Text

Annual Radioactive Effluent Release Report for 2014, Enclosure 3
	ML15125A059
Person / Time
Site:	Vogtle
Issue date:	12/31/2014
From:	Olive C; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML15125A049	List: ML15125A054; ML15125A056; ML15125A058; NL-15-0803, Annual Radioactive Effluent Release Report for 2014, Enclosure 3; NL-15-0803, E. I. Hatch Radioactive Effluent Release Reports for 2014, Enclosure 1; NL-15-0803, J. M. Farley - Annual Radioactive Effluent Release Report for 2014, Enclosure 2; NL-15-0803, J. M. Farley, E. I. Hatch and Vogtle - Submittal of Annual Radioactive Effluent Release Reports for 2014;
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	NL-15-0803
	Download: ML15125A059 (84)
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Joseph M. Farley Nuclear Plant; Edwin I. Hatch Nuclear Plant; Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2014 Enclosure 3 Vogtle Annual Radioactive Effluent Release Report for 2014

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.

Chemistry Manaer 163

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNITS I AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERA TING LICENSE NOS. NPF-68 AND NPF-81 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1, 2014 TO DECEMBER 31, 2014 Prepared by: age of 164 Reviewed by:.*.~

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VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2014 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-IC Liquid Effluents - Summation of All Releases Site (Quarters 1,2,3, and 4) 15 Table 1-2A Liquid Effluents -Unit I (Quarters 1,2,3, and 4) 16 Table 1-2B Liquid Effluents -Unit I (Quarters 1,2,3, and 4) 19 Page 2 of 82 165

Table 1-2C Liquid Effluents -Unit I (Quarters 1,2,3, and 4) 22 Table 1-3A Doses to a Member of the Public Due to Liquid Releases Unit I (Quarters 1,2,3, and 4) 25 Table 1-3B Doses to a Member of the Public Due to Liquid Releases Unit 2 (Quarters 1,2,3, and 4) 26 Table 1-3C Doses to a Member of the Public Due to Liquid Releases Site (Quarters 1,2,3, and 4) 27 Table 1-4 Minimum Detectable Concentration - Liquid 28 Table 1-5A Liquid Effluents Batch Release Summary Unit I (Quarters 1,2,3, and 4) 29 Table 1-5B Liquid Effluents Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 30 Table 1-5C Liquid Effluents Batch Release Summary Site (Quarters 1,2,3, and 4) 31 Table 1-6A Liquid Effluents Abnormal Release Summary Unit 1 (Quarters 1,2,3, and 4) 32 Table 1-6B Liquid Effluents Abnormal Release Summary Unit I (Quarters 1,2,3, and 4) 33 Table 1-6C Liquid Effluents Abnormal Release Summary Site (Quarters 1,2,3, and 4) 34 2.0 Gaseous Effluents 35 2.1 Regulatory Requirements 35 2.1.1 Dose Rate Limits 35 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 35 Page 3 of 82 166

2.1.3 Doses to a Member of the Public 35 2.2 Measurements and Approximations of Total Radioactivity 36 2.2.1 Sample Collection and Analysis 36 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 37 2.2.2.1 Fission and Activation Gases 37 2.2.2.2 Radioiodines, Tritium and Particulate Releases 37 2.2.2.3 Gross Alpha Release 37 2.2.3 Total Error Estimation 38 2.3 Gaseous Effluent Release Data 39 2.4 Radiological Impact Due to Gaseous Releases 40 2.5 Gaseous Effluents - Batch Releases 40 2.6 Gaseous Effluents - Abnormal Releases 40 Table 2-IA Gaseous Effluents Summation of All Releases Unit I (Quarters 1,2,3, and 4) 41 Table 2-1 B Gaseous Effluents Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 42 Table 2-IC Gaseous Effluents Summation of All Releases Site (Quarters 1,2,3, and 4) 43 Table 2-2A Gaseous Effluents Mixed Mode Releases Unit 1 (Quarters 1,2,3, and 4) 44 Table 2-2B Gaseous Effluents Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 46 Page 4 of 82 167

Table 2-2C Gaseous Effluents Mixed Mode Releases Site (Quarters 1,2,3, and 4) 48 Table 2-3A Gaseous Effluents Ground Level Releases Unit 1 (Quarters 1,2,3, and 4) 50 Table 2-3B Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 52 Table 2-3C Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 54 Table 2-4A Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 56 Table 2-4B Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 57 Table 2-4C Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 58 Table 2-5A Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 59 Table 2-5B Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 60 Table 2-5C Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 61 Table 2-6 Minimum Detectable Concentrations - Gaseous 62 Table 2-7A Gaseous Effluents - Batch Release Summary Unit I (Quarters 1,2,3, and 4) 63 Page 5 of 82 168

Table 2-7B Gaseous Effluents - Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 64 Table 2-7C Gaseous Effluents - Batch Release Summary Site (Quarters 1,2,3, and 4) 65 Table 2-8A Gaseous Effluents - Abnormal Release Summary Unit I (Quarters 1,2,3, and 4) 66 Table 2-8B Gaseous Effluents - Abnormal Release Summary Unit 2 (Quarters 1,2,3, and 4) 67 Table 2-8C Gaseous Effluents - Abnormal Release Summary Site (Quarters 1,2,3, and 4) 68 3.0 Solid Waste 69 3.1 Regulatory Requirements 69 3.1.1 Solid Radioactive Waste System 69 3.1.2 Reporting Requirements 69 3.2 Solid Waste Data 69 Table 3-1 Solid Waste and Irradiated Fuel Shipments 70 4.0 Doses to Members of the Public Inside the Site Boundary 75 4.1 Regulatory Requirements 75 4.2 Demonstration of Compliance 75 Table 4-1 Doses to Members of the Public Due to Activities Inside the Site Boundary 76 5.0 Total Dose from Uranium Fuel Cycle (40CFRI90) 78 5.1 Regulatory Requirements 78 5.2 Demonstration of Compliance 78 Page 6 of 82 169

6.0 Meteorological Data 78 7.0 Program Deviations 79 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 79 7.1.1 Regulatory Requirement 79 7.1.2 Description of Deviations 79 7.2 Tanks Exceeding Curie Content Limits 80 7.2.1 Regulatory Requirements 80 7.2.2 Description of Deviations 80 8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 80 8.1 Regulatory Requirements 80 8.2 Description of Changes 80 9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 81 9.1 Regulatory Requirements 81 9.2 Description of Major Changes 81 Appendix A Carbon-14 82 Page 7 of 82 170

1.0 Liquid Effluents 1.1 Regulatory Requirements 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 gCi/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, 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 1E-04 jiCi/ml total activity.

For gross alpha in liquid radwaste, the ECL is 2 E-09 jiCi/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 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, 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, 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

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 Page 9 of 82 172

1.3.1 Total Radioactivity Determination cont'd 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.

Tritium, Gross Alpha, Sr-89, Sr-90, Fe-55 and Ni-63 are, in some cases, analyzed offsite.

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. Ifthe release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for approval and release. When the release is completed, the necessary data from the release (i.e., release volume, etc.) are provided by the Operations Department to the Chemistry Department. These data are input 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 1.23 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 cont'd

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-iB, 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 2014 Page 12 of 82 175

Table 1-1 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Summation of All Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 2.62E-02 9.05E-03 3.33E-02 3.34E-02

2. Average diluted concentration during period uCi/mL 2.18E-09 2.71E-09 4.48E-09 6.86E-09

3. Percent of Applicable Umit B. Tritium

1. Total Release Curies 4.38E+02 1.89E+02 3.40E+02 1.09E+02

2. Average diluted Concentration during period uCi/mL 3.65E-05 5.66E-05 4.58E-05 2.24E-05

3. Percent of Applicable Umit C. Dissolved and Entrained Gases

1. Total Release Curies 7.03E-06 4.30E-04 3.15E-04 1.80E-05

2. Average diluted Concentration during period uCi/mL 5.86E-13 1.28E-10 4.25E-11 3.70E-12

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution) Liters 3.64E+i07 4.09E+07 4.59E+07 3.35E4-07 F. Volume of Dilution Water Used Liters 1.20E+10 3.30E+09 7.37E+09 4.83E+09

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

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Table 1-1 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Summation of All Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 2.61E-02 9.25E-03 3.33E-02 3.34E-02

2. Average diluted concentration during period uCi/mL 2.35E-09 2.74E-09 4.48E-09 6.88E-09

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 4.39E+02 2.23E+02 3.40E+02 1.09E+02

2. Average diluted Concentration during period uCi/mL 3.94E-05 6.60E-05 4.58E-05 2.24E-05

3. Percent of Applicable Limit C. Dissolved and Entrained Gases

1. Total Release Curies 7.03E-06 4.30E-04 3.15E-04 1.80E-05

2. Average diluted Concentration during period uCi/mL 6.32E-13 1.27E-10 4.25E-11 3.71E-12

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.00E4-OO E: Waste Vol Release (Pre-Dilution) Liters 3.59E4-07 3.98E+07 3.75E+07 2.56E+07 F. Volume of Dilution Water Used Liters 1.11E+10 3.34E+09 7.38E+09 4.83E+09

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

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Table 1-1 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Summation of All Releases Unit: Site Starting: l-Jan-2014 Ending: 31-Dec-2014 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 5.23E-02 1.83E-02 6.65E-02 6.67E-02

2. Average diluted concentration during period uCi/mL 2.26E-09 2.73E-09 4.48E-09 6.87E-09

3. Percent of Applicable Limit B. Tritum

1. Total Release Curies 8.77E+02 4.12E+02 6.80E+02 2.17E+02

2. Average diluted Concentration during period uCi/mL 3.79E-05 6.13E-05 4.58E-05 2.24E-05

3. Percent of Applicable Limit C. Dissolved and Entrained Gases

1. Total Release Curies 1.41E-05 8.59E-04 6.31E-04 3.60E-05

2. Average diluted Concentration during period uCi/ml 6.08E-13 1.28E-10 4.25E-11 3.70E-12

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution) Liters 7.24E+07 8.07E4-07 8.34E+07 *5.91E+07 F. Volume of Dilution Water Used Liters 2.31E+10 6.63E+09 1.48E+10 9.65E+09

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

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Table 1-2 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter ITH Quarter Fission & Activation Products Fe-55 Curies 4.08E-05 4.59E-04 O.OOE+O0 O.OOE+O0 Total For Period Curies 4.08E-05 4.59E-04 O.OOE+00 O.OOE+00 Tritium H-3 Curies 6.88E-02 9.29E-02 7.52E-02 7.37E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha Radioactivity No Nudides Found Curies O.OOE+O0 O.OOE+O0 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.

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Table 1-2 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch mode Nudides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-60 Curies 2.81E-03 6. 12E-04 4.32E-03 6.36E-04 Sr-89 Curies 6.32E-06 1.56E-07 O.OOE+OO 0.OOE+00 Co-57 Curies 1.65E-05 5.08E-06 2.87E-05 1.14E-07 Zn-65 Curies 9.59E-05 1.0gE-05 6.33E-05 2.22E-06 Te-125M Curies 1.1IOE-02 5.36E-04 1.02E-02 2.50E-02 Fe-59 Curies 1.19E-05 O.OOE+00 1.49E-04 4.26E-05 Cs-134 Curies 1.19E-04 9.26E-05 6.58E-05 2.86E-06 Mo-99 Curies O.OOE+0O O.OaE+OO 4.03E-07 O.OOE+OO Sb-125 Curies 2.69E-04 O.OOE+OO 2.57E-04 2.94E-04 Tc-99M Curies O.OOE+OO O.OOE+OO 4. lOE-07 0.OOE+00 Rb-86 Curies O.OOE+OO 1.51E-06 0.OOE+ 00 0.OOE+00 Sn-l17M Curies 3.OOE-06 O.OOE+OO 1.27E-05 2.81E-05 Sr-90 Curies O.OOE+OO O.OOE+00 8.42E-07 O.OOE+O0 Te-129 Curies O.OOE+OO O.OOE+00 O.OOE+00 2.57E-05 Te-131M Curies O.OOE+00 O.OOE+0O 0.OOE+00 5.37E-06 Rh-105 Curies O.OOE+OO O.OOE+0O 2.03E-05 1.30E-05 Mn-54 Curies 1.80E-04 4.18E-05 3.52E-04 4.15E-05 Cr-51 Curies 4.58E-04 O.OOE+OO 1.97E-03 5.25E-04 Fe-55 Curies 3.25E-03 1.02E-03 6.24E-03 2.00E-03 Zr-95 Cures O.OOE+0O O.OOE+OO 2.OOE-04 1.59E-05 Te-132 Curies O.OOE+0O O.OOE+OO 1.35E-05 1.26E-05 Nb-95 Curies 1.22E-05 1.52E-06 3.84E-04 5.80E-05 Cs-137 Curies 8.43E-04 7.33E-04 6.79E-04 1.82E-04 Ni-63 Curies 1.58E-03 7.83E-04 1.64E-03 2.99E-03 1-132 Curies O.OOE+OO O.OOE+OO 1.36E-05 6.72E-06 Co-58 Curies 5.42E-03 4.76E-03 6.61E-03 1.47E-03 Total For Period Curies 2.61E-02 8.59E-03 3.33E-02 3.34E-02 Page 17 of 82 180

Table 1-2 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 aitch Mode Nudides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 4.38E+02 1.89E+02 3.40E+02 1.09E+02 Dissolved And Entrained Gases Xe-133 Curies 7.03E-06 4.12E-04 3.15E-04 1.80E-05 Xe-131M Curies O.OOE+00 O.OOE+00 2.10E-07 O.OOE+00 Xe-135 Curies O.OOE+O0 1.73E-05 1.87E-07 O.OOE+O0 Total For Period Curies 7.03E-06 4.30E-04 3.15E-04 1.80E-05 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 18 of 82 181

Table 1-2 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+O0 O.OOE+O0 OOOE+O0 O.OOE+O0 Tritium H-3 Curies 7.40E-02 5.53E-02 5.60E-02 3.03E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha Radioactivity No Nudides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 19 of 82 182

Table 1-2 B VogUe Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Zn-65 Curies 9.59E-05 l09E-05 6.33E-05 2.22E-06 Sb-125 Curies 2.69E-04 O.OOE+00 2.57E-04 2.94E-04 Te-129 Curies O.OOE+00 O.OOE+00 O.OOE+00 2.57E-05 Te-131M Curies O.OOE+00 O.OOE+00 O.OOE+00 5.37E-06 Sn-117M Curies 3.OOE-06 O.OOE+00 1.27E-05 2.81E-05 1-132 Curies O.OOE+0O O.OOE+00 1.36E-05 6.72E-06 Rb-86 Curies O.OOE+00 1.51E-06 O.OOE+00 O.OOE+00 Zr-95 Curies 0.00E+00 O.OOE+00 2.OOE-04 1.59E-05 Co-58 Curies 5.42E-03 4.99E-03 6.61E-03 1.47E-03 Fe-59 Curies 1.19E-05 O.OOE+O0 1.49E-04 4.26E-05 Mn-54 Curies 1.80E-04 4.18E-05 3.52E-04 4.15E-05 Cs-134 Curies 1.19E-04 9.26E-OS 6.58E-05 2.86E-06 Rh-105 Curies O.OOE+O0 O.OOE+O0 2.03E-05 1.30E-05 Sr-89 Curies 6.32E-06 1.56E-07 O.OOE+O0 O.OOE+O0 Sr-90 Curies O.OOE+O0 O.OOE+O0 8.42E-07 O.OOE+O0 Nb-95 Curies 1.22E-05 1.52E-06 3.84E-04 S.80E-05 Cs-137 Curies 8.43E-04 8.12E-04 6.79E-04 1.82E-04 Co-60 Curies 2.81E-03 7.38E-04 4.32E-03 6.36E-04 Tc-99M Curies O.OOE+O0 O.OOE+O0 4.1OE-07 O.OOE+O0 Co-57 Curies 1.65E-05 5.08E-06 2.87E-05 1.14E-07 Te-125M Curies 1.1OE-02 5.36E-04 1.02E-02 2.50E-02 Mo-99 Curies O.OOE+O0 O.OOE+O0 4.03E-07 O.OOE+O0 Cr-51 Curies 4.58E-04 O.OOE+O0 1.97E-03 5.25E-04 Fe-55 Curies 3.25E-03 1.13E-03 6.24E-03 2.OOE-03 Te-132 Curies O.OOE+O0 O.OOE+O0 1.35E-05 1.26E-05 Ni-63 Curies 1.58E-03 8.36E-04 1.64E-03 2.99E-03 Total For Period Curies 2.61E-02 9.25E-03 3.33E-02 3.34E-02 Page 20 of 82 183

Table 1-2 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 4.38E+02 2.23E+02 3.40E+02 1.09E+02 Dissolved And Entrained Gases Xe-133 Curies 7.03E-06 4.12E-04 3.15E-04 1.80E-05 Xe-135 Curies O.OOE+O0 1.73E-05 1.87E-07 O.OOE+O0 Xe-131M Curies O.OOE+O0 O.OOE+O0 2.10E-07 O.OOE+O0 Total For Period Curies 7.03E-06 4.30E-04 3.15E-04 1.80E-05 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 21 of 82 184

Table 1-2 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies 4.08E-05 4.59E-04 O.OOE+O0 O.OOE+O0 Total For Period Curies 4.08E-05 4.59E-04 O.OOE+00 O.OOE+00 Tritium H-3 Curies 4.78E-02 O.OOE+OO 2.46E-02 1.97E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.00E4-OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 22 of 82 185

Table 1-2 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-58 Curies 1.08E-02 9.75E-03 1.32E-02 2.93E-03 Sn-117M Curies 6.OOE-06 O.OOE+O0 2.54E-05 5.62E-05 Cs-137 Curies 1.69E-03 1.54E-03 1.36E-03 3.63E-04 Rh-105 Curies O.OOE+O0 O.OOE+O0 4.05E-05 2.61E-05 Cr-51 Curies 9.16E-04 0.00E+00 3.94E-03 1.05E-03 Ni-63 Curies 3.16E-03 1.67E-03 3.29E-03 5.98E-03 Sb-125 Curies 5.38E-04 O.OOE+00 5.14E-04 5.89E-04 Te-125M Curies 2.21E-02 1.07E-03 2.05E-02 5.00E-02 Fe-55 Curies 6.49E-03 2.15E-03 1.25E-02 4.00E-03 1-132 Curies O.OOE+O0 O.OOE+O0 2.72E-05 1.34E-05 Cs-134 Curies 2.39E-04 1.85E-04 1.32E-04 5.71E-06 Co-60 Curies 5.63E-03 1.35E-03 8.65E-03 1.27E-03 Mn-54 Curies 3.60E-04 8.35E-05 7.05E-04 8.30E-05 Rb-86 Curies O.OOE+00 3.02E-06 O.OOE+00 O.OOE+O0 Te-129 Cunes O.OOE+00 O.OOE+00 O.OOE+00 5.15E-05 Fe-59 Cunes 2.39E-05 O.OOE+O0 2.97E-04 8.51E-05 Co-57 Cunes 3.31E-05 1.02E-05 5.74E-05 2.27E-07 Sr-90 Cunes O.OOE+O0 O.OOE+O0 1.68E-06 O.OOE+O0 Nb-95 Curies 2.45E-05 3.04E-06 7.68E-04 1.16E-04 Te-131M Curies O.OOE+00 O.OOE+00 O.OOE+00 1.07E-05 Zr-95 Curies O.OOE+00 O.OOE+00 4.01E-04 3.18E-05 Sr-89 Curies 1.26E-05 3.12E-07 O.OOE+O0 O.OOE+00 Zn-65 Curies 1.92E-04 2.19E-05 1.27E-04 4.45E-06 Tc-99M Curies O.OOE+00 O.OOE+00 8.20E-07 O.OOE+00 Mo-99 Curies O.OOE+00 O.OOE+00 8.06E-07 O.OOE+00 Te-132 Curies O.OOE+00 O.OOE+00 2.70E-05 2.52E-05 Total For Period Curies 5.22E-02 1.79E-02 6.65E-02 6.67E-02 Page 23 of 82 186

Table 1-2 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 8.77E+02 4.12E+02 6.80E+02 2.17E+02 Dissolved And Entrained Gases Xe-131M Curies O.OOE+O0 O.OOE+O0 4.19E-07 O.OOE+O0 Xe-133 Curies 1.41E-05 8.25E-04 6.30E-04 3.60E-05 Xe-135 Curies O.OOE+O0 3.47E-05 3.74E-07 O.OOE+O0 Total For Period Curies 1.41E-05 8.59E-04 6.31E-04 3.60E-05 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 24 of 82 187

Table 1-3 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Organ ODCM Lint Units 1ST QW" % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM GI-Ui 5.00E+00 mRem 8.13E-03 1.63E-01 3.68E-03 7.37E-02 1.13E-02 2.27E-01 7.72E-03 1.54E-01 Lung 5.OOE+00 mRem 7.42E-03 1.48E-01 4.OOE-03 7.99E-02 9.32E-03 1.86E-01 3.52E-03 7.04E-02 Kidney 5.00E+00 mRem 9.60E-03 1.92E-01 5.38E-03 1.08E-01 1.23E-02 2.47E-01 8.13E-03 1.63E-01 Bone 5.00E+00 mRem 4.78E-03 9.56E-02 4.59E-03 9.18E-02 5.98E-03 1.20E-01 4.44E-03 8.88E-02 Thyroid 5.OOE+00 mRem 6.53E-03 1.31E-01 3.31E-03 6.61E-02 8.22E-03 1.64E-01 3.OOE-03 6.OOE-02 Total Body 1.50E+00 mRem 1.04E-02 6.95E-01 7.40E-03 4.93E-01 1.26E-02 8.37E-01 4.13E-03 2.75E-01 Liver 5.OOE+00 mRem 1.23E-02 2.47E-01 9.37E-03 1.87E-01 1.48E-02 2.97E-01 5.12E-03 1.02E-01 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Umit GI-Li 1.00E+01 mRem 3.09E-02 3.09E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 3.45E-02 1.15E+00 Maximum Individual Liquid Liquid Effluent TB Annual Thyroid 1.00E+01 mRem 2.11E-02 2.11E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.OOE+01 mRem 2.43E-02 2.43E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 4.17E-02 4.17E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 1.98E-02 1.98E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 3.55E-02 3.55E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Page 25 of 82 188

Table 1-3 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Liver 5.OOE+00 mRem 1.24E-02 2.47E-01 1.13E-02 2.27E-01 1.49E-02 2.97E-01 5.12E-03 1.02E-01 Thyroid 5.OOE+O0 mRem 6.53E-03 1.31E-01 4.34E-03 8.68E-02 8.22E-03 1.64E-01 3.OOE-03 6.OOE-02 Total Body 1.50E+00 mRem 1.04E-02 6.95E-01 9.05E-03 6.03E-01 1.26E-02 8.37E-01 4.13E-03 2.75E-01 Kidney 5.00E+00 mRem 9.60E-03 1.92E-01 6.74E-03 1.35E-01 1.23E-02 2.47E-01 8.13E-03 1.63E-01 Bone 5.OOE+00 mRem 4.78E-03 9.56E-02 5.32E-03 1.06E-01 5.98E-03 1.20E-01 4.44E-03 8.88E-02 Lung 5.OOE+00 mRem 7.43E-03 1.49E-01 5.12E-03 1.02E-01 9.32E-03 1.86E-01 3.52E-03 7.04E-02 GI-Lli 5.OOE+00 mRem 8.13E-03 1.63E-01 4.75E-03 9.50E-02 1.13E-02 2.27E-01 7.72E-03 1.54E-01 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Thyroid 1.OOE+01 mRem 2.21E-02 2.21E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Li 1.OOE+01 mRem 3.19E-02 3.19E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.OOE+01 mRem 4.37E-02 4.37E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.OOE+01 mRem 3.68E-02 3.68E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.00E+01 mRem 2.05E-02 2.05E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 3.62E-02 1.21E+00 Maximum Individual Liquid Liquid Effluent TB Annual Lung 1.00E+01 mRem 2.54E-02 2.54E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Page 26 of 82 189

Table 1-3 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a member of the public due to Liquid Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Lung 5.OOE+00 mRem 1.49E-02 2.97E-01 9.12E-03 1.82E-01 1.86E-02 3.73E-01 7.04E-03 1.41E-01 Kidney 5.OOE+00 mRem 1.92E-02 3.84E-01 1.21E-02 2.42E-01 2.47E-02 4.94E-01 1.63E-02 3.25E-01 Bone 5.OOE+00 mRem 9.56E-03 1.91E-01 9.91E-03 1.98E-01 1.20E-02 2.39E-01 8.88E-03 1.78E-01 Thyroid 5.OOE+00 mRem 1.31E-02 2.61E-01 7.65E-03 1.53E-01 1.64E-02 3.29E-01 6.OOE-03 1.20E-01 Liver 5OOE+00 mRem 2.47E-02 4.94E-01 2.07E-02 4.14E-01 2.97E-02 5.94E-01 1.02E-02 2.05E-01 GI-Ui 5.OOE+00 mRem 1.63E-02 3.25E-01 8.43E-03 1.69E-01 2.27E-02 4.53E-01 1.54E-02 3.09E-01 Total Body 1.50E+00 mRem 2.08E-02 1.39E+00 1.65E-02 1.10E+00 2.51E-02 1.67E+00 8.25E-03 5.50E-01 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit GI-Uli 1.00E+01 mRem 6.28E-02 6.28E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.OOE+01 mRem 4.31E-02 4.31E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Bone 1.OOE+01 mRem 4.03E-02 4.03E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 7.23E-02 7.23E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 8.53E-02 8.53E-01 Maximum Individual Liquid Uquid Effluent Organ Annual Total Body 3.OOE+00 mRem 7.07E-02 2.36E+00 Maximum Individual Liquid Liquid Effluent TB Annual Lung 1.00E+01 mRem 4.96E-02 4.96E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Page 27 of 82 190

Table 1-4 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 ACi/ml Fe-59 8.33E-08 ACi/ml Co-58 3.78E-08 gCi/ml Co-60 6.76E-08 ACi/ml Zn-65 1.32E-07 pCi/ml Mo-99 4.31E-07 gCi/ml Cs-134 3.06E-08 gCi/ml Cs-137 4.51E-08 pci/ml Ce-141 6.99E-08 ,Ci/ml Ce-144 2.95E-07 ACi/ml 1-131 5.97E-08 pCi/ml Xe-133 9.11E-08 ,Ci/ml Xe-135 4.27E-08 gCi/ml Fe-55 1.OOE-06 PCi/ml Sr-89 5.OOE-08 pCi/ml Sr-90 7.OOE-09 pCi/ml H-3 2.OOE-06 pCi/ml Gross Alpha 7.OOE-08 pCi/ml Page 28 of 82 191

Table 1-5 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 37 34 51 27 149

2. Total time period for Batch releases (Minutes) 7.88E+03 5.46E+03 1.26E+04 4.74E+03 3.12E+04

3. Maximum time period for a batch release (Minutes) 4.08E+02 4.75E+02 5.84E+02 4.9gE+02 5.84E+02

4. Average time period for a batch release Minutes) 2.13E+02 1.71E+02 2.48E+02 1.76E+02 2.10E+02

5. Minimum time period for a batch release Minutes) 4.50E+01 4.50E+01 4.70E+01 5.30E+01 4.50E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * (CFS ) 1.68E+04 8.99E+03 6.49E+03 5.38E+03 2.62E+04

Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, GA. 32 miles downstream of Plant Vogtle.

Page 29 of 82 192

Table 1-5 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 37 34 51 27 149

2. Total time period for Batch releases (Minutes) 7.88E+03 5.97E+03 1.26E+04 4.74E+03 3.12E+04

3. Maximum time period for a batch release (Minutes) 4.08E+02 4.75E+02 5.84E+02 4.99E+02 5.84E+02

4. Average time period for a batch release Minutes) 2.13E+02 1.76E+02 2.48E+02 1.76E+02 2.10E+02

5. Minimum time period for a batch release (Minutes) 4.50E+01 4.50E+01 4.70E+01 5.30E+01 4.50E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * (CFS) 1.68E+04 8.99E+03 6.49E+03 5.38E+03 2.62E+04

Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, GA. 32 miles downstream of Plant Vogtle.

Page 30 of 82 193

Table 1-5 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Batch Release Summary Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 37 34 51 27 149

2. Total time period for Batch releases (Minutes) 7.88E+03 5.97E+03 1.26E+04 4.74E+03 3.12E+04

3. Maximum time period for a batch release (Minutes) 4.08E+02 4.75E+02 5.84E+02 4.99E+02 5.84E+02

4. Average time period for a batch release Minutes) 2.13E+02 1.76E+02 2.48E+02 1.76E+02 2.iOE+02

5. Minimum lime period for a batch release Minutes) 4.50E+01 4.50E+01 4.70E+01 5.30E+01 4.50E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * (CFS ) 1.68E+04 8.99E+i03 6.49E+i03 5.38E+03 2.62E+04

Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, GA. 32 miles downstream of Plant Vogtle.

Page 31 of 82 194

Table 1-6 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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.OOE+00 0.00E+00 0.OOE+00 0.OOE+00

3. Maximum Time For A Release Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00

4. Average Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00

5. Minimum Time For A Release Minutes 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00

6. Total activity for all releases (Curies ) 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 Page 32 of 82 195

Table 1-6 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

3. Maximum Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release (Minutes) O.OOE+0O 0.OOE+00 0.OOE+00 O.00E+00 0.00E+00

5. Minimum Time For A Release Minutes) 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Page 33 of 82 196

Table 1-6 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 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.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00

3. Maximum Time For A Release Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

4. Average Time For A Release Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

5. Minimum Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

6. Total activity for all releases ( Curies ) 0.OOE+0O 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Page 34 of 82 197

2.0 Gaseous Effluents 2.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit I 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-1 31, for Iodine-1 33, 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-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.

Page 35 of 82 198

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.

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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 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 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 Page 82 of 82 245

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 37 of 82 200

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. 1-131 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 38 of 82 201

2.2.3 Total Error Estimation cont'd

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 2-1 B, 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

[tCi/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 39 of 82 202

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 2-41B.

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 2014.

Page 40 of 82 203

Table 2-1 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.19E+00 5.39E-02 6.19E-02 1.26E-01

2. Average Release rate for period uCi/sec 7.85E-01 6.84E-03 7.85E-03 1.60E-02

3. Percent of Applicable Umit B. Radioiodines

1. Total Iodine-131 Curies O.OOE+O0 O.OOE+O0 O.OOE+OO O.OOE+O0

2. Average Release rate for period uCi/sec O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+OO

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 4.32E-08 4.36E-08 3.58E-08 O.OOE+OO

2. Average Release rate for period uCi/sec 5.48E-09 5.53E-09 4.54E-09 O.OOOE+OO

3. Percent of Applicable Limit D. Tritum

1. Total Release Curies 8.76E+00 7.78E+00 8.60E+00 1.55E+01

2. Average Release rate for period uCi/sec 1.11E+00 9.87E-01 1.09E+00 1.96E+00

3. Percent of Applicable Limit E. Gross Alpha

1. Total Release Curies O.OOE+O0 O.OOE+OO O.OOE+OO O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+O0 O.OOE+O0 O.OOE+OO O.OOE+OO

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

Page 41 of 82 204

Table 2-1 B VogUe Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.17E-01 2.68E-02 5.95E-01 2.12E-02

2. Average Release rate for period uCi/sec 1.48E-02 3.40E-03 7.55E-02 2.69E-03

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 7.83E-06 2.68E-05

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 9.93E-07 3.40E-06

3. Percent of Applicable Umit C. Particulates

1. Particulates ( Half-Uves > 8 Days) Curies 3.59E-07 2.34E-08 O.OOE+O0 O.OOE+0O

2. Average Release rate for period uCi/sec 4.56E-08 2.97E-09 O.OOE+00 O.OOOE+00

3. Percent of Applicable Umit D. Tritium

1. Total Release Curies 5.97E-02 9.64E+00 1.88E+01 3.87E+00

2. Average Release rate for period uCi/sec 7.58E-03 1.22E+00 2.38E+00 4.91E-01

3. Percent of Applicable Limit

.OE0 *.OE0 *.OE0 *.O E. Gross Alpha

1. Total Release Curies

2. Average Release rate for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO uCi/sec

Applicable limits are expressed interms of dose. See Tables 2-5A and 2-5B of this report.

Page 42 of 82 205

Table 2-1 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.30E+00 8.07E-02 6.57E-01 1.47E-01

2. Average Release rate for period uCi/sec 8.OOE-01 1.02E-02 8.33E-02 1.87E-02

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies O.OOEi-OO O.OOE÷OO 7.83E-06 2.68E-05

2. Average Release rate for period uCi/sec O.OOE+OO O.OOE+OO 9.93E-07 3.40E-06

3. Percent of Applicable Umit C. Particulates

1. Particulates ( Half-Uves > 8 Days) Curies 4.03E-07 6.70E-08 3.58E-08 O.OOE+OO

2. Average Release rate for period uO/sec 5.11E-08 8.50E-09 4.54E-09 O.OOOE+OO

3. Percent of Applicable Umit D. Tritium

1. Total Release Curies 8.82E+00 1.74E+01 2.73E+01 1.93E+01

2. Average Release rate for period uCi/sec 1.12E+00 2.21E+00 3.47E+00 2.45E+00

3. Percent of Applicable Limit E. Gross Alpha

1. Total Release Curies O.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+O0

Applicable limits are expressed interms of dose. See Tables 2-5A and 2-5B of this report.

Page 43 of 82 206

Table 2-2 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-135 Curies 5.46E+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 5.46E+00 O.OOE+00 O.OOE+00 O.OOE+00 lodines No Nuclides Found Curies 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates Sr-90 Curies 4.32E-08 4.36E-08 3.58E-08 O.OOE+O0 Total For Period Curies 4.32E-08 4.36E-08 3.58E-08 0.00E+00 Tritium H-3 Curies 8.40E+00 7.73E+00 8.57E+00 1.54E+01 Gmss Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 44 of 82 207

Table 2-2 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: l-Jan-2014 Ending: 31-Dec-2014 Batc~h Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 6.85E-01 5.39E-02 6.15E-02 1.24E-01 Xe-133 Curies O.OOE+O0 O.OOE+O0 4.18E-04 1.83E-03 Total For Period Curies 6.85E-01 5.39E-02 6.19E-02 1.26E-01 Iodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium H-3 Curies 3.31E-01 4.35E-02 2.77E-02 1.04E-01 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 45 of 82 208

Table 2-2 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 lodines 1-131 Curies O.OOE+00 O.OOE+00 7.83E-06 2.68E-05 Total For Period Curies O.OOE+O0 O.OOE+O0 7.83E-06 2.68E-05 Particulates Sr-89 Curies 3.59E-07 0.00E+00 O.OOE+00 O0OOE+00 Sr-90 Curies O.OOE+00 2.34E-08 O.OOE+00 O.OOE+00 Total For Period Curies 3.59E-07 2.34E-08 O.OOE+O0 O.OOE+O0 Tritium H-3 Curies O.OOE+00 9.56E+00 8.55E+00 3.87E+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 OOOE+00 Page 46 of 82 209

Table 2-2 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.84E-02 1.85E-02 5.18E-01 1.53E-02 Xe-133 Curies 8.39E-02 8.30E-03 7.32E-02 5.86E-03 Xe-135 Curies 4.52E-03 O.OOE+00 5.15E-05 2.78E-05 Total For Period Curies 1.17E-01 2.68E-02 5.92E-01 2.12E-02 lodines No Nuclides Found Curies 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium H-3 Curies 5.97E-02 8.71E-02 9.93E+00 3.50E-03 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 47 of 82 210

Table 2-2 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-135 Curies 5.46E+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 5.46E+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 lodines 1-131 Curies O.OOE+O0 O.OOE+O0 7.83E-06 2.68E-05 Total For Period Curies O.OOE+00 0.00E+00 7.83E-06 2.68E-05 Particulates Sr-89 Curies 3.59E-07 O.OOE+O0 O.OOE+O0 O.OOE+O0 Sr-90 Curies 4.32E-08 6.70E-08 3.58E-08 O.OOE+O0 Total For Period Curies 4.03E-07 6.70E-08 3.58E-08 O.OOE+O0 Tritium H-3 Curies 8.40E+00 1.73E+01 1.71E+01 1.92E+01 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 48 of 82 211

Table 2-2 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 7.13E-01 7.24E-02 5.80E-01 1.40E-01 Xe-133 Curies 8.39E-02 8.30E-03 7.36E-02 7.70E-03 Xe-135 Curies 4.52E-03 O.OOE+O0 5.15E-05 2.78E-05 Total For Period Curies 8.01E-01 8.07E-02 6.54E-01 1.47E-01 lodines No Nuclides Found Curies 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Tritium H-3 Curies 3.91E-01 1.31E-01 9.96E+00 1.08E-01 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 49 of 82 212

Table 2-3 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 lodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 50 of 82 213

Table 2-3 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released u' nits 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Q uries 4.43E-02 O.OOE+O0 O.OOE+O0 O.OOE+00 Total For Period c'uries 4.43E-02 O.OOE+00 O.OOE+00 0.00E+00 Iodines No Nuclides Found Cu.uries O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 Particulates No Nuclides Found Cu.ties O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium H-3 Cu.uries 3.03E-02 2.90E-03 O.OOE+00 O.OOE+00 Gross Alpha No Nuclides Found Cu.ries O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 51 of 82 214

Table 2-3 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 lodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nudides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 52 of 82 215

Table 2-3 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+00 O.OOE+00 3.38E-03 O.OOE+00 Total For Period Curies O.OOE+00 0.00E+00 3.38E-03 0.00E+00 lodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ParUculates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium H-3 Curies O.0OE+00 0.001E+00 2.75E-01 0.00E+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 53 of 82 216

Table 2-3 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 lodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nucides Found Curies O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Page 54 of 82 217

Table 2-3 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released U'lnits 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Cu Fission Gases Ar-41 C' uries 4.43E-02 O.OOE+O0 3.38E-03 O.OOE+O0 Total For Period uries 4.43E-02 0.00E+00 3.38E-03 O.OOE+00 lodines No Nuclides Found Cuuries O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Cu ries O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium H-3 Cuiries 3.03E-02 2.90E-03 2.75E-01 O.OOE+O0 Gross Alpha No Nuclides Found Cuuries O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Page 55 of 82 218

Table 2-4 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Type of ODCt4 Lmt Units 1ST Qtr % ODCI M 2ND Qtr %lODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Radiation Gamma Air 5.00E+00 mRad 2.80E-04 5.60E-0: 3 7.35E-06 1.47E-04 8.38E-06 1.68E-04 1.70E-05 3.39E-04 Beta Air 1.OOE+01 mRad 2.41E-04 2.41E-0: 3 2.59E-06 2.59E-05 2.96E-06 2.96E-05 6.01E-06 6.01E-05 Cumulative Doses Per Year Type of ODCM Lmt Units Year to End Date %/oODCM Receptor Limit Radiation Gamma Air 1.OOE+01 mRad 3.13E-04 3.13E-03 Si te Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 2.53E-04 1.26E-03 Site Boundary / Child Air Dose Beta Annual 1.21 Page 56 of 82 219

Table 2-4 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Air Doses Due to Gaseous Releases Unit: 2 Starting: l-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Type of ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Radiation Gamma Air 5.OOE+O0 mRad 4.43E-06 8.86E-05 2.57E-06 5.13E-05 7.36E-05 1.47E-03 2.12E-06 4.24E-05 Beta Air 1.OOE+01 mRad 2.82E-06 2.82E-05 1.02E-06 1.02E-05 2.69E-05 2.69E-04 8.27E-07 8.27E-06 Cumulative Doses Per Year Type of ODCM Lmt Units Year to End Date % ODCM Receptor Limit Radiation Gamma Air 1.00E+01 mRad 8.27E-05 8.27E-04 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 3.16E-05 1.58E-04 Site Boundary / Child Air Dose Beta Annual 1.21 Page 57 of 82 220

Table 2-4 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Type of ODCM Lmt Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Radiation Gamma Air 5.OOE+00 mRad 2.85E-04 5.69E-03 9.91E-06 1.98E-04 8.19E-05 1.64E-03 1.91E-05 3.82E-04 Beta Air 1.OOE+01 mRad 2.44E-04 2.44E-03 3.61E-06 3.61E-05 2.99E-05 2.99E-04 6.84E-06 6.84E-05 Cumulative Doses Per Year Type of ODCM Lint Units Year to End Date % ODCM Receptor Limit Radiation Gamma Air 1.OOE+01 mRad 3.96E-04 3.96E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 2.85E-04 1.42E-03 Site Boundary / Child Air Dose Beta Annual 1.21 Page 58 of 82 221

Table 2-5 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 1.92E-04 2.57E-03 1.69E-04 2.25E-03 1.86E-04 2.48E-03 3.34E-04 4.46E-03 Liver 7.50E+00 mRem 1.92E-04 2.56E-03 1.68E-04 2.25E-03 1.86E-04 2.48E-03 3.34E-04 4.46E-03 Thyroid 7.50E+00 mRem 1.92E-04 2.56E-03 1.68E-04 2.25E-03 1.86E-04 2.48E-03 3.34E-04 4.46E-03 Bone 7.50E+00 mRem 1.71E-06 2.29E-05 1.73E-06 2.31E-05 1.42E-06 1.89E-05 O.00E+00 O.OOE+00 Kidney 7.50E+00 mRem 1.92E-04 2.56E-03 1.68E-04 2.25E-03 1.86E-04 2.48E-03 3.34E-04 4.46E-03 GI-Lli 7.50E+00 mRem 1.92E-04 2.56E-03 1.68E-04 2.25E-03 1.86E-04 2.48E-03 3.34E-04 4.46E-03 Lung 7.50E+00 mRem 1.92E-04 2.56E-03 1.68E-04 2.25E-03 1.86E-04 2.48E-03 3.34E-04 4.46E-03 Cumulative Doses per Year Organ ODC4 Lmt Units Year to Ending Date % ODCM Receptor Limit Total Body 1.500E+01 mRem 8.818E-04 5.878E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 8.805E-04 5.870E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 8.805E-04 5.870E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Bone 1.500E+01 mRem 4.863E-06 3.242E-05 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 8.806E-04 5.871E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 8.805E-04 5.870E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 8.805E-04 5.870E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 59 of 82 222

Table 2-5 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1STQtr W % ODCM 2ND Qtr % ODCMl 3RD Qtr % ODCM 4TH Qtr %/oODCM1 Thyroid 7.50E+00 mRem 1.29E-06 1.72E-05 2.08E-04 2.78E-03 4.42E-04 5.89E-03 1.30E-04 1.73E-03 Total Body 7.50E+00 mRem 1.30E-06 1.74E-05 2.09E-04 2.78E-03 4.29E-04 5.71E-03 8.38E-05 1.12E-03 Liver 7.50E+00 mRem 1.29E-06 1.72E-05 2.08E-04 2.78E-03 4.29E-04 5.71E-03 8.39E-05 1.12E-03 Kidney 7.50E+00 mRem 1.29E-06 1.72E-05 2.08E-04 2.78E-03 4.29E-04 5.71E-03 8.40E-05 1.12E-03 Bone 7.50E+00 mRem 4.23E-07 5.63E-06 9.29E-07 1.24E-05 4.49E-08 5.99E-07 1.54E-07 2.05E-06 Lung 7.50E+00 mRem 1.29E-06 1.73E-05 2.08E-04 2.78E-03 4.28E-04 5.71E-03 8.37E-05 1.12E-03 GI-Lli 7.50E+00 mRem 1.31E-06 1.74E-05 2.08E-04 2.78E-03 4.29E-04 5.71E-03 8.37E-05 1.12E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit GI-Ui 1.500E+01 mRem 7.220E-04 4.814E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Bone 1.500E+01 mRem 1.550E-06 1.033E-05 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 7.223E-04 4.815E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 7.222E-04 4.814E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 7.818E-04 5.212E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 7.223E-04 4.816E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 7.220E-04 4.813E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 60 of 82 223

Table 2-5 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 2.14E-06 2.85E-05 2.66E-06 3.54E-05 1.46E-06 1.95E-05 1.54E-07 2.05E-06 Liver 7.50E+00 mRem 1.93E-04 2.58E-03 3.77E-04 5.03E-03 6.14E-04 8.19E-03 4.18E-04 5.57E-03 GI-Ui 7.50E+00 mRem 1.93E-04 2.58E-03 3.77E-04 5.03E-03 6.14E-04 8.19E-03 4.18E-04 5.57E-03 Kidney 7.50E+00 mRem 1.93E-04 2.58E-03 3.77E-04 5.03E-03 6.14E-04 8.19E-03 4.18E-04 5.58E-03 Thyroid 7.50E+00 mRem 1.93E-04 2.58E-03 3.77E-04 5.03E-03 6.28E-04 8.37E-03 4.64E-04 6.19E-03 Total Body 7.50E+00 mRem 1.94E-04 2.58E-03 3.78E-04 5.03E-03 6.15E-04 8.20E-03 4.18E-04 5.57E-03 Lung 7.50E+00 mRem 1.93E-04 2.58E-03 3.77E-04 5.03E-03 6.14E-04 8.19E-03 4.18E-04 5.57E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date % ODCM Receptor Limit Lung 1.500E+01 mRem 1.603E-03 1.068E-02 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 1.662E-03 1.108E-02 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Bone 1.500E+01 mRem 6.413E-06 4.275E-05 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 1.604E-03 1.069E-02 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 1.603E-03 1.068E-02 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 1.603E-03 1.069E-02 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 1.603E-03 1.068E-02 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 61 of 82 224

Table 2-6 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 MINIMUM DETECTABLE CONCENTRATIONS GASEOUS SAMPLE ANALYSES Starting: 1-Jan-2014 Ending: 31-Dec-2014 RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 g*Ci/ml Kr-88 2.53E-08 tiCi/ml Xe-133 2.05E-08 iCi/ml Xe-133m 8.63E-08 pCi/ml Xe-135 7.12E-08 PCi/ml Xe-138 1.05E-07 tACi/mi 1-131 7.93E-15* ACi/ml Mn-54 3.94E-14* pCi/ml Fe-59 2.45E-14* pCi/ml Co-58 1.39E-14* pCi/ml Co-60 1.75E-14* pCi/ml Zn-65 2.82E-14* p*Ci/ml Mo-99 9.57E-14* pCi/ml Cs-134 1.12E-14* pCi/ml Cs-137 8.71E-15* pCi/ml Ce-141 8.62E-15* pCi/ml Ce-144 2.77E-14* pCi/ml Sr-89 1.OOE-13 pCi/ml Sr-90 1.OOE-13 ipCi/ml H-3 9.OOE-08 ACi/ml Gross Alpha 1.OOE-13 iCi/ml

Based on an estimated sample volume of 5.7E+08 mis for particulate filters and charcoal cartridges Page 62 of 82 225

Table 2-7 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 35 52 48 54 189

2. Total time period for batch releases (Minutes) 2.57E+04 6.31E+03 2.72E+03 3.07E+03 3.78E+04

3. Maximum time period for a batch release (Minutes) 9.32E+03 2.28E+03 1.00E+02 1.74E+02 9.32E+03

4. Average time period for a batch release (Minutes) 7.34E+02 1.21E+02 5.67E+01 5.69E+01 2.OOE+02 S. Minimum time period for a batch release (Minutes) 2.30E+01 1.60E+01 3.50E+01 4.OOE+OO 4.OOE+O0 Page 63 of 82 226

Table 2-7 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 16 12 23 20 71

2. Total time period for batch releases ( Minutes ) 4.62E+03 2.04E+03 2.62E+04 7.54E+03 4.04E+04

3. Maximum time period for a batch release ( Minutes ) 3.98E+03 1.49E+03 5.74E+03 1.97E+03 5.74E+03

4. Average time period for a batch release ( Minutes ) 2.89E+02 1.70E+02 1.14E+03 3.77E+02 5.69E+02

5. Minimum time period for a batch release ( Minutes ) 7.OOE+00 3.30E+01 1.90E+01 6.OOE+00 6.OOE+00 Page 64 of 82 227

Table 2-7 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Batch Release Summary Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 51 64 71 74 260

2. Total time period for batch releases ( Minutes ) 3.03E+04 8.35E+03 2.90E+04 1.06E+04 7.82E+04

3. Maximum time period for a batch release ( Minutes ) 9.32E+03 2.28E+03 5.74E+03 1.97E+03 9.32E+03

4. Average time period for a batch release ( Minutes ) 5.94E+02 1.30E+02 4.08E+02 1.43E+02 3.01E+02

5. Minimum time period for a batch release ( Minutes ) 7.OOE+00 1.60E+01 1.90E+01 4.OOE+00 4.OOE+00 Page 65 of 82 228

Table 2-8 A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00

3. Maximum Time For A Release Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00

4. Average Time For A Release Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00

5. Minimum Time For A Release (Minutes) 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

6. Total activity for all releases (Curies ) 0.OOE+00 O.OOE+00 O.OOE+0O 0.00E+00 O.OOE+00 Page 66 of 82 229

Table 2-8 B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00

3. Maximum Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00

6. Total activity for all releases (Curies) O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 67 of 82 230

Table 2-8 C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 lime 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.OOE+00

6. Total activity for all releases (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 68 of 82 231

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 69 of 82 232

Table 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1, 2014 THROUGH JUNE 30, 2014 Regulatory Guide 1.21: Effluent and Waste Disposal Semi-Annual Report of Solid Waste and Irradiated Fuel Shipments PERIOD COVERED: FROM: /1/2014 TO: 6/31/2014 FOR UNIT: C (Con inon U-I and U-2)

A 'SOT Tf WASTF SHIPPEDl O'FFSITF FOR RI JRIAI. OR DISPOSAL. (Not irradiated fluefl

.L.

. . ... ..... . . ..... . . . . . . ... . . . .. . ....... . .. . ... . SA

... L .... .......... ...... l

1. Type of waste (NRC Waste Class B) UNIT 6 month Est. Total period ERROR %

a. Spent resins, filter sludges, evaporator m3 2.69 +/-25 bottoms, etc. None Ci 7.47E+1 +/-25

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 None Ci N/A N/A 3

d. Control Rod Drive Filters in N/A N/A None Ci N/A N/A

e. Other (describe) equip. etc m3 N/A N/A Steam Generator Blow Down Resin (GIC) Ci N/A N/A

1. Type of waste (NRC Waste Class A) UNIT 6 month Est. Total period ERROR %

3

a. Spent resins, filter sludges, evaporator in N/A N/A bottoms, etc. None Ci N/A N/A

b. Dry compressible waste, contaminated equip. m3 3.00 E2 +/- 25 etc. Ci 1.07 +/-25 3

c. Irradiated components, control rods, in N/A N/A None Ci N/A N/A

d. Control Rod Drive Filters m3 N/A N/A None Ci N/A N/A

e. Other (describe) equip. etc m3 1.84 El +/-25 Steam Generator Blow Down Resin (GIC) Ci 1.96 E-3 +/- 25 Page 70 of 82 233

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

Waste Class B ISOTOPE PERCENT CURIES a C-14 0.047 3.49E-02 Mn-54 0.490 3.66E-01 Fe-55 6.339 4.73E+00 Co-57 0.039 2.89E-02 Co-58 0.000 2.07E-04 Co-60 31.976 2.39E+01 Ni-59 0.42 1 3.14E-01 Ni-63 51.810 3.87E+01 Zn-65 0.040 2.97E-02 Sr-90 0.003 2.23E-03 Tc-99 0.001 1.07E-03 Sb-125 0.322 2.41E-01 Cs-134 2.189 1.63E+00 Cs-137 6.323 4.72E+00 N/A N/A N/A N/A N/A N/A

d. N/A N/A N/A

e. N/A N/A N/A Page 71 of 82 234

Waste Class A ISOTOPE PERCENT CURIES

a. N/A N/A N/A

b. H-3 0.256 2.74 E-3 C- 14 0.058 6.22 E-4 Cr-51 6.959 7.44 E-2 Mn-54 3.491 3.73 E-2 Fe-55 10.505 1.12 E-l Fe-59 0.437 4.67 E-3 Co-57 0.231 2.47 E-3 Co-58 44.817 4.79 E-I Co-60 20.602 2.20 E-1 Ni-63 4.838 5.17 E-2 Zn-65 0.427 4.56 E-3 Sr-90 0.012 1.26 E-4 Zr-95 2.399 2.56 E-2 Nb-95 3.836 4.10 E-2 Sn-113 0.248 2.65 E-3 Sb-125 0.446 4.76 E-3 Cs-134 0.110 1.18 E-3 Cs-137 0.327 3.49 E-3

c. N/A N/A N/A

d. N/A N/A N/A

e. H-3 0.394 7.72 E-6 C-14 0.091 1.78 E-6 Cr-51 1.851 3.62 E-5 Mn-54 4.568 8.94 E-5 Fe-55 15.472 3.03E-4 Fe-59 0.216 4.23 E-6 Co-57 0.295 5.77E-6 Co-58 33.222 6.50 E-4 Co-60 31.174 6.10 E-4 Ni-63 7.522 1.47 E-4 Zn-65 0.532 1.04E-5 Sr-90 0.018 3.56 E-7 Zr-95 1.651 3.23 E-5 Nb-95 1.429 2.80 E-5 Sn-113 0.243 4.75 E-6 Sb-125 0.657 1.29 E-5 Cs-134 0.159 3.12 E-6 Cs-137 0.506 9.91 E-6

3. Solid Waste Disposition Number of Shipments 1h4ode of Transportation Destination 1 I--ittman Transport Energy Solutions Barnwell Processing Facility 6 F-iittman Transport Energy Solutions Bear Creek 6 1 ri-State Motor Transit Energy Solutions Gallhear Rd 7 total B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A Page 72 of 82 235

TABLE 3-1 VogUe Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY 1, 2014 THROUGH DECEMBER 31, 2014 Regulatory Guide 1.21: Effluent and Waste Disposal Semi-Annual Report of Solid Waste and Irradiated Fuel Shipments PERIOD COVERED: FROM: 7/1/2014 TO: 12/31/2014 FOR UNIT: C (Common U-I and U-2)

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

. Type of waste (NRC Waste Class A) 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 1.79 E+2 25 etc. Ci 9.08E-1 25

c. Irradiated components, control rods, m _3 N/A N/A None Ci N/A N/A

d. Control Rod Drive Filters m3 N/A N/A None Ci N/A N/A

e. Other (describe) equip. etc. m_3 9.27 E+1 25 Steam Generator Blow Down Resin (GIC) Ci 2.79 E-2 25 Page 73 of 82 236

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

ISOTOPE PERCENT CURIES

a. N/A N/A N/A

b. H-3 0.001 1.09E-05 CR-51 0.000 2.14E-07 Mn-54 0.610 5.54E-03 FE-55 20.125 1.83E-01 Co-57 0.053 4.84E-04 Co-58 6.033 5.48E-02 Co-60 36.362 3.30E-01 Ni-63 34.916 3.17E-0 I SR-90 0.000 1.89E-07 Zr-95 0.475 4.31E-03 Nb-94 0.000 2.40E-08 Nb-95 0.900 8.18E-03 Sn-113 0.000 5.59E-08 Sb-124 0.000 4.75E-08 Sb-125 0.000 1.03E-06 Cs-134 0.000 8.07E-07 Cs-137 0.524 4.76E-03 Ce- 144 0.000 5.85E-08 c N/A N/A N/A

d. N/A N/A N/A

e. Mn-54 0.509 1.42E-4 Fe-55 19.713 5.50E-3 Co-57 0.043 1.21E-5 Co-58 3.553 9.91E-4 Co-60 37.282 1.04E-2 Ni-63 37.623 1.05E-2 Zr-95 0.273 7.61E-5 Nb-95 0.444 1.24E-4 Cs-137 0.560 1.56E-4

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Truck Energy Solutions Bear Creek Road 5 Truck Energy Solutions Gallaher B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A Page 74 of 82 237

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 - 2014 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Location Name: Visitor's Center Receptor Distance (kilometers): 4.47E-01 Sector: SE Occupancy Factor: 4.57E-04 Age Group: Child Mixed Mode Release Noble Gas X/Q (sec/m3): 7.12E-07 Ground Level Release Noble Gas X/Q (sec/m3): 5.93E-06 Mixed Mode Release Particulate and Radioiodine X/Q (sec/rm3): 6.74E-07 D/Q (m-2): 5.77E-09 Ground Level Release Particulate and Radioiodine X/Q (seclm3): 5.58E-06 D/Q (m-2): 2.28E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Total Body mRem 1.05E-09 2.03E-09 3.41E-09 2.25E-09 8.74E-09 Liver mRem 1.05E-09 2.03E-09 3.41E-09 2.25E-09 8.74E-09 Lung mRem 1.05E-09 2.03E-09 3.41E-09 2.25E-09 8.74E-09 GI-Ui mRem 1.05E-09 2.03E-09 3.41E-09 2.25E-09 8.74E-09 Skin mRem 7.54E-18 O.OOE+00 1.37E-13 4.68E-13 6.05E-13 Thyroid mRem 1.05E-09 2.03E-09 3.43E-09 2.29E-09 8.79E-09 Bone mRem 4.48E-13 6.62E-13 5.03E-13 5.11E-13 2. 12E-12 Kidney mRem 1.05E-09 2.03E-09 3.41E-09 2.25E-09 8.74E-09 Page 76 of 82 239

Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 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 Ground Level Release Particulate and Radioiodine X/Q (seqjrm3): 6.96E-06 D/Q (m-2): 2.88E-08 Ground Level Release Noble Gas X/JQ (sec/m3): 1.81E-05 Mixed Mode Release Particulate and Radioiodine X/Q (seclm3): 9.17E-07 D/Q (m-2): 7.14E-09 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Liver mRem 8.69E-07 1.62E-06 2.99E-06 1.80E-06 7.28E-06 Lung mRem 8.70E-07 1.62E-06 2.99E-06 1.80E-06 7.28E-06 Bone mRem 3.04E-1O 4.60E-10 3.31E-10 2.94E-10 1.39E-09 Total Body mRem 8.69E-07 1.62E-06 2.99E-06 1.80E-06 7.28E-06 Skin mRem 4.85E-15 O.OOE+O0 8.79E-11 3.01E-10 3.89E-10 Thyroid mRem 8.69E-07 1.62E-06 3.OOE-06 1.82E-06 7.31E-06 GI-Ui mRem 8.69E-07 1.62E-06 2.99E-06 1.80E-06 7.28E-06 Kidney mRem 8.69E-07 1.62E-06 2.99lt-06 1.80E-06 7.28E-06 Page 77 of 82 240

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.

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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, 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. 1RE-0018 This monitor was out of service greater than 30 days due to manpower challenges. A refueling outage was in progress during the same timeframe. The monitor has been returned to service.

b. 1RE-12839 Equipment repair required bypass of steam packing exhaust and steam jet air ejector filters. The monitor was out of service due to having no sample flow. It is not required due to no indications of primary-to-secondary leakage.

Additionally, there were 4 other radiation monitors that could provide indication of primary-to-secondary leakage during repair. Sample flow has been restored and the monitor is in service.

c. 2RE-12442 This monitor was out of service greater than 30 days due to an upgrade of the monitor. A redundant radiation monitor and auxiliary monitoring remained in service during most of the replacement duration*. The monitor has been returned to service.

(2) *A Green self-revealing NCV of TS 5.5.4, "Radioactive Effluent Controls Program," was identified for the licensee's failure to maintain continuous monitoring of the minimum required channels on the Unit 2 plant vent radiation monitors and failure to implement the required compensatory measures as required by the ODCM between March 16 and March 26, 2014.

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During the period both monitors were inoperable there were no unplanned releases and all planned releases were within regulatory limits. Releases from the waste gas decay system and Unit 2 containment are planned, sampled, permitted, and monitored by another set of radiation monitors prior to release. In addition, radiation monitors installed throughout the auxiliary building would have provided an indication of any elevated airborne conditions indicative of an unplanned release. During the period that both monitors were out of service, dose to the public was determined from two Unit 2 containment releases.

Causal analysis was performed and corrective actions were created to prevent reoccurrence.

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 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 There were no changes made to the VEGP ODCM in 2014.

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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 2014 assessment period.

Liquid Radwaste System There were no major changes to the liquid radwaste systems occurred during the 2014 assessment period.

Solid Radwaste System There were no major changes to the solid radwaste systems in the 2014 assessment period.

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NL-15-0803, Annual Radioactive Effluent Release Report for 2014, Enclosure 3

Text

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