
| |
| https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific reports/nmp1-2.html Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 21 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 5.8 Carbon-14
| |
| | |
| Carbon (C)-14 is a naturally occurring isotope of carbon. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
| |
| Commercial nuclear reactors also produce C-14 but in much lower amounts than those produced naturally or from weapons testing. IAEA Report Number 421 provides relevant information ori C-14 releases. In BWRs such as NMP1, NMP2, and JAF, C-14 is primarily formed via neutron activation of 170 in light-water 17Ocn,a) 14C nuclear reaction). In reactor coolant and subsequent alpha decay to 14C (abbreviated as the BWRs, the majority of the C-14 produced (>95%) is released as gaseous carbon dioxide (1 4CO2) from the Main Stack(s).
| |
| | |
| Regulations in 1 0 CFR 50.36a require that operating procedures be developed for the control of effluents and that quantities of principal radionuclides be reported. The radioactive effluents from commercial nuclear power plants over time has decreased to the point that C-14 is likely to have become a principal radionuclide in gaseous effluents.
| |
| | |
| Estimation of gaseous release of C-14 from the NMP1 and NMP2 Main Stack(s) is determined using the methodology described in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents (December 2010). The estimate is based on a normalized C-14 proc:luction rate of 5.1 Ci/GWt-yr, a gaseous release fraction of 0.99, a 14 CO2 release fraction of 0.95, and rated thermal power and Equivalent Full Power Days (EFPD) of operation for each reactor unit during 2023.
| |
| | |
| The estimated C-14 activity released from each BWR during 2023 is summarized below.
| |
| | |
| Table 4, Estimated C-14 Activity Released From NMP1, NMP2, and JAF in 2023
| |
| | |
| Gaseous 14CO2 Total 14CO2 Form BWR
| |
| * Release Release EFPD Release Release Fraction Fraction (Ci) (Ci)
| |
| | |
| NMP1 317 8.12 7.72 NMP2 0.99 0.95 356 19.63 18.64 JAF 364. 10.80 10.26 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 22 of 40 Company: Constellation* I Plant: Nine Mile Point Unit 1
| |
| | |
| 5.9 Errata/Corrections to Previous ARERRs
| |
| | |
| For the 2021 NMP1 and NMP2 ARERRs, the groundwater tritium results for 2020 were erroneously submitted. The 2021 groundwater tritium results are included in Attachment 4, Errata and Corrections to the 2021 NMP1 and NMP2 ARERRs.
| |
| | |
| Multiple errata were identified in the 2022 NMP1 ARERR. A full summary of all errata and the corrected pages in their entirety are included in Attachment 5, Errata and Corrections to the 2022 NMP1 ARERR.
| |
| | |
| 5.10 Other Information
| |
| | |
| An external vendor performs particulate gross alpha measurements for NMP and participates in a quarterly crosscheck program. In the 3 rd Quarter of 2023, for a gross alpha crosscheck sample, a disagreement was discovered between the result obtained by the vendor and the reference value. The gross alpha crosscheck is a particulate filter with a mylar cover that seals the sample to the filter. The vendor only measured the filter and the majority of the spike sample which remained on the mylar cover was not included in the reported result. Following investigation, the vendor identified that the sample was incorrectly analyzed. This was confirmed after analysis of the mylar cover was performed. When summing the results from the filter and mylar cover, the total concentration agreed with the reference value.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 23 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM
| |
| | |
| Nine Mile Point has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative-Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. Monitoring wells installed as part of GPI program are sampled and analyzed for Tritium (H-3) annually and quarterly.
| |
| | |
| Table 5, Groundwater Protection Program Monitoring Well Results
| |
| | |
| Nine Mile Point 1 and 2 Groundwater Tritium Results
| |
| * Reporting Period: January - December 2023
| |
| | |
| Well Identification # Samples # Minimum H-3 Maximum H-3 Positive Concentration Concentration Number Collected Samples (pCi/L) (pCi/L)
| |
| | |
| GMX-MW1* 1 0 <176 <176 MW-1 1 0 <172 <173 MW-5 4 0 <175 <191 MW-6 1 0 <179 <179 MW-7 1 0 <195 <195 MW-8 4 0 <176 <193 MW-9 1 4 0 <177 <197 MW-10 1 1 0 <197 <197 MW-11 1 0 <194 <194 MW-12 1 0 <196 <196 MW-13 1 0 <192 <192 MW-14* 1 *o <198 <198 MW-15 4 0 <173 <198 MW-16 1 0 <194 <194 MW-17 4 0 <174 <196 MW-18 4 0 <175 <198 MW-19 *1 0 <194 <194 MW-20 1 0 <199 <199 MW-21 1 0 <198 <198 PZ-1 2 0 <180 <197.
| |
| PZ-7 4 0 <176 <195 PZ-8 4 0 <177 <198
| |
| * Control Location 1 Sentinel well location Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 24 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 7.0 BIBLIOGRAPHY
| |
| | |
| [1] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http}/www.nrc.gov/reading rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].
| |
| [2] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading rm/basic-ref/students/ariimated-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:l/www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November2020].
| |
| [6] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:
| |
| https://www.jaea.go.jp/english/04/ntokai/houk~n/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 07-07 - Industry Ground Water Protection Initiative - Final Guidance Document, Rev .. 1,"
| |
| Nuclear Energy Institute, Washington, D.C., 2019.
| |
| [1 O] "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 Commis/on, 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 25 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Attachment 1, Effluent Summary Tables Table 6, Average Energies, Batch & Abnormal Releases
| |
| | |
| Average Energy (Fission and Activation gases - MeV):
| |
| | |
| Qrtr.1 Ey = NIA El3 = NIA Qrtr.l Ey = NIA El3 = NIA Qrtr.J Ey = NIA El3 = NIA Qrtr.1 Ey = NIA El3 = NIA
| |
| | |
| Liquid: Radwaste m Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0 Maximum Time Period for a Batch Release (hrs) 0 Average Time Period for a Batch Release (hrs) 0 Minimum Time Period for a Batch Release (hrs) 0
| |
| | |
| Total volume of water used to 1st 2nd 3rd 4th dilute the liquid effluent during release period (L)
| |
| Radwaste NIA I NIA I NIA NIA EC Vent NIA NIA NIA NIA I I I
| |
| | |
| Total volume of water available to 1st 2nd 3rd 4th dilute the liquid effluent during report period (L) Radwaste 1.05E+11 1.08E+11 I 1.36E+11 I 1.33E+11 I EC Vent NIA NIA I NIA I NIA I
| |
| | |
| Gaseous (Emergency Condenser Vent):
| |
| Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0 Maximum Time Period for a Batch Release (hrs) 0 Average Time Period for a Batch Rele.ase (hrs) 0 Minimum Time Period for a Batch Release (hrs) 0
| |
| | |
| Gaseous (Primary Containment Purge):
| |
| Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0 Maximum Time Period for a Batch Release (hrs) 0 Average Time Period for a Batch Release (hrs) 0 Minimum Time Period for a Batch Release (hrs) 0
| |
| | |
| Abnormal Releases:
| |
| A. Liquids:
| |
| I Number of Releases I 0 I I Total Activity Released I NIA I Ci
| |
| | |
| B. Gaseous:
| |
| I Number of Releases I 0 I I Total Activity Released I NIA I Ci Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 26 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 7, Gaseous Effluents - Summation of All Releases, Elevated and Ground Level
| |
| | |
| 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR%
| |
| | |
| A. Fission & Activation Gases (1)
| |
| : 1. Total Release Ci 5.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec .. .. ** ** I .. I .. I .. I .. I
| |
| | |
| B. Iodines (1)
| |
| : 1. Total Iodine - 131 Ci 2.51E-03 4.46E-04 1.38E-03 1.89E-03 3.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec 3.23E-04 5.68E-05 1.73E-04 2.37E-04
| |
| | |
| C. Particulates (1)
| |
| : 1. Particulates with Half-lives>B days Ci 4.71E-03 7.36E-03 7.63E-03 7.71E-03 3.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec 6.06E-04 9.36E-04 9.60E-04 9.?0E-04
| |
| : 3. Gross Alpha Radioactivity Curies .. .. .. . . 2.50E+01
| |
| | |
| D. Tritium (1)
| |
| : 1. Total Release Ci 4.58E+00 2.89E+00 5.35E+00 5.48E+00 5.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec 5.89E-01 3.67E-01 6.74E-01 6.89E-01
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 27 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| | |
| Table 8, Gaseous Effluents - Elevated Release Continuous Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci .. .. ** ..
| |
| Kr-85 Ci .. ** .. **
| |
| Kr-85m Ci .. .. ** ..
| |
| Kr-87 Ci .. ** .. ..
| |
| Kr-88 Ci ** .. .. **
| |
| Xe-131m Ci .. ** ** ..
| |
| Xe-133 Ci .. ** .. **
| |
| Xe-133m Ci .. ** ** ..
| |
| Xe-135 Ci .. ** ** ..
| |
| Xe-135m Ci .. ** ** **
| |
| Xe-137 Ci ** .. ** **
| |
| Xe-138 Ci .. ** ** **
| |
| | |
| Iodines (1) 1-131 Ci 2.51E-03 4.46E-04 1.38E-03 1.89E-03 1-133 Ci 9.13E-03 7.01E-03 1.67E-02 2.1.0E-02 1-135 Ci 1.18E-03 4.61E-03 2.61E-02 4.38E-02
| |
| | |
| Particulates (1 l Cr-51 Ci 1.46E-04 6.98E-05 ** **
| |
| Mn-54 Ci 2.47E-04 5.94E-04 3.89E-04 3.71 E-04 Fe-55 Ci 6.35E-04 1.41 E-03 1.31 E-03 9.66E-04 Fe-59 Ci ** 2.85E-05 ** **
| |
| Co-58 Ci 8.43E-04 1.22E-03 1.54E-03 1.64E-03 Co-60 Ci 2.29E-03 3.41 E-03 2.94E-03 3.18E-03 Zn-65 Ci 4.43E-04 5.59E-04 1.14E-03 1.04E-03 Sr-89 Ci .. ** ** **
| |
| Sr-90 Ci ** ** ** **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci 2.51 E-06 ** ** **
| |
| Cs-136 Ci ** ** .. **
| |
| Cs-137 Ci 1.09E-05 3.88E-06 1.93E-05 **
| |
| Ba-140 Ci 4.68E-05 4.22E-05 2.95E-04 5.02E-04 La-140 Ci ** .. ** ..
| |
| Ce-141 Ci .. ** .. 1.28E-05 Ce-144 Ci ** .. .. **
| |
| Nd-147 Ci ** ** .. **
| |
| Sb-124 Ci 4.12E-05 2.00E-05 .. **
| |
| | |
| H-3 (1) Ci I 3.94E+00 I 2.42E+00 I 4.53E+00 I 4.97E+00 I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 28 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 9, Gaseous Effluents - Elevated Release Batch Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci .. .. . . ..
| |
| Kr-85 Ci .. .. .. . .
| |
| Kr-85m Ci .. .. .. . .
| |
| Kr-87 Ci .. .. .. . .
| |
| Kr-88 Ci .. .. .. . .
| |
| Xe-131m Ci .. .. .. . .
| |
| Xe-133 Ci ** .. .. ..
| |
| Xe-133m Ci ** ** .. ..
| |
| Xe-135 Ci ** .. ** ..
| |
| Xe-135m Ci ** .. .. ..
| |
| Xe-137 Ci .. ** .. ..
| |
| Xe-138 Ci .. .. .. **
| |
| | |
| Iodines (11 1-131 Ci .. ** .. **
| |
| 1-133 Ci .. ** ** ..
| |
| 1-135 Ci .. ** .. **
| |
| | |
| Particulates (1 l Cr-51 Ci ** .. .. ..
| |
| Mn-54 Ci .. ** .. ..
| |
| Fe-55 Ci ** ** .. **
| |
| Fe-59 Ci ** .. .. **
| |
| Co-58 Ci ** ** ** ..
| |
| Co-60 Ci .. ** ** **
| |
| Zn-65 Ci ** ** ** ..
| |
| Sr-89 Ci ** ** ** **
| |
| Sr-90 Ci ** ** ** **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci .. ** ** **
| |
| Cs-136 Ci .. ** ** **
| |
| Cs-137 Ci ** ** ** **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci ** .. ** **
| |
| Ce-141 Ci ** ** ** **
| |
| Ce-144 Ci ** ** ** **
| |
| Nd-147 Ci ** ** .. **
| |
| | |
| H-3 (1) Ci I ** I .. I ** I ** I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 29 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 10, Gaseous Effluents - Ground Release Continuous Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci ** ** ** **
| |
| Kr-85 Ci ** ** ** **
| |
| Kr-85m Ci ** ** ** **
| |
| Kr-87 Ci ** ** ** **
| |
| Kr-88 Ci ** ** ** **
| |
| Xe-131m Ci ** ** ** **
| |
| Xe-133 Ci ** ** ** **
| |
| Xe-133m Ci ** ** ** **
| |
| Xe-135 Ci ** ** ** **
| |
| Xe-135m Ci ** ** ** **
| |
| Xe-137 Ci ** ** ** **
| |
| Xe-138 Ci ** ** ** **
| |
| | |
| Iodines (1l 1-131 Ci ** ** ** **
| |
| 1-133 Ci ** ** ** **
| |
| 1-135 Ci ** ** ** **
| |
| | |
| Particulates (1)
| |
| Cr-51 Ci ** ** ** ..
| |
| Mn-54 Ci ** ** ** **
| |
| Fe-55 Ci ** ** ** **
| |
| Fe-59 Ci ** ** ** **
| |
| Co-58 Ci ** ** ** **
| |
| Co-60 Ci ** ** ** **
| |
| Zn-65 Ci ** ** ** **
| |
| Sr-89 Ci ** ** ** **
| |
| Sr-90 Ci ** ** ** **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci ** ** ** **
| |
| Cs-136 Ci .. ** ** **
| |
| Cs-137 Ci ** ** ** **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci ** ** ** **
| |
| Ce-141 Ci ** ** ** **
| |
| Ce-144 Ci ** ** ** **
| |
| Nd-147 Ci .. ** ** **
| |
| | |
| H-3 (1) Ci I 6.46E-01 I 4.64E-01 I 8.23E 0 01 I 5.0?E-01 I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report / YEAR: 2023 / Page 30 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 11, Gaseous Effluents - Ground Release Batch Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci ** ** ** **
| |
| Kr-85 Ci ** ** ** **
| |
| Kr-85m Ci .. .. . . ..
| |
| Kr-87 Ci .. .. ** **
| |
| Kr-88 Ci ** .. ** **
| |
| Xe-131m Ci .. ** .. ..
| |
| Xe-133 Ci ** .. ** **
| |
| Xe-133m Ci ** ** ** **
| |
| Xe-135 Ci ** ** ** **
| |
| Xe-135m Ci ** ** ** **
| |
| Xe-137 Ci ** ** ** **
| |
| Xe-138 Ci ** ** ** **
| |
| | |
| Iodines (1) 1-131 Ci ** ** ** **
| |
| 1-133 Ci ** ** ** **
| |
| 1-135 Ci ** ** ** **
| |
| | |
| Particulates (1)
| |
| Cr-51 Ci ** ** ** **
| |
| Mn-54 Ci ** ** ** **
| |
| Fe-55 Ci ** ** ** **
| |
| Fe-59 Ci ** ** ** **
| |
| Co-58 Ci ** ** ** **
| |
| Co-60 Ci ** ** ** **
| |
| Zn-65 Ci ** ** ** **
| |
| Sr-89 Ci ** ** ** **
| |
| Sr-90 Ci ** ** ** **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci ** ** ** **
| |
| Cs-136 Ci ** ** ** **
| |
| Cs-137 Ci ** ** ** **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci ** ** ** **
| |
| Ce-141 Ci ** ** ** **
| |
| Ce-144 Ci ** ** ** **
| |
| Nd-147 Ci ** ** ** **
| |
| | |
| H-3 (1) Ci I ** I ** I ** I ** I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 31 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 12, Liquid Effluents - Summation of All Releases
| |
| | |
| 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR%
| |
| | |
| A. Fission & Activation Products
| |
| : 1. Total Release (not including Curies No. Releases Tritium, gases, alpha) No Releases No Releases No Releases 5.00E+01
| |
| : 2. Average diluted concentration µCi/ml No Releases No Releases No Releases No Releases during the reporting period
| |
| | |
| B. Tritium
| |
| : 1. Total Release Curies No Releases No Releases No Releases No Releases 5.00E+01
| |
| : 2. Average diluted concentration µCi/ml No Releases during the reporting period No Releases No Releases No Releases
| |
| | |
| C. Dissolved & Entrained Gases
| |
| : 1. Total Release Curies No Releases No Releases No Releases No Releases 5.00E+01
| |
| : 2. Average diluted concentration µCi/ml No Releases during the reporting period No Releases No Releases No Releases
| |
| | |
| D. Gross Alpha
| |
| : 1. Total Release Curies No Releases No Releases No Releases No Releases 5.00E+01
| |
| | |
| E. Volumes
| |
| : 1. Prior to Dilution Liters No Releases No Releases No Releases No Releases 5.00E+01
| |
| : 2. Volume of dilution water used Liters No Releases No Releases No Releases No Releases 5.00E+01 during release period
| |
| : 3. Volume of dilution water available during reporting period - Cooling Liters 1.05E+11 1.08E+11 1.36E+11 1.33E+11 5.00E+01
| |
| | |
| F. Percent of Tech. Spec. Limits Percent of Quarterly Whole Body % No Releases Dose Limit (1.5 mrem) No Releases No Releases No Releases Percent of Annual Whole Body Dose % No Releases Limit to Date (3 mrem) No Releases No Releases No Releases Percent of Quarterly Organ Dose % No Releases Limit (5 mrem) No Releases No Releases No Releases Percent of Annual Organ Dose Limit % No Releases No Releases No Releases No Releases to Date (10 mrem)
| |
| Percent of 1 0CFR20 Concentration % No Releases Limit No Releases No Releases No Releases Percent of Dissolved or Entrained % No Releases Noble Gas Limit (2.00E-04 uCi/ml) No Releases No Releases No Releases
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 32 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 13, Liquid Effluents Released Batch Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission & Activation Products Na-24 Ci No Releases No Releases No Releases No Releases Cr-51 Ci No Releases No Releases No Releases No Releases Mn-54 Ci No Releases No.Releases No Releases No Releases Mn-56 Ci No Releases No Releases No Releases No Releases Fe-55 Ci No Releases No Releases No Releases No Releases Fe-59 Ci No Releases No Releases No Releases No Releases Co-60 Ci No Releases No Releases No Releases No Releases Ni-65 Ci No Releases No Releases No Releases No Releases Cu-64 Ci No Releases No Releases No Releases No Releases Zn-65 Ci No Releases No Releases No Releases No Releases Sr-89 Ci No Releases No Releases No Releases No Releases Sr-90 Ci No Releases No Releases No Releases No Releases Zr-95 Ci No Releases No Releases No Releases No Releases Nb-95 Ci No Releases No Releases No Releases No Releases Mo-99 Ci No* Releases No Releases No Releases No Releases 1-133 Ci No Releases No Releases No Releases No Releases Cs-134 Ci No Releases No Releases No Releases No Releases Cs-136 Ci No Releases No Releases No Releases No Releases Cs-137 Ci No Releases No Releases No Releases No Releases Ba-140 Ci No Releases No Releases No Releases No Releases La-140 Ci No Releases No Releases No Releases No Releases Ce-141 Ci No Releases No Releases No Releases No Releases Ce-144 Ci No Releases No Releases No Releases No Releases
| |
| | |
| Dissolved - or Entrained Ci I No Releases I No Releases I No Releases I No Releases I
| |
| | |
| H-3 Ci I No Releases j No Releases j No Releases j No Releases I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 33 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 14, Liquid Effluents Released Continuous Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission & Activation Products Na-24 Ci No Releases No Releases No Releases No Releases Cr-51 Ci No Releases No Releases No Releases No Releases Mn-54 Ci No Releases No Releases No Releases No Releases Mn-56 Ci No Releases No Releases No Releases No Releases Fe-55 Ci No Releases No Releases No Releases No Releases Fe-59 Ci No Releases No Releases No Releases No Releases Co-60 Ci No Releases No Releases No Releases No Releases Ni-65 Ci No Releases No Releases No Releases No Releases Cu-64 Ci No Releases No Releases No Releases No Releases Zn-65 Ci No Releases No Releases No Releases No Releases Sr-89 Ci No Releases No Releases No Releases No Releases Sr-90 Ci No Releases No Releases No Releases No Releases Zr-95 Ci No Releases No Releases No Releases No Releases Nb-95 Ci No Releases No Releases No Releases No Releases Mo-99 Ci No Releases No Releases No Releases No Releases 1-133 Ci No Releases No Releases No Releases No Releases Cs-134 Ci No Releases No Releases No Releases No Releases Cs-136 Ci No Releases No Releases No Releases No Releases Cs-137 Ci No Releases No Releases No Releases No Releases Ba-140 Ci No Releases No Releases No Releases No Releases La-140 Ci No Releases. No Rele*ases No Releases No Releases Ces141 Ci No Releases No Releases No Releases
| |
| * No Releases Ce-144 Ci No Releases No Releases No Releases No Releases
| |
| | |
| Dissolved - or Entrained Ci I No Releases I No Releases I No Releases I No Releases I
| |
| | |
| H-3 Ci I No Releases I No Releases I No Releases I No Releases I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Rad ioactive Effluent Release Report I YE A R: 2023 I Page 34 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Attachment 2, Solid Waste Information
| |
| | |
| NRC Reg u latory Gulde 1.21 Aepor1 Solid Waste Shipped Offtite for Olsposa l and Estimates of Ma Jot Nuclide& b)' wute Clast and Stream Du ring Period From : 01/0112023 lo 12/31/2023
| |
| | |
| O.OOE+OO O.OOE+OO O.OOE+OO Al 1.3SE+03 3.81E+01 2.25£+01 Ma jor Nuclide* for the Above Table
| |
| * H*3, C*14, Mn,54 . Fe,ss, Co-60, NJ-63, Zn-85. s,-~o. Tc-99, 1-12&, Cs-137, Pu-~sa . Pu,?39 , Pu ,241 ,
| |
| Atn-241 ,
| |
| | |
| 0,, Adfe Wa* (OAW)
| |
| ..... Cud ..
| |
| CIIN ftl
| |
| | |
| U__.led O.OOE+OO O.OOE+OO
| |
| | |
| Mafor NuclklH for the Above Table :
| |
| H-3, C-14. Cr,51. Mn*5-4, Fa,55, Fa -59, Cc>-58, Co-60, Ni-63, Zn-65, Sr-90, Tc:-99, 1*129, Ci-137 , Pu -238, P
| |
| * 9 Pu 41 A
| |
| * 4
| |
| | |
| Unclullied o .ooe+oo O.OOE+OO Alf O.OOE Major Nuc:JidH for the Above Table :
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 35 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| NRC Regul a tory Guide 1.21 Report Solid Waste Shipped Off site tor Disposal and Estimates of Ma)or Nuclldes by Waste Class and Stream During Period From : 01/01/2023 to 12/31/2023
| |
| .... Yolltat **
| |
| Cleu "'
| |
| | |
| UnclaMHled O.OOE+OO Alt O.OOE+OO O.OOE+OO Major Nuclides tor the Above Table :
| |
| | |
| Su* 01 All low-le.ti W11tt lhlpptd Fro* ...
| |
| Cul'IH tt* ** Shipped
| |
| | |
| Unctasalfied O.OOE+OO O.OOE+OO All 1.~E+04 3.85E+02 3.31E+01 Ma jor Nuclides for the Above Table :
| |
| H-3. C-14, Cr-51, Mn-54, Fe*SS. Fe-59, Co-58 , Co-60 , Nl-63, Zn-65 , Sr-90, Tc-99, 1-129, Cs-137, Pu-2 38 ,
| |
| Pu-239, Pu -241, Am*241 , Cm *242, Cm-244 A nnual Radioactive Effluent Release Report I Y EA R : 2 02 3 I Page 36 of 40 Company: Constellation I Plant : Nine Mile Point Unit 1
| |
| | |
| NRC R egu la to ry Guld e 1.21 Activity Rep o rt So lid Waste Shipped Ollsite for Olspoql and Estimates of Major Nuclides by Shipment, Package , and Category During Period From : 01/01/2023 lo 12/31/2023 Percent Cutoff: 1.0%
| |
| | |
| A1tunc1,11ce Actlvhy (Cl)
| |
| Cr-51 70 .64% 7.52E+00 Mn-54 2 .23% 2.37E-01 Fe-55 5.01% 5.33E*01 Co-60 19.28% 2.0SE+00 Total c-ttlMd NucJldt Na ae AltUlldlllCI AcfMtr(CI)
| |
| Cr-st 70.64% 7.52E+OO Mn-54 2.23% 2.37E-01 Fe-55 5.01% 5. 33E-01 Co-6 0 19.28% 2.0SE+OO Nucllde N*** AltundlllCI ActlYlty (Cl)
| |
| Fe-55 6.00E-01
| |
| | |
| Ni-63 1.56% 3.51E-01 Zn-65 1.72% 3.86E-01 Cs-137 1.66% 3.74E-01 Total c-111nect Nuclklt N1111 Altunde11ce Acllv lty ( Cl)
| |
| Fe-55 2.67% 6.00E-01 Co-60 90.34% 2.03E+0t Nl-63 1.56% 3.51E-01 Zn-65 1.72% 3.86E-01 Cs-137 1.66% 3.74E*01 Annual Radioactive Effluent Release Report I Y EA R: 2023 I Page 37 of 40 Company: Constellation I Plant : Nine Mile Point Unit 1
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| | |
| NRC Regu lat o ry Gulde 1.21 Ac tivity Report So lid Waste Shipped Offslte for Disposal and Estimates of Major Nuc lides by Shipment, Package, and Category Outing Period From : 0 1/01/2023 10 12/31/2023 Percent Cutoff : 1.0%
| |
| 911M o t Atl
| |
| * CtMgor!M w.- CIMI A Nuclldelulfte Alnllldallce Activity (Cl)
| |
| | |
| Cr*51 22 .69% 7 .52E+00 Mn-54 1.35% 4 .48E-01 Fe-55 3.42% 1.13E+00 Co-60 67.52% 2.24E+01 Nl-63 1.2"1. 3.98E-01 Z n-65 1.31% 4 .32E*01 Cs-137 1.27% 4 .19E*01 Total Co 1111111Md N11elkMI Name A.1>1111dpce AcUvlly (C:I)
| |
| Cr-51 22 .69% 7.52E+00 Mn-54 1.35% 4 .48E*01 Fe-55 3.42% 1.13E+00 Co-60 67. 52% 2 .24E+01 Nl-63 1.2% 3 .98E-01 Zn-65 1.31% 4 .32E*01 Cs-137 1.27% 4. 19E.01 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 38 of 40 Companv: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Total Shipments by Carrier Number of Shipments per each carrier
| |
| | |
| Number of Mode of Transportation Destination Shipments 11 Hittman Transport Energy Solutions (CVAF)
| |
| Bear Creek Operations 8 Hittman Transport Energy Solutions Clive CW F Conlaineri2ed Waste Facility Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 39 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| WMG Suite 9.6.2 Report date: 3/12/2024 NRC Regulatory Gulde Shipment and Package Summary 1.21 Report
| |
| | |
| Solid Waste Shipped Oflslte for Disposal During Period from: l/1/2023 to 12/31/2023
| |
| | |
| 2/2/2023 22*1168 Energy Solutions ESUU500022 Dry Active A A LSA-11 (CVRF) Waste
| |
| | |
| 2/612023 23*1032 Energy Solullons 685207*3 Ory Active A Type A Waste (CVRF}
| |
| 2/8/2023 23-t040 Energy 685207-2 Dry Active A Type A Solulions Was1e (CVRF) 3/16/2023 23-1034 Energy ESUU400021 Ory Active A Typo A Sofutlons Waste (CVRF) 3/24/2023 23*1088 Energy ESUU500027 Dry Active A A LSA-11 Solutions Waste (CVRF).
| |
| 3/31/2023 23*1107 Energy Solulions ESUU400076 Dry Active A A LSA*II (CVRF) Waste
| |
| | |
| 6/8/2023-*-- 23~1083--*--- Energy Solutrons ESUU30060S* Dry-Aclive-- A--* M,SA-11-- -*
| |
| (eVRf')-- Waste
| |
| | |
| 6/6/2023 23-1086 Energy Solutions ESUU300689 O,y Aclive A ALSl\\-11
| |
| {CVRF) Waslo
| |
| | |
| 6/13/2023 23-1119 Energy Solutions ESUU400049 Dry Active A A LSA*II (CVRF) Waste
| |
| | |
| 6/15/2023 1039-C-0073 Energy P0703215-18 Rosins, Fillers. A Type A Solutions Clive and Evap CWF Bottoms 6/22/2023 1039*C*0075 Energy P0708125*5 Resins, Filters, A Typo A Solutions Clive and Evap CWF Bottoms 8/14/2023 1039*C*0081 Energy P0708125*13 Resins. Filters, A Type A Solullons Clive and Evap CWF Bolloms 8/21/2023 1039-C-0082 Energy Solutions P0708125*6 Rosins, FIiiers, A Type A CWF Clive and Evap Bottoms 8/28/2023 1039-C-0083 Energy P0705952-31 Resins, Filters, A Type A Solutions Clive and Evap CWF Boltoms Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 40 of 40 Company: Constellation I Plant: Nine Mile Point Unit 1
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| | |
| WMG Suite 9.6.2 Report date: 311212024 NRC Regulatory Gulde Shlpmenl and Package Summary 1.2.1 Report
| |
| | |
| Solid waste Sh1pped Olfsite for Disposal During Period from: 1/112023 lo 12131/2023 9/812023 NM P-2023-1210 Energy ESUU600070 Other Waste A Type A Solutions
| |
| {CVRF) 11/13/2023 1039-C-0086 Energy P0709436*45 Resirns, Filters, A Type A Solulicms ctive and Evap CWF Bottoms Constellation ~ PRIDE - IN THE POINT
| |
| | |
| Nine Mile Point Clean Energy Center
| |
| | |
| Unit 2
| |
| | |
| 2023 Radioactive Effluent Release Report Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| Page intentionally left blank Annual Radioactive Effluent Release Report . I YEAR: 2023 I Page 2 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS ................................................................................ 4 2.0 EXECUTIVE
| |
| | |
| ==SUMMARY==
| |
| .............. , .............................................................................................. 6 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 for Gaseous and Liquid Effluent Doses ............................................. 15 4.2 40 CFR 190 Regulatory Dose Limits for a Member of the Public .................................. *16 4.3 Measurements and Approximations of Total Radioactivity ............................................ 17 4.4 Onsite Doses (Within Site Boundary) ............................................................................. 19 5.0 SUPPLEMENTAL INFORMATION ...... * ........................ , .......................................................... , .... 20 5.1 Land Use Census Changes .......................................................................................... 20 5.2 Meteorological Data ....................................................................................................... 20 5.3 Effluent Monitoring System lnoperability ....................................................................... 20 5.4 Offsite Dose Calculation Manual (ODCM) Changes ........... : .. :********* .............................. 20 5.5 Process Control Program (PCP) Changes ..................................................................... 20 5.6 Radioactive Waste Treatment System Changes ........................................................... 20 5.7 Independent Spent Fuel Storage lnstall.ation (ISFSI) Monitoring Program .................... 20 5.8 Carbon-14 ..................................................................................................................... 21 5.9 Errata/Corrections to Previous ARERRs ....................................................................... 22 5.10 Other Information .................................... ,. ...................................................................... 22 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM ............... 23 7.0 BIBLIOGRAPHY ........................................................................................................................ 24 TABLES Table 1, Nine Mile Point Unit 2 Dose Comparison to 1 O CFR 50 Appendix I Limits ................................ 7 Table 2, Maximum Dose Received by a Member of the Public in an Unrestricted Area During 2023 Compared to EPA 40 CFR 190 Limits ..................................................... Error! Bookmark not defined.
| |
| Table 3, Onsite Doses (Within Site Boundary) ..................................................................................... 19 Table 4, Estimated C-14 Activity Released From NMP1, NMP2, and JAF in 2023 ............................... 21 Table 5, Groundwater Protection Program Monitoring Well Results ...................................................... 23 Table 6, Average*Energies, Batch & Abnormal Releases .................................................................... 25 Table 7, Gaseous Effluents - Summation of All Releases, Elevated and Ground Level. ...................... 26 Table 8, Gaseous Effluents - Elevated Release Continuous Mode ..................................................... 27 Table 9, Gaseous Effluents - Elevated Release Batch Mode .............................................................. 28 Table 10, Gaseous Effluents - Ground Release Continuous M.ode ..................................................... 29 Table 11, Gaseous Effluents - Ground Release Batch Mode .............................................................. 30 Table 12, Liquid Effluents -Summation of All Releases ...................... , ................................................ 31 Table *13, Liquid Effluents Released Batch Mode .................................................................................. 32 Annual. Radioactive Effluent Release Report I YEAR: 2023 I Page 3 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 14, Liquid Effluents Released Continuous Mode ........................................................................ 33 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 Figure4, Potential exposure pathways to Members of the Public due to Plant Operations [6] ............. 13 ATTACHMENTS , Effluent Summary Tables .............................................................................................. 25 , Solid Waste Information ................................................................................................. 34 ATTACHMENTS FOLLOWING BOTH SUBMITTALS , Classification of Atmospheric Stability and Joint Frequency Tables for 2023 ERRATA/CORRECTIONS TO PREVIOUS ARERRS , Errata and Corrections to the 2021 NMP1 and NMP2 ARERRs , Errata and Corrections to the 2022 NMP1 ARERR , Errata and Corrections to the 2022 NMP2 ARERR , Classification of Atmospheric Stability and Joint Frequency Tables for 2022 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 4 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| 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 inteNals 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. Critical Organ (Max Organ): That part of the body that is most susceptible to radiation damage under the specific conditions under consideration.
| |
| : 7. Curie (Ci): A measure of radioactivity; equal to 3. 7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.
| |
| : 8. Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thernioluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.
| |
| : 9. Grab Sample: A single discrete sample drawn at one point in time. *
| |
| : 10. Indicator: A sampling location that is potentially affected by plant effluents due to its proximity and/or direction from the plant.
| |
| : 11. 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.
| |
| : 12. ISFSI: Independent Spent Fuel Storage Installation
| |
| : 13. Lower Limit of Detection (LLD): 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. LLDs are specified by a regulator, such as the NRC, and are typically listed in the ODCM.
| |
| : 14. Minimum Detectable Activity (MDA): 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 obseNation represents a true signal.
| |
| : 15. Minimum Detectable Concentration (MDC): Essentially synonymous with -MDA for the purposes of radiological monitoring.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 5 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| : 16. Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.
| |
| : 17. Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x10 6 disintegrations per minute.
| |
| : 18. millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.
| |
| : 19. milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X- or gamma radiation.
| |
| : 20. N/A: Not Applicable
| |
| : 21. NEI: Nuclear Energy Institute
| |
| : 22. NRG: Nuclear Regulatory Commission
| |
| : 23. ODCM: Offsite Dose Calculation Manual
| |
| : 24. OSLO: Optically Stimulated Luminescence Dosimeter
| |
| : 25. Protected Area: The fenced area immediately surrounding the Plant. Access to the protected area requires a security badge or escort.
| |
| : 26. PWR: Pressurized Water Reactor
| |
| : 27. REC: Radiological Effluent Control
| |
| : 28. REMP: Radiological Environmental Monitoring Program
| |
| : 29. Restricted Area: Any area to which access is limited by the licensee for the protection of individuals from exposure to radiation and radioactive materials.
| |
| : 30. Total Effective Dose Equivalent (TEDE): The sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
| |
| : 31. TLD: Thermoluminescent Dosimeter
| |
| : 32. TRM: Technical Requirements Manual *
| |
| : 33. Technical Specifications (TS): Part of an NRG license authorizing the operation of a nuclear production or utilization facility. A Technical Specification establishes requirements for items such as safety limits, limiting safety system settings, limiting control settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls.
| |
| : 34. Unrestricted Area: Any area to which access is neither limited nor controlled by the licensee.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 6 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 2.0 EXECUTIVE
| |
| | |
| ==SUMMARY==
| |
| | |
| The Nine Mile Point (NMP) Radiological Effluent Control (REC) Program was established to ensure compliance with NMP Technical Specifications, 1 O CFR 20, 1 O CFR 50, and 40 CFR 190, and to assure that the release of radioactive materials in plant effluents and the resultant dose to members of the public is kept "as low as reasonably achievable" (ALARA). The dose calculation methodology implemented by the station as described in the Offsite Dose Calculation Manual(s) (ODCMs) is consistent with the methodology provideo in the following US NRC Regulatory Guidance for Power Reactors:
| |
| * Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine
| |
| * Releases .of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1
| |
| * Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1
| |
| * Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1
| |
| | |
| Doses to members of the public as a result of plant operation during 2023 were calculated to be a fraction of the applicable regulatory limits and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1, Comparison to Regulatory Limits.
| |
| | |
| The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements, NMP Technical Specifications, and 10 CFR 50.36(a). The ARERR 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 addition to monitoring radioactive effluents, Nine Mile Point and James A.
| |
| FitzPatrick Clean Energy Center (JAF) share a Radiological Environmental Monitoring Program (REMP). The REMP is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 1 O CFR 20, 40 CFR 190, and 1 O CFR 72. Samples are collected from the aquatic and terrestrial pathways applicable to the JAF/NMP site. Aquatic pathways include fish from Lake Ontario, surface water, and lakeshore sediment.
| |
| Terrestrial pathways include airborne particulate and radioiodine, milk, food products, and direct radiation.
| |
| | |
| Data from the REMP is published in the JAF/NMP Annual Radiological Environmental Operating Report .(AREOR), which can be found on the NRC's website:
| |
| https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific reports/nmp1-2.html Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 7 of 42 Company: Constellation / Plant: Nine Mile Point Unit 2
| |
| | |
| 2.1 Comparison to Regulatory Limits
| |
| | |
| Table 1 provides a summary of the maximum dose received by a mernber of the public in an unrestricted area in 2023 from all gaseous and liquid effluents from Nine Mile Point Unit 2 in comparison with 10 CFR 50 Appendix I limits.
| |
| * Table 1, Nine Mile Point Unit 2 Pose Comparison to 1 0 CFR 50 Appendix I Limits1
| |
| | |
| Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 2 Liquid Effluent Dose Limit, Ji:Nfit;/t;;;,;:f:/\\xL? *)($,i:t:nt~o\\;~ '.,f"s,iif~m,** :,~:t~~i;p~/1fr'1 7:f~;'Mrirtf:ii ::;'JhYr~lrr\\:,
| |
| Total Body Total Body Dose * * * * *
| |
| % of Limit * * * *
| |
| * Liquid Effluent Dose Limit, \\Qm'.ii'/ ;,_,:~i,.~:",::*:;:; <~)iir~ri"i:J :\\~rnr~m* ,, ". *~ip,r'ehj ,".: '..."\\*s.oiie.n(,,r .joJ;r;l1/2.O:
| |
| Any Organ Max Organ Dose 2 * * * * *
| |
| % of Limit * * * *
| |
| * Gaseous Effluent Dose !IJrriif ?: :t:'\\( \\:*\\~, *. :<'~':i'iif~i,t: \\'.,:s:ipr~c1.1t: : :,~.,1if~~<~, ::~:'*1:5:rr1f~~,::~: 1/1q)tr~~4:
| |
| Limit, Gamma Air Dose *
| |
| * 1.66E-08
| |
| * 1.66E-08 Gamma Air (Noble Gas) % of Limit *
| |
| * 3.31E-07
| |
| * 1.66E-07 Gaseous Effluent Dose Limit, Beta Air Dose
| |
| * 4.33E-10
| |
| * 4.33E-10 Beta Air (Noble Gas) % of Limit *
| |
| * 4.33E-09
| |
| * 2.17E-09 Gaseous Effluent Organ Pmif:T.:*:*,*;,~~;,, '.:::::?, W;$r&e:6f* f,tirMeht:~ :)'J.roi~rri:.: t.v.s)1,f~tff~: Aif~reflf}
| |
| Dose Limit (lodine-131, Max Organ D0se2 8.37E-04 7.B0E-04 1.45E-03 6.48E-04 3.58E-03 lodine-133, Tritium, Particulates with. % of Limit 1.12E-02 1.04E-02 1.94E-02 8.63E-03 2.38E-02
| |
| > 8-day half-life)
| |
| | |
| 1 Doses based on quarterly and annual limits, on a per reactor basis.
| |
| 2 The sum of quarterly max organ doses may not equal the annual max organ dose if the quarterly max organ differs from the annual max organ.
| |
| 3 If activity was not detected, (*) indicates no dose for the period ..
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 8 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Table 2 provides a summary of the maximum dose received by a member of the public in an unrestricted area in 2023 as a result of operations at NMP1, NMP2, and JAF, evaluated against 40 CFR 190 limits.
| |
| | |
| Table 2, Maximum Dose Received by a Member .of the Public in an Unrestricted Area During 2023 Compared to EPA 40 CFR 190 Limits
| |
| | |
| Dose Limit 6.89E-06 9.08E-02 2.29E-01 2.29E-01 4.16E-02 2.08E-01 2.08E-01
| |
| _.t J1f:,,,' ,, ;. ,,,,*, :" 1/ ~
| |
| DirecfBaaiation* 2.69E-01 2.69E-01 2.69E-01 4.01E-01 7.06E-01 7.06E-01 1.61E+00 9.41E-01 2.82E+00 Annual Radioactive Effluent Release Report I YEAR : 2023 I Page 9 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| ==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 Struc:tirc
| |
| | |
| Figure 1, Pressurized Water Reactor ( PWR) [1]
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 10 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 3.1 (Continued)
| |
| | |
| Cont ainm en t Stru c ture
| |
| | |
| Control Ro ds - - .
| |
| | |
| 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 so lids 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 YE A R : 2023 I Page 11 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 3.2 About Radiation Dose
| |
| | |
| Ionizing radiation , including alpha , beta , and gamma radiation from radioactive decay ,
| |
| has enough energy to break chemical bonds in tissues and result in damage to tissue or genetic material. The amount of ionization that will be generated by a given e x posure to ionizing radiation is quantified as dose . Radiation dose is generally reported in units of millirem (mrem ) in the US .
| |
| | |
| Space (background)
| |
| (5%)
| |
| | |
| Terrestrial (background)
| |
| (3%)
| |
| | |
| Radon & thoron (background)
| |
| (37 %)
| |
| | |
| Computed tomograpny (medical)
| |
| (24%)
| |
| | |
| Industrial
| |
| (<0.1 %)
| |
| | |
| Nuclear medicine Occupational (medical) (<0 .1%)
| |
| (12%) Consumer Conventiona l (2%)
| |
| lnterventiona l fluoroscopy radiography/fluoroscopy (medical) (medical)
| |
| (7%) (5%)
| |
| | |
| Figure 3 , Sources of Rad iation Ex p o sure (NCRP Report No . 160) [3)
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 12 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 3.2 (Continued)
| |
| | |
| The National Council on Radiation Protection (NCRP) has evaluated the population dose for the US and determined that the average individual is exposed to approximately 620 mrem per year [3]. There are many sources for radiation dose, ranging from natural background sources to medical procedures, air travel, and industrial processes. Approximately half (310 mrem) of the average exposure is due to natural sources of radiation including exposure to radon, cosmic radiation, and internal radiation and terrestrial due to naturally occurring radionuclides. The remaining 310 mrem of exposure is due to man-made sources of exposure, with the most significant contributors being medical (48% 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 42*
| |
| Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 3.3 About Dose Calculation
| |
| | |
| Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples . To overcome this, dose calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public , including : Ingestion of radionuclides in food or water ; Inhalation of radionuclides in air; Immersion in a plume of noble gases ; and Direct Radiation from the ground , the plant or from an elevated plume .
| |
| | |
| * . 0 * ~ 0 ** .. Livestoc k prod u cts
| |
| | |
| 0
| |
| | |
| : Radia tio n
| |
| ** 0 ~c o ; Ra dionucl ides
| |
| **** : Beha vior of ra dionuel ides M a rino prod u c?s
| |
| | |
| 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 e ither 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 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 3.3 (Continued)
| |
| | |
| For liquid releases, dilution and mixing factors are used to model the environmental concentrations in water. Drinking water pathways are modeled by determining the concentration of nuclides in the water at the point where the drinking water is sourced (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 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 enviro*nment or people living near the plant.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 15 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS
| |
| | |
| 4.1 . Regulatory Limits for Gaseous and Liquid Effluent Doses
| |
| : 1. Fission and Activation gases:
| |
| : a. The dose rate limit of noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be:
| |
| : 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. The air dose due to noble gases released in gaseous effluents from each reactor unit to areas at and beyond the site boundary shall be limited to the following:
| |
| : 1) Quarterly
| |
| | |
| a) Less than or equal to 5 mrads gamma
| |
| | |
| b) Less than or equal to 10 mrads beta
| |
| : 2) Yearly
| |
| | |
| a) Less than or equal to 1 0 mrads gamma
| |
| | |
| b) Less than or equal to 20 mrads beta
| |
| : 2. Tritium, Iodines, and Particulates with Half Lives > 8 Days
| |
| : a. The dose rate for lodine-131, lodine-133, tritium, and all radionuclide~ 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 frorrt lodine-131, lodine-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 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 16 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| : 3. Liquid Effluents
| |
| : a. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, 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 2E-04 microcuries/ml total activity.
| |
| : b. 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:
| |
| : 1) Quarterly
| |
| | |
| a) Less than or equal to 1.5 mrem total body
| |
| | |
| b) Less than or equal to 5 mrem to any organ
| |
| : 2) Yearly
| |
| | |
| a) Less than or equal to 3 mrem total body
| |
| | |
| b) Less than or equal to 10 mrem to any organ
| |
| | |
| 4.2 40 CFR 190 Regulatory Dose Limits for a Member of the Public
| |
| : 1. For any member of the public as the result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium fuel cycle operations and to radiation from these operations, the annual dose equivalent shall not exceed:
| |
| : a. 25 millirems to the Whole Body
| |
| : b. 75 millirems to the Thyroid
| |
| : c. 25 millirems to any other organ Annual Radioactive Effluent.Release Report I YEAR: 2023 I Page 17 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 4.3 Measurements and Approximations of Total Radioactivity
| |
| | |
| Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
| |
| : 1. Fission and Activation Gases Noble gas effluent activity is determined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.
| |
| : 2. Iodines Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.
| |
| : 3. Particulates Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.
| |
| : 4. Tritium Tritium effluent activity is* measured by liquid scintillation of monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity is measured during purge and weekly when fuel is offloaded until stable tritium relea_se rates are demonstrated.
| |
| : 5. Emergency Condenser Vent Effluents The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water .. Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.
| |
| : 6. Liquid Effluents Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters. Tritium activity is estimated on the most recent analysis of the Condensate Storage Tarik water. Initial release rates of Sr-89, Sr-90, and Fe-55 are estimated by applying scaling. factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results.
| |
| Annual Radioactive Effluent Release Report I YEAR:. 2023 I Page 18 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| : 7. Solid Effluents Isotopic contents of waste shipments are determined by gamma spectroscopy analysis of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
| |
| : 8. C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code).
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 19 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 4.4 Onsite Doses (Within Site Boundary)
| |
| | |
| Prior to September 11, 2001, the public had access to the Nine Mile Point Nuclear Learning Center (NLC; formerly known as the Energy Information Center) for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose receivec:l by a member of the public.
| |
| | |
| Following September 11, 2001, public access to the NLC has been restricted and fishing by members of the public at locations on site was prohibited. Although fishing was not conducted onsite by members of the public during 2023, the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location.
| |
| | |
| It is conservatively assumed that the maximum exposed individual spends an average of 8 hours per week from April to December fishing from the shoreline at a location between the NLC and NMP1.
| |
| | |
| 4.4.1 Dose Pathways for Evaluation of Doses to Members of the Public Within the Site Boundary
| |
| | |
| The pathways considered for the evaluation include the inhalation pathway, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway With the associated whole body dose. The direct radiation dose pathway includes gamma plume shine, gamma plume submersion, direct shine from the NMP1, NMP2, and JAF facilities, and ground plane deposition, and is evaluated by average environmental TLD readings at the shoreline fishing location between the NLC and NMP1.
| |
| | |
| Other pathways, such as the ingestion pathway, are not applicable since these doses are included under calculations for doses to members of the public outside of the site boundary. In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here. These include swimming, boating and wading which-are prohibited at the facility.
| |
| | |
| Table 3, Onsite Doses (Within Site Boundary)
| |
| Exposure Pathway Dose (mrem)
| |
| | |
| Ground Inhalation Direct (Max Organ: Thyroid) Radiation Total (mrem)
| |
| | |
| 0.00E+00 5.66E-03 4.03E-01 4.09E-01 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 20 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 5.0 SUPPLEMENTAL INFORMATION
| |
| | |
| 5.1 Land Use Census Changes
| |
| | |
| In 2022, three new gardens were planted in the E, ESE, and SE sectors of the JAF owner-controlled area (OCA) which have since served as indicator locations for broad-leaf vegetation sampling. The gardens were planted due to a decline in local personal gardens in recent years and less sample availability.
| |
| | |
| Based on the 2023 annual land use census, there were no changes to critical receptors and no new sampling locations were required.
| |
| | |
| 5.2 Meteorological Data
| |
| | |
| NMP and JAF share a joint meteorological monitoring program. During 2023, 74,574 hours of data were captured out of a possible 78,840 parameter hours, which represents an overall data recovery rate of 94.6%. Atmospheric stability classes as measured by 200'-30' vertical temperature difference (Lff) and joint frequency tables of wind speed and wind direction for each stability class are provided in Attachment 3.
| |
| | |
| 5.3 Effluent Monitoring System lnoperability
| |
| | |
| Liquid discharge radiation monitor 2LWS-CAB206 and associated discharge flow rate measuring devices 2LWS-FT330 and 2LWS-FT331 are retired in place and were inoperable for all of 2023, as.liquid batch discharges are no .longer expected to occur and were not performed at NMP2 durihg 2023. No other effluent radiation monitors or equipment required by the ODCM were inoperable for more than 30 days in 2023.
| |
| | |
| 5.4 Offsite Dose Calculation Manual (ODCM) Changes
| |
| | |
| No changes to the NMP2 ODCM were made in 2023.
| |
| | |
| 5.5 Process Control Program (PCP) Changes
| |
| | |
| There were no changes to the PCP in 2023.
| |
| | |
| 5.6 Radioactive Waste Treatment System Changes
| |
| | |
| There were no changes or modifications to the gaseous radioactive waste treatment system or the liquid radioactive waste treatment system in 2023.
| |
| | |
| 5.7 Independent Spent Fuel. Storage Installation (ISFSI) Monitoring Program
| |
| | |
| Information concerning the ISFSI monitoring program and 2023 annual dose can be found in the 2023 JAF/NMP Annual Radiological Environmental Operating Report, which is published on the NRC's website:
| |
| https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific reports/nmp1-2.html Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 21 of 42 Company: Constellation
| |
| * I Plant: Nine Mile Point Unit 2
| |
| | |
| 5.8 Carbon-14
| |
| | |
| Carbon (C)-14 is a naturally occurring isotope of carbon. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
| |
| Commercial nuclear reactors also produce C-14 but in much lower amounts than those produced naturally or from weapons testing. IAEA Report Number 421 provides relevant information on C-14 releases: In BWRs such as NMP1, NMP2, and JAF, C-14 is primarily formed via neutron activation of 170 in light-water reactor coolant and subsequent alpha decay to 14C (abbreviated as the 17Ocn,a) 14 C nuclear reaction). In BWRs, the majority of the C-14 produced (>95%) is released as gaseous carbon dioxide (1 4 CO2) from the Main Stack(s).
| |
| | |
| Regulations in 1 0 CFR 50.36a require that operating procedures be developed for the control of effluents and that quantities of principal radionuclides be reported. The
| |
| * radioactive effluents from commercial nuclear power plants over time has decreased to the point that C-14 is likely to have become a principal radionuclide_ in gaseous effluents.
| |
| | |
| Estimation of gaseous release of c~14 from the NMP1 and NMP2 Main Stack(s) is determined using the methodology described in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents (December 2010). The estimate is based on a normalized C-14 production rate of 5.1 Ci/Gwt-yr, a gaseous release fraction of 0.99, a 14CO2 release fraction of 0.95, and rated thermal power and Equivalent Full Power Days (EFPD) of operation for each reactor unit during 2023.
| |
| | |
| The estimated C-14 activity released from each BWR during 2023 is summarized below.
| |
| | |
| Table 4, Estimated C-14 Activity Released From NMP1, NMP2, and JAF in 2023
| |
| | |
| 14CO2 Total 14CO2 Gaseous Form BWR Release Release EFPD Release Release Fraction Fraction (Ci) (Ci)
| |
| | |
| NMP1 317 8.12 7.72 NMP2 0.99 0.95 356 19.63 18.64 JAF 364 10.80 10.26 Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 22 of 42 Company: Conste.llation I Plant: Nine Mile Point Unit 2
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| | |
| 5.9 Errata/Corrections to Previous ARERRs
| |
| | |
| For the 2021 NMP1 and NMP2 ARERRs, the groundwater tritium results for 2020 were erroneously submitted. The 2021 groundwater tritium results are included in Attachment 4, Errata and Corrections to the 2021 NMP1 and NMP2 ARERRs.
| |
| | |
| Multiple errata were identified in the 2022 NMP2 ARERR. A full summary of all errata and the corrected pages in their entirety are included in Attachment 6, Errata and Corrections to the 2022 NMP2 ARERR.
| |
| | |
| 5.10. Other Information
| |
| | |
| An external vendor performs particulate gross alpha measurements for NMP and participates in a quarterly crosscheck program. In the 3 rd Quarter of 2023, for a gross alpha crosscheck sample, a disagreement was discovered between the result obtained by the vendor and the reference value. The gross alpha crosscheck is a particulate filter with a mylar cover that seals the sample to the filter. The vendor only measured the filter and the majority of the spike sample which remained on the mylar cover was not included in the reported result. Following investigation, the vendor identified that the sample was incorrectly analyzed. This was confirmed after analysis of the mylar cover was performed. When summing the results from the filter and mylar cover, the total concentration agreed with the reference value.
| |
| | |
| J Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 23 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM
| |
| | |
| Nine Mile Point has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. Monitoring wells installed as part of GPI program are sampled and analyzed for Tritium (H-3) annually and quarterly.
| |
| | |
| Table 5, Groundwater Protection Program Monitoring Well Results
| |
| | |
| Nine Mile Point 1 and 2 Groundwater Tritium Results Reporting Period: January - December 2023
| |
| | |
| Well Identification #Samples # Minimum H-3 Maximum H-3 Positive Concentration Concentration Number Collected Samples (pCi/L) (pCi/L)
| |
| | |
| GMX-MW1* 1 0 <176 <176 MW-1 1 0 <172 <173 MW-5 4 0 <175 <191
| |
| | |
| I 0 <179 <179 MW-6 1 MW-7 1 0 <195 <195 MW-8 4 0 <176 <193 MW-9 1 4 0 <177 <197 MW-10 1 1 0 <197 <197 MW-11 1 0 <194 <194 MW-12 1 0 <196 <196 MW-13 1 0 <192 <192 MW-14* 1 0 <198 <198 MW-15 4 0 <173 <198 MW-16 1 0 <194 <194 MW-17 4 0 <174 <196 MW-18 4 0 <175 <198 MW-19 1 0 <194 <194 MW-20 1 0 <199 <199 MW-21 1 0 <198 <198 PZ-1 2 0 <180 <197 PZ-7 4 0 <176 <195 PZ-8 4 0 <177 <198
| |
| * Control Location 1 Sentinel well location Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 24 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| 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 07-07 - Industry Ground Water Protection Initiative - Final Guidance Document, Rev. 1,"
| |
| Nuclear Energy Institute, Washington, D.C., 2019.
| |
| [10] "10CFR 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: 2023 I Page 25 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Attachme~t 1, Effluent Summary Tables Table 6, Average Energies, Batch & Abnormal Releases
| |
| | |
| Average Energy (Fission and Activation gases - MeV):
| |
| | |
| Qrtr.1 Ey = N/A E[3 = N/A Qrtr.i Ey = N/A E[3 = NIA Qrtr.J Ey = 1.62E-04 E[3 = 2.07E-04 Qrtr.1 Ey = N/A E[3 = N/A
| |
| | |
| Liquid: Radwaste Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0 Maximum Time Period for a Batch Release (hrs) 0 Average Time Period for a Batch Release (hrs) 0 Minimum Time Period for a Batch Release (hrs) 0
| |
| | |
| Total volume of water used to dilute 1st 2nd 3rd 4th the liquid effluent during release period (L) Radwaste I N/A I N/A I N/A I N/A I
| |
| | |
| Total volume of water available to 1st 2nd 3rd 4th dilute the liquid effluent during report period (L) Radwaste I 9.12E+09 I 9.69E+09 I 1.22E+10 I 1.06E+10 I
| |
| | |
| Gaseous (Primary Containment Purge):
| |
| Number of Batch Releases 4 Total Time Period for Batch Releases (hrs) 8.47 Maximum Time Period for a Batch Release (hrs) 2.12 Average Time Period for a Batch Release (hrs) 2.12 Minimum Time Period for a Batch Release (hrs) 2.12
| |
| | |
| Abnormal Releases:
| |
| A. Liquids:
| |
| I Number of Releases I 0 I Total Activity Released I N/A Ci
| |
| | |
| B. Gaseous:
| |
| I Number of Releases I 0 I Total Activity Released I N/A Ci Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 26 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 7, Gaseous Effluents - Summation of All Releases, Elevated and Ground Level
| |
| | |
| 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR%
| |
| | |
| A. Fission & Activation Gases (1)
| |
| : 1. Total Release Ci ** ** 6.55E-04 I ** 5.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec ** ** 8.23E-05 ** I I I I
| |
| | |
| B. Iodines (1)
| |
| : 1. Total Iodine -131 Ci ** ** 2.93E-05 I ** 3.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec ** ** 3.69E-06 ** I I I I
| |
| | |
| C. Particulates (1)
| |
| : 1. Particulates with Half-lives>B days Ci 3.06E-04 2.73E-04 3.76E-04 2.15E-04 3.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec 3.94E-05 3.48E-05 4.73E-05 2.71 E-05
| |
| : 3. Gross Alpha Radioactivity Curies ** ** ** ** 2.50E+01
| |
| | |
| D. Tritium (1)
| |
| : 1. Total Release Ci 2.01E+01 2.16E+01 2.35E+01 1.95E+01 5.00E+01
| |
| : 2. Average Release Rate for Period µCi/sec 2.59E+00 2.74E+0O 2.95E+00 2.46E+OO
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 27 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 8, Gaseous Effluents - Elevated Release Continuous Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci ** ** ** **
| |
| Kr-85 Ci ** ** ** **
| |
| Kr-85m Ci ** ** ** **
| |
| Kr-87 Ci ** ** ** **
| |
| Kr-88 Ci ** ** ** **
| |
| Xe-131m Ci ** ** ** **
| |
| Xe-133 Ci ** ** ** **
| |
| Xe-133m Ci ** ** ** **
| |
| Xe-135 Ci ** ** ** **
| |
| Xe-135m Ci ** ** ** **
| |
| Xe-137 Ci ** ** .. **
| |
| Xe-138 Ci ** ** ** **
| |
| Xe-127 Ci ** ** ** ..
| |
| | |
| Iodines (1) 1-131 Ci .. ** 2.93E-05 **
| |
| 1-133 Ci ** ** 2.57E-04 1.75E-05 1-135 Ci ** ** ** ..
| |
| | |
| Particulates (1 l Cr-51 Ci .. .. ** **
| |
| Mn-54 Ci .. ** 5.26E-07 **
| |
| Fe-55 Ci ** ** .. ..
| |
| Fe-59 Ci ** .. .. **
| |
| Co-58 Ci .. ** ** **
| |
| Co-60 Ci 1.0BE-04 9.93E-05 1.27E-04 8.90E-05 Zn-65 Ci ** ** ** ..
| |
| Sr-89 Ci .. ** ** ..
| |
| Sr-90 Ci ** ** .. **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci ** ** ** **
| |
| Cs-136 Ci ** ** ** **
| |
| Cs-137 Ci .. ** .. **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci ** ** ** **
| |
| Ce-141 Ci .. ** .. ..
| |
| Ce-144 Ci .. .. .. ..
| |
| Nd-147 Ci .. .. ** ..
| |
| | |
| H-3 (1) Ci I 1.38E+01 I 1.56E+01 I 1.60E+01 I 1.37E+01 I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 28 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 9, Gaseous Effluents - Elevated Release Batch Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci ** ** ** **
| |
| Kr-85 Ci ** ** ** **
| |
| Kr-85m Ci ** ** ** **
| |
| Kr-87 Ci ** ** ** **
| |
| Kr-88 Ci ** ** ** **
| |
| Xe-131m Ci ** ** ** **
| |
| Xe-133 Ci ** ** ** **
| |
| Xe-133m Ci ** ** ** **
| |
| Xe-135 Ci ** ** 6.55E-04 **
| |
| Xe-135m Ci ** ** ** **
| |
| Xe-137 Ci ** ** ** **
| |
| Xe-138 Ci ** ** ** **
| |
| Xe-127 Ci ** ** ** **
| |
| | |
| Iodines (1) 1-131 Ci .. ** ** **
| |
| 1-133 Ci ** ** ** **
| |
| 1-135 Ci ** ** ** **
| |
| | |
| Particulates (1)
| |
| Cr-51 Ci ** ** ** **
| |
| Mn-54 Ci ** ** ** **
| |
| Fe-55 Ci ** .. ** **
| |
| Fe-59 Ci ** ** ** **
| |
| Co-58 Ci ** ** ** **
| |
| Co-60 Ci ** ** 2.36E-05 **
| |
| Zn-65 Ci ** ** ** **
| |
| Sr-89 Ci ** ** ** **
| |
| Sr-90 Ci ** ** ** **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci .. ** ** **
| |
| Cs-136 Ci ** ** ** **
| |
| Cs-137 Ci ** ** 6.23E-06 **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci ** ** ** **
| |
| Ce-141 Ci ** ** ** **
| |
| Ce-144 Ci ** ** ** **
| |
| Nd-147 Ci ** ** ** **
| |
| | |
| H-3 (1l Ci I ** I 1.52E-01 I 1.52E-01 I ** I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 29 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 10, Gaseous Effluents - Ground Release Continuous Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci ** ** ** **
| |
| Kr-85 Ci .. ** ** **
| |
| Kr-85m Ci ** ** ** **
| |
| Kr-87 Ci .. ** ** **
| |
| Kr-88 Ci ** ** ** **
| |
| Xe-131m Ci ** ** ** **
| |
| Xe-133 Ci ** ** ** **
| |
| Xe-133m Ci ** ** ** **
| |
| Xe-135 Ci ** ** ** **
| |
| Xe-135m Ci ** ** ** **
| |
| Xe-137 Ci ** ** ** **
| |
| Xe-138 Ci ** ** ** **
| |
| Xe-127 Ci ** ** ** **
| |
| | |
| Iodines (1) 1-131 Ci .. .. .. . .
| |
| 1-133 Ci .. .. .. ..
| |
| 1-135 Ci .. .. .. . .
| |
| | |
| Particulates (1 l Cr-51 Ci .. .. .. . .
| |
| Mn-54 Ci 3.25E-06 .. .. . .
| |
| Fe-55 Ci .. .. .. . .
| |
| Fe-59 Ci .. .. .. ..
| |
| Co-58 Ci .. .. .. . .
| |
| Co-60 Ci 1.95E-04 1.74E-04 2.19E-04 1.26E-04 Zn-65 Ci ** ** .. **
| |
| Sr-89 Ci ** ** .. ..
| |
| Sr-90 Ci .. .. .. ..
| |
| Nb-95 Ci .. .. .. . .
| |
| Cs-134 Ci ** ** .. **
| |
| Cs-136 Ci ** .. ** ..
| |
| Cs-137 Ci ** ** ** **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci .. ** .. **
| |
| Ce-141 Ci .. ** ** **
| |
| Ce-144 Ci ** .. ** ..
| |
| Nd-147 Ci .. .. ** ..
| |
| | |
| H-3 (1) Ci I 6.36E+00 I 5.86E+00 I 7.27E+00 I 5.89E+00 I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 30 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 11, Gaseous Effluents - Ground Release Batch Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission Gases (1)
| |
| Ar-41 Ci ** ** ** **
| |
| Kr-85 Ci ** ** ** **
| |
| Kr-85m Ci ** ** ** **
| |
| Kr-87 Ci ** ** ** **
| |
| Kr-88 Ci ** ** ** **
| |
| Xe-131m Ci ** ** ** **
| |
| Xe-133 Ci ** ** ** **
| |
| Xe-133m Ci ** ** ** **
| |
| Xe-135 Ci ** ** ** **
| |
| Xe-135m Ci ** ** ** **
| |
| Xe-137 Ci ** ** ** **
| |
| Xe-138 Ci ** ** ** **
| |
| Xe-127 Ci ** ** ** **
| |
| | |
| Iodines (1) 1-131 Ci ** ** ** **
| |
| 1-133 Ci ** ** ** **
| |
| 1-135 Ci ** ** ** **
| |
| | |
| Particulates (1)
| |
| Cr-51 Ci ** ** ** **
| |
| Mn-54 Ci ** ** ** **
| |
| Fe-55 Ci ** ** ** **
| |
| Fe-59 Ci ** ** ** **
| |
| Co-58 Ci ** ** ** **
| |
| Co-60 Ci ** ** ** **
| |
| Zn-65 Ci ** ** ** **
| |
| Sr-89 Ci ** ** ** **
| |
| Sr-90 Ci ** ** ** **
| |
| Nb-95 Ci ** ** ** **
| |
| Cs-134 Ci ** ** ** **
| |
| Cs-136 Ci ** ** ** **
| |
| Csc137 Ci ** ** ** **
| |
| Ba-140 Ci ** ** ** **
| |
| La-140 Ci ** ** ** **
| |
| Ce-141 Ci ** ** ** **
| |
| Ce-144 Ci ** ** ** **
| |
| Nd-147 Ci ** ** ** **
| |
| | |
| H-3 (1) Ci I ** I ** I ** I ** I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 31 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Table 12, Liquid Effluents - Summation of All Releases
| |
| | |
| 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST.TOTAL ERROR%
| |
| | |
| A. Fission & Activation Products
| |
| : 1. Total Release (not including Curies No Releases No Releases No Releases No Releases 5.00E+01 Tritium, gases, alpha)
| |
| : 2. Average diluted concentration µCi/ml No Releases No Releases No Releases No Releases during the reporting period
| |
| | |
| B. Tritium
| |
| : 1. Total Release Curies No Releases No Releases No Releases No Releases 5.00E+01
| |
| : 2. Average diluted concentration µCi/ml No Releases No Releases No Releases No Releases during the reporting period
| |
| | |
| C. Dissolved & Entrained Gases
| |
| : 1. Total Release Curies No Releases No Releases No Releases No Releases 5.00E+01
| |
| : 2. Average diluted concentration µCi/ml No Releases No Releases No Releases No Releases during the reporting period
| |
| | |
| D. Gross Alpha
| |
| : 1. Total Release Curies No Releases No Releases No Releases No Releases 5.00E+01
| |
| | |
| E. Volumes
| |
| : 1. Prior to Dilution Liters No Releases No Releases No Releases No Releases 5.00E+01
| |
| : 2. Volume of dilution water used Liters No Releases during release period No Releases No Releases No Releases 5.00E+01
| |
| : 3. Volume of dilution water available during reporting period - Cooling Liters 9.12E+09 9.69E+09 1.22E+10 1.06E+10 5.00E+01
| |
| | |
| F. Percent of Tech. Spec. Limits Percent of Quarterly Whole Body % No Releases No Releases No Releases No Releases Dose Limit (1.5 mrem)
| |
| Percent of Annual Whole Body Dose % No Releases No Releases No Releases No Releases Limit to Date (3 mrem)
| |
| Percent of Quarterly Organ Dose Limit % No Releases No Releases No Releases No Releases (5 mrem)
| |
| Percent of Annual Organ Dose Limit % No Releases No Releases No Releases No Releases to Date (10 mrem)
| |
| Percent of 1 0CFR20 Concentration % No Releases Limit No Releases No Releases No Releases Percent of Dissolved or Entrained % No Releases No Releases No Releases No Releases Noble Gas Limit (2.00E-04 uCi/ml)
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 32 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Table 13, Liquid Effluents Released Batch Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission & Activation Products Na-24 Ci No Releases No Releases No Releases No Releases Cr-51 Ci No Releases No Releases No Releases No Releases Mn-54 Ci No Releases No Releases No Releases No Releases Mn-56 Ci No Releases No Releases No Releases No Releases Fe-55 Ci No Releases No Releases No Releases No Releases Fe-59 Ci No Releases No Releases No Releases No Releases Co-60 Ci No Releases No Releases No Releases No Releases Ni-65 Ci No Releases No Releases No Releases No Releases Cu-64 Ci No Releases No Releases No Releases No Releases Zn-65 Ci No Releases No Releases No Releases No Releases Sr-89 Ci No Releases No Releases No Releases No Releases Sr-90 Ci No Releases No Releases No Releases No Releases Zr-95 Ci No Releases No Releases No Releases No Releases Nb-95 Ci No Releases No Releases No Releases No Releases Mo-99 Ci No Releases No Releases No Releases No Releases 1-133 Ci No Releases No Releases No Releases No Releases Cs-134 Ci No Releases No Releases No Releases No Releases Cs-136 Ci No Releases No Releases No Releases No Releases Cs-137 Ci No Releases No Releases No Releases No Releases Ba-140 Ci No Releases No Releases No Releases No Releases La-140 Ci No Releases No Releases No Releases No Releases Ce-141 Ci No Releases No Releases No Releases No Releases Ce-144 Ci No Releases No Releases No Releases No Releases
| |
| | |
| Dissolved or Entrained Ci No Releases No Releases No Releases No Releases
| |
| | |
| H-3 Ci I No Releases I No Releases I No Releases I No Releases I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 \\ Page 33 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Table 14, Liquid Effluents Released Continuous Mode
| |
| | |
| Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
| |
| | |
| Fission & Activation Products Na-24 Ci No Releases No Releases No Releases No Releases Cr-51 Ci No Releases No Releases No Releases No Releases Mn-54 Ci No Releases No Releases No Releases No Releases Mn-56 Ci No Releases No Releases No Releases No Releases Fe-55 Ci No Releases No Releases No Releases No Releases Fe-59 Ci No Releases No Releases No Releases No Releases Co-60 Ci No Releases No Releases No Releases No Releases Ni-65 Ci No Releases No Releases No Releases No Releases Cu-64 Ci No Releases No Releases No Releases No Releases Zn-65 Ci No Releases No Releases No Releases No Releases Sr-89 Ci No Releases No Releases No Releases No Releases Sr-90 Ci No Releases No Releases No Releases No Releases Zr-95 Ci No Releases No Releases No Releases No Releases Nb-95 Ci No Releases No Releases No Releases No Releases Mo-99 Ci No Releases No Releases No Releases No Releases 1-133 Ci No Releases No Releases No Releases No Releases Cs-134 Ci No Releases No Releases No Releases No Releases Cs-136 Ci No Releases No Releases No Releases No Releases Cs-137 Ci No Releases No Releases No Releases No Releases Ba-140 Ci No Releases No Releases No Releases No Releases La-140 Ci No Releases No Releases No Releases No Releases Ce-141 Ci No Releases No Releases No Releases No Releases Ce-144 Ci No Releases No Releases No Releases No Releases
| |
| | |
| Dissolved or Entrained Ci I No Releases j No Releases I No Releases I No Releases I
| |
| | |
| H-3 Ci I No Releases I No Releases I No Releases j No Releases I
| |
| | |
| (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
| |
| A nnual Radi o a c tive Effluent R elease Rep o rt I Y EAR : 2023 I Pag e 34 o f 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Attachment 2, Solid Waste Informat ion
| |
| | |
| NR C Regulat o ry Gu id e 1.21 Report
| |
| | |
| Solid Waste Shipped Otlsite for Disposal and Estimates of Ma jor Nuclides by Waste Class and Stream Du ring Period From : 01/01/2023 to 12/31/2023
| |
| | |
| Rnlna, Fllllra, And lnpomo, lofloffll Wlffl YOlvlllt Curilt ClaH ft' **
| |
| | |
| Unclasalfled 0 .OOE+OO 0.OOE+OO All 3 .17E+03 8.98E+01 6 .57E+01 Major Nuclldes for the Above Table :
| |
| H*3, C*14, Mn-54 , Fe-55, Co-58 , Co-60, Nl-63, Zn-65 , Sr-90, Zr-95. Nb-95, Tc-99 . Sn-113, Sb -125, 1-129, Cs-137 Pu-238 Pu-239 P -241 Am-241 Cm-244
| |
| | |
| O,y ActlH Waatt (DAW)
| |
| ..... Yolu** Curila CIIH n* **
| |
| | |
| AU 1.57E+OO Major Nuclldes for the Above Table :
| |
| H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, Co-60 , Nl-63, Zn-EIS , Sr-90, Nb -95, Tc-99, 1*129, Cs-137, Pu-238 ,
| |
| Pu-241 Am-241 C -242 Cm -244
| |
| | |
| ***** Yolu** ...
| |
| Cllu
| |
| | |
| C 0 .OOE+OO O.OOE+OO 0 .OOE+OO Unclaaif led O.OOE+OO O.OOE+OO O.OOE+OO All 4 .90E+OO 1.39E-01 4 .76E+OO Major Nuclides for the Above Table :
| |
| H-3, C-1 4, Fe-55, Co-60, Nl-59, Nl*63 , Sr-90, Nb-94 , Tc-99 , 1*129, Cs-137, Pu-238, Pu-241, Am-24 1, Cm-242 ,
| |
| C *2 A nnual Ra d ioa c tive Efflue nt R e lease Repo rt I YEAR: 2023 I Page 35 o f 42 Company: Constellation I Plant : Nine Mile Poin t Unit 2
| |
| | |
| NRC Reg u latory Gulde 1.21 Report
| |
| | |
| Solid Waste Shipped Ollsite fo r Disposal and Estimates o l Ma jor Nuclldes by Waste Class and Stream During Period From : 01/01/2023 to 12/31/2023 01!\\erWeetie w,ei. Vol11
| |
| * Ctln ft'
| |
| | |
| C 0 .OOE+OO 0.OOE+OO 0 .00E+00 U nc la9'Hied 0.OOE+O0 0.OOE+OO 0 .OOE+0O All 1.5 5E+0 3 4 .4 0E+0 1 1.54E+01 Major Nuclides for the Above Table :
| |
| H-3, C -14, Cr-51, Mn-54 , Fe-55, Fe-59, Co-60 , Ni-63 , Zn-65, Sr-90, Nb -95, Tc-99 , 1-129, Cs*137 . Pu-238 ,
| |
| Pu-241 Am-241 Cm-242 C m-244
| |
| | |
| Iv* ot Afl l.ow-level WHte S hip ped F,o Sit.I
| |
| ..... Cv rlH c, ...
| |
| | |
| Unclaulfled 0.OO E+OO 0.OOE+OO 0.OOE+OO All 2.97E+04 8.42E+ 02 8.74E+01 Ma jor Nuc lides for the Above Table :
| |
| H-3, C -1 4, Cr-51, Mn -54 , Fe-55 , Fe-59, Co-58 , Co-60, Ni-59, Nl-63, Zn-65, Sr-90, Zr-95, Nb-94, Nb -95 ,
| |
| Tc-99, Sn-1 13, Sb-125 , 1*129, Cs-137 , Pu -238 , Pu-239 , Pu-241 , Am-241, Cm-242 , Cm-244 Annual Radioactive Effluent Release Report I YEAR : 2023 I Page 36 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| NRC R egu latory Gulde 1.2 1 Ac tiv ity Repo rt Solid Waste Shipped Offslte for Disposal and Esllmates of Ma jor Nuclides by Shipment, Package, and Catego,y Dur ing Pe riod From : 01 /01/2023 to 12/31/2023 Percent Cutoff: 1.0%
| |
| | |
| O!yActlvtWute WMIICleNA Nuc lldtNa1111 Ab1111ctanu ActMtr (Cl)
| |
| Mn-54 2 .46% 3 .87E*02 Fe-55 9 .68% 1.52E*01 Co -60 85 .41 % 1.34E+0O Zn-65 1.23% 1.92E-02 Total Cot11blfttcl Nuclldt Ntfflt Abu11d111ct Activity (Cl)
| |
| Mn -54 2 .46% 3.87E-02 Fe-55 9.68% 1.52E-01 Co-60 85.41% 1.34E+00 Zn *65 1.23% 1.92E-02
| |
| | |
| lrrtdMttcl CoMpoMnta
| |
| *--CIINA Nucllclt NUtt Abu11d111c, Activity (Cl)
| |
| Fe-55 42 .41 % 2.02E+OO
| |
| | |
| Nl-63 10.27% 4.88E*01 Total c-bbltd NucllcftN1111t Abu11d111ct Actlv My (Cl)
| |
| Fe-55 42.41 % 2 .02E+00 Co-60 ,47% 2 .24E+OO Ni-63 10.27% 4.88E-01 Annual Radioactive Effluent R e lease Report I Y EA R: 202 3 I Page 37 o f 4 2 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| NRC Regu latory Gu id e 1.21 Ac tiv ity Report
| |
| | |
| Solid Waste Shipped Offslte for Disposal and Estimates of Major Nuclldes by Sh ipment , Package , and Category During Period From : 01/01/2023 to 12/31/2023 Percent Cutoff: 1.0%
| |
| othefW..-.
| |
| WNIIC.... A Nuclide Na111e ActMty (Cl)
| |
| | |
| Cr-51 2 . 11% 3 .26E*01 Mn-54 3 .09% 4 .77E-01 Fe-55 7 .61% 1. 17E+OO Co-60 82 .43% 1.27E+01 Zn-65 2 .23% 3.44E-01 Total Co111blnlCI Nuclide Neme Abundance AcUvlty (Cl)
| |
| Cr-51 2 . 11% 3 .26E-01 Mn-54 3 .09% 4 .77E-01 Fe-55 7 .61% 1.17E+OO Co-60 82 .43% 1.27E+01 Zn-65 2 .23% 3.44E-01
| |
| | |
| Ruins , Fllt9ra, and Enp lotto111a WNII CIIN A NuctkffNa1111 Abundance Activity (Cl)
| |
| | |
| Mn-54 2 .9% 1.90E+OO Fe-55 13.18% 8 .65E+OO Co-60 63 .3% 4 .16E+01 Zr-95 5.37% 3.53E+OO Nb-95 11 .78% 7 .73E+OO Total Coablned NucQde Name Abundance Act!Ylty (Cl)
| |
| Mn-54 2 .9% 1.90E+OO Fe-55 13. 18% 8 .65E+OO Co-60 63 .3% 4.1 6E+01 Zr-95 5 .37% 3.53E+OO Nb-95 11 .78% 7.73E+OO A n n u a l R adioacti ve Effluen t Release R ep o rt I Y EA R: 2 023 I Pag e 3 8 o f 42 Company : Constellation I Plant: N ine Mile Point Unit 2
| |
| | |
| NRC Re gula to ry Gul de 1.21 Activity Re po rt
| |
| | |
| Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuc lides by Shipment , Package , and Category Dur ing Period Fro m : 01/01/2023 to 12/31/2023 Percent Cutoff: 1.0%
| |
| lu111 o1 All 4 C1tetorte1 WNleCIINA Nucllele Nlffll Abundance Activity (Cl)
| |
| Mn -54 2.78% 2.43E+00 Fe -55 13.73% 1.20E+01 Co -60 66 .19% 5.79E+01 Ni- 63 1. 1% 9 .60E*01 Zn-65 1.06% 9.26E-0 1 Zr*95 4. 03% 3.53E + 00 Nb -95 8.98% 7 .85E+00 Total COfflblMcl Nuclldl Ha lftt Abundance Activity (Cl)
| |
| Mn- 54 2.78% 2 .43E+OO Fe - 55 13.73% 1.20E+01 Co-60 66 .19% 5 .79E+0 1 Nl-63 1.1% 9 .60E-01 Zn - 65 1.06% 9.26 E*01 Zr- 95 4. 03% 3 .53E+ 0O 8 .98% 7.85E+OO Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 39 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| WMG Suite 9.6,2 Report dato: 3/12/2024 NRC Regulatory Gulde Shipment 1.21 Report and Paekage Summary
| |
| | |
| Solid Waste Shipped Offslte for Olst>osal During Period from: 1/112023 to 12/3112023
| |
| | |
| j211M?'023 23*2003 Energy 685221*4 Ory Active A Type A j Solutions I Waste
| |
| ! r (CVRF)
| |
| ' 1512023 2*2073 Energy ESUU600125 OthorWasro A A LSA*H (CVRf} Solutiol15
| |
| | |
| 2/1612023 23*2004 Ent}rgy 685221*5 Ory Active A Type A
| |
| $Glulions Waste (CVAF) 3/212023 1039*C*0062 Energy SoMions Clwe PO708125*3 Res:lns, flltars, A Type A CWF and evap Bottoms 3/612023 103.9-C-0063 Energy P0701178*14 Resins, Fillers, A Type A Solutions Clive and Evap CWF Bottom1:1
| |
| '31912023 1039'-C--0064 Energy P0701176-9 Resins, FEiiers, A TypeA So!ullons Cllvo and Evap l3Jt312023'** ------ -, t039;C-;-OOSS- CWf Bottoms
| |
| *- -- emngr*--- -- PO7032t~33' Aescns;-Fllters;-A=-~**------* Typ-erA-- *------
| |
| | |
| "/'~~-,., Solutions ,,,,,-~ C'WF' ____ Clive
| |
| "~-- and Evap Botfoms* - ,,.-~~ -~ -*~----* --,*---"""
| |
| 3/1812023 1039-C*OOSG Energy P0708125-4 Aeaina, Fitten., A Type A Solutions Clive andEvap CWF Bottoms 3/20l2023 1039-0-0067 Energy PO70S952-27 Rel:lins, Filters, A Type A Solutions CliVt and Evap CWF Bottoms 312212023 Hil-2020 Energy 692070*3 Irradiated A Type A Solutions Components (CVRF) 3/2312023 1039*C--0068 Energy Sofulions PO70214f*31 Raslns, Filters, A TypeA cnve f1Jap CWF Bouoms
| |
| .312712023 1039-C-0069 Energy PO703215*15 Reains, Fillets, A Type A I
| |
| SolutlGns Cli\\*e and Evap I CWF Bottoms 313012023 1039.C-0070 Energy PO701178*13 Restns, Fi!tots, A Type A Solutions Cfive and evap CWF Bottoms 41312023 1 ()~9-C-0071 Energ~ P0703215*19 Rosins, Flftern, A TypeA Solutions Clive and evap CWF Bottoms Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 40 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| WMG Sullo 9.6.2 Report dale; 3/12f2024 NRC Regulatory Gu Idle un Report Shf:pment i;md Pac:kege summary
| |
| | |
| Solid Waste Shipped Offsite for Disposal D!llti:nl} Period Imm: 11112023 to 121811'2023 4.15/2023 1039*C*0072 Em:trg\\f P07032115*39 II A,esllllis, fillers, i-\\ TweA Sotullon.s. Cllv~ 1 and EviTIJP
| |
| | |
| -- CWf IBolloms 4/20/2023 23-2006 Energy ESUIJS->00123- Other1Naete A A lSA*II Solutions
| |
| {C\\ffiF) 51301202;3 NMP-2023*20\\1 l:nargy 2023*2011 OtherWa~e A Type A Solutions
| |
| . - '(CVRf}
| |
| 6/1212023 N MP-202s-:2009 energy E$UlJ300GS:2 DryActiv8 A A L:$A. .. ll 18$,te lr;:J<<mS, \\'i.r)
| |
| | |
| 6(19/2023 1039-C-0074 Energy P0701U.IM5 Reslfis, Ftltlers, A type A Solution5: Olive and Eva,p CWF :Bottoms 6/26'202:3 1039-C-007'6 l:n(!tg~ : P0705952*:25 . Reiins, FIiters, I A Type A Solutions Clive sm:t Evap iCWf B-olloms 6/.2912023 1038~C-00'.1'7 EmHQll P07091fl36-48 Resins, fillers, A T~*pe A Solullons Clive and! E\\iap CWf eo-nom:s 7/24J2023 10:39-C-0078 Energy P0711398..S9 Aeslmi:, lfil4era, A : Type A Solutions Cllvo and liva,p CWF Bottoms 71311202-a 1 039,C-0079 Energy P071139B-:27 Resins, Fitters, A Type A Solutions Clbro and Evap CWF Boltorns '
| |
| M'/2023 ! 038-'C-0080 Enetgy fl071139S,.93 Resins, Ftll,era, A. WpeA
| |
| ' Solutions Cl'ive and Evap CWIF Bottoms
| |
| | |
| 8/1612023 N!MP-2028-2018 Energy ESUU30 6&6 Ot!,1' Ac.live A ! A LSA~ll s.oJutions Wa,;,te (CVAF)
| |
| -8'2312023 NIMP-2023*2020 Energy 2023-2020 Other Waste A 'Type A
| |
| | |
| I SoMions
| |
| {CVRF) 1013012023 2a..:200; Enef9Y PO'i't08:36*38 OtherW.asie A Typ,e A
| |
| 'SGIULions (Cl/RF}
| |
| 10/30/2023 19-2002: Energy ?0674444-18 OtherWas.e A Type A
| |
| 'Solutlon:a (CVAf) 11/6i2023 : H:t39'-C-OOS5 .Energy .P071 t $'93*941 Res1ns, Fille:rn, A TweA jSolu!lons Cil11e and l:vap IOWf Bottoms 11/'61202:3 1-0S9,C~0064 l 202',3*20:27 Reahraa, filte1;1. A Type A
| |
| !~iY!ns Clive F Bottoms and Evap '
| |
| Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 41 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| WMG Sul1e 9.6.2 Repor1 dalo: 3/12/2024 NRC R@gulatory Gulde 1.21 Report Shipment and Package Summary
| |
| | |
| SoE!d Waste Shipped Offaite for Disposal During PerlQd from: 1/112023 to 12/31/2023 11/D/2023 20*2064 Energy NMP-023 DryActrve A A LSA*II (Memphis) Solutions Was1e
| |
| | |
| NMP-067 Dry Active A Umlted Woslo Quantity 111912023 20-2085 Enorgy NMP-032 Ory Active A A l.SA*U Solutions Waste
| |
| {Memphis)
| |
| NMP*0:37 Ory Aclive A A lSA*II Waste 11/9l2023 20*2086 Enetgy NMP-033 Ory Ac1ive A A. LSA-11 Solutions Waste (Memphis) 300168 . 0.-yAclive A A. LSA-11 Waste 11/16/2023 20-2069 NMP*064 Dry Active A A LSA*U lrJ~i~ ~$) Waste
| |
| | |
| NMP*012 Ory ActlYO A A LSA*II Waste 11/f&/2023 20*2068 Energy 55113 Dry Active A A LSA-11 Solutions Waste (Memphis) ..
| |
| - - *--~*"--*~~*-~ - .. .. """"'"
| |
| * _,._,, w*~-- ,-~- *, " ._.,,, * . - -NMll--04" "'fY-AOW-.. I.SA.fl-*
| |
| Waste l l/lti/2023 IC:U*it!Vti/ t:nergy -~~ IDty ACll\\10 A
| |
| ,y-,. ----- Ws$te A LSA*II Solutions (Memphis)
| |
| NMP-017 Dry Aotlv-0 A A LSA*II Waste 11/29/2023 NMP*2023*2015 Enevgy ESUU400056 Dry Active A A LSA*U Solutions Waste (CVAF) 11/3012023 20*2070 Energy NMP*011 Dry Ac1ive A A lSA*lt SoPuUons Waste
| |
| {Memphis) 288006 Dry Active A A LSA*ll Wame 11/34)/2023 20-2071 energy NMP-053 Ory Active A A LSA*U (Memphis) Solutions Waslo
| |
| | |
| NMP-007 Dry Actlvo A A LSA*H Waste Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 42 of 42 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Total Shipments by Carrier Number of Shipments per each carriot
| |
| | |
| Number of Mode of Transportation Destination Shfpments 13 Hittman Transport Energy Solutions (CVRF)
| |
| Bear Creek Operations 8 Hittman Transport Energy Solulions (Momphfs) 1790 Dock Street 19 Hlttm an Transport En0rgv Solutlons Clive CWF Clive Disposal Sile* Containerized Waste Facility Attachment 3 Classification of Atmospheric Stability
| |
| * and Joint Frequency Tables for 2023 6
| |
| | |
| Table 5
| |
| | |
| Atmospheric Stability Classes
| |
| | |
| Differential Temperature Differential Temperature Differential Temperature Interval Interval (in °F over the Interval (in °F over the Class (in °C/1 00m) <1> 100-30ft. range) <2J 200-30ft. range) <2J
| |
| | |
| Extremely Unstable LiT .::.-1.9 LiT.::. -0.7 LiT .::. -1.8
| |
| | |
| Moderately Unstable -1.9 < LiT,::. -1.7 -0.7 < LiT.::. -0.6 -1.8 < 8T 5. -1.6
| |
| | |
| Slightly Unstable -1.7 < 8T 5. -1.5 -0.6 < Li T 5. -0.5 -1.6 < 8T ,::. -1.4
| |
| | |
| Neutral -1.5 < 8T 5. -0.5 -0.5 < Li T ,::. -0.2 -1.4 < 8T ,::. -0.5
| |
| | |
| Slightly Stable -0.5 < LlT.::. 1.5 -0.2 < !lT,::. 0.5 -0.5 < LlT .::. 1.4
| |
| | |
| Moderately Stable 1.5 < Li T ,::. 4.0 0.5 < .LiT,::. 1.5 1.4 < 8T .::. 3.7
| |
| | |
| Extremely Stable 4.0 < 8T 1.5 < 8T 3.7 < !lT
| |
| | |
| (1l from NRC Regulatory Guide 1.23, Revision 1 (2l Reg Guide 1.23, Rev 1 intervals scaled for instrument heights on the Nine Mile Point meteorological tower
| |
| | |
| Murray & Trettel, Inc. 1602 Barclay Blvd Buffalo Grove, Illinois 60089 (847) 963-9000 18
| |
| | |
| 2023
| |
| | |
| Joint Frequency Tables
| |
| | |
| Murray & Trettel, Inc. 1602 Barclay Blvd Buffalo Grove, Illinois 60089 (847) 963-9000 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| All Stabilities
| |
| | |
| Elevations: : Winds 30ft Stability 200ft
| |
| | |
| Wind Wirid Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >10 .00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 10 16 39 86 98 7} 43 31 1 0 401
| |
| | |
| NNE 0 8 16 34 121 152 71 20 2 0 0 424
| |
| | |
| , *1 *,1 *'
| |
| NE 2 16 32 67 128 80 15 1 0 0 0 341
| |
| | |
| I\\
| |
| ENE 3 22 63 52 48 4 0 0 0 0 0 192
| |
| | |
| E 4 37 67 62 47 16 0 0 0 0 0 233
| |
| | |
| ESE .6 39 73 83 143 91 40 12 5 0 0 492
| |
| | |
| SE 8 62 111 96 254 309 122 57 32 0 0 1051
| |
| | |
| . :, *. SSE , 5 57 82 108 240 206 73 26 8 .o '* 0 805 s 2 16 48 72 195 220 55 35 5 0 0 648
| |
| | |
| SSW 4 14 33 47 90 114 14 7 0 0 0 323
| |
| | |
| SW 2 19 34 33 75 83 36 53 23 6 0 364
| |
| | |
| WSW 0 12 30 26 169 247 98 52 108 39 35 816
| |
| | |
| w 0 11 26 26 95 138 72 48 96 126 159 797
| |
| | |
| WNW 5 10 39 35 85 82 38 34 88 66 75 557
| |
| | |
| NW 3 9 22 35 62 94 54 57 91 53 18 498
| |
| | |
| NNW 2 8 24 40 63 57 43 30 48 14 4 333
| |
| | |
| Tot 46 350 716 855 1901 1991 808 475 537
| |
| * 305 291 8275
| |
| | |
| Hours of Calm .. 11 Hours of Variable Direction 0 Hours of Valid Data .. 8286 Hours of Missing Data . 474 Hours in Period .... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023
| |
| * 2023
| |
| | |
| Stability Cl ass A Extremely Unstable based on Lapse Rate
| |
| | |
| El ev11ti ens: : Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1* 4.1- 5.1* 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 0 0 6 10 15 10 13 1 0 55
| |
| | |
| NNE 0 0 0 0 2 21 6 2 1 0 0 32
| |
| | |
| ,, 'I * **,!
| |
| NE 0 0 0 1 2 0 0 0 0 0 0 3
| |
| : it .. ;-~ ) I '.' r*
| |
| ENE 0 0 1 0 1 0 0 0 0 0 0 2
| |
| | |
| i, :, * :'' I ~ '*.'. . '*~~.' .. ,*;,.-,*
| |
| E 0 0 1 1 1 0 0 0 0 0 0 3
| |
| -:,-,;**.I:, { ;;" 1., *1 cj:;f : *, ~'. , *-~,,:
| |
| ESE 0 0 0 0 1 0 1 0 0 0 0 2
| |
| | |
| ( ; :* ,; '" :. ~ ::,; ! *. \\.1,. :::*:
| |
| SE 0 0 0 0 2 1 1 0 0 0 0 4
| |
| '.;:: *.:,SSE-** 0 (!,'.*0 ,o *O j l 3 1 0 'o* i :, 0 0 5
| |
| ... ,[:**' .... ** l, _:_i'..;
| |
| s 0 0 0 0 2 2 0 0 0 0 0 4
| |
| | |
| SSW *o 0 0 1 0 *2 0 0 0 0 :o 3
| |
| | |
| . SW 0 0 0 0 0 1 1 1 0 0 0 3
| |
| | |
| WSW 0 *o *o 0 11 35 5 0 10 6 3 70
| |
| | |
| *W 0 0 0 3 13 25 6 1 5 16 20 89
| |
| | |
| WNW 0 '0 5 16 34 17 2 3 14 13 17 121
| |
| * Nw :o 0 3 5 21 18 4 9 5 21 12 98
| |
| | |
| ... ~ NNW :o *o *o 3 17 8 9 10 15 6 1 69
| |
| | |
| **Tot
| |
| * 0 0 10 30 114 143 51 36 63 63 53 563
| |
| | |
| Hour{ of Calm 0 Hours of Variable Direction 0 Hours of Valid *Data 563 Hours of Missing Data 474 Hours *in Period*. 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| Stability Cl ass B Moderately Unstable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 0 1 7 7 15 16 8 0 0 54
| |
| | |
| NNE 0 0 0 0 4 14 9 4 0 0 0 31
| |
| | |
| *;/ ,ii I; NE 0 0 0 0 3 2 2 0 0 0 0 7
| |
| | |
| ENE 0 0 0 0 0 0 0 0 0 0 0 0
| |
| ;*, :*::* ! * *) f ,*, j 1 ~. , ,
| |
| E 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 1 3 3 1 0 0 0 0 8
| |
| .1*;:*:*:
| |
| SE 0 0 0 0 4 12 2 1 5 0 0 24
| |
| | |
| *,;ii, '!1/.
| |
| - , -'SSE* 0 *o 0 0 .,',: 8 '6 *O 2 0 *O O* 16
| |
| | |
| ")t'.t s 0 0 0 0 1 7 0 D 0 0 0 8
| |
| | |
| SSW 0 0 0 0 1 0 0 0 0 0 0 . 1
| |
| | |
| *SW 0 0 0 1 l 3 2 1 1 0 0 9
| |
| | |
| WSW *o 0 0 l 11 17 6 3 2 2 7 49
| |
| | |
| w 0 0 D 2 6 17 8 10 9 15 14 81
| |
| | |
| WNW 0 0 3 1 7 10 8 6 13 11 23 82
| |
| | |
| NW 0 0 0 4 5 5 4 11 16 9 4 58
| |
| | |
| NNW 0 0 1 1 4 3 7 5 5 -3 0 29
| |
| * Tot 0 0 4 12 65 106 64 59 59 40 48 457
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours-of Valid Data . 457 Hours of Missing Data 474 Hours,,in Period *. 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months .Jan
| |
| * Dec for years 2023 - 2023
| |
| | |
| Stability Class C Slightly Unstable based on Lapse Rate
| |
| | |
| .El ev.ati ons: : Winds 30ft Stability 200ft
| |
| | |
| . Wind Wind Speed Range (m/s)
| |
| Directiqn 0.5- 1.1- 1.6- 2.1- 3.1* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 1 6 8 18 29 9 5 0 0 76
| |
| | |
| NNE 0 0 1 0 14 18 21 7 0 0 0 61
| |
| | |
| NE 0 0 2 1 7 11 1 0 0 0 0 22
| |
| _..t: 1!-
| |
| ENE 0 0 0 0 0 0 0 0 0 0 0 0
| |
| :*;1'. :I.;
| |
| E 0 0 0 3 3 0 0 0 0 .0 0 6
| |
| | |
| ::\\ ':;-:: ... *:*:' l ESE 0 0 1 1 8 5 0 2 0 0 0 17
| |
| | |
| :., 1_:\\ *' .:t; SE 0 0 2 1 3 9 4 3 2 0 0 24
| |
| | |
| ** SSE 0 *O *2 1 9 3 4 1 1 0 .. 0 21 ...
| |
| | |
| *.) M s 0 0 0 2 3 12 3 4 2 0 0 26
| |
| | |
| SSW 0 0 0 1 6 3 0 1 0 0 0 11
| |
| | |
| '*SW 0 0 0 3 2 3 0 2 1 0 0 11
| |
| | |
| WSW 0 0 0 0 12 28 7 4 19 6 6 82
| |
| *w 0 0 1 1 7 24 14 12 18 20 32 129
| |
| | |
| WNW 0 0 4 2 10 21 5 4 19 14 18 97
| |
| | |
| NW 0 0 2 4 4 19 11 11 49 15 1 116
| |
| | |
| NNW 0 0 3 7 5 18 14 8 18 i 0 74
| |
| | |
| , Tot 0 0 19 33 101 192 113 68 134 '56 *, 57 773
| |
| | |
| Hours* of Calm 0 Hours of Variable Direction 0 Hours*of Valid Data . 773 Hours of Missing Data 474 Hours in Period . . 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| Stability Cl ass D Neutral based on Lapse Rate
| |
| | |
| Elevations:: Wtnds 30ft Stability 200ft
| |
| | |
| *Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >10.00 Sector *<0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 3 7 24 42 61 17 8 5 0 0 167
| |
| | |
| NNE 0 2 5 22 79 89 35 7 1 0 0 240
| |
| | |
| NE 1 9 14 41 81 60 12 1 0 0 0 219
| |
| *1';
| |
| ENE 0 7 32 39 35 4 0 0 0 0 0 117
| |
| .,,*,.*,;,1* ,:;.)':
| |
| E 1 5 22 32 28 14 0 0 0 0 0 102 ESE 0 6 16 24 72 60 38 10 3 0 0 229
| |
| . ;,* ~ i . .. *,; ,: ., .. ,; ,;_.:
| |
| SE 1 4 6 23 92 171 96 43 19 0 0 455
| |
| .:\\, *,
| |
| * **SSE.* 1 *; ',3 ) ''* 7 15 (, 64 75 35 14 7 0 O* 221
| |
| * i.' 1,(! J :*
| |
| s 0 1 9 27 55 71 31 23 2 0 0 219
| |
| | |
| SSW :1 3 8 18 22 64 12 4 0 0 0 132
| |
| | |
| SW 0 4 9 12 42 45 20 33 14 2 0 181
| |
| | |
| WSW 0 2 7 9 60 95 44 23 46 18 15 319
| |
| | |
| w 0 3 9 9 50 52 33 16 42 61 78 353
| |
| | |
| WNW 0 6 8 10 25 30 20 17 34 27 17 194
| |
| | |
| NW 1 3 6 12 30 45 33 26 19 8 1 184
| |
| | |
| NNW 0 6 9 18 28 25 13 7 10 4 3 123
| |
| | |
| Tot
| |
| * 6 67 174 335 805 961 439 232 202 120 114 3455
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 3455 Hours of Missing Data 474 Hours in Period . 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| Stability Class E Slightly Stable based on Lapse Rate
| |
| | |
| El evati.ons: : *: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 5 8 6 8 1 1 0 0 0 0 29
| |
| | |
| NNE 0 5 5 5 9 3 0 0 0 0 0 27
| |
| | |
| NE 1 3 11 15 16 7 0 0 0 0 0 53
| |
| | |
| ENE 2 9 23 11 10 0 0 0 0 0 0 55
| |
| ',',.Yt:*.
| |
| E 0 21 29 15 10 2 0 0 0 0 0 77 ., '. ><f : * * ~., *::~ I .. .,
| |
| ESE 1 12 23 26 40 22 0 0 2 0 0 126
| |
| .. :, *,. i=:t**;_ .'.:1 SE 2 11 20 32 103 108 19 10 6 0 0 311
| |
| ~**, , ..... **t ,. *.
| |
| . ssE .. 1 i: 12 18 28 52 101 32 9 0 0 0 253 s 0 5 14 18 68 95 21 8 1 0 0 230
| |
| | |
| SSW 1 7 18 17 47 39 2 2 0 'O 0 133
| |
| | |
| *SW 1 7 15 15 28 29 13 16 7 '3 0 134
| |
| | |
| WSW 0 4 13 11 60 52 28 16 26 5 4 219
| |
| | |
| w 0 5 11 7 13 12 9 8 22 14 15 116
| |
| | |
| WNW 2 *1 12 4 5 2 3 4 8 1 0 42
| |
| | |
| NW 1 4 *7 7 0 6 1 0 2 0 0 28
| |
| | |
| NNW 1 2 9 6 5 3 0 0 0 0 0 26
| |
| | |
| Tot 13 113 236 223 474 482 129 73 74 23 19 1859
| |
| | |
| Hours of Calm . 6 Hours of Variable Direction 0 Hours *of Valid Data . 1865 Hours of Missing Data 474 Hours in Period. 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2023 - 2023
| |
| | |
| Stability Class F Moderately Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stabi.1 ity 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5* 1.1- 1.6* 2.1* 3.1- 4.1* 5.1- 6.1- 8.1* >10,00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 1 0 2 9 1 0 0 0 0 0 13
| |
| | |
| NNE 0 1 3 6 3 7 0 0 0 0 0 20
| |
| | |
| NE 0 1 5 8 10 0 0 0 0 0 0 24
| |
| | |
| ENE 1 5 3 2 2 0 0 0 0 0 0 13 ...
| |
| E 0 7 12 8 4 0 0 0 0 0 0 31
| |
| ,i ,*, ;~1, *. : : l i.: ., :.:1** , .* f . *,
| |
| ESE 1 12 15 22 17 0 0 0 0 0 0 67
| |
| | |
| SE 1 11 11 19 34 6 0 0 0 0 0 82
| |
| ,,,_. ,i ;,*: *,
| |
| SSE** 3 *i **9 18 28 35 8 1 0 0 0 0 102 s 0 6 18 19 44 25 0 0 0 0 0 112
| |
| | |
| SSW 2 2 5 9 14 6 0 0 0 0 0 38
| |
| *,sw 1 6 7 2 2 2 0 0 0 1 0 21
| |
| | |
| WSW 0 5 8 4 11 17 7 5 5 2 0 64 w 0 3 4 4 5 7 1 1 0 0 0 25
| |
| | |
| WNW 1 2 6 0 2 0 0 o* 0 0 0 11
| |
| | |
| NW 1 1 4 3 0 1 0 0 0 0 0 10
| |
| | |
| NNW 1 0 2 3 3 0 0 0 0 0 0 9
| |
| | |
| Tot 12 72 121 139 195 80 9 6 5 3 0 642
| |
| | |
| Hours of Calm . 4 Hours of Variable Direction 0 Hours of Valid Data . 646 Hours of Missing Data 474 Hours in Period . 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| Stability Class G Extremely Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Win.ct Speed Range (m/s)
| |
| Direction 0.5* 1.1- 1.6* 2.1- 3.1* 4.1- 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 1 0 0 6 0 0 0 0 0 0 7
| |
| | |
| NNE 0 0 2 1 10 0 0 0 0 0 0 13
| |
| . ~ :** . . *'*
| |
| NE 0 3 0 1 9 0 0 0 0 0 0 13
| |
| | |
| ENE 0 1 4 0 0 0 0 0 0 0 0 5
| |
| | |
| E 3 4 3 3 1 0 0 0 0 0 0 14
| |
| | |
| ESE 4 9 18 9 2 1 0 0 0 0 0 43
| |
| | |
| '\\ ;;. ~
| |
| SE 4 36 72 21 16 2 0 0 0 0 0 151
| |
| | |
| :SSE
| |
| * 0 .. 33
| |
| * 37 36 71 10 0 0 0 0 0 187 s 2 4 7 6 22 8 0 0 0 0 0 49
| |
| | |
| SSW 0 2 2 1 0 0 0 0 0 0 0 5
| |
| | |
| SW 0 2 ' 3 0 0 0 0 0 0 0 0 5
| |
| | |
| WSW 0 1 2 1 4 3 1 1 0 0 0 13
| |
| | |
| w 0 0 1 0 1 1 1 0 0 0 0 4
| |
| | |
| WNW 2 1 1 2 2 2 0 0 0 0 0 10
| |
| | |
| NW 0 1 0 0 2 0 1 0 0 0 0 4
| |
| | |
| NNW 0 *o 0 2 1 0 0 0 0 0 0 3
| |
| | |
| Tot 15 98 152 83 147 27 3 1 0 0 0 526
| |
| | |
| Hours of Calm .. 1 Hours of Variable Direction 0 Hours of Val id Data . . 527 Hours of Missing Data. 474 Hours in Period .... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan , Dec for years 2023 - 2023
| |
| | |
| All Stabilities
| |
| | |
| El evati ans: : Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5* 1.1- 1.6- 2.1* 3.1* 4.1* 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 3 9 21 35 87 42 59 88 60 66 470
| |
| | |
| NNE 2 4 8 9 40 84 67 44 99 71 73 501
| |
| , .Ji" ;*: "'; * . .-:* ~* ~*'
| |
| NE 0 3 11 15 67 98 53 31 55 10 6 349
| |
| -~ ! ~.* ' . :. ,,,
| |
| ENE 0 5 10 13 61 50 19 4 1 0 0 163 E 2 4 13 16 45 50 21 13 11 0 0 175
| |
| | |
| '*l * '*.
| |
| ESE 2 4 7 13 35 75 55 33 59 15 2 300
| |
| -:',.;' -~*
| |
| SE 1 6 6 7 28 95 100 121 315 102 32 813
| |
| | |
| <i. -SSE 2 2 '6 7 27 91 90 112 239 , 86 22 684
| |
| | |
| s 3 7 6 6 39 94 67 79 154 59 3 517
| |
| | |
| SSW 1 6 11 11 37 77 77 91 132 -7 0 450
| |
| | |
| SW 1 6 15 18 53 96 76 63 105 14 5 452
| |
| | |
| WSW 2 5 7 16 64 155 130 132 221 103 162 997
| |
| | |
| w 0 2 9 14 61 157 88 67 114 79 293 884
| |
| | |
| WNW 0 5 10 12 55 80 62 32 74 71 190 591
| |
| | |
| NW 2 4 16 8 52 60 50 42 111 76 116 537
| |
| | |
| NNW 0 5 8 16 32 57 34 42 82 *59 66 401
| |
| | |
| Tot 18 71 152 202 731 1406 1031 965 1860 812 1036 8284
| |
| | |
| Hours of Calm .. 2 Hours of Variable Direction 0 Hours of Valid Data . 8286 Hours of Missing Data 474 Hours in Period ... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023
| |
| * 2023
| |
| | |
| Stability Class A Extremely Unstable based* on Lapse Rate
| |
| | |
| El evati ans: : Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 - 10.0 Total
| |
| | |
| N 0 0 0 0 0 8 9 4 14 8 21 64
| |
| | |
| NNE 0 0 0 0 0 1 1 4 7 7 14 34
| |
| | |
| NE 0 0 0 0 1 1 2 0 0 0 0 4
| |
| | |
| * ; **** -,j ~
| |
| ENE 0 0 0 0 1 0 0 1 0 0 0 2 E 0 0 0 0 1 1 0 0 0 0 0 2
| |
| .. !,:* :. ~ ~' '
| |
| ESE 0 0 0 0 0 1 1 0 0 0 0 2
| |
| | |
| SE 0 0 0 0 0 1 1 0 3 0 0 5
| |
| | |
| *SSE** 0 . '' 0 *o *o *o 0 4 0 0 :1 0 5 s 0 0 0 0 0 2 1 1 0 0 0 4
| |
| | |
| SSW 0 0 0 0 0 0 1 0 0 0 0 1
| |
| | |
| SW 0 0 0 0 1 0 0 0 2 1 0 4
| |
| | |
| WSW 0 0 0 0 0 2 15 17 16 1 13 64
| |
| | |
| w 0 0 0 0 3 13 16 10 3 4 32 81
| |
| | |
| WNW 0 0 0 0 9 23 17 6 7 11 27 100
| |
| | |
| NW 0 0 0 0 15 16 18 5 5 4 40 103
| |
| | |
| NNW 0 0 0 0 3 14 9 7 17 15 23 88
| |
| | |
| Tot 0 0 0 0 34 83 95 55 74 52 170 563
| |
| | |
| Hours of Calm . . . . .. 0 Hours of Variable Direction 0 Hours of Valid Data . 563 Hours of Missing Data . 474 Hours in Period .... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2023
| |
| * 2023
| |
| | |
| Stability Cl ass B Moderately Unstable based on Lapse Rate
| |
| | |
| Elevations: : Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range Cm/s)
| |
| Direction 0.5* 1.1* 1.6- 2.1- 3.1- 4.1* 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10 .0 Total
| |
| | |
| N 0 0 0 0 3 3 2 3 11 10 14 46
| |
| | |
| NNE 0 0 0 0 0 6 9 4 5 10 10 44
| |
| | |
| NE 0 0 0 0 0 2 0 0 2 0 0 4
| |
| | |
| ',,** 'l ( ... ~, ;*
| |
| ENE 0 0 0 0 0 0 0 0 0 0 0 0
| |
| | |
| ~ .. r;. '.
| |
| E 0 0 0 0 0 0 0 0 0 d 0 0
| |
| ~-1,,/>i ,1, :*'. ,, .. . { ~:
| |
| ESE 0 0 0 0 0 2 4 0 0 0 0 6
| |
| ,1; . : '
| |
| SE 0 0 0 0 0 3 4 2 10 0 6 25
| |
| | |
| *,/
| |
| SSE 0 0 0 *o 1 10 3 0 0 '
| |
| * 2 0 16 s 0 0 0 0 0 1 5 2 0 0 0 8
| |
| | |
| SSW 0 0 0 0 0 1 0 1 0 0 0 2
| |
| | |
| SW 0 0 0 0 1 0 0 0 2 *1 0 4
| |
| | |
| WSW 0 0 0 0 0 4 7 10 14 6 6 47
| |
| *w 0 0 0 1 2 8 8 7 17 6 24 73
| |
| | |
| WNW 0 1 0 1 1 7 4 10 12 11 37 84
| |
| | |
| NW 0 0 0 0 4 5 1 2 14 14 21 61
| |
| | |
| NNW 0 0 0 0 2 3 2 2 8 11 9 37
| |
| | |
| Tot 0 1 0 2 14 55 49 43 95 71 127 457
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 457 Hours of Missing Data 474 Hours in Period . 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| Stabi 1 ity Cl ass C Slightly Unstable based on Lapse Rate
| |
| | |
| Elevations:: Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6* 2.1* 3.1* 4.1- 5.1- 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 0 0 6 8 7 13 23 18 13 88
| |
| | |
| NNE 0 0 0 0 2 9 4 7 15 16 12 65
| |
| | |
| NE 0 0 0 0 3 4 2 6 2 4 0 21
| |
| | |
| ENE 0 0 0 0 1 0 0 0 0 0 0 1
| |
| | |
| E 0 0 0 0 2 1 1 0 0 0 0 4
| |
| -.:-::*1-ESE 0 0 0 0 2 3 4 2 0 2 0 13
| |
| ,:f*
| |
| * SE 0 0 0 3 0 4 3 4 6 3 2 25
| |
| | |
| SSE 0 *.o ,0 1 2 7 2 *O 6 1 . 0 19 s 0 0 0 0 0 7 3 9 7 4 1 31
| |
| | |
| SSW 0 0 0 1 1 3 4 0 1 .o 0 10
| |
| | |
| SW 0 0 o 0 3 o 4 1 2 0 1 11
| |
| | |
| WSW o 0 o 0 0 8 6 14 20 5 20 73
| |
| | |
| w 0 0 0 1 3 19 9 10 24 11 47 124
| |
| | |
| WNW o 0 1 1 5 13 9 2 10 11 37 89
| |
| | |
| NW o 0 0 0 4 7 7 7 25 34 31 115
| |
| | |
| NNW o 0 1 3 3 7 4 14 23 14 15 84
| |
| | |
| Tot 0 0 2 10 37 100 69 89 164 123 179 773
| |
| | |
| Hours of Calm 0 Hours of Variable Direction o Hours of Valid Data .. 773 Hours of Missing Data . 474 Hours in Period .... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| /
| |
| Period:: Months Jan
| |
| * Dec for years 2023
| |
| * 2023
| |
| | |
| Stability Class D Neutral based on Lapse Rate
| |
| | |
| Elevations: : Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1* 3.1* 4.1* 5.1* 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 1 3 8 17 53 21 30 32 12 12 189
| |
| | |
| NNE 0 1 2 5 27 54 42 26 58 33 27 275
| |
| | |
| NE 0 2 3 6 37 62 39 22 41 6 5 223
| |
| | |
| ENE 0 0 2 2 28 32 10 2 0 0 0 76 .... ? .
| |
| | |
| J' E 0 0 4 5 18 21 8 3 7 0 0 66
| |
| | |
| ._ .*. t ~* ..
| |
| ESE 0 1 4 5 13 32 24 15 30 13 2 139
| |
| .. \\*. l ,-:*,/,1*;
| |
| SE 0 2 2 2 14 48 51 60 159 84 22 4.44
| |
| | |
| SSE.* 0 .o *1 1 8 34 48 56 92 '46 8 294 s 1 1 4 2 18 42 26 25 56 26 2 203
| |
| | |
| SSW 1 0 1 2 21 20 30 34 42 2 0 153
| |
| | |
| SW 0 3 2 5 8 19 21 15 37 9 2 121
| |
| | |
| WSW 0 0 1 4 17 44 50 51 103 46 60 376
| |
| | |
| w 0 0 3 4 15 65 34 27 39 36 141 364
| |
| | |
| WNW 0 '1 5 5 14 20 24 11 28 23 75 206
| |
| | |
| NW 0 0 4 1 13 22 21 23 61 21 21 187
| |
| | |
| NNW 0 0 4 7 16 20 12 14 30 16 19 BB
| |
| | |
| Tot 2 12 45 64 284 588 461 414 815 373 396 3454
| |
| | |
| Hours of Calm . *** '!
| |
| * 1 Hours of Variable Direction 0 Hours of Valid Data .. 3455 Hours of Missing Data . 474 Hours in Period .... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2023 - 2023
| |
| | |
| Stability Class E Slightly Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range Cm/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1* 4.1* 5.1* 6.1- 8.i: >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 1 3 9 4 7 1 7 2 6 1 41
| |
| | |
| NNE 0 0 5 2 2 6 8 1 9 0 1 34
| |
| | |
| NE a 0 6 3 18 20 9 2 6 0 0 64
| |
| | |
| ENE 0 3 1 7 19 14 6 0 1 0 0 51
| |
| | |
| E 1 0 4 1 9 16 8 8 1 0 0 48
| |
| | |
| ESE 0 0 0 3 10 18 13 10 14 0 0 68
| |
| | |
| SE 0 2 2 1 8 24 30 39 107 14 2 229
| |
| | |
| SSE 0 1 1 2 5 21 18 44 113 35 14 254 s 0 3 1 3 9 16 22 30 68 28 0 180
| |
| | |
| SSW 0 0 3 1 7 28 27 35 71 5 0 177
| |
| | |
| SW 0 0 3 4 13 27 30 23 29. 3 2 134
| |
| | |
| WSW 0 0 1 6 15 48 28 33 52 41 53 277
| |
| | |
| w 0 0 0 2 13 34 17 8 24 17 44 159
| |
| | |
| WNW 0 2 2 3 11 9 5 3 13 14 13 75
| |
| | |
| NW 0 2 8 4 11 8 2 4 4 2 0 45
| |
| | |
| NNW 0 1 0 3 5 7 4 4 3 .2 0 29
| |
| | |
| Tot 1 15 40 54 159 303 228 251 517 167 130 1865
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data .. 1865 Hours of Missing Data . 474 Hours in Period .... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2023
| |
| * 2023
| |
| | |
| Stability Cl ass F Moderately Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5* 1.1* 1.6- 2.1* 3.1* 4.1* 5.1* 6.1- 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 1 0 1 3 3 2 1 3 4 1 19
| |
| | |
| NNE 0 1 1 1 6 4 3 2 4 4 2 28
| |
| | |
| NE 0 0 1 4 6 7 1 1 3 0 1 24
| |
| | |
| ENE 0 1 3 2 11 3 2 1 0 0 0 23
| |
| | |
| E 0 4 0 4 8 6 3 2 2 0 0 29
| |
| | |
| '"'* t ESE 0 0 1 2 8 11 4 4 12 0 0 42
| |
| | |
| SE 0 2 2 0 3 5 8 7 18 0 0 45
| |
| | |
| SSE 0 *O 2 1 5 6 8 11 19 ;1 0 53 s 0 2 0 0 5 7 5 4 15 1 0 39
| |
| | |
| SSW 0 1 4 2 3 8 7 14 16 0 0 55
| |
| | |
| SW 0 0 4 3 9 25 15 17 29 0 0 102
| |
| | |
| WSW 0 1 1 0 14 26 14 6 13 4 9 88
| |
| | |
| w 0 1 2 1 13 13 4 4 6 5 4 53
| |
| | |
| WNW 0 0 0 1 8 7 1 0 4 1 0 22
| |
| | |
| NW 1 0 2 3 3 1 1 1 1 0 0 13
| |
| | |
| NNW 0 3 1 0 2 3 0 1 1 0 0 11
| |
| | |
| Tot 1 17 24 25 107 135 78 76 146 20 17 646
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Val1d Data . 646 Hours of Missing Data 474 Hours in Period ... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2023
| |
| * 2023
| |
| | |
| Stability Class G Extremely Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 3 3 2 5 0 1 3 2 4 23
| |
| | |
| NNE 2 2 0 1 3 4 0 0 1 1 7 21
| |
| | |
| NE 0 1 1 2 2 2 0 0 1 0 0 9
| |
| | |
| ENE 0 1 4 2 1 1 1 0 0 0 0 10
| |
| | |
| E 1 0 5 6 7 5 1 0 1 0 0 26
| |
| | |
| ESE 2 3 2 3 2 8 5 2 3 0 0 30
| |
| | |
| SE 1 0 0 1 3 10 3 9 12 1 0 40
| |
| | |
| SSE 2 1 2 2 6 13 7 1 9 0 0 43 s 2 1 1 1 7 19 5 8 8 0 0 52
| |
| | |
| SSW 0 5 3 5 5 17 8 7 2 0 0 52
| |
| | |
| SW 1 3 6 6 18 25 6 7 4 0 0 76
| |
| | |
| WSW 2 4 4 6 18 23 10 1 3 0 1 72
| |
| | |
| w 0 1 4 5 12 5 0 1 1 0 1 30
| |
| | |
| WNW 0 1 2 1 7 1 2 0 0 0 1 15
| |
| | |
| NW 1 2 2 0 2 1 0 0 1 1 3 13
| |
| | |
| NNW 0 1 2 3 1 3 3 0 0 1 0 14.
| |
| | |
| Tot 14 26 41 47 96 142 51 37 49 6 17 526
| |
| | |
| Hours of Calm .. 1 Hours of Variable Direction 0 Hours of Valid Data . 527 Hours of Missing Data 474 Hours in Period ... 8760 Attachment 4 Errata and Corrections to the 2021 NMP1 and NMP2 ARERRs
| |
| | |
| For both the NMP1 and NMP2 ARERRs for 2021, the groundwater tritium data for 2020 was erroneously provided instead of for 2021. The 2021 groundwater tritium data is provided on the next page in its entirety.
| |
| ATTACHMENT 12 Page 1 of 1
| |
| | |
| Nine Mile Point 1 and 2 Groundwater Tritium Results Re(!Orting Period: Janau!Y - December 2021
| |
| | |
| Well Identification # Samples # Positive Minimum Concentration Maximum Number Collected Samples (pCi/I) Concentration (pCi/I)
| |
| | |
| GMX-MWl* 1 0 <199 <199 MW-1 1 0 "9196 <196 MW-5 4 0 <171 <190 MW-6 1 0 <197 <197 MW-7 1 0 <191 <191 MW-8 4 0 <182 <195 MW-9 1 4 0 <188 <196 MW-10 1 1 0 <198 <198 MW-11 1 0 <185 <185 MW-12 1 0 <191 <191 MW-13 1 0 <188 <188 MW-14* 1 0 <192 <192 MW-15 4 0 <181 <202 MW-16 1 0 <192 <192 MW-17 4 0 <179 <191 MW-18 4 0 <182 <191 MW-19 1 0 <187 <187 MW-20 1 0 <188 <188 MW-21 1 0 <192 <192 NMP2 MAT 2 *3 1 0 <199 <199 PZ-1 2 0 <187 <195 PZ-7 4 0 <183 <196 PZ-8 4 0 <189 <194
| |
| | |
| Notes: * - Control Location 1 - Sentinel well location
| |
| | |
| 2 - NMP2 Groundwater Depression Cone
| |
| | |
| 3 - Samples collected from storm drain system which includes precipitation
| |
| | |
| 4 - No samples were collected durir;ig 2 nd due to Covid-19 Attachment 5 Errata and Corrections to the 2022 NMP1ARERR Summary .of Identified Errata and Corrections
| |
| | |
| Multiple errata were identified in the 2022 ARERR submittal for NMP1. The corrections are summarized below, and the corrected pages are included in their entirety .in the order in which t_hey are listed, unless otherwise noted.
| |
| | |
| Corrections are indicated with revision bars on the right-hand side of the page. Corrected activities, doses, and numbers are balded and italicized.
| |
| | |
| For all errata described below, dose was originally over-:-reported, and the corrected doses are lower.
| |
| * 1 .. On pages 5 and 19, the James A. FitzPatrick Nuclear Power Plant (JAFNPP) is erroneously referred to as "John A. FitzPatrick Nuclear Power Plant". This is a typographical-only error.
| |
| : 2. Page 7, Table 2, Dose Potentially Received by the Likely Most Exposed Member of the Pub.lie Outside the Site Boundary During 2022:
| |
| | |
| Gaseous effluent dose (excluding C-14) for both units slightly changed as a result of corrections to gaseous activity released in the 2022 NMP2 ARERR (Tables 7, 8, and 9).
| |
| : 3. Page 16, Table 3, Onsite Doses (Within Site Boundary)
| |
| Several issues were identified:
| |
| a) Dose from Iodine, Particulate, C-14 & H-3 was significantly overreported.
| |
| b) In accordance with the NMP1 and NMP2 ODCMs, dose from Noble Gas releases is evaluated by TLD measurement at the shoreline fishing location.
| |
| c) The incorrect TLDs were used for reporting dose at the shoreline fishing location.
| |
| d) The corrected table,*for both units,. also encompasses slight changes to calculated dose as a result of the over-reported Fe-55, Sr-89, Sr-90, and omitted Primary Containment Purges .from NMP2 during 2022.
| |
| | |
| 4.* Page 18, Section 5.4, Land Use Census Changes
| |
| | |
| In 2022, three new gardens were planted in the E, ESE, and SE sectors of the JAF owner-controlled area (OCA) which have since served as indicator locations for broad-leaf vegetation sampling. Vegetation samples were obtained from these gardens in 2022, and results were included in the JAF/NMP 2022 AREOR in Table 6-12 on Page 6-23.
| |
| : 5.
| |
| * Page 18, Section 5.6, Effluent Radiation Monitors Out of Service Greater Than 30 Days:
| |
| | |
| At both NMP1 and NMP2, Liquid Radwaste Discharge Radiation Monitors have been retired .in place and were inoperable for all of 2022, as liquid batch discharges are no longer expected to occur, and were not performed at either unit for the year. This information has historically been included in ARERR submittals.
| |
| : 6. Pages 33-34, Attachment 3, Meteorological Data:
| |
| | |
| The only joint frequency table included is for the 200 ft Wind elevation for All Stability Classes as determined by 200-30 ft Vertical Temperature Difference (~T). Historically, Nine Mile Point has not included meteorological Joint frequency distributions in ARERR submittals, which would be provided to the NRC upon request per both NMP1 and NMP2 ODCMs. As a correction, Attachment 7 to the 2023 ARERR contains classifications of atmospheric stability and meteorological joint frequency tables for 2022.
| |
| : 7. Page 31, Table 14, Major Nuclides NMP Unit 1:
| |
| | |
| Under "a. Spent resins, filter sludges, evaporator bottoms, etc." the nuclides C-14 and Zn-65 were not listed under the "Isotope", "%", and "Curies" columns, and "Zn-65 <1 %
| |
| * 93.02E-01 curies)" should read "Zn-65 <1 % (3.02E-01 curies)
| |
| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 5 .of34 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 2.0 EXECUTIVE
| |
| | |
| ==SUMMARY==
| |
| | |
| Nine Mile Point Unit 1 (NMP1) Radiological Effluent Control (REC) Program was established to limit the quantities of radioactive material that may be released based on calculated radiation doses or dose rates. Dose to Members of the Public due to radioactive materials released from the plant is limited l:ly Appendix I of 1 O CFR 50 and by 40 CFR 190. Operational doses to the public during 2022 were calculated to be very small compared to the limits required by regulation and compared to other sources of radiation dose and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1, Comparison to Regulatory Limits, below.
| |
| | |
| The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements and provides data related to plant operation, including: quantities of radioactive materials released in liquid and gaseous effluents; radiation doses to members of the public; solid radioactive waste shipped offsite for disposal; and other information as required by site licensing documents.
| |
| | |
| In 2022 the Land Use Census dose assessments due to radioactive gaseous effluents showed that the critical receptor for Nine Mile Point Unit 1 is child, due to C-14, at the nearest resident. The maximum Annual Organ Dose calculated for this receptor was 3.67E-01 mrem to the bone. This annual dose is a small fraction of the 10 CFR 50, Appendix I guideline of 15 mrem to the Maximum Organ per reactor unit.
| |
| | |
| Solid radioactive waste shipped offsite for disposal inclu.ded 3.47E+02 Curies and 3.30E+01 m 3 , shipped in eight shipments.
| |
| | |
| In addition to monitoring radioactive effluents, NMP has: a Radiological Environmental Monitoring Program (REMP) that monitors for buildup of radioactivity in the offsite environment. Data from the REMP is published in the James A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Envirorimental Operating Report (AREOR).
| |
| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 7 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Table 2, Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2022
| |
| * Exposure Pathway Dose Type Dose (mrem)
| |
| Fish and Vegetation Consumption Total Whole Body No Dose Total Maxium Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin of Whole No Dose Body Gaseous Effluents Total Whole Body 1.46E-01 (excluding C-14) Thyroid 1.49E-01 Maximum Organ Skin: 1.60E-01 Bone 1.3BE-01 Gaseous Effluent Total Whole Body 4.52E-02 (C-14 only) Maximum Organ Bone: 2.27E-01
| |
| | |
| Direct Radiation Total Whole Body 0.66E+00 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 16 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 4 .4 40 CFR 190 Regulatory Dose Limits for a Member of the Public
| |
| : 1. Total Dose (40 CFR 190)
| |
| : a. The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC in the unrestricted area due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:
| |
| : 1) Less than or equal to 25 mrem , Total Body or any Organ except Thyroid .
| |
| : 2) Less than or equal to 75 mrem , Thyroid .
| |
| | |
| 2 . In accordance with NRC memorandum 19 HPPOS-140 PDR-9111210378 ,
| |
| Guidance on Reporting Dose to Members of the Public from Normal Operations , updated October 17, 20 17, NMP1 dose to the public is less than (<)
| |
| 2 .25 mrem dose to any organ or the total body and less than(<) 1.75 mrem dose to the thyroid. Memorandum can be found on the NRC website:
| |
| https://www .nrc .gov/a bout -nrc/radiation / protects-you / hppos/hppos 140 . html.
| |
| | |
| 4.5 Onsite Doses (Within Site Boundary)
| |
| | |
| This section evaluates dose to non-occupationally exposed workers and members of the public that may be onsite for various reasons . The report must inclu de any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases as required by 1 O CFR 50.36a(a)(2). While within controlled or restricted areas , the limits from Sections 4 . 1 through 4.4 do not apply ; howeve r, 10 CFR 20.1301 dose lim it of 100 mrem per year TEDE and dose rate limit of 2 mrem per hour from externa l sources continue to apply. Occupancy times within the contro lled areas are generally sufficiently low to compensate for increase in the atmospheric dispersion factor above the site boundary . Groups of concern includ e fishermen, visitors, and daily contractors . Use of a conserva tive assumption for fishermen is 8 hours per week for 39-weeks spent inside the site boundary by these groups conservatively represents the most-exposed individual.
| |
| | |
| Table 3, Onsite Doses (Within Site Boundary)
| |
| Inhalation Dose External Effluent Approx. XIQ XIQ (mrem) Dose Source Sector Distance s/m"3 s/m"3 Iodine, Particulate , TLD and Total (Meters) (Vent) (Stack) C-14 & H-3 Gamma
| |
| | |
| Combined w 805 2 .S0E-06 9.60E -07 5.40E-03 (Bone) 4.33E-01 4.38E-01 Note: combined refers to the combined dose from the stack and reactor building and radwaste.
| |
| EC - Emeraency Condenser Annual Radioactive Effluent Release Report . I YEAR: 2022 I Page 18 of 34 Company: Constellation I Plant: Nine M.ile Point Unit 1
| |
| | |
| 5.4 Land Use Census Changes
| |
| | |
| In 2022, three new gardens were planted in the E, ESE, and SE sectors of the JAF owner-controlled area (OCA) which have since served as indicator locations for broad-leaf vegetation sampling. The gardens were planted due to a decline in local personal gardens in recent years and less sample availability. Aside from the addition of the three on-:site gardens, no changes to receptors or sampling locations were identified from the annual land use census.
| |
| | |
| 5.5 Meteorological Data
| |
| | |
| Meteorology data provided via Murray and Trettel, Inc. report. The Nine Mile Point meteorology tower was used to collect meteorology for both the JAF and NMP power plants. Accordingly, NMP meteorological monitoring program produced 77,447 hours of valid data out of 78,840 parameter hours during 2022'. Data recovery was 98.2%.
| |
| Calibrations were performed in May, August, and Octob,er. Specific sensor and data collection errors are available upon request.
| |
| 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days
| |
| | |
| Liquid radwaste discharge radiation monitors 11 and 12 are retired in place and were inoperable for all of 2022, as liquid batch discharges are* no longer expected to occur and were not performed at NMP1 during 2022. No other effluent radiation monitors required by the ODOM were inoperable for more than 30 days in 2022.
| |
| | |
| 5~7 Offsite Dose Calculation Manual (ODCM) Changes
| |
| | |
| NMP Unit 1 ODOM, CY-NM-170-301 Revision 38 was valid January to December 2022 with no changes required.
| |
| | |
| 5.8 Process Control Program (PCP) Changes
| |
| | |
| There were no changes to PCP in 2022.
| |
| | |
| 5.9 Radioactive Waste Treatment System Changes
| |
| | |
| There were no changes to the radioactive waste treatment system in 2022.
| |
| | |
| 5.10 Other Supplemental Information
| |
| | |
| During 2022, Nine Mile Point Units 1 and 2 had two non-emergency notifications to the NRC:
| |
| : 1. Event 55821 was completed on April 5, 2022.
| |
| : 2. Event 56089 was completed on September 4, 2022.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2022 l Page 19 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| 5.10.2 Independent Spe11t Fuel Storage Installation (ISFSI) Monitoring Program
| |
| | |
| Information concerning the ISFSI monitoring program and 2022 annual dose can be found in the 2022 James A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Environmental Operating Report published on the Nuclear Regulatory Commission website:
| |
| * https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific reports/nmp1-2. html.
| |
| | |
| 5.10.3 Carbon-14
| |
| | |
| Carbon-14 (C-14) is a naturally occurring radionuclide with a 5730-year half-life.
| |
| Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
| |
| | |
| In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents ar:id Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using EPRI Report 1021106, "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents".
| |
| This calculation uses active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for NMP Unit 1 during 2022 was 8.84E+00 curies.
| |
| | |
| Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. Carbon dioxide is assumed to make up 20-30% of the Carbon-14 gaseous emissions from the station based upon available references and on-site testing.
| |
| * 5.10.4 Errata/Corrections to Previous ARERRs
| |
| | |
| There are no corrections to prior ARERRs.
| |
| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 31 of 34 Company: Constellation I Plant: Nine Mile Point Unit 1
| |
| | |
| Attachment 2, Solid Waste Information
| |
| | |
| 1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
| |
| | |
| Table 13, Types of Solid Waste Summary NMP Unit 1
| |
| | |
| Total Volume Total Activity Est. Total Types of Waste (m3) (Ci) Error
| |
| (%)
| |
| : a. Spent resins, filter sludges, evaporator bottoms, etc. 3.30E+01 3.47E+02 25
| |
| : b. Dry compressible waste, contaminated equip, etc. 0.00E+00 0.00E+00 25
| |
| : c. Irradiated components, control rods, etc. o.oo*E+oo 0.00E+00 25
| |
| : d. Other (None reported) 0.00E+00 0.00E+00 25
| |
| | |
| 2.0 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY WASTE TYPE) ONLY >1%
| |
| ARE REPORTED. [NOTE 1]
| |
| | |
| Table 14, Major Nuclides NMP Unit 1
| |
| | |
| Major Nuclide Composition Isotope_ % Curies
| |
| : a. Spent resins, filter sludges, evaporator bottoms, etc. Co-60 79.39 2.75E+02
| |
| | |
| Fe-55 13.2 4.58E+01
| |
| | |
| Cs-137 3.09 1.07E+01 '
| |
| | |
| Mn-54 2.31 8.00E+00
| |
| * C-14 <1% 3.33E-01
| |
| | |
| Zn-65 <1% 3.02E-01
| |
| : b. Dry compressible waste, contaminated equip, etc.
| |
| * 0 00Et00
| |
| | |
| C. Irradiated components, control rods, etc.
| |
| * 0 00E+00
| |
| : d. Other (describe)
| |
| * 0 00E+00 Attachment 6 Errata and Corrections to the 20*22 NMP2 ARERR Summary of Identified Errata and Corrections
| |
| | |
| Multiple errata wete identified in the 2022 ARERR submittal for NMP2. The corrections are summarized below., and the corrected pages are included in their entirety in the order in which they are listed, unless otherwise noted.
| |
| * Corrections are indicated with revision bars on the right-hand side of the page. Corrected activities, doses, and numbers are balded and.italicized.
| |
| | |
| For all errata described below, dose was originally over-reported, and the corrected doses are lower.
| |
| : 1. On pages 5 and 19, the James A. FitzPatrick Nuclear Power Plant (JAFNPP) is erroneously referred to as "John A. FitzPatrick Nuclear Power Plant". This is a typographical-only error. *
| |
| | |
| *2. Page 7, Table 2, Dose Potentially Received by the Likely Most Exposed Member of the*
| |
| Public Outside the Site Boundary During 2022:
| |
| | |
| Gaseous effluent dose (excluding C-14) for both units slightly changed as a result of corrections to gaseous activity released in the 2022 NMP2 ARERR (Tables 7, 8, and 9).
| |
| : 3. Page 16, Table 3, Onsite Doses (Within Site Boundary)
| |
| Several issues were identified:
| |
| a) Dose from Iodine, Particulate, C-14 & H-3 was significantly overreported.
| |
| b) In accordance with the NMP1 and NMP2 ODCMs, dose from Noble Gas releases is evaluated by TLD measurement at the shoreline fishing location.
| |
| c) The incorrect TLDs were used for reporting dose at the shoreline fishing location.
| |
| d) The corrected table, for both units, also encompasses slight changes to calculated dose as a result of the over-reported Fe-55, Sr-89, Sr-90, and omitted Primary Containment Purges from NMP2 during 2022.
| |
| : 4. Page 18, Section 5.4, Land Use Census Changes
| |
| | |
| In 2022, three new gardens were planted in the E, ESE, and SE sectors of the JAF owner-controlled area (OCA) which have since served as indicator locations for broad-leaf vegetation sampling. Vegetation samples were obtained from these gardens in 2022, and results were included in the JAF/NMP 2022 AREOR in Table 6-12 on Page 6-23. *
| |
| : 5. Page 18, Section 5.6, Effluent Radiation Monitors Out of Service Greater Than 30 Days:
| |
| | |
| At both NMP1 and NMP2, Liquid Radwaste Discharge Radiation Monitors have been retired in place and were inoperable for all of-2022, as liquid batch discharges are no longer expected to occur, and were not performed at either unit for the year. This information has historically been included in ARERR submittals.
| |
| : 6. Pages 33-34, Attachment 3, Meteorological Data:
| |
| | |
| The only joint frequency table included is for the 200 ft Wind elevation for All Stability Classes as determined by 200'-30 ft Vertical Temperature Difference (b.T). Historically, Nine Mile Point has not included meteorological joint frequency distributions in ARERR submittals, which would be provided to the NRG upon request per both NMP1 and NMP2 ODCMs. As a correction, Attachment 7 to the 2023 ARERR contains classifications of atmospheric stability and meteorological joint frequency tables for 2022.
| |
| : 7. Page 18, Section 5.7, Offsite Dose Calculation Manual (ODCM) Changes:
| |
| | |
| CY-AA-170-3100 is incorrectly listed as the NMP2 dDCM procedure. N2-ODCM
| |
| .is the correct procedure.
| |
| : 8. Total activity of Noble Gases, Particulates with half-lives > 8 days, and Tritium were incorrectly reported in the following sections:
| |
| | |
| a) Page 23 - Gaseous Effluents Summation of All Releases NMP2
| |
| | |
| b) Page 25 - Gaseous Effluents - Ground Level Release Continuous Mode NMP2
| |
| | |
| c) Page 26 - Gaseous Effluents - Elevated Level Release Batch Mode NMP2
| |
| | |
| d) Pc,1ge 27 -Gaseous Effluents - Elevated Level Release Continuous Mode NMP2 e) Fe-55, Sr-89, and Sr-90 were overreported in 1st Quarter 2022 on Page 25 and in 1st and 2nd Quarter 2022 on Page 27. Activity was identified in two purges of the Primary Containme*nt, which occurred in 2 nd and 3rd Quarter 2022, that was omitted from Page 17, 5.1 Gaseous Batch Releases, and also from Page 26, Table 8 Gaseous Effluents - Elevated Level Release Batch Mode NMP2.
| |
| | |
| Due to these identified errata (2a through 2e above), dose included in several tables was recalculated. In addition to corrections made on Page 7, Table 2 and Page 16, Table 3 for both NMP1 and NMP2 ARERRs for 2022 as previously mentioned above, Page 6, Table 1, Nine Mile Point Unit 2 Dose Summary, was corrected as well.
| |
| * Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 5 of 34 Company: Constellation I Plant: Nine *Mile Point Unit 2
| |
| | |
| 2.0 EXECUTIVE
| |
| | |
| ==SUMMARY==
| |
| | |
| Nine Mile Point Unit 2 (NMP2) Radiological Effluent Co11trol (REC) Program was established to limit the quantities of radioactive material that may be released based on calculated radiation doses or dose rates. Dose to Members of the Public due to radioactive materials released from the plant is limited by Appendix I of 10 CFR 50 and by 40 CFR 190. Operational doses to the public during 2022 were calculated to be very small compared to the limits required by regulation and compared to other
| |
| * sources of radiation dose and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1, Comparison to Regulatory Limits, below.
| |
| | |
| The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements and provides data related 'to plant operation, including: quantities of radioactive materials re.leased in liquid and gaseous effluents; radiation doses to members of the public; solid radioactive waste shipped offsite for disposal; and other information as required by site licensing documents.
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| * In 2022 the Land Use Census dose assessments due to radioactive gaseous effluents showed that the critical receptor for Nine Mile point Unit 2 is child, due to C-14, at the nearest resident. The maximum Annual Organ Dose calculated for this receptor was 3.67E-01 mrem to the bone. This annual dose is a small fraction of the 10 CFR 50, Appendix I guideline of 15 mrem to the Maximum Organ per reactor unit.
| |
| | |
| Solid radioactive waste shipped offsite for disposal included 1.89E+01 Curies and 5.73E+02 m 3 , shipped in twenty-one shipments.
| |
| | |
| In addition to monitoring radioactive effluents, NMP has a Radiological Environmental Monitoring Program (REMP) that monitors for buildup of radioactivity in the offsite environment. Data from the REMP is published in the James A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Environmental Operating Report (AREOR).
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| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 7 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 2, Dose Potentially Received by the Likely Most Exposeg Member of the Public Outside the Site
| |
| * Boundary During 2022
| |
| | |
| Exposure Pathway Dose Type Dose (mrem)
| |
| Fish and Vegetation Consumption Total Whole Body No Dose Total Maxium Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin ofWhole No Dose Body Gaseous Effluents Total Whole Body 1.46E-01 (excluding C-14) Thyroid 1.49E-01 Maximum Organ Skin: 1.60E-01 Bone 1.3BE-01 Gaseous Effluent Total Whole Body 4.52E-02 (C-14 only) Maximum Organ Bone:. 2.27E-01 Direct Radiation Total Whole Body 0.66E+00 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 16 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| 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 e x cept Thyroid .
| |
| : 2) Less than or equal to 75 mrem , Thyroid .
| |
| | |
| 2 . In a c cordance with NRC memorandum 19 HPPOS - 140 PDR- 9111210378 ,
| |
| Guidance on Reporting Dose to Members of the Public from Normal Operations , updated October 17, 2017 , NMP2 dose to the public is less than( <)
| |
| 2 .25 mrem dose to any organ or the total body and less than ( <) 1. 75 mrem dose to the thyroid. Memorandum can be found on the NRC website:
| |
| https://www .nrc .gov/about-nrc/radiation/protects-you/hppos/hppos 140 . html.
| |
| | |
| 4.5 Onsite Doses (Within Site Boundary)
| |
| | |
| This section evaluate s 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 b e 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 c ontrolled areas are generally sufficiently low to compensate for increase in the atmo spheric dispersion factor above the site boundary . Groups of concern include fishermen, visitors, and daily contractors . Use of a conservat ive assumption for fishermen is 8 hours per week for 39-weeks spent inside the site boundary by these groups c onservatively represents the most - ex posed individual.
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| | |
| Table 3, Onsite Doses (Within Site Boundary)
| |
| Inhalation Dose External Effluent Appro x. X / Q XI Q (mrem) Dose 3 s/m 11 3 Iodine , Particulate, TLD and Total Sour c e Secto r Distance s/m /\\(Meters) (Vent) (Stack) C-14 & H-3 Gamma
| |
| | |
| Combined w 805 2.80 E-06 9 .60 E-07 5.40E-03 (Bone) 4.33E -01 4 .38E-01 No te : combine d refers to the co m b ined dose fro m the sta ck an d reac tor building and radwaste.
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| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 18 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| 5.4 Land Use Census Changes
| |
| | |
| In 2022, three new gardens were planted in the E, ESE, and SE sectors of the JAF owner-controlled area (OCA) which have since served as indicator locations for broad-leaf vegetation sampling. The gardens were planted due to a decline in local personal gardens in recent years and less sample availability. Aside from the addition of the three on-site gardens, no changes to receptors or. sampling locations were identified from the annual .land use census.
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| | |
| 5.5 Meteorological Data
| |
| | |
| Meteorology data provided via Murray and Trettel, Inc. report. The Nine Mile Point meteorology tower was used to collect meteorology for both the JAF and NMP power plants. Accordingly, NMP meteorological monitoring program produced 77,447 hours of valid data out of 78,840 parameter hours during 2022. Data recovery was 98.2%.
| |
| Calibrations were performed in May, August, and October. Specific sensor and data collection errors are available upon request.
| |
| * 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days
| |
| | |
| Liquid discharge radiation monitor 2LWS-CAB206 and associated discharge flow rate measuring devices 2LWS-FT330 and 2LWS-FT331 are retired in place and were inoperable for all of 2022, as liquid batch discharges are no longer expected to occur and were not performed at NMP2 during 2022. No other effluent radiation monitors required by the ODCM were inoperable for more than 30 days in 2022.
| |
| | |
| 5.7 Offsite Dose Calculation Manual (ODCM) Changes
| |
| | |
| NMP Unit 2 ODCM, N2-ODCM Revision 37 was valid January to December 2022 with no changes required.
| |
| | |
| 5.8 Process Control Program (PCP) Changes
| |
| | |
| There were no changes to PCP in 2022.
| |
| | |
| 5.9 Radioactive Waste Treatment System Changes
| |
| | |
| There were no changes to the radioactive waste treatment system in 2022.
| |
| | |
| 5.10 Other Supplemental Information
| |
| : a. During 2022, Nine Mile Point Units 1 and 2 had two non-emergency notifications to the NRC:
| |
| : 1. Event 55821 was completed on April 5, 2022.
| |
| : 2. Event 56089 was completed on September 4, 2022.
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| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 19 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 5.10.1 Outside Tanks
| |
| | |
| During 2022, there were no external water storage tanks containing radioactive material that leaked onto the ground or storm drain .
| |
| | |
| . 5.10.2 Independent Spent Fuel Storage Installation {ISFSI) Monitoring Program
| |
| | |
| Information concerning the ISFSI monitoring program and 2022 annual dose can be found in the 2022 James A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Station Annual Radiological Environmental Operating Report published on the Nuclear Regulatory Commission website:
| |
| https://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-specific reports/nmp1-2.html.
| |
| | |
| 5.10.3 Carbon-14
| |
| | |
| Carbon-14 (C-14) is a naturally occurring radionuclide with a 5730~year half-life.
| |
| Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
| |
| | |
| In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid arid Gaseous Effluents arid Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using EPRI Report 1021106, "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents".
| |
| This calculation uses active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for unit 2 during 2022 was 1.68E+01 curies.
| |
| | |
| Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. Carbon dioxide is assumed to make up 20-30% of the Carbon-14 gaseous emissions from the station based upon available references and on-site testing.
| |
| | |
| 5.10.4 Errata/Corrections to Previous ARERRs
| |
| | |
| There are no corrections to prior ARERRs:
| |
| Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 23 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Attachment 1, ARERR Release Summary Tables (RG-1.21 Tables)
| |
| | |
| 1.0 GASEOUS EFFLUENTS
| |
| | |
| Table 5, Gaseous Effluents Summation of All Releases NMP2
| |
| | |
| A. Fission & Activation Gases Units Quarter Quarter Quarter Quarter Est. Total 1 2 3 4 Error%
| |
| : 1. Total Release Ci
| |
| * 4.21E-07 2.82E+00
| |
| * 5.00E+01
| |
| : 2. Average release rate for the period µCi/sec
| |
| * 5.36E-08 3.55E-01
| |
| * B. Iodine
| |
| : 1. Total lodine-131 Ci 1.61 E-06 2.61 E-06 *
| |
| * 3.00E+01 I
| |
| : 2. Average release rate for the period µCi/sec 2.0?E-07 3.32E-07 *
| |
| * C. Particulates
| |
| : 1. Particulates with half-lives > 8 days Ci 1.59E-04 2.51E-04 6.44E-02 5.87E-02 3.00E+01 I
| |
| : 2. Average release rate for the period µCi/sec 2.04E-05 3.19E-05 8.11E-03 7.39E-03
| |
| | |
| D. Tritium
| |
| : 1. Total Release Ci 1.80E+01 2:0BE+01 1.93E+01 1.93E+01 5.00E+01 I
| |
| : 2. Average release rate for the period µCi/sec 2.32E+00 2.65E+00 2.43E+00 2.43E+00
| |
| | |
| E. Gross Alpha
| |
| : 1. Total Release Ci * * *
| |
| * 5.00E+01 I
| |
| : 2. Average release rate for the period µCi/sec * * *
| |
| * F. Carbon-14
| |
| : 1. Total Release Ci 3.34E+O0 4.52E+00 4.15E+0O 4.82E+00 5.00E+01 I
| |
| : 2. Average release rate for the period µCi/sec 3.18E-03 4.30E-03 3.95E-03 4.59E-03
| |
| | |
| % of limit is on Table 1, Nine Mile Point Unit 2 Dose Summary Annual Radioactive Effluent Release Report . I YEAR: 2022 I Page 25 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 7, Gaseous Effluents - Ground Level Release Continuous Mode NMP2
| |
| | |
| Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year
| |
| | |
| Ar-41 Ci * * * *
| |
| * Kr-85 Ci * * * *
| |
| * Kr-85m Ci * * * *
| |
| * Kr-87 Ci * * * *
| |
| * Kr-88 Ci * * * *
| |
| * Xe-133 Ci * * * *
| |
| * Xe-135 Ci * * * *
| |
| * Xe-135m Ci * '* * *
| |
| * Xe-138 Ci * * * *
| |
| * Total for Period Ci * * * *
| |
| * T~~(~~i;:f:/*){, i*
| |
| 1-131 Ci * * * *
| |
| * 1-133 Ci * * * *
| |
| * 1-135 Ci * * * *
| |
| * Total for Period Ci * * * *
| |
| * Co-58 Ci 4.24E-06
| |
| * 9.76E-06
| |
| * 1.40E-05 Co-60 Ci 1.21E-04 1.75E-04 2.90E-04 3.12E-04 8.98E-04 Sr-89 Ci * (Corrected) * * * * (Corrected)
| |
| Sr-90 Ci * (Corrected) * * * * (Corrected)
| |
| Cs-137 Ci
| |
| * 6.27E-06 *
| |
| * 6.27E-06 Fe-55 Ci * (Corrected) * * * * (Corrected)
| |
| Mn-54 Ci
| |
| * 7.01E-06 *
| |
| * 7.01E-06 Total for Period Ci 1.25E-06 1.88E-04 3.00E-04 3.12E-04 8.01E-04 Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 26 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| Table 8, Gaseous Effluents - Elevated Level Release Batch Mode NMP2
| |
| | |
| Units . Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year
| |
| | |
| Ar-41 Ci
| |
| * 4.21E-07 *
| |
| * 4.21E-01 Kr-85 Ci * * * *
| |
| * Kr-85m Ci * * * *
| |
| * Kr-87 Ci * * * *
| |
| * Kr-88 Ci * * * *
| |
| * Xe-133 Ci * * * *
| |
| * Xe-135 Ci * * * *
| |
| * Xe-135m Ci * * * *
| |
| * Xe-138 Ci * * * *
| |
| * Total for Period Ci
| |
| * 4:21E-07 *
| |
| * 4.21E-07
| |
| | |
| 1-131 Ci * * * *
| |
| * 1~133 Ci * * * *
| |
| * 1-135 Ci * * * *
| |
| * Total for Period Ci * * * *
| |
| * Co-58 Ci * * * *
| |
| * Co-60 Ci
| |
| * 2.72E-12 *
| |
| * 2.72E-12 Sr-89 Ci
| |
| * 5.76E-0B *
| |
| * 5.76E-0B Sr-90 Ci
| |
| * 7.20E-09 *
| |
| * 7.20E-09 Cs-137 Ci
| |
| * 1.20E-11 *
| |
| * 1.20E-11 Fe-55 Ci
| |
| * 8.00E-09* *
| |
| * 8.00E-09 Total for Period Ci
| |
| * 7.28E-0B *
| |
| * 7.28E-0B Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 27 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| Table 9, Gaseous Effluents - Elevated Level Release Continuous Mode NMP2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released
| |
| | |
| Ar-41 Ci *
| |
| * 2.40E+OO
| |
| * 2.40E+OO Kr-85 Ci * * * *
| |
| * Kr-85m Ci * * * *
| |
| * Kr-87 Ci * * * *
| |
| * Kr-88 Ci * * * *
| |
| * Xe-133 Ci * * * *
| |
| * Xe-135 Ci * * * *
| |
| * Xe-135m Ci * * * *
| |
| * Xe-138 Ci *
| |
| * 4.20E,-01
| |
| * 4.20E-01 Total for Period Ci *
| |
| * 2.82E+OO
| |
| * 2.82E+OO
| |
| | |
| 1-131 Ci 1.61E-06 2.61E-06 *
| |
| * 4.22E-06 1-133 Ci 8.70E-05 1.41 E-04 *
| |
| * 2.28E-04 1-135 Ci * * * *
| |
| * Total for Period Ci 8.86E-05 1.44E-04 *
| |
| * 2.32E-04
| |
| '!5arti2ffl~'t'es~ ~:r:r*c .,
| |
| ;,~ .. ~, ~ ,, ,,: ,;, ,<,; '.* , f, '" -'}<i', I' Co-58 Ci * * * *
| |
| * Co-60 Ci 3.38E-05 s.93E~os 6.41E-02 5.84E-02 1.23E-01 Sr-89 Ci * (Corrected) * (Corrected) * * * (Corrected)
| |
| Sr-90 Ci * (Corrected) * (Corrected) * * * (Corrected)
| |
| Cs-134 Ci * * * *
| |
| * Mn-54 Ci
| |
| * 1.93E-06
| |
| * 2.35E-06 4.28E-06 Fe-55 Ci * (Corrected) 1.30E-06 4.24E~os
| |
| * 4.37E-05 Zn-65 Ci * * * *
| |
| * Cs-137 Ci * *
| |
| * 1.84E-09 1.84E-09 Ni-63 Ci * * * *
| |
| * Ag-110m Ci * * * *
| |
| * Total for Period Ci 3.38E-05 6.25E-05 6.41 E-02 5.84E-02 1.23E-01 Annual Radioactive Effluent Release Report , I YEAR: 2022 I Page 17 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
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| | |
| 5.0 SUPPLEMENTAL INFORMATION
| |
| | |
| 5.1 Gaseous Batch Releases
| |
| | |
| 5.1.1 NMP Unit 2
| |
| * Number of batch releases 6 Total time period for batch releases 608 minutes Maximum time period for a batch release 127 minutes Average time period for a batch release 101 minutes Minimum time period for a batch release 50 minutes
| |
| | |
| 5.2 Liquid Batch Releases
| |
| | |
| 5.2.1 NMP Unit 2
| |
| | |
| Number of batch releases 0 Total time period for batch releases 0 minutes Maximum time period for a batch release 0 minutes Average time period for a batch release 0 minutes Minimum time period for a batch release 0 minutes Average total flow during period of release O gpm
| |
| | |
| 5.3 Abnormal Releases
| |
| | |
| 5.3.1 Gaseous Abnormal Releases
| |
| | |
| Number of releases 0 I Total activity released 0 Ci
| |
| | |
| 5.3.2 Liquid Abnormal Releases
| |
| | |
| Number of releases 0 Total activity released 0 Ci Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 6 of 34 Company: Constellation I Plant: Nine Mile Point Unit 2
| |
| | |
| 2.1 Comparison to Regulatory Limits
| |
| | |
| During 2022 all solid, liquid, and gaseous radioactive effluents from Nine Mile Point Unit 2 were well below regulatory limits, as summarized in Table 1 and Table 2.
| |
| | |
| Table 1, Nine Mile Point Unit 2 Dose Summary1
| |
| | |
| Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Dose Limit, Total Body Dose 00E+00 00E+00 00E+00 00E+00 00E+00 Total Body % of Yearly Limit * * * *
| |
| * Liquid Effluent Limit 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Dose Limit, Max Organ Dose 00E+00 00E+00 00E+00 00E+00 00E+00 Any Organ % of Yearly Limit * * * *
| |
| * Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose 00E+00 6.79E-11 4.41E-04 00E+00 4.41E-04 Gamma Air (Noble Gas) % of Yearly Limit
| |
| * 1.36E-09 8.82E-03
| |
| * 4.41E-03 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Dose Limit, Beta Air Dose 00E+00 3.72E-13 1.41E-05 00E+00 1.41E-05 Beta Air (Noble Gas) % of Yearly Limit
| |
| * 3.72E-12 1.41E-04
| |
| * 7.05E-05 Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 6.43E-04 7.32E-04 1.32E-01 1.21E-03 1.33E-01 (Iodine, Tritium, Particulates with % of Yearly Limit 8.57E-03 9.76E-03 1.76E+00 1.61E-02 8.87E-01
| |
| > 8-day half-life)
| |
| | |
| 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.
| |
| Attachment 7 Classification of Atmospheric Stability and Joint Frequency Tables for 2022 6
| |
| | |
| Table 5
| |
| | |
| Atmospheric Stabilitv Classes
| |
| | |
| Differential Temperature Differential Temperature Differential Temperature Interval Interval (in °F over the Interval (in °F over the Class (in °C/1 00m) <1> 100-30ft. range) (2l 200-30ft. range) <2J
| |
| | |
| Extremely Unstable AT :::. -1.9 AT:::_ -0.7 AT :::. -1.8
| |
| | |
| Moderately Unstable -1.9 < AT :::. -1.7 -0.7 <AT:::_ -0.6 -1.8 < AT :::. -1.6
| |
| | |
| Slightly Unstable -1.7 < AT:::. -1.5 -0.6 <AT:::. -0.5 -1.6 < AT :::. -1.4
| |
| | |
| Neutral -1.5 < AT:::. -0.5 -0.5< AT:::_ -0.2 -1.4 < AT :::. -0.5
| |
| | |
| Slightly Stable ~o.5 < AT:::. 1.5 -0.2 <AT:::. 0.5 -0.5 < AT :::. 1.4
| |
| | |
| Moderately Stable 1.5 < AT:::. 4.0 0.5< AT:::. 1.5 1.4 < AT :::. 3.7
| |
| | |
| ** **Extremely Stable 4.0 < AT 1.5< LI.T 3.7 < AT
| |
| | |
| i ** ;-*: ,*:: '' *.
| |
| * f: *.
| |
| | |
| (1l from NRC Regulatory Guide 1.23, Revision 1 (2l Reg Guide 1.23, Rev 1 intervals scaled for instrument heights on the Nine Mile Point meteorological tower
| |
| | |
| Murray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 (847) 963-9000 2022
| |
| | |
| Joint Frequency Tables
| |
| | |
| Murray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 <I> (847) 963-9000 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2022 - 2022
| |
| | |
| All Stabilities
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 1 10 16 34 82 64 31 20 21 3 0 282
| |
| | |
| NNE 0 8 15 29 83 118 59 53 30 0 0 395
| |
| ; ,,ii:.
| |
| NE 4 10 20 42 101 78 33 10 12 0 0 310
| |
| :,i :J't'' t** 1 i C p,,, '',!..
| |
| ENE 6 31 41 40 27 8 0 0 0 0 0 153
| |
| | |
| ' *~)I :,I ! ' '."
| |
| * E 6 31 67 59 40 20 0 0 0 0 0 223
| |
| ? ~ , .
| |
| ESE 5 39 63 99 124 72 32 8 4 5 1 452
| |
| | |
| :.-: . :'i! i ,, '!
| |
| SE 4 . 52 92 98 264 347 128 64 38 1 0 1088
| |
| | |
| SSE 6 29 59 82 292 337 154 65 38 0 0 1062 s 4 22 29 61 258 362 103 48 43 7 0 937
| |
| | |
| SSW 2 18 14 17 108 168 72 28 34 0 0 461
| |
| | |
| SW 0 10 12 26 52 96 51 32 17 1 0 297
| |
| | |
| WSW 3 10 17 29 110 198 105 80 94 27 44 717
| |
| | |
| w 3 7 21 24 84 109 83 56 171 107 147 812
| |
| | |
| WNW 2 6 26 32 49 66 56 55 99 58 94 543
| |
| | |
| NW 1 11 20 36 50 75 65 55 114 59 25 511
| |
| | |
| NNW 1 4 26 40 51 56 48 28 41 11 2 308
| |
| | |
| Tot 48 298 538 748 1775 2174 1020 602 756 279 313 8551
| |
| | |
| Hours of Calm . 21 Hours of Variable Direction 0 Hours of Valid Data . 8572 Hours of Missing Data 188 Hours in Period . .. 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022 - 2022
| |
| | |
| Stability Cl ass A Extremely Unstable based on Lapse Rate
| |
| | |
| El evati ans: : Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1* 3.1- 4.1* 5.1- 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 0 3 22 16 7 5 8 1 0 62
| |
| | |
| NNE 0 0 0 1 3 17 6 22 13 0 0 62
| |
| | |
| NE 0 0 0 0 3 5 1 0 0 0 0 9
| |
| | |
| ENE 0 0 . 0 0 0 1 0 0 0 0 0 1
| |
| | |
| E 0 0 0 0 1 0 0 0 0 0 0 1
| |
| | |
| ESE 0 0 1 0 0 2 4 0 0 0 0 7 SE 0 0 0 3 5 19 10 4 8 0 0 49
| |
| | |
| SSE 0 .. *, 0 0 1 11 24 10 2 0 0 0 48
| |
| <fl , r, ;,
| |
| s 0 0 1 1 8 16 4 3 1 0 0 34
| |
| | |
| SSW i) 0 0 0 5 7 0 1 0 0 0 13
| |
| | |
| SW 0 0 0 0 4 3 1 0 1 0 0 9
| |
| | |
| \\6W 0 *o 0 1 12 40 14 8 13 7 10 105
| |
| | |
| w tJ 0 3 2 25 41 26 9 33 20 40 199
| |
| | |
| ~/NW 0 0 5 20 18 8 13 7 16. 19 33 139
| |
| | |
| NW 0 0 5 17 26 9 10 12 19 25 17 140
| |
| | |
| NNW 0 0 2 13 27 19 5 6 14 5 0 91
| |
| | |
| Tot *o 0 17 62 170 227 111 79 126 77 ioo 969
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 969 Hours of Missing Data 188 Hours in Period ... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022
| |
| * 2022
| |
| | |
| Stability Class B Moderately Unstable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1* 4.1- 5.1- 6.1- 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5,0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 0 7 7 3 2 1 3 0 0 23
| |
| | |
| NNE o 0 0 1 9 11 10 11 12 0 0 54
| |
| | |
| NE 0 o 1 D 2 3 0 o o 0 D 6
| |
| '' ~ '.. : .
| |
| ENE 0 0 1 1 0 D D D D D D 2
| |
| , . !!~
| |
| * I.
| |
| E D 0 0 0 1 0 0 0 0 0 0 1 ESE 0 0 1 2 2 4 1 1 D 0 0 11
| |
| | |
| SE 0 0 1 1 7 18 4 1 0 D 0 32
| |
| | |
| SSE
| |
| * 0 :*, 0 0 2 9 17 5 2 D D 0 35 s 0 0 0 1 5 14 11 5 0 0 0 36
| |
| | |
| SSl1 0 0 1 0 4 5 1 0 0 D 0 11
| |
| | |
| SW 0 0 0 2 4 2 0 0 0 a 0 8
| |
| | |
| WSW 0 0 0 D 4 12 4 6 5 5 4 40
| |
| | |
| w 0 0 0 1 5 9 4 5 21 25 17 87
| |
| | |
| WNW 0 1 2 4 4 4 8 8 17 11 12 71
| |
| | |
| NW 0 2 1 5 2 14 13 9 36 18 4 104
| |
| | |
| NNW 0 0 3 4 2 3 10 6 13 4 2 47
| |
| | |
| Tot 0 3 11 31 67 119 73 55 107 63 39 568
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 568 Hours of Missing Data 188 Hours in Period ... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022 - 2022
| |
| | |
| Stability Class C Slightly Unstable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1* 3.1* 4.1- 5.1* 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 2 1 4 7 9 13 5 6 2 0 49
| |
| | |
| NNE 0 0 1 5 9 8 15 12 5 0 0 55
| |
| | |
| NE 0 0 1 3 2 3 1 0 10 0 0 20
| |
| | |
| ENE 0 0 0 1 2 0 0 0 0 0 0 3
| |
| | |
| E 0 0 3 3 1 0 0 0 0 0 0 7
| |
| | |
| ESE 0 0 0 0 2 3 0 2 0 0 0 7
| |
| | |
| SE 0 1 1 1 2 20 6 3 2 0 0 36
| |
| | |
| SSE** 0 .* ',o *o 1 7 13 11 4 4 0 0 40
| |
| . ( .,.
| |
| s 0 0 1 2 6 26 7 2 2 0 0 46
| |
| | |
| SSW 0 0 1 1 4 5 0 1 0 0 0 12
| |
| | |
| SW 0 0 1 1 1 4 4 1 1 0 0 13
| |
| | |
| WSW 0 0 0 0 4 14 12 13 14 3 6 66
| |
| | |
| w 0 0 1 2 11 10 14 11 22 21 33 125
| |
| | |
| WNW 0 0 4 1 3 12 7 18 28 10 13 96
| |
| | |
| NW 0 1 3 2 7 8 19 11 38 11 0 100
| |
| | |
| NNW 1 0 0 3 1 5 18 8 8 1 0 45
| |
| | |
| Tot 1 *4 18 30 69 140 127 91 140 48 52 720
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 720 Hours of Missing Data 188 Hours in Period ... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022 - 2022
| |
| | |
| Stability Class D Neutral based on Lapse Rate
| |
| | |
| Elevations: : Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1* 1.6- 2.1- 3.1* 4.1* 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 1 6 7 13 26 31 8 8 2 0 0 102
| |
| | |
| NNE 0 3 9 11 45 75 27 8 0 0 0 178
| |
| . ; q' NE 1 4 9 17 73 64 31 10 2 a a 211
| |
| ;,\\ :*c **j' t****j In~-
| |
| ENE 2 11 18 16 15 6 0 a 0 o 0 68
| |
| * .. r !/*,' *1_,_;,
| |
| E 0 7 18 21 16 17 o o 0 0 0 79
| |
| | |
| \\: i**;
| |
| ESE 0 7 10 14 37 44 23 4 4 1 0 144 SE 0 4 7 16 78 118 69 43 24 0 0 359
| |
| | |
| SSE 0 ,o 10 12 57 108 66 42 27 0 0 322 s 1 3 12 17 80 122 46 26 31 7 ,Q 345
| |
| | |
| SSW a 6 2 5 40 101 66 24 34 0 0 278
| |
| | |
| SW 0 1 5 4 19 60 40 29 14 1 0 173
| |
| | |
| WSW 1 3 7 9 43 86 51 44 49 9 24 326
| |
| | |
| w 1 ,3 8 7 20 36 36 26 83 35 53 308
| |
| | |
| WNW 1 2 5 6 20 32 25 19 29 16 36 191
| |
| | |
| NW 0 4 3 7 11 34 23 22 21 5 4 134
| |
| | |
| NNW *o 2 12 14 12 23 13 8 6 1 0 91
| |
| | |
| Tot 8 66 142 189 592 957 524 313 326 75 117 3309
| |
| | |
| Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 3309 Hours of Missing Data 188 Hours in Period .. 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022
| |
| * 2022
| |
| | |
| Stability Class E Slightly Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/sl Direction 0.5- 1.1- 1.6- 2.1* 3.1* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 1 5 6 14 0 1 1 2 0 0 30
| |
| | |
| NNE 0 3 3 6 8 2 1 0 0 0 0 23
| |
| | |
| NE 1 5 6 14 11 2 0 0 0 0 0 39 ENE 2 11 16 13 6 1 0 0 D 0 0 49
| |
| | |
| E 2 11 29 23 15 3 0 0 0 0 0 83
| |
| | |
| ESE 3 10 17 27 51 17 4 1 0 4 1 135
| |
| | |
| SE 0 6 21 20 88 155 39 13 4 1 0 347
| |
| | |
| SSE 1 *9 8 21 96 154 62 15 7 0 0 373 s 2 7 6 18 69 150 35 12 9 0 0 308
| |
| | |
| SSW 0 3 5 6 37 49 5 2 0 0 0 107
| |
| | |
| SW 0 6 2 17 20 27 4 2 1 0 0 79
| |
| | |
| WSW 1 5 4 14 37 41 18 6 9 2 0 137
| |
| | |
| w 1 4 5 5 17 10 3 5 11 6 4 71
| |
| | |
| WNW 0 3 4 0 3 9 3 2 9 2 0 35
| |
| | |
| NW 1 4 2 1 3 7 0 1 0 0 0 19
| |
| | |
| NNW 0 2 5 2 8 5 2 0 0 0 0 24
| |
| | |
| Tot 14 90 138 193 483 632 177 60 52 15 5 1859
| |
| | |
| Hours of Calm .. 18 Hours of Variable Direction 0 Hours of Valid Data . 1877 Hours of Missing Data 188 Hours in Period .. , 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2022
| |
| * 2022
| |
| | |
| Stability Class *F Moderately Stable based on Lapse Rate
| |
| | |
| Elevations:: Winds 30ft Stability 200ft
| |
| | |
| Wind Wind.Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1* 3.1- 4.1- 5.1- 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N D 1 3 0 3 4 a D 0 0 D 11
| |
| | |
| NNE 0 2 2 3 4 2 0 0 0 0 0 13
| |
| | |
| NE 2 1 2 5 8 1 0 0 0 0 0 19
| |
| | |
| ENE 1 4 3 5 3 0 0 0 0 0 0 16
| |
| | |
| E 1 9 15 9 3 0 0 0 0 0 0 37
| |
| | |
| ESE 2 11 18 33 17 2 0 0 0 0 0 83
| |
| | |
| ''!*'.," 1_.* '
| |
| SE 3 17 16 20 44 13 0 0 0 0 0 113
| |
| | |
| SSE 2 10 11 20 47 16 0 0 0 0 0 106 s 0 6 7 14 50 28 0 0 0 0 0 105
| |
| | |
| SSW 0 4 5 3 17 1 0 0 0 0 0 30
| |
| | |
| SW 0 2 4 2 4 0 1 0 0 0 0 13
| |
| | |
| WSL1 1 0 5 3 6 5 6 3 3 1 0 33
| |
| | |
| w 1 0 0 2 3 3 0 0 1 0 0 10
| |
| | |
| WNW 0 *o 4 1 1 1 0 1 0 0 0 8
| |
| | |
| NW 0 0 1 2 0 3 0 0 0 0 0 6
| |
| | |
| NNW 0 0 2 3 0 1 0 0 0 0 0 6
| |
| | |
| Tot 13 67 98 125 210 80 7 4 4 1 0 609
| |
| | |
| Hours of Calm .. 1 Hours of Variable Direction 0 Hours of Valid Data . 610 Hours of Missing Data 188 Hours in Period ... 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan
| |
| * Dec for years 2022
| |
| * 2022
| |
| | |
| Stability Class G Extremely Stable based on Lapse Rate
| |
| | |
| El evati ans: : ~Jinds 30ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1* 5.1* 6.1* 8,1* >10 .00 Sector <D.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 0 0 1 3 1 0 0 0 0 o 5
| |
| | |
| NNE 0 o o 2 5 3 o o o 0 o 10
| |
| | |
| NE 0 o 1 3 2 o o o o 0 0 6
| |
| .-*,,-:7 ENE 1 5 3 4 1 o o 0 0 0 0 14
| |
| ;,;. ':',,(
| |
| E 3 4 2 3 3 0 D D 0 D 0 15
| |
| | |
| ESE 0 11 16 23 15 0 0 0 0 0 o 65 SE 1 24 46 37 40 4 0 D 0 o 0 152
| |
| | |
| .4.'
| |
| SSE 3 '' '10 30 25 65 5 0 o 0 0 0 138 s 1 6 2 8 40 6 0 o 0 0 a 63
| |
| | |
| SSW 2 5 0 2 1 0 a 0 0 0 a 10
| |
| | |
| SW a 1 0 0 0 0 1 0 0 0 0 2
| |
| | |
| WSW 0 2 1 2 4 a 0 D 1 0 0 10
| |
| | |
| w o 0 4 5 3 0 D 0 0 0 D 12
| |
| | |
| WNW 1 D 2 D 0 0 0 0 0 0 0 3
| |
| | |
| NW D 0 5 2 1 0 0 D D 0 0 8
| |
| | |
| NNW 0 0 2 1 1 0 0 D D D D 4
| |
| | |
| Tot 12 68 114 118 184 19 1 D 1 0 D 517
| |
| | |
| Hours of Calm . 2 Hours of Variable Direction 0 Hours of Valid Data . 519 Hours of Missing Data 188 Hours in Period . .. 8760 Joint Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022 - 2022
| |
| | |
| All Stabilities
| |
| | |
| Elevations: : Winds 200ft Stability 200ft
| |
| | |
| Wind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N 0 4 12 17 40 58 43 27 54 19 44 318
| |
| | |
| NNE 1 2 8 9 38 67 34 47 99 50 116 471
| |
| | |
| NE 0 4 12 20 50 51 46 44 40 25 12 304
| |
| | |
| ENE 0 3 10 21 39 47 10 4 6 0 0 140
| |
| | |
| E 0 2 10 11 58 65 22 12 17 0 0 197
| |
| | |
| ESE 1 4 3 13 37 65 55 42 48 17 7 292
| |
| | |
| ~, 'I f
| |
| * SE 0 3 9 10 35 96 103 113 303 116 38 826
| |
| | |
| SSE 0 ,; :, 1 6 10 27 114 80 132 355 125 44 894 s 0 5 3 11 25 95 109 132 344 108 4.5 877
| |
| | |
| SSW 1 3 6 6 31 76 109 133 210 21 1 597
| |
| | |
| SW 1 4 6 15 25 74 68 86 163 48 20 510
| |
| | |
| ~/SW 0 4 9 11 38 104 82 106 206 110 150 820
| |
| | |
| w 0 4 7 18 37 103 63 70 143 123 288 856
| |
| | |
| WNW 1 3 9 12 34 67 34 23 101 82 221 587
| |
| | |
| NW 1 5 4 9 38 42 40 41 116 84 141 521
| |
| | |
| NNW 1 3 12 13 43 44 34 26 82 45 46 349
| |
| | |
| Tot 7 54 126 206 595 1168 932 1038 2287 973 1173 8559
| |
| | |
| Hours of Calm 12 Hours of Variable Direction 0 Hours of Valid Data . 8571 Hours of Missing Data 189 Hours in Period ... 8760 Joi*nt Frequency Distribution
| |
| | |
| Site:: Nine Mile Point
| |
| | |
| Period:: Months Jan - Dec for years 2022 - 2022
| |
| | |
| Stability Class A Extremely Unstable based on Lapse Rate
| |
| | |
| Elevations:: Winds 200ft Stability 200ft
| |
| | |
| l1ind Wind Speed Range (m/s)
| |
| Direction 0.5- 1.1- 1.6- 2.1* 3.1- 4.1- 5.1- 6.1- 8.1- >10.00 Sector <0,50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total
| |
| | |
| N o 0 0 0 11 16 8 4 12 7 9 67
| |
| | |
| NNE 0 0 0 1 1 8 3 4 9 7 34 67
| |
| | |
| NE 0 0 0 0 0 2 1 1 3 1 0 8
| |
| ,*ni ENE 0 0 0 0 0 0 0 0 0 0 0 0
| |
| | |
| 1_. ..
| |
| E 0 0 0 0 0 1 0 1 0 0 0 2
| |
| " *' ( *,~ i . *( ,.,,' l "/ l i '* !
| |
| ESE 0 0 0 1 0 0 1 0 3 0 0 5
| |
| | |
| '.,'!) , 1 :: )'t(l f I SE o 0 0 0 1 4 4 8 19 5 4 45 SSE** 0 *; '*O ;o 0 2 13 10 7 8 6 0 46 .,
| |
| s 0 0 0 o 3 8 4 7 13 5 0 40
| |
| | |
| SSW o 'O 0 0 1 2 6 2 0 1 0 12
| |
| | |
| SW *o *o 0 0 0 0 3 2 3 0 0 8
| |
| | |
| WSW 0 0 0 1 0 14 14 23 29 11 29 121
| |
| | |
| w 0 0 0 1 8 22 17 20 29 23 60 180
| |
| | |
| WNW 0 o 1 o 11 26 13 2 14 12 63 142
| |
| | |
| NW o o o 2 13 21 4 2 17 15 47 121
| |
| | |
| NNW 0 *o o 6 17 14 11 6 10 13 28 105
| |
| | |
| Tot' o *O 1 12 68 151 99 89 169
| |
| * 106 274 969
| |
| | |
| Hours of Calm o Hours of Variable Direction 0 Hours of Valid Data . 969 Hours of Missing Data 189 Hours in Period . 8760}}
| |
