Text

Enclosure 2: Farley Annual Radioactive Effluent Release Report for 2013
	ML14125A099
Person / Time
Site:	Farley
Issue date:	04/30/2014
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML14125A094	List: ML14125A097; ML14125A098; ML14125A099; ML14125A100; ML14125A101; NL-14-0659, Edwin I. Hatch, Units 1 & 2, Joseph M. Farley, Units 1 & 2, Vogtle, Units 1 & 2, Southern Nuclear Operating Company'S Submittal of Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manuals for 2013; NL-14-0659, Enclosure 1: Hatch Annual Radioactive Effluent Release Report for 2013; NL-14-0659, Enclosure 2: Farley Annual Radioactive Effluent Release Report for 2013; NL-14-0659, Enclosure 3: Vogtle Annual Radioactive Effluent Release Report for 2013; NL-14-0659, Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23; NL-14-0659, Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 29;
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Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manuals for 2013 Farley Annual Radioactive Effluent Release Report for 2013

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 2013

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 27 2.1 Regulatory Requirements 27 2.1.1 Dose Rate Limits 27 2.1.2 Air Doses Due to Noble Gases in 27 Gaseous Releases 2.1.3 Doses to a Member of the Public 28 2.2 Measurements and Approximation 28 of Total Radioactivity 2.2.1 Sample Collection and Analysis 29

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 2.2.2 Total Quantities of Radioactivity, Dose 29 Rates and Cumulative Doses 2.2.2.1 Fission and Activation Gases 30 2.2.2.2 Radioiodine, Tritium and Particulate 30 Releases 2.2.2.3 Gross Alpha Release 31 2.2.3 Total Error Estimation 31 2.3 Gaseous Effluent Release Data 32 2.4 Radiological Impact Due to Gaseous 33 Releases 2.5 Gaseous Effluents - Batch Releases 33 2.6 Gaseous Effluents -

Abnormal Releases 33 3.0 SOLID WASTE 58 3.1 Regulatory Requirements 58 3.1.1 Solid Radioactive Waste System 58 3.1.2 Reporting Requirements 58 3.2 Solid Waste Data 58 4.0 DOSES TO MEMBERS OF THE PUBLIC 61 INSIDE THE SITE BOUNDARY 4.1 Regulatory Requirements 61 4.2 Demonstration of Compliance 61

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 5.0 TOTAL DOSE FROM URANIUM FUEL 65 CYCLE (40CFR190) 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 SERVICE WATER DILUTION BIAS 68 App.A Appendix A, Carbon-14 Supplement for 2013 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, 12 3 and 4) 1-2C Liquid Effluents, Site (Quarters 1,2, 16 3 and 4) 1-3A Doses to a MEMBER OF THE PUBLIC 20 Due to Liquid Releases, Unit 1 (Quarters 1,2,3 and 4) 1-3B Doses to a MEMBER OF THE PUBLIC 21 Due to Liquid Releases, Unit 2 (Quarters 1,2,3 and 4) 1-4 Minimum Detectable Concentration -

22 Liquid Sample Analyses 1-5A Liquid Effluents - Batch Release 23 Summary, Unit 1 1-5B Liquid Effluents - Batch Release 24 Summary, Unit 2

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-6A Liquid Effluents -

Abnormal Release 25 Summary, Unit 1 1-6B Liquid Effluents - Abnormal Release 26

Summary, Unit 2 2-1A Gaseous Effluents -

Summation of 34 All Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-1B Gaseous Effluents -

Summation of 35 All Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-1C Gaseous Effluents -

Summation of 36 All Releases, Site (Quarters 1,2, 3 and 4) 2-2A Gaseous Effluents -

Mixed Mode 37 Level Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-2B Gaseous Effluents -

Mixed Mode 39 Level Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-2C Gaseous Effluents -

Mixed Mode 41 Level Releases, Site (Quarters 1,2, 3 and 4) 2-3A Gaseous Effluents -

Ground 43 Level Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-3B Gaseous Effluents -

Ground 45 Level Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-3C Gaseous Effluents -

Ground 47 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 49 Gaseous Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-4B Air Doses Due to Noble Gases in 50 Gaseous Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-5A Doses to a MEMBER OF THE PUBLIC 51 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 52 Due to Radioiodines, Tritium, and Particulates in Gaseous Releases, Unit 2 (Quarters 1,2,3 and 4) 2-6 Minimum Detectable Concentration -

53 Gaseous Effluent Analyses 2-7A Gaseous Effluents -

Batch Release 54

Summary, Unit 1 2-7B Gaseous Effluents - Batch Release 55 Summary, Unit 2 2-8A Gaseous Effluents - Abnormal Release 56 Summary, Unit 1 2-8B Gaseous Effluents - Abnormal Release 57 Summary, Unit 2 3-1 Solid Waste and Irradiated 59 Fuel Shipments 4-1 Doses to a MEMBER OF THE PUBLIC 62 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 2013.

These quantities are summarized on a quarterly basis and include any unplanned releases. A tabulation of the total body and organ doses which were calculated in accordance with ODCM 2.4 are presented to show conformance with the limits of ODCM 2.1.3.

1.1 Regulatory Requirements 1.1.1 Concentration Limits Technical Specifications 5.5.4.b and 5.5.4.c state that the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited at all times to ten times the concentrations specified in

10CFR20, Appendix B, Table 2,

Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-04 uCi/ml total activity.

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

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b.

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

1.2 Effluent Concentration Limit (ECL)

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

A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor setpoints which can accommodate effluent releases at concentrations higher than the ECL values stated in

10CFR20, Appendix B, Table 2, Column 2.

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

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

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

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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.

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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 2013 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-IB, and 1-IC; 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 2013 Doses to a Member of the Public due to Liquid Releases:

Table 1-3A Unit 2 2013 Doses to a Member of the Public due to Liquid Releases:

Table 1-3B 3 -

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

Unit 1 2013 Liquid Effluents -

Batch Release Summary: Table 1-5A Unit 2 2013 Liquid Effluents -

Batch Release Summary: Table 1-5B 1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases during 2013.

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

Unit 1 2013 Liquid Effluents - Abnormal Release Summary: Table 1-6A Unit 2 2013 Liquid Effluents - Abnormal Release Summary: Table 1-6B 4 -

Table 1-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Summation of All Releases Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Type of Effluent A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha)

2. Average diluted concentration during period

3. Percent of Applicable Limit B. Tritium

1. Total Release

2. Average diluted Concentration during period

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

1. Total Release

2. Average diluted Concentration during period

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Curies uCi/mL Curies uCi/mL Curies uCi/mL Curies Liters Liters 1.47E-02 1.35E-08 1.60E+0-2 1.47E-04 5.50E-04 5.05E-10 O.OOE+OO 1.34E+06 1.09E+09 1.44E-02 1.21E-08 1.43E+02 1.20E-04 1.74E-03 1.46E-09 O.OOE+00 1.32E+06 1.19E+09 1.68E-02 1.07E-09 9.68E+01 6.14E-06 1.07E-02 6.81E-10 0.OOE+00 2.57E+07 1.57E+10 3.13E-02 3.86E-08 3.94E+01 4.86E-05 1.27E-03 1.57E-09 0.OOE+00 9.79E+05

8. 10E+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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Summation of All Releases Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Type of Effluent A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha)

2. Average diluted concentration during period

3. Percent of Applicable Limit B. Tritium

1. Total Release

2. Average diluted Concentration during period

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

1. Total Release

2. Average diluted Concentration during period

3. Percent of Applicable Limit O: Gross Alpha Radioactivity

1. Total Release E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Curies uCi/mL Curies uCi/mL Curies uCi/mL Curies 3.43E-02 2.14E-08 1.90E+02 1.18E-04 6.89E-04 4.30E-10 O.OOE+00 1.80E+06 1.60E+09 1.72E-02 1.18E-08 9.95E+01 6.83E-05 1.66E-03

1. 14E-09 O.OOE+O0 1.71E+06 1.45E+09 2.40E-02 1.59E-09 7.40E+01 4.91E-06 8.43E-03 5.60E-10 O.OOE+O0

2. 10E+07 1.51E+10 3.70E-02 3.84E-08 5.96E+01 6.19gE-05 1.28E-03 1.33E-09 0.OOE+00

1. 17E+06 9.62E+08 Liters Liters

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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Summation of All Releases Unit: Site Starting: 1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Type of Effluent A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha)

2. Average diluted concentration during period

3. Percent of Applicable Limit B. Tritium

1. Total Release

2. Average diluted Concentration during period

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

1. Total Release

2. Average diluted Concentration during period

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Curies uCi/mL Curies uCi/mL Curies uCi/mL Curies Liters Liters 4.90E-02 1.82E-08 3.50E+02 1.30E-04 1.24E-03 4.61E-10 0.OOE+00

3. 14E+06 2.69E+09 3.16E-02 1.19E-08 2.43E+02 9.17E-05 3.40E-03 1.28E-09 0.OOE+00 3.03E+06 2.64E+09 4.09E-02 1.32E-09 1.71E+02 5.54E-06 1.92E-02 6.22E-10 0.OOE+00 4.68E+07 3.08E+10 6.83E-02 3.85E-08 9.90E+01 5.58E-05 2.55E-03 1.44E-09 0.OOE+00 2.15E+06 1.77E+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 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode Nuclides Released Fission & Activation Products Sr-90 Total For Period Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.16E-05 8.16E-05 O.OOE+00 O.OOE+00 Curies O.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Curies Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Y-88 Curies 0.OOE+00 3.12E-07 0.OOE+00 3.09E-07 Y-91 Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.46E-04 Y-94 Curies 1.79E-06 0.OOE+00 0.OOE+00 0.OOE+00 As-76 Curies 0.OOE+00 2.02E-05 0.OOE+00 3.28E-06 Co-58 Curies 4.66E-04 6.ý9E-04 3.48E-04 2.90E-03 Co-60 Curies 4.59E-04 4.39E-04 5.54E-04 1.27E-03 Cr-51 Curies 2.24E-04 2.31E-04 4.82E-05 1.22E-03 Fe-55 Curies 3.60E-05 9.66E-05 5.1OE-05 1.11E-03 Fe-59 Curies O.OOE+00 1.36E-06 O.OOE+00 8.44E-06 1-130 Curies O.OOE+00 O.OOE+00 O.OOE+00 5.94E-07 1-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 6.81E-07 1-132 Curies O.OOE+O0 O.OOE+00 O.OOE+00 1.92E-06 1-133 Curies O.OOE+O0 O.OOE+00 2.22E-06 O.OOE+00 Mn-54 Curies 4.76E-06 1.06E-06 1.03E-05 1.85E-05 Nb-95 Curies 6.23E-05 6.68E-05 6.27E-05 4.48E-04 Nb-97 Curies O.OOE+00 5.20E-06 O.OOE+00 2.49E-05 Ni-56 Curies 2.10E-06 3.14E-05 3.52E-05 4.94E-05 Ni-63 Curies 3.08E-04 1.70E-04 4.16E-04 8.22E-04 Sr-85 Curies O.OOE+00 O.OOE+00 5.55E-07 O.OOE+00 Sr-90 Curies 8.52E-06 4.29E-06 6.04E-06 3.73E-06 Sr-92 Curies O.OOE+00 O.OOE+00 O.OOE+O0 6.07E-07 Zn-65 Curies 2.07E-06 1.94E-06 1.16E-06 1.64E-05 Zr-95 Curies 2.95E-05 3.11E-05 2.36E-05 2.36E-04 Ce-141 Curies 1.59E-06 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 Curies 1.85E-05 1.63E-06 1.03E-04 3.21E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released CS-139 Hg-203 Pr-144 Pr-146 Rh-105 Sb-122 Sb-124 Sb-125 Sn-113 Tc-99M Te-129 Te-132 Ag-108M Ag-110M Sn-117M Te-125M Te-129M Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

1. 12E-04 O.OOE+00 1.17E-05 4.11E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.80E-06 1.25E-02 O.OOE+00 2ND Quarter O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O 9.86E-05 O.OOE+00 5.42E-06 2.30E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.77E-05 1.25E-02 O.OOE+00 3RD Quarter 2.95E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.12E-06 1.71E-04 0.OOE+00 3.32E-06 0.OOE+00 0.OOE+00 2.73E-07 0.OOE+00 4.12E-07 1.49E-02 0.00E+00 1.67E-02 9.68E+01 4TH Quarter O.OOE+00 6.98E-07 4.34E-04 1.40E-06 5.24E-04 5.90E-07 2.89E-05 5.70E-04 5.91E-06 0.OOE+00 6.70E-05 8.98E-06 3.57E-06 2.46E-05 0.OOE+00 2.12E-02 1.02E-04 3.13E-02 3.94E+01 1.47E-02 1.44E-02 Tritium H-3 Curies 1.60E+02 1.43E+02 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Dissolved And Entrained Gases Ar-41 Kr-85 Kr-88 Xe-133 Xe-135 Xe-131M Xe-133M Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter 4.24E-05 O.OOE+00 0.OOE+00 5.08E-04 0.OOE+00 0.OOE+00 0.OOE+00 5.50E-04 2.02E-05 0.OOE+00 0.OOE+00 1.68E-03 3.28E-05 0.OOE+00 3.51E-06 1.74E-03 1.12E-06 1.23E-04 0.OOE+00 1.05E-02 3.56E-05 O.OOE+00 4.87E-05 1.07E-02 0.OOE+00 0.OOE+O0 9.45E-06 1.25E-03 0.OOE+00 1.64E-05 0.OOE+00 1.27E-03 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

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Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode Nuclides Released Fission & Activation Products Sr-90 Total For Period Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies Curies Curies O.OOE+O0 O.OOE+O0 O.OOE+O0

0. OOE+ 00 0.OOE+00 O.OOE+OO 0.OOE+00 O.OOE+00 8.86E-05 0.OOE+00 8.86E-05 O.OOE+OO 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Curies Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

12 -

Table 1-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Y-94 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 1.32E-06 As-76 Curies O.OOE+O0 1.27E-05 O.OOE+O0 3.41E-05 Br-82 Curies O.OOE+O0 O.OOE+O0 3.20E-05 O.OOE+O0 Br-84 Curies O.OOE+O0 O.OOE+O0 1.49E-06 O.OOE+O0 Co-57 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 1.97E-06 Co-58 Curies 1.35E-03 4.90E-04 3.22E-04 1.83E-03 Co-60 Curies 1.24E-03 7.14E-04 5.97E-04 9.37E-04 Cr-51 Curies 5.71E-04 2.69E-04 1.27E-05 3.36E-04 Fe-55 Curies 4.84E-05 1.OOE-04 2.77E-05 4.30E-04 Fe-59 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 9.36E-06 1-131 Curies 1.90E-06 1.07E-06 2.83E-07 O.OOE+O0 1-132 Curies 4.41E-07 O.OOE+O0 4.29E-07 5.27E-06 1-133 Curies 2.76E-05 1.96E-05 8.98E-06 O.OOE+O0 Mn-54 Curies 2.47E-05 9.76E-06 1.81E-06 1.15E-05 Mn-56 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 5.53E-07 Mo-99 Curies O.OOE+O0 2.72E-06 O.OOE+O0 O.OOE+O0 Na-24 Curies 1.38E-04 9.07E-05 2.49E-04 O.OOE+O0 Nb-95 Curies 1.43E-04 9.90E-05 3.97E-05 1.13E-04 Nb-97 Curies O.OOE+O0 3.67E-07 O.OOE+O0 8.83E-06 Ni-56 Curies 1.80E-06 2.98E-05 3.90E-05 3.55E-05 Ni-63 Curies 3.13E-04 2.33E-04 3.96E-04 3.89E-04 Sr-90 Curies O.OOE+O0 O.OOE+O0 6.50E-06 O.OOE+O0 Y-91M Curies O.OOE+O0 O.OOE+O0 2.86E-06 O.OOE+O0 Zn-65 Curies 3.03E-05 2.60E-06 7.87E-06 O.OOE+O0 Zr-95 Curies 8.64E-05 4.06E-05 1.36E-05 4.54E-05 Zeroes in this table indicate 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 - 2013 Liquid Effluents Unit: 2 1-Jan-2013 Ending: 31-Dec-2013 Starting:

Batch Mode Nuclides Released Ce-141 Ce-144 Cs-137 Eu-155 La-142 Pr-144 Pr-146 Rh-105 Sb-122 Sb-124 Sb-125 Sn-113 Tc-99M Te-129 Te-132 Te-133 Ag-108M Ag-110M Sn-117M Te-125M Te-129M Total For Period Tritium H-3 Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 0.OOE+00 0.00E+00 2.19E-06 0.OOE+00 0.OOE+00 3.76E-05 0.OOE+00 3.OOE-04 0.OOE+00 1.10E-05 2.50E-04 0.OOE+00 1.87E-05 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 O.OOE+00 8.22E-06 2.97E-02 O.OOE+00 2ND Quarter 0.00E+00 2.81E-06 1.35E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

1. 16E-04 0.OOE+00 0.OOE+00 9.38E-05 0.OOE+00 1.1OE-05 0.OOE+00 0.OOE+00 0.OOE+00 2.85E-07 0.OOE+00 3.96E-05 1.48E-02 0.OOE+00 3RD Quarter 0.OOE+00 0.OOE+00 1.13E-05 9.04E-07 1.47E-06 0.OOE+00 1.10E-06 1.30E-06 2.43E-05 8.68E-05 8.06E-05 0.OOE+00 1.37E-05 3.50E-06 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 1.88E-05 2.19E-02 0.OOE+00 4TH Quarter 9.50E-07 0.OOE+00 1.58E-05 0.OOE+00 0.OOE+00 8.61E-05 0.00E+00 1.59E-04 6.11E-06 7.14E-05 6.79E-04 2.74E-06 7.07E-07 1.25E-04 1.12E-05 2.16E-06 1.84E-06 1.11E-05 3.33E-06 3.16E-02 2.20E-05 Curies 3.43E-02 1.72E-02 2.39E-02 3.70E-02 Curies 1.90E+02 9.95E+01 7.40E+01 5.96E+01 14

Table 1-213 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nuclides Released Unit Dissolved And Entrained Gases Ar-41 Kr-87 Kr-88 Xe-133 Xe-135 Xe-133M Total For Period Curies 7.38E-05 Curies O.OOE+O0 Curies O.OOE+O0 Curies 6.14E-04 Curies 1.1OE-06 Curies O.OOE+O0 Curies 6.89E-04 2.05E-05 O.OOE+O0 1.32E-06 1.60E-03 3.30E-05 6.87E-06 1.66E-03 3.52E-06 1.30E-06 O.OOE+O0 8.37E-03 3.18E-05 3.25E-05 8.43E-03 O.OOE+O0 O.OOE+O0 O.OOE+00 1.27E-03 6.52E-06 O.OOE+0O 1.28E-03 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

15 -

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: Site Starting: 1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode Nuclides Released Fission & Activation Products Sr-90 Total For Period Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies Curies Curies O.OOE+00 O.OOE+O0 0.00E+00 O.OOE+OO 1.70E-04 1.70E-04 0.00E+00 O.OOE+OO Tritium No Nuclides Found 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies Zeroes in this table indicate 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 - 2013 Liquid Effluents Unit: Site Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter Fission & Activation Products Y-88 Y-91 Y-94 AS-76 Br-82 Br-84 Co-57 CO-58 Co-60 Cr-51 Fe-55 Fe-59 1-130 1-131 1-132 1-133 Mn-54 Mn-56 Mo-99 Na-24 Nb-95 Nb-97 Ni-56 Ni-63 Sr-85 Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 0.OOE+00 0.OOE+O0 1.79E-06 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 1.8 1E-03 1.70E-03 7.95E-04 8.44E-05 0.OOE+00 0.001E+00 1.90E-06 4.41E-07 2.76E-05 2.95E-05 0.OOE+00 0.OOE+00 1.38E-04 2.05E-04 0.OOE+00 3.90E-06 6.21E-04 0.OOE+00

3. 12E-07 0.OOE+00 0.OOE+00 3.30E-05 0.OOE+00 0.OOE+00 0.OOE+00

1. 15E-03

1. 15E-03 5.OOE-04 1.97E-04 1.36E-06 O.OOE+00 1.07E-06 0.OOE+O0 1.96E-05 1.08E-05 0.OOE+00 2.72E-06 9.07E-05 1.66E-04

5. 56E-06

6. 12E-05 4.03E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.20E-05 1.49E-06 0.OOE+00 6.70E-04

1. 15E-03 6.09E-05 7.86E-05 0.OOE+00 0.OOE+00 2.83E-07 4.29E-07 1.12E-05 1.2 1E-05 O.OOE+00 0.OOE+00 2.49E-04 1.02E-04 0.OOE+00 7.41E-05

8. 12E-04 5.55E-07 4TH Quarter 3.09E-07 1.46E-04 1.32E-06 3.74E-05 0.OOE+00 0.OOE+00 1.97E-06 4.73E-03 2.21E-03 1.56E-03 1.54E-03 1.78E-05 5.94E-07 6.81E-07

7. 19E-06 0.OOE+00 3.OOE-05 5.53E-07 0.OOE+00 0.OOE+00 5.61E-04 3.37E-05 8.48E-05 1.2 1E-03 0.OOE+00 Zeroes in this table indicate 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 - 2013 Liquid Effluents Unit: Site Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter Sr-90 Sr-92 Y-91M Zn-65 Zr-95 Ce-141 Ce-144 Cs-137 Cs-139 Eu-155 Hg-203 La-142 Pr-144 Pr-146 Rh-105 Sb-122 Sb-124 Sb-125 Sn-113 Tc-99M Te-129 Te-132 Te-133 Ag-108M Ag-110M Sn-117M Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 8,52E-06 0.OOE+00 0.OOE+00 3.23E-05

1. 16E-04 1.59E-06 0.OOE+00 2.06E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.76E-05 0.OOE+00

4. 11E-04 0.00E+00 2.27E-05 6.61E-04 0.OOE+00 1.87E-05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00

1. lOE-05 4.29E-06 0.O0E+00 0.00E+00 4.54E-06 7.17E-05 0.OOE+00 2.81E-06 1.51E-05 0.00E+00 0.O0E+00 0.00E+00 0.O0E+00 0.00E+00 0.OOE+00 2.15E-04 0.OOE+00 5.42E-06

1. 17E-04 0.O0E+00 1.10E-05 0.O0E+00 0.OOE+00 0.00E+00 2.85E-07 0.00E+00 6.73E-05 1.25E-05 0.O0E+00 2.86E-06 9.03E-06 3.72E-05 0.OOE+00 0.00E+00

1. 14E-04 2.95E-05 9.04E-07 0.OOE+00 1.47E-06 0.00E+00 1.10E-06 1.30E-06 2.43E-05 9.29E-05 2.52E-04 0.00E+00 1.70E-05 3.50E-06 0.OOE+00 0.OOE+00 2.73E-07 0.C0E+00 1.92E-05 4TH Quarter 3.73E-06 6.07E-07 0.O0E+00 1.64E-05 2.81E-04 9.50E-07 0.0OE+00 4.79E-05 0.OOE+00 0.O0E+00 6.98E-07 0.00E+00 5.20E-04 1.40E-06 6.83E-04 6.70E-06 1.00E-04 1.25E-03 8.65E-06 7.07E-07 1.92E-04 2.02E-05 2.16E-06 5.42E-06 3.57E-05 3.33E-06 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

18

Table 1-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents Unit: Site Starting: 1-Jan-2013 Ending: 31-Dec-2013 Batch Mode Nuclides Released Te-125M Te-129M Total For Period Unit Curies Curies Curies 1ST Quarter 4.22E-02 0.00E+00 4.90E-02 2ND Quarter 2.73E-02 0.OOE+00 3.16E-02 3RD Quarter 3.68E-02 0.OOE+00 4.07E-02 4TH Quarter 5.28E-02 1.24E-04 6.83E-02 Tritium H-3 Dissolved And Entrained Gases Ar-41 Kr-85 Kr-87 Kr-88 Xe-133 Xe-135 Xe-131M Xe-133M Total For Period Curies 3.50E+02 2.43E+02 1.71E+02 9.90E+01 Curies Curies Curies Curies Curies Curies Curies Curies Curies

1. 16E-04 O.OOE+00 O.OOE+00 O.OOE+00

1. 12E-03

1. 1OE-06 O.OOE+00 O.OOE+00 1.24E-03 4.07E-05 0.OOE+00 0.OOE+00 1.32E-06 3.28E-03 6.58E-05 0.OOE+00 1.04E-05 3.40E-03 4.64E-06 1.23E-04 1.30E-06 0.OOE+00 1.89E-02 6.74E-05 0.OOE+00

8. 12E-05 1.92E-02 0.OOE+00 0.OOE+00 0.OOE+00 9.45E-06 2.52E-03 6.52E-06 1.64E-05 0.OOE+00 2.5SE-03 19 -

Table 1-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Doses to a member of the public due to Liquid Releases Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Cumulative Doses Per Quarter Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body Total Body ODCM Lmt 5.OOE+00 5.OOE+0O 5.OOE+00 5.OOE+00 5.00E+00 5.OOE+00 5.OOE+00 1.50E+00 Units mRem mRem mRem mRem mRem mRem mRem mRem 1ST Qtr

/o ODCM 6.38E-03 1.28E-01 2.48E-02 4.96E-01 2.47E-02 4.94E-01 4.20E-03 8.40E-02 4.94E-03 9.87E-02 3.76E-03 7.52E-02 2.97E-03 5.95E-02 2.97E-03 1.98E-01 2ND Qtr 5.53E-03 2.24E-02 2.26E-02 3.57E-03 1.79E-03 3.20E-03 2.41E-03 2.41E-03 0/b ODCM 1.11E-01 4.49E-01 4.51E-01 7.15E-02 3.58E-02 6.40E-02 4.82E-02 1.61E-01 3RD Qtr 0/ ODCM 1.23E-02 2.37E-02 2.37E-02 3.28E-03 1.98E-03 2.71E-03 3.42E-03 3.42E-03 2.46E-01 4.74E-01 4.73E-01 6.57E-02 3.96E-02 5.42E-02 6.85E-02 2.28E-01 4TH Qtr 0/0 ODCM 1.00E-02 2.01E-01 3.52E-02 7.04E-01 3.41E-02 6.82E-01 3.90E-03 7.81E-02 3.94E-03 7.88E-02 2.96E-03 5.92E-02 1.85E-03 3.69E-02 1.85E-03 1.23E-01 Cumulative Doses per Year Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body Total Body ODCM Lint 1.OOE+01 1.00E+01 1.00E+01 1.OOE+01 1.00E+01 1.00E+01 1.00E+01 3.OOE+00 Units mRem mRem mRem mRem mRem mRem mRem mRem Year to Ending Date 3.42E-02 1.06E-01 1.05E-01 1.50E-02 1.26E-02 1.26E-02 1.07E-02 1.07E-02 0/0 ODCM 3.42E-01 1.06E+00 1.05E+00 1.50E-01 1.26E-01 1.26E-01 1.07E-01 3.55E-01 Receptor Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Limit Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual ULquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent TB Annual 20

Table 1-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Doses to a member of the public due to Liquid Releases Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Cumulative Doses Per Quarter Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body Total Body ODCM Lmnt 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.50E+00 Units mRem mRem mRem mRem mRem mRem mRem mRem 1ST Qtr

1. 13E-02 4.58E-02 4.60E-02 6.03E-03 3.15E-03 5.29E-03 3.56E-03 3.56E-03

% ODCM 2ND Qtr

% ODCM 2.26E-01 6.02E-03 1.20E-01 9.16E-01 2.40E-02 4.79E-01 9.21E-01 2.40E-02 4.81E-01 1.21E-01 3.24E-03 6.48E-02 6.30E-02 1.62E-03 3.25E-02 1.06E-01 2.82E-03 5.64E-02 7.12E-02 1.94E-03 3.87E-02 2.37E-01 1.94E-03 1.29E-01 3RD Qtr

%/o ODCM 4TH Qtr 0/o ODCM 1.53E-02 3.06E-01 1.25E-02 2.50E-01 3.41E-02 6.82E-01 4.88E-02 9.77E-01 3.41E-02 6.83E-01 4.86E-02 9.73E-01 3.85E-03 7.69E-02 5.13E-03 1.03E-01 1.26E-03 2.51E-02 4.22E-03 8.44E-02 3.26E-03 6.53E-02 4.21E-03 8.42E-02 3.56E-03 7.12E-02 2.37E-03 4.75E-02 3.56E-03 2.37E-01 2.37E-03 1.58E-01 Cumulative Doses per Year Organ ODCM Lint Bone 1.OOE+01 GI-Lli 1.OOE+01 Kidney 1.OOE+01 Liver 1.OOE+01 Lung 1.OOE+01 Thyroid 1.OOE+01 Total Body 1.OOE+01 Total Body 3.OOE+00 Units mRem mRem mRem mRem mRem mRem mRem mRem Year to Ending Date 4.51E-02 1.53E-01 1.53E-01 1.82E-02 1.02E-02 1.56E-02

1. 14E-02

%/o ODCM 4.51E-01 1.53E+00 1.53E+00 1.82E-01 1.02E-01 1.56E-01 1.14E-01 3.81E-01 Receptor Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Limit Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent TB Annual 21

TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 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 22 -

Table 1-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 100 100 104

2. Total time period for Batch releases (Minutes) 1.14E+04 1.12E+04 1.22E+04

3. Maximum time period for a batch release (Minutes) 1.60E+02 1.41E+02 1.95E+02

4. Average time period for a batch release (Minutes) 1.14E+02 1.12E+02 1.17E+02

5. Minimum time period for a batch release (Minutes) 9.50E+01 5.00E+01 9.00E+01

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

(CFS) 1.27E+04 9.14E+03 1.07E+04

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

74 7.94E+03 1.61E+02 1.07E+02 2.OOE+01 7.83E+03 378 4.27E+04 1.95E+02

1. 13E+02 2.00E+01 1.01E+04 23 -

Table 1-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals

1. Number of batch releases 136 129 127 88 480

2. Total time period for Batch releases

( Minutes )

1.39E+04 1.34E+04 1.28E+04 8.75E+03 4.89E+04

3. Maximum time period for a batch release

( Minutes )

1.75E+02 1.80E+02 1.35E+02 1.41E+02 1.80E+02

4. Average time period for a batch release

( Minutes )

1.02E+02 1.04E+02 1.01E+02 9.94E+01 1.02E+02

5. Minimum time period for a batch release

( Minutes )

8.70E+01 8.60E+01 8.90E+01 8.50E+01 8.50E+01

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

( CFS) 1.27E+04 9.14E+03 1.07E+04 7.83E+03 1.01E+04

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

24 -

iquid Releases

1. Number of Releases

2. Total Time For All Releases

3. Maximum Time For A Release

4. Average Time For A Release

5. Minimum Time For A Release

6. Total activity for all releases Table 1-6A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter 0

0 0

(Minutes)

O.OOE+00 0.OOE+00 O.OOE+00 (Minutes)

O.OOE+00 O.OOE+00 O.OOE+0O (Minutes)

O.OOE+O0 O.OOE+00 O.OOE+00 (Minutes)

O.OOE+00 O.OOE+00 O.OOE+00 (Curies )

O.OOE+00 O.OOE+00 O.OOE+00 4TH Quarter Year Totals 0

0 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 25 -

iquid Releases

1. Number of Releases

2. Total Time For All Releases

3. Maximum lime For A Release

4. Average Time For A Release

5. Minimum Time For A Release

6. Total activity for all releases Table 1-6B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 0

0 0

(Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 (Minutes) 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 (Minutes) 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 (Minutes) 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 (Curies )

0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 26 -

2.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2013.

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.

27 -

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 28 -

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:

29

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.

30 -

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

Doses to a Member of the Public (individual doses) due to radioiodine, tritium and particulates are calculated for the controlling receptor, which is described in the ODCM.

Individual doses are calculated for each release period, and cumulative totals are kept for each unit, for the current calendar quarter and year. Cumulative individual doses are compared to the dose limits specified in ODCM 3.1.4. The current percent of ODCM limits are shown on the printout for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate

filters, for each week for gross alpha activity in a proportional counter.

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

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

Fission and Activation Gases Iodine Particulates Tritium 75%

60%

50%

45%

The average error associated with counting is estimated to be:

Fission and Activation Gases Iodine Particulates Tritium 19%

28%

20%

8%

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2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, lB and IC are found in this report as Tables 2-1A, 2-1B, 2-IC, 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-iC 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.

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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 2013 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2013 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4B Unit 1 2013 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases:

Table 2-5A Unit 2 2013 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 2013 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2013 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 2013.

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

Unit 1 2013 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2013 Gaseous Effluents - Abnormal Release Summary: Table 2-8B 33 -

Table 2-1A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 8.54E-01 9.53E-01 1.07E+00 2.26E+00

2. Average Release rate for period uCi/sec 1.08E-01 1.21E-01 1.35E-01 2.87E-01

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 6.25E-07

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 7.93E-08

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days)

Curies O.OOE+00 3.07E-09 3.33E-08 6.42E-08

2. Average Release rate for period uCi/sec O.OOE+00 3.90E-10 4.22E-09 8.140E-09

3. Percent of Applicable Limit D. Tritium

1. Total Release Curies 1.52E+00 1.12E+00 1.14E+00 1.73E+00

2. Average Release rate for period uCi/sec 1.92E-01 1.43E-01 1.44E-01 2.20E-01

3. Percent of Applicable Limit E. Gross Aloha

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

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

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

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Table 2-1B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Gaseous Effluents - Summation Of All Releases Unit: 2 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 6.61E-01 6.03E-01 1.73E-01 3.97E-01

2. Average Release rate for period uCi/sec 8.38E-02 7.65E-02 2.19E-02 5.03E-02

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies O.OOE+00 7.51E-08 O.OOE+00 O.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 9.53E-09 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days)

Curies O.OOE+00 O.OOE+00 6.46E-09 O.OOE+00

2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 8.20E-10 O.OOOE+00

3. Percent of Applicable Limit D. Tritium

1. Total Release Curies 2.39E+00 4.94E+00 2.26E+01 3.12E+00

2. Average Release rate for period uCi/sec 3.04E-01 6.27E-01 2.87E+00 3.95E-01

3. Percent of Applicable Limit E. Gross Alpha

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

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

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

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Table 2-1C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2013 Ending: 31-Dec-2013 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.51E+00 1.56E+00 1.24E+00 2.66E+00

2. Average Release rate for period uCi/sec 1.92E-01 1.97E-01 1.57E-01 3.37E-01

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies O.OOE+00 7.51E-08 O.OOE+00 6.25E-07

2. Average Release rate for period uCi/sec O.OOE+00 9.53E-09 O.OOE+00 7.93E-08

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days)

Curies O.OOE+00 3.07E-09 3.97E-08 6.42E-08

2. Average Release rate for period uCi/sec O.OOE+00 3.90E-10 5.04E-09 8.140E-09

3. Percent of Applicable Limit D. Tritium

1. Total Release Curies 3.91E+00 6.07E+00 2.37E+01 4.85E+00

2. Average Release rate for period uCi/sec 4.96E-01 7.70E-01 3.01E+00 6.15E-01

3. Percent of Applicable Limit E. Gross Alpha

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

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

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

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Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2013 Gaseous Effluents - Mixed Mode Level Releases Unit: 1 Starting: 1-Jan-2013 Ending: 31-Dec-2013 Continuous Mode Nuclides Released Fission Gases Ar-41 Total For Period lodines 1-131 Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter O.OOE+00 0.00E+00 O.OOE+00 2.00E+00 0.00E+00 0.00E+00 O.OOE+O0 2.OOE+00 Particulates Co-60 Sr-90 Ru-103 O.OOE+O0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E+00 0.00E+00 0.00E+00 5.85E-07 O.00E+00 O.00E+00 5.85E-07 Total For Period O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+O0 1.03E+00 0.OOE+00 3.33E-08 0.OOE+00 3.33E-08 1.05E+00 5.58E-08 O.OOE+00 8.40E-09 6.42E-08 1.73E+00 Tritium H-3 Curies Gross Alpha No Nuclides Found Curies O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.