Text

Enclosure 1: Hatch Annual Radioactive Effluent Release Report for 2013
	ML14125A098
Person / Time
Site:	Hatch
Issue date:	04/30/2014
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML14125A094	List: ML14125A097; ML14125A098; ML14125A099; ML14125A100; ML14125A101; NL-14-0659, Edwin I. Hatch, Units 1 & 2, Joseph M. Farley, Units 1 & 2, Vogtle, Units 1 & 2, Southern Nuclear Operating Company'S Submittal of Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manuals for 2013; NL-14-0659, Enclosure 1: Hatch Annual Radioactive Effluent Release Report for 2013; NL-14-0659, Enclosure 2: Farley Annual Radioactive Effluent Release Report for 2013; NL-14-0659, Enclosure 3: Vogtle Annual Radioactive Effluent Release Report for 2013; NL-14-0659, Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23; NL-14-0659, Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 29;
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	NL-14-0659
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Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manuals for 2013 Enclosure 1 Hatch Annual Radioactive Effluent Release Report for 2013 SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT- UNITS I 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, 2013 TO DECEMBER 31, 2013 Prepared by:.Reviewed by: t,,t/lA. £ enMCA SECTION 1.0 1.1 1.1.1 1.1.2 1.2 1.3 1.3.1 1.4 1.4.1 1.5 1.6 1.7 1.8 1.9 TITLE Liquid Effluents Regulatory Requirements Concentration Limits Dose Limits Effluent Concentration Limit Measurements and Approximations of Total Radioactivity for Liquid Radwaste Total Radioactivity Determination for Liquid Radwaste Measurements and Approximations of Total Radioactivity for Groundwater Outfall -Y22N008A Total Radioactivity Determination for Groundwater Outfalls Total Error Estimation Liquid Effluent Release Data Radiological Impact Due to Liquid Releases Liquid Effluents

-Batch Releases Liquid Effluents

-Continuous Releases PAGE 2 1 1 1 1 2 2 4 4 5 6 7 7 7 SECTION 1.10 2.0 2.1 2.1.1 2.1.2 2.1.3 2.2 2.2.1 2.2.2 2.2.2.1 2.2.2.2 2.2.2.3 2.2.3 2.3 2.4 2.5 2.6 3.0 3.1 3.1.1 3.1.2 TITLE Liquid Effluents

-Abnormal Releases Gaseous Effluents Regulatory Requirements Dose Rate Limits Air Doses Due to Noble Gases in Gaseous Releases Doses to a Member of the Public Measurements and Approximations of Total Radioactivity Sample Collection and Analysis Total Quantities of Radioactivity, Dose Rates and Cumulative Doses Fission and Activation Gases Radioiodine, Tritium and Particulate Releases Gross Alpha Release Total Error Estimation Gaseous Effluent Release Data Radiological Impact Due to Gaseous Releases Gaseous Effluents

-Batch Releases Gaseous Effluents

-Abnormal Releases Solid Waste Regulatory Requirements Solid Radioactive Waste System Reporting Requirements PAGE 7 28 28 28 28 28 29 29 30 30 30 31 31 33 34 34 34 64 64 64 64 ii zECT/ON 3.2 4.0 4.1 4.2 5.0 5.1 5.2 6.0 7.0 7.1 7.1.1 7.1.2 7.2 7.2.1 7.2.2 7.3 7.3.1 7.3.2 TITLE Solid Waste Data Doses to Members of the Public Inside The Site Boundary Regulatory Requirements Demonstration of Compliance Total Dose from Uranium Fuel Cycle (40 CFR 190)Regulatory Requirements Demonstration of Compliance Meteorological Data Program Deviations Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation Regulatory Requirements Description of Deviations Tanks Exceeding Curie Content Limits Regulatory Requirements Description of Deviations Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC)Regulatory Requirement Description of Deviation 65 69 69 69 74 74 74 75 76 76 76 76 76 76 76 7 7 77 Vi

-SECTION 8.0 8.1 8.2 9.0 9.1 9.2 T/T/PA n TITI F IIIII ...77 Changes to the Plant Hatch Offsite Dose Calculation Manual (ODCM)Regulatory Requirements Description of Changes Major Changes to the Liquid, Gaseous or Solid Radwaste Treatment Systems Regulatory Requirements Description of Major Changes 77 77 78 78 78 vi 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 I (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 I (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 vi rA V I IZT n I 1=4 TAI /.-I 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 I (Quarters 1, 2, 3 and 4)2-1 B 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 38 Unit I (Quarters 1, 2, 3 and 4)2-2B Gaseous Effluents

-Elevated Releases 41 Unit 2 (Quarters 1, 2, 3 and 4)2-2C Gaseous Effluents

-Elevated Releases 44 Site (Quarters 1, 2, 3 and 4)2-3A Gaseous Effluents

-Ground Level Releases 47 Unit I (Quarters 1, 2, 3 and 4)2-3B Gaseous Effluents

-Ground Level Releases 49 Unit 2 (Quarters 1, 2, 3 and 4)2-3C Gaseous Effluents

-Ground Level Releases 51 Site (Quarters 1, 2, 3 and 4)2-4A Air Doses Due to Noble Gases in Gaseous 54 Releases -Unit I (Quarters 1, 2, 3 and 4)vi TAI I=I VZ T nP TA Al F-4Z pArI:: 2-4B Air Doses Due to Noble Gases in Gaseous 55 Releases-Unit 2 (Quarters 1, 2, 3 and 4)2-5A Doses to a Member of the Public Due to 56 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 57 Radioiodine, Tritium, and Particulates in Gaseous Releases -Unit 2 (Quarters 1, 2, 3 and 4)2-6 Minimum Detectable Concentration

-58 Gaseous Sample Analyses 2-7A Gaseous Effluents

-Batch Release 59 Summary Unit 1 2-7B Gaseous Effluents

-Batch Release 60 Summary Unit 2 2-8A Gaseous Effluents

-Abnormal Release 61 Summary Unit I 2-8B Gaseous Effluents

-Abnormal Release 62 Summary Unit 2 2-8C Gaseous Effluents

-Abnormal Release 63 Summary Site 3-1 Solid Waste and Irradiated Fuel Shipments 66 4-1 Doses to a Member of the Public Due to 70 Activities Inside The Site Boundary vii ATTACHMENT APPENDIX $APPENDIX B ADDENDUM TITI P 10 A f2 =79 Carbon-14 Summary of Groundwater Protection Program 2012 Program Deviations 81 83 viii 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 1 E-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, 1-131, 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 1 E-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.1 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, 1-131, 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

1. Gamma Isotopic 2. Dissolved or entrained noble gas 3. Tritium 4. Gross Alpha 5. Sr-89 & Sr-90 FREQUENCY Each Batch Each Batch Monthly Composite Monthly Composite Quarterly Composite METHOD Gamma Spectroscopy with computerized data reduction Gamma Spectroscopy with computerized data reduction Distillation and liquid scintillation counting Gas flow proportional counting Chemical separation and gas flow proportional or scintillation counting Chemical separation and liquid scintillation counting 6. Fe-55 Quarterly Composite 2 Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2 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-1 34, Cs-1 37, 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 a qualified Chemistry Technician.

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.3 1.4 Measurements and Approximations of Total Radioactivity for Groundwater Outfalls -Y22NO03A/12B and Y22NO08A 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 outfall's 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

1. Gamma Isotopic 2. Tritium 3. Gross Beta*4. Sr-89 & Sr-90**FREQUENCY Weekly Composite Weekly Composite Quarterly Composite Quarterly Composite (as required)METHOD Gamma Spectroscopy with computerized data reduction Distillation and liquid scintillation counting Chemical separation and gas flow proportional or scintillation counting Chemical separation and gas flow 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.

4 Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2 keV or lower. The detectors are shielded by four inches of lead. A weekly composite sample is typically counted to Environmental MDC's 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-1 34, Cs-1 37, 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%.5 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 1-1 B 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 (MDC's) used for analyses are found in Table 1-4.The values for the four categories of Tables 1 -1A, 1-1 B, 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.

6 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.7 Table 1-1A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Liquid Effluents

-Summation Of All Releases Unit: 1 Starting:

1-Jan- 2013 Ending: 31-Dec-2013 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 2.67E-03 6.63E-04 1. IOE-03 7.45E-04 2. Average diluted concentration during period uCi/mL 7.94E-09 2.79E-09 1.31E-09 2.87E-08 3. Percent of Applicable Limit % * * * *B. Tritium 1. Total Release Curies 8.34E+00 5.17E+00 1.86E+01 8.01E-01 2. Average diluted Concentration during period uCi/mL 2.48E-05 2.17E-05 2.22E-05 3.08E-05 3. Percent of Applicable Limit %* * * *C. Dissolved and Entrained Gases 1. Total Release Curies 4.17E-04 3.12E-05 1.OOE-04 6.91E-06 2. Average diluted Concentration during period uCi/mL 1.24E-09 1.31E-10 1.20E-10 2.66E-10 3. Percent of Applicable Limit % * * * *D: Gross Alpha Radioactivity

1. Total Release Curies 7.97E-07 4.76E-06 O.OOE+00 O.OOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 1.56E+06 1.17E+06 4.05E+06 9.10E+04 F. Volume of Dilution Water Used Liters 3.36E+08 2.38E+08 8.35E+08 2.60E+07* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.8 Table 1-1B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Liquid Effluents

-Summation Of All Releases Unit: 2 Starting:

1-Jan- 2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter Type of Effluent A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha)2. Average diluted concentration during period 3. Percent of Applicable Limit 4TH Quarter 1.52E-03 3.33E-10 Curies uCi/mL 9.05E-03 1.53E-09 2.19E-03 4.54E-10 1.32E-03 2.37E-10 B. Tritium 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit C. Dissolved and Entrained Gases 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Curies uCi/mL Curies uCi/mL Curies 9.95E+00 1.68E-06 8.19E-05 1.38E-11 0.O0E+00 5.34E+06 5.92E+09 7.83E+00 1.63E-06 4.48E-04 9.31E-1 1 3.79E-08 5.18E+06 4.82E+09 4.68E+00 8.40E-07 8.38E-05 1.50E-11 0.OOE+00 6.08E+06 5.57E+09 1.07E+00 2.33E-07 1.70E-04 3.72E-11 0.OOE+00 2.48E+06 4.58E+09 Liters Liters* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.9 Table 1-IC Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Liquid Effluents

-Summation Of All Releases Unit: Site Starting:

1-Jan- 2013 Ending: 31-Dec-2013 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 1.18E-02 2.85E-03 2.42E-03 2.27E-03 2. Average diluted concentration during period uCi/mL 1.88E-09 5.64E-10 3.77E-10 4.93E-10 3. Percent of Applicable Limit %* * * *B. Tritium 1. Total Release Curies 1.85E+01 1.30E+01 2.32E+01 1.87E+00 2. Average diluted Concentration during period uCi/mL 2.95E-06 2.57E-06 3.62E-06 4.06E-07 3. Percent of Applicable Limit %* * * *C. Dissolved and Entrained Gases 1. Total Release Curies 5.26E-04 4.80E-04 1.84E-04 1.77E-04 2. Average diluted Concentration during period uCi/mL 8.41E-11 9.49E-11 2.88E-11 3.85E-11 3. Percent of Applicable Limit %* * * *D: Gross Alpha Radioactivity

1. Total Release Curies 8.25E-07 4.80E-06 O.OOE+00 O.OOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 6.89E+06 6.35E+06 1.01E+07 2.57E+06 F. Volume of Dilution Water Used Liters 6.26E+09 5.05E+09 6.41E+09 4.60E+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- 2013 Liquid Effluents Unit: 1 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nuclides Released Fission & Activation Products No Nudides Found Unit Curies Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+0O 0.OOE+00 0.OOE+00 0.OOE-t00 O.OOE+00 0.OOE-i00 0.OOE+0O O.OOE+00 O.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nuclides Found Curies Curies Zeroes in this table indicate 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- 2013 Liquid Effluents Unit: 1 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nuclides Released Fission & Activation Products As-76 Co-57 Co-58 Co-60 Cr-51 Fe-55 Fe-59 Mn-54 Mn-56 Na-24 Nb-97 Sr-89 Sr-90 Sr-92 Zn-65 Au-199 Cs-137 La-140 Sb-122 Sb-124 Zn-69M Ag-110M Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 0.OOE+00 O.OOE+00 4.38E-05 1.58E-03 9.87E-05 1.51E-04 2.33E-06 1.54E-04 0.OOE+00 8.85E-06 2.87E-04 3.70E-05 0.OOE+00 5. 12E-07 7.27E-05 0.OOE+00 1.88E-04 0.OOE+00 3.33E-07 2.01E-06 0.OOE+00 0.OOE+O0 0.OOE+00 4.57E-05 2.52E-04 0.OOE+00 1. 15E-04 0.OOE+00 5.99E-05 8.43E-07 7.52E-05 8.52E-06 1.89E-05 0.OOE-i00 0.OOE+00 2.44E-05 0.OOE+00 6.29E-05 0.OOE+00 0.OOE+00 0.COE+00 0.OOE+00 0.OOE+00 3.90E-07 5.38E-05 4.39E-04 0.OOE+00 0.OOE+00 O.OOE+00 9.61E-05 1.56E-05 3.20E-04 2.09E-05 0.OOE+00 0.OOE+00 5.52E-07 4. 13E-05 0.OOE+00 1.O1E-04 2.54E-06 0.OOE+00 0.OOE+00 6.46E-06 2.99E-06 0.OOE+00 3.42E-05 1.52E-04 2.23E-05 5.73E-05 0.OOE+00 8.77E-05 7.76E-05 1.57E-06 6.88E-06 0.OOE+00 6.04E-07 0.OOE+00 2.69E-04 1.71lE-05 8.86E-06 0.OOE+00 0.OOE+00 0.OOE+00 7.29E-06 Curies 3.92E-05 0.OOE+00 0.OOE+00 0.OOE+00 Curies 2.67E-03 6.63E-04 1.10E-03 7.45E-04 Zeroes in this table indicate 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 -2013 Liquid Effluents Unit: 1 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Nuclides Released Trtium H-3 Unit Curies Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter 8.34E+00 5.17E+00 1.86E+01 8.01E-01 2.54E-04 6.14E-06 2.98E-06 5.54E-06 1.63E-04 2.51E-05 9.75E-05 1.38E-06 4.17E-04 3.12E-05 1.00E-04 6.91E-06 Dissolved And Entrained Gases Xe-133 Xe-135 Total For Period Curies Curies Cures Curies Gross Alpha Radioactivity G-Alpha 7.97E-07 4.76E-06 O.OOE+O0 O.OOE+O0 Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.

13 Table 1-25 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Liquid Effluents Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Curies 1.73E-02 2.09E-02 3.43E-02 1.11E-02 Nuclides Released Fission & Activation Products No Nuclides Found Tritium H-3 Dissolved And Entrained Gases No Nudides Found Gross Alpha Radioactivity No Nuclides Found Curies Curies O.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate 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 -2013 Liquid Effluents Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Y-92 Curies 2.39E-05 5.67E-05 O.OOE+00 O.OOE+00 As-76 Curies 1.72E-05 1.72E-05 O.OOE+00 3.79E-05 Co-58 Curies 4.85E-04 7.33E-05 7.87E-05 9.OOE-05 Co-60 Curies 2.97E-03 4.71E-04 2.84E-04 1.84E-04 Cr-51 Curies 1.04E-03 5.85E-06 1.67E-05 1.76E-05 Fe-55 Curies 7.57E-05 8.93E-05 O.OOE+00 1.73E-05 Fe-59 Curies 3.37E-05 O.OOE+00 O.OOE+00 O.OOE+00 1-131 Curies 0.OOE+00 1.09E-06 6.20E-06 3.53E-05 1-133 Curies 1.68E-05 8.48E-06 1.08E-05 2.97E-05 Mn-54 Curies 2.12E-03 2.53E-04 2.53E-04 1.13E-04 Mn-56 Curies 2.40E-04 6.96E-05 5.72E-05 1.52E-04 Na-24 Curies 7.17E-04 3.81E-04 2.27E-04 2.82E-04 Nb-95 Curies 1.92E-05 9.89E-07 O.O0E+00 O.OOE+00 Nb-97 Curies 1.55E-04 4.55E-04 2.41E-05 1.58E-05 Sr-89 Curies 1.00E-04 6.02E-05 1.10E-04 4.55E-05 Sr-91 Curies 3.08E-05 8.06E-06 O.OOE+00 8.32E-05 Sr-92 Curies 1.58E-05 1.96E-06 O.OOE+00 1.69E-05 Y-91M Curies 1.47E-05 3.77E-05 9.30E-06 1.40E-05 Zn-65 Curies 3.79E-04 8.36E-05 1.43E-04 8.45E-05 Zr-95 Curies 1.1OE-05 O.OOE+00 O.OOE+00 O.OOE+00 Au-199 Curies O.OOE+00 O.OOE+00 2.21E-06 5.32E-06 Ba-140 Curies O.OOE+O0 O.OOE+00 O.OOE+O0 4.50E-05 Ce-141 Curies 7.56E-06 O.OOE+O0 O.OOE+O0 6.40E-06 Cs-137 Curies 2.42E-04 3.61E-05 6.07E-05 1.59E-05 La-140 Curies 7.96E-06 2.83E-05 3.62E-06 2.83E-05 Zeroes in this table indicate 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- 2013 Liquid Effluents Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Sb-124 Sb-125 Tc-99M Zn-69M Ag-iIOM Total For Period Unit 1ST Quarter Curies 2.40E-04 Curies 2.29E-05 Curies 1.85E-05 Curies 3.79E-05 Curies 7.47E-06 Curies 9.05E-03 2ND Quarter 3.33E-06 0.00E+00 1.30E-05 2.71E-05 6.13E-06 2.19E-03 3RD Quarter 0.OOE+00 O.OOE+00 2.27E-05 9.16E-06 O.OOE+00 1.32E-03 4TH Quarter O.OOE+00 O.OOE+00 3.62E-05 1.62E-04 6.68E-06 1.52E-03 Tritium H-3 Curies 9.93E+00 7.81E+00 4.65E+00 1.05E+00 Dissolved And Entrained Gases Kr-88 Xe-133 Xe-135 Xe-133M Xe-135M Total For Period Curies Curies Curies Curies Curies Curies Curies 1.25E-06 9.65E-06 7.10E-05 0.OOE+00 0.OOE+00 0.OOE+00 1.74E-04 2.75E-04 0.OOE+00 0.OOE+00 0.OOE+0O 4.35E-05 4.04E-05 0.OOE+00 0.OOE+00 O.OOE+00 3.39E-05 5.35E-05 2.6 1E-06 8.02E-05 8.19E-05 0.OOE+00 4.48E-04 3.79E-08 8.38E-05 0.OOE+0Q 1.70E-04 0.OOE+00 Gross Alpha Radioactivity G-Alpha Zeroes in this table indicate 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- 2013 Liquid Effluents Unit: Site Starting:

1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nuclides Released Fission & Activation Products No Nuclides Found Unit Curies Curies Tritium 0.OOE+00 1. 73E-02 0.OOE+00 2.09E-02 0.OOE+00 3.43E-02 O.OOE+00 1.11E-02 H-3 Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nuclides Found Curies Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate 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- 2013 Liquid Effluents Unit: Site Starting:

1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Y-92 Curies 2.39E-05 5.67E-05 O.OOE+00 O.OOE+00 As-76 Curies 1.72E-05 1.72E-05 O.OOE+00 4.09E-05 Co-57 Curies O.OOE+O0 O.OOE+O0 3.90E-07 O.OOE+OO Co-58 Curies 5.32E-04 1.19E-04 1.32E-04 1.24E-04 Co-60 Curies 4.58E-03 7.23E-04 7.23E-04 3.36E-04 Cr-51 Curies 1.13E-03 5.85E-06 1.67E-05 3.99E-05 Fe-55 Curies 2.30E-04 2.04E-04 O.OOE+O0 7.46E-05 Fe-59 Curies 3.61E-05 O.OOE+O0 O.OOE+O0 O.OOE+O0 1-131 Curies O.OOE+O0 1.09E-06 6.20E-06 3.53E-05 1-133 Curies 1.68E-05 8.48E-06 1.08E-05 2.97E-05 Mn-54 Curies 2.28E-03 3.13E-04 3.49E-04 2.01E-04 Mn-56 Curies 2.40E-04 7.05E-05 7.28E-05 2.29E-04 Na-24 Curies 7.26E-04 4.56E-04 5.47E-04 2.84E-04 Nb-95 Curies 1.92E-05 9.89E-07 0.00E+00 O.OOE+00 Nb-97 Curies 4.42E-04 4.63E-04 4.50E-05 2.27E-05 Sr-89 Curies 1.38E-04 7.91E-05 1.10E-04 4.55E-05 Sr-90 Curies O.OOE+00 O.OOE+00 O.OOE+00 6.04E-07 Sr-91 Curies 3.08E-05 8.06E-06 O.OOE+00 8.32E-05 Sr-92 Curies 1.63E-05 1.96E-06 5.52E-07 1.69E-05 Y-91M Curies 1.47E-05 3.77E-05 9.30E-06 1.40E-05 Zn-65 Curies 4.56E-04 1.08E-04 1.85E-04 3.54E-04 Zr-95 Curies 1.10E-05 O.OOE+00 O.OOE+00 O.OOE+00 Au-199 Curies O.OOE+00 O.OOE+00 2.21E-06 2.24E-05 Ba-140 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.50E-05 Ce-141 Curies 7.56E-06 0.00E+00 0.00E+00 6.40E-06 Zeroes in this table indicate 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- 2013 Liquid Effluents Unit: Site Starting:

1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Cs-137 La-140 Sb-122 Sb-124 Sb-125 Tc-99M Zn-69M Ag-110M Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 4.30E-04 7.96E-06 3.33E-07 2.42E-04 2.29E-05 1.85E-05 3.79E-05 5.85E-05 9.90E-05 2.83E-05 O.OOE+00 3.33E-06 O.OOE+00 1.30E-05 2.71E-05 6.13E-06 1.61E-04 6.16E-06 0.OOE+00 0.00E+00 0.OOE+00 2.27E-05 1.56E-05 0.OOE+00 2.48E-05 2.83E-05 0.00E+00 0.00E+00 0.00E+00 3.62E-05 1.69E-04 6.68E-06 2.27E-03 2ND Quarter 3RD Quarter 4TH Quarter 1. 18E-02 2.85E-03 2.42E-03 Tritium H-3 Dissolved And Entrained Gases Kr-88 Xe-133 Xe-135 Xe-133M Xe-135M Total For Period Gross Alpha Radioactivity G-Alpha Curies 1.84E+01 1.30E+01 2.32E+01 1.86E+00 Curies Curies Curies Curies Curies Curies Curies 1.25E-06 2.91E-04 2.34E-04 0.00E+00 0.00E+00 0.00E+00 1.80E-04 3.OOE-04 0.00E+00 0.OOE+00 0.00E+00 4.65E-05 1.38E-04 0.00E+00 0.00E+00 O.OOE+00 3.94E-05 5.49E-05 2.61E-06 8.02E-05 5.26E-04 8.25E-07 4.80E-04 4.80E-06 1.84E-04 0.00E+00 1.77E-04 O.OOE+00 Zeroes in this table indicate 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- 2013 Doses to a member of the public due to Liquid Releases Unit: 1 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Cumulative Doses Per Quarter Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body ODCM Lint 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.50E+00 Units mRem mRem mRem mRem mRem mRem mRem 1ST Qtr 0/0 ODCM 2ND Qtr 0/o ODCM 6.81E-04 1.36E-02 2.16E-04 4.31E-03 9.88E-04 1.98E-02 1.92E-04 3.85E-03 3.85E-04 7.71E-03 1.42E-04 2.84E-03 1.05E-03 2.09E-02 3.44E-04 6.87E-03 1.60E-04 3.19E-03 7.07E-05 1.41E-03 5.62E-05 1. 12E-03 3.81E-05 7.62E-04 7.65E-04 5.10E-02 2.47E-04 1.65E-02 3RD Qtr 0/o ODCM 4TH Qtr 0/o ODCM 3.78E-04 7.56E-03 7.17E-05 1.43E-03 4.08E-04 8. 16E-03 1.78E-04 3.57E-03 3.15E-04 6.31E-03 9.37E-05 1.87E-03 6.72E-04 1.34E-02 1.69E-04 3.39E-03 1.90E-04 3.79E-03 1.OOE-05 2.OOE-04 1.32E-04 2.64E-03 4.30E-06 8.61E-05 5.02E-04 3.35E-02 9.79E-05 6.53E-03 Cumulative Doses per Year Organ ODCM Lmt Bone 1.OOE+01 GI-Uli 1.OOE+01 Kidney 1.OOE+01 Liver 1.OOE+01 Lung 1.OOE+01 Thyroid 1.00E+01 Total Body 3.OOE+00 Units Year to Ending Date mRem 1.35E-03 mRem 1.77E-03 mRem 9.36E-04 mRem 2.23E-03 mRem 4.30E-04 mRem 2.31E-04 mRem 1.61E-03%/o ODCM 1.35E-02 1.77E-02 9.36E-03 2.23E-02 4.30E-03 2.31E-03 5.37E-02 Receptor MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult Limit Ann Cum Organ Liq Dose Ann Cum Organ UIq Dose Ann Cum Organ Liq Dose Ann Cum Organ Liq Dose Ann Cum Organ Uq Dose Ann Cum Organ Uq Dose Ann Cum Tot Body Uq Dose 20 Table 1-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Doses to a member of the public due to Liquid Releases Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Cumulative Doses Per Quarter Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body ODCM Lmt 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.50E+00 Units mRem mRem mRem mRem mRem mRem mRem 1ST Qtr 0/o ODCM 2ND Qtr 9.57E-04 1.91E-02 1.72E-04 2.17E-03 4.34E-02 4.31E-04 6.08E-04 1.22E-02 1.62E-04 1.61E-03 3.22E-02 3.34E-04 2.18E-04 4.36E-03 8.95E-05 8.93E-05 1.79E-03 7.91E-05 1.16E-03 7.76E-02 2.55E-04%/ ODCM 7.4-4E-03 8.62E-03 3.24E-03 6.69E-03 1.79E-03 1.58E-03 1.70E-02 3RD Qtr 2.76E-04 2.95E-04 1.94E-04 4.51E-04 7.67E-05 8.76E-05 3.09E-04--/% ODCM 4TH Qtr 5.52E-03 8.68E-05 5.89E-03 2.09E-04 3.87E-03 6.89E-05 9.02E-03 1.53E-04 1.53E-03 2.07E-05 1.75E-03 2.85E-04 2.06E-02 1.06E-04 0/6 ODCM 1.74E-03 4.18E-03 1.38E-03 3.05E-03 4.14E-04 5.71E-03 7.04E-03 Cumulative Doses per Year Organ ODCM Lmt Bone 1.OOE+01 GI-Lli 1.OQE+O1 Kidney 1.OOE+01 Liver 1.OOE+01 Lung 1.OOE+01 Thyroid 1.OOE+01 Total Body 3.OOE+00 Units Year to Ending Date mRem 1.49E-03 mRem 3.10E-03 mRem 1.03E-03 mRem 2.55E-03 mRem 4.05E-04 mRem 5.41E-04 mRem 1.83E-03%/o ODCM 1.49E-02 3. IOE-02 1.03E-02 2.55E-02 4.05E-03 5.41E-03 6.11E-02 Receptor MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult MAX INDIVIDUAL LIQUID / Adult Limit Ann Cum Organ Liq Dose Ann Cum Organ Liq Dose Ann Cum Organ liq Dose Ann Cum Organ Liq Dose Ann Cum Organ Liq Dose Ann Cum Organ Uq Dose Ann Cum Tot Body Uq Dose 21 Table 1-4 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 MINIMUM DETECTABLE CONCENTRATIONS

-LIQUID SAMPLE ANALYSES STARTING:

1-Jan-2013 ENDING: 31-Dec-2013 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/mI Cs-137 1.62E-08 uCi/mI Ce-141 1.92E-08 uCi/ml Ce-144 8.83E-08 uCi/ml 1-131 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.OOE-07 uCi/ml 22 Table 1-5A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2013 Liquid Effluents

-Batch Release Summary Unit: 1 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Liquid Releases 1. Number of batch releases 2. Total time period for Batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release 5. Minimum time period for a batch release 6. Average stream flow during periods of release of liquid effluent into a flowing stream *Units Minutes Minutes Minutes Minutes 1ST Quarter 44 5.69E+03 1.65E+02 1.29E+02 8.70E+01 1.70E+04 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 32 119 3 198 4.57E+03 1.53E+04 4.02E+02 2.60E+04 1.70E+02 1.73E+02 1.55E+02 1.73E+02 1.43E+02 1.29E+02 1.34E+02 1.31E+02 1.10E+02 2.20E+01 9.60E+01 2.20E+01 ( CFS )1.39E+04 1.83E+04 1.55E+03 1.27E+04* Data obtained from United States Geological Survey (USGS) website 23 Table 1-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2013 Liquid Effluents

-Batch Release Summary Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Uquid Releases 1. Number of batch releases 2. Total time period for Batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release 5. Minimum time period for a batch release 6. Average stream flow during periods of release of liquid effluent into a flowing stream *Units Minutes Minutes Minutes Minutes 1ST Quarter 72 6.92E+03 1.30E+02 9.62E+01 7.70E+01 1.70E+04 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 49 38 9 168 5.48E+03 3.95E+03 9.31E+02 1.73E+04 1.45E+02 1.25E+02 1.15E+02 1.45E+02 1.12E+02 1.04E+02 1.03E+02 1.03E+02 8.20E+01 6.70E+01 7.80E+01 6.70E+01 ( CFS )1.39E+04 1.83E+04 1.55E+03 1.27E+04* Data obtained from United States Geological Survey (USGS) website 24 Table 1-6A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2013 Liquid Effluents

-Abnormal Release Summary Unit: 1 Starting:

l-Jan-2013 Ending: 31-Dec-2013 Liquid Releases 1. Number of Releases 2. Total Time For All Releases 3. Maximum Time For A Release 4. Average Time For A Release 5. Minimum Time For A Release 6. Total activity for all releases Units 1ST Quarter 0 Minutes Minutes (Minutes Minutes (Curies )0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 2ND Quarter 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3RD Quarter 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4TH Quarter 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Year Totals 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 25 Table 1-65 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Liquid Effluents

-Abnormal Release Summary Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter 0 0 0 Liquid Releases 1. Number of Releases 2. Total Time For All Releases 3. Maximum Time For A Release 4. Average Time For A Release 5. Minimum Time For A Release 6. Total activity for all releases Minutes Minutes Minutes Minutes (Curies )O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+0O 4TH Quarter 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Year Totals 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 26 Table 1-6C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2013 Liquid Effluents

-Abnormal Release Summary Unit: Site Starting:

1-Jan-2013 Ending: 31-Dec-2013 Liquid Releases 1. Number of Releases 2. Total Time For All Releases 3. Maximum Time For A Release 4. Average Time For A Release 5. Minimum Time For A Release 6. Total activity for all releases Units Minutes Minutes Minutes Minutes (Curies )1ST Quarter 0 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2ND Quarter 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3RD Quarter 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4TH Quarter 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Year Totals 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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 lodine-131, Iodine-1 33, 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-1 31, Iodine-1 33, 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 analysis 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 analysis 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%1-131 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, and 2-3C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all quarters.To complete table 2-1A, 2-1 B, 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, 2-1 B, 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 2-58, 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- 2013 Gaseous Effluents

-Summation Of All Releases Unit: 1 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases 1. Total Release Curies 2.50E+00 2.81E-01 1.06E+00 4.55E+00 2. Average Release rate for period uCi/sec 3.17E-01 3.56E-02 1.34E-01 5.77E-01 3. Percent of Applicable Limit %* * * *B. Radiolodines

1. Total Iodine-131 Curies 9.31E-05 2.22E-05 6.66E-05 1.48E-04 2. Average Release rate for period uCi/sec 1.18E-05 2.81E-06 8.45E-06 1.88E-05 3. Percent of Applicable ULmit %* * * *C. Particulates

1. Particulates ( Half-Lives

> 8 Days ) Curies 1.98E-05 3.30E-05 5.37E-04 3.88E-05 2. Average Release rate for period uCi/sec 2.51E-06 4.18E-06 6.81E-05 4.915E-06 3. Percent of Applicable Limit %* * * *D. Tritium 1. Total Release Curies 4.44E+00 3.81E+00 5.65E+00 2.21E+01 2. Average Release rate for period uCi/sec 5.63E-01 4.83E-01 7.16E-01 2.80E+00 3. Percent of Applicable Limit * * * *E. Gross Alpha 1. Total Release Curies O.OOE+00 O.O0E+00 O.OOE+00 O.OOE+00 2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00* 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- 2013 Gaseous Effluents

-Summation Of All Releases Unit: 2 Starting:

1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter Type of Effluent A. Fission And Activation Gases 4TH Quarter 1. Total Release Curies 2.50E+00 2.79E-01 2. Average Release rate for period uCi/sec 3.17E-01 3.54E-02 3. Percent of Applicable Limit % * *B. Radioiodines

1. Total Iodine-131 Curies 1.05E-04 3.20E-05 2. Average Release rate for period uCi/sec 1.33E-05 4.06E-06 3. Percent of Applicable Limit % *C. Particulates

1. Particulates ( Half-Lives

> 8 Days ) Curies 1.62E-05 2.51E-05 2. Average Release rate for period uCi/sec 2.06E-06 3.19E-06 3. Percent of Applicable Limit %* *D. Tritium 1. Total Release Curies 3.26E+00 4.12E+00 2. Average Release rate for period uCi/sec 4.13E-01 5.23E-01 3. Percent of Applicable Umit * *E. Gross Alpha 1. Total Release Curies O.OOE+00 O.OOE+00 2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.36 1.06E+00 1.34E-01 5.95E-05 7.54E-06 3.03E-05 3.85E-06 5.54E+00 7.03E-01 0.OOE+00 1.19E+01 1.5 1E+00 1 .48E-G4 1.88E-05 3.66E-05 4.645E-06 2.24E+01 2.85E+00 0.OOE+00 Table 2-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2013 Gaseous Effluents

-Summation Of All Releases Unit: Site Starting:

1-Jan-2013 Ending: 31-Dec-2013 1ST Quarter 2ND Quarter 3RD Qu;Type of Effluent A. Fission And Activation Gases Units arter 4TH Quarter 1. Total Release Curies 5.01E+00 5.60E-01 2. Average Release rate for period uCi/sec 6.35E-01 7.1OE-02 3. Percent of Applicable Limit %* *B. Radioiodines

1. Total Iodine-131 Curies 1.98E-04 5.42E-05 2. Average Release rate for period uCi/sec 2.51E-05 6.87E-06 3. Percent of Applicable Limit % * *C. Particulates

1. Particulates ( Half-Uves

> 8 Days ) Curies 3.60E-05 5.81E-05 2. Average Release rate for period uCi/sec 4.56E-06 7.37E-06 3. Percent of Applicable Limit %* *D. Tritium 1. Total Release Curies 7.70E+00 7.93E+00 2. Average Release rate for period uCi/sec 9.76E-O1 1.01E+00 3. Percent of Applicable Limit * *E. Gross Alpha 1. Total Release Curies O.OOE+00 O.OOE+00 2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.37 2.12E+00 2.69E-01 1.26E-04 1.60E-05 5.67E-04 7. 19E-05 1.12E+01 1.42E+00 0.00E+00 0.OOE+00 1.64E+01 2.09E+00 2.97E-04 3.76E-05 7.54E-05 9.561E-06 4.45E+01 5.65E+00 0.OOE+00 Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2013 Gaseous Effluents

-Elevated Level Releases Unit: 1 Starting:

1-Jan- 2013 Ending: 31-Dec-2013 Continuous Mode Nuclides Released Fission Gases Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Ar-41 Curies Kr-85M Curies Xe-133 Curies Xe-135 Curies Total For Period Curies 4.40E-01 1.69E-01 1.30E+00 5.92E-01 2.50E+00 7.60E-05 1.24E-04 2.00E-04 Iodines 1-131 1-133 Total For Period Mn-54 Co-60 Sr-89 Sr-90 Cs-137 Ba-140 Ce-144 1-131P Total For Period Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 0.OOE+00 0.00E+00 1.13E-01 1.67E-01 2.79E-01 2.00E-05 3.42E-05 5.42E-05 0.00E+00 0.00E+00 1.40E-05 5.86E-09 2.27E-08 1.08E-05 O.OOE+00 O.OOE+00 2.48E-05 0.OOE+00 2.12E-01 7.86E-01 6.02E-02 1.06E+00 5.20E-05 6.83E-05 1.20E-04 0.OOE+00 0.OOE+00 1.71E-05 4.86E-08 5.79E-08 1.04E-05 0.OOE+00 0.OOE+00 2.76E-05 1.11E+00 4.11E-01 2.69E+00 3.40E-01 4.55E+00 1 .26E-04 1 .O1E-04 2.27E-04 1.46E-08 8.22E-08 2.08E-05 6.40E-08 0.OOE+00 1.13E-05 1 .29E-07 1.83E-07 3.25E-05 0.OOE+00 0.OOE+00 9.41E-06 0.OOE+00 0.OOE+00 9.89E-06 0.OOE+00 0.OOE-i00 1.93E-05 If Not Detected, Nuclide is Not Reported.