Text

Edwin I.Hatch Nuclear Station, Units 1 & 2; Joseph M. Farley Nuclear Station, Units 1 & 2; and Vogtle Electric Station, Units 1 & 2 - Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports Fo
	ML20119B062
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	04/27/2020
From:	Gayheart C; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-20-0419
	Download: ML20119B062 (260)
	v • d • e

Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316 cagayhea@southernco.com April 27, 2020 Docket Nos.: 50-321 50-348 50-424 NL-20-0419 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Ladies and Gentlemen:

In accordance with subsection 5.4.1 of the referenced plants Environmental Protection Plans (Appendix B to the operating licenses), Southern Nuclear Operating Company hereby submits the Annual Non-Radiological Environmental Operating Reports for 2019.

In accordance with section 5.6.3 of the referenced plants Technical Specifications, Southern Nuclear Operating Company hereby submits the Annual Radioactive Effluent Release Reports for 2019. Technical Specification 5.5.1.c for each plant requires that the Offsite Dose Calculation Manual (ODCM) be provided as part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. During the reporting period for the Annual Radioactive Effluent Release Reports for 2019, there were no ODCM revisions.

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.

Respectfully submitted, Cheryl A. Gayheart Regulatory Affairs Director CAG/kgl/sm

U. S. Nuclear Regulatory Commission NL-20-0419 Page 2

Enclosures:

1. Edwin I. Hatch Nuclear Plant - Units 1&2 Annual Non-Radiological Environmental Operating Report for 2019

2. Joseph M. Farley Nuclear Plant - Units 1&2 Annual Non-Radiological Environmental Operating Report for 2019

3. Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Report for 2019

4. Edwin I. Hatch Nuclear Plant - Units 1&2 Annual Radioactive Effluent Release Report for 2019

5. Joseph M. Farley Nuclear Plant - Units 1&2 Annual Radioactive Effluent Release Report for 2019

6. Vogtle Electric Generating Plant - Units 1&2 Annual Radioactive Effluent Release Report for 2019 cc: Regional Administrator, Region ll NRR Project Manager - Farley, Hatch, Vogtle 1&2 Senior Resident Inspector - Farley, Hatch, Vogtle 1&2 RType: CGA02.001

NL-20-0419 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Enclosure 1 Edwin I. Hatch Nuclear Plant - Units 1&2 Annual Non-Radiological Environmental Operating Report for 2019 Page 1 of 2 Annual Non-Radiological Environmental Operating Reports for 2019 EDWIN I. HATCH NUCLEAR PLANT - UNITS 1 AND 2 I. Introduction This report is submitted in accordance with Subsection 5.4.1 of the Edwin I. Hatch Nuclear Plant Environmental Protection Plan, Appendix B to Facility Operating Licenses DPR-57 and NPF-5.

This report describes implementation of the Environmental Protection Plan for the calendar year 2019.

II. Reporting Requirements A. Summaries and Analyses of Results of Environmental Protection Activities Required by Subsection 4.2 of the Environmental Protection Plan (EPP) for the Reporting Period

1. Aquatic Monitoring - Liquid effluent monitoring was performed in accordance with the State of Georgia National Pollutant Discharge Elimination System (NPDES)

Permit GA0004120; there was no additional requirement for aquatic monitoring during the year.

2. Terrestrial Monitoring - Terrestrial monitoring is not required.

3. Maintenance of Transmission Line Corridors - There is no reporting requirement associated with this condition.

B. Comparisons of the Years Monitoring Activities with Preoperational Studies, Operational Controls, and Previous Nonradiological Environmental Monitoring Reports These comparisons were not required because no nonradiological environmental monitoring programs were conducted during the reporting period beyond those performed in accordance with NPDES Permit No. GA0004120.

C. Assessment of the Observed Impacts of Plant Operation on the Environment There were no significant adverse environmental impacts associated with plant operation during the year.

D. EPP Noncompliance and Corrective Actions There were no EPP noncompliances during the year.

Page 2 of 2 Annual Non-Radiological Environmental Operating Reports for 2019 E. Changes in Station Design or Operation, Tests, or Experiments Made in Accordance with EPP Subsection 3.1 Which Involved a Potentially Significant Unreviewed Environmental Question There were no changes in station design or operation, tests, or experiments which involved a potentially significant, unreviewed environmental question.

F. Nonroutine Reports Submitted in Accordance with EPP Section 5.4.2 There were no nonroutine reports submitted during the year.

NL-20-0419 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Enclosure 2 Joseph M. Farley Nuclear Plant - Units 1&2 Annual Non-Radiological Environmental Operating Report for 2019 Page 1 of 1 Annual Non-Radiological Environmental Operating Reports for 2019 JOSEPH M. FARLEY NUCLEAR PLANT - UNITS 1 AND 2 I. Introduction In accordance with Subsection 5.4.1 of the Joseph M. Farley Nuclear Plant Environmental Protection Plan, Appendix B to Facility Operating License Nos. NPF-2 and NPF-8, this report is submitted summarizing implementation of the Environmental Protection Plan for calendar year 2019.

II. Reporting Requirements A. Summaries and Analyses of Results of Environmental Protection Activities Required by Subsection 4.2 of the Environmental Protection Plan (EPP) for the Reporting Period

1. Aerial Remote Sensing - Aerial Remote Sensing is no longer required.

2. Herbicide Application - There is no reporting requirement associated with this condition.

3. Land Management - There is no reporting requirement associated with this condition.

B. Comparison of the Years Monitoring Activities with Preoperational Studies, Operational Controls, and Previous Non-Radiological Monitoring Reports These comparisons were not required because no nonradiological environmental monitoring programs were conducted during the reporting period beyond those performed in accordance with NPDES Permit No. AL0024619.

C. Assessment of the Observed Impacts of Plant Operation on the Environment There were no significant adverse environmental impacts associated with plant operation during the year.

D. EPP Noncompliance and Corrective Actions There were no EPP noncompliances during the year.

E. Changes in Station Design or Operation, Tests, or Experiments Made in Accordance with EPP Section 3.1 Which Involved a Potentially Significant Unreviewed Environmental Question There were no changes in station design or operation, tests, or experiments which involved a potentially significant, unreviewed environmental question.

F. Nonroutine Reports Submitted in Accordance with EPP Section 5.4.2 There were no nonroutine reports submitted during the year.

NL-20-0419 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Enclosure 3 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Report for 2019 Page 1 of 2 Annual Non-Radiological Environmental Operating Reports for 2019 VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 I. Introduction In accordance with Subsection 5.4.1 of the Vogtle Electric Generating Plant (VEGP)

Environmental Protection Plan (Nonradiological), Appendix B to Facility Operating License Nos.

NPF-68 and NPF-81, this report is submitted describing implementation of the Environmental Protection Plan for the calendar year 2019.

II. Reporting Requirements A. Summaries and Analyses of Results of Environmental Protection Activities Required by Subsection 4.2 of the Environmental Protection Plan (EPP) for the Reporting Period

1. Aquatic Monitoring - Liquid effluent monitoring was performed in accordance with State of Georgia National Pollutant Discharge Elimination System (NPDES) Permit GA0026786; there was no additional requirement for aquatic monitoring during the year.

2. Terrestrial Monitoring - Terrestrial monitoring is not required.

3. Maintenance of Transmission Line Corridors - There is no reporting requirement associated with this condition.

4. Noise Monitoring - There were no complaints reported regarding noise along the VEGP-related, high-voltage transmission lines.

B. Comparison of the Years Monitoring Activities with Preoperational Studies, Operational Controls, and Previous Monitoring Reports These programs were not required because no nonradiological environmental monitoring programs were conducted during the reporting period beyond those performed in accordance with NPDES Permit No. GA0026786 referenced in Section A above.

C. Assessment of the Observed Impacts of Plant Operation on the Environment There were no significant adverse environmental impacts associated with plant operation during the year.

D. EPP Noncompliance and Corrective Actions There were no EPP noncompliances during the year.

Page 2 of 2 Annual Non-Radiological Environmental Operating Reports for 2019 E. Changes in Station Design or Operation, Tests, or Experiments Made in Accordance with EPP Subsection 3.1 Which Involved a Potentially Significant Unreviewed Environmental Question There were no changes in station design or operation, tests, or experiments which involved a potentially significant, unreviewed environmental question.

F. Nonroutine Reports Submitted in Accordance with EPP Section 5.4.2 There were no nonroutine reports submitted during the year.

NL-20-0419 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Enclosure 4 Edwin I. Hatch Nuclear Plant - Units 1&2 Annual Radioactive Effluent Release Report for 2019

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT- UNITS 1 AND 2 NRC DOCKET NOS. 50-321 AND 50-366 FACILITY OPERATING LICENSE NOS. DPR-57 AND NPF-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1, 2019 TO DECEMBER 31, 2019 Prepared by: Brianna Hughes ~

Jamie Johnson~

Reviewed by:_ _ _ _ _ _ ~---""5~-=-------

ACKNOWLEDGEMENT OF OWNERSHIP The contents of this Annual Radioactive Effluent Release Report, contained herein, are true and accurate to the best of my knowledge. I understand that I am ultimately responsible for the information that has been captured within these pages.

Jamie Johnson ~

Chemistry Manager

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1, 2019 THROUGH DECEMBER 31, 2019 SECTION TITLE PAGE 1.0 Liquid Effluents 1 1.1 Regulatory Requirements 1 1.1.1 Concentration Limits 1 1.1.2 Dose Limits 1 1.2 Effluent Concentration Limit 1 1.3 Measurements and Approximations of Total 2 Radioactivity for Liquid Radwaste 1.3.1 Total Radioactivity Determination for Liquid Radwaste 2 1.4 Measurements and Approximations of Total 4 Radioactivity for Groundwater Outfalls -

Y22N003A/12B and Y22N008A 1.4.1 Total Radioactivity Determination for Groundwater 4 Outfalls 1.5 Total Error Estimation 5 1.6 Liquid Effluent Release Data 6 1.7 Radiological Impact Due to Liquid Releases 7 1.8 Liquid Effluents - Batch Releases 7 1.9 Liquid Effluents - Continuous Releases 7 i

SECTION TITLE PAGE 1.10 Liquid Effluents - Abnormal Releases 7 2.0 Gaseous Effluents 28 2.1 Regulatory Requirements 28 2.1.1 Dose Rate Limits 28 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 28 2.1.3 Doses to a Member of the Public 28 2.2 Measurements and Approximations of Total 29 Radioactivity 2.2.1 Sample Collection and Analysis 29 2.2.2 Total Quantities of Radioactivity, Dose Rates 30 and Cumulative Doses 2.2.2.1 Fission and Activation Gases 30 2.2.2.2 Radioiodine, Tritium and Particulate Releases 30 2.2.2.3 Gross Alpha Release 31 2.2.3 Total Error Estimation 31 2.3 Gaseous Effluent Release Data 33 2.4 Radiological Impact Due to Gaseous Releases 34 2.5 Gaseous Effluents - Batch Releases 34 2.6 Gaseous Effluents - Abnormal Releases 34 3.0 Solid Waste 69 3.1 Regulatory Requirements 69 3.1.1 Solid Radioactive Waste System 69 3.1.2 Reporting Requirements 69 ii

SECTION TITLE PAGE 3.2 Solid Waste Data 70 4.0 Doses to Members of the Public Inside The 74 Site Boundary 4.1 Regulatory Requirements 74 4.2 Demonstration of Compliance 74 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 79 5.1 Regulatory Requirements 79 5.2 Demostration of Compliance 79 6.0 Meteorological Data 79 7.0 Program Deviations 79 7.1 Inoperable Liquid or Gaseous Effluent 79 Monitoring Instrumentation 7.1.1 Regulatory Requirements 79 7.1.2 Description of Deviations 80 7.2 Tanks Exceeding Curie Content Limits 80 7.2.1 Regulatory Requirements 80 7.2.2 Description of Deviations 80 7.3 Effluent Sample Analysis Exceeding Minimum 80 Detectable Concentration (MDC) 7.3.1 Regulatory Requirement 80 7.3.2 Description of Deviation 80 iii

SECTION TITLE PAGE 8.0 Changes to the Plant Hatch 80 Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements 80 8.2 Description of Changes 81 9.0 Major Changes to the Liquid, Gaseous or 81 Solid Radwaste Treatment Systems 9.1 Regulatory Requirements 81 9.2 Description of Major Changes 82 APPENDIX:

A Carbon 14 Letter 83 iv

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases 8 Unit 1 (Quarters 1, 2, 3 and 4) 1-1B Liquid Effluents - Summation of All Releases 9 Unit 2 (Quarters 1, 2, 3 and 4) 1-1C Liquid Effluents - Summation of All Releases 10 Site (Quarters 1, 2, 3 and 4) 1-2A Liquid Effluents - Unit 1 (Quarters 1, 2, 3 and 4) 11 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3 and 4) 14 1-2C Liquid Effluents - Site (Quarters 1, 2, 3 and 4) 17 1-3A Doses to a Member of The Public Due to Liquid 20 Releases Unit 1 (Quarters 1, 2, 3 and 4) 1-3B Doses to a Member of The Public Due to Liquid 21 Releases Unit 2 (Quarters 1, 2, 3 and 4) 1-4 Minimum Detectable Concentration - 22 Liquid Sample Analysis 1-5A Liquid Effluents - Batch Release Summary 23 Unit 1 1-5B Liquid Effluents - Batch Release Summary 24 Unit 2 v

TABLE LIST OF TABLES PAGE 1-6A Liquid Effluents - Abnormal Release 25 Summary Unit 1 1-6B Liquid Effluents - Abnormal Release 26 Summary Unit 2 1-6C Liquid Effluents - Abnormal Release 27 Summary Site 2-1A Gaseous Effluents - Summation of All 35 Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-1B Gaseous Effluents - Summation of All 36 Releases -Unit 2 (Quarters 1, 2, 3 and 4) 2-1C Gaseous Effluents - Summation of All 37 Releases - Site (Quarters 1, 2, 3 and 4) 2-2A Gaseous Effluents - Elevated Releases Unit 38 1 (Quarters 1, 2, 3 and 4) 2-2B Gaseous Effluents - Elevated Releases Unit 43 2 (Quarters 1, 2, 3 and 4) 2-2C Gaseous Effluents - Elevated Releases Site 48 (Quarters 1, 2, 3 and 4) 2-3A Gaseous Effluents - Ground Level 53 Releases Unit 1 (Quarters 1, 2, 3 and 4) 2-3B Gaseous Effluents - Ground Level 55 Releases Unit 2 (Quarters 1, 2, 3 and 4) 2-3C Gaseous Effluents - Ground Level 57 Releases Site (Quarters 1, 2, 3 and 4) 2-4A Air Doses Due to Noble Gases in Gaseous 59 Releases - Unit 1 (Quarters 1, 2, 3 and 4) vi

TABLE LIST OF TABLES PAGE 2-4B Air Doses Due to Noble Gases in Gaseous 60 Releases- Unit 2 (Quarters 1, 2, 3 and 4) 2-5A Doses to a Member of the Public Due to 61 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-5B Doses to a Member of the Public Due to 62 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-6 Minimum Detectable Concentration - 63 Gaseous Sample Analyses 2-7A Gaseous Effluents - Batch Release 64 Summary Unit 1 2-7B Gaseous Effluents - Batch Release 65 Summary Unit 2 2-8A Gaseous Effluents - Abnormal Release 66 Summary Unit 1 2-8B Gaseous Effluents - Abnormal Release 67 Summary Unit 2 2-8C Gaseous Effluents - Abnormal Release 68 Summary Site 3-1 Solid Waste and Irradiated Fuel Shipments 71 4-1 Doses to a Member of the Public Due to 75 Activities Inside The Site Boundary vii

1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration Limits 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 1E-04 microcuries/ml total activity.

1.1.2 Dose Limits The dose or dose commitment, to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, shall be limited:

a. During any calendar quarter, to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year, to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

1.2 Effluent Concentration Limit ECL values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55, are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2.

A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2.

For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 uCi/ml total activity.

For gross alpha in liquid radwaste, the ECL is 2E-09 uCi/ml.

Furthermore, for all the above radionuclides, or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.

The method utilizing the ECL fraction to determine liquid radwaste release rates and effluent radiation monitor set points is described in Subsection 1.3 of this report.

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The method utilizing the ECL fraction to determine the dose released from groundwater outfalls is described in Subsection 1.4 of this report.

1.3 Measurements and Approximations of Total Radioactivity for Liquid Radwaste Prior to the release of any tank containing liquid radwaste, following the required recirculations, samples are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3.

A sample from each tank planned for release is analyzed for principal gamma emitters, I-131, and dissolved and entrained noble gases, by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks released.

Liquid radwaste sample analyses are performed as described in Section 1.3.1.

1.3.1 Total Radioactivity Determination for Liquid Radwaste MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.

2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gas with computerized data reduction.

3. Tritium Monthly Distillation and liquid Composite scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting 2

Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 keV or lower. The detectors are shielded by four inches of lead. A liquid radwaste sample is typically counted for 2000 seconds and a peak search of the resulting gamma ray spectrum is performed. Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present. Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.

The radionuclide concentrations determined by gamma spectroscopic analysis of samples taken from tanks planned for release, in addition to the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55, are used along with the corresponding ECL values to determine the ECL fraction for these tanks. This ECL fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded.

A monitor reading in excess of the calculated setpoint will result in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.

Radionuclide concentrations, safety factors, dilution stream flow rate, and the liquid effluent radiation monitor calibration factor, are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate warnings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Foreman on duty. The pertinent information is transferred manually from the prerelease printout to a one-page release permit, which is forwarded to Radwaste Operations. When the release is completed, the release permit is returned from Radwaste Operations to Chemistry with the actual release data provided. These data are input into the computer and a post-release printout is generated. The post release printout contains the actual release rates, the actual release concentrations and quantities, the actual dilution flow, and the calculated doses to a Member of the Public.

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1.4 Measurements and Approximations of Total Radioactivity for Groundwater Outfalls - Y22N003A/12B and Y22N008A Samples are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3. Weekly, monthly and quarterly composites are prepared for analysis by extracting aliquots from each outfalls automatic sampler, which collects a composite sample over a seven-day period. Sample analyses are performed as described in Section 1.4.1.

1.4.1 Total Radioactivity Determination for Groundwater Outfalls MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Weekly Composite Gamma Spectroscopy with computerized data reduction.

2. Tritium Weekly Composite Distillation and liquid scintillation counting

3. Gross Beta

Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

4. Sr-89 & Sr-90 ** Quarterly Chemical separation Composite and gas flow (as required) proportional or scintillation counting

Gross Beta analysis is used for sample screening.

- If the Gross Beta analysis yields a detectable value above background, a Sr-89/90 analysis will be performed.

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Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 keV or lower. The detectors are shielded by four inches of lead. A weekly composite sample is typically counted to Environmental MDCs and a peak search of the resulting gamma ray spectrum is performed.

Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

Tritium, Gross Beta, Sr-89 and Sr-90 are, in some cases, analyzed offsite.

The radionuclide concentrations determined by gamma spectroscopic analysis of the weekly composite sample, in addition to the most current sample analysis results available for tritium, gross beta, Sr-89 and Sr-90, are used along with the corresponding ECL values to determine the ECL fraction for these composite samples. This ECL fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate projected dose released.

Radionuclide concentrations, safety factors and dilution stream flow rate are entered into the computer and a pre-release printout is generated for each release period. When the release period is complete, the release permit is updated with the actual release data collected during the release period. These data are input into the computer and a post-release printout is generated. The post release printout contains the actual release rates, the actual release concentrations and quantities, the actual dilution flow, and the calculated doses to a Member of the Public. Cumulative dose results are tabulated along with the percent of the ODCM limit for each release period, for the current quarter and year.

1.5 Total Error Estimation The maximum error associated with volume and flow measurements, based upon plant calibration practice, is estimated to be + or - 10%. The average error associated with counting is estimated to be less than + or - 15%. Therefore, the total error estimation is + or - 18%.

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1.6 Liquid Effluent Release Data Regulatory Guide 1.21, Tables 2A and 2B are found in this report as Table 1-1A, for Unit 1, Table 1-1B, for Unit 2 and Table 1-1C, for the site; and Table 1-2A, for Unit 1, 1-2B, for Unit 2, and Table 1-2C, for the site. Typical liquid minimum detectable concentrations (MDCs) used for analyses are found in Table 1-4.

The evaluation for the release of radioactive RHR Service Water for 2019 can be found in Appendix A of this report.

The values for the four categories of Tables 1-1A, and 1-1B, and 1-1C, are calculated and the Tables completed as follows:

1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective quarter.

2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period.

3. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy using a one liter sample from each liquid radwaste batch. The measured concentrations are used to calculate the total release and the average diluted concentration during the period. Radioisotopes of iodine in any form are also determined during the isotopic analysis for each batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not provide additional information.

4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity.

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1.7 Radiological Impact Due to Liquid Releases Doses to a Member of the Public due to radioactivity in liquid effluents were calculated in accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-3A for Unit 1, and 1-3B for Unit 2, for all four quarters.

1.8 Liquid Effluents - Batch Releases Batch Release information for Units 1 and 2 is summarized in the following tables:

Unit 1 Liquid Batch Releases: Table 1-5A Unit 2 Liquid Batch Releases: Table 1-5B 1.9 Liquid Effluents - Continuous Releases Continuous Release information is summarized in the following tables:

Unit 1 Liquid Continuous Releases: Table 1-2A Unit 2 Liquid Continuous Releases: Table 1-2B Hatch Site Conitinuous Releases: Table 1-2C 1.10 Liquid Effluents - Abnormal Releases There were no abnormal liquid releases for this reporting period.

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Table 1-1A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 8.41E-05 5.38E-04 2.55E-04 9.25E-04

2. Average diluted concentration during period uCi/mL 2.43E-10 1.19E-09 2.79E-10 1.00E-09

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 7.00E+00 1.23E+01 1.62E+01 2.33E+01

2. Average diluted Concentration during period uCi/mL 2.02E-05 2.73E-05 1.77E-05 2.52E-05

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 1.82E-05 3.16E-05 1.07E-05 3.48E-05

2. Average diluted Concentration during period uCi/mL 5.26E-11 7.00E-11 1.17E-11 3.76E-11

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 1.55E+06 2.07E+06 3.39E+06 4.30E+06 F. Volume of Dilution Water Used Liters 3.46E+08 4.51E+08 9.13E+08 9.25E+08

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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Table 1-1B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 3.65E-04 2.43E-04 3.13E-04 6.91E-04

2. Average diluted concentration during period uCi/mL 7.36E-11 4.19E-11 4.86E-11 1.48E-10

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 2.66E+00 8.23E+00 1.23E+01 6.66E+00

2. Average diluted Concentration during period uCi/mL 5.37E-07 1.42E-06 1.91E-06 1.42E-06

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 1.84E-05 3.30E-05 5.05E-05 6.58E-05

2. Average diluted Concentration during period uCi/mL 3.71E-12 5.69E-12 7.85E-12 1.41E-11

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 5.38E+06 4.74E+06 5.86E+06 5.93E+06 F. Volume of Dilution Water Used Liters 4.95E+09 5.80E+09 6.43E+09 4.68E+09

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

9

Table 1-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 4.49E-04 7.81E-04 5.68E-04 1.62E-03

2. Average diluted concentration during period uCi/mL 8.47E-11 1.25E-10 7.73E-11 2.88E-10

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 9.66E+00 2.05E+01 2.85E+01 3.00E+01

2. Average diluted Concentration during period uCi/mL 1.82E-06 3.28E-06 3.87E-06 5.35E-06

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 3.66E-05 6.46E-05 6.12E-05 1.01E-04

2. Average diluted Concentration during period uCi/mL 6.91E-12 1.03E-11 8.34E-12 1.80E-11

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 6.93E+06 6.81E+06 9.25E+06 1.02E+07 F. Volume of Dilution Water Used Liters 5.30E+09 6.25E+09 7.35E+09 5.60E+09

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

10

Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 11

Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Cs-137 Curies 8.65E-06 2.04E-05 1.93E-05 1.19E-04 Cr-51 Curies 0.00E+00 1.93E-05 3.89E-06 0.00E+00 Sb-124 Curies 0.00E+00 3.85E-05 0.00E+00 4.31E-07 Zn-69M Curies 0.00E+00 4.27E-06 8.09E-07 5.08E-07 Co-58 Curies 3.77E-06 2.52E-05 7.47E-06 1.96E-05 Co-60 Curies 3.32E-05 1.58E-04 1.26E-04 2.33E-04 Zn-65 Curies 4.69E-06 4.86E-05 2.34E-05 1.63E-04 Mn-54 Curies 1.29E-05 6.26E-05 5.28E-05 5.09E-05 Ag-110M Curies 3.08E-06 2.12E-05 7.03E-07 9.31E-06 Sr-90 Curies 1.37E-05 0.00E+00 0.00E+00 0.00E+00 As-76 Curies 0.00E+00 1.37E-05 1.58E-06 1.30E-05 Fe-55 Curies 0.00E+00 0.00E+00 0.00E+00 1.90E-04 Na-24 Curies 4.14E-06 3.58E-05 1.91E-05 1.27E-04 Sr-89 Curies 0.00E+00 8.95E-05 0.00E+00 0.00E+00 Sr-92 Curies 0.00E+00 9.03E-07 0.00E+00 0.00E+00 Total For Period Curies 8.41E-05 5.38E-04 2.55E-04 9.25E-04 Tritium H-3 Curies 7.00E+00 1.23E+01 1.62E+01 2.33E+01 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 12

Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Xe-135 Curies 1.71E-05 2.99E-05 8.97E-06 2.25E-05 Xe-131M Curies 0.00E+00 0.00E+00 0.00E+00 9.95E-06 Xe-133 Curies 1.17E-06 1.68E-06 1.75E-06 2.36E-06 Total For Period Curies 1.82E-05 3.16E-05 1.07E-05 3.48E-05 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 13

Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies 0.00E+00 4.06E-05 1.37E-04 0.00E+00 Total For Period Curies 0.00E+00 4.06E-05 1.37E-04 0.00E+00 Tritium H-3 Curies 6.98E-03 6.40E-03 9.81E-03 1.57E-02 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 14

Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Cs-137 Curies 4.82E-06 1.21E-06 3.87E-06 6.88E-06 Co-58 Curies 3.75E-05 8.52E-06 4.58E-06 4.12E-05 Sb-124 Curies 2.12E-05 0.00E+00 3.11E-07 0.00E+00 La-140 Curies 0.00E+00 0.00E+00 1.43E-05 7.98E-06 Sr-89 Curies 0.00E+00 0.00E+00 0.00E+00 3.17E-05 Co-60 Curies 1.64E-04 1.23E-04 9.85E-05 3.18E-04 Zn-69M Curies 0.00E+00 0.00E+00 0.00E+00 3.37E-07 Sr-92 Curies 0.00E+00 2.75E-06 0.00E+00 6.24E-06 Nb-97 Curies 0.00E+00 2.69E-06 0.00E+00 0.00E+00 Sr-90 Curies 1.07E-05 0.00E+00 0.00E+00 0.00E+00 Cr-51 Curies 7.71E-06 3.79E-06 0.00E+00 2.24E-05 Mn-54 Curies 6.45E-05 2.91E-05 1.55E-05 1.01E-04 Zn-65 Curies 2.38E-05 7.40E-07 9.24E-06 7.04E-05 Na-24 Curies 0.00E+00 1.40E-05 3.80E-06 0.00E+00 Ag-110M Curies 3.05E-05 1.71E-05 2.52E-05 8.56E-05 Total For Period Curies 3.65E-04 2.03E-04 1.75E-04 6.91E-04 Tritium H-3 Curies 2.65E+00 8.22E+00 1.23E+01 6.65E+00 Dissolved And Entrained Gases Xe-135 Curies 9.75E-07 1.87E-05 3.08E-05 3.43E-05 Xe-133 Curies 1.74E-05 1.43E-05 1.97E-05 3.16E-05 Total For Period Curies 1.84E-05 3.30E-05 5.05E-05 6.58E-05 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 15

Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 16

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies 0.00E+00 4.06E-05 1.37E-04 0.00E+00 Total For Period Curies 0.00E+00 4.06E-05 1.37E-04 0.00E+00 Tritium H-3 Curies 6.98E-03 6.40E-03 9.81E-03 1.57E-02 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 17

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Na-24 Curies 4.14E-06 4.99E-05 2.29E-05 1.27E-04 Co-58 Curies 4.12E-05 3.37E-05 1.21E-05 6.09E-05 Nb-97 Curies 0.00E+00 2.69E-06 0.00E+00 0.00E+00 Cs-137 Curies 1.35E-05 2.16E-05 2.31E-05 1.26E-04 Zn-69M Curies 0.00E+00 4.27E-06 8.09E-07 8.44E-07 Sr-89 Curies 0.00E+00 8.95E-05 0.00E+00 3.17E-05 Sr-92 Curies 0.00E+00 3.65E-06 0.00E+00 6.24E-06 La-140 Curies 0.00E+00 0.00E+00 1.43E-05 7.98E-06 As-76 Curies 0.00E+00 1.37E-05 1.58E-06 1.30E-05 Co-60 Curies 1.97E-04 2.80E-04 2.25E-04 5.51E-04 Sb-124 Curies 2.12E-05 3.85E-05 3.11E-07 4.31E-07 Cr-51 Curies 7.71E-06 2.31E-05 3.89E-06 2.24E-05 Ag-110M Curies 3.35E-05 3.83E-05 2.59E-05 9.49E-05 Fe-55 Curies 0.00E+00 0.00E+00 0.00E+00 1.90E-04 Zn-65 Curies 2.85E-05 4.93E-05 3.27E-05 2.33E-04 Mn-54 Curies 7.74E-05 9.17E-05 6.83E-05 1.52E-04 Sr-90 Curies 2.44E-05 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 4.49E-04 7.40E-04 4.30E-04 1.62E-03 Tritium H-3 Curies 9.65E+00 2.05E+01 2.84E+01 2.99E+01 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 18

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Xe-133 Curies 1.86E-05 1.60E-05 2.15E-05 3.39E-05 Xe-131M Curies 0.00E+00 0.00E+00 0.00E+00 9.95E-06 Xe-135 Curies 1.80E-05 4.86E-05 3.98E-05 5.67E-05 Total For Period Curies 3.66E-05 6.46E-05 6.12E-05 1.01E-04 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. 19

Table 1-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Total Body 1.50E+00 mRem 8.08E-05 5.39E-03 1.53E-04 1.02E-02 1.52E-04 1.01E-02 5.99E-04 4.00E-02 Lung 5.00E+00 mRem 4.98E-05 9.96E-04 8.93E-05 1.79E-03 1.01E-04 2.02E-03 2.40E-04 4.79E-03 Bone 5.00E+00 mRem 5.68E-05 1.14E-03 7.53E-05 1.51E-03 5.75E-05 1.15E-03 4.49E-04 8.97E-03 Kidney 5.00E+00 mRem 6.00E-05 1.20E-03 1.20E-04 2.39E-03 1.23E-04 2.46E-03 4.12E-04 8.23E-03 Thyroid 5.00E+00 mRem 4.53E-05 9.06E-04 7.95E-05 1.59E-03 9.26E-05 1.85E-03 1.73E-04 3.46E-03 Liver 5.00E+00 mRem 8.80E-05 1.76E-03 1.87E-04 3.74E-03 1.79E-04 3.58E-03 8.27E-04 1.65E-02 GI-Lli 5.00E+00 mRem 7.06E-05 1.41E-03 2.04E-04 4.08E-03 1.58E-04 3.17E-03 3.68E-04 7.36E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Bone 1.00E+01 mRem 6.38E-04 6.38E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Liver 1.00E+01 mRem 1.28E-03 1.28E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Thyroid 1.00E+01 mRem 3.91E-04 3.91E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Kidney 1.00E+01 mRem 7.14E-04 7.14E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Lung 1.00E+01 mRem 4.80E-04 4.80E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose GI-Lli 1.00E+01 mRem 8.01E-04 8.01E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Total Body 3.00E+00 mRem 9.85E-04 3.28E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Tot Body Liq Dose 20

Table 1-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Total Body 1.50E+00 mRem 6.59E-05 4.39E-03 7.93E-05 5.29E-03 1.21E-04 8.07E-03 1.22E-04 8.12E-03 Thyroid 5.00E+00 mRem 2.57E-05 5.13E-04 6.58E-05 1.32E-03 9.83E-05 1.97E-03 5.68E-05 1.14E-03 Bone 5.00E+00 mRem 4.79E-05 9.57E-04 5.19E-06 1.04E-04 1.72E-05 3.43E-04 4.20E-05 8.40E-04 GI-Lli 5.00E+00 mRem 1.97E-04 3.95E-03 1.74E-04 3.49E-03 1.97E-04 3.93E-03 4.41E-04 8.81E-03 Lung 5.00E+00 mRem 2.86E-05 5.72E-04 6.66E-05 1.33E-03 1.01E-04 2.02E-03 6.13E-05 1.23E-03 Kidney 5.00E+00 mRem 4.15E-05 8.30E-04 6.88E-05 1.38E-03 1.08E-04 2.17E-03 9.18E-05 1.84E-03 Liver 5.00E+00 mRem 6.88E-05 1.38E-03 7.79E-05 1.56E-03 1.27E-04 2.54E-03 1.41E-04 2.83E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Bone 1.00E+01 mRem 1.12E-04 1.12E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Liver 1.00E+01 mRem 4.15E-04 4.15E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Thyroid 1.00E+01 mRem 2.47E-04 2.47E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Kidney 1.00E+01 mRem 3.10E-04 3.10E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Lung 1.00E+01 mRem 2.57E-04 2.57E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose GI-Lli 1.00E+01 mRem 1.01E-03 1.01E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Total Body 3.00E+00 mRem 3.88E-04 1.29E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Tot Body Liq Dose 21

Table 1-4 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES STARTING: 1-Jan-2019 ENDING: 31-Dec-2019 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 1.97E-08 uCi/ml Fe-59 3.94E-08 uCi/ml Co-58 1.59E-08 uCi/ml Co-60 1.72E-08 uCi/ml Zn-65 2.92E-08 uCi/ml Mo-99 1.20E-07 uCi/ml Cs-134 1.75E-08 uCi/ml Cs-137 1.62E-08 uCi/ml Ce-141 1.92E-08 uCi/ml Ce-144 8.83E-08 uCi/ml I-131 1.43E-08 uCi/ml Xe-135 1.03E-08 uCi/ml Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml Sr-90 8.50E-09 uCi/ml H-3 6.00E-07 uCi/ml 22

Table 1-5A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 46 61 98 120 Totals 325

2. Total time period for Batch releases ( Minutes ) 5.87E+03 7.50E+03 1.37E+04 1.78E+04 4.48E+04

3. Maximum time period for a batch release ( Minutes ) 1.65E+02 1.59E+02 1.75E+02 1.76E+02 1.76E+02

4. Average time period for a batch release ( Minutes ) 1.28E+02 1.23E+02 1.40E+02 1.48E+02 1.38E+02

5. Minimum time period for a batch release ( Minutes ) 8.10E+01 9.10E+01 9.10E+01 8.00E+01 8.00E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 24.82E+03 9.13E+03 2.74E+03 6.60E+03 10.82E+03

Data obtained from United States Geological Survey (USGS) website 23

Table 1-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 39 49 74 63 Totals 225

2. Total time period for Batch releases ( Minutes ) 4.36E+03 5.61E+03 8.98E+03 7.02E+03 2.60E+04

3. Maximum time period for a batch release ( Minutes ) 1.56E+02 1.29E+02 2.36E+02 1.45E+02 2.36E+02

4. Average time period for a batch release ( Minutes ) 1.12E+02 1.15E+02 1.21E+02 1.11E+02 1.15E+02

5. Minimum time period for a batch release ( Minutes ) 7.70E+01 6.00E+00 1.03E+02 2.60E+01 6.00E+00

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 24.82E+03 9.13E+03 2.74E+03 6.60E+03 10.82E+03

Data obtained from United States Geological Survey (USGS) website 24

Table 1-6A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 25

Table 1-6B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 26

Table 1-6C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 27

2.0 Gaseous Effluents 2.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2.

2.1.1 Dose Rate Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,

b. For Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

2.1.2 Air Doses Due To Noble Gases in Gaseous Effluents The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.3 Doses To A Member of the Public The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following.

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ.

b. During any calendar year: Less than or equal to 15 mrems to any organ.

28

2.2 Measurements and Approximations of Total Radioactivity Waste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit 1 reactor building vent; Unit 2 reactor building vent, and the recombiner building vent. Each of these four paths is continuously monitored for gaseous radioactivity.

2.2.1 Sample Collection and Analysis Each of the four gaseous effluent paths is equipped with an integrating-type sample collection device for collecting particulates and iodines. Unless required more frequently under certain circumstances, samples are collected as follows:

1. Noble gas samples are collected by grab sampling monthly.

2. Tritium samples are collected by grab sampling monthly.

3. Radioiodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period.

4. Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period.

5. The 7-day particulate filters above are analyzed for gross alpha activity.

6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the samples are analyzed for Sr-89 and Sr-90.

Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, the dose rates associated with gaseous releases, and the cumulative doses for the current quarter and year. This task is normally performed with computer assistance.

The noble gas grab sample analysis results are used along with maximum expected release flow rates from each of the four vents to calculate monitor setpoints for the gaseous effluent monitors serving the four release points.

Calculation of monitor setpoints is described in the ODCM. Typically achieved minimum detectable concentrations for gaseous effluents sample and analyses are reported in Table 2-6.

For each release period, released radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated along with the percent of the ODCM limit for each release, for the current quarter and year.

29

2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:

2.2.2.1 Fission and Activation Gases The released radioactivity is determined using sample analyses results collected as described above and the average release flow rates over the period represented by the collected sample.

Dose rates due to noble gases, radioiodines, tritium, and particulates are calculated (with computer assistance). The calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodine, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year. Cumulative air doses are compared to the dose limits specified in ODCM 3.1.3. The current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.

2.2.2.2 Radioiodine, Tritium and Particulate Releases Released quantities of radioiodines are determined using the weekly samples and release flow rates for the four release points. Radioiodine concentrations are determined by gamma spectroscopy.

Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the four release points. Gamma spectroscopy is used to quantify concentrations of principal gamma emitters.

After each quarter, the particulate filters from each vent are combined, fused, and a strontium separation is performed. Since sample flows and vent flows are almost constant over each quarterly period the filters from each vent can be dissolved together. Decay corrections are performed back to the middle of the quarterly collection period. If Sr-89 or Sr-90 is not detected, MDC's are calculated.

Strontium concentrations are input into the composite file of the computer and used for release dose rate and dose calculations for a Member of the Public.

30

Tritium samples are obtained monthly from each vent by passing the sample stream through a cold trap. The grams of water vapor/cubic foot is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory and the results are furnished in uCi/ml of water. The tritium concentration in water is converted to the tritium concentration in air and this value is input into the composite file of the computer and used in release, dose rate, and individual dose calculations.

Dose rates due to radioiodine, tritium and particulates are calculated for a hypothetical child exposed to the inhalation pathway at the location in the unrestricted area where the potential dose rate is expected to be the highest.

Dose rates are calculated, for each release point for each release period, and the dose rates from each release point are compared to the dose rate limits as described in ODCM 3.1.2 Doses due to radioiodine, tritium and particulates are calculated for the controlling receptor, which is described in the ODCM. Doses to a Member of the Public are calculated for each release period, and cumulative totals are kept for each unit, for the current calendar quarter and year. Cumulative doses are compared to the dose limits specified in ODCM 3.1.4. The current percent of ODCM limits are shown on the printout for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters, for each week for gross alpha activity in a proportional counter. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. The summed activity is then divided by the total monthly volume to determine the concentration. This concentration is input into the composite file of the computer and used for release calculations.

2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total process of sampling and measurement. Due to the difficulty with assigning error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective is to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

Estimated errors are associated with counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non steady release rates, chemical yield factors and sample losses for such items as charcoal cartridges.

31

Fission and activation total release was calculated from sample analysis results and release point flow rates.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Non-steady release rates 20%

TOTAL ERROR 65%

I-131 releases were calculated from each weekly sample.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 64%

Particulates with half lives greater than 8 days releases were calculated from sample analysis results and release point flow rates.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

Total tritium releases were calculated from sample analysis results and release point flow rates.

Water vapor in sample stream determination 20%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 50%

TOTAL ERROR 56%

32

Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found in this report as Tables 2-1A, 2-1B, 2-1C, 2-2A, ,2-2B, 2-2C, 2-3A, 2-3B, 2-3C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all quarters.

To complete table 2-1A, 2-1B, and 2-1C, total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each category for each quarter. However, the percent of the ODCM limits are not applicable because we have no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases, and due to radioiodine, tritium, and particulates were calculated as part of the pre-release and post-release permits on individual permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Table 2-1A, 2-1B, and 2-1C, as curies released in each quarter.

Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A and 2-4B, along with percent of ODCM limits.

Limits for cumulative doses to a Member of the Public due to radioiodine, tritium and particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member of the Public doses are presented in Table 2-5A, and 2-5B, along with percent of ODCM limits.

33

2.4 Radiological Impact Due to Gaseous Releases Dose rates due to noble gas release were calculated for the site in accordance with ODCM 3.1.2. Dose rates due to radioiodine, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.1.2.

These dose rates were calculated as part of the pre-release and post release on individual release permits. No limits were exceeded for this reporting period.

Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.1.3. These results are presented in Tables 2-4A and 2-4B.

Cumulative doses to a Member of the Public due to radioiodine, tritium and particulates in gaseous releases were calculated for each unit in accordance with ODCM 3.1.4. These results are presented in Tables 2-5A and 2-5B.

Dose rates and doses were calculated using the methodology presented in the ODCM.

2.5 Gaseous Effluents - Batch Releases There are no gaseous batch releases from Plant Hatch.

2.6 Gaseous Effluents - Abnormal Releases There were no unplanned or uncontrolled gaseous releases during this reporting period.

34

Table 2-1A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.93E-01 6.82E-01 4.25E-01 5.10E-01

2. Average Release rate for period uCi/sec 2.45E-02 8.64E-02 5.39E-02 6.47E-02

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 2.94E-05 7.03E-06 9.46E-06 5.70E-06

2. Average Release rate for period uCi/sec 3.73E-06 8.92E-07 1.20E-06 7.23E-07

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 2.24E-06 2.93E-06 1.79E-06 2.66E-06

2. Average Release rate for period uCi/sec 2.84E-07 3.72E-07 2.27E-07 3.379E-07

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 5.88E+00 6.58E+00 5.18E+00 6.52E+00

2. Average Release rate for period uCi/sec 7.46E-01 8.35E-01 6.57E-01 8.27E-01

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 3.01E-07 7.27E-08 5.41E-08 8.37E-07

2. Average Release rate for period uCi/sec 3.82E-08 9.22E-09 6.86E-09 1.06E-07

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

35

Table 2-1B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.93E-01 6.82E-01 3.22E-01 5.10E-01

2. Average Release rate for period uCi/sec 2.45E-02 8.64E-02 4.08E-02 6.47E-02

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 1.82E-05 8.82E-06 5.70E-06 1.80E-05

2. Average Release rate for period uCi/sec 2.31E-06 1.12E-06 7.23E-07 2.29E-06

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 2.62E-06 3.09E-06 2.26E-06 3.74E-06

2. Average Release rate for period uCi/sec 3.32E-07 3.92E-07 2.87E-07 4.745E-07

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 4.51E+00 6.31E+00 7.55E+00 9.57E+00

2. Average Release rate for period uCi/sec 5.72E-01 8.00E-01 9.58E-01 1.21E+00

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 2.70E-07 7.85E-08 1.38E-07 2.45E-07

2. Average Release rate for period uCi/sec 3.42E-08 9.95E-09 1.75E-08 3.11E-08

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

36

Table 2-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 3.86E-01 1.36E+00 7.47E-01 1.02E+00

2. Average Release rate for period uCi/sec 4.90E-02 1.73E-01 9.47E-02 1.29E-01

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 4.76E-05 1.59E-05 1.52E-05 2.37E-05

2. Average Release rate for period uCi/sec 6.03E-06 2.01E-06 1.92E-06 3.01E-06

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 4.86E-06 6.03E-06 4.24E-06 6.41E-06

2. Average Release rate for period uCi/sec 6.16E-07 7.64E-07 5.38E-07 8.124E-07

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 1.04E+01 1.29E+01 1.42E+01 1.61E+01

2. Average Release rate for period uCi/sec 1.32E+00 1.64E+00 1.80E+00 2.04E+00

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 5.71E-07 1.51E-07 2.19E-07 1.08E-06

2. Average Release rate for period uCi/sec 7.24E-08 1.92E-08 2.78E-08 1.37E-07

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

37

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.93E-01 6.82E-01 3.76E-01 4.89E-01 Kr-85M Curies 0.00E+00 0.00E+00 4.87E-02 2.13E-02 Total For Period Curies 1.93E-01 6.82E-01 4.25E-01 5.10E-01 Iodines I-131 Curies 5.36E-06 2.14E-06 5.04E-06 1.64E-06 I-133 Curies 2.40E-05 4.89E-06 4.43E-06 4.06E-06 Total For Period Curies 2.94E-05 7.03E-06 9.46E-06 5.70E-06 Particulates Mn-54 Curies 0.00E+00 3.63E-08 0.00E+00 0.00E+00 Co-58 Curies 0.00E+00 1.88E-08 0.00E+00 0.00E+00 Co-60 Curies 1.41E-07 2.64E-07 6.44E-08 2.13E-07 Zn-65 Curies 1.36E-07 3.43E-08 0.00E+00 0.00E+00 Sr-89 Curies 1.26E-06 1.27E-06 1.35E-06 1.55E-06 Sr-90 Curies 1.42E-08 3.16E-09 0.00E+00 9.79E-09 Cs-137 Curies 0.00E+00 0.00E+00 0.00E+00 2.37E-08 Ba-140 Curies 0.00E+00 1.04E-07 0.00E+00 0.00E+00 Total For Period Curies 1.55E-06 1.73E-06 1.42E-06 1.79E-06 Tritium H-3 Curies 1.09E-01 2.46E-01 2.49E-01 6.45E-01 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 38

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha G-Alpha Curies 2.77E-08 9.11E-09 1.69E-08 3.31E-08 Total For Period Curies 2.77E-08 9.11E-09 1.69E-08 3.31E-08 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 39

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 40

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 41

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 42

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.93E-01 6.82E-01 2.98E-01 4.89E-01 Kr-85M Curies 0.00E+00 0.00E+00 2.34E-02 2.13E-02 Total For Period Curies 1.93E-01 6.82E-01 3.22E-01 5.10E-01 Iodines I-131 Curies 1.17E-06 3.48E-06 1.44E-06 1.64E-06 I-133 Curies 3.96E-06 5.34E-06 3.79E-06 4.06E-06 Total For Period Curies 5.13E-06 8.82E-06 5.23E-06 5.70E-06 Particulates Mn-54 Curies 0.00E+00 9.75E-08 0.00E+00 0.00E+00 Co-58 Curies 0.00E+00 7.51E-08 0.00E+00 0.00E+00 Co-60 Curies 0.00E+00 5.15E-07 6.44E-08 2.13E-07 Zn-65 Curies 0.00E+00 1.02E-07 0.00E+00 0.00E+00 Sr-89 Curies 3.36E-07 1.40E-06 1.14E-06 1.55E-06 Sr-90 Curies 3.77E-09 3.48E-09 0.00E+00 9.79E-09 Cs-137 Curies 0.00E+00 0.00E+00 0.00E+00 2.37E-08 Ba-140 Curies 0.00E+00 1.04E-07 0.00E+00 0.00E+00 Total For Period Curies 3.39E-07 2.30E-06 1.20E-06 1.79E-06 Tritium H-3 Curies 4.85E-02 2.66E-01 2.06E-01 6.45E-01 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 43

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha G-Alpha Curies 7.28E-09 1.03E-08 1.29E-08 3.31E-08 Total For Period Curies 7.28E-09 1.03E-08 1.29E-08 3.31E-08 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 44

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 45

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 46

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 47

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 3.86E-01 1.36E+00 6.75E-01 9.78E-01 Kr-85M Curies 0.00E+00 0.00E+00 7.21E-02 4.25E-02 Total For Period Curies 3.86E-01 1.36E+00 7.47E-01 1.02E+00 Iodines I-131 Curies 6.53E-06 5.63E-06 6.47E-06 3.29E-06 I-133 Curies 2.80E-05 1.02E-05 8.22E-06 8.12E-06 Total For Period Curies 3.45E-05 1.59E-05 1.47E-05 1.14E-05 Particulates Mn-54 Curies 0.00E+00 1.34E-07 0.00E+00 0.00E+00 Co-58 Curies 0.00E+00 9.39E-08 0.00E+00 0.00E+00 Co-60 Curies 1.41E-07 7.79E-07 1.29E-07 4.26E-07 Zn-65 Curies 1.36E-07 1.36E-07 0.00E+00 0.00E+00 Sr-89 Curies 1.60E-06 2.67E-06 2.49E-06 3.09E-06 Sr-90 Curies 1.79E-08 6.64E-09 0.00E+00 1.96E-08 Cs-137 Curies 0.00E+00 0.00E+00 0.00E+00 4.74E-08 Ba-140 Curies 0.00E+00 2.09E-07 0.00E+00 0.00E+00 Total For Period Curies 1.89E-06 4.02E-06 2.62E-06 3.59E-06 Tritium H-3 Curies 1.58E-01 5.13E-01 4.54E-01 1.29E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 48

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha G-Alpha Curies 3.49E-08 1.94E-08 2.98E-08 6.61E-08 Total For Period Curies 3.49E-08 1.94E-08 2.98E-08 6.61E-08 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 49

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Elevated Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 50

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 51

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 52

Table 2-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Mn-54 Curies 0.00E+00 3.67E-07 0.00E+00 0.00E+00 Co-60 Curies 0.00E+00 7.10E-07 0.00E+00 0.00E+00 Sr-89 Curies 6.87E-07 0.00E+00 3.69E-07 8.71E-07 Sr-90 Curies 0.00E+00 1.28E-07 0.00E+00 0.00E+00 Total For Period Curies 6.87E-07 1.20E-06 3.69E-07 8.71E-07 Tritium H-3 Curies 5.77E+00 6.34E+00 4.93E+00 5.87E+00 Gross Alpha G-Alpha Curies 2.74E-07 6.35E-08 3.72E-08 8.04E-07 Total For Period Curies 2.74E-07 6.35E-08 3.72E-08 8.04E-07 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 53

Table 2-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 54

Table 2-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines I-131 Curies 4.57E-06 0.00E+00 4.73E-07 1.43E-06 I-133 Curies 8.50E-06 0.00E+00 0.00E+00 1.09E-05 Total For Period Curies 1.31E-05 0.00E+00 4.73E-07 1.23E-05 Particulates Sr-89 Curies 2.28E-06 6.43E-07 1.06E-06 1.95E-06 Sr-90 Curies 0.00E+00 1.55E-07 0.00E+00 0.00E+00 Total For Period Curies 2.28E-06 7.98E-07 1.06E-06 1.95E-06 Tritium H-3 Curies 4.46E+00 6.04E+00 7.35E+00 8.92E+00 Gross Alpha G-Alpha Curies 2.62E-07 6.81E-08 1.25E-07 2.12E-07 Total For Period Curies 2.62E-07 6.81E-08 1.25E-07 2.12E-07 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 55

Table 2-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 56

Table 2-3C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines I-131 Curies 4.57E-06 0.00E+00 4.73E-07 1.43E-06 I-133 Curies 8.50E-06 0.00E+00 0.00E+00 1.09E-05 Total For Period Curies 1.31E-05 0.00E+00 4.73E-07 1.23E-05 Particulates Mn-54 Curies 0.00E+00 3.67E-07 0.00E+00 0.00E+00 Co-60 Curies 0.00E+00 7.10E-07 0.00E+00 0.00E+00 Sr-89 Curies 2.96E-06 6.43E-07 1.62E-06 2.82E-06 Sr-90 Curies 0.00E+00 2.83E-07 0.00E+00 0.00E+00 Total For Period Curies 2.96E-06 2.00E-06 1.62E-06 2.82E-06 Tritium H-3 Curies 1.02E+01 1.24E+01 1.38E+01 1.48E+01 Gross Alpha G-Alpha Curies 5.36E-07 1.32E-07 1.90E-07 1.02E-06 Total For Period Curies 5.36E-07 1.32E-07 1.90E-07 1.02E-06 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 57

Table 2-3C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations. 58

Table 2-4A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Gamma Air 5.00E+00 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gamma Air 5.00E+00 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta Air 1.00E+01 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta Air 1.00E+01 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date % ODCM Receptor Limit Gamma Air 1.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U1 Ann Cum Gamma Airdose Gamma Air 1.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U2 Ann Cum Gamma Airdose Beta Air 2.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U1 Ann Cum Beta Airdose Beta Air 2.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U2 Ann Cum Beta Airdose 59

Table 2-4B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Gamma Air 5.00E+00 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gamma Air 5.00E+00 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta Air 1.00E+01 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta Air 1.00E+01 mRad 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date % ODCM Receptor Limit Gamma Air 1.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U1 Ann Cum Gamma Airdose Gamma Air 1.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U2 Ann Cum Gamma Airdose Beta Air 2.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U1 Ann Cum Beta Airdose Beta Air 2.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUNDARY / Child U2 Ann Cum Beta Airdose 60

Table 2-5A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Bone 7.50E+00 mRem 9.89E-06 1.32E-04 5.26E-05 7.01E-04 6.01E-06 8.01E-05 1.20E-05 1.60E-04 Liver 7.50E+00 mRem 2.99E-03 3.98E-02 3.29E-03 4.39E-02 2.56E-03 3.41E-02 3.05E-03 4.06E-02 Total Body 7.50E+00 mRem 2.99E-03 3.99E-02 3.30E-03 4.40E-02 2.56E-03 3.41E-02 3.05E-03 4.07E-02 Thyroid 7.50E+00 mRem 3.00E-03 4.00E-02 3.29E-03 4.39E-02 2.57E-03 3.42E-02 3.05E-03 4.07E-02 Kidney 7.50E+00 mRem 2.99E-03 3.98E-02 3.29E-03 4.39E-02 2.56E-03 3.41E-02 3.05E-03 4.06E-02 Lung 7.50E+00 mRem 2.99E-03 3.98E-02 3.29E-03 4.39E-02 2.56E-03 3.41E-02 3.05E-03 4.07E-02 GI-Lli 7.50E+00 mRem 2.99E-03 3.99E-02 3.29E-03 4.39E-02 2.56E-03 3.41E-02 3.05E-03 4.07E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Bone 1.500E+01 mRem 8.052E-05 5.368E-04 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Liver 1.500E+01 mRem 1.188E-02 7.922E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Total Body 1.500E+01 mRem 1.190E-02 7.931E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Thyroid 1.500E+01 mRem 1.191E-02 7.943E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Kidney 1.500E+01 mRem 1.188E-02 7.922E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Lung 1.500E+01 mRem 1.188E-02 7.923E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose GI-Lli 1.500E+01 mRem 1.189E-02 7.924E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose 61

Table 2-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Bone 7.50E+00 mRem 2.44E-05 3.26E-04 6.47E-05 8.63E-04 1.26E-05 1.68E-04 2.32E-05 3.10E-04 Liver 7.50E+00 mRem 2.31E-03 3.08E-02 3.13E-03 4.18E-02 3.81E-03 5.08E-02 4.63E-03 6.17E-02 Total Body 7.50E+00 mRem 2.31E-03 3.08E-02 3.15E-03 4.19E-02 3.81E-03 5.08E-02 4.63E-03 6.17E-02 Thyroid 7.50E+00 mRem 2.38E-03 3.18E-02 3.14E-03 4.18E-02 3.82E-03 5.09E-02 4.66E-03 6.21E-02 Kidney 7.50E+00 mRem 2.31E-03 3.08E-02 3.13E-03 4.18E-02 3.81E-03 5.08E-02 4.63E-03 6.17E-02 Lung 7.50E+00 mRem 2.31E-03 3.08E-02 3.13E-03 4.18E-02 3.81E-03 5.08E-02 4.63E-03 6.17E-02 GI-Lli 7.50E+00 mRem 2.32E-03 3.09E-02 3.13E-03 4.18E-02 3.81E-03 5.08E-02 4.63E-03 6.17E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Bone 1.500E+01 mRem 1.250E-04 8.331E-04 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Liver 1.500E+01 mRem 1.387E-02 9.249E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Total Body 1.500E+01 mRem 1.389E-02 9.259E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Thyroid 1.500E+01 mRem 1.400E-02 9.332E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Kidney 1.500E+01 mRem 1.387E-02 9.249E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Lung 1.500E+01 mRem 1.387E-02 9.250E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose GI-Lli 1.500E+01 mRem 1.388E-02 9.255E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose 62

TABLE 2-6 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES STARTING: 1-Jan-2019 ENDING: 31-Dec-2019 The values in this table represent a priori Minimum Detectable Concentration (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 2.94E-08 uCi/cc Kr-88 3.22E-08 uCi/cc Xe-133 2.30E-08 uCi/cc Xe-133m 7.30E-08 uCi/cc Xe-135 8.73E-09 uCi/cc Xe-138 1.99E-07 uCi/cc I-131 1.34E-13* uCi/cc I-133 1.53E-13* uCi/cc Mn-54 1.62E-13* uCi/cc Fe-59 3.42E-13* uCi/cc Co-58 1.30E-13* uCi/cc Co-60 1.54E-13* uCi/cc Zn-65 2.54E-13* uCi/cc Mo-99 9.61E-13* uCi/cc Cs-134 1.42E-13* uCi/cc Cs-137 1.28E-13* uCi/cc Ce-141 1.26E-13* uCi/cc Ce-144 5.64E-13* uCi/cc Sr-89 1.10E-16 uCi/cc Sr-90 6.70E-16 uCi/cc H-3 4.00E-07 uCi/cc

Based on an estimated sample quantity of 4.078E+07 ccs.

63

Table 2-7A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 0 0 0 0 0

2. Total time period for batch releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum time period for a batch release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average time period for a batch release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum time period for a batch release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 64

Table 2-7B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 0 0 0 0 0

2. Total time period for batch releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum time period for a batch release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average time period for a batch release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum time period for a batch release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 65

Table 2-8A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 66

Table 2-8B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 67

Table 2-8C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 68

3.0 Solid Waste 3.1 Regulatory Requirements The Process Control Program (PCP) and the ODCM requirements presented in this section are for Unit 1 and Unit 2 and are stated in part.

3.1.1 Solid Radioactive Waste System PCP Section A.3.1 Solid Radioactive Waste System control states:

The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure that they meet requirements of 10 CFR Parts 20 and 71, prior to shipment of radioactive wastes from the site.

3.1.2 Reporting Requirements Technical Specification 5.6.3 requires in part:

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

PCP Section A.4.1 states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units as outlined in Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 1974, with data summarized on a 6 month basis following the format of Appendix B thereof.

69

For each type of solid radwaste shipped offsite during the report period, the report shall include the following information:

a. Container volume.

b. Total curie quantity (specify whether determined by measurement or estimate).

c. Principal radionuclides (specify whether determined by measurement or estimate).

d. Type of waste (such as spent resin, compacted dry waste, evaporator bottoms).

e. Type of container (such as LSA, type A, type B, large quantity).

f. Solidification agent (such as cement).

Major changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed and accepted by the PRB.

3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.

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TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jan-2019 ENDING: 30-Jun-2019 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est. Total period ERROR %

3

a. Spent resins, filter sludges, evaporator m 6.710E+01 bottoms, etc. Ci 3.390E+02 1.00 E+01 3

b. Dry compressible waste, contaminated equip. m 6.670E+02 etc. Ci 2.93E-01 2.00 E+01 3

c. Irradiated components, control rods, m Ci 3

d. Control Rod Drive Filters m Ci 3

e. Other (describe) m Equip. etc. Ci

2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES a.Fe-55 29.92 1.01E+02 Co-60 41.95 1.42E+02 Zn-65 10.27 3.48E+01 Mn-54 23.8 1.968E+02 Co-58 3.86 1.31E+01 Other 7.82 1.35E+01 b.Fe-55 59.04 1.73E-01 Co-60 31.59 2.978E+00 Mn-54 2.36 6.93E-03 Zn-65 1.21 3.54E-03 Other 7.01 2.055E-02 c.

d.

e.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination All waste sent to processors N/A N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 71

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jul-2019 ENDING: 31-Dec-2019 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est. Total period ERROR %

3

a. Spent resins, filter sludges, evaporator m 5.01E+01 bottoms, etc. Ci 8.50E+01 1.00 E+01 3

b. Dry compressible waste, contaminated equip. m 3.10E+02 etc. Ci 2.98E-02 2.00 E+01 3

c. Irradiated components, control rods, m Ci 3

d. Control Rod Drive Filters m Ci 3

e. Other (describe) m 7.65E+00 Equip. etc. Ci 4.52E-06 2.00E+01

2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES a.Fe-55 19.92 1.69E+01 Co-60 41.34 3.51E+01 Zn-65 9.65 8.20E+00 Mn-54 10.3 8.76E+00 Other 18.78 1.60E+01 b.Fe-55 61.33 1.83E-02 Co-60 31.06 9.25E-03 Mn-54 1.53 4.56E-04 Ni-63 3.41 1.02E-03 Other 2.67 7.94E-04 c.

d. Fe-55 56.95 2.58E-06 Co-60 28.6 1.29E-06 Cs-137 8.19 3.70E-07 Other 6.26 2.83E-07 e.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination All waste sent to processors N/A N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 72

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jan-2019 ENDING: 30-Jun-2019 TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATION OF QUANTITY/ NUCLIDES/ CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBIC FEET (FT 3)

Dewatered 339 Zn-65,Fe-55,Co-60 High 14 N/A 207.4, 125.2 LSA-II, Type B Resins Mn-54, Co-58, Ag-110m, Intergrity

See Note C-14, Cr-51 Container Dry 0.293 Fe-55,Co-60,Mn-54 B-25 73 90, 1040, N/A 2080 LSA-I, SCO-II, Active Waste Zn-65, Ni-63, Cs-137, Boxes/High

See Note LSA-I/SCO-II Co-58, Cr-51 Integrity Container

Note: The actual size and number of the containers may vary from the recorded values due to the use of different containers by waste processors.

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-JUL-2019 ENDING:31-DEC-2019 TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATION OF QUANTITY/ NUCLIDES/ CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBIC FEET (FT 3)

Dewatered 850 Zn-65,Fe-55,Co-60 High 10 207.4 LSA-II, Type B N/A Resins Mn-54, C-14, Ni-63 Intergrity

See Note Co-58, Cs-137, H-3 Container Dry 2.98E-02 Fe-55,Co-60,Mn-54 B-25 22 96/2080/ LSA-I, SCO-II N/A Active Waste Zn-65, Cs-137, Boxes/High

See Note 1040 Ni-63, Co-58 Integrity Container Oil 4.52E-06 Fe-55,Co-60,Mn-54 1 335 Exempt N/A N/A Zn-65, Cs-137,

See Note Ni-63, Co-58

Note: The actual type, size and number of the containers may vary from the recorded values due to the use of different containers by waste processors for final disposal of processed resin and DAW.

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4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part that the Radioactive Effluent Release Report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with the ODCM.

4.2 Demonstration of Compliance The locations of concern within the site boundary are the Roadside Park, the Camping Area, the Recreation Area, and the Visitors Center. Listed in Table 4-1 are: The distance and direction from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the Main Stack (elevated) and from the reactor building (ground level); and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.

The source term is not listed in Table 4-1 . The source term is listed in Tables 2-2A and 2-2B, for the elevated releases. Similarly the source term is listed in Tables 2-3A and 2-3B for the ground level releases.

The maximum doses in units of mrem accumulated by an individual MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period are presented in Table 4-1.

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Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Location Name: ROADSIDE PARK Distance (kilometers): 1.18E+00 Sector: WNW Occupancy Factor: 2.28E-04 Age Group: Child Elevated Release Particulate and Radioiodine X/Q (sec/m3): 2.37E-08 D/Q (m-2): 1.29E-09 Elevated Release Noble Gas X/Q (sec/m3): 2.42E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 7.00E-06 D/Q (m-2): 2.01E-08 Ground Level Release Noble Gas X/Q (sec/m3): 7.83E-06 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Total Body mRem 5.83E-09 7.08E-09 7.85E-09 8.44E-09 2.92E-08 GI-Lli mRem 5.86E-09 7.08E-09 7.85E-09 8.44E-09 2.92E-08 Lung mRem 5.84E-09 7.09E-09 7.86E-09 8.44E-09 2.92E-08 Kidney mRem 5.83E-09 7.08E-09 7.85E-09 8.44E-09 2.92E-08 Skin mRem 2.31E-12 2.90E-11 5.54E-13 2.15E-12 3.40E-11 Bone mRem 3.92E-12 3.93E-11 9.88E-13 3.30E-12 4.75E-11 Thyroid mRem 5.89E-09 7.08E-09 7.86E-09 8.47E-09 2.93E-08 Liver mRem 5.83E-09 7.08E-09 7.85E-09 8.44E-09 2.92E-08 75

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Location Name: CAMPING AREA Distance (kilometers): 1.27E+00 Sector: WNW Occupancy Factor: 5.48E-03 Age Group: Child Elevated Release Noble Gas X/Q (sec/m3): 2.38E-08 Ground Level Release Noble Gas X/Q (sec/m3): 7.03E-06 Elevated Release Particulate and Radioiodine X/Q (sec/m3): 2.33E-08 D/Q (m-2): 2.01E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 6.27E-06 D/Q (m-2): 1.80E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Total Body mRem 1.26E-07 1.53E-07 1.69E-07 1.82E-07 6.30E-07 Skin mRem 2.08E-10 1.33E-09 2.02E-10 4.73E-10 2.21E-09 Lung mRem 1.26E-07 1.53E-07 1.69E-07 1.82E-07 6.30E-07 GI-Lli mRem 1.26E-07 1.53E-07 1.69E-07 1.82E-07 6.31E-07 Bone mRem 2.20E-10 1.44E-09 1.85E-10 4.35E-10 2.28E-09 Liver mRem 1.26E-07 1.53E-07 1.69E-07 1.82E-07 6.30E-07 Thyroid mRem 1.27E-07 1.53E-07 1.69E-07 1.83E-07 6.32E-07 Kidney mRem 1.26E-07 1.53E-07 1.69E-07 1.82E-07 6.30E-07 76

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Location Name: RECREATION AREA Distance (kilometers): 1.03E+00 Sector: SSE Occupancy Factor: 2.37E-02 Age Group: Child Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 5.73E-06 D/Q (m-2): 2.36E-08 Elevated Release Noble Gas X/Q (sec/m3): 3.30E-08 Ground Level Release Noble Gas X/Q (sec/m3): 6.42E-06 Elevated Release Particulate and Radioiodine X/Q (sec/m3): 3.21E-08 D/Q (m-2): 1.56E-09 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Total Body mRem 4.96E-07 6.04E-07 6.68E-07 7.18E-07 2.49E-06 Thyroid mRem 5.01E-07 6.04E-07 6.69E-07 7.21E-07 2.49E-06 Lung mRem 4.97E-07 6.04E-07 6.69E-07 7.19E-07 2.49E-06 Bone mRem 4.09E-10 4.26E-09 1.04E-10 3.53E-10 5.13E-09 Liver mRem 4.97E-07 6.04E-07 6.68E-07 7.18E-07 2.49E-06 GI-Lli mRem 4.99E-07 6.04E-07 6.68E-07 7.18E-07 2.49E-06 Skin mRem 2.84E-10 3.54E-09 6.96E-11 2.67E-10 4.16E-09 Kidney mRem 4.96E-07 6.04E-07 6.68E-07 7.18E-07 2.49E-06 77

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Location Name: VISITORS CENTER Distance (kilometers): 6.94E-01 Sector: WSW Occupancy Factor: 4.57E-04 Age Group: Child Elevated Release Particulate and Radioiodine X/Q (sec/m3): 4.97E-08 D/Q (m-2): 2.26E-09 Elevated Release Noble Gas X/Q (sec/m3): 5.00E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 1.72E-05 D/Q (m-2): 5.47E-08 Ground Level Release Noble Gas X/Q (sec/m3): 1.87E-05 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Liver mRem 2.87E-08 3.49E-08 3.87E-08 4.16E-08 1.44E-07 Lung mRem 2.88E-08 3.49E-08 3.87E-08 4.16E-08 1.44E-07 Bone mRem 1.96E-11 2.03E-10 4.21E-12 1.52E-11 2.42E-10 Kidney mRem 2.87E-08 3.49E-08 3.87E-08 4.16E-08 1.44E-07 Total Body mRem 2.87E-08 3.49E-08 3.87E-08 4.16E-08 1.44E-07 Thyroid mRem 2.90E-08 3.49E-08 3.87E-08 4.17E-08 1.44E-07 Skin mRem 1.17E-11 1.54E-10 1.97E-12 9.37E-12 1.77E-10 GI-Lli mRem 2.89E-08 3.49E-08 3.87E-08 4.16E-08 1.44E-07 78

5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 5.1 Regulatory Requirements The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

5.2 Demonstration of Compliance No dose limits stated in ODCM Sections 2.1.3, 3.1.3, and 3.1.4 were exceeded.

Therefore, compliance with 40 CFR 190 dose limits was demonstrated in accordance with the requirements of ODCM Section 5.1.3.

6.0 Meteorological Data The Radioactive Effluent Release Report, to be submitted by May 1 of each year, shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured), on magnetic tape, or, in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has retained this summary of required meteorological data on site in a file. It will be provided to the NRC upon request.

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirements ODCM, Chapter 7, Section 7.2.2.6.2 states that the Radioactive Effluent Release Report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively.

79

7.1.2 Description of Deviations There were no deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements during this reporting period.

7.2 Tanks Exceeding Curie Content Limits 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include notifications if the contents within any outside temporary tank, for liquids, exceed the limit of Technical Specification 5.5.8.b.

7.2.2 Description of Deviations There were no outside temporary tanks, for liquids, that exceeded the limit of Technical Specification 5.5.8.b during this reporting period.

7.3 Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) 7.3.1 Regulatory Requirements ODCM 7.2.2.6 states in part that deviations from MDC(s) required in Table 3-3 shall be included in the Radioactive Effluent Release Report.

7.3.2 Description of Deviation There were no deviations from MDC(s) required in Table 3-3 during this reporting period.

8.0 Changes to the Plant Hatch Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements Pursuant to Technical Specification 5.5.1 and ODCM Section 7.2.2.5, licensee initiated changes shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

80

8.2 Description of Changes There were no changes to the Hatch ODCM in 2019.

9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems No major changes were made to the Liquid, Gaseous, or Solid Radwaste Treatment Systems.

9.1 Regulatory Requirements The Radioactive Effluent Release Report shall include any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to ODCM Chapter 7, Section 7.2.2.7.

81

9.2 Description of Major Changes Gaseous Radwaste System There were no major changes to the gaseous radwaste system during this reporting period.

Solid Radwaste System There were no major changes to the solid radwaste system during this reporting period.

Liquid Radwaste System There were no major changes to the Liquid Radwaste Treatment System during this reporting period.

82

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1, 2019 - DECEMBER 31, 2019 APPENDIX A 83

Hatch Nuclear Plant Appendix A 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.

As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of principal radionuclides in gaseous effluents have changed, and C-14 has become a larger percentage. Principal radionuclides are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21), Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, the NRC recommended re-evaluating principal radionuclides and reporting C-14 as appropriate. In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants will report C-14 amounts released and resulting doses to the maximally exposed member of the public.

Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation. The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.

At Plant Hatch, the quantity of C-14 released in gaseous effluents in 2010 was estimated to be 14.16 Curies (per unit). Approximately 95% of the C-14 released is in the form of 14 CO 2 and is incorporated into plants through photosynthesis. Ingestion dose results from this pathway. The remaining 5% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Hatch ODCM, the resulting bone dose to a child located at the controlling receptor location would be 1.59E-01 mrem in a year which is 1.06% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents.

The resulting total body dose to a child located at the controlling receptor location would be 3.18E-02 mrem in a year which is 0.21% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.

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NL-20-0419 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Enclosure 5 Joseph M. Farley Nuclear Plant - Units 1&2 Annual Radioactive Effluent Release Report for 2019

A[KNOWLEDGEMENT OF OWNERSHIP The contents of this Annual Radioactive Effluent Release Report, contained herein, are true and accurate to the best of my knowledge. I understand that I am ultimately responsible for the information that has been captured within these pages.

4 t:U\eM C-<--;) ~.J.AA---

Valencia Flowers Farley Chemistry Manager Chemistry Superintendent

AtKNOWLEDGEMENT OF OWNERSHIP The contents of this Annual Radioactive Effluent Release Report, contained herein, are true and accurate to the best of my knowledge. I understand that I am ultimately responsible for the information that has been captured within these pages.

Valencia Flowers Farley Chemistry Manager Shawn lux Chemistry Supervisor

SOUTHERN NUCLEAR OPERATING COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALENDAR YEAR 2019

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 1.0 LIQUID EFFLUENTS 1 1.1 Regulatory Requirements 1 1.1.1 Concentration Limits 1 1.1.2 Dose Limits 1 1.2 Effluent Concentration Limit (ECL) 1 1.3 Measurements and Approximation of Total Radioactivity 2 1.3.1 Total Radioactivity Determination 2 1.3.2 Total Error Estimation 3 1.4 Liquid Effluents - Release Data 3 1.5 Radiological Impact Due to Liquid Releases 3 1.6 Liquid Effluents - Batch Releases 3 1.7 Liquid Effluents - Abnormal Releases 3 2.0 GASEOUS EFFLUENTS 24 2.1 Regulatory Requirements 24 2.1.1 Dose Rate Limits 24 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 24 2.1.3 Doses to a Member of the Public 24 2.2 Measurements and Approximation of Total Radioactivity 25 2.2.1 Sample Collection and Analysis 26

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 2.2.2 Total Quantities of Radioactivity, Dose Rates and Cumulative Doses 26 2.2.2.1 Fission and Activation Gases 26 2.2.2.2 Radioiodine, Tritium and Particulate Releases 26 2.2.2.3 Gross Alpha Release 26 2.2.3 Total Error Estimation 26 2.3 Gaseous Effluent Release Data 27 2.4 Radiological Impact Due to Gaseous Releases 28 2.5 Gaseous Effluents - Batch Releases 28 2.6 Gaseous Effluents - Abnormal Releases 28 3.0 SOLID WASTE 53 3.1 Regulatory Requirements 53 3.1.1 Solid Radioactive Waste System 56 3.1.2 Reporting Requirements 56 3.2 Solid Waste Data 56 4.0 DOSES TO MEMBERS OF THE PUBLIC INSIDE THE SITE BOUNDARY 56 4.1 Regulatory Requirements 56 4.2 Demonstration of Compliance 56

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 5.0 TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190) 60 5.1 Regulatory Requirements 60 5.2 Demonstration of Compliance 60 6.0 METEOROLOGICAL DATA 60 7.0 PROGRAM DEVIATIONS 60 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 70 7.1.1 Regulatory Requirements 60 7.1.2 Description of Deviations 60 7.2 Effluent Sample Analysis Exceeding Minimum Detectable Concentration 60 (MDC) 7.2.1 Regulatory Requirements 61 7.2.2 Description of Deviations 61 7.3 Incorrect Compositing of Liquid or Gaseous Effluent Samples 61 7.3.1 Regulatory Requirements 61 7.3.2 Description of Deviations 61 8.0 CHANGES TO THE PLANT FARLEY ODCM 61 8.1 Regulatory Requirements 61 8.2 Description of Changes 61

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR SOLID RADWASTE 61 TREATMENT SYSTEMS 9.1 Regulatory Requirements 61 9.2 Description of Major Changes 61 App. A Appendix A, Carbon-14 Supplement for 2019 63 App. B Appendix B, Correction to 2018 Annual Radioactive Effluent Release 63 Report

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases, Unit 1 (Quarters 1,2, 3 and 4 4) 1-1B Liquid Effluents - Summation of All Releases, Unit 2 (Quarters 1,2, 3 and 5 4) 1-1C Liquid Effluents - Summation of All Releases, Site (Quarters 1,2, 3 and 4) 6 1-2A Liquid Effluents, Unit 1 (Quarters 1,2, 3 and 4) 7 1-2B Liquid Effluents, Unit 2 (Quarters 1,2, 3 and 4) 10 1-2C Liquid Effluents, Site (Quarters 1,2, 3 and 4) 14 1-3A Doses to a MEMBER OF THE PUBLIC Due to Liquid Releases, Unit 1 17 (Quarters 1,2,3 and 4) 1-3B Doses to a MEMBER OF THE PUBLIC Due to Liquid Releases, Unit 2 18 (Quarters 1,2,3 and 4) 1-4 Minimum Detectable Concentration - Liquid Sample Analyses 19 1-5A Liquid Effluents - Batch Release Summary, Unit 1 20 1-5B Liquid Effluents - Batch Release Summary, Unit 2 21 1-6A Liquid Effluents - Abnormal Release Summary, Unit 1 22 1-6B Liquid Effluents - Abnormal Release Summary, Unit 2 23

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 2-1A Gaseous Effluents - Summation of All Releases, Unit 1 (Quarters 1,2, 3 29 and 4) 2-1B Gaseous Effluents - Summation of All Releases, Unit 2 (Quarters 1,2, 3 30 and 4) 2-1C Gaseous Effluents - Summation of All Releases, Site (Quarters 1,2, 3 and 31 4) 2-2A Gaseous Effluents - Mixed Mode Level Releases, Unit 1 (Quarters 1,2, 3 32 and 4) 2-2B Gaseous Effluents - Mixed Mode Level Releases, Unit 2 (Quarters 1,2, 3 34 and 4) 2-2C Gaseous Effluents - Mixed Mode Level Releases, Site (Quarters 1,2, 3 36 and 4) 2-3A Gaseous Effluents - Ground Level Releases, Unit 1 (Quarters 1,2, 3 and 38 4) 2-3B Gaseous Effluents - Ground Level Releases, Unit 2 (Quarters 1,2, 3 and 40 4) 2-3C Gaseous Effluents - Ground Level Releases, Site (Quarters 1,2, 3 and 4) 43

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 2-4A Air Doses Due to Noble Gases in Gaseous Releases, Unit 1 (Quarters 1,2, 44 3 and 4) 2-4B Air Doses Due to Noble Gases in Gaseous Releases, Unit 2 (Quarters 1,2, 45 3 and 4) 2-5A Doses to a MEMBER OF THE PUBLIC Due to Radioiodines, Tritium, and 47 Particulates in Gaseous Releases, Unit 1 (Quarters 1,2,3 and 4) 2-5B Doses to a MEMBER OF THE PUBLIC Due to Radioiodines, Tritium, and 47 Particulates in Gaseous Releases, Unit 2 (Quarters 1,2,3 and 4) 2-6 Minimum Detectable Concentration - Gaseous Effluent Analyses 48 2-7A Gaseous Effluents - Batch Release Summary, Unit 1 49 2-7B Gaseous Effluents - Batch Release Summary, Unit 2 50 2-8A Gaseous Effluents - Abnormal Release Summary, Unit 1 51 2-8B Gaseous Effluents - Abnormal Release Summary, Unit 2 52 3-1 Solid Waste and Irradiated Fuel Shipments 54 4-1 Doses to a MEMBER OF THE PUBLIC Due to Activities Inside the Site 57 Boundary, Site

1.0 LIQUID EFFLUENTS This section contains applicable ODCM limits for liquid effluents as well as the quantities of radioactive liquid effluents released during 2019. These quantities are summarized on a quarterly basis and include any unplanned releases. A tabulation of the total body and organ doses which were calculated in accordance with ODCM 2.4 are presented to show conformance with the limits of ODCM 2.1.3.

1.1 Regulatory Requirements 1.1.1 Concentration Limits Technical Specifications 5.5.4.b and 5.5.4.c state that the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited at all times to ten times the concentrations specified in 10CFR20, 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 1.0E-04 µCi/ml total activity.

1.1.2 Dose Limits Technical Specifications 5.5.4.d and 5.5.4.e state that the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

1.2 Effluent Concentration Limit (ECL)

ECL values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, I-131, tritium, Sr-89, Sr-90, and Fe-55, are taken from 10CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of 10 is utilized to allow flexibility in establishing practical monitor setpoints which can accommodate effluent releases at concentrations higher than the ECL values stated in 10CFR20, Appendix B, Table 2, Column 2.

For dissolved or entrained noble gases in liquid radwaste, the ECL is 1.0E-04 uCi/ml total activity.

For gross alpha in liquid radwaste, the ECL is 2.0E-09 uCi/ml.

Furthermore, for all the above radionuclides, or categories of radioactivity, the overall ECL fraction is determined in accordance with 10CFR Part 20, Appendix B.

1.3 Measurements and Approximation of Total Radioactivity The radionuclides listed below are specifically considered when evaluating liquid effluents:

MN-54 CS-134 FE-59 CS-137 CO-58 CE-141 CO-60 CE-144 ZN-65 MO-99 SR-89 FE-55 SR-90 H-3 I-131 1.3.1 Total Radioactivity Determination Batch Releases: Representative pre-release grab samples are obtained and analyzed in accordance with ODCM Table 2-3. Isotopic analyses are performed by the computerized pulse height analysis system utilizing high resolution germanium detectors. Isotopic radionuclide concentrations thus obtained are used for release rate calculations as specified in the ODCM. Only those nuclides that are detected are used in the calculations. All Gross Alpha, Strontium, and Iron-55, samples are sent offsite to the Georgia Power Environmental Laboratory for analysis. Gross beta determinations are made using 2 pi gas flow proportional counters. Tritium determinations are made using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on the gamma spectrometry system.

The sample analyses results are used along with the ECL values to determine the ECL fraction for the planned release. The ECL fraction is then used, with the appropriate safety factors, and the expected dilution stream flow, to calculate the maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded. A monitor reading in excess of the calculated setpoint will result in automatic termination of the liquid radwaste discharge.

Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibration factors are used by the computer to generate a pre-release printout. If the release is not permissible, appropriate warnings will be displayed on the computer screen and on the printout. If the release is permissible, it is approved by a Chemistry Technician. The release permit is transferred from the Chemistry Department to the Operations Department for release.

When the release is completed, the actual release data are provided to the Chemistry Department.

These release data, including release rate and release duration, are input into the computer and a post-release printout is generated. This printout contains the actual release rates, radionuclide concentrations and quantities, dilution flow, and calculated doses to an individual.

Continuous Releases: Continuous releases are analogous to batch releases except that they are analyzed on a weekly composite basis in accordance with ODCM Table 2-3.

Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

1.3.2 Total Error Estimation The maximum error associated with volume and flow measurements, based upon plant calibration practice is estimated to be + or - 10%. The average error associated with counting is estimated to be less than + or - 15%.

1.4 Liquid Effluent Release Data Summaries of all radioactive liquid effluents released from Units 1 and 2 during 2019 are presented in accordance with Regulatory Guide 1.21 Tables 2A and 2B. Information required by Table 2A is found in this report in Tables 1-1A, 1-1B, and 1-1C; Table 2-B information is presented in Tables 1-2A, 1-2B, and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.

1.5 Radiological Impact Due to Liquid Releases The total body and organ doses for Units 1 and 2 are provided in the following tables in order to show conformance with the limits of ODCM 2.1.3:

Unit 1 2019 Doses to a Member of the Public due to Liquid Releases: Table 1-3A Unit 2 2019 Doses to a Member of the Public due to Liquid Releases: Table 1-3B 1.6 Liquid Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables:

Unit 1 2019 Liquid Effluents - Batch Release Summary: Table 1-5A Unit 2 2019 Liquid Effluents - Batch Release Summary: Table 1-5B 1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases during 2019.

Abnormal release information for Units 1 and 2 is summarized in the following tables:

Unit 1 2019 Liquid Effluents - Abnormal Release Summary: Table 1-6A Unit 2 2019 Liquid Effluents - Abnormal Release Summary: Table 1-6 Table 1-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation of All Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 4.86E-03 2.63E-03 2.11E-03 3.41E-03

2. Average diluted concentration during period uCi/mL 2.78E-09 2.54E-09 1.76E-09 3.50E-09

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 2.79E+02 1.54E+02 2.07E+02 7.41E+01

2. Average diluted Concentration during period uCi/mL 1.59E-04 1.49E-04 1.73E-04 7.62E-05

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 8.32E-04 8.83E-05 5.37E-04 6.03E-04

2. Average diluted Concentration during period uCi/mL 4.77E-10 8.54E-11 4.49E-10 6.19E-10

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 1.56E+06 1.02E+06 1.04E+06 8.92E+05 F. Volume of Dilution Water Used Liters 1.74E+09 1.03E+09 1.19E+09 9.72E+08

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

Table 1-1B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation of All Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 1.17E-02 1.40E-02 1.42E-03 1.93E-03

2. Average diluted concentration during period uCi/mL 6.98E-09 9.87E-09 1.11E-09 2.29E-09

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 3.60E+02 1.02E+02 1.06E+02 1.39E+02

2. Average diluted Concentration during period uCi/mL 2.15E-04 7.19E-05 8.28E-05 1.65E-04

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 4.93E-04 8.99E-05 5.53E-04 6.02E-04

2. Average diluted Concentration during period uCi/mL 2.94E-10 6.34E-11 4.33E-10 7.15E-10

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 1.41E+06 1.30E+06 8.49E+05 7.46E+05 F. Volume of Dilution Water Used Liters 1.67E+09 1.42E+09 1.28E+09 8.42E+08

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

Table 1-1C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation of All Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 1.65E-02 1.66E-02 3.53E-03 5.34E-03

2. Average diluted concentration during period uCi/mL 4.84E-09 6.78E-09 1.43E-09 2.94E-09

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 6.38E+02 2.56E+02 3.13E+02 2.13E+02

2. Average diluted Concentration during period uCi/mL 1.87E-04 1.04E-04 1.26E-04 1.18E-04

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 1.32E-03 1.78E-04 1.09E-03 1.20E-03

2. Average diluted Concentration during period uCi/mL 3.87E-10 7.27E-11 4.41E-10 6.64E-10

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 2.98E+06 2.32E+06 1.89E+06 1.64E+06 F. Volume of Dilution Water Used Liters 3.42E+09 2.45E+09 2.47E+09 1.81E+09

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Cr-51 Curies 3.81E-06 0.00E+00 0.00E+00 3.06E-04 Te-131M Curies 0.00E+00 1.41E-07 0.00E+00 0.00E+00 Ba-133 Curies 0.00E+00 1.69E-08 0.00E+00 0.00E+00 Sn-113 Curies 0.00E+00 0.00E+00 0.00E+00 1.45E-06 Co-58 Curies 8.43E-05 6.73E-05 1.14E-04 1.04E-03 Ni-56 Curies 1.18E-06 8.74E-07 0.00E+00 0.00E+00 Co-60 Curies 2.85E-03 1.60E-03 1.14E-03 7.23E-04 Ce-141 Curies 0.00E+00 0.00E+00 0.00E+00 8.42E-07 Ag-108M Curies 7.78E-06 0.00E+00 0.00E+00 3.02E-06 I-131 Curies 0.00E+00 1.31E-06 0.00E+00 0.00E+00 Ni-63 Curies 4.49E-04 5.29E-04 3.18E-04 3.16E-04 Mo-101 Curies 0.00E+00 7.29E-07 0.00E+00 0.00E+00 Sb-125 Curies 1.02E-03 3.67E-04 4.03E-04 2.16E-04 Cs-138 Curies 1.40E-06 0.00E+00 0.00E+00 0.00E+00 Zr-95 Curies 0.00E+00 0.00E+00 2.42E-06 1.92E-04 Nb-97 Curies 1.11E-05 1.05E-06 2.54E-06 6.94E-07 Zn-65 Curies 1.46E-05 0.00E+00 0.00E+00 2.64E-06 Sr-89 Curies 0.00E+00 0.00E+00 0.00E+00 2.06E-05 Nb-95 Curies 4.52E-06 0.00E+00 1.63E-05 3.41E-04 Sn-117M Curies 1.59E-06 0.00E+00 0.00E+00 0.00E+00 Sr-92 Curies 0.00E+00 4.77E-07 0.00E+00 0.00E+00 Rh-105 Curies 0.00E+00 0.00E+00 0.00E+00 1.19E-05 La-142 Curies 0.00E+00 0.00E+00 5.55E-07 0.00E+00 As-76 Curies 0.00E+00 1.08E-06 0.00E+00 0.00E+00 Ru-103 Curies 0.00E+00 0.00E+00 0.00E+00 1.01E-06 Ag-110M Curies 0.00E+00 0.00E+00 1.92E-06 9.81E-06 Mn-54 Curies 2.24E-05 1.07E-05 6.49E-06 1.39E-05 Fe-55 Curies 1.12E-04 5.07E-05 6.25E-05 1.94E-04 Y-91 Curies 1.52E-04 0.00E+00 0.00E+00 0.00E+00 Te-125M Curies 8.87E-05 0.00E+00 0.00E+00 0.00E+00 Cs-137 Curies 2.86E-05 0.00E+00 2.25E-05 1.09E-05 I-132 Curies 0.00E+00 6.42E-07 0.00E+00 4.09E-06 Sb-124 Curies 0.00E+00 0.00E+00 0.00E+00 2.72E-06 Pm-149 Curies 0.00E+00 0.00E+00 5.27E-06 0.00E+00 Te-129M Curies 0.00E+00 0.00E+00 1.44E-05 0.00E+00 Total For Period Curies 4.86E-03 2.63E-03 2.11E-03 3.41E-03 Tritium H-3 Curies 2.79E+02 1.54E+02 2.07E+02 7.41E+01 Dissolved And Entrained Gases Xe-133 Curies 8.31E-04 8.60E-05 5.37E-04 6.02E-04 Ar-41 Curies 0.00E+00 2.24E-06 0.00E+00 4.76E-07 Xe-135 Curies 1.57E-06 1.21E-07 0.00E+00 0.00E+00 Total For Period Curies 8.32E-04 8.83E-05 5.37E-04 6.03E-04 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Ni-63 Curies 3.87E-04 1.30E-03 1.74E-04 3.19E-04 Zr-95 Curies 5.77E-06 2.04E-04 4.23E-06 7.87E-05 I-132 Curies 0.00E+00 0.00E+00 0.00E+00 5.79E-07 Tc-99M Curies 0.00E+00 4.76E-07 0.00E+00 0.00E+00 Fe-55 Curies 1.19E-04 1.67E-04 1.00E-04 1.58E-04 Ce-141 Curies 6.21E-07 0.00E+00 2.77E-07 1.21E-06 Nb-95 Curies 4.46E-05 3.94E-04 1.75E-05 1.29E-04 Y-90M Curies 0.00E+00 0.00E+00 1.70E-07 0.00E+00 Co-58 Curies 2.27E-04 5.37E-03 2.87E-04 3.08E-04 Ru-106 Curies 5.18E-06 0.00E+00 0.00E+00 0.00E+00 Nb-97 Curies 1.18E-05 1.83E-05 2.13E-06 1.55E-06 Hg-203 Curies 8.86E-07 0.00E+00 0.00E+00 0.00E+00 Cs-137 Curies 2.80E-06 7.99E-07 0.00E+00 0.00E+00 Sb-124 Curies 0.00E+00 2.49E-05 3.23E-07 0.00E+00 Ag-108M Curies 2.81E-05 3.79E-06 0.00E+00 0.00E+00 Te-125M Curies 5.80E-05 9.45E-05 4.55E-05 0.00E+00 Ni-56 Curies 8.83E-07 7.58E-07 0.00E+00 0.00E+00 Sn-117M Curies 2.63E-06 9.38E-07 0.00E+00 0.00E+00 Co-60 Curies 9.36E-03 4.63E-03 6.38E-04 6.93E-04 Ag-110M Curies 3.67E-05 0.00E+00 0.00E+00 6.19E-06 Tc-101 Curies 0.00E+00 0.00E+00 3.82E-07 0.00E+00 Sb-125 Curies 1.13E-03 6.88E-04 1.42E-04 1.42E-04 Sn-113 Curies 0.00E+00 1.25E-05 0.00E+00 2.17E-06 Mn-54 Curies 1.25E-04 8.94E-05 4.47E-06 1.02E-05 Rh-106 Curies 5.18E-06 0.00E+00 0.00E+00 0.00E+00 Sr-92 Curies 1.48E-05 9.61E-07 0.00E+00 0.00E+00 Cr-51 Curies 0.00E+00 9.02E-04 0.00E+00 7.62E-05 Zn-65 Curies 1.05E-04 6.70E-05 3.01E-06 0.00E+00 Ce-144 Curies 1.45E-06 0.00E+00 0.00E+00 0.00E+00 Co-57 Curies 0.00E+00 1.31E-05 0.00E+00 0.00E+00 Nb-95M Curies 0.00E+00 0.00E+00 1.57E-06 0.00E+00 Te-131 Curies 1.55E-06 0.00E+00 3.89E-07 0.00E+00 Total For Period Curies 1.17E-02 1.40E-02 1.42E-03 1.93E-03 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Tritium H-3 Curies 3.60E+02 1.02E+02 1.06E+02 1.39E+02 Dissolved And Entrained Gases Xe-133 Curies 4.92E-04 8.31E-05 5.51E-04 6.02E-04 Ar-41 Curies 0.00E+00 5.65E-06 1.08E-06 0.00E+00 Xe-135 Curies 4.06E-07 1.16E-06 1.64E-06 6.65E-07 Total For Period Curies 4.93E-04 8.99E-05 5.53E-04 6.02E-04 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-89 Curies 0.00E+00 0.00E+00 0.00E+00 2.06E-05 Co-60 Curies 1.22E-02 6.23E-03 1.77E-03 1.42E-03 Sr-92 Curies 1.48E-05 1.44E-06 0.00E+00 0.00E+00 Co-57 Curies 0.00E+00 1.31E-05 0.00E+00 0.00E+00 Hg-203 Curies 8.86E-07 0.00E+00 0.00E+00 0.00E+00 Nb-95M Curies 0.00E+00 0.00E+00 1.57E-06 0.00E+00 Zr-95 Curies 5.77E-06 2.04E-04 6.65E-06 2.71E-04 Sb-125 Curies 2.16E-03 1.05E-03 5.45E-04 3.59E-04 Tc-99M Curies 0.00E+00 4.76E-07 0.00E+00 0.00E+00 Cs-138 Curies 1.40E-06 0.00E+00 0.00E+00 0.00E+00 Ru-103 Curies 0.00E+00 0.00E+00 0.00E+00 1.01E-06 Ru-106 Curies 5.18E-06 0.00E+00 0.00E+00 0.00E+00 Tc-101 Curies 0.00E+00 0.00E+00 3.82E-07 0.00E+00 Nb-97 Curies 2.29E-05 1.94E-05 4.66E-06 2.25E-06 Cs-137 Curies 3.14E-05 7.99E-07 2.25E-05 1.09E-05 Ag-110M Curies 3.67E-05 0.00E+00 1.92E-06 1.60E-05 I-131 Curies 0.00E+00 1.31E-06 0.00E+00 0.00E+00 Y-90M Curies 0.00E+00 0.00E+00 1.70E-07 0.00E+00 La-142 Curies 0.00E+00 0.00E+00 5.55E-07 0.00E+00 Mn-54 Curies 1.48E-04 1.00E-04 1.10E-05 2.41E-05 Te-125M Curies 1.47E-04 9.45E-05 4.55E-05 0.00E+00 Ce-144 Curies 1.45E-06 0.00E+00 0.00E+00 0.00E+00 Ag-108M Curies 3.59E-05 3.79E-06 0.00E+00 3.02E-06 Sb-124 Curies 0.00E+00 2.49E-05 3.23E-07 2.72E-06 Nb-95 Curies 4.92E-05 3.94E-04 3.38E-05 4.70E-04 Rh-105 Curies 0.00E+00 0.00E+00 0.00E+00 1.19E-05 Sn-117M Curies 4.22E-06 9.38E-07 0.00E+00 0.00E+00 Pm-149 Curies 0.00E+00 0.00E+00 5.27E-06 0.00E+00 Fe-55 Curies 2.32E-04 2.18E-04 1.63E-04 3.52E-04 I-132 Curies 0.00E+00 6.42E-07 0.00E+00 4.67E-06 As-76 Curies 0.00E+00 1.08E-06 0.00E+00 0.00E+00 Rh-106 Curies 5.18E-06 0.00E+00 0.00E+00 0.00E+00 Te-131M Curies 0.00E+00 1.41E-07 0.00E+00 0.00E+00 Cr-51 Curies 3.81E-06 9.02E-04 0.00E+00 3.82E-04 Ni-63 Curies 8.36E-04 1.83E-03 4.92E-04 6.34E-04 Ba-133 Curies 0.00E+00 1.69E-08 0.00E+00 0.00E+00 Ce-141 Curies 6.21E-07 0.00E+00 2.77E-07 2.05E-06 Y-91 Curies 1.52E-04 0.00E+00 0.00E+00 0.00E+00 Ni-56 Curies 2.06E-06 1.63E-06 0.00E+00 0.00E+00 Te-129M Curies 0.00E+00 0.00E+00 1.44E-05 0.00E+00 Sn-113 Curies 0.00E+00 1.25E-05 0.00E+00 3.62E-06 Zn-65 Curies 1.20E-04 6.70E-05 3.01E-06 2.64E-06 Co-58 Curies 3.11E-04 5.44E-03 4.01E-04 1.35E-03 Te-131 Curies 1.55E-06 0.00E+00 3.89E-07 0.00E+00 Mo-101 Curies 0.00E+00 7.29E-07 0.00E+00 0.00E+00 Total For Period Curies 1.65E-02 1.66E-02 3.53E-03 5.34E-03 Tritium H-3 Curies 6.38E+02 2.56E+02 3.13E+02 2.13E+02 Dissolved And Entrained Gases Xe-135 Curies 1.98E-06 1.29E-06 1.64E-06 6.65E-07 Ar-41 Curies 0.00E+00 7.89E-06 1.08E-06 4.76E-07 Xe-133 Curies 1.32E-03 1.69E-04 1.09E-03 1.20E-03 Total For Period Curies 1.32E-03 1.78E-04 1.09E-03 1.20E-03 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Lmt Total Body 5.00E+00 mRem 3.78E-03 7.56E-02 1.91E-03 3.82E-02 2.25E-03 4.49E-02 9.35E-04 1.87E-02 Total Body 1.50E+00 mRem 3.78E-03 2.52E-01 1.91E-03 1.27E-01 2.25E-03 1.50E-01 9.35E-04 6.23E-02 Total Body 5.00E+00 mRem 3.78E-03 7.56E-02 1.91E-03 3.82E-02 2.25E-03 4.49E-02 9.35E-04 1.87E-02 Total Body 1.50E+00 mRem 3.78E-03 2.52E-01 1.91E-03 1.27E-01 2.25E-03 1.50E-01 9.35E-04 6.23E-02 GI-Lli 5.00E+00 mRem 5.22E-03 1.04E-01 2.54E-03 5.08E-02 2.78E-03 5.57E-02 1.50E-03 3.01E-02 Kidney 5.00E+00 mRem 3.76E-03 7.52E-02 1.82E-03 3.63E-02 2.27E-03 4.54E-02 8.62E-04 1.72E-02 Liver 5.00E+00 mRem 3.77E-03 7.54E-02 1.91E-03 3.82E-02 2.26E-03 4.52E-02 9.63E-04 1.93E-02 Thyroid 5.00E+00 mRem 3.60E-03 7.20E-02 1.82E-03 3.64E-02 2.17E-03 4.34E-02 8.55E-04 1.71E-02 Bone 5.00E+00 mRem 7.88E-04 1.58E-02 8.01E-04 1.60E-02 4.94E-04 9.88E-03 5.52E-04 1.10E-02 Lung 5.00E+00 mRem 8.88E-03 1.78E-01 3.77E-03 7.55E-02 4.09E-03 8.18E-02 2.01E-03 4.01E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Lung 1.00E+01 mRem 1.88E-02 1.88E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 2.64E-03 2.64E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 8.45E-03 8.45E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 8.90E-03 8.90E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 8.71E-03 8.71E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 1.20E-02 1.20E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.00E+01 mRem 8.87E-03 8.87E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+00 mRem 8.87E-03 2.96E-01 Maximum Individual Liquid Liquid Effluent TB Annual 1

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

Table 1-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Lmt Total Body 5.00E+00 mRem 4.01E-03 8.01E-02 1.34E-03 2.69E-02 1.09E-03 2.18E-02 1.43E-03 2.86E-02 Total Body 1.50E+00 mRem 4.01E-03 2.67E-01 1.34E-03 8.96E-02 1.09E-03 7.26E-02 1.43E-03 9.54E-02 Total Body 5.00E+00 mRem 4.01E-03 8.01E-02 1.34E-03 2.69E-02 1.09E-03 2.18E-02 1.43E-03 2.86E-02 Total Body 1.50E+00 mRem 4.01E-03 2.67E-01 1.34E-03 8.96E-02 1.09E-03 7.26E-02 1.43E-03 9.54E-02 Lung 5.00E+00 mRem 8.87E-03 1.77E-01 4.58E-03 9.16E-02 1.73E-03 3.45E-02 2.06E-03 4.11E-02 Bone 5.00E+00 mRem 6.01E-04 1.20E-02 1.78E-03 3.56E-02 2.61E-04 5.23E-03 4.45E-04 8.90E-03 Kidney 5.00E+00 mRem 3.80E-03 7.59E-02 1.18E-03 2.37E-02 1.12E-03 2.23E-02 1.39E-03 2.77E-02 Thyroid 5.00E+00 mRem 3.71E-03 7.42E-02 1.05E-03 2.10E-02 1.06E-03 2.11E-02 1.39E-03 2.77E-02 GI-Lli 5.00E+00 mRem 6.50E-03 1.30E-01 3.71E-03 7.42E-02 1.39E-03 2.77E-02 1.71E-03 3.43E-02 Liver 5.00E+00 mRem 3.90E-03 7.80E-02 1.31E-03 2.62E-02 1.10E-03 2.20E-02 1.45E-03 2.91E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Liver 1.00E+01 mRem 7.76E-03 7.76E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 1.33E-02 1.33E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 7.20E-03 7.20E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 7.48E-03 7.48E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 3.09E-03 3.09E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 1.72E-02 1.72E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.00E+01 mRem 7.87E-03 7.87E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+00 mRem 7.87E-03 2.62E-01 Maximum Individual Liquid Liquid Effluent TB Annual

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 MINIMUM DETECTABLE CONCENTRATION - LIQUID SAMPLE ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

Nuclide MDC(µCi/ML)

Mn-54 3.09E-08 Co-58 3.83E-08 Fe-59 7.00E-08 Co-60 5.29E-08 Zn-65 1.16E-07 Mo-99 2.29E-07 I-131 3.02E-08 Cs-134 2.34E-08 Cs-137 4.29E-08 Ce-141 4.41E-08 Ce-144 1.68E-07 Table 1-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 118 77 77 66 338

2. Total time period for Batch releases ( Minutes ) 1.50E+04 9.67E+03 1.02E+04 8.62E+03 4.36E+04

3. Maximum time period for a batch release ( Minutes ) 1.65E+02 1.80E+02 1.70E+02 1.75E+02 1.80E+02

4. Average time period for a batch release ( Minutes ) 1.27E+02 1.26E+02 1.33E+02 1.31E+02 1.29E+02

5. Minimum time period for a batch release ( Minutes ) 1.06E+02 1.00E+02 1.18E+02 1.10E+02 1.00E+02

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 1.55E+04 1.93E+04 1.09E+04 3.82E+03 1.24E+04 Replace this text in the Station Parameters

Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.

Table 1-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 106 97 64 56 323

2. Total time period for Batch releases ( Minutes ) 1.34E+04 1.19E+04 8.04E+03 6.90E+03 4.02E+04

3. Maximum time period for a batch release ( Minutes ) 2.06E+02 1.70E+02 1.80E+02 2.40E+02 2.40E+02

4. Average time period for a batch release ( Minutes ) 1.26E+02 1.23E+02 1.26E+02 1.23E+02 1.24E+02

5. Minimum time period for a batch release ( Minutes ) 1.00E+01 9.00E+01 9.00E+01 9.50E+01 1.00E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 1.55E+04 1.93E+04 1.09E+04 3.82E+03 1.24E+04 Replace this text in the Station Parameters

Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.

Table 1-6A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Table 1-6B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2019. These quantities are summarized on a quarterly basis and include any unplanned releases. Tabulations are provided of the offsite air doses calculated in accordance with ODCM 3.4.2 to show conformance with the limits of ODCM 3.1.3, and the offsite organ doses to a member of the public calculated in accordance with ODCM 3.4.3 to show conformance with ODCM 3.1.4.

2.1 Regulatory Requirements The requirements presented in this section are for Unit 1 and Unit 2.

2.1.1 Dose Rate Limits The dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr. to the whole body and less than or equal to 3000 mrem/yr. to the skin, and

b. For Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr. to any organ.

2.1.2 Air Doses Due to Noble Gases in Gaseous Releases Technical Specifications 5.5.4.e and 5.5.4.h state that the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODCM Figure 10-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.3 Doses to a Member of the Public Technical Specifications 5.5.4.e and 5.5.4.i state that the dose to a MEMBER OF THE PUBLIC from I-131, I-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 (see ODCM Figure 10-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: Less than or equal to 15 mrem to any organ.

2.2 Measurements and Approximation of Total Radioactivity The following noble gases are specifically considered in evaluating gaseous effluents:

KR-87 XE-133 KR-88 XE-135 XE-133M XE-138 The following radioiodines and radioactive materials in particulate form are specifically considered in evaluating gaseous effluents:

MN-54 MO-99 FE-59 I-131 CO-58 CS-134 CO-60 CS-137 ZN-65 CE-141 SR-89 CE-144 SR-90 H-3 2.2.1 Sample collection and Analysis Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system utilizing high resolution germanium detectors. Samples are obtained and analyzed in accordance with ODCM Table 3-3. Isotopic values thus obtained are used for release rate calculations as specified in ODCM 3.4.2 and ODCM 3.4.3. Only those nuclides which are detected are used in calculations. For radioiodines and particulates, in addition to the nuclides listed above other nuclides with half-lives greater than 8 days which are identified are also considered.

Continuous Releases: Continuous sampling is performed on the continuous release points (i.e. the Plant Vent Stack, Containment Purge when in continuous mode, and the Turbine Building Vent).

Particulate material is collected by filtration. At least weekly, these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters.

Particulate filters are then analyzed for gross alpha and strontium as required. All gross alpha, Sr-89 and Sr-90 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis.

Batch Releases: The processing of batch type releases (from Containment when in batch mode, or Waste Gas Decay Tanks) is analogous to continuous releases, except that the release is not commenced until samples have been obtained and analyzed. Containment Purge batch releases were commenced at FNP beginning in 2006 in order to take advantage of additional decay time for short lived radionuclides.

Typically achieved minimum detectable concentrations for gaseous effluent sample analyses are reported in Table 2-6.

2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:

2.2.2.1 Fission and Activation Gases The released radioactivity is determined using sample analyses results collected as described in section 2.2.1 and the average release flow rates over the period represented by the collected sample.

Dose rates due to noble gases, radioiodines, tritium, and particulates are calculated (with computer assistance). The calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodine, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year.

Cumulative air doses are compared to the dose limits specified in ODCM 3.1.3. The current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.

2.2.2.2 Radioiodine, Tritium, and Particulate Releases Released quantities of radioiodines are determined using the weekly samples and release flow rates for the applicable release points. Radioiodine concentrations are determined by gamma spectroscopy.

Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the applicable release points. Gamma spectroscopy is used to quantify the concentrations of principal gamma emitters.

After each quarter, the particulate filters from each applicable vent (plant vent stack and containment purge) are combined, fused, and a strontium separation is performed. Since sample flows and vent flows are almost constant over each quarterly period the filters from each vent can be dissolved together. Decay corrections are performed back to the middle of the quarterly collection period. If Sr-89 or Sr-90 is not detected, MDCs are calculated. Strontium concentrations are input into the composite file of the computer and used for release dose rate and individual dose calculations.

Tritium samples are obtained monthly from the Plant Vent Stack, the Containment Purge when in batch mode, and the Turbine Building Vent (and weekly for Containment Purge when in continuous mode) by passing the sample stream through a cold trap or by using the bubble method. The grams of water vapor/cubic meter are measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed onsite and the results furnished in µCi/ml of water. The tritium concentration in water is converted to the tritium concentration in air and this value is input into the composite file of the computer and used in release, dose rate, and individual dose calculations.

Dose rates due to radioiodine, tritium and particulates are calculated for a hypothetical child exposed to the inhalation pathway at the location in the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated, for each release point for each release period, and the dose rates from each release point is compared to the dose rate limits specified in ODCM 3.1.2, allocated for each release point as described in ODCM 3.3.2.

Doses to a Member of the Public (individual doses) due to radioiodine, tritium and particulates are calculated for the controlling receptor, which is described in the ODCM. Individual doses are calculated for each release period, and cumulative totals are kept for each unit, for the current calendar quarter and year. Cumulative individual doses are compared to the dose limits specified in ODCM 3.1.4. The current percent of ODCM limits are shown on the printout for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters, for each week for gross alpha activity in a proportional counter. The highest concentration calculated for any of these weeks is used for the monthly value. This value is input into the composite file of the computer and used for release calculations.

2.2.3 Total Error Estimation The maximum errors associated with monitor readings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedure are collectively estimated to be:

Fission and Activation Gases Iodine Particulates Tritium 75% 60% 50% 45%

The average error associated with counting is estimated to be:

Fission and Activation Gases Iodine Particulates Tritium 19% 28% 20% 8%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 1B and 1C are found in this report as Tables 2-1A, 2-1B, 2-1C, 2-2A, 2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data are presented on a quarterly basis as required by Regulatory Guide 1.21.

To complete Tables 2-1A and 2-1B, the total release for each of the four categories (fission and activation gases, radioiodines, particulates and tritium) was divided by the number of seconds in the quarter to obtain a release rate in µCi/second for each category. However, the percent of the ODCM limits are not applicable because FNP has no curie limit for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases and due to radioiodines, tritium and particulate releases were calculated as part of the pre-release and post-release permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Tables 2-1A, 2-1B and 2-1C as curies released in each quarter.

Limits for cumulative beta and gamma air doses due to noble gases are presented in Tables 2-4A and 2-4B along with the percent of ODCM limits.

Limits for cumulative doses to an individual due to radioiodines, tritium and particulates are specified in ODCM 3.1.4. Cumulative individual doses are presented in Tables 2-5A and 2-5B along with percent of ODCM limits.

2.4 Radiological Impact Due to Gaseous Releases The air doses due to noble gases and doses to a Member of the Public due to radioiodines, tritium and particulates in gaseous effluents for Units 1 and 2 are provided in the following tables in order to show conformance with the limits of ODCM 3.1.3 and ODCM 3.1.4:

Unit 1 2019 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2019 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4B Unit 1 2019 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5A Unit 2 2019 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5B 2.5 Gaseous Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables:

Unit 1 2019 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2019 Gaseous Effluents - Batch Release Summary: Table 2-7B 2.6 Gaseous Effluents - Abnormal Releases There were no abnormal releases on Unit 1 or Unit 2 during 2019.

Abnormal release information for Units 1 and 2 is summarized in the following tables:

Unit 1 2019 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2019 Gaseous Effluents - Abnormal Release Summary: Table 2-8B Table 2-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 4.01E-01 4.09E-01 2.98E-01 1.02E+00

2. Average Release rate for period uCi/sec 5.08E-02 5.19E-02 3.77E-02 1.29E-01

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 0.00E+00 8.49E-05 0.00E+00 5.95E-06

2. Average Release rate for period uCi/sec 0.00E+00 1.08E-05 0.00E+00 7.55E-07

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 1.63E-07 4.37E-07 2.46E-08 7.19E-07

2. Average Release rate for period uCi/sec 2.07E-08 5.54E-08 3.12E-09 9.115E-08

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 4.90E+00 1.87E+00 4.39E+00 2.99E+00

2. Average Release rate for period uCi/sec 6.21E-01 2.37E-01 5.57E-01 3.79E-01

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 1.93E-06 5.94E-07 1.32E-06 8.91E-07

2. Average Release rate for period uCi/sec 2.45E-07 7.53E-08 1.68E-07 1.13E-07

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Table 2-1B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.25E+00 1.39E-01 2.92E+00 1.52E+00

2. Average Release rate for period uCi/sec 1.58E-01 1.76E-02 3.70E-01 1.93E-01

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 0.00E+00 6.96E-07 0.00E+00 0.00E+00

2. Average Release rate for period uCi/sec 0.00E+00 8.83E-08 0.00E+00 0.00E+00

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 0.00E+00 1.11E-07 6.11E-08 0.00E+00

2. Average Release rate for period uCi/sec 0.00E+00 1.40E-08 7.75E-09 0.000E+00

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 2.91E+00 2.63E+00 2.94E+00 3.22E+00

2. Average Release rate for period uCi/sec 3.69E-01 3.33E-01 3.73E-01 4.09E-01

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 1.44E-06 4.36E-07 8.15E-07 5.12E-07

2. Average Release rate for period uCi/sec 1.83E-07 5.54E-08 1.03E-07 6.49E-08

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Table 2-1C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.65E+00 5.48E-01 3.21E+00 2.54E+00

2. Average Release rate for period uCi/sec 2.09E-01 6.95E-02 4.08E-01 3.22E-01

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 0.00E+00 8.56E-05 0.00E+00 5.95E-06

2. Average Release rate for period uCi/sec 0.00E+00 1.09E-05 0.00E+00 7.55E-07

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 1.63E-07 5.47E-07 8.57E-08 7.19E-07

2. Average Release rate for period uCi/sec 2.07E-08 6.94E-08 1.09E-08 9.115E-08

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 7.81E+00 4.49E+00 7.33E+00 6.21E+00

2. Average Release rate for period uCi/sec 9.90E-01 5.70E-01 9.30E-01 7.88E-01

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 3.37E-06 1.03E-06 2.14E-06 1.40E-06

2. Average Release rate for period uCi/sec 4.28E-07 1.31E-07 2.71E-07 1.78E-07

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 0.00E+00 0.00E+00 6.51E-02 2.01E-01 Total For Period Curies 0.00E+00 0.00E+00 6.51E-02 2.01E-01 Iodines I-131 Curies 0.00E+00 4.06E-06 0.00E+00 4.45E-06 I-133 Curies 0.00E+00 8.09E-05 0.00E+00 0.00E+00 Total For Period Curies 0.00E+00 8.49E-05 0.00E+00 4.45E-06 Particulates Cr-51 Curies 0.00E+00 0.00E+00 0.00E+00 1.40E-07 Co-58 Curies 0.00E+00 0.00E+00 0.00E+00 1.57E-07 Co-60 Curies 0.00E+00 0.00E+00 0.00E+00 1.69E-07 Sr-89 Curies 1.63E-07 4.37E-07 6.50E-09 3.87E-09 Zr-95 Curies 0.00E+00 0.00E+00 0.00E+00 9.29E-08 Nb-95 Curies 0.00E+00 0.00E+00 0.00E+00 1.51E-07 Eu-155 Curies 0.00E+00 0.00E+00 1.81E-08 0.00E+00 Total For Period Curies 1.63E-07 4.37E-07 2.46E-08 7.14E-07 Tritium H-3 Curies 4.76E+00 1.75E+00 4.35E+00 2.96E+00 Gross Alpha G-Alpha Curies 1.93E-06 5.94E-07 1.32E-06 8.91E-07 Total For Period Curies 1.93E-06 5.94E-07 1.32E-06 8.91E-07 Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 3.99E-01 4.09E-01 2.32E-01 4.96E-01 Kr-85M Curies 0.00E+00 0.00E+00 0.00E+00 1.39E-03 Kr-87 Curies 0.00E+00 0.00E+00 0.00E+00 4.21E-04 Kr-88 Curies 0.00E+00 0.00E+00 0.00E+00 1.58E-03 Xe-131M Curies 0.00E+00 0.00E+00 0.00E+00 2.71E-03 Xe-133M Curies 0.00E+00 0.00E+00 0.00E+00 3.94E-03 Xe-133 Curies 1.97E-03 6.62E-04 2.66E-05 2.57E-01 Xe-135 Curies 0.00E+00 0.00E+00 0.00E+00 5.25E-02 Total For Period Curies 4.01E-01 4.09E-01 2.32E-01 8.16E-01 Iodines I-131 Curies 0.00E+00 0.00E+00 0.00E+00 3.92E-07 I-133 Curies 0.00E+00 0.00E+00 0.00E+00 1.11E-06 I-135 Curies 0.00E+00 0.00E+00 0.00E+00 2.69E-07 Total For Period Curies 0.00E+00 0.00E+00 0.00E+00 1.77E-06 Particulates Co-58 Curies 0.00E+00 0.00E+00 0.00E+00 4.33E-09 Total For Period Curies 0.00E+00 0.00E+00 0.00E+00 4.33E-09 Tritium H-3 Curies 1.39E-01 1.15E-01 3.56E-02 2.99E-02 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 0.00E+00 0.00E+00 2.57E+00 1.32E+00 Xe-133 Curies 7.16E-01 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 7.16E-01 0.00E+00 2.57E+00 1.32E+00 Iodines I-131 Curies 0.00E+00 6.90E-07 0.00E+00 0.00E+00 Total For Period Curies 0.00E+00 6.90E-07 0.00E+00 0.00E+00 Particulates Co-58 Curies 0.00E+00 1.05E-07 0.00E+00 0.00E+00 Sr-89 Curies 0.00E+00 5.05E-09 6.11E-08 0.00E+00 Total For Period Curies 0.00E+00 1.11E-07 6.11E-08 0.00E+00 Tritium H-3 Curies 2.88E+00 2.62E+00 2.85E+00 3.19E+00 Gross Alpha G-Alpha Curies 1.44E-06 4.36E-07 8.15E-07 5.12E-07 Total For Period Curies 1.44E-06 4.36E-07 8.15E-07 5.12E-07

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 5.32E-01 1.34E-01 3.51E-01 2.02E-01 Xe-133 Curies 0.00E+00 4.38E-03 1.02E-04 0.00E+00 Total For Period Curies 5.32E-01 1.39E-01 3.51E-01 2.02E-01 Iodines I-131 Curies 0.00E+00 5.62E-09 0.00E+00 0.00E+00 Total For Period Curies 0.00E+00 5.62E-09 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 3.21E-02 8.35E-03 9.29E-02 3.40E-02 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 0.00E+00 0.00E+00 2.63E+00 1.52E+00 Xe-133 Curies 7.16E-01 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 7.16E-01 0.00E+00 2.63E+00 1.52E+00 Iodines I-131 Curies 0.00E+00 4.75E-06 0.00E+00 4.45E-06 I-133 Curies 0.00E+00 8.09E-05 0.00E+00 0.00E+00 Total For Period Curies 0.00E+00 8.56E-05 0.00E+00 4.45E-06 Particulates Cr-51 Curies 0.00E+00 0.00E+00 0.00E+00 1.40E-07 Co-58 Curies 0.00E+00 1.05E-07 0.00E+00 1.57E-07 Co-60 Curies 0.00E+00 0.00E+00 0.00E+00 1.69E-07 Sr-89 Curies 1.63E-07 4.42E-07 6.76E-08 3.87E-09 Zr-95 Curies 0.00E+00 0.00E+00 0.00E+00 9.29E-08 Nb-95 Curies 0.00E+00 0.00E+00 0.00E+00 1.51E-07 Eu-155 Curies 0.00E+00 0.00E+00 1.81E-08 0.00E+00 Total For Period Curies 1.63E-07 5.47E-07 8.57E-08 7.14E-07 Tritium H-3 Curies 7.64E+00 4.37E+00 7.20E+00 6.15E+00 Gross Alpha G-Alpha Curies 3.37E-06 1.03E-06 2.14E-06 1.40E-06 Total For Period Curies 3.37E-06 1.03E-06 2.14E-06 1.40E-06 Table 2-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 9.30E-01 5.43E-01 5.83E-01 6.99E-01 Kr-85M Curies 0.00E+00 0.00E+00 0.00E+00 1.39E-03 Kr-87 Curies 0.00E+00 0.00E+00 0.00E+00 4.21E-04 Kr-88 Curies 0.00E+00 0.00E+00 0.00E+00 1.58E-03 Xe-131M Curies 0.00E+00 0.00E+00 0.00E+00 2.71E-03 Xe-133M Curies 0.00E+00 0.00E+00 0.00E+00 3.94E-03 Xe-133 Curies 1.97E-03 5.04E-03 1.28E-04 2.57E-01 Xe-135 Curies 0.00E+00 0.00E+00 0.00E+00 5.25E-02 Total For Period Curies 9.32E-01 5.48E-01 5.83E-01 1.02E+00 Iodines I-131 Curies 0.00E+00 5.62E-09 0.00E+00 3.92E-07 I-133 Curies 0.00E+00 0.00E+00 0.00E+00 1.11E-06 I-135 Curies 0.00E+00 0.00E+00 0.00E+00 2.69E-07 Total For Period Curies 0.00E+00 5.62E-09 0.00E+00 1.77E-06 Particulates Co-58 Curies 0.00E+00 0.00E+00 0.00E+00 4.33E-09 Total For Period Curies 0.00E+00 0.00E+00 0.00E+00 4.33E-09 Tritium H-3 Curies 1.71E-01 1.24E-01 1.28E-01 6.39E-02 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Table 2-4A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of ODCM Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Radiation Lmt Gamma Air 5.00E+00 mRad 1.27E-04 2.54E-03 1.30E-04 2.60E-03 9.48E-05 1.90E-03 2.30E-04 4.59E-03 Beta Air 1.00E+01 mRad 4.49E-05 4.49E-04 4.59E-05 4.59E-04 3.34E-05 3.34E-04 9.27E-05 9.27E-04 Cumulative Doses Per Year Type of ODCM Units Year to End Date % ODCM Receptor Limit Radiation Lmt Gamma Air 1.00E+01 mRad 5.82E-04 5.82E-03 Site Boundary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.00E+01 mRad 2.17E-04 1.08E-03 Site Boundary SSE Mixed Mode R Air Dose Beta Annual Table 2-4B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of ODCM Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Radiation Lmt Gamma Air 5.00E+00 mRad 1.78E-04 3.56E-03 4.28E-05 8.56E-04 9.29E-04 1.86E-02 4.84E-04 9.68E-03 Beta Air 1.00E+01 mRad 8.55E-05 8.55E-04 1.52E-05 1.52E-04 3.28E-04 3.28E-03 1.71E-04 1.71E-03 Cumulative Doses Per Year Type of ODCM Units Year to End Date % ODCM Receptor Limit Radiation Lmt Gamma Air 1.00E+01 mRad 1.63E-03 1.63E-02 Site Boundary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.00E+01 mRad 5.99E-04 3.00E-03 Site Boundary SSE Mixed Mode R Air Dose Beta Annual Table 2-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM GI-Lli 7.50E+00 mRem 6.70E-04 8.93E-03 2.56E-04 3.41E-03 6.00E-04 8.01E-03 4.10E-04 5.47E-03 Bone 7.50E+00 mRem 1.98E-06 2.64E-05 5.75E-06 7.67E-05 7.90E-08 1.05E-06 1.59E-06 2.11E-05 Liver 7.50E+00 mRem 6.70E-04 8.93E-03 2.56E-04 3.41E-03 6.00E-04 8.01E-03 4.10E-04 5.47E-03 Total Body 7.50E+00 mRem 6.70E-04 8.93E-03 2.56E-04 3.41E-03 6.00E-04 8.01E-03 4.10E-04 5.47E-03 Thyroid 7.50E+00 mRem 6.70E-04 8.93E-03 3.59E-04 4.78E-03 6.00E-04 8.01E-03 4.98E-04 6.64E-03 Lung 7.50E+00 mRem 6.70E-04 8.93E-03 2.56E-04 3.41E-03 6.00E-04 8.01E-03 4.10E-04 5.47E-03 Kidney 7.50E+00 mRem 6.70E-04 8.93E-03 2.56E-04 3.42E-03 6.00E-04 8.01E-03 4.10E-04 5.47E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date % ODCM Receptor Limit Lmt GI-Lli 1.500E+01 mRem 1.937E-03 1.291E-02 Gas Controlling Receptor Iodine/Part Dose Annual Bone 1.500E+01 mRem 9.399E-06 6.266E-05 Gas Controlling Receptor Iodine/Part Dose Annual Liver 1.500E+01 mRem 1.937E-03 1.291E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body 1.500E+01 mRem 1.937E-03 1.291E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid 1.500E+01 mRem 2.127E-03 1.418E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung 1.500E+01 mRem 1.936E-03 1.291E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney 1.500E+01 mRem 1.937E-03 1.291E-02 Gas Controlling Receptor Iodine/Part Dose Annual Table 2-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Lung 7.50E+00 mRem 3.98E-04 5.31E-03 3.59E-04 4.79E-03 4.02E-04 5.36E-03 4.41E-04 5.88E-03 Thyroid 7.50E+00 mRem 3.98E-04 5.31E-03 3.72E-04 4.96E-03 4.02E-04 5.36E-03 4.41E-04 5.88E-03 GI-Lli 7.50E+00 mRem 3.98E-04 5.31E-03 3.59E-04 4.79E-03 4.02E-04 5.36E-03 4.41E-04 5.88E-03 Bone 7.50E+00 mRem 0.00E+00 0.00E+00 1.17E-07 1.55E-06 7.43E-07 9.91E-06 0.00E+00 0.00E+00 Liver 7.50E+00 mRem 3.98E-04 5.31E-03 3.59E-04 4.79E-03 4.02E-04 5.36E-03 4.41E-04 5.88E-03 Kidney 7.50E+00 mRem 3.98E-04 5.31E-03 3.59E-04 4.79E-03 4.02E-04 5.36E-03 4.41E-04 5.88E-03 Total Body 7.50E+00 mRem 3.98E-04 5.31E-03 3.59E-04 4.79E-03 4.02E-04 5.36E-03 4.41E-04 5.88E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date % ODCM Receptor Limit Lmt Lung 1.500E+01 mRem 1.600E-03 1.067E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid 1.500E+01 mRem 1.612E-03 1.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli 1.500E+01 mRem 1.600E-03 1.067E-02 Gas Controlling Receptor Iodine/Part Dose Annual Bone 1.500E+01 mRem 8.595E-07 5.730E-06 Gas Controlling Receptor Iodine/Part Dose Annual Liver 1.500E+01 mRem 1.600E-03 1.067E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney 1.500E+01 mRem 1.600E-03 1.067E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body 1.500E+01 mRem 1.600E-03 1.067E-02 Gas Controlling Receptor Iodine/Part Dose Annual TABLE 2-6 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS EFFLUENT ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

Nuclide MDC(uCi/ML) Nuclide MDC(uCi/ML)

MN-54 3.32E-13 KR-87 4.69E-08 CO-58 2.31E-13 KR-88 4.32E-08 FE-59 3.97E-13 XE-133 3.37E-08 CO-60 4.30E-13 XE-133M 1.33E-07 ZN-65 6.59E-13 XE-135 1.58E-08 MO-99 1.44E-12 XE-138 6.87E-08 CS-134 1.67E-13 I-131 2.15E-13 CS-137 1.45E-13 I-133 3.85E-13 CE-141 2.06E-13 CE-144 6.78E-13 Table 2-7A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 95 92 54 95 336

2. Total time period for batch releases ( Minutes ) 4.48E+03 4.05E+03 8.71E+03 1.07E+04 2.80E+04

3. Maximum time period for a batch release ( Minutes ) 2.05E+02 1.15E+02 9.18E+02 1.08E+03 1.08E+03

4. Average time period for a batch release ( Minutes ) 4.72E+01 4.40E+01 1.61E+02 1.13E+02 8.33E+01

5. Minimum time period for a batch release ( Minutes ) 1.00E+00 1.00E+00 1.00E+00 4.00E+00 1.00E+00 Table 2-7B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 59 39 28 44 170

2. Total time period for batch releases ( Minutes ) 2.98E+03 4.17E+03 1.66E+03 2.13E+03 1.09E+04

3. Maximum time period for a batch release ( Minutes ) 4.08E+02 4.41E+02 2.58E+02 1.60E+02 4.41E+02

4. Average time period for a batch release ( Minutes ) 5.05E+01 1.07E+02 5.94E+01 4.83E+01 6.43E+01

5. Minimum time period for a batch release ( Minutes ) 2.00E+00 4.00E+00 3.00E+00 3.00E+00 2.00E+00 Table 2-8A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Table 2-8B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.0 SOLID WASTE 3.1 Regulatory Requirements 3.1.1 Solid Radioactive Waste System FNP-0-M-30, PROCESS CONTROL PROGRAM, step B.3.1 states that the radwaste solidification system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

3.1.2 Reporting Requirements FNP-0-M-30, PROCESS CONTROL PROGRAM, step B.5.1 states that the Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specifications 5.6.2 and 5.6.3, shall include a summary of the quantities of solid radwaste released from the units as outlined in Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 2, issued June 2009 , with data summarized on an annual basis following the format of Table A-3 thereof.

3.2 Solid Waste Data Regulatory Guide 1.21 Revision 2 Table A-3 is found in the report as Table 3-1.

TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 SOLID RADIOACTIVE WASTE SHIPPED FOR PROCESSING OR DISPOSAL Starting 01-Jan-2019 Ending 31-Dec-2019 Resins, Filters, and Volume Curies Shipped Evaporator Bottoms Waste Class ft3 m3 A 2.42E+01 6.84E-01 1.01E+00 B 1.45E+02 4.11E+00 1.54E+02 C 2.75E+01 7.79E-01 2.81E+00 Unclassified 3.29E+01 9.31E-01 2.73E+01 ALL 1.97E+02 5.57E+00 1.58E+02 Major Nuclides for the Above Table:

Waste Class A: C-14 2.1% Be-7 1.04% Co-58 20.14% Co-60 25.21% Fe-55 21.98%

Ni-63 8.18% Sb-125 1.02% Cr-51 9.9% Zr-95 2.88% Nb-95 4.74%

Waste Class B: Fe-55 8.35% Co-60 43.66% Ni-63 42.59% Sb-125 2.6%

Waste Class C: C-14 3.62% Fe-55 38.95% Co-58 4.43% Co-60 37.04%

Ni-63 7.68% Sb-125 1.23% Zr-95 1.17% Nb-95 2.2%

Unclassified: H-3 2.29% C-14 7.3% Fe-55 51.7% Co-58 1.76%

Ni-63 9.95% Nb-95 1.15% Sb-125 1.26% Co-60 22.45%

ALL: C-14 1.59% Fe-55 15.28% Co-60 40.33% Ni-63 37.01%

Sb-125 2.37%

Dry Active Waste Volume Curies Shipped Waste Class ft3 m3 A 1.96E+04 5.55E+02 1.91E+00 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 ALL 1.96E+04 5.55E+02 1.91E+00 Major Nuclides for the Above Table:

Waste Class A: H-3 13.15% Sb-125 1.19% Cr-51 3.98% Fe-55 10.82%

Co-58 12.09% Co-60 12.53% Ni-63 10.6% Zr-95 12.53%

Nb-95 16.7% Tc-99 2.9%

Waste Class B N/A Waste Class C N/A ALL: H-3 13.15% Sb-125 1.19% Cr-51 3.98% Fe-55 10.82%

Co-58 12.09% Co-60 12.53% Ni-63 10.6% Zr-95 12.53%

Nb-95 16.7% Tc-99 2.9%

Irradiated Components Volume Curies Shipped Waste Class ft 3 m 3 A 0.00E+00 0.00E+00 0.00E+00 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 ALL 0.00E+00 0.00E+00 0.00E+00 Major Nuclides for the Above Table:

(Continued)

Other Waste Volume Curies Shipped Waste Class ft3 m3 A 0.00E+00 0.00E+00 0.00E+00 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 ALL 0.00E+00 0.00E+00 0.00E+00 Major Nuclides for the Above Table:

Waste Class A: N/A Waste Class B: N/A Waste Class C: N/A ALL: N/A Sum of All Low-Level Volume Curies Shipped Waste Shipped from Site Waste Class ft3 m3 A 1.96E+04 5.56E+02 2.92E+00 B 1.45E+02 4.11E+00 1.54E+02 C 2.75E+01 7.79E-01 2.81E+00 Unclassified 3.29E+01 9.31E-01 2.73E+01 ALL 1.98E+04 5.61E+02 1.60E+02 Major Nuclides for the Above Table:

Waste Class A: H-3 8.58% Cr-51 6.04% Ni-63 9.76% Co-58 14.89%

Co-60 16.93% Fe-55 14.7% Zr-95 9.18% Nb-95 12.55%

Sb-125 1.13% Tc-99 1.92%

Waste Class B: Fe-55 8.35% Co-60 43.66% Ni-63 42.59% Sb-125 2.6%

Waste Class C : Sb-125 1.23% C-14 3.62% Fe-55 38.95% Co-58 4.43%

Co-60 37.04% Ni-63 7.68% Zr-95 1.17% Nb-95 2.2%

Unclassified H-3 2.29% C-14 7.3% Fe-55 51.7% Co-58 1.76%

Co-60 22.45% Ni-63 9.59% Nb-95 1.15% Sb-125 1.26%

ALL: C-14 1.58% Fe-55 15.24% Sb-125 2.36% Co-60 40.05%

Ni-63 36.74%

4.0 DOSES TO MEMBERS OF THE PUBLIC INSIDE THE SITE BOUNDARY 4.1 Regulatory Requirements Current FNP effluent controls as established by ODCM 6.1 do not require assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (ODCM Figure 10-1).

4.2 Demonstration of Compliance However, this assessment has been performed for 2019 using the methods described in ODCM 6.2 and is included in this section as Table 4-1.

Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Unit: Site Location Name: Visitor Center Distance (kilometers): 3.06E-01 Sector: N Occupancy Factor: 1.37E-03 Age Group: Child Mixed Mode Release Noble Gas X/Q (sec/m3): 8.80E-06 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 8.80E-06 D/Q (m-2): 6.20E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 1.04E-04 D/Q (m-2): 4.80E-07 Ground Level Release Noble Gas X/Q (sec/m3): 1.04E-04 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Liver mRem 3.35E-08 1.93E-08 3.14E-08 2.67E-08 1.11E-07 Thyroid mRem 3.35E-08 2.08E-08 3.14E-08 2.70E-08 1.13E-07 Bone mRem 3.74E-13 1.56E-11 1.55E-13 1.04E-10 1.20E-10 Total Body mRem 3.35E-08 1.93E-08 3.14E-08 2.67E-08 1.11E-07 Skin mRem 1.10E-16 1.04E-11 4.57E-17 1.21E-10 1.32E-10 Kidney mRem 3.35E-08 1.93E-08 3.14E-08 2.67E-08 1.11E-07 Lung mRem 3.35E-08 1.93E-08 3.14E-08 2.67E-08 1.11E-07 GI-Lli mRem 3.35E-08 1.93E-08 3.14E-08 2.67E-08 1.11E-07 Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Unit: Site Location Name: Service Water Pond Distance (kilometers): 9.66E-01 Sector: N Occupancy Factor: 7.57E-03 Age Group: Child Mixed Mode Release Noble Gas X/Q (sec/m3): 9.75E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 9.75E-07 D/Q (m-2): 2.78E-08 Ground Level Release Noble Gas X/Q (sec/m3): 4.74E-05 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 4.74E-05 D/Q (m-2): 1.31E-07 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Total Body mRem 2.05E-08 1.18E-08 1.92E-08 1.66E-08 6.81E-08 Liver mRem 2.05E-08 1.18E-08 1.92E-08 1.66E-08 6.81E-08 Thyroid mRem 2.05E-08 1.27E-08 1.92E-08 1.68E-08 6.92E-08 Skin mRem 2.73E-16 2.58E-11 1.13E-16 3.00E-10 3.26E-10 Kidney mRem 2.05E-08 1.18E-08 1.92E-08 1.66E-08 6.81E-08 Lung mRem 2.05E-08 1.18E-08 1.92E-08 1.66E-08 6.81E-08 GI-Lli mRem 2.05E-08 1.18E-08 1.92E-08 1.66E-08 6.81E-08 Bone mRem 2.29E-13 2.56E-11 9.50E-14 2.56E-10 2.82E-10 Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Unit: Site Location Name: River Water Discharge - Air Distance (kilometers): 1.64E+00 Sector: N Occupancy Factor: 1.14E-02 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3): 1.63E-05 Mixed Mode Release Noble Gas X/Q (sec/m3): 7.05E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 7.05E-07 D/Q (m-2): 1.39E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 1.63E-05 D/Q (m-2): 4.55E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Kidney mRem 2.23E-08 1.29E-08 2.10E-08 1.79E-08 7.41E-08 Skin mRem 2.05E-16 1.95E-11 8.52E-17 2.26E-10 2.46E-10 Lung mRem 2.23E-08 1.29E-08 2.10E-08 1.79E-08 7.41E-08 GI-Lli mRem 2.23E-08 1.29E-08 2.10E-08 1.79E-08 7.41E-08 Total Body mRem 2.23E-08 1.29E-08 2.10E-08 1.79E-08 7.41E-08 Liver mRem 2.23E-08 1.29E-08 2.10E-08 1.79E-08 7.41E-08 Thyroid mRem 2.23E-08 1.39E-08 2.10E-08 1.82E-08 7.53E-08 Bone mRem 2.49E-13 2.08E-11 1.03E-13 1.93E-10 2.14E-10 5.0 TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190) 5.1 Regulatory Requirements Technical Specification 5.5.4.j states that the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem (as stated in ODCM 5.1).

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM 2.1.3, 3.1.3, or 3.1.4, calculations shall be made according to ODCM 5.2 methods to determine whether the above (ODCM 5.1) limits have been exceeded (as stated in ODCM 5.1.2).

5.2 Demonstration of Compliance Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded during 2019, no calculations were required.

6.0 METEOROLOGICAL DATA Meteorological data are retained onsite; these data are available to the NRC upon request. The meteorological data include annual summaries of hourly measurements of wind speed, wind direction and atmospheric stability in the form of joint frequency distribution tables.

7.0 PROGRAM DEVIATIONS 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the Annual Radioactive Effluent Release Report (the report) shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1 of the ODCM. The report must also include an explanation as to why the inoperability was not corrected in a timely manner.

7.1.2 Description of Deviations

1. Unit 2, R60C Main steam line radiation monitor OOS for greater than 30 days due to a slave link fault.

This is a new monitor that required vendor support and long lead time parts to repair.

2. Unit-1 RE-23B was declared inoperable on 6/27/19. Thirty days later (7/27/19), the rad-monitor (SGBD dilution radiation monitor) was still not restored to operable status as required by the ODCM. This was discovered to be a power supply issue. No replacement parts were available within the required time frame.

7.2 Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include deviations from the MDC requirements included in ODCM Tables 2-3 and 3-3.

7.2.2 Description of Deviations There were no deviations during 2019.

7.3 Incorrect Compositing of Liquid or Gaseous Effluent Samples 7.3.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include deviations from composite sampling requirements included in ODCM Tables 2-3 and 3-3.

7.3.2 Description of Deviations There were no deviations during 2019.

8.0 CHANGES TO THE PLANT FARLEY ODCM 8.1 Regulatory Requirements Pursuant to Technical Specification 5.5.1.c and ODCM 7.2.2.5, licensee initiated changes to the ODCM shall be submitted to the Nuclear Regulatory Commission as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period in which any changes were made. Included are changes to the radiological environmental monitoring program sampling locations or dose calculation locations or pathways, including any changes made pursuant to ODCM 4.1.2.2.2 (land use census).

8.2 Description of Changes No ODCM changes made during 2019 9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR SOLID RADWASTE TREATMENT SYSTEMS 9.1 Regulatory Requirements ODCM 7.2.2.7 states in part that, as required by ODCM 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluents Release Report covering the period in which the change was reviewed and accepted for implementation.

Process Control Program (PCP) B.5.1.2 states that licensee initiated major changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report for the period in which the change was implemented. The discussion of each change shall include the information specified in PCP B.4.1.

9.2 Description of Major Changes Changes to the Process Control Program during 2019:

LDCR19-040

1. Added statement to clarify the PCP purpose applies to waste processed on-site and shipped directly to a disposal facility.

2. Removed vendor procedure embeds and referenced those by title. The PCP directs use of those procedures which are approved by the Vendor Procedure Approval Process.

3. Added Vendor Procedure to references for Dewatering Bead Resin and Activated carbon and added PCP guidance to direct used of this procedure.

4. Added NEI 07-010A, Engineering Test Instruction & Test Report, and CNS Topical Report for dewatering process contains to references.

Justification:

1. NEI 07.010A PCP Template which is approved by the NRC states the PCP does not apply to radwaste shipments sent to vendors for processing instead of directly to a disposal facility.

This is consistent with SNC Fleet and the Industry.

2. The Vendor Procedure Approval Process Is the correct method to get Vendor Procedures into Documentum.

3. Procedure for Dewatering Bead Resin & Activated Carbon needed to be added to the PCP.

4. NEI 07-010A Is a generic guidance document for PCP development. Other references added as background documents that demonstrate compliance with 10CFR61 requirements

Farley Nuclear Plant Appendix A 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.

As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of principal radionuclides in gaseous effluents have changed, and C-14 has become a larger percentage. Principal radionuclides are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21), Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, the NRC recommended re-evaluating principal radionuclides and reporting C-14 as appropriate.

In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants started reporting C-14 amounts released and resulting doses to the maximally exposed member of the public.

Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation. The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents.

Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.

At Plant Farley, the annual quantity of C-14 released in gaseous effluents was estimated to be 9.28 Curies (per unit). Approximately 30% of the C-14 released is in the form of 14CO 2 and is incorporated into plants through photosynthesis. Ingestion dose results from this pathway. The remaining 70% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Farley ODCM, the resulting bone dose to a child located at the controlling receptor location would be 4.11E-01 mrem in a year which is 2.74% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents. The resulting total body dose to a child located at the controlling receptor location would be 8.21E-02 mrem in a year which is 0.54% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.

Farley Nuclear Plant Appendix B Correction to 2018 Annual Radioactive Effluent Release Report: N/A NL-20-0419 Edwin I. Hatch Nuclear Plant - Units 1&2 Joseph M. Farley Nuclear Plant - Units 1&2 Vogtle Electric Generating Plant - Units 1&2 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2019 Enclosure 6 Vogtle Electric Generating Plant - Units 1&2 Annual Radioactive Effluent Release Report for 2019

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1, 2019 TO DECEMBER 31, 2019 Page 1 of 81

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Requirements 8 1.1.1 Concentration Limits 8 1.1.2 Dose Limits 8 1.2 Effluent Concentration Limit (ECL) 8 1.3 Measurements and Approximations of Total Radioactivity 9 1.3.1 Total Radioactivity Determination 9 1.3.2 Total Error Estimation 11 1.4 Liquid Effluent Release Data 12 1.5 Radiological Impact Due to Liquid Releases 12 1.6 Liquid Effluents - Batch Releases 12 1.7 Liquid Effluents - Abnormal Releases 12 Table 1-1A Liquid Effluents - Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 13 Table 1-1B Liquid Effluents - Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 14 Table 1-1C Liquid Effluents - Summation of All Releases Site (Quarters 1,2,3, and 4) 15 Table 1-2A Liquid Effluents -Unit 1 (Quarters 1,2,3, and 4) 16 Page 2 of 81

Table 1-2B Liquid Effluents -Unit 2 (Quarters 1,2,3, and 4) 19 Table 1-2C Liquid Effluents -Site (Quarters 1,2,3, and 4) 21 Table 1-3A Doses to a Member of the Public Due to Liquid Releases Unit 1 (Quarters 1,2,3, and 4) 24 Table 1-3B Doses to a Member of the Public Due to Liquid Releases Unit 2 (Quarters 1,2,3, and 4) 25 Table 1-3C Doses to a Member of the Public Due to Liquid Releases Site (Quarters 1,2,3, and 4) 26 Table 1-4 Minimum Detectable Concentration - Liquid 27 Table 1-5A Liquid Effluents Batch Release Summary Unit 1 (Quarters 1,2,3, and 4) 28 Table 1-5B Liquid Effluents Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 29 Table 1-5C Liquid Effluents Batch Release Summary Site (Quarters 1,2,3, and 4) 30 Table 1-6A Liquid Effluents Abnormal Release Summary Unit 1 (Quarters 1,2,3, and 4) 31 Table 1-6B Liquid Effluents Abnormal Release Summary Unit 2 (Quarters 1,2,3, and 4) 32 Table 1-6C Liquid Effluents Abnormal Release Summary Site (Quarters 1,2,3, and 4) 33 2.0 Gaseous Effluents 34 2.1 Regulatory Requirements 34 2.1.1 Dose Rate Limits 34 Page 3 of 81

2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 34 2.1.3 Doses to a Member of the Public 34 2.2 Measurements and Approximations of Total Radioactivity 35 2.2.1 Sample Collection and Analysis 35 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 36 2.2.2.1 Fission and Activation Gases 36 2.2.2.2 Radioiodines, Tritium and Particulate Releases 36 2.2.2.3 Gross Alpha Release 36 2.2.3 Total Error Estimation 37 2.3 Gaseous Effluent Release Data 38 2.4 Radiological Impact Due to Gaseous Releases 39 2.5 Gaseous Effluents - Batch Releases 39 2.6 Gaseous Effluents - Abnormal Releases 39 Table 2-1A Gaseous Effluents Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 40 Table 2-1B Gaseous Effluents Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 41 Table 2-1C Gaseous Effluents Summation of All Releases Site (Quarters 1,2,3, and 4) 42 Table 2-2A Gaseous Effluents Mixed Mode Releases Unit 1 (Quarters 1,2,3, and 4) 43 Table 2-2B Gaseous Effluents Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 45 Page 4 of 81

Table 2-2C Gaseous Effluents Mixed Mode Releases Site (Quarters 1,2,3, and 4) 47 Table 2-3A Gaseous Effluents Ground Level Releases Unit 1 (Quarters 1,2,3, and 4) 49 Table 2-3B Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 51 Table 2-3C Gaseous Effluents Ground Level Releases Site (Quarters 1,2,3, and 4) 53 Table 2-4A Gaseous Effluents Ground Level Releases Unit 1 (Quarters 1,2,3, and 4) 55 Table 2-4B Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 56 Table 2-4C Gaseous Effluents Ground Level Releases Site (Quarters 1,2,3, and 4) 57 Table 2-5A Gaseous Effluents Ground Level Releases Unit 1 (Quarters 1,2,3, and 4) 58 Table 2-5B Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 59 Table 2-5C Gaseous Effluents Ground Level Releases Site (Quarters 1,2,3, and 4) 60 Table 2-6 Minimum Detectable Concentrations - Gaseous 61 Table 2-7A Gaseous Effluents - Batch Release Summary Unit 1 (Quarters 1,2,3, and 4) 62 Page 5 of 81

Table 2-7B Gaseous Effluents - Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 63 Table 2-7C Gaseous Effluents - Batch Release Summary Site (Quarters 1,2,3, and 4) 64 Table 2-8A Gaseous Effluents - Abnormal Release Summary Unit 1 (Quarters 1,2,3, and 4) 65 Table 2-8B Gaseous Effluents - Abnormal Release Summary Unit 2 (Quarters 1,2,3, and 4) 66 Table 2-8C Gaseous Effluents - Abnormal Release Summary Site (Quarters 1,2,3, and 4) 67 3.0 Solid Waste 68 3.1 Regulatory Requirements 68 3.1.1 Solid Radioactive Waste System 68 3.1.2 Reporting Requirements 68 3.2 Solid Waste Data 68 Table 3-1 Solid Waste and Irradiated Fuel Shipments 69 4.0 Doses to Members of the Public Inside the Site Boundary 74 4.1 Regulatory Requirements 74 4.2 Demonstration of Compliance 74 Table 4-1 Doses to Members of the Public Due to Activities Inside the Site Boundary 75 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 77 5.1 Regulatory Requirements 77 5.2 Demonstration of Compliance 77 Page 6 of 81

6.0 Meteorological Data 77 7.0 Program Deviations 77 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 77 7.1.1 Regulatory Requirement 77 7.1.2 Description of Deviations 78 7.2 Tanks Exceeding Curie Content Limits 78 7.2.1 Regulatory Requirements 78 7.2.2 Description of Deviations 78 8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 78 8.1 Regulatory Requirements 78 8.2 Description of Changes 79 9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 79 9.1 Regulatory Requirements 79 9.2 Description of Major Changes 79 Appendix A Carbon-14 81 Page 7 of 81

1.0 Liquid Effluents 1.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2.

1.1.1 Concentration Limits In accordance with Technical Specification 5.5.4.b, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 E-04 µCi/ml total activity.

1.1.2 Dose Limits The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited as follows:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

1.2 Effluent Concentration Limit (ECL)

ECL values used for determining the allowable liquid radwaste release rates and concentrations for the principal gamma emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2.

For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 µCi/ml total activity.

For gross alpha in liquid radwaste, the ECL is 2 E-09 µCi/ml.

For all the above radionuclides or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B. The method utilizing the ECL fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.

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1.3 Measurements and Approximations of Total Radioactivity 1.3.1 Total Radioactivity Determination Prior to the release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) Table 2-3 Radioactive Liquid Waste Sampling and Analysis Program. A sample from each tank which is planned for release is analyzed for principal gamma emitters, I-131, and dissolved and entrained noble gases by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks, which are released. Liquid radwaste sample analyses are performed as follows:

MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.

2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gases with computerized data reduction

3. Tritium Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting (1)

5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting (1)

6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation Counting (1)

7. Ni-63 Quarterly Chemical separation Composite and liquid scintillation Counting (1)

(1) Analysis performed by an off-site laboratory Page 9 of 81

1.3.1 Total Radioactivity Determination contd Gamma isotopic measurements are performed using germanium detectors with a resolution of 2.1 keV or lower. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and a quantitative reduction or MDC calculation is performed. This ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

ECL fraction is determined using radionuclide concentrations of a tank planned for release, the most current results available for tritium, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 and the corresponding ECL values.

This ECL fraction is used, with appropriate safety factors, tolerance factors, and the minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) are not exceeded.

A monitor reading in excess of the calculated setpoint results in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.

Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate warnings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for release. When the release is completed, the necessary data from the release (i.e., release volume, etc.) is provided by the Operations Department to the Chemistry Department. This data is inputed to the computer and a post-release printout is generated. The post release printout contains the actual release rates, release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

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1.3.2 Total Error Estimation The total or maximum error associated with the effluent measurement includes the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in effluents (Reference Reg. Guide 1.21 Rev 1). Total Error is calculated by the root mean square method. The root mean square value is the square root of the arithmetic mean (average) of the squares of the original values.

a. Fission and activation total release was calculated from sample analysis results and release point flow rates.

Sampling and statistical error 10%

Counting Equipment Calibration 10%

Tank Volumes and System Flow Rates 20%

TOTAL ERROR 24.5%

b. Total Tritium release was calculated from sample analysis results and release point volumes.

Sampling and statistical errors 10%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 24.5%

c. Dissolved and entrained gases were calculated from sample analysis results and release point volumes.

Sampling and statistical error 20%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 30%

d. Gross alpha radioactivity was calculated from sample analysis results and release point volumes.

Sampling and statistical error 10%

Counting Equipment calibration 10%

Tank volumes and system flowrates 20%

TOTAL ERROR 24.5%

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1.3.2 Total Error Estimation contd

e. Volume of waste prior to dilution was calculated from level indicators on the tanks and pump discharge flow rates and times.

Level Indicator error 10%

Operator Interpretation of gauge 10%

TOTAL ERROR 14%

f. Volume of dilution water used was calculated from flow totalizers and pump discharge flow rates and times.

Flow totalizer error 10%

Operator interpretation of gauge 10%

TOTAL ERROR 14%

g. Gross alpha, Sr-89, Sr-90, Fe-55, Ni-63 and H-3 radioactivity has an additional error associated with sample compositing.

Compositing sample error 5%

1.4 Liquid Effluent Release Data Regulatory Guide 1.21 Rev. 1 Tables 2A and 2B are found in this report as Tables 1-1A, 1-1B, 1-1C, 1-2A, 1-2B and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 Rev. 1 for all four quarters.

1.5 Radiological Impact Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated in accordance with the Offsite Dose Calculation Manual.

Results are presented in Table 1-3A for Unit 1 and 1-3B for Unit 2, for all four quarters.

1.6 Liquid Effluents - Batch Releases Batch release information for liquid effluents is presented in Table 1-5A for Unit 1 and Table 1-5B for Unit 2.

1.7 Liquid Effluents - Abnormal Releases There were no abnormal liquid releases during 2019 Page 12 of 81

Table 1-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 5.32E-03 4.64E-03 1.60E-03 2.83E-02

2. Average diluted concentration during period uCi/mL 9.05E-10 2.02E-09 8.00E-10 8.22E-09

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 4.03E+02 1.91E+02 1.39E+02 9.96E+01

2. Average diluted Concentration during period uCi/mL 6.85E-05 8.34E-05 6.93E-05 2.89E-05

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 3.43E-03 1.79E-03 2.51E-04 1.00E-04

2. Average diluted Concentration during period uCi/mL 5.83E-10 7.81E-10 1.25E-10 2.90E-11

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 2.74E+07 2.51E+07 2.64E+07 2.52E+07 F. Volume of Dilution Water Used Liters 5.85E+09 2.27E+09 1.97E+09 3.42E+09

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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Table 1-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 3.56E-03 5.16E-04 8.81E-05 1.07E-03

2. Average diluted concentration during period uCi/mL 5.60E-10 2.34E-10 4.59E-11 3.18E-10

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 2.97E+02 5.55E+01 6.93E+01 4.09E+01

2. Average diluted Concentration during period uCi/mL 4.68E-05 2.52E-05 3.61E-05 1.22E-05

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 2.71E-03 3.88E-04 2.76E-04 0.00E+00

2. Average diluted Concentration during period uCi/mL 4.27E-10 1.76E-10 1.44E-10 0.00E+00

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 2.36E+07 1.38E+07 2.18E+07 2.20E+07 F. Volume of Dilution Water Used Liters 6.33E+09 2.19E+09 1.90E+09 3.33E+09

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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Table 1-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 8.87E-03 5.16E-03 1.69E-03 2.94E-02

2. Average diluted concentration during period uCi/mL 7.25E-10 1.15E-09 4.30E-10 4.32E-09

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies 7.00E+02 2.47E+02 2.08E+02 1.41E+02

2. Average diluted Concentration during period uCi/mL 5.72E-05 5.49E-05 5.30E-05 2.07E-05

3. Percent of Applicable Limit % * * *

C. Dissolved and Entrained Gases

1. Total Release Curies 6.14E-03 2.18E-03 5.27E-04 1.00E-04

2. Average diluted Concentration during period uCi/mL 5.02E-10 4.85E-10 1.34E-10 1.47E-11

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E: Waste Vol Release (Pre-Dilution) Liters 5.10E+07 3.88E+07 4.82E+07 4.72E+07 F. Volume of Dilution Water Used Liters 1.22E+10 4.46E+09 3.87E+09 6.75E+09

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies 0.00E+00 0.00E+00 0.00E+00 2.70E-02 Total For Period Curies 0.00E+00 0.00E+00 0.00E+00 2.70E-02 Tritium H-3 Curies 9.17E-02 8.15E-02 1.40E-01 1.12E-01 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-58 Curies 1.67E-03 1.96E-03 3.64E-04 1.98E-04 Cs-137 Curies 0.00E+00 0.00E+00 3.86E-06 8.65E-06 Sb-125 Curies 0.00E+00 0.00E+00 2.23E-05 1.52E-05 Fe-59 Curies 0.00E+00 1.50E-05 0.00E+00 0.00E+00 Cr-51 Curies 0.00E+00 3.18E-04 3.09E-05 0.00E+00 Fe-55 Curies 7.26E-04 6.97E-04 1.39E-04 2.26E-04 Co-60 Curies 6.19E-04 7.86E-04 4.30E-04 2.79E-04 Mn-54 Curies 1.60E-05 5.34E-05 3.36E-05 1.78E-05 Nb-95 Curies 3.99E-06 1.54E-04 6.18E-05 1.02E-05 Ni-63 Curies 5.35E-04 5.79E-04 4.78E-04 6.13E-04 Zr-95 Curies 0.00E+00 8.11E-05 3.65E-05 0.00E+00 Sn-117M Curies 3.36E-06 0.00E+00 0.00E+00 0.00E+00 Co-57 Curies 1.05E-06 0.00E+00 0.00E+00 2.05E-06 Y-88 Curies 3.08E-08 0.00E+00 0.00E+00 0.00E+00 Te-125M Curies 1.74E-03 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 5.32E-03 4.64E-03 1.60E-03 1.37E-03 Tritium H-3 Curies 4.03E+02 1.91E+02 1.38E+02 9.95E+01 Dissolved And Entrained Gases Xe-135 Curies 1.62E-05 0.00E+00 0.00E+00 0.00E+00 Xe-133 Curies 3.41E-03 1.79E-03 2.51E-04 1.00E-04 Total For Period Curies 3.43E-03 1.79E-03 2.51E-04 1.00E-04 Page 17 of 81

Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 18 of 81

Table 1-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 5.65E-02 3.27E-02 1.03E-01 1.44E-01 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 19 of 81

Table 1-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Cs-137 Curies 0.00E+00 0.00E+00 0.00E+00 6.47E-06 Co-58 Curies 8.91E-04 2.99E-04 2.91E-05 4.40E-05 Fe-55 Curies 4.64E-04 4.48E-05 1.69E-05 6.31E-05 Ni-63 Curies 2.67E-04 9.24E-05 2.16E-05 1.30E-04 Sr-90 Curies 3.93E-06 0.00E+00 0.00E+00 0.00E+00 Te-125M Curies 0.00E+00 0.00E+00 0.00E+00 7.43E-04 Nb-95 Curies 1.53E-05 0.00E+00 0.00E+00 0.00E+00 Mn-54 Curies 7.50E-05 0.00E+00 0.00E+00 4.77E-06 Co-57 Curies 6.89E-06 0.00E+00 0.00E+00 0.00E+00 Co-60 Curies 1.83E-03 7.97E-05 2.06E-05 7.58E-05 Total For Period Curies 3.56E-03 5.16E-04 8.81E-05 1.07E-03 Tritium H-3 Curies 2.97E+02 5.55E+01 6.92E+01 4.08E+01 Dissolved And Entrained Gases Xe-135 Curies 1.10E-06 0.00E+00 0.00E+00 0.00E+00 Xe-133 Curies 2.71E-03 3.88E-04 2.76E-04 0.00E+00 Total For Period Curies 2.71E-03 3.88E-04 2.76E-04 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 20 of 81

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies 0.00E+00 0.00E+00 0.00E+00 2.70E-02 Total For Period Curies 0.00E+00 0.00E+00 0.00E+00 2.70E-02 Tritium H-3 Curies 1.48E-01 1.14E-01 2.43E-01 2.56E-01 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 21 of 81

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies 1.19E-03 7.42E-04 1.56E-04 2.89E-04 Cr-51 Curies 0.00E+00 3.18E-04 3.09E-05 0.00E+00 Nb-95 Curies 1.93E-05 1.54E-04 6.18E-05 1.02E-05 Sb-125 Curies 0.00E+00 0.00E+00 2.23E-05 1.52E-05 Te-125M Curies 1.74E-03 0.00E+00 0.00E+00 7.43E-04 Co-60 Curies 2.45E-03 8.65E-04 4.50E-04 3.54E-04 Cs-137 Curies 0.00E+00 0.00E+00 3.86E-06 1.51E-05 Co-57 Curies 7.94E-06 0.00E+00 0.00E+00 2.05E-06 Sn-117M Curies 3.36E-06 0.00E+00 0.00E+00 0.00E+00 Zr-95 Curies 0.00E+00 8.11E-05 3.65E-05 0.00E+00 Y-88 Curies 3.08E-08 0.00E+00 0.00E+00 0.00E+00 Ni-63 Curies 8.02E-04 6.72E-04 5.00E-04 7.43E-04 Fe-59 Curies 0.00E+00 1.50E-05 0.00E+00 0.00E+00 Co-58 Curies 2.56E-03 2.26E-03 3.93E-04 2.42E-04 Mn-54 Curies 9.11E-05 5.34E-05 3.36E-05 2.25E-05 Sr-90 Curies 3.93E-06 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 8.87E-03 5.16E-03 1.69E-03 2.44E-03 Tritium H-3 Curies 7.00E+02 2.47E+02 2.08E+02 1.40E+02 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 22 of 81

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Xe-133 Curies 6.12E-03 2.18E-03 5.27E-04 1.00E-04 Xe-135 Curies 1.73E-05 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 6.14E-03 2.18E-03 5.27E-04 1.00E-04 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 23 of 81

Table 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Total Body 1.50E+00 mRem 1.57E-02 1.05E+00 5.56E-03 3.71E-01 6.51E-03 4.34E-01 1.21E-02 8.08E-01 Thyroid 5.00E+00 mRem 1.57E-02 3.13E-01 5.52E-03 1.10E-01 6.45E-03 1.29E-01 4.17E-03 8.33E-02 Liver 5.00E+00 mRem 1.57E-02 3.14E-01 5.59E-03 1.12E-01 6.55E-03 1.31E-01 3.80E-02 7.61E-01 GI-Lli 5.00E+00 mRem 1.60E-02 3.19E-01 5.84E-03 1.17E-01 6.61E-03 1.32E-01 2.36E-02 4.72E-01 Lung 5.00E+00 mRem 1.57E-02 3.14E-01 5.53E-03 1.11E-01 6.54E-03 1.31E-01 2.30E-02 4.61E-01 Bone 5.00E+00 mRem 5.71E-04 1.14E-02 6.23E-04 1.25E-02 5.34E-04 1.07E-02 4.94E-02 9.89E-01 Kidney 5.00E+00 mRem 1.59E-02 3.17E-01 5.52E-03 1.10E-01 6.47E-03 1.29E-01 4.20E-03 8.40E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Kidney 1.00E+01 mRem 3.20E-02 3.20E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 5.12E-02 5.12E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 5.08E-02 5.08E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 5.20E-02 5.20E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 6.59E-02 6.59E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 3.18E-02 3.18E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+00 mRem 3.99E-02 1.33E+00 Maximum Individual Liquid Liquid Effluent TB Annual Page 24 of 81

Table 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Kidney 5.00E+00 mRem 1.20E-02 2.40E-01 2.65E-03 5.31E-02 2.92E-03 5.84E-02 2.37E-03 4.75E-02 Thyroid 5.00E+00 mRem 1.20E-02 2.40E-01 2.65E-03 5.31E-02 2.92E-03 5.84E-02 2.18E-03 4.35E-02 Total Body 1.50E+00 mRem 1.20E-02 8.02E-01 2.66E-03 1.77E-01 2.92E-03 1.95E-01 2.24E-03 1.49E-01 Lung 5.00E+00 mRem 1.20E-02 2.40E-01 2.66E-03 5.32E-02 2.93E-03 5.85E-02 2.18E-03 4.36E-02 Liver 5.00E+00 mRem 1.20E-02 2.40E-01 2.66E-03 5.32E-02 2.92E-03 5.85E-02 2.29E-03 4.58E-02 Bone 5.00E+00 mRem 3.44E-04 6.88E-03 1.03E-04 2.06E-03 2.03E-05 4.06E-04 2.52E-04 5.04E-03 GI-Lli 5.00E+00 mRem 1.22E-02 2.44E-01 2.68E-03 5.36E-02 2.93E-03 5.86E-02 2.36E-03 4.72E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit GI-Lli 1.00E+01 mRem 2.02E-02 2.02E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 7.19E-04 7.19E-03 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 1.99E-02 1.99E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 1.98E-02 1.98E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+00 mRem 1.99E-02 6.62E-01 Maximum Individual Liquid Liquid Effluent TB Annual Thyroid 1.00E+01 mRem 1.97E-02 1.97E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 1.99E-02 1.99E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Page 25 of 81

Table 1-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a member of the public due to Liquid Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Thyroid 5.00E+00 mRem 2.77E-02 5.53E-01 8.17E-03 1.63E-01 9.37E-03 1.87E-01 6.34E-03 1.27E-01 Bone 5.00E+00 mRem 9.15E-04 1.83E-02 7.26E-04 1.45E-02 5.54E-04 1.11E-02 4.97E-02 9.94E-01 Lung 5.00E+00 mRem 2.77E-02 5.54E-01 8.19E-03 1.64E-01 9.47E-03 1.89E-01 2.52E-02 5.04E-01 GI-Lli 5.00E+00 mRem 2.81E-02 5.63E-01 8.52E-03 1.70E-01 9.54E-03 1.91E-01 2.59E-02 5.19E-01 Kidney 5.00E+00 mRem 2.78E-02 5.57E-01 8.17E-03 1.63E-01 9.39E-03 1.88E-01 6.58E-03 1.32E-01 Total Body 1.50E+00 mRem 2.77E-02 1.85E+00 8.22E-03 5.48E-01 9.44E-03 6.29E-01 1.44E-02 9.57E-01 Liver 5.00E+00 mRem 2.77E-02 5.55E-01 8.25E-03 1.65E-01 9.47E-03 1.89E-01 4.03E-02 8.07E-01 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Liver 1.00E+01 mRem 8.58E-02 8.58E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+00 mRem 5.97E-02 1.99E+00 Maximum Individual Liquid Liquid Effluent TB Annual Kidney 1.00E+01 mRem 5.20E-02 5.20E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 7.22E-02 7.22E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 7.06E-02 7.06E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 5.19E-02 5.19E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 5.15E-02 5.15E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Page 26 of 81

Table 1-4 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES Starting: 1-Jan-2019 Ending: 31-Dec-2019 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 2.73E-08 µCi/ml Fe-59 8.33E-08 µCi/ml Co-58 3.78E-08 µCi/ml Co-60 6.76E-08 µCi/ml Zn-65 1.32E-07 µCi/ml Mo-99 4.31E-07 µCi/ml Cs-134 3.06E-08 µCi/ml Cs-137 4.51E-08 µCi/ml Ce-141 6.99E-08 µCi/ml Ce-144 2.95E-07 µCi/ml I-131 5.97E-08 µCi/ml Xe-133 9.11E-08 µCi/ml Xe-135 4.27E-08 µCi/ml Fe-55 1.00E-06 µCi/ml Sr-89 5.00E-08 µCi/ml Sr-90 7.00E-09 µCi/ml H-3 2.00E-06 µCi/ml Gross Alpha 7.00E-08 µCi/m Page 27 of 81

Table 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 11 8 5 4 T 28 l

2. Total time period for Batch releases ( Minutes ) 3.56E+03 2.37E+03 2.32E+03 1.76E+03 1.00E+04

3. Maximum time period for a batch release ( Minutes ) 5.44E+02 3.23E+02 7.99E+02 6.06E+02 7.99E+02

4. Average time period for a batch release ( Minutes ) 3.24E+02 2.96E+02 4.64E+02 4.39E+02 3.57E+02

5. Minimum time period for a batch release ( Minutes ) 2.01E+02 2.78E+02 2.16E+02 2.66E+02 2.01E+02

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 2.0957E+04 1.0516E+04 6.1573E+03 6.2110E+03 1.0960E+04 Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, GA. 32 miles downstream Page 28 of 81

Table 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 10 4 2 2 T 18 l

2. Total time period for Batch releases ( Minutes ) 2.37E+03 1.17E+03 1.10E+03 5.29E+02 5.17E+03

3. Maximum time period for a batch release ( Minutes ) 4.46E+02 4.38E+02 9.11E+02 2.99E+02 9.11E+02

4. Average time period for a batch release ( Minutes ) 2.37E+02 2.93E+02 5.49E+02 2.65E+02 2.87E+02

5. Minimum time period for a batch release ( Minutes ) 5.10E+01 7.20E+01 1.87E+02 2.30E+02 5.10E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 2.0957E+04 1.0516E+04 6.1573E+03 6.2110E+03 1.0960E+04 Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, GA. 32 miles downstream Page 29 of 81

Table 1-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Batch Release Summary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 21 12 7 6 T 46 l

2. Total time period for Batch releases ( Minutes ) 5.93E+03 3.54E+03 3.42E+03 2.29E+03 1.52E+04

3. Maximum time period for a batch release ( Minutes ) 5.44E+02 4.38E+02 9.11E+02 6.06E+02 9.11E+02

4. Average time period for a batch release ( Minutes ) 2.83E+02 2.95E+02 4.88E+02 3.81E+02 3.30E+02

5. Minimum time period for a batch release ( Minutes ) 5.10E+01 7.20E+01 1.87E+02 2.30E+02 5.10E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 2.0957E+04 1.0516E+04 6.1573E+03 6.2110E+03 1.0960E+04 Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, GA. 32 miles downstream Page 30 of 81

Table 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 31 of 81

Table 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 32 of 81

Table 1-6C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Liquid Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 33 of 81

2.0 Gaseous Effluents 2.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2.

2.1.1 Dose Rate Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases, Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,

b. For Iodine-131, for Iodine-133, for tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

2.1.2 Air Doses Due to Noble Gases in Gaseous Releases The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.3 Doses to a Member of the Public The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following.

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ.

b. During any calendar year: Less than or equal to 15 mrems to any organ.

Page 34 of 81

2.2 Measurements and Approximations of Total Radioactivity 2.2.1 Sample Collection and Analysis Gaseous Effluents at the Vogtle Electric Generating Plant are currently confined to five paths: plant vents (Unit 1 and Unit 2), the condenser air ejector, the steam packing exhauster systems (Unit 1 and Unit 2), and the Radwaste Processing Facility (RPF).

Waste gas decay tanks are batch released through the Unit 1 plant vent. The containment purges are released through their respective plant vents.

Containment atmosphere is also released via the containment equipment hatch during periods when the equipment hatch is open with containment purge/vent being stopped. Approval was granted by the NRC to open the equipment hatch during fuel movement; a release permit is generated when the equipment hatch is opened and the containment exhaust fan is not discharging to the plant vent.

Any detected activity in the containment equipment hatch permit is included in the Ground Release Table of the effluent report.

All of the paths with the exception of the RPF can be continuously monitored for gaseous radioactivity. The RPF is equipped with an integrated-type sample collection device for collecting particulates. Plant vent, containment, steam jet air ejector, steam-packing exhauster are equipped with an integrated-type sample collection device for collecting particulates and iodines. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and the steam packing exhauster system vents. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release. The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.

Sample analysis results and release flow rates form the basis for calculating released quantities of radionuclide specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year.

With each release period and batch release, radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated, along with the percent of the ODCM limits for each release for the current quarter and year.

Typically achieved minimum detectable concentrations for gaseous effluent sample analyses are reported in Table 2-6.

Page 35 of 81

2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses are as follows:

2.2.2.1 Fission and Activation Gases The released radioactivity is determined from sample analysis results collected as described above and average release flow rates over the period represented by the collected sample. Dose rates due to noble gases, radioiodines, tritium, and particulates are calculated. Calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodines, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year. Cumulative air doses are compared with the dose limits specified in ODCM 3.1.3. Current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.

2.2.2.2 Radioiodines, Tritium and Particulate Releases The released quantities of radioiodines, tritium and particulates are determined using the weekly samples and release flow rates for the two plant vent release points.

After each quarter, the particulate filters from each plant vent are combined, for strontium analysis. Strontium concentrations are input to the composite file of the computer to be used for release dose rate and individual dose calculations.

Doses to a Member of the Public due to radioiodines, tritium and particulates are calculated for the controlling receptor, which is described in Table 3-7of the ODCM. Doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative doses are compared to the dose limits specified in ODCM 3.1.4.

Current percent of ODCM limits are shown in this report for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is calculated each month by counting the particulate filters for each week for gross alpha activity. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is used for release calculations.

Page 36 of 81

2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

Estimated errors are based on errors in counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges. Total Error is calculated by the root mean square method. The root mean square value is the square root of the arithmetic mean (average) of the squares of the original values.

a. Fission and activation total release was calculated from sample analysis results and release point flow rates.

Sampling and statistical error in counting 10%

Counting equipment calibration 10%

Vent flow Rates 10%

Non-steady release rates 20%

TOTAL ERROR 26.5%

b. I-131 releases were calculated from each weekly sample:

Statistical error in counting 10%

Counting equipment calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 50%

Non-Steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 55%

c. Particulates with half-lives greater than 8 day releases were calculated from sample and analysis results and release point flow rates.

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non steady release rates 10%

TOTAL ERROR 54%

Page 37 of 81

2.2.3 Total Error Estimation contd

d. Total tritium releases were calculated from sample analysis results and release point flow rates.

Water vapor in sample stream determination 10%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 10%

TOTAL ERROR 20%

e. Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non Steady release rates 10%

TOTAL ERROR 55%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Rev. 1 Tables 1A, 1B, and 1C are found in this report as Tables 2-1A, 2-1B, 2-1C, 2-2A, 2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data are presented on a quarterly basis as required by Regulatory Guide 1.21 Rev. 1.

To complete table 2-1A, and 2-1B, the total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in

µCi/second for each category. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases and due to radioiodines, tritium, and particulate releases were calculated as part of the pre-release and post-release permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Table 2-1A and 2-1B as curies released in each quarter.

Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A, and 2-4B along with the percent of the ODCM limits.

Page 38 of 81

Limits for cumulative doses to a Member of the Public due to radioiodines, tritium and particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member of the Public are presented in Table 2-5A, and 2-5B along with percent of ODCM limits.

2.4 Radiological Impact Due to Gaseous Releases Dose rates due to the release of noble gases were calculated for the site in accordance with ODCM 3.4.1.1. Dose rates due to radioiodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.

Dose rates were calculated as part of pre-release and post release permits. No limits were exceeded for this reporting period.

Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.4.2. These results are presented in Tables 2-4A and 2-4B.

Cumulative doses to a Member of the Public were calculated for each unit in accordance with ODCM 3.4.3. These results are presented in Tables 2-5A and 2-5B.

Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.

2.5 Gaseous Effluents - Batch Releases Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 2-7A and 2-7B.

2.6 Gaseous Effluents - Abnormal Releases There were no abnormal releases for 2019.

Page 39 of 81

Table 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.04E+01 1.86E+01 4.97E+01 6.21E+01

2. Average Release rate for period uCi/sec 2.59E+00 2.35E+00 6.31E+00 7.87E+00

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 2.19E-08 0.00E+00 0.00E+00 0.00E+00

2. Average Release rate for period uCi/sec 2.78E-09 0.00E+00 0.00E+00 0.00E+00

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Average Release rate for period uCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 5.73E+01 5.15E+00 1.55E+01 1.72E+01

2. Average Release rate for period uCi/sec 7.27E+00 6.54E-01 1.97E+00 2.18E+00

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 1.52E-06 1.34E-06 1.36E-06 1.27E-06

2. Average Release rate for period uCi/sec 1.93E-07 1.70E-07 1.72E-07 1.61E-07

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 40 of 81

Table 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 4.64E-01 2.34E-02 1.41E+00 3.20E-02

2. Average Release rate for period uCi/sec 5.89E-02 2.97E-03 1.79E-01 4.06E-03

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Average Release rate for period uCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 7.96E-05 0.00E+00 0.00E+00 3.68E-08

2. Average Release rate for period uCi/sec 1.01E-05 0.00E+00 0.00E+00 4.67E-09

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 2.43E+01 5.13E-03 7.37E+00 7.72E+00

2. Average Release rate for period uCi/sec 3.09E+00 6.51E-04 9.34E-01 9.79E-01

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 1.05E-06 6.17E-07 7.87E-07 4.88E-07

2. Average Release rate for period uCi/sec 1.33E-07 7.83E-08 9.99E-08 6.19E-08

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Page 41 of 81

Table 2-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.09E+01 1.86E+01 5.12E+01 6.21E+01

2. Average Release rate for period uCi/sec 2.65E+00 2.36E+00 6.49E+00 7.88E+00

3. Percent of Applicable Limit % * * *

B. Radioiodines

1. Total Iodine-131 Curies 2.19E-08 0.00E+00 0.00E+00 0.00E+00

2. Average Release rate for period uCi/sec 2.78E-09 0.00E+00 0.00E+00 0.00E+00

3. Percent of Applicable Limit % * * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 7.96E-05 0.00E+00 0.00E+00 3.68E-08

2. Average Release rate for period uCi/sec 1.01E-05 0.00E+00 0.00E+00 4.67E-09

3. Percent of Applicable Limit % * * *

D. Tritium

1. Total Release Curies 8.16E+01 5.16E+00 2.29E+01 2.49E+01

2. Average Release rate for period uCi/sec 1.04E+01 6.54E-01 2.90E+00 3.16E+00

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 2.57E-06 1.96E-06 2.14E-06 1.75E-06

2. Average Release rate for period uCi/sec 3.26E-07 2.49E-07 2.72E-07 2.22E-07

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 42 of 81

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies 1.03E+01 1.43E+01 4.38E+01 5.49E+01 Total For Period Curies 1.03E+01 1.43E+01 4.38E+01 5.49E+01 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 9.79E+00 5.09E+00 1.47E+01 1.63E+01 Gross Alpha G-Alpha Curies 1.44E-06 1.34E-06 1.36E-06 1.26E-06 Total For Period Curies 1.44E-06 1.34E-06 1.36E-06 1.26E-06 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 43 of 81

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 6.73E-02 6.26E-02 7.77E-02 8.85E-02 Xe-131M Curies 1.46E-01 3.56E-02 1.17E-01 1.27E-01 Xe-133M Curies 7.72E-02 2.15E-02 2.55E-02 3.40E-02 Xe-133 Curies 9.76E+00 4.18E+00 5.71E+00 6.94E+00 Xe-135 Curies 1.55E-02 2.18E-03 1.61E-03 3.39E-03 Total For Period Curies 1.01E+01 4.30E+00 5.93E+00 7.19E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 5.87E-02 3.18E-02 3.51E-02 4.00E-02 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 44 of 81

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies 0.00E+00 0.00E+00 1.38E+00 0.00E+00 Total For Period Curies 0.00E+00 0.00E+00 1.38E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Co-60 Curies 2.22E-07 0.00E+00 0.00E+00 0.00E+00 Sr-90 Curies 0.00E+00 0.00E+00 0.00E+00 3.68E-08 Total For Period Curies 2.22E-07 0.00E+00 0.00E+00 3.68E-08 Tritium H-3 Curies 2.42E+01 0.00E+00 7.36E+00 7.71E+00 Gross Alpha G-Alpha Curies 1.05E-06 6.17E-07 7.87E-07 4.88E-07 Total For Period Curies 1.05E-06 6.17E-07 7.87E-07 4.88E-07 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 45 of 81

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.11E-01 2.24E-02 2.14E-02 2.55E-02 Xe-133 Curies 2.18E-01 1.04E-03 7.84E-03 6.12E-03 Xe-135 Curies 2.70E-02 0.00E+00 0.00E+00 3.19E-04 Total For Period Curies 4.56E-01 2.34E-02 2.92E-02 3.20E-02 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 1.09E-01 5.13E-03 4.70E-03 6.43E-03 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 46 of 81

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies 1.03E+01 1.43E+01 4.52E+01 5.49E+01 Total For Period Curies 1.03E+01 1.43E+01 4.52E+01 5.49E+01 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Co-60 Curies 2.22E-07 0.00E+00 0.00E+00 0.00E+00 Sr-90 Curies 0.00E+00 0.00E+00 0.00E+00 3.68E-08 Total For Period Curies 2.22E-07 0.00E+00 0.00E+00 3.68E-08 Tritium H-3 Curies 3.40E+01 5.09E+00 2.21E+01 2.40E+01 Gross Alpha G-Alpha Curies 2.49E-06 1.96E-06 2.14E-06 1.75E-06 Total For Period Curies 2.49E-06 1.96E-06 2.14E-06 1.75E-06 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 47 of 81

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.78E-01 8.50E-02 9.90E-02 1.14E-01 Xe-131M Curies 1.46E-01 3.56E-02 1.17E-01 1.27E-01 Xe-133M Curies 7.72E-02 2.15E-02 2.55E-02 3.40E-02 Xe-133 Curies 9.98E+00 4.18E+00 5.72E+00 6.95E+00 Xe-135 Curies 4.25E-02 2.18E-03 1.61E-03 3.71E-03 Total For Period Curies 1.05E+01 4.32E+00 5.96E+00 7.23E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 1.68E-01 3.69E-02 3.98E-02 4.64E-02 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 48 of 81

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines I-131 Curies 2.19E-08 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 2.19E-08 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 1.03E-01 2.73E-02 9.98E-02 3.23E-01 Gross Alpha G-Alpha Curies 8.27E-08 3.27E-09 6.53E-10 7.03E-09 Total For Period Curies 8.27E-08 3.27E-09 6.53E-10 7.03E-09 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 49 of 81

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 4.74E+01 0.00E+00 6.42E-01 5.47E-01 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 50 of 81

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 51 of 81

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 8.43E-04 0.00E+00 0.00E+00 0.00E+00 Xe-133 Curies 6.37E-03 0.00E+00 0.00E+00 0.00E+00 Xe-135 Curies 1.06E-03 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 8.28E-03 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Co-58 Curies 3.33E-05 0.00E+00 0.00E+00 0.00E+00 Co-60 Curies 4.61E-05 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 7.94E-05 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 1.25E-03 0.00E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 52 of 81

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines I-131 Curies 2.19E-08 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 2.19E-08 0.00E+00 0.00E+00 0.00E+00 Particulates No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 1.03E-01 2.73E-02 9.98E-02 3.23E-01 Gross Alpha G-Alpha Curies 8.27E-08 3.27E-09 6.53E-10 7.03E-09 Total For Period Curies 8.27E-08 3.27E-09 6.53E-10 7.03E-09 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 53 of 81

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 8.43E-04 0.00E+00 0.00E+00 0.00E+00 Xe-133 Curies 6.37E-03 0.00E+00 0.00E+00 0.00E+00 Xe-135 Curies 1.06E-03 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 8.28E-03 0.00E+00 0.00E+00 0.00E+00 Iodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Co-58 Curies 3.33E-05 0.00E+00 0.00E+00 0.00E+00 Co-60 Curies 4.61E-05 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 7.94E-05 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Curies 4.74E+01 0.00E+00 6.42E-01 5.47E-01 Gross Alpha No Nuclides Found Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

A Unit 1 fuel leak, which developed in October 2018, explains increases in radioisotopic concentrations between 2019 and 2018.

Page 54 of 81

Table 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Gamma Air 5.00E+00 mRad 1.14E-04 2.28E-03 1.04E-04 2.08E-03 2.67E-04 5.34E-03 3.32E-04 6.64E-03 Beta Air 1.00E+01 mRad 3.17E-04 3.17E-03 2.88E-04 2.88E-03 7.68E-04 7.68E-03 9.58E-04 9.58E-03 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date % ODCM Receptor Limit Gamma Air 1.00E+01 mRad 8.18E-04 8.18E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.00E+01 mRad 2.33E-03 1.17E-02 Site Boundary / Child Air Dose Beta Annual 1.21 Page 55 of 81

Table 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Gamma Air 5.00E+00 mRad 3.16E-05 6.32E-04 3.06E-06 6.11E-05 1.01E-05 2.02E-04 3.52E-06 7.04E-05 Beta Air 1.00E+01 mRad 1.54E-05 1.54E-04 1.09E-06 1.09E-05 2.24E-05 2.24E-04 1.33E-06 1.33E-05 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date % ODCM Receptor Limit Gamma Air 1.00E+01 mRad 4.83E-05 4.83E-04 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.00E+01 mRad 4.03E-05 2.01E-04 Site Boundary / Child Air Dose Beta Annual 1.21 Page 56 of 81

Table 2-4C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Air Doses Due to Gaseous Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Gamma Air 5.00E+00 mRad 1.46E-04 2.92E-03 1.07E-04 2.14E-03 2.77E-04 5.54E-03 3.36E-04 6.71E-03 Beta Air 1.00E+01 mRad 3.32E-04 3.32E-03 2.89E-04 2.89E-03 7.90E-04 7.90E-03 9.59E-04 9.59E-03 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date % ODCM Receptor Limit Gamma Air 1.00E+01 mRad 8.66E-04 8.66E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.00E+01 mRad 2.37E-03 1.19E-02 Site Boundary / Child Air Dose Beta Annual 1.21 Page 57 of 81

Table 2-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Total Body 7.50E+00 mRem 8.27E-03 1.10E-01 5.24E-05 6.98E-04 2.65E-04 3.54E-03 3.02E-04 4.02E-03 Lung 7.50E+00 mRem 8.27E-03 1.10E-01 5.24E-05 6.98E-04 2.65E-04 3.54E-03 3.02E-04 4.02E-03 Thyroid 7.50E+00 mRem 8.27E-03 1.10E-01 5.24E-05 6.98E-04 2.65E-04 3.54E-03 3.02E-04 4.02E-03 Bone 7.50E+00 mRem 3.64E-10 4.86E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 GI-Lli 7.50E+00 mRem 8.27E-03 1.10E-01 5.24E-05 6.98E-04 2.65E-04 3.54E-03 3.02E-04 4.02E-03 Kidney 7.50E+00 mRem 8.27E-03 1.10E-01 5.24E-05 6.98E-04 2.65E-04 3.54E-03 3.02E-04 4.02E-03 Liver 7.50E+00 mRem 8.27E-03 1.10E-01 5.24E-05 6.98E-04 2.65E-04 3.54E-03 3.02E-04 4.02E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Total Body 1.500E+01 mRem 8.889E-03 5.926E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 8.889E-03 5.926E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 8.889E-03 5.926E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Bone 1.500E+01 mRem 3.645E-10 2.430E-09 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 8.889E-03 5.926E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 8.889E-03 5.926E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 8.889E-03 5.926E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Page 58 of 81

Table 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Thyroid 7.50E+00 mRem 6.15E-04 8.20E-03 1.11E-07 1.48E-06 1.59E-04 2.12E-03 1.67E-04 2.22E-03 Lung 7.50E+00 mRem 6.23E-04 8.30E-03 1.11E-07 1.48E-06 1.59E-04 2.12E-03 1.67E-04 2.22E-03 Bone 7.50E+00 mRem 2.18E-04 2.91E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.53E-08 3.37E-07 GI-Lli 7.50E+00 mRem 6.27E-04 8.36E-03 1.11E-07 1.48E-06 1.59E-04 2.12E-03 1.67E-04 2.22E-03 Liver 7.50E+00 mRem 6.17E-04 8.23E-03 1.11E-07 1.48E-06 1.59E-04 2.12E-03 1.67E-04 2.22E-03 Total Body 7.50E+00 mRem 6.22E-04 8.29E-03 1.11E-07 1.48E-06 1.59E-04 2.12E-03 1.67E-04 2.23E-03 Kidney 7.50E+00 mRem 6.15E-04 8.20E-03 1.11E-07 1.48E-06 1.59E-04 2.12E-03 1.67E-04 2.22E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Thyroid 1.500E+01 mRem 9.416E-04 6.277E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 9.487E-04 6.325E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Bone 1.500E+01 mRem 2.179E-04 1.453E-03 Units 3&4 Construction Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 9.533E-04 6.355E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 9.437E-04 6.291E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 9.481E-04 6.321E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 9.416E-04 6.277E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 59 of 81

Table 2-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Kidney 7.50E+00 mRem 8.71E-03 1.16E-01 5.24E-05 6.99E-04 3.34E-04 4.45E-03 3.73E-04 4.98E-03 GI-Lli 7.50E+00 mRem 8.71E-03 1.16E-01 5.24E-05 6.99E-04 3.34E-04 4.45E-03 3.73E-04 4.98E-03 Thyroid 7.50E+00 mRem 8.71E-03 1.16E-01 5.24E-05 6.99E-04 3.34E-04 4.45E-03 3.73E-04 4.98E-03 Total Body 7.50E+00 mRem 8.71E-03 1.16E-01 5.24E-05 6.99E-04 3.34E-04 4.45E-03 3.73E-04 4.98E-03 Lung 7.50E+00 mRem 8.73E-03 1.16E-01 5.24E-05 6.99E-04 3.34E-04 4.45E-03 3.73E-04 4.98E-03 Liver 7.50E+00 mRem 8.71E-03 1.16E-01 5.24E-05 6.99E-04 3.34E-04 4.45E-03 3.73E-04 4.98E-03 Bone 7.50E+00 mRem 2.18E-04 2.91E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.53E-08 3.37E-07 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Kidney 1.500E+01 mRem 9.473E-03 6.316E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 9.474E-03 6.316E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 9.473E-03 6.316E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 9.473E-03 6.316E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 9.489E-03 6.326E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 9.473E-03 6.316E-02 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Bone 1.500E+01 mRem 2.179E-04 1.453E-03 Units 3&4 Construction Iodine/Part Dose Annual 1.21 Page 60 of 81

Table 2-6 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 MINIMUM DETECTABLE CONCENTRATIONS GASEOUS SAMPLE ANALYSES Starting: 1-Jan-2019 Ending: 31-Dec-2019 RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 µCi/ml Kr-88 2.53E-08 µCi/ml Xe-133 2.05E-08 µCi/ml Xe-133m 8.63E-08 µCi/ml Xe-135 7.12E-08 µCi/ml Xe-138 1.05E-07 µCi/ml I-131 7.93E-15* µCi/ml Mn-54 3.94E-14* µCi/ml Fe-59 2.45E-14* µCi/ml Co-58 1.39E-14* µCi/ml Co-60 1.75E-14* µCi/ml Zn-65 2.82E-14* µCi/ml Mo-99 9.57E-14* µCi/ml Cs-134 1.12E-14* µCi/ml Cs-137 8.71E-15* µCi/ml Ce-141 8.62E-15* µCi/ml Ce-144 2.77E-14* µCi/ml Sr-89 1.00E-13 µCi/ml Sr-90 1.00E-13 µCi/ml H-3 9.00E-08 µCi/ml Gross Alpha 1.00E-13 µCi/ml

Based on an estimated sample volume of 5.7E+08 mls for particulate filters and charcoal cartridges Page 61 of 81

Table 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 54 52 58 56 220

2. Total time period for batch releases ( Minutes ) 4.62E+03 2.08E+03 2.74E+03 2.87E+03 1.23E+04

3. Maximum time period for a batch release ( Minutes ) 2.16E+03 9.80E+01 1.23E+02 1.56E+02 2.16E+03

4. Average time period for a batch release ( Minutes ) 8.55E+01 4.00E+01 4.73E+01 5.13E+01 5.60E+01

5. Minimum time period for a batch release ( Minutes ) 8.00E+00 9.00E+00 1.10E+01 9.00E+00 8.00E+00 Page 62 of 81

Table 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 30 16 17 18 81

2. Total time period for batch releases ( Minutes ) 2.29E+04 7.02E+02 6.36E+02 8.09E+02 2.51E+04

3. Maximum time period for a batch release ( Minutes ) 6.01E+03 1.24E+02 6.80E+01 8.30E+01 6.01E+03

4. Average time period for a batch release ( Minutes ) 7.64E+02 4.39E+01 3.74E+01 4.49E+01 3.10E+02

5. Minimum time period for a batch release ( Minutes ) 3.00E+00 2.20E+01 9.00E+00 2.60E+01 3.00E+00 Page 63 of 81

Table 2-7C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Batch Release Summary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 84 68 75 74 301

2. Total time period for batch releases ( Minutes ) 2.75E+04 2.78E+03 3.38E+03 3.68E+03 3.74E+04

3. Maximum time period for a batch release ( Minutes ) 6.01E+03 1.24E+02 1.23E+02 1.56E+02 6.01E+03

4. Average time period for a batch release ( Minutes ) 3.28E+02 4.09E+01 4.50E+01 4.98E+01 1.24E+02

5. Minimum time period for a batch release ( Minutes ) 3.00E+00 9.00E+00 9.00E+00 9.00E+00 3.00E+00 Page 64 of 81

Table 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 65 of 81

Table 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 66 of 81

Table 2-8C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Gaseous Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Maximum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release ( Minutes ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 67 of 81

3.0 Solid Waste 3.1 Regulatory Requirements The ODCM requirements presented in this section are stated in part for Unit 1 and Unit 2.

3.1.1 Solid Radioactive Waste System 10.2.1 Process Control Program (PCP)

Radioactive wastes shall be solidified or dewatered in accordance with the PCP to meet shipping and transportation requirements during transit and disposal site requirements when received at the disposal site.

3.1.2 Reporting Requirements 12.1 PCP states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units, as outlined in Regulatory Guide 1.21 Rev 2.

3.2 Solid Waste Data Regulatory Guide 1.21 Rev 2, Table 3 is found in this report as Table 3-1. GEL Laboratories performs hard-to-detect analysis for solid waste. Final calculations for nuclides include sample analysis performed on resin from High Integrity Containers.

For Gaseous and Liquid composites, the Georgia Power Environmental Laboratory performs hard-to-detect analysis.

Page 68 of 81

Table 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1, 2019 THROUGH JUNE 30, 2019 Regulatory Guide 1.21: Effluent and Waste Disposal Semi-Annual Report of Solid Waste and Irradiated Fuel Shipments A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste - NRC Waste Class A UNIT 6 month Est. Total Period ERROR %

a. Spent resins, filter sludges, evaporator m3 2.89E+00 +/- 10 bottoms, etc. Ci 1.48+00 +/- 10

b. Dry compressible waste, contaminated equip. m3 2.11+02 +/- 25 etc. Ci 6.22E-01 +/- 25

c. Irradiated components, control rods, m3 -N/A- -N/A-Ci -N/A- -N/A-

d. Control Rod Drive Filters m3 -N/A- -N/A-Ci -N/A- -N/A-

e. Other (describe) m3 1.78E+01 -N/A-Steam Generator Blowdown Resin (GIC) Ci 5.96E-03 -N/A-

1. Type of waste - NRC Waste Class B UNIT 6 month Est. Total period ERROR %

a. Spent resins, filter sludges, evaporator m3 2.69E+00 +/- 10 bottoms, etc. Ci 1.00E+02 +/- 10

b. Dry compressible waste, contaminated equip. m3 -N/A- -N/A-etc. Ci -N/A- -N/A-

c. Irradiated components, control rods, m3 -N/A- -N/A-Ci -N/A- -N/A-

d. Control Rod Drive Filters m3 -N/A- -N/A-Ci -N/A- -N/A-

e. Other (describe) m3 -N/A- -N/A-equip. etc. Ci -N/A- -N/A-Page 69 of 81

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION:

NRC WASTE CLASS A (1% Percent)

ISOTOPE PERCENT CURIES

a. 3 H 4.18 6.19E-02 14 C 1.39 2.06E-02 55 Fe 16.23 2.40E-01 58 Co 11.82 1.75E-01 60 Co 8.56 1.27E-01 63 Ni 19.12 2.83E-01 125 Sb 35.88 5.31E-01

b. 51 Cr 6.58 4.09E-02 54 Mn 1.42 8.85E-03 55 Fe 30.84 1.92E-01 58 Co 28.24 1.76E-01 60 Co 14.26 8.86E-02 63 Ni 11.69 7.27E-02 95 Zr 1.6 9.93E-03 95 Nb 3.23 2.01E-02

c. -N/A- -N/A- -N/A-

d. -N/A- -N/A- -N/A-

e. 51 Cr 6.64 3.96E-04 54 Mn 1.42 8.47E-05 55 Fe 30.76 1.83E-03 58 Co 28.31 1.69E-03 60 Co 14.22 8.47E-04 63 Ni 11.66 6.95E-04 95 Zr 1.6 9.55E-05 95 Nb 3.24 1.93E-04

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION:

NRC WASTE CLASS B (1% Percent)

ISOTOPE PERCENT CURIES

a. 54 Mn 2.68 2.69E+00 55 Fe 15.06 1.51E+01 58 Co 7.69 7.71E+00 60 Co 27.05 2.71E+01 63 Ni 44.72 4.48E+01

b. -N/A- -N/A- -N/A-

c. -N/A- -N/A- -N/A-

d. -N/A- -N/A- -N/A-

e. -N/A- -N/A- -N/A-Page 70 of 81

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 6 Hittman Transport Energy Solutions - Bear Creek 1 Hittman Transport Energy Solutions - Gallaher Rd 1 Interstate Ventures WCS B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination

-N/A- -N/A- -N/A Page 71 of 81

Table 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY 1, 2019 THROUGH DECEMBER 31, 2019 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste - NRC Waste Class A UNIT 6 month Est. Total period ERROR %

a. Spent resins, filter sludges, evaporator m3 8.01E+00 +/- 10 bottoms, etc. Ci 1.12E+02 +/- 10

b. Dry compressible waste, contaminated equip. m3 6.34E+01 +/- 25 etc. Ci 9.68E-01 +/- 25

c. Irradiated components, control rods, m3 -N/A- -N/A-Ci -N/A- -N/A-

d. Control Rod Drive Filters m3 -N/A- -N/A-Ci -N/A- -N/A-

e. Other (describe) m3 -N/A- -N/A-Steam Generator Blowdown Resin Ci -N/A- -N/A-

1. Type of waste - NRC Waste Class B UNIT 6 month Est. Total period ERROR %

a. Spent resins, filter sludges, evaporator m3 -N/A- -N/A-bottoms, etc. Ci -N/A- -N/A-

b. Dry compressible waste, contaminated equip. m3 -N/A- -N/A-etc. Ci -N/A- -N/A-

c. Irradiated components, control rods, m3 -N/A- -N/A-Ci -N/A- -N/A-

d. Control Rod Drive Filters m3 -N/A- -N/A-Ci -N/A- -N/A-

e. Other (describe) m3 -N/A- -N/A-equip. etc. Ci -N/A- -N/A-

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION:

NRC WASTE CLASS A (1% Percent)

ISOTOPE PERCENT CURIES

a. 14 C 1.3 1.45E+00 54 Mn 2.22 2.48E+00 55 Fe 46.55 5.20E+01 58 Co 2.6 2.90E+00 60 Co 37.39 4.17E+01 63 Ni 4.79 5.35E+00 125 Sb 2.68 2.99E+00 137 Cs 1.17 1.31E+00 Page 72 of 81

b. 51 Cr 6.58 6.37E-02 54 Mn 1.42 1.38E-02 55 Fe 30.83 2.98E-01 58 Co 28.24 2.73E-01 60 Co 14.25 1.38E-01 63 Ni 11.69 1.13E-01 95 Zr 1.6 1.55E-02 95 Nb 3.24 3.13E-02

c. -N/A- -N/A- -N/A-

d. -N/A- -N/A- -N/A-

e. -N/A- -N/A- -N/A-

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION:

NRC WASTE CLASS B (1% Percent)

ISOTOPE PERCENT CURIES

a. 54 Mn 3.77 4.32E+00 55 Fe 25.46 2.91E+01 58 Co 4.13 4.73E+00 60 Co 25.03 2.86E+01 63 Ni 35.01 4.01E+01 65 Zn 1.02 1.16E+00 125 Sb 3.24 3.71E+00

b. -N/A- -N/A- -N/A-

c. -N/A- -N/A- -N/A-

d. -N/A- -N/A- -N/A-

e. -N/A- -N/A- -N/A-

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Hittman Transport Energy Solutions - Bear Creek B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination N/A N/A N/A Page 73 of 81

4.0 Doses to Members of the Public inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part:

"The report shall also include assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in the report".

4.2 Demonstration of Compliance The location of concern within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.

There will be no radiation dose at this location due to radioactive liquid effluents. Delineated in Table 4-1 for this location are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents.

Listed in this table are distance and direction from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the plant vent (mixed mode) and from the turbine building (ground level), and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.

The source term is listed in Tables 2-2A, and 2-2B for the mixed mode releases. Similarly, it is listed in Tables 2-3A and 2-3B for the ground level releases.

The maximum doses in units of mrem to a MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period are presented in Table 4-1.

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Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Location Name: Visitor's Center Receptor Distance (kilometers): 4.47E-01 Sector: SE Occupancy Factor: 4.57E-04 Age Group: Child Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 5.58E-06 D/Q (m-2): 2.28E-08 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 6.74E-07 D/Q (m-2): 5.77E-09 Mixed Mode Release Noble Gas X/Q (sec/m3): 7.12E-07 Ground Level Release Noble Gas X/Q (sec/m3): 5.93E-06 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year GI-Lli mRem 5.32E-08 6.23E-10 3.29E-09 3.64E-09 6.08E-08 Bone mRem 3.32E-09 0.00E+00 0.00E+00 3.64E-13 3.32E-09 Thyroid mRem 5.32E-08 6.23E-10 3.29E-09 3.64E-09 6.08E-08 Lung mRem 5.35E-08 6.23E-10 3.29E-09 3.64E-09 6.11E-08 Skin mRem 3.91E-09 0.00E+00 0.00E+00 0.00E+00 3.91E-09 Liver mRem 5.32E-08 6.23E-10 3.29E-09 3.64E-09 6.08E-08 Kidney mRem 5.32E-08 6.23E-10 3.29E-09 3.64E-09 6.08E-08 Total Body mRem 5.32E-08 6.23E-10 3.29E-09 3.64E-09 6.08E-08 Page 75 of 81

Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2019 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2019 Ending: 31-Dec-2019 Location Name: Units 3&4 Construction Distance (kilometers): 4.83E-01 Sector: SW Occupancy Factor: 2.37E-01 Age Group: Adult Mixed Mode Release Noble Gas X/Q (sec/m3): 9.75E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 0.00E+00 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 6.96E-06 D/Q (m-2): 2.88E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 6.93E-06 D/Q (m-2): 2.88E-08 Ground Level Release Noble Gas X/Q (sec/m3): 1.81E-05 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 9.17E-07 D/Q (m-2): 7.14E-09 Mixed Mode Release Noble Gas X/Q (sec/m3): 0.00E+00 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Kidney mRem 8.71E-05 5.24E-07 3.34E-06 3.73E-06 9.47E-05 GI-Lli mRem 8.71E-05 5.24E-07 3.34E-06 3.73E-06 9.47E-05 Skin mRem 2.56E-06 0.00E+00 0.00E+00 0.00E+00 2.56E-06 Thyroid mRem 8.71E-05 5.24E-07 3.34E-06 3.73E-06 9.47E-05 Total Body mRem 8.71E-05 5.24E-07 3.34E-06 3.73E-06 9.47E-05 Lung mRem 8.73E-05 5.24E-07 3.34E-06 3.73E-06 9.49E-05 Liver mRem 8.71E-05 5.24E-07 3.34E-06 3.73E-06 9.47E-05 Bone mRem 2.18E-06 0.00E+00 0.00E+00 2.53E-10 2.18E-06 Page 76 of 81

5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Requirements ODCM 5.1 states in part that the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

5.2 Demonstration of Compliance No dose limits stated in ODCM Sections 2.1.3, 3.1.3, and 3.1.4 were exceeded. Therefore, compliance with 40 CFR 190 dose limits was demonstrated in accordance with the requirements of ODCM Section 5.1.3.

6.0 Meteorological Data ODCM 7.2.2.2 states in part:

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirement ODCM 7.2.2.6 states in part that the report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, Page 77 of 81

respectively. The report shall include an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.

7.1.2 Description of Deviations (1) The inoperability of liquid and gaseous effluent monitors not corrected within the specified time for this reporting period is detailed below. When applicable, compensatory measures were utilized per ODCM Action Statements:

a. 2FT-0021 This flow transmitter was out of service greater than 30 days because the flow transmitter failed and needs to be replaced.

It was removed from service December 12, 2016 and currently awaiting Design Change implementation. Work Order SNC832477 is closed. Work Orders SNC1048033 and SNC1048612 are tracking the design change and implementation. This was omitted in the 2017 ARERR.

Stated here as an amendment to the 2017 ARERR.

7.2 Tanks Exceeding Curie Content Limits 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.

7.2.2 Description of Deviations Limits for outdoor liquid hold-up tanks used for radioactive liquids were not exceeded during this reporting period.

Limits for the gas storage tanks were not exceeded during this reporting period.

8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements Page 78 of 81

ODCM 7.2.2.5 states in part that changes to the ODCM shall be submitted with the Radioactive Effluent Release Report. These changes may be due to changes in the radiological environmental monitoring program sampling locations as required by ODCM 4.1.1.2.3 or changes to dose calculation locations as required by ODCM 4.1.2.2.2. Land uses and dose calculation locations within five miles of VEGP must be determined by a land use census as required by ODCM 4.1.2.

8.2 Description of Changes No changes made to VEGP ODCM in 2019.

9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 9.1 Regulatory Requirements ODCM 7.2.2.7 states in part:

As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation.

Note 1: In lieu of inclusion in the Radioactive Effluents Release Report, this same information may be submitted as part of the annual FSAR update.

PCP 12.1 states in part:

Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented.

9.2 Description of Major Changes Gaseous Radwaste System There were no major changes to the gaseous radwaste systems in the 2019 assessment period.

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Liquid Radwaste System There were no major changes to the liquid radwaste systems occurred during the 2019 assessment period.

Solid Radwaste System There were no major changes to the solid radwaste systems in the 2019 assessment period.

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Appendix A Vogtle Electric Generating Plant 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.

As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of principal radionuclides in gaseous effluents have changed, and C-14 has become a larger percentage. Principal radionuclides are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21),

Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, the NRC recommended re-evaluating principal radionuclides and reporting C-14 as appropriate. In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants started reporting C-14 amounts released and resulting doses to the maximally exposed member of the public.

Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation. The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.

At Plant Vogtle, the annual quantity of C-14 released in gaseous effluents was estimated to be 12.08 Curies (per unit). Approximately 30% of the C-14 released is in the form of 14CO2 and is incorporated into plants through photosynthesis. Ingestion dose results from this pathway. The remaining 70% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Vogtle ODCM, the resulting bone dose to a child located at the controlling receptor location would be 8.46E-02 mrem in a year which is 0.56% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents. The resulting total body dose to a child located at the controlling receptor location would be 1.69E-02 mrem in a year which is 0.11% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.

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NL-20-0419, Edwin I.Hatch Nuclear Station, Units 1 & 2; Joseph M. Farley Nuclear Station, Units 1 & 2; and Vogtle Electric Station, Units 1 & 2 - Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports

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NL-20-0419, Edwin I.Hatch Nuclear Station, Units 1 & 2; Joseph M. Farley Nuclear Station, Units 1 & 2; and Vogtle Electric Station, Units 1 & 2 - Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports

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