Text

Annual Radioactive Effluent Release Reports for 2007
	ML081290295
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	04/29/2008
From:	Godfrey J; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-08-0668
	Download: ML081290295 (283)
	v • d • e

i ý -

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN COMPANY April 29, 2008 Energy to Serve Your World" Docket Nos.: 50-321 50-348 50-424 NL-08-0668 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2007 Ladies and Gentlemen:

In accordance with section 5.6.3 of the referenced plants' Technical Specifications, Southern Nuclear Operating Company hereby submits the Annual Radioactive Effluent Release Reports for 2007. The Annual Radioactive Effluent Release Report for the Edwin I. Hatch Nuclear Plant (Hatch), Joseph M. Farley Nuclear Plant (Farley), and the Vogtle Electric Generating Plant (Vogtle) are provided in Enclosures 1, 2, and 3, respectively.

Technical Specification 5.5.1.c. for each plant requires that the Offsite Dose Calculation Manual (ODCM) be provided as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. During the reporting period for the Annual Radioactive Effluent Release Report for 2007, the Hatch and Vogtle ODCMs were revised. Accordingly, copies of the Hatch and Vogtle ODCMs are provided in Enclosures 4 and 5, respectively. Revision bars provided in the Vogtle ODCM represent changes associated with Revision 23, dated January 2007. Due to issuance of multiple revisions to the Hatch ODCM during the reporting period, revision bars provided in the Hatch ODCM are identified by the applicable revision and date of the change. A description of the changes for each ODCM, summarized by revision, is provided in Section 8.0 of the Annual Radioactive Effluent Release Report for the corresponding plant.

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U. S. Nuclear Regulatory Commission NL-08-0668 Page 2 This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely, J. M. Godfrey ' //

Manager, Environmental Affairs JMG/TWS/daj

Enclosures:

1. Hatch Annual Radioactive Effluent Release Report for 2007

2. Farley Annual Radioactive Effluent Release Report for 2007

3. Vogtle Annual Radioactive Effluent Release Report for 2007

4. Hatch Offsite Dose Calculation Manual - Version 21

5. Vogtle Offsite Dose Calculation Manual - Version 23 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CFA04.054; CHA02.004; CVC7000; LC# 14759 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Acting Regional Administrator Mr. R. A. Jervey, NRR Project Manager - Farley Mr. R. E. Martin, NRR Project Manager - Hatch Mr. R. A. Jervey, NRR Project Manager - Vogtle Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. J. A. Hickey, Senior Resident Inspector - Hatch Mr. G. J. McCoy, Senior Resident Inspector - Vogtle State of Alabama Mr. K. E. Whatley, Department of Public Health, Division of Radiation Control State of Georgia Mr. T. V. Jackson, Department of Natural Resources Georgia Power Company Mr. M. C. Nichols American Nuclear Insurers Mr. R. A. Oliveira

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2007 Enclosure 1 Hatch Annual Radioactive Effluent Release Report for 2007

SOUTHERN COMPANY E. L HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1, 2007 THROUGH DECEMBER 31,2007 SECTION TITLE PAGE 1.0 Liquid Effluents 1 1.1 Regulatory Requirements 1 1.1.1 Concentration Limits 1 1.1.2 Dose Limits 1 1.2 Effluent Concentration Limit 1 1.3 Measurements and Approximations of Total 2 Radioactivity for Liquid Radwaste 1.3.1 Total Radioactivity Determination for Liquid Radwaste 2 1.4 Measurements and Approximations of Total 4 Radioactivity for Groundwater Outfalls -

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

SECTION TITLE PAGE 1.10 Liquid Effluents - Abnormal Releases 7 2.0 Gaseous Effluents 29 2.1 Regulatory Requirements 29 2.1.1 Dose Rate Limits 29 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 29 2.1.3 Doses to a Member of the Public 29 2.2 Measurements and Approximations of Total 30 Radioactivity 2.2.1 Sample Collection and Analysis 30 2.2.2 Total Quantities of Radioactivity, Dose Rates 31 and Cumulative Doses 2.2.2.1 Fission and Activation Gases 31 2.2.2.2 Radioiodine, Tritium and Particulate Releases 31 2.2.2.3 Gross Alpha Release 32 2.2.3 Total Error Estimation 32 2.3 Gaseous Effluent Release Data 34 2.4 Radiological Impact Due to Gaseous Releases 35 2.5 Gaseous Effluents - Batch Releases 35 2.6 Gaseous Effluents - Abnormal Releases 35 3.0 Solid Waste 67 3.1 Regulatory Requirements 67 3.1.1 Solid Radioactive Waste System 67 3.1.2 Reporting Requirements 67 ii

SECTION TITLE PAGE 3.2 Solid Waste Data 68 4.0 Doses to Members of the. Public Inside The 72 Site Boundary 4.1 Regulatory Requirements 72 4.2 Demonstration of Compliance 72 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 81 5.1 Regulatory Requirements 81 5.2 Demostration of Compliance' 81 6.0 Meteorological Data 81 7.0 .Program Deviations 81 7.1 Inoperable Liquid or Gaseous Effluent 81 Monitoring Instrumentation 7.1.1 Regulatory Requirements 81 7.1.2 Description of Deviations 82 7.2 Tanks Exceeding Curie Content Limits 82 7.2.1 Regulatory Requirements 82 7.2.2 Description of Deviations 82 7.3 Effluent Sample Analysis Exceeding Minimum 82 Detectable Concentration (MDC) 7.3.1 Regulatory Requirement 82 7.3.2 Description of Deviation 82 iii

SECTION TITLE PAGE 8.0 Changes to the Plant Hatch .82 Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements 82 8.2 Description of Changes 83 9.0 Major Changes to the Liquid, Gaseous or 83 Solid Radwaste Treatment Systems 9.1 Regulatory Requirements 83 9.2 Description of Major Changes 84 Appendix A 85 iv

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases 8 Unit 1 (Quarters 1, 2, 3 and 4) 1-1B Liquid Effluents - Summation of All Releases 10 Unit 2 (Quarters 1, 2, 3 and 4) 1-ic Liquid Effluents - Summation of All Releases 12 Site (Quarters 1, 2, 3 and 4) 1-ALiquid Effluents - Unit 1 (Quarters 1, 2, 3 and 4) 14 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3 and 4) 16 1-2C Liquid Effluents - Site (Quarters 1, 2, 3 and 4) 18 1-3A Doses to a Member of The Public Due to Liquid 20 Releases Unit 1 (Quarters 1, 2, 3 and 4) 1-3B Doses to a Member of The Public Due to Liquid 22 Releases Unit 2 (Quarters 1, 2, 3 and 4),

1-4 Minimum Detectable Concentration - 24 Liquid Sample Analysis 1-5A Liquid Effluents - Batch Release Summary 25 Unit 1 1-5B Liquid Effluents - Batch Release Summary 26 Unit 2 V

TABLE LIST OF TABLES PAGE 1-6A Liquid Effluents - Abnormal Release 27 Summary Unit 1 1-6B Liquid Effluents - Abnormal Release 28 Summary Unit 2 2-1A Gaseous Effluents - Summation of All 36 Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-1 B Gaseous Effluents - Summation of All 38 Releases -Unit 2 (Quarters 1, 2, 3 and 4) 2-1C Gaseous Effluents - Summation of All 40 Releases - Site (Quarters 1, 2, 3 and 4) 2-2A Gaseous Effluents - Elevated Releases 42 Unit 1 (Quarters 1, 2, 3 and 4) 2-2B Gaseous Effluents - Elevated Releases 44 Unit 2 (Quarters 1, 2, 3 and 4) 2-2C Gaseous Effluents - Elevated Releases 46 Site (Quarters 1, 2, 3 and 4) 2-3A Gaseous Effluents - Ground Level Releases 48 Unit 1 (Quarters 1, 2, 3 and 4) 2-3B Gaseous Effluents - Ground Level Releases 50 Unit 2 (Quarters 1, 2, 3 and 4) 2-3C Gaseous Effluents - Ground Level Releases 52 Site (Quarters 1, 2, 3 and 4) 2-4A. Air Doses Due to Noble Gases in Gaseous 54 Releases - Unit 1 (Quarters 1, 2, 3 and 4) vi

TABLE LIST OF TABLES PAGE 2-4B Air Doses Due to Noble Gases in Gaseous 56 Releases- Unit 2 (Quarters 1, 2, 3 and 4) 2-5A Doses to a Member of the Public Due to 58 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 1 (Quarters 1, 2, 3 and 4) 2-5B Doses to a Member of the Public Due to 60 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-6 Minimum Detectable Concentration - 62 Gaseous Sample Analyses 2-7A Gaseous Effluents - Batch Release 63 Summary Unit 1 2-7B Gaseous Effluents - Batch Release 64 Summary Unit 2 2-8A Gaseous Effluents - Abnormal Release 65 Summary Unit 1 2-8B Gaseous Effluents - Abnormal Release 66 Summary Unit 2 3-1 Solid Waste and Irradiated Fuel Shipments 69 4-1 Doses to a Member of the Public Due to 73 Activities Inside The Site Boundary vii

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

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

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

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

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

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

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

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

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

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

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

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

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

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

1.3.1 Total Radioactivity Determinationfor Liquid Radwaste MEASUREMENT FREQUENCY METHOD

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

2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gas with computerized data reduction.

3. Tritium Monthly Distillation and liquid Composite scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting 2

Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 keV or lower. The detectors are shielded by four inches of lead. A liquid radwaste sample is typically counted for 2000 seconds and a peak search of the resulting gamma ray spectrum is performed. Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-1 37, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present. Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

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

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

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

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

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1.4 Measurements and Approximations of Total Radioactivity for Groundwater Outfalls - Y22NO03A/12B and Y22NO08A Samples are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-,3. Weekly, monthly and quarterly composites are prepared for analysis by extracting aliquots from each outfall's automatic sampler, which collects a composite sample over a seven-day period. Sample analyses are performed as described in Section 1.4.1.

1.4.1 Total Radioactivity Determination for GroundwaterOutfalls MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Monthly Composite Gamma Spectroscopy with computerized data reduction.

2. Tritium Weekly Composite Distillation and liquid scintillation counting

3. Gross Beta* Quarterly. Chemical separation Composite and gas flow proportional or scintillation counting

4. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

Gross Beta analysis is used for sample screening.

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

Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

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

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

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

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

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

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

The evaluation for the release of radioactive RHR Service Water for 2007 can be found in Appendix A of this report.

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

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

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

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

4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly composite samples are Used to calculate the total release of alpha radioactivity.

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

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

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

Unit 1 Liquid Continuous Releases: Table 1-2A Unit 2 Liquid Continuous Releases: Table 1-2B Hatch Site Conitinuous Releases: Table 1-2C 1.10 Liquid Effluents - Abnormal Releases Over the period of 12/21/07 to 12/27/07, approximately 5700 gallons of groundwater with an average tritium concentration of 2.49E4 pCi/L leaked from disjointed connections of newly-installed discharge piping. The piping was installed to permanently route the subsurface groundwater from 1Y22-NO08A to the permitted radiological effluent release point. The leakage was maintained onsite and totaled approximately 5.37E-4 Curies. The potential ingested total body dose from this event was approximately 5.35E-4 mRem. The piping issues were addressed and no additional leakage resulted from the design change.

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TABLE 1-lA E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

-. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 3.42E-03 4.40E-04 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.92E-09 4.08E-09

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 8.41E+00 2.18E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.95E-05 2.02E-05

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 0.00E+00 0.OOE+00 I.OOE+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.31E-07 6.73E-07 1.20E+02 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.37E+07 1.18E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 4.32E+08 1.08E+08 1.60E+02 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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TABLE 1-lA E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 6.57E-04 1.05E-03 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.63E-09 5.11E-09

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 3.44E+00 9.46E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.90E-05 4.59E-05

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 1.OOE+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 9.25E-07 3.72E-07 1.20E+02 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.06E+07 9.80E+06 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 1.81E+08 2.06E+08 1.60E+02 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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TABLE 1-lB E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR-%

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 3.14E-04 1.18E-04 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.58E-II 2.85E-11

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 3.51E+00 2.73E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML. 9.60E-07 6.59E-07

3. PERCENT OF APPLICABLE LIMIT %*

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.28E-06 1.43E-06 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.49E-13 3.45E-13

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 3.34E-07 1.20E+02 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 3.84E+06 2.43E+06 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 3.66E+09 4.14E+09- 1.60E+02 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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TABLE 1-lB E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 2 Starting l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.72E-04 8.02E-04 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.78E-11 1.09E-15

3. PERCENT OF APPLICABLE LIMIT

B. TRITIUM

1. TOTAL RELEASE CURIES 1.18E+01 3.95E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.20E-06 5.39E-12

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 9.47E-06 0.OOE+00 1.OOE+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.76E-12 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 1.35E-06 5.88E-08 1.20E+02 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 5.36E+06 2.85E+06 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 5.38E+09 7.33E+09 1.60E+02 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

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TABLE l-lC E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit:.Site Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 3.73E-03 5.58E-04 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.13E-10 1.31E-10

3. PERCENT OF APPLICABLE LIMIT *6 B. TRITIUM

1. TOTAL RELEASE CURIES 1.19E+01 4.91E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.92E-06 1.16E-06

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.28E-06 1.43E-06 1.OOE+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.12E-13 3.36E-13

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.31E-07 1.01E-06 1.20E+02 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.75E+07 1.43E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 4.09E+09 4.25E+09 1.60E+02 Applicable limits are expressed in terms Of dose. See Tables 1-3A and 1-3B of this report.

12

TABLE 1-IC E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: Site Starting : 1-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.13E-03 1.87E-03 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.04E-10 2.55E-15

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 1.53E+01 1.34E+01 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.75E-06 1.83E-11

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 9.47E-06 0.OOE+00 1.OOE+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.71E-12 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.28E-06 4.31E-07 1.20E+02 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.60E+07 1.26E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 5.56E+09 7.54E+09 1.60E+02 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

13

TABLE l-2A*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 I CURIES 1.03E-01 1.50E-02 8.30E+00 2.17E+00 FISSION & ACTIVATION PRODUCTS CO-58 CURIES 0.OOE+00 0.OOE+00 2.16E-06 0.OOE+00 CO-60 CURIES 0.OOE+00 0.OOE+00 8.80E-04 1.99E-04 CR-51 CURIES 0.00E+00 0.00E+00 7.77E-06 0.00E+00 CS-137 CURIES- O.00E+00 O.00E+00 3.17E-04 1.57E-04 FE-55 CURIES 0.00E+00 0.00E+00 1.94E-03 2.36E-05 MN-54 CURIES 0.00E+00 0.00E+00 1.44E-04 3.09E-05 NA-24 CURIES 0.00E+00 0.OOE+00 3.21E-05 1.59E-05 ZN-65 CURIES 0.00E+00 O.OOE+00 9.10E-05 1.36E-05 ZN-69M CURIES 0.00E+00 O.OOE+00 0.00E+00 1.30E-06 TOTALS CURIES O.OOE+00 O.OOE+00 3.42E-03 j 4.41E-04 DISSOLVED AND ENTRAINED GASES CURIES j O.OOE+00 0.00E+00 0.00+E00 I 0.00+E00 G-ALPHA CURIES I 0.00E+00 I O.OOE+00 2.51E-07 I 6.73E-07 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

14

TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT 1QUARTER 3 1QUARTER 4 1QUARTER 3 1QUARTER 4 1 H-3 I CURIES I 1.lIE-01 4.98E-02 3.33E+00 9.41E+00 FISSION & ACTIVATION PRODUCTS CE-141 CURIES 0 0.OOE+00 O.OOE+00 3.36E-06 0.OOE+00 CO-58 CURIES 0.OOE+00 0.OE+00 8.53E-07 0.OOE+00 CO-60 CURIES 0.OE+00 0.OE+00 2.12E-04 5.25E-04 CS-137 CURIES 0.OOE+00 0.OE+00 i .08E-04 2.46E-04 FE-55 CURIES 0.OOE+00 0.OE+00 2.74E-04 9.38E-05 MN-54 CURIES 0.OOE+00 0.OOE+00 3.01E-05 7.74E-05 NA-24 CURIES 0.OOE+00 0.OE+00 3.84E-06 2.11E-05 SR-89 CURIES 0.OE+00 0.OE+00 2.OOE-06 4.25E-05 SR-90 CURIES 0.00E+00 0.OE+00 .OOE+00 0.OOE+00 ZN-65 CURIES 0.OOE+00 0.OE+00 2.36E-05 4.42E-05 ZN-69M CURIES 0.OOE+00 00.0E+00 0.OOE+00 3.64E-06 TOTALS CURIES 0.OOE+00 0.OOE+00 I 6.57E-04 I 1.05E-03 I DISSOLVED AND ENTRAINED GASES I CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 G-ALPHA I CURIES 0.OOE+00 0.OOE+00 I 9.25E-07 I 3.72E-07 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

15

TABLE 1-2B*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDE UNIT 1QUARTER 1 1QUARTER 2 1QUARTER 1 QUARTER 2 1 H-3. CURIES .15.39E-02 I 3.31E-02 I 3.46E+00 I 2.70E+00 I FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0.OOE+00 I 0.OOE+00 I 3.26E-06.1 0.OOE+00 I AU-199 'CURIES 0.O0E+00 0.OOE+00 9.01E-06 0.OOE+00 CO-58 CURIES 0.OE+00 0.OE+00 2.22E-06 0.OOE+00 CO-60 CURIES .0.00E+00 0.OOE+00 8.85E-05 2.95E-05 CS-137 CURIES I 0.OOE+00 I 0.00E+00 I654E-06 2.27E-06 FE-55 CURIES 0.OE+00 0.OE+00 6 .20E-05 3.71E-05 FE-59 CURIES 0.OOE+00 0.OOE+00 1 .12E-05 0.OOE+00 MN-54 CURIES 0.OOE+00 0.OOE+00 8.14E-05 5.26E-06 NA-24 CURIES 0 .OOE+00 0.0E+00

0. I 0.OOE+00 I 3.68E-05 SR-89 CURIES 0.OE+00 9.35E-12 0.0E+00 0.OOE+00 TC-99M CURIES O.OOE+00 O.OOE+00 O.OOE+00 1.45E-06 ZN-65 CURIES O.OOE+00 O.OOE+00 4.21E-05 5.53E-06 ZN-69M CURIES O.OOE+00 O.OOE+00 7".31E-06 O.OOE+00 TOTALS I CURIES I O.OOE+00 I 9.35E-12 3.14E-04 1.18E-04 I DISSOLVED AND ENTRAINED GASES XE-133 CURIES O.OOE+00 O.OOE+00 O.OOE+00 1.43E-06 XE-135 CURIES O.OOE+00 O.OOE+00 1.28E-06 0.00E+00 TOTALS- CURIES O.OOE+00 O.OOE+00 1.28E-06 1.43E-06 G-ALPHA I CURIES O.OOE+oo O.OOE+00 I O.OOE+00 I 3.34E-07 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

16

TABLE 1-2B*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 CONTINUOUS MODE BATCH MODE NUCLIDE I UNIT QUARTER 3 IQUARTER 4 QUARTER 3 1QUARTER 4 H-3 I CURIES 5.27E-02 I 4.55E-02 I 1.17E+01 3.90E+00 FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0.OOE+00 0.OOE+00 1.40E-05 2.38E-05 AU-199 CURIES 0.OOE+00 0.OOE+00 1.36E-06 0.OOE+00 CE-141 CURIES 0.OE+00 0.OOE+00 1.89E-05 4.18E-06 CO-58 CURIES 0.OOE+00 0.OE+00 1.76E-06 0.OE+00 CO-60 CURIES 0.OOE+00 0.OE+00 1.16E-04 4.92E-05 CS-137 CURIES 0.OOE+00 0.OE+00 9.05E-06 2.24E-05 FE-55 CURIES 0.OE+00 0.OE+00 4.41E-05 3.30E-12 MN-54 CURIES 0.OE+00 0.OE+00 1.42E-04 1 .85E-04 NA-24 CURIES 0.OOE+00 0.OOE+00 6.18E-05 3.63E-04 NB-97 CURIES 0.OE+00 0.OOE+00 2.03E-06 0.OOE+00 SB-122 CURIES 0.OOE+00 0.OOE+00 2.31E-06 6.25E-07 SR-89 CURIES 0.OE+00 0.OE+00 1.28E-06 1 19E-04 TC-99M CURIES 0.OE+00 0.OOE+00 2.74E-05 3.26E-06 ZN-65 CURIES 0.OE+00 0.OOE+00 1.19E-05 1.33E-05 ZN-69M CURIES 0.OOE+00 0.OE+00 1.84E-05 1 .77E-05 TOTALS I CURIES I 0.OOE+00 I 0.OOE+00 I 4.72E-04 I 8.02E-04 DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 0.OOE+00 I 2.43E-06 I 0.00E+00 XE-135 CURIES 0.OOE+00 0.00E+00 I 7.04E-06 I 0.OOE+00 TOTALS CURIES 0.OOE+00 0.OOE+00 I 9.47E-06 I 0.OOE+00 G-ALPHA CURIES 0.OOE+00 I 0.OOE+00 I 1.35E-06 I 5.88E-08 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*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDE UNIT QUARTER 1 1QUARTER 2 IQUARTER 1 IQUARTER 2 H-3 I CURIES 1.57E-01 I 4.81E-02 1.18E+01 I 4.87E+0'0 FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0.OOE+00 0.OOE+00 3.26E-06 0.OOE+00 AU-199 CURIES 0.OOE+00 0.OOE+00 9.01E-06 0.OOE+00 CO-58 CURIES 0.OE+00 0.OOE+00 4.38E-06 0.OOE+00 CO-60 CURIES 0.OE+00 0.OE+00 9.68E-04 2.28E-04 CR-51 CURIES 0.OE+00 0.OE+00 7.77E-06 0.OOE+00 CS-137 CURIES 0.OE+00 0.OE+00 3.24E-04 1.59E-04 FE-55 CURIES 0.OOE+00 0.OE+00 2.01E-03 6.07E-05 FE-59 CURIES 0.OOE+00 0.OOE+00 1 12E-05 0.OOE+00 MN-54 CURIES 0.OOE+00 0.OE+00 2.26E-04 3.62E-05 NA-24 CURIES 0.OE+00 0.OE+00 3.21E-05 5.27E-05 SR-89 CURIES 0.OOE+00 9.35E-12 0.OOE+00 0.OOE+00 TC-99M CURIES 0.OOE+00 0.OE+00 0.OE+00 1.45E-06 ZN-65 CURIES 0.OOE+00 0.OOE+00 1.33E-04 1.91E-05 ZN-69M CURIES 0.OE+00 0.OE+00 7.31E-06 1 30E-06 TOTALS CURIES I 0.OOE+00 I 9.35E-12 I 3.73E-03 I 5.59E-04 DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.43E-06 XE-135 CURIES 0.OOE+00 0.OOE+00 1.28E-06 0.OOE+00 TOTALS CURIES 0.OOE+00 0.OOE+00 1.28E-06 1.43E-06 G-ALPHA CURIES 0.OOE+00 I 0.OOE+00 I 2.51E-07 I 1.01E-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*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT 1QUARTER 3 1QUARTER 4 1QUARTER 3 1QUARTER 4 1 H-3 I CURIES 1.83E-01 I 1.01E-01 I 1.51E+01 I 1.33E+01 I FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0 OOE+00 0 OOE+00 1.40E-05 2.38E-05 AU-199 CURIES 0 OOE+00 0 OOE+00 1. 36E-06 0 OOE+00 CE-141 CURIES 0 OOE+00 0 OOE+00 2. 23E-05 4. 18E-06 CO-58 CURIES 0 OOE+00 0 OOE+00 2 61E-06 0 OOE+00 CO-60 CURIES 0 OOE+00 0 OOE+00 3 .28E-04 5. 74E-04 CS-137 CURIES 0 OOE+00 0 OOE+00 1. 17E-04 2. 68E-04 FE-55 CURIES 0. OOE+00 0 OOE+00 3. 18E-04 9. 38E-05 MN-54 CURIES 0. OOE+00 0 OOE+00 1. 72E-04 2. 63E-04 NA-24 CURIES 0 OOE+00 0 OOE+00 6. 56E-05 3. 84E-04 NB-97 CURIES 0 OOE+00 0 OOE+00 2 . 03E-06 0 OOE+00 SB-122 CURIES 0 OOE+00 0 OOE+00 2 31E-06 6.25E-07 SR-89 CURIES 0 OOE+00 0 OOE+00 3 .28E-06 1.62E-04 SR-90 CURIES 0 OOE+00 0 OOE+00 0 OOE+00 0. OOE+00 TC-99M CURIES 0 OOE+00 0 OOE+00 2. 74E-05 3.26E-06 ZN-65 CURIES 0 OOE+00 0 OOE+00 3. 55E-05 5.75E-05 ZN-69M CURIES 0 OOE+00 0 OOE+00 1. 84E-05 2. 14E-05 TOTALS I CURIES I 0.OOE+00 I 0.OOE+00 I 1.13E.-03 1.86E-03 I DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 0.OOE+00 2.43E-06 0.OOE+00 I XE-135 I CURIES 0.OOE+00 I 0.OOE+00 I 7.04E-06 I 0.OOE+00 I TOTALS I CURIES 0.OOE+00 0.OOE+00 9.47E-06 I 0.OOE+00 I G-ALPHA I CURIES 0.OOE+00 I 0.OOE+00 2.28E-06 I 4.31E-07 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

19

-TABLE 1-3A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -- 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ Tech Units Quarter % of, Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 1.12E-03 2.24E-02 5.94E-04 1.19E-02 Liver 5.0 mrem 1.96E-03 3.92E-02 1.18E-03 2.36E-02 TBody 1.5 mrem 1.44E-03 9.61E-02 9.05E-04 6.04E-02 Thyroid 5.0 mrem 3.82E-04 7.63E-03 3.59E-04 7.17E-03 Kidney 5.0 mrem 9.18E-04 1.84E-02 6.37E-04 1.27E-02 Lung 5.0 mrem 5.54E-04 1lIE-02 4.50E-04 9.OOE-03 GILLI 5.0 mrem 8.86E-04 1.77E-02 4.91E-04 9.83E-03 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mrem 1.71E-03 1.71E-02 Liver 10.0 mrem 3.14E-03 3.14E-02 TBody 3.0 mrem 2.35E-03 7.82E-02 Thyroid 10.0 mrem 7.40E-04 7.40E-03.

Kidney i0'0 mrem 1.56E-03 1.56E-02 Lung 10.0 mrem 1.00E-03 1.OOE-02 GILLI 10.0 mrem 1.38E-03 1.38E-02 20

TABLE 1-3A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO.A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ Tech Units Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem .3.71E-04 7.42E-03 1.47E-02 2.93E-01 Liver 5.0 mrem 7.46E-04 1.49E-02 1.53E-03 3.06E-02 TBody 1.5 mrem 5.74E-04 3.83E-02 4.49E-03 2.99E-01 Thyroid 5.0 mrem 2.29E-04 4.57E-03 2.67E-04 5.34E-03 Kidney 5.0 mrem 4.05E-04 8.09E-03 6.95E-04 1.39E-02 Lung 5.0 mrem 2.86E-04 5.71E-03 4.06E-04 8.11E-03 GILLI 5.0 mrem 3.54E-04 7.07E-03 9.95E-04 1.99E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mrem 1.67E-02 1.67E-01 Liver 10.0 mrem 7.27E-03 7.27E-02 TBody 3.0 mrem 9.26E-03 3.09E-01 Thyroid 10.0 mrem 3.09E-03 3.09E-02 Kidney 10.0 mrem 4.51E-03 4.51E-02 Lung 10.0 mrem 3.55E-03 3.55E-02 GILLI 10.0 mrem 4.58E-03 4.58E-02 21

TABLE 1-3B E. I. HATCH NUCLEAR.PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ Tech Units Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 2.55E-05 5.10E-04 1.OOE-05 2.OOE-04 Liver 5.0 mrem 4.89E-04 9.78E-03 3.76E-05 7.51E-04 TBody 1.5 mrem 4.72E-04 3.14E-02 3.30E-05 2..20E-03 Thyroid 5.0 mrem 4.40E-04 8.80E-03 2.i8E-05 4.37E-04 Kidney 5.0 mrem 4.61E-04 9.21E-03 2.75E-05 5.50E-04 Lung 5.0 mrem 4.43E-04 8.86E-03 2.33E-05 4.66E-04 GILLI 5.0 mrem 5.09E-04 1.02E-02 4.09E-05 8.18E-04 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mrem 3.55E-05 3.55E-04 Liver 10.0 mrem 5.27E-04 5.27E-03 TBody 3.0 mrem 5.05E-04 1.68E-02 Thyroid 10.0 mrem 4.62E-04 4.62E-03 Kidney 10.0 mrem 4.88E-04 4.88E-03 Lung 10.0 mrem 4.66E-04 4.66E-03 GILLI 10.0 mrem 5.50E-04 5.50E-03 22

TABLE 1-3B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ Tech Units Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 4.19E-05 8.38E-04 1.03E-04 2.06E-03 Liver 5.0 mrem 1.57E-04 3.14E-03 1.67E-04 3.33E-03 TBody 1.5 mrem 1.38E-04 9.17E-03 1.20E-04 7.97E-03 Thyroid- 5.0 mrem 9.30E-05 1.86E-03 3.38E-05 6.76E-04 Kidney 5.0 mrem 1.15E-04 2.30E-03 7.99E-05 1.60E-03 Lung 5.0 mrem 9.88E-05 1.98E-03 4.73E-05 9.45E-04 GILLI 5.0 mrem 1.83E-04 3.65E-03 9.27E-05 1.85E-03 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mrem 1.80E-04 1.80E-03 Liver 10.0 mrem 1.01E-03 1.01E-02 TBody 3.0 mrem 9.23E-04 3.08E-02 Thyroid 10.0 mrem 7.50E-04 7.50E-03 Kidney 10.0 mrem 8.44E-04 8.44E-03 Lung 10.0 mrem 7.74E-04 7.74E-03 GILLI 10.0 mrem 9.87E-04 9.87E-03 23

Table 1-4 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES STARTING: 1-Jan-2007 ENDING: 31-Dec-2007 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 1.97E-08 uCi/ml Fe-59 3.94E-08 uCi/ml Co-58 1.59E-08 uCi/ml Co-60 1.72E-08 uCi/ml Zn-65 2.92E-08 uCi/ml Mo-99 1.20E-07 uCi/ml Cs-134 1.75E-08 uCi/ml Cs-137 1.62E-08 uCi/ml Ce-141 1.92E-08 uCi/ml Ce-144 8.83E-08 uCi/ml 1-131 1.43E-08 uCi/ml Xe-135 1.03E-08 uCi/ml Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml Sr-90 8.50E-09 uCi/ml H-3 6.OOE-07 uCi/ml 24

Table 1-5A E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT- 2007 LIQUID EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF RELEASES 71 TOTAL TIME FOR ALL RELEASES 9020.00 MINUTES MAXIMUM TIME FOR A RELEASE 201.00 MINUTES AVERAGE TIME FOR A RELEASE : 127.04 MINUTES MINIMUM TIME FOR A RELEASE : 85.00 MINUTES PRE-DILUTED VOLUME DISCHARGED 2.011 E+06 LITERS AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 5370 CFS Table 1-5A E. I. HA TCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF RELEASES 47 TOTAL TIME FOR ALL RELEASES : 6115.00 MINUTES MAXIMUM TIME FOR A RELEASE 181.00 MINUTES AVERAGE TIME FOR A RELEASE : 130.11 MINUTES MINIMUM TIME FOR A RELEASE : 85.00 MINUTES PRE-DILUTED VOLUME DISCHARGED 1.492E+06 LITERS AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 5370 CFS 25

Table 1-5B E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF RELEASES 49 TOTAL TIME FOR ALL RELEASES : 5131.00 MINUTES MAXIMUM TIME FOR A RELEASE 140.00 MINUTES AVERAGE TIME FOR A RELEASE : 104.71 MINUTES MINIMUM TIME FOR A RELEASE : 3.00 MINUTES PRE-DILUTED VOLUME DISCHARGED 1.408E+06 LITERS AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 5370 CFS Table 1-5B E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF RELEASES 110 TOTAL TIME FOR ALL RELEASES 11864.00 MINUTES MAXIMUM TIME FOR A RELEASE .141.00 MINUTES AVERAGE TIME FOR A RELEASE : 107.85 MINUTES MINIMUM TIME FOR A RELEASE : 81.00 MINUTES PRE-DILUTED VOLUME DISCHARGED 3.226E+06 LITERS AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 5370 CFS 26

Table 1-6A E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.OOE+00 CURIES There were no abnormal liquid releases for this reporting period.

Table 1-6A E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.00E+00 CURIES There were no abnormal liquid releases for this reporting period.

27

Table 1-6B E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME-FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.OOE+00 CURIES There were no abnormal liquid releases for this reporting period.

Table 1-6B E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 LIQUID EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES. O.00E+0(- CURIES There were no abnormal liquid releases for this reporting period.

28

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

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

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

b. For Iodine-1 31, Iodine-1 33, tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

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

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

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

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

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

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

29

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

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

1. Noble gas samples are collected by grab sampling monthly.

2. Tritium samples are collected by grab sampling monthly.

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

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

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

6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the samples are analyzed for Sr-89 and Sr-90.

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

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

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

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

30

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

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

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

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

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

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

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

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

31

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

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

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

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

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

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

32

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Non-steady release rates 20%

TOTAL ERROR 65%

1-131 releases were calculated from each weekly sample.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 64%

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

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

Water vapor in sample stream determination 20%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 50%

TOTAL ERROR 56%

33

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

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

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

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

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

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

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

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

34

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

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

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

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

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

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

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

35

TABLE 2-1A E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 6.50E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 2.77E-05 1.90E-05 6.40E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.56E-06 2.42E-06

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 2.73E-06 5.51E-06 6.30E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.51E-07 7.01E-07

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 6.62E+00 6.16E+00 5.60E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.52E-01 7.84E-01

3. PERCENT OF APPLICABLE LIMIT *

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

36

TABLE 2-1A E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.OOE+00 4.62E-02 6.50E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 5.81E-03

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 2.47E-05 9.51E-06 6.40E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.11E-06 1.20E-06

3. PERCENT OF APPLICABLE LIMIT %*

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 5.39E-06 5.43E-06 6.30E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.78E-07 6.83E-07

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 9.73E+00 1.26E+01 5.60E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.22E+00 1.58E+00

3. PERCENT OF APPLICABLE LIMIT *

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

37

TABLE 2-1B E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-JunL2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 6.50E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.00E+00

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 2.19E-05 1.90E-05 6.40E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.82E-06 2.42E-06

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 3.39E-06 7.09E-06 6.30E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.36E-07 9.02E-07

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.06E+0l 8.63E+00 5.60E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.37E+00 1.10E+00

3. PERCENT OF APPLICABLE LIMIT *

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

38

TABLE 2-1B E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.OOE+00 4.62E-02 6.50E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec O.OOE+00 5.81E-03

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 2.47E-05 9.51E-06 6.40E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.11E-06 1.20E-06

3. PERCENT OF APPLICABLE LIMIT %*

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 8.86E-06 5.46E-06 6.30E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sed 1.lIE-06 6.87E-07

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.08E+01 1.34E+01 5.60E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.36E+00 1.69E+00

3. PERCENT OF APPLICABLE LIMIT *

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

39

TABLE 2-lC E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 6.50E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 4.95E-05 3.81E-05 6.40E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.37E-06 4.84E-06

3. PERCENT OF APPLICABLE LIMIT C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 6.12E-06 1.26E-05 6.30E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.87E-07 1.60E-06

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.73E+01 1.48E+01 5.60E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.22E+00 1.88E+00

3. PERCENT OF APPLICABLE LIMIT %*

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

40

TABLE 2-IC E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.OOE+00 9.23E-02 6.50E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 1.16E-02

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 4.94E-05 1.90E-05 6.40E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.21E-06 2.39E-06

3. PERCENT OF APPLICABLE LIMIT

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 1.43E-05 1.09E-05 6.30E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.79E-06 1.37E-06

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 2.05E+01 2.60E+01 *5.60E+01

2. AVERAGE RELEASE RATE-FOR PERIOD uCi/Sec 2.58E+00 3.27E+00

3. PERCENT OF APPLICABLE LIMIT %*

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

41

TABLE 2-2A*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Elevated Level Releases Unit: 1 Starting : l-Jan-.2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE**

NUCLIDES RELEASED UNIT 1QUARTER 1 1QUARTER 2 1QUARTER 1 JQUARTER 2 IODINES 1-133 CURIES 9.18E-05 1.15E-04 O.OOE+00 0.OOE+00 1-131 CURIES 2.58E-05 1.90E-05 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.18E-04 1.34E-04 0.OOE+00 0.OOE+00 PARTICULATES SR-89 CURIES 2.52E-06 4.06E-06 I 0.OOE+00 0.OOE+00.

MN-54 CURIES 0.IOE-E+00j 2.32E-07 0.OOE+00 0.OOE+00 CO-60 CURIES O.OOE+00 3.08E-07 O.OOE+00 O.OOE+00 SR-90 CURIES 2.50E-08 4.45E-08 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD I CURIES 2.54E-06 4.65E-06 O.OOE+00 I O.OOE+00 H-3 I CURIES 1.18E+00 1.12E+00 O.OOE+00 I O.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

42

TABLE 2-2A*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Elevated Level Releases Unit: 1 Starting l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE j BATCH MODE**

NUCLIDES RELEASED I UNIT 1QUARTER 3 1QUARTER 4 1QUARTER 3 ]QUARTER 4 1 FISSION GASES XE-135 I CURIES I o.OOE+00 I 4.62E-02 I 0.OOE+00 I0.OOE+00 I TOTAL FOR PERIOD I CURIES I0.OOE+00 I 4.62E-02 I0.OOE+00 I0.OOE+00 I IODINES 1-133 j CURIES 8.85E-05 3.86E-05 0.OOE+00 0.OOE+00 1-131 j CURIES 2.47E-05 9.51E-06 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.13E-04 4.81E-05 0.OOE+00 0.OOE+00 PARTICULATES SR-89 CURIES 4.79E-06 3.29E-06 0.OOE+00 0.OOE+00 SR-90 CURIES- 5.36E-09 7.84E-08 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD CURIES 4.80E-06 j 3.36E-06 O.OOE+00 O.OOE+00 H-3 CURIES 1.61E+00 1.71E+00 O.OOE+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- - There are no batch mode radioactive gaseous release pathways at Plant Hatch.

43

TABLE 2-2B*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Elevated Level Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE BATCH MODE**

NUCLIDES RELEASED UNIT QUARTER 1 1QUARTER 2 QUARTER 1 1QUARTER 2 IODINES 1-133 CURIES 6.97E-0-5 1.15E-04 0.OOE+00 0.OOE+00 1-131 CURIES 2.19E-05 1.90E-05 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 9.16E-05 I 1.34E-04 0.OOE+00 0.OOE+00 PARTICULATES SR-89 CURIES 2.12E-06 4.06E-06 0.OOE+00 0.OOE+00 MN-54 CURIES 0.OOE+00 2.32E-07 0.OOE+00 0.OOE+00 CO-60 CURIES O.OOE+00 3.08E-07 0.00E+00 O.OOE+00 SR-90 CURIES 2.50E-08 j 4.45E-08 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 2.15E-06 I 4.65E-06 0.00E+00 0.OOE+00 H-3 CURIES 1.03E+00 I 1.12E+00 I 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

44

TABLE 2-2B*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Elevated Level Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE**

NUCLIDES RELEASED I UNIT IQUARTER 3 QUARTER 4 IQUARTER 3 1QUARTER 4 1 FISSION GASES XE-135 CURIES 0.OOE+00 4.62E-02 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 0.OOE+00 4.62E-02 0.OOE+00 0.OOE+00 IODINES 1-133 CURIES 8.85E-05 3.86E-05 0.OOE+00 0.OOE+00 1-131 CURIES 2.47E-05 9.51E-06 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.13E-04 4.81E-05 0.OOE+00 0.OOE+00 PARTICULATES SR-89 CURIES 4.79E-06 3.29E-06 0.OOE+00 0.OOE+00 SR-90 CURIES 5.36E-09 7.84E-08 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 4.80E-06 3.36E-06 0.OOE+00 0.OOE+00 H-3 j CURIES I 1.61E+00 1.71E+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

45

TABLE 2-2C*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Elevated Level Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE**

NUCLIDES RELEASED I UNIT [QUARTER 1 IQUARTER 2 QUARTER 1 [QUARTER 2 IODINES 1-133 CURIES 1.61E-04 2.31E-04 0.OOE+00 0.OOE+00 1-131 CURIES 4.77E-05 3.81E-05 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD [ CURIES 2.09E-04 I 2.69E-04 0.OOE+00 I 0.OOE+00 PARTICULATES SR-89 CURIES 4.64E-06 [ 8.12E-06 0.OOE+00 0.OOE+00 MN-54 CURIES 0.OOE+00 j 4.64E-07 0.OOE+00 0.OOE+00 CO-60 CURIES O.OOE+00 [ 6.15E-07 O.OOE+00 O.OOE+00 SR-90 CURIES 5.OOE-08 [ 8.90E-08 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD I CURIES I 4.69E-06 I 9.29E-06 'O.OOE+00 I O.OOE+O0.

H-3 . CURIES I 2.21E+00 I 2.24E+00 j O.OOE+00 O.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

46

TABLE 2-2C*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Elevated Level Releases Unit: Site Starting : i-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE**

NUCLIDES RELEASED UNIT 1QUARTER 3 1QUARTER 4 1QUARTER 3 IQUARTER 4 1 FISSION GASES XE-135 CURIES 0.OOE+00 9.23E-02 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD CURIES I 0.OOE+00 9.23E-02 0.OOE+00 I 0.OOE+00 IODINES 1-133 CURIES 1.77E-04 7.72E-05 0.OOE+00 0.OOE+00 1-131 CURIES 4.94E-0S 1.90E-05 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 2.26E-04 I 9.62E-05 I0OOE-00 j 0.OOE+00 PARTICULATES SR-89 CURIES 9.59E-06 6.57E-06 0.OOE+00 0.OOE+00 SR-90 CURIES 1.07E-08 l.57E-07 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 9.60E-06 6.73E-06 0.OOE+00 0.OOE+00 H-3 CURIES 3.21E+00 3.42E+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

47

TABLE 2-3A*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE**

NUCLIDES RELEASED UNIT 1QUARTER 1 QUARTER 2 IQUARTER 1 QUARTER 2 IODINES 1-131 CURIES 1.89E-06 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.89E-06 0.OOE+00 j 0.00E+00 0.OOE+00 PARTICULATES SR-89 I CURIES 1.87E-07 8.67E-07 j 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD I CURIES 1.87E-07 8.67E-07 j 0.OOE+00 I 0.OOE+00 H-3 I CURIES 5.44E+00 5.04E+00 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

48

TABLE 2-3A*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE**

NUCLIDES RELEASED UNIT QUARTER 3 QUARTER 4 QUARTER 3 1QUARTER 4 PARTICULATES SR-89 CURIES 5.89E-07 2.07E-06 0.OOE+00 0.00E+00 SR-90 CURIES 3.09E-09 0.00E+00 O.OOE+00 0.00E+00 TOTAL FOR PERIOD CURIES 5.92E-07 2.07E-06 0.OOE+00 0.00E+00 I H-3 CURIES 8.13E+00 1.08E+01 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

49

TABLE 2-3B*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE**

NUCLIDES RELEASED UNIT 1QUARTER 1 QUARTER 2 1QUARTER 1 QUARTER 2 PARTICULATES SR-89 CURIES 1.24E-06 2.44E-06 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD CURIES 1.24E-06 I 2.44E-06 0.OOE+00 0.OOE+00 H-3 I CURIES I 9.62E+00 I 7.51E+00 I 0.OOE+00 I 0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

50

TABLE 2-3B*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 2 Starting l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE j BATCH MODE**

NUCLIDES RELEASED I UNIT IQUARTER 3 IQUARTER 4 1QUARTER 3 1QUARTER 4 1 PARTICULATES SR-89 I CURIES 4.06E-06 I 2.09E-06 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD I CURIES I 4.06E-06 I 2.09E-06 I 0.OOE+00 I 0.OOE+00 I H-3 I CURIES 9.17E+00 I 1.17E+01 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

51

TABLE 2-3C*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jan-2007 Ending 30-Jun-2007 CONTINUOUS MODE BATCH MODE**

NUCLIDES RELEASED I UNIT QUARTER 1 QUARTER 2 IQUARTER 1 IQUARTER 2 IODINES 1-131 CURIES 1.89E-06 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD I CURIES 1.89E 0.OOE+00 0.OOE+00 0.OOE+00 PARTICULATES SR-89 CURIES 1.43E-06 3.31E-06 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD F CURIES 1.43E-06 3.31E-06 0.OOE+00 I 0.OOE+00 H-3 CURIES I 1.51E+01 1.26E+01 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

52

TABLE 2-3C*

E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE**

NUCLIDES RELEASED I UNIT 1QUARTER 3 QUARTER 4 1QUARTER 3 IQUARTER 4 1 PARTICULATES SR-89 CURIES 4.65E-06 4.16E-06 0.OOE+00 I 0.OOE+00 SR-90 CURIES 3.09E-09 0.OOE+00 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD I CURIES 4.65E-06 I 4.16E-06 0.OOE+00 I 0.00E+00 H-3 I CURIES I 1.73E+01 I 2.26E+01 I 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

53

TABLE 2-4A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 1 Tech 2 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Beta 10.0 mrad 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Cumulative Doses per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 0.OOE+00 0.OOE+00 Beta 20.0 mrad 0.OOE+00 0.OOE+00 54

TABLE 2-4A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 3 Tech 4 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 0.OOE+00 0.OOE+00 2.08E-07 4.16E-06 Beta 10.0 mrad 0.OOE+00 0.OOE+00 1.48E-07 1.48E-06 Cumulative Doses per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 2.08E-07 2.08E-06 Beta 20.0 mrad 1.48E-07 7.38E-07 55

TABLE 2-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 1 Tech 2 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Beta 10.0 mrad 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Cumulative Doses per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 0.OOE+00 0.00E+00 Beta 20.0 mrad 0.OOE+00 0.00E+00 56

TABLE 2-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 3 Tech 4 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 0.OOE+00 0.OOE+00 2.08E-07 4.16E-06 Beta 10.0 mrad 0.OOE+00 0.OOE+00 1.48E-07 1.48E-06 Cumulative Doses per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 2.08E-07 2.08E-06 Beta 20.0 mrad 1.48E-07 7.38E-07 57

TABLE 2-5A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 9.23E-06 1.23E-04 1.83E-05 2.44E-04 Liver 7.5 mrem 2.83E-03 3.78E-02 2.62E-03 3.50E-02 TBody 7.5 mrem 2.83E-03 3.78E-02 2.62E-03 3.50E-02 Thyroid 7.5 mrem 2.92E-03 3.89E-02 2.67E-03 3.55E-02 Kidney 7.5 mrem 2.83E-03 3.78E-02 2.62E-03 3.50E-02 Lung 7.5 mrem 2.83E-03 3.78E-02 2.62E-03 3.50E-02 GILLI 7.5 mrem 2.83E-03 3.78E-02 2.62E-03 3.50E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mrem 2.75E-05 1.83E-04 Liver 15.0 mrem 5.45E-03 3.64E-02 TBody 15.0 mrem 5.45E-03 3.64E-02 Thyroid 15.0 mrem 5.58E-03 3.72E-02 Kidney 15.0 mrem 5.45E-03 3.64E-02 Lung 15.0 mrem 5.45E-03 3.64E-02 GILLI 15.0 mrem 5.45E-03 3.64E-02 58

TABLE 2-5A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 4.87E-05 6.49E-04 2.82E-05 3.76E-04 Liver 7.5 mrem 4.22E-03 5.63E-02 5.63E-03 7.51E-02 TBody 7.5 mrem 4.23E-03 5.64E-02 5.63E-03 7.51E-02 Thyroid 7.5 mrem 4.28E-03 5.70E-02 5.65E-03 7.54E-02 Kidney 7.5 mrem 4.22E-03 5.63E-02 5.63E-03 7.51E-02 Lung 7.5 mrem 4.22E-03 5.63E-02 5.63E-03 7.51E-02 GILLI 7.5 mrem 4.22E-03 5.63E-02 5.63E-03 7.51E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mrem 1.04E-04 6.96E-04 Liver 15.0 mrem 1.53E-02 1.02E-01 TBody 15.0 mrem 1.53E-02 1.02E-01 Thyroid 15.0 mrem 1.55E 7 02 1.03E-01 Kidney 15.0 mrem 1.53E-02 1.02E-01 Lung 15.0 mrem. 1.53E-02 1.02E-01 GILLI 15.0 mrem 1.53E-02 1.02E-01 59

TABLE 2-5B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A. MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2

,Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 1.62E-05 2.15E-04 3.42E-05 4.56E-04 Liver 7.5 mrem 4.98E-03 6.65E-02 3.90E-03 5.20E-02 TBody 7.5 mrem 4.99E-03 6.65E-02 3.90E-03 5.20E-02 Thyroid 7.5 mrem 5.03E-03 6.71E-02 3.94E-03 5.26E-02 Kidney 7.5 mrem 4.98E-03 6.65E-02 3.90E-03 5.20E-02 Lung 7.5 mrem 4.98E-03 6.65E-02 3.90E-03 5.20E-02 GILLI 7.5 mrem 4.99E-03 6.65E-02 3.90E-03 5.20E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mrem 5.03E-05 3.36E-04 Liver 15.0 mrem 8.88E-03 5.92E-02 TBody 15.0 mrem 8.89E-03 5.92E-02 Thyroid 15.0 mrem 8.98E-03 5.98E-02 Kidney 15.0 mrem 8.88E-03 5.92E-02 Lung 15.0 mrem 8.88E-03 5.92E-02 GILLI 15.0 mrem 8.89E-03 5.92E-02 60

TABLE 2-5B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 4.92E-05 6.56E-04 3.07E-05 4.10E-04 Liver 7.5 mrem 4.76E-03 6.35E-02 6.07E-03 8.10E-02 TBody 7.5 mrem 4.77E-03 6.35E-02 6.08E-03 8.10E-02 Thyroid 7.5 mrem 4.82E-03 6.43E-02 6.09E-03 8.13E-02 Kidney 7.5 mrem 4.76E-03 6.35E-02 6.07E-03 8.10E-02 Lung 7.5 mrem 4.76E-03 6.35E-02 6.07E-03 8.10E-02 GILLI 7.5 mrem 4.77E-03 6.35E-02 6.07E-03 8.10E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mrem 1.30E-04 8.68E-04 Liver 15.0 mrem 1.97E-02 1.31E-01 TBody 15.0 mrem 1.97E-02 1.32E-01 Thyroid 15.0 mrem 1.99E-02 1.33E-01 Kidney 15.0 mrem 1.97E-02 1.31E-01 Lung 15.0 mrem 1.97E-02 1.31E-01 GILLI 15.0 mrem 1.97E-02 1.32E-01 61

TABLE 2-6 E. L HA TCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANAL YSES STARTING: 1-Jan-2007 ENDING: 31-Dec-2007 The values in this table representa priori Minimum Detectable Concentration (MDC) that are typically achieved in laboratoryanalyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 2.94E-08 uCi/cc Kr-88 3.22E-08 uCi/cc Xe-133 2.30E-08 uCi/cc Xe-133m 7.30E-08 uCi/cc Xe-135 8.73E-09 uCi/cc Xe-138 1.99E-07 uCi/cc 1-131 1.34E-13* uCi/cc 1-133 1.53E-13* uCi/cc Mn-54 1.62E-13* uCi/cc Fe-59 3.42E-13* uCi/cc Co-58 1.30E-13* uCi/cc Co-60 1.54E-13* uCi/cc Zn-65 2,54E-13* uCi/cc Mo-99 9.61 E-13* uCi/cc Cs-134 1.42E-13* uCi/cc Cs-137 1.28E- 13* uCi/cc Ce-141 1.26E- 13* uCi/cc Ce-144 5.64E- 13* uCi/cc Sr-89 1.10E-16 uCi/cc Sr-90 6.70E-16 uCi/cc H-3 4.OOE-07 uCi/cc

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

62

Table 2-7A E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF BATCH RELEASES 0 TOTAL TIME PERIOD FOR BATCH RELEASES

0 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 0 MINUTES AVERAGE TIME FOR BATCH RELEASES 0 MINUTES MINIMUM TIME FOR A BATCH RELEASE 0 MINUTES There were no batch gaseous releases for this reporting period.

Table 2-7A E. I. HA TCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF BATCH RELEASES 0 TOTAL TIME PERIOD FOR BATCH RELEASES : 0 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 0 MINUTES AVERAGE TIME FOR BATCH RELEASES : 0 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 0 MINUTES There were no batch gaseous releases for this reporting period.

63

Table 2-7B E. I. HATCH NUCLEAR PLANT.

RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF BATCH RELEASES 0 TOTAL TIME PERIOD FOR BATCH RELEASES : 0 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 0 MINUTES AVERAGE TIME FOR BATCH RELEASES : 0 MINUTES MINIMUM TIME FOR A BATCH RELEASE 0 MINUTES There were no batch gaseous releases for this reporting period.

Table 2-7B E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - BATCH RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF BATCH RELEASES : 0 TOTAL TIME PERIOD FOR BATCH RELEASES 0 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 0 MINUTES AVERAGE TIME FOR BATCH RELEASES 0 MINUTES MINIMUM TIME FOR A BATCH RELEASE 0 MINUTES There were no batch gaseous releases for this reporting period.

64

Table 2-8A E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE. 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.00E+00 CURIES There were no abnormal gaseous releases for this reporting period.

Table 2-8A E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 1 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.00E+00 CURIES There were no abnormal gaseous releases for this reporting period.

65

Table 2-8B E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.00E+00 CURIES There were no abnormal gaseous releases for this reporting period.

Table 2-8B E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 GASEOUS EFFLUENTS - ABNORMAL RELEASE

SUMMARY

UNIT 2 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0 MINUTES MAXIMUM TIME FOR A RELEASE 0 MINUTES AVERAGE TIME FOR A RELEASE 0 MINUTES MINIMUM TIME FOR A RELEASE 0 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.00E+00 CURIES There were no abnormal gaseous releases for this reporting period.

66

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

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

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

3.1.2 Reporting Requirements Technical Specification 5.6.3 requires in part:

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

PCP Section A.4.1 states in part:

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

67

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

a. Container volume.

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

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

d. Type of waste (such as spent resin, compacted dry waste, evaporator bottoms).

e. Type of container (such as LSA, type A, type B, large quantity).

f. Solidification agent (such as cement).

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

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

68

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 A. SOLID WASTE SHIPPED OFESITE FOR BURIAL OR DISPOSAL (Not irradiated fuel'~

1. Type of waste UNIT 6 month Est. Total period ERROR %

a. Spent resins, filter sludges, evaporator m3 1.340E+01 bottoms, etc. Ci 1.320E+02 1.00 E 01

b. Dry compressible waste, contaminated equip. m3 9.600E+01 etc. Ci 2.720E-01 2.00 E 01

c. Irradiated components, control rods, m3 Ci

d. Control Rod Drive Filters m3 Ci

e. Other (describe) m3 Equip. etc. Ci

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

ISOTOPE PERCENT CURIES a.Fe-55 8.94 1.180E+01 Co-60 27.8 3.670E+01 Zn-65 12.6 1.660E+01 Mn-54 32.8 4.330E+01 Cr-51 3.37 4.450E+00 Other 14.4 1.900E+01 b.Fe-55 22.2 6.050E-02 Co-60 25.6 6.970E-02 Mn-54 5.71 1.550E-02 Zn-65 35.2 9.590E-02 Other 11.3 3.070E-02 C.

d.

e.

1-

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

Number of Shipments Mode of Transportation Destination 0 N/A N/A 69

TABLE 3-1 E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jul-2007 ENDING: 31-Dec-2007 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est. Total period ERROR %

a. Spent resins, filter sludges, evaporator m3 1.23E+01 bottoms, etc. Ci 3.12E+01 1.00 E 01

b. Dry compressible waste, contaminated equip. m3 2.68E+01 etc. Ci 3.1OE-02 2.00 E 01 3

c. Irradiated components, control rods, m 6.66E+00 Ci 3.27E+04 2.00 E 01

d. Control Rod Drive Filters m_3 Ci

e. Other (describe) m_3 Equip. etc. Ci

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

ISOTOPE PERCENT CURIES a.Fe-55 8.27 2.57E+00 Co-60 45.6 1.42E+01 Zn-65 14.5 4.52E+00 Mn-54 13.0 4.04E+00 Other -18.7 5.82E+00

b. Fe-55 22.2 6.89E-03 Co-60 25.6 7.95E-03 Mn-54 5.71 1.77E-03 Zn-65 35.2 1.09E-02 Other 11.3 3.50E-03 c.Fe-55 41.6 1.36E+04 Co-60 36.1 1.18E+04 Hf-1 81 2.34 7.65E+02 Ta-1 82 13.7 4.48E+03 Ni-63 4.53 1.48E+03 Other 1.73 5.66E+02 d.

e.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Irradiated Hardware (3 shipments) Tractor/Trailer Barnwell All Other Wastes to Processors Studsvik and Energy Solutions B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 70

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2007 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-Jan-2007 ENDING: 30-Jun-2007 TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATION OF QUANTITY/ NUCLIDES/ CONTAINER. CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBIC FEET (FT 3)

Dewatered 132 Zn-65,Fe-55,Co-60 High 3.93 120.3 14-210 DOT 7A N/A Resins Mn-54, Cr-51 Intergrity See Note TYPE A CASK/

Container 8-120(B) CASK/

14-210"*STC Cask Dry 0.270 Fe-55,Co-60,Mn-54 B-25 37.7 90 **STC N/A Active Waste Zn-65 Boxes/High See Note (B-25)

Integrity Container

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

- STC-Strong Tight Container TABLE 3-1 E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2007 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2

~TARTINf~: 1-IIJL-2007 ENDINt~ 1-DEC-2007 TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATION OF QUANTITY/ NUCLIDES/ CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBIC FEET (FT 3)

Dewatered 31.2 Zn-65,Fe-55,Co-60 High 3.61 120.3 14-210 Cask N/A Resins Mn-54 Intergrity See Note Container Dry 3.10 E-02 Fe-55,C0-60,Mn-54 B-25 9.85 96 Excepted N/A Active Waste Zn-65 Boxes/High See Note Packages Integrity (B-25)

Container Irradiated 32,700 Fe-55,Co-60, CNSI 3-55 3 57.4 (2) CNSI 3-55 Type B N/A Hardware Hf-181,Ta-182, Liner 120.3 (1) CNSI 8-210 Type B Ni-63 CNSI 8-120 HIC Note: The actual type, size and number of the containers may vary from the recorded values due to the use of different containers by waste processors for final disposal of processed resin and DAW.

71

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

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

The source term is not listed in Table 4-1 . The source term is listed in Tables 2-2A and 2-213, for the elevated releases. Similarly the source term is listed in Tables 2-3A and 2-3B for the ground level releases.

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

72

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page: 1 Location Name ROADSIDE PARK Distance (kilometers) 1.18E+00 Sector WNW Occupancy Factor 2.28E-04 (22.00E+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 7.83E-06 Particulate X/Q (sec/m3) 7.OOE-06 Particulate D/Q (m-2) 2. 01E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 2.42E-08 Particulate X/Q (sec/m3) 2. 37E-08 Particulate D/Q (m-2) 1.29E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 6.93E-I1 2.47E-10 3 .17E-10 3.17E-10 Liver mrem 8.75E-07 7.35E-07 1. 61E-06 1.61E-06 TBody mrem 8.75E-07 7.35E-07 1. 61E-06 1.61E-06 Thyroid mrem 8.77E-07 7.35E-07 1. 61E-06 1.61E-06 Kidney mrem 8.75E-07 7.35E-07 1. 61E-06 1.61E-06 Lung mrem 8.75E-07 7.35E-07 1. 61E-06 1.61E-06 GI-LLI mrem 8.75E-07 7.35E-07 1. 61E-06 1.61E-06 73

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page: 2 Location Name CAMPING AREA Distance (kilometers) 1.27E+00 Sector WNW Occupancy Factor 5.48E-03 (4.80E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 7.03E-06 Particulate X/Q (sec/m3) 6.27E-06 Particulate D/Q (m-2) 1.80E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 2.38E-08 Particulate X/Q (sec/m3) 2.33E-08 Particulate D/Q (m-2) 1.21E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem .151E-09 5.47E-09 6.98E-09 6.98E-09

Liver mrem 1.88E-05 1.58E-05 3.47E-05 3.47E-05 TBody mrem 1.88E-05 1.58E-05 3.47E-05 3.47E-05 Thyroid mrem 1.89E-05, 1.58E-05 3.47E-05 -3.47E-05 Kidney mrem 1.88E-05 1..58E-05 3.47E-05 3.47E-05 Lung mrem 1.88E-05 1.58E-05 3.47E-05 3.47E-05 GI-LLI mrem 1.88E-05 1.58E-05 3.47E-05 3.47E-05 74

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page: 3 Location Name RECREATION AREA Distance (kilometers) 1.03E+00 Sector SSE Occupancy Factor 2.37E-02 (2.08E+02 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 6.42E-06 Particulate X/Q (sec/m3) 5. 73E-06 Particulate D/Q (m-2) 2. 36E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 3.30E-08 Particulate X/Q (sec/m3) 3 .21E-08 Particulate D/Q (m-2) 1. 56E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 6.74E-09 2. 69E-08 3.37E-08 3.37E-08 Liver mrem 7.45E-05 6 .26E-05 1.37E-04 1. 37E-04 TBody mrem 7.45E-05 6.26E-05 1. 37E-04 1.37E-04 Thyroid mrem 7.46E-05 6 .26E-05 1. 37E-04 1.37E-04 Kidney mrem 7.45E-05 6. 26E-05 1. 37E-04 1. 37E-04 Lung mrem 7.45E-05 6 .26E-05 1. 37E-04 1. 37E-04 GI-LLI mrem 7.45E-05 6 .26E-05 1. 37E-04 1.37E-04 75

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page:. 4 Location Name VISITORS CENTER Distance (kilometers) 6.94E-01 Sector WSW Occupancy Factor 4.57E-04 (4.OOE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.87E-05 Particulate X/Q (sec/m3) 1.72E-05 Particulate D/Q (m-2) 5.47E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble GasX/Q (sec/m3) 5. OOE-08 Particulate X/Q (sec/m3) *4.97E-08 Particulate D/Q (m-2) 2.26E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 3.24E-10 1.02E-09 1. 34E-09 1.34E-09 Liver mrem 4.31E-06 3. 62E-06 7. 93E-06 7. 93E-06 TBody mrem 4.31E-06 3. 62E-06 7. 93E-06 7. 93E-06 Thyroid mrem 4.32E-06 3. 62E-06 7. 94E-06 7. 94E-06 Kidney mrem 4.31E-06 3.62E-06 7. 93E-06 7. 93E-06 Lung mrem 4.31E-06 3.62E-06 7. 93E-06 7. 93E-06 GI-LLI mrem 4.31E-06 3.62E-06 7. 93E-06 7.93E-06 76

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page:

Location Name ROADSIDE PARK Distance (kilometers) 1.18E+00 Sector WNW Occupancy Factor 2.28E-04 2.OOE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 7. 83E-06 Particulate X/Q (sec/m3) 7. OOE-06 Particulate D/Q (m-2) 2. 01E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 2 .42E-08 Particulate X/Q (sec/m3) 2 .37E-08 Particulate D/Q (m-2) 1.29E-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4. Ending Date Bone mrem 6.60E-10 2.23E-10 8. 82E-10 1 .20E-09 Liver mrem 9.74E-07 1.26E-06 2 .23E-06 3. 84E-06 TBody mrem 9.74E-07 1.26E-06 2 .23E-06 3. 84E-06 Thyroid mrem 9.75E-07 1.26E-06 2 .23E-06 3. 84E-06 Kidney mrem 9.74E-07 1.26E-06 2 .23E-06 3.84E-06 Lung mrem 9.75E-07 1.26E-06 2 .23E-06 3.84E-06 GI-LLI mrem 9.74E-07 1.26E-06 2 .23E-06 3. 84E-06 77

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page: 2 Location Name CAMPING AREA Distance (kilometers) 1.27E+00 Sector WNW Occupancy Factor 5.48E-03 (4.,80E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 7.03E-06 Particulate X/Q (sec/m3) 6.27E-06 Particulate D/Q (m-2) 1.80E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 2.38E-08 Particulate X/Q (sec/m3) 2.33E-08 Particulate D/Q (m-2) 1.21E-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 1.42E-08 4.87E-09 1.91E-08 2.61E-08 Liver mrem 2.10E-05 2.71E-05 4.80E-05 8.27E-05 TBody mrem 2.10E-05 2.71E-05 4.81E-05 8.27E-05 Thyroid mrem 2.10E-05 2.71E-05 4.81E-05 8.28E-05 Kidney mrem 2.10E-05 2.71E-05 4.80E-05 8.27E-05 Lung mrem 2.10E-05 2.71E-05 4.81E-05 8.27E-05 GI-LLI mrem 2.10E-05 2.71E-05 4.81E-05 8.27E-05 78

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page: 3 Location Name RECREATION AREA Distance (kilometers) 1.03E+00 Sector SSE Occupancy Factor 2.37E-02 (2.08E+02 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 6.42E-06 Particulate X/Q (sec/m3) 5.73E-06 Particulate D/Q (m-2) 2. 36E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 3. 30E-08 Particulate X/Q (sec/m3) 3.21E-08 Particulate D/Q (m-2) 1.56E-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 5.67E-08 1. 98E-08 7.65E-08 1.10E-07 Liver mrem 8.29E-05 1. 07E-04 1. 90E-04 3.27E-04 TBody mrem 8.30E-05 1. 07E-04 1. 90E-04 3.27E-04 Thyroid mrem 8.30E-05 1. 07E-04 1. 90E-04 3.27E-04 Kidney mrem 8.29E-05 1. 07E-04 1. 90E-04 3.27E-04 Lung mrem 8.30E-05 1. 07E-04 1. 90E-04 3.27E-04 GI-LLI mrem 8.30E-05 1. 07E-04 1. 90E-04 3.27E-04 79

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page: 4 Location Name VISITORS CENTER Distance (kilometers) 6.94E-01 Sector WSW Occupancy Factor 4.57E-04 (4.OOE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.87E-05 Particulate X/Q (sec/m3) 1.72E-05 Particulate D/Q (m-2) 5.47E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 5. OOE-08 Particulate X/Q (sec/m3) 4. 97E-08 Particulate D/Q (m-2) 2 .26E-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 3.23E-09 9.60E-10 4. 19E-09 5.53E-09 Liver mrem 4.80E-06 6. 19E-06 1. 10E-05 1. 89E-05 TBody mrem 4.80E-06 6. 19E-06 1. 10E-05 1. 89E-05 Thyroid mrem 4.80E-06 6. 19E-06 1. 10E-05 1. 89E-05 Kidney mrem 4.80E-06 6. 19E-06 1. 10E-05 1. 89E-05 Lung mrem 4.80E-06 6. 19E-06 1. 10E-05 1. 89E-05 GI-LLI mrem 4.80E-06 6. 19E-06 1. 10E-05 1. 89E-05 80

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

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

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

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

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

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

81

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

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

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

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

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

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

82

8.2 Descriptionof Changes There were two revisions to the Hatch ODCM in 2007. They are described below.

Version 20, February2007 Tables 2-1 and 2-2 contained location numbers of various outfalls. These numbers have been confused with MPLs for the monitoring equipment located at the outfalls. Minor changes have been made in the two Tables to clarify that the number designations are for the outfall locations and not identifying equipment.

The flowmeter at Y22N003A (3A) monitors the combination of flow from two streams -- effluent stream Y22N012B (12B) and an additional stream which essentially dilutes the effluent stream from 12B. If the flowmeter is out of service at 12B, the flowmeter at 3A could be used to conservatively estimate the flow from 12B (would consider the entire flow as the effluent stream). Similarly, if the flowmeter is out of service at 3A, then 12B could be used to conservatively estimate the flow from 3A (no credit taken for the dilution stream). Footnote "d."

was added to Table 2-1 to reflect these substitutions. Action 105 would only be applicable if neither flowmeter was operable.

Version 21, November 2007 Deleted wording in Chapter 2, Liquid Effluents, Actions Sections 2.1.1.2, 2.1.2.2, 2.1.3.2, and 2.1.4.2. "When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit." Also deleted the same wording in Chapter 3, Gaseous Effluents, Actions Section 3.1.1.2, 3.1.2.2, 3.1.3.2, 3.1.4.2, and 3.1.5.2 to be consistent with L.C.O. 3.0.4 regarding Mode change requirements. Added wording to Liquid Effluents, Actions Section 2.1.1.2 and Gaseous Effluents, Actions Section 3.1.1.2. "Otherwise, restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a timely manner."

Added operability and surveillance guidance for the Recombiner Building Ventilation Monitoring System Flowrate Measurement Device to Table 3-1, Radioactive Gaseous Effluent Monitoring Instrumentation, and Table 3-2, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.

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

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

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

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

84

SOUTHERN COMPANY E. L HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1, 2007 - DECEMBER 31,2007 APPENDIX A 85

Release of Radioactive RHR Service Water for 2007 The following historical information is provided to create a perspective for the release of radioactivity during the year 2007 relative to the RHR Service Water System.

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

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

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

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

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

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

86

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

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

The highest concentrations of radionuclides found in the RHRSW samples for 2007 were from 4/11/07, when the total concentration released was 3.58E-8 iiCi/ml. As shown in the following table, the highest concentrations were found in 1997, when the total concentration released was 1.21 E-5 gCi/ml.

Radio- 1997 1998 1999 1 2000 2001

-nuclide (IiCi/ml) (Ciml I (g) iCi/ml) [(Ci/ml)

(iCi/ml)

Cr-51 1.07E-6 3.16E-7 Mn-54 2.37E-6 4.95E-7 2.49E-7 2.53E-7 Fe-59 1.19E-7 Co 4.94E-6 1.12E-6 2.27E-8 2.82E-7 1.99E-7 Zn-65 2.06E-6 7.96E-8 2.24E-7 Co-58 1.06E-6 Gs-1 34< 2.1 OE-7____ ________

Cs-1 37 4.43E-7

-Radio-*-" 2002 T 2003 2004' 2005 2006 2007:

nuclide, (gti/m (pCi/ml) I(lC/ml)

(gli) (I,Ci/ml)(

Mn-54 2.78E-8 1.46E-8 8.59E-9 1.23E-8 Co-60 1.99E-7 2.65E-7 3.78E-8 2.96E-8 1.24E-7 2.43E-7 Nb-95 5.46E-9 Cs.-137. , 7.77E-9 Fe-59 was identified in one sample (7/18/01). Heat exchanger testing and the analysis result indicate no new leaks to the system. The results of the samples analyzed in 2005 indicate we are monitoring residual contamination from the 1996 leaks.

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

The following discussion is based on a release duration of 1 minute, a release volume of 4,000 gallons, a total dilution of only 10,000 gallons, and the radionuclide concentrations from 1997. This is a very conservative estimate, since credit for the additional dilution provided by the circulating water flume was not taken into consideration and the activity from 1997 was higher with more radionuclides. The sum of the ratios of the concentration of each radionuclide in the mixture to its effluent concentration limit (ECL) was 1.15. The sum of the ECL fractions must be less than ten (<10) to ensure that the concentration limit for the mixture is not exceeded. As can be seen, the sum is much less than ten. (10CFR20 Appendix B states that the sum of the fractions of the nuclides divided by their effluent concentration limits (ECLs) must be less than one. Further NRC guidance, Technical Specifications, and the ODCM allow the 87

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

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

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

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

100FR20.1501 (a)(2)(ii) & (iii) requires the licensee to evaluate the concentration or quantities of radioactive materials and the potential radiological hazard, respectively. The concentrations and quantity of the radioactive materials in the release were evaluated by sampling and analysis as discussed above. The potential radiological hazard was also evaluated by performance of the dose calculations, which would be a result of the release, as discussed above in the assessment of ODCM section 2.1.3.

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

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

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

88

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

40CFR190 is concerned with the annual dose to any member of the public due to releases of radioactivity and to radiation from the uranium fuel cycle sources. This is addressed by TS 5.5.4.j and implemented by ODCM section 5.1.2, which states that additional calculation and reporting is required when any of the dose limits as specified in the ODCM sections 2.1.3, 3.1.3, or 3.1.4 are exceeded by a factor of two. This requirement is not applicable for the release based on the doses as discussed above in the assessment of ODCM section 2.1.3.

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

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

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

89

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2007 Enclosure 2 Farley Annual Radioactive Effluent Release Report for 2007

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 2007

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 3 1.7 Liquid Effluents - Abnormal Releases 4 2.0 GASEOUS EFFLUENTS 36 2.1 Regulatory Requirements 36 2.1.1 Dose Rate Limits 36 2.1.2 Air Doses Due to Noble Gases in 36 Gaseous Releases 2.1.3 Doses to a Member of the Public 37 2.2 Measurements and Approximation 37 of Total Radioactivity 2.2.1 Sample Collection and Analysis 37

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 2.2.2 Total Quantities of Radioactivity, Dose 38 Rates and Cumulative Doses 2.2.2.1 Fission and Activation Gases 38 2.2.2.2 Radioiodine, Tritium and Particulate 38 Releases 2.2.2.3 Gross Alpha Release 39 2.2.3 Total Error Estimation 40 2.3 Gaseous Effluent Release Data 40 2.4 Radiological Impact Due to Gaseous 41 Releases 2.5 Gaseous Effluents - Batch Releases 41

'2.6 Gaseous Effluents - Abnormal Releases 41 3.0 SOLID WASTE 77 3.1 Regulatory Requirements 77 3.1.1 Solid Radioactive Waste System 77 3.1.2 Reporting Requirements 77 3.2 Solid Waste Data 77 4.0 DOSES TO MEMBERS OF THE PUBLIC 83 INSIDE THE SITE BOUNDARY 4.1 Regulatory Requirements 83 4.2 Demonstration of Compliance 83

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 5.0 TOTAL DOSE FROM URANIUM FUEL 90 CYCLE (40CFRI90) 5.1 Regulatory Requirements 90 5.2 Demonstration of Compliance 90 6.0 METEOROLOGICAL DATA 90 7.0 PROGRAM DEVIATIONS 90 7.1 Inoperable Liquid or Gaseous Effluent 90 Monitoring Instrumentation 7.1.1 Regulatory Requirements 90 7.1.2 Description of Deviations 90 7.2 Effluent Sample Analysis Exceeding 91 Minimum Detectable Concentration (MDC) 7.2.1 Regulatory Requirements 91 7.2.2 Description of Deviations 91 7.3 Incorrect Compositing of Liquid 91 or Gaseous Effluent Samples 7.3.1 Regulatory Requirements 91 7.3.2 Description of Deviations 91 8.0 CHANGES TO THE PLANT FARLEY ODCM 91 8.1 Regulatory Requirements' 91 8.2 Description of Changes 91

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR 92 SOLID RADWASTE TREATMENT SYSTEMS 9.1 Regulatory Requirements 92 9.2 Description of Major Changes 92

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 7 All Releases, Unit 2 (Quarters 1,2, 3 and 4)

I-IC Liquid Effluents - Summation of 9 All Releases, Site (Quarters 1,2, 3 and 4) 1-2A Liquid Effluents, Unit 1 (Quarters 1,2, 11 3 and 4) 1-2B Liquid Effluents, Unit 2 (Quarters 1,2, 15 3 and 4) 1-2C Liquid Effluents, Site (Quarters 1,2, 19 3 and 4) 1-3A Doses to a MEMBER OF THE PUBLIC 23 Due to Liquid Releases, Unit 1 (Quarters 1,2,3 and 4) 1-3B Doses to a MEMBER OF THE PUBLIC 25 Due to Liquid Releases, Unit 2 (Quarters 1,2,3 and 4) 1-4 Minimum Detectable Concentration - 27 Liquid Sample Analyses 1-5A Liquid Effluents - Batch Release 28 Summary, Unit 1 1-SB Liquid Effluents - Batch Release 30 Summary, Unit 2

FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-6A Liquid Effluents - Abnormal Release 32 Summary, Unit 1 1-6B Liquid Effluents - Abnormal Release 34 Summary, Unit 2 2-lA Gaseous Effluents - Summation of 42 All Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-lB Gaseous Effluents - Summation of 44 All Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-1C Gaseous Effluents - Summation of 46 All Releases, Site (Quarters 1,2, 3 and 4) 2-2A Gaseous Effluents - mixed Mode 48 Level Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-2B Gaseous Effluents - Mixed Mode 50 Level Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-2C Gaseous Effluents - mixed Mode 52 Level Releases, Site (Quarters 1,2, 3 and 4) 2-3A Gaseous Effluents - Ground 54 Level Releases, Unit 1 (Quarters 1,2, 3 and.4) 2-3B Gaseous Effluents - Ground 56 Level Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-3C Gaseous Effluents Ground 58 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 60 Gaseous Releases, Unit 1 (Quarters 1,2, 3 and 4) 2-4B Air Doses Due to Noble Gases in 62 Gaseous Releases, Unit 2 (Quarters 1,2, 3 and 4) 2-5A Doses to a MEMBER OF THE PUBLIC 64 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 66 Due to Radioiodines, Tritium, and Particulates in Gaseous Releases, Unit 2 (Quarters 1,2,3 and 4) 2-6 Minimum Detectable Concentration - 68 Gaseous Effluent Analyses 2-7A Gaseous Effluents - Batch Release 69 Summary, Unit 1 2-7B Gaseous Effluents - Batch Release 71 Summary, Unit 2 2-8A Gaseous Effluents - Abnormal Release 73 Summary, Unit 1 2-8B Gaseous Effluents - Abnormal Release 75 Summary, Unit 2 3-1 Solid Waste and Irradiated 78 Fuel Shipments 4-1 Doses to a MEMBER OF THE PUBLIC 84 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 2007. 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/ ODCM 2.1.2 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.OE-04 uCi/ml total activity.

1.1.2 Dose Limits Technical Specifications 5.5.4.d and 5.5.4.e/ ODCM 2.1.3 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.

1

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

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 obtainedare 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 OperationsDepartment for release. When the release is completed, the actual release data are provided to the Chemistry 2

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 2007 are presented in accordance with Regulatory Guide 1.21 Tables 2A and 2B. Information required by Table 2A is found in this report in Tables 1-lA, 1-1B, and 1-1C; Table 2-B information is presented in Tables 1-2A, 1-2B, and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 .for all four quarters.

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

Unit 1 2007 Doses to a Member of the Public due to Liquid Releases: Table 1-3A Unit 2 2007 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 2007 Liquid Effluents - Batch Release Summary: Table 1-5A Unit 2 2007 Liquid Effluents - Batch Release Summary: Table 1-5B 3

1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases during 2007.

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

Unit 1 2007 Liquid Effluents - Abnormal Release Summary: Table 1-6A Unit 2 2007 Liquid Effluents - Abnormal Release Summary: Table 1-6B 4

TABLE 1-lA Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION.& ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.05E-03 2.71E-02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.99E-10 1.69E-09

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 1.56E+02 1.23E+02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.15E-05 7.68E-06

3. PERCENT OF APPLICABLE LIMIT %*

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 9.61E-04 2.34E-04 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.09E-11 1.46E-11

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 1.38E-05 1.80E+01 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 4.98E+07 1.61E+07 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.35E+10 1.60E+10 1.00E+01 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

5

TABLE 1-lA Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.32E-02 2.39E-02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.76E-10 1.73E-09

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 2.86E+02 3.42E+01 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.68E-05 2.48E-06

3. PERCENT OF APPLICABLE LIMIT %*

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 7.34E-03 5.61E-04 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.32E-10 4.06E-11

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.86E-11 3.66E-04 1.80E+01 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 1.40E+06 2.96E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 1.70E+10 1.38E+10 1.00E+01 Applicable limits are expressed in terms of dose. See Tables 1-3A and l-3B of this report.

6

TABLE I-lB Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 6.69E-03 4.61E-02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.15E-10 3.62E-09

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 2.20E+02 3.03E+01 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.69E-05 2.39E-06

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 4.55E-04 1.13E-04 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.50E-11 8.92E-12

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 3.09E-05 1.80E+01 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 1.85E+06 2.41E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 1.30E+10 1.27E+10 1.00E+01 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

7

TABLE 1-lB Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.63E-02 2.33E-02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.19E-10 1.30E-09

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 2.19E+02 7.69E+01 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.10E-05 4.29E-06

3. PERCENT OF APPLICABLE LIMIT %*

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 4.95E-03 5.99E-04 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.48E-10 3.34E-11

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 5.05E-05 3.87E-06 1.80E+01 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 4.57E+07 1.54E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 1.99E+10 1.79E+10 1.OOE+01 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

8

TABLE 1-IC Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.07E-02 7.32E-02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.03E-10 2.55E-09

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 3.76E+02 1.53E+02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.42E-05 5.32E-06

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.42E-03 3.47E-04 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.35E-11 1.21E-11

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 4.47E-05 1.80E+01 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 5.17E+07 4.02E+07. 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 2.65E+10 2.87E+10 1.00E+01 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

9

TABLE .1-IC Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 2.95E-02 4.71E-02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.98E-10 1.48E-09

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 5.05E+02 1.lIE+02 1.80E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.37E-05 3.50E-06

3. PERCENT OF APPLICABLE LIMIT %*

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.23E-02 1.16E-03 180E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.33E-10 3.65E-11

3. PERCENT OF APPLICABLE LIMIT %*

D.' GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 5.05E-05 3.70E-04 1.80E+01 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 4.71E+07 4.50E+07 1.OOE+01 F. VOLUME OF DILUTION WATER USED LITERS 3.69E+10 3.17E+10 1.OOE+01 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

10

TABLE 1-2A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 QUARTER 1 IQUARTER 2 H-3 I CURIES I 0.00E+00 I 0.OOE+00 I 1.56E+02 I 1.23E+02 FISSION & ACTIVATION PRODUCTS AG-108M CURIES 0. OOE+00 0. OOE+00 7. 77E-06 4. 47E-05 AG-ilOM CURIES 0. OOE+00 0. OOE+00 2. 82E-05 1.29E-04 BA-140 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 7. 26E-06 CO-57 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 1.44E-06 CO-58 CURIES 0. OOE+00 0. OOE+00 3. 42E-05 3. 84E-03 CO-60 CURIES 0. OOE+00 0 OOE+00 9. 78E-04 2. 79E-03 CR-51 CURIES 0. OOE+00 0 OOE+00 0 . OOE+00 1.34E-03 CS-137 CURIES 0. OOE+00 0 OOE+00 2 .23E-05 1.21E-05 FE-55 CURIES 0. OOE+00 0 OOE+00 6. 98E-04 8. 98E-04 FE-59 CURIES 0. OOE+00 0 OOE+00 0. OOE+00 2. 75E-06 MN-54 CURIES 0 OOE+00 0. OOE+00 0. OOE+00 6. 61E-05 MO-101 CURIES 0 OOE+00 0. OOE+00 5 10E-05 0. OOE+00 NB-95 CURIES 0 OOE+00 0. OOE+00 0. OOE+00 2. 46E-04 NI-56 CURIES 0 OOE+00 0. OOE+00 0. OOE+00 3. 06E-07 RH-105 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 6. 42E-05 SB-124 CURIES 0 .OOE+00 0. OOE+00 0. OOE+00 2. 45E-05 SB-125 CURIES 0. OOE+00 0. OOE+00 9 28E-05 5. 48E-04 SN-113 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 2. 33E-06 SN-117M CURIES 0. OOE+00 0. OOE+00 1. 22E-06 7. 88E-05 SR-89 CURIES 0. OOE+00 0. OOE+00 7 . 05E-12 1. 23E-05 SR-90 CURIES 2. 92E-04 3. 02E-06 0 . OOE+00 0 . OOE+00 TE-125M CURIES 0. OOE+00 0. OOE+00 1 . 59E-03 1.49E-02 TE-129M CURIES 0. OOE+00 0 .OOE+00 0 OOE+00 5. 12E-05 TE-133M CURIES 0. OOE+00 0. OOE+00 0 OOE+00 7. 15E-06 TE-134 CURIES 0. OOE+00 0. OOE+00 4. 33E-06 0. OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

11

TABLE 1-2A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER,2 I FISSION & ACTIVATION PRODUCTS ZN-65 CURIES 0.OOE+00 0.OOE+00 2.48E-04 1.90E-03 ZR-95 CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 1.09E-04 TOTALS I CURIES I 2.92E-04 3.02E-06 I 3.76E-03 I 2.71E-02 DISSOLVED AND ENTRAINED GASES XE-133 I CURIES 0.00E+00 0.0OE+00 1.95E-04 2.34E-04 XE-138 I CURIES 0.OOE+00 0.OOE+00 7.66E-04 0.OOE+00 TOTALS I CURIES I 0.00E+00 I 0.OOE+00 9.61E-04 I 2.34E-04 I G-ALPHA I CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.38E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

12

TABLE 1-2A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 QUARTER 4 H-3 I CURIES I 0.OOE+00 0.OOE+00 2.86E+02 3.42E+01 FISSION & ACTIVATION PRODUCTS AG-108M CURIES 0. OOE+00 0. OOE+00 1.40E-05 0. OOE+00 AG-iIOM CURIES 0. OOE+00 0 . OOE+00 6.76E-05 1. 08E-04 AS-76 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 1. 01E-04 BA-140 CURIES 0 .00E+00 0. OOE+00 0. OOE+00 3. 29E-06 CO-57 CURIES 0. 00E+00 0. OOE+00 0. OOE+00 1.40E-05 CO-58 CURIES 0. OOE+00 0. OOE+00 1. 45E-03 8. 53E-03 CO-60 CURIES 0. OOE+00 0. OOE+00 2. 32E-03 4. 08E-03 CR-51 CURIES 0 .OOE00 0 .OOE+00 2. lOE-04 2. 35E-03 CS-134 CURIES 0 .OOE+00 0. OOE+00 0. OOE+00 7. 83E-06 CS-137 CURIES 0 .OOE+00 0. OOE+00 3. 48E-05 4. 55E-05 EU-154 CURIES 0 .OOE+00 0. OOE+/-00 0. OOE+00 1.16E-05 FE-55 CURIES 0. OOE+00 0. OOE+00 6. 99E-04 7.42E-04 FE-59 CURIES 0 .OOE+00 0. OOE+00 1. 47E-05 2. 39E-05 HG-203 CURIES 0 .OOE+00 0. OOE+00 3.90E-07 0. OOE+00 MN-54 CURIES 0 OOE+00 0. OOE+00 0. OOE+00 1. 06E-04 NB-95 CURIES 0 .OOE+00 0. OOE+00 5.69E-05 5. 76E-04 NI-56 CURIES 0 .OOE+00 0 .OOE+00 1. 61E-06 0. OOE+00 RB-86 CURIES 0. OOE+00 0. OOE+00 1. 60E-05 0. OOE+00 RH-105 CURIES 0 .OOE+00 0. OOE+00 0..OOE+00 9. 06E-05 RU-103 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 3.35E-06 SB-124 CURIES 0. OOE+00 0. OOE+00 4. 47E-06 i.34E-04 SB-125 CURIES 0 .OOE+00 0 . OOE+00 1. 54E-04 6.53E-04 SE-75 CURIES 0. OOE+00 0. OOE+00 6.73E-07 2.56E-06 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

13

TABLE 1-2A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 JQUARTER, 4 FISSION & ACTIVATION PRODUCTS SN-113 CURIES 0 . 00E+00 0. OOE+00 1.10E-06 3.95E-06 SN-117M CURIES 0. OOE+00 0. OOE+00 1. 83E-05 2. OOE-05 SR-85 CURIES 0 . OOE+00 0. OOE+00 1.37E-06 0. OOE+00 SR-89 CURIES 0. 00E+00 0. OOE+00 1. 38E-'05 1. 05E-11 SR-90 CURIES 0 .00E+00 0. OOE+00 8. 07E-12 3. 40E-06 TC-104 CURIES 0. OOE+00 0. OOE+00 7. 72E-07 0. 00E+00 TE-125M CURIES 0. OOE+00 0. OOE+00 7. 45E-03 3.59E-03 TE-131 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 2. 15E-06 TE-132 CURIES 0. OOE+00 0. OOE+00 4. 39E-06 2. 90E-06 Y-90M CURIES 0. OOE+00 0. OOE+00 2.82E-07 0. OOE+00 Y-94 CURIES 0. OOE+00 0. OOE+00 0 . 00E+00 4.40E-06 ZN-65 CURIES 0. OOE+00 0. OOE+00 6.09E-04 2.38E-03 ZN-69M CURIES 0. OOE+00 0. OOE+00 2.28E-06 0. OOE+00 ZR-95 CURIES 0. OOE+00 0. OOE+00 6. 14E-06 2. 69E-04 TOTALS CURIES 0.OOE+00 0.OOE+00 1.32E-02 I 2.39E-02 DISSOLVED AND ENTRAINED GASES KR-85 CURIES 0.OOE+00 0.OOE+00 3.03E-04 0.OOE+00 XE-133 CURIES 0.OOE+00 0.00E+00 6.83E-03 5.47E-04 XE-133M CURIES 0.OOE+00 0.00E+00 4.35E-05 0.OOE+00 XE-135 CURIES 0.OOE+00 0.OOE+00 1.64E-04 1.35E-05 TOTALS CURIES 0.OOE+00 0.00E+00 I 7.34E-03 5.61E-04 G-ALPHA I CURIES 0.OOE+00 3.60E-04 I 2.86E-11 I 6.69E-06 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

14

TABLE 1-2B*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 1 H-3 I CURIES 0.OOE+00 I 0.OOE+00 I 2.20E+02 I 3.03E+01 I FISSION & ACTIVATION PRODUCTS AG-108M CURIES 0. OOE+00 0. OOE+00 5.66E-06 2. 73E-05 AG-I1OM CURIES 0. OOE+00 0. OOE+00 2.20E-05 8.72E-05 CO-57 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 5. 91E-06 CO-58 CURIES 0. OOE+00 0. OOE+00 3.93E-06 5. 57E-03 CO-60 CURIES 0 .OOE+00 0. OOE+00 1 . 62E-03 6. 27E-03 CR-51 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 2. 70E-03 CS-137 CURIES 0. OOE00 0. OOE+00 9. OOE-05 9. 24E-05 CS-138 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 4.34E-06 EU-155 CURIES 0. OOE+00 0. OOE+00 8. 80E-07 0. OOE+00 FE-55 CURIES 0. OOE+00 1. 40E-09 3. 95E-03 1.12E-03 FE-59 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 1.42E-05 HF-181 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 8. 94E-07 HG-203 CURIES 0. OOE+00 0. OOE+00 4.64E-07 0. OOE+00 1-133 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 8. 84E-07 1-135 CURIES 0 OOE+00 0. OOE+00 0 . OOE+00 1. 16E-05 MN-54 CURIES 0 OOE+00 0. OOE+00 0. OOE+00 1.42E-04 NB-95 CURIES 0 OOE+00 0. OOE+00 8. 90E-07 7. 15E-04 NB-97 CURIES 0 OOE+00 0. OOE+00 1.78E-05 0. OOE+00 PR-146 CURIES 0 OOE+00 0. OOE+00 0. OOE+00 5. 14E-06 RH-105 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 2. 05E-04 SB-122 CURIES 0. OOE+00 0 .OOE+00 0. OOE+00 1. 72E-06 SB-124 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 3.89E-05 SB-125 CURIES 0. OOE+00 0. OOE+00 1. 51E-04 8. 72E-04 SN-113 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 3. 84E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

15

TABLE 1-2B4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT IQUARTER 1 QUARTER 2 IQUARTER 1 JQUARTER, 2 FISSION & ACTIVATION PRODUCTS SN-117M CURIES 0.OOE+00 0.00E+00 7.02E-07 1.18E-04 SR-89 CURIES 0.OE+00 7.28E-1I 0.OOE+00 0.OOE+00 SR-90 CURIES 0.OOE+00 0.00E÷00 5.54E-13 7.57E-06 TE-125M CURIES 0.OOE+00 0.OE+00 6.42E-04 2.34E-02 TE-127M CURIES 0.OE+00 0.OE+00 0.OOE+00 1 .44E-04 Y-91M CURIES 0.OE+00 0.OE+00 0.OOE+00 1.33E-05 Y-94 CURIES 0.OOE+00 0.OE+00 0.OOE+00 1 .85E-05 ZN-65 CURIES 0.OE+00 0 0.OE+00 1.83E-04 4.13E-03 ZR-95 CURIES 0.OOE+00 0.OE+00 0.OOE+00 3.76E-04 TOTALS j CURIES 0.OOE+00 I 1.47E-09 6.69E-03 4.61E-02 DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.OOE+00 0.OOE+00 1.89E-06 0.OOE+00 KR-85M CURIES 0.OOE+00 0.OOE+00 3.09E-07 0.OOE+00 XE-133 CURIES 0.OOE+00 0.OOE+00 4.35E-04 1.13E-04 XE-137 CURIES 0.OOE+00 0.OOE+00 1.72E-05 0.OOE+00 TOTALS I CURIES I 0.OOE+00 I 0.00E+00 4.55E-04 1.13E-04 G-ALPHA CURIES 0.OOE+00 I 1.54E-05 0.OOE+00 1.55E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

16

TABLE 1-2B*

Joseph M. Farley Nuclear Plant.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 CONTINUOUS MODE BATCH MODE I NUCLIDE I UNIT QUARTER 3 IQUARTER 4 QUARTER 3 IQUARTER 4 H-3 I CURIES 0.OOE+00 0.OOE+00 2.19E+02 I 7.69E+01 FISSION & ACTIVATION PRODUCTS AG-108M CURIES 0. OOE+00 0. OOE+00 6. 97E-06 0. OOE+00 AG-11OM CURIES 0. OOE+00 0. OOE+00 2 33E-05 2. 75E-05 AS-76 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 4. 40E-04 CE-139 CURIES 0. OOE+00 0. OOE+00 0 OOE+00 6. 03E-07 CO-58 CURIES 0. OOE+00 0. OOE+00 1. 09E-03 4. 22E-03 CO-60 CURIES 0. OOE+00 0 . OOE+00 1. 67E-03 2. 16E-03 CR-51 CURIES 0. OOE+00 0. OOE+00 8. 86E-05 1. 44E-03 CS-134 CURIES 0. OOE+00 0. OOE+00 1. 57E-05 0. OOE+00 CS-137 CURIES 0. OOE+00 0. OOE+00 2. 16E-04 1. 52E-04 CS-138 CURIES 0. OOE+00 0. OOE+00 4. 91E-06 3. 37E-05 EU-152 CURIES 0. OOE+00 0. OOE+00 3 62E-06 3. 69E-06 EU-154 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 6. 87E-06 FE-55 CURIES 6. 88E-04 1. 53E-05 6. 46E-04 3 90E-04 FE-59 CURIES 0. OOE+00 0. OOE+00 5. 09E-06 0. OOE+00 1-131 CURIES 0. OOE+00 0. OOE+00 6. 87E-07 0. OOE+00 1-134 CURIES 0. OOE+00 0. OOE+00 3. 59E-06 0. OOE+00 MN-54 CURIES 0. OOE+00 0. OOE+00 1. 07E-05 5. 45E-05 NB-95 CURIES 0. OOE+00 0. OOE+00 5. 91E-05 5. 38E-04 NI-56 CURIES 0. OOE+00 0. OOE+00 1. 27E-06 7. 91E-07 NP-239 CURIES 0. OOE+00 0. OOE+00 1.09E-05 0. OOE+00 RH-105 CURIES 0. OOE+00 0. OOE+00 3. 16E-05 5. 04E-05 SB-122 CURIES 0. OOE+00 0. OOE+00 3. 03E-06 2. 84E-06 SB-124 CURIES 0. OOE+00 0. OOE+00 2 . 04E-06 3. 23E-05 SB-125 CURIES 0. OOE+00 0. OOE+00 7 .25E-04 4. 97E-04 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

17

TABLE 1-2B*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 JQUARTER, 4 FISSION & ACTIVATION PRODUCTS SN-117M I CURIES 0.00E+00 I 0.OOE+00 I 2.10E-05 I 6.83E-05 SR-89 CURIES 6.75E-04 1.50E-05 0.OOE+00 0.OE+00 SR-90 CURIES 0.OOE+00 0.OOE+00 8.53E-14 0.OOE+00 TA-182 CURIES 0.OOE+00 0.OOE+00 9.54E-06 0 00E+00 TE-125M CURIES 0.OE+00 0.OOE+00 9.55E-03 1.07E-02 Y-91M CURIES 0.OOE+00 0.OOE+00 1.32E-06 0.OE+00 ZN-65 CURIES 0.OOE+00 0.OOE+00 7.57E-04 2.10E-03 ZN-69M CURIES 0.OE+00 0.OOE+00 9.47E-07 0.OOE+00 ZR-95 CURIES 0.OOE+00 0.OOE+00 1.79E-05 2.82E-04 TOTALS CURIES 1.36E-03 I3.03E-05 1.50E-02 I 2.32E-02 DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.OOE+00 0.OOE+00 4.61E-06 0.OOE+00 XE-133 CURIES 0.OOE+00 0.OOE+00 4.67E-03 5.76E-04 XE-133M CURIES 0.OOE+00 0.OOE+00 1.37E-05 1.46E-05 XE-135 CURIES 0.OOE+00 0.OOE+00 1.44E-04 8.24E-06 XE-138 CURIES 0.OOE+00 0.OOE+00 1.17E-04 0.OOE+00 TOTALS CURIES 0.00E+00 I 0.OOE+00 4.95E-03 5.99E-04 G-ALPHA CURIES 3.01E-05 0.OOE+00 I 2.04E-05 I 3.87E-06 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

18

TABLE 1-2C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents.

Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT IQUARTER 1 QUARTER 2 IQUARTER 1 IQUARTER 2 H-3 I CURIES I 0.OOE+00 I 0.OOE+00 I 3.76E+02 I 1.53E+02 I FISSION & ACTIVATION PRODUCTS AG-108M CURIES 0. OOE+00 0. OOE+00 1. 34E-05 7.20E-05 AG-11OM CURIES 0. 00E+00 0. OOE+00 5. 03E-05 2.17E-04 BA-140 CURIES 0. 00E+00 0. OOE+00 0. OOE+00 7 .26E-06 CO-57 CURIES 0. 00E+00 0. OOE+00 0. OOE+00 7 35E-06 CO-58 CURIES 0. OOE+00 0. OOE+00 3. 82E-05 9. 41E-03 CO-60 CURIES 0. OOE+00 0. OOE+00 2. 60E-03 9. 06E-03 CR-51 CURIES 0. OOE+00 0. OOE+00 0 OOE+00 4. 03E-03 CS-137 CURIES 0. OOE+00 0. OOE+00 1.12E-04 1. 05E-04 CS-138 CURIES 0. OOE+00 0 . OOE+00 0 . OOE+00 4. 34E-06 EU-155 CURIES 0 .OOE+00 0. OOE+00 8. 80E-07 0. OOE+00 FE-55 CURIES 0 OOE+00 1.40E-09 4 64E-03 2. 02E-03 FE-59 CURIES 0 OOE+00 0. OOE+00 0 . OOE+00 1. 69E-05 HF-181 CURIES 0 . OOE+00 0. OOE+00 0 . OOE+00 8. 94E-07 HG-203 CURIES 0 OOE+00 0. OOE+00 4 64E-07 0 . OOE+00 1-133 CURIES 0 . OOE+00 0. OOE+00 0 . OOE+00 8. 84E-07 1-135 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 1.16E-05 MN-54 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 2. 08E-04 MO-101 CURIES 0. OOE+00 0 . OOE+00 5. IE-05 0 OOE+00 NB-95 CURIES 0. OOE+00 0. OOE+00 8. 90E-07 9 61E-04 NB-97 CURIES 0. OOE+00 0 OOE+00 1. 78E-05 0 . OOE+00 NI-56 CURIES 0. OOE+00 0 . OOE+00 0. OOE+00 3. 06E-07 PR-146 CURIES 0. OOE+00 0 . OOE+00 0 OOE+00 5. 14E-06 RH-105 CURIES 0. OOE+00 0. OOE+00 0 . OOE+00 2 69E-04 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

19

TABLE l-2C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE BATCH MODE NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 QUARTER 1 IQUARTER, 2 FISSION & ACTIVATION PRODUCTS SB-122 CURIES 0.OOE+00 0.OE+00 0.OOE+00 1.72E-06 SB-124 I CURIES 0.OE+00 0 0.OE+00 0.OOE+00 6.34E-05 SB-125 CURIES 0.00E+00 0.OE+00 2.44E-04 1.42E-03 SN-113 CURIES 0.OOE+00 0.OOE+00 0.OE+00 4.07E-05 SN-117M CURIES 0.00E+00 0.OOE+00 1.92E-06 1.97E-04 SR-89 CURIES 0.00E+00 7.28E-11 7.05E-12 1.23E-05 SR-90 CURIES 2.92E-04 3.02E-06 5.54E-13 7.57E-06 TE-125M CURIES 0.00E+00 0.00E+00 2.23E-03 3.83E-02 TE-127M CURIES 0.00E+00 0.OOE+00 0.00E+00 1.44E-04 TE-129M CURIES 0.00E+00 0.00E+00 0.00E+00 5.12E-05 TE-133M CURIES 0.OE+00 0.OOE+00 0.00E+00 7.15E-.06 TE-134 CURIES 0.OOE+00 0.OOE+00 4.33E-06 I0.00E+00 I Y-91M CURIES 0.OOE+00 0 00E+00 0.OE+00 1.33E-05 Y-94 CURIES 0.00E+00 0.OE+00 0.OOE+00 1.85E-05 ZN-65 CURIES 0.00E+00 0.OOE+00 4.31E-04 6.02E-03 ZR-95 CURIES 0.00E+00 0 00E+00 0.00E+00 4.85E-04 TOTALS CURIES 2.92E-04 I 3.02E-06 I 1.04E-02 I 7.32E-02 DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 1.89E-06 0.OOE+00 KR-85M CURIES 0.00E+00 0.OOE+00 3.09E-07 0.OOE+00 XE-l33 CURIES 0.OOE+00 0.OOE+00 6.30E-04 3.47E-04 XE-137 CURIES 0.OOE+00 0.OOE+00 1.72E-05. 0.OOE+00 I XE-138 CURIES 0.00E+00 I 0.OOE+00 7.66E-04 0.OOE+00 I TOTALS I CURIES 0.OOE+00 I 0.OOE+00 I 1.42E-03 3.47E-04 I G-ALPHA I CURIES 0.00E+00 I 1.54E-05 I 0.OOE+00 I 2.93E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

20

TABLE I-2C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE I NUCLIDE I UNIT IQUARTER 3 IQUARTER 4 QUARTER 3 IQUARTER 4 H-3 I CURIES I 0.00E+00 0.00E+00 I 5.05E+02 1.1iE+02 FISSION & ACTIVATION PRODUCTS AG-108M CURIES 0. 00E+00 0. 00E+00 2. lE-05 0. OOE+00 AG-il0M CURIES 0. 00E+00 0. 00E+00 9. 09E-05 1. 36E-04 AS-76 CURIES 0. OOE+00 0. OOE+00 0. 00E+00 5 .42E-04 BA-140 CURIES 0 . OOE+00 0. 00E+00 0 . OOE+00 3. 29E-06 CE-139 CURIES 0. OOE+00 0 .00E+00 0. 00E+00 6. 03E-07 CO-57 CURIES 0. OOE+00 0 .OOE+00 0. OOE+00 1. 40E-05 CO-58 CURIES 0. OOE+00 0 00E+00 2 54E-03 1. 28E-02 CO-60 CURIES 0. OOE+00 0 OOE+00 3. 99E-03 6. 23E-03 CR-51 CURIES 0. OOE+00 0. 00E+00 2. 99E-04 3. 79E-03 CS-134 CURIES 0. 00E+00 0. 00E+00 1. 57E-05 7. 83E-06 CS-137 CURIES 0. 00E+00 0. 00E+00 2 51E-04 1. 98E-04 CS-138 CURIES 0 OOE+00 0. 00E+00 4 .91E-06 3. 37E-05 EU-152 CURIES 0 00E+00 0 . 00E+00 3 62E-06 3. 69E-06 EU-154 CURIES 0. OOE+00 0. 00E+00 0. OOE+00 1. 84E-05 FE-55 CURIES 6. 88E-04 1 53E-05 1 34E-03 1. 13E-03 FE-59 CURIES 0. 00E+00 0 OOE+00 1. 98E-05 2 39E-05 HG-203 CURIES 0. 00E+00 0 OOE+00 3 90E-07 0. OOE+00 1-131 CURIES 0. 00E+00 0 00E+00 6. 87E-07 0. OOE+00 1-134 CURIES 0. 00E+00 0 . 00E+00 3. 59E-06 0. OOE+00 MN-54 CURIES 0. OOE+00 0. OOE+00 1. 07E-05 1. 60E-04 NB-95 CURIES 0. OOE+00 0. 00E+00 1. 16E-04 1. IE-03 NI-56 CURIES 0 . OOE+00 0. OOE+00 2 88E-06 7 91E-07 NP-239 CURIES 0. 00E+00 0 00E+00 1. 09E-05 0. OOE+00 RB-86 CURIES 0. 00E+00 0 OOE+00 1. 60E-05 0. OOE+00 RH-105 CURIES 0. OOE+00 0 OOE+00 3. 16E-05 1. 41E-04 RU-103 CURIES 0. OOE+00 '0 00E+00 0. OOE+00 3. 35E-06 SB-122 CURIES 0. OOE+00 0 00E+00 3. 03E-06 2. 84E-06 SB-124 CURIES 0. 00E+00 0. 00E+00 6.51E-06 1. 66E-04 SB-125 CURIES 0. OOE+00 0. 00E+00 8.79E-04 1.15E-03 SE-75 CURIES 0. OOE+00 0. 00E+00 6. 73E-07 2. 56E-06 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typically achieved minimum detectable concentrations.

21

TABLE 1-2C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE 1BATCH MODE NUCLIDE .I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 JQUARTER, 4 FISSION & ACTIVATION PRODUCTS SN-113. CURIES 0.OOE+00 0.OE+00 1.10E-06 3.95E-06 SN-117M CURIES I 0.OOE+00 0.OE+00 3.93E-05 8.83E-05 SR-85 CURIES 0.OOE+00 0.OOE+00 1.37E-06 0.OOE+00 SR-89 CURIES 6.75E-04 1 .50E-05 1 .38E-05 1 .05E-1I SR-90 CURIES 0.OOE+00 0.OE+00 8.16E-12 3.40E-06 TA-182 CURIES 0.OOE+00 0.OE+00 9.54E-06 0.OOE+00 TC-104 CURIES 0.OOE+00 0.OE+00 7.72E-07 0 0.OE+00 TE-125M CURIES 0.OE+00 0.OE+00 1 .70E-02 1 .43E-02 TE-131 CURIES 0.OOE+00 0.OE+00 0.OE+00 2.15E-06 TE-132 CURIES 0.OOE+/-00 0.OOE+00 4.39E-06 2.90E-06 Y-90M CURIES 0.00E+00 0.OOE+00 2.82E-07 0.OOE+00 Y-91M CURIES I 0.OOE+00 0.00E+00 I132E-06 I 0.OOE+00 I Y-94 CURIES 0.OOE+00 0.OE+00 0.OE+00 4.40E-06 ZN-65 CURIES 0.OOE+00 .OOE+00 1.37E-03 4.48E-03 ZN-69M CURIES 0.OOE+00 0.OOE+00 3.23E-06 0.OOE+00 ZR-95 CURIES 0.OOE+00 0.OE+00 2.40E-05 5.51E-04 TOTALS I CURIES 1.36E-03 I 3.03E-05 2.81E-02 4.71E-02 DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.OOE+00 0.OOE+00 4.61E-06 0.OE+00 KR-85 CURIES 0.OOE+00 0.OOE+00 3.03E-04 0.OE+00 XE-133 CURIES 0.OE+00 0.OOE+00 1.15E-02 1.12E-03 XE-133M CURIES 0.OE+00 0.OOE+00 5.72E-05 1.46E-05 XE-135 CURIES 0.OOE+00 0.OOE+00 3.08E-04 2.17E-05 XE-138 CURIES 0.OOE+00 0.OOE+00 1.17E-04 0.OE+00 TOTALS I CURIES 0.OOE+00 0.OOE+00 1.23E-02 I 1.16E-03 I G-ALPHA CURIES 3.01E-05 3.60E-04 2.04E-05 I 1.06E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table L-4 for typically achieved minimum detectable concentrations.-

22

TABLE 1-3A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mrem 9.22E-03 1.84E-01 5.68E-03 1.14E-01 Liver 5.0 mrem 2.82E-03 5.63E-02 3.20E-03 6.41E-02 TBody 1.5 mrem 3.16E-03 2.11E-01 1.88E-03 1.25E-01 Thyroid 5.0 mrem 1.33E-03 2.66E-02 2.49E-03 4.97E-02 Kidney 5.0 mrem 3.86E-03 7.72E-02 2.27E-02 4.54E-01 Lung 5.0 mrem 2.39E-03 4.77E-02 3.37E-03 6.74E-02 GILLI 5.0 mrem 5.12E-03 1.02E-01 2.39E-02 4.78E-01 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 1.49E-02 1.49E-01 Liver 10.0 mrem 6.02E-03 6.02E-02 TBody 3.0 mrem 5.04E-03 1.68E-01 Thyroid 10.0 mrem 3.81E-03 3.81E-02 Kidney 10.0 mrem 2.65E-02 2.65E-01 Lung 10.0 mrem 5.76E-03 5.76E-02 GILLI 10.0 mrem 2.90E-02 2.90E-01 23

TABLE 1-3A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 2.79E-03 5.59E-02 1.55E-03 3.10E-02 Liver 5.0 mrem 3.19E-03 6.38E-02 1.18E-03 2.36E-02 TBody 1.5 mrem 2.51E-03 1.67E-01 8 08E-04 5.39E-02 Thyroid 5.0 mrem 2.75E-03 5.51E-02 5.97E-04 1.19E-02 Kidney 5.0 mrem 1.26E-02 2.51E-01 5.32E-03 1.06E-01 Lung 5.0 mrem 2.73E-03 5.45E-02 2.96E-03 5.93E-02 GILLI 5.0 mrem 1.33E-02 2.66E-01 7.74E-03 1.55E-01 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 1.92E-02 1.92E-01 Liver 10.0 mrem 1.04E-02 1.04E-01 TBody 3.0 mrem 8.36E-03 2.79E-01 Thyroid 10.0 mrem 7.16E-03 7.16E-02 Kidney 10.0 mrem 4.44E-02 4.44E-01 Lung 10.0 mrem 1.15E-02 1.15E-01 GILLI 10.0 mrem 5.01E-02 5.01E-01 24

TABLE 1-3B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mrem 1.14E-03 2.27E-02 8.57E-03 1.71E-01 Liver 5.0 mrem 2.25E-03 4.49E-02 3.82E-03 7.65E-02 TBody 1.5 mrem 1.77E-03 1.18E-01 1.79E-03 1.19E-01 Thyroid 5.0 mrem 1.55E-03 3.lIE-02 2.59E-03 5.18E-02 Kidney 5.0 mrem 2.82E-03 5.63E-02 3.31E-02 6.62E-01 Lung 5.0 mrem 2.56E-03 5.13E-02 3.99E-03 7.98E-02 GILLI 5.0 mrem 3.49E-03 .6.99E-02 3.49E-02 6.97E-01 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 9.70E-03 9.70E-02 Liver 10.0 mrem 6.07E-03 6.07E-02 TBody 3.0 mrem 3.56E-03 1.19E-01 Thyroid 10.0 mrem 4.14E-03 4.14E-02 Kidney 10.0 mrem 31.59E-02 3.59E-01 Lung 10.0 mrem 6.55E-03 6.55E-02 GILLI 10.0 mrem 3.84E-02 3.84E-01 25

TABLE 1-3B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 3.70E-03 7.41E-02 3.71E-03 7.41E-02 Liver 5.0 mrem 2.86E-03 5.72E-02 2.19E-03 4.38E-02 TBody 1.5 mrem 2.01E-03 1.34E-01 1.26E-03 8.42E-02 Thyroid 5.0 mrem 2.15E-03 4.29E-02 1.48E-03 2.97E-02 Kidney 5.0 mrem 1.30E-02 2.60E-01 1.45E-02 2.90E-01 Lung 5.0 mrem 4.31E-03 8.61E-02 2.66E-03 5.32E-02 GILLI 5.0 mrem 1.36E-02 2.72E-01 1.55E-02 3.11E-01 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 1.71E-02 1.71E-01 Liver 10.0 mrem 1.11E-02 1.l1E-01 TBody 3.0 mrem 6.83E-03 2.28E-01 Thyroid 10.0 mrem 7.77E-03 7.77E-02 Kidney 10.0 mrem 6.34E-02 6.34E-01 Lung 10.0 mrem 1.35E-02 1.35E-01 GILLI 10.0 mrem 6.75E-02 6.75E-01 26

TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 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 3.14E-08 CO-58 4.92E-08 FE-59 7.19E-08 CO-60 4.77E-08 ZN-65 8.lIE-08 MO-99 1.29E-07 1-131 2.53E-08 CS-134 3.51E-08 CS-137 4.28E-08 CE-141 5.41E-08 CE-144 1.95E-07 27

TABLE .- 5A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 LIQUID RELEASES NUMBER OF BATCH RELEASES 174 TOTAL TIME PERIOD FOR BATCH RELEASES 19253.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 190.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 110.65 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 85.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 5.70E+03 CFS *

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

28

TABLE 1-5A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 1 Starting l-Jul-2007 Ending : 31-Dec-2007 LIQUID RELEASES NUMBER OF BATCH RELEASES 158 TOTAL TIME PERIOD FOR BATCH RELEASES 17448.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 157.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 110.43 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 85.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 2.19E+03 CFS *

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

29

TABLE 1-5B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 LIQUID RELEASES NUMBER OF BATCH RELEASES 227 TOTAL TIME PERIOD FOR BATCH RELEASES 22756.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 295.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 100.25 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 3.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 5.70E+03 CFS *

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

30

TABLE 1-5B Joseph M. Farley Nuclear Plant.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 2 Starting : 1-Jul-2007 Ending : 31-Dec-2007 LIQUID RELEASES NUMBER OF BATCH RELEASES 179 TOTAL TIME PERIOD FOR BATCH RELEASES 17982.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 120.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 100.46 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 80.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM 2.19E+03 . CFS *

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

31

TABLE .- 6A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 LIQUID RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.OOE+00 CURIES 32

TABLE 1-6A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 LIQUID RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES : 0.00 MINUTES MAXIMUM TIME FOR A RELEASE : 0.00 MINUTES AVERAGE TIME FOR A RELEASE : 0.00 MINUTES MINIMUM TIME FOR A RELEASE : 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.OOE+00 CURIES 33

TABLEIl-6B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 LIQUID RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIES 34

TABLE 1-6B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting : 1-Jul-2007 Ending : 31-Dec-2007 LIQUID RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE : 0.00 MINUTES AVERAGE TIME FOR A RELEASE : 0.00 MINUTES MINIMUM TIME FOR A RELEASE : 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.OOE+00 CURIES 35

2.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2007. 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/ ODCM 3.1.3 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.

36

2.1.3 Doses to a Member of the Public Technical Specifications 5.5.4.e and 5.5.4.i/ ODCM 3.1.4 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 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.

37

Particulate filters are then analyzed for gross alpha and strontium as required. All gross alpha, Sr-89 and SR-90 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis.

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

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

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

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

38

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.

39

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%

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.

40

2.4 Radiological Impact Due to Gase6ds 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 2007 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2007 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4B Unit 1 2007 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases: Table 2-5A Unit 2 2007 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 2007 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2007 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 2007.

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

Unit 1 2007 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2007 Gaseous Effluents - Abnormal Release Summary: Table 2-8B 41

TABLE 2-lA Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 3.58E-01 6.82E-01 7.74E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.61E-02 8.67E-02

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 7.99E-06 0.OOE+00 6.62E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec l.03E-06 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 0.OOE+00 4.32E-11 5.39E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 5.49E-12

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.05E+00 8.12E+00 4.57E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.36E-01 1.03E+00

3. PERCENT OF APPLICABLE LIMIT %*

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

42

TABLE 2-1A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION.& ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 9.68E+00 1.17E+01 7.74E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.22E+00 1.47E+00

3. PERCENT OF APPLICABLE LIMIT %

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 4.03E-07 9.14E-07 6.62E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.07E-08 1.15E-07

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 1.75E-07 7.08E-08 5.39E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.20E-08 8.91E-09

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 6.41E+00 6.54E+00 4.57E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.06E-01 8.22E-01

3. PERCENT OF APPLICABLE LIMIT %*

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

43

TABLE 2-1B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 9.59E-01 1.01E+00 7.74E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.23E-01 1.28E-01

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.OOE+00 1.99E-08 6.62E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.O0E+00 2.53E-09

3. PERCENT OF APPLICABLE LIMIT %*

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 0.OOE+00 1.02E-07 5.39E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 1.30E-08

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.33E+00 1.45E+00 4.57E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.71E-01 1.84E-01

3. PERCENT OF APPLICABLE LIMIT %*

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

44

TABLE 2-1B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Sumimation of All Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION.& ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 7.46E-01 4.03E-01 7.74E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.39E-02 5.07E-02

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.OOE+00 0.OOE+00 6.62E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 0.OOE+00 3.73E-09 5.39E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 4.69E-10

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 5.06E+00 2.09E+00 4.57E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.36E-01 2.63E-01

3. PERCENT OF APPLICABLE LIMIT %*

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

45

TABLE 2-1C Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1;32E+00 1.69E+00 7.74E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.69E-01 2.15E-01

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 7.99E-06 1.99E-08 6.62E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.03E-06 2.53E-09

3. PERCENT OF APPLICABLE LIMIT %*

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 0.OOE+00 1.02E-07 5.39E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 1.30E-08

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 2.38E+00 9.57E+00 4.57E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.07E-01 1.22E+00

3. PERCENT OF APPLICABLE LIMIT %*

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

46

TABLE 2-1C Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION.& ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.04E+01 1.21E+01 7.74E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.31E+00 1.52E+00

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 4.03E-07 9.14E-07 6.62E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.07E-08 1.15E-07

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(IHALF-LIVES>8 DAYS) CURIES 1.75E-07 7.45E-08 5.39E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.20E-08 9.37E-09

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.15E+01 8.63E+00 4.57E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.44E+00 1.09E+00

3. PERCENT OF APPLICABLE LIMIT %*

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

47

TABLE 2-2A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 IQUARTER 2 QUARTER 1 JQUARTER 2 FISSION GASES AR-41 CURIES 0.OOE+00 6.88E-03 3.55E-01 6.51E-01 KR-85M CURIES 0.OOE+00 0.OOE+00 0.OOE+00 2.22E-04 XE-135 CURIES 1.62E-03 4.63E-04 0.OOE+00 0.OOE+00 XE-133 CURIES 2.13E-03 2.19E-03 0.OOE+00 2.14E-02 TOTAL FOR PERIOD CURIES 3.75E-03 9.53E-03 3.55E-01 j 6.72E-01 IODINES 1-133 CURIES 8.85E-05 0.OOE+00 0.OOE+00 0.OOE+00 1-131 CURIES 7.99E-06 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 9.65E-05 0.OOE+00 0.OOE+00 0.OOE+00 PARTICULATES

SR-89 CURIES 0.OOE+00 4.32E-11 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 0.OOE+00 4.32E-11 0.OOE+00 0.OOE+00 H-3 CURIES 9.36E-01 7.91E+00 1.19E-01 2.06E-01 G-ALPHA CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

48

TABLE 2-2A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER 3 IQUARTER 4 QUARTER 3 IQUARTER 4 1 FISSION GASES AR-41 CURIES 5.59E+00 3.72E+00 9.10E-01 I 0.OOE+00 XE-135 CURIES 1.65E+00 1.58E+00 0.OOE+00 0.OOE+00 XE-133M CURIES 0.OOE+00 0.OOE+00 4.63E-05 *9.82E-05 XE-133 CURIES 1.52E+00 6.35E+00 4.64E-03 2.43E-02 XE-131M CURIES 0.OOE+00 0.OOE+00 3.OOE-04 I 4.06E-04 TOTAL FOR PERIOD CURIES 8.76E+00 1.17E+01 9.15E-01 I 2.48E-02 IODINES 1-131 CURIES 4.03E707 I 8.93E-07 I 0.OOE+00 I 2.07E-08 TOTAL FOR PERIOD CURIES 4.03E-07 I 8.93E-07 I 0.OOE+00 I 2.07E-08 PARTICULATES SR-;89 CURIES 1.75E-07 2.90E-09 0.OOE+00 0.OOE+00 CO-60 CURIES 0.OOE+00 6.78E-08 0.OOE+00 0.OOE+00 SR-90 CURIES 0.OOE+00 8.70E-1I 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.75E-07 7.08E-08 0.OOE+00 I 0.OOE+00 H-3 CURIES 6.27E+00 6.54E+00 1.37E-01 I 0.OOE+00 G-ALPHA CURIES 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

49

TABLE 2-2B*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED I UNIT IQUARTER 1 JQUARTER 2 IQUARTER 1 JQUARTER 2 FISSION GASES AR-41 I CURIES 6.80E-01 8.68E-01 2.79E-01 1.36E-01 XE-135 .1 CURIES 0.00E+00 0.OOE+00 0.OOE+00 1.82E-05 XE-133 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 3.12E-03 XE-131M CURIES 0.OOE+00 0.OOE+00 4.54E-04 0.OOE+00 TOTAL FOR PERIOD CURIES 6.80E-01 I 8.68E-01 I 2.79E-01 I 1.39E-01 IODINES 1-133 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 8.59E-09 1-131 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.99E-08 TOTAL FOR PERIOD CURIES 0.OOE+00 0.OOE+00 0.OOE+00 I 2.85E-08 PARTICULATES SR-89 I CURIES I 0.OOE+00 I 1.02E-07 0.OOE+00 0.OOE+00 I TOTAL FOR PERIOD I CURIES 0.OOE+00 1.02E-07 0.OOE+00 I 0.OOE+00 I H-3 CURIES 1.33E+00 1.44E+00 3.85E-04 6.27E-03 G-ALPHA CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

50

TABLE 2-2B*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting l-Jul-2007 Ending : 31-Dec-2007 CONTINUOUS MODE BATCH MODE I NUCLIDES RELEASED UNIT QUARTER 3 IQUARTER 4 QUARTER 3 IQUARTER 4 1 FISSION GASES AR-41 CURIES 5.27E-01 2.42E-01 2.18E-01 1.46E-01 I XE-135 CURIES 0.OOE+00 0.OOE+00 1.58E-05 0.OOE+00 I XE-133M CURIES 0.00E+00 0.OOE+00 I 0.OOE+00 1 .36E-04 I XE-133 CURIES 0.OOE+00 0.OOE+00 3.18E-04 1.47E-02 I TOTAL FOR PERIOD I CURIES I 5.27E-01 I 2.42E-01 2.19E-01 1.61E-01 I IODINES TOTAL FOR PERIOD I CURIES 0.OOE+00 I 0.OOE+00 0.OOE+00 I 0.OOE+00 I PARTICULATES SR-90 CURIES 0.OOE+00 I 3.73E-09 I 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD CURIES 0.OOE+00 3.73E-09 0.OOE+00 I 0.OOE+00 H-3 CURIES 5.02E+00 2.08E+00 4.22E-02 1.63E-02 G-ALPHA CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

51

TABLE 2-2C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE I NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 FQUARTER,2 I FISSION GASES AR-41 CURIES F 6.80E-01 8.75E-01 6.34E-01 j 7.87E-01 KR-85M CURIES 0.OOE+00 I 0.OOE+00 0.OOE+00 I 2.22E-04 XE-135 CURIES 1.62E-03 1 F 4.63E-04 0.OOE+00 11.82E-05 XE-133 CURIES F 2.13E-03 F 2.19E-03 0.OOE+00 2.45E-02 F XE-131M CURIES F 0.OOE+00 F 0.OOE+00 4.54E-04 I 0.OOE+00 F TOTAL FOR PERIOD F CURIES F 6.84E-01 I 8.77E-01 I 6.34E-01 I 8.11E-01 F

IODINES 1-133 CURIES F 8.85E-05 F 0.OOE+00 0.OOE+00 F 8.59E-09 1-131 CURIES F 7.99E-06 F 0.OOE+00 0.OOE+00 1.99E-08 TOTAL FOR PERIOD I CURIES I 9.65E-05 I 0.OOE+O0 I 0.OOE+00 I 2.85E-08 I PARTICULATES SR-89 CURIES 0.00E+00 1.02E-07 I 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 1.02E-07 I 0.OOE+00 .1 0.OOE+00 H-3 CURIES 2.26E+00 9.35E+00 1 1.19E-01 F 2.13E-01 G-ALPHA CURIES 0.OOE+00 0.OOE+00 I 0.OOE+00 F 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

52

TABLE 2-2C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 1 FISSION GASES AR-41 CURIES 6.12E+00 3.96E+00 1.13E+00 1.46E-01 XE-135 CURIES 1.65E+00 1.58E+00 1.58E-05 0.OOE+00 XE-133M CURIES 0.OOE+00 0.OOE+00 4.63E-05 2.34E-04 XE-133 *CURIES 1.52E+00 6.35E+00 4.96E-03 3.90E-02 XE-131M CURIES 0.OOE+00 0.OOE+00 3.OOE-04 4.06E-04 TOTAL FOR PERIOD I CURIES I 9.29E+00 1.19E+01 1.13E+00 I 1.86E-01 IODINES 1-131 CURIES 4.03E707 I 8.93E-07 0.OOE+00 2.07E-08 TOTAL FOR PERIOD I CURIES 4.03E-07 I 8.93E-07 I 0.OOE+00 I 2.07E-08 I PARTICULATES SR-89 CURIES 1.75E-07 2.90E-09 0.OOE+00 0.OOE+00 CO-60 CURIES 0.00E+00 6.78E-08 0.OOE+00 0.OOE+00 SR-90 CURIES 0.OOE+00 3.81E-09 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.75E-07 7.45E-08 0.OOE+00 I 0.OOE+00 H-3 I CURIES I 1.13E+01 8.61E+00 1.79E-01 1 1.63E-02 G-ALPHA CURIES 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

53

TABLE 2-3A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED I UNIT QUARTER 1 QUARTER 2 QUARTER 1 JQUARTER, 2 FISSION GASES TOTAL FOR PERIOD I CURIES 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 IODINES TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 PARTICULATES TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 0.OOE+00 0.OOE+00 H-3 CURIES l.0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

54

TABLE 2-3A*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 1 Starting l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED UNIT QUARTER 3 QUARTER 4 QUARTER 3 IQUARTER 4 FISSION GASES TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 0.OOE+00 0.OOE+00 IODINES TOTAL FOR PERIOD CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PARTICULATES I CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD CURIES 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 H-3 I CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

55

TABLE 2-3B*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 1 QUARTER 2 IQUARTER 1 JQUARTER 2 I FISSION GASES TOTAL FOR PERIOD CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 I IODINES TOTAL FOR PERIOD CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 I PARTICULATES TOTAL FOR PERIOD CURIES I 0.OOE+00 0.OOE+00 I 0.OOE+00 I 0.OOE+00 H-3 CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

56

TABLE 2=3B*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -2007 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE I NUCLIDES RELEASED UNIT IQUARTER 3 IQUARTER 4 QUARTER 3 IQUARTER 4 FISSION GASES TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 0.OOE+00 1,0.00E+00 I IODINES TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 0.OOE+00 PARTICULATES TOTAL FOR PERIOD I CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 0.OOE+00 H-3 CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

57

TABLE 2-3C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED I UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 QUARTER, 2 FISSION GASES TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 0.OOE+00 I 0.OOE+00 IODINES TOTAL FOR PERIOD CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 PARTICULATES TOTAL FOR PERIOD CURIES 0.OOE+00 0.OOE+00 I 0.OOE+00 I 0.OOE+00 H-3 I CURIES I 0.OOE+00 0.OOE+00 I 0.00E+00 0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

58

TABLE 2-3C*

Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED UNIT QUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 1 FISSION GASES TOTAL FOR PERIOD CURIES 0.OOE+00 0.OOE+00 I 0.OOE+00 0.OOE+00 IODINES TOTAL FOR PERIOD CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PARTICULATES CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD J CURIES I 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typically achieved minimum detectable concentrations.

59

TABLE 2-4A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO NOBLE GASES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 1.13E-04 2.26E-03 2.10E-04 4.19E-03 Beta 10.0 mrad 4.00E-05 4.OOE-04 7.47E-05 7.47E-04 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 3.23E-04 3.23E-03 Beta 20.0 mrad 1.15E-04 5.74E-04 60

TABLE 2-4A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO NOBLE GASES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 2.20E-03 4.39E-02 1.36E-03 2.73E-02 Beta 10.0 mrad 9.24E-04 9.24E-03 7.80E-04 7.80E-03 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 3.88E-03 3.88E-02 Beta 20.0 mrad 1.82E-03 9.09E-03 61

TABLE 2-4B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO NOBLE GASES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 3.05E-04 6.10E-03 3.20E-04 6.39E-03 Beta 10.0 mrad 1.08E-04 1.08E-03 1.13E-04 1.13E-03 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 6.25E-04 6.25E-03 Beta 20.0 mrad 2.21E-04 1.10E-03 62

TABLE 2-4B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO NOBLE GASES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 2.37E-04 4.75E-03 1.24E-04 2.47E-03 Beta 10.0 mrad 8.37E-05 8.37E-04 4.41E-05 4.41E-04 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 9.86E-04 9.86E-03 Beta 20.0 mrad 3.48E-04 1.74E-03, 63

TABLE 2-5A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 6.93E-07 9.25E-06 2.06E-08 2.75E-07 Liver 7.5 mrem 1.45E-04 1.93E-03 1.lIE-03 1.48E-02 TBody 7.5 mrem 1.44E-04 1.93E-03 1.lIE-03 1.48E-02 Thyroid 7.5 mrem 3.21E-04 4.28E-03 1.1lE-03 1.48E-02 Kidney 7.5 mrem 1.45E-04 1.94E-03 1.1lE-03 1.48E-02 Lung 7.5 mrem 1.44E-04 1.92E-03 1.1lE-03 1.48E-02 GILLI 7.5 mrem 1.44E-04 1.92E-03 1.lIE-03 1.48E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 7.14E-07 4.76E-06 Liver 15.0 mrem 1.25E-03 8.35E-03 TBody 15.0 mrem 1.25E-03 8.35E-03 Thyroid 15.0 mrem 1.43E-03 9.53E-03 Kidney. 15.0 mrem 1.25E-03 8.36E-03 Lung 15.0 mrem 1.25E-03 8.35E-03 GILLI 15.0 mrem 1.25E-03 8.35E-03 64

TABLE 2-5A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 7.5 mrem 3.08E-06 4.10E-05 9.26E-07 1.23E-05 Liver 7.5 mrem 8.75E-04 1.17E-02 8.93E-04 1.19E-02 TBody 7.5 mrem 8.75E-04 1.17E-02 8.93E-04 1.19E-02 Thyroid 7.5 mrem 8.82E-04 1.18E-02 9.09E-04 1.21E-02 Kidney 7.5 mrem 8..75E-04 1.17E-02 8.93E-04 1.19E-02 Lung 7.5 mrem 8.75E-04 1.17E-02 8.93E-04 1.19E-02 GILLI 7.5 mrem 8.75E-04 1.17E-02 8.93E-04 1.19E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 4.72E-06 3.15E-05 Liver 15.0 mrem 3.02E-03 2.01E-02 TBody 15.0 mrem 3.02E-03 2.01E-02 Thyroid 15.0 mrem 3.22E-03 2.15E-02 Kidney 15.0 mrem 3.02E-03 2.01E-02 Lung 15.0 mrem 3.02E-03 2.01E-02 GILLI 15.0 mrem 3.02E-03 2.01E-02 65

TABLE 2-5B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 1.25E-12 1.66E-11 1.67E-06 2.22E-05 Liver 7.5 mrem 1.82E-04 2.42E-03 1.98E-04 2.64E-03 TBody 7.5 mrem 1.82E-04 2.42E-03 1.98E-04 2.64E-03 Thyroid 7.5 mrem 1.82E-04 2.42E-03 1.98E-04 2.64E-03 Kidney 7.5 mrem 1.82E-04 2.42E-03 1.98E-04 2.64E-03 Lung 7.5 mrem 1.82E-04 2.42E-03 1.98E-04 2.64E-03 GILLI 7.5 mrem 1.82E-04 2.42E-03 1.98E-04 2.64E-03 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 1.67E-06 1.11E-05 Liver 15.0 mrem 3.80E-04 2.53E-03 TBody 15.0 mrem 3.80E-04 2.53E-03 Thyroid 15.0 mrem 3.80E-04 2.53E-03 Kidney 15.0 mrem 3.80E-04 2.53E-03 Lung 15.0 mrem 3.80E-04 2.53E-03 GILLI 15.0 mrem 3.80E-04 2.53E-03 66

TABLE 2-5B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 7.5 mrem 6.68E-08 8.90E-07, 7.16E-06 9.54E-05 Liver 7.5 mrem 6.91E-04 9.21E-03 2.86E-04 3.81E-03 TBody 7.5 mrem 6.91E-04 9.21E-03 2.87E-04 3.83E-03 Thyroid 7.5 mrem 6.91E-04 9.21E-03 2.86E-04 3.81E-03 Kidney 7.5 mrem 6.91E-04 9.21E-03 2.86E-04 3.81E-03 Lung 7.5 mrem 6.91E-04 9.21E-03 2.86E-04 3.81E-03 GILLI 7.5 mrem 6.91E-04 9.21E-03 2.86E-04 3.81E-03 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 8.89E-06 5.93E-05 Liver 15.0 mrem 1.36E-03 9.04E-03 TBody 15.0 mrem 1.36E-03 9.05E-03 Thyroid 15.0 mrem 1.36E-03 9.04E-03 Kidney 15.0 mrem 1.36E-03 9.04E-03 Lung 15.0 mrem 1.36E-03 9.04E-03 GILLI 15.0 mrem 1.36E-03 9.04E-03 67

TABLE 2-6 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS EFFLUENT ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

Nuclide MDC(uCi/ML)

MN-54 3.21E-15 CO-58 1.53E-14 FE-59 7.96E-15 CO-60 1.95E-14 ZN-65 2.34E-14 MO-99 1.81E-13 CS-134 1.41E-14 CS-137 7.83E-15 CE-141 6.96E-15 CE-144 3.47E-14 KR-87 8.18E-07 KR-88 3.94E-08 XE-133 4.30E-08 XE-133M 4.82E-08 XE-135 1.78E-08 XE-138 1.99E-07 1-131 9.67E-15 1-133 1.80E-13 68

TABLE 2-7A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 1 Starting l-Jan-2007 Ending : 30-Jun-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 70 TOTAL TIME PERIOD FOR BATCH RELEASES 10502.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 507.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 150.03 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 37.00 MINUTES 69

TABLE 2-7A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 1 Starting : l-Jul-2007 Ending : 31-DecZ2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 55 TOTAL TIME PERIOD FOR BATCH RELEASES 15308.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 2614.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 278.33 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 78.00 MINUTES 70

TABLE 2-7P Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 55 TOTAL TIME PERIOD FOR BATCH RELEASES : 10456.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 662.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 190.11 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 49.00 MINUTES 71

TABLE 2-7B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 45 TOTAL TIME PERIOD FOR BATCH RELEASES 7024.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 630.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 156.09 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 57.00 MINUTES 72

TABLE 2-8A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 GASEOUS RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM 'TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.OOE+00 CURIES 73

TABLE,2-8A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary.

Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 GASEOUS RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIES 74

TABLE 2-8B Joseph M. Farley Nuclear Plant.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 GASEOUS RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE : 0.00 MINUTES AVERAGE TIME FOR A RELEASE : 0.00 MINUTES MINIMUM TIME FOR A RELEASE : 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.00E+00 CURIES 75

TABLE 2-8B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 GASEOUS RELEASES NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE : 0.00 MINUTES AVERAGE TIME FOR A RELEASE : 0.00 MINUTES MINIMUM TIME FOR A RELEASE : 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.00E+00 CURIES 76

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

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

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

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

77

TABLE 3-i Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-2007 Ending: 30-Jun-2007 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

1. Type of Waste. UNITS 6-Months 3

a. Spent resins, Filter sludges, m 3.143E+00 evaporator bottoms, etc. Ci* 3.010E+02 3

b. Dry compressible waste, contaminated m 3.285E+01 equipment, etc. Ci* 3.700E-01 3

c. Irradiated components, control m None rods, etc. Ci* None 3

d. Other (describe) m None Ci* None

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

a. NI-63 27.9%

ZN-65 24.0%

FE-55 23.3%

CO-60 20.4%

b. H-3 21.4%

FE-55 19.4%

ZN-65 17.0%

CO-60 11.0%

CO-58 7.3%

NI-63 7.1%

ZR-95 5.2%

NB-95 4.7%

CR-51 1.8%

C-14 1.2%

BE-7 1.1%

Measured and/or estimated by correlations in accordance with 10CFR61.55.

78

TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-2007 Ending: 30-Jun-2007 (continued)

3. Solid Waste Disposition Number of Shipments Mode of Trans portation Destination 8 Highwaay Envirocare of Utah 9 Highwa3y Barnwell, SC 17 Rail Envirocare of Utah

4. Type of Containers (Shipped offsite for burial/processing)

Container Type of Number Container 3 Description Container of Volume (m Containers

a. RADLOC 500 General Design 3 3.850E+00 Package CNS 8-120 High Integrity 3 3.410E+00 Container 55 Gallon General Design 8 2.120E-01 Drum Package

b. 20' Sealand General Design 18 2.945E+01 Package

5. Solidification Agent

a. None

b. None B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A 79

TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jul-2007 Ending: 31-Dec-2007 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

1. Type of Waste. UNITS 6-Months 3

a. Spent resins, Filter sludges, m 2.220E+00 evaporator bottoms, etc. Ci* 5.260E+01 3

b. Dry compressible waste, contaminated m 7.844E+01 equipment, etc. Ci* 9.390E-01 3

c. Irradiated components, control m 0.OOOE+00 rods, etc. Ci* 0.OOOE+00 3

d. Other (describe) m None Ci* None

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

a. CO-60 29.2%

ZN-65 25.5%

NI-63 18.3%

C-14 8.5%

H-3 3.3%

FE-55 2.8%

MN-54 2.5%

CS-137 2.3%

CO-58 2.1%

ZR-95 1.2%

b. FE-55 19.8%

H-3 18.5%

ZN-65 17.5%

CO-60 10.3%

NI-63 7.1%

CO-58 6.8%

ZR-95 6.6%

NB-95 6.4%

CR-51 2.0%

BE-7 1.7%

Measured and/or estimated by correlations in accordance with I0CFR61.55.

80

TABLE 3-1 Joseph M. Farley Niuclar Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jul-2007 Ending: 31-Dec-2007 (continued)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 9 Highway Envirocare of Utah 18 Rail Envirocare of Utah

4. Type of Containers (Shipped offsite for burial/processing)

Container Type of Number Container 3 Description Container of Volume (m Containers

a. 55 Gallon General Design 14 2.120E-01 Drum Package CNS 8-120 High Integrity 2 3.410E+00 Container LSA BOX(METAL) General Design 1 2.590E+00 Package

b. 20' Sealand General Design 10 2.945E+01 Package 55 Gallon General Design 2 2.120E-01 Drum Package LSA BOX(METAL) General Design 10 2.590E+00 Package 81

TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jul-2007 Ending: 31-Dec-2007 (continued)

.5. Solidification Agent

a. None

b. None B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A 82

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

4.2 Demonstration of Compliance However, this assessment has been performed for 2007 using the methods described in ODCM 6.2 and is included in this section as Table 4-1.

83

TABLE 4-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page: 1 Location Name VISITOR LOCATION 1 (VIS.CENTER)

Distance (kilometers) 3.06E-01 Sector WSW Occupancy Factor 1.37E-03 (1.20E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1. 04E-04 Particulate X/Q (sec/m3) 1. 04E-04 Particulate D/Q (m-2) 4. 80E-07 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 8. 80E-06 Particulate X/Q (sec/m3) 8. 80E-06 Particulate D/Q (m-2) 6.20E-08 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 4.44E-06 5.62E-06 1.01E-05 1.01E-05 Liver mrem 5.52E-06 9.79E-06 1.53E-05 1.53E-05 TBody mrem 5.52E-06 9.79E-06 1.53E-05 1.53E-05 Thyroid mrem 5.70E-06 9.79E-06 1.55E-05 1.55E-05 Kidney mrem 5.52E-06 9.79E-06 1.53E-05 1.53E-05 Lung mrem 5.52E-06 9.79E-06 1.53E-05 1.53E-05 GI-LLI mrem 5.52E-06 9.79E-06 1.53E-05 1.53E-05 84

TABLE 4-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page: 2 Location Name VISITOR LOCATION 2 (SW POND)

Distance (kilometers) 9.66E-01 Sector SSW Occupancy Factor 7.53E-03 (6.60E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 4.74E-05 Particulate X/Q (sec/m3) 4.74E-05 Particulate D/Q (m-2) 1.31E-07 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 9.75E-07 Particulate X/Q (sec/m3) 9.75E-07 Particulate D/Q (m-2) 2.78E-08 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 2.71E-06 3.42E-06 6.13E-06 6.13E-06 Liver mrem 3.36E-06 5.96E-06 9.32E-06 9.32E-06 TBody mrem 3.36E-06 5.96E-06 9.32E-06 9.32E-06 Thyroid mrem 3.47E-06 5.96E-06 9.43E-06 9.43E-06 Kidney mrem 3.36E-06 5.96E-06 9.32E-06 9.32E-06 Lung mrem 3.36E-06 5.96E-06 9.32E-06 9.32E-06 GI-LLI mrem 3.36E-06 5.96E-06 9.32E-06 9.32E-06 85

TABLE 4-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Page: 3 Location Name VISITOR LOCATION 3 (RW DISCH.)

Distance (kilometers) 1.64E+00 Sector SE Occupancy Factor 1.14E-02 (9.99E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.63E-05 Particulate X/Q (sec/m3) 1.63E-05 Particulate D/Q (m-2) 4.55E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.05E-07 Particulate X/Q (sec/m3) 7.05E-07 Particulate D/Q (m-2) 1.39E-08 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 2.96E-06 3.75E-06 6.71E-06 6.71E-06 Liver mrem 3.68E-06 6.53E-06 1.02E-05 1.02E-05 TBody mrem 3.68E-06 6.53E-06 1.02E-05 1.02E-05 Thyroid mrem 3.80E-06 6.53E-06 1.03E-05 1.03E-05 Kidney mrem 3.68E-06 6.53E-06 1.02E-05 1.02E-05 Lung mrem 3.68E-06 6.53E-06 1.02E-05 1.02E-05 GI-LLI mrem 3.68E-06 6.53E-06 1.02E-05 1.02E-05 86

TABBLE 4'4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page:

Location Name VISITOR LOCATION 1 (VIS.CENTER)

Distance (kilometers) 3.06E-01 Sector WSW Occupancy Factor 1.37E-03 (1.20E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.04E-04 Particulate X/Q (sec/m3) 1.04E-04 Particulate D/Q (m-2) 4.80E-07 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 8.80E-06 Particulate X/Q (sec/m3) 8.80E-06 Particulate D/Q (m-2) 6.20E-08 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem .2.59E-05 1.56E-05 4.15E-05 5.16E-05 Liver mrem 3.08E-05 1.92E-05 5.OOE-05 6.53E-05 TBody mrem 3.08E-05 1.92E-05 5.OOE-05 6.53E-05 Thyroid mrem 3.08E-05 1.92E-05 5.OOE-05 6.55EL05 Kidney mrem 3.08E-05 1.92E-05 5.OOE-05 6.53E-05 Lung mrem 3.08E-05 1.92E-05 5.OOE-05 6.53E-05 GI-LLI mrem 3.08E-05 1.92E-05 5.OOE-05 6.53E-05 87

TABLE 4-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page: 2 Location Name VISITOR LOCATION 2 (SW POND)

Distance (kilometers) 9.66E-01 Sector SSW Occupancy Factor 7.53E-03 (6.60E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 4.74E-05 Particulate X/Q (sec/m3) 4.74E-05 Particulate D/Q (m-2) 1.31E-07 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 9.75E-07 Particulate X/Q (sec/m3) 9.75E-07 Particulate D/Q (m-2) 2.78E-08 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Year to 3 'and 4 Ending Date Bone mrem 1.58E-05 9.52E-06 2.53E-05 3.14E-05 Liver mrem 1.87E-05 1.17E-05 3.04E-05 3.98E-05 TBody mrem 1.87E-05 1.17E-05 3.04E-05 3.98E-05 Thyroid mrem 1.87E-05 1.17E-05 3.04E-05 3.99E-05 Kidney mrem 1.87E-05 1.17E-05 3.04E-05 3.98E-05 Lung mrem 1.87E-05 1.17E-05 3.04E-05 3.98E-05 GI-LLI mrem 1.87E-05 1.17E-05 3.04E-05 3.98E-05 88

TABLE 4-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Page: 3 Location Name VISITOR LOCATION 3 (RW DISCH.)

Distance (kilometers) 1.64E+00 Sector SE Occupancy Factor 1.14E-02 (9.99E+01 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.63E-05 Particulate X/Q (sec/m3) 1.63E-05 Particulate D/Q (m-2) 4.55E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.05E-07 Particulate X/Q .(sec/m3) 7.05E-07 Particulate D/Q (m-2) 1.39E-08 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 1.73E-05 1.04E-05 2.77E-05 3.44E-05 Liver mrem 2.05E-05 1.28E-05 3.33E-05 4.35E-05 TBody mrem 2.05E-05 1.28E-05 3.33E-05 4.35E-05 Thyroid mrem 2.05E-05 1.28E-05 3.33E-05 4.36E-05 Kidney mrem 2.05E-05 1.28E-05 3.33E-05 4.35E-05 Lung mrem 2.05E-05 1.28E-05 3.33E-05 4.35E-05 GI-LLI mrem 2.05E-05 1.28E-05 3.33E-05 4.35E-05 89

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

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

5.2 Demonstration of Compliance Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded during 2007, no calculations were required.

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

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

7.1.2 Description of Deviations There were no deviations during 2007.

90

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

7.2.2 Description of Deviations There were no deviations during 2007.

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

7.3.2 Description of Deviations There was one deviation from liquid effluent sampling requirements during 2007. Unit 2 had a deviation on October 29, 2007, when the autosampler for Turbine Building Sump 2B failed to collect a sample for the day. Details of this event are documented in condition report 2007110944.

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

8.2 Description of Changes There were no revisions to the ODCM during 2007.

91

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

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

9.2 Description of Major Changes There were no major changes during 2007..

92

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2007 Enclosure 3 Vogtle Annual Radioactive Effluent Release Report for 2007

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERA TING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 ANNUAL RADIOACTIVE EFFLUENTRELEASE REPORT FOR JANUARY 12007 TO DECEMBER 31,2007 Page 1 of 82

IVOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Requirements 8 1.1.1 Concentration Limits 8 1.1.2 Dose Limits .8 1.2 Effluent Concentration Limit 8 1.3 Measurement and Approximations of Total 9 Radioactivity 1.3.11 Total Radioactivity Determination 9 1.3.2 Total Error Estimation 11 1.4 Liquid Effluent Release Data 12 1.5 Radiological Impact Due to Liquid Releases 12 1.6 Liquid Effluents - Batch Releases 12 1.7 Liquid Effluents - Abnormal Releases 12 2.0 Gaseous Effluents 34 2.1 Regulatory Requirements 34 2.1.1 Dose Rate Limits 34 Page 2 of 82

SECTION TITLE 'PAGE 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 34 2.1.3 Doses to a Member of the Public 34 2.2 Measurements and Approximation of Total 35 Radioactivity 2.2.1 Sample Collection and Analysis 35 2.2.2 Total Quantitiesof Radioactivity, Dose Rates and 36 Cumulative Doses 2.2.2.1 Fissionand Activation Gases 36

.2.2.2.2 Radioiodines, Tritium, and ParticulateReleases 36 2.2.2.3 Gross Alpha Release 36 2.2.3 Total ErrorEstimation 37 2.3 Gaseous Effluent Release Data 38 2.4 RadiologicalImpact Due to Gaseous Releases 39 2.5 Gaseous Effluents - Batch Releases 39 2.6 Gaseous Effluents - Abnormal Releases 39 3.0 Solid Waste 71 3.1 Regulatory Requirements 71 3.1.1 Solid Radioactive Waste System 71 3.1.2 Reporting Requirements 71 3.2 Solid Waste Data 71 Page 3 of 82

SECTION TITLE PAGE 4.0 Doses to Members of the Public Inside the Site 76 Boundary 4.1 Regulatory Requirements 76 4.2 Demonstrationof Compliance 76 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 79 5.1 Regulatory Requirements 79 5.2 Demonstrationof Compliance 79 6.0 MeteorologicalData 79 7.0 ProgramDeviations 79 7.1 InoperableLiquid or Gaseous Effluent Monitoring 79 Instrumentation 7.1.1 Regulatory Requirement 79 7.1.2 Descriptionof Deviations 80 7.2 Tanks Exceeding Curie Content Limits 81 7.2.1 Regulatory Requirements 81 7.2.2 Descriptionof Deviations 81 8.0 Changes to the Vogtle Electric GeneratingPlant 81 Offsite Dose CalculationManual (ODCM) 8.1 Regulatory Requirement 81 8.2 Descriptionof Changes 81 9.0 Major Changes to the Liquid, Gaseous, or Solid 82 Radwaste Treatment System 9.1 Regulatory Requirements 82 9.2 Descriptionof Major Changes 82 Page 4 of 82

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT- 2007 TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases Unit 1 13 (Quarters 1, 2, 3, and 4) 1-1B Liquid Effluents - Summation of All Releases Unit 2 15 (Quarters 1, 2, 3, and 4) 1-1C Liquid Effluents - Summation of All Releases Site 17 (Quarters 1, 2, 3, and 4) 1-2A Liquid Effluents - Unit 1 (Quarters 1, 2,. 3, and 4) 19 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3, and 4) 21 1-2C Liquid Effluents - Site (Quarters 1, 2, 3, and 4) 23 1-3A Doses to a Member of the PublicDue to Liquid 25 Releases Unit 1 (Quarters 1, 2, 3, and 4) 1-3B Doses to a Member of the PublicDue to Liquid 27 Releases Unit 2 (Quarters 1, 2, 3, and 4) 1-4 Minimum Detectable ConcentrationLiquid Sample 29 Analysis 1-5A Liquid Effluents - Batch Release Summary Unit 1 30 1-5B Liquid Effluents - Batch Release Summary Unit 2 31 1-6A Liquid Effluents - Abnormal Release Summary Unit 1 32 Page 5 of 82

TABLE LIST OF TABLES PAGE 1-6B Liquid Effluents - Abnormal Release Summary Unit 2 33 2-1A Gaseous Effluents - Summation of All Releases - 40 Unit 1 (Quarters 1, 2, 3, and 4) 2-1B Gaseous Effluents - Summation of All Releases - 42 Unit 2 (Quarters 1, 2, 3, and 4) 2-1C Gaseous Effluents - Summation of All Releases - 44 Site (Quarters 1, 2, 3, and 4) 2-2A Gaseous Effluents - Mixed Mode Releases Unit 1 46 (Quarters 1, 2, 3, and 4) 2-2B Gaseous Effluents - Mixed Mode Releases Unit 2 48 (Quarters 1, 2, 3, and 4) 2-2C Gaseous Effluents - Mixed Mode Releases Site 50 (Quarters 1, 2, 3, and 4) 2-3A Gaseous Effluents - Ground Level Releases Unit 1 52 (Quarters 1, 2, 3, and 4) 2-3B Gaseous Effluents - Ground Level Releases Unit 2 54 (Quarters 1, 2, 3, and 4) 2-3C Gaseous Effluents - Ground Level Releases Site 56 (Quarters 1, 2, 3, and 4) 2-4A Air Doses Due to Noble Gases in Gaseous Releases 58 Unit 1 (Quarters 1, 2, 3, and 4) 2-4B Air Doses Due to Noble Gases in Gaseous Releases 60 Unit 2 (Quarters 1, 2, 3, and 4) 2-5A Doses to a Member of the Public Due to Radioiodines, 62 Tritium, and Particulatesin Gaseous Releases Unit 1 (Quarters 1, 2, 3, and 4)

Page 6 of 82

TABLE LIST OF TABLES PAGE 2-5B Doses to a Member of the Public Due to Radioiodines, 64 Tritium, and Particulatesin Gaseous Releases Unit 2 (Quarters 1, 2, 3, and 4) 2-6 Minimum Detectable Concentration- GaseousSample 66 Analysis 2-7A Gaseous Effluents - Batch Release Summary Unit 1 67 2-7B Gaseous Effluents - Batch Release Summary Unit 2 68 2-8A Gaseous Effluents - Abnormal Release Summary 69 Unit 1 2-8B Gaseous Effluents - Abnormal Release Summary 70 Unit 2 3-1 Solid Waste and IrradiatedFuel Shipments 72 4-1 Doses to a Member of the Public Due to Activities 78 Inside the Site Boundary Page 7 of 82

1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration Limits In accordance with Technical Specification 5.5.4.b, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 E-04 gCi/ml total activity.

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

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

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

1.2 Effluent Concentration Limit (ECL)

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

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

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

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

Page 8 of 82

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

MEASUREMENT FREQUENCY METHOD

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

2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gases with computerized data reduction

3. Tritium Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting Page 9 of 82

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

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

ECL fraction is determined using radionuclide concentrations of a tank planned for release, the most current results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55 and the corresponding ECL values.

This ECL fraction is used, with appropriate safety factors, tolerance factors, and the minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) are not exceeded.

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

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

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

Page 10 of 82

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

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

Sampling and statistical error 10%

Counting Equipment Calibration 10%

Tank Volumes and System Flow Rates 20%

TOTAL ERROR 24.5%

b. Total Tritium release was calculated from sample analysis results and release point volumes.

Sampling and statistical errors. 10%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 24.5%

C. Dissolved and entrained gases were calculated from sample analysis results and release point volumes.

Sampling and statistical error 20%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 30%

d. Gross alpha radioactivity was calculated from sample analysis results and release point volumes.

Sampling and statistical error 10%

Counting Equipment calibration 10%

Tank volumes and system flowrates 20%

TOTAL ERROR 24.5%

Page 11 of 82

1.3.2 Total Error Estimation cont'd

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

Level Indicator error 10%

Operator Interpretation of gauge 10%

TOTAL ERROR 14%

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

Flow totalizer error 10%

Operator interpretation of gauge 10%

TOTAL ERROR 14%

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

Compositing sample error 5%

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

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

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

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

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

Page 12 of 82

TABLE 1-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.49E-02 9.72E-03 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.28E-08 7.89E-08

3. PERCENT OF APPLICABLE LIMIT % *

B. TRITIUM

1. TOTAL RELEASE CURIES 2.70E+02 2.87E+01 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.96E-04 2.33E-04

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 5.78E-04 0.OOE+00 30

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.28E-09 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 25 E. WASTE VOL RELEASED(PRE2DILUTION) LITERS 9.71E+05 3.02E+05 14 F. VOLUME OF DILUTION WATER USED LITERS 4.52E+08 1.23E+08 14 Applicable limits are expressed in terms of dose.

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

Page 13 of 82

TABLE 1-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 1 Starting l-Jul-2007 Ending : 31-Dec-2007 TYPE OF .EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 8.59E-03 3.44E-03 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.22E-08 1.59E-08

3. PERCENT OF APPLICABLE LIMIT %*

B. TRITIUM

1. TOTAL RELEASE CURIES 8.56E+01 1.03E+02 24.5 2t AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.21E-04 4.75E-04

3. PERCENT OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 0.OOE+00 1.38E-0S 30

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 0.OOE+00 6.38E-11

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 25 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 5.18E+05 3.38E+05 14 F. VOLUME OF DILUTION WATER USED LITERS 2.67E+08 2.16E+08 14 Applicable limits are expressed in terms of dose.

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

Page 14 of 82

TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.13E-02 6.50E-03 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.37E-08 4.33E-08

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 1.77E+02 5.83E+01 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.28E-04 3.88E-04

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 2.64E-04 0.OOE+00 30

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.87E-10 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT %*

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 25 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 7.42E+05 3.93E+05 14 F. VOLUME OF DILUTION WATER USED LITERS 3.35E+08 1.50E+08 14 Applicable limits are expressed in terms of dose.

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

Page 15 of 82

TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 6.15E-04 3.46E-04 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.69E-08 8.57E-09

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 1.02E+01 2.38E+01 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.81E-04 5.91E-04

3. PERCENT OF.APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 0.OOE+00 3.10E-06 30

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 0.OOE+00 7.69E-11

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 25 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 9.15E+04 7.75E+04 14 F. VOLUME OF DILUTION WATER USED LITERS 3.63E+07 4.03E+07 14 Applicable limits are expressed in terms of dose.

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

Page 16 of 82

TABLE 1-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR%

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 2.62E-02 1.62E-02 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.32E-08 5.93E-08

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 4.47E+02 8.70E+01 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.67E-04 3.18E-04

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 8.42E-04 0.OOE+00 30

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.07E-09 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 25 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 1.71E+06 6.95E+05 14 F. VOLUME OF DILUTION WATER USED LITERS 7.87E+08 2.73E+08 14 Applicable limits are expressed in terms of dose.

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

Page 17 of 82

TABLE 1-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Summation of All Releases Unit: Site Starting : l-Jul-2007 Ending-: 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 9.20E-03 3.78E-03 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.03E-08 1.47E-08

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 9.58E+01 1.27E+02 24.5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.16E-04 4.93E-04

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

.1. TOTAL RELEASE CURIES 0.OOE+00 1.69E-05 30

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 0.OOE+00 6.58E-11

3. PERCENT OF APPLICABLE LIMIT. %

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 25 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 6.09E+05 4.16E+05 14 F. VOLUME OF DILUTION WATER USED LITERS 3.03E+08 2.57E+08 14 Applicable limits are expressed in terms of dose.

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

Page 18 of 82

TABLE 1-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE NUCLIDE I UNIT 1QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 I CURIES I 0.OOE+00 0.00E+00 I 2.70E+02 2.87E+01 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0.OOE+00 0.OOE+00 7.87E-06 0.OOE+00 CO-58 CURIES 0.OE+00 0.OOE+00 1.17E-03 6.34E-04 CO-60 CURIES 0.OOE+00 0.OOE+00 2.21E-03 1.64E-03 CR-51 CURIES 0.OE+00 0.OOE+00 1.17E-04 0.OOE+00 CS-134 CURIES 0.OE+00 0.OOE+00 0.OOE+00 3.41E-05 CS-137 CURIES 0.OE+00 0.OOE÷00 5.56E-05 3.89E-04 FE-55 CURIES 0.OOE+00 0.OOE+00 4.44E-03 5.98E-03 MN-54 CURIES 0.OOE+00 0.OOE+00 2.28E-04 1.13E-04 NB-95 CURIES 0.OOE+00 0.OOE+00 9.52E-05 1.15E-05 SB-125 CURIES 0.OOE+00 I 0.OOE+00 2.19E-03 I 9.10E-04 SR-89 CURIES 0.OE+00 0.OOE+00 6.82E-13 S.23E-06 TE-125M CURIES. 0.OOE+00 0.OOE+00 4.33E-03 0.OOE+00 ZR-95 CURIES 0.OE+00 0.OOE+00 3.86E-05 0.OOE+00 TOTALS I CURIES I 0.OOE+00 I 0.o0E+00 I 1.49E-02 9.72E-03 I DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 0.OOE+00 5.74E-04 0..OOE+00 XE-135 I CURIES 0.OOE+00 0.OOE+00 3.28E-06 0.OOE+00 TOTALS CURIES 0.OOE+00 1 0.OOE+00 5.78E-04 I 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 Page 19 of 82

TABLE 1-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 ICONTINUOUS MODE i BATCH MODE I NUCLIDE I UNIT 1QUARTER 3 1QUARTER 4 1QUARTER 3 JQUARTER 4 1 H-3 CURIES 0.00E+00 I 0.OOE+00 8.56E+01 I 1.03E+02 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0. 00E+00 0. OOE+00 3 .52E-06 0. OOE+00 CO-58 CURIES 0 00E+00 0. OOE+00 8. 81E-04 3.06EL05 CO-60 CURIES 0 00E+00 0. OOE+00 2. 05E-03 2.71E-04 CS-134 CURIES 0 00E+00 0. OOE+00 3. 08E-06 2.61E-05 CS-137 CURIES 0 00E+00 0 OOE+00 1. 69E-04 2.42E-04 FE-55 CURIES 0 00E+00 0 OOE+00 3. 94E-03 1. 07E-03 1-133 CURIES 0 00E+00 0 OOE+00 0. OOE+00 9. 12E-07 MN-54 CURIES 0 00E+00 0 OOE+00 1 .23E-04 1.19E-05 NB-95 CURIES 0 OOE+00 0 OOE+00 1 .21E-05 0. OOE+00 SB-125 CURIES 0 00E+00 0 OOE+00 1. 39E-03 1. 79E-03 SR-89 CURIES 0 OOE+00 0 00E+00 1. 14E-13 7.11E-15 SR-90 CURIES 0 OOE+00 0 OOE+00 7. lIE-14 1.14E-13 ZR-95 CURIES 0 OOE+00 0 00E+00 4 .49E-06 0 . OOE+00 TOTALS I CURIES 0.OOE+00 0.00E+00 8.59E-03 I 3.44E-03 I DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 1.38E-05 I TOTALS CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 1.38E-05 I Zeroes in this table indicate that no radioactivity was present at detectable levels.* See Table 1-4 for typical minimum detectable concentrations.

Page 20 of 82

TABLE 1-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE BATCH MODE NUCLIDE UNIT 1QUARTER 1 1QUARTER 2 IQUARTER 1 1QUARTER 2 H-3 CURIES 0.00E+00 I 0.OOE+00 I 1.77E+02 I 5.83E+01 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0 OOE+00 0. OOE+00 0 . OOE+00 4. 12E-06 CO-58 CURIES 0 OOE+00 0. OOE+00 7. 68E-04 2 17E-03 CO-60 CURIES 0 OOE+00 0. OOE+00 8. 84E-04 1. 5E-03 I.

CR-51 CURIES 0 OOE+00 0 ..OOE+00 5. 03E-05 3. 52E-04 CS-134 CURIES 0 OOE+00 0 OOE+00 2. 69E-06 0 OOE+00 I.

CS-137 CURIES 0 OOE+00 0 OOE+00 3. 38E-05 0 OOE+00 FE-55 CURIES 0 OOE+00 0 OOE+00 2. 70E-03 1. 58E-03 MN-54 CURIES 0 OOE+00 0 OOE+00 3.42E-05 8.44E-05 NB-95 CURIES 0 OOE+00 0 OOE+00 1.24E-05 1. 17E-04 NB-97 CURIES 0 OOE+00 0 OOE+00 1.40E-06 0 OOE+00 SB-124 CURIES 0 00E-s00 0 OOE+00 7. 39E-06 0 OOE+00 SB-125 CURIES 0 OOE+00 0 OOE+00 2. 61E-03 9. 72E-04 SR-89 CURIES 0 OOE+00 0 OOE+00 0. OOE+00 9. 09E-13 SR-90 CURIES 0 OOE+00 0 OOE+00 0. OOE+00 8. 53E-14 TE-125M CURIES 0 OOE+00 0 OOE+00 4.21E-03 0 OOE+00 ZR-95 CURIES 0 OOE+00 0 OOE+00 0. OOE+00 6 .42E-05 TOTALS I CURIES I 0.OOE+00 I 0.OOE+00 I 1.13E-02 I 6.S0E-03 I DISSOLVED AND ENTRAINED GASES XE-133 I CURIES I0.OOE+0 0 .OOE+00 I 2.64E-04 I 0.OOE+00 I TOTALS I CURIES I 0.OOE+00 I 0.OOE+00 I 2.64E-04 I 0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page21 of 82

TABLE 1-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT 1QUARTER 3 1QUARTER 4 IQUARTER 3 QUARTER 4 1 H-3 I CURIES 0.OOE+00 0.OOE+00 1.02E+01 I 2.38E+01 FISSION & ACTIVATION PRODUCTS CO-58 CURIES 0.OOE+00 0.OOE+00 2.83E-05 6.42E-06 CO-60 CURIES 0.OOE+00 0.OOE+00 9.19E-05 2.28E-05 CS-134 CURIES 0.OOE+00 0.OOE+00 0.OE+00 3.26E-06 CS-137 CURIES 0.OOE+00 0.OOE+00 6.26E-06 4.52E-05 FE-55 CURIES 0.OOE+00 0.OOE+00 3.27E-04 5.29E-05 SB-125 CURIES 0.OOE+00 0.OOE+00 i .62E-04 2.15E-04 TOTALS I CURIES I 0.OOE+00 0.OOE+00 I 6.15E-04 I 3.46E-04 I DISSOLVED AND ENTRAINED GASES XE-133 I CURIES I O.OOE+00.1 0.OOE+00 I 0.OOE+00 3.10E-06 I TOTALS I CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 3.10E-06 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 22 of 82

TABLE 1-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 CONTINUOUS MODE BATCH MODE NUCLIDE I UNIT. QUARTER 1 1QUARTER 2 QUARTER 1 QUARTER 2 H-3 I CURIES 0.OOE+00 I 0.OOE+00 4.47E+02 8.70E+01 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0. OOE+00 0 OOE+00 7. 87E-06 4.12E-06 CO-58 CURIES 0. OOE+00 0 OOE+00 1.94E-03 2. 81E-03 CO-60 CURIES 0. OOE+00 0 OOE+00 3.,09E-03 2.79E-03 CR-51 CURIES 0 .OOE+00 0 OOE+00 1.68E-04 3.52E-04 CS-134 CURIES 0 .OOE+00 0 OOE+00 2. 69E-06 3.41E-05 CS-137 CURIES 0 .OOE+00 0 OOE+00 8. 94E-05 3. 89E-04 FE-55 CURIES 0 .OOE+00 0 OOE+00 7. 14E-03 7. 56E-03 MN-54 CURIES 0. OOE+00 0 OOE+00 2 63E-04 1.97E-04 NB-95 CURIES 0 OOE+00 0 OOE+00 1. 08E-04 1.28E-04 NB-97 CURIES 0 OOE+00 0 OOE+00 1 .40E-06 0. OOE+00 SB-124 CURIES 0 OOE+00 0 OOE+00 7. 39E-06 0. OOE+00 SB-125 CURIES 0 OOE+00 0.. OOE+00 4. 79E-03 1. 88E-03 SR-89 CURIES 0 OOE+00 0. OOE+00 6. 82E-13 5.23E-06 SR-90 CURIES 0 OOE+00 0. OOE+00 0 OOE+00 -8.53E-14 TE-125M CURIES 0 OOE+00 0 .OOE+00 8. 53E-03 0 . OOE+00 ZR-95 CURIES 0 OOE+00 0 .OOE+00 3. 86E-05 6.42E-05 TOTALS I CURIES 0.OOE+00 I 0.OOE+00 I 2.62E-02 1.62E-02 DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 0.OOE+00 8.39E-04 0.OOE+00 XE-135 CURIES 0.OOE+00 0.OOE+00 I 3.28E-06 0.OOE+00 TOTALS I CURIES 0.OOE+00 0.OOE+00 I 8.42E-04 I 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.

Page 23 of 82

TABLE 1-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT QUARTER 3 ]QUARTER 4 QUARTER 3 1QUARTER 4 H-3 I CURIES 0.OOE+00 0.OOE+00 9.58E+01 1.27E+02 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0. 00E+00 0 .OOE+00 3.52E-06 0. OOE+00 CO-58 CURIES 0 .OOE+00 0 .OOE+00 9. 09E-04 3. 71E-05 CO-60 CURIES 0 .OOE+00 0 .OOE+00 2. 15E-03 2. 94E-04 CS-134 CURIES 0. 00E+00 0 .OOE+00 3.08E-06 2.94E-05 CS-137 CURIES 0. OOE+00 0. OOE+00 1.,75E-04 2.87E-04 FE-55 CURIES 0. OOE+00 0. OOE+00 4.27E-03 1.12E-03 1-133 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 9. 12E-07 MN-54 CURIES 0. OOE+00 0. OOE+00 1.23E-04 1. 19E-05 NB-95 CURIES 0. OOE+00 0. OOE+00 1.21E-05 0. OOE+00 SB-125 CURIES 0. OOE+00 0. OOE+00 1. 56E-03 2. OOE-03 SR-89 CURIES 0. OOE+00 0. OOE+00 1.14E-13 7. 11E-15 SR-90 CURIES 0. OOE+00 0. OOE+00 7. 11E-14 1. 14E-13 ZR-95 CURIES 0. OOE+00 0. OOE+00 4.49E-06 0. OOE+00 TOTALS CURIES I 0.OOE+00 I 0.OOE+00 9.20E-03 I 3.78E-03 I DISSOLVED AND ENTRAINED GASES XE-133 I CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.69E-05 TOTALS I CURIES I 0.OOE+00 0.OOE+00 I 0.OOE+00 I 1.69E-05 I Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 24 of 82

TABLE l-3A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Juh-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mrem 3.79E-04 7.58E-03 3.00E-03 6.01E-02 Liver 5.0 mrem 4.00E-03 7.99E-02 4.86E-03 9.72E-02 TBody 1.5 mrem 3.86E-03 2.57E-01 3.46E-03 2.31E-01 Thyroid 5.0 mrem 3.66E-03 7.32E-02 6.llE-04 1.22E-02 Kidney 5.0 mrem 4.17E-03 8.34E-02 2.03E-03 4.05E-02 Lung 5.0 mrem 6.26E-03 1.25E-01 2.62E-03 5.24E-02, GItLI 5.0 mrem 4.49E-03 8.99E-02 1.03E-03 2.06E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 3.38E-03 3.38E-02 Liver 10.0 mrem 8.86E-03 8.86E-02 TBody 3.0 mrem 7.32E-03 2.44E-01 Thyroid 10.0 mrem 4.27E-03 4.27E-02 Kidney 10.0 mrem 6.20E-03 6.20E-02 Lung 10.0 mrem 8.88E-03 8.88E-02 GILLI 10.0 mrem 5.53E-03 5.53E-02 Page 25 of 82.

TABLE 1-3A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 1.43E-03 2.86E-02 2.00E-03 4.01E-02 Liver 5.0 mrem 4.76E-03 9.52E-02 5.27E-03 1.05E-01 TBody 1.5 mrem 4.11E-03 2.74E-01 4.36E-03 2.91E-01 Thyroid 5.0 mrem 2.87E-03 5.74E-02 2.46E-03 4.93E-02 Kidney 5.0 mrem 3.49E-03 6.97E-02 3.41E-03 6.81E-02 Lung 5.0 mrem 6.37E-03 1.27E-01 7.33E-03 1.47E-01 GILLI 5.0 mrem 3.50E-03 6.99E-02 2.95E-03 5.89E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 6.82E-03 6.82E-02 Liver 10.0 mrem 1.89E-02 1.89E-01 TBody 3.0 mrem 1.58E-02 5.26E-01 Thyroid 10.0 mrem 9.60E-03 9.60E-02 Kidney 10.0 mrem 1.31E-02 1.31E-01 Lung 10.0 mrem 2.26E-02 2.26E-01 GILLI 10.0 mrem 1.20E-02 1.20E-01 Page 26 of 82

TABLE 1-3B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mrem 2.99E-04 5. 98E-03 3.04E-05 6.09E-04 Liver 5.0 mrem 2.63E-03 5.26E-02 1.14E-03 2.28E-02 TBody 1.5 mrem 2.54E-03 1. 69E-01 1.14E-03 7.60E-02 Thyroid 5.0 mrem 2.41E-03 4.82E-02 1.lIE-03 2.23E-02 Kidney 5.0 mrem 2.91E-03 5.82E-02 1.lIE-03 2.23E-02 Lung 5.0 mrem 5.36E-03 1. 07E-01 2.69E-03 5.38E-02 GILLI 5.0 mrem 3.17E-03 6.34E-02 1.51E-03 3.03E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 3.30E-04 3. 30E-03 Liver 10.0 mrem 3.77E-03 3.77E-02 TBody 3.0 mrem 3.68E-03 1.23E-01 Thyroid 10.0 mrem 3.52E-03 3.52E-02 Kidney 10.0 mrem 4.02E-03 4. 02E-02 Lung 10.0 mrem 8.05E-03 8.05E-02 GILLI 10.0 mrem 4.68E-03 4.68E-02 Page 27 of 82

TABLE 1-3B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 5.36E-05 1.07E-03 3.47E-04 6.93E-03 Liver 5.0 mrem 3.16E-04 6.33E-03 1.06E-03 2.12E-02 TBody 1.5 mrem 2.94E-04 1.96E-02 9.03E-04 6.02E-02 Thyroid 5.0 mrem 2.50E-04 5.00E-03 5.78E-04 1.16E-02 Kidney 5.0 mrem 2.71E-04 5.42E-03 7.41E-04 1.48E-02 Lung 5.0 mrem 6.14E-04 1.23E-02 1.16E-03 2.32E-02 GILLI 5.0 mrem 2.93E-04 5.86E-03 6.36E-04 1.27E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 7.30E-04 7.30E-03 Liver 10.0 mrem 5.15E-03 5.15E-02 TBody 3.0 mrem 4.87E-03 1.62E-01 Thyroid 10.0 mrem 4.35E-03 4.35E-02 Kidney 10.0 mrem 5.04E-03 5.04E-02 Lung 10.0 mrem 9.83E-03 9.83E-02 GILLI 10.0 mrem 5.61E-03 5.61E-02 Page 28 of 82

TABLE 1-4 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES JANUARY 2007 - DECEMBER 2007 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 2. 73E708 gCi/ml Fe-59 8.33E-08 gCi/ml Co-58 3.78E-08 gCi/ml Co-60 6.76E-08 gCi/ml Zn-65 1.32E-07 gCi/ml Mo-99 4. 31E-07 gCi/ml Cs-134 3 06E-08 gCi/ml Cs-137 4. 51E-08 RCi/ml Ce-141 6. 99E-08 gCi/ml Ce-144 2. 95E-07 gCi/ml 1-131 5 97E-08 gCi/ml Xe-133 9. lE-08 gCi/ml Xe-135 4 .27E-08 gCi/ml Fe-55 1.OOE-06 gCi/ml Sr-89 5. 00E-08 gCi/ml Sr-90 7. OOE-09 gCi/ml H-3 2. OOE-06 gCi/ml Gross Alpha 7. 00E-08 jICi/ml Page 29 of 82

TABLE 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 1 Starting : -l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF BATCH RELEASES 37 TOTAL TIME PERIOD FOR BATCH RELEASES 6061.22 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 419.38 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 163.82 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 40.03 MINUTES TABLE 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 NUMBER OF BATCH RELEASES 41 TOTAL TIME PERIOD FOR BATCH RELEASES 4945.57 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 563.65 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 120.62 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 10.00 MINUTES The average flow rate of the Savannah River at Augusta for the Radioactive Effluent Release Report period was obtained from the U.S.G.S website.

http://waterdata.usgs.gov/nwis/sw The average flow rate for 2007 was 5979 cubic feet per sec.

USGS Site Number -. 021973269 USGS Site Name - Savannah River near Waynesboro, Ga.

Page 30 of 82

TABLE 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF BATCH RELEASES 38 TOTAL TIME PERIOD FOR BATCH RELEASES 5348.28 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 380.83 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 140.74 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 10.00 MINUTES TABLE 1-SB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Batch Release Summary Unit: 2 Starting :. l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF BATCH RELEASES 38 TOTAL TIME PERIOD FOR BATCH RELEASES 5348.28 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 380.83 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 140-.74. MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 10.00 MINUTES The average flow rate of the Savannah River at Augusta for the Radioactive Effluent Release Report period was obtained from the U.S.G.S website.

http://waterdata.usgs.gov/nwis/sw The average flow rate for 2007 was 5979 cubic feet per sec.

USGS Site Number - 021973269 USGS Site Name - Savannah River near Waynesboro, Ga.

Page 31 of 82

TABLE 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.00E+00 CURIES TABLE 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIES Page 32 of 82

TABLE 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.OOE+00 CURIES TABLE 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.OOE+00 CURIES Page 33 of 82

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

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

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

b. For Iodine-1 31, for Iodine-1 33, for tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

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

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

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

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

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

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

Page 34 of 82

2.2 Measurements and Approximations of Total Radioactivity 2.2.1 Sample Collection and Analysis Gaseous Effluents at the Vogtle Electric Generating Plant are currently confined to six paths: plant vents (Unit 1 and Unit 2), the condenser air ejector, the steam packing exhauster systems (Unit 1 and Unit 2), Radwaste Processing Facility and the DAW (Dry Active Waste Building).

Waste gas decay tanks are batch released through the Unit 1 plant vent. The containment purges are released through their respective plant vents.

Containment atmosphere is also released via the containment equipment hatch during periods when the equipment hatch is open with containment purge/vent being stopped. Approval was granted by the NRC to open the equipment hatch during fuel movement; a release permit is generated when the equipment hatch is opened and the containment exhaust fan is not discharging to the plant vent.

Any detected activity in the containment equipment hatch permit is included in the Ground Release Table of the effluent report.

All of the paths with the exception of the DAW and RPF can be continuously monitored for gaseous radioactivity. The RPF is equipped with an integrated-type sample collection device for collecting particulates. Plant vent, containment, steam jet air ejector, steam-packing exhauster are equipped with an integrated-type sample collection device for collecting particulates and iodines. Samples of the DAW are collected using portable monitoring equipment during periods of operation. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and the steam packing exhauster system vents. There were no releases from the DAW. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release. The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.

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

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

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

Page 35 of 82

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

2.2.2.1 Fission and Activation Gases The released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample. Dose rates due to noble gases, radioiodines, tritium, and particulates are calculated. Calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodines, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

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

2.2.2.2 Radioiodines, Tritium and Particulate Releases The released quantities of radioiodines, tritium and particulates are determined using the weekly samples and release flow rates for the two plant vent release points.

After each quarter, the particulate filters from each plant vent are combined, for strontium analysis. Strontium concentrations are input to the composite file of the computer to be used for release dose rate and individual dose calculations.

Doses to a Member of the Public due to radioiodines, tritium and particulates are calculated for the controlling receptor, which is described in Table 3-7of the ODCM. Doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative doses are compared to the dose limits specified in ODCM 3.1.4.

Current percent of ODCM limits are shown in this report for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is calculated each month by counting the particulate filters for each week for gross alpha activity. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is used for release calculations.

Page 36 of 82

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

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

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

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

Sampling and statistical .error in counting 10%

Counting equipment calibration 10%

Vent flow Rates 10%

Non-steady release rates 20%

TOTAL ERROR 26.5%

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

Statistical error in counting 10%

Counting equipment calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 50%

Non-Steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 55%

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

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non steady release rates 10%

TOTAL ERROR 54%

Page 37 of 82

2.2.3 Total Error Estimation cont'd

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

Water vapor in sample stream determination 10%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 10%

TOTAL ERROR 20%

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

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non Steady release rates 10%

TOTAL ERROR 55%

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

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

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

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

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

Page 38 of 82

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

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

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

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

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

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

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

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

Page 39 of 82

TABLE 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.60E-01 5.51E-02 26.5

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.05E-02 7.01E-03

3. PERCENT OF APPLICABLE LIMIT %*

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.OOE+00 0.OOE+00 55

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT %

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 2.48E-07 6.56E-07 54

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.19E-08 8.34E-08

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 55 D. TRITIUM

1. TOTAL RELEASE CURIES 2.47E+01 2.41E+01 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.17E+00 3.06E+00

3. PERCENT OF APPLICABLE LIMIT *

Applicable limits are expressed in terms of dose.

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

Page 40 of 82

TABLE 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2007 Ending :' 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE- CURIES 5.61E-02 7.30E-02 26.5

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.06E-03 9.19E-03

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.OOE+00 0.OOE+00 55

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT %

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 4.34E-09 1.51E-14 54

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.46E-10 1.90E-15

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 55 D. TRITIUM

1. TOTAL RELEASE CURIES 8.21E+00 4.10E+00 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.03E+00 5.15E-01

3. PERCENT OF APPLICABLE LIMIT % *

Applicable limits are expressed in terms of dose.

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

Page 41 of 82

TABLE 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 2.96E-01 1.17E-02 26.5

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.81E-02 1.48E-03

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 3.74E-07 1.12E-07 55

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.81E-08 1.42E-08

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 1.32E-07 8.14E-06 54

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.69E-08 1.04E-06

3. PERCENT OF APPLICABLE LIMIT %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 55 D. TRITIUM

1. TOTAL RELEASE CURIES 8.44E+00 6.13E-01 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.09E+00 7.79E-02

3. PERCENT OF APPLICABLE LIMIT *

Applicable limits are expressed in terms of dose.

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

Page 42 of 82

TABLE 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: 2 Starting l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 2.04E-02 8.73E+01 26.5

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.57E-03 1.10E+01

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.OOE+00 0.OOE+00 55

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 3.30E-08 1.60E-07 54

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.15E-09 2.01E-08

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 55 D. TRITIUM

1. TOTAL RELEASE CURIES 3.35E-02 9.57E-01 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.21E-03 1.20E-01

3. PERCENT OF APPLICABLE LIMIT % *

Applicable limits are expressed in terms of dose.

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

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TABLE 2-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS 1..TOTAL RELEASE CURIES 4.56E-01 6.68E-02 26.5

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.86E-02 8.49E-03

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 3.74E-07 1.12E-07 55

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec .4.81E-08 1.42E-08

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 3.79E-07 8.80E-06 54

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.88E-08 1.12E-06

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 55 D. TRITIUM

1. TOTAL RELEASE CURIES 3.31E+01 2.47E+01 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.26E+00 3.14E+00

3. PERCENT OF APPLICABLE LIMIT *

Applicable limits are expressed in terms of dose.

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

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TABLE 2-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 7.65E-02 8.74E+01 26.5

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.62E-03 1.10E+01

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.OOE+00 0.OOE+00 55

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 3.73E-08 1.60E-07 54

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.69E-09 2.01E-08

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 55 D. TRITIUM

1. TOTAL RELEASE CURIES 8.24E+00 5.05E+00 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.04E+00 6.36E-01

3. PERCENT OF APPLICABLE LIMIT *

Applicable limits are expressed in terms of dose.

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

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TABLE 2-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 FISSION GASES AR-41 CURIES 0.OOE+00 0.OOE+00 1.59E-01 5.35E-02 XE-133 CURIES 0.OOE+00 0.OOE+00 6.61E-04 1.58E-03 TOTAL FOR PERIOD CURIES 0.OOE+00 0.OOE+00 1.60E-01 5.51E-02 PARTICULATES SR-89 CURIES 2.48E-07 3.82E-07 0.OOE+00 0.00E+0o0 CO-58 CURIES 0.OOE+00 2.74E-07 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 2.48E-07 6.56E-07 0.OOE+00 0.OOE+00 H-3 CURIES 2.45E+01 2.41E+01 1.49E-01 1.29E-02

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

See Table 2-6 for typical minimum detectable concentrations.

Page 46 of 82

TABLE 2-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED I UNIT QUARTER 3 1QUARTER 4 QUARTER 3 1QUARTER 4 FISSION GASES AR-41 CURIES O.OOE+00 O.OOE+00 5.34E-02 6.58E-02 XE-135 CURIES 0.OOE+00 0.OOE+00 2.53E-05 0.OOE+00 XE-133 CURIES 0.OOE+00 0.OOE+00 2.64E-03 7.18E-03 TOTAL FOR PERIOD CURIES 0.OOE+00 I0.OOE+00 I 5.61E-02 I 7.30E-02 PARTICULATES SR-89 CURIES 4.34E-09 1.51E-14 0.OOE+00 j 0.OOE+00 SR-90 CURIES O.OOE+00 O.OOE+00 j O.OOE+00 O.OOE+00 TOTAL FOR PERIOD I CURIES 4.34E-09 1.SE-14 I O.OOE+00 O.OOE+00 H-3 CURIES 8.20E+00 4.08E+00 I 3.88E-03 1l.53E-02 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 47 of 82

TABLE 2-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 1QUARTER 2 QUARTER 1 1QUARTER 2 FISSION GASES AR-41 CURIES 0.OOE+00 O.OOE+00 1.61E-01 9.48E-03 XE-135 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 3.50E-05 XE-133 CURIES 0.OOE+00 0.OOE+00 1.34E-01 2.15E-03 TOTAL FOR PERIOD I CURIES I 0.OOE+00 0.OOE+00 2.94E-01 1.17E-02 IODINES 1-131 CURIES 3.74E-07 1.12E-07 I 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD I CURIES I 3.74E-07 1.12E-07 0.OOE+00 I 0.OOE+00 PARTICULATES CR-51 CURIES- 0.OOE+00 1.32E-06 0.OOE+00 0.OOE+00 SR-89 CURIES 1.32E-07 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 CURIES 0.OOE+00 3.02E-07 0.OOE+00 0.OOE+00 NB-95 CURIES 0.OOE+00 3.04E-07 0.0OE+00 0.OOE+00 CO-58 CURIES 0.OOE+00 4.42E-06 0.OOE+00 0.OOE+00 MN-54 CURIES 0.OOE+00 4.94E-07 0.OOE+00 0.OOE+00 CO-60 CURIES 0.OOE+00 1.30E-06 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 1.32E-07 I 8.14E-06 I 0.OOE+00 0.OOE+00 H-3 CURIES 2.45E-06 2.38E-06 8.27E+00 4.01E-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 48 of 82

TABLE 2-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 1QUARTER 3 ]QUARTER 4 QUARTER 3 1QUARTER 4 FISSION GASES XE-'I35M , CURIES O.OOE+00 0.OE+00 7.99E-05 0.OOE+00 AR-41 CURIES 0.OOE+00 0.OOE+00 1 .37E-02 4.83E-01 KR-85M CURIES 0.OOE+00 0.OOE+00 0.OE+00 7*21E-03 7

XE-135 CURIES 0.OOE+00 0.OE+00 3.70E-05 3.14E-01 XE-133M CURIES 0.OE+00 0.OE+00 0.OOE+00 7.44E-01 XE-133 CURIES 0.OE+00 0.OE+00 6.59E-03 8.48E+01 XE-131M CURIES 0.OOE+00 0.OOE+00 0.OOE+00 9.82E-01 TOTAL FOR PERIOD CURIES . 0.OOE+00 I 0.OOE+00 I 2.04E-02 I 8.73E+01 PARTICULATES SR-89 I CURIES 3.30E-08 I 1.60E-07 I 0.OOE+00 I 0.OOE+00 I TOTAL FOR PERIOD I CURIES 3.30E-08 I 1.60E-07 I 0.OOE+00 I 0.OOE+00 I H-3 CURIES 2.03E-06 I 1.19E-07 I 3.35E-02 I 9.57E-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 49 of 82

TABLE 2-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED UNIT 1QUARTER 1 QUARTER 2 IQUARTER 1 1QUARTER 2 FISSION GASES AR-41 CURIES 0.OOE+00 0.OOE+00 3.20E-01 6.30E-02 XE-135 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 3.50E-05 XE-133 CURIES 0.OOE+00 0.OOE+00 1.34E-01 3.73E-03 TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 I 4.54E-01 6.68E-02 IODINES 1-131 CURIES 3.74E-07 1.12E-07 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 3.74E-07 1.12E-07 I 0.OOE+00 I 0.OOE+00 PARTICULATES CR-51 CURIES 0.OOE+00 1.32E-06 0.OOE+00 0.OOE+00 SR-89 CURIES 3.79E-07 3.82E-07 0.OOE+00 0.OE+00 ZR-95 CURIES 0.OE+00 3.02E-07 0.OOE+00 0.OOE+00 NB-95 CURIES 0.OE+00 3.04E-07 0.OOE+00 0.OE+00 CO-58 CURIES 0.OE+00 4.70E-06 00.OOE+00 0.OE+00 MN-54 CURIES 0.OE+00 4.94E-07 0.OOE+00 0 0.OE+00 CO-60 CURIES 0.OE+00 1 .30E-06 0.OOE+00 0.OE+00 TOTAL FOR PERIOD CURIES 3.79E-07 I 8.80E-06 0.OOE+00 I 0.OOE+00 H-3 CURIES 2.45E+01 I 2.41E+01 8.42E+00 I 4.14E-101 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 50 of 82

TABLE 2-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED I UNIT 1QUARTER 3 [QUARTER 4 1QUARTER 3 1QUARTER 4 1 FISSION GASES XE-135M CURIES 0.O'OE+00 0.OOE+00 7.99E-05 0.OOE+00 AR-41 CURIES 0.OE+00 0.OOE+00 6.71E-02 5.49E-01 KR-85M CURIES 0.OOE+00 0.OOE+00 0.OOE+00 7.21E-03 XE-135 CURIES 0.OOE+00 0.OOE+00 6.23E-05 3.14E-01 XE-133M CURIES 0.OOE+00 0 .OOE+00 1 0.00E+00 7.44E-01 XE-133 CURIES 0.OOE+00 0.OOE+00 9.23E-03 8.48E+01 XE-131M CURIES 0.OOE+00 0.OE+00 0.OOE+00 9.82E-01 TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 7.65E-02 8.74E+01 PARTICULATES SR-89 CURIES 3.73E-08 1.60E-07 0.OOE+00 0.OOE+00 SR-90 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 3.73E-08 I 1.60E-07 I 0.OOE+00 0.OOE+00 H-3 CURIES 8.20E+00 I 4.08E+00 I 3.74E-02 9.72E-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 51 of 82

TABLE 2-3A*

RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE I NUCLIDES RELEASED I UNIT 1QUARTER 1 IQUARTER 2 QUARTER 1 1QUARTER 2 TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 52 of 82

TABLE 2-3A*

RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE j BATCH MODE' NUCLIDES RELEASED I UNIT 1QUARTER 3 1QUARTER 4 1QUARTER 3 1QUARTER 4 1 TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 0.OOE+00 I0 .OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 53 of 82

TABLE 2-3B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED UNIT 1QUARTER 1 1QUARTER 2 QUARTER 1 1QUARTER 2 FISSION GASES XE-133 CURIES 0.OOE+00 I 0.OOE+00 1.75E-03 0.OOE+00 TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 I 1.75E-03 I.OOE+00 I H-3 CURIES 0.OOE+00 I 0.OOE+00 I 1.68E-01 2.12E-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 54 of 82

TABLE 2-3B*

RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED I UNIT QUARTER 3 1QUARTER 4 1QUARTER 3 1QUARTER 4 1 TOTAL FOR PERIOD 1 CURIES 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I O.OOE+.00 Zeroes in this table indicate that no radioactivity was present

at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 55 of 82

TABLE 2-3C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jan-2007 Ending : 30-Jun-2007 I CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 1QUARTER 1 QUARTER 2 1QUARTER 1 1QUARTER 2 FISSION GASES XE-133 CURIES 0.OOE+00 0.OOE+00 I 1.75E-03 I 0.OOE+00 TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 I 1.75E-03 I 0.OOE+00 H-3 I CURIES I 0.OOE+00 I0.OOE+00 I.68E-01 I 2.12E-01 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 56 of 82

TABLE 2-3C*

RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jul-2007 Ending : 31-Dec-2007 CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED I UNIT QUARTER 3 IQUARTER 4 1QUARTER 3 QUARTER 4 TOTAL FOR PERIOD I CURIES 0.OOE+00 0.OOE+00 I 0.OOE+00 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

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

Page 57 of 82

TABLE 2-4A Vogtle Electric Gener&ting Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 2.16E-05 4.33E-04 7.30E-06 1.46E-04 Beta 10.0 mrad 7.64E-06 7.64E-05 2.60E-06 2.60E-05 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date limit ation Gamma 10.0 mrad 2.89E-05 2.89E-04 Beta 20.0 mrad 1.02E-05 5.12E-05 Page 58 of 82

TABLE 2-4A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 7.29E-06 1.46E-04 9.OOE-06 1.80E-04 Beta 10.0 mrad 2.61E-06 2.61E-05 3.27E-06 3.27E-05 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date limit ation Gamma 10.0 mrad 4.52E-05 4.52E-04 Beta 20.0 mrad 1.61E-05 8.06E-05 Page 59 of 82

TABLE 2-4B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 2.26E-05 4.53E-04 1.30E-06 2.61E-05 Beta 10.0 mrad 9.92E-06 9.92E-05 4.90E-07 4.90E-06 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 2.39E-05 2.39E-04 Beta 20.0 mrad 1.04E-05 5.21E-05 Page 60 of 82

TABLE 2-4B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 1.90E-06 3.81E-05 5.19E-04 1.04E-02 Beta 10.0 mrad 7.61E-07 7.61E-06 1.37E-03 1.37E-02 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date limit ation Gamma 10.0 mrad 5.45E-04 5.45E-03 Beta 20.0 mrad 1.38E-03 6.91E-03 Page 61 of 82

TABLE 2-5A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit LImit Bone 7.5 mrem 5.86E-08 7.81E-07 9.10E-08 1.21E-06 Liver 7.5 mrem 1.59E-04 2.12E 1.55E-04 2.06E-03 TBody 7.5 mrem 1.59E-04 2.12E-03 1.55E-04 2.06E-03 Thyroid 7.5 mrem 1.59E-04 2.12E-03 1.55E-04 2.06E-03 Kidney 7.5 mrem 1.59E-04 2.12E-03 1.55E-04 2.06E-03 Lung 7.5 mrem 1.59E-04. 2.12E-03 1.55E-04 2.06E-03 GILLI 7.5 mrem 1.59E-04 2.12E-03 1.55E-04 2.06E-03 Cumulative Doses per Year Organ ODCM Units Year to

of limit Ending ODCM Date limit Bone 15.0 mrem 1.50E-07 9.97E-07 Liver 15.0 mrem 3.13E-04 2.09E-03 TBody 15.0 mrem 3.13E-04 2.09E-03 Thyroid 15.0 mrem 3.13E-04 2.09E-03 Kidney 15.0 mrem 3.13E-04 2.09E-03 Lung 15.0 mrem 3.13E-04 2.0.9E-03 GILLI 15.0 mrem 3.13E-04 2.09E-03 Page 62 of 82

TABLE 2-5A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Bone 7.5 mrem 1.03E-09 1.37E-08 5.66E-15 7.54E-14 Liver 7.5 mrem 5.28E-05 7.04E-04 2.63E-05 3.51E-04 TBody 7.5 mrem 5.28E-05 7.04E-04 2.63E-05 3.51E-04 Thyroid 7.5 mrem 5.28E-05 7.04E-04 2.63E-05 3.51E-04 Kidney 7.5 mrem 5.28E-05 7.04E-04 2.63E-05 3.51E-04 Lung 7.5 mrem 5.28E-05 7.04E-04 2.63E-05 3.51E-04 GILLI 7.5 mrem 5.28E-05 7.04E-04 2.63E-05 3.51E-04 Cumulative Doses per Year Organ ODCM Units Year to % of limit Ending ODCM Date limit Bone 15.0 mrem 1.51E-07 1.OOE-06 Liver 15.0 mrem 3.93E-04 2.62E-03 TBody 15.0 mrem 3.93E-04 2.62E-03 Thyroid 15.0 mrem 3.93E-04 2.62E-03 Kidney 15.0 mrem 3.93E-04 2.62E-03 Lung 15.0 mrem 3.93E-04 2.62E-03 GILLI 15.0 mrem 3.93E-04 2.62E-03 Page 63 of 82

TABLE 2-5B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2007 Ending: 30-Jun-2007 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 3.16E-08 4.21E-07 1.92E-07 2.55E-06 Liver 7.5 mrem 5.54E-05 7.39E-04 5.58E-06 7.44E-05 TBody 7.5 mrem 5.54E-05 7.39E-04 5.59E-06 7.45E-05 Thyroid 7;5 mrem 5.55E-05 7.40E-04 5.61E-06 7.48E-05 Kidney 7.5 mrem 5.54E-05 7.39E-04 5.57E-06 7.43E-05 Lung 7.5 mrem 5.54E-05 7.39E-04 5.59E-06 7.45E-05 GILLI 7.5 mrem 5.54E-05 7.39E-04 5.61E-06 7.48E-05 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 2.23E-07 1.49E-06 Liver 15.0 mrem 6.10E-05 4.07E-04 TBody 15.0 mrem 6.10E-05 4.07E-04 Thyroid 15.0 mrem 6.lIE-05 4.08E-04 Kidney 15.0 mrem 6.10E-05 4.07E-04 Lung 15.0 mrem 6.10E-05 4.07E-04 GILLI 15.0 mrem 6.10E-0S 4.07E-04 Page 64 of 82

TABLE 2-5B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2007 Ending: 31-Dec-2007 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Bone 7.5 mrem 7.80E-09 1.04E-07 3.78E-08 5.04E-07 Liver 7.5. mrem 2.15E-07 2.87E-06 6.15E-06 8.20E-05 TBody 7.5 mrem 2.16E-07 2.87E-06 6.15E-06 8.21E-05 Thyroid 7.5 mrem 2.15E-07 2.87E-06 6.15E-06 8.20E-05 Kidney 7.5 mrem 2.15E-07 2.87E-06 6.15E-06 8.20E-05 Lung 7.5 mrem 2.15E-07 2.87E-06 6.15E-06 8.20E-05 GILLI 7.5 mrem 2.16E-07 2.87E-06 6.15E-06 8.21E-05 Cumulative Doses per Year Organ ODCM. Units Year to % of limit Ending ODCM Date limit Bone 15.0 mrem 2.69E-07 1.79E-06 Liver 15.0 mrem 6.74E-05 4.49E-04 TBody 15.0 mrem 6.74E-05 4.49E-04 Thyroid 15.0 mrem 6.75E-05 4.50E-04 Kidney 15.0 mrem 6.73E-05 4.49E-04 Lung 15.0 mrem 6.74E-05 4.49E-04 GILLI 15.0 mrem 6.74E-05 4.49E-04 Page 65 of 82

TABLE 2-6 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES JANUARY, 2007 THROUGH DECEMBER, 2007 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 iCi/ml Kr-88 2. 53E-08 iCi/ml Xe-133 2 05E-08 iCi/ml Xe-133m 8. 63E-08 iCi/ml Xe-135 7. 12E-08 iCi/ml Xe-138 1. 05E-07 gCi/ml 1-131 7. 93E-15" ICi/ml Mn-54 3 94E-14" gCi/ml Fe-59 2 .45E-14* ICi/ml Co-58 1. 39E-14* gCi/ml Co-60 1. 75E-14* iCi/ml Zn-6S 2. 82E-14* iCi/ml Mo-99 9. 57E-14" gCi/ml Cs-134 1. 12E-14* gCi/ml Cs-137 8. 71E-15* iCi/ml Ce-141 8. 62E-15* iCi/ml Ce-144 2 .77E-14* gCi/ml Sr-89 1.OOE-13 gCi/ml Sr-90 1.OOE-13 iCi/ml H-3 9 OOE-08 iCi/ml Gross Alpha 1. OOE-13 iCi/ml

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

Page 66 of 82

TABLE 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 51 TOTAL TIME PERIOD FOR BATCH RELEASES 21991.93 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 8863.'98 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 431.21 MINUTES MINIMUM TIME FOR A BATCH RELEASE 3.00 MINUTES TABLE 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents -,Batch Release Summary Unit: 1 Starting : I-Jul-2007 Ending : 31-Dec-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 56 TOTAL TIME PERIOD FOR BATCH RELEASES 5505.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 1460.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 98.30 MINUTES MINIMUM TIME FOR A BATCH RELEASE 27.00 MINUTES Page 67 of 82

TABLE 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 37 TOTAL TIME PERIOD FOR BATCH RELEASES 62533.57 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 10076.92 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 1690.10 MINUTES MINIMUM TIME FOR A BATCH RELEASE 26.00 MINUTES TABLE 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Batch Release Summary Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 GASEOUS RELEASES NUMBER OF BATCH RELEASES 35 TOTAL TIME PERIOD FOR BATCH RELEASES 14430.83 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 3226.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 412.31 MINUTES MINIMUM TIME FOR A BATCH RELEASE 3.00 MINUTES Page 68 of 82

TABLE 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF RELEASES .0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIES TABLE 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jul-2007 Ending : 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0.OOE+00 CURIES Page 69 of 82

TABLE 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jan-2007 Ending : 30-Jun-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES : 0.00 MINUTES MAXIMUM TIME FOR A RELEASE . 0.00 MINUTES AVERAGE TIME FOR A RELEASE : 0.00 MINUTES MINIMUM TIME FOR A RELEASE . 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.00E+00 CURIES TABLE 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jul-2007 Ending : 31-Dec-2007 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES . 0.00 MINUTES MAXIMUM TIME FOR A RELEASE : 0.00 MINUTES AVERAGE TIME FOR A RELEASE : 0.00 MINUTES MINIMUM TIME FOR A RELEASE : 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES : 0.OOE+00 CURIES Page 70 of 82

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

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

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

3.1.2 Reporting Requirements 12.1 PCP states in part:

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

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

Page 71 of 82

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 1 of 4 JANUARY 1, 2007 THROUGH JUNE 30, 2007 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period Error, %

a. Spent resins, filter sludges, evaporator m3 NONE bottoms, etc. Ci NONE N/A

b. Dry compressible waste, contaminated m3 26.64 equip, etc. Ci 477.7 40

c. Irradiated components, control m3 NONE rods, etc. Ci NONE N/A

d. Other (describe) m3 NONE Ci NONE N/A

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

a. N/A % N/A N/A % N/A N/A % N/A N/A % N/A

b. Fe-55 % 64.05 Ni-63 % 16.47 Co-60 % 11.00 All others % 8.484

c. N/A % N/A N/A % N/A N/A % N/A N/A % N/A

d. N/A % N/A N/A % N/A

3. Solid Waste Disposition Number of Mode of Shipments Transportation Destination 5 Tractor / Trailer Duratek, Oak Ridge, TN 3 Cask / Tractor / Trailer Studsvik, Erwin, TN 4 Cask / Tractor / Trailer Studsvik, Race, Memphis TN 3 Rail Road Tanker Pacific Ecosolutions, Richland, Wa Page 72 of 82

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 2 of 4 JANUARY 1, 2007 THROUGH JUNE 30, 2007 B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of Sit~LlffC aain anipu . - ýatihlaLAUAA None None None ADDITIONAL INFORMATION REQUIRED BY ODCM:

Shipments Sent Directly to Disposal at Barnwell, SC.

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

NONE Shipments to a Waste Processor:

Shipment No. Waste Class Type Container Shipping Class Solidification Agent Processor RVRS-07-001 B DOT 7A Type A LSA (2) None Studsvik RVRS-07-002 B Class B Cask Yellow III None Studsvik RVRS-07-003 AU Excepted Package LSA (1) None Duratek RVRS-07-004 AU Excepted Package LQ None Duratek RVRS-07-005 AU Excepted Package LSA (1) None Duratek RVRS-07-006 AU Expected Package LSA (1) None Duratek RVRS-07-007 AU Excepted Package LSA (1) None Duratek RVRS-07-008 AU Excepted Package LQ None Pacific Eco Sol RVRS-07-009 AU Excepted Package LQ None Pacific Eco Sol RVRS-07-010 AU Excepted Package LQ None Pacific Eco Sol RVRS-07-011 AU Excepted Package LQ None Pacific Eco Sol RVRS-07-012 AU Excepted Package LSA (1) None Studsvik/Race RVRS-07-013 AU Excepted Package LQ None Studsvik/Race RVRS-07-014 AU Excepted Package LQ None Studsvik/Race RVRS-07-015 AU Excepted Package LSA (1) None Studsvik/Race Page 73 of 82

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 3 of 4 JULY 1, 2007 THROUGH DECEMBER 31, 2007 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period Error, %

a. Spent resins, filter sludges, evaporator m3 NONE bottoms, etc. Ci NONE N/A

b. Dry compressible waste, contaminated m3 13.65 equip, etc. Ci 149.6 40

c. Irradiated components, control m3 NONE rods, etc. Ci NONE N/A

d. Other (describe) m3 NONE Ci NONE N/A

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

a. N/A % N/A N/A % N/A N/A % N/A N/A % N/A

b. Fe-55 % 21.66 Ni-63 % 41.67 Co-60 % 29.46 All others % 7.214

c. N/A % N/A N/A % N/A N/A % N/A N/A % N/A

d. N/A % N/A N/A % N/A

3. Solid Waste Disposition Number of Mode of Shipments Transportation Destination 2 Cask/ Tractor/ Trailer Studsvik, Erwin, TN 7 Tractor / Trailer Duratek, Oak Ridge, TN 11 Cask/ Tractor / Trailer Duratek, Oak Ridge, TN Page 74 of 82

TABLE 3-1 Vogtle Electric. Generating Plant RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units I and 2 Page 4 of 4 July 1, 2007 THROUGH December 31, 2007 B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of T-nrinnto-tnnn None None None ADDITIONAL INFORMATION REQUIRED BY ODCM:

Shipments Sent Directly to Disposal at Barnwell, SC.

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

NONE Shipments to a Waste Processor:

Shipment No. Waste Class Type Container Shipping Class Solidification Agent Processor RVRS-07-016 B Type B Yellow III None Studsvik RVRS-07-017 AU Expected Package LSA (1) None Duratek RVRS-07-018 AU Excepted Package LSA (1) None ES RVRS-07-019 B Type B Yellow III None Studsvik RVRS-07-020 AU Expected Package LQ None Duratek RVRS-07-021 AU Excepted Package LQ None Duratek RVRS-07-022 AS DOT 7A Type A LSA (2) None Duratek RVRS-07-023 AU Excepted Package LQ None Duratek RVRS-07-024 AU Excepted Package LQ None Duratek RVRS-07-025 AU Excepted Package LSA (1) None Duratek Page 75 of 82

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

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

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

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

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

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

Similarly, it is listed in tables 2-3A and 2-3B3 for the ground level releases.

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

Page 76 of 82

TABLE 4-1 Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2007 Ending: 30-Jun-2007 Location Name VISITOR CENTER Distance (kilometers) 4.47E-01 Sector SE Occupancy Factor 4.57E-04 (4.OOE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 5.93E-06 Particulate X/Q (sec/m3) 5.58E-06 Particulate D/Q (m--2) 2.28E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.12E-07 Particulate X/Q (sec/m3) 6.74E-07 Particulate D/Q (m-2) 5.77E-09 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Total Body Dose mrem 2.98E-08 5.79E-09 3.56E-08 3.56E-08 Bone mrem 2.96E-08 8.31E-09 3.79E-08 3.79E-08 Liver mrem 4.18E-07 2.85E-07 7.03E-07 7.03E-07 TBody mrem 4.18E-07 2.85E-07 7.03E-07 7.03E-07 Thyroid mrem 4.18E-07 2.85E-07 7.03E-07 7.03E-07 Kidney mrem 4.18E-07 2.85E-07 7.03E-07 7.03E-07 Lung mrem 4.18E-07 2.86E-07 7.03E-07 7.03E-07 GI-LLI mrem 4.18E-07 2.85E-07 7.03E-07 7.03E-07 Page 77 of 82

TABLE 4-1 Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2007 DOSES TO'A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2007 Ending: 31-Dec-2007 Location Name VISITOR CENTER Distance (kilometers) 4.47E-01 Sector SE Occupancy Factor 4.57E-04 (4.OOE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 5.93E-06 Particulate X/Q (sec/m3) 5.58E-06 Particulate D/Q (m-2) 2.28E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.12E-07 Particulate X/Q (sec/m3) 6.74E-07 Particulate D/Q (m-2) 5.77E-09 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Total Body Dose mrem 6.16E-09 3.18E-07 3.24E-07 3.60E-07 Total Body Dose mrem Bone mrem 6.15E-09 3.16E-07 3.22E-07 3.60E-07 Liver mrem 9.67E-08 3.71E-07 4.68E-07 1.17E-06 TBody mrem 9.67E-08 3.71E-07 4.68E-07 1.17E-06 Thyroid mrem 9.67E-08 3.71E-07 4.68E-07 1.17E-06 Kidney mrem 9.67E-08 3.71E-07 4.68E-07 1.17E-06 Lung mrem 9.67E-08 3.71E-07 4.68E707 1.17E-06 GI-LLI mrem 9.67E-08 3.71E-07 4.68E-07 1.17E-06 Page 78 of 82

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

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

6.0 Meteorological Data ODCM 7.2.2.2 states in part:

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

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

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

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

Page 79 of 82

7.1.2 Description of Deviations 7.1.2.1 The Unit 1 Steam Generator Blowdown Effluent Line flow transmitter, 1FT-0021, was determined to be inoperable and not corrected within the specified time requirement of ODCM Section 2.1.1.

Condition Reports 2007101836 and 2007103758 document the events of inoperability.

2-17-2007, the instrument was declared inoperable and removed from service with CR 2007101836 initiated to document conditions and WO 1070272701 initiated for repairs.

A failure of the Plant Vogtle work order scheduling process resulted in Unit 1 FT-0021 remaining Out of Service for greater than 30 days.

Personnel involved did not adequately monitor the progress of work allowing the work to be scheduled beyond the 30 day reporting period.

Personnel recognized the flow transmitter provided data to be used for determining effluent release volumes and that no releases were in progress at the time.

No unacceptable risk to personnel exposure would have been incurred since a conservative estimate of flow would have been used in discharge flow estimation.

Flow transmitter Unit 1 FT-0021 was subsequently determined to have been operable but was administratively removed from service as a precautionary measure.

Compensatory actions required by the ODCM action statements were appropriately taken.

March 2 7 th, Unit 1 FT-0021 was determined to be operable and returned to service.

Page 80 of 82

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

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

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

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

8.2 Description of Changes Changes were made to the Vogtle Electric Generating Plant ODCM for the period January 1, 2007 through December 31, 2007. Revision 23 became effective January 2007. A complete copy of the ODCM will be included with this report with changes identified by bars in the right hand margin of the document. Changes were made to Table 4-4 "Radiological Environmental Monitoring Locations", Figure 4-3 "Terrestrial Stations Beyond 5 miles" and Figure 4-4 "Drinking Water Stations".

The Land Use Census was conducted November 13, 2007 by Georgia Power Company Environmental Lab personnel. Due to the results of the census for 2007, changes will be made to the REMP sampling locations and the dose calculation locations and will be described in the next revision to the Vogtle ODCM.

Page 81 of 82

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

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

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

PCP 12.1 states in part:

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

9.2 Description of Major Changes Gaseous Radwaste System There were no major changes to the gaseous radwaste systems in the 2007 assessment period.

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

This is to indicate that no major changes to the liquid radwaste systems occurred during the 2007 assessment period.

Solid Radwaste System There were no major changes to the solid radwaste systems in the 2007 assessment period.

Page 82 of 82

NL-08-0668, Annual Radioactive Effluent Release Reports for 2007

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