Text

Enclosure 3 - Vogtle Annual Radioactive Effluent Release Report for 2011
	ML12122A144
Person / Time
Site:	Vogtle
Issue date:	12/31/2011
From:	; Southern Co, Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12122A144 (85)
	v • d • e

Edwin I. Hatch Joseph M. FarleyNuclear Plant Nuclear Plant Vogtle Electric Generating Annual Radioactive Effluent Release Plant Reports for 2011 Enclosure 3 Vogtle Annual Radioactive Effluent Release Report for 2011

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERA TING LICENSE NOS. NPF-68AND NPF-81 ANNUAL RADIOACTIVE EFFLUENTRELEASE REPORT FOR JANUARY 1, 2011 TO DECEMBER 31,2011 Page 1 of 84

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2011 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 9 1.1 Regulatory Requirements 9 1.1.1 Concentration Limits 9 1.1.2 Dose Limits 9 1.2 Effluent Concentration Limit (ECL) 9 1.3 Measurements and Approximations of Total Radioactivity 10 1.3.1 Total Radioactivity Determination 10 1.3.2 Total Error Estimation 12 1.4 Liquid Effluent Release Data 13 1.5 Radiological Impact Due to Liquid Releases 13 1.6 Liquid Effluents - Batch Releases 13 1.7 Liquid Effluents - Abnormal Releases 13 Table 1-1A Liquid Effluents - Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 14 Table 1-1B Liquid Effluents - Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 15 Table 1-1C Liquid Effluents - Summation of All Releases Site (Quarters 1,2,3, and 4) 16 Table 1-2A Liquid Effluents -Unit I (Quarters 1,2,3, and 4) 17 Page 2 of 84

Table 1-2B Liquid Effluents -Unit 2 (Quarters 1,2,3, and 4) 20 Table 1-2C Liquid Effluents -Site (Quarters 1,2,3, and 4) 22 Table 1-3A Doses to a Member of the Public Due to Liquid Releases Unit 1 (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 Sample Analysis 28 Table 1-5A Liquid Effluents Batch Release Summary Unit 1 (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 2 (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 Page 3 of 84

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 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 2-1A Gaseous Effluents Summation of All Releases Unit 1 (Quarters 1,,2,3, and 4) 41 Table 2-1B Gaseous Effluents Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 42 Table 2-1C 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 Page 4 of 84

Table 2-2B Gaseous Effluents Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 46 Table 2-C 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 Site (Quarters 1,2,3, and 4) 54 Table 2-4A Air Doses Due to Noble Gases in Gaseous Releases Unit 1 (Quarters 1,2,3, and 4) 56 Table 2-4B Air Doses Due to Noble Gases in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 57 Table 2-4C Air Doses Due to Noble Gases in Gaseous Releases Site (Quarters 1,2,3, and 4) 58 Table 2-5A Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit 1 (Quarters 1,2,3, and 4) 59 Table 2-5B Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 60 Page 5 of 84

Table 2-5C Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Site (Quarters 1,2,3, and 4) 61 Table 2-6 Minimum Detectable Concentrations Gaseous Sample Anayses 62 Table 2-7A Gaseous Effluents - Batch Release Summary Unit 1 (Quarters 1,2,3, and 4) 63 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 1 (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 Page 6 of 84

4.0 Doses to Members of the Public Inside the Site Boundary 74 4.1 Regulatory Requirements 74 4.2 Demonstration of Compliance 74 Table 4-1 Doses to Members of the Public Due to Activities Inside the Site Boundary 75 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 77 5.1 Regulatory Requirements 77 5.2 Demonstration of Compliance 77 6.0 Meteorological Data 77 7.0 Program Deviations 78 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 78 7.1.1 Regulatory Requirement 78 7.1.2 Description of Deviations 78 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 81 9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 82 9.1 Regulatory Requirements 82 Page 7 of 84

9.2 Description of Major Changes 82 Appendix A Carbon-1 4 83 Revised Previous Reports 84 Page 8 of 84

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 gCi/ml total activity.

For gross alpha in liquid radwaste, the ECL is 2 E-09 gCi/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 10 of 84

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-1 37, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 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 and Fe-55 and the corresponding ECL values.

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

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

Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate warnings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for 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 liquid effluents.

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 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 Tables 2A and 2B are found in this report as Tables 1-1A, 1-1B, 1-1C, 1-2A, 1-2B and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 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 2011.

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Table 1-1A Vogtle Electric Generating Plant Liquid Effluents - Summation of All Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Ouarter 2ND C:uarter 3RD Ouarter 4TH Ouarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 2. 1OE-02 3.48E-03 5.03E-02 2.65E-02

2. Average diluted concentration during period uCi/mL 3.76E-09 9.89E-10 9.99E-09 6.35E-09

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 3.44E+02 1.60E+02 6.10E+02 5.77E+01

2. Average diluted Concentration during period uCi/mL 6.15E-05 4.55E-05 1.21E-04 1.38E-05

3. Percent of Applicable Limit

.OE0 C. Dissolved and Entrained Gases

1. Total Release Curies 5.45E-04 2.63E-04 1.06E-02

2. Average diluted Concentration 0.OOE+00 during period uCi/mL 9.77E-11 7.48E-11 2.11E-09

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 1.26E-06 1.03E-04 3.93E-07 E: Waste Vol Release (Pre-Dilution) Liters 3.42E+07 3.68E+07 3.44E+07 3.32E+07 F. Volume of Dilution Water Used Liters 5.55E+09 3.48E+09 5.OOE+09 4.14E+09

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

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Table 1-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Summation Of All Releases Unit: 2 S1 tartina: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST fluarter 2ND fluart~r 3RD An;*rt~r 4TH flu~rter 1ST Ouarter 2ND Ouarter 3RD Oua er 4TH inuarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 2.15E-03 3.91E-04 6.97E-05 3.94E-03

2. Average diluted concentration during period uCi/mL 4.09E-10 1.22E-10 1.75E-11 9.34E-10

3. Percent of Applicable Limit %

B. Tritium

1. Total Release Curies 1.47E+02 1.62E+01 1.66E+01 1.03E+01

2. Average diluted Concentration during period uCi/mL 2.79E-05 5.05E-06 4.17E-06 2.44E-06

3. Percent of Applicable Limit %

.OE0 C. Dissolved and Entrained Gases

1. Total Release Curies 9.36E-04 2.93E-05 3.78E-03

2. Average diluted Concentration 0.OOE+00 during period uCi/mL 1.78E-10 9.15E-12 9.51E-10

3. Percent of Applicable Limit %

D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 7.88E-07 E: Waste Vol Release (Pre-Dilution) Liters 1.71E+07 1.12E+07 1.89E+07 2.OOE+07 F. Volume of Dilution Water Used Liters 5.23E+09 3.19E+09 3.95E+09 4.20E+09 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

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Table 1-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Summation Of All Releases Unit: Site S tartinq: 1-Jan- 2011 Endinq: 31-Dec-2011 Type of Effluent Units 1ST luar-ter 2ND Ouarter 3RD fluarter 4TH fluarter 1ST Ouarter 2ND Ouarter 3RD fWarter 4TH fluarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 2.31E-02 3.87E-03 5.03E-02 3.04E-02

2. Average diluted concentration during period uCi/mL 2.13E-09 5.76E-10 5.59E-09 3.63E-09

3. Percent of Applicable Limit %

B. Tritium

1. Total Release Curies 4.90E+02 1.76E+02 6.27E+02 6.79E+01

2. Average diluted Concentration during period uCi/mL 4.53E-05 2.62E-05 6.96E-05 8.09E-06

3. Percent of Applicable Limit %

C. Dissolved and Entrained Gases

1. Total Release Curies 1.48E-03 2.92E-04 1.44E-02 O.OOE+00

2. Average diluted Concentration during period uCi/mL 1.37E-10 4.35E-11 1 .60E-09 O.OOE+00

3. Percent of Applicable Limit %

D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 1.26E-06 1.03E-04 1.18E-06 E: Waste Vol Release (Pre-Dilution) Liters 5.13E+07 4.79E+07 5.33E+07 5.31E+07 F. Volume of Dilution Water Used Liters 1.08E+10 6.67E+09 8.95E+09 8.34E+09

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

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Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Ouarter 2ND Ouarter 3RD Quarter 4TH Ouarter Fission & Activation Be-7 Curies O.OOE+O0 O.OOE+O0 3.12E-05 2.04E-04 Co-57 Curies O.OOE+O0 O.OOE+O0 1.04E-06 O.OOE+O0 Co-58 Curies 7.68E-04 1.1OE-03 3.93E-03 2.29E-03 Co-60 Curies 1.09E-03 2.06E-04 8.77E-04 4.38E-04 Cr-51 Curies 8.49E-05 O.OOE+O0 4.94E-04 2.61E-04 Fe-55 Curies 4.01E-04 3.42E-04 2.30E-03 1.12E-02 1-131 Curies O.OOE+O0 O.OOE+O0 3.73E-04 5.94E-05 1-132 Curies O.OOE+O0 O.OOE+O0 2.59E-03 1.87E-04 Mn-54 Curies 1.17E-05 5.52E-06 2.06E-05 2.35E-05 Nb-95 Curies O.OOE+O0 O.OOE+O0 8.23E-05 1.29E-05 Ni-65 Curies O.OOE+O0 O.OOE+O0 2.22E-06 O.OOE+O0 Sr-89 Curies 8.15E-05 8.78E-06 6.19E-04 5.51E-06 Sr-90 Curies 4.71E-06 O.OOE+O0 O.OOE+O0 O.OOE+O0 Zr-95 Curies O.OOE+O0 O.OOE+O0 4.54E-05 O.OOE+O0 Cs-134 Curies 2.19E-04 2.08E-05 1.83E-05 9.76E-05 Cs-137 Curies 6.12E-04 9.72E-05 1.50E-04 2.90E-04 Eu-152 Curies O.OOE+O0 O.OOE+O0 3.12E-06 O.OOE+O0 Np-239 Curies O.OOE+O0 O.OOE+O0 8.65E-07 O.OOE+O0 Sb-122 Curies 4.24E-06 O.OOE+O0 8.13E-06 O.OOE+O0 Sb-124 Curies O.OOE+O0 1.38E-05 1.11E-04 3.86E-05 Sb-125 Curies 6.72E-03 1.69E-03 2.35E-02 1.12E-02 Sb-126 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 1.19E-05 Te-132 Curies O.OOE+O0 O.OOE+O0 3.16E-04 1.59E-04 Zn-69M Curies O.OOE+O0 O.OOE+O0 1.98E-06 O.OOE+O0 Te-125M Curies 1.1OE-02 O.OOE+O0 1.42E-02 O.OOE+O0 Te-129M Curies O.OOE+O0 O.OOE+O0 5.91E-04 O.OOE+O0 Total For Period Curies 2.10E-02 3.48E-03 5.03E-02 2.65E-02 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations Page 17 of 84

Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 3.43E+02 1.60E+02 6.10E+02 5.76E+01 Dissolved And Entrained Gases Xe-133 Curies 5.45E-04 2.63E-04 1.04E-02 0.OOE+O0 Xe-135 Curies O.OOE+00 O.OOE+00 1.78E-04 0.OOE+OO Xe-133M Curies O.OOE+00 O.OOE+00 4.OOE-05 O.OOE+O0 Total For Period Curies 5.45E-04 2.63E-04 1.06E-02 0.OOE-I00 Gross Alpha Radioactivity G-Alpha Curies 0.OOE+00 1.26E-06 3.08E-06 3.93E-07 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 18 of 84

Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium H-3 Curies 4.47E-02 6.03E-02 7.34E-02 8.07E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Gross Alpha Radioactivity G-Alpha Curies O.OOE+00 O.OOE+00 9.97E-05 O.OOE+00

Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-57 Curies 3.04E-06 O.OOE+00 O.OOE+00 O.OOE+00 Co-58 Curies 7.22E-05 2.86E-05 3.76E-05 6.44E-05 Co-60 Curies 4.51E-04 1.84E-05 1.06E-05 2.81E-05 Cr-51 Curies 5.24E-05 0.OOE+00 O.OOE+00 O.OOE+00 Fe-55 Curies 1.19E-04 1.26E-05 1.70E-06 3.69E-03 1-131 Curies O.OOE+00 O.OOE+00 4.12E-06 O.OOE+00 Mn-54 Curies 1.16E-05 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 Curies 4.78E-06 5.62E-07 O.OOE+00 1.73E-05 Sr-90 Curies O.OOE+00 O.OOE+00 O.OOE+00 1.72E-06 Cs-134 Curies 2.09E-05 1.42E-05 O.OOE+00 3.45E-05 Cs-137 Curies 5.05E-05 3.15E-05 O.OOE+00 1.07E-04 Eu-152 Curies 9.10E-06 O.OOE+00 O.OOE+00 O.OOE+00 Sb-125 Curies 1.35E-03 1.76E-04 1.56E-05 O.OOE+00 Total For Period Curies 2.15E-03 2.82E-04 6.97E-05 3.94E-03 Tritium H-3 Curies 1.47E+02 1.61E+01 1.65E+01 1.03E+01 Dissolved And Entrained Gases Xe-133 Curies 9.23E-04 2.93E-05 3.65E-03 O.OOE+00 Xe-135 Curies 1.25E-05 O.OOE+00 3.72E-05 O.OOE+00 Xe-133M Curies O.OOE+00 O.OOE+00 8.72E-05 O.OOE+00 Total For Period Curies 9.36E-04 2.93E-05 3.78E-03 0.OOE+00 Gross Alpha Radioactivity, G-Alpha Curies O.OOE+00 O.OOE+00 O.OOE+00 7.88E-07

Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 20 of 84

Table 1-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-89' Curies O.OOE+O0 1.09E-04 O.OOE+00 O.OOE+O0 Tritium H-3 Curies 6.37E-02 2.38E-02 5.17E-02 3.43E-02 Dissolved and Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 0.OOE+00 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00

Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 21 of 84

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Be-7 Curies O.OOE+O0 O.OOE+O0 3.12E-05 2.04E-04 Co-57 Curies 3.04E-06 O.OOE+O0 1.04E-06 O.OOE+O0 Co-58 Curies 8.40E-04 1.12E-03 3.96E-03 2.36E-03 Co-60 Curies 1.54E-03 2.24E-04 8.88E-04 4.66E-04 Cr-51 Curies 1.37E-04 O.OOE+00 4.94E-04 2.61E-04 Fe-55 Curies 5.20E-04 3.55E-04 2.30E-03 1.49E-02 1-131 Curies O.OOE+00 O.OOE+00 3.77E-04 5.94E-05 1-132 Curies O.OOE+00 O.OOE+00 2.59E-03 1.87E-04 Mn-54 Curies 2.33E-05 5.52E-06 2.06E-05 2.35E-05 Nb-95 Curies O.OOE+00 O.OOE+00 8.23E-05 1.29E-05 Ni-65 Curies O.OOE+00 O.0OE+00 2.22E-06 O.OOE+00 Sr-89 Curies 8.63E-05 9.35E-06 6.19E-04 2.28E-05 Sr-90 Curies 4.71E-06 O.OOE+00 O.OOE+00 1.72E-06 Zr-95 Curies O.OOE+00 O.OOE+00 4.54E-05 0.OOE+00 Cs-134 Curies 2.40E-04 3.50E-05 1.83E-05 1.32E-04 Cs-137 Curies 6.62E-04 1.29E-04 1.50E-04 3.97E-04 Eu-152 Curies 9.10E-06 O.OOE+00 3.12E-06 O.OOE+00 Np-239 Curies O.OOE+00 O.OOE+00 8.65E-07 O.OOE+00 Sb-122 Curies 4.24E-06 O.OOE+00 8.13E-06 O.OOE+00 Sb-124 Curies O.OOE+00 1.38E-05 1.11E-04 3.86E-05 Sb-125 Curies 8.07E-03 1.86E-03 2.35E-02 1.12E-02 Sb-126 Curies O.OOE+00 O.OOE+00 O.OOE+00 1.19E-05 Te-132 Curies O.OOE+00 O.OOE+00 3.16E-04 1.59E-04 Zn-69M Curies O.OOE+00 O.OOE+00 1.98E-06 O.OOE+00 Te-125M Curies 1.10E-02 O.OOE+00 1.42E-02 O.OOE+00 Te-129M Curies O.OOE+00 O.OOE+00 5.91E-04 O.OOE+00 Total for Period Curies 2.31E-02 3.76E-03 5.03E-02 3.04E-02

Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 22 of 84

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 4.90E+02 1.76E+02 6.27E+02 6.78E+01 Dissolved And Entrained Gases Xe-133 Curies 1.47E-03 2.92E-04 1.40E-02 O.OOE+O0 Xe-135 Curies 1.25E-05 O.OOE+0O 2.15E-04 0.OOE+00 Xe-133M Curies O.OOE+00 O.OOE+0O 1.27E-04 O.OOE+00 Total For Period Curies 1.48E-03 2.92E-04 1.44E-02 0.OOE+00 Gross Alpha Radioactivity G-Alpha Curies O.OOE+O0 1.26E-06 3.08E-06 1.18E-06

Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 23 of 84

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-89 Curies O.OOE+00 1.09E-04 0.OOE+0O 0.OOE+00 Tritium H-3 Curies 1.08E-01 8.41E-02 1.25E-01 1.15E-01 Dissolved and Entrained Gases No Nuclides Found Curies O.OOE+O0 O.QOE+OO 0.OOE+00 0.OOE+00 Gross Alpha Radioactivity G-Alpha Curies O.OOE+O0 Q.OOE+OO 9.97E-05 0.OOE+00

Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 24 of 84

Table 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a member of the public due to Liquid Releases Unit: Unit 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter Oraan ODCM Lint Units 1ST Qtr O/o ODCM 2ND Otr %/oODCM 3RD Otr %/oODCM 4TH Qtr o/o ODCM Bone 5.OOE+00 mRem 3'60E-03 7.20E-02 6.06E-04 1.21E-02 3.12E-03 6.24E-02 3.61E-03 7.22E-02 GI-Lli 5.O0E+00 mRem 8.55E-03 1.71E-01 3.92E-03 7.83E-02 2.58E-02 5.15E-01 4.21E-03 8.43E-02 Kidney 5.OOE+00 mRem 9.29E-03 1.86E-01 3.78E-03 7.56E-02 2.06E-02 4.13E-01 3.29E-03 6.58E-02 Liver 5.OOE+00 mRem 1.11E-02 2.23E-01 4.33E-03 8.67E-02 1.84E-02 3.68E-01 6.74E-03 1.35E-01 Lung 5.OOE+00 mRem 1.51E-02 3.03E-01 7.51E-03 1.50E-01 7.28E-02 1.46E+00 2.73E-02 5.45E-01 Thyroid 5.OOE+00 mRem 6.26E-03 1.25E-01 3.50E-03 7.OOE-02 1.70E-02 3.41E-01 1.66E-03 3.32E-02 Total Body 1.50E+00 mRem 9.67E-03 6.44E-01 4.08E-03 2.72E-01 1.77E-02 1.18E+00 5.22E-03 3.48E-01 Cumulative Doses Per Year Oraan ODCM Lmt Units Year to Ending Date /o ODCM Receptor Limit Bone 1.OOE+01 mRem 1.09E-02 1.09E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.OOE+01 mRem 4.24E-02 4.24E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.OOE+01 mRem 3.70E-02 3.70E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 4.06E-02 4.06E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.OOE+01 mRem 1.23E-01 1.23E+00 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 2.84E-02 2.84E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+O0 mRem 3.67E-02 1.22E+00 Maximum Individual Liquid Liquid Effluent TB Annual Page 25 of 84

Table 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Ouarter Oraan 1ST Qtr 0/6 ODCM Lmt Units ODCM 2ND Otr 0/0 ODCM 3RD Qtr %/oODCM 4TH Qtr %/aODCM Bone 5.OOE+O0 mRem 3.85E-04 7.69E-03 3.49E-04 6.99E-03 3.81E-07 7.62E-06 1.15E-03 2.31E-02 GI-LIi 5.OOE+O0 mRem 3.12E-03 6.25E-02 2.64E-04 5.28E-03 4.53E-04 9.06E-03 3.40E-04 6.79E-03 Kidney 5.OOE+O0 mRem 3.12E-03 6.25E-02 2.97E-04 5.95E-03 4.47E-04 8.93E-03 8.42E-04 1.68E-02 Liver 5.OOE+O0 mRem 3.52E-03 7.05E-02 4.71E-04 9.42E-03 4.47E-04 8.94E-03 2.OOE-03 3.99E-02 Lung 5.OOE+O0 mRem 4.62E-03 9.23E-02 4.37E-04 8.74E-03 4.83E-04 9.66E-03 4.87E-04 9.73E-03 Thyroid 5.OOE+O0 mRem 2.92E-03 5.85E-02 2.11E-04 4.21E-03 4.53E-04 9.07E-03 2.79E-04 5.59E-03 Total Body 1.50E+00 mRem 3.36E-03 2.24E-01 4.03E-04 2.69E-02 4.47E-04 2.98E-02 1.48E-03 9.86E-02 Cumulative Doses Rer Year Organ ODCM Lmt Units Year to Ending Date /o ODCM Receptor Limit Bone 1.OOE+01 mRem 1.89E-03 1.89E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.OOE+01 mRem 4.18E-03 4.18E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.OOE+01 mRem 4.71E-03 4.71E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 6.44E-03 6.44E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 6.02E-03 6.02E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 3.87E-03 3.87E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 5.69E-03 1.90E-01 Maximum Individual Liquid Liquid Effluent TB Annual Page 26 of 84

Table 1-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a member of the public due to Liquid Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Ouarter Organ ODCM Lmt Units 1ST Otr %/oODCM 2ND Qtr %/oODCM 3RD Otr O/o ODCM 4TH Qtr O/% ODCM Bone 5.O0E+00 mRem 3.98E-03 7.97E-02 9.55E-04 1.91E-02 3.12E-03 6.24E-02 4.76E-03 9.52E-02 GI-Lli 5.OOE+00 mRem 1.17E-02 2.34E-01 4.18E-03 8.36E-02 2.62E-02 5.24E-01 4.55E-03 9.11E-02 Kidney 5.OOE+00 mRem 1.24E-02 2.48E-01 4.08E-03 8.15E-02 2.11E-02 4.22E-01 4.13E-03 8.26E-02 Liver 5.OOE+00 mRem 1.47E-02 2.93E-01 4.81E-03 9.61E-02 1.89E-02 3.77E-01 8.73E-03 1.75E-01 Lung 5.OOE+00 mRem 1.97E-02 3.95E-01 7.95E-03 1.59E-01 7.33E-02 1.47E+00 2.77E-02 5.55E-01 Thyroid 5.OOE+00 mRem 9.18E-03 1.84E-01 3.71E-03 7.42E-02 1.75E-02 3.50E-01 1.94E-03 3.87E-02 Total Body 1.50E+00 mRem 1.30E-02 8.68E-01 4.48E-03 2.99E-01 1.82E-02 1.21E+00 6.70E-03 4.47E-01 Cumulative Doses per Year Organ ODCM Lmt 0/oODCM Receptor Units Year to Ending Date Limit Bone 1.00E+01 mRem 1.28E-02 1.28E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 4.66E-02 4.66E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 4.17E-02 4.17E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 4.71E-02 4.71E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.OOE+01 mRem 1.29E-01 1.29E+00 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.OOE+01 mRem 3.23E-02 3.23E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 4.24E-02 1.41E+00 Maximum Individual Liquid Liquid Effluent TB Annual Page 27 of 84

Table 1-4 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES Starting: 1-Jan-2011 Ending: 31-Dec-2011 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 gCi/ml Fe-59 8.33E-08 iCi/ml Co-58 3.78E-08 l.Ci/ml Co-60 6.76E-08 i.tCi/ml Zn-65 1.32E-07 lxCi/ml Mo-99 4.31E-07 l.Ci/ml Cs-134 3.06E-08 gCi/ml Cs-137 4.51E-08 gCi/ml Ce-141 6.99E-08 gCi/ml Ce-144 2.95E-07 pCi/ml 1-131 5.97E-08 gCi/ml Xe-133 9.11E-08 gCi/ml Xe-135 4.27E-08 gCi/ml Fe-55 1.OOE-06 gCi/ml Sr-89 5.OOE-08 gCi/ml Sr-90 7.OOE-09 gCi/ml H-3 2.OOE-06 gCi/ml Gross Alpha 7.OOE-08 gCi/ml Page 28 of 84

Table 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Liquid Releases Unitss 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 22 14 34 8 78

2. Total time period for Batch releases ( Min utes ) 6.94E+03 3.61E+03 1.28E+03 2.01E+03 2.53E+04

3. Maximum time period for a batch ( Min utes ) 1.01E+03 4.57E+02 1.11E+03 3.71E+02 1.11E+03

4. Average time period for a batch ( Min utes ) 3.15E+02 2.58E+02 3.75E+02 2.51E+02 3.24E+02

5. Minimum time period for a batch ( Min utes ) 5.OOE+01 4.60E+01 6.20E+01 5.50E+01 4.60E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 5910 7333 5047 3851 5535

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 for quarters 1,2, and 3. Qtr 4 data taken from U.S. Army Corps of Engineers Lake Thurmond Discharge rate.

http://water.sas.usace.army.mil/cf/AvgMonthly/AvgMonthly.cfm Page 29 of 84

Table 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Liquid Releases Unit.s 1ST Quarter 2ND Quarter 3Rr Quarter 4TH Quarter Year Totals

1. Number of batch releases 8 1 1 2 12

2. Total time period for Batch releases ( Min utes ) 2.91E+03 4.09E+02 9. 96E+02 5.05E+02 4.82E+03

3. Maximum time period for a batch ( Min utes) 6.97E+02 4.09E+02 9. 96E+02 2.68E+02 9.96E+02

4. Average time period for a batch ( Min utes ) 3.64E+02 4.09E+02 9. 96E+02 2.53E+02 4.02E+02

5. Minimum time period for a batch ( Min utes ) 5.10E+01 4.09E+02 9. 96E+02 2.37E+02 5.10E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 5910 7333 5047 3851 5535

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 for quarters 1,2, and 3. Qtr 4 data taken from U.S. Army Corps of Engineers Lake Thurmond Discharge rate.

http://water.sas.usace.army.mil/cf/AvgMonthly/AvgMonthly.cfm Page 30 of 84

Table 1-SC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Batch Release Summary Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Liquid Releases Unit s 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 30 15 35 10 90

2. Total time period for Batch releases (Min utes ) 9.85E+03 4.02E+03 1.38E+04 2.51E+03 3.01E+04

3. Maximum time period for a batch (Min utes ) 1.01E+03 4.57E+02 1.11E+03 3.71E+02 1.11E+03

4. Average time period for a batch (Min utes ) 3.28E+02 2.68E+02 3.93E+02 2.51E+02 3.35E+02

5. Minimum time period for a batch (Min utes )

J 5.00E+01 4.60E+01 6.20E+01 5.50E+01 4.60E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 5910 7333 5047 3851 5535

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 for quarters 1,2, and 3. Qtr 4 data taken from U.S. Army Corps of Engineers Lake Thurmond Discharge rate.

http://water.sas.usace.army.mil/cf/AvgMonthly/AvgMonthly.cfm Page 31 of 84

Table 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Liquid Releases Unit s 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 (Min utes) 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00

3. Maximum Time For A Release (Min utes) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

4. Average Time For A Release (Min utes) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

5. Minimum Time For A Release (Min utes) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

6. Total activity for all releases (Cur ries ) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 32 of 84

Table 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes) 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00

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

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

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

6. Total activity for all releases (Curies ) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 33 of 84

Table 1-6C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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.OOE+00 0.OOE+00 0.OOE+00

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

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

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

6. Total activity for all releases ( Curies ) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Page 34 of 84

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

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

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

b. For Iodine-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-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following.

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

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

Page 35 of 84

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.

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 analyses results and release flow rates form the basis for calculating released quantities of radionuclide specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year.

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

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

Page 36 of 84

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 analyses 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 84

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.

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 84

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

To complete 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 gCi/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 84

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

2.4 Radiological Impact Due to Gaseous Releases Dose rates due to the release of noble gases were calculated for the site in accordance with ODCM 3.4.1.1. Dose rates due to radioiodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.

Dose rates were calculated as part of pre-release and post release permits, no limits were exceeded for this reporting period.

Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.4.2. These results are presented in Tables 2-4A and 2-4B.

Cumulative doses to a Member of the Public were calculated for each unit in accordance with ODCM 3.4.3. These results are presented in Tables 2-5A and 2-5B.

Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.

2.5 Gaseous Effluents - Batch Releases Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 2-7A and 2-7B.

2.6 Gaseous Effluents- Abnormal Releases During disposal of a Unit 2 Reactor Coolant System filter into a High Integrity Container (HIC) in the Radwaste Processing Facility's (RPF), Radiation Monitor 16980A (radioactive particulate building exhaust) air channel went into alarm.

The alarm was in for approximately 20 seconds and then cleared. The alarm was not due to any particulate being present. When the filter was dropped into the HIC, a small, immeasurable puff of noble gas reached the radiation monitor (most likely Xe-1 33). A permit was not needed for the sparse amount released.

However, this work activity was closely monitored throughout the rest of the year. There were no more occurrences of alarms during HIC transfer and drop.

Page 40 of 84

Table 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.79E+00 5.98E-01 3.66E-01 5.25E-02

2. Average Release rate for period uCi/sec 2.27E-01 7.59E-02 4.65E-02 6.66E-03

3. Percent of Applicable Limit %* * *

B. Radioiodines

1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit %* * *

C. Particulates

1. Particulates ( Half-Lives > 8 Curies 2.67E-07 9.99E-07 O.OOE+00 3.63E-07

2. Average Release rate for period uCi/sec 3.38E-08 1.27E-07 O.OOE+00 4.60E-08

3. Percent of Applicable Limit %* * *

D. Tritium

1. Total Release Curies 4.80E+00 1.12E+00 1.42E+00 5.12E+00

2. Average Release rate for period uCi/sec 6.08E-01 1.42E-01 1.80E-01 6.50E-01

3. Percent of Applicable Limit %* * *

E. Gross Alpha

1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

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

Page 41 of 84

Table 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.47E+00 1.33E+01 3.33E+01 3.42E+00

2. Average Release rate for period uCi/sec 8.21E-01 1.69E+01 4.23E+00 4.33E-01

3. Percent of Applicable Limit %* * *

B. Radioiodines

1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit %* * *

C. Particulates

1. Particulates ( Half-Lives > 8 Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit %* * *

D. Tritium

1. Total Release Curies 2.45E+00 3.66E+00 1.02E+01 1.21E+01

2. Average Release rate for period uCi/sec 3.11E-01 4.64E-01 1.30E+00 1.54E+00

3. Percent of Applicable Limit %* * *

E. Gross Alpha

1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

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

Page 42 of 84

Table 2-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Unit s 1ST Quarter 2ND Ouarter 3R1) Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 8.27E+00 1.39E+01 3.37E+01 3.47E+00

2. Average Release rate for period uCi/sec 1.05E+00 1.76E+00 4.27E+00 4.40E-01

3. Percent of Applicable Limit B. Radioliodines

1. Total Iodine-131 Curies 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00

2. Average Release rate for period uCi/sec 0.00E+00 0.00E+00 0.00E+00 0.OOE+00

3. Percent of Applicable Limit %*

C. Particulates

1. Particulates ( Half-Lives > 8 Curies 2.67E-07 9.99E-07 0.00E+00 3.63E-07

2. Average Release rate for period uCi/sec 3.38E-08 1.27E-07 0.00E+00 4.60E-08

3. Percent of Applicable Limit %*

D. Tritium

1. Total Release Curies 7.25E+00 4.79E+00 1.17E+01 1.72E+01

2. Average Release rate for period uCi/sec 9.19E-01 6.07E-01 1.48E+00 2.18E+00

3. Percent of Applicable Limit *

E. Gross Alpha

1. Total Release Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average Release rate for period uCi/sec 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00

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

Page 43 of 84

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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 Be-7 Curies O.OOE+O0 4.41E-07 O.OOE+O0 O.OOE+O0 Co-58 Curies O.OOE+O0 5.58E-07 O.OOE+O0 O.OOE+O0 Sr-89 Curies 2.67E-07 O.OOE+O0 O.OOE+O0 3.63E-07 Total For Period Curies 2.67E-07 9.99E-07 0.OOE+00 3.63E-07 Tritium H-3 Curies 3.07E+00 9.43E-01 9.41E-01 5.03E+00 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 44 of 84

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.78E+00 5.40E-02 3.66E-01 5.05E-02 Kr-85M Curies 0.OOE+00 1.22E-03 0.OOE+00 0.OOE+00 Kr-85 Curies 0.OOE+00 3.64E-01 0.OOE+00 0.OOE+00 Xe-133M Curies 0.OOE+00 1.20E-03 0.OOE+00 0.OOE+00 Xe-133 Curies 0.OOE+00 1.47E-01 0.OOE+00 0.OOE+00 Xe-135 Curies 0.OOE+00 3.04E-02 0.OOE+00 0.OOE+00 Total For Period Curies 1.78E+00 5.98E-01 3.66E-01 5.05E-02 lodines No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Particulates No Nuclides Found Curies 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium H-3 Curies 1.65E+00 1.81E-01 4.75E-01 9.19E-02 Gross Alpha No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 45 of 84

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units .1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies 0.00E+00 0.00E+00 2.94E+00 3.35E+00 Total For Period Curies 0.OOE+00 0.00E+00 2.94E+00 3.35E+00 lodines No Nuclides Found Curies 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Particulates Sr-89 Curies 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Tritium H-3 Curies 1.27E+00 3.37E+00 9. 10E+00 1.20E+01 Gross Alpha No Nuclides Found Curies 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 46 of 84

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 8.77E-01 6.63E-01 2.85E+00 2.12E-02 Kr-85M Curies 0.OOE+00 3.97E-02 1.31E-02 0.OOE+00 Kr-85 Curies 5.74E-01 1.92E+00 0.OOE+00 0.OOE+00 Kr-87 Curies 0.OOE+00 3.06E-03 0.00E+00 0.OOE+00 Kr-88 Curies 0.00E+00 3.78E-02 0.OOE+00 2.18E-02 Xe-133M Curies 0.OOE+00 1.25E-01 2.37E-02 0.OOE+00 Xe-133 Curies 4.94E+00 9.46E+00 2.40E+01 4.40E-02 Xe-135 Curies 7.87E-02 1.06E+00 3.29E+00 4.73E-04 Total For Period Curies 6.47E+00 1.33E+01 3.04E+01 6.57E-02 Iodines No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Particulates No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium H-3 Curies 1.17E+00 2.88E-01 1.14E+00 1.17E-01 Gross Alpha No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Page 47 of 84

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies 0.OOE+00 0.OOE+00 2.94E+00 3.35E+00 Total For Period Curies 0.OOE+00 0.OOE+00 2.94E+00 3.35E+00 lodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates Be-7 Curies O.OOE+00 4.41E-07 0.OOE+00 0.00E+00 Co-58 Curies O.OOE+O0 5.58E-07 0.OOE+O0 0.OOE+00 Sr-89 Curies 2.67E-07 0.OOE+00 0.OOE+00 3.63E-07 Total For Period Curies 2.67E-07 9.99E-07 0.OOE+00 3.63E-07 Tritium H-3 Curies 4.35E+00 4.32E+00 1.0OE+01 1.70E+01 Gross Alpha No Nuclides Found Curies 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 48 of 84

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.65E+00 7.17E-01 3.21E+00 7.17E-02 Kr-85M Curies O.OOE+00 4.09E-02 1.31E-02 O.OOE+00 Kr-85 Curies 5.74E-01 2.29E+00 O.OOE+00 O.OOE+00 Kr-87 Curies O.OOE+00 3.06E-03 O.OOE+00 O.OOE+00 Kr-88 Curies O.OOE+00 3.78E-02 O.OOE+00 O.OOE+00 Xe-133M Curies O.OOE+00 1.27E-01 2.37E-01 O.OOE+00 Xe-133 Curies 4.94E+00 9.61E+00 2.40E+01 4.40E-02 Xe-135 Curies 7.87E-02 1.09E+00 3.29E+00 4.73E-04 Total For Period Curies 8.25E+00 1.39E+01 3.07E+01 1.16E-01 lodines No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Particulates No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium H-3 Curies 2.83E+00 4.68E-01 1.61E+00 2.09E-0 1 Gross Alpha No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 49 of 84

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2010 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-. 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Iodines No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Page 50 of 84

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.58E-02 0.OOE+00 0.OOE+00 1.99E-03 Total For Period Curies 1.58E-02 0.OOE+0O 0.OOE+OO 1.99E-03 lodines No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 Particulates No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium H-3 Curies 6.91E-02 0.OOE+0O 0.OOE+00 1.44E-03 Gross Alpha No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 51 of 84

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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 Iodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

Page 52 of 84

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+00 O.OOE+00 7.74E-04 O.OOE+00 Xe-133 Curies O.OOE+00 O.OOE+00 5.96E-03 O.OOE+00 Xe-135 Curies O.OOE+00 O.OOE+00 1.07E-03 O.OOE+00 Total For Period Curies 0.OOE+00 0.OOE+00 7.80E-03 0.OOE+00 lodines No Nuclides Found Curies 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium H-3 Curies 0.OOE+00 O.OOE+00 2.84E-03 3.05E-03 Gross Alpha No Nuclides Found Curies 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 53 of 84

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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 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 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 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 54 of 84

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.58E-02 O.OOE+00 7.74E-04 1.99E-03 Xe-133 Curies O.OOE+00 O.OOE+00 5.96E-03 O.OOE+00 Xe-135 Curies O.OOE+00 O.OOE+00 1.07E-03 O.OOE+00 Total For Period Curies 1.58E-02 0.OOE+00 7.80E-03 1.99E-03 Iodines No Nuclides Found Curies 0.OOE+00 0.OOE+/-00 O.OOE+00 0.OOE+00 Particulates No Nuclides Found Curies 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Tritium H-3 Curies 6.91E-02 0.OOE+00 2.84E-03 4.49E-03 Gross Alpha No Nuclides Found Curies 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+/-00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 55 of 84

Table 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Air Doses Due to Gaseous Release Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter 0

Type of Radiation ODCM Units 1ST Qtr 0/0 ODCM 2ND Qtr %/oODCM 3RD Qtr °/o ODCM 4TH Qtr /6 ODCM Gamma Air 5.00E+00 mRad 2.54E-04 5.08E-03 9.09E-06 1.82E-04 4.99E-05 9.98E-04 6.88E-06 1.38E-04 Beta Air 1.OOE+01 mRad 8.96E-05 8.96E-04 1.64E-O5 1.64E-04 1.76E-05 1.76E-04 2.43E-06 2.43E-05 Cumulative Doses Per Year Type of Radiation ODCM Unit Year to End %/oODCM Receptor Limit Gamma Air 1.00E+01 mRad 3.20E-04 3.20E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 1.26E-04 6.30E-04 Site Boundary / Child Air Dose Beta Annual 1.21 Page 56 of 84

Table 2-4B3 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Air Doses Due to Gaseous Release Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter 0

Type of Radiation ODCM Units 1ST Qtr /6 ODCM 2ND Qtr %oODCM 3RD Qtr %/oODCM 4TH Qtr %/oODCM Gamma Air 5.OOE+00 mRad 1.47E-04 2.95E-03 1.80E-04 3.59E-03 6.22E-04 1.24E-02 2.04E-05 4.09E-04 Beta Air 1.00E+01 mRad 1.37E-04 1.37E-03 2.76E-04 2.76E-03 6.76E-04 6.76E-03 5.32E-05 5.32E-04 Cumulative Doses Per Year Type of Radiation ODCM Unit Year to End 0/0 ODCM Receptor Limit Gamma Air 1.OOE+01 mRad 9.69E-04 9.69E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 1.14E-03 5.71E-03 Site Boundary / Child Air Dose Beta Annual 1.21 Page 57 of 84

Table 2-4C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Air Doses Due to Gaseous Release Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter 0

Type of Radiation ODCM Units 1ST Qtr /o ODCM 2ND Qtr 0/o ODCM 3RD Qtr 0/0 ODCM 4TH Qtr %/cODCM Gamma Air 5.00E+00 mRad 4.01E-04 8.03E-03 1.89E-04 3.77E-03 6.72E-04 1.34E-02 2.73E-05 5.47E-04 Beta Air 1.00E+01 mRad 2.27E-04 2.27E-03 2.93E-04 2.93E-03 6.93E-04 6.93E-03 5.57E-05 5.57E-04 Cumulative Doses Per Year Type of Radiation ODCM Unit Year to End %/oODCM Receptor Limit Gamma Air 1.00E+01 mRad 1.29E-03 1.29E-02 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 1.27E-03 6.34E-03 Site Boundary / Child Air Dose Beta Annual 1.21 Page 58 of 84

Table 2-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter 0

Organ ODCM Units 1ST Qtr /b ODCM 2ND Qtr %/oODCM 3RD Qtr %/oODCM 4TH Qtr 0/0 ODC-I4 Bone 7.50E+00 mRem 3.13E-07 4.18E-06 6.64E-09 8.86E-08 O.OOE+00 0.O0E+00 4.26E-07 5.69E-06 GI-Lli 7.50E+00 mRem 1.10E-04 1.46E-03 2.43E-05 3.24E-04 3.06E-05 4.08E-04 1.11E-04 1.48E-03 Kidney 7.50E+00 mRem 1.10E-04 1.46E-03 2.43E-05 3.24E-04 3.06E-05 4.08E-04 1.11E-04 1.48E-03 Liver 7.50E+00 mRem 1. 1OE-04 1.46E-03 2.43E-05 3.24E-04 3.06E-05 4.08E-04 1.11E-04 1.48E-03 Lung 7.50E+00 mRem 1.10E-04 1.46E-03 2.43E-05 3.24E-04 3.06E-05 4.08E-04 1.11E-04 1.48E-03 Thyroid 7.50E+00 mRem 1. 1OE-04 1.46E-03 2.43E-05 3.24E-04 3.06E-05 4.08E-04 1.11E-04 1.48E-03 Total Body 7.50E+00 mRem 1. 1OE-04 1.46E-03 2.43E-05 3.24E-04 3.06E-05 4.08E-04 1.11E-04 1.48E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date %/oODCM Receptor Limit Bone 1.500E+01 mRem 7.465E-07 4.977E-06 Maximum Ind ividual/ Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 2.751E-04 1.834E-03 Maximum Ind ividual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 2.751E-04 1.834E-03 Maximum Ind ividual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 2.751E-04 1.834E-03 Maximum Ind ividual/ Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 2.751E-04 1.834E-03 Maximum Ind ividual/ Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 2.751E-04 1.834E-03 Maximum Ind ividual/ Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 2.751E-04 1.834E-03 Maximum Ind ividual/ Child Iodine/Part Dose Annual 1.21 Page 59 of 84

Table 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr %/oODCM 2ND Qtr %/oODCM 3RD Qtr O/o ODCM 4TH Qtr °/o ODCM Bone 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 GI-Lli 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 Kidney 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 Liver 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 Lung 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 Thyroid 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 Total Body 7.50E+00 mRem 5.29E-05 7.06E-04 7.92E-05 1.06E-03 2.22E-04 2.96E-03 2.62E-04 3.49E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date %/oODCM Receptor Limit Bone 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 6.157E-04 4.105E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 60 of 84

Table 2-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr %/oODCM 2ND Qtr %/oODCM 3RD Qtr %/oODCM 4TH Qtr % ODCM Bone 7.50E+00 mRem 3.13E-07 4.18E-06 6.64E-09 8.86E-08 O.OOE+00 O.OOE+00 4.26E-07 5.96E-06 GI-Lli 7.50E+00 mRem 1.62E-04 2.17E-03 1.03E-04 1.38E-03 2.52E-04 3.36E-03 3.37E-04 4.97E-03 Kidney 7.50E+00 mRem 1.62E-04 2.17E-03 1.03E-04 1.38E-03 2.52E-04 3.36E-03 3.37E-04 4.97E-03 Liver 7.50E+00 mRem 1.62E-04 2.17E-03 1.03E-04 1.38E-03 2.52E-04 3.36E-03 3.37E-04 4.97E-03 Lung 7.50E+00 mRem 1.62E-04 2.17E-03 1.03E-04 1.38E-03 2.52E-04 3.36E-03 3.37E-04 4.97E-03 Thyroid 7.50E+00 mRem 1.62E-04 2.17E-03 1.03E-04 1.38E-03 2.52E-04 3.36E-03 3.37E-04 4.97E-03 Total Body 7.50E+00 mRem 1.62E-04 2.17E-03 1.03E-04 1.38E-03 2.52E-04 3.36E-03 3.37E-04 4.97E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date % ODCM Receptor Limit Bone 1.500E+01 mRem 7.465E-07 4.977E-06 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 8.909E-04 5.939E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 8.908E-04 5.939E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 8.908E-04 5.939E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 8.908E-04 5.939E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 8.908E-04 5.939E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 8.909E-04 5.939E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 61 of 84

Table 2-6 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 MINIMUM DETECTABLE CONCENTRATIONS GASEOUS SAMPLE ANALYSES Starting: 1-Jan-2011 Ending: 31-Dec-2011 RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 gCi/ml Kr-88 2.53E-08 gCi/ml Xe-133 2.05E-08 gCi/ml Xe-133m 8.63E-08 gCi/ml Xe-135 7.12E-08 gCi/ml Xe-138 1.05E-07 gCi/ml 1-131 7.93E-15* gCi/ml Mn-54 3.94E-14* pCi/ml Fe-59 2.45E-14* gCi/ml Co-58 1.39E-14* gCi/ml Co-60 1.75E-14* gCi/ml Zn-65 2.82E-14* gCi/ml Mo-99 9.57E-14* gCi/ml Cs-134 1.12E-14* pCi/ml Cs-137 8.71E-15* pCi/ml Ce-141 8.62E-15* gCi/ml Ce-144 2.77E-14* gCi/ml Sr-89 1.00E-13 gCi/ml Sr-90 1.OOE-13 gCi/ml H-3 9.OOE-08 ptCi/ml Gross Alpha 1.OOE-13 gCi/ml

Based on an estimated sample volume of 5.7E+08 mls for particulate filters and charcoal cartridges.

Page 62 of 84

Table 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 44 32 30 25 131

2. Total time period for batch releases ( Minutes ) 3.71E+04 7.86E+03 1.27E+04 1.75E+03 5.95E+04

3. Maximum time period for a batch ( Minutes ) 6.49E+03 1.74E+03 3.37E+03 1.62E+02 6.49E+03

4. Average time period for a batch ( Minutes ) 8.44E+02 2.46E+02 4.24E+02 7.01E+01 4.54E+02

5. Minimum time period for a batch ( Minutes ) 1.50E+01 1.50E+01 9.OOE+00 2.70E+01 9.OOE+00 Page 63 of 84

Table 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 21 25 38 20 104

2. Total time period for batch releases ( Minutes ) 1.27E+04 2.32E+04 4.56E+04 1.11E+04 9.25E+04

3. Maximum time period for a batch ( Minutes ) 4.09E+03 6.19E+03 5.71E+03 5.64E+03 6.19E+03

4. Average time period for a batch ( Minutes ) 6.03E+02 9.26E+02 1.23E+03 5.54E+02 8.89E+02

5. Minimum time period for a batch ( Minutes ) 3.70E+01 3.10E+01 1.OOE+00 2.OOE+01 1.OOE+00 Page 64 of 84

Table 2-7C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Batch Release Summary Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 65 57 68 45 235

2. Total time period for batch releases ( Minutes ) 4.98E+04 3.10E+04 5.83E+04 1.28E+04 1.52E+05

3. Maximum time period for a batch ( Minutes ) 6.49E+03 6.19E+03 5.71E+03 5.64E+03 6.49E+03

4. Average time period for a batch ( Minutes ) 7.66E+02 5.44E+02 8.58E+02 2.85E+02 6.47E+02

5. Minimum time period for a batch ( Minutes ) 1.50E+01 1.50E+O1 1.OOE+O0 2.00E+O1 1.OOE+O0 Page 65 of 84

Table 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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 O.OOE+00 0.OOE+00 0.OOE+00

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

4. Average Time For A Release ( Minutes ) O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+/-00 0.OOE+00

5. Minimum Time For A Release ( Minutes ) O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+/-00 0.OOE+00

6. Total activity for all releases ( Curies ) O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 A. Fission And Activation Products

1. Total Release (not includinq tritium, gases, alpha) Curies O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00

2. Average diluted concentration during period uCi/mL O.OOE+00 O.OOE+00 0.OOE+00

3. Percent of Applicable Limit 0.OOE+00 B. Tritium *.OE0

1. Total Release Curies O.OOE+00 O.OOE+00

2. Average diluted Concentration 0.OOE+00 0.OOE+00 during period uCi/mL O.OOE+00 O.OOE+00

3. Percent of Applicable Limit 0.OOE+00 0.OOE+00 C. Dissolved and Entrained Gases

1. Total Release Curies O.OOE+00 O.OOE+00

2. Average diluted Concentration 0.OOE+00 0.OOE+00 during period uCi/mL O.OOE+00 O.OOE+00

3. Percent of Applicable Limit Page 66 of 84

Table 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT'- 2011 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

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

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

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

6. Total activity for all releases ( Curies ) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 A. Fission And Activation Products

1. Total Release (not includinq tritium, gases, alpha) Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average diluted concentration during period uCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average diluted Concentration during period uCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

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

1. Total Release Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average diluted Concentration during period uCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

t

3. Percent of Applicable Limit Page 67 of 84

Table 2-8C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

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

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

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

6. Total activity for all releases ( Curies ) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 A. Fission And Activation Products

1. Total Release (not includinq tritium, gases, alpha) Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average diluted concentration during period uCi/mL 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00

3. Percent of Applicable Limit B. Tritium *.OE0

1. Total Release Curies 0.OOE+00 0.OOE+00 0.OOE+00

2. Average diluted Concentration 0.OOE+00 during period uCi/mL 0.OOE+00 0.OOE+00 0.OOE+00

3. Percent of Applicable Limit 0.OOE+00 C. Dissolved and Entrained Gases

1. Total Release Curies 0.OOE+00 0.OOE+00 0.OOE+00

2. Average diluted Concentration 0.OOE+00 during period uCi/mL 0.OOE+00 0.OOE+00 0.OOE+00

3. Percent of Applicable Limit Page 68 of 84

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.

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

Page 69 of 84

Table 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 1 of 4 JANUARY 1, 2011 THROUGH JUNE 30, 2011 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Non Irradiated Fuel)

1. Type of waste Type of Waste Unit 6 month Est. Total Period Error, %

a. Spent Resins, Filter sludges, evaporator Bottoms, m3 NONE N/A etc Ci

b. Dry Compressible Waste, Contaminated m3 147.25 10%

Equipment, etc Ci 1.98e-1

c. Irradiated components, control rods, etc m3 Ci CiNONE N/A 3

d. Other (describe) Secondary Side Resin (SGBD) m 31.31 Ci 1.65E-2

As Shipped

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

Type of Nuclide Percentage waste

a. N/A %

N/A %

b. Co-58 % 34.454 Co-60 % 30.192 Ni-63 % 13.919 Fe-55 % 8.113 H-3 % 3.744 Others 9.578

c. N/A %

N/A %

d. Ni-63 % 33.128 Co-60 % 33.018 Fe-55 % 20.472 H-3 % 7.814 others % 5.568

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Tractor/Trailer Energy Solutions, Oak Ridge, TN 2 Tractor/Trailer Energy Solutions, Kingston, TN Page 70 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 2 of 4 JANUARY 1, 2011 THROUGH JUNE 30, 2011 B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination NONE ADDITIONAL INFORMATION REQUIRED BY ODCM:

Shipments to a Waste Processor Shipment No. Waste Type Container Shipping Solidification Agent Processor Class Class RVRS-11-001 A IP-1 Limited NONE Energy Quantity Solutions RVRS-11-002 A IP-1 LSA-I NONE Energy Solutions RVRS- 11-003 A IP- 1 LSA-I NONE Energy Solutions RVRS- 11-004 A IP-1 LSA-I NONE Energy Solutions RVRS-11-005* A IP-1 Limited NONE Energy Quantity Solutions

Steam Generator Blowdown resin goes to Energy Solutions for final evaluation and release.

Page 71 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units I and 2 Page 3 of 4 JULY 1, 2011 THROUGH DECEMBER 31, 2011 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of waste Type of Waste Unit 6 month Est. Total Period Error, %

a. Spent Resins, Filter sludges, evaporator Bottoms, m3 13.5 25%

etc Ci 2.832

b. Dry Compressible Waste, Contaminated m3 299.875 25%

Equipment, etc Ci 1.8

c. Irradiated components, control rods, etc m1 Ci

d. Other (describe) Secondary Side Resin (SGBD) m3 78.83*

- GIC Program Ci 1.03E-2

As Shipped

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

Type of Nuclide Percentage waste

a. Ni-63 % 45.84 Co-60 % 25.61 Fe-55 % 18.29 Mn-54 % 3.18 Cs-137 % 2.02 Other % 5.06

b. Co-60 % 36.77 Ni-63 % 20.58 Fe-55 % 14.66 Co-58 % 9.23 H-3 % 11.68 Others % 7.08

c. N/A %

N/A %

D Co-60 % 37.49 Ni-63 % 21.14 Fe-55 % 14.84 Co-58 % 11.97 H-3 % 7.90 Others % 6.66

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2 Cask/Tractor/Trailer Energy Solutions, Oak Ridge, TN 5 Tractor/Trailer Energy Solutions, Oak Ridge, TN 4 Tractor/Trailer Energy Solutions, Kingston, TN Page 72 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2010 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 4 of 4 July 1, 2011 THROUGH December 31, 2011 B. Irradiated Fuel Shipments NNNumber of Shipments Mode of Transportation Destination NONE Additional Information Required by ODCM:

Shipments Sent Directly to Di;posal Shipment No. Waste Type Container Shipping Class Solidification Volume Class Agent NONE Shipments to a Waste Processor Shipment No. Waste Type Container Shipping Class Solidification Processor Class Agent RVRS-11-006 A IP-1 LSA-I NONE Energy Solutions RVRS- 11-007 A IP- 1 LSA-II NONE Energy Solutions RVRS-11-008" A IP-1 (SGBD) Limited NONE Energy Quantity Solutions RVRS-1 1-009 A IP-1 LSA-I NONE Energy Solutions RVRS-11-010 A IP-1 LSA-I NONE Energy Solutions RVRS-11-011 A IP-1 LSA-I NONE Energy Solutions RVRS-11-012* A IP-I (SGBD) Limited NONE Energy Quantity Solutions RVRS- 11-013 A IP-I LSA-I NONE Energy Solutions RVRS-11-014 A IP-I LSA-I NONE Energy Solutions RVRS-11-015* A IP-I (SGBD) Limited NONE Energy Quantity Solutions RVRS-11-016* A IP-I (SGBD) Limited NONE Energy Quantity Solutions

Steam Generator blowdown resin goes to Energy Solutions for final evaluation and release.

Page 73 of 84

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 - 2011 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Location Name: Visitor's Center Receptor Distance (kilometers): 4.47E-01 Sector: SE Occupancy Factor: 4.57E-04 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3): 5.93E-06 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 5.58E-06 D/Q (m-2): 2.28E-08 Mixed Mode Release Noble Gas X/Q (sec/m3): 7.12E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 6.74E-07 D/Q (m-2): 5.77E-09 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 1.56E-12 1.77E-11 0.O0E+00 2.13E-12 2.14E-11 Liver mRem 9.01E-08 5.56E-08 1.36E-07 2.OOE-07 4.82E-07 Total Body mRem 9.01E-08 5.56E-08 1.36E-07 2.OOE-07 4.82E-07 Thyroid mRem 9.01E-08 5.56E-08 1.36E-07 2.OOE-07 4.82E-07 Kidney mRem 9.01E-08 5.56E-08 1.36E-07 2.OOE-07 4.82E-07 Lung mRem 9.01E-08 5.56E-08 1.36E-07 2.OOE-07 4.82E-07 GI-Lli mRem 9.01E-08 5.56E-08 1.36E-07 2.OOE-07 4.82E-07 NG Total Body rnRern 2.71E-07 1.22E-07 4.38E-07 1.68E-08 8.47E-07 Whole Body Dose mRem 3.61E-07 1.78E-07 5.74E-07 2.17E-07 1.33E-06 Page 75 of 84

Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Location Name: Units 3&4 Construction Distance (kilometers): 4.83E-01 Sector: SW Occupancy Factor: 2.37E-01 Age Group: Adult Ground Level Release Noble Gas X/Q (sec/m3): 1.81E-05 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 6.93E-06 D/Q (m-2): 2.88E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/rn3): 6.96E-06 D/Q (m-2): 2.88E-08 Mixed Mode Release Noble Gas X/Q (sec/m3): 9.75E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 9.17E-07 D/Q (m-2): 7.14E-09 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 5.61E-10 1.14E-08 O.OOE+00 7.63E-10 1.27E-08 Liver mRem 7.86E-05 4.45E-05 1.09E-04 1.61E-04 3.92E-04 Total Body mRem 7.86E-05 4.45E-05 1.09E-04 1.61E-04 3.92E-04 Thyroid mRem 7.86E-05 4.45E-05 1.09E-04 1.61E-04 3.92E-04 Kidney mRem 7.86E-05 4.45E-05 1.09E-04 1.61E-04 3.92E-04 Lung mRem 7.86E-05 4.45E-05 1.09E-04 1.61E-04 3.92E-04 GI-Lli mRem 7.86E-05 4.45E-05 1.09E-04 1.61E-04 3.92E-04 NG Total Body mRem 2.03E-04 8.68E-05 3.12E-04 1.20E-05 6.14E-04 Whole Body Dose mRem 2.82E-04 1.31E-04 4.21E-04 1.73E-04 1.01E-03 Page 76 of 84

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 The inoperability of liquid and gaseous effluent monitors not corrected within the specified time for this reporting period is detailed below:

a. 1RE-12839C,D,E,F 1RE-1 2839C was experiencing multiple power resets. The Analog to Digital Converter board was replaced. The monitor was out of service greater than 30 days due to extensive troubleshooting to identify the problem in addition to the lack parts availability. 1RE-12839C,D,E was returned to service on 2/21/12. 1RE-12839F was returned to service 3/11/12.

b. 1FT-1085A This flow transmitter was taken out of service due to failing calibration in November 2011. This monitor remains out of service because many resources and manpower were dedicated to troubleshooting and completing repair work on 1RE-006. Due to limited resources, the work needed for this monitor was not scheduled within 30 days of the monitor being out of service.

c. 1FT-12442 The flow transmitter for 1RE-1 2442 failed calibration and as a result, it was taken out of service. The correct part that is needed is scheduled to be onsite by 4/20/12. It is scheduled to be returned to service on 5/5/12.

d. AFT-0014 This flow transmitter is used to account for flow during a waste gas release. It was repaired during a waste gas system outage inJune 2011. It is awaiting functional testing during an actual waste gas release to be declared as returned to service.

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e. ARE-16980 A "No Process Flow" alarm started alarming approximately every five seconds. ARE 16980F was only showing 700 to 1500 SCFM. Flow is required to be 3000 to 18000. This monitor remains out of service because many resources and manpower were dedicated to troubleshooting and completing repair work on 1 RE-006. Due to limited resources, the work needed for this monitor was not scheduled within 30 days of the monitor being out of service. The expected return to service timeframe is 07/2012.

f. 2RE-12444 DE The D channel failed calibration with a high background. The E channel was out of service administratively since the D channel triggers the E channel to operate. Many resources and manpower was dedicated to troubleshooting and restoring 1 RE-006 to service when this monitor went out of service. Due to limited resources, the work needed for this monitor was not scheduled within 30 days of the monitor-being out of service. This monitor was returned to service on 2/21/12.

g. 2FT-1085B This flow transmitter was taken out of service due to failing calibration in November 2011. This monitor remains out of service because many resources and manpower were dedicated to troubleshooting and completing repair work on 1 RE-006. Due to limited resources, the work needed for this monitor was not scheduled within 30 days of the monitor being out of service.

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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.

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8.2 Description of Changes Changes were made to the Vogtle Electric Generating Plant ODCM for the period January 1, 2011 through December 31, 2011. Revision 28 was released in February 2011. A complete copy of the ODCM will be included with this report with changes identified by bars in the right hand margin of the document.

Revision 28, February 2011 Action Statements 47 and 51 were revised to include guidance for monitoring and estimating releases from the Plant Vent during short durations when the sample line heat tracing requires immediate maintenance action to prevent failure or to address an existing failed condition.

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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 2011 assessment period.

Liquid Radwaste System Major changes to the liquid radwaste facilities are those that contribute to significant changes in release; i.e., either decreases or increases in release volume or activity/dose.

There were no major changes to the liquid radwaste systems occurred during the 2011 assessment period.

Solid Radwaste System There were no major changes to the solid radwaste systems in the 2011 assessment period.

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Appendix A Vogtle Electric Generating Plant CARBON-14 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.

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

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

At Plant Vogtle, the annual quantity of C-14 released in gaseous effluents was estimated to be 12.08 Curies (per unit). Approximately 30% of the C-14 released is in the form of 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.

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Attachment 1 Revised Previous Reports 2010 Annual Radwaste Effluent Report Table 4-1 for Units 3&4 Construction Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2010 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2010 Ending: 31-Dec-2010 Location Name: Units 3&4 Construction Distance (kilometers): 4.83E-01 Sector: SW Occupancy Factor: 2.37E-01 Age Group: Adult Ground Level Release Noble Gas X/Q (sec/m3): 1.81E-05 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 6.93E-06 D/Q (m-2): 2.88E-08 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 6.96E-06 D/Q (m-2): 2.88E-08 Mixed Mode Release Noble Gas X/Q (sec/m3): 9.75E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 9.17E-07 D/Q (m-2): 7.14E-09 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 1.34E-06 1.17E-07 4.61E-08 2.75E-10 1.50E-06 Liver mRem 1.13E-04 7.84E-05 9.36E-05 4.26E-05 3.28E-04

Total Body mRem 1.13E-04 7.84E-05 9.36E-05 4.26E-05 3.28E-04 Thyroid mRem 2.57E-04 7.84E-05 9.36E-05 4.26E-05 4.71E-04 Kidney mRem 1. 14E-04 7.84E-05 9.36E-05 4.26E-05 3.28E-04 Lung mRem 1.13E-04 7.84E-05 9.36E-05 4.26E-05 3.28E-04 GI-Lli mRem .1.13E-04 7.84E-05 9.36E-05 4.26E-05 3.28E-04 NG Total Body mRem 9.22E-04 1.05E-04 1.04E-04 8.33E-05 1.21E-03 Whole Body Dose mRem 1.03E-03 1.83E-04 1.97E-04 1.26E-04 1.54E-03 Page 84 of 84

ML12122A144

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