ML091260689

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Annual Radioactive Effluent Release Reports for 2008
ML091260689
Person / Time
Site: Hatch, Vogtle, Farley  Southern Nuclear icon.png
Issue date: 04/27/2009
From:
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML091260689 (238)
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Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2008 Enclosure 1 Hatch Annual Radioactive Effluent Release Report for 2008

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENTRELEASES JANUARY 1, 2008 THROUGH DECEMBER 31,2008 SECTION TITLE PAGE 1.0 Liquid Effluents 1 1.1 Regulatory Requirements 1 1.1.1 Concentration Limits 1 1.1.2 Dose Limits 1 1.2 Effluent Concentration Limit 1 1.3 Measurements and Approximations of Total 2 Radioactivity for Liquid Radwaste 1.3.1 Total Radioactivity Determination for Liquid Radwaste 2 1.4 Measurements and Approximations of Total 4 Radioactivity for Groundwater Outfalls -

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

SECTION TITLE PAGE 1.10 Liquid Effluents - Abnormal Releases 7 2.0 Gaseous Effluents 27 2.1 Regulatory Requirements 27 2.1.1 Dose Rate Limits 27 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 27 2.1.3 Doses to a Member of the Public 27 2.2 Measurements and Approximations of Total 28 Radioactivity 2.2.1 Sample Collection and Analysis 28 2.2.2 Total Quantities of Radioactivity, Dose Rates 29 and Cumulative Doses 2.2.2.1 Fission and Activation Gases 29 2.2.2.2 Radioiodine, Tritium and Particulate Releases 29 2.2.2.3 Gross Alpha Release 30 2.2.3 Total Error Estimation 30 2.3 Gaseous Effluent Release Data 32 2.4 Radiological Impact Due to Gaseous Releases 33 2.5 Gaseous Effluents - Batch Releases 33 2.6 Gaseous Effluents - Abnormal Releases 33 3.0 Solid Waste 59 3.1 Regulatory Requirements 59 3.1.1 Solid Radioactive Waste System 59 3.1.2 Reporting Requirements 59 ii

SECTION TITLE PAGE 3.2 Solid Waste Data 60 4.0 Doses to Members of the Public Inside The 64 Site Boundary 4.1 Regulatory Requirements 64 4.2 Demonstration of Compliance 64 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 69 5.1 Regulatory Requirements 69 5.2 Demostration of Compliance 69 6.0 Meteorological Data 69 7.0 Program Deviations 69 7.1 Inoperable Liquid or Gaseous Effluent 69 Monitoring Instrumentation 7.1.1 Regulatory Requirements 69 7.1.2 Description of Deviations 70 7.2 Tanks Exceeding Curie Content Limits 70 7.2.1 Regulatory Requirements 70 7.2.2 Description of Deviations 70 7.3 Effluent Sample Analysis Exceeding Minimum 70 Detectable Concentration (MDC) 7.3.1 Regulatory Requirement 70 7.3.2 Description of Deviation 70 iii

SECTION TITLE PAGE 8.0 Changes to the Plant Hatch 70 Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements 70 8.2 Description of Changes 71 9.0 Major Changes to the Liquid, Gaseous or 71 Solid Radwaste Treatment Systems 9.1 Regulatory Requirements 71 9.2 Description of Major Changes 71 iv

SOUTHERN COMPANY E. I.HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENTRELEASES TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases 8 Unit 1 (Quarters 1, 2, 3 and 4) 1-1B Liquid Effluents - Summation of All Releases 9 Unit 2 (Quarters 1, 2, 3 and 4) 1-1C Liquid Effluents - Summation of All Releases 10 Site (Quarters 1, 2, 3 and 4) 1-2A Liquid Effluents - Unit 1 (Quarters 1, 2, 3 and 4) 11 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3 and 4) 13 1-2C Liquid Effluents - Site (Quarters 1, 2, 3 and 4) 16 1-3A Doses 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) 1-4 Minimum Detectable Concentration - 21 Liquid Sample Analysis 1-5A Liquid Effluents - Batch Release Summary 22 Unit 1 1-5B Liquid Effluents - Batch Release Summary 23 Unit 2 V

TABLE LIST OF TABLES PAGE 1-6A Liquid Effluents- Abnormal Release 24 Summary Unit 1 1-66 Liquid Effluents- Abnormal Release 25 Summary Unit 2 1-6C Liquid Effluents- Abnormal Release 26 Summary - Site 2-1A Gaseous Effluents - Summation of All 34 Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-1 B Gaseous Effluents - Summation of All 35 Releases -Unit 2 (Quarters 1, 2, 3 and 4) 2-1 C Gaseous Effluents - Summation of All 36 Releases - Site (Quarters 1, 2, 3 and 4) 2-2A Gaseous Effluents - Elevated Releases 37 Unit 1 (Quarters 1, 2, 3 and 4) .

2-2B Gaseous Effluents - Elevated Releases 39 Unit 2 (Quarters 1, 2, 3 and 4) 2-2C Gaseous Effluents - Elevated Releases 41 Site (Quarters 1, 2, 3 and 4) 2-3A Gaseous Effluents - Ground Level Releases 43 Unit 1 (Quarters 1, 2, 3 and 4) 2-3B Gaseous Effluents - Ground Level Releases 45 Unit 2 (Quarters 1, 2, 3 and 4) 2-3C Gaseous Effluents - Ground Level Releases 47 Site (Quarters 1, 2, 3 and 4) 2-4A Air Doses Due to Noble Gases in Gaseous 49 Releases - Unit 1 (Quarters 1, 2, 3 and 4) vi

TABLE LIST OF TABLES PAGE 2-4B Air Doses Due to Noble Gases in Gaseous 50 Releases- Unit 2 (Quarters 1, 2, 3 and 4) 2-5A Doses to a Member of the Public Due to 51 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 52 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-6 Minimum Detectable Concentration - 53 Gaseous Sample Analyses 2-7A Gaseous Effluents - Batch Release 54 Summary Unit 1 2-7B Gaseous Effluents - Batch Release 55 Summary Unit 2 2-8A Gaseous Effluents - Abnormal Release 56 Summary Unit 1 2-8B Gaseous Effluents - Abnormal Release 57 Summary Unit 2 2-8C Gaseous Effluents - Abnormal Release 58 Summary Unit Site 3-1 Solid Waste and Irradiated Fuel Shipments 61 4-1 Doses to a Member of the Public Due to 65 Activities Inside The Site Boundary Vii

1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 ConcentrationLimits 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 ConcentrationLimit ECL values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, 1-131, tritium, Sr-89, Sr-90 and Fe-55, are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2.

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

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

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

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

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

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

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

A sample from each tank planned for release is analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases, by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks released.

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

1.3.1 Total RadioactivityDeterminationfor Liquid Radwaste MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.
2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gas with computerized data reduction.
3. Tritium Monthly Distillation and liquid Composite scintillation counting
4. Gross Alpha Monthly Gas flow proportional Composite counting
5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting
6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting 2

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

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

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

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

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

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1.4 Measurements and Approximations of Total Radioactivity for Groundwater Outfalls - Y22NO03A112B and Y22NO08A Samples are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3. Weekly, monthly and quarterly composites are prepared for analysis by extracting aliquots from each outfall's automatic sampler, which collects a composite sample over a seven-day period. Sample analyses are performed as described in Section 1.4.1.

1.4.1 Total Radioactivity Determinationfor GroundwaterOutfalls MEASUREMENT FREQUENCY METHOD

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

"**]

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

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

Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-1 37, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

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

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

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

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

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

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

The evaluation for the release of radioactive RHR Service Water for 2008 can be found in Appendix A of this report.

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

1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective quarter.
2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period.
3. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy using a one liter sample from each liquid radwaste batch. The measured concentrations are used to calculate the total release and the average diluted concentration during the period. Radioisotopes of iodine in any form are also determined during the isotopic analysis for each batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not provide additional information.
4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity.

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

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

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

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

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Table 1-1A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Releas (not including tritium, gases, alpha) Curies 2A49E03 1,72E-02 3.05E-(13 1.12E-03
2. Average diluted concentration during period uCi/mL .6.67E-09 5.83 E-08 8,05E-09 2.60E-08
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 9.61E+100 1.10E+01 8.61IE+00 5.76E-01
2. Average diluted Concentration during period uCinmL 2.58E-05 3.72E-05 2.27E-05 1.34E-05 1;
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release Curies 0.OOE+00 4.96E-07 1.17E-06 O.IXIE+l00
2. Average diluted Concentration during period uCijmL 0,00E+G0 1.68E-12 3.09 E-12 0.0ME+0l1
3. Percent of Applicable Limit D: Gross Alpha Radioactivity
1. Total Release Curies 8.49E-07 4.79E-07 6.89E-07 6.237E-08 E: Waste Vol Release (Pre-Dilution) Liters 1.26E4-07 1.30E+07 2,03 E+I07 1.89E+07 F. Volume of Dilution Water Used Liters 3.73E+08 2.94E+08 3.79E+08 4.30E+07
  • Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report 8

Table 1-1B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-lan- 2008 Ending: 31-Dec-2008 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) Cu ries 1.79E-03 4.21E-03 2.27E-03 6.37E-05
2. Average diluted concentration during period uCi/mL 4.37E-10 7.56E-10 4.25E-10 1.59E-11
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 6.64E+00 5.93E+00 1.64E-+00 1.50E-01
2. Average diluted Concentration during period uCi/mL 1.63E-06 1,07E-06 3.06E-07 3.74E-08
3. Percent of Applicable Limit wE 41 C. Dissolved and Entrained Gases
1. Total Release Curies 6.87E-06 1.13E-06 0.00E+00 0.00E+00
2. Average diluted Concentration during period uCi/mL 1,68E-12 2.04E-13 0,006+00 0.00E+00
3. Percent of Applicable Limit 4ý D- Gross Alpha Radioactivity
1. Total Release Curies 7.60E-08 0.00E+00 9.53E-08 E: Waste Vol Release (Pre-Dilution) Liters 4.37E+,6 3.66E+06 3.36E-+06 2.70E+06 F. Volume of Dilution Water Used Liters 4M0BE+09 5.57E+09 5.35E+09 4.01E+09
  • Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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Table 1-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Sutmmation Of All Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 4.27E-03 2.14E-02 5.33E-03 1.18E-03
2. Average diluted concentration during period uCi/mL 9.59E-10 3.65E-09 9.29E-10 2.92E-10
3. Percent of Applicable Limit  %

B. Tritium

1. Total Release Curies 1.63E+01 1.69E+01 1.02E+01 7.26E-01
2. Average diluted Concentration during period uCi/mL 3.65E-06 2.88E-06 1.79E-06 1.79E-07
3. Percent of Applicable Limit  %*

C. Dissolved and Entrained Gases

1. Total Release Curies 6.87E-06 1.63E-06 1.17E-06 O.OOE+O0
2. Average diluted Concentration during period uCi/mL 1.54E-12 2.78E-13 2.05E-13 O.OOE+O0
3. Percent of Applicable Limit  %* * *
  • D: Gross Alpha Radioactivity
1. Total Release Curi6es 9.25E-07 4.79E-07 7.85E-07 6.37E-08 E: Waste Vol Release (Pre-Dilution) Liters 1.69E+07 1.67E+07 2.37E+07 2.16E+07 F. Volume of Dilution Water Used Liters 4.46E+09 5.86E+09 5.73E+09 4.05E+09
  • Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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Table 1-2A Hatchi Nuclear Planit RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluenfts Uni1t: 1 Starting: I-Jaii-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-89 curies I.02E-0S- 4.81E-04 0ODOE 4-00 0.00f+00 Sr-90 Curies 3.28E-05 5,48E-05 0.OOE+00 0.OOE+00 G-Beta curies O.OOE+OO O.OOE+ao 7,37E-07 8.99E-05 Total For Period Curies 4.30E-05 5.36F-04 7.37E-07 8.99E-05 Tritium H'-3 Curies 1.76E-02 2.47E-02 3.57E-02 1.64E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OE+00 O.OOE+00 0.OOE+00 O.OOE4-O0 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 1 Starting: 1-]an-2008 Endinig: 31-Dec-2008 Batchi Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-58 Curies 4.79E-06 7.50E-06 2.84E-05 O.OOE+00 Co-60 Cu ries 1.14E-03 5.57E-04 6.68E-04 4.10E-05 Cr-5S Curies 1.86E-04 0.00E+00 0.00E+00 0.00E+00 Fe-55 Curies 6.06E-04 1.56E-02 1.43E-03 9.42E-04 Mn-54 Curies 2.37E-04 1,23E-04 1.93E-04 6.40E-06 Na-24 Curies 8.13E-06 4.62E-05 1.52E-04 3.65E-06 Nb-97 Cu ries 2.82E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 Curies 3.18E-05 1.56E-05 5.72E-05 O.OOE+00 Zn-65 Curies 4.14E-05 5.25E-05 7.66E-05 0.00E+00 Cs-134 Curies 3.80E-06 0,00E+00 0.OOE+00 0.00E+00 Cs-137 Curies 1.77E-04 2.07E-04 4.36E-04 3.59E-05 Sb-122 Curie5 3.26E-07 0.00E+00 0.00E+00 0.00E+00 Sb-124 Curies 5.46E-06 0.00E+00 O.00E+00 O.OOE+00 Zn-69M Curies 1.17E-06 G.OOE+00 1.36E-05 0.00E+00 Ag-1lOM Curies 2.54E-06 0,00E+00 0.00E+00 0.00E+00 Total For Period Curies 2.44E-03 1.66E-02 3.05E-03 1.03E-03 Tritium H-3 Curies 9.60E+00 1.09E+01 8.57E+00 5.60E-01 Dissolved And Entrained Gases Xe-135 Curies 0.00E+00 4.96E-07 1.17E-06 0.00E+00 Total For Period Curies 0.00E+00 4.96E-07 1.17E-06 O.00E+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 tiqluid Efflue1nts Unit: 2 Starting: 1-Ian-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit IST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-90 Curies 4.3 1E-07 4.87E-06 O,00E+00 0.00E+00 G-Beta Curies 1.27E-06 1.64E-05 1.69E-05 O.OOE+OO Total For Period Curies 1.70E-06 2.13E-05 1.69E-05 O.OOE+OO Tritium H-3 Curies 5.81E-02 1.04E-01 7.56E-02 4.07E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 K

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

See Table 1-4 for btpical minimum detectable concentrations.

13

Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluenlts Unit: 2 Starting: I.-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nticlides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products As-76 Curies 1.14E-04 0.00E+00 O.OOE+00 0.00E+00 Co-58 Curies 262E-05 2,87E-06 5.28E-07 0.00E+00 Co-60 Curies 372E-04 1.48E-04 6.67E-05 6,87E-06 Cr-51 Curies 6.32E-05 2.26E-05 O.OGE+C0 0.00E+00 fe-55 Curies 5.13E-04 3.81E-03 2.04E-03 5.45E-05 Fe-59 Curies 7.59E-06 0.00E+00 0.0E+G0 0.00E+00 1-131 Curies 0.00E+00 0.00E+00 1.02E-06 0.00E+00 I-ln-54 Curies 2.20E-04 8.54E-05 3.35E-05 2.28E-06 Mn-56 Curies 1.82E-05 0.00E+00 0.OOE+O0 0.00E+00 Na-24 Curies 1.85E-04 0.00E+00 8.44E-05 0.00E+00 Nb-97 Curies 7.04E-06 1.77E-05 9.53E-07 O.OOE+00 Sr-89 Curies 1.36E-05 1.37E-05 3.55E-06 0.00E+00 Y-91t Curies 2.41E-05 0.00E+00 0.00E+00 0.00E+00 Zn-65 Curies 5.28E-05 5.18E-05 8.93E-06 0.00E+00 Ce-141 Curies 2.83E-06 0.00E+00 O.OE+00 0.00E+00 Cs-137 Curies 9.11E-05 3.16E-05 1.63E-05 0.00E+00 Ru-103 Curies 4.13E-07 0.00E+00 0.00E+00 0.00E+00 Sb-122 Curies 9.79E-07 0.00E+00 0.OOE+O0 O.0OE+00 5b-124 Curies 1.64E-05 0.OOE+00 0.00E+00 O.00E+00 Tc-99M Curies 2.08E-06 0.00E+00 0.O0E+00 0.00E+00 Zn-69M Curies 4.25E-05 7.05E-07 0.OOE+00 0.00E+00 Ag-llOM Curies 1.09E-05 0.00E+00 7.48E-07 0.00E+00 Total For Period Curies 1.78E-03 4.19E-03 2.26E-03 6.37E-05 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

14

Table 1-213 Hatch Nuclcear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-]an-2008 Ending: 31-Dec-2008 Batcl Mode Nuclides Released Unit 1STQuarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 6.58E+00 5.83E+00 1.56E+O0 1.09E-01 Dissolved And Entrained Gases Xe-135 Curies 6.87E-06 L 13E-06 O.OOE+OO 0.0OE+00 Total For Period Curies 6.87E-06 1.13E-06 O.OOE+OO O.OOE+0O Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentnations.

15

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-]an-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products SI-89 Curies 1.02E-05 4,81E-04 0.0DE+00 0.OOE+00 Sr-90 Curies 3.32E-0S 5,97E-05 0.00E+00 O.OOE+0O G-Beta Curies 1.27E-06 1.64E-05 1.76E-05 8.99E-05 Total For Period Curies 4.47E-05 5.57E-04 1.76E-05 8.99E-05 Tritium H-3 Curies 7.56E-02 1.29E-01 1.11E-0O 5.71E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+0O 0.OOE+O0 O.OOE+O0 0.O0E+O0 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

16

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-ban-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products As-76 Curies 1.14E-04 0.0OE+00 O.OOE-00 0.00E+00 Co-58 Curies 3.10E-05 1.04E-05 2.89E-05 0.00E+00 Co-60 Curies 1.51E-03 7.05E-04 7.35E-04 4.79E-05 Cr-51 Curies 2.49E-04 2,26E-05 O.OOE+00 O.00E+00 Fe-55 Curies 1.12E-03 1.94E-02 3.47E-03 9.97E-04 Fe-59 Curies 7.59E-06 O.OOE+00 0.00E+00 0.00E+00 1-131 Curies O.GDE+00 0.OOE+00 1.02E-06 0.00E+00 Mn-54 Curies 4.57E-04 2.09E-04 2.27E-04 8.67E-06 Mn-56 Curies 1.82E-05 0.00E+00 0.00E+00 O.OOE+00 Na-24 Curies 1.93E-0-4 4.62E-05 2.36E-04 3.65E-06 Nb-97 Curies 9.86E-06 1.77E-05 9.53E-07 0.00E+00 Sr-89 Curies 4.54E-05 2.94E-05 6.07E-05 0.00E+00 Y-91M Curies 2.41E-05 O.OOE+00 0.00E+00 O.OE+00 Zn-65 Curies 9.42E-05 1.04E-04 8.56E-05 O.0OE+00 Ce- 141 Curies 2.83E-06 O.OOE+00 0.00E+00 0.00E+00 Cs-134 Curies 3.80E-06 O.OOE+00 O.OE+00 0.00E+00 Cs-137 Curies 2.68E-04 2.39E-04 4.52E-04 3.59E-05 Ru-103 Curies 4.13E-07 O.OOE+00 0.06E+00 0.00E+00 Sb-122 Curies 1.31E-06 O.OOE+00 O.OOE+00 0.00E+00 Sb-124 Curies 2.18E-05 O.OOE+00 0.OOE+00 O.OOE+00 Tc-99M Curies 2.08E-06 0.00E+00 0.00E+00 0.00E+00 Zn-69M Curies 4.37E-05 7.05E-07 1.36E-05 0.00E+00 Ag-iiON Curies 1.35E-05 O.OOE+00 7.40E-07 0.00E+00 Total For Period Curies 4.23E-03 2.08E-02 5.31E-03 1.09E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

17

Table 1-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-iJan-2008 Ending: 31-Dec-2008 Batch Mode NTclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H--3 Curies 1.62E+01 1.68E+01 1.01E+01 6.69E-01 Dissolved And Entrained Gases Xe-135 Curies 6.87E-06 1.63E-06 1.17E-06 0.00E+00 Total For Period Curies 6.87E-06 1.63E-06 1.17E-06 0.OOE+O0 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

18

Table 1-3A Hatcl Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a menmber of the public due to Liquid Releases Unit: 1 Starting, l-Ian-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ ODCM Lint Units 1ST Qtr (/o 0DCM 2ND Qtr 0/b ODCM 3RD Qtr  % ODCM 4TH Qtr G/o0DCM Bone 5.00E+00 mRem 1.74E-02 3.49E-01 1.71E-02 3.42E-01 2.03E-03 4.05E-02 1.44E-04 2.88E-03 GI-LUi 5.00E+00 mRem 1,20E-03 2.39E-02 3.12E-03 6.24E-02 5.99E-04 1.20E-02 6.71E-05 1.34E-03 Kidney 5.00E+00 mRem 4.28E-04 8.55E-03 4.98E-04 9.96E-03 7.92E-04 1.58E-02 1.04E-04 2.0SE-03 Liver 5.00E+00 mRem 1,07E-03 2.13E-02 1.19E-03 2.38E-02 2.13E-03 4.26E-02 2.36E-04 4.71E-03 Lung 5.00E+00 mRem 2.12E-04 4.25E-03 2.69E-04 5.37E-03 3.26E-04 6.53E-03 6.04E-05 1.21E-03 Thyroid 5.OOE+00 mRem 1.09E-04 2.19E-03 1.50E-04 2.99E-03 1.03E-04 2.05E-03 3.78E-05 7.57E-04 Total Body 1.50E+00 mRem 4.84E-03 3.23E-01 1.31E-03 8.75E-02 1.47E-03 9.77E-02 1.69E-04 1.13E-02 Cumulative Doses per Year Organ ODCM Lint Units Year to Ending Date 0/b ODCM Receptor Limit Bone 1.00E+01 mRemn 3.67E-02 3.67E-01 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose GI-Li 1.00E+01 rnRem 4.99E-03 4.99E-02 MAX INDIVIDUAL LIQUID I Adult Ann Cum Organ Uq Dose Kidney 1.00E+01 mRem 1.82E-03 1.82E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Liver 1.00E+01 mRem 4.62E-03 4.62E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Lung 1.00E+01 mRem 8.68E-04 8.68E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Thyroid 1.00E+01 mRem 4.00E-04 4.00E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Total Body 3.00E+00 mRem 7.79E-03 2,60E-01 MAX INDIVIDUAL LIQUID / Adult Ann Cure Tot Body Liq Dose 19

Table 1-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 200B Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-]an-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ ODCM Lint Units 1ST Qtr 0/b ODCM 2ND Qtr  %/oODCM 3RD Qtr  % ODCM 4TH Qtr 0% ODCM Bone 5.ODE+00 mRem 3,35E-04 6.71E-03 1124E-04 2.48E-*3 7.06E-05 1.41E-03 B.44E-08 1.69E-06 GI-Lli 5.00E+00 mRem 2,92E-04 5,85E-03 1,58E-04 3.16E-03 6.37E-O5 1.27E-03 619E-06 1.24E-04 Kidney 5.00E+00 mRern 2.16E-04 4.33E-03 1.13E-04 2.26E-03 4.73E-05 9.46E 1i5E-06 3.03E-05 Liver 5,00E+00 mRern 5.32E-04 1.06E-02 2.30E-04 4.60E-03 1.13E-04 2.26E-03 187E-06 3.73E-05 Lung 5,00E+00 mRem 1.03E-04 2,06E-03 6.68E-05 1.34E-03 2.53E-05 S.06E-04 1,52E-06 3.04E-05 Thyroid 5.00E+O0 mRem 5.23E-05 1O05E-03 4.76E-05 9.51E-04 2.11E-05 4.22E-04 1.49E-06 2.97E-05 Total Body 1,50E+00 mRem 3.76E-04 251E-02 1.67E-04 L1I2E-02 7.99E-O5 S.33E-03 O03E-06 1.36E-04 Cumulative Doses per Year Organ ODCM Lint Units Year to Ending Date 0 ODCM Receptor Limit Bone 1.OOE+01 mRem 5.30E-04 5.30E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose GI-LUi 1.GOE+01 mRem 5.20E-04 5.20E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cure Organ Liq Dose Kidney 1,OOE+DI mRem 3.78E-04 3.78E-03 MAXINDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Liver L.ODE+Ol mRem 8.77E-04 8.77E-03 M-AXINDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Lung LODOE+CI mRem 1.97E-04 1.97E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Thyroid 1.00E+01 mRem 1,22E-04 1,22E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Total Body 3.OOE+OO0 mRem &.26E-04 2.09E-02 MAX INDI'VIDUAL LIQUID / Adult Ann Cum Tot Body Uq Dose 20

Table 1-4 E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES STARTING: 1-Jan-2008 ENDING: 31-Dec-2008 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 1.97E-08 uCi/ml Fe-59 3.94E-08 uCi/ml Co-58 1.59E-08 uCi/ml Co-60 1.72E-08 uCi/ml Zn-65 2.92E-08 uCi/ml Mo-99 1.20E-07 uCi/ml Cs-134 1.75E-08 uCi/ml Cs-137 1.62E-08 uCi/ml Ce-141 1.92E-08 uCi/ml Ce-144 8.83E-08 uCi/ml 1-131 1.43E-08 uCi/ml Xe-1 35 1.03E-08 uCi/ml Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml Sr-90 8.50E-09 uCi/ml H-3 6.OOE-07 uCi/ml 21

Table 1-5A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-ian-2008 Ending, 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 45 41 52 4 142
2. Total time period for Batch releases Minutes) 6.17E+03 5.09E+03 5.94E+03 3.89E+02 1.76E+04
3. Maximum time period for a batch release (Minutes) 1.80E+02 1.75E+02 1.73E+02 1.05E+02 1.BOE+02
4. Average time period for a batch release Minutes) 1.37E+02 1.24E+02 1.14E+02 9.73E+01 1.24E+02
5. Minimum time period for a batch release Minutes) 7.10JE+01 8.0OE+01 6.70E+01 8.30E+01 6.70E+01
6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) l.25E-+04 5.13E+03 1.68E+03 1.76E+03 5.24E+03 Replace this text in the Station Parameters 22

Table 1-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 38 44 16 1 99
2. Total time period for Batch releases (Minutes) 4.01E+03 4.69E+03 1.555+03 9.60E+01 1.04E+04
3. Maximum time period for a batch release Minutes) 1.36E+02 1.3BE+02 1.17E+02 9.60E+01 1.38E+02
4. Average time period for a batch release Minutes) 1.06E+02 1.07E+02 9.69E+01 9.6OE+01 1.05E+02
5. Minimum time period for a batch release Minutes) 7.1I0E+01 8.60E+01 7.50E+01 9.60E+01 7.10E+01
6. Average stream flow during periods of release of liquid effluent into a flowing stream :' ( CFS ) 1.25E+04 5.13E+03 1.68E+03 1.76E+03 5.24E+03 Replace this text in the Station Parameters 23

Table 1-6A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnormal Release Summary Unit, 1 Starting: 1-Ian-2008 Ending: 31-Dec-2008 Liquid Releases Units 1tST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Min utes ) 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00
3. Maximum Time For A Release ( Min rtes 4 0.OOE+00 0.00E+00 0.OE+00 0.006E-01 O.00E+00
4. Average Time For A Release (Min utes 4 O.O0E+00 0.0o0+00 .OIJE+00 0.00E+00 0.00E+00
5. Minimum Time For ARelease ( Min utes 4 O.OOE+00 O.OOE+00 O.GDE+00 O.OOE00 0 0.00E+00
6. Total activlfy for all releases (Curl les ) 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 24

Table 1-6B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnonmal Release Summary Unit: 2 Starting: 1-Ian-2008 Ending: 31-Dec-2008 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+0D O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00
3. Maximum Time For A Release ( Minutes) O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+O0 0.00E+00
4. Average Time For A Release ( Minutes) O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00
5. Minimum Time For A Release ( Minutes) O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00
6. Total activity for all releases ( Curies) O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 25

Table 1-6C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnonial Release Summary Unit: Site Starting: 1-]an-2008 Ending: 31-Dec-2008 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 (Minu utes) 0.OOE+00 0.00E+00 0.00E+00 O.00E+00 O.OOE+00
3. Maximum Time For A Release (Min utes) 0.60E+00 O.00E+00 O.OOE+00' O.GDE+00 O.OOE+00
4. Average Time For A Release (Mini utes) 0.O0E+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00
5. Minimum Time For A Release Minuutes) 0.0OE+00 OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00
6. Total activity for all releases (Curi es 0O.OOE+00 O.OOE÷O0 0.OOE+O0 O.OOE+00 O.OOE+00 26

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

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

a. For noble gases: Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,
b. For Iodine-1 31, Iodine-1 33, tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

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

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.3 Doses To A Member of the Public The dose to a MEMBER OF THE PUBLIC from Iodine-1 31, Iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following.

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ.
b. During any calendar year: Less than or equal to 15 mrems to any organ.

27

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

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

1. Noble gas samples are collected by grab sampling monthly.
2. Tritium samples are collected by grab sampling monthly.
3. Radioiodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period.
4. Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period.
5. The 7-day particulate filters above are analyzed for gross alpha activity.
6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the samples are analyzed for Sr-89 and Sr-90.

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

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

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

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

28

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

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

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

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

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

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

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

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

29

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

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

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

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

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

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

30

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Non-steady release rates 20%

TOTAL ERROR 65%

1-131 releases were calculated from each weekly sample.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 64%

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

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

Water vapor in sample stream determination 20%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 50%

TOTAL ERROR 56%

31

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

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

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

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

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

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

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

32

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

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

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

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

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

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

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

33

Table 2-1A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Sumnitation Of All Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies O.OOE+O0 0,OOE+O0 O.OOE+OO 0.OOE+OO
2. Average Release rate for period uci/sec 0.O0E+O0 O.OE+00 0.00E+00 0.00E+00
3. Percent of Applicable Limit %9
  • C B. Radioiodines
1. Total Iodine-131 Curies 1.23E-05 3.33E-05 2.35E-05 1.43E-05
2. Average Release rate for period uCi/sec 1.56E-O6 4.23E-06 2.PSE-06 1.S1E-06
3. Percent of Applicable Limit  % *
  • C C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies 2.45E-06 4.03E-06 1.79E-05 2.09E-05
2. Average Release rate for period uCi/sec 3.11E-07 5.11E-07 2.27E-06 2.653E-06
3. Percent of Applicable Limit  %
1. Total Release Curies 5.67E+00 8.11E+00 7.99E+00 7.E+00
2. Average Release rate for period uCi/sec 7.20E-01 1.03E+00 1.01E+00 8.98E-01
3. Percent of Applicable Limit
  • t *
  • E. Gross Alpha
1. Total Release Curies 0.00E+00 0.00E+00 0.O0E+00 0.00E+00
2. Average Release rate for period uCi/sec 0MOOE+90 0.00E+00 0.00E+00 0.00E+00 Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

34

Table 2-1B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2008 EBiding: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies O.OOE+OO 0.OOE+O0 O.OOE+O0 O.OOE+O0
2. Average Release rate for period uCi/sec 0.OOE+O0 O.OOE+00 O.OOE+00 0.00E+O0
3. Percent of Applicable Limit  % * .-

B. Radioiodines

1. Total Iodine-131 Cuues 3.57E-O5 3.33E-05 2.91E-05 1.67E-05
2. Average Release rate for period uCi/sec 4.52E-06 4.23E-06 3.69E-06 2.12E-06
3. Percent of Applicable Limit  %* 5 C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies 5.60E-06 4.97E-06 6.21E-06 4.61E-06
2. Average Release rate for period uCi/sec 7.10E-07 6.31E-07 7.88E-07 5.847E-07
3. Percent of Applicable Limit  % 4
1. Total Release Curies 8.55E+O0 1,08E+01 9.34E+00 7.99E+00
2. Average Release rate for period uCi/sec 1.08E+O0 1.37E+00 1.19E+00 1.01E+00
3. Percent of Applicable Limit E. Gross Alpha
1. Total Release Curies O.OOE+O0 O.00E+00 O.OOE+00 O,OE+00
2. Average Release rate for period ucilsec OOOE+O0 O.OOE+00 0.OOE+00 0100E+00
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

35

Table 2-1C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: I-]an-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 0.00E+O0 O,0OE+00 D.0OE+00 O.OOE+00
2. Average Release rate for period uCi/sec 0.00E+00 O.OOE++0 0.00E+00 O.OOE+00
3. Percent of Applicable Limit  % 4 *
  • B. Radioiodines
1. Total Iodine-131 Curies 4.79E-05 6,67E-05 5.26E-05 3.10E-05
2. Average Release rate for period uCi/sec 6.0SE-06 8.46E-06 6.67E-06 3.94E-06
3. Percent of Applicable Limit  %

C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 8.05E-06 9.OOE-06 2.41E-05 2,55E-05
2. Average Release rate for period uCi/sec 1.02E-06 1.14E-06 3.06E-06 3.238E-06
3. Percent of Applicable Limit  %-

D. Tritium

1. Total Release Curies 1.42E+01 1.89E+01 1.73E+01 1.51E+01
2. Average Release rate for period uCi/sec 1.80E+00 2.40E+00 2.20E+a0 1.91E+00
3. Percent of Applicable Limit *
  • 0 E. Gross Alpha
1. Total Release Curies 0.00E+00 O.00E+00 0.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec 0.00E+00 OO.0E÷00 O.*0E+OO O.00E+00
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-41, 2-5A, 2-5B of this report.

36

Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-lan- 2008 Ending: 31-Dec-2008 Continuotus Mode Nuclides Released Unit IST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.00E+00 O.OOE+O0 O.OOE+00 lodines 1-131 Curies 1.02E-05 3.33E-05 2.35E-05 1.33E-05 1-133 Curies 4.99 E-05 7.9-6E-05 6.55E-05 1.36E-05 Total For Period Curies 6.01E-05 1.13E-04 8.90E-05 2.69E-0,5 Particulates Cr-51 Curies O.OOE+00 0.09E+00 0.00E+00 O.00E+00 Mn-54 Curies O.OOE+00 0.00E+00 0.00E+00 O.00E+00 Co-60 Curies 600E+00 0.00E+00 0.O0E+00 O.00E+00 Sr-89 Curies 9.19E-07 3.37E-06 4.03E-06 2.09E-06 Sr-90 Curies 5.93E-09 2.33E-08 8.75 E-09 O.OOE+00 Ba-140 Curies O.OOE+00 0.OOE+00 1.94E-07 0.00E+00 Total For Period Curies 9.25E-07 3.39E-06 4.23E-06 2.09E-06 Tritium H-3 Curies 2.78 E-0 1 9.11E-01 1.18E+00 6.63E-01 Gross Alpha No Nuclides Found Curies 0,00E+00 0.00E+00 O.00E+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactMty 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 - 2008 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-lan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curie s O.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+O0 lodines No Nuclides Found Curie s O.O0E+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curie s OOOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOE+O0 O.O0E+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

38

Table 2-2B Hatch Nuclear Plant RADIOACTI[VE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2006 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O3MOE+OO o.0oE÷O0 0.00E+00 lodines 1-131 Curies 3.04E-0i5 3.33 E-05 2.35E-05 1.33E-05 1-133 Curies 9.43E-05 7.96E-05 6.55E-05 1,36E-05 Total For Period Curies 1.25E-04 1.13E-04 8.90E-05 2.69E-05 Particuilates-Cr-Si Curies 5.83E-07 DOGJE+00 0.00E+00 0.OOE+00 Mn-54 Curies 2.92E-07 IJJ0E+00 0.OOE+O0 0.00E+00 Co-60 Curies 3.76 E-07 0.00E+00 0.OOE+00 0.00E+00 Sr-89 Curies 2.92E-06 3.37E-06 4.03E-06 2,09E-06 Sr--so Curies 1.88E-08 2.33 E-08 8.75E-09 0O.OE+O0 Ba-140 Curies Oj.00E+r00 0.13E+00 1.94E-07 0.00E+00 Total For Period Curies 4.19E-06 3.39E-06 4.23E-06 2.09E-06 Tritium H-3 Curies 6.02E-01 9.11E-01 1.18E+00 6.63E-01 Gross Alpha No Nuclides Found Curies 0.00E+00 OMOE+O0 0.OOE÷00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

39

Table 2-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Unit Nuclides Released Fission Gases O.00E+O0 O.DDE+00 O.OBE400 O.OOE+O0 No Nuclides Found Curie s lodines O.OOE+oo O.OOE+O0 OO0E+O0 O.OE+O0 No Nuclides Found Curie s Particulates O.OOE400 0.00E+00 O.OOE+O0 O.OOE+O0 No Nuclides Found Curie s Tritium O.OOEO0 O.0OE+O0 O.OOE+O0 OOOE+O0 No Nuclides Found curie eS Gross Alpha O.OE+O0 O.0OE+O0 O.OOE+O0 OOOEO0 No Nuclides Found Curie s no radioactivity was present at detectable levels.

If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that See Table 2-6 for typical minimum detectable concentrations.

40

Table 2-2C Hatci Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Elevated Level Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 lodines 1-131 Curies 4.06E-05 6.67E-05 4.70E-05 2.66E-05 1-133 Cu ries 1.44E-04 1.59E-04 1.31E-04 2.72E-05 Total For Period Curies 1.85E-04 2.26E-04 1.78E-04 5.37E-05 Particulates Cr-5i Curies 5,83E-07 0.00E+00 0.005+00 0.00E+00 Mn-54 Curies 2.92E-07 O.OOE+00 O.OOE+OO 0.00E+00 Co-60 Curies 3.76E-07 0.06E+00 0.00E+00 0.00E+00 Sr-89 Curies 3.84E-06 6.74E-(16 8.06E-06 4.17E-06 Sr-90 Curies 2.48E-08 4.66E-08 1.75E-08 O.OOE+00 Ba-140 Curies O.OOE+00 O.OOE+00 3.89E-07 0.00E+00 Total For Period Curies 5.11E-06 6.79E-06 8.47E-06 4.17E-06 Tritium.

H-3 Curies 8.80E-01 1.82E+00 2.36E+00 1.33E+00 Gross Alpha No Nuclides Found Cu ries O.OOE+00 0.06E+00 0.00E+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

41

Table 2-2C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Elevated Level Releases Unit: Site Starting: I-Jan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 lodines No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOEO00 0.OOE+O0 Gross Alpha No Nuclides Found Curie s O.OOE+O0 O.OOE+O0 O.OOE÷OD O.O0E+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

42

Table 2-3A Hatdi Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases t: 1 Starting: 1-lan-2008 Ending: 31-Dec.-2008 Continuous Mode Nuclides Released Unit lST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OE+O0 O.OOE+O0 O.OOE+0O O.OOE+00 lodines 1-131 Curies 2.03E-06 O.OOE+00 0.00 E+00 1.01E-06 Total For Period Curies 2.03E-06 O.OOE+OO S.00 E+0 0 1.O1E-015 Particulates Mn-54 Curies 0.00E+00 0.OOE+0O 5.32E-06 6.49E-06 Co-58 Curies 0.00E+00 0.00E+00 1,.78E-06 4.16E-065 Co-60 Curies 0.OOE+O0 0.DDE+0O 6.55E-06 6.78E416 Zn-65 Curies 0.OOE+OO 0.0OE+00 O.OOE+00 1.40E-06 5r1-89j Curies 1.52E-06 6,36E-07 O.OOE+00 DM0E+00 Total For Period Curies 1.5ZE-06 6.36E-07 1.37E-05 1.88E-05 Tritium H-3 Curies 5.39E+00 7.20E+00 fi81E+00 6.41E+00 Gross Alpha No Nuclides Found Curies 0.00E+O0 0,00E+00 0.06E+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

43

Table 2-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Ur.1it" .

Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nudides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+O0 D.OOE+00 lodines No Nuclides Found Curies 0.OOE+O0 OOOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.O0E+O0 OOOE+O00 0.0E+00 O.OOE+OO0 Tritium No Nuclides Found Curies O.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

44

Table 2-38 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effienits - Ground Level Releases Unit: 2 Starting: 1-]an-2008 Ending: 31-Dec-2008 Continu~ous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 0.OOE+O0 O.OOE+O0 Iodines 1-131 Curies 5.29E-06 O.OOE+O0 5.57E-06 3.44E-06 1-133 Curies O.OOE+0O 0.OOE+OO 1.47E-05 O.4OE+O0 Total For Period Curies 5.29E-06 O.OOE+O0 2.03E-05 3.44E-06 Particulates Sr-89 Curies 1.31E-06 1.58E-06 1.98E-06 2.52E-06 Sr-90 Curies 1.06E-07 0.00E+00 O.OOE+0O 0.OOEC00 Total For Period Curies 1.41E-06 1.58E-06 1.98E-06 Z.52E-06 Tritium H-3 Curies 7.95E+00 9.87E+00 8.16E+00 7.33E+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentratons.

45

Table 2-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-]an-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Iodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+O0 O.GDE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+OO O.OOE+O0 0.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

46

Table 2-3C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies 0.OOE+00 0.OOE-O0 O.OOE+00 O.OOE+N0 lodines 1-131 Curies 7.31E-06 O.OOE+O0 557E-06 4.45E-06 1-133 Curies 0.06E+00 0.00E+00 1.47E-05 0.00E +00 Total For Period Curies 7.31E-06 O.OOE+O0 2.03E-05 4.45E-06 Particulates Mn-54 Curies O.OOE+00 O.OOE+00 5,32E-06 6.49E-06 Co-5S Curies 0.OOE+00 O.OOE+O0 1.78E-06 4.16E-06 Co-60 Curies 0OOE+00 O.OOE+O0 655E-06 6.78E-06 Zn-65 (Juries O.OE+00 O.OOEO00 O.OOE+00 1.40E-06 S1-89 Curies 2.83E-06 2,22E-06 1.98E-06 2.52E-06 Sr-90 Curies 1.06E-07 O.OOE+-0 6.OOE+00 O0OOE+00 Total For Period Curies 2.94E-06 2.22E-06 1.56E-05 2.14E-05 Tritium H-3 cJuries 1.33E+01 1.71E+01 1.50E+01 1.37E+01 Gross Alpha No Nuclides Found Curies 0.OOE+00 0.OOE+O0 O.OOE+00 0.00E+00 If Not Detected, Nuclide is Not Repomted. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

47

Table 2-3C Hatci NLiclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-]an-2008 Ending: 31-Dec-2008 Batchl Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.0OE+00 O.OOE+O0 O.00E+00 0.OOE+00 Iodines No Nuclides Found Curies 0.00E+01 O.OOE+00 0.O0E+00 0.OOE+01)

Particulates No Nuclides Found Curies ..OOE+OO 0.0E+OO .OOE+O0 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+0O O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 0.OOE+O0 OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

48

Table 2-4A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-]an-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Type of Radiation ODCM Lint Units 1ST Qtr 0/a ODCM 2ND Qtr 0/b ODCM 3RD Qtr  % ODCM 4TH Qtr */a ODCM Gamma Air 5.00E+00 mRad O.00E-+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.QQE+00 0.OOE+00 0.00E+00 Gamma Air 5.OOE+00 mRad O.00E+00 0,OOE+00 00,0E+00 0.00E+00 0.00E+00 0 0.00E+00 0.00E+00 Beta Air 1.00E+01 rnRad 0.OOE400 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 O.0E0E00 0.00E+00 0.00E+00 Beta Air 1.00E+01 mRad O.0CE+00 0.OOE+O 0OOE+00 0.00E+00 0.OO.+00 00DE-OO 00.OOE+0D 0.OE+00 Cumulative Doses Per Year Type of Radiation ODCM Lint Units Year to End Date  % ODCM Receptor Limit Gamma Air l,00E+01 mRad O.OOE+00 O.OOE+O0 SITE BOUNDARY / Child U1 Ann Cum Gamma Airdose Gamma Air 1.OOE+01 mRad 0.OOE+O0 O.OOE+00 SITE BOUNDARY / Child U2 Ann Cum Gamma Airdose Beta Air 2.00E+01 mRad 0.00E+00 0.OOE+00 SITE BOUNDARY / Child UI Ann Cum Beta Airdose Beta Air 2.00E+01 mRad 0.00E+00 O.OOE+00 SITE BOUNDARY / Child U2 Ann Cum Beta Airdose 49

Table 2-4B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: 2 Starting: 1-]an-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Type of Radiation ODCM Lint Units 1ST Qtr o/o ODCM 2ND Qtr  % ODCM 3RD Qtr oe ODCM 4TH Qtr 0/b 00CM Gamma Air 5.OOE+00 mRad 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Gamma Air 5.00E+00 mRad 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.03E+00 Beta Air 1.O0E+01 mRad 0.0E+00 0.00E+00 0.00E+00 O.OOE+O0 0.00E+00 0.00E+00 0.00E+00 M.OE+00 Beta Air 1.00E+01 mRad 0.OCE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cumulative Doses Per Year 0

Type of Radiation ODCM Lint Units Year to End Date /4 ODCM Receptor Limit Gamma Air 1.00E+01 mRad 0.00E+00 0.00E+00 SITE BOUN DARY / Child U1 Ann Cum Gamma Airdose Gamma Air 1.00E+01 mRad 0.O0E+00 0.OOE+00 SITE BOUN DARY / Child U2 Ann Cum Gamma Airdose Beta Air 2.OO)E+0I mRad 0.OOE+00 O.00E+00 SITE BOUNIDARY / Child U1 Ann Cum Beta Aiidose Beta Air 2.OOE+01 mRad 0.005+00 0.00E+00 SITE BOUN DARY / Child U2 Ann Gum Beta Airdose 50

Table 2-5A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-]an-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ ODCM Lint Units 1ST Qtr 0 ODCM 2ND Qtr  % ODCM 3RD Qtr  % ODCM 4TH Qtr 3/4 ODCM Bone 7.50E+00 mRem 1.73E-05 2.31E-04 1.32E-05 1.76E-04 4.86E-05 6.48E-04 4.79E-05 6.39E-04 GI-LJi 7.50E+00 mRem 2.80E-03 3.73E-02 3.74E-03 4.98E-02 3.59E-03 4.78E-02 3.38E-03 4.50E-02 Kidney 7.50E+00 mRem 2.80E-03 3.73E-02 3.74E-03 4.98E-02 3.58E-03 4.78E-02 3,37E-03 4.50E-02 Liver 7.50E+00 mRem 2.80E-03 3.73E-02 3.74E-03 4.98E-02 3.58E-03 4.78E-02 3.37E-03 4.50E-02 Lung 7.50E+00 mRem 2.80E-03 3.73E-02 3.74E-03 4,98E-02 3.59E-03 4,78E-02 3.38E-03 4.50E-02 Thyroid 7.50E+00 mRem 2.85E-03 3.80E-02 3.81E-03 5.08E-02 3.63E-03 4.84E-02 3.42E-03 4.55E-02 Total Body 7.50E+00 mRem 2.80E-03 3.73E-02 3.74E-03 4.98E-02 3.58E-03 4.78E-02 3.38E-03 4.50E-02 Cumulative Doses per Year Organ ODCMi Lint Units Year to Ending Date 3/4 ODCM Receptor Limit Bone 1.500E+01 mRem 1.271E-04 8.472E-04 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose GI-Lli 1.500E+01 mRem 1.350E-02 8,999E-02 MAX IND. AIRBORNE I Child Ann Cum lod/Part Airdose Kidney 1.500E+01 mRem 1.349E-02 8,99LE-02 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose Liver 1.500E+01 mRem 1.349E-02 8.993E-02 MAX IND. AIRBORNE / Child Ann Cum load/PartAirdose Lung 1.500E+01 mRem 1.350E-02 8.998E-02 MAX IND. AIRBORNE i Child Ann Cum lod/Part Ahodose Thyroid 1.500E+01 mRem 1.371E-02 9.138 E-02 M4AXIND. AIRBORNE / Child Ann Cum lod/Part Airdose Total Body 1.500E+01 mRem 1.349E-02 8,995E-02 MAX IND. AIRBORNE / Child Ann Cum lod/Part Airdose 51

Table 2-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radiolodines, Tritium, and PartiCeilates in Gaseous Releases Unit: 2 Starting: 1-]an-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ ODCM Lint Units 151 Qtr 0/b 00CM 2ND Qtr  % ODCM 3RD Qtr 0/b 00CM 4TH Qtr 0/ 01DCM Bone 7.50E+00 mRem 5.75E-05 7.66E-04 2.27E-05 3.03E-04 2.73E-05 3.63E-04 2.90E-05 3.87E-04 GI-LIi 7.50E+00 mRem 4.12E-03 5.50E-02 5.12E-03 6.83E-02 4.24E-03 5.65E-02 3.80E-03 5.07E-02 Kidney 7.50E+00 mRem 4.12E-03 5.50E-02 5.12E-03 6.83E-02 4.24E-03 5.65E-02 3.80E-03 5.07E-02 Liver 7.50E+00 mRem 4.12E-03 5.50E-02 5.12E-03 6.83E-02 4.24E-03 5.65E-02 3.80E-G3 5.07E-02 Lung 7.50E+00 mRem 4.12E-03 5,50E-02 5. 12 E-03 6.83 E-02 4.24E-03 5.65E-02 3,80E-0,3 5.07E-02 Thyroid 7.50E+00 mRem 4.27E-03 5.69E-02 5.20E-03 6.93 E-02 4,38E-63 5.84E-02 3.8BE-03 5.18E-02 Total Body 7.50E+00 mRem 4.13E-03 5.51 E-02 5.12E-03 6.83 E-02 4.24E-03 5.65E-02 3.80E-03 5.07E-02 Cumulative Doses per Year Organ 00CM Lmt Units Year to Ending Date 0/ 00CM Receptor Limit Bone 1.500E+01 mRem 1,365E-G4 9,097E-04 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose GI-LIi 1.500E+01 mRem 1.729E-02 1.153E-01 MAX IND. AIRBORNE / Child Ann Cum IodlPart Airdose Kidney 1.500E+01 mRem, 1.729E-02 1.152E-01 MAX IND, AIRBORNE /Child Ann Cum Iod/Part Airdose Liver 1.500E+01 mRem 1.729E-02 1.152E-01 MAX IND. AIRBORNE / Child Ann Cure Iod/Part Airdose Lung 1.500E+01 mRem 1.729E-02 1.152E-01 MAX IND. AIRBORNE / Child Ann Cum Iod/Part Airdose Thyroid 1.500E+01 mReni 1,773E-02 1.182E-01 MAX IND. AIRBORNE Child Ann Cure Iod/Patt Airdose Total Body 1.500E +01 mRem 1.730E-02 1.153E-01 MAX INO, AIRBORNE /Child Ann Cum Iod/Part Airdose 52

TABLE 2-6 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2008?

MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANAL YSES STARTING: 1-Jan-2008 ENDING: 31-Dec-2008 The values in this table represent a priori Minimum Detectable Concentration (MDC) that are typically achieved in laboratoryanalyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 2.94E-08 uCi/cc Kr-88 3.22E-08 uCi/cc Xe-133 2.30E-08 uCi/cc Xe-1 33m 7.30E-08 uCi/cc Xe-1 35 8.73E-09 uCi/cc Xe-1 38 1.99E-07 uCi/cc 1-131 1.34E-13* uCi/cc 1-133 1.53E-13* uCi/cc Mn-54 1.62E-1 3* uCi/cc Fe-59 3.42E-1 3* uCi/cc Co-58 1.30E-1 3* uCi/cc Co-60 1.54E-1 3* uCi/cc Zn-65 2.54E-13* uCi/cc Mo-99 9.61 E-1 3* uCi/cc Cs-134 1.42E-1 3* uCi/cc Cs-137 1.28E-13* uCi/cc Ce-141 1.26E-1 3* uCi/cc Ce-144 5.64E-1 3* uCi/cc Sr-89 1.10E-16 uCi/cc Sr-90 6.70E- 16 uCi/cc H-3 4.OOE-07 uCi/cc

  • Based on an estimated sample quantity of 4.078E+07cc's.

53

Table 2-7A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: 1 Starting. l-Jan--2008 Eniding: 31-Dec-2008 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) COQOE 4GO O.OOE+O0 O.OOE+0 O..OOE+O0 ,.OOE+00
3. Mwamum time period for a batch release Minutes) O.OOE+OO O.OOE+O0 0.GGE+0-0 0.00E+OO O.OOE+O0
4. Average time period for a batch release Minutes) O.OOE+0O 0.OOE+00 O.OOE+O0 0.00E+00 0.OOE+00
5. Minimum time period for a batch release Minutes) 0.00E+00 000]E+00 0.00E+00 0.00E+00 0.OOE+00 54

Table 2-7B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Ian-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 0 0 0 0 0
2. Total time period for batch releases Minutes) 0.00E+00 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00
3. Maximum time period for a batch release Minutes) 0.00E+00Q O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00
4. Average time period for a batch release Minutes) 0.0OEt-00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00
5. Minimum time period for a batch release (Minutes) 0.00JE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 55

Table 2-8A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes) 0.GDE+00 0.00E+00 O.OOE+E00 OOOE+00 O.OOE+00
3. Maximum Time For A Release Minutes ) 0.OOE+00 O.OOE+00 O.OOE+O0 O.00E+O0 O.OOE+00
4. Average Time For A Release Minutes) O.OOE+00 0.0OE+00 O.OOE+O0 O.OOE+O0 O.OOE+O0
5. Minimum Time For A Release (Minutes) O.OOE+00 O.00E+00 .06E+O0 OOOE+00 0.00E+00
6. Total activity for all releases (Curies ) 0.00E+00 0.00E+00 O.OOE+O0 O.OOE+00 O.OOE+O0 56

Table 2-8B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Ian-2008 Ending: 31-Dec-2008 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 FoC All Releases Minutes) 0.OE++00 0.005+00 0.OOE+O0 0.00E+00 0.0E5+00 3, Maximum Time For A Release Minutes) 0,00E+00 0,0OE+00 O.05E+00 0,00E+00 0.OOE+00 4, Average Time For A Release Minutes) 0M00E+00 0.00E+00 0.OOE+00 0.00E+00 0}OE+00 S. Minimum Time For A Release Minutes) 0.00E+00 0.00E+00 O.0OE+00 0.00E+00 0.0E5+00 6&Total activity for all releases ( Curies ) 00OE+000 0.00E+00 O.0E+00 0.00E+00 0.00E+00 57

Table 2-8C Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release SUnnmary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

i. Number of Releases a 0 0 0 0
2. Total Time For All Releaser, Minutes) U.00E +00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+O0
3. Maximum Time For A Release Minutes) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE÷00
4. Average Time For A Release Minutes 0.OQE+Q0 0,00E+00 0.OOE+0O 0.00E+00 0.OOE+00
5. Minimum Time For A Release Minutes) 0.00E+00 OOOE+00 0.OOE+00 0.00E+00 0.OOE+00
6. Total activity for all releases (Curies ) O.OOE+00 O.00E+00 0.00E+00 0.OOE+00 0.OOE+00 58

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

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

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

3.1.2 Reporting Requirements Technical Specification 5.6.3 requires in part:

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

PCP Section A.4.1 states in part:

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

59

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

a. Container volume.
b. Total curie quantity (specify whether determined by measurement or estimate).
c. Principal radionuclides (specify whether determined by measurement or estimate).
d. Type of waste (such as spent resin, compacted dry waste, evaporator bottoms).
e. Type of container (such as LSA, type A, type B, large quantity).
f. Solidification agent (such as cement).

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

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

60

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jan-2008 ENDING: 30-Jun-2008 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est. Total period ERROR %
a. Spent resins, filter sludges, evaporator m3 1.241 E+01 bottoms, etc. Ci 1.01 8E+03 1.00 E 01
b. Dry compressible waste, contaminated equip. m3 1.41 0E+02 etc. Ci 4.960E-01 2.00 E 01
c. Irradiated components, control rods 3 m_

Ci

d. Control Rod Drive Filters 3 Ci
e. Other (describe) m3 Equip. etc. Ci
2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES a.Fe-55 75.4 7.680E+02 Co-60 13.1 1.329E+02 Zn-65 2.22 2.260E+01 Mn-54 5.97 6.080E+01 Cr-51 0.9 9.020E+00 Other 2.42 2.467E+01 b.Fe-55 22.2 1.100E-01 Co-60 25.6 1.270E-01 Mn-54 5.71 2.830E-02 Zn-65 35.2 1.750E-01 Other 11.3 5.600E-02 C.

d.

e.

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

Number of Shipments Mode of Transportation Destination 0 N/A N/A 61

TABLE 3-1 E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jul-2008 ENDING: 31-Dec-2008 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est. Total period ERROR %
a. Spent resins, filter sludges, evaporator m 4.70E+01 bottoms, etc. Ci 3.20E+01 1.00 E 01
b. Dry compressible waste, contaminated equip. m_3 7.28E+01 etc. Ci 2.58E+01 2.00 E 01
c. Irradiated components, control rods, m3 Ci
d. Control Rod Drive Filters m3 Ci
e. Other (describe) m3 Equip. etc. Ci
2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES a.Fe-55 51.8 1.66E+01 Co-60 31.1 9.95E+00 Zn-65 3.4 1.09E+00 Mn-54 6.40 2.05E+00 Other 7.3 2.34E+00 b.Fe-55 22.2 5.73E+00 Co-60 25.6 6.61 E+00 Mn-54 5.71 1.47E+00 Zn-65 35.2 9.09E+00 Other 11.3 2.91 E+00 C.

d.

e.

t 4

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination All waste sent to processors Tractor/Trailer Energy Solutions B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 62

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 l*lklrll&lfi, rjft i.._ i.ll, tl.ti.J S T AiRi I Il I -..

d;iln- yUUo ivulivu;: 3U-IJun-0UUO TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATION OF QUANTITY/ NUCLIDES/ CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBIC FEET (FT 3)

Dewatered 1018 Zn-65,Fe-55,Co-60 High 3.64 120.3 14-210 DOT 7A N/A Resins Mn-54, Cr-51 Integrity See Note TYPE A CASK/

Container 8-120(B) CASK/

14-210"*STC Cask Dry 0.496 Fe-55,Co-60,Mn-54 B-25 55.32 90 **STC N/A Active Waste Zn-65 Boxes/High See Note (B-25)

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

    • STC-Strong Tight Container TABLE 3-1 E. 1. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2008 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-JUL-2008 ENDING:31-DEC-2008 TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATION OF QUANTITY/ NUCLIDES/ CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBIC FEET

____ ____(FT 3)

Dewatered 8.48 Zn-65,Fe-55,Co-60 Carbon Steel 4 195 14-210 CASK N/A Resins Mn-54 Liners (External)

Dry 72.8 Fe-55,CO-60,Mn-54 B-25 29 96 B-25 Boxes, N/A Active Waste Zn-65 Boxes/High See Note Sealand Integrity Containers Container Note: The actual type, size and number of the containers may vary from the recorded values due to the use of different containers by waste processors for final disposal of processed resin and DAW.

63

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

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

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

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

64

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-]an-2008 Ending: 31-Dec-2008 Location Name: ROADSIDE PARK Distance (kilometers): 1.18E+00 Sector: WNW Occupancy Factor: 2.28E-04 Age Group: Child Elevated Release Noble Gas X/Q.(sec/m3): 2.42E-08 Elevated Release Particulate and Radioiodine X/Q (sec/m3): 2.37E-08 DIQ (m-2): 1.29E-09 Ground Level Release Noble Gas X/Q (sec/m3): 7.83E-06 Ground Level Release Particulate and Radioiodine XIQ (sec/inS): 7.OOE-06 D/Q (m-2); 2.01E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 7.5SE-12 8.41E-13 2.1BE-10 2.31E-10 4,58E-10 Liver mRem 7.61E-09 9.74E-09 8.76E-09 8.07E-09 3.42E-08 Total Body mRem 7.61E-09 9.74E-09 8.76E-09 8.07E-09 3 .42E-08 IThyroid mRem 7.67E-09 9.74E-0J9 8.84E-09 8. 11 E-09 3.44E-08 Kidney mRem 7.61E-09 9.74E-09 8.76E-09 8.07E-09 3.42E-08 Lung mRem 7.61E-09 9.74E-09 8.79E-09 8.10E-09 3.42E-08 GI-Lli mRem 7.61E-09 9.74E-09 8.76E-09 8.07E-09 3.42E-08 Skin mRem 1.27E-12 1.74E-13 2.55E-10 2.70E-10 5.27E-10 65

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - -2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-]an-2008 Ending: 31-Dec-2008 Location Name: CAMPING AREA Distance (kilometers): 1.27E+00 Sector: WNW Occupancy Factor: 5.46E-03 Age Group: Child Elevated Release Noble Gas X/Q (secm3): 2.38E-08 Elevated Release Particulate and Radiolodine XIQ (sec/m3): 2.33E-08 D/Q (m-2): 2.01E-08 Ground Level Release Noble Gas XIQ (sec/m3): 7.03E-06 Ground Level Release Particulate and Radiolodine X/Q (sec/m3): 6.27E-06 D/Q (m-2): 1.80E-08 Units 1S1 Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone rnRern 4.77E-10 6.88E-11 4.73E-09 4.99E-09 1.03E-08 Liver mRem 1.64E-O7 2.10E-07 1.69E-07 1.74E-07 7.36E-07 Total Body mRem 1.64E-07 2.10E-07 1.89E-07 1.74E-07 7.36E-07 Thyroid mRern 1.6SE-O7 2.10E-07 1.90E-07 1.75E-07 7.40E-07 Kidney rnRem 1.64E-07 2.10E-07 1.89E-07 1.74E-07 7.36E-07 Lung rnRem 1.64E-07 2.1OE-07 1.89E-07 1.74E-07 7.38E-07 GI-Lli rnRern 1.64E-O7 2.10E-07 1,89E-07 1.74E-07 7.36E-07 Skin mRem 3.98E-10 6.52E-11 5.54E-09 5.84E-09 1.18E-08 66

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Location Namne: RECREATION AREA Distance (kilometers): 1.03E+W0 Sector: SSE Occupancy Factor: 2,37E-02 Age Group: Child Elevated Release Noble Gas XIQ (sec/m3): 3.30E-08 Elevated Release Particulate and Radioiodine X/Q (seclm3): 3.21E-0B D/Q (m-2): 1.56E-09 Ground Level Release Noble Gas X/Q (sec/m3): 6.42E-06 Ground Level Release Particulate and Radioiodine XIQ (sec/m3): 5.73E-06 DJQ (m-2): 2.36E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 6.86E-10 7.88E-11 2.66E-08 2.82E-08 5.55E-08 Liver mRem 6.48E-07 8.29E-07 7.54E-07 6.95E-07 2.92 E-06 Total Body mRem 6.48E-07 8.29E-07 7,54E-07 6.95E-07 2.92E-06 Thyroid mRem 6.53E-07 8.29E-07 7.60E-07 6.98E-07 2.94E-06 Kidney mRem 6.48E-07 8.29E-07 7.54E-07 6.95E-07 2,92E-06 Lung mRem 6.48E-07 8.29E-07 7.56E-07 6.98E-07 2,93E-06 GI-Lli mRem 6.48E-07 8.29E-07 7.54E-07 6.96E-07 2.93E-06 5kin mRem 1.59E-10 2.19E-11 3.12E-08 3.30E-08 6.43E-08 67

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: l-]an-2008 Ending: 31-Dec-2008 Location Name: VISITORS CENTER Distance (kilometers): 6.94E-01 Sector: WSW Occupancy Factor: 4.57E-04 Age Group: Child Elevated Release Noble Gas X/Q (sec/m21): 5.OOE-08 Elevated Release Paiticulate and Radioiodine X/Q (sec/m3): 4.97E-08 D/Q Cm-2): 2.26E-09 Ground Level Release Noble Gas XJQ (secim3): 1.87E-05 Ground Level Release Papticulate and Radiolodine X/Q (sec/m3): 1.72E-05 DOQ (m-2): 5.47E-08 Units 1-S1 Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 3.60E-11 3.92E-12 1.19E-09 1.26E-09 2.49E-09 Liver mRem 3.75E-08 4.79E-08 4.33E-08 3.99E-08 1.69E-07 Total Body mRem 3.75E-08 4.79E-08 4.33E-08 3.99E-08 1.69E-07 Thyroid rnRem 3.78E-08 4.80E-08 4.36E-08 4.00E-08 1.69E-07 Kidney mRem 3.75E-08 4.79E-08 4.33E-08 3.99E-08 1.69E-07 Lung mRem 3.75E-OB 4.80E-08 4.34E-08 4.06E-08 1.69E-07 GI-Lli mRem 3.75E-08 4.79E-08 4.33E-08 3.99E-08 1.69E-07 Skin mRem 4.90E-12 6.12E-13 1.39E-09 1.47E-09 2.87E-09 68

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

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

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

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

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

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

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

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

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

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

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

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

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8.2 Descriptionof Changes There were no changes to the Hatch ODCM in 2008.

9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 9.1 Regulatory Requirements The Radioactive Effluent Release Report shall include.... any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to ODCM Chapter 7, Section 7.2.2.7.

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

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

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

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SOUTHERN COMPANY E. ILHATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1, 2008 - DECEMBER 31,2008 APPENDIX A 72

Release of Radioactive RHR Service Water for 2008 The following historical information is provided to create a perspective for the release of radioactivity during the year 2008 relative to the RHR Service Water System.

In 1996, the analysis of samples from the Unit 1 RHR "B" Loop service water (RHRSW) system identified several radionuclides at very low concentrations. The first indication of contamination was noted on August 8, 1996 and the second indication was noted on August 23, 1996. The total activity in the RHRSW contained within the heat exchanger, which has a volume of approximately 4000 gallons, was respectively estimated to be about 13.7 jICi and 25.6 I.Ci. On August 23, 1996 repairs were made to a Ap instrument in an effort to stop the inleakage into the service water side of the heat exchanger. To determine if the leak had been repaired, the service water loop of the heat exchanger was decontaminated by flushing and the service water in the loop was then resampled and analyzed. The circulating water flume has a blowdown line, which diverts a small portion of the total circulating water to the river via the discharge structure.

This resulted in a release to an unrestricted area. Though this release was both monitored and controlled, it was not through the normally utilized liquid radwaste system but the release to the unrestricted area did in fact take the same release path to the river. The regulatory discreteness of this release is discussed in the 1996 evaluation of the release, which is documented in the 10CFR50.59 Evaluation titled "Unit 1 RHR Service Water: Release of Contaminated Water."

The requirements of the Radioactive Effluent Controls Program are spelled out in TS 5.5.4.

The Offsite Dose Calculation Manual (ODCM) implements this program and it conforms to the requirements of 10CFR50.36a for the control of radioactive effluents and for maintaining the doses as low as reasonable achievable. Compliance with TS 5.5.4 regarding liquid releases can be assured by adhering to the requirements of ODCM sections 2.1.2, 2.1.3 and 2.1.4 which respectively provide limits on the concentration of the radioactive material at the point of release to an unrestricted area, the resultant dose to a member of the public from the release, and the necessity of using the radwaste treatment system.

MWO 1-96-02845 was worked during the Unit 1 outage to repair the leaks in the Ul RHR "B" Heat Exchanger. The RHR side of the Heat Exchanger was pressurized with helium and a helium detector on the RHRSW side was used to look for the presence of leaks. Based on this it was determined that one of the outermost tubes (tube 1-1) was definitely leaking. No other tubes were identified as definite leakers; however, the eight tubes closest to tube 1-1 were identified as possible leakers.

Integrated Technologies, Inc. performed an eddy current inspection of 245 of the tubes, including all of the suspected leakers and surrounding tubes. This inspection also identified tube 1-1 as a leaker. The tube breach is located next to the top support in the outlet leg. The cause is unknown. No other leaking tubes were identified.

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The conservative decision was made to plug the leaker as well as the eight surrounding tubes.

After plugging the tubes a hydrostatic pressure test was conducted at 300 psi and the Heat Exchanger was inspected for signs of leakage. No leakage was noted at this time. The Heat Exchanger was deconned, closed up and placed back in service. The Chemistry Department has sampled and monitored the activity during the operation of the Heat Exchanger.

The only concentrations of radionuclides found in the RHRSW samples for 2008 were from 3/9/08, when the total concentration released was 3.01 E-8 gCi/ml. As shown in the following table, the highest concentrations were found in 1997, when the total concentration released was 1.21 E-5 gCi/ml.

Radio-

'nuc!ide* '1997 r;,l~(.gic l 1 1998

i/ml) 1999
(gAI Ci/ml) 2000 , (gcift/

',(4lCi/ml) 2001 l)*,

,Cre-51i 1.07E-6 3.16E-7

ý.Mn-54 2.37E-6 4.95E-7 2.49E-7 2.53E-7 Fe-59. 1.19E-7 Co-60 4.94E-6 1.12E-6 2.27E-8 2.82E-7 1.99E-7 Zn-65 2.06E-6 7.96E-8 2.24E-7 Co-58 1.06E-6 Cs-134 2.1OE-7 Cs-137 4.43E-7 Radio- F 2002 2003 2004 2005 2006 2007 2008 nuclide I(gcifi/l) I(cifi/rl) I(gcifi/l) I(lgCi/ml) -(glCi/ml) (giCi/ml) (lgQ/ml Mn-54 2.78E-8 1.46E-8 8.59E-9 1.23E-8 1.89E-8 Co-60 1.99E-7 2.65E-7 3.78E-8 2.96E&8 1.24E-7 2.43E-7 1.12E-8 Nb-95 5.46E-9 Cs-137 7.77E-9 Fe-59 was identified in one sample (7/18/01). Heat exchanger testing and the analysis result indicate no new leaks to the system. The results of the samples analyzed in 2005 indicate we are monitoring residual contamination from the 1996 leaks.

ODCM section 2.1.2 requires that the concentrations of the radioactive materials released be limited to 10 times (1OX) the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, with the exception for dissolved or entrained noble gases whose concentration shall be limited to 1.OE-4 gCi/ml.

The following discussion is based on a release duration of 1 minute, a release volume of 4,000 gallons, a total dilution of only 10,000 gallons, and the radionuclide concentrations from 1997. This is a very conservative estimate, since credit for the additional dilution provided by the circulating water flume was not taken into consideration and the activity from 1997 was higher with more radionuclides. The sum of the ratios of the concentration of each radionuclide in the mixture to its effluent concentration limit (ECL) was 1.15. The sum of the ECL fractions must be less than ten (<10) to ensure that the concentration limit for the mixture is not exceeded. As can be seen, the sum is much less that ten. (10CFR20 Appendix B states that the sum of the fractions of the nuclides divided by their effluent concentration limits (ECLs) must be less than one. Further NRC guidance, Technical Specifications, and the ODCM allow the 74

ECLs in Appendix B to be increased by a factor of 10. Mathematically this can be achieved by dividing the nuclides by the original 1OCR 20 Appendix B ECLs and insuring that the sum of the fractions is less than 10. The plant software performs the sum of the ECL fractions and comparisons this way to insure compliance with 1OCRF20 limits.)

ODCM section 2.1.3 requires that the annual dose to a member of the public, in unrestricted areas, due to liquid releases from each unit be limited to 3 mrem to the total body and 10 mrem to any organ. The dose in any quarter is limited to half of the annual limits. Dose calculations were performed for this release, in accordance with ODCM section 2.4, to evaluate the doses relative to this release. The total body dose was 6.66 E-5 mrem (2.2 E-3 % of its annual limit) and the highest organ dose was 7.39 E-5 mrem to the GI-LLI, gastrointestinal track, (7.4 E-4 % of its annual limit). The resultant doses are quite low and essentially do not contribute to the quarterly and/or the annual dose limits. This provides a high degree of assurance that the release in no way presented a threat to the health and safety of a member of the public, even using the very low dilution rate. With a higher dilution value the ECL fraction and the resultant doses are reduced further and become even less significant.

ODCM section 2.1.4 requires that the radwaste system be employed to reduce the radioactivity in the liquid waste prior to its discharge whenever the projected dose due to the release would exceed 0.06 mrem to the total body and 0.2 mrem to any organ. As shown in the previous paragraph, the total body dose due to the release of the RHRSW was much less than 0.06 mrem and the maximum organ dose was much less than 0.2 mrem.

10CFR20.1302 (b)(1) requires that a licensee show compliance with the annual limit of 100 mrem to any member of the public by demonstrating that certain concentration limits of the effluent at the point of release are not exceeded. This was addressed above in the assessment of ODCM section 2.1.2.

10CFR20.1501 (a)(2)(ii) & (iii) requires the licensee to evaluate the concentration or quantities of radioactive materials and the potential radiological hazard, respectively. The concentrations and quantity of the radioactive materials in the release was evaluated by sampling and analysis as discussed above. The potential radiological hazard was also evaluated by performance of the dose calculations, which would be a result of the release, as discussed above in the assessment of ODCM section 2.1.3.

This release does not constitute a Licensee Event Report (LER) based on the following.

10CFR 50.73 (A)(2)(VIII)(B) requires the licensee to report any liquid effluent release which exceeds 20 times the applicable concentration specified in 10CFR20, Appendix B, Table 2, column 2, at the point of entry into the receiving waters (i.e., unrestricted area). This is justified as discussed above in the assessment of ODCM section 2.1.3; it can be seen that the concentrations are much less that the applicable limits.

Design Criterion 64 in Appendix A to 10CFR50 requires the monitoring of effluent discharge paths. Performance of the sampling and analysis of the RHRSW service water before its release complied with this criterion.

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Compliance with Appendix I to 10CFR50 was assured by adherence to the applicable ODCM sections as discussed above. Furthermore, Appendix I is the bases for one of these ODCM sections.

40CFR1 90 is concerned with the annual dose to any member of the public due to releases of radioactivity and to radiation from the uranium fuel cycle sources. This is addressed by TS 5.5.4.j and implemented by ODCM section 5.1.2, which states that additional calculation and reporting is required when any of the dose limits as specified in the ODCM sections 2.1.3, 3.1.3, or 3.1.4 are exceeded by a factor of two. This requirement is not applicable for the release based on the doses as discussed above in the assessment of ODCM section 2.1.3.

NRC Bulletin 80-10, "Contamination of Nonradioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Releases of Radioactivity to the Environment" lists four actions for the licensee. First: identify the affected systems; the Unit 1 RHR "B" loop was identified.

Second: establish a sampling/analysis of monitoring program for the affected systems; this was done. Third: restrict use of the system until the cause of the contamination is identified and corrected, and the system is decontaminated. The release was the result of identifying the leakage, implementation of corrective action and of decontaminating the system. The third action also states, that, if it is considered necessary to continue operation of the system as contaminated, then a 10CFR50.59 evaluation must be performed. This was done in 1996. The fourth action calls attention to the regulations to be complied with and states that releases must be monitored and controlled. The release of the RHR service water was sampled and monitored (evaluated) by the sampling and analysis prior to the flush taking place; the release was controlled in the fact that the flush was a planned evolution.

Administrative controls and sampling have been established to ensure that any future releases would be within 10CFR20 limits, reference Lab Standing Order, SO-HPC-001-0402, and 64CH-SAM-028-0.

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Edwin 1. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2008 Enclosure 2 Farley Annual Radioactive Effluent Release Report for 2008

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 2008

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 1.0 LIQUID EFFLUENTS 1 1.1 Regulatory Requirements 1 1.1.1 Concentration Limits 1 1.1.2 Dose Limits 1 1.2 Effluent Concentration Limit (ECL) 1 1.3 Measurements and Approximation 2 of Total Radioactivity 1.3.1 Total Radioactivity Determination 2 1.3.2 Total Error Estimation 3 1.4 Liquid Effluents - Release Data 3 1.5 Radiological Impact Due to Liquid Releases 3 1.6 Liquid Effluents - Batch Releases 4 1.7 Liquid Effluents - Abnormal Releases 4 2.0 GASEOUS EFFLUENTS 26 2.1 Regulatory Requirements 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 Approximation 27 of Total Radioactivity 2.2.1 Sample Collection and Analysis 28

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 2.2.2 Total Quantities of Radioactivity, Dose 28 Rates and Cumulative Doses 2.2.2.1 Fission and Activation Gases 28 2.2.2.2 Radioiodine, Tritium and Particulate 29 Releases 2.2.2.3 Gross Alpha Release 30 2.2.3 Total Error Estimation 30 2.3 Gaseous Effluent Release Data 31 2.4 Radiological Impact Due to Gaseous 32 Releases 2.5 Gaseous Effluents - Batch Releases 32 2.6 Gaseous Effluents - Abnormal Releases 32 3.0 SOLID WASTE 57 3.1 Regulatory Requirements 57 3.1.1 Solid Radioactive Waste System 57 3.1.2 Reporting Requirements 57 3.2 Solid Waste Data 57 4.0 DOSES TO MEMBERS OF THE PUBLIC 62 INSIDE THE SITE BOUNDARY 4.1 Regulatory Requirements 62 4.2 Demonstration of Compliance 62

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 5.0 TOTAL DOSE FROM URANIUM FUEL 66 CYCLE (40CFR190) 5.1 Regulatory Requirements 66 5.2 Demonstration of Compliance 66 6.0 METEOROLOGICAL DATA 66 7.0 PROGRAM DEVIATIONS 66 7.1 Inoperable Liquid or Gaseous Effluent 66 Monitoring Instrumentation 7.1.1 Regulatory Requirements 66 7.1.2 Description of Deviations 67 7.2 Effluent Sample Analysis Exceeding 67 Minimum Detectable Concentration (MDC) 7.2.1 Regulatory Requirements 67 7.2.2 Description of Deviations 67 7.3 Incorrect Compositing of Liquid 67 or Gaseous Effluent Samples 7.3.1 Regulatory Requirements 67 7.3.2 Description of Deviations 67 8.0 CHANGES TO THE PLANT FARLEY ODCM 68 8.1 Regulatory Requirements 68 8.2 Description of Changes 68

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR 68 SOLID RADWASTE TREATMENT SYSTEMS 9.1 Regulatory Requirements 68 9.2 Description of Major Changes 68

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-lA Liquid Effluents - Summation of 5 All Releases, Unit 1 (Quarters 1,2, 3 and 4) 1-lB Liquid Effluents - Summation of 6 All Releases, Unit 2 (Quarters 1,2, 3 and 4)

I-IC Liquid Effluents - Summation of 7 All Releases, Site (Quarters 1,2, 3 and 4) 1-2A Liquid Effluents, Unit 1 (Quarters 1,2, 8 3 and 4) 1-2B Liquid Effluents, Unit 2 (Quarters 1,2, 11 3 and 4) 1-2C Liquid Effluents, Site (Quarters 1,2, 15 3 and 4) 1-3A Doses to a MEMBER OF THE PUBLIC 19 Due to Liquid Releases, Unit 1 (Quarters 1,2,3 and 4) 1-3B Doses to a MEMBER OF THE PUBLIC 20 Due to Liquid Releases, Unit 2 (Quarters 1,2,3 and 4) 1-4 Minimum Detectable Concentration 21 Liquid Sample Analyses 1-5A Liquid Effluents - Batch Release 22 Summary, Unit 1 1-5B Liquid Effluents - Batch Release 23 Summary, Unit 2

'FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-6A Liquid Effluents - Abnormal Release 24 Summary, Unit 1 1-6B Liquid Effluents - Abnormal Release 25 Summary, Unit 2 2-1A Gaseous Effluents - Summation of 33 All Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-1B Gaseous Effluents - Summation of 34 All Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-1C Gaseous Effluents - Summation of 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, 3 and 4) 2-3B 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 OF TABLES PAGE 2-4A Air Doses Due to Noble Gases in 48 Gaseous Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-4B 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, Tritium, 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, Tritium, 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 53 Summary, Unit 1 2-7B Gaseous Effluents - Batch Release 54 Summary, Unit 2 2-8A Gaseous Effluents - Abnormal Release 55 Summary, Unit 1 2-8B Gaseous Effluents - Abnormal Release 56 Summary, Unit 2 3-1 Solid Waste and Irradiated 58 Fuel Shipments 4-1 Doses to a MEMBER OF THE PUBLIC 63 Due to Activities Inside the Site Boundary, Site

1.0 LIQUID EFFLUENTS This section contains applicable ODCM limits for liquid effluents as well as the quantities of radioactive liquid effluents released during 2008. These quantities are summarized on a quarterly basis and include any unplanned releases. A tabulation of the total body and organ doses which were calculated in accordance with ODCM 2.4 are presented to show conformance with the limits of ODCM 2.1.3.

1.1 Regulatory Requirements 1.1.1 Concentration Limits Technical Specifications 5.5.4.b and 5.5.4.c state that the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited at all times to ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-04 uCi/ml total activity.

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

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

1.2 Effluent Concentration Limit (ECL)

ECL Values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, 1-131, tritium, Sr-89, Sr-90 and Fe-55, are taken from 10CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor setpoints which can accommodate effluent releases at concentrations higher than the ECL values stated in 10CFR20, Appendix B, Table 2, Column 2.

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

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

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

- 1 -

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.

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

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

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

1.4 Liquid Effluent Release Data Summaries of all radioactive liquid effluents released from Units 1 and 2 during 2008 are presented in accordance with Regulatory Guide 1.21 Tables 2A and 2B. Information required by Table 2A is found in this report in Tables 1-lA, 1-1B, and 1-1C; Table 2-B information is presented in Tables 1-2A, 1-2B, and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.

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

Unit 1 2008 Doses to a Member of the Public due to Liquid Releases:

Table 1-3A Unit 2 2008 Doses to a Member of the Public due to Liquid Releases:

Table 1-3B 1.6 Liquid Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables:

Unit 1 2008 Liquid Effluents - Batch Release Summary: Table 1-SA Unit 2 2008 Liquid Effluents - Batch Release Summary: Table 1-5B 1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases during 2008.

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

Unit 1 2008 Liquid Effluents - Abnormal Release Summary: Table 1-6A Unit 2 2008 Liquid Effluents - Abnormal Release Summary: Table 1-6B

- 4 -

Table 1-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

.1. Total Release (not including tritium, gases, alpha) Curies 8.70E-03 3.34E-03 9.80E-04 4.43E-03

2. Average diluted concentration during period uCi/mL 5.81E-10 2.09E-10 6.49E-11 3.26E-10
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 8.79E+01 8.87E+01 2.59E+02 1.26E+02
2. Average diluted Concentration during period uCi/mL 5.87E-06 5.55E-06 1.72E-05 9.26E-06
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release Curies 1.68E-05 1.94E-05 2.29E-04 2.32E-03
2. Average diluted Concentration during period uCi/mL 1.12E-12 1.21E-12 1.51E-11 1.71E-10
3. Percent of Applicable Limit D: Gross Alpha Radioactivity
1. Total Release Curies 0.OOE+00 4.54E-05 1.26E-05 4.72E-06 E: Waste Vol Release (Pre-Dilution)

Liters 8.08E+07 7.81E+07 7.59E+07 7.84E+07 F. Volume of Dilution Water Used Liters 1.49E+10 1.59E+10 1.50E+10 1.35E+10

  • Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report. - 5

Table 1-11B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 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 1.43E-02 8.77E-03 6.29E-03 4.47E-03
2. Average diluted concentration during period uCi/mL 8.56E-10 4.95E-10 3.59E-10 2.83E-10
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 7.14E+01 1.69E+02 3.10E+02 6.26E+01
2. Average diluted Concentration during period uCi/mL 4.26E-06 9.53E-06 1.77E-05 3.97E-06
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release Curies 2.55E-04 5.77E-05 4.33E-04 1.63E-03
2. Average diluted Concentration during period uCi/mL 1.52E-11 3.26E-12 2.47E-11 1.03E-10
3. Percent of Applicable Limit D: Gross Alpha Radioactivity
1. Total Release Curies 0.OOE+00 4.28E-05 4.62E-05 1.54E-05 E: Waste Vol Release (Pre-Dilution)

Liters 7.30E+07 6.92E+07 6.42E+07 4.53E+07 F. Volume of Dilution Water Used Liters 1.67E+10 1.76E+10 1.75E+10 1.57E+10

  • Applicable limits are expressed in terms of dose. - 6 See Tables 1-3A and 1-3B of this report.

Table 1-1C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 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 2.30E-02 1.21E-02 7.27E-03 8.89E-03
2. Average diluted concentration during period uCi/mL 7.26E-10 3.60E-10 2.23E-10 3.03E-10
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 1.59E+02 2.57E+02 5.70E+02 1.88E+02
2. Average diluted Concentration during period uCi/mL 5.02E-06 7.64E-06 1.74E-05 6.42E-06
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release Curies 2.72E-04 7.71E-05 6.62E-04 3.95E-03
2. Average diluted Concentration during period uCi/mL 8.56E-12 2.29E-12 2.03E-11 1.35E-10
3. Percent of Applicable Limit D: Gross Alpha Radioactivity
1. Total Release Curies O.OOE+00 8.82E-05 5.88E-05 2.01E-05 E: Waste Vol Release (Pre-Dilution)

Liters 1.54E+08 1.47E+08 1.40E+08 1.24E+08 F. Volume of Dilution Water Used Liters 3.16E+10 3.35E+10 3.25E+10 2.92E+ 10

  • Applicable limits are expressed in terms of dose.

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

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Dissolved And Entrained Gases No Nuclides Found O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 Zeroes in this table indicates that no radioactivity was present at detectable levels.

- 8 -

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &Activation Products Y-88 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.24E-07 Y-94 Curies O.OOE+00 O.OOE+00 O.OOE+00 1.93E-06 As-76 Curies O.OOE+00 O.OOE+00 O.OOE+00 7.30E-07 Co-57 Curies 1.26E-06 O.OOE+00 O.OOE+00 6.78E-07 Co-58 Curies 9.57E-04 1.93E-04 9.69E-05 7.16E-04 Co-60 Curies 1.14E-03 1.41E-03 4.19E-04 1.24E-03 Cr-51 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 6.38E-04 Fe-55 Curies O.OOE+O0 6.52E-04 1.81E-04 6.42E-04 Mn-54 Curies 1.04E-05 2.O0E-05 O.OOE+O0 2.12E-05 Na-24 Curies O.OOE+O0 4.38E-06 O.OOE+O0 O.OOE+O0 Nb-95 Curies 6.51E-05 3.38E-05 8.67E-07 1.21E-04 Nb-97 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 1.63E-05 Sr-89 Curies O.OOE+O0 8.15E-06 3.98E-05 O.OOE+O0 Sr-90 Curies O.OOE+O0 O.OOE+O0 4.30E-06 O.OOE+O0 Y-90M Curies O.OOE+O0 O.OOE+O0 2.87E-07 O.OOE+O0 Y-91M Curies O.OOE+O0 O.OOE+O0 8.96E-07 O.OOE+O0 Zn-65 Curies 4.62E-04 7.70E-04 1.61E-04 5.30E-04 Zn-69 Curies O.OOE+O0 O.OOE+O0 2.89E-06 O.OOE+O0 Zr-95 Curies 2.94E-05 1.15E-05 O.OOE+O0 6.48E-05 Cd-115 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 1.04E-06 Cs-134 Curies O.OOE+O0 1.62E-06 O.OOE+O0 O.OOE+O0 Cs-137 Curies 9.66E-06 6.62E-05 4.62E-05 2.74E-05 Cs-138 Curies O.OOE+O0 O.OOE+O0 1.85E-06 O.OOE+O0 Hf-181 Curies O.OOE+O0 5.64E-07 O.OOE+O0 O.OOE+O0 Nb-95M Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 7.59E-07 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Rh-105 Curies O.OOE+O0 O.OOE+0O O.OOE+O0 3.25E-04 Sb-124 Curies O.OOE+O0 O.OOE+00 O.OOE+O0 3.08E-06 Sb-125 Curies 1.12E-04 1.45E-04 2.44E-05 6.99E-05 Sn-113 Curies O.OOE+O0 2.93E-06 O.OOE+0O 2.41E-07 Te-131 Curies O.OOE+O0 O.OOE+O0 4.21E-07 O.OOE+0O Ag-108M Curies O.OOE+O0 1.06E-05 O.OOE+0O 1.76E-06 Ag-110M Curies O.OOE+O0 1.13E-05 O.OOE+0O 8.87E-07 In-115M Curies O.OOE+00 O.OOE+O0 O.OOE+0O 1.14E-06 Sn-117M Curies 8.79E-07 O.OOE+O0 O.OOE+0O 0.OOE+00 Te-125M Curies 5.91E-03 O.OOE+O0 O.OOE+0O 0.OOE+00 Total For Period Curies 8.70E-03 3.34E-03 9.80E-04 4.43E-03 Tritium H-3 Curies 8.79E+01 8.87E+01 2.59E+02 1.26E+02 Dissolved And Entrained Gases Ar-41 Curies 0.OOE+0O 1.03E-05 O.OOE+O0 1.90E-05 Xe-133 Curies 1.68E-05 6.OOE-06 2.29E-04 6.61E-04 Xe-135 Curies 0.OOE+00 7.87E-07 O.OOE+0O 0.OOE+00 Xe-137 Curies 0.OOE+00 O.OOE+O0 O.OOE+0O 1.64E-03 Xe-138 Curies O.OOE+00 2.32E-06 O.OOE+00 0.OOE+00 Total For Period Curies 1.68E-05 1.94E-05 2.29E-04 2.32E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-213 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-90 Curies 3.90E-04 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 3.90E-04 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium H-3 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 11 -

Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &Activation Products Be-7 Curies O.OOE+O0 O.OOE+O0 2.78E-05 O.OOE+O0 Co-57 Curies 9.05E-07 O.OOE+O0 O.OOE+O0 O.OOE+O0 Co-58 Curies 8.29E-04 2.73E-04 3.52E-04 1.12E-03 Co-60 Curies 3.55E-03 3.11E-03 2.54E-03 9.73E-04 Cr-51 Curies 1.39E-05 O.OOE+O0 5.OOE-05 4.32E-04 Fe-55 Curies 9.22E-04 1.91E-03 6.23E-04 3.85E-04 Fe-59 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 9.06E-07 Mn-54 Curies 8.73E-05 4.54E-05 3.28E-05 1.76E-05 Na-24 Curies 2.39E-06 O.OOE+O0 4.19E-06 2.30E-06 Nb-95 Curies 1.65E-04 5.08E-05 5.39E-05 4.09E-05 Nb-97 Curies O.OOE+O0 2.89E-06 2.87E-04 2.29E-05 Se-75 Curies 7.19E-07 O.OOE+O0 O.OOE+O0 O.OOE+O0 Sr-85 Curies 1.04E-06 O.OOE+O0 O.OOE+O0 O.OOE+O0 Sr-89 Curies 1.26E-05 O.OOE+O0 O.OOE+O0 O.OOE+O0 Sr-91 Curies O.OOE+O0 3.45E-06 O.OOE+O0 O.OOE+O0 Sr-92 Curies 1.49E-06 O.OOE+O0 O.OOE+O0 O.OOE+O0 Y-91M Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 1.67E-06 Zn-65 Curies 1.58E-03 1.95E-03 8.52E-04 5.06E-04 Zn-69 Curies O.OOE+O0 3.91E-05 O.OOE+O0 O.OOE+O0 Zr-95 Curies 3.06E-05 8.62E-06 1.94E-05 1.11E-05 Ce-146 Curies O.OOE+O0 1.76E-06 O.OOE+O0 O.OOE+O0 Cs-137 Curies 8.81E-05 1.58E-04 2.22E-04 1.40E-04 Cs-138 Curies 9.61E-06 1.88E-05 8.87E-06 O.OOE+O0 Eu-152 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 La-142 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 6.70E-07 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nd-147 Curies 1.54E-06 O.OOE+00 O.OOE+00 O.OOE+00 Rh-105 Curies O.OOE+O0 O.OOE+00 3.21E-06 2.10E-04 Sb-124 Curies 5.84E-06 6.47E-06 O.OOE+00 3.76E-05 Sb-125 Curies 6.41E-04 1.08E-03 9.91E-04 5.60E-04 Sn-113 Curies O.OOE+00 2.57E-05 O.OOE+00 O.OOE+O0 Tc-99M Curies O.OOE+00 O.OOE+00 3.28E-06 O.OOE+O0 Te-134 Curies O.OOE+00 2.89E-05 0.O0E+00 O.OOE+O0 Zn-69M Curies 9.16E-07 O.OOE+00 0.OOE+00 O.OOE+0O Ag-108M Curies O.OOE+00 1.66E-05 4.80E-06 1.40E-06 Ag-110M Curies 8.47E-06 3.98E-05 1.48E-05 O.OOE+0O Sn-117M Curies 1.28E-06 O.OOE+00 0.OOE+00 O.OOE+0O Te-125M Curies 6.OOE-03 0.OOE+00 1.98E-04 O.OOE+0O Total For Period Curies 1.40E-02 8.77E-03 6.29E-03 4.47E-03 Tritium H-3 Curies 7.14E+01 1.69E+02 3.10E+02 6.26E+01 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 13 -

Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Kr-85 Curies 2.31E-04 O.OOE+O0 O.OOE+00 O.OOE+0O Kr-88 Curies 1.55E-06 O.OOE+O0 O.OOE+0O 1.21E-06 Kr-85M Curies O.OOE+O0 O.OOE+O0 3.05E-07 O.OOE+00 Xe-133 Curies 2.29E-05 2.43E-05 4.33E-04 1.62E-03 Xe-135 Curies O.OOE+O0 O.OOE+00 0.OOE+0O 2.27E-06 Xe-131M Curies O.OOE+O0 3.34E-05 0.OOE+00 O.OOE+00 Xe-133M Curies O.OOE+O0 O.OOE+0O 0.OOE+O0 4.33E-06 Xe-135M Curies O.OOE+O0 O.OOE+00 0.OOE+O0 1.95E-06 Total For Period Curies 2.55E-04 5.77E-05 4.33E-04 1.63E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 14 -

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Sr-90 Curies 3.90E-04 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 3.90E-04 O.OOE+00 O.OOE+00 O.OOE+00 Tritium H-3 Curies O.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+O0 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

- 15

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Be-7 Curies O.OOE+O0 O.OOE+O0 2.78E-05 O.OOE+0O Y-88 Curies O.OOE+00 O.OOE+O0 0.OOE+00 4.24E-07 Y-94 Curies O.OOE+00 O.OOE+O0 0.OOE+00 1.93E-06 As-76 Curies O.OOE+00 O.OOE+O0 0.OOE+00 7.30E-07 Co-57 Curies 2.16E-06 O.OOE+O0 0.OOE+00 6.78E-07 Co-58 Curies 1.79E-03 4.66E-04 4.49E-04 1.84E-03 Co-60 Curies 4.70E-03 4.52E-03 2.96E-03 2.21E-03 Cr-51 Curies 1.39E-05 O.OOE+O0 5.OOE-05 1.07E-03 Fe-55 Curies 9.22E-04 2.56E-03 8.04E-04 1.03E-03 Fe-59 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 9.06E-07 Mn-54 Curies 9.77E-05 6.54E-05 3.28E-05 3.88E-05 Na-24 Curies 2.39E-06 4.38E-06 4.19E-06 2.30E-06 Nb-95 Curies 2.30E-04 8.47E-05 5.47E-05 1.62E-04 Nb-97 Curies O.OOE+O0 2.89E-06 2.87E-04 3.92E-05 Se-75 Curies 7.19E-07 O.OOE+O0 O.OOE+00 O.OOE+0O Sr-85 Curies 1.04E-06 O.OOE+O0 O.OOE+00 O.OOE+00 Sr-89 Curies 1.26E-05 8.15E-06 3.98E-05 O.OOE+00 Sr-90 Curies O.OOE+00 O.OOE+O0 4.30E-06 O.OOE+O0 Sr-91 Curies O.OOE+00 3.45E-06 O.OOE+00 O.OOE+O0 Sr-92 Curies 1.49E-06 O.OOE+0O O.OOE+O0 O.OOE+00 Y-90M Curies O.OOE+O0 O.OOE+0O 2.87E-07 O.OOE+00 Y-91M Curies O.OOE+00 O.OOE+O0 8.96E-07 1.67E-06 Zn-65 Curies 2.04E-03 2.72E-03 1.01E-03 1.04E-03 Zn-69 Curies O.OOE+00 3.91E-05 2.89E-06 O.OOE+00 Zr-95 Curies 6.OOE-05 2.01E-05 1.94E-05 7.60E-05 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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Cd-115 Curies O.OOE+00 0.OOE+00 0.OOE+00 1.04E-06 Ce-146 Curies O.OOE+00 1.76E-06 0.OOE+00 0.OOE+00 Cs-134 Curies O.OOE+00 1.62E-06 0.OOE+00 0.OOE+00 Cs-137 Curies 9.78E-05 2.24E-04 2.68E-04 1.67E-04 Cs-138 Curies 9.61E-06 1.88E-05 1.07E-05 0.OOE+00 Eu-152 Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Hf-181 Curies O.OOE+00 5.64E-07 0.O0E+00 0.OOE+00 La-142 Curies O.OOE+00 0.OOE+00 0.OOE+00 6.70E-07 Nb-95M Curies O.OOE+00 0.OOE+00 0.OOE+00 7.59E-07 Nd-147 Curies 1.54E-06 0.OOE+00 O.OOE+00 0.OOE+00 Rh-105 Curies O.OOE+00 0.OOE+O0 3.21E-06 5.36E-04 Sb-124 Curies 5.84E-06 6.47E-06 0.OOE+00 4.07E-05 Sb-125 Curies 7.53E-04 1.22E-03 1.01E-03 6.30E-04 Sn-113 Curies O.OOE+00 2.86E-05 0.OOE+00 2.41E-07 Tc-99M Curies O.OOE+00 0.OOE+00 3.28E-06 0.OOE+00 Te-131 Curies 0.OOE+00 0.OOE+00 4.21E-07 0.OOE+00 Te-134 Curies 0.OOE+00 2.89E-05 0.OOE+00 0.OOE+00 Zn-69M Curies 9.16E-07 0.OOE+0O 0.OOE+00 0.OOE+00 Ag-108M Curies 0.OOE+00 2.72E-05 4.80E-06 3.16E-06 Ag-110M Curies 8.47E-06 5.11E-05 1.48E-05 8.87E-07 In-115M Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.14E-06 Sn-117M Curies 2.16E-06 0.OOE+00 0.OOE+00 0.OOE+00 Te-125M Curies 1.19E-02 0.OOE+00 1.98E-04 0.OOE+00 Total For Period Curies 2.27E-02 1.21E-02 7.27E-03 8.89E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Tritium H-3 Curies 1.59E+02 2.57E+02 5.70E+02 1.88E+02 Dissolved And Entrained Gases Ar-41 Curies O.OOE+00 1.03E-05 O.OOE+00 1.90E-05 Kr-85 Curies 2.31E-04 O.OOE+00 O.OOE+00 0.OOE+OO Kr-88 Curies 1.55E-06 O.OOE+00 O.OOE+00 1.21E-06 Kr-85M Curies O.OOE+00 O.OOE+00 3.05E-07 O.OOE+OO Xe-133 Curies 3.97E-05 3.03E-05 6.61E-04 2.28E-03 Xe-135 Curies O.OOE+00 7.87E-07 O.OOE+0O 2.27E-06 Xe-137 Curies O.OE+00 0.O0E+00 0.OOE+0O 1.64E-03 Xe-138 Curies O.OOE+00 2.32E-06 0.OOE+0O 0.OOE+00 Xe-131M Curies O.OOE+00 3.34E-05 0.OOE+0O 0.OOE+00 Xe-133M Curies O.OOE+00 0.OOE+00 0.OOE+0O 4.33E-06 Xe-135M Curies O.OOE+00 0.OOE+00 0.OOE+0O 1.95E-06 Total For Period Curies 2.72E-04 7.71E-05 6.62E-04 3.95E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

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Table 1-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr  % ODCM 2ND Qtr  % ODCM 3RD Qtr  % ODCM 4TH Qtr  % ODCM Bone 5.OOE+00 mRem 2.OOE-03 4.O0E-02 2.76E-04 5.53E-03 2.38E-04 4.75E-03 2.59E-04 5.18E-03 GI-Lli 5.OOE+00 mRem 9.16E-03 1.83E-01 1.46E-03; 2.92E-02 2.83E-03 5.65E-02 2.27E-03 4.55E-02 Kidney 5.OOE+00 mRem 8.88E-03 1.78E-01 9.82E-04 1.96E-02 2.68E-03 5.37E-02 1.55E-03 3.10E-02 Liver 5.OOE+00 mRem 1.63E-03 3.27E-02 1.21E-03 2.42E-02 2.78E-03 5.55E-02 1.77E-03 3.54E-02 Lung 5.OOE+00 mRem 1.34E-03 2.68E-02 1.60E-03 3.20E-02 2.79E-03 5.58E-02 2.03E-03 4.06E-02 Thyroid 5.OOE+00 mRem 1.43E-03 2.87E-02 8.99E-04 1.80E-02 2.65E-03 5.30E-02 1.49E-03 2.97E-02 Total Body 5.OOE+00 mRem 1.18E-03 2.36E-02 1.07E-03 2.14E-02 2.75E-03 5.50E-02 1.65E-03 3.29E-02 Total Body 1.50E+00 mRem 1.18E-03 7.86E-02 1.07E-03 7.13E-02 2.75E-03 1.83E-01 1.65E-03 1.10E-01 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date 0/0 ODCM Receptor Limit Bone 1.00E+01 mRem 2.77E-03 2.77E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.OOE+01 mRem 1.57E-02 1.57E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 1.41E-02 1.41E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.OOE+01 mRem 7.39E-03 7.39E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.OOE+01 mRem 7.77E-03 7.77E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 6.47E-03 6.47E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.OOE+01 mRem 6.64E-03 6.64E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+O0 mRem 6.64E-03 2.21E-01 Maximum Individual Liquid Liquid Effluent TB Annual

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Table iTable 1-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ 0 ODCM Lmt Units 1ST Qtr  %/oODCM 2ND Qtr %bODCM 3RD Qtr  %/oODCM 4TH Qtr /b ODCM Bone 5.OOE+00 mRem 3.03E-02 6.07E-01 7.07E-04 1.41E-02 4.79E-04 9.59E-03 3.20E-04 6.39E-03 GI-Lli 5.OOE+00 mRem 1.09E-02 2.18E-01 3.01E-03 6.02E-02 4.22E-03 8.44E-02 1.47E-03 2.95E-02 Kidney 5.OOE+00 mRem 9.06E-03 1.81E-01 1.74E-03 3.48E-02 3.27E-03 6.54E-02 7.96E-04 1.59E-02 Liver 5.OOE+00 mRem 1.90E-03 3.80E-02 2.29E-03 4.59E-02 3.37E-03 6.75E-02 1.06E-03 2.12E-02 Lung 5.OOE+00 mRem 3.47E-03 6.93E-02 6.31E-03 1.26E-01 7.03E-03 1.41E-01 3.57E-03 7.13E-02 Thyroid 5.OOE+00 mRem 1.30E-03 2.60E-02 1.55E-03 3.10E-02 2.88E-03 5.76E-02 6.82E-04 1.36E-02 Total Body 5.OOE+00 mRem 8.11E-03 1.62E-01 1.94E-03 3.88E-02 3.19E-03 6.38E-02 9.23E-04 1.85E-02 Total Body 1.50E+00 mRem 8.11E-03 5.41E-01 1.94E-03 1.29E-01 3.19E-03 2.13E-01 9.23E-04 6.15E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date 0

/o ODCM Receptor Limit Bone 1.00E+01 mRem 2.77E-03 2.77E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 1.57E-02 1.57E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.OOE+01 mRem 1.41E-02 1.41E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 7.39E-03 7.39E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 7.77E-03 7.77E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.OOE+01 mRem 6.47E-03 6.47E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.OOE+01 mRem 6.64E-03 6.64E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 6.64E-03 2.21E-01 Maximum Individual Liquid Liquid Effluent TB Annual

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TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 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-08 CO-58 3.12E-08 FE-59 9.04E-08 CO-60 1.76E-08 ZN-65 1.19E-07 MO-99 2.98E-07 1-131 3.05E-08 CS-134 4.01E-08 CS-137 3.84E-08 CE-141 4.21E-08 CE-144 1.51E-07 Table 1-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases  : 46 45 65 66 222
2. Total time period for Batch releases (Minutes): 5.14E+03 5.05E+03 7.39E+03 7.24E+03 2.48E+04
3. Maximum time period for a batch release (Minutes): 1.23E+02 1.40E+02 1.35E+02 1.49E+02 1.49E+02
4. Average time period for a batch release (Minutes): 1.12E+02 1.12E+02 1.14E+02 1.10E+02 1.12E+02
5. Minimum time period for a batch release (Minutes): 9.OOE+01 9.OOE+01 9.30E+01 9.20E+01 9.OOE+01
6. Average stream flow during periods of release of liquid Effluent into a flowing stream* (CFS)  : 7.38E+03 3.71E+03 2.88E+03 6.03E+03 5.OOE+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 1-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 69 90 122 99 380
2. Total time period for Batch releases (Minutes): 6.71E+03 9.39E+03 1.22E+04 1.03E+04 3.86E+04
3. Maximum time period for a batch release ( Minutes): 1.25E+02 1.46E+02 1.23E+02 1.60E+02 1.60E+02
4. Average time period for a batch release (Minutes): 9.73E+01 1.04E+02 1.00E+02 1.04E+02 1.02E+02
5. Minimum time period for a batch release (Minutes): 6.OOE+01 8.70E+01 8.50E+01 8.10E+01 6.OOE+01
6. Average stream flow during periods of release of liquid Effluent into a flowing stream* (CFS)  : 7.38E+03 3.71E+03 2.88E+03 6.03E+03 5.OOE+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 1-6A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
3. Maximum Time For A Release (Minutes): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Average Time For A Release (Minutes): 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release (Minutes): 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
6. Total activity for all releases (Curies)  : 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00

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Table 1-6B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases ( Minutes ): 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
3. Maximum Time For A Release ( Minutes ): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Average Time For A Release ( Minutes ): O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release ( Minutes): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
6. Total activity for all releases ( Curies) 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

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2.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2008. These quantities are summarized on a quarterly basis and include any unplanned releases. Tabulations are provided of the offsite air doses calculated in accordance with ODCM 3.4.2 to show conformance with the limits of ODCM 3.1.3, and the offsite organ doses to a member of the public calculated in accordance with ODCM 3.4.3 to show conformance with ODCM 3.1.4.

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

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

a. For noble gases: Less than or equal to 500 mrem/yr. to the whole body and less than or equal to 3000 mrem/yr. to the skin, and
b. For Iodine-131, Iodine-133,tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr. to any organ.

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

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.3 Doses to a Member of the Public Technical Specifications 5.5.4.e and 5.5.4.i state that the dose to a MEMBER OF THE PUBLIC from 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 in 2006 in order to take advantage of additional decay time for short lived radionuclides.

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

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

2.2.2.1 Fission and Activation Gases The released radioactivity is determined using sample analyses results collected as described in section 2.2.1 andthe 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.

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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.

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%

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2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, lB 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.

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

Unit 1 2008 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2008 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4B Unit 1 2008 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5A Unit 2 2008 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 2008 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2008 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 2008.

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

Unit 1 2008 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2008 Gaseous Effluents - Abnormal Release Summary: Table 2-8B

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Table 2-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.09E+00 6.55E+00 7.94E+00 6.61E+00
2. Average Release rate for period uCi/sec 7.72E-01 8.31E-01 1.01E+00 8.39E-01
3. Percent of Applicable Limit  %* * *
  • B. Radioiodines
1. Total Iodine-131 Curies 5.83E-06 8.72E-06 O.OOE+00 9.43E-07
2. Average Release rate for period uCi/sec 7.39E-07 1.11E-06 O.OOE+00 1.20E-07
3. Percent of Applicable Limit  %* * *
  • C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies O.OOE+00 2.10E-07 9.89E-07 7.12E-08
2. Average Release rate for period uCi/sec O.OOE+00 2.67E-08 1.26E-07 9.034E-09
3. Percent of Applicable Limit  %* * *
1. Total Release Curies 2.18E+00 3.17E+00 3.04E+00 2.26E+00
2. Average Release rate for period uCi/sec 2.77E-01 4.02E-01 3.86E-01 2.87E-01
3. Percent of Applicable Limit * * *
  • E. Gross Alpha
1. Total Release Curies O.OOE+00 1.28E-05 O.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec O.OOE+00 1.62E-06 O.OOE+00 O.OOE+00
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

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Table 2-1B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.54E-01 2.72E-01 8.55E-01 4.52E+00
2. Average Release rate for period uCi/sec 3.23E-02 3.44E-02 1.08E-01 5.73E-01
3. Percent of Applicable Limit  %* * *
  • B. Radioiodines
1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 3.10E-08
2. Average Release rate for period uCi/sec O.OOE+00 0.OOE+00 O.OOE+00 3.93E-09
3. Percent of Applicable Limit  %* * *
  • C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies 3.33E-08 7.94E-08 7.41E-08 2.08E-07
2. Average Release rate for period uCi/sec 4.22E-09 1.01E-08 9.40E-09 2.639E-08
3. Percent of Applicable Limit  %* * *
1. Total Release Curies 3.06E+00 1.66E+01 3.OOE+00 6.10E+00
2. Average Release rate for period uCi/sec 3.88E-01 2.10E+00 3.81E-01 7.73E-01
3. Percent of Applicable Limit * * *
  • E. Gross Alpha
1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

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Table 2-1C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.34E+00 6.82E+00 8.80E+00 1.11E+01
2. Average Release rate for period uCi/sec 8.05E-01 8.65E-01 1.12E+00 1.41E+00
3. Percent of Applicable Limit  %**

B. Radioiodines

1. Total Iodine-131 Curies 5.83E-06 8.72E-06 O.OOE+00 9.74E-07
2. Average Release rate for period uCi/sec 7.39E-07 1.11E-06 O.OOE+00 1.24E-07
3. Percent of Applicable Limit  %* * *
  • C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies 3.33E-08 2.90E-07 1.06E-06 2.79E-07
2. Average Release rate for period uCi/sec 4.22E-09 3.67E-08 1.35E-07 3.543E-08
3. Percent of Applicable Limit  %* * *
1. Total Release Curies 5.24E+00 1.97E+01 6.04E+00 8.36E+00
2. Average Release rate for period uCi/sec 6.65E-01 2.50E+00 7.66E-01 1.06E+00
3. Percent of Applicable Limit * * *
  • E. Gross Ailha
1. Total Release Curies O.OOE+00 1.28E-05 O.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec O.OOE+00 1.62E-06 O.OOE+00 O.OOE+00
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 6.09E+00 6.55E+00 7.91E+00 6.61E+00 Total For Period Curies 6.09E+00 6.55E+00 7.91E+00 6.61E+00 Iodines 1-131 Curies 5.83E-06 8.72E-06 O.OOE+00 9.43E-07 1-133 Curies 1.04E-04 1.85E-04 O.OOE+00 9.OOE-06 Total For Period Curies 1.10E-04 1.93E-04 O.OOE+00 9.94E-06 Particulates Sr-89 Curies O.OOE+O0 2.1OE-07 9.89E-07 7.12E-08 Total For Period Curies O.OOE+O0 2.10E-07 9.89E-07 7.12E-08 Tritium H-3 Curies 2.18E+00 3.17E+00 3.04E+00 2.26E+00 Gross Alpha G-Alpha Curies O.OOE+00 1.28E-05 O.OOE+00 O.OOE+O0 Total For Period Curies O.OOE+O0 1.28E-05 O.OOE+00 O.00E4-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.

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Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released, Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies O.OOE+00 O.OOE+00 2.68E-02 O.OOE+00 Total For Period Curies 0.00E+00 0.00E+00 2.68E-02 0.00E+00 Iodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

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Table 2-2B3 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+00 O.OOE+00 5.32E-01 4.37E+00 Total For Period Curies O.OOE+00 O.OOE+O0 5.32E-01 4.37E+00 lodines 1-131 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 2.68E-08 Total For Period Curies O.OOE+00 O.OOE+00 O.OOE+00 2.68E-08 Particulates Co-60 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 2.47E-08 Sr-89 Curies O.OOE+O0 7.94E-08 2.69E-08 1.83E-07 Sr-90 Curies 3.33E-08 O.OOE+O0 4.72E-08 O.OOE+O0 Total For Period Curies 3.33E-08 7.94E-08 7.41E-08 2.08E-07 Tritium H-3 Curies 3.03E+00 1.65E+01 2.96E+00 6. 1OE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.54E-01 2.71E-01 3.22E-01 1.48E-01 Xe-133M Curies O.OOE+O0 O.OOE+O0 7.59E-05 O.OOE+O0 Xe-133 Curies 2.20E-04 6.12E-04 9.21E-04 7.07E-03 Total For Period Curies 2.54E-01 2.72E-01 3.23E-01 1.55E-01 lodines 1-131 Curies O.OOE+00 O.OOE+00 0.OOE+00 4.25E-09 Total For Period Curies O.OOE+00 O.OOE+00 O.OOE+O0 4.25E-09 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium H-3 Curies 3.58E-02 6.01E-02 3.61E-02 1.66E-03 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 6.09E+00 6.55E+00 8.45E+00 1.10E+01 Total For Period Curies 6.09E+00 6.55E+00 8.45E+00 1.10E+01 lodines 1-131 Curies 5.83E-06 8.72E-06 O.OOE+O0 9.70E-07 1-133 Curies 1.04E-04 1.85E-04 O.OOE+O0 9.OOE-06 Total For Period Curies 1.10E-04 1.93E-04 O.OOE+O0 9.97E-06 Particulates Co-60 Curies O.OOE+00 O.OOE+O0 O.OOE+O0 2.47E-08 Sr-89 Curies O.OOE+00 2.90E-07 1.02E-06 2.55E-07 Sr-90 Curies 3.33E-08 O.OOE+O0 4.72E-08 O.OOE+00 Total For Period Curies 3.33E-08 2.90E-07 1.06E-06 2.79E-07 Tritium H-3 Curies 5.21E+00 1.97E+01 6.OOE+00 8.36E+00 Gross Alpha G-Alpha Curies O.OOE+00 1.28E-05 O.OOE+OO O.OOE+00 Total For Period Curies O.OOE+O0 1.29E-05 0.00E+00O O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 2.54E-01 2.71E-01 3.22E-01 1.48E-01 Xe- 133M Curies O.OOE+O0 O.OOE+O0 7.59E-05 O.OOE+O0 Xe- 133 Curies 2.20E-04 6.12E-04 2.77E-02 7.07E-03 Total For Period Curies 2.54E-01 2.72E-01 3.50E-01 1.55E-01 Iodines 1-131 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 4.25E-09 Total For Period Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 4.25E-09 Particulates No Nuclides Found Curies O.OOE+O0 0.OOE+00 O.OOE+0O O.OOE+00 Tritium H-3 Curies 3.58E-02 6.01E-02 3.61E-02 1.66E-03 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 0.OOE+00 Kr-90 Curies O.OOE+O0 O.OOE+00 O.OOE+O0 0.OOE+00 Xe-127 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 0.OOE+00 Total For Period Curies O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+OO Iodines No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+00 Tritium No Nuclides Found Curies 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 0.OOE+O0 0.OOE+OO 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Iodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 Kr-90 Curies O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 Total For Period Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 lodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+O0 0.O0E+00 Tritium No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 0.OOE+00 O.OOE+00 O.OOE+O0 lodi nes No Nuclides Found Curies O.OOE+O0 0.OOE+OO 0.OOE+0O 0.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+OO 0.OOE+O0 0.OOE+0O Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 0.OOE+OO 0.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Kr-90 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Xe-127 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 lodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 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.

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Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Iodines No Nuclides Found O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

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Table 2-4A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr 0/ ODCM 2ND Qtr  %/oODCM 3RD Qtr  % ODCM 4TH Qtr %bODCM Gamma Air 5.OOE+00 mRad 1.94E-03 3.88E-02 2.09E-03 4.17E-02 2.52E-03 5.04E-02 2.11E-03 4.21E-02 Beta Air 1.OOE+01 mRad 6.84E-04 6.84E-03 7.36E-04 7.36E-03 8.90E-04 8.90E-03 7.43E-04 7.43E-03 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date  %/oODCM Receptor Limit Gamma Air 1.OOE+01 mRad 8.65E-03 8.65E-02 Site Boundlary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.OOE+01 mRad 3.05E-03 1.53E-02 Site Boundlary SSE Mixed Mode R Air Dose Beta Annual

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Table 2-4B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units 1ST Qtr 0/0 ODCM 2ND Qtr  %/oODCM 3RD Qtr O/o ODCM 4TH Qtr 0/o ODCM Gamma Air 5.OOE+00 mRad 8.09E-05 1.62E-03 8.63E-05 1.73E-03 2.72E-04 5.44E-03 1.44E-03 2.88E-02 Beta Air 1.OOE+01 mRad 2.86E-05 2.86E-04 3.05E-05 3.05E-04 9.59E-05 9.59E-04 5.07E-04 5.07E-03 Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Year to End Date  % ODCM Receptor Limit Gamma Air 1.00E+01 mRad 1.88E-03 1.88E-02 Site Bound ary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.OOE+01 mRad 6.62E-04 3.31E-03 Site Bound ary SSE Mixed Mode R Air Dose Beta Annual

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Table 2-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ ODCM Lint Units 1ST Qtr 0 0  %/oODCM 0/0 ODCM 2ND Qtr /b ODCM 3RD Qtr /b ODCM 4TH Qtr Bone 7.50E+00 mRem 6.02E-07 8.03E-06 3.53E-06 4.70E-05 1.04E-05 1.38E-04 9.45E-07 1.26E-05 GI-Lli 7.50E+00 mRem 2.31E-04 3.09E-03 3.49E-04 4.66E-03 2.86E-04 3.81E-03 2.46E-04 3.27E-03 Kidney 7.50E+00 mRem 2.32E-04 3.10E-03 3.50E-04 4.67E-03 2.86E-04 3.81E-03 2.46E-04 3.28E-03 Liver 7.50E+00 mRem 2.32E-04 3.09E-03 3.50E-04 4.67E-03 2.86E-04 3.81E-03 2.46E-04 3.28E-03 Lung 7.50E+00 mRern 2.31E-04 3.09E-03 3.49E-04 4.65E-03 2.86E-04 3.81E-03 2.46E-04 3.27E-03 Thyroid 7.50E+00 mRern 3.75E-04 5.OOE-03 5.75E-04 7.66E-03 2.86E-04 3.81E-03 2.66E-04 3.55E-03 Total Body 7.50E+00 mRern 2.32E-04 3.09E-03 3.50E-04 4.66E-03 2.86E-04 3.81E-03 2.46E-04 3.28E-03 Cumulative Doses per Year Organ ODCM Lint Units Year to Ending Date 0/0 ODCM Receptor Limit Bone 1.500E+01 mRem 1.544E-05 1.029E-04 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli 1.500E+01 mRem 1.112E-03 7.417E-03 Gas Controlling Receptor Iodine/Part Dose Annual Kidney 1.500E+01 mRem 1.114E-03 7.427E-03 Gas Controlling Receptor Iodine/Part Dose Annual Liver 1.500E+01 mRem 1.113E-03 7.421E-03 Gas Controlling Receptor Iodine/Part Dose Annual Lung 1.500E+01 mRem 1.112E-03 7.411E-03 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid 1.500E+01 mRem 1.501E-03 1.001E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body 1.500E+01 mRem 1.113E-03 7.418E-03 Gas Controlling Receptor Iodine/Part Dose Annual

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Table 2-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Organ 0 0 ODCM Lint Units 1ST Qtr /o ODCM 2ND Qtr /o ODCM 3RD Qtr  %/oODCM 4TH Qtr  %/oODCM Bone 7.50E+00 mRem 1.39E-05 1.86E-04 9.66E-07 1.29E-05 2.01E-05 2.68E-04 1.34E-06 1.79E-05 GI-Lli 7.50E+00 mRem 4.19E-04 5.59E-03 2.27E-03 3.02E-02 4.01E-04 5.35E-03 7.68E-04 1.02E-02 Kidney 7.50E+00 mRem 4.19E-04 5.58E-03 2.27E-03 3.02E-02 4.01E-04 5.35E-03 7.68E-04 1.02E-02 Liver 7.50E+00 mRem 4.19E-04 5.58E-03 2.27E-03 3.02E-02 4.01E-04 5.35E-03 7.68E-04 1.02E-02 Lung 7.50E+00 mRem 4.19E-04 5.58E-03 2.27E-03 3.02E-02 4.01E-04 5.35E-03 7.68E-04 1.02E-02 Thyroid 7.50E+00 mRem 4.19E-04 5.58E-03 2.27E-03 3.02E-02 4.01E-04 5.35E-03 7.68E-04 1.02E-02 Total Body 7.50E+00 mRern 4.22E-04 5.63E-03 2.27E-03 3.02E-02 4.06E-04 5.41E-03 7.68E-04 1.02E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date 0/o ODCM Receptor Limit Bone 1.500E+01 mRem 3.635E-05 2.424E-04 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli 1.500E+01 mRem 3.853E-03 2.569E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney 1.500E+01 mRem 3.853E-03 2.569E-02 Gas Controlling Receptor Iodine/Part Dose Annual Liver 1.500E+01 mRem 3.853E-03 2.569E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung 1.500E+01 mRem 3.853E-03 2.569E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid 1.500E+01 rnRem 3.853E-03 2.569E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body 1.500E+01 mRem 3.861E-03 2.574E&02 Gas Controlling Receptor Iodine/Part Dose Annual

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TABLE 2-6 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS EFFLUENT ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

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

MN-54 4. 17E-14 KR-87 4. 64E-'08 CO-58 7 .65E- 14 KR-88 7.46E-08 FE-59 2 .53E-14 XE-133 4.71E-08 CO-60 6. 01E-14 XE-133M 1.42E-07 ZN-65 2 .40E-13 XE-135 1.58E-08 MO-99 4 .46E-13 XE-138 1.21E-07 CS-134 5. 17E-14 1-131 5. 95E-14 CS-137 6. 95E-15 1-133 8. 96E-14 CE-141 4. 28E-14 CE-144 1. 64E-13

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Table 2-7A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 0 0 1 4 5
2. Total time period for batch releases (Minutes) 0.OOE+0O 0.OOE+00 3.04E+02 1.36E+03 1.66E+03
3. Maximum time period for a batch release (Minutes) 0.OOE+00 0.OOE+00 3.04E+02 3.87E+02 3.87E+02
4. Average time period for a batch release ( Minutes) 0.OOE+00 0.OOE+00 3.04E+02 3.40E+02 3.33E+02
5. Minimum time period for a batch release ( Minutes) 0.OOE+00 0.OOE+00 3.04E+02 2.69E+02 2.69E+02

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Table 2-7B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 49 57 66 39 211
2. Total time period for batch releases (Minutes) 3.75E+03 4.26E+03 6.21E+03 5.26E+03 1.95E+04
3. Maximum time period for a batch release (Minutes) 4.98E+02 3.35E+02 5.04E+02 5.35E+02 5.35E+02
4. Average time period for a batch release (Minutes) 7.64E+01 7.48E+01 9.40E+01 1.35E+02 9.23E+01
5. Minimum time period for a batch release (Minutes )O 3.OOE+O0 3.OOE+O0 3.OOE+O0 3.OOE+O0 3.OOE+O0

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Table 2-8A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes): 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
3. Maximum Time For A Release (Minutes): 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
4. Average Time For A Release (Minutes): O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release (Minutes): 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
6. Total activity for all releases (Curies) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00

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Table 2-8B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes): O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00
3. Maximum Time For A Release (Minutes): O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00
4. Average Time For A Release (Minutes): O.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00
5. Minimum Time For A Release (Minutes): O.OOE+0O 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00
6. Total activity for all releases (Curies ) O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00

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3.0 SOLID WASTE 3.1 Regulatory Requirements 3.1.1 Solid Radioactive Waste System PCP B.3.1 states in part that the radwaste solidification system shall be operable and used for the solidification and packaging of radioactive wastes to ensure meeting the requirements of 10CFR Part 20 and 10CFR Part 71 prior to shipment of radioactive wastes from the site.

3.1.2 Reporting Requirements PCP B.5.1.1 states in part that the Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units as outlined in Regulatory Guide 1.21, with data summarized on a six-month basis following the format of Appendix B thereof.

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

The error involved in determining the contents of solid radwaste shipments is estimated to be less than + or - 15%.

TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-2008 Ending: 30-Jun-2008

$12?ID S0 WKST 'HIPllf k!#(TEFb IAI

1. Tye f Was UNITS - 67ff S -~
a. Spent resins, Filter sludges, m3 1.666 evaporator bottoms, etc. Ci* 155.2
b. Dry compressible waste, contaminated m3 40.39 equipment, etc. Ci* 7.207
c. Irradiated components, control m3 5.663E-4 rods, etc. Ci* 0.597
d. Other (describe) m3 None Ci* None r~ua op~ao~uqoiomoiun(oyt~ype~ofwasze 6 55 65
a. 13Ni 45.11% "Co 23.68% Fe 10.96% Zn 9.03% 125Sb 2.12% 58 Co 2.10% 3 H 1.79%

14C 1.24%

63

b. 65Zn 21.88%95 60Co 15.70% Ni 12.53% 55Fe 10.41% 3H 10.16% 58 Co 5.40% 95Zr 5.08%

14C 4.55% Nb 4.48% 5 1Cr 1.95% 137Cs 1.77% 7 Be 1.26% 12 5Sb 1.21% 99"Tc 1.08%

55 54 63

c. Fe 74.97% 6°Co 18.11% Mn 5.13% Ni 1.54%
d. None
  • Measured and/or estimated by correlations in accordance with 10CFR61.55.

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TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-2008 Ending: 30-Jun-2008 (Continued) f 3., Sold Wase Dispositions Number of Shipments Mode of Transportation Destination 3 Highway Clive, Utah 3 Highway Barnwell, SC 11 Rail Clive, Utah L 4' A veofe inlpe aofsle *or burial/processlng_

Container Description Type of Container Number of Containers Container Volume (M3 )

a. Radlok 500 Inner package Liner 1 3.85 CNS-8-120 Inner package Liner 2 3.41
b. 20' Seavan General Design Package 8 29.45 20' Intermodal General Design Package 4 29.25
c. 1 liter bottle Inner package 1 0.001
a. None b. None lriiiat~i Fel' hIp n~D-isposif io)

Number of Shipments Mode of Transportation Destination None N/A N/A

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TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jul-2008 Ending: 31-Dec-2008 (Continued)

SOLID WASTE OFFSITE FOR BURIALOR'DI PHIPED rait4dfu)J--

j~

Cjipf 2 Waste.- 6-Months

a. Spent resins, Filter sludges, m3 0.348 evaporator bottoms, etc. Ci* 2.677 m3
b. Dry compressible waste, contaminated 19.66 equipment, etc. Ci* 0.958
c. Irradiated components, control Ci* None rods, etc. None 3

m

d. Other (describe) Ci* None None tZ.--;
a. 55Fe 32.64% 6°Co 21.47% 6Zn 20.72% 14C 6.55% 3H 3.68% 58 Co 3.47% 137Cs 2.19%

63Ni 2.09% 95Zr 2.08% 12 5Sb 1.47%

b. 65 Zn 14.51% 95Zr 10.93% 55Fe 10.71% 6 "Co 9.98% 95 Nb 9.54% 3 H 9.38% 58Co 7.93%

51Cr 6.42% 99Tc 5.85% 63Ni 4.76% 14C 4.44% 1291 1.16%

c. None
d. None
  • Measured and/or estimated by correlations in accordance with 10CFR61.55.

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TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jul-2008 Ending: 31-Dec-2008 (Continued)

  • '*:o* *
  • Oll wale~isps ito~

ln <N; Number of Shipments Mode of Transportation Destination 9 Highway Clive, Utah 9 Rail Clive, Utah 4TVye of Containers (Shippedfsf r R I/rocessig)*

Container Description Type of Container Number of Containers Container Volume 3 (M )

a. 55 Gal Drum General Design Package 9 0.212
c. 55 Gal Drum General Design Package 5 0.212 20' Seavan General Design Package 11 29.45 20' Intermodal General Design Package 12 29.25
  • .54,SolMidfi ationAgent <Xo ., 71
a. None b. None

ýB Irradiated FueI§hipmrents (Dispositio) Y Number of Shipments Mode of Transportation Destination None N/A N/A

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

4.2 Demonstration of Compliance However, this assessment has been performed for 2008 using the methods described in ODCM 6.2 and is included in this section as Table 4-1.

Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Location Name: Visitor Center Distance (kilometers): 3.06E-01 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): 8.80E-06 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 8.80E-06 D/Q (m-2): 6.20E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 3.02E-09 3.02E-09 2.03E-09 1.65E-09 9.72E-09 Liver mRem 2.04E-06 8.20E-06 2.15E-06 3.18E-06 1.56E-05 Total Body mRem 2.04E-06 8.20E-06 2.15E-06 3.18E-06 1.56E-05 Thyroid mRem 2.23E-06 8.52E-06 2.15E-06 3.20E-06 1.61E-05 Kidney mRem 2.04E-06 8.20E-06 2.15E-06 3.18E-06 1.56E-05 Lung mRem 2.04E-06 8.20E-06 2.15E-06 3.18E-06 1.56E-05 GI-Lli mRem 2.04E-06 8.20E-06 2.15E-06 3.18E-06 1.56E-05 NG Total Body mRem 2.14E-05 2.30E-05 2.96E-05 3.76E-05 1.12E-04 Whole Body Dose mRem 2.35E-05 3.12E-05 3.18E-05 4.08E-05 1.27E-04

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Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Location Name: Service Water Pond Distance (kilometers): 9.66E-01 Sector: N Occupancy Factor: 7.57E-03 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3): 4.74E-05 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 4.74E-05 D/Q (m-2): 1.31E-07 Mixed Mode Release Noble Gas X/Q (sec/m3): 9.75E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 9.75E-07 D/Q (m-2): 2.78E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 3.64E-09 4.88E-09 1.24E-09 3.88E-09 1.36E-08 Liver mRem 1.25E-06 5.02E-06 1.32E-06 1.95E-06 9.54E-06 Total Body mRem 1.25E-06 5.02E-06 1.32E-06 1.95E-06 9.54E-06 Thyroid mRem 1.37E-06 5.22E-06 1.32E-06 1.96E-06 9.86E-06 Kidney mRem 1.25E-06 5.02E-06 1.32E-06 1.95E-06 9.54E-06 Lung mRem 1.25E-06 5.02E-06 1.32E-06 1.95E-06 9.54E-06 GI-Lli mRem 1.25E-06 5.02E-06 1.32E-06 1.95E-06 9.54E-06 NG Total Body mRem 1.31E-05 1.41E-05 1.81E-05 2.30E-05 6.84E-05 Whole Body Dose mRem 1.44E-05 1.91E-05 1.95E-05 2.50E-05 7.79E-05

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Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Location Name: River Water Discharge - Air Distance (kilometers): 1.64E+00 Sector: N Occupancy Factor: 1.14E-02 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3): 1.63E-05 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 1.63E-05 D/Q (m-2): 4.55E-08 Mixed Mode Release Noble Gas X/Q (sec/m3): 7.05E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 7.05E-07 D/Q (m-2): 1.39E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 3.16E-09 3.96E-09 1.35E-09 2.94E-09 1.14E-08 Liver mRem 1.36E-06 5.47E-06 1.43E-06 2.12E-06 1.04E-05 Total Body mRem 1.36E-06 5.47E-06 1.43E-06 2.12E-06 1.04E-05 Thyroid mRem 1.49E-06 5.68E-06 1.43E-06 2.13E-06 1.07E-05 Kidney mRem 1.36E-06 5.47E-06 1.43E-06 2.12E-06 1.04E-05 Lung mRem 1.36E-06 5.47E-06 1.44E-06 2.12E-06 1.04E-05 GI-Lli mRem 1.36E-06 5.47E-06 1.43E-06 2.12E-06 1.04E-05 NG Total Body mRem 1.43E-05 1.54E-05 1.98E-05 2.51E-05 7.45E-05 Whole Body Dose 1.57E-05 2.08E-05 2.12E-05 2.72E-05 8.49E-05

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5.0 TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190) 5.1 Regulatory Requirements Technical Specification 5.5.4.j states that the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem (as stated in ODCM 5.1).

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

5.2 Demonstration of Compliance Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded during 2008, no calculations were required.

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

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

- 66 -

7.1.2 Description of Deviations There were no deviations during 2008.

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

7.2.2 Description of Deviations There were no deviations during 2008.

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

7.3.2 Description of Deviations There were two deviations from liquid effluent sampling requirements during 2008.

Unit 1 had a deviation on October 17, 2008, when the service water flow transmitter was erratic for a period of - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This event was documented in CR2008110644.

Unit 2 had a deviation on February 14, 2008, when the autosampler for Turbine Building Sump 2A failed to collect two samples for the day. Details of this event are documented in condition report 2008101423.

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

8.2 Description of Changes The 2008 revision to the Farley ODCM included the following changes: the outdated references to the Farley QA Manual were removed from the ODCM in Section 2.1.5, Section 3.1.6, and in the References Section; and the requirements of the onsite radiological groundwater protection program were added to the Farley Radiological Environmental Monitoring Program in the ODCM Table 4-1, Table 4-5 and Figure 4-5.

9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR SOLID RADWASTE TREATMENT SYSTEMS 9.1 Regulatory Requirements ODCM 7.2.2.7 states in part that, as required by ODCM 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluents Release Report covering the period in which the change was reviewed and accepted for implementation.

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

9.2 Description of Major Changes There were no major changes during 2008.

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2008 Enclosure 3 Vogtle Annual Radioactive Effluent Release Report for 2008

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERA TING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68AND NPF-81 ANNUAL RADIOACTIVE EFFLUENTRELEASE REPORT FOR JANUARY 12008 TO DECEMBER 31,2008 Page 1 of 76

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2008 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 9 1.1 Regulatory Requirements 9 1.1.1 Concentration Limits 9 1.1.2 Dose Limits 9 1.2 Effluent Concentration Limit (ECL) 9 1.3 Measurements and Approximations of Total Radioactivity 10 1.3.1 Total Radioactivity Determination 10 1.3.2 Total Error Estimation 12 1.4 Liquid Effluent Release Data 13 1.5 Radiological Impact Due to Liquid Releases 13 1.6 Liquid Effluents - Batch Releases 13 1.7 Liquid Effluents- Abnormal Releases 13 2.0 Gaseous Effluents 33 2.1 Regulatory Requirements 33 2.1.1 Dose Rate Limits 33 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 33 2.1.3 Doses to a Member of the Public 33 2.2 Measurements and Approximations of Total Radioactivity 34 2.2.1 Sample Collection and Analysis 34 Page 2 of 76

SECTION TITLE PAGE 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 35 2.2.2.1 Fission and Activation Gases 35 2.2.2.2 Radioiodines, Tritium and Particulate Releases 35 2.2.2.3 Gross Alpha Release 35 2.2.3 Total Error Estimation 36 2.3 Gaseous Effluent Release Data 37 2.4 Radiological Impact Due to Gaseous Releases 38 2.5 Gaseous Effluents - Batch Releases 38 3.0 Solid Waste 67 3.1 Regulatory Requirements 67 3.1.1 Solid Radioactive Waste System 67 3.1.2 Reporting Requirements 67 3.2 Solid Waste Data 67 4.0 Doses to Members of the Public Inside the Site Boundary 72 4.1 Regulatory Requirements 72 4.2 Demonstration of Compliance 72 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 74 5.1 Regulatory Requirements 74 5.2 Demonstration of Compliance 74 Page 3 of 76

SECTION TITLE PAGE 6.0 Meteorological Data 74 7.0 Program Deviations 74 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 74 7.1.1 Regulatory Requirement 74 7.1.2 Description of Deviations 74 7.2 Tanks Exceeding Curie Content Limits 75 7.2.1 Regulatory Requirements 75 7.2.2 Description of Deviations 75 8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 75 8.1 Regulatory Requirements 75 8.2 Description of Changes 75 9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 76 9.1 Regulatory Requirements 76 9.2 Description of Major Changes 76 Page 4 of 76

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2008 TABLE OF CONTENTS TABLE LIST OF TABLES PAGE Table 1-1A Liquid Effluents - Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 14 Table 1-1B Liquid Effluents - Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 15 Table 1-1C Liquid Effluents - Summation of All Releases Site (Quarters 1,2,3, and 4) 16 Table 1-2A Liquid Effluents - Summation of All Releases Unit 1 (Quarters 1,2,3, and 4) 17 Table 1-2B Liquid Effluents - Summation of All Releases Unit 2 (Quarters 1,2,3, and 4) 19 Table 1-2C Liquid Effluents - Summation of All Releases 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) 23 Table 1-3B Doses to a Member of the Public Due to Liquid Releases Unit 2 (Quarters 1,2,3, and 4) 24 Table 1-3C Doses to a Member of the Public Due to Liquid Releases Site (Quarters 1,2,3, and 4) 25 Page 5 of 76

TABLE LIST OF TABLES PAGE TABLE LIST OF TABLES PAGE Table 1-4 Minimum Detectable Concentration Liquid Sample Analysis 26 Table 1-5A Liquid Effluents - Batch Release Summary Unit 1 27 Table 1-5B Liquid Effluents - Batch Release Summary Unit 2 28 Table 1-5C Liquid Effluents - Batch Release Summary Site 29 Table 1-6A Liquid Effluents - Abnormal Release Summary Unit 1 30 Table 1-6B Liquid Effluents - Abnormal Release Summary Unit 2 31 Table 1-6C Liquid Effluents - Abnormal Release Summary Site 32 Table 2-1A Gaseous Effluents - Summation of All Releases .- Unit 1 (Quarters 1,2,3, and 4) 39 Table 2-1B Gaseous Effluents - Summation of All Releases - Unit 2 (Quarters 1,2,3, and 4) 40 Table 2-1C Gaseous Effluents - Summation of All Releases - Site (Quarters 1,2,3, and 4) 41 Table 2-2A Gaseous Effluents - Mixed Mode Releases Unit 1 (Quarters 1,2,3, and 4) 42 Table 2-2B Gaseous Effluents - Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 44 Table 2-2C Gaseous Effluents - Mixed Mode Releases Site (Quarters 1,2,3, and 4) 46 Page 6 of 76

TABLE LIST OF TABLES PAGE TABLE LIST OF TABLES PAGE Table 2-3A Gaseous Effluents - Ground Level Releases Unit 1 (Quarters 1,2,3, and 4) 48 Table 2-3B Gaseous Effluents - Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 50 Table 2-3C Gaseous Effluents - Ground Level Releases Site (Quarters 1,2,3, and 4) 52 Table 2-4A Air Doses Due to Noble Gases in Gaseous Releases Unit 1(Quarters 1,2,3, and 4) 54 Table 2-4B Air Doses Due to Noble Gases in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 55 Table 2-4C Air Doses Due to Noble Gases in Gaseous Releases Site (Quarters 1,2,3, and 4) 56 Table 2-5A Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit 1 (Quarters 1,2,3, and 4) 57 Table 2-5B Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 58 Table 2-5C Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Site (Quarters 1,2,3, and 4) 59 Page 7 of 76

TABLE LIST OF TABLES PAGE Table 2-6 Minimum Detectable Concentrations Gaseous Sample Anayses 60 Table 2-7A Gaseous Effluents - Batch Release Summary Unit 1 61 Table 2-7B Gaseous Effluents - Batch Release Summary Unit 2 62 Table 2-7C Gaseous Effluents - Batch Release Summary Site 63 Table 2-8A Gaseous Effluents - Abnormal Release Summary Unit 1 64 Table 2-8B Gaseous Effluents - Abnormal Release Summary Unit 2 65 Table 2-8C Gaseous Effluents - Abnormal Release Summary Site 66 Table 3-1 Solid Waste and Irradiated Fuel Shipments 68 Table 4-1 Doses to a Member of the Public Due to Activities Inside the Site Boundary 73 Page 8 of 76

1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration Limits In accordance with Technical Specification 5.5.4.b, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 E-04 gCi/mI 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, l'-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2.

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

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

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

Page 9 of 76

1.3 Measurements and Approximations of Total Radioactivity 1.3.1 Total Radioactivity Determination Prior to the release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3 "Radioactive Liquid Waste Sampling and Analysis Program". A sample from each tank which is planned for release is analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks, which are released. Liquid radwaste sample analyses are performed as follows:

MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.
2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gases with computerized data reduction
3. Tritium Monthly Distillation and Composite liquid scintillation counting
4. Gross Alpha Monthly Gas flow proportional Composite counting
5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting
6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting Page 10 of 76

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-1 34, Cs-1 37, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

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 ifthe 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. Ifthe release is not permissible, appropriate warnings will be displayed on the computer screen. Ifthe release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for approval and release. When the release is completed, the necessary data from the release (i.e., release volume, etc.) are provided by the Operations Department to the Chemistry Department. These data are input to the computer and a post-release printout is generated. The post release printout contains the actual release rates, release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

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

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1.3.2 Total Error Estimation The total or maximum error associated with the effluent measurement includes the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in 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 12 of 76

1.3.2 Total Error Estimation cont'd

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

Level Indicator error 10%

Operator Interpretation of gauge 10%

TOTAL ERROR 14%

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

Flow totalizer error 10%

Operator interpretation of gauge 10%

TOTAL ERROR 14%

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

Compositing sample error 5%

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

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

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

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

1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases for this reporting period.

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Table 1-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Ouarter 2ND Quarter 3RD Ouarter 4TH Ouarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 1.35E-02 2.06E-03 1.14E-02 3.99E-03
2. Average diluted concentration during period uCi/mL 2.08E-08 1.25E-08 3.47E-08 2.11E-08
3. Percent of Applicable Limit  %

B. Tritium

1. Total Release Curies 3.16E+02 7.64E+01 1.46E+02 4.70E+01
2. Average diluted Concentration during period uCi/mL 4.85E-04 4.62E-04 4.45E-04 2.48E-04
3. Percent of Applicable Limit  %

C. Dissolved and Entrained Gases

1. Total Release Curies 7.92E-03 7.63E-05 1.48E-03 2.91E-03
2. Average diluted Concentration during period uCi/mL 1.21E-08 4.62E-10 4.52E-09 1.54E-08
3. Percent of Applicable Limit  %

D: Gross Alpha Radioactivity

1. Total Release Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 8.27E+05 3.04E+05 5.71E+05 3.73E+05 F. Volume of Dilution Water Used Liters 6.53E+08 1.65E+08 3.28E+08 1.89E+08
  • Applicable limits are expressed in terms of dose.

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

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Table 1-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Tvna nf Iffhant IInitc niinlrt-ar 2ND Ouarter 3RD Ouarter 4TH Ouarter 4TH 14ZT 2ND Ouarter 3RD Ouarter Ouarter A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 1.05E-02 1.29E-03 2.27E-02 1.63E-02
2. Average diluted concentration during period uCi/mL 1.94E-08 1.05E-08 1.81E-08 4.63E-08
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 2.45E+02 5.54E+01 3.15E+02 1.63E+02
2. Average diluted Concentration during period uCi/mL 4.53E-04 4.53E-04 2.50E-04 4.65E-04
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release Curies 6.16E-03 8.79E-06 9.13E-02 5.93E-03
2. Average diluted Concentration during period uCi/mL 1.14E-08 7.18E-11 7.26E-08 1.69E-08
3. Percent of Applicable Limit D: Gross Alpha Radioactivity
1. Total Release Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 0.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 6.33E+05 2.02E+05 1.50E+06 7.71E+05 F. Volume of Dilution Water Used Liters 5.41E+08 1.22E+08 1.26E+09 3.51E+08
  • Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-313 of this report.

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Table 1-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan- 2008 Ending: 31-Dec-2008 Type of Effluent Ilnitc I CT nm.=rtar )Nfn lm.mrtar qDn lumn+r AT4 f"=rmmar A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 2.41E-02 3.35E-03 3.41E-02 2.03E-02
2. Average diluted concentration during period uCi/mL 2.02E-08 1.16E-08 2.15E-08 3.75E-08
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 5.62E+02 1.32E+02 4.60E+02 2.10E+02
2. Average diluted Concentration during period uCi/mL 4.70E-04 4.58E-04 2.90E-04 3.89E-04
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release Curies 1.41E-02 8.51E-05 9.28E-02 8.84E-03
2. Average diluted Concentration during period uCi/mL 1.18E-08 2.96E-10 5.85E-08 1.64E-08
3. Percent of Applicable Limit D: Gross Aloha Radioactivity
1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 1.46E+06 5.06E+05 2.07E+06 1.14E+06 F. Volume of Dilution Water Used Liters 1.19E+09 2.88E+08 1.59E+09 5.40E+08
  • Applicable limits are expressed in terms of dose.

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

Page 16 of 76

Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 1 Startina: 1-Jan-2008 B Endino: 31-Dec-200S Endina: 31-Dec-2008 Batch Mode Nnnr~rlac R,*la,©,*l Ilnir I CTniiuui r )Nf fl mr4% 2Dfl rflufn 'r ATU nilp+ýr

-. -. -u .. ~ -- . ~ s~I ~ ~ u.~. ~rt~ ~ L~. -r * *

  • t01 L~*

Fission & Activation Products Co-57 Curies 7.36E-06 O.OOE+0O O.OOE+00 0.OOE+0O Co-58 Curies 6.97E-04 7.89E-04 1.99E-03 1.36E-03 Co-60 Curies 1.42E-03 2.92E-04 1.87E-03 8.80E-04 Cr-51 Curies 7.75E-06 8.88E-05 O.OOE+O0 9.88E-05 Fe-55 Curies 1.47E-03 8.10E-04 5.16E-03 1.33E-03 1-131 Curies 3.11E-06 O.OOE+00 O.OOE+00 1.03E-05 Mn-54 Curies 9.93E-05 2.16E-05 1.35E-04 7.58E-05 Nb-95 Curies O.OOE+00 8.54E-06 1.11E-05 1.56E-05 Sr-89 Curies 1.15E-05 O.OOE+0O 1.21E-05 6.20E-06 Sr-90 Curies O.OOE+0O 4.14E-06 O.OOE+O0 0.OOE+OO Cs-134 Curies 1.86E-05 O.OOE+00 5.39E-06 9.26E-06 Cs-137 Curies 4.26E-04 3.77E-05 1.70E-04 1.08E-04 Sb-125 Curies 1.45E-03 7.04E-06 2.03E-03 *9.97E-05 Te-125M Cuirie* 7.g4F-o3 ftOOF+A-lf O OOF+i-lf Total For Period Curies 1.35E-02 2.06E-03 1.14E-02 3.99E-03 Tritium H-3 Curies 3.16E+02 7.64E+01 1.46E+02 4.70E+01 Dissolved And Entrained Gases Xe-133 Curies 7.79E-03 7.63E-05 1.48E-03 2.91E-03 Xe-131M Curies 8.72E-05 O.OOE+00 O.OOE+00 O.OOE+00 Xe-133M Curies 3.92E-05 O.OOE+00 O.OOE+00 O.OOE+00 Total For Period Curies 7.92E-03 7.63E-05 1.48E-03 2.91E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 17 of 76

Table 1-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 1

R .- .1 _-l -n_)nnolI IC A.l-* o2 I r%**. olnn WI I I! EM I~~JI cogDU I ILIU EI * . LLI Continuous Mode Nm-rlidac RPglic-rl lnit I QT fu m,-rtar 2ND Ouarter 3RD Ouarter 4TH Ouarter Fission & Activation Products No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 18 of 76

Table 1-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-Jan-2008 Endina: 31-Dec-2008 Batch Mode N.i rlirflc RIncka I nit 14ZT ir%"arltar ,jpn n~imrthr 40n n. ,inrk~r AT14l .r4Fnr Fission & Activation Products Co-57 Curies O.OOE+O0 0.OOE+00 0.OOE+00 1.44E-05 Co-58 Curies 5.18E-04 6. 15E-04 6.25E-03 .5.87E-03 Co-60 Curies 6.18E-04 2.31E-04 3.82E-03 3.83E-03 Cr-51 Curies O.OOE+O0 3.13E-05 2.38E-05 1.58E-03 Fe-55 Curies 1.08E-03 3.89E-04 1.96E-03 3.21E-03 Fe-59 Curies O.OOE+00 0.OOE+00 0.OOE+00 3.74E-05 1-131 Curies 8.96E-07 0.OOE+00 5.32E-05 8.84E-06 Mn-54 Curies 3.02E-05 1.53E-05 4.22E-04 3.81 E-04 Nb-95 Curies O.OOE+0O 5.20E-06 2.20E-05 2.40E-04 Sr-89 Curies 7.46E-06 0.OOE+00 1.84E-06 7.20E-06 Sr-90 Curies O.OOE+00 1.73E-06 6.96E-06 0.OOE+0O Zr-95 Curies O.OOE+00 0.OOE+00 0.OOE+00 1.35E-04 Cs-134 Curies 1.03E-05 0.OOE+00 7.86E-05 8.08E-05 Cs-137 Curies 2.11E-04 0.OOE+00 7.35E-04 3.44E-04 Sb-125 Curies 5.40E-04 0.OOE+00 6.27E-03 5.38E-04 Te-125M Curies 7.51E-03 1ORE-03 n-OOE+nn Total For Period Curies 1.05E-02 1.29E-03 2.27E-02 1.63E-02 Tritium H-3 Curies 2.45E+02 5.54E+01 3.15E+02 1.63E+02 Dissolved And Entrained Gases Xe-133 Curies 6.05E-03 8.79E-06 8.98E-02 5.93E-03 Xe-135 Curies O.OOE+00 O.OOE+0O 4.59E-05 O.OOE+00 Xe-131M Curies 8.72E-05 O.OOE+00 9.OOE-04 O.OOE+00 Xe-133M Curies 2.99E-05 O.OOE+00 5.12E-04 O.OOE+00 Total For Period Curies 6.16E-03 8.79E-06 9.13E-02 5.93E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 19 of 76

Table 1-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: 2 Starting: 1-Jan-2008 Fndinn~ ~1~fler~~flflR Endinn: 31-Dec-2008 Continuous Mode NlIrlielac Pdalancad lnit 1T fnlurtar 2ND Ouarter 3RD Ouarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 20 of 76

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Startina: 1-Jan-2008 B Endina: 31-Dec-2008 I Endina: 31-Dec-2008 Batch Mode Nmzrlirhac Palanarl 'Arn Mirin,-'ar I Init I CT n in &+ga )fljn flmmrr ATl flmnrl-gar Fission & Activation Products Co-57 Curies 7.36E-06 0.00E+00 0.OOE+00 1.44E-05 Co-58 Curies 1.22E-03 1.40E-03 8.24E-03 7.23E-03 Co-60 Curies 2.04E-03 5.24E-04 5.69E-03 4.71E-03 Cr-51 Curies 7.75E-06 1.20E-04 2.38E-05 1.68E-03 Fe-55 Curies 2.55E-03 1.20E-03 7.13E-03 4.53E-03 Fe-59 Curies O.OOE+00 0.OOE+00 0.OOE+00 3.74E-05 1-131 Curies 4.01E-06 0.OOE+00 5.32E-05 1.91E-05 Mn-54 Curies 1.30E-04 3.69E-05 5.58E-04 4.57E-04 Nb-95 Curies O.OOE+00 1.37E-05 3.31E-05 2.56E-04 Sr-89 Curies 1.89E-05 0.OOE+00 1.39E-05 1.34E-05 Sr-90 Curies O.OOE+00 5.87E-06 6.96E-06 0.OOE+00 Zr-95 Curies O.OOE+00 0.OOE+00 0.OOE+00 1.35E-04 Cs-134 Curies 2.89E-05 0.OOE+00 8.40E-05 9.01E-05 Cs-137 Curies 6.36E-04 3.77E-05 9.05E-04 4.52E-04 Sb-125 Curies 1.98E-03 7.04E-06 8.30E-03 6.38E-04 Te-125M Cujries 1 _F'SF-NO2 ft.NNF+iNN 0NNNF+NNlf Total For Period Curies 2.41E-02 3.35E-03 3.41E-02 2.03E-02 Tritium H-3 Curies 5.62E+02 1.32E+02 4.60E+02 2.10E+02 Dissolved And Entrained Gases Xe-133 Curies 1.38E-02 8.51E-05 9.13E-02 8.84E-03 Xe-135 Curies O.OOE+00 0.OOE+00 4.59E-05 0.OOE+00 Xe-131M Curies 1.74E-04 0.OOE+00 9.OOE-04 0.OOE+00 Xe-133M Curies 6.91E-05 0.OOE+00 5.12E-04 0.OOE+00 Total For Period Curies 1.41E-02 8.51E-05 9.28E-02 8.84E-03 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 21 of 76

Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents Unit: Site Startina: 1-Jan-2008 Endina: 31-Dec-2008 in . .. . .. ....

St a n :1 -3.. n 2 0.......

Continuous Mode N imrlidec PaIamcdr I"nit I CT1" =..:ark 2ND Ouarter 3RD fluarter 4TH fluarter 2ND Ouarter 3RD Ouarter 4TH Duarter Fission & Activation Products No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 0.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+00 0.OOE+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 22 of 76

Table 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2008 Endina: 31-Dec-2008 I

Cumulative Doses Per Quarter 0 0 Organ ODCM Limit Units lsT Otr  % ODCM 2NDOtr / ODCM 3RD Otr / ODCM 4TH Ot 0/b ODCM Bone 5.OOE+00 mRem 2.05E-03 4.10E-02 2.63E-04 5.26E-03 1.68E-03 3.35E-02 8.73E-04 1.75E-02 GI-Lli 5.OOE+00 mRem 7.93E-03 1.59E-01 2.22E-03 4.45E-02 5.85E-03 1.17E-01 1.67E-03 3.33E-02 Kidney 5.OOE+00 mRem 8.47E-03 1.69E-01 2.23E-03 4.45E-02 5.66E-03 1.13E-01 1.85E-03 3.70E-02 Liver 5.OOE+00 mRem 9.37E-03 1.87E-01 2.41E-03 4.82E-02 7.16E-03 1.43E-01 2.69E-03 5.37E-02 Lung 5.OOE+00 mRem 8.90E-03 1.78E-01 2.18E-03 4.36E-02 1.07E-02 2.13E-01 1.86E-03 3.71E-02 Thyroid 5.OOE+00 mRem 6.82E-03 1.36E-01 2.14E-03 4.27E-02 4.94E-03 9.87E-02 1.46E-03 2.91E-02 Total Body 1.50E+00 mRem 8.47E-03 5.65E-01 2.33E-03 1.55E-01 6.41E-03 4.27E-01 2.28E-03 1.52E-01 Cumulative Doses per Year Organ ODCM Limit Units Year to Ending Date 0/0 ODCM Receptor Limit Bone 1.OOE+01 mRem 4.87E-03 4.87E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 1.77E-02 1.77E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 1.82E-02 1.82E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver LOOE+01 mRem 2.16E-02 2.16E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 2.36E-02 2.36E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 1.53E-02 1.53E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 1.95E-02 6.50E-01 Maximum Individual Liquid Liquid Effluent TB Annual Page 23 of 76

Table 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a member of the public due to Liquid Releases Unit: 2 Startina: 1-Jan-2008 Endino: 31-Dec-2008 Cumulative Doses Per Ouarter Endina: 31-Dec-2008 Oraan ODCM Limit Units 1ST Otr 0/0 ODCM 2ND Otr  %/oODCM 3RD Otr 0/o ODCM 4TH Otr  %/ ODCM Bone 5.OOE+00 mRem 1.06E-03 2.12E-02 2.99E-05 5.98E-04 5.24E-03 1.05E-01 2.78E-03 5.56E-02 GI-Lli 5.OOE+00 mRem 6.23E-03 1.25E-01 1.43E-03 2.86E-02 9.80E-03 1.96E-01 5.01E-03 1.OOE-O1 Kidney 5.OOE+00 mRem 6.50E-03 1.30E-01 1.38E-03 2.75E-02 1.04E-02 2.08E-01 5.48E-03 1.1OE-01, Liver 5.OOE+00 mRem 6.58E-03 1.32E-01 1.38E-03 2.76E-02 1.47E-02 2.94E-01 8.31E-03 1.66E-01 Lung 5.OOE+00 mRem 6.18E-03 1.24E-01 1.38E-03 2.76E-02 1.96E-02 3.92E-01 5.65E-03 1.13E-01 Thyroid 5.OOE+00 mRem 5.37E-03 1.07E-01 1.37E-03 2.75E-02 7.56E-03 1.51E-01 4.10E-03 8.21E-02 Total Body 1.50E+00 mRem 6.14E-03 4.09E-01 1.39E-03 9.25E-02 1.24E-02 8.26E-01 7.03E-03 4.69E-01 Cumulative Doses per Year Organ ODCM Limit Units Year to Ending Date  % ODCM Receptor Limit Bone 1.OOE+01 mRem 9.11E-03 9.11E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 2.25E-02 2.25E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 2.38E-02 2.38E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 3.10E-02 3.10E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 3.28E-02 3.28E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+01 mRem 1.84E-02 1.84E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 2.69E-02 8.98E-01 Maximum Individual Liquid Liquid Effluent TB Annual Page 24 of 76

Table 1-3C Vogtle Electric Generating Plant.

RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a member of the public due to Liquid Releases Unit: Site Ctnrfinn, 1-1=n-*nlfl I:nedinna '211 naae.InnR Cumulative Doses Per Ouarter Oraan ODCM Limit Units 1ST Qtr  % ODCM 2ND Qtr O/o ODCM 3RD Qtr O/% ODCM 4TH Otr /o ODCM Bone 5.OOE+00 mRem 3.11E-03 6.23E-02 2.93E-04 5.86E-03 6.92E-03 1.38E-01 3.65E-03 7.30E-02 GI-Lli 5.OOE+00 mRem 1.42E-02 2.83E-01 3.66E-03 7.31E-02 1.57E-02 3.13E-01 6.68E-03 1.34E-01 Kidney 5.OOE+00 mRem 1.50E-02 2.99E-01 3.60E-03 7.20E-02 1.61E-02 3.21E-01 7.33E-03 1.47E-01 Liver 5.OOE+00 mRem 1.59E-02 3.19E-01 3.79E-03 7.59E-02 2.18E-02 4.37E-01 1.10E-02 2.20E-01 Lung 5.OOE+00 mRem 1.51E-02 3.02E-01 3.56E-03 7.12E-02 3.02E-02 6.05E-01 7.50E-03 1.50E-01 Thyroid 5.OOE+00 mRem 1.22E-02 2.44E-01 3.51E-03 7.02E-02 1.25E-02 2.50E-01 5.56E-03 1.11E-01 Total Body 1.50E+00 mRem 1.46E-02 9.74E-01 3.72E-03 2.48E-01 1.88E-02 1.25E+00 9.31E-03 6.21E-01 Cumulative Doses per Year Oraan ODCM Limit Units Year to Ending Date  % ODCM Receptor Limit Bone 1.OOE+01 mRem 1.40E-02 1.40E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.OOE+01 mRem 4.01E-02 4.01E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.OOE+01 mRem 4.20E-02 4.20E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.OOE+01 mRem 5.26E-02 5.26E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.OOE+01 mRem 5.64E-02 5.64E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.OOE+01 mRem 3.38E-02 3.38E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+O0 mRem 4.64E-02 1.55E+00 Maximum Individual Liquid Liquid Effluent TB Annual Page 25 of 76

Table 1-4 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES JANUARY 2008 - DECEMBER 2008 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 2.73E-08 gCi/ml Fe-59 8.33E-08 gCi/ml Co-58 3.78E-08 gCi/ml Co-60 6.76E-08 gCi/ml Zn-65 1.32E-07 gCi/ml Mo-99 4.31E-07 gCi/ml Cs-134 3.06E-08 gCi/ml Cs-137 4.51E-08 gCi/ml Ce-141 6.99E-08 pCi/ml Ce-144 2.95E-07 gCi/ml 1-131 5.97E-08 lCi/ml Xe-133 9.11E-08 gCi/ml Xe-135 4.27E-08 gCi/ml Fe-55 1.00E-06 iCi/ml Sr-89 5.OOE-08 pCi/ml Sr-90 7.OOE-09 gCi/ml H-3 2.OOE-06 gCi/ml Gross Alpha 7.OOE-08 gCi/ml Page 26 of 76

Table 1-SA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 39 17 19 15 90
2. Total time period for Batch releases (Minutes.) 1.16E+04 3.19E+03 5.03E+03 2.17E+03 2.20E+04
3. Maximum time period for a batch release ( Minutes) 6.85E+02 6.08E+02 1.19E+03 4.79E+02 1.19E+03
4. Average time period for a batch release ( Minutes) 2.97E+02 1.88E+02 2.65E+02 1.44E+02 2.44E+02
5. Minimum time period for a batch release ( Minutes) 3.OOE+00 1.OOE+00 1.OOE+00 1.OOE+00 1.00E+00
6. Average stream flow during periods of release of liquid effluent into Annual Avg Flow a flowing stream *

( CFS ) 6,035 4,947 4,525 5,582 5,272

  • Average River Flow Rate, taken from USGS Monitoring Station 02197500 Savannah River at Burton's Ferry Bridge near Millhaven, Ga 32 River miles downstream of Plant Vogtle Page 27 of 76

Table 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 27 9 33 18 87
2. Total time period for Batch releases ( Minutes) 1.05E+04 2.63E+03 1.44E+04 4.OOE+03 3.16E+04
3. Maximum time period for a batch release ( Minutes) 6.85E+02 6.08E+02 8.90E+02 3.28E+02 8.90E+02
4. Average time period for a batch release ( Minutes) 3.89E+02 2.92E+02 4.37E+02 2.22E+02 3.63E+02
5. Minimum time period for a batch release ( Minutes) 3.OOE+00 7.6E+01 1.00E+00 6.OOE+00 1.00E+00
6. Average stream flow during periods of release of liquid effluent into Annual Avg Flow a flowing stream *

( CFS ) 6,035 4,947 4,525 5,582 5,272

  • Average River Flow Rate, taken from USGS Monitoring Station 02197500 Savannah River at Burton's Ferry Bridge near Millhaven, Ga 32 River miles downstream of Plant Vogtle Page 28 of 76

Table 1-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Batch Release Summary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 42 20 48 33 143
2. Total time period for Batch releases (Minutes) 1.19E+04 3.43E+03 1.84E+04 6.16E+03 3.99E+04
3. Maximum time period for a batch release ( Minutes) 6.85E+02 6.08E+02 1.19E+03 4.79E+02 1.19E+03
4. Average time period for a batch release ( Minutes) 2.83E+02 1.72E+02 3.83E+02 1.87E+02 2.79E+02
5. Minimum time period for a batch release (Minutes) 3.OOE+00 1.OOE+00 1.00E+00 1.OOE+00 1.00E+00
6. Average stream flow during periods of release of liquid effluent into Annual Avg Flow a flowing stream *

(CFS ) 6,035 4,947 4,525 5,582 5,272

  • Average River Flow Rate, taken from USGS Monitoring Station 02197500 Savannah River at Burton's Ferry Bridge near Millhaven, Ga 32 River miles downstream of Plant Vogtle Page 29 of 76

Table 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 I I D

A
in tI I lnifI I CT NIlm m nu,'-r '2 J %l mr- 2Dfl 11r-a ATM f~e%+~ VanVr0T-MlC
  • ~dS~J *t~*~~ ~.D* **LC a
  • US. t~. ~** 1 L~* .fl Utfl t, ~ * ** t* ~* * ~O*
  • L0.a
1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases ( Minutes) 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00
3. Maximum Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Average Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release ( Minutes) 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00
6. Total activity for all releases ( Curies ) 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Page 30 of 76

Table 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Liquid Releases Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes) 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00
3. Maximum Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00
4. Average Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00
5. Minimum Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00
6. Total activity for all releases (Curies) 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Page 31 of 76

Table 1-6C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Liquid Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 I inuirl R~lIa IlInit*@ Ye2r TnI'21I Linuid Releases Units 14rr Nll*rtpr 1*

niiartar 2ND n"Artar 'ARD n"n air 4TH nuartar Year Tntnic

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
3. Maximum Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Average Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
6. Total activity for all releases (Curies ) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Page 32 of 76

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

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

a. For noble gases, Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,
b. For Iodine-1 31, for Iodine-1 33, for tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

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

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

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

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ.
b. During any calendar year: Less than or equal to 15 mrems to any organ.

Page 33 of 76

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 six paths: plant vents (Unit 1 and Unit 2), the condenser air ejector, the steam packing exhauster systems (Unit 1 and Unit 2), Radwaste Processing Facility and the DAW (Dry Active Waste Building).

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 DAW and 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. Samples of the DAW are collected using portable monitoring equipment during periods of operation. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and the steam packing exhauster system vents. There were no releases from the DAW. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release. The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.

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

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

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

Page 34 of 76

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 35 of 76

2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested.

The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

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

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

Sampling and statistical error in counting 10%

Counting equipment calibration 10%

Vent flow Rates 10%

Non-steady release rates 20%

TOTAL ERROR 26.5%

b. 1-131 releases were calculated from each weekly sample:

Statistical error in counting 10%

Counting equipment calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 50%

Non-Steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 55%

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

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non steady release rates 10%

TOTAL ERROR 54%

Page 36 of 76

2.2.3 Total Error Estimation cont'd

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

Water vapor in sample stream determination 10%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 10%

TOTAL ERROR 20%

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

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non Steady release rates 10%

TOTAL ERROR 55%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found in this report as Tables 2-1A, 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 table 2-1A, and 2-1 B, the total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in gCi/second for each category. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

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

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

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

Page 37 of 76

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

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

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

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

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

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

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

2.6 Gaseous Effluents - Abnormal Releases There were no abnormal releases of gaseous radioactivity for this reporting period.

Page 38 of 76

Table 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 2.33E-01 8.68E-01 7.77E-02 1.05E-01
2. Average Release rate for period uCi/sec 2.95E-02 1.10E-01 9.86E-03 1.33E-02
3. Percent of Applicable Limit  %

B. Radioiodines

1. Total Iodine-131 Curies 1.81E-05 O.OOE+00 O.OOE+00 7.12E-07
2. Average Release rate for period uCi/sec 2.29E-06 O.OOE+00 O.OOE+00 9.03E-08
3. Percent of Applicable Limit  %

C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 1.54E-06 8.72E-07 2.11E-07 3.15E-07
2. Average Release rate for period uCi/sec 1.95E-07 1.11E-07 2.68E-08 3.996E-08
3. Percent of Applicable Limit  %* *
1. Total Release Curies 3.80E+00 6.45E+00 3.59E+00 1.33E+00
2. Average Release rate for period uCi/sec 4.83E-01 8.18E-01 4.55E-01 1.68E-01
3. Percent of Applicable Limit * *
  • E. Gross Alpha
1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Page 39 of 76

Table 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Ouarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.19E+02 1.24E+02 3.31E+02 7.11E+01
2. Average Release rate for period uCi/sec 1.51E+01 1.57E+01 4.20E+01 9.01E+00
3. Percent of Applicable Limit *
  • B. Radioiodines
1. Total Iodine-131 Curies O.OOE+O0 O.OOE+O0 2.21E-06 1.95E-06
2. Average Release rate for period uCi/sec O.OOE+O0 O.OOE+O0 2.81E-07 2.48E-07
3. Percent of Applicable Limit *
  • C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies O.OOE+O0 1.82E-07 1. 14E-05 1.63E-05
2. Average Release rate for period uCi/sec O.OOE+O0 2.31E-08 1.45E-06 2.062E-06
3. Percent of Applicable Limit D. Tritium
1. Total Release Curies 1.95E-01 9.19E-01 4.22E+00 1.39E+00
2. Average Release rate for period uCi/sec 2.47E-02 1.17E-01 5.36E-01 1.76E-01 Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Page 40 of 76

Table 2-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Type of Effluent Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter A. Fission And Activation Gases

1. Total Release Curies 1.19E+02 1.24E+02 3.31E+02 7.12E+01
2. Average Release rate for period uCi/sec 1.51E+01 1.58E+01 4.20E+01 9.03E+00
3. Percent of Applicable Limit
  • B. Radioiodines
1. Total Iodine-131 Curies 1.81E-05 O.OOE+O0 2.21E-06 2.67E-06
2. Average Release rate for period uCi/sec 2.29E-06 O.OOE+O0 2.81E-07 3.38E-07
3. Percent of Applicable Limit *
  • C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies 1.54E-06 1.05E-06 1.16E-05 1.66E-05
2. Average Release rate for period uCi/sec 1.95E-07 1.34E-07 1.48E-06 2.102E-06
3. Percent of Applicable Limit D. Tritium
1. Total Release Curies 4.OOE+00 7.37E+00 7.81E+00 2.72E+00
2. Average Release rate for period uCi/sec 5.07E-01 9.34E-01 9.90E-01 3.45E-01 Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

Page 41 of 76

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 lodines 1-131 Curies 1.81E-05 O.OOE+O0 O.OOE+O0 7.12E-07 Total For Period Curies 1.81E-05 0.OOE+00 0.OOE+00 7.12E-07 Particulates Sr-89 Curies O.OOE+O0 8.72E-07 2.11E-07 3.15E-07 Nb-95 Curies 1.54E-06 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 1.54E-06 8.72E-07 2.11E-07 3.15E-07 Tritium H-3 Curies 3.26E+00 1.98E+00 3,42E+00 O.OOE+O0 Gross Aloha No Nuclides Found Curies O.OOE+OO O.OOE+O0 O.OOE+OO O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 42 of 76

Table 2-2A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Ouarter 2ND Ouarter 3RD Quarter 4TH Ouarter Fission Gases Ar-41 Curies 5.84E-02 8.28E-01 7.44E-02 8.29E-02 Kr-85 Curies 2.56E-02 O.OOE+O0 O.OOE+O0 O.OOE+O0 Xe-133 Curies 1.31E-01 4.07E-02 3.33E-03 2.18E-02 Total For Period Curies 2.15E-01 8.68E-01 7.77E-02 1.05E-01 Iodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 Tritium H-3 Curies 4.53E-01 4.47E+00 1.64E-01 1.33E+00 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 0.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 43 of 76

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Fission Gases Ar-41 Curies O.OOE+00 O.OOE+00 6.98E-01 O.OOE+00 Kr-85M Curies O.OOE+00 O.OOE+00 2.55E-01 O.OOE+00 Xe-133 Curies O.OOE+00 O.OOE+00 1.49E+01 1.35E+01 Xe-135 Curies O.OOE+00 O.OOE+00 1.70E+00 2.63E+00 Total For Period Curies 0.OOE+00 0.OOE+00 1.75E+01 1.61E+01 Iodines 1-131 Curies O.OOE+O0 O.OOE+O0 2.21E-06 1.95E-06 Total For Period Curies 0.OOE+00 0.OOE+00 2.21E-06 1.95E-06 Particulates Sr-89 Curies 0.OOE+00 1.82E-07 9.25E-08 1.82E-07 3.92E-07 9.25E-08 Total For Period Curies O.OOE+O0 Tritium H-3 Curies O.OOE+00 O.OOE+O0 2.21E+00 1.06E+00 Gross Alpha No Nuclides Found Curies 0.00E+00 O.OOE+O0 O.OOE+OO O.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 44 of 76

Table 2-2B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Fission Gases Ar-41 Curies 6.14E-01 6.84E-01 3.49E+00 6.14E-01 Kr-85M Curies 3.37E-03 7.16E-05 7.14E-03 1.90E-03 Kr-85 Curies 1.94E-01 6.93E-03 O.OOE+00 O.OOE+00 Xe-131M Curies 1.57E+00 2.04E+00 8.52E-01 1.79E-01 Xe-133M Curies 7.59E-01 8.83E-01 2.89E+00 6.21E-01 Xe-133 Curies 1.15E+02 1.20E+02 3.06E+02 5.31E+01 Xe-135 Curies 2.21E-01 9.01E-02 5.32E-01 3.54E-01 Total For Period Curies 1.19E+02 1.24E+02 3.14E+02 5.48E+01 Iodines No Nuclides Found Curies O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+O0 Particulates No Nuclides Found Curies 0.O0E+00 0.OOE+OO 0.OOE+00 O.OOE+O0 Tritium H-3 Curies 1.95E-01 9.19E-01 2.01E+00 3.33E-01 Gross Alpha No Nuclides Found Curies 0.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 45 of 76

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Ouarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies O.OOE+00 O.OOE+00 6.98E-01 O.OOE+00 Kr-85M Curies O.OOE+00 O.OOE+00 2.55E-01 O.OOE+00 Xe-133 Curies O.OOE+00 O.OOE+00 1.49E+01 1.35E+01 Xe-135 Curies O.OOE+00 O.OOE+00 1.70E+00 2.63E+00 Total For Period Curies 0.OOE+00 0.OOE+00 1.75E+01 1.61E+01 Iodines 1-131 Curies 1.81E-05 O.OOE+O0 2.21E-06 2.67E-06 Total For Period Curies 1.81E-05 0.OOE+00 2.21E-06 2.67E-06 Particulates Sr-89 Curies O.OOE+O0 1.05E-06 6.03E-07 4.08E-07 Nb-95 Curies 1.54E-06 O.OOE+O0 O.OOE+O0 O.OOE+O0 Total For Period Curies 1.54E-06 1.05E-06 6.03E-07 4.08E-07 Tritium H-3 Curies 3.26E+00 1.98E+00 5.64E+00 1.06E+00 Gross Alpha No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 46 of 76

Table 2-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Mixed Mode Level Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Ouarter Fission Gases Ar-41 Curies 6.72E-01 1.51E+00 3.56E+00 6.97E-01 Kr-85M Curies 3.37E-03 7.16E-05 7.14E-03 1.90E-03 Kr-85 Curies 2.19E-01 6.93E-03 O.OOE+00 O.OOE+00 Xe-131M Curies 1.57E+00 2.04E+00 8.52E-01 1.79E-01 Xe-133M Curies 7.59E-01 8.83E-01 2.89E+00 6.21E-01 Xe-133 Curies 1.16E+02 1.20E+02 3.06E+02 5.31E+01 Xe-135 Curies 2.21E-01 9.01E-02 5.32E-01 3.54E-01 Total For Period Curies 1.19E+02 1.24E+02 3.14E+02 5.50E+01 Iodines No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Particulates No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Tritium H-3 Curies 6.48E-01 5.39E+00 2.17E+00 1.66E+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 47 of 76

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode NNIrlidavP RPdalanr Ilnit- 1T f lmmart~r 7Nfl fl~mrt~'r *l*n N.Rrt*r £TH f~liurI~r Unit 1ST nuarter 2ND nuarter 3RD nuarter 4TH nuarter Fission Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+0O Iodines No Nuclides Found Curies O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+0O Particulates No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 48 of 76

Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Nnnrlifigic RAIalncar I Init I CT fln =rImr f"l=+,ar

)Mrfln 20r%fl..&1rIgr ATU f~si~a Fission Gases Xe-133 Curies 1.76E-02 O.OOE+O0 O.OOE+00 0.OOE+O0

-Iodines No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+00 0.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+00 0.OOE+O0 Tritium No Nuclides Found Curies 9.03E-02 O.OOE+O0 O.OOE+00 O.OOE+0O Gross Alpha No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+O0 0.OOE+O0 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 49 of 76

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 lodines No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 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 76

Table 2-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode llnit Unit 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Nuclides Released Fission Gases Ar-41 Curies O.OOE+OO O.OOE+00 6.90E-04 O.OOE+OO Xe-133 Curipq flOO-nn-00 n-nnF+ 00 .21 E-fl2 Total For Period Curies 0.OOE+00 0.OOE+00 5.28E-02 7.68E-02 lodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates Co-58 Curies O.OOE+00 O.OOE+00 1.10E-05 1.62E-05 Total For Period Curies O.OOE+00 0.OOE+00 1.10E-05 1.62E-05 Tritium H-3 Curies 0.OOE+00 O.OOE+00 1.05E-03 1.02E-03 Gross Alpha No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 51 of 76

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Continuous Mode kn nA-IArle Dýl1e A I Ifit- ICYTf leMrl l'4r ) l-l-r% 2Dfl lerl ATUJ ivr~~

  • ~L**~J~~ *'t~*~~~U *
  • t0* L~. ~ J0* L~. fl~ 0* L~* *I U U* U.~*

Fission Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Iodines No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+O0 0.OOE+0O Particulates No Nuclides Found Curies O.OOE+O0 O.OOE+0O O.OOE+O0 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+O0 0.OOE+00 Gross Alpha No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+O0 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 52 of 76

Table 2-3C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Batch Mode Numrlidiac PgaIoacdarI "nit 1ST Ouarter 2ND Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter 1ST Ouarter Fission Gases Ar-41 Curies O.OOE+00 0.OOE+ 00 6.90E-04 0.OOE+00 Xe-133 Ciiripr, 1 71F-fl2 '21 F-fl?

Total For Period Curies 1.76E-02 0.OOE+00 5.28E-02 7.68E-02 lodines No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Particulates Co-58 Curies O.OOE+00 0.OOE+00 1.10E-05 1.62E-05 Total For Period Curies 0.OOE+00 0.OOE+00 1.10E-05 1.62E-05 Tritium H-3 Curies 9.03E-02 O.OOE+00 1.05E-03 1.02E-03 Gross Alpha No Nuclides Found Curies 0.OOE+0O O.OOE+00 0.OOE+00 0.obE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 53 of 76

Table 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Type of Radiation ODCM Limit Units 1ST Otr 0/0 ODCM 2ND Otr 0/o ODCM 3RD Qtr  %/aODCM 4TH Otr  %/aODCM Gamma Air 5.OOE+00 mRad 9.15E-06 1.83E-04 1.13E-04 2.26E-03 1.02E-05 2.03E-04 1.14E-05 2.28E-04 Beta Air 1.00E+01 mRad 7.04E-06 7.04E-05 4.04E-05 4.04E-04 3.63E-06 3.63E-05 4.32E-06 4.32E-05 Cumulative Doses Per Year Type of Radiation ODCM Limit Units Year to End Date 0/o ODCM Receptor Limit Gamma Air 1.OOE+01 mRad 1.44E-04 1.44E-03 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 5.54E-05 2.77E-04 Site Boundary / Child Air Dose Beta Annual 1.21 Page 54 of 76

Table 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Ouarter Type of Radiation ODCM Limit Units 1ST Otr  % ODCM 2ND Otr  % ODCM 3RD Otr  %/oODCM 4TH Otr  %/oODCM Gamma Air 5.OOE+00 mRad 6.94E-04 1.39E-02 7.25E-04 1.45E-02 2.32E-03 4.63E-02 5.18E-04 1.04E-02 Beta Air 1.00E+01 mRad 1.86E-03 1.86E-02 1.93E-03 1.93E-02 5.31E-03 5.31E-02 1.18E-03 1.18E-02 Cumulative Doses Per Year Tvye of Radiation ODCM Limit Units Year to End Date  %/ODCM Receptor Limit Gamma Air 1.OOE+01 mRad 4.25E-03 4.25E-02 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 1.03E-02 5.14E-02 Site Boundary / Child Air Dose Beta Annual 1.21 Page 55 of 76

Table 2-4C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Air Doses Due to Gaseous Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Ouarter Type of Radiation ODCM Limit Units 1ST Otr  % ODCM 2ND Qtr  %/bODCM 3RD Qtr  %/oODCM 4TH Otr  %/oODCM Gamma Air 5.OOE+00 mRad 7.03E-04 1.41E-02 8.38E-04 1.68E-02 2.33E-03 4.65E-02 5.29E-04 1.06E-02 Beta Air 1.00E+01 mRad 1.87E-03 1.87E-02 1.97E-03 1.97E-02 5.31E-03 5.31E-02 1.19E-03 1.19E-02 Cumulative Doses Per Year Type of Radiation ODCM Limit Units Year to End Date  % ODCM Receptor Limit Gamma Air 1.OOE+01 mRad 4.40E-03 4.40E-02 Site Boundary / Child Air Dose Gamma Annual 1.21 Beta Air 2.OOE+01 mRad 1.03E-02 5.17E-02 Site Boundary / Child Air Dose Beta Annual 1.21 Page 56 of 76

Table 2-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Ouarter Oroan ODCM Limit Units ~Rfl fltr O/o AflCM 0/,~

ODC 4TH 4TH fltr ntr O/~

O/o flfl~M ODC 1ST Otr O/o ODC 2ND ntr O/o ODC 3RD ntr Bone 7.50E+00 mRem 2.26E-08 3.02E-07 1.03E-06 1.37E-05 2.48E-07 3.31E-06 3.75E-07 4.99E-06 GI-Lli 7.50E+00 mRem 5.57E-05 7.43E-04 4.15E-05 5.54E-04 7.09E-05 9.45E-04 2.87E-05 3.83E-04 Kidney 7.50E+00 mRem 5.57E-05 7.43E-04 4.15E-05 5.53E-04 7.09E-05 9.45E-04 2.87E-05 3.83E-04 Liver 7.50E+00 mRem 5.57E-05 7.43E-04 4.15E-05 5.53E-04 7.09E-05 9.45E-04 2.87E-05 3.83E-04 Lung 7.50E+00 mRem 5.57E-05 7.43E-04 4.15E-05 5.53E-04 7.09E-05 9.45E-04 2.87E-05 3.83E-04 Thyroid 7.50E+00 mRem 6.21E-05 8.28E-04 4.15E-05 5.53E-04 7.09E-05 9.45E-04 2.99E-05 3.99E-04 Total Body 7.50E+00 mRem 5.57E-05 7.43E-04 4.15E-05 5.53E-04 7.09E-05 9.45E-04 2.87E-05 3.83E-04 Cumulative Doses oer Year Ornan flDCM Limit Iinit~ Y~r tn Fnrlinn fl~t~ O/n Afl1rM I~r~ntnr Imirni I imit ODC Limit Units Year to Endinn Data q/. nDr Parantnr Bone 1.500E+01 mRem 1.671E-06 1.114E-05 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 1.969E-04 1.312E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 1.968E-04 1.312E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 1.968E-04 1.312E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 1.968E-04 1.312E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 2.044E-04 1.363E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 1.968E-04 1.312E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 57 of 76

Table 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Quarter Oraan ODCM Limit Units 1ST Otr 0/0 ODCM 2ND Otr 0/0 ODCM 3RD Otr  %/oODCM 4TH Otr 0/o ODCM Bone 7.50E+00 mRem O.OOE+00 O.OOE+00 2.14E-07 2.86E-06 8.44E-07 1.13E-05 6.64E-07 8.85E-06 GI-Lli 7.50E+00 mRem 1.25E-06 1.67E-05 1.19E-05 1.59E-04 7.95E-05 1.06E-03 3.14E-05 4.19E-04 Kidney 7.50E+00 mRem 1.25E-06 1.67E-05 1.19E-05 1.59E-04 7.91E-05 1.05E-03 3.07E-05 4.10E-04 Liver 7.50E+00 mRem 1.25E-06 1.67E-05 1.19E-05 1.59E-04 7.92E-05 1.06E-03 3.08E-05 4.11E-04 Lung 7.50E+00 mRem 1.25E-06 1.67E-05 1.19E-05 1.59E-04 7.93E-05 1.06E-03 3.11E-05 4.14E-04 Thyroid 7.50E+00 mRem 1.25E-06 1.67E-05 1.19E-05 1.59E-04 8.29E-05 1.11E-03 3.41E-05 4.54E-04 Total Body 7.50E+00 mRem 1.25E-06 1.67E-05 1.19E-05 1.59E-04 7.93E-05 1.06E-03 3.11E-05 4.14E-04 Cumulative Doses Rer Year frn:n flnfrM I mit Imii'c Vg,"nr #-t%Inrinn n-nt-* q/- fnnrM DAM&r-4anr I imil" Lw %I te Bone 1.500E+01 mRem 1.723E-06 1.148E-05 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 1.241E-04 8.274E-04 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 1.230E-04 8.197E-04 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 1.231E-04 8.209E-04 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 1.235E-04 8.235E-04 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 1.301E-04 8.675E-04 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 1.236E-04 8.237E-04 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 58 of 76

Table 2-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Cumulative Doses Per Ouarter flrn:n nlrltM I imi- Init'c I CT 1%#-r 0/- flfll

. .uzL

)RFl fir 0/.- fflrk U

  • 20nl ti flk-u. 0/, fflffM Y. I ~ ~ATU f*

fhl.

b O/-u fflffM Bone 7.50E+00 mRem 2.26E-08 3.02E-07 1.24E-06 1.65E-05 1.09E-06 1.46E-05 1.04E-06 1.38E-05 GI-Lli 7.50E+00 mRem 5.70E-05 7.60E-04 5.34E-05 7.12E-04 1.50E-04 2.01E-03 6.01E-05 8.01E-04 Kidney 7.50E+00 mRem 5.70E-05 7.60E-04 5.34E-05 7.12E-04 1.50E-04 2.OOE-03 5.94E-05 7.92E-04 Liver 7.50E+00 mRem 5.70E-05 7.60E-04 5.34E-05 7.12E-04 1.50E-04 2.OOE-03 5.95E-05 7.94E-04 Lung 7.50E+00 mRem 5.70E-05 7.59E-04 5.34E-05 7.12E-04 1.50E-04 2.OOE-03 5.98E-05 7.97E-04 Thyroid 7.50E+00 mRem 6.34E-05 8.45E-04 5.34E-05 7.12E-04 1.54E-04 2.05E-03 6.40E-05 8.53E-04 Total Body 7.50E+00 mRem 5.70E-05 7.60E-04 5.34E-05 7.12E-04 1.50E-04 2.OOE-03 5.98E-05 7.97E-04 Cumulative Doses per Year ANrti~n Nnr'M I imil Ilnil'e Va:r I'n Inrlinn nltl-*, Oln fnltM Dnrnnlnr lim~i*

groan nnrm i imit "nite Ynar M Fnelinq nnt-a o/- nnrm D'od-da &Ei-nr I imit.

Bone 1.500E+01 mRem 3.393E-06 2.262E-05 Maximum Individual / Child Iodine/Part Dose Annual 1.21 GI-Lli 1.500E+01 mRem 3.210E-04 2.140E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Kidney 1.500E+01 mRem 3.198E-04 2.132E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Liver 1.500E+01 mRem 3.199E-04 2.133E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Lung 1.500E+01 mRem 3.203E-04 2.135E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Thyroid 1.500E+01 mRem 3.345E-04 2.230E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Total Body 1.500E+01 mRem 3.204E-04 2.136E-03 Maximum Individual / Child Iodine/Part Dose Annual 1.21 Page 59 of 76

Table 2-6 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES Starting: 1-Jan-2008 Ending: 31-Dec-2008 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 gCi/ml Kr-88 2.53E-08 4Ci/ml Xe-133 2.05E-08 aCi/ml Xe-133m 8.63E-08 lCi/ml Xe-135 7.12E-08 pCi/ml Xe-138 1.05E-07 gCi/ml 1-131 7.93E-15* 4Ci/ml Mn-54 3.94E-14* lCi/ml Fe-59 2.45E-14* gCi/ml Co-58 1.39E-14* laCi/ml Co-60 1.75E-14* lCi/ml Zn-65 2.82E-14* lCi/ml Mo-99 9.57E-14* gCi/ml Cs-134 1.12E-14* gCi/ml Cs-137 8.71E-15* laCi/ml Ce-141 8.62E-15* lCi/ml Ce-144 2.77E-14* gCi/ml Sr-89 1.OOE-13 gCi/ml Sr-90 1.OOE-13 ACi/ml H-3 9.OOE-08 gCi/ml Gross Alpha 1.OOE-13 lCi/ml

  • Based on an estimated sample volume of 5.7E+08 ml.

Page 60 of 76

Table 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 45 35 36 36 152
2. Total time period for batch releases ( Minutes) 4.27E+04 4.38E+04 2.30E+03 2.55E+03 9.13E+04
3. Maximum time period for a batch release ( Minutes) 1.01E+04 1.01E+04 1.12E+02 1.40E+02 1.01E+04
4. Average time period for a batch release ( Minutes) 9.49E+02 1.25E+03 6.40E+01 7.08E+01 6.01E+02
5. Minimum time period for a batch release ( Minutes) 1.00E+O0 1.OOE+01 3.40E+01 2.10E+01 1.OOE+00 Page 61 of 76

Table 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 21 16 51 34 122
2. Total time period for batch releases ( Minutes ) 1.80E+04 3.69E+03 7.44E+04 3.90E+04 1.35E+05
3. Maximum time period for a batch release ( Minutes ) 7.91E+03 1.24E+03 8.08E+03 4.56E+03 8.08E+03
4. Average time period for a batch release ( Minutes ) 8.57E+02 2.30E+02 1.46E+03 1.15E+03 1.11E+03
5. Minimum time period for a batch release (Minutes) 3.50E+01 5.OOE+O0 9.OOE+O0 1.OOE+O0 1.OOE+O0 Page 62 of 76

Table 2-7C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Batch Release Summary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 66 51 87 70 274
2. Total time period for batch releases (Minutes) 6.07E+04 4.74E+04 7.67E+04 4.16E+04 2.26E+05
3. Maximum time period for a batch release (Minutes) 1.01E+04 1.01E+04 8.08E+03 4.56E+03 1.01E+04
4. Average time period for a batch release (Minutes ) 9.20E+02 9.30E+02 8.82E+02 5.94E+02 8.26E+02
5. Minimum time period for a batch release (Minutes ) 1.OOE+00 5.OOE+00 9.OOE+00 1.OOE+00 1.OOE+00 Page 63 of 76

Table 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases ( Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00
3. Maximum Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Average Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release ( Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
6. Total activity for all releases (Curies ) 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Page 64 of 76

Table 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes) 0.00E+00 O.00E+00 0.OOE+00 0.00E+00 0.00E+00
3. Maximum Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00
4. Average Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
5. Minimum Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
6. Total activity for all releases (Curies) 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Page 65 of 76

Table 2-8C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Gaseous Effluents - Abnormal Release Summary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes) 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00
3. Maximum Time For A Release (Minutes) 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
4. Average Time For A Release (Minutes) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
5. Minimum Time For A Release (Minutes) 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00
6. Total activity for all releases (Curies) 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Page 66 of 76

3.0 Solid Waste 3.1 Regulatory Requirements The ODCM requirements presented in this section are stated in part for Unit 1 and Unit 2.

3.1.1 Solid Radioactive Waste System 10.2.1 Process Control Program (PCP)

Radioactive wastes shall be solidified or dewatered in accordance with the PCP to meet shipping and transportation requirements during transit and disposal site requirements when received at the disposal site.

3.1.2 Reporting Requirements 12.1 PCP states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units, as outlined in Regulatory Guide 1.21.

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

Page 67 of 76

Table 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units I and 2 Page 1 of 4 JANUARY 1, 2008 THROUGH JUNE 30, 2008 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period Error, %
a. Spent resins, filter sludges, evaporator m3 NONE bottoms, etc. Ci NONE N/A
b. Dry compressible waste, contaminated m3 55.0 equip, etc. Ci 212.5 40
c. Irradiated components, control m3 NONE rods, etc. Ci NONE N/A
d. Other (describe) m3 NONE Ci NONE N/A
2. Estimate of major nuclide composition (by type of waste).
a. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A
b. Fe-55  % 47.70 Ni-63  % 18.63 Co-60  % 12.79 All others  % 68.58
c. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A
d. N/A  % N/A N/A N/A
3. Solid Waste Disposition Number of Mode of Shipments Transportation Destination 3 Tractor and Trailer, Cask Studsvik, Johnson City, TN 8 Tractor and Trailer Duratek, Oak Ridge, TN Page 68 of 76

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 2 of 4 JANUARY 1, 2008 THROUGH JUNE 30, 2008 B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

Shipments Sent Directly to Disposal at Barnwell, SC.

Shipment No. Waste Class Type Container Shipping Class Solidification Agent Volume (direct disposal only)

NONE Shipments to a Waste Processor:

Shipment No. Waste Class Type Container Shipping Class Solidification Agent Processor RVRS-08-001 B USA DOT 7A Type A LSA II None Used Studsvik RVRS-08-002 A Excepted Package Limited Quantity None Used Duratek RVRS-08-003 A Excepted Package LSA I None Used Duratek RVRS-08-004 B USA DOT 7A Type A LSA II None Used Studsvik RVRS-08-005 A Excepted Package LSA I None Used Duratek RVRS-08-006 A Expected Package Limited Quantity None Used Duratek RVRS-08-007 A Excepted Package LSA I None Used Duratek RVRS-08-008 B USA DOT 7A Type A LSA II None Used Studsvik RVRS-08-009 A Excepted Package LSA I None Used Duratek RVRS-08-010 A Excepted Package LSA II None Used Duratek RVRS-08-011 A Excepted Package Limited Quantity None Used Duratek Page 69 of 76

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 3 of 4 JULY 1, 2008 THROUGH DECEMBER 31, 2008 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period Error, %
a. Spent resins, filter sludges, evaporator m3 NONE bottoms, etc. Ci NONE N/A
b. Dry compressible waste, contaminated m3 41.8 equip, etc. Ci 11.45 40
c. Irradiated components, control m3 NONE rods, etc. Ci NONE N/A
d. Other (describe) m3 NONE Ci NONE N/A
2. Estimate of major nuclide composition (by type of waste).
a. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A
b. Fe-55  % 71.99 Ni-63  % 20.00 Co-60  % 3.128 All others  % 4.884
c. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A
d. N/A  % N/A N/A  % N/A
3. Solid Waste Disposition Number of Mode of Shipments Transportation Destination I Cask/ Tractor/ Trailer Energy Solutions, Oak Ridge, TN 8 Tractor / Trailer Energy Solutions, Oak Ridge, TN Page 70 of 76

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2008 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 4 of 4 July 1, 2008 THROUGH December 31, 2008 B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

Shipments Sent Directly to Disposal at Barnwell, SC.

Shipment No. Waste Class Type Container Shipping Class Solidification Agent Volume (direct disposal only)

NONE Shipments to a Waste Processor:

Shipment No. Waste Class Type Container Shipping Class Solidification Agent Processor RVRS-08-012 AU Expected Package Limited Quantity None Used Energy Solutions RVRS-08-013 AU Expected Package LSA I None Used Energy Solutions RVRS-08-014 AS Excepted Package LSA II None Used Energy Solutions RVRS-08-0 15 AU Expected Package LSA I None Used Energy Solutions RVRS-08-016 AU Expected Package Limited Quantity None Used Energy Solutions RVRS-08-017 AU Excepted Package LSA I None Used Energy Solutions RVRS-08-018 AU Expected Package Limited Quantity None Used Energy Solutions RVRS-08-019 AU Excepted Package LSA II None Used Energy Solutions RVRS-08-020 AU Excepted Package Limited Qunatity None Used Energy Solutions Page 71 of 76

4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part:

"The report shall also include assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments ( i.e., specific activity, exposure time, and location) shall be included in the report".

4.2 Demonstration of Compliance The location of concern within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.

There will be no radiation dose at this location due to radioactive liquid effluents.

Delineated in Table 4-1 for this location are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents. Listed in this table are distance and direction from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the plant vent (mixed mode) and from the turbine building (ground level), and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.

The source term is listed in Tables 2-2A, and 2-2B for the mixed mode releases.

Similarly, it is listed in tables 2-3A and 2-3B for the ground level releases.

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

Page 72 of 76

Table 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2008 Ending: 31-Dec-2008 Location Name: Visitor's Center Receptor Distance (kilometers): 4.47E-01 Sector: N Occupancy Factor: 4.57E-04 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3): 5.93E-06 Ground Level Release Particulate and Radioiodine X/Q (sec/m3): 5.58E-06 D/Q (m-2): 2.28E-08 Mixed Mode Release Noble Gas X/Q (sec/m3): 7.12E-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3): 6.74E-07 D/Q (m-2): 5.77E-09 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 5.25E-11 6.18E-12 1.39E-09 2.03E-09 3.48E-09 Liver mRem 5.42E-08 8.56E-08 9.22E-08 3.37E-08 2.66E-07 Total Body mRem 5.42E-08 8.56E-08 9.22E-08 3.37E-08 2.66E-07 Thyroid mRem 5.71E-08 8.56E-08 9.26E-08 3.41E-08 2.69E-07 Kidney mRem 5.42E-08 8.56E-08 9.22E-08 3.37E-08 2.66E-07 Lung mRem 5.42E-08 8.56E-08 9.32E-08 3.52E-08 2.68E-07 GI-Lli mRem 5.42E-08 8.56E-08 9.23E-08 3.38E-08 2.66E-07 NG Total Body mRem 4.20E-07 5.08E-07 1.42E-06 3.25E-07 2.67E-06 Whole Body Dose mRem 4.74E-07 5.93E-07 1.51E-06 3.59E-07 2.94E-06 Page 73 of 76

5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Requirements ODCM 5.1 states in part that the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

5.2 Demonstration of Compliance The requirements of 40CFR1 90 were met.

6.0 Meteorological Data ODCM 7.2.2.2 states in part:

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year.

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

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

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirement ODCM 7.2.2.6 states in part that the report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.

7.1.2 Description of Deviations The inoperability of liquid and gaseous effluent monitors was corrected within the specified time for this reporting period.

Page 74 of 76

7.2 Tanks Exceeding Curie Content Limits 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.

7.2.2 Description of Deviations Limits for outdoor liquid hold-up tanks used for radioactive liquids were not exceeded during this reporting period.

Limits for the gas storage tanks were not exceeded during this reporting period.

8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements ODCM 7.2.2.5 states in part that changes to the ODCM shall be submitted with the Radioactive Effluent Release Report. These changes may be due to changes in the radiological environmental monitoring program sampling locations as required by ODCM 4.1.1.2.3 or changes to dose calculation locations as required by ODCM 4.1.2.2.2. Land uses and dose calculation locations within five miles of VEGP must be determined by a land use census as required by ODCM 4.1.2.

8.2 Description of Changes Changes were made to the Vogtle Electric Generating Plant ODCM for the period January 1, 2008 through December 31, 2008. Revision 24 became effective May 2008. A complete copy of the ODCM will be included with this report with changes identified by bars in the right hand margin of the document. Changes were made to Table 2-1 "Radioactive Liquid Effluent Monitoring Instrumentation", Table 3-7 "Attributes of the Controlling Receptor", Table 4-1 "REMP Samples", Figure 4-5 Groundwater Monitoring Locations, Figure 4-5 "Groundwater Monitoring Wells", Table 4-4 Radiological Monitoring Locations and Figure 4-2 Terrestrial Stations and Aquatic Stations, 0-5 miles..

The Land Use Census was conducted November 11, 2008 by Georgia Power Company Environmental Lab personnel. Due to the results of the census for 2008, no changes will be made to the REMP sampling locations and the dose calculation locations.

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9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 9.1 Regulatory Requirements ODCM 7.2.2.7 states in part:

As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation.

Note 1: In lieu of inclusion in the Radioactive Effluents Release Report, this same information may be submitted as part of the annual FSAR update.

PCP 12.1 states in part:

Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented.

9.2 Description of Major Changes Gaseous Radwaste System There were no major changes to the gaseous radwaste systems in the 2008 assessment period.

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

This is to indicate that no major changes to the liquid radwaste systems occurred during the 2008 assessment period.

Solid Radwaste System There were no major changes to the solid radwaste systems in the 2008 assessment period.

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