NL-13-0889, Annual Radioactive Effluent Release Report for 2012

Annual Radioactive Effluent Release Report for 2012

ML13121A351
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	04/30/2013
From:	Pierce C Southern Nuclear Operating Co, Southern Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-13-0889
Download: ML13121A351 (249)

Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Cente r Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 April 30, 2013 SOUTHERN ' \

COMPANY Docket Nos. : 50-321 50-348 50-424 NL-13-0889 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATIN : Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Units 1 & 2 Joseph M. Farley Nuclear Plant - Units 1 & 2 Vogtle Electric Generating Plant - Units 1 & 2 Annual Radioactive Effluent Release Reports for 2012 Ladies and Gentlemen:

In accordance with section 5.6.3 of the referenced plants' Technical Specifications, Southern Nuclear Operating Company hereby submits the Annual Radioactive Effluent Release Reports for 2012 . The Annual Radioactive Effluent Release Report for the Edwin I. Hatch Nuclear Plant (Hatch), Joseph M. Farley Nuclear Plant (Farley), and the Vogtle Electric Generating Plant (Vogtle) are provided in Enclosures 1,2, and 3, respectively.

Technical Specification 5.5.1.c. for each plant requires that the Offsite Dose Calculation Manual (ODCM) be provided as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. During the reporting period for the Annual Radioactive Effluent Release Report for 2012, there were no changes to the ODCM from any of the sites.

Respectfully submitted, C . R. Pierce Regulatory Affairs Director CRP/GAUlac

U. S. Nuclear Regulatory Commission NL-13-0889 Page 2

Enclosures:

1. Hatch Annual Radioactive Effluent Release Report Effluent Release for II"\~I"TI\,IQ Effluent Release Report for cc:

U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Administrator Mr. R. Martin, Manager - Hatch, VogUe Mr. E. Morris, Inspector - Hatch Mr. L. M. Cain, Inspector - Vogtle Ms. A. Brown, Manager - Farley Mr. P. K. Niebaum, Inspector - Farley Mr. J. R. Inspector - Farley Mr. J. L. McNees, of Public Health, Office of Radiation State of Georgia Mr. M. Williams, lQr'\,~",rn""nT of Natural Resources

Edwin I. Hatch Nuclear Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2012 Enclosure 1 Hatch Annual Radioactive Effluent HeleSlse Report for 2012

SOUTHERN COMPANY E. I. HA TCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1,2012 THROUGH DECEMBER 31,2012

1.0 Liquid Effluents 1 1.1 Regulatory Requirements 1 1.1.1 Concentration limits 1 1.1.2 Dose limits 1 1 Effluent Concentration Lim it 1 1 Measurements and Approximations of Total 2 Radioactivity liquid Radwaste 1.3.1 Total Radioactivity Determ for liquid Radwaste 2 1.4 Measurements and Approximations Total 4 Radioactivity for Groundwater Outfall Y22N008A 1.4.1 Total Radioactivity Determination for Groundwater 4 Outfalls 1.5 Total Error Estimation 5 1.6 liquid Effluent Release Data 6 1.7 Radiological Impact Due to Liquid 7 1.8 liquid Effluents - Batch Releases 7 1.9 liquid Effluents - Continuous Releases 7

1.10 Liquid Effluents - Abnormal 7 Gaseous Effluents 27 2.1 Regulatory Requirements 27 2.1.1 Dose Rate Lim its 27 2.1 Air Doses Due to Noble ~g.:n:;,"" in Gaseous Releases 2.1.3 &.IV.;!::',"" to a Member the Public 27 2.2 Measurements and Approximations of Total 28 Rad i oactivity 2.2.1 Sample Collection and Analysis 28 Total Quantities of Radioactivity, Dose Rates 29 and Cumulative Doses 2.2.2.1 Fission and Activation 29 Radioiodine, Tritium and Particulate Releases 29 2.2.2.3 Gross Alpha Release 30 2.2.3 Total Estimation 30 2.3 Gaseous Effluent Release Data 2.4 Radiological Impact Due to Gaseous Kellea!;eS 33 2.5 Gaseous EfflUents - Batch Kellea~;es 33 2.6 Gaseous - Abnormal Releases 33 3.0 Solid Waste 62 3.1 Regulatory Requirements 62 3.1.1 Solid Radioactive Waste System 3.1.2 Reporting Requirements 62 ii

Solid Waste Data 63 4.0 Doses to Members of the Public Inside The 66 Site Boundary 4.1 Regulatory Requirements 66 4.2 Demonstration of Com 66 5.0 Total from Uranium Cycle (40 CFR 190) 71 5.1 Regulatory Requirements 71 5.2 Demonstration of Compliance 71 6.0 Meteorological Data 72 7.0 Program Deviations 73 7.1 Inoperable Liquid or Effluent 73 Monitoring Instrumentation 7.1.1 Regulatory Requirements 73

.2 Description of Deviations 73 Tanks Exceeding Curie Content Limits 73 7.2.1 Regulatory Requirements 73 Description of Deviations 73 7.3 Effluent Analysis Minimum 73 Detectable Concentration (MDC) 7.3.1 Regulatory Requirement 73 Description of Deviation 73 iii

8.0 Changes to the Plant Hatch 74 Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements 8.2 Description of Changes 74 9.0 Major Changes to the Liquid, Gaseous or 75 Solid Radwaste Treatment Systems 9.1 Regulatory Requirements 75 9.2 Description of Major Changes 75 iv

TABLE LIST Of TABLES PAGE 1-1A Liquid Effluents - Summation of All 8 Unit 1 (Quarters 1, 2, 3 and 4) 1-1B Liquid Effluents - Summation of All Releases 9 Unit 2 (Quarters 1, 3 and 4) 1-1C Liquid Effluents - Summation of All Kellea~;es 10 Site (Quarters 1, 3 and 4) 1 Liquid Effluents - Unit 1 (Quarters 1, 3 and 4) 11 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3 and 4) 14 1-2C Liquid Effluents - Site (Quarters 1, 2, 3 4) 16 1-3A to a Member of The Public Due to Liquid 19 Releases Unit 1 (Quarters 1.2,3 and 4) 1-3B Doses to a Member of The Public Due to Liquid 20 Releases Unit 2 (Quarters 1, 2, 3 and 4) 1 Minimum Detectable Concentration - 21 Liquid Sample Analysis 1-5A Liquid Effluents - Batch Release Summary 22 Unit 1 1-5B Liquid Effluents - Batch Release Summary Unit 2 v

1-6A Liquid Effluents - Abnormal Release 24 Summary Unit 1 1-68 Liquid Effluents - Abnormal Releas 25 Summary Unit 2 1 Liquid Effluents - Abnormal Release 26 Summary Site 2-1A Gaseous Effluents - Summation of All 34 Releases - Unit 1 (Quarters 1, 2, 3 and 4) 8 Effluents - Summation All Releases -Unit 2 (Quarters 1, 2, 3 and 4) 2-1C Gaseous Effluents - Summation of All 36 Releases - Site (Quarters 1,2,3 and 4) 2-2A Gaseous Effluents - Elevated K9119a!:t9S 37 Unit 1 (Quarters 1, 2, 3 and 4) 2-28 Gaseous Effluents - Elevated Releases 40 Unit 2 (Quarters 1, 2, 3 and 4) 2-2C Gaseous Effluents - Elevated Releases 43 Site (Quarters 1, 2, 3 and 4) 2-3A Gaseous Effluents - Ground Level 46 Unit 1 (Quarters 1, 3 and 4) 2-38 Gaseous Effluents - Ground Level Releases 48 Unit 2 (Quarters 1, 2, 3 and 4) 2-3C Gaseous Effluents - Ground Level Releases 50 (Quarters 1, 3 and 4) 2-4A Air Doses Due Noble \.:ICI;:Ilt:;::, in Gaseous 52 Releases - Unit 1 (Quarters 1, 3 and 4) vi

TABLE LIST OE TABLES PAGE 2-4B Air Doses Due to Noble Gases in Gaseous 53 Releases- Unit 2 (Quarters 1, 2, 3 and 4) 2-5A Doses to a Member of the Public Due to 54 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-5B Doses to a Member of the Public Due to 55 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-6 Minimum Detectable Concentration 56 Gaseous Sample Analyses 2-7A Gaseous Effluents - Batch Release 57 Summary Unit 1 2-7B Gaseous Effluents - Batch Release 58 Summary Unit 2 2-8A Gaseous Effluents - Abnormal Release 59 Summary Unit 1 2-8B Gaseous Effluents - Abnormal Release 60 Summary Unit 2 2-8C Gaseous Effluents - Abnormal Release 61 Summary Site 3-1 Solid Waste and Irradiated Fuel Shipments 64 4-1 Doses to a Member of the Public Due to 61 Activities Inside The Site Boundary vii

1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration Limits The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1E-04 microcuries/ml total activity.

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

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

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

1.2 Effluent Concentration Limit ECl values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, 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 uCi/ml total activity.

For gross alpha in liquid radwaste, the ECl is 2E-09 uCilml.

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

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

The method utilizing the ECl fraction to determine dose released from groundwater outfalls is described in Subsection 1 of this report.

1.3 Measurements and Approximations of Total Radioactivity for Liquid Radwaste Prior to the any tank containing liquid following the required recirculations, are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose (ODCM) sample from planned for for principal gamma 131, and entrained noble by gamma spectroscopy. Monthly quarterly are prepared for analysis by extracting aliquots from taken from the Liquid radwaste in Section 1.3.1.

1.3.1 Total Radioactivity Determination for Liquid ~a,nllll'a"'J MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with com puterized reduction

2. or entrained Each Gamma Spectroscopy with computerized data reduction

3. Tritium Monthly Com Distillation and liquid scintillation counting

4. Gross Monthly Gas flow proportional counting

s. & Quarterly Chemical separation flow proportional

6. Quarterly Chemical separation and liquid scintillation counting 2

Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 keV or lower. The detectors are shielded by four inches of lead.

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

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

The radionuclide concentrations determined by gamma spectroscopic analysis of samples taken from tanks planned for release, in addition to the most current sample analysis results available for trWum, gross alpha, Sr-89, Sr-90 and Fe-55, are used along with the corresponding ECl values to determine the ECl fraction for these tanks.

This ECl fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded.

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

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

3

1.4 Measurements and Approximations of Total Radioactivity for Groundwater Outfall-Y22N008A Samples are collected and analyzed in accordance with the I. Hatch Nuclear Plant Dose Calculation Manual (ODeM) Table Weekly, monthly and quarterly com are for analysis by extracting aliquots from each outfall's automatic sampler, which collects a composite sample over a seven-day Sample are as described in Section 1.4.1 1.4.1 Total Radioactivity Determination for Groundwater Outfalls MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Weekly Composite Gamma Spectroscopy with computerized reduction Tritium Weekly Composite Distillation and liquid scintil counting Gross Quarterly Composite Chemical separation and flow proportional or scintillation counting

4. Sr-89 & 90*

• Quarterly Composite Chemical separation and gas flow proportional or scintillation counting

• Gross anaylsis is used for sample screening.

• • If Gross beta analysis yields a detectable value background, a Sr-89/90 analysis will performed.

4

Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 keV or lower. The detectors are shielded by four inches of lead.

A weekly composite sample is typically counted to Environmental MOC's and a peak search of the resulting gamma ray spectrum is performed. Energy and net count data for all significant peaks are determined and a quantitative reduction or MOC calculation is performed to ensure that the MOC's are met for the nuclides specified in the aOCM Chapter 10 (i.e., Mn-54, Fe-59,Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MOC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present. Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

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

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

Radionuclide concentrations, safety factors and dilution stream flow rate are entered into the computer and a pre-release printout is generated for each release period.

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

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

1.6 Liquid Effluent Release Data Regulatory Guide 1.21, 2A and are found in this report as Unit 1, Table 1-18, for Unit 2 and Table 1-1C, for the site; Table 1 Unit 1, 1-28, for Unit and 1-2C, for the site. Typical liquid minimum detectable concentrations (MDC's) used for analyses are found in Table 1-4.

values for the four categories of Tables 1-1A, and 1-18, 1-1 C, are calculated and the completed as follows:

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

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

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

Gross radioactivity - measured gross alpha concentrations in the monthly composite samples are used to calculate total of alpha rad ioactivity.

6

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

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

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

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Table l-lA Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 1.73E-03 O.OOE+OO 6.S2E-04 1. 64E-04

2. Average diluted concentration during period uCi/mL S.43E-09 O.OOE+OO 2.06E-09 3.3SE-09

3. Percent of Applicable Limit  % * * *

• B. Tritium

1. Total Release Curies S.63E+OO O.OOE+OO 3.S2E+OO 1.41E+OO

2. Average diluted Concentration during period uCi/mL 1.76E-OS O.OOE+OO 1.06E-OS 2.S9E-OS

3. Percent of Applicable Limit  % * * * *

c. Dissolved and Entrained Gases

1. Total Release Curies O.OOE+OO O.OOE+OO 2.0SE-06 3.03E-06

2. Average diluted Concentration during period uCi/mL O.OOE+OO O.OOE+OO 6.2SE-12 6.1SE-ll

3. Percent of Applicable Limit  % * * *

• D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution) Liters 1.63E+06 O.OOE+OO 1.2SE+06 2.3SE+OS F. Volume of Dilution Water Used Liters 3.19E+OS O.OOE+OO 3.32E+OS 4.90E+07

• Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-38 of this report.

8

Table 1-18 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 liquid Effluents - Summation Of All Releases Unit: 2 Starting: I-Jan- 2012 31-Dec-2012 of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release tritium, gases, alpha) Curies 3.3SE-04 1.33E-OS S.02E-OS O.OOE+OO

2. Average diluted concentration period uCi/mL 8.S7E-ll 1.81E-12 9.S1E-12 O.OOE+OO

3. Percent of Limit  % * * * *

1. Total Release Curies 4.33E+OO 4. 19E-02 1.46E-02 1.46E-02

2. Average diluted Concentration during period uCi/mL 1.11E-06 S.73E-09 2.76E-09 3.74E-09

3. Percent of Applicable Limit  % * * *

• C. Gases

1. Total Release Curies 1.27E-03 O.OOE+OO O.OOE+OO O.OOE+OO

2. Average diluted Concentration during period uCi/mL 3.24E-IO O.OOE+OO O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit  % * * *

• D:

1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Release Liters 3.90E+06 3.S7E+06 3.S4E+06 2.05E+06 F. Volume of Dilution Water Used Liters 3.91E+09 7.32E+09 S.28E+09 3.89E+09

• limits are in terms of dose. See Tables 1-3A and 1-38 of this 9

Table 1-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Summation Of All Releases Unit: Site Starting: I-Jan- 2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 2.07E-03 1.33E-OS 7.32E-04 1.64E-04

2. Average diluted concentration during period uCi/ml 4.89E-1O 1.81E-12 1.30E-1O 4.16E-U

3. Percent of Applicable limit  % * * *

• B. Tritium

1. Total Release Curies 9.96E+OO 4.61E-02 3.S3E+OO 1.43E+OO

2. Average diluted Concentration during period uCi/ml 2.36E-06 6.30E-09 6.29E-07 3.63E-07

3. Percent of Applicable limit  % * * *

• C. Dissolved and Entrained Gases

1. Total Release Curies 1.27E-03 O.OOE+OO 2.0SE-06 3.03E-06

2. Average diluted Concentration during period uCi/ml 3.00E-IO O.OOE+OO 3.71E-13 7.68E-13

3. Percent of Applicable limit  % * * *

• D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution) liters S.S3E+06 3.S7E+06 4.79E+06 2.2SE+06 F. Volume of Dilution Water Used liters 4.23E+09 7.32E+09 S.61E+09 3.94E+09

• Applicable Ii mits are expressed in terms of dose. See Tables 1-3A and 1-38 of this report.

10

Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 1

';:t:!lI+inn' l-Jan-20l2 Ending: 3l-Dec-20l2 Continuous Mode Nuclides Released Unit 1ST Quarter 2NDuuan:er 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O,OOE+OO O.OOE+OO O.OOE+OO O,OOE+OO Tritium NO Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Curies O,OOE+OO O,OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was at detectable levels.

See Table 1-4 for minimum detectable concentrations. 11

Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Effluents Unit: 1 Starting: l-lan-20l2 3l-Dec-20l2 Batch Mode Unit lSTQuarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products As-76 Curies O.OOE+OO O.OOE+OO O.OOE+OO l.22E-OS Co-58 Curies 4.6SE-OS O.OOE+OO 2.84E-OS 2.7SE-06 Co-60 Curies 6.63E-04 O.OOE+OO 2.64E-04 S.36E-OS Cr-Sl Curies 3.84E-04 O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 Curies 3.1SE-04 O.OOE+OO O.OOE+OO O.OOE+OO Fe-59 Curies 2.41E-06 O.OOE+OO O.OOE+OO O.OOHOO Mn-S4 Curies 1.05E-04 O.OOE+OO 7.01E-OS 1.48E-OS Mn-56 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-OS Na-24 Curies O.OOE+OO O.OOE+OO 1. 59E-04 2.30E-OS Nb-9S Curies 6.23E-07 O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 Curies 2.S7E-OS O.OOE+OO O.OOE+OO 3.68E-09 Sr-89 Curies 6.89E-05 O.OOE+OO 2.24E-OS O.OOE+OO Sr-90 Curies 1.57E-OS O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 Curies 2.82E-OS O.OOE+OO 4.8SE-05 9.07E-06 Cs-137 Curies 6.52E-05 O.OOE+OO 8.95E-05 1.49E-OS Cs-138 Curies O.OOE+OO O.OOE+OO O.OOE+OO 7.80E-06 Zn-69M Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.52E-06 Curies 1.19E-05 O.OOE+OO O.OOE+OO O.OOE+OO Totar For Period Curies l.73E-03 O.OOE+OO 6.82E-04 1.64E-04 Tritium H-3 Curies S.63E+00 O.OOE+OO 3.52E+OO 1.41E+OO Zeroes in this table indicates that no was present at detectable levels.

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

Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec::-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Xe-135 Curies O.OOE+OO O.OOE+OO 2.0SE-06 3.03E-06 Total for Period Curies O.OOHOO O.OOE+OO 2.08E-06 3.03E-06 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table 1-28 Hatch Nuclear Plant RADIOA.CTIVE EFFLUENT RElEA.SE REPORT - 2012 Effluents Unit: 2 l-lan-2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD QU:lIrt.~r 4TH Quarter fission &. Activation Products Sr-89 Curies 1.17E-04 1.33E-05 5.02E-05 O.OOE+OO Total for Period Curies 1. 17E-04 1.33E-OS S.02E-OS O.OOE+OO Tritium H-3 Curies 1.78E-02 4.19E-02 1.46E-02 1.46E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no was present at detectable levels.

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

Table 1-2B Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Effluents Unit: 2 l-Jan-2012 31-Dec-2012 Batch Mode Nuclides Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &. Activation Products Y-92 Curies 1.12E-04 O.OOE+OO O.OOE+OO O.OOE+OO Co-58 Curies 2.1SE-06 O.OOE+OO O.OOE+OO O.OOE+OO Co-60 Curies 2.38E-OS O.OOE+OO O.OOE+OO O.OOE+OO Mn-S4 Curies 9.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO Sr-gO Curies 8.2SE-06 O.OOE+OO O.OOE+OO O.OOE+OO Y-91M Curies 2.22E-OS O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 Curies 2.88E-06 O.OOE+OO O.OOE+OO O.OOE+OO la-140 Curies 6.16E-06 O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 Curies 2.SSE-07 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99M Curies 1.17E-OS O.OOE+OO O.OOE+OO O.OOE+OO Zn-69M Curies 1.91E-05 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 2. 18E-04 O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 4.31E+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases Xe-133 Curies 4.SSE-04 O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 Curies 8.12E-04 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.27E-03 O.OOE+OO O.OOE+OO O.OOE+OO No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no was present at detectable levels.

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

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Effluents Unit: Site Starting: l-lan-2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit lSTQuarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &. Activation Products Sr-89 Curies 1.17E-04 1.33E-05 5.02E-05 O.OOE+OO Total for Period Curies l.llE-04 1.33E-OS S.02E-OS O.OOE+OO Tritium H-3 Curies 1.78E-02 4.61E-02 1.46E-02 1.46E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity NO Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Effluents Unit: Site l-lan-2012 31-Dec-2012 Batch Mode Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission 8. Activation Products Y-92 Curies 1.12E-04 O.OOE+OO O.OOE+OO O.OOE+OO As-76 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1. 22E-05 Co-58 Curies 4.86E-OS O.OOE+OO 2.84E-OS 2.7SE-06 Co-50 Curies 6.87E-04 O.OOE+OO 2.64E-04 S.36E-OS Cr-51 Curies 3.84E-04 O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 Curies 3.15E-04 O.OOE+OO O.OOE+OO O.OOE+OO Fe-59 Curies 2,41E-06 O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 Curies 1.15E-04 O.OOE+OO 7.0iE-05 1.48E-OS Mn-S6 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-OS Na-24 Curies O.OOE+OO O.OOE+OO 1.59E-04 2.30E-05 Nb-95 Curies 6.23E-07 O.OOE+OO O.OOE+OO O.OOHOO Nb-97 Curies 2.57E-OS O.OOE+OO O.OOE+OO 3.68E-09 Sr-89 Curies 6.89E-OS O.OOE+OO 2.24E-05 O.OOE+OO Sr-90 Curies 2.39E-05 O.OOE+OO O.OOE+OO O.OOE+OO Y-91M Curies 2.22E-05 O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 Curies 3.11E-05 O.OOE+OO 4.85E-05 9.07E-06 Cs-137 Curies 6.52E-OS O.OOE+OO 8.95E-OS 1.49E-OS Cs-138 Curies O.OOE+OO O.OOE+OO O.OOE+OO 7.80E-06 La-140 Curies 6.16E-06 O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 Curies 2.S5E-07 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99M Curies 1.17E-05 O.OOE+OO O.OOE+OO O.OOE+OO Zn-69M Curies 1.91E-OS O.OOE+OO O.OOE+OO 2.S2E-06 Curies L19E-OS O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.9SE-03 O.OOE+OO 6.S2E-04 1.64E-04 Zeroes in this table indicates that no was at detectable levels.

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

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Effluents Unit: Site l-Jan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 9.94E+OO O.OOE+OO 3.S2E+OO 1.41E+OO Dissolved And Entrained Gases Xe-133 Curies 4.SSE-04 O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 Curies 8.12E-04 O.OOE+OO 2.0SE-06 3.03E-06 Total for Period Curies 1.27E-03 O.OOE+OO 2.08E-06 3.03E-06 No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was at detectable levels.

See Table 1-4 for minimum detectable concentrations. 18

Table 1-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses to a member of the due to Liquid Releases Unit: 1 1-lan-2012 31-Dec-2012 Cumulative Doses Per ODCM lmt Units 1ST %ODCM 2ND o/oODCM 3RD %ODCM 4TH %ODCM Bone 5.00E+OO mRem 2.73E-04 SA6E-03 O.OOE+OO O.OOE+OO 2.90E-04 S.79E-03 S.16E-OS 1.03E-03 GHIi 5.00E+OO mRem 4.0SE-04 S.16E-03 O.OOE+OO O.OOE+OO 1.73E-04 3A6E-03 4.27E-OS 8.S4E-04 Kidney S.OOE+OO mRem L53E-04 3.06E-03 O.OOE+OO O.OOE+OO 1.64E-04 3.29E-03 3.63E-OS 7.26E-04 Liver 5.00E+OO mRem 3.85E-04 7.69E-03 O.OOE+OO O.OOE+OO 4.33E-04 S.66E-03 SASE-OS 1.70E-03 Lung 5.00E+OO mRem 7.54E-05 1.51E-03 O.OOE+OO O.OOE+OO 6.65E-OS 1.33E-03 1.84E-OS 3.69E-04 S.OOE+OO mRem 3.9SE-OS 7.91E-04 O.OOE+OO O.OOE+OO 2.2SE-OS 4.57E-04 1.06E-05 2.13E-04 Total Body 1.50E+OO mRem 2.98E-04 1.99E-02 O.OOE+OO O.OOE+OO 2.98E-04 1.99E-02 6.07E-05 4.04E-03 Cumulative Doses per Yea r ODCM lmt Units Year to Date %OQCM limit Bone 1.00E+Ol mRem 6.15E-04 6.1SE-03 MAX INDIVIDUAL LIQUID I Adult Ann Cum Organ Liq Dose GHIi 1.00E+Ol mRem 6.24E-04 6.24E-03 MAX INDIVIDUAL UQUID I Adult Ann Cum Organ Liq Dose Kidney 1.00E+Ol mRem 3.S4E-04 3.54E-03 MAX INDIVIDUAL UQUID I Adult Ann Cum Organ Uq Dose Liver 1.00E+01 mRem 9.02E-04 9.02E-03 MAX INDIVIDUAL LIQUID I Adult Ann Cum Organ UQ Dose Lung 1.00E+Ol mRem 1.60E-04 1.60E-03 MAX INDIVIDUAL UQUID I Adult Ann Cum Organ LiQ Dose 1.00E+Ol mRem 7.30E-OS 7.30E-04 MAX INDIVIDUAL UQUID I Adult Ann Cum Organ Uq Dose Total Body 3.00E+OO mRem 6.57E-04 2.19E-02 MAX INDIVIDUAL UQUID I Adult Ann Cum Tot Body Uq Dose 19

Table 1-38 Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Doses to a member of the due to Releases Unit: 2 l-lan-2012 Ending: 31-Dec-2012 Cumulative Doses Per ODCMtmt Units 1ST OfoODCM 2ND Qtr %ODCM 3RDQtr %ODCM 4TH %ODCM Bone 5.00E+OO mRem 4.01E-OS S.03E-04 l.S6E-06 3. llE-OS S.64E-06 l.13E-04 O.OOE+OO O.OOE+OO GHIi S.OOE+OO mRem 7.31E-OS 1.46E-03 6.2SE-07 1.2SE-OS 1.04E-06 2.0SE-OS 1.94E-07 3.S7E-06 Kidney S.OOE+OO mRem S.20E-05 1.04E-03 3.76E-07 7.51E-06 1.36E-07 2.73E-06 1.94E-07 3.S7E-06 liver S.OOE+OO mRem 5.35E-05 1.07E-03 3.76E-07 7.51E-06 1.36E-07 2.73E-06 1.94E-07 3.S7E-06 Lung S.OOE+OO mRem 5.lDE-05 1.02E-03 3.76E-07 7.51E-06 1.36E-07 2.73E-06 1.94E-07 3.S7E-06 S.OOE+OO mRem S.10E-05 1.02E-03 3.76E-07 7.S1E-06 1.36E-07 2.73E-06 1.94E-07 3.S7E-06 Total Body 1.50E+OO mRem S.9SE-05 3.97E-03 4.20E-07 2.S0E-OS 2.9SE-07 1.99E-05 1.94E-07 1.29E-OS Cumulative Doses per Year ODCM Lmt Units Year to Date OfoODCM Limit Bone l.OOE+Ol mRem 4.73E-05 4.73E-04 MAX INDIVIDUAL UQUID I Adult Ann Cum Uq Dose GHli 1.00E+Ol mRem 7,49E-05 7,49E-04 MAX INDIVIDUAL LIQUID I Adult Ann Cum Uq Dose Kidney 1.00E+Ol mRem S.27E-OS 5.27E-04 MAX INDIVIDUAL Adult Ann Cum Uq Dose Uver l.OOE+Ol mRem S,42E-05 5,42E-04 MAX INDIVIDUAL UQUID I Adult Ann Cum Uq Dose Lung 1.00E+Ol mRem S.lSE-05 5.1SE-04 MAX INDMDUAL LIQUID I Adult Ann Cum Uq Dose 1.00E+Ol mRem S.18E-05 5.I8E-04 MAX INDIVIDUAL I Adult Ann Cum Uq Dose Total Body 3.00E+OO mRem 6.04E-OS 2.0IE-03 MAX INDIVIDUAL UQUID I Adult Ann Cum Tot Body Uq Dose 20

Table 1-4 E. I. HA TCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 MINIMUM DETECTABLE CONCENTRA TlONS - LIQUID SAMPLE ANAL YSES STARTING: 1-Jan-2012 ENDING: 31-Dec-2012 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 1.97E-OS uCilml Fe-59 3.94E-OS uCilml Co-5S 1.59E-OS uCi/ml Co-60 1.72E-OS uCi/ml Zn-65 2.92E-OS uCilml Mo-99 1.20E-07 uCi/ml Cs-134 1.75E-OS uCi/ml Cs-137 1.62E-OS uCi/ml Ce-141 1.92E-OS uCilml Ce-144 S.S3E-OS uCi/ml 1-131 1.43E-OS uCi/ml Xe-135 1.03E-OS uCilml Fe-55 2.34E-OS uCilml Sr-S9 1.44E-OS uCi/ml Sr-90 S.50E-09 uCilml H-3 6.00E-07 uCi/ml 21

Table l-SA Hatch Nuclear Plant RADIOACTIVE EfflUENT RELEASE REPORT 2012 Effluents Batch Release Unit: 1 l-Jan-20l2 Ending: :31-Dec-20l2 Liquid Releases Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Totals

1. Number of batch releases 48 0 42 8 98

2. Total time period for Batch releases ( Minutes) S.71E+03 O.OOE+OO 5.S6E+03 9.43E+02 1.22E+04

3. Maximum time period for a batch release ( Minutes) 1.70E+02 O.OOE+OO 1.80E+02 1.77E+02 1.80E+02

4. Average time period for a batch release ( Minutes) 1.19E+02 O.OOE+OO 1.32E+02 1.18E+02 1.2SE+02

5. Minimum time period for a batch release ( Minutes) 7.90E+Ol O.OOE+OO 8.80E+Ol 7.80E+Ol 7.80E+Ol

6. Average stream flow during periods of release of liquid effluent into a stream ,. (CFS) 5.2SE+03 2.26E+03 l.S8E+03 1.67E+03 2.69E+03 Replace this text in the Station Parameters 22

Table 1-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Effluents - Batch Release Unit: 2 Starting: 1-Jan-20U 31-Dec-2012 Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 26 0 0 0 26

2. Total time period for Batch releases ( Minutes) 3.07E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.07E+03

3. Maximum time period for a batch release ( Minutes) 1.72E+02 O,OOE+OO O.OOE+OO O.OOE+OO 1.72E+02

4. Average time for a batch release ( Minutes) 1.18E+02 O,OOE+OO O.OOE+OO O,OOE+OO L18E+02

5. Minimum time period for a batch release ( Minutes) 6.00E+OO O,OOE+OO O.OOE+OO O.OOE+OO 6.00E+OO

6. Average stream flow of release of effluent into a stream * (CFS) S,2SE+03 2,26E+03 l.S8E+03 1.67E+03 2.69E+03 Replace this text in the Station Parameters 23

Table l-SA Hatch Nueiear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 liquid Effluents - Abnormal Release Summall'V Unit: 1 1-lan-2012 Ending: 31-Dec-2012 liquid Releases Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total lime For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum lime For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

6. Total for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 24

Table 1-6B Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Effluents - Abnormal Release Summary Unit: 2 Starting: l-lan-2012 Ending: 31-Dec-2012 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) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum TIme For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average TIme For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum TIme For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25

Table 1-6C Hatch Nuclear Plant RADIOACTIVE EffLUENT RElEASE REPORT - 2012 liquid Effluents - Abnormal Release Summary Unit: Site 1-1an-2012 Ending: 31-Dec-2012 liquid Releases Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total lime For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOHOO O.OOE+OO O.OOHOO

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26

2.0 Gaseous Effluents 1 Regulatory Requirements ODCM Specifications in this are for Unit 1 and Unit 1.1 Dose Limits The rate due to radioactive materials released in gaseous effluents from site to areas at and beyond the NDARY shall be limited to the following:

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

b. lodine-1 , lodine-1 tritium and for all radionuclides in particulate form with half greater than 8 days: than or equal to 1500 mrems/yr. to any 1.2 Air IJv..:tow., Due To Noble Gases in Gaseous Effluents air dose to noble effluents, from each unit, to areas at and beyond the S be limited to the following:

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

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

1.3 Doses A Member of the Public dose to a MEMBER OF PUBLIC from lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, in effluents released from unit, to areas at and beyond the S BOUNDARY, shall be limited to the following.

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

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

27

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

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

1. Noble gas are collected by grab sampling monthly.

2. Tritium samples are collected by grab sampling monthly.

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

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

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

Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and samples are analyzed for and Sample analyses and flow from the four pOints form the for calculating quantities of radionuclide-specific radioactivity, the associated with the cumulative for the current quarter and year. This task is normally performed with computer assistance.

The noble grab sample analysis results are used along with maximum expected flow rates from each of the four vents to late monitor the gaseous effluent monitors serving the four release points. Calculation of monitor setpoints is described in ODCM. Typically achieved minimum detectable concentrations gaseous effluents sample are reported in Table For each release period, released radioactivity, dose rates, and cumulative doses are calculated. Cumulative results are tabulated along with the of ODCM limit for for cu quarter and 28

2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative vu.:n:;,;::t The methods determining quantities of radioactivity, dose rates, and cumulative follow:

2.2.2.1 Fission and Activation Gases The radioactivity is determined using sample results as described above and the release flow over the ncr'l..... n represented by collected Dose due to noble gases, radioiodines, tritium, and particulates are calculated (with computer assistance). The calculated dose rates are compared to rate limits specified in aDCM 3.1 for noble radioiodine, tritium, and particulates.

rate calculation methodology is presented in aDCM.

Beta and gamma air due to gases are for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases.

Air doses are calculated for release period and cumulative totals are kept for each unit for calendar quarter and year. Cumulative air are compared the limits in aDCM 1 The current of the limits are shown on the printout for each period. Air calculation methodology is nr",.<::'Qnr",.n in the aDCM.

Radioiodine, Tritium and Particulate rU:fIt:f",'3C'3 lea!"ea quantities radioiodines are determined using the weekly samples and reIE~as,e l:low rates for four release points. Radioiodine concentrations are determined by gamma spectroscopy.

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

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

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

29

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

tritium and particulates are calculated for a hypothetical pathway at the location in the eX[)eClea to the highest. Dose are period, and the dose rates from limits as described in aDCM 3.1 are calculated for the controlling a Member of the Public are release period, totals are kept for current calendar quarter and doses are limits specified in aDCM 3.1.4. of aDCM limits are shown on printout for each release period.

2.2.2.3 Gross Alpha The gross alpha is computed each month by counting the particulate each week for gross alpha activity in a proportional counter. The four or numbers are then on a data sheet and the activity is summed at the month. The summed activity is then divided by the total monthly volume determine the This concentration is input into the computer and 2.2.3 Total Error EstlnratJron aS~iOClaIEm with the effluent measurement cumulative errors of sampling and to the difficulty error for each parameter affecting the final measurement, evaluation of error is not suggested. The to obtain an overall of the error associated with measurements materials released in liquid and effluents and solid waste.

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

30

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

Statistical error 60%

Counting equipment calibration 10%

flow 10%

Non-steady rates 20%

TOTAL 65%

1-1 releases were calculated from weekly sample.

error 60%

Counting equipment calibration 10%

Vent flow 10%

Vent sample flow rates 10%

Non-steady rates 1 from charcoal cartridges 1 TOTAL 64%

Particulates with half greater than 8 days were calculated from sample analysis results and point flow

,t'::lticlrlf"!l error 60%

Counting equipment calibration 10%

Vent flow 10%

Vent sample flow rates 10%

Non-steady release 10%

TOTAL ERROR 63%

Total tritium were calculated from sample analysis results release point flow Water vapor in sample stream determination 20%

Vent flow 10%

Counting calibration and 10%

Non-steady rates ERROR 56%

31

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady 10%

Gaseous Effluent Release Data ulatory Guide 1 Tables 1A, 1B, and 1C are found in this report as 2-1A, 2-1 B, C, 2-2B, 2-3A, 2-3B, Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all Dose due to noble and due to radioiodine, tritium, and particulates were calculated as part of the post-release permits on individual No were for this reporting period.

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

Limits for cumulative and gamma air are specified in aDCM 3.1. Cum air are .... rc'c:"::'.ntc'rI and along with percent of aDCM limits.

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

32

2.4 Radiological Impact Due to Gaseous Releases rates were calculated for the site in with aDCM 3.1 Dose due to radioiodine, tritium, particulates in releases were calculated in accordance with aDCM 3.1.2.

These dose rates were calculated as of the nrl"'_rl"'rF>;;~"'F> and post release on individual permits. No limits were reporting period.

Cumulative doses to noble gas were calculated for each unit in accordance with aDCM 3.1.3. results are presented in Tables 2-4A and Cumulative to a Member of the Public to radioiodine, tritium and particulates in gaseous were calculated for each unit in accordance with aDCM 3.1.4.

results are nr<:,C'c.nT"' in 2-5A 2-58.

Dose and were calculated using the methodology presented in the aDCM.

2.5 Gaseous Effluents - Batch Releases There are no gaseous batch 2.6 Gaseous Effluents - Abnormal n:e/eil'Stl!S were no unplanned or uncontrolled during this reporting period.

33

Table 2-1A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Unit: 1 l-lan-2012 EndinQ: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 4.86E+OO 6.34E+OO 1.19E+Ol 1.97E+01

2. Average Release rate for period uO/sec 6.16E-Ol 8.04E-Ol l.S1E+OO 2.S0E+OO

3. Percent of Applicable Limit  % " " * *

1. Total Iodine-13I Curies 2.86E-OS 1.46E-04 1.12E-04 8.S7E-OS

2. Average Release rate for period uCi/sec 3.62E-06 1.86E-OS 1.42E-OS 1.09E-OS

3. Percent of limit  %

C.

1. Particulates ( Half-Lives> 8 Days) Curies 9.89E-06 3.92E-OS 3.62E-OS 3.02E-OS

2. Average Release rate for period uCi/sec USE-06 4.97E-06 4.S9E-06 3.83SE-06 Limit

3. Percent of °/0 * " * *

1. Total Release Curies 4.23E+OO 4.40E+OO S.76E+OO 7.72E+OO

2. Average Release rate for period uCi/sec S.37E-Ol S.S8E-Ol 7.3IE-Ol 9.79E-Ol

3. Percent of limit " " * "

E.

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

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

• limits are in terms of dose. See Tables 2-48 1 2-58 of this 34

Table 2-1B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: l-Jan-2012 31-Dec-2012 Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter

1. Total Release Curies 4.94E+OO 6.34E+OO 1.19E+Ol 1.97E+Ol

2. Average Release rate for uOjsec 6.26E-Ol 8.04E-Ol 1.51E+OO 2.50E+OO

3. Percent of Limit  % *

• 11<

B.

1. Total Iodine-131 Curies 6.44E-05 l.S7E-04 1.20E-04 l.06E-04

2. Average Release rate for uCijsec 8.16E-06 1.99E-05 1.52E-05 1.34E-OS

3. Percent of Limit  % * * * *

1. Particulates ( Half-lives> 8 Days) Curies 1.93E-OS 4.20E-05 3.79E-OS 3.27E-OS

2. Average Release rate for period uCi/sec 2.4SE-06 S.33E-06 4.81E-06 4.1S0E-06

3. Percent of Applicable Limit  % * * * *

1. Total Release Curies 3.S3E+OO 4.2SE+OO 4.07E+OO 4.30E+OO

2. Average Release rate for uCi/sec 4,48E-Ol S.39E-Ol S.16E-Ol S,46E-O!

3. Percent of Limit * * *

• E.

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

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

• limits are in terms of dose. See Tables 2-4B, 2-5B of this 35

Table 2-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of AU Releases Unit: Site l-lan-2012 Ending: 31-Dec-2012 of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. fission And Activation Gases

1. Total Release Curies 9.80E+OO L27E+Ol 2.38E+Ol 3.9SE+Ol

2. Average Release rate for period uCi/sec L24E+OO L61E+OO 3.02E+OO S.OlE+OO

3. Percent of Applicable Limit '% * * '" '"

1. Total Iodine-131 Curies 9.29E-OS 3.03E-04 2.32E-04 1.91E-04

2. Average Release rate for period uCi/sec U8E-OS 3.8SE-OS 2. 94E-OS 2A3E-OS

3. Percent of Applicable Limit (I/o

1. Particulates ( Half-Lives> 8 Days) Curies 2.92E-05 8.12E-OS 7.41E-OS 6.30E-OS

2. Average Release rate for period uCi/sec 3.71E-06 1.03E-OS 9.40E-06 7.98SE-06

3. Percent of Applicable Limit  % * * * *

1. Total Release Curies 7.76E+OO 8.64E+OO 9.83E+OO 1.20E+Ol

2. Average Release rate for period uO/sec 9.84E-Ol 1.10E+OO 1.25E+OO LS3E+OO

3. Percent of ADDlicable Limit * * *

• E.

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

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

• limits are in terms of dose. See Tables 2-4A, 2-58 of this 36

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies S.91E-01 O.OOE+OO l.77E+OO 3.89E+00 Kr-8SM Curies 1.03E-01 O.OOE+OO l.S1E+00 3.38E+00 Kr-88 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.86E+00 Xe-133 Curies 3.76E+00 6.09E+00 7.40E+00 8.41E+00 Xe-13S Curies 4.09E-01 2.S2E-01 1. 22E+OO 1.20E+00 Total For Period Curies 4.86E+OO 6.34E+OO 1.19E+Ol 1.97E+Ol Iodines 1-131 Curies 2.28E-OS 1.41E-04 1.03E-04 7.88E-OS 1-133 Curies 4. 13E-OS 1.96E-04 2.00E-04 l.4SE-04 Total For Period Curies 6.40E-OS 3.37E-04 3.03E-04 2.24E-04 ParticUlates Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.03E-08 Sr-89 Curies 3.83E-06 2.10E-OS 1.54E-OS 1.46E-OS Sr-90 Curies 2.34E-08 1.19E-07 7.74E-08 6.38E-08 Cs-137 Curies 4.96E-08 1.30E-07 8.48E-08 O.OOE+OO Ba-140 Curies 2.S6E-06 1.69E-OS 1.82E-OS 1.39E-OS Total For Period Curies 6.47E-06 3.82E-OS 3.38E-OS 2.8SE-OS Tritium H-3 Curies 1.10E-01 6.60E-01 7.49E-01 S.42E-01 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations . 37

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents Elevated level Releases Unit: 1 l-Jan- 2012 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not NUclide is Not Zeroes in this table indicates that no was present at detectable levels.

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

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Gaseous Effluents Elevated Level Releases Unit: 1 1-Jan- 2012 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no '1"1::'I'1',v,T\! was present at detectable levels.

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

Table 2-28 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies S.91E-Ol O.OOE+OO l.77E+OO 3.89E+00 Kr-8SM Curies 1.03E-Ol O.OOE+OO l.SlE+OO 3.38E+00 Kr-88 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.86E+00 Xe-133 Curies 3.76E+00 6.09E+00 7.40E+00 8.41E+00 Xe-13S Curies 4.86E-01 2.S2E-01 1.22E+00 1.20E+00 Total For Period Curies 4.94E+OO 6.34E+OO 1.19E+01 1.97E+01 Iodines 1-131 Curies 4.60E-OS 1.41E-04 1.03E-04 7.88E-OS 1-133 Curies 8.llE-OS 1.96E-Q4 2.00E-Q4 1.4SE-Q4 Total For Period Curies 1.27E-04 3.37E-04 3.03E-04 2.24E-04 Particulates Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.03E-08 Sr-89 Curies 8.7SE-06 2.10E-OS l.S4E-OS 1.46E-OS Sr-90 Curies S.33E-08 1.19E-07 7.74E-08 6.38E-08 Cs-137 Curies 4.96E-08 1.30E-07 8.48E-08 O.OOE+OO Ba-140 Curies 4.8SE-06 1.69E-OS 1.82E-OS 1.39E-OS Total For Period Curies 1.37E-OS 3.S2E-OS 3.3SE-OS 2.SSE-OS Tritium H-3 Curies 1.81E-01 6.60E-Ol 7.49E-Ol S.42E-Ol If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table 2-28 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents Elevated Level Releases Unit: 2 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no was present at detectable levels.

See Table 2-6 for minimum detectable concentrations. 41

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents Elevated level Releases Unit: 2 Starting: l-lan- 2012 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no radioactivity was at detectable levels.

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

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Gaseous Effluents Elevated Level Unit: Site I-Jan- 2012 Endina: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Fission Gases Ar-41 Curies 1.18E+OO O.OOE+OO 3.S4E+OO 7.7SE+OO Kr-8SM Curies 2.07E-01 O.OOE+OO 3.03E+OO 6.76E+OO Kr-SS Curies O.OOE+OO O.OOE+OO O.OOE+OO S.72E+OO Xe-133 Curies 7.S1E+OO 1.22E+Ol 1.4SE+Ol 1.6SE+Ol Xe-13S Curies S.9SE-01 S.OSE-Ol 2ASE+OO 2AOE+00 Total For Period Curies 9.801:+00 1.27E+Ol 2.381:+01 3.951:+01 Iodines 1-131 Curies 6.88E-OS 2.82E-04 2.07E-04 1.58E-04 1-133 Curies 1.22E-04 3.91E-04 4.00E-04 2.90E-04 Total For Period Curies 1.91E-04 6.73E-04 6.07E-04 4.48E-04 Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.21E-07 Sr-89 Curies 1.26E-OS 4.21E-OS 3.09E-OS 2.91E-OS Sr-90 Curies 7.S7E-OS 2.39E-07 l.SSE-07 U8E-07 C5-137 Curies 9.92E-OS 2.60E-07 1.70E-07 O.OOE+OO Ba-140 Curies 7A1E-OS 3.39E-OS 3.64E-OS 2.77E-OS Total For Period Curies 2.02E-05 7.641:-05 6.761:-05 5.71E-05 Tritium H-3 Curies 2.91E-Ol 1.32E+OO 1.50E+OO 1.08E+OO If Not Nuclide is Not Zeroes in this table indicates that no in;,rtivitv was present at detectable levels.

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

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Gaseous Effluents Elevated Level Releases Unit: Site l-Jan- 2012 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no radioactivity was at detectable levels.

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

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents Elevated Level Releases Unit: Site I-Jan- 2012 3I-Dec-2012 Batch Mode Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no in;,rth,ihi was present at detectable levels.

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

Table 2-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-lan-2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines I-131 Curies S.76E-06 S.S6E-06 S.62E-06 6.SSE-06 I-133 Curies O.OOE+OO 4.03E-06 3.46E-06 7.63E-06 Total For Period Curies S.76E-06 9.S9E-06 1.21E-OS 1.4SE-OS Particulates Mn-S4 Curies 6.27E-07 O.OOE+OO O.OOE+OO O.OOE+OO Co-60 Curies 2.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO Sr-S9 Curies 7.94E-07 9.22E-07 2.40E-06 1.69E-06 Sr-90 Curies O.OOE+OO 6.79E-OS O.OOE+OO O.OOE+OO Total For Period Curies 3.42E-06 9.90E-07 2.40E-06 1.69E-06 Tritium H-3 Curies 4.12E+OO 3.74E+OO S.01E+OO 7.1SE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table 2-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: l-lan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table 2-38 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Gaseous Effluents - Ground level Releases Unit: 2 1-.lan-2012 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines H31 Curies 1. 84E-OS 1.60E-OS l.64E-OS 2.68E-OS 1-133 Curies 2. 29E-OS 2.33E-OS 3.79E-OS S.96E-OS Total For Period Curies 4.13E-OS 3.93E-OS S.43E-05 S.ME-OS Sr-89 Curies S.63E-06 3.82E-06 4.1SE-06 4.17E-06 Total For Period Curies S.63E-06 3.S2E-06 4.1SE-06 4.11E-06 Tritium H-3 Curies 3.3SE+OO 3.S9E+OO 3.32E+OO 3.76E+OO Gross No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Zeroes in this table indicates that no was present at detectable levels.

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

Table 2-3B Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents Ground Level Releases Unit: 2 I-Jan-2012 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table 2-3C Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: Site l-lan-2012 31-Dee-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines 1-131 Curies 2.41E-05 2.16E-05 2.S0E-OS 3.36E-OS 1-133 Curies 2. 29E-OS 2.73E-OS 4.14E-05 6.73E-05 Total for Period Curies 4.71E-OS 4.S9E-OS 6.ME-OS 1.OlE-04 Mn-S4 Curies 6.27E-07 O.OOE+OO O.OOE+OO O.OOE+OO Co-60 Curies 2.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO Sr-S9 Curies 6,42E-06 4.74E-06 6.S6E-06 5.S6E-06 Sr-90 Curies O.OOE+OO 6.79E-OS O.OOE+OO O.OOE+OO Total for Period Curies 9.0SE-06 4.S1E-06 6.SSE-OS S.SSE-OS Tritium H-3 Curies 7,47E+00 7.32E+00 8.33E+OO l.09E+Ol Gross Alpha No NUClides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no was at detectable levels.

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

Table 2-3C Hatch Nuclear Plant RADIOACTIVE EfflUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground level Releases Unit: Site 1-lan-2012 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter fission Gases No Nuclides found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Nuclide is Not Zeroes in this table indicates that no was present at detectable levels.

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

Table 2-4A Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Releases Unit: 1 Starting: l-Jan-20l2 3l-Dec-20l2 Cumulative Doses Per Quarter of Radiation ODCMlmt Units 1ST %ODCM 2ND %ODCM 3RD %ODCM 4TH %ODCM Gamma Air S.OOE+OO mRad 1.83E-OS 3.66E-04 3.90E-06 7.79E-OS S.64E-OS 1.13E-03 2.16E-04 4.33E-03 Beta Air 1.00E+Ol mRad 1.47E-OS 1.47E-04 lASE-OS 1.4SE-04 4.0SE-OS 4.0SE-04 8.20E-OS 8.20E-04 Cumulative Doses Per Year Type of Radiation ODCMl..mt Units Year to End Date %ODCM Receptor Umit Gamma Air l.OOE+Ol mRad 2.9SE-04 2.9SE-03 SITE BOUNDARY I Child Ann Cum Gamma Airdose Beta Air 2.00E+Ol mRad l.S2E-04 7.58E-04 MAX IND. AIRBORNE I Child Ann Cum Beta Airdose 52

Table 2-4B Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Releases Unit: 2 l-lan-20l2 Ending: 3l-Dec-20l2 Cumulative Doses Per of Radiation ODCM lmt Units 1ST %ODCM 2ND %ODCM 3RD %ODCM 4TH %ODCM Gamma Air 5.00E+OO mRad l.B6E-OS 3.73E-04 3.90E-06 7.79E-OS S.64E-OS 1.13E-03 2. 16E-04 4.33E-03 Beta Air 1.00E+Ol mRad 1.51E-05 l.S1E-04 lASE-OS 1.4SE-04 4.0SE-OS 4.0SE-04 B.20E-OS B.20E-04 Cumulative Doses Per Year of Radiation ODCM Lmt Units Year to End Date 0/0 ODCM Receptor Limit Gamma Air 1.00E+Ol mRad 2.95E-04 2.95E-03 SITE BOUNDARY I Child Ann Cum Gamma Airdose Beta Air 2.00E+Ol mRad 1.52E-04 7.60E-04 MAX IND. AIRBORNE I Child Ann Cum Beta Airdose 53

Table 2-5A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1

...".l1'i'......

• l-Jan-2012 31-Dec-2012 Cumulative Doses Per Organ ODCM lmt Units 1STQtr lifo ODCM 2NDQtr %ODCM 3RD Qtr %ODCM 4TH Qtr 0/0 ODCM Bone 7.S0E+OO mRem 2.81E-OS 3.74E-04 7.47E-OS 9.96E-04 SAlE-OS 7.22E-04 4.4SE-05 S.93E-04 GI-Lli 7.S0E+OO mRem 2.1SE-03 2.87E-02 1.94E-03 2.S9E-02 2.61E-03 3.47E-02 3.72E-03 4.97E-02 Kidney 7.50E+OO mRem 2.1SE-03 2.86E-02 1.94E-03 2.59E-02 2.61E-03 3.47E-02 3.72E-03 4.97E-02 Liver 7.50E+OO mRem 2.1SE-03 2.86E-02 1.94E-03 2.S9E-02 2.60E-03 3.47E-02 3.72E-03 4.96E-02 7.S0E+OO mRem 2.1SE-03 2.87E-02 1.94E-03 2.59E-02 2.60E-03 3.47E-02 3.72E-03 4.96E-02 7.S0E+OO mRem 2. 28E-03 3.04E-02 2.33E-03 3.11E-02 2.96E-03 3.9SE-02 4.00E-03 S.34E-02 Total Body 7.S0E+OO mRem 2.1SE-03 2.87E-02 1.9SE-03 2.60E-02 2.61E-03 3.48E-02 3.73E-03 4.97E-02 Cumulative Doses per Year Organ ODeM lmt Units Year to Ending Date %ODCM Receptor limit Bone l.S00E+Ol mRem 2.014E-04 1.342E-03 MAX IND. AIRBORNE I Child Ann Cum Iod/Part Airdose GHli 1.500E+Ol mRem 1.042E-02 6.949E-02 MAX IND. AIRBORNE I Child Ann Cum lad/Part Airdose Kidney l.SOOE+Ol mRem 1.042E-02 6.948E-02 MAX IND. AIRBORNE / Child Ann Cum lad/Part Airdose Liver l.S00E+Ol mRem 1.042E-02 6.946E-02 MAX IND. AIRBORNE I Child Ann Cum lad/Part Airdose Lung l.S00E+Ol mRem 1.042E-02 6.946E-02 MAX IND. AIRBORNE I Child Ann Cum lad/Part Airdase l.S00E+Ol mRem 1.1S7E-02 7.716E-02 MAX IND. AIRBORNE I Child Ann Cum lad/Part Airdose Total Body 1.500E+Ol mRem 1.043E-02 6.95SE-02 MAX IND. AIRBORNE I Child Ann Cum lad/Part Airdose 54

Table 2-58 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public:: Due To Tritium, and Particulates in Gaseous Releases Unit: 2 1-Jan-2012 31-Dec-2012 Cumulative Doses Per Organ ODeM lmt Units lSTQtr %ODCM 2ND Qtr %ODCM 3RDQtr %ODCM 4TH Qtr %ODCM Bone 7.S0E+OO mRem 7.48E-OS 9.97E-04 8.02E-OS l.07E-03 7.23E-OS 9. 64E-04 7.07E-OS 9.43E-04 GHIi 7.50E+OO mRem l.74E-03 2.32E-02 1.87E-03 2.49E-02 1.73E-03 2.30E-02 1.96E-03 2.61E-02 Kidney 7.50E+OO mRem l.74E-03 2.32E-02 1.87E-03 2.49E-02 1.73E-03 2.30E-02 1.96E-03 2.61E-02 Liver 7.S0E+OO mRem l.74E-03 2.32E-02 1.87E-03 2.49E-02 1.73E-03 2.30E-02 1.96E-03 2.61E-02 Lung 7.50E+OO mRem l.74E-03 2.32E-02 1.86E-03 2.49E-02 1.73E-03 2.30E-02 1.96E-03 2.61E-02 Thyroid 7.S0E+OO mRem 2. 12E-03 2.83E-02 2.42E-03 3.23E-02 2.22E-03 2.96E-02 2.56E-03 3.41E-02 Total Body 7.50E+OO mRem L74E-03 2.32E-02 1.87E-03 2.49E-02 1.73E-03 2.31E-02 1.96E-03 2.61E-02 Cumulative Doses per Year ODeM lmt Units Year to Date %ODCM Receptor limit Bone 1. 500E+ 01 mRem 2.980E-04 1.987E-03 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose GHli 1.500E+Ol mRem 7.291E-03 4.861E-02 MAX IND. AIRBORNE I Child Ann Cum lod/Part Airdose Kidney l.SOOE+Ol mRem 7. 290E-03 4.860E-02 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose Liver l.S00E+Ol mRem 7.286E-03 4.8S7E-02 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose Lung LSOOE+Ol mRem 7.283E-03 4.856E-02 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose l.S00E+Ol mRem 9.322E-03 6.215E-02 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Total Body l.S00E+Ol mRem 7.29SE-03 4.863E-02 MAX IND. AIRBORNE I Child Ann Cum lad/Part Airdose 55

I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE 2012 TIONS - GASEOUS SAMPLE ANAL YSES STARTING: 1-Jan-2012 that are RADIONUCLIDE MDC UNITS 2.

33 30E-OS Xe-1 S.

1 1.34E-1 1 3*

1 1 30E-1 Co-60 1 2.54E-1 E-1 1 3*

3*

44 1.10E-16 6

• on an of 56

Table 2-7A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-lan-2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 0 0 0 0 0

2. Total time period for batch releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum time period for a batch release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average time period for a batch release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum time period for a batch release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 57

Table 2-7B Nuclear Plant RADIOACTIVE EfFLUENT RELEASE REPORT - 2012 Gaseous Release Summary Unit: 2 1-lan-2012 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Totals

1. Number of batch releases 0 0 0 o o

2. Total time period for batch releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum time period for a batch release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average time period for a batch release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum time period for a batch release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 58

Table 2-8A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous - Abnormal Summary Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 59

Table 2-88 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: l-lan-2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0

2. Total lime For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S. Minimum lime For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 60

Table 2-8C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Gaseous Effluents - Abnormal Release summarY Unit: Site 1-lan-20l2 Ending: 31-Dec-20l2 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+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 61

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

3.1.1 Solid Radioactive Waste System PCP Section A.3.1 Solid Radioactive Waste System control The solid radwaste system shall used in accordance with the PROGRAM to provide for SOLIDIFICATION of wet solid and for SOLIDIFICATION and packaging of other radioactive wastes, as required, ensure that they requirements of 10 CFR Parts and , prior to ipment of radioactive wastes from the site.

3.1.2 Reporting Requirements Technical Specification requires in part:

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

PCP Section A.4.1 in part:

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

62

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

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

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

c. Type of waste (such as spent compacted dry evaporator bottoms).

Major changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed and accepted by the 3.2 Solid Waste Data Regulatory Guide 1 1, Table 3 is found in this report as 3-1.

63

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jan-2012 ENDING: 30-Jun-2012 1.

a. Spent resins, filter sludges, evaporator bottoms, etc.

b. Dry compressible waste, contaminated equip.

etc.

c. Irradiated

d. Control Rod Drive Filters

e. Other (describe)

E ui . etc.

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

ISOTOPE PERCENT CURIES a.Fe-55 18.6 9.45 E+OO Co-60 41.6 2.11 E+01 Zn-65 6.4 3.21 E+OO Mn-54 13.3 6.78 E+OO Cs-137 5.3 2.75 E+OO Cr-51 6.3 3.21 E+OO Other 8.6 4.42 E+OO b.Fe-55 62.8 3.80 E-01

<"'- "'" 15.6 9.42 E-02 Mn-54 4.59 2.77 E-02 Zn-65 2.13 1.29 E-02 Other 14.9 9.02 E-02 c.

i d.

e.

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

Destination N/A 64

TABLE 3-1 E. I. HA TCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 SOLID WASTE AND IRRADIA FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jul-2012 ENDING: 31-Dec-2012 A. SOLID WASTE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL Not irradiated fuel

1. of waste UNIT 6 month

a. Spent resins, filter sludges, bottoms, etc. 1.00 E 01

b. Dry compressible waste, contaminated equip.

etc. 2.00 E 01

c. Irradiated components, control

d. Control Rod Drive Filters 2, Estimate of nuclide ,..nn" .... "."t,,\.... (by of ISOTOPE PERCENT CURIES a.Fe-55 44.6 2.07 E+02 Co-60 36.4 1.69 E+02 I Zn-65 5.1 2.37 E+01 I Mn-54 10.4 4.81 E+01 Cs-137 0.1 4.56 E-01 Cr-51 0.1 3.29 E-01 Other 3.3 1.52 E+01 b.Fe-55 62.8 3.56 E+OO Co-60 15.6 8.84 E-01 Mn-54 4.59 2.60 E-01 Zn-65 2.13 1.21 E-01 Other 14,9 8.45 E-01 I c.

d.

e.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination All waste sent to processors N/A N/A B. IRRADIATED FUEL SHIPMENTS UISPOSHIor N/A 65

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

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

The source term is not listed in Table . The source term is listed in Tables and for the elevated releases. Similarly source term is listed in Tables 2-3A and for ground level The maximum doses in units of mrem accumulated by an individual MEMBER OF THE PUBLiC to their activities inside the site boundary during the reporting period are c;,on.tor1 in Table 66

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RElEASE REPORT - 2012 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site 1-lan-20l2 Ending: 3l-Dec-20l2 Location Name: ROADSIDE PARK Distance (kilnmfl!tfl!N1.\: 1.lSE+OO Sector: WNW Occupancy factor: 2.2SE-04 Age Group: Child Elevated Release Noble Gas X/Q (sec/m3): 2.42E-OS Elevated Release Particulate and Radioiodine (sec/m3): 2.37E-OS D/Q (m-2): 1.29E-09 Ground Level Release Noble Gas X/Q (sec/m3): 7.S3E-06 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 7.00E-06 D/O (m-2): 2.0IE-OB Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 6.7SE-ll 7.29E-12 4,47E-12 4.94E-12 8.43E-ll Liver mRem 4.33E-09 4.1SE-09 4.7SE-09 6. 24E-09 1.9SE-OS Total Body mRem 4.33E-09 4.1SE-09 4.7SE-09 6.24E-09 1.9SE-OS mRem 4.S7E-09 4,42E-09 S.OSE-09 6.66E-09 2.07E-OS mRem 4.33E-09 4. 18E-09 4.7SE-09 6.24E-09 1.9SE-OS mRem 4.34E-09 4.1SE-09 4.76E-09 6. 25 E-09 1.9SE-OS GI-Ui mRem 4.33E-09 4.1SE-09 4.7SE-09 6.24E-09 1.9SE-OS Skin mRem 7.62E-ll l.S0E-12 1.73E-12 2.0SE-12 8.1SE-ll 67

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site l-Jan-2012 Ending: 31-Dec-2012 location Name: CAMPING AREA Distance (kilometers): 1.27E+OO Sector: WNW Occupancy Factor: S,4SE-03 Age Group: Child Elevated Release Noble Gas 2.38E-08 Elevated Release Particulate and Radioiodine X/Q (sec/m3): 2.33E-08 D/Q (m-2): 2.0IE-OB Ground Level Release Noble Gas 7.03E-06 Ground Level Release Particulate and Radioiodine (m-2): 1.BOE-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem l.S4E-09 4.61E-IO 3.29E-IO 3.23E-1O 2.6SE-09 Uver mRem 9.32E-08 9.03E-08 1.03E-07 1.3SE-07 4.21E-07 Total Body mRem 9.32E-OB 9.03E-08 1.03E-07 1.3SE-07 4.21E-07 mRem 9.8SE-08 9.SSE-OB 1.09E-07 1.44E-07 4,46E-07 Kidney mRem 9.32E-08 9.03E-OB 1.03E-07 1.3SE-07 4.21E-07 Lung mRem 9.3SE-08 9.D4E-OB 1.03E-07 1.3SE-07 4.21E-07 GI-Ui mRem 9.32E-OB 9.03E-OB 1.03E-07 1.3SE-07 4.21E-07 Skin mRem 1.7SE-09 4.01E-1O 3.ISE-1O 3.03E-1O 2.76E-09 68

Table 4*1 Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT* 2012 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site I-Jan-2012 =.,....;"".... 31-Dec-2012 Location Name: RECREATION AREA Distance (kilometers) 1.03E+OO Sector: SSE Occupancy factor: 2.37E-02 Age Group: Child Elevated Release Noble Gas X/Q 3.30E-OS Elevated Release Particulate and Radioiodine X/Q 3.21E-08 D/Q (m-2): l.S6E-09 Ground level Release Noble Gas X/Q (sec/m3): 6.42E-06 Ground level Release Particulate and Radioiodine (sec/m3): S.73E-06 (m-2): 2.36E-OS Units 1ST Quarter 2ND 3RD 4TH Year Bone mRem 8.14E-09 6.86E-IO 4.41E-1O 4.S9E-I0 9.76E-09 Liver mRem 3.70E-07 3.S6E-07 4.0SE-07 S.31E-07 1.66E-Q6 Total Body mRem 3.70E-07 3.56E-07 4.0SE-07 S.31E-07 1.66E-06 Thyroid mRem 3.91E-07 3.77E-07 4.30E-07 S.67E-07 1. 77E-06 Kidney mRem 3.71E-07 3.S6E-07 4.0SE-07 S.31E-07 1.66E-06 lung mRem 3.72E-07 3.S6E-07 4.0SE-07 S.32E-07 1.67E-06 GHli mRem 3.70E-07 3.S6E-07 4.0SE-07 S.31E-07 1.66E-06 Skin mRem 9.31E-09 2.23E-IO 2.13E-1O 2.S2E-1O 9.99E-09 69

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: l-lan-20l2 3l-Dec-20l2 Location Name: VISITORS CENTER Distance 6.94E-Ol Sector: WSW Occupancy Factor: 4.S7E-04 Age Group: Child Elevated Release Noble Gas X/Q S.OOE-08 Elevated Release Particulate and Radioiodine X/Q (sec/m3): 4.97E-08 D/Q (m-2): 2.26E-09 Ground Level Release Noble Gas XlQ l.S7E-OS Ground Level Release Particulate and Radioiodine X/Q (sec/m3l: l.72E-OS D/Q SA7E-OS Units 1ST 2ND Quarter 3RD Quarter 4TH Year Bone mRem 3.66E-IO 3.S0E-ll 2.14E-ll 2.40E-ll 4A7E-I0 Liver mRem 2. 13E-OS 2.06E-OS 2.34E-08 3.07E-OS 9.61E-OS Total Body mRem 2.13E-OS 2.06E-08 2.34E-08 3.07E-OS 9.61E-OS Thyroid mRem 2.2SE-OB 2.1BE-OS 2.49E-08 3.28E-OS 1.02E-07 Kidney mRem 2. 13E-08 2.06E-08 2.34E-OS 3.0SE-OS 9.61E-OS Lung mRem 2. 14E-08 2.06E-OS 2.34E-OS 3.0SE-OS 9.62E-OS GI-Ui mRem 2. 13E-OS 2.06E-OS 2.34E-OS 3.07E-08 9.61E-08 Skin mRem 4.1SE-IO 7.82E-12 7.8SE-12 9.73E-12 4,41E-1O 70

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

Demonstration of Compliance No dose limits stated in aDCM Sections 1.3, 1.3, and 1.4 were exceeded. Therefore, compliance with 40 CFR 190 dose limits was demonstrated accordance with the requirements of aDCM Section 5.1 71

6.0 Meteorological Data The Radioactive Effluent Release Report, to be submitted by May 1 of each year, shall include an annual summary of hourly meteorological data collected over the previous r.

This annual summary may be either in the form of an hour-by-hour listing of wind wind direction, atmospheric stability, and precipitation (if measured), on magnetic the form of jOint frequency distributions of wind wind direction and atmospheric stability.

In lieu of with the Radioactive Effluent Report, the 1....l'>lnc:.""1'>

retained this of required meteorological in a file. It will be the NRC upon 72

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirements ODCM, Chapter 7, Section states that the Radioactive Effluent Report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in 1.1 and 1.1, respectively.

7.1.2 Description Deviations There were two deviations from the liquid and gaseous monitoring instrumentation operability requirements during this reporting period.

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

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

7.3 Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) 7.3.1 Regulatory Requirements aDCM 7. in part that from MDC(s) in shall be included in Radioactive Effluent Release Report.

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

73

8.0 Changes to the Plant Hatch Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements Pursuant to Technical Specification 1 and ODCM Section licensee initiated changes shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Report for the period of the report in which any change in the ODCM was made. Each change shall identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (Le., month and year) the change was implemented.

8.2 Description of Changes There were no changes the Hatch ODCM in 2012.

74

9.0 Major Changes to Liquid, Gaseous, or Solid f"CRlrrIN'R_"I'~ Treatment Systems 1 Regulatory Requirements Radioactive \:;;1:;;0;:':;; Report shall major change to liquid, or solid radwaste tro'!:ltnnor'\t systems pursuant Chapter 7, Section 9.2 Description of Major Changes Gaseous Radwaste There were no major to the gaseous n\O'<:I""'<:> system during this reporting period.

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

75

SOUTHERN COMPANY I. HA TCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1, 2012 - DECEMBER 31,2012 APPENDIX A 76

Nuclear Appendix A CARBON-14 14 (C-14) is a naturally-occurring radionuclide with a year half Nuclear weapons testing in the I and 1960s significantly increased the amount of C 14 in the Nuclear power plants also 14, but the amount is infinitesimal compared to what been distributed in the environment to weapons testing what is produced by natural ray nuclear plants have improved waste processing and improved fuel performance, percentages of "principal radionuclides" in gaseous have changed, and 14 has become a "Principal are based on public contribution or amount of activity discharged to other radionuclides of the same type. In 2 (June 2009) of Regulatory Guide 1.2] (RG 1.21), Evaluating, Reporting Material in Liquid and Gaseous Effluents and Solid Waste," NRC recommended re evaluating "principal radionuclides" and reporting 14 as appropriate. In 2010 Radioactive Release virtually all nuclear plants will report 4 amounts released to maximally member of publ Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated the effluent stream before it can be measured, RG 1.21 provides the option of calculating the 14 source term on power generation. The Electric Research (EPRI) developed an accepted methodology for and published in Technical Report 1021106 (December 2010),

of Carbon-14 in Power Plant Effluents." Evaluation in radioactive liquid effluents is not required because the quantity and dose contribution has been to be At quantity of C-14 to J4.16 unit). 95% 14 released is in form of 14C02 and is incorporated into plants through photosynthesis. Ingestion results from pathway. The 5% is estimated to Both organic and of C-14 to inhalation maximally exposed individual, and bone dose is the highest organ dose. Using calculation methodology from Hatch ODCM, resulting bone to a child located at the controlling location would 1.59E-Ol mrem in a which is 1.06% ofthe regulatory limit IS mrem per (per unit) to any organ due to effluents.

The resulting total body dose to a child located at controlling receptor location would be 3.1 which is 0.21 % the regulatory limit IS mrem per (per to gaseous 77

SOUTHERN COMPANY E I. HA TCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1,2012 - DECEMBER 31,2012 APPENDIX B 78

Appendix B Summary of Groundwater Protection Program Nuclear Management Procedure NMP-EN-002 provides the methodology and criteria for implementation of the Radiological Groundwater Protection Program (GWPP) including evaluating hydrology and geology, conducting a risk assessment, establishing and modifying on-site ground water monitoring, voluntary communications, corrective actions, reporting, and record keeping. Each program element of NEI 07-07 "Industry Ground Water Protection Initiative - Final Guidance Document" is identified in the corresponding procedure element.

At Plant Hatch procedure 64CH-SAM-028-0 Releases Via Planned and Unplanned Routes :

Sampling and Analysis procedure provides instructions for the sampling of groundwater sample wells, drainage outfalls, STP effluent and drinking water deep wells for the Releases via Unplanned Routes (RVUR) sampling and analysis program.

The Attachments to 64CH-SAM-028-0 contain the maps of the sampling points, the locations, collection frequency and the analyses required .

In 2012 there was one leak detected by routine sampling. On 12/19/12 the samples from the T11 and T12 wells near the Unit One CST had a tritium concentration of 4.8E6 and 5.7E6 picocurieslliter respectively which was 100 times the normal values 79

Edwin I. Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Plant Annual Radioactive Effluent Release Reports for 2012 Enclosure 2 Farley Annual Radioactive Effluent Release Report for 2

SOUTHERN NUCLEAR OPERATING COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALENDAR YEAR 2012

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 1.0 LIQUID EFFLUENTS 1 1.1 latory s 1 1.1.1 Concentration Limits 1

.1.2 Dose Limit 1 1.2 Effluent Concentration Limit (ECL) 1 1.3 Measurements and ion 2 of Total Radioactivity

1. 3.1 Total Radioactivity Determination 2 1.3.2 Total Error Estimation 3 1.4 id Effluents - Release 3 1.5 Due to Releases 3 1.6 Effluents - Batch Releases 4 1.7 id Effluents - Abnormal Releases 4 2.0 GASEOUS EFFLUENTS 26 2.1 26 2.1.1 Dose Rate Limits 26 2.1 2 Air Doses Due to Noble Gases in 26 Gaseous Releases 2.1. 3 Doses to a Member of the Public 27 2.2 Measurements and ion 27 of Total Radioactivity 2.2.1 Collection and is 28

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE

.2.2 Total Quantities of Radioactivity, Dose 28 Rates and Cumulative Doses 2.2.2.1 Fission and Activation Gases 29 2.2.2.2 Radioiodine, Tritium and Particulate 29 Releases 2.2.2. Gross Release 30 2.2.3 Total Error Estimation 30 2.3 Gaseous Effluent Release Data 31 2.4 Impact Due to Gaseous 32 Releases

2. Gaseous Effluents - Batch Releases 32 2.6 Gaseous Effluents - Abnormal Releases 3.0 SOLID WASTE 57 3.1 Regula s 57

.1.1 Solid Radioactive Waste System 3.1.2 rements 57 3.2 Solid Waste Data 57 4.0 DOSES TO MEMBERS OF THE PUBLIC 60 INSIDE THE ITE BOUNDARY 4.1 60 4.2 Demonstration of iance 60

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 5.0 TOTAL DOSE FROM URANIUM FUEL 65 CYCLE (40CFR190) 5.1 irements 65 5.2 Demonstration of iance 65 6.0 METEOROLOGICAL DATA 65 7.0 PROGRAM DEVIATIONS 65 7.1 Gaseous Effluent 65 7.1.1 Requ rements 65 7.1. 2 of Deviations 66 7.2 Effluent Analysis 66 Minimum Detectable Concentration (MDC) 7.2.1 rements 66 7.2.2 ion of Deviations 66 7.3 Incorrect Compos 66 or Gaseous Effluent 7.3.1 rements 66 7.3.2 of Deviations 66 8.0 CHANGES TO THE PLANT FARLEY ODCM 66 8.1 Regu 6 8.2 Des ion of 66

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR 67 SOLID RADWASTE TREATMENT SYSTEMS 9.1 rements 67 9.2 Des of Major 67 10.0 SERVICE WATER DILUTION BIAS 67

.A A, Carbon-14 for 2012 68

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1 1A Effluents Summation of All Releases, Unit 1 (Quarters 1,2, 3 and 4) 1-lB Effluents - Summation of 6 All Releases, Unit 2 (Quarters 1,2, 3 and 4) 1-lC id Effluents - Summation f 7 All Releases, Site (Quarters 1,2, 3 and 4) 1-2A Effluents, Unit 1 (Quarters 1,2, 8 3 and 4) 1-2B Effluents, Unit 2 (Quarters 1,2, 12 3 and 4) 1-2C Effluents, Site (Quarters 1,2, 15 3 and 4) 1 3A Doses 19 Due to Releases, Unit 1 (Quarters 1,2,3 and 4) 1 3B Doses to a MEMBER OF THE PUBLIC 20 Due to Releases, Unit 2 (Quarters 1,2,3 and 4) 1-4 Minimum Detectable Concentration - 21 Analyses I-5A id Effluents Batch Release 22 Summary, Unit 1 1-5B Effluents Batch Release 23 Summary, Unit 2

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-6A - Abnormal Release 24 Unit 1 1-6B Effluents Abnormal Release 25 Unit 2 2 1A Gaseous Effluents - Summation of 33 All Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-18 Gaseous Effluents - Summation of 34 All Releases, Unit 2 (Quarters 1,2, 3 and 4) 2 1C Gaseous Effluents Summation 35 All Releases, Site (Quarters 1,2, 3 and 4) 2-2A Gaseous Effluents Mixed Mode 36 Level Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-2B Gaseous Effluents - Mixed Mode 38 Level Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-2C Gaseous Effluents Mixed Mode 40 Level Releases, Site (Quarters 1,2, 3 and 4) 2-3A Gaseous Effluents - Ground 42 Level Releases, Unit 1 (Quarters 1,2, and 4) 2 38 Gaseous Effluents - Ground 44 Level Releases, Unit 2 (Quarters 1,2, 3 and 4) 2 3C Gaseous Effluents - Ground 46 Level Releases, Site (Quarters 1,2, 3 and 4)

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST TABLES PAGE 2-4A Air Doses Due to Noble Gases in 48 Gaseous Releases, Unit 1 (Quarters 1,2, 3 and 4) 2 48 Air Doses Due to Noble Gases in 49 Gaseous Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-5A Doses to a MEMBER OF THE PUBLIC 50 Due to Radioiodines, Tri and Particulates in Gaseous Releases, Unit 1 (Quarters 1,2,3 and 4) 2-5B Doses to a MEMBER OF THE PUBLIC 51 Due to Radioiodines, Trit and Particulates in Gaseous Releases, Unit 2 (Quarters 1,2,3 and 4) 2-6 Minimum Detectable Concentration - 52 Gaseous Effluent Analyses 2 7A Gaseous Effluents Batch Release 5 Unit 1 2-7B Gaseous Effluents Batch Release 54 Unit 2

-8A Gaseous Effluents Abnormal Release 55 Unit 1 2-8B Gaseous Effluents Abnormal Release 56 Unit 2 3 1 Solid Waste and Irradiated 58 Fuel 4 1 Doses to a MEMBER OF THE PUBLIC 61 Due to Activities Inside the Site

, Site

1.0 ID EFFLUENTS This section contains icable aDCM limits for liquid effluents as well as the ities of radioactive 1 id effluents released during 2012. These ties are summarized on a rly basis and include any unplanned releases. A tabulation of the total and organ doses which were calculated in accordance with aDCM 2.4 are presented to show conformance with the limits of aDCM 2.1.3.

1.1 irements 1.1.1 Concentration Limits Technical fications S.S.4.b and S.S.4.cstate that the concentration of radioactive material released in 1 id effluents to UNRESTRICTED AREAS (see aDCM re 10-1) shall be limited at all times to ten times the concentrations specified in 10CFR20, ndix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-04 uCi/ml total act 1.1.2 Dose Limits Technical ifications 5.5.4.d and 5.5.4.e state that the dose or dose commitment to a MEMBER aF THE PUBLIC from radioactive materials in 1 id effluents re from each unit, to UNRESTRICTED AREAS (see aDCM re 10-1) shall be limited:

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

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

1.2 Effluent Concentration Limit (ECL)

ECL values used in determin 1 id radwaste release rates and concentrations, for princ gamma emitters, I-131, trit Sr-89, Sr-90 and Fe 55, are taken from 10CFR Part 20, B, Table 2, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establi ical monitor which can accommodate effluent releases at concentrations higher than the ECL values stated in 10CFR20, B, Table 2, Column 2.

For dissolved or entrained noble gases in 1 id radwaste, the ECL is 1.OE-04 uCi total For gross a in 1 id radwaste, the ECL is 2.0E-09 uCi Furthermore, for all the above radionuclides, or s of radioactivi , the overall ECL fraction is determined in accordance with OCFR Part 20, x B.

- 1

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

MN-54 CS-134 FE-59 CS-137 CO-58 CE-141 CO-60 CE-144 ZN-65 MO-99 SR-89 FE-55 SR-90 H-3 1-131

1. 3.1 Total Radioactivity Determination Batch Releases: Representative pre-release grab samples are obtained and analyzed in accordance with ODCM Table 2-3. Isotopic analyses are performed using the computerized pulse height analysis system utilizing high resolution germanium detectors. Isotopic values thus obtained are used for release rate calculations as specified in the ODCM. Only those nuclides that are detected are used in the calculations. All Strontium and Iron-55 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis. Gross beta and gross alpha determinations are made using 2 pi gas flow proportional counters. Tritium determinations are made using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on the pulse height analyzer.

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

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

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

- 2

Continuous Releases: Continuous releases are to batch releases that are ana on a weekly composite basis in accordance with ODCM Table 2 3.

ly achieved liquid effluent sample analyses minimum detectable concentrations are in Table 1 4.

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

1.4 Effluent Release Data Su~~aries of all radioactive I id effluents released from Units 1 and 2 2012 are presented in accordance with Regulatory Guide 1.21 Tables 2A and 2B. Information required Table 2A is found in this report in Tables 1- 1-lB, and 1 lCi Table 2-B information is in Tables 1-2B, and 1-2C. Data is presented on a basis as by ry Guide 1.21 for all four 1.5 Radi Impact Due to id Releases The total body and organ doses for Units 1 and 2 are in the foll tables in order to show conformance with the limits of ODCM 2.1.3:

Unit 1 2012 Doses to a Member of the Public due to Releases:

Table 1 3A Unit 2 2012 Doses to a Member of the Public due to Liquid Releases:

Table 1-3B

- 3

1.6 id Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the fol tables:

Unit 1 2012 d Effluents - Batch Release Table 1-SA Unit 2 2012 Effluents Batch Release Table 1-5B 1.7 Liquid Effluents - Abnormal Releases There was one abnormal release du 2012. A Unit 2 Component Cool Water (CCW) heat experienced a leak of CCW into the service water side. No limits were exceeded due to this abnormal release. The details of this event are included in Condition 440063.

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

Unit 1 2012 Effluents - Abnormal Release Table 1-6A Unit 2 2012 Effluents Abnormal Release Table 1-6B

- 4

Table Joseph M Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Effluents - Summation of All Unit: 1 2012 Ending: 31-Dec-2012 Type Units 1ST A. And Activation Products

1. Total Release Curies 3.12E-02 2.30E-02

2. diluted concentration 4.62E-08

3. Percent of Limit  % * * *

• Curies 1 J{::>F+n? 1.28E+Ol

2. diluted Concentration during l.S8E-OS 1.49E-04

3. Percent of  % * * *

• C.

1. Total Curies 4.29E-OS 2.43E-04

2. Averaoe diluted Concentration 6.6SE-09 1 2.S2E-1O S.31E-l0

3. Percent of Applicable Limit  % * * *

• Curies 1.iSE-OS O.OOE+OO O.OOE+OO Liters 6.11E+OS Water 1.3SE+09

• are

- 5

Joseph M Farley Nuclear RADIOACTIVE EFFLU Liquid - Summation 2

1-Jan- 2012 Ending:

of Effluent 1ST 2ND Quarter 3RD A.

1.41E-02 2.83E-02 1.40E-08 1.53E-08

3. Percent of Limit  % * * * *

1. Total Release Curies 1.29E+02 1.87E+Ol 1.15E+02 3.15E+02

2. Concentration 6.69E-OS 1.19E-04 3.22E-04

3. Percent Applicable Limit  % * * * *

1. Total Release 1.61E-04 2.22E-04

2. Averaae Concentration 1 2.27E-1O

3. Percent Applicable Limit  % * * *

• 9.50E-06 O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Liters 9.2SE+OS F. Volume of Liters 1.92E+09 1.01E+09 9.67E+08 9.77E+08

• are of 6

Table JO!;eDln M Farley Nuclear RADIOACTIVE EFFLUENT REPORT All ReUi!!aS~!S Ending: 31-Dec-2012 of Effluent 2ND Quarter 3R.D A. Products Curies 3.66E-02 4.S3E-02 3.08E-02 S.13E-02 2.

uCi/ml 1

3. Percent of limit  % * * *

• Curies 3.11E+02 3.16E+Ol 2,44E+02 Concentration uCi/ml 1.33E-04

3. Percent of Limit  % * * *

• Curies 1.80E-02 6.S3E-OS 4.04E-04 4.87E-04

2. diluted Concentration during period 1 2.21E-1O 3.30E-1O

3. Percent of Limit  % * * *

• Curies 2.13E-OS O.OOE+OO O.OOE+OO Liters 1.83E+09 1.47E+09

• limits are terms of and this

- 7

Table farley Nuclear Plant RADIOACTIVE EffLUENT RELEASE REPORT 2012 Unit: 1 Starting:

Continuous Mode Nuclides Kellea!!Oea Units 1ST Fission & Activation products No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO no radioactivity was ...... 0<:'0,.,

concentrations.

8

Table l-lA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Be-7 Curies O.OOE+OO 9.34E-06 O.OOE+OO O.OOE+OO Y-88 Curies 3.88E-07 O.OOE+OO O.OOE+OO O.OOE+OO Y-9S Curies O.OOE+OO 2.23E-OS O.OOE+OO O.OOE+OO As-76 Curies O.OOE+OO O.OOE+OO 3.l6E-06 O.OOE+OO Co-57 Curies O.OOE+OO 1.70E-06 O.OOE+OO O.OOE+OO Co-58 Curies 3.07E-04 S.S3E-03 7.04E-04 l.42E-04 Co-60 Curies 1.l7E-03 1.7lE-03 S.29E-04 2.82E-04 Cr-Sl Curies O.OOE+OO 2.37E-03 1.l2E-OS O.OOE+OO Fe-55 Curies 3.42E-04 S.lSE-04 2.S9E-04 6.72E-OS Fe-59 Curies O.OOE+OO S.28E-06 O.OOE+OO O.OOE+OO 1-132 Curies O.OOE+OO l.90E-OS O.OOE+OO O.OOE+OO Mn-S4 Curies O.OOE+OO S.03E-OS 3.S6E-06 1. llE-06 Nb-95 Curies S.86E-06 6.40E-04 4.84E-OS 2.82E-06 Nb-97 Curies 1.0lE-OS l.4lE-OS 2.7lE-OS 4.32E-06 Ni-S6 Curies 1. 70E-OS 3.66E-OS 1.37E-06 7.96E-07 Sr-89 Curies 2.6SE-OS O.OOE+OO O.OOE+OO 1.4lE-OS Sr-90 Curies O.OOE+OO O.OOE+OO 1.2lE-OS O.OOE+OO Sr-92 Curies O.OOE+OO 1.03E-06 8.79E-07 O.OOE+OO Y-9lM Curies O.OOE+OO 7.94E-07 3.43E-07 O.OOE+OO Zn-65 Curies S.20E-06 6.08E-OS 2.13E-06 1.SSE-06 Zr-9S Curies 6.lSE-07 3.S8E-04 1.l0E-OS O.OOE+OO Ce-143 Curies O.OOE+OO 1.03E-06 O.OOE+OO O.OOE+OO Ce-l46 Curies O.OOE+OO 3.l8E-06 O.OOE+OO O.OOE+OO Cs-134 Curies S.89E-07 O.OOE+OO O.OOE+OO 3.13E-07 Cs-137 Curies 2.0SE-OS 9.S2E-06 2.32E-OS 1.99E-OS Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. - 9

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Pr-144 Curies O.OOE+OO 3.44E-04 O.OOE+OO O.OOE+OO Rh-l0S Curies O.OOE+OO 1.01E-03 S.82E-06 O.OOE+OO Ru-l03 Curies O.OOE+OO 4.63E-06 O.OOE+OO O.OOE+OO Sb-124 Curies O.OOE+OO 2.24E-OS 1. 17E-06 3.11E-07 Sb-12S Curies 9.S8E-OS S.23E-04 2.48E-04 1.24E-04 Sn-113 Curies O.OOE+OO 6.79E-06 O.OOE+OO O.OOE+OO Tc-l0l Curies O.OOE+OO O.OOE+OO 1. 18E-OS O.OOE+OO Te-129 Curies O.OOE+OO 7.79E-OS O.OOE+OO O.OOE+OO Te-132 Curies O.OOE+OO 1.6SE-OS O.OOE+OO O.OOE+OO Zn-69M Curies S.24E-07 O.OOE+OO O.OOE+OO O.OOE+OO Ag-lOSM Curies 4.76E-06 6. 16E-06 7.66E-06 O.OOE+OO Ag-ll0M Curies 2.21E-06 S.37E-OS 3.6SE-OS S.40E-07 Sn-117M Curies 1.46E-OS 2.21E-06 O.OOE+OO O.OOE+OO Te-12SM Curies 1.S7E-02 1.77E-02 1.40E-02 2.23E-02 Te-129M Curies O.OOE+OO 7.74E-OS O.OOE+OO O.OOE+OO Total For Period Curies 1.77E-02 3.12E-02 1.60E-02 2.30E-02 Tritium H-3 Curies 1.S2E+02 1.28E+Ol 1.28E+02 1.74E+02 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 10

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Ar-41 Curies 2.38E-06 1.21E-06 O.OOE+OO 4.21E-06 Xe-133 Curies 8.9SE-03 4.17E-OS 2,43E-04 2.60E-04 Xe-13S Curies S.9SE-06 O.OOE+OO O.OOE+OO O.OOE+OO Xe-133M Curies 1.84E-OS O.OOE+OO O.OOE+OO O.OOE+OO Xe-13SM Curies 2.84E-06 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 8.98E-03 4.29E-OS 2.43E-04 2.64E-04 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 11

Table 1-28 loseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 2 Starting: l-lan-2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &. Activation Products No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 12

Table 1-28 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 2 Starting: 1-Jan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Be-7 Curies 2,94E-05 6,61E-06 O.OOE+OO O.OOE+OO Y-92 Curies O,OOE+OO 2.58E-06 O.OOE+OO O.OOE+OO Y-94 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-06 Br-82 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.96E-06 Co-58 Curies 9.58E-04 1.50E-03 1.54E-04 1.37E-04 Co-60 Curies 2.49E-03 8.52E-04 3.31E-04 3.08E-04 Cr-51 Curies O.OOE+OO 6.30E-04 O.OOE+OO O.OOE+OO Fe-55 Curies 6.67E-04 2.52E-05 5.41E-05 1.28E-04 1-131 Curies O.OOE+OO O.OOE+OO 6.92E-07 2.46E-05 1-132 Curies O.OOE+OO 1.73E-06 O.OOE+OO O.OOE+OO 1-133 Curies O.OOE+OO O.OOE+OO 1.88E-06 6.46E-05 Mn-54 Curies 1.82E-05 1.56E-05 O.OOE+OO 4.51E-06 Mo-99 Curies O.OOE+OO O.OOE+OO O.OOE+OO 4.87E-05 Na-24 Curies O.OOE+OO O.OOE+OO 2.51E-05 3.07E-04 Nb-95 Curies 1.36E-04 1.40E-04 2.52E-06 O.OOE+OO Nb-97 Curies 8.31E-05 1.37E-05 7.42E-06 4.60E-06 Ni-56 Curies 1.72E-05 2.42E-05 3.96E-06 O.OOE+OO Sr-89 Curies 2.46E-05 O.OOE+OO O.OOE+OO 1.72E-05 Sr-90 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.63E-06 Sr-92 Curies 4. 14E-06 2.50E-06 O.OOE+OO O.OOE+OO Y-91M Curies O.OOE+OO O.OOE+OO O.OOE+OO 5.55E-06 Zn-65 Curies 1.05E-04 4.48E-05 1. 17E-06 O.OOE+OO Zr-95 Curies 3.85E-05 5.32E-05 O.OOE+OO O.OOE+OO Zr-97 Curies 4.58E-07 O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 Curies 3.20E-06 O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels.

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

Table Joseph M Nuclear RADIOACTIVE EFFLUENT REPORT - 2012 2

l-Jan-2012 Ending: 31-Dec-2012 Mode 1ST 2ND Quarter 3RD Quarter 4TH Quarter C5-137 Curies 1. 17E-04 S.92E-06 1.76E-06 S.27E-06 Curies O.OOE+OO O.OOE+OO Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.62E-06 2.0BE-04 1.26E-04 Sn-113 Curies O.OOE+OO 2.90E-06 O.OOE+OO O.OOE+OO Tc-104 Curies 2.77E-07 O.OOE+OO O.OOE+OO O.OOE+OO Curies 4.29E-06 1.1SE-04 Te-129 Curies O.OOE+OO Te-132 Curies O.OOE+OO O.OOE+OO Ag-l0BM 10M 2.06E-OS 2.17E-OS 2.71E-06 Sn-117M Curies B.S4E-06 Curies 1. 35E-02 Curies 1.89E-02 Tritium Curies 1.87E+Ol 3.1SE+02 nio;:c::nhlt:l,t1 And Gases Ar-41 Curies 4.7SE-06 O.OOE+OO 1.14E-OS O.OOE+OO O.OOE+OO 3.01E-06 1.71E-OS O.OOE+OO O.OOE+OO Period Curies 9.00E-03 detectable

- 14

1-2C Joseph M Farley Nuclear Plant RADIOACTIVE RELEASE REPORT Liquid Effluents Site Starting: Ending:

Units 1ST Curies u.uut:+uu U.UUt:+UU u.uut:+uu O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O,OOE+OO Dissolved And e ... *I-..""; .........

No Nuclides Curies O.OOE+OO O.OOE+OO

Table M Farley Nuclear Plant EFFLUENT RELEASE Effluents 2

Batch Nuclides Units 1ST 4TH Quarter Fission &. Activation 8e-7 Curies 2.94E-05 1.59E-05 O.OOE+OO O.OOE+OO Y-88 Curies 3.88E-07 O.OOE+OO O.OOE+OO O.OOE+OO Y-92 Curies O.OOE+OO Y-94 O.OOE+OO L64E-06 Y-95 2.23E-05 O.OOE+OO O.OOE+OO As-76 Curies O.OOE+OO 3.16E-06 O.OOE+OO L96E-06 Co-57 Curies O.OOE+OO 1.70E-06 O.OOE+OO O.OOE+OO Co-58 Curies 2.79E-04 Co-60 5.91E-04 Cr-51 Curies 3.00E-03 L12E-05 Fe-55 Curies 1.01E-03 S,40E-04 3. 13E-04 1.95E-04 Curies O.OOE+OO S.28E-06 O.OOE+OO 1-131 Curies O.OOE+OO 6.92E-07 2,46E-05 1-132 Curies O.OOE+OO O.OOE+OO Curies Mn-S4 6.60E-05 Mo-99 Curies O.OOE+OO O,OOE+OO O.OOE+OO Curies O.OOE+OO O.OOE+OO 2.S1E-05 3.07E-04 Curies 1.42E-04 7.80E-04 5.09E-05 2.82E-06 Nb-97 CUries 8.92E-06 Ni-56 Curies 7.96E-07 Curies 5.12E-05 O.OOE+OO O.OOE+OO 3.13E-OS Curies O.OOE+OO O.OOE+OO 1.21E-05 3.63E-06 Curies 4.14E-06 3.S3E-06 8.79E-07 O.OOE+OO 16

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Y-91M Curies O.OOE+OO 7.94E-07 3.43E-07 S.SSE-06 Zn-6S Curies 1.10E-04 1.06E-04 3.29E-06 l.SSE-06 Zr-9S Curies 3.91E-OS 4.12E-04 1.lOE-OS O.OOE+OO Zr-97 Curies 4.5SE-07 O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 Curies 3.20E-06 O.OOE+OO O.OOE+OO O.OOE+OO Ce-143 Curies O.OOE+OO 1.03E-06 O.OOE+OO O.OOE+OO Ce-146 Curies O.OOE+OO 3.1SE-06 O.OOE+OO O.OOE+OO Cs-134 Curies S.S9E-07 O.OOE+OO O.OOE+OO 3.13E-07 Cs-137 Curies 1.3SE-04 1.S4E-OS 2.S0E-OS 2.S2E-OS Pr-144 Curies O.OOE+OO 3.44E-04 O.OOE+OO O.OOE+OO Rh-lOS Curies O.OOE+OO 1.31E-03 S.82E-06 O.OOE+OO Ru-103 Curies O.OOE+OO 4.63E-06 O.OOE+OO O.OOE+OO Sb-122 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.49E-06 Sb-124 Curies O.OOE+OO 2.62E-OS 1.17E-06 1.93E-06 Sb-12S Curies 7.37E-04 7.31E-04 3.74E-04 2.67E-04 Sn-113 Curies O.OOE+OO 9.69E-06 O.OOE+OO O.OOE+OO Tc-1Ol Curies O.OOE+OO O.OOE+OO 1.18E-OS O.OOE+OO Tc-104 Curies 2.77E-07 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99M Curies O.OOE+OO O.OOE+OO 4.29E-06 1.1SE-04 Te-129 Curies O.OOE+OO 9.S1E-OS O.OOE+OO O.OOE+OO Te-132 Curies O.OOE+OO 2.41E-OS O.OOE+OO O.OOE+OO Zn-69M Curies S.24E-07 O.OOE+OO O.OOE+OO O.OOE+OO Ag-108M Curies 8.98E-06 8.62E-06 9.01E-06 3.39E-07 Ag-llOM Curies 3.66E-OS 7.43E-OS S.84E-OS 3.SSE-06 Sn-117M Curies 2.32E-OS 3.0SE-06 O.OOE+OO O.OOE+OO Te-12SM Curies 2.92E-02 2.80E-02 2.81E-02 4.93E-02 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations. - 1 7

Table Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT REPORT - 2012 liquid l-Jan- 2012 31-Dec-2012 Batch Mode Nuclides Units 1ST Quarter 2ND Te-129M O.OOE+OO Total for 3.66E-02 3.0SE-02 S.13E-02 H-3 Curies 3.11E+02 3. 2.44E+02 4.89E+02 Ar-41 Curies 7. 13E-06 O.OOE+OO 2.1SE-OS

1. 79E-02 4.04E-04 Xe-13S Curies 1.73E-OS O.OOE+OO Xe-133M Curies 3.55E-05 O.OOE+OO O.OOE+OO Xe-135M 2.84E-06 O.OOE+OO O.OOE+OO O.OOE+OO for Period 1.S0E-02 6.S3E-OS 4.04E-04 4.S7E-04

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Table Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT REPORT-Doses to a member of public due to liquid Releases 1

Ending: 31-Dec-2012 Cumulative 1ST %ODCM Bone 5.00E+OO mRem 7.73E-03 1.55E-Ol 1 5.00E+OO mRem 6.64E-Ol 3.39E-02 6.77E-Ol 2.06E-02 4. llE-Ol 4.l8E-02 8.35E-Ol 5.00E+OO mRem 3.32E-02 6.64E-Ol 6.47E-Ol 2.06E-02 4.l2E-Ol 4.24E-02 8A7E-Ol Liver 5.00E+OO mRem 5A8E-03 1.1OE-Ol 3.21E-03 6.43E-02 3.08E-03 6.l6E-02 5.87E-03 l.l7E-Ol mRem mRem 9.70E-02 2.69E-03 S.20E-03 1 5.00E+OO mRem 3.71E-03 1.40E-03 2.79E-02 4.06E-02 3.60E-03 7.21E-02 l.S0E+OO mRem 3.71E-03 2.47E-Ol lAOE-03 9.30E-02 2.03E-03 1.3SE-Ol 3.60E-03 2.40E-Ol Cumulative Doses ODCM lmt Units Date Bone 1.00E+Ol mRem 1.00E+Ol mRem 1.29E-Ol 1.29E+OO 1.00E+Ol mRem 1.29E+OO 1.00E+Ol mRem 1.76E-02 1.76E-Ol mRem l.l7E-02 1.

mRem 1 1 mRem 1.07E-02 1.07E-Ol Maximum Individual Total 3.00E+OO mRem 1.07E-02 Maximum Individual Liauid

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Table 1-38 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter ODCM Lmt Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr OfoODCM 4TH Qtr %ODCM Organ Bone S.OOE+OO mRem S.97E-03 1.19E-Ol 4.02E-03 B.04E-02 4.7BE-03 9.S6E-02 8.4BE-03 1.70E-Ol GI-Lli S.OOE+OO mRem 2.S0E-02 S.OOE-Ol 1.7SE-02 3.49E-Ol 2.01E-02 4.03E-Ol 3.63E-02 7.26E-Ol Kidney S.OOE+OO mRem 2.42E-02 4.B3E-Ol 1.72E-02 3.43E-Ol 2.04E-02 4.0BE-Ol 3.68E-02 7.36E-Ol Liver S.OOE+OO mRem 3.92E-03 7.83E-02 2.40E-03 4.79E-02 2.77E-03 S.S4E-02 S.B9E-03 1.1BE-Ol Lung S.OOE+OO mRem S.19E-03 1.04E-Ol 1.94E-03 3.BBE-02 1.S6E-03 3.11E-02 3.42E-03 6.BSE-02 Thyroid S.OOE+OO mRem 3.17E-03 6.33E-02 2.11E-03 4.21E-02 2.46E-03 4.91E-02 S.39E-03 1.0BE-Ol Total Body S.OOE+OO mRem 2.S3E-03 S.OSE-02 1.S0E-03 3.00E-02 1.68E-03 3.36E-02 3.9BE-03 7.97E-02 Total Body 1.S0E+OO mRem 2.S3E-03 1.6BE-Ol 1.S0E-03 1.00E-Ol 1.6BE-03 1.12E-Ol 3.9BE-03 2.66E-Ol Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %ODCM Receptor Limit Bone 1.00E+Ol mRem 2.33E-02 2.33E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+Ol mRem 9.B9E-02 9.89E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+Ol mRem 9.BSE-02 9.BSE-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 1.S0E-02 1.S0E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+Ol mRem 1.21E-02 1.21E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 1.31E-02 1.31E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.00E+Ol mRem 9.69E-03 9.69E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+OO mRem 9.69E-03 3.23E-Ol Maximum Individual Liquid Liquid Effluent TB Annual

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TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 MINIMUM DETECTABLE CONCENTRATION - LIQUID SAMPLE ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

Nuclide MDC(uCi/ML)

MN-54 4.01E-OS CO-5S 3.12E-OS FE-59 9.04E-OS CO-60 1.76E-OS ZN-65 1.19E-07 MO-99 2.9SE-07 I-131 3.05E-OS CS-134 4.01E-OS CS-137 3.S4E-OS CE-141 4.21E-OS CE-144 1.51E-07

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Table l-SA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Batch Release Summary Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 134 71 65 46 316

2. Total time period for Batch releases ( Minutes) 1.57E+04 7.52E+03 7.00E+03 5.02E+03 3.53E+04

3. Maximum time period for a batch release ( Minutes) 1.90E+02 1.33E+02 1.22E+02 1.28E+02 1.90E+02

4. Average time period for a batch release ( Minutes) 1. 17E+02 1.06E+02 1.08E+02 1.09E+02 1. 12E+02

5. Minimum time period for a batch release ( Minutes) 9.70E+01 3.00E+00 8.50E+01 9.60E+01 3.00E+00

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 6.61E+03 3.22E+03 2.46E+03 2.31E+03 3.64E+03

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

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Table 1-58 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - 8atch Release Summary Unit: 2 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 118 79 67 70 334

2. Total time period for Batch releases ( Minutes) 1.21E+04 1.84E+04 7.03E+03 7.10E+03 4.46E+04

3. Maximum time period for a batch release ( Minutes) l.S6E+02 1.01E+04 1.60E+02 1.71E+02 1.01E+04

4. Average time period for a batch release ( Minutes) 1.02E+02 2.33E+02 1.0SE+02 1.01E+02 1.34E+02

5. Minimum time period for a batch release ( Minutes) 7.80E+Ol 8.00E+Ol 9.30E+Ol 8.70E+Ol 7.80E+Ol

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 6.61E+03 3.22E+03 2.46E+03 2.31E+03 3.64E+03

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

- 23

Table 1-6A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 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) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

- 24

JO~;eDln M Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT Effluents - Abnormal Unit: 2 Starting: l-lan- Ending:

units 1ST Year Totals 0 1 0 0 1

2. Total Time For All Releases ( Minutes) O.OOE+OO

3. Maximum Time For A ( Minutes) O.OOE+OO 1.01E+04 O.OOE+OO O.OOE+OO 1.01E+04

4. Time For A ( Minutes) O.OOE+OO 1.01E+04 O.OOE+OO O.OOE+OO 1.01E+04

5. Minimum Time For A ( ) O.OOE+OO O.OOE+OO O.OOE+OO 1.01E+04

6. Total for ( Curies) O.OOE+OO

- 25

2.0 GASEOUS EFFLUENTS This section contains applicable ODeM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2012.

These quantities are summarized on a quarterly basis and include any unplanned releases. Tabulations are provided of the offsite air doses calculated in accordance with ODeM 3.4.2 to show conformance with the limits of ODeM 3.1.3, and the offsite organ doses to a member of the public calculated in accordance with ODeM 3.4.3 to show conformance with ODeM 3.1. 4.

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

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

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

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

2.1.2 Air Doses Due to Noble Gases in Gaseous Releases Technical Specifications S.5.4.e and S.5.4.h state that the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODeM Figure 10-1) shall be limited to the following:

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

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

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2.1.3 Doses to a Member of the Public Technical Specifications 5.5.4.e and 5.5.4.i state that the dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODCM Figure 10-1) shall be limited to the following:

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

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

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

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

MN-54 MO-99 FE-59 1-131 CO-58 CS-134 CO-60 CS-137 ZN-65 CE-141 SR-89 CE-144 SR-90 H-3

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2.2.1 Sample collection and Analysis Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system utilizing high resolution germanium detectors. Samples are obtained and analyzed in accordance with ODCM Table 3-3. Isotopic values thus obtained are used for release rate calculations as specified in ODCM 3.4.2 and ODCM 3.4.3. Only those nuclides which are detected are used in calculations. For radioiodines and particulates, in addition to the nuclides listed above other nuclides with half-lives greater than 8 days which are identified are also considered.

Continuous Releases: Continuous sampling is performed on the continuous release points (i.e. the Plant Vent Stack, Containment Purge when in continuous mode, and the Turbine Building Vent). Particulate material is collected by filtration. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and strontium as required. All gross alpha, Sr-89 and Sr-90 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis.

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

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

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

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

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

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

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

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

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

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

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

- 29

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

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

2.2.2.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters, for each week for gross alpha activity in a proportional counter.

The highest concentration calculated for any of these weeks is used for the monthly value. This value is input into the composite file of the computer and used for release calculations.

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

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

The average error associated with counting is estimated to be:

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

- 30

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

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

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

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

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

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

- 31

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

Unit 1 2012 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2012 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4B Unit 1 2012 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5A Unit 2 2012 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5B 2.5 Gaseous Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables:

Unit 1 2012 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2012 Gaseous Effluents - Batch Release Summary: Table 2-7B 2.6 Gaseous Effluents - Abnormal Releases There were no abnormal releases on Unit 1 or Unit 2 during 2012.

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

Unit 1 2012 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2012 Gaseous Effluents - Abnormal Release Summary: Table 2-8B

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Table 2-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.21E+OO 1.25E+OO S.S3E-Ol 7.96E-Ol

2. Average Release rate for period uCi/sec 2.S1E-Ol 1.59E-Ol 1.12E-Ol 1.01E-Ol

3. Percent of Applicable Limit  % * * *

• B. Radioiodines

1. Total Iodine-131 Curies O.OOE+OO S.62E-06 O.OOE+OO O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+OO 1.09E-06 O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit  % * * *

• C. Particulates

1. Particulates ( Half-Lives> S Days) Curies 1.55E-07 7.41E-07 1.72E-07 O.OOE+OO

2. Average Release rate for period uCi/sec 1.97E-OS 9.40E-OS 2.1SE-OS O.OOE+OO

3. Percent of Applicable Limit  % * * *

• D. Tritium

1. Total Release Curies 1.47E+OO 7.7SE-Ol 1.50E+OO 1.51E+OO

2. Average Release rate for period uCi/sec l.S7E-Ol 9.S7E-02 1.91E-Ol 1.91E-Ol

3. Percent of Applicable Limit * * *

• E. Gro~s AIQha

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

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

• Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-48, 2-5A, 2-58 of this report.

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Table 2-18 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.B3E-Ol 2.1SE-Ol 2.60E-Ol 4.0BE-Ol

2. Average Release rate for period uCi/sec 3.S9E-02 2.73E-02 3.30E-02 S.18E-02

3. Percent of Applicable Limit  % * * *

• B. Radioiodines

1. Total Iodine-13l Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

3. Percent of Applicable Limit  % * * *

• C. Particulates

1. Particulates ( Half-Lives> 8 Days) Curies 2.01E-OB O.OOE+OO O.OOE+OO O.OOE+OO

2. Average Release rate for period uCi/sec 2.SSE-09 O.OOE+OO O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit  % * * *

• D. Tritiym

1. Total Release Curies 6.31E+OO 6.9SE+OO 7.24E+OO 1.04E+Ol

2. Average Release rate for period uCi/sec 8.00E-Ol 8.B1E-Ol 9.l9E-Ol 1.32E+OO

3. Percent of Applicable Limit * * *

• E. Gross Alpha

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

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

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

- 34

Table 2-1C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: l-Jan-2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.S0E+OO 1.47E+OO lo14E+OO 1.20E+OO

2. Average Release rate for period uCi/sec 3.17E-Ol 1.86E-Ol 1.4SE-Ol l.S3E-Ol

3. Percent of Applicable Limit  % * * *

• B. Radioiodines

1. Total Iodine-131 Curies O.OOE+OO 8.62E-06 O.OOE+OO O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+OO lo09E-06 O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit  % * * *

• C. Particulates

1. Particulates ( Half-Lives> 8 Days) Curies lo7SE-07 7,41E-07 lo72E-07 O.OOE+OO

2. Average Release rate for period uCi/sec 2.22E-08 9,40E-08 2.18E-08 O.OOE+OO

3. Percent of Applicable Limit  % * * *

• D. Tritium

1. Total Release Curies 7.78E+OO 7.72E+OO 8.7SE+OO lo19E+Ol

2. Average Release rate for period uCi/sec 9.87E-Ol 9.80E-Ol lollE+OO lo51E+OO

3. Percent of Applicable Limit * * *

• E. ~ross All2ha

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

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

• Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-48, 2-5A, 2-58 of this report.

- 35

Table 2-2A loseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: l-lan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.37E+00 5.60E-01 O.OOE+OO O.OOE+OO Total For Period Curies 1.37E+OO S.60E-01 O.OOE+OO O.OOE+OO Iodines 1-131 Curies O.OOE+OO 8.S8E-06 O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO S.SSE-06 O.OOE+OO O.OOE+OO Particulates Co-60 Curies O.OOE+OO 7.36E-07 O.OOE+OO O.OOE+OO 5r-89 Curies 1.5SE-07 O.OOE+OO 1.72E-07 O.OOE+OO Total For Period Curies 1.SSE-07 7.36E-07 1.72E-07 O.OOE+OO Tritium H-3 Curies 1.46E+00 7.5SE-01 1.29E+00 1.2SE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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.

- 36

Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 8.23E-01 3.24E-01 7.61E-01 6.9SE-01 Kr-8SM Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.40E-OS Kr-87 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.26E-04 Xe-131M Curies O.OOE+OO 2.77E-03 O.OOE+OO O.OOE+OO Xe-133M Curies 8.llE-OS 1.S8E-03 S.40E-OS O.OOE+OO Xe-133 Curies 1.87E-02 3.S7E-01 1.lOE-01 9.21E-02 Xe-13S Curies O.OOE+OO 6.48E-03 1.24E-02 8.4SE-03 Total For Period Curies S.42E-01 6.91E-01 S.S3E-01 7.96E-01 Iodines 1-131 Curies O.OOE+OO 3.44E-08 O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO 3.44E-OS O.OOE+OO O.OOE+OO Particulates Y-88 Curies O.OOE+OO 4.0BE-09 O.OOE+OO O.OOE+OO Sn-l13 Curies O.OOE+OO 1. 16E-09 O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO S.23E-09 O.OOE+OO O.OOE+OO Tritium H-3 Curies 1. 71E-02 2.28E-02 2.17E-01 2.S3E-01 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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. - 37 _

Table 2-28 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: I-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates Sr-90 Curies 2.01E-OS O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 2.01E-OS O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 6.30E+OO 6.91E+OO 7.20E+OO 1.04E+Ol Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

- 38

Joseph Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Ga!.eOlJS Effluents - Mixed Mode Level "..".,...

2 l-Jan- 3 -..... O;:;L.-- .c;.1L6 Batch Mode Released 1ST ....,..."'. ",.., Quarter 3RD Quarter 4TH

--~--

fission Gases Ar-41 Curies 2.

Curies 4.21E-04 O.OOE+OO Total for Period No Found Particulates No Found Curies Tritium H-3 1. 16E-02 Alpha No I 'II UI.. "U 0::::::' O.OOE+OO was at l"I""t-,..,""'-'"

- 39

Table 2-2C loseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: l-lan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.37E+00 S.60E-01 O.OOE+OO O.OOE+OO Total For Period Curies 1.37E+OO S.60E-01 O.OOE+OO O.OOE+OO Iodines 1-131 Curies O.OOE+OO 8.S8E-06 O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO 8.S8E-06 O.OOE+OO O.OOE+OO Particulates Co-60 Curies O.OOE+OO 7.36E-07 O.OOE+OO O.OOE+OO Sr-89 Curies l.SSE-07 O.OOE+OO 1.72E-07 O.OOE+OO Sr-90 Curies 2.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.7SE-07 7.36E-07 1.72E-07 O.OOE+OO Tritium H-3 Curies 7.7SE+00 7.66E+00 8.48E+00 1.16E+01 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

- 40

Table 2-2C M Farley Nuclear Plant EFFLUENT RELEASE REPORT - 20

- Mixed Mode Level Kellea:ses Gases Ar-41 Curies l.llE+OO 1.02E+OO 1.10E+OO Curies O.OOE+OO O.OOE+OO 6.40E-OS Kr-S7 O.OOE+OO Xe-131M Curies O.OOE+OO 2.77E-03 O.OOE+OO Xe-133M Curies S.llE-OS S.40E-OS O.OOE+OO Xe-133 3.S7E-Ol 1.

Xe-13S O.OOE+OO 6.4SE-03 1.24E-02 Total for Period 1.13E+OO 9.07E-Ol 1.20E+OO Iodines 1-131 Curies O.OOE+OO 3.44E-OS Total for Period O.OOE+OO 3.44E-08 Particulates V-S8 O.OOE+OO 4.0SE-09 Sn-1l3 Curies O.OOE+OO 1. O.OOE+OO Total for Period O.OOE+OO O.OOE+OO H-3 Curies 2.S7E-02 2.63E-Ol No O.OOE+OO O.OOE+OO If no was 41

Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

- 42

2-3A RADIOACTIVE RELEASE -2012 Gaseous - Ground Unit: 1 Starting: Ending: 3

.......,.-..-.... Mode Released Unit 1ST 2ND Quarter 4TH

---=---

Fission Gases No O.OOE+OO No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Curies O.OOE+OO O.OOE+OO Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO No Found Curies O.OOE+OO O.OOE+OO is Zeroes in indicates that no radioactivity was

- 43

2-38 RADIOACTIVE RELEASE -2012 Gaseous - Ground Unit: 2 Starting: Ending: 3

",-_.a.. IU""U;;;o Mode Released Unit 1ST Fission Gases No Found Curies O.OOE+OO O.OOE+OO O.OOE+OO No Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO No Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

~U\"IIUC;) Found Curies O.OOE+OO O.OOE+OO O.OOE+OO Gross No U\..IIUC;) Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Reported. no was detectable

- 44

Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground level Releases Unit: 2 Starting: l-Jan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

- 45

Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: Site Starting: l-Jan-2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

- 46

Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: Site Starting: l-Jan-2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

- 47

Table 2-4A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Releases Unit: 1 Starting: l-Jan-2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Type of Radiation aDCM Lmt Units 1ST Qtr 0/0 aDCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Gamma Air S.OOE+OO mRad 6.99E-04 1.40E-02 2.S6E-04 S.72E-03 2.4SE-04 4.89E-03 2.23E-04 4.46E-03 Beta Air 1.00E+Ol mRad 2.47E-04 2.47E-03 1. 13E-04 1. 13E-03 9.0SE-OS 9.0SE-04 S.21E-OS 8.21E-04 Cumulative Doses Per Year Type of Radiation aDCM Lmt Units Year to End Date %aDCM Receptor Limit Gamma Air 1.00E+Ol mRad 1.4SE-03 1.4SE-02 Site Boundary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.00E+Ol mRad S.33E-04 2.66E-03 Site Boundary SSE Mixed Mode R Air Dose Beta Annual

- 48

Table 2-48 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Releases Unit: 2 Starting: l-Jan-2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Gamma Air S.OOE+OO mRad 9.01E-OS 1.80E-03 6.8SE-OS 1.37E-03 8.28E-OS 1.66E-03 1.30E-04 2.60E-03 Beta Air 1.00E+Ol mRad 3.18E-OS 3.18E-04 2.42E-OS 2.42E-04 2.92E-OS 2.92E-04 4.S8E-OS 4.S8E-04 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date %ODCM Receptor Limit Gamma Air 1.00E+Ol mRad 3.71E-04 3.71E-03 Site Boundary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.00E+Ol mRad 1.31E-04 6.SSE-04 Site Boundary SSE Mixed Mode R Air Dose Beta Annual

- 49

Table 2-SA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: I-Jan-2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Organ ODCM Lmt Units lSTQtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Bone 7.S0E+OO mRem 1.4SE-06 1.93E-OS S.79E-06 7.72E-OS 2.09E-06 2.79E-OS O.OOE+OO O.OOE+OO GI-Lli 7.S0E+OO mRem 1.98E-04 2.6SE-03 1.12E-04 l.S0E-03 2.06E-04 2.74E-03 2.06E-04 2.7SE-03 Kidney 7.S0E+OO mRem 1.98E-04 2.6SE-03 1.12E-04 l.S0E-03 2.06E-04 2.74E-03 2.06E-04 2.7SE-03 Liver 7.S0E+OO mRem 1.98E-04 2.6SE-03 1.12E-04 l.SOE-03 2.06E-04 2.74E-03 2.06E-04 2.7SE-03 Lung 7.S0E+OO mRem 1.98E-04 2.6SE-03 1.12E-04 1.49E-03 2.06E-04 2.74E-03 2.06E-04 2.7SE-03 Thyroid 7.S0E+OO mRem 1.98E-04 2.6SE-03 2.67E-04 3.S6E-03 2.06E-04 2.74E-03 2.06E-04 2.7SE-03 Total Body 7.S0E+OO mRem 1.98E-04 2.6SE-03 1.12E-04 l.SOE-03 2.06E-04 2.74E-03 2.06E-04 2.7SE-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %ODCM Receptor Limit Bone l.SOOE+Ol mRem 9.327E-06 6.218E-OS Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli l.SOOE+Ol mRem 7.227E-04 4.818E-03 Gas Controlling Receptor Iodine/Part Dose Annual Kidney l.SOOE+Ol mRem 7.227E-04 4.818E-03 Gas Controlling Receptor Iodine/Part Dose Annual Liver l.S00E+Ol mRem 7.22SE-04 4.817E-03 Gas Controlling Receptor Iodine/Part Dose Annual Lung l.SOOE+Ol mRem 7.221E-04 4.814E-03 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid l.SOOE+Ol mRem 8.77SE-04 S.8S0E-03 Gas Controlling Receptor Iodine/Part Dose Annual Total Body l.SOOE+Ol mRem 7.226E-04 4.817E-03 Gas Controlling Receptor Iodine/Part Dose Annual

- 50

Table 2-58 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: l-Jan-2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Organ ODCM Lmt Units lSTQtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Bone 7.S0E+OO mRem 8.43E-06 1. 12E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO GI-Lli 7.S0E+OO mRem 8.63E-04 1.1SE-02 9.S0E-04 1.27E-02 9.91E-04 1.32E-02 1.42E-03 1.90E-02 Kidney 7.S0E+OO mRem 8.63E-04 1.1SE-02 9.S0E-04 1.27E-02 9.91E-04 1.32E-02 1.42E-03 1.90E-02 Liver 7.S0E+OO mRem 8.63E-04 1.1SE-02 9.S0E-04 1.27E-02 9.91E-04 1.32E-02 1.42E-03 1.90E-02 Lung 7.S0E+OO mRem 8.63E-04 1.lSE-02 9.S0E-04 1.27E-02 9.91E-04 1.32E-02 1.42E-03 1.90E-02 Thyroid 7.S0E+OO mRem 8.63E-04 1.1SE-02 9.S0E-04 1.27E-02 9.91E-04 1.32E-02 1.42E-03 1.90E-02 Total Body 7.S0E+OO mRem 8.6SE-04 1.1SE-02 9.S0E-04 1.27E-02 9.91E-04 1.32E-02 1.42E-03 1.90E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %ODCM Receptor Limit Bone l.SOOE+Ol mRem 8.427E-06 S.618E-OS Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli l.SOOE+Ol mRem 4.22SE-03 2.817E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney l.SOOE+Ol mRem 4.22SE-03 2.817E-02 Gas Controlling Receptor Iodine/Part Dose Annual Liver l.SOOE+Ol mRem 4.22SE-03 2.817E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung l.SOOE+Ol mRem 4.22SE-03 2.817E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid l.SOOE+Ol mRem 4.22SE-03 2.817E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body l.SOOE+Ol mRem 4.227E-03 2.818E-02 Gas Controlling Receptor Iodine/Part Dose Annual

- 51

TABLE 2-6 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS EFFLUENT ANALYSES The va lue s in th is table represent a priori Minimum Detectable Concentrat i o ns (MDC) that are typ ic ally ach i eved in laboratory analyses of gaseous radwaste samples.

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

MN-54 4.17E-14 KR-87 4.64E-08 CO - 58 7 . 65E -14 KR - 88 7 .4 6E - 08 FE-59 2.53E -14 XE-133 4.71E-08 CO - 60 6.01 E-14 XE - 133M 1.42E-07 ZN - 65 2.40E- 1 3 XE -1 35 1.58E-08 MO - 99 4.46E-13 XE -1 38 1. 21E - 07 C5 -1 34 5.17E -14 I-131 5 . 95E -14 C5- 1 37 6.95E-15 I-133 8.96E -14 CE- 1 41 4.28E-14 CE- 1 44 1.64E-13

- 52

Table 2-7A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 175 84 129 157 545

2. Total time period for batch releases ( Minutes) 1.33E+04 8.81E+03 1. 14E+04 8.08E+03 4.16E+04

3. Maximum time period for a batch release ( Minutes) 5.92E+02 8.45E+02 2.36E+03 3.54E+02 2.36E+03

4. Average time period for a batch release ( Minutes) 7.61E+01 1.05E+02 8.83E+Ol 5.15E+01 7.63E+Ol S. Minimum time period for a batch release ( Minutes) 4.00E+OO 4.00E+OO 5.00E+OO 4.00E+OO 4.00E+OO

- 53

Table 2-7B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: I-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 34 49 56 90 229

2. Total time period for batch releases ( Minutes) 3.09E+03 2.41E+03 2.S3E+03 4.22E+03 1.22E+04

3. Maximum time period for a batch release ( Minutes) 1.53E+03 2.81E+02 1.04E+02 3.03E+02 l.S3E+03

4. Average time period for a batch release ( Minutes) 9.08E+Ol 4.92E+Ol 4.S2E+Ol 4.68E+Ol S.3SE+Ol S. Minimum time period for a batch release ( Minutes) 3.00E+00 S.OOE+OO 6.00E+00 S.OOE+OO 3.00E+00

- 54

Table 2-SA loseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: l-lan- 2012 Ending: 31-Dec-2012 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+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

- 55

Table 2-88 loseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: l-lan-2012 Ending: 31-Dec-2012 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+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum Time For A Release ( Minutes): O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average Time For A Release ( Minutes): O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies) : O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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3.0 SOLID WASTE 3.1 Regulatory 3.1.1 Solid Radioactive Waste System FNP-O-M-30 s B.3.1 states that the radwaste solidification system shall be OPERABLE and u as applicable in accordance with a PROCESS CONTROL for the SOLIDIFICATION and ng of radioactive wastes to ensure meeting the rements of 10 CFR Part 20 and 10 CFR Part 71 or to of radioactive wastes from the site.

3.1 .2 Reporting rements FNP-O-M-30 step B.5.1 states that the Annual Radioactive Effluent Release Report, submitted in accordance with Technical fications 5.6.2 and 5.6.3, shall include a summary of the ities of solid radwaste released from the units as outlined in atory Guide 1.21. "Measuring, Evaluat , and Reporting Radioactive Material in and Gaseous Effluents and Solid Waste," Revision 2, June 2009, with data summarized on an annua bas s following the format of Table A-3 thereof.

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

57

TABLE Joseph M.

RADIOACTIVE REPORT - 2012 SOLID RADIOACTIVE WASTE SHIPPED FOR PROCESSING OR DISPOSAL Starting .:::..:::-==-=-:~

Resins, Filters, and Volume Curies Shipped Evaporator Bottoms Waste Class ft" m" A 3.24E+02 9.18E+00 3.63E+00 B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO ALL 3.24E+02 9.18E+00 3.63E+00 Major Nuclides for the Above Table:

Waste Class A Co-60 C-14 18.594% Fe-55 18.151 NI-63 14.71 Zn-65 4.135% Sb-125 2.657% Cs-137 2.619%

Waste Class B N/A Waste Class C N/A ALL Co-60 C-14 18.594% Fe-55 18.151% NI-63 14.71 Zn-65 4.135% Sb-125 2.657% Cs-137 2.619%

Dry Active Waste Volume Curies Shipped Waste Class ft" m" A 1.15E+04 3.25E+02 3.23E-01 B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO ALL 1.15E+04 3.25E+02 3.23E-01 Major Nuclides for the Above Table:

Waste Class A Fe-55 1 H-3 14.975% Co-60 14.9300/ 0 Nb-95 11 Zr-95 10.731% Ni-63 Co-58 7.813% Sb-125 Cr-51 2.998% C-14 1 Zn-65 1.078% Mn-54 1.001 %

Waste Class B N/A Waste Class C N/A ALL Fe-55 19.524% H-3 14.975% Co-60 14.930% Nb-95 11 Zr-95 10.731% Ni-63 9.352% Co-58 7.813% Sb-125 3.202%

Cr-51 2.998% C-14 1.244% Zn-65 1.078% Mn-54 1.001%

Irradiated Components Volume Curies Shipped Waste Class ft" m" A O.OOE+OO O.OOE+OO O.OOE+OO B O.OOE+OO O.OOE+OO O.OOE+OO

! C O.OOE+OO O.OOE+OO O.OOE+OO

! ALL O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides for the Above Table:

Waste Class A N/A Waste Class B N/A Waste Class C N/A ALL N/A

Joseph M.

RADIOACTIVE EFFLUENT REPORT - 2012 SOLID RADIOACTIVE WASTE SHIPPED FOR PROCESSING OR DISPOSAL Ol-Jan-2012 31-Dec-2012 (Continued)

Other Waste Volume Curies Shipped Waste Class ft" m" A 2.48E+02 7.01E+OO 2.09E-04 B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO ALL 2.48E+02 7.01E+OO 2.09E-04 Major Nuclides for the Above Table:

Waste Class A H-399.837%

Waste Class B N/A Waste Class C N/A ALL H-3 99.837%

Sum of All Low-Level Volume Curies Shipped Waste Shipped from Site Waste Class ft" m" A 1.21E+04 3.42E+02 3.95E+OO

~LL O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.21 E+04 3.42E+02 3.95E+OO Major Nuclides for the Above Table:

Waste Class A Co-60 35.633% Fe-55 18.262% C-14 17.175% Ni-63 14.272%

Zn-65 Sb-125 2.702% Cs-137 2.446% H-3 1.229%

Co-58 1.1 Waste Class B N/A Waste Class C N/A ALL Co-60 35.633% Fe-55 18.262% C-14 17.175% Ni-63 14.272%

Zn-65 3.885% Sb-125 2.702% Cs-137 2.446% H-3 1.229%

Co-58 1 .136%

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

4.2 Demonstration of iance However, this assessment has been performed for 2012 using the methods described in ODCM 6.2 and is included in this section as Table 4 1.

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Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2012 Ending: 31-Dec-2012 Location Name: Visitor Center Distance (kilometers): 3.06E-Ol Sector: N Occupancy Factor: 1.37E-03 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3): 1.04E-04 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 1.04E-04 D/Q (m-2): 4.80E-07 Mixed Mode Release Noble Gas X/Q (sec/m3): S.SOE-06 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): S.SOE-06 D/Q (m-2): 6.20E-OS Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem S.OSE-lO 4.32E-OS 3.94E-ll O.OOE+OO 4.40E-08 Liver mRem 3.33E-06 3.36E-06 3.7SE-06 S.10E-06 l.SSE-OS Total Body mRem 3.33E-06 3.36E-06 3.7SE-06 S.lOE-06 l.SSE-OS Thyroid mRem 3.33E-06 3.41E-06 3.7SE-06 S.10E-06 l.S6E-OS Kidney mRem 3.33E-06 3.36E-06 3.7SE-06 S.10E-06 l.SSE-OS Lung mRem 3.33E-06 3.36E-06 3.7SE-06 5.10E-06 l.SSE-OS GI-Lli mRem 3.33E-06 3.36E-06 3.7SE-06 5.lOE-06 l.SSE-OS NG Total Body mRem S.3SE-06 3.76E-06 3.47E-06 3.74E-06 1.93E-OS Whole Body Dose mRem 1.17E-05 7.11E-06 7.22E-06 S.SSE-06 3.49E-05

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Table 4-1 JO~ielJ~n M a Member o-LJlI... IIL. Due to Activities Boundary Site Starting: Ending:

Loc:atJlon Name: ,""1"'\/1("'1'> Water Pond Sector: N Level and Mixed Mode Release Mixed Mode Release Particulate and (sec/m3): (m-2):

Year Bone mRem 4.93E-10 Liver mRem 2.04E-06 2. 2.30E-06 3.

mRem 2.04E-06 2. 2.30E-06 3.12E-06 9.59E-06 mRem 2.04E-06 2. 2.30E-06 3.

mRem 2.04E-06 2. 3.12E-06 mRem 2.04E-06 2. 14E-06 3.12E-06 mRem 2.04E-06 2. 3.12E-06 NG Total Body mRem 5. 13E-06 2. 13E-06 Whole Body Dose mRem 7.17E-06 4.42E-06

- 62

Table 4-1 JO!;eClh M farley Nuclear EffLUENT RELEASE a Public Due to Activities l-Jan-2012 Ending:

Name: River Water - Air (kilometers) : 1.64E+OO N

1.14E-02 Child X/Q (seC/m3): 1.63E-05 (sec/m3): 1.63E-OS (sec/m3): 7.0SE-07 7.0SE-07 1.39E-08 Units 3RD Year mRem 2.63E-ll mRem 2.22E-06 2.S0E-06 3.40E-06 1.04E-OS mRem 2.22E-06 2.29E-06 2.S0E-06 3.40E-06 mRem Kidney mRem 2.22E-06 2.29E-06 2.S0E-06 3.40E-06 1.04E-OS Lung mRem 2.22E-06 2.29E-06 2.S0E-06 3.40E-06 1.04E-OS GI-Lli mRem 2.S0E-06 1.04E-05 mRem 2.S0E-06 1.29E-OS mRem 4.79E-06 4.81E-06 S.90E-06 2.33E-OS 63

Table 4-1 JO!;epin M Farley Nuclear Plant EFFLUENT RELEASE a MAft'IIhAr Due to Activities Site l-Jan-2012 Location Name: New Distance Sector: S Occupancy factor:

Group: Adult Ground Level Release X/Q (sec/m3): 1.8SE-04 Ground Level Release X/Q (sec/m3): 6.66E-OS Mixed Mode Release X/Q (sec/m3): 2.42E-06 Mixed Mode Release X/Q (sec/m3): 2.23E-06 3RD Quarter Year Bone mRem 8.4SE-IO 1.04E-06 Liver mRem 1.59E-04 1.79E-04 2.43E-04 7.39E-04 mRem 1. 59E-04 mRem 1.60E-04 1.79E-04 2.43E-04 7.40E-04 mRem 1.79E-04 7.39E-04 mRem 1.79E-04 7.39E-04 mRem 1.79E-04 mRem 1.72E-04 l.S9E-04 8.86E-04 mRem 3.3IE-04 3.38E-04 1.62E-03

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5.0 TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190) 5.1 1 rements Technical fication 5.5.4.j states that the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioact and to radiation from uranium fuel rces, shall be limited to less than or equal to 25 mrem to the total or to any organ, the id, which shal be imited to less than or to 75 mrem (as stated in ODCM 5. ).

With the calcu ated doses from the release of radioactive materials in or gaseous effluents twice the limits of ODCM 2 . . 3, 3.1.3, or 3.1.4, calculations shall be made to ODCM 5.2 methods to determine whether the above (ODCM 5.1) limits have been exceeded (as stated in ODCM 5 .

• 2).

5.2 Demonstration of iance Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded dur 2012, no calculations were required.

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

7.0 PROGRAM DEVIATIONS 7.1 Inoperable or Gaseous Effluent Monitor Instrumentation

7. rements ODCM 7.2.2.6 states in that the Annual Radioactive Eff uent Release (the report) shall include deviations from the id and gaseous effluent moni instrumentation 1 requirements included in Sections and 3. . of the ODCM. The report must also include an ion as to the inoperability was not corrected in a

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7.1.2 Description of Deviations There were no deviations during 2012.

7.2 Effluent e Analysis Minimum Detectable Concentration (MDC) 7.2.1 ry s aDCM 7.2.2.6 states in that the report shall include deviations from the MDC rements included in aDCM Tables 2-3 and 3 3.

7.2.2 De on of Deviations There were no deviations during 2012.

7.3 Incorrect it of id or Gaseous Effluent Samp 7.3.1 ry rements aDCM 7.2.2.6 states in shall include deviations from composite sampling aDCM Tables 2-3 and 3-3.

7.3.2 ion of Deviations There were no deviations dur 2012.

8.0 CHANGES Ta THE PLANT FARLEY aDCM 8.1 tory rements Pursuant ification S.S.I.c and aDCM 7.2.2.5, licensee initiated to the aDCM shall be submitted to the Nuclear atory Commission as a part of or concurrent with the Annual Radioactive Effluent Release for the period in which any s were made. Included to the cal environmental monitor ing locations or dose calculation locations or any s made to aDCM 4.1.2.2.2 ( and 8.2 Description of There were no to the aDCM 2012.

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9.0 MAJOR CHANGES TO 10, GASEOUS, OR SOLID RADWASTE TREATMENT SYSTEMS 9.1 atory irements ODCM 7.2.2.7 states in part that, as required ODCM 2 . . 5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (1 and gaseous) shall be to the Nuclear Commission in the Annual Radioactive Effluents Release Report the in which the was reviewed and Process Control (PCP) B.5.1.2 states that licensee initiated or s to the solid radioactive waste treatment system shall be to the Nuclear Commission in the Annual Radioactive Effluent Release for the period in which the was . The discussion of each shall include the information specified in PCP B.4.1.

9.2 Descr ion of Major There were no to the Process Control Program during 20 2.

10.0 SERVICE WATER DILUTION BIAS In March, 2013, the Unit 2 Service Water dilution flow recorder was determined to be biased a factor of about 1.43 based on ultrasonic flow detection. Details of this determination can be found in Condition 600325 and Technical Evaluation 601127.

Calculations of Curies released were not this bias since dilution not a in those calculations. The calculation of concentrations and doses for this and previous however, we biased low a factor of

.43.

Based on an application of the 1.43 correction factor to a random number of 1 id releases over the five years, no 10CFR20 concentration limits were exceeded as a result of the bias. Since FNP's 1 been a smal fraction of the ODCM imit (less than one of the ODCM limit for this year's ), the bias would not have resulted in any 1 id dose limits being exceeded or approached. Details of this assessment are included in Technical Evaluation 600968.

67

Farley Nuclear Plant Appendix A CARBON-14 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount ofC-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 aU U. S. nuclear power plants started reporting C-14 amounts released and resulting doses to the maximally exposed member of the public.

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

At Plant Farley, the annual quantity ofC-14 released in gaseous effluents was estimated to be 9.28 Curies (per unit). Approximately 30% of the C-14 released is in the form of 14C02 and is incorporated into plants through photosynthesis. Ingestion dose results from this pathway. The remaining 70% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Farley ODCM, the resulting bone dose to a child located at the controlling receptor location would be 4.11E-Ol mrem in a year which is 2.74% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents. The resulting total body dose to a child located at the controlling receptor location would be 8.21E-02 mrem in a year which is 0.54% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.

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Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2012 Enclosure 3 Vogtle Annual Radioactive Effluent Release Report for 2012

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1, 2012 TO DECEMBER 31, 2012 Page 1 of 80

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Requirements 8 1.1.1 Concentration Limits 8 1.1.2 Dose Limits 8 1.2 Effluent Concentration Limit (ECl) 8 1.3 Measurements and Approximations of Total Radioactivity 9 1.3.1 Total Radioactivity Determination 9 1.3.2 Total Error Estimation 11 1.4 Liquid Effluent Release Data 12 1.5 Radiological Impact Due to Liquid Releases 12 1.6 Liquid Effluents - Batch Releases 12 1.7 Liquid Effluents - Abnormal Releases 12 Table 1-1A Liquid Effluents - Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 13 Table 1-1 B Liquid Effluents - Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 14 Table 1-1C Liquid Effluents - Summation of All Releases Site (Quarters 1,2,3, and 4) 15 Table 1-2A Liquid Effluents -Unit 1 (Quarters 1,2,3, and 4) 16 Table 1-2B Liquid Effluents -Unit 2 (Quarters 1,2,3, and 4) 19 Page 2 of 80

Table 1-2C Liquid Effluents -Site (Quarters 1,2,3, and 4) 21 Table 1-3A Doses to a Member of the Public Due to Liquid Releases Unit 1 (Quarters 1,2,3, and 4) 24 Table 1-3B Doses to a Member of the Public Due to Liquid Releases Unit 2 (Quarters 1,2,3, and 4) 25 Table 1-3C Doses to a Member of the Public Due to Liquid Releases Site (Quarters 1,2,3, and 4) 26 Table 1-4 Minimum Detectable Concentration Liquid Sample Analysis 27 Table 1-5A Liquid Effluents Batch Release Summary Unit 1 (Quarters 1,2,3, and 4) 28 Table 1-5B Liquid Effluents Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 29 Table 1-5C Liquid Effluents Batch Release Summary Site (Quarters 1,2,3, and 4) 30 Table 1-6A Liquid Effluents Abnormal Release Summary Unit 1 (Quarters 1,2,3, and 4) 31 Table 1-6B Liquid Effluents Abnormal Release Summary Unit 2 (Quarters 1,2,3, and 4) 32 Table 1-6C Liquid Effluents Abnormal Release Summary Site (Quarters 1,2,3, and 4) 33 2.0 Gaseous Effluents 34 2.1 Regulatory Requirements 34 2.1.1 Dose Rate Limits 34 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 34 Page 3 of 80

2.1.3 Doses to a Member of the Public 34 2.2 Measurements and Approximations of Total Radioactivity 35 2.2.1 Sample Collection and Analysis 35 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 36 2.2.2.1 Fission and Activation Gases 36 2.2.2.2 Radioiodines, Tritium and Particulate Releases 36 2.2.2.3 Gross Alpha Release 36 2.2.3 Total Error Estimation 37 2.3 Gaseous Effluent Release Data 38 2.4 Radiological Impact Due to Gaseous Releases 39 2.5 Gaseous Effluents - Batch Releases 39 2.6 Gaseous Effluents - Abnormal Releases 39 Table 2-1A Gaseous Effluents Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 40 Table 2-1B Gaseous Effluents Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 41 Table 2-1C Gaseous Effluents Summation of All Releases Site (Quarters 1,2,3, and 4) 42 Table 2-2A Gaseous Effluents MixedMode Releases Unit 1 (Quarters 1,2,3, and 4) 43 Table 2-2B Gaseous Effluents Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 45 Page 4 of 80

Table 2-2C Gaseous Effluents Mixed Mode Releases Site (Quarters 1,2,3, and 4) 47 Table 2-3A Gaseous Effluents Ground Level Releases Unit 1 (Quarters 1,2,3, and 49 Table 2-38 Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)

Table 2-3C Gaseous Effluents Ground Level Releases Site (Quarters 1,2,3, and 4) 53 Table 2-4A Air Doses Due to Noble Gases in Gaseous Releases Unit 1 (Quarters 1 and 4) 55 Table 2-48 Air Doses Due to Noble Gases in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 56 Table 2-4C Air Doses Due to Noble Gases Gaseous nt::'llt::'d~:II<t::'., Site (Quarters 1,2,3, and 4)

Table Doses To A Member Of The Public Due Radioiodines, Tritium, and Particulates in Gaseous Hellea=;es Unit 1 (Quarters 1,2,3, and 4) 58 Table 2-58 Doses To A Member Of The Public Due Radioiodines, Tritium, and Particulates in Gaseous (Quarters 1,2,3, and 4)

Table Doses To A Member Of The Public Due Radioiodines, Tritium, and Particulates in Gaseous Releases Site (Quarters 1,2,3, and 4) 60 Page 5 of 80

Table 2-6 Minimum Detectable Concentrations Gaseous Sample Anayses 61 Table 2-7A Gaseous Effluents - Batch Release Summary Unit 1 (Quarters 1,2,3, and 4) 62 Table 2-7B Gaseous Effluents - Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 63 Table 2-7C Gaseous Effluents - Batch Release Summary Site (Quarters 1,2,3, and 4) 64 Table 2-8A Gaseous Effluents - Abnormal Release Summary Unit 1 (Quarters 1,2,3, and 4) 65 Table 2-8B Gaseous Effluents - Abnormal Release Summary Unit 2 (Quarters 1,2,3, and 4) 66 Table 2-8C Gaseous Effluents - Abnormal Release Summary Site (Quarters 1,2,3, and 4) 67 3.0 Solid Waste 68 3.1 Regulatory Requirements 68 3.1.1 Solid Radioactive Waste System 68 3.1.2 Reporting Requirements 68 3.2 Solid Waste Data 68 Table 3-1 Solid Waste and Irradiated Fuel Shipments 69 4.0 Doses to Members of the Public Inside the Site Boundary 73 4.1 Regulatory Requirements 73 4.2 Demonstration of Compliance 73 Page 6 of 80

Table 4-1 Doses to Members of the Public Due to Activities Inside the Site Boundary 74 5.0 Total Dose 'from Uranium Fuel Cycle (40CFR190) 76 5.1 Regulatory Requirements 76 5.2 Demonstration of Compliance 76 6.0 Meteorological Data 76 7.0 Prog.ram Deviations 76 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 76 7.1.1 Regulatory Requirement 76 7.1.2 Description of Deviations 77 7.2 Tanks Exceeding Curie Content Limits 77 7.2.1 Regulatory Requirements 77 7.2.2 Description of Deviations 77 8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 78 8.1 Regulatory Requirements 78 8.2 Description of Changes 78 9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 78 9.1 Regulatory Requirements 78 9.2 Description of Major Changes 78 Appendix A Carbon-14 80 Page 7 of80

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 J.lCi/rnl 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 !lCi/ml total activity.

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

Page 8 of 80

1 Measurements and Approximations of Total Radioactivity 1.3.1 Total Radioactivity Determination Prior to the 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 tanks, which are released. Liquid radwaste analyses are performed as follows:

MEASUREMENT METHOD

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

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 flow proportional Composite counting Sr-89 & Quarterly Chemical separation Composite and gas flow proportional or scintillation counting Quarterly Chemical separation Composite and liquid scintiilation counting 90f80

1.3.1 Total Radioactivity Determination cont'd Gamma isotopic measurements are performed using germanium detectors with a resolution of 2.1 keV or lower. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and a quantitative reduction or MDC calculation is performed. This ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sarnple 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.

Page 10 of 80

1.3.2 Total Error Estimation The total or maximum error associated with the etnuent 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%

Page 11 of 80

1 Total Error Estimation cont'd

e. Volume of waste prior to dilution was calculated from indicators on the tanks and pump discharge flow and Level Indicator error 10%

Operator Interpretation of 10%

TOTAL ERROR 1

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

Flow totalizer error 10%

Operator interpretation of 10%

TOTAL ERROR 14%

g. Gross alpha, Sr-89, an additional error associated with sample compositing.

Compositing sample error 1.4 Liquid Effluent Release Data Regulatory Guide 1.21 Rev. 1 this report as Tables 1-1A, 1-18, 1-1 1-2A,1 and 1 on a quarterly basis as required by Regulatory 1 for all four quarters.

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

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

1.6 Liquid Effluents - Batch Releases Batch release information for liquid effluents is 1 for Unit 1 and Table 1-58 for Unit 2.

1 Liquid Effluents - Abnormal Releases There were no abnormal liquid Page of SO

Table l-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Summation of All Releases Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Type of Effl uent Units 1ST Ouarter 2ND Ouarter 3RD Quarter 4TH Ouarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 3.36E-03 2.S3E-02 6.03E-02 1.76E-02

2. Average diluted concentration during period uCi/mL 8.24E-10 4.49E-09 8.16E-09 2.09E-09

3. Percent of Applicable Limit  % * * *

• B. Tritium

1. Total Release Curies 2.68E+01 3.S4E+02 4.43E+02 1.67E+02

2. Average diluted Concentration during period uCi/mL 6.S8E-06 6.28E-OS S.99E-OS 1.98E-OS

3. Percent of Applicable Limit  % * * *

• C. Dissolved and Entrained Gases

1. Total Release Curies O.OOE+OO O.OOE+OO 6.00E-04 2.63E-04

2. Average diluted Concentration during period uCi/mL O.OOE+OO O.OOE+OO 8.llE-ll 3.12E-ll

3. Percent of Applicable Limit  % * * *

• D: Gross Alpha Radioactivity

1. Total Release Curies S.26E-07 S.72E-07 O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution) Liters 2.61E+07 2.98E+07 3.03E+07 3.80E+07 F. Volume of Dilution Water Used Liters 4.0SE+09 S.62E+09 7.37E+09 8.40E+09

• Applicable limits are expressed in terms of dose.

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

Page 13 of 80

Table 1-18 Vogtle Generating RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 liquid - Summation Of All Rellea!ses 2

A. Activation Products

1. Total Curies 2.84E-03 1 6.S1E-03 2.

uCi/mL 6.06E-lO S.68E-1O

3. Percent of Limit  % * * *

• B.

1. Total Release Curies 1.17E+Ol 2.84E+Ol 8.28E+Ol 6.61E+Ol

2. Concentration period uCi/mL 2.92E-06 S.67E-06 1.23E-OS 8.97E-06

3. Percent of Applicable Limit  % * * *

• and Curies O.OOE+OO O.OOE+OO 7.S7E-OS S.3SE-OS diluted Concentration

1. 13E-ll Limit  % * * *

• Curies 1.01E-06 O.OOE+OO O.OOE+OO O.OOE+OO E: Waste (Pre-Dilution) Liters 1.71E+07 3.19E+07 2.8SE+07 F. Volume of Water Liters 3.99E+09 4.98E+09 6.69E+09 7.34E+09

• in terms this report.

14 80

Table l-lC Vogtle Electric Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 liquid - Summation Of All Relleaises A. Fission And Activation Products

1. Release 7.84E-02

2. '-...*'r'...

during l.S3E-09

3. Percent of Limit  % * * *

• B. Tritium

1. Total KelE!aSe

2. Averaae diluted Concentration 4.76E-06 3.60E-OS 3.73E-OS lA8E-OS Limit  % * * *

• C. and Gases

1. Total Release 6.76E-04

2. Concentration during O.OOE+OO O.OOE+OO 4.79E-ll 2.00E-ll

3. Percent of Limit  % * * *

• D: Gross Alpha Radioactivity

1. Total Release Curies S.72E-07 O.OOE+OO E: Waste Vol Liters 4.32E+07 6.23E+07 F. of Water Used Liters 8.04E+09 1.06E+1O 1.41E+lO

• limits are dose.

l-3A and 15 80

Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2012 Liquid Effluents Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Ouarter 2ND Ouarter 3 RD Ouarter 4TH Oyarter Eission & Activation Co-57 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-06 CO-SS Curies 2.63E-04 l.s2E-04 l.l1E-03 2,4sE-03 Co-60 Curies 2.04E-04 2.SsE-04 l.60E-03 6.s9E-04 Cr-s1 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.1SE-04 Fe-55 Curies 2. 12E-03 2,41E-02 2.00E-02 l.61E-03 Fe-59 Curies O.OOE+OO O.OOE+OO O.OOE+OO l.S7E-Os 1-131 Curies O.OOE+OO O.OOE+OO 2.6SE-06 O.OOE+OO 1-133 Curies O.OOE+OO O.OOE+OO 4.s7E-06 O.OOE+OO Mn-54 Curies l.09E-Os s.s7E-06 l.s7E-03 3.S4E-Os Ni-63 Curies O.OOE+OO O.OOE+OO 1.70E-03 1.02E-03 Sr-S9 Curies 9.36E-Os 3.04E-Os 1.76E-Os O.OOE+OO Sr-90 Curies O.OOE+OO O.OOE+OO 4.19E-06 O.OOE+OO Cs-134 Curies 6.22E-Os l.lSE-04 2.SsE-04 3,49E-Os Cs-137 Curies 2.17E-04 4,49E-04 l.12E-03 4,47E-04 Eu-152 Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.93E-06 Ru-10s Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-05 Sb-124 Curies O.OOE+OO O.OOE+OO O.OOE+OO l.sOE-Os Sb-125 Curies 3.92E-04 l.67E-04 s.61E-03 6.0sE-03 Sb-126 Curies O.OOE+OO l.s7E-06 O.OOE+OO O.OOE+OO Te-12sM Curies O.OOE+OO O.OOE+OO 2.73E-02 s.03E-03 Total For Period Curies 3.36E-03 2.S3E-02 6.03E-02 1.76E-02 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations Page 16 of 80

1-2A Electric Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 1

l-Jan- Ending: 31-Dec-2012 Batch 1ST 2ND 3RD 4TH

---

=--

Tritium nic:cnlv~.rI And 11="",...."',"""'....

Xe-133 Curies O.OOE+OO O.OOE+OO 2.63E-04 Xe-13S Curies O.OOE+OO O.OOE+OO O.OOE+OO Total For Period O.OOE+OO O.OOE+OO 6.00E-04 2.63E-04 Gross Alpha Ra'lllo'aC1:IVlity Curies S.26E-07 S.72E-07 O.OOE+OO Zeroes in this no at deb~ctclble levels. See typical minimum rlol".~", concentrations.

80

Table 1-2A RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 liquid Effluents Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Units 1ST Fi~:s:itlln &. Products No O.OOE+OO O.OOE+OO H-3 Curies 1.07E-Ol FntrainAti Gases Curies O.OOE+OO Curies O.OOE+OO 9.97E-OS O.OOE+OO

• Zeroes in no radioactivity was at del:edtable levels. See minimum detectable concentrations.

18

Nuclides Kelealsea FISiSlcm & Activation Co-58 Fe-55 Mn-54 Ni-63 Sr-89 Sr-90 W-187 Cs-134 Cs-137 Sb-125 Total For Period H-3 Dissolved And Xe-133 for Period Gross Alpha Ra!Clloaa:lvI1ty Curies 1.01E-06 O.OOE+OO O.OOE+OO in this indicates that no In:::lrmmv was at detectab See 1-4 for minimum detecta concentrations.

19

Vogtle Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: 2 Starting: 1-Jan 31-Dec-2012 Continuous Mode NUCU(leS Released Units 1ST Fission &. Activation Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 3.99E-02 1.23E-01 7.47E-02 IFntrM'tinpri Gases Curies O.OOE+OO Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-57 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-06 Co-58 Curies 3.S8E-04 1.60E-04 1.82E-03 3.16E-03 Co-60 Curies 2.81E-04 2.99E-04 1.92E-03 1. 13E-03 Cr-S1 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.18E-04 Fe-55 Curies 4.27E-03 2.69E-02 2.60E-02 1.77E-03 Fe-59 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.87E-OS 1-131 Curies O.OOE+OO O.OOE+OO 2.68E-06 O.OOE+OO 1-133 Curies O.OOE+OO O.OOE+OO 4.S7E-06 O.OOE+OO Mn-S4 Curies 1.09E-OS S.S7E-06 1.69E-03 3.84E-OS Ni-63 Curies O.OOE+OO O.OOE+OO 1.70E-03 1.41E-03 Sr-89 Curies 9.nE-OS 4.34E-OS 2.7SE-OS O.OOE+OO Sr-90 Curies O.OOE+OO 1.29E-06 4.19E-06 O.OOE+OO W-187 Curies O.OOE+OO O.OOE+OO 2.86E-OS O.OOE+OO Cs-134 Curies 7.63E-OS 1.24E-04 3.S1E-04 9.S9E-OS Cs-137 Curies 2.68E-04 4.69E-04 1.4SE-03 7.S6E-04 Eu-1S2 Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.93E-06 Ru-10S Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-OS Sb-124 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.S0E-OS Sb-12S Curies 4.18E-04 1.84E-04 6.63E-03 6.S4E-03 Sb-126 Curies O.OOE+OO 1.S7E-06 O.OOE+OO O.OOE+OO Te-12SM Curies O.OOE+OO O.OOE+OO 3.68E-02 8.9SE-03 Total For Period Curies S.78E-03 2.82E-02 7.84E-02 2.41E-02

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

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2C Page 21 of 80

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 3.84E+01 3.83E+02 5.26E+02 2.33E+02 Dissolved And Entrained Gases Xe-133 Curies O.OOE+OO O.OOE+OO 6.72E-04 3.17E-04 Xe-135 Curies O.OOE+OO O.OOE+OO 3.78E-06 O.OOE+OO Total For Period Curies O.OOE+OO O.OOE+OO 6.76E-04 3.17E-04 Gross Alpha Radioactivity G-Alpha Curies 1.53E-06 5.72E-07 O.OOE+OO O.OOE+OO

• 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 80

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 1.38E-01 2.03E-01 1.86E-01 1.23E-01 Dissolved and Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• 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 80

Table 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses to a member of the public due to Liquid Releases Unit: Unit 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Ouarter Oraan ODCM Lmt Units 1ST Otr %ODCM 2ND Otr %ODCM 3RD Otr %ODCM 4TH Otr %ODCM Bone 5.00E+00 mRem 1.37E-03 2.73E-02 3.66E-03 7.32E-02 1.16E-02 2.33E-01 5.44E-03 1.09E-01 GI-Lli 5.00E+00 mRem 5.90E-04 1. 18E-02 9.48E-03 1.90E-01 1.69E-02 3.38E-01 9.01E-03 1.80E-01 Kidney 5.00E+00 mRem 1. 14E-03 2.28E-02 1.09E-02 2.19E-01 1.95E-02 3.90E-01 8.68E-03 1.74E-01 Liver 5.00E+00 mRem 2.51E-03 5.01E-02 1.46E-02 2.91E-01 2.44E-02 4.87E-01 1.07E-02 2.15E-01 Lung 5.00E+00 mRem 1.40E-03 2.80E-02 1.02E-02 2.04E-01 2.22E-02 4.44E-01 2.83E-02 5.66E-01 Thyroid 5.00E+00 mRem 4.55E-04 9.10E-03 9.20E-03 1.84E-01 1.04E-02 2.09E-01 4.99E-03 9.98E-02 Total Body 1.50E+00 mRem 1.89E-03 1.26E-01 1.28E-02 8.57E-01 1.97E-02 1.31E+00 8.77E-03 5.85E-01 Cumulative Doses per Year Oraan ODCM Lmt Units Year to Ending Date %ODCM Receptor Limit Bone 1.00E+01 mRem 2.21E-02 2.21E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 3.60E-02 3.60E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 4.02E-02 4.02E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 5.22E-02 5.22E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 6.21E-02 6.21E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 2.51E-02 2.51E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+00 mRem 4.32E-02 1.44E+00 Maximum Individual Liquid Liquid Effluent TB Annual Page 24 of 80

Table 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Ouarter OrQan ODCM Lmt Units 1ST Otr %ODCM 2ND Otr %ODCM 3RD Otr %ODCM 4TH Otr %ODCM Bone S.OOE+OO mRem 4.66E-04 9.32E-03 1.22E-04 2,44E-03 3.32E-03 6.64E-02 2.79E-03 S.SSE-02 GI-Lli S.OOE+OO mRem 3.23E-04 6,46E-03 3.SSE-04 7.71E-03 4.10E-03 S.19E-02 2,4SE-03 4.90E-02 Kidney S.OOE+OO mRem S.09E-04 1.02E-02 4.20E-04 S.39E-03 S.14E-03 1.03E-Ol 3,44E-03 6.S7E-02 Liver S.OOE+OO mRem 9.7SE-04 1.96E-02 S.2SE-04 1.06E-02 6.39E-03 1.2SE-Ol S.22E-03 1.04E-Ol Lung S.OOE+OO mRem 4.2SE-04 S.SOE-03 4.14E-04 8.29E-03 4.72E-03 9,44E-02 2.97E-03 S.93E-02 Thyroid S.OOE+OO mRem 2.S3E-04 S.66E-03 3.72E-04 7,43E-03 2.09E-03 4.18E-02 1.60E-03 3.20E-02 Total Body l.S0E+OO mRem 7.61E-04 S.07E-02 4.77E-04 3.1SE-02 4.9SE-03 3.30E-Ol 4.06E-03 2.71E-Ol Cumulative Doses per Year QrQan ODCM Lmt Units Year to Ending Date %ODCM Receptor Limit Bone 1.00E+Ol mRem 6.70E-03 6.70E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI -Lli 1.00E+Ol mRem 7.2SE-03 7.2SE-02 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+Ol mRem 9.S0E-03 9.50E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 1.31E-02 1.31E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+Ol mRem S.S2E-03 8.S2E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 4.3SE-03 4.3SE-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+OO mRem 1.02E-02 3,42E-Ol Maximum Individual Liquid Liquid Effluent TB Annual Page 25 of 80

1-3C Vogtle Electric I£..... n ... lra RADIOACTIVE EffLUENT RELEASE REPORT - 2012 Doses to a member of public to liquid Releases Site l-lan- 2012

%ODCM Bone S.OOE+OO mRem 3.67E-02 3.78E-03 7.56E-02 l.S0E-02 2.99E-Ol 8.23E-03 1.6SE-Ol S.OOE+OO mRem 9.12E-04 1.82E-02 9.86E-03 1.97E-Ol 2.10E-02 4.20E-Ol 2.29E-Ol S.OOE+OO mRem 1.6SE-03 3.30E-02 1. 14E-02 2.27E-Ol 2.46E-02 4.93E-Ol 2.42E-Ol Liver S.OOE+OO mRem 3.49E-03 6.97E-02 3.02E-Ol 6.1SE-Ol 3.19E-Ol mRem 1.06E-02 2.69E-02 6.2SE-Ol 5.00E+OO mRem 7.38E-04 1.48E-02 1.91E-Ol 1.25E-02 2.50E-Ol 6.59E-03 1.32E-Ol l.SOE+OO mRem 2.6SE-03 l.77E-Ol 1.33E-02 2.46E-02 1.64E+OO 1. 28E-02 8.S6E-Ol Bone 1.00E+Ol mRem 2.88E-Ol Maximum Individual Liquid Organ Annual mRem 4.32E-02 4.32E-Ol Maximum Individual Liquid Organ Annual mRem 4.98E-02 4.98E-Ol Maximum Individual Oroan Annual Liver mRem 6.53E-02 Maximum mRem 7.06E-02 7.06E-Ol Maximum l.OOE+Ol mRem 2.94E-02 2.94E-Ol 1.78E+OO 26

Table 1-4 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES Starting: 1-Jan-2012 Ending: 31-Dec-2012 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIOI\JUCLIDE MDC UNITS Mn-54 2.73E-OS ~Ci/ml Fe-59 S.33E-OS ~Ci/ml Co-5S 3.7SE-OS ~Ci/ml Co-60 6.76E-OS ~Ci/ml Zn-65 1.32E-07 ~Ci/ml Mo-99 4.31E-07 ~Ci/ml Cs-134 3.06E-OS ~Ci/ml Cs-137 4.51E-OS ~Ci/ml Ce-141 6.99E-OS ~Ci/ml Ce-144 2.95E-07 ~Ci/ml 1-131 5.97E-OS ~Ci/ml Xe-133 9.11E-OS ~Ci/ml Xe-135 4.27E-OS ~Ci/ml Fe-55 1.00E-06 ~Ci/ml Sr-S9 5.00E-OS ~Ci/ml Sr-90 7.00E-09 ~Ci/ml H-3 2.00E-06 ~Ci/ml Gross Alpha 7.00E-OS ~Ci/ml Page 27 of 80

Table l-SA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Batch Release Summary Unit: 1 Starting: I-Jan- 2012 Ending: 31-Dec-2012 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 7 16 23 19 65

2. Total time period for Batch releases ( Minutes) 1. 72E+03 7.S3E+03 8.51E+03 6.03E+03 2.38E+04

3. Maximum time period for a batch ( Minutes) 3.71E+02 4.57E+02 1. llE+03 3.71E+02 1. llE+03

4. Average time period for a batch ( Minutes) 2.46E+02 2.58E+02 3.75E+02 2.51E+02 3.24E+02

5. Minimum time period for a batch ( Minutes) 5.70E+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 ) 4632 4402 4862 4196 4523

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

Page 28 of 80

Table l-sB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Batch Release Summary Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 3 1 5 6 15

2. Total time period for Batch releases ( Minutes) 8.13E+02 3.03E+02 2.45E+03 1.66E+03 5.23E+03

. 3. Maximum time period for a batch ( Minutes) 5.38E+02 3.03E+02 7.60E+02 4.86E+02 7.60E+02

4. Average time period for a batch ( Minutes) 2.71E+02 3.03E+02 4.90E+02 2.77E+02 3.48E+02

5. Minimum time period for a batch ( Minutes) 1.28E+02 3.03E+02 3.39E+02 7.40E+01 7.40E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 4632 4402 4862 4196 4523

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

Page 29 of 80

Table 1-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Batch Release Summary Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 10 17 28 25 80

2. Total time period for Batch releases ( Minutes) 2.54E+03 7.84E+03 1.10E+04 7.69E+03 2.90E+04

3. Maximum time period for a batch ( Minutes) 5.38E+02 1.01E+03 9.97E+02 8.60E+02 1.01E+03

4. Average time period for a batch ( Minutes) 2.54E+02 4.61E+02 3.92E+02 3.08E+02 3.63E+02

5. Minimum time period for a batch ( Minutes) 5.70E+01 8.60E+01 6.70E+01 7AOE+01 5.70E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 4632 4402 4862 4196 4523

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

Page 30 of 80

Table 1-6A Vogtle Electric r.ll'llrlll'llr::!II"'

RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Effluents - Abnormal Release Unit: 1 Starting: l-Jan- 2012 Year of Releases 0 0

2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 31 80

Table 1-68 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 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) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 32 of 80

Table 1-6C Vogtle Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Liquid Effluents - Abnormal Summary Unit: Site starting: l-Jan- 2012 31-Dec-2012 Units 1ST 4TH Year Totals

--~---

o 0 0

2. Total Time For All ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum Time For A ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO

4. Time For A ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

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

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

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

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

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

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

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

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

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

Page 34 of 80

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 aDCM limits for each release for the current quarter and year.

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

Page 35 of80

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 36 of 80

2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement wi" 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 MOC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non steady release rates 10%

TOTAL ERROR 54%

Page 37 of80

Total Estimation cont'd

d. Total tritium were calculated from sample analysis results and release point flow Water vapor in sample stream determination 10%

Vent flow 10%

Counting calibration and statistics 10%

Non-steady release 10%

TOTAL ERROR 20%

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

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non Steady release rates 10%

TOTAL ERROR 55%

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

To complete table 2-1A, and 2-1 the total release for each of the four categories (fission and activation iodines, particulates, and tritium) was divided by the number of seconds in quarter to obtain a rate in

!-lCi/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 of dose. Noble gases are limited as specified in aDCM 3.1.2. The three (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 1 Dose 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 for this reporting period.

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

Limits for cumulative beta and gamma air due to noble are specified in ODCM 3.1 Cumulative air are presented in Table 2-4A, and 2-4B along with the percent ODCM limits.

38 80

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 To support Dry Cask Storage on plant site, a cask crane replacement took place in the Auxiliary Building. This required a 4' x 5' hole to be cut on the roof of the building. When the Railroad Bay Doors and Penetration were open simultaneously, this caused a release from the building. Temporary equipment was setup to collect samples and quantify activity released through Gaseous Effluent permits.

Page 39 of 80

Table 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: I-Jan- 2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies S.33E-02 S.S7E-02 S.9SE-Ol 3.6SE-02

2. Average Release rate for period uCi/sec 6.76E-03 7.07E-03 7.SSE-02 4.63E-03

3. Percent of Applicable Limit  % * * *

• B. Radioiodines

1. Total Iodine-131 Curies O.OOE+OO O.OOE+OO S.94E-06 O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+OO O.OOE+OO 1. 13E-06 O.OOE+OO

3. Percent of Applicable Limit  % * * *

• C. Particulates

1. Particulates ( Half-Lives > S Curies 1. 13E-07 2.S1E-07 2.29E-07 4.19E-OB

2. Average Release rate for period uCi/sec 1,44E-OS 3.1SE-OB 2.90E-OB S.32E-09

3. Percent of Applicable Limit  % * * *

• D. Tritium

1. Total Release Curies 2.30E+Ol 1.01E+Ol 6.B2E+OO 6.72E+OO

2. Average Release rate for period uCi/sec 2.92E+OO 1.2SE+OO S.6SE-Ol B.S3E-Ol

3. Percent of Applicable Limit  % * * *

• E. Gross Alpha

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

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

• Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-48, 2-SA, 2-S8 of this report.

Page 40 of 80

Table 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies l.SOE-Ol l.S6E-Ol 1.04E+Ol 1.21E+Ol

2. Average Release rate for period uCi/sec 1.90E-02 2.36E-02 1.32E+00 l.S3E+00

3. Percent of Applicable Limit  % * * *

• B. Radioiodines

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

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

3. Percent of Applicable Limit  % * * *

• C. Particulates

1. Particulates ( Half-Lives > S Curies O.OOE+OO 2.22E-07 2.0SE-07 O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+OO 2.S2E-OS 2.61E-OS O.OOE+OO

3. Percent of Applicable Limit  % * * *

• D. Tritium

1. Total Release Curies 3.2SE+00 6.66E+00 l.S6E+00 1.21E+Ol

2. Average Release rate for period uCi/sec 4.12E-Ol SASE-Ol 2.3SE-Ol 6.S6E-02

3. Percent of Applicable Limit  % * * *

• E. Gross Alpha

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

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

• Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-46, 2-SA, 2-S6 of this report.

Page 41 of 80

Table 2-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Type of Effluent Units 1ST Ouarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.03E-Ol 2.42E-Ol 1.1OE+Ol 1.21E+Ol

2. Average Release rate for period uCi/sec 2.S7E-02 3.06E-02 1.40E+OO l.S4E+OO

3. Percent of Applicable Limit  % * * *

• B. Radioiodines

1. Total Iodine-13l Curies O.OOE+OO O.OOE+OO S.94E-06 O.OOE+OO

2. Average Release rate for period uCi/sec O.OOE+OO O.OOE+OO 1. 13E-06 O.OOE+OO

3. Percent of Applicable Limit  % * * *

• C. Particulates

1. Particulates ( Half-Lives> S Curies 1.13E-07 4.73E-07 4.34E-07 4.l9E-OS

2. Average Release rate for period uCi/sec 1.44E-OS 6.00E-OS S.SlE-OS S.32E-09

3. Percent of Applicable Limit  % * * *

• D. Tritium

1. Total Release Curies 2.63E+Ol 1.6SE+Ol S.6SE+OO 7.26E+OO

2. Average Release rate for period uCi/sec 3.33E+OO 2.13E+OO l.l0E+OO 9.21E-Ol

3. Percent of Applicable Limit * * *

• E. Gross Alpha

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

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

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

Page 42 of 80

Table 2-2A Vogtle Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Mode Releases Unit: 1 Starting: l-Jan- 2012 Continuous Mode Nuclides ReBealsea Units 1ST 1I"11Iii;1I;;1£1ln Gases No Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines 1-131 For Period Co-58 Curies O.OOE+OO L08E-07 Curies 1. 13E-07 L21E-07 4. 19E-08 For Period 1.13E-07 2.S0E-07 2.29E-07 4.19E-08 Tritium H-3 Curies 2.30E+Ol Curies O.OOE+OO O.OOE+OO If Not Nuclide is Not Reported.

Zeroes in this lnalcates no was present at levels.

See Table 2-6 for minimum de1tectz concentrations.

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-4l Curies S.33E-02 S.S7E-02 S.92E-Ol 3.6SE-02 Total For Period Curies S.33E-02 S.S7E-02 S.92E-Ol 3.6SE-02 Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 4.24E-02 lAOE-Ol 1.8SE-Ol 1.2SE-Ol Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Kr-8SM Curies O.OOE+OO O.OOE+OO 9.46E-02 1.10E-Ol Xe-133 Curies O.OOE+OO O.OOE+OO 4.7SE+OO S.S2E+OO Xe-13S Curies O.OOE+OO O.OOE+OO S.37E+OO 6.24E+OO Total For Period Curies O.OOE+OO O.OOE+OO 1.02E+Ol 1.19E+Ol Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates Sr-89 Curies O.OOE+OO 1.91E-07 1.87E-07 O.OOE+OO Sr-90 Curies O.OOE+OO 3.13E-08 1.86E-08 O.OOE+OO Total For Period Curies O.OOE+OO 2.22E-07 2.0SE-07 O.OOE+OO nitium H-3 Curies 3.21E+OO 6.63E+OO l.77E+OO 2.30E-Ol Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.62E-02 2.43E-02 2.8SE-02 3.28E-02 Xe-133M Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.S7E-04 Xe-133 Curies 1.21E-Ol 1.60E-Ol 1.91E-Ol 1.97E-Ol Xe-13S Curies 2.12E-03 1.86E-03 2.02E-03 2.82E-03 Total For Period Curies 1.S0E-Ol 1.86E-Ol 2.22E-Ol 2.33E-Ol lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 3.38E-02 3.23E-02 8.23E-02 3.11E-Ol Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2*2C Electric Plant RADIOACTIVE EffLUENT RELEASE REPORT - 2012 GaseolJs - Mixed Mode Level Releases Unit:

I-Jan- 2012 31-Dec-2012 Continuous Nuclides Units fission Gases Curies O.OOE+OO O.OOE+OO 9.46E-02 1.10E-Ol Xe-133 Curies O.OOE+OO O.OOE+OO S.S2E+OO Xe-135 Curies O.OOE+OO O.OOE+OO S.37E+OO Total for Period Curies O.OOE+OO O.OOE+OO 1.02E+Ol lodines for Period Co-5S Curies O.OOE+OO 1.0SE-07 O.OOE+OO Sr-S9 Curies 1. 13E-07 4.41E-07 3.07E-07 4. 19E-OS Sr-90 Curies O.OOE+OO 3.13E-OS O.OOE+OO Total for Period Curies l.l3E-07 4.73E-07 4.34E-07 4.19E-OB H-3 Curies 2.62E+Ol 1.66E+Ol S.38E+OO 6.83E+OO Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detl~ed, is Not Zeroes in no was present at detecta levels.

See Table 2-6 minimum concentrations.

of 80

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Fission Gases Ar-41 Curies 7.9SE-02 8.00E-02 6.20E-Ol 6.93E-02 Xe-133M Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.S7E-04 Xe-133 Curies 1.21E-Ol 1.60E-Ol 1.91E-Ol 1.97E-Ol Xe-13S Curies 2.12E-03 1.86E-03 2.02E-03 2.82E-03 Total For Period Curies 2.03E-Ol 2.42E-Ol S.14E-Ol 2.70E-Ol Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates Sr-89 Curies O.OOE+OO 4.9SE-ll O.OOE+OO O.OOE+OO O.OOE+OO 4.9SE-ll O.OOE+OO O.OOE+OO Total For Period Tritium H-3 Curies 7.62E-02 1. 72E-O 1 2.67E-Ol 4.36E-Ol Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+OO O.OOE+OO 3.S2E-03 O.OOE+OO Total For Period Curies O.OOE+OO O.OOE+OO 3.S2E-03 O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates Sr-89 Curies O.OOE+OO 1.20E-ll O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO 1.20E-U O.OOE+OO O.OOE+OO Tritium H-3 Curies O.OOE+OO 1.42E-03 2.64E-02 8.19E-04 Gross AI~ha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-38 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies O.OOE+OO O.OOE+OO 2.84E-03 3.0SE-03 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Ground Level Releases Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Pa rticu lates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effl uents - Ground Level Releases Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+OO O.OOE+OO 3.52E-03 O.OOE+OO Total For Period Curies O.OOE+OO O.OOE+OO 3.S2E-03 O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates Sr-89 Curies O.OOE+OO 1.20E-ll O.OOE+OO O.OOE+OO Total For Period O.OOE+OO 1.20E-ll O.OOE+OO O.OOE+OO Tritium H-3 Curies O.OOE+OO 1.42E-03 2.64E-02 8.19E-04 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 80

-~~

Table 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Release Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Type of Radiation ODCM Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Gamma Air S.OOE+OO mRad 7.27E-06 1.4SE-04 7.S9E-06 1.S2E-04 8.33E-OS 1.67E-03 4.98E-06 9.9SE-OS Beta Air 1.00E+01 mRad 2.S6E-06 2.S6E-OS 2.68E-06 2.68E-OS 2.94E-OS 2.94E-04 1.7SE-06 1.7SE-OS Cumulative Doses Per Year Type of Radiation ODCM Unit Year to End 0/0 ODCM ...;;..R;;.;;e;..;;ce~pt.;;.;o;;.;;r_ _ _ _ _ _ _ __ limit Gamma Air 1.00E+01 mRad 1.03E-04 1.03E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.00E+01 mRad 3.64E-OS 1.82E-04 Site Boundary / Child Air Dose Beta Annual 1.21 Page 55 of 80

Table 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Release Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Type of Radiation ODCM Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Gamma Air S.OOE+OO mRad 4.2SE-06 8.S0E-OS 4.19E-06 8.38E-OS 1.82E-04 3.64E-03 2.12E-04 4.23E-03 Beta Air 1.00E+Ol mRad 3.20E-06 3.20E-OS 3.69E-06 3.69E-OS 2.74E-04 2.74E-03 3.18E-04 3.18E-03 Cumulative Doses Per Year Type of Radiation ODCM Unit Year to End 0/0 ODCM _R_e_c...;;..eL..pt....;o'-r_ _ _ _ _ _ _ __ Limit Gamma Air 1.00E+Ol mRad 4.02E-04 4.02E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.00E+Ol mRad S.98E-04 2.99E-03 Site Boundary / Child Air Dose Beta Annual 1.21 Page 56 of 80

Table 2-4C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Air Doses Due to Gaseous Release Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Type of Radiation ODCM Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Gamma Air S.OOE+OO mRad 1.1SE-OS 2.30E-04 1.18E-OS 2.36E-04 2.66E-04 S.31E-03 2.17E-04 4.33E-03 Beta Air 1.00E+01 mRad S.76E-06 S.76E-OS 6.37E-06 6.37E-OS 3.03E-04 3.03E-03 3.19E-04 3.19E-03 Cumulative Doses Per Year Type of Radiation ODCM Unit Year to End %ODCM Receptor Limit Gamma Air 1.00E+01 mRad S.OSE-04 S.OSE-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.00E+01 mRad 6.3SE-04 3.17E-03 Site Boundary / Child Air Dose Beta Annual 1.21 Page 57 of 80

Table 2-SA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Bone 7.S0E+00 mRem 1.33E-07 1.7SE-06 2.9SE-07 3.93E-06 1.94E-07 2.S9E-06 4.93E-OS 6.S7E-07 GI-Lli 7.S0E+00 mRem 4.9SE-04 6.64E-03 2. 19E-04 2.92E-03 1.S0E-04 2.00E-03 1.4SE-04 1.94E-03 Kidney 7.S0E+00 mRem 4.9SE-04 6.64E-03 2. 19E-04 2.92E-03 1.S0E-04 2.00E-03 1.4SE-04 1.94E-03 Liver 7. SOE +00 mRem 4.9SE-04 6.64E-03 2. 19E-04 2.92E-03 1.S0E-04 2.00E-03 1.4SE-04 1.94E-03 Lung 7.S0E+00 mRem 4.9SE-04 6.64E-03 2.19E-04 2.92E-03 1.S0E-04 2.00E-03 1.4SE-04 1.94E-03 Thyroid 7.S0E+00 mRem 4.9SE-04 6.64E-03 2.19E-04 2.92E-03 1.6SE-04 2.00E-03 1.4SE-04 1.94E-03 Total Body 7.S0E+00 mRem 4.9SE-04 6.64E-03 2.19E-04 2.92E-03 1.S0E-04 2.00E-03 1.4SE-04 1.94E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date O/oODCM Rece~tor Limit Bone 1.S00E+01 mRem 6.71SE-07 4.977E-06 Maximum Individual/Child Iodine/Part Dose Annual 1.2 GI-Lli 1.S00E+01 mRem 1.012E-03 1.S34E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Kidney 1.S00E+01 mRem 1.012E-03 1.S34E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Liver 1.S00E+01 mRem 1.012E-03 1.S34E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Lung 1.S00E+01 mRem 1.012E-03 1.S34E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Thyroid 1.S00E+01 mRem 1.027E-03 6.S47E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Total Body 1.S00E+01 mRem 1.012E-03 1.S34E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Page 58 of 80

Table2-SB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Bone 7.S0E+OO mRem O.OOE+OO O.OOE+OO 1.47E-06 1.96E-OS 9.SSE-07 1.28E-OS O.OOE+OO O.OOE+OO GI-L1i 7.S0E+OO mRem 7.02E-OS 9 .36E-04 1.44E-04 1.92E-03 4.01E-OS S.3SE-04 1. 17E-OS 1.S6E-04 Kidney 7.S0E+OO mRem 7.02E-OS 9 .36E-04 1.44E-04 1.92E-03 4.01E-OS S.3SE-04 1. 17E-OS 1.S6E-04 Liver 7.S0E+OO mRem 7.02E-OS 9.36E-04 1.44E-04 1.92E-03 4.01E-OS S.3SE-04 1. 17E-OS 1.S6E-04 Lung 7.S0E+OO mRem 7.02E-OS 9.36E-04 1.44E-04 1.92E-03 4.01E-OS S.3SE-04 1. 17E-OS 1.S6E-04 Thyroid 7.S0E+OO mRem 7.02E-OS 9.36E-04 1.44E-04 1.92E-03 4.01E-OS S.3SE-04 1. 17E-OS 1.S6E-04 Total Body 7.S0E+OO mRem 7.02E-OS 9.36E-04 1.44E-04 1.92E-03 4.03E-OS S.37E-04 1. 17E-OS 1.S6E-04 Cumulative Doses per Year Organ ODCM Units Year to Ending Date %ODCM Rece~tor Limit Bone 1.S00E+Ol mRem 1.616E-OS 1.616E-OS Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-L1i 1.500E+Ol mRem 2.661E-04 1.774E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.S00E+Ol mRem 2.660E-04 1.773E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.S00E+Ol mRem 2.660E-04 1.773E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.S00E+Ol mRem 2.660E-04 1.773E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.S00E+Ol mRem 2.660E-04 1.773E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.S00E+Ol mRem 2.66SE-04 1.777E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 59 of 80

Table 2-SC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM Bone 7.S0E+OO mRem 1.33E-07 1.7BE-06 1.76E-06 2.3SE-OS 1.1SE-06 1.S4E-OS 4.93E-OB 6.S7E-07 GI-Lli 7.S0E+OO mRem S.6BE-04 3.63E-04 3.63E-04 4.B4E-03 1.90E-04 2.S3E-03 1.S7E-04 2.09E-03 Kidney 7.S0E+OO mRem S.6BE-04 3.63E-04 3.63E-04 4.B4E-03 1.90E-04 2.S3E-03 1.S7E-04 2.09E-03 Liver 7.S0E+OO mRem S.6BE-04 3.63E-04 3.63E-04 4.B4E-03 1.90E-04 2.S3E-03 1.S7E-04 2.09E-03 Lung 7.S0E+OO mRem S.6BE-04 3.63E-04 3.63E-04 4.B4E-03 1.90E-04 2.S3E-03 1.S7E-04 2.09E-03 Thyroid 7.S0E+OO mRem S.6BE-04 3.63E-04 3.63E-04 4.B4E-03 2.0SE-04 2.74E-03 1.S7E-04 2.09E-03 Total Body 7.S0E+OO mRem S.6BE-04 3.63E-04 3.63E-04 4.B4E-03 1.90E-04 2.S3E-03 1.S7E-04 2.09E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date O/oODCM Rece~tor Limit Bone 1.S00E+01 mRem 7.46SE-07 4.977E-06 Maximum Individual/Child Iodine/Part Dose Annual 1.21 GI-Lli 1.S00E+01 mRem B.909E-04 S.939E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.21 Kidney 1.S00E+01 mRem B.90BE-04 S.939E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.21 Liver 1.S00E+01 mRem B.90BE-04 S.939E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.21 Lung 1.S00E+01 mRem B.90BE-04 S.939E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.21 Thyroid 1.S00E+01 mRem B.90BE-04 S.939E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.21 Total Body 1.S00E+01 mRem B.909E-04 S.939E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.21 Page 60 of 80

Table 2-6 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 MINIMUM DE"rECTABLE CONCENTRATIONS GASEOUS SAMPLE ANALYSES Starting: 1-lan-2012 Ending: 31-Dec-2012 RADIONUCLIDE MDC UNITS Kr-S7 l.S2E-OS IlCi/ml Kr-SS 2.s3E-OS IlCi/ml Xe-133 2.0sE-OS IlCi/ml Xe-133m S.63E-OS IlCi/ ml Xe-13s 7.12E-OS IlCi/ml Xe-13S 1.0sE-07 IlCi/ ml 1-131 7.93E-1s* IlCi/ml Mn-s4 3.94E-14* IlCi/ml Fe-59 2.4sE-14* IlCi/ml Co-ss 1.39E-14* IlCi/ml Co-60 1.7sE-14* IlCi/ml Zn-6s 2.S2E-14* IlCi/ ml Mo-99 9.s7E-14* IlCi/ml Cs-134 1.12E-14* IlCi/ ml Cs-137 S.71E-1s* IlCi / ml Ce-141 S.62E-1s* IlCi/ ml Ce-144 2.77E-14* IlCi/ml Sr-S9 1.00E-13 IlCi/ ml Sr-90 1.00E-13 IlCi/ml H-3 9.00E-OB Il Ci/ ml Gross Alpha 1.00E-13 IlCi/ml

• Based on an estimated sample volume of s.7E+OS mls for particulate filters and charcoal cartridges.

Page 61 of 80

Table 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 28 30 36 33 127

2. Total time period for batch releases ( Minutes) 2.07E+03 2.07E+03 2.20E+04 1. 17E+04 3.78E+04

3. Maximum time period for a batch ( Minutes) 3.25E+02 2.23E+02 7.35E+03 5.44E+03 7.35E+03

4. Average time period for a batch ( Minutes) 7.38E+01 6.90E+01 6.10E+02 3.54E+02 2.97E+02 S. Minimum time period for a batch ( Minutes) 1.30E+01 1.90E+01 1.40E+01 8.00E+00 8.00E+00 Page 62 of 80

Table 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 16 14 13 18 61

2. Total time period for batch releases ( Minutes) 9.80E+02 8.83E+02 8.11E+02 1.12E+04 1.38E+04

3. Maximum time period for a batch ( Minutes) 1.37E+02 1.21E+02 2.44E+02 l.OOE+04 l.OOE+04

4. Average time period for a batch ( Minutes) 6.13E+01 6.31E+01 6.24E+01 6.20E+02 2.27E+02

5. Minimum time period for a batch ( Minutes) l.SOE+01 2.90E+01 3.00E+01 3.70E+01 l.SOE+01 Page 63 of 80

Table 2-7C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Batch Release Summary Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 44 44 49 51 188

2. Total time period for batch releases ( Minutes) 3.05E+03 2.95E+03 2.28E+04 2.29E+04 5.16E+04

3. Maximum time period for a batch ( Minutes) 3.25E+02 2.23E+02 7.35E+03 l.OOE+04 l.OOE+04

4. Average time period for a batch ( Minutes) 6.92E+Ol 6.71E+Ol 4.65E+02 4.48E+02 2.75E+02 S. Minimum time period for a batch ( Minutes) 1.30E+Ol 1.90E+Ol 1.40E+Ol 8.00E+OO 8.00E+OO Page 64 of 80

Table 2-SA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: l-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 3 0 0 3

2. Total Time For All Releases ( Minutes) O.OOE+OO 4.29E+02 O.OOE+OO O.OOE+OO 4 .29E+02

3. Maximum Time For A Release ( Minutes) O.OOE+OO 2.23E+02 O.OOE+OO O.OOE+OO 2.23E+02

4. Average Time For A Release ( Minutes) O.OOE+OO 1.43E+02 O.OOE+OO O.OOE+OO 1.43E+02

5. Minimum Time For A Release ( Minutes) O.OOE+OO 8.00E+Ol O.OOE+OO O.OOE+OO 8.00E+Ol

6. Total activity for all releases ( Curies) O.OOE+OO 4 .29E-03 O.OOE+OO O.OOE+OO 4 .29E-03 Page 65 of80

Table 2-88 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: l-Jan- 2012 Ending: 31-Dec-2012 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+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

6. Total activity for all releases ( Curies ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 66 of 80

Table 2-8C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Gaseous Effluents - Abnormal Release Summary Unit: Site Starting: l-Jan- 2012 Ending: 31-Dec-2012 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 3 0 0 3

2. Total Time For All Releases ( Minutes) O.OOE+OO 4.29E+02 O.OOE+OO O.OOE+OO 4.29E+02

3. Maximum Time For A Release ( Minutes) O.OOE+OO 2.23E+02 O.OOE+OO O.OOE+OO 2.23E+02

4. Average Time For A Release ( Minutes) O.OOE+OO 1.43E+02 O.OOE+OO O.OOE+OO 1.43E+02

5. Minimum Time For A Release ( Minutes) O.OOE+OO 8.00E+Ol O.OOE+OO O.OOE+OO 8.00E+Ol

6. Total activity for all releases ( Curies) O.OOE+OO 4.29E-03 O.OOE+OO O.OOE+OO 4.29E-03 Page 67 of 80

3.0 Solid Waste 3.1 Regulatory Requirements aDCM requirements ....."',.,."'.. . 1'1'.1"1 in this section are stated Unit 1 Unit

.1 Solid Radioactive Waste System 10.2.1 Process Control Program Radioactive wastes shall or dewatered in accordance with to meet shipping and transportation requirements during transit and requirements when received disposal site.

3.1 Reporting Requirements 1 1 states in part:

The Radioactive Effluent submitted in accordance with Specification 5.6.3, shall of the quantities of solid

"':::;ct,:>",u from the units, as Guide 1.21 Rev 3.2 Solid Waste Data Regulatory Guide 1.21 3 is found in this report as Table

Table Vogtle Electric Plant RADIOACTIVE EffLUENT AND WASTE DISPOSAL REPORT - 2012 WASTE AND IRRADIATED SHIPMENTS Units 1 and 2 1 4 JANUARY 1, 2012 THROUGH JUNE 30, 2012 Regulatory Guide 1.21 Effluent and Waste Disposal Semi-Annual Report of and Irradiated Fuel Shipments PERIOD COVERED: ,_ _ _~~,-=-_ _ _ _ _ _ TO: _--"'-'~""'"""--_ _ _ _ _ FOR UNIT: ""-"!.J~""-""'-"'-_

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

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

a. Spent resins, filter evaporator m3 6.38EOI 25 bottoms, etc. Ci 6,40Eoo 25

b. Dry compressible waste, contaminated equip. m3 I.77E02 25 etc. 25

c. Irradiated components, control rods, N/A N/A Control Rod Drive Filters N/A N/A

e. Other (describe) N/A e ui . etc, N/A

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

ISOTOPE PERCENT CURIES

a. Ni-63 45.406 2.9 Co-60 21.047 1.35 Co-58 12.757 8.16 E-l Fe-55 9.373 6.00 e-l Cs-137 3.757 2.40 E-I b Co-60 36.372 1.38 E-2 Ni-63 16.775 6.35 E-3 Fe-55 15.270 5.78 E-3 H-3 lU93 4.24 E-3 Cs-137 5.537 2,10 E-3 c N/A N/A N/A

d. N/A N/A N/A

e. N/A N/A N/A 3.

Destination 12 total Truck Energy Solutions 4 Bear Creek Road or 8 Gallaher Road B. IRRADIATED FUEL SHlPMENTS (Disposition)

Destination o N/A N/A Completed By: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date Reviewed Date Page 69 of 80

Table 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2012 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 2 of 4 JANUARY 1, 2012 THROUGH JUNE 30, 2012 ADDITIONAL INFORMATION REQUIRED BY ODCM:

ShiIpments Sent 0 Irectly

' to 0'Isposa Shipment No , Waste Type Container Shipping Class Solidification Volume Class Agent NONE ShiIpments to a Waste Processor Shipment No, Waste Type Container Solidification Processor Class Agent RVRS-12-012 A 14-170 Cask as an Radioactive NONE Energy IP-l LSA II Solutions RVRS-12-011 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-010 A IP-l Radioactive NONE Energy LSA I Solutions RVRS-12-008 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-007 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-006 A IP-I Limited NONE Energy Quantity Solutions RVRS-12-005 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-009 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-004 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-003 A IP-I Radioactive NONE Energy LSA I Solutions RVRS-12-002 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-001 A 14-170 Cask as an Radioactive NONE Energy IP-I LSA II Solutions

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

Page 70 of 80

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 2012 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 30f4 JULY 1, 2012 THROUGH DECEMBER 31, 2012 Regulatory Guide 1.21 Rev. 2: Effluent and Waste Disposal Semi-Annual Report of Solid Waste and Irradiated Fuel Shipments PERIOD COVERED: FROM :_ _----'7"-1"-C1I""20"-'1-=.2 _ _ _ _ _ _ TO: _--!I'-=21~3'-!.1!..:./2""0.!.i12"---- _ _ _ _ _ FOR UNIT: Vogtle 1& 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fu el)

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

a. Spent resins, filter sludges, evaporator m3 4.73 EOI 25 bottoms, etc. Ci 2.04 E01 25

b. Dry compressible waste, contaminated equip . m3 1.77E02 25 etc. Ci 6.09E-Ol 25

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

d. Control Rod Drive Filters m3 N/A N/A Ci N/A N/A

e. Other (descri be) m3 N/A N/A equip. etc. Ci N/A N/A

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

ISOTOPE PERCENT CURlES

a. Ni-63 54.765 1.12 EI Co-60 23.562 4.81 Cs-137 8.106 1.65 Fe-55 6.019 1.23 Cs-134 3.424 6.98 E-I b Co-60 36.773 2.24 E-I Ni-63 20.501 1.25 E-l Fe-55 14.674 8.94 E-2 H-3 11.677 7.11E-2 Co-58 9.156 5.58 E-2 c N/A N/A N/A

d. N/A N/A N/A

e. N/A N/A N/A

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 12 total Truck Energy Solutions I Barnwell 7 Bear Creek Road or 4 Gallaher Road B. IRRADIA TED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination o N/A N/A Page 71 of 80

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 2012 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 4 of4 JULY 1, 2012 THROUGH DECEMBER 31, 2012 Additional Information Required by ODCM:

Sh'Ipments Sent D'lrecUy I to D Isposa

' I Shipment No. Waste Type Container Shipping Class Solidification Volume Class Agent NONE Sh'Ipments to a Waste Processor Shipment No. Waste Type Container Shipping Class Solidification Processor Class Agent RVRS-12-024 A IP-l Radioactive NONE Energy LSA I Solutions RVRS-12-023 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-022 A 14-215 Cask as an Radioactive NONE Energy IP-l LSAII Solutions RVRS-12-021 A IP-l Radioactive NONE Energy LSA I Solutions RVRS-12-020 A IP-l Radioactive NONE Energy LSA I Solutions RVRS-12-019 A 14-170 Cask as an Radioactive NONE Energy IP-l LSA II Solutions RVRS-12-016 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-018 A 14-170 Cask as an Radioacti ve NONE Energy IP-l LSA II Solutions RVRS-12-0 17 A 14-170 Cask as an Radioactive NONE Energy IP-l LSA II Solutions RVRS-12-01S A IP-l Limited NONE Energy Quantity Solutions RVRS-12-014 A IP-l Limited NONE Energy Quantity Solutions RVRS-12-013 A IP-l Limited NONE Energy Quantity Solutions

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

Page 72 of 80

4.0 to Members of the Public inside the Site Boundary 4.1 Regulatory Requirements ODCM states in part:

"The report shall include assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC to their activities inside the SITE BOUNDARY during the report period; this be performed in accordance with Chapter 6. All assumptions in making these assessments ( i.e., activity, exposure time, and location) shall be included in the report".

4.2 Demonstration of Compliance location of concern within boundary is the Visitors Center. The at the Visitor Center consist of occasional attendance at meetings and/or short for informational purposes.

will no radiation dose at location due to radioactive liquid effluents.

Delineated in Table 4-1 for this location are values of basic data assumed in the assessment due to radioactive effluents. Listed in this table are distance and direction from a point midway between the center of Unit 1 and Unit 2 reactors, the dispersion and deposition factors for any from the plant vent (mixed mode) and from turbine building (ground level), and the estimated maximum occupancy factor for an individual and assumed age group of this individual.

source term is listed in 2-2A, and 2-2B for the mixed mode Similarly, it is listed in 2-3A and for ground level releases.

The maximum ao~;es in units of mrem to a MEMBER PUBLIC due to activities inside site boundary during reporting period are presented Table 4-1.

af80

Table 4-1 VnntlA Generating Plant RADIOACTIVE EffLUENT RELEASE REPORT Doses to a of the Public Due to Activities Inside the Site Boundary Unit: Site location Name: Center Kec:ept1or Distance (kilometers): 4A7E-Ol Sector: SE Occupancy factor:

S.93E-06 S.SSE-06 (m-2):

Noble Gas 7.12E-07 Particulate and KadlOIOdtne 6.74E-07 Units 1ST Quarter 2ND 3RD 4TH Quarter Year Bone mRem 6.64E-13 3.3SE-11 4.07E-ll 2A6E-13 7.S1E-ll Liver mRem SASE-OS 6.SSE-07 mRem 1.03E-07 6.SSE-07 3.0SE-07 1.0SE-07 SASE-OS 1.03E-07 6.SSE-07 mRem 1 1.03E-07 SASE-OS GI-Lli mRem 1.9SE-07 1 SASE-OS 6.SSE-07 NG mRem 7.66E-09 1 1.42E-07 Body Dose mRem 1.02E-06

Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2012 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: l-Jan-2012 Ending: 31-Dec-2012 Location Name: Units 3&4 Construction Distance (kilometers): 4.83E-Ol Sector: SW Occupancy Factor: 2.37E-Ol Age Group: Adult Ground Level Release Noble Gas X/Q (sec/m3): 1.81E-OS 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): 9.7SE-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 2.38E-1O 2.24E-08 2.S4E-08 8.82E-l l 4.82E-08 Liver mRem 2.44E-04 l.S6E-04 8.49E-OS 6.76E-OS S.S3E-04 Total Body mRem 2.44E-04 l.S6E-04 8.49E-OS 6.76E-OS S.S3E-04 Thyroid mRem 2.44E-04 l.S6E-04 8.S7E-OS 6.76E-OS S.S4E-04 Kidney mRem 2.44E-04 l.S6E-04 8.49E-OS 6.76E-OS S.S3E-04 Lung mRem 2.44E-04 l.S6E-04 8.49E-OS 6.76E-OS S.53E-04 GI-Ui mRem 2.44E-04 l.S6E-04 8.49E-OS 6.76E-OS S.S3E-04 NG Total Body mRem S.4SE-06 S.S6E-06 1.27E-04 1.01E-04 2.39E-04 Whole Body Dose mRem 2.S0E-04 1.62E-04 2.12E-04 1.68E-04 7.92E-04 Page 75 of 80

5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Requirements aDCM 5.1 in annual (calendar commitment to any THE PUBLIC radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to than or to mrems.

5.2 Demonstration of Compliance No dose limits stated in aDCM Sections 2.1.3, 3.1 and 1.4 were exceeded.

Therefore, compliance with 40 CFR 190 dose limits was demonstrated in accordance with requirements of aDCM Section 1 6.0 Meteorological Data aDCM 7 .2.2.2 <'~"'i',"<' in part:

The Radioactive Release Report shall an annual summary of hourly meteorological data collected over 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 or in the form of joint frequency distributions of wind speed, wind and atmospheric stability.

In lieu of with the Radioactive Effluent licensee has of retaining this summary of meteorological data on in a file that shall upon request.

7.0 Program Deviations Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation

.1 Regulatory Requirement aDCM 7.2.2.6 in part that the report shall include deviations from the liquid and '-'....'...""'""VI effluent monitoring instrumentation operability in Sections 2.1.1 and 1.1 , The report shall an explanation as to why the gaseous effluent monitoring instrumentation was specified time requirement.

Page 76 of 80

7.1 Description of Deviations inoperability of liquid and gaseous effluent monitors not corrected within the specified time for this reporting period is detailed below. When applicable, compensatory measures were utilized:

a.

This monitor was out of service for 30 because it was replaced with a new monitor. Installation started in August 2012 and was finished in November 2012. The monitor is now in service.

b.

This flow transmitter was taken out of due to failing calibration in November 2011. This transmitter delayed with repair vv...... "'*.., of the unavailability of scheduled to arrive and repair c.

flow transmitter for 1 and as a result, it was taken out of service in June 201 A replacement transmitter has not been available. Engineering is a plan for replacement. It is currently scheduled for return to in May 2013.

The mechanical seal on the sample pump failed in November 2011 .

The pump had to be refurbished which retum to service. The monitor was placed back into in August 2012.

e.

This flow transmitter was taken out of for indicating zeros during release in August 201 It was returned to service in November 201 During this time period, there was an and a new radiation monitor, 1RE-12442, was installed on Unit 1. This r"""'TnT".on resources for radiation monitor 1.

flow transmitter was taken due to failing calibration in November 2011. This flow C'n'I,.t1'to'was returned to service on May 2012.

Exceeding Curie Content Limits 7.2.1 ulatory Requirements aDeM 7.2.2.6 states in part that the report include a description of events leading to liquid holdup tanks or tanks exceeding limits of Technical Specifications 1 7.2.2 Description of Deviations Limits for outdoor liquid hold-up tanks for radioactive liquids were not exceeded during this reporting period.

for the gas storage tanks were not during this reporting 80

8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements ODCM 7.2.2.5 states in part that changes to the ODCM shall be submitted with the Radioactive Effluent Release Report. These changes may be due to changes in the radiological environmental monitoring program sampling locations as required by ODCM 4.1.1.2.3 or changes to dose calculation locations as required by ODCM 4.1.2.2.2. Land uses and dose calculation locations within five miles of VEGP must be determined by a land use census as required by ODCM 4.1.2.

8.2 Description of Changes There were no new versions released in 2012.

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 2012 assessment period.

Page 78 of 80

liquid Radwaste System Major changes liquid radwaste facilities are those that contribute to significant changes in Le., either or increases in release volume or activity/dose.

There were no to the liquid occurred during the 2012 period.

Solid Radwaste System There were no major changes to the solid radwaste systems in the 2012 assessment period.

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Appendix A VogUe ---.. ....,....",. Generating Plant CARBON-14 Carbon-14 (C-14) is a naturally-occurring with a 5730 year in the 1950s 1 significantly amount of C-14 in atmosphere.

power plants also 14, but the amount is been distributed environment weap{)ns testing nuclear plants have gaseous waste systems and fuel performance, percentages of "principal radionuclides" in effluents have changed, and 14 has become a larger percentage. "Principal radio nuclides" are determined based on public dose contribution or amount of activity compared to other radionuclides of the same type. In Revision 2 (June 2009) of 1.21 (RG 1.21), Evaluating, in Liquid Effluents Solid " the NRC "principal and reporting C-14 as In 2010 """'UIVU'-'<

virtually all U. power plants reporting C-14 amounts released and to the maximally member of the public.

C-14 is a hard:"to-detect which must effluent stream before it can measured, RG 1.21 provides the option term based on power The Electric Research Institute methodology for C-14, and published "Estimation in Nuclear liquid to quantity of C-14 in gaseous effluents was estimated to be 12.08 (per unit). Approximately 30% of the 14 released is in the form of and is incorporated into plants through photosynthesis. Ingestion from this pathway. remaining 70% is to be organic. organic and forms of C- to inhalation is the maximally individual, and is the highest Using the calculation methodology the Vogtle ODCM, the resulting bone to a child located at the be mrem a the regulatory mrem per unit) to any organ due to effluents. 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 %

regulatory limit of 15 mrem per year (per unit) total body dose due to effluents of80