Text

Enclosure 2 - Farley Annual Radioactive Effluent Release Report for 2011
	ML12122A143
Person / Time
Site:	Farley
Issue date:	12/31/2011
From:	; Southern Co, Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12122A143 (78)
	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 2 Farley Annual Radioactive Effluent Release Report for 2011

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 2011

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 29 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 60 INSIDE THE SITE BOUNDARY 4.1 Regulatory Requirements 60 4.2 Demonstration of Compliance 60

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 5.0 TOTAL DOSE FROM URANIUM FUEL 65 CYCLE (40CFRl90) 5.1 Regulatory Requirements 65 5.2 Demonstration of Compliance 65 6.0 METEOROLOGICAL DATA 65 7.0 PROGRAM DEVIATIONS 65 7.1 Inoperable Liquid or Gaseous Effluent 65 Monitoring Instrumentation 7.1.1 Regulatory Requirements 65 7.1.2 Description of Deviations 66 7.2 Effluent Sample Analysis Exceeding 66 Minimum Detectable Concentration (MDC) 7.2.1 Regulatory Requirements 66 7.2.2 Description of Deviations 66 7.3 Incorrect Compositing of Liquid 66 or Gaseous Effluent Samples 7.3.1 Regulatory Requirements 66 7.3.2 Description of Deviations 67 8.0 CHANGES TO THE PLANT FARLEY ODCM 67 8.1 Regulatory Requirements 67 8.2 Description of Changes 67

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 10.0 CORRECTIONS TO PREVIOUSLY SUBMITTED 68 REPORTS App. A Appendix A, Carbon-14 Supplement for 2011 69

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) 1-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 61 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 2011. 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 1.0E-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 2011 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-lB, 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 2011 Doses to a Member of the Public due to Liquid Releases:

Table 1-3A Unit 2 2011 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 2011 Liquid Effluents - Batch Release Summary: Table 1-5A Unit 2 2011 Liquid Effluents - Batch Release Summary: Table 1-5B 1.7 Liquid Effluents - Abnormal Releases There was one abnormal release during 2011. A Unit 1 Component Cooling Water (CCW) heat exchanger experienced a leak of CCW into the service water side. No limits were exceeded due to this abnormal release. The details of this event are included in Condition Report 384280.

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

Unit 1 2011 Liquid Effluents - Abnormal Release Summary: Table 1-6A Unit 2 2011 Liquid Effluents - Abnormal Release Summary: Table 1-6B

- 4 -

Table 1-1A Joseph M Farley 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 tritium, gases, alpha) Curies 9.24E-03 1.65E-02 2.17E-02 6.90E-03

2. Average diluted concentration during period uCi/mL 9.38E-09 2.65E-08 2.28E-08 4.66E-09

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 7.12E+01 1.14E+02 1.85E+02 1.54E+02

2. Average diluted Concentration during period uCi/mL 7.23E-05 1.84E-04 1.95E-04 1.04E-04

3. Percent of Applicable Limit ,

C. Dissolved and Entrained Gases

1. Total Release Curies 6.27E-06 5.67E-05 2.98E-04 2.89E-04

2. Average diluted Concentration during period uCi/mL 6.37E-12 9.12E-11 3.14E-10 1.95E-10

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 0.OOE+00 3.82E-07 0.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 1.31E+06 7.23E+05 9.73E+05 1.06E+06 F. Volume of Dilution Water Used Liters 9.84E+08 6.20E+08 9.48E+08 1.48E+09

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

Table 1-1B Joseph M Farley 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 tritium, gases, alpha) Curies 3.04E-02 3. 1OE-02 5.61E-02 9.27E-03

2. Average diluted concentration during period uCi/mL 3.56E-08 3.42E-08 3.62E-08 8.40E-09

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 1.89E+02 1.61E+02 1.77E+02 5.42E+01

2. Average diluted Concentration during period uCi/mL 2.22E-04 1.78E-04 1.14E-04 4.92E-05

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

1. Total Release Curies 4.96E-05 5.21E-05 7.15E-04 2.36E-04

2. Average diluted Concentration during period uCi/mL 5.81E-11 5.75E-11 4.61E-10 2.14E-10

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies 0.OOE+00 0.00E+00 6.30E-07 O.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 1.15E+06 9.66E+05 1.51E+06 1.25E+06 F. Volume of Dilution Water Used Liters 8.53E+08 9.05E+08 1.55E+09 1.10E+09

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

- 6 -

Table 1-1C Joseph M Farley 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 tritium, gases, alpha) Curies 3.96E-02 4,75E-02 7.78E-02 1.62E-02

2. Average diluted concentration during period uCi/mL 2.15E-08 3.11E-08 3.11E-08 6.26E-09

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 2.60E+02 2.75E+02 3.62E+02 2.08E+02

2. Average diluted Concentration during period uCi/mL 1.42E-04 1.80E-04 1.45E-04 8.05E-05

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

1. Total Release Curies 5.59E-05 1.09E-04 1.01E-03 5.25E-04

2. Average diluted Concentration during period uCi/mL 3.04E-11 7.12E-11 4.05E-10 2.03E-10

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release Curies 0.OOE+00 0.OOE+O0 1.01E-06 0.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 2.45E+06 1.69E+06 2.48E+06 2.30E+06 F. Volume of Dilution Water Used Liters 1.84E+09 1.53E+09 2.50E+09 2.58E+09

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

- 7

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011

.Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+O0 O.OOE+00 0,0OE+00 0.OOE+OQ Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+00 0.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

- 8 -

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products As-76 Curies 3.61E-05 O.OOE+00 0.OOE+00 6.46E-06 Br-84 Curies 3.30E-06 O.OOE+00 O.OOE+00 0.OOE+00 Co-57 Curies 3.46E-07 0.00E+00 O.OOE+00 0.OOE+00 Co-58 Curies 2.61E-03 1.36E-03 2.58E-04 3.47E-04 Co-60 Curies 9.04E-04 5.24E-04 1.68E-03 1.28E-03 Cr-51 Curies 2.10E-05 O.00E+00 0.00E+00 8.45E-05 Fe-55 Curies 1.06E-04 4.53E-04 5.16E-04 1.61E-04 Fe-59 Curies 1.90E-06 O.00E+00 0.OOE+00 0.OOE+00 1-132 Curies 2.63E-05 0.OOE+00 5.04E-07 0.OOE+00 Mn-54 Curies 5.78E-06 2.46E-06 5.62E-06 1.45E-05 Nb-95 Curies 8.43E-05 1.08E-05 2.06E-06 2.11E-05 Nb-97 Curies 4.63E-07 6.90E-06 O.OOE+00 0.OOE+00 Ni-56 Curies 4.44E-06 3.61E-06 1.09E-06 1.85E-05 Rb-86 Curies 7.88E-06 0.OOE+00 O.00E+00 0.OOE+00 Sr-90 Curies O.OOE+00 2.85E-06 0.OOE+00 4.75E-06 Sr-92 Curies 0.OOE+00 0.OOE+00 6.55E-07 0.OOE+00 Y-91M Curies 4.68E-07 0.OOE+00 0.OOE+00 0.00E+00 Zn-65 Curies 1.60E-05 4.24E-06 9.34E-05 5.31E-05 Zr-95 Curies 2.80E-05 O.OOE+00 0.00E+00 5.60E-06 Ba-140 Curies O.OOE+00 O.00E+00 1.99E-06 0.00E+00 Cd- 109 Curies 0.OOE+00 0.OOE+00 2.38E-05 0.OOE+00 Cd-115 Curies 0.OOE+00 0.OOE+00 O.OOE+00 2.63E-07 Cs-137 Curies 7.67E-06 4.41E-05 6.02E-05 3.25E-05 La-142 Curies 2.16E-06 0.OOE+00 4.30E-06 0.OOE+00 Pr- 146 Curies 0.OOE+00 O.OOE+00 9.35E-07 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.

Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Rh-105 Curies 0.OOE+00 O.OOE+0O O.OOE+O0 4.46E-05 Sb-124 Curies 2.97E-05 2. 16E-05 0.OOE+00 O.OOE+00 Sb-125 Curies 5.28E-04 6.68E-04 3,0OE-03 3.93E-04 Te-127 Curies 0.0OE+00 O.OOE+00 0.OOE+Q0 2.33E-05 Te-132 Curies 8.28E-06 O.OOE+0O 5.24E-07 O.OOE+00 Ag- 108M Curies O.OOE+00 0.OOE+O0 2.58E-05 9.68E-06 Ag-110M Curies 3.05E-06 0.OOE+0O O.OOE+O0 0.OOE+00 In-115M Curies O.OOE+00 0.OOE+00 0.OOE+0Q 2.73E-07 Sn-117M Curies O.OOE+00 2.35E-06 0.OOE+00 3.86E-06 Te-125M Curies 4.81E-03 1.34E-02 1.60E-02 4.39E-03 Total For Period Curies 9.24E-03 1.65E-02 2.17E-02 6.90E-03 Tritium H-3 Curies 7.12E+01 1.14E+02 1.85E+02 1.54E+02 Dissolved And Entrained Gases Ar-41 Curies 6.27E-06 0.OOE+00 0.OOE+0O 1.45E-05 Xe-133 Curies O.OOE+00 4.58E-05 2.97E-04 2.75E-04 Xe-135 Curies O.OOE+00 0.OOE+00 1.08E-06 0,00E+00 Xe-133M Curies 0.OOE+00 1.09E-05 0.OOE+O0 0.OOE+00 Total For Period Curies 6.27E-06 5.67E-05 2.98E-04 2.89E-04 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 - 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 0.OOE+OO 0.OQE+OO 0.OOE+00 Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+00 0.OOE+0O 0.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 0.OQE+00 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 - 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 Be-7 Curies 3.44E-05 1.26E-05 5.57E-06 1.86E-05 Y-92 Curies O.OOE+00 0.OOE+00 0.OOE+00 7.66E-06 Y-93 Curies O.OE+00 O.OOE+00 3.55E-06 O.OOE+00 Y-94 Curies 1.91E-06 O.OOE+00 O.OOE+00 O.OOE+00 As-76 Curies 1.99E-04 0.00E+00 O.OOE+00 1.26E-06 Br-84 Curies O.OOE+00 1.37E-06 O.OOE+00 O.OOE+00 Co-57 Curies 3.62E-06 O.OOE+00 O.0OE+00 2.89E-07 Co-58 Curies 4.02E-03 3.01E-03 9.26E-04 9.O0E-04 Co-60 Curies 1.06E-03 1.41E-03 3.79E-03 2.1OE-03 Cr-51 Curies 3.19E-05 7.77E-05 2.16E-05 1.33E-04 Fe-55 Curies 1.67E-04 2.69E-05 1.36E-03 2.15E-04 Fe-59 Curies 5.64E-07 O.OOE+00 O.0OE+00 8.85E-07 1-132 Curies 2.72E-05 O.OOE+00 O.OOE+00 O.OOE+00 1-133 Curies 0.0OE+00 4.12E-06 0.0OE+00 O.OE+00 Mn-54 Curies 4.92E-06 5.33E-06 1.59E-05 1.12E-05 Mn-56 Curies O.OOE+00 O.OOE+00 O.OOE+00 1.15E-06 Na-24 Curies 4.19E-05 1.73E-05 O.0OE+00 1.35E-06 Nb-95 Curies 4.05E-06 6.56E-06 7.12E-06 9.21E-05 Nb-97 Curies 2.90E-06 1.36E-05 5.87E-06 1.30E-04 Ni-56 Curies 1.86E-05 4.28E-06 9.82E-06 3.17E-05 Rb-86 Curies 2.68E-05 O.0OE+00 O.OOE+00 O.OOE+00 Sr-85 Curies O.OOE+00 O.OOE+00 6.01E-07 O.OOE+00 Sr-90 Curies O.OOE+00 O.OOE+00 9.77E-06 O.OOE+00 Sr-92 Curies O.0OE+00 1.94E-06 6.27E-07 O.OE+00 Y-91M Curies 1.37E-06 O.0OE+00 O.OOE+00 O.OOE+00 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Table 1-2B Joseph M Farley 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 Zn-65 Curies 2.03E-05 5.93E-05 2.35E-04 1.02E-04 Zr-95 Curies O.OOE+O0 O.00E+00 0.OOE+00 3.27E-05 Zr-97 Curies O.OOE+0Q 0.OQE+0Q 5.60E-07 0.00E+00 Ba-140 Curies O.OOE+00 5.98E-06 0.OOE+00 0.OOE+00 Cd-109 Curies O.OOE+O0 0. OOE+O0 7.18E-05 0.OOE+00 Cd-115 Curies 0.00E+00 0.00E+00 1.58E-06 0.00E+00 Ce-141 Curies 0.OOE+00 0.OOE+00 9.73E-07 0.00E+00 Cs-137 Curies 6.34E-05 1.70E-04 5.44E-05 7.12E-06 Eu-155 Curies 0.00E+00 3.3 1E-06 4.11E-06 0.00E+00 La-142 Curies 2.53E-07 1.73E-06 0.OOE+00 0.OOE+00 Rh-105 Curies 0.OOE+00 3.34E-05 0.OOE+00 4.53E-05 Sb-122 Curies 9.87E-06 0.OOE+Q0 0.OOE+00 0.00E+00 Sb-124 Curies 8.30E-05 7.99E-05 0.OOE+00 2.19E-06 Sb-125 Curies 1.81E-03 1.23E-03 8.22E-03 5.11E-04 Sb-126 Curies 1.07E-06 0.OOE+00 0.OOE+00 0.00E+00 Sn-113 Curies 0.OOE+00 0.OOE+00 0.OOE+00 2.58E-06 Tc-101 Curies 8.39E-07 0.OOE+00 0.OOE+00 0.00E+00 Tc-104 Curies 1.43E-06 0.OOE+00 0.OOE+00 0.OOE+00 Tc-99M Curies 1.33E-05 6.75E-06 0.OOE+00 0.OOE+00 Te-131 Curies 1.66E-07 O.OOE+00 0.00E+00 0.OOE+00 Te-132 Curies 3.92E-05 0.OOE+00 3.80E-07 0.OOE+00 Ag-108M Curies O.OOE+00 1.11E-06 4.54E-05 1.77E-06 Ag-110M Curies 0.OOE+00 1.31E-05 0.OOE+00 1.14E-05 In-115M Curies 0.OOE+00 0.OOE+00 1.65E-06 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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Sn-117M Curies 5.21E-06 1.86E-06 O.OE+00 O.OOE+00 Te-125M Curies 2.27E-02 2.48E-02 4.13E-02 4.91E-03 Total For Period Curies 3.04E-02 3.10E-02 5.61E-02 9.27E-03 Tritium H-3 Curies 1.89E+02 1.61E+02 1.77E+02 5.42E+01 Dissolved And Entrained Gases Ar-41 Curies 2.02E-06 0.0OE+00 0.00E+00 1.52E-05 Kr-85 Curies O.OOE+00 O.OOE+00 1.33E-04 O.OOE+00 Xe-133 Curies 3.85E-05 2.19E-05 5.68E-04 2.21E-04 Xe-135 Curies 4.82E-07 0.OOE+00 7.36E-07 O.OOE+00 Xe-131M Curies 8.67E-06 3.02E-05 O.OOE+00 O.OOE+00 Xe-133M Curies O.OOE+00 O.OOE+O0 5.59E-06 O.OE+00 Xe-135M Curies 0.00E+00 O.OOE+O0 8.21E-06 O.OOE+00 Total For Period Curies 4.96E-05 5.21E-05 7.15E-04 2.36E-04 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 - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products No Nuclides Found Curies O.OOE+O0 O.OOE+0O O.OOE+00 0.OOE+OO Tritium No Nuclides Found Curies O.OOE+O0 O.OOE+00 0.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.

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Be-7 Curies 3.44E-05 1.26E-05 5,57E-06 1.86E-05 Y-92 Curies O.OOE+00 O.OOE+O0 0.OOE+00 7,66E-06 Y-93 Curies O.OOE+O0 O.OOE+00 3,55E-06 Q.OOE+0O Y-94 Curies 1.91E-06 O.OOE+00 0.OOE+00 0.OOE+00 As-76 Curies 2.35E-04 O.OOE+O0 0.OOE+00 7.72E-06 Br-84 Curies 3.30E-06 1.37E-06 0.QOE+00 0.00E+O0 Co-57 Curies 3.97E-06 O.OOE+00 0.00E+00 2.89E-07 Co-58 Curies 6.62E-03 4.36E-03 1.18E-03 1.25E-03 Co-60 Curies 1.97E-03 1.93E-03 5.47E-03 3.37E-03 Cr-51 Curies 5.29E-05 7.77E-05 2.16E-05 2.17E-04 Fe-55 Curies 2.74E-04 4.80E-04 1.87E-03 3,77E-04 Fe-59 Curies 2.47E-06 O.OOE+00 0.OOE+00 8.85E-07 1-132 Curies 5.34E-05 O.OOE+00 5.04E-07 0.OOE+00 1-133 Curies O.OOE+O0 4.12E-06 0.OOE+00 O.OOE+00 Mn-54 Curies 1.07E-05 7.79E-06 2.15E-05 2.57E-05 Mn-56 Curies O.OOE+00 O.OOE+00 0.OOE+00 1.15E-06 Na-24 Curies 4.19E-05 1.73E-05 0.OOE+00 1.35E-06 Nb-95 Curies 8.84E-05 1.73E-05 9. 19E-06 1.13E-04 Nb-97 Curies 3.37E-06 2.05E-05 5.87E-06 1.30E-04 Ni-56 Curies 2.30E-05 7.89E-06 1.09E-05 5.01E-05 Rb-86 Curies 3.46E-05 O.OOE+00 O.00E+00 0.00E+00 Sr-85 Curies O.OOE+00 O.OOE+00 6.01E-07 O.00E+O0 Sr-90 Curies O.OOE+00 2.85E-06 9.77E-06 4.75E-06 Sr-92 Curies O.OOE+O0 1.94E-06 1.28E-06 0.00E+0O Y-91M Curies 1.84E-06 O.OOE+00 0.OOE+00 Q.OOE+00 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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Zn-65 Curies 3.63E-05 6.35E-05 3.28E-04 1.55E-04 Zr-95 Curies 2.80E-05 O.OOE+00 0.OOE+00 3.83E-05 Zr-97 Curies O.OOE+00 0.OOE+00 5.60E-07 0.OOE+00 Ba-140 Curies 0.00E+00 5.98E-06 1.99E-06 0.OOE+00 Cd-109 Curies 0.00E+00 0.OOE+00 9.56E-05 0.OOE+00 Cd-115 Curies 0.00E+00 0.OOE+00 1.58E-06 2.63E-07 Ce-141 Curies 0.00E+00 0.OOE+00 9.73E-07 0.OOE+00 Cs-137 Curies 7.11E-05 2.14E-04 1.15E-04 3.97E-05 Eu-155 Curies 0.00E+00 3.31E-06 4.11E-06 0.00E+00 La-142 Curies 2.42E-06 1.73E-06 4.30E-06 0.OOE+00 Pr-146 Curies 0.00E+00 0.OOE+00 9.35E-07 O.OOE+00 Rh-105 Curies 0.O0E+00 3.34E-05 0.00E+00 8.99E-05 Sb-122 Curies 9.87E-06 0.OOE+00 0.OOE+00 0.OOE+00 Sb-124 Curies 1.13E-04 1.01E-04 O.00E+00 2.19E-06 Sb-125 Curies 2.34E-03 1.90E-03 1.12E-02 9.04E-04 Sb-126 Curies 1.07E-06 0.00E+00 0.00E+00 0.00E+00 Sn-113 Curies 0.O0E+00 0.00E+00 0.00E+00 2.58E-06 Tc-101 Curies 8.39E-07 0.OOE+00 0.OOE+00 0.OOE+00 Tc- 104 Curies 1.43E-06 0.OOE+00 0.00E+00 0.OOE+00 Tc-99M Curies 1.33E-05 6.75E-06 0.00E+00 0.OOE+00 Te-127 Curies 0.00E+00 0.OOE+00 0.00E+00 2.33E-05 Te-131 Curies 1.66E-07 0.OOE+00 0.00E+00 0.OOE+00 Te-132 Curies 4.75E-05 0.OOE+00 9.04E-07 0.OOE+00 Ag-108M Curies 0.OOE+00 1.11E-06 7.13E-05 1. 14E-05 Ag-110M Curies 3.05E-06 1.31E-05 0.OOE+00 1.14E-05 In-115M Curies 0.00E+00 0.OOE+00 1.65E-06 2.73E-07 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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents Unit: Site Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Sn-117M Curies 5.21E-06 4.22E-06 O.OOE+O0 3.86E-06 Te-125M Curies 2.75E-02 3.82E-02 5.73E-02 9.31E-03 Total For Period Curies 3.96E-02 4.75E-02 7.78E-02 1.62E-02 Tritium H-3 Curies 2.60E+02 2.75E+02 3.62E+02 2.08E+02 Dissolved And Entrained Gases Ar-41 Curies 8.29E-06 0.OOE+00 O.OOE+00 2.97E-05 Kr-85 Curies O.OOE+00 0.OOE+00 1.33E-04 O.OOE+0Q Xe-133 Curies 3.85E-05 6.77E-05 8.65E-04 4.95E-04 Xe-135 Curies 4.82E-07 0.OOE+Q0 1.82E-06 0.OOE+00 Xe-131M Curies 8.67E-06 3.02E-05 O.OOE+O0 0.OOE+00 Xe-133M Curies O.OOE+00 1.09E-05 5.59E-06 0.OOE+00 Xe-135M Curies O.OOE+00 0.OQE+O0 8.21E-06 0.OOE+00 Total For Period Curies 5.59E-05 1.09E-04 1.01E-03 5.25E-04 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 Joseph M Farley 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 1ST Qtr %/oODCM 2ND Qtr %/oODCM 3RD Qtr %/oODCM 4TH Qtr %/aODCM Bone 5.0OE+00 mRem 2.60E-03 5.20E-02 6.54E-03 1.31E-01 6.23E-03 1.25E-01 2.37E-03 4.75E-02 GI-Lli 5.O0E+00 mRem 1.23E-02 2.46E-01 2.71E-02 5.41E-01 2.72E-02 5.44E-01 1.12E-02 2.24E-01 Kidney 5.OOE+00 mRem 1.13E-02 2.25E-01 2.67E-02 5.35E-01 2.59E-02 5.17E-01 1.07E-02 2.14E-01 Liver 5.OOE+00 mRem 2.08E-03 4.16E-02 3.93E-03 7.85E-02 4.37E-03 8.75E-02 3.03E-03 6.06E-02 Lung 5.OOE+00 mRem 4.61E-03 9.23E-02 5.45E-03 1.09E-01 1.70E-02 3.39E-01 4.32E-03 8.63E-02 Thyroid 5.0OE+00 mRem 1.81E-03 3.62E-02 3.34E-03 6.68E-02 3.77E-03 7.54E-02 2.76E-03 5.53E-02 Total Body 5.O0E+00 mRem 1.52E-03 3.03E-02 2.45E-03 4.90E-02 2.98E-03 5.95E-02 2.56E-03 5.12E-02 Total Body 1.50E+00 mRem 1.52E-03 1.01E-01 2.45E-03 1.63E-01 2.98E-03 1.98E-01 2.56E-03 1.71E-01 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %/aODCM Receptor Limit Bone 1.OOE+01 mRem 1.77E-02 1.77E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+01 mRem 7.78E-02 7.78E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+01 mRem 7.46E-02 7.46E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+01 mRem 1.34E-02 1.34E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.OOE+01 mRem 3.13E-02 3.13E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.OOE+01 mRem 1.17E-02 1.17E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Bodv 1.00E+01 mRem 9.50E-03 9.50E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 9.50E-03 3.17E-01 Maximum Individual Liquid Liquid Effluent TB Annual

- 19 -

Table 1-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per Quarter

%/oODCM 4TH Qtr 0/b ODCM Organ ODCM Lmt Units 1ST Qtr 0/o ODCM 2ND Qtr O/o ODCM 3RD Qtr Bone 5.O0E+00 mRem 9.86E-03 1.97E-01 8.95E-03 1.79E-01 1.43E-02 2.87E-01 2.16E-03 4.33E-02 GI-Lli 5.OOE+00 mRem 4.29E-02 8.59E-01 3.77E-02 7.54E-01 5.92E-02 1.18E+00 9.79E-03 1.96E-01 Kidney 5.OOE+00 mRem 4.15E-02 8.29E-01 3.71E-02 7.42E-01 5.62E-02 1.12E+00 9.01E-03 1.80E-01 Liver 5.0OE+00 mRem 6.08E-03 1.22E-01 5.07E-03 1.01E-01 6.84E-03 1.37E-01 1.44E-03 2.88E-02 Lung 5.00E+00 mRem 1.26E-02 2.52E-01 7.45E-03 1.49E-01 3.65E-02 7.31E-01 2.94E-03 5.87E-02 Thyroid 5.OOE+00 mRem 5.19E-03 1.04E-01 4.25E-03 8.49E-02 5.63E-03 1.13E-01 1.21E-03 2.42E-02 Total Body 5.OOE+00 mRem 3.84E-03 7.67E-02 3.05E-03 6.1OE-02 3.74E-03 7.48E-02 9.73E-04 1.95E-02 Total Body 1.50E+00 mRem 3.84E-03 2.56E-01 3.05E-03 2.03E-01 3.74E-03 2.49E-01 9.73E-04 6.49E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %/oODCM Receptor Limit Bone 1.00E+01 mRem 3.53E-02 3.53E-01 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.OOE+01 mRem 1.50E-01 1.50E+00 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.OOE+01 mRem 1.44E-01 1.44E+00 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.OOE+01 mRem 1.94E-02 1.94E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 5.95E-02 5.95E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.OOE+01 mRem 1.63E-02 1.63E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.OOE+01 mRem 1.16E-02 1.16E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.OOE+00 mRem 1.16E-02 3.87E-01 Maximum Individual Liquid Liquid Effluent TB Annual TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 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

- 21 -

Table 1-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Batch 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 batch releases 98 54 73 80 305

2. Total time period for Batch releases ( Minutes) 1.16E+04 6.56E+03 8.42E+03 1.76E+04 4.42E+04

3. Maximum time period for a batch release ( Minutes) 1.35E+02 1.48E+02 1.37E+02 8.62E+03 8.62E+03

4. Average time period for a batch release ( Minutes) 1.18E+02 1.21E+02 1.15E+02 2.20E+02 1.45E+02

5. Minimum time period for a batch release ( Minutes) 1.02E+02 1.09E+02 1.OOE+02 9.80E+01 9.80E+01

6. Average stream flow during periods of release of liquid effluent into a flowing stream * (CFS) 8.46E+03 5.61E+03 3.32E+03 2.46E+03 4.94E+03

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

22 -

Table 1-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Liquid Effluents - Batch 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 batch releases 88 76 114 94 372

2. Total time period for Batch releases ( Minutes) 8.37E+03 7.43E+03 1.15E+04 9.62E+03 3.69E+04

3. Maximum time period for a batch release ( Minutes) 1.29E+02 1.30E+02 1.34E+02 1.45E+02 1.45E+02

4. Average time period for a batch release ( Minutes) 9.51E+01 9.77E+01 1.01E+02 1.02E+02 9.93E+01

5. Minimum time period for a batch release ( Minutes) 6.70E+01 2.OOE+00 8.50E+01 8.50E+01 2.OOE+00

6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS) 8.46E+03 5.61E+03 3.32E+03 2.46E+03 4.94E+03

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

- 23 -

Table 1-6A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 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 1 1

2. Total Time For All Releases ( Minutes) O.OOE+00 O.OOE+00 O.OOE+00 8.62E+03 8.62E+03

3. Maximum Time For A Release ( Minutes) O.OOE+00 O.OOE+00 O.OOE+00 8.62E+03 8.62E+03

4. Average Time For A Release ( Minutes) O.OOE+O0 O.00E+00 0.OOE+00 8.62E+03 8.62E+03

5. Minimum Time For A Release ( Minutes) O.OOE+00 O.OOE+00 0.OOE+00 8.62E+03 8.62E+03

6. Total activity for all releases ( Curies ) O.OOE+00 0.00E+00 0.OOE+00 1.16E-04 1.16E-04

- 24 -

Table 1-6B Joseph M Farley 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 (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 O.OOE+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.OOF+00 O.OOE+00

6. Total activity for all releases (Curies ) O.OOE+00 O.OOE+00 O.OOE+O0 0.OOlE+00 O.OOE+00 2.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2011.

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

- 27 -

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

The average error associated with counting is estimated to be:

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

- 30 -

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 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.

- 31 -

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

Unit 1 2011 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2011 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4B Unit 1 2011 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5A Unit 2 2011 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 2011 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2011 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 2011.

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

Unit 1 2011 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2011 Gaseous Effluents - Abnormal Release Summary: Table 2-8B

- 32 -

Table 2-1A Joseph M Farley 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 2.37E-01 7.87E-01 8.62E-01 1.52E+00

2. Average Release rate for period uCi/sec 3.OOE-02 9.99E-02 1.09E-01 1.93E-01

3. Percent of Applicable Limit % * *

B. Radioiodines

1. Total Iodine-131 Curies 1.92E-06 O.OOE+00 O.OOE+00 O.OOE+00

2. Average Release rate for period uCi/sec 2.44E-07 0.OOE+00 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit %* * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 2.77E-04 O.OOE+00 1.46E-06 2.74E-07

2. Average Release rate for period uCi/sec 3.51E-05 O.OOE+00 1.85E-07 3.48E-08

3. Percent of Applicable Limit %* * *

D. Tritium

1. Total Release Curies 1.35E+00 1.40E+00 1.97E+00 1.41E+00

2. Average Release rate for period uCi/sec 1.71E-01 1.78E-01 2.50E-01 1.78E-01

3. Percent of Applicable Limit * * *

E. Gross Alpha

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

- 33 -

Table 2-1B Joseph M Farley 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 8.77E-01 8.25E-01 3.86E-01 1.06E+00

2. Average Release rate for period uCi/sec 1.11E-01 1.05E-01 4.90E-02 1.35E-01

3. Percent of Applicable Limit %* * *

B. Radioiodines

1. Total Iodine-131 Curies 5.86E-07 O.OOE+00 O.OOE+00 2.44E-07

2. Average Release rate for period uCi/sec 7.43E-08 0.OOE+00 O.OOE+00 3.09E-08

3. Percent of Applicable Limit %* * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 1.26E-08 3.79E-09 0.OOE+00 2.39E-09

2. Average Release rate for period uCi/sec 1.59E-09 4.81E-10 0.00E+00 3.03E-10

3. Percent of Applicable Limit %* * *

D.Tritium

1. Total Release Curies 3.67E+00 3.62E+00 3.81E+00 8.56E+00

2. Average Release rate for period uCi/sec 4.65E-01 4.60E-01 4.83E-01 1.09E+00

3. Percent of Applicable Limit * * *

E. Gross Alpha

1. Total Release Curies 0.OE+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.

- 34 -

Table 2-1C Joseph M Farley 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 1.11E+00 1.61E+00 1.25E+00 2.59E+00

2. Average Release rate for period uCi/sec 1.41E-01 2.04E-01 1.58E-01 3.28E-01

3. Percent of Applicable Limit %

B. Radioiodines

1. Total Iodine-131 Curies 2.51E-06 O.OOE+00 O.OOE+00 2.44E-07

2. Average Release rate for period uCi/sec 3.18E-07 O.OE+00 O.OOE+00 3.09E-08

3. Percent of Applicable Limit %* * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 2.77E-04 3.79E-09 1.46E-06 2.77E-07

2. Average Release rate for period uCi/sec 3.51E-05 4.81E-10 1.85E-07 3.51E-08

3. Percent of Applicable Limit %* * *

D. Tritium

1. Total Release Curies 5.01E+00 5.03E+00 5.78E+00 9.97E+00

2. Average Release rate for period uCi/sec 6.36E-01 6.38E-01 7.33E-01 1.26E+00

3. Percent of Applicable Limit * * *

E. Gross Alpha

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

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

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

- 35 -

Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2011 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan- 2011 Ending: 31-Dec-2011 Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 0.OE+00 5.13E-01 2.64E-01 6.56E-01 Total For Period Curies O.OOE+00 5.13E-01 2.64E-01 6.56E-01 lodines 1-131 Curies 1.92E-06 O.OOE+O0 O.OOE+0Q 0.OOE+Q0 Total For Period Curies 1.92E-06 O.OOE+O0 O.OOE+OO Particulates Be-7 Curies O.OOE+O0 0.O0E+00 1.44E-06 O.OOE+00 Sr-89 Curies O.OOE+O0 O.OOE+00 2.27E-08 2.74E-07 Total For Period Curies O.OOE+00 O.OOE+00 1.46E-06 2.74E-07 Tritium H-3 Curies 1.33E+00 1.35E+00 1.79E+00 1.29E+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.