Text

Enclosure 1 - Hatch Annual Radioactive Effluent Release Report for 2011
	ML12122A142
Person / Time
Site:	Hatch
Issue date:	12/31/2011
From:	; Southern Co, Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12122A142 (91)
	v • d • e

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2011 Enclosure 1 Hatch Annual Radioactive Effluent Release Report for 2011

SOUTHERN COMPANY E. L HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENTRELEASES JANUARY 1, 2011 THROUGH DECEMBER 31,2011 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 Outfall -

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

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 62 3.1 Regulatory Requirements 62 3.1.1 Solid Radioactive Waste System 62 3.1.2 Reporting Requirements 62 Hi

SECTION TITLE PAGE 3.2 Solid Waste Data 63 4.0 Doses to Members of the Public Inside The 68 Site Boundary 4.1 Regulatory Requirements 68 4.2 Demonstration of Compliance 68 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 73 5.1 Regulatory Requirements 73 5.2 Demonstration of Compliance 73 6.0 Meteorological Data 73 7.0 Program Deviations 73 7.1 Inoperable Liquid or Gaseous Effluent 73 Monitoring Instrumentation 7.1.1 Regulatory Requirements 73 7.1.2 Description of Deviations 74 7.2 Tanks Exceeding Curie Content Limits 74 7.2.1 Regulatory Requirements 74 7.2.2 Description of Deviations 74 7.3 Effluent Sample Analysis Exceeding Minimum 74 Detectable Concentration (MDC) 7.3.1 Regulatory Requirement 74 7.3.2 Description of Deviation 74 iii

SECTION TITLE PAr.'F TITLE PA(E 8.0 Changes to the Plant Hatch 75 Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements 75 8.2 Description of Changes 75 9.0 Major Changes to the Liquid, Gaseous or 76 Solid Radwaste Treatment Systems 9.1 Regulatory Requirements 76 9.2 Description of Major Changes 76 Appendix A Release of Radioactive RHR Service Water for 2011 78 Appendix B Carbon-14 Supplement for 2011 83 iv

SOUTHERN COMPANY E. L 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

"rACl =' I I*'r '*C" "/AI21 CC=' D A f 2C 1-6A Liquid Effluents - Abnormal Release 24 Summary Unit 1 1-6B 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) 2-1C 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 40 Unit 2 (Quarters 1, 2, 3 and 4)

.2-2C Gaseous Effluents - Elevated Releases 43 Site (Quarters 1, 2, 3and 4) 2-3A Gaseous Effluents - Ground Level Releases 46 Unit 1 (Quarters 1, 2, 3 and 4) 2-3B Gaseous Effluents - Ground Level Releases 48 Unit 2 (Quarters 1, 2, 3 and 4) 2-3C Gaseous Effluents - Ground Level Releases 50 Site (Quarters 1, 2, 3 and 4) 2-4A Air Doses Due to Noble Gases in Gaseous 52 Releases - Unit 1 (Quarters 1, 2, 3 and 4) vi

TARI = I ICT n= TA 121 CC D AI"* I 2-4B Air Doses Due to Noble Gases in Gaseous 53 Releases- Unit 2 (Quarters 1, 2, 3 and 4) 2-5A Doses to a Member of the Public Due to 54 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-5B Doses to a Member of the Public Due to 55 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-6 Minimum Detectable Concentration - 56 Gaseous Sample Analyses 2-7A Gaseous Effluents - Batch Release 57 Summary Unit 1 2-7B Gaseous Effluents - Batch Release 58 Summary Unit 2 2-8A Gaseous Effluents - Abnormal Release 59 Summary Unit 1 2-8B Gaseous Effluents - Abnormal Release 60 Summary Unit 2 2-8C Gaseous Effluents - Abnormal Release 61 Summary Site 3-1 Solid Waste and Irradiated Fuel Shipments 64 4-1 Doses to a Member of the Public Due to 69 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 RadioactivityDetermination for Liquid Radwaste MEASUREMENT FREQUENCY METHOD

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

2. Dissolved or entrained noble Each Batch Gamma Spectroscopy 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. Ifthe release is not permissible, appropriate warnings will be displayed on the computer screen. Ifthe 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 Radioactivityfor Groundwater Outfalls - 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 RadioactivityDeterminationfor 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 (as and gas flow 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-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 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 2011 can be found in Appendix A of this report.

The values for the four categories of Tables 1-1 A, 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 Continuous 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 - 2011 Liquid Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including Curies O.OOE+00 O.OOE+00 1.25E-03 7.89E-05 tritium, gases, alpha)

2. Average diluted concentration uCi/mL O.OOE+OO O.OOE+OO 2.96E-09 5.78E-10 during period

3. Percent of Applicable Limit % * * *

B. Tritium

1. Total Release Curies O.OOE+00 O.OOE+00 4.26E+00 5.44E+00

2. Average diluted Concentration during period uCi/mL O.OOE+00 O.OOE+00 1.01E-05 3.98E-05

3. Percent of Applicable Limit %* * * *

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

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

3. Percent of Applicable Limit % * * *

D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 O.OOE+00 1.27E-06 2.62E-07 C. Dissolved and Entrained Gases E: Waste Vol Release (Pre-Dilution) Liters O.OOE+O0 O.OOE+O0 1.85E+06 8.39E+05 F. Volume of Dilution Water Used Liters O.OOE+O0 O.OOE+O0 4.21E+08 1.37E+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 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including Curies O.OOE+O0 9.32E-04 O.OOE+O0 6.09E-04 tritium, gases, alpha)

2. Average diluted concentration uCi/mL O.OOE+O0 1.69E-10 O.OOE+O0 1.50E-10 during period

3. Percent of Applicable Limit %* * *

B. Tritium

1. Total Release Curies 2.38E-02 3.20E+00 1.31E-02 6.11E-01

2. Average diluted Concentration during period uCi/mL 7.87E-09 5.81E-07 2.35E-09 1.50E-07

3. Percent of Applicable Limit %* * * *

1. Total Release Curies O.OOE+00 2.06E-06 O.OOE+00 3.07E-06

2. Average diluted Concentration during period uCi/mL O.OOE+00 3.73E-13 O.OOE+00 7.54E-13

3. Percent of Applicable Limit %* * *

D: Gross Alpha Radioactivity

1. Total Release Curies O.0OE+00 1.25E-06 O.OOE+00 O.OOE+00 C. Dissolved and Entrained Gases E: Waste Vol Release (Pre-Dilution) Liters 3.16E+06 3.37E+06 2.90E+06 2.29E+06 F. Volume of Dilution Water Used Liters 3.02E+09 5.51E+09 5.57E+09 4.06E+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 - 2011 Liquid Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products

1. Total Release (not including Curies 0.00E+00 9.32E-04 1.25E-03 6.88E-04 tritium, gases, alpha)

2. Average diluted concentration uCi/mL 0.00E+00 1.69E-10 2.09E-10 1.64E-10 during period

3. Percent of Applicable Limit *

B. Tritium

1. Total Release Curies 2.38E-02 3.20E+00 4.38E+00 6.05E+00

2. Average diluted Concentration during period uCi/mL 7.87E-09 5.81E-07 7.31E-07 1.44E-06

3. Percent of Applicable Limit

1. Total Release Curies O.OOE+00 2.06E-06 0.00E+00 3.07E-06

2. Average diluted Concentration during period uCi/mL O.OOE+00 3.73E-13 O.OOE+00 7.30E-13

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 1.25E-06 1.34E-06 2.62E-07 C. Dissolved and Entrained Gases E: Waste Vol Release (Pre-Dilution) Liters 3.16E+06 3.37E+06 4.74E+06 3.13E+06 F. Volume of Dilution Water Used Liters 3.02E+09 5.51E+09 5.99E+09 4.20E+09

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

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Table 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+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 1-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: l-Jan-2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-58 Curies O.OOE+00 0.00E+00 3.89E-05 0.00E+00 Co-60 Curies O.OOE+00 0.00E+00 3.03E-04 6.45E-06 Fe-55 Curies O.OOE+00 0.00E+00 3.27E-04 5.86E-05 Mn-54 Curies O.OOE+00 0.OOE+00 1.31E-04 0.00E+00 Na-24 Curies O.OOE+00 0.00E+00 3.16E-04 0.00E+00 Sr-89 Curies O.OOE+00 0.00E+00 0.00E+00 1.38E-05 Zn-65 Curies O.OOE+00 0.00E+00 2.30E-05 0.00E+00 Cs-137 Curies O.OOE+00 0.00E+00 1.03E-04 0.00E+00 Zn-69M Curies O.OOE+00 0.00E+00 3.41E-06 0.00E+00 Total For Period Curies O.OOE+00 O.OOE+OO 1.25E-03 7.89E-05 Tritium H-3 Curies O.OOE+00 0.00E+00 4.26E+00 5.44E+00 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Gross Alpha Radioactivity G-Alpha Curies O.OOE+00 0.00E+00 1.27E-06 2.62E-07 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 1-213 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 2 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Tritium H-3 Curies 2.38E-02 1.34E-02 1.31E-02 1.33E-02 Dissolved And Entrained Gases No Nuclides Found Curies 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Gross Alpha Radioactivity No Nuclides Found Curies 0.00E+00 0.00E+00 0.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. 13

Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 2 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-58 Curies O.OOE+00 1.97E-05 0.OOE+00 3.51E-05 Co-60 Curies 0.OOE+00 2.11E-04 0.OOE+00 2.13E-04 Cr-51 Curies 0.OOE+00 8.31E-05 0.OOE+00 0.OOE+00 Fe-55 Curies 0.OOE+00 2.25E-04 0.OOE+00 1.11E-04 1-131 Curies 0.OOE+00 4.47E-06 O.OOE+00 0.OOE+00 Mn-54 Curies 0.OOE+00 1.22E-04 0.OOE+O0 1.44E-04 Nb-97 Curies O.OOE+00 1.80E-05 0.OOE+O0 0.OOE+00 Sr-89 Curies O.OOE+00 O.OOE+00 0.OOE+00 2.30E-05 Zn-65 Curies O.OOE+00 4.91E-05 0.OOE+00 6.67E-05 Ce-141 Curies O.OOE+00 1.09E-06 0.OOE+00 3.48E-06 Cs-134 Curies O.OOE+00 6.81E-05 0.OOE+00 0.OOE+00 Cs-137 Curies O.OOE+00 1.26E-04 0.OOE+00 0.OOE+00 La-140 Curies O.OOE+00 8.30E-07 0.OOE+00 1.25E-05 Ag-110M Curies O.OOE+O0 3.46E-06 0.OOE+00 0.OOE+00 Total For Period Curies O.OOE+00 9.32E-04 O.OOE+OO 6.09E-04 Tritium H-3 Curies O.OOE+O0 3.19E+00 0.OOE+00 5.98E-01 Dissolved And Entrained Gases Xe-133 Curies O.OOE+00 O.OOE+00 0.OOE+00 3.07E-06 Xe-135 Curies O.OOE+O0 2.06E-06 0.OOE+00 0.OOE+00 Total For Period Curies O.OOE+O0 2.06E-06 O.OOE+OO 3.07E-06 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 - 2011 Liquid Effluents t: 2 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha Radioactivity G-Alpha Curies O.OOE+O0 1.25E-06 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.

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J Uwýý J .- S~ tA;.-

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Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Tritium H-3 Curies 2.38E-02 1.34E-02 1.31E-02 1.33E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 16 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 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Co-58 Curies 0.00E+00 1.97E-05 3.89E-05 3.51E-05 Co-60 Curies 0.00E+00 2.11 E-04 3.04E-04 2.20E-04 Cr-51 Curies 0.00E+00 8.31E-05 0.00E+00 0.00E+00 Fe-55 Curies 0.00E+00 2.25E-04 3.34E-04 1.69E-04 1-131 Curies 0.00E+00 4.47E-06 0.00E+00 0.OOE+00 Mn-54 Curies 0.00E+00 1.22E-04 1.3 1E-04 1.44E-04 Na-24 Curies 0.00E+00 0.00E+00 3.16E-04 0.00E+00 Nb-97 Curies O.OOE+00 1.80E-05 0.00E+00 0.00E-i00 Sr-89 Curies O.OOE+00 0.00E+00 0.OOE+00 3.68E-05 Zn-65 Curies O.OOE+00 4.91E-05 2.30E-05 6.67E-05 Ce-141 Curies O.OOE+00 1.09E-06 0.00E+00 3.48E-06 Cs-134 Curies O.OOE+00 6.81E-05 0.00E+00 0.00E+00 Cs-137 Curies O.OOE+00 1.26E-04 1.03E-04 0.00E+00 La-140 Curies O.OOE+00 8.30E-07 0.OOE+00 1.25E-05 Zn-69M Curies O.OOE+00 0.00E+00 3.41E-06 0.00E+00 Ag-110M Curies O.OOE+00 3.46E-06 0.00E+00 0.00E+00 Total For Period Curies O.OOE+00 9.32E-04 1.25E-03 6.88E-04 Tritium H-3 Curies O.OOE+00 3.19E+00 4.37E+00 6.03E+00 17 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 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Unit Xe-133 Curies O.OOE+00 0.OOE+00 O.OOE+00 3.07E-06 Xe-135 Curies O.OOE+00 2.06E-06 O.OOE+00 0.OOE+00 Total For Period Curies O.OOE+O0 2.06E-06 O.OOE+O0 3.07E-06 Gross Alpha Radioactivity G-Alpha Curies O.OOE+00 1.25E-06 1.34E-06 2.62E-07 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 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter Organ ODCM Lmt Units 0 1ST Qtr 0/0 ODCM 2ND Qtr /b ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Bone 5.00E+00 mRem O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.52E-04 7.04E-03 1.39E-06 2.78E-05 GI-Lli 5.OOE+O0 mRem O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.09E-04 4.18E-03 4.62E-05 9.24E-04 Kidney 5.00E+00 mRem O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 1.99E-04 3.97E-03 4.20E-05 8.41E-04 Liver 5.OOE+O0 mRem O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 5.27E-04 1.05E-02 4.23E-05 8.46E-04 Lung 5.00E+00 mRem 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 8.46E-05 1.69E-03 4.21E-05 8.41E-04 Thyroid 5.00E+00 mRem O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.07E-05 6.14E-04 4.20E-05 8.41E-04 Total Body 1.50E+00 mRem O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.65E-04 2.43E-02 4.25E-05 2.84E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %/oODCM Receptor Limit Bone 1.00E+01 mRem 3.54E-04 3.54E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose GI-Lli 1.00E+01 mRem 2.55E-04 2.55E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Kidney 1.00E+01 mRem 2.41E-04 2.41E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Liver 1.00E+01 mRem 5.69E-04 5.69E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Lung 1.00E+01 mRem 1.27E-04 1.27E-03 MAX INDIVIDUAL LIQUID Adult Ann Cum Organ Liq Dose Thyroid 1.00E+01 mRem 7.27E-05 7.27E-04 MAX INDIVIDUAL LIQUID Adult Ann Cum Organ Liq Dose Total Body 3.00E+00 mRem 4.07E-04 1.36E-02 MAX INDIVIDUAL LIQUID Adult Ann Cum Tot Body Liq Dose 19

Table 1-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: l-Jan-2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter Organ ODCM Lint Units 1ST Qtr % ODCM 2ND Qtr % ODCM 3RD Qtr % ODCM 4TH Qtr % ODCM Bone 5.OOE+00 mRem O.OOE+O0 O.OOE+O0 7.08E-04 1.42E-02 O.OOE+00 O.OOE+00 9.77E-06 1.95E-04 GI-Lli 5.OOE+00 mRem 4.08E-07 8.15E-06 2.02E-04 4.05E-03 1.19E-07 2.37E-06 1.61E-04 3.22E-03 Kidney 5.OOE+00 mRem 4.08E-07 8.15E-06 4.28E-04 8.56E-03 1.19E-07 2.37E-06 2.21E-05 4.42E-04 Liver 5.OOE+00 mRem 4.08E-07 8.15E-06 1.22E-03 2.45E-02 1.19E-07 2.37E-06 4.OOE-05 8.OOE-04 Lung 5.OOE+00 4.08E-07 8.15E-06 1.55E-04 3.10E-03 1.19E-07 2.37E-06 4.75E-06 9.50E-05 Thyroid 5.OOE+00 4.08E-07 8.15E-06 5.51E-05 1.10E-03 1.19E-07 2.37E-06 4.69E-06 9.39E-05 Total Body 1.50E+00 mRem 4.08E-07 2.72E-05 8.96E-04 5.97E-02 1.19E-07 7.91E-06 3.10E-05 2.07E-03 Cumulative Doses per Year Organ ODCM Lint Units Year to Ending Date % ODCM Receptor Limit Bone 1.00E+01 mRem 7.18E-04 7.18E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose GI-Lli 1.00E+01 mRem 3.64E-04 3.64E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Kidney 1.OOE+01 mRem 4.51E-04 4.51E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Liver 1.OOE+01 mRem 1.26E-03 1.26E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Lung 1.OOE+01 mRem 1.60E-04 1.60E-03 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Thyroid 1.OOE+01 mRem 6.03E-05 6.03E-04 MAX INDIVIDUAL LIQUID / Adult Ann Cum Organ Liq Dose Total Body 3.OOE+00 mRem 9.27E-04 3.09E-02 MAX INDIVIDUAL LIQUID / Adult Ann Cum Tot Body Liq Dose 20

Table 1-4 E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES STARTING: 1-Jan-2011 ENDING: 31-Dec-2011 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 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-135 1.03E-08 uCi/ml Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml Sr-90 8.50E-09 uCi/ml H-3 6.OOE-07 uCi/ml 21

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

1. Number of batch releases 0 0 57 24 81

2. Total time period for Batch releases Minutes 0.00 E+00 0.OOE+00 7.56E+03 2.76E+03 1.03E+04

3. Maximum time period for a batch release Minutes 0.OOE+00 O.OOE+00 1.75E+02 1.52E+02 1.75E+02

4. Average time period for a batch release ( Minutes 0.OOE+00 O.OOE+00 1.33E+02 1.15E+02 1.27E+02

5. Minimum time period for a batch release Minutes 0.OOE+00 O.OOE+00 8.30E+01 9.20E+01 8.30E+01

6. Average stream flow during periods of release of liquid effluent into (CFS ) 9.93E+03 6.46E+03 1.50E+03 3.95E+03 5.43E+03 a flowing stream

Replace this text in the Station Parameters 22

Table 1-5B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Liquid Releases Uniits 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 0 27 0 8 35

2. Total time period for Batch releases (Minutes ) 0.OOE+00 2.93E+03 0.OOE+00 9.05E+02 3.84E+03

3. Maximum time period for a batch release (M inutes ) O.OOE+00 1.36E+02 0.OOE+00 1.20E+02 1.36E+02

4. Average time period for a batch release (M inutes ) 0.OOE+00 1.09E+02 0.OOE+00 1.13E+02 1.10E+02

5. Minimum time period for a batch release (M inutes ) 0.OOE+00 7.90E+01 0.OOE+00 1.07E+02 7.90E+01

6. Average stream flow during periods of release of liquid effluent into

( CFS ) 9.93E+03 6.46E+03 1.50E+03 3.95E+03 5.43E+03 a flowing stream

Replace this text in the Station Parameters 23

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

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases Minute s) 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00

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

4. Average Time For A Release Minute s 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00

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

6. Total activity for all releases ( Curies ) 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 24

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

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases Minute s) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Maximum Time For A Release Minute s O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00

4. Average Time For A Release Minute s) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

5. Minimum Time For A Release Minute s) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

6. Total activity for all releases ( Curies ) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 25

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

1. Number of Releases 0 0 0 0 0

2. Total Time For All Releases Minutes O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

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

4. Average Time For A Release Minutes O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

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

6. Total activity for all releases ( Curies ) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 Quantitiesof 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 2-1 C, 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 - 2011 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.39E+00 4.64E+00 3.32E+00 1.37E+01

2. Average Release rate for period uCi/sec 8.11E-01 5.88E-01 4.21E-01 1.73E+00

3. Percent of Applicable Limit

B. Radioiodines

1. Total Iodine-131 Curies 1.76E-04 1.69E-04 5.11E-05 7.13E-05

2. Average Release rate for period uCi/sec 2.23E-05 2.14E-05 6.49E-06 9.04E-06

3. Percent of Applicable Limit

C. Particulates

1. Particulates ( Half-Lives > 8 Days ) Curies 3.49E-05 3.06E-05 2.85E-05 1.69E-05

2. Average Release rate for period uCi/sec 4.43E-06 3.88E-06 3.61E-06 2.138E-06

3. Percent of Applicable Limit % * *

1. Total Release Curies 4.64E+00 4.16E+00 3.28E+00 4.03E+00

2. Average Release rate for period uCi/sec 5.88E-01 5.27E-01 4.17E-01 5.11E-01

3. Percent of Applicable Limit *

E. Gross Alpha

1. Total Release Curies 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00

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

34

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

1. Total Release Curies 4.41E+00 2.00E+00 3.32E+00 1.37E+01

2. Average Release rate for period uCi/sec 5.59E-01 2.53E-01 4.21E-01 1.73E+00

3. Percent of Applicable Limit B. Radiolodines

1. Total Iodine-131 Curies 2.86E-04 1.03E-04 8.20E-05 9.80E-05

2. Average Release rate for period uCi/sec 3.62E-05 1.3 1E-05 1.04E-05 1.24E-05

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days Curies 4.01E-05 1.70E-05 3.92E-05 2.68E-05

2. Average Release rate for period uCi/sec 5.09E-06 2.16E-06 4.97E-06 3.402E-06

3. Percent of Applicable Limit

1. Total Release Curies 6.33E+00 2.93E+00 3.09E+00 2.60E+00

2. Average Release rate for period uCi/sec 8.03E-01 3.72E-01 3.92E-01 3.29E-01

3. Percent of Applicable Limit E. Gross Alpha

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

2. Average Release rate for period uCi/sec 0.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 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.08E+01 6.63E+00 6.64E+00 2.73E+01

2. Average Release rate for period uCi/sec 1.37E+00 8.42E-01 8.43E-01 3.47E+00

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies 4.61E-04 2.72E-04 1.33E-04 1.71E-04

2. Average Release rate for period uCi/sec 5.85E-05 3.45E-05 1.69E-05 2.17E-05

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days Curies 7.50E-05 4.76E-05 6.76E-05 4.46E-05

2. Average Release rate for period uCi/sec 9.52E-06 6.03E-06 8.58E-06 5.653E-06

3. Percent of Applicable Limit D, Tritium

1. Total Release Curies 1.10E+01 7.09E+00 6.38E+00 6.81E+00

2. Average Release rate for period uCi/sec 1.39E+00 8.99E-01 8.09E-01 8.63E-01

3. Percent of Applicable Limit E. Gross Alpha

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

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

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 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 0.OOE+00 9.75E-01 0.OOE+00 7.03E-01 Kr-85M Curies 2.33E-01 2.86E-01 4.99E-01 1.85E-01 Kr-87 Curies 1.39E+00 4.72E-01 0.OOE+00 0.00E+00 Xe-133 Curies 0.00 E+00 0.OOE+00 1.27E+00 1.23E+01 Xe-135M Curies 1.70E+00 1.73E+00 6.10E-01 2.07E-01 Xe-135 Curies 3.07E+00 1.18E+00 9.46E-01 2.27E-01 Total For Period Curies 6.39E+00 4.64E+00 3.32E+00 1.37E+01 lodines 1-131 Curies 1.47E-04 1.48E-04 4.60E-05 7.13E-05 1-133 Curies 2.57E-04 1.29E-04 6.68E-05 4.87E-05 Total For Period Curies 4.03E-04 2.77E-04 1.13E-04 1.20E-04 Sr-89 Curies 2.09E-05 1.16E-05 1.24E-05 8.20E-06 Sr-90 Curies 2.70E-08 9.02E-08 9.86E-08 2.28E-08 Cs-137 Curies 7.28E-08 5.94E-08 1.73E-08 0.OOE+00 Ba-140 Curies 1.14E-05 1.64E-05 1.50E-05 7.82E-06 I-131P Curies 1.01E-07 0.OOE+00 0.OOE+00 0.OOE+00 Total For Period Curies 3.25E-05 2.82E-05 2.75E-05 1.60E-05 Tritium H-3 Curies 5.87E-01 4.73E-01 5.99E-01 4.53E-01 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

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Table 2-2A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter 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.