View source for NL-11-0811, Edwin I. Hatch, Units 1 and 2, Joseph M. Farley, Units 1 and 2, and Vogtle, Units 1 and 2, Annual Radioactive Effluent Release Reports for 2010, Cover Letter Through Page 2-25

{{Adams
| number = ML111220085
| issue date = 04/29/2011
| title = Edwin I. Hatch, Units 1 and 2, Joseph M. Farley, Units 1 and 2, and Vogtle, Units 1 and 2, Annual Radioactive Effluent Release Reports for 2010, Cover Letter Through Page 2-25
| author name = Ajluni M J
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000321, 05000348, 05000364, 05000366, 05000424, 05000425
| license number = 
| contact person = 
| case reference number = NL-11-0811
| package number = ML111220082
| document type = Annual Report, Letter
| page count = 300
}}

=Text=
{{#Wiki_filter:Mark J. A;luni. P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel Fax April 29, SOUTHERN'\'
COMPANY Docket 50-321 50-348 50-424 NL-11-0811 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Unit 1 & Joseph M. Farley Nuclear Plant Unit 1 & Vogtle Electric Generating Plant Unit 1 & Annual Radioactive Effluent Release Reports for 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 2010. 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 EfI:luent Release Report for 2010, the Farley and Vogtle ODCMs were revised. Accordingly, copies of Version 24 of the Farley ODCM, dated January 2010, and Version 27 of the Vogtle ODCM, dated October 2010 are provided in Enclosures 4 and 5, respectively.
Revision bars are provided in the margin to show the changes for Version 24 of the Farley ODCM and Version 27 of the Vogtle ODCM. A description of the changes to each ODCM is provided in Section 8.0 of the Annual Radioactive Effluent Release Report for the corresponding plant. Changes to the Process Control Program (PCP) and to previous Annual Radioactive Effluent Release Reports, as applicable, are described in section 9.2 of the corresponding Radioactive Effluent Release Report for each site.
U. S. Nuclear Regulatory Commission Nl-11-0811 Page 2 This letter contains no NRC commitments.
If you have any questions, please advise. Respectfully submitted, M. J. Ajluni Nuclear licensing Director MJNlWW/lac 

==Enclosures:==
: 1. Hatch Annual Radioactive Effluent Release Report for 2010 2. Farley Annual Radioactive Effluent Release Report for 2010 3. Vogtle Annual Radioactive Effluent Release Report for 2010 4. Farley Offsite Dose Calculation Manual -Version 24 5. Vogtle Offsite Dose Calculation Manual -Version 27 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. l. M. Stinson, Vice President 
-Farley Mr. D. R Madison, Vice President 
-Hatch Mr. T. E. Tynan, Vice President 
-Vogtle Ms. P. M. Marino, Vice President 
-Engineering RType:CFA04.054; CHA02.004; CVC7000 U. S. Nuclear Regulatory Commission Mr. V.M. McCree, Regional Administrator Mr. R E. Martin, NRR Project Manager -Farley, Hatch and Vogtle Mr. P. G. Boyle, NRR Project Manager Mr. E. l. Crowe, Senior Resident Inspector 
-Farley Mr. E. D. Morris, Senior Resident Inspector 
-Hatch Mr. M. Cain, Senior Resident Inspector 
-Vogtle State of Alabama Mr. J. l. McNees, Department of Public Health, Division of Radiation Control State of Mr. Jim Hardeman, Department of Natural Georgia Power Mr. Rickey E. American Nuclear Mr. R A.
Edwin I. Hatch Nuclear Joseph M. Farley Nuclear Vogtle Electric Generating Annual Radioactive Effluent Release Reports for Enclosure Hatch Annual Radioactive Effluent Release Report for SOUTHERN E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1,2010 THROUGH DECEMBER 31, 2010 SECTION TITLE PAGE Liquid Effluents 1 Regulatory Requirements 1 Concentration Limits 1 Dose Limits 1 Effluent Concentration Limit 1 Measurements and Approximations of Total 2 Radioactivity for Liquid Radwaste Total Radioactivity Determination for Liquid Radwaste 2 Measurements and Approximations of Total 4 Radioactivity for Groundwater Outfall-Y22N008A Total Radioactivity Determination for Groundwater 4 Outfalls Total Error Estimation 5 Liquid Effluent Release Data 6 Radiological Impact Due to Liquid Releases 7 Liquid Effluents 
-Batch Releases 7 Liquid Effluents 
-Continuous Releases 7 SECTION 1.10 Liquid Effluents 
-Abnormal 2.0 Gaseous 2.1 Regulatory 2.1.1 Dose Rate Air Doses Due to Noble Gases in Gaseous Releases Doses to a Member of the Public Measurements and Approximations of Total Sample Collection and Analysis Total Quantities of Radioactivity, Dose Rates and Cumulative Fission and Activation Gases Radioiodine, Tritium and Particulate Releases Gross Alpha Release Total Error Estimation Gaseous Effluent Release Data Radiological Impact Due to Gaseous Releases Gaseous Etnuents -Batch Releases Gaseous Effluents 
-Abnormal Releases Solid Waste Regulatory Requirements Solid Radioactive Waste System Reporting Requirements ii SECTION PAGE Solid Waste Data Doses to Members of the Public Inside The Site Regulatory Requirements Demonstration of Compliance Total Dose from Uranium Fuel Cycle (40 CFR 190) Regulatory Requirements Demonstration of Compliance Meteorological Data Program Deviations Inoperable Liquid or Gaseous Effluent Monitoring Regulatory Requirements Description of Deviations Tanks Exceeding Curie Content Limits Regulatory Requirements Description of Deviations Effluent Sample Analysis Exceeding Minimum Detectable Concentration Regulatory Requirement Description of Deviation iii SECTION PAGE Changes to the Plant Hatch Offsite Dose Calculation Manual Regulatory Requirements Description of Changes Major Changes to the Liquid, Gaseous or Solid Radwaste Treatment Regulatory Requirements Description of Major Changes iv SOUTHERN E. I. HATCH NUCLEAR UNITS NO. 1 &ANNUAL PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents 
-Summation of All Releases Unit 1 (Quarters 1, 2, 3 and 4) 8 1-1B Liquid Effluents 
-Summation of All Releases Unit 2 (Quarters 1, 2, 3 and 4) 9 1-1C Liquid Effluents 
-Summation of All Releases Site (Quarters 1, 2, 3 and 4) 10 1-2A Liquid Effluents 
-Unit 1 (Quarters 1, 2, 3 and 4) 11 1-2B Liquid Effluents 
-Unit 2 (Quarters 1, 2, 3 and 4) 13 1-2C Liquid Effluents 
-Site (Quarters 1, 2, 3 and 4) 16 1-3A Doses to a Member of The Public Due to Liquid Releases Unit 1 (Quarters 1, 2, 3 and 4) 19 1-3B Doses to a Member of The Public Due to Liquid Releases Unit 2 (Quarters 1, 2, 3 and 4) 20 1-4 Minimum Detectable Concentration Liquid Sample Analysis 21 1-5A Liquid Effluents 
-Batch Release Summary Unit 1 22 1-5B Liquid Ef1:luents 
-Batch Release Summary Unit 2 23 TABLE LIST OF TABLES 1*6A Liquid Effluents*
Abnormal Release Summary Unit 1 24 1-68 Liquid Effluents 
-Abnormal Release Summary Unit 2 25 1-6C Liquid Effluents-Abnormal Release Summary -Site 26 2-1A Gaseous Effluents 
-Summation of All Releases -Unit 1 (Quarters 1, 2, 3 and 4) 34 2-18 Gaseous Effluents 
-Summation of All Releases -Unit 2 (Quarters 1, 2, 3 and 4) 35 2-1C Gaseous Effluents 
-Summation of All Releases -Site (Quarters 1, 2, 3 and 4) 36 2*2A Gaseous Effluents 
-Elevated Releases Unit 1 (Quarters 1, 2, 3 and 4) 37 2-28 Gaseous Effluents 
-Elevated Releases Unit 2 (Quarters 1, 2, 3 and 4) 40 2-2C Gaseous Effluents 
-Elevated Releases Site (Quarters 1, 2, 3 and 4) 44 2-3A Gaseous Effluents 
-Ground Level Releases Unit 1 (Quarters 1,2,3 and 4) 47 2-38 Gaseous Effluents 
-Ground Level Releases Unit 2 (Quarters 1, 2, 3 and 4) 49 2-3C Gaseous Effluents 
-Ground Level Releases Site (Quarters 1,2,3 and 4) 51 2-4A Air Doses Due to Noble Gases in Gaseous Releases -Unit 1 (Quarters 1, 2, 3 and 4) 53 vi TABLE LIST OF TABLES PAGE 2-4B Air Doses Due to Noble Gases in Gaseous Releases-Unit 2 (Quarters 1, 2, 3 and 4) 54 2-5A Doses to a Member of the Public Due to Radioiodine, Tritium, and Particulates in Gaseous Releases -Unit 1 (Quarters 1, 2, 3 and 4) 55 2-5B Doses to a Member of the Public Due to Radioiodine, Tritium, and Particulates in Gaseous Releases -Unit 2 (Quarters 1, 2, 3 and 4) 56 2-6 Minimum Detectable Concentration Gaseous Sample Analyses 57 2-7A Gaseous Effluents 
-Batch Release Summary Unit 1 58 2-7B Gaseous Effluents 
-Batch Release Summary Unit 2 59 2-8A Gaseous Effluents 
-Abnormal Release Summary Unit 1 60 2-8B Gaseous EfHuents -Abnormal Release Summary Unit 2 61 2-8C Gaseous Effluents 
-Abnormal Release Summary Unit Site 62 3-1 Solid Waste and Irradiated Fuel Shipments 65 4-1 Doses to a Member of the Public Due to Activities Inside The Site Boundary 69 vii Liquid Effluents Regulatory Requirements Concentration Limits 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 1 E-04 microcuries/ml total activity. 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: 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 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. Effluent Concentration Limit 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/ml 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. 1 The method utilizing the ECl fraction to determine the dose released from groundwater outfalls is described in Subsection 1.4 of this report. 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 (ODeM) 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. Total Radioactivity Determination for Liquid Radwaste MEASUREMENT METHOD Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction. 
: 2. Dissolved or entrained Each Gamma Spectroscopy noble with computerized data reduction. Tritium Monthly Distillation and liquid Composite scintillation counting Gross Alpha Monthly Gas flow proportional Composite counting 5. Sr-89 & Sr-90 Chemical separation and gas flow proportional or scintillation counting 6. Quarterly Chemical separation and liquid scintillation counting Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 keY 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 MOC calculation is performed to ensure that the MOC's are met for the nuclides specified in the OOCM Chapter 10 (Le., 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 MOC 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 OOCM 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 qualified technician 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.
Measurements and Approximations of Total Radioactivity for Groundwater Dutfa/l-Y22N008A 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 the 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. Total Radioactivity Determination for Groundwater Dutfalls MEASUREMENT METHOD Gamma Isotopic
* Weekly Composite Gamma Spectroscopy with computerized data
* Additional analysis may be required based abnormal Tritium
* Weekly Composite Distillation and liquid scintillation counting
* Additional analysis be required based abnormal 3. Sr-89 & Sr-90 Chemical separation and gas flow proportional or scintillation counting 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 or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (Le., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.
Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4. Tritium, Gross Beta, Sr-89 and Sr-90 are, in some cases, analyzed offsite. The radionuclide concentrations determined by gamma spectroscopic analysis of the weekly composite sample, in addition to the most current sample analysis results available for tritium, gross beta, Sr-89 and Sr-90, are used along with the corresponding ECl values to determine the ECl fraction for these composite samples. This ECl fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate projected dose released.
Radionuclide concentrations, safety factors and dilution stream flow rate are entered into the computer and a pre-release printout is generated for each release period. When the release period is complete, the release permit is updated with the actual release data collected during the release period. These data are input into the computer and a post-release printout is generated.
The post release printout contains the actual release rates, the actual release concentrations and quantities, the actual dilution 'flow, and the calculated doses to a Member of the Public. Cumulative dose results are tabulated along with the percent of the aDCM 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%.
Liquid Effluent Release Data Regulatory Guide 1.21, Tables 2A and 28 are found in this report as Table 1-1A, for Unit 1, Table 1-18, for Unit 2 and Table 1-1C, for the site; and Table 1-2A, for Unit 1-28, 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 2010 can be found in Appendix A of this report. The values for the fou r categories of Tables 1-1 A, and 1-18, and 1-1 C, are calculated and the Tables completed as follows: 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. Tritium -The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period. 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. Gross alpha radioactivity 
-The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity.
1.7 Radiological Impact 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 Unit 2 Liquid Batch Releases:
Table 1.9 Liquid Effluents 
-Continuous Releases Continuous Release information is summarized in the following tables: Unit 1 Liquid Continuous Releases:
Table 1-2A * (No continuous release points for U1). Unit 2 Liquid Continuous Releases:
Table 1-2B Hatch Site Continuous Releases:
Table 1-2C 1.10 Liquid Effluents 
-Abnormal Releases There were no abnormal liquid releases for this reporting period.
Table 1*1A HIItd NtIIefMt RAD10ACT'l'Yf EfflLUENT RRIE.A.Sf REPORT* IJqIiIId Elllueftb 
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'it1UEH15 
:t4"E',U7 lh4E'05 319&#xa3;,00 ?..Ct1iHl4i 1.J3[:-00 Uot'06 UI<5E-03 LD)!" ,01 3.77E-01 3.17E-07 !U7&#xa3;Hl1 6.ti1&#xa3;{!i 
: 11. IXE 1" 00 lAS'E..m G.IXE'.OO .s.H&#xa3;.(15 O.OC&#xa3;.OO 1l.t:l(J&#xa3; 00 ItlXE.OO l.3OE-D4 LllBE.iU 1.00&#xa3;<{f.f' 7.aOE-ol' UlSf{)5 4lHQtMfbKt IHICE.'!l!l 1l.000tOO O.OCE.OO fl. t).'Erl)!l fl.OCE.l)O fl.tL'E.OO 
(/;OCE.OO OJ:)OE+DC 
!I.OCE.oo 1l.000tOO OJ:)OE+OO n.ncE.oo H<'I CUrlf:.ll O.IXE'.OO And Emlr..lllined Xe-l15 G&rw; Ctt:l(J&#xa3; HID y/lotiil 11M ,tiIiWJ CIlf10II O.OtlihlMl G_At_ Ftadio.tdfylty CJ,rIelI 0,00&#xa3; H)} n ttIIs tl'Ible Inl!k:IIl!!!!;
ttI!.t n:1 VIm!!;,
at  ied'!l!i.
See fMIIl! l-'i tor mII'ln1.l1f1 Tablel-2B Hatch Nuclear RADIOACTIVE EFFLUENT REtEA,5E REPORT -Liquid Unib Slarting:
l-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nudides Released FI!IIJtIoft
* Af:tilIIII6oA PYodIIId.lII Slc69 Total For Period UtIft CW'li6 CUries 1STQwIrW J.Olf-l}S 3.071'-05 2ND QU.iIdet 5.llf-l}S 5.12f-05 lRDQuIUt l.501f-l}S 3.54&#xa3;-05 4THQlIBdet 3.97f-re l.t7f-DG TI'IdIMt Cll!'les 'USf-Q2 4.58:f-l)2 0.).310-1}2 2.1llE-I}2 DlllICII\Ied A.IId fntl1iiMld G.ties No NiK:lillIi!'>
Four'd O.OOf...QO O.OOE+OO I:..l:OE"OO 1).!lOE-..(10 Gtou Alpha Alldiolildiritv Nu::1ide.>
fCuIld C",'iI!S O.OO&#xa3;"')(j O.OOE*OO O.Oo:Jf"OO O.OOE-OO Zerces in this !.ollie indic..tes; thdt no fcd'o.:!ct:i\'ity WtlS :present ,.:It l@veIs. See T..b!e 1-4 for typicdl minirr",m  cor.ce'ltr#.&#xa3;II1S.
Table 1-28 Hatch Nuefear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit:: Starting:
1-lan-l010 Ending: 31-Dec-2010 BakhMode Nudides Released Unit 1STQvarter FIiUiOft
* AdiYatiol!l CJ.Jtllf!S Q,OOE+fJO 1.&*]6 CUf/es 0.001:+00 V",>-S!! CI.I!IeI'.
O,OOE+OO ({rID 0.001:+00 Fe* 55 0.001'+00 H31 CUI>e5 0.001'+00 H31 (1Jf<es 0.001:+00 "111*51' O.OOE+<JQ Mn-S6 Cl.lleS O.OOf+OO ffa*24 OJXIE+OO NI:J..95 Cl..tiIie!;
O.OOE+OO Nlr'l1 0.1):)&#xa3;+<)0 Sf-59 0.00&#xa3;+00 St*gl Cut.es 0.001'+00 St-92 CutIel O.OOE+OO Y*"HM 0.001'+00 CtrleS 0.001:+00 
&#xa3;5*136 CUfiie5 (!.OOE+<:tO CiJIle5 O.OOE+OO La* i40 CI.I!1e:.
0.ooE+<30 r(.-99M CI.I!1e:.
0.001:+00 ZIHS9M CUfiie5 0.011:.+00 2ND QIW'tB O.l>>)E.ao 1.111:,01\
O.OOE"'OO 9,73&#xa3;'05 !U4E*OS ".64E-07 0.711:-07 
],011:-06 0.001'+00 LOBE-OS J.!l1Nfl 0.001':+00 
:L94f-05 0.001'+00 O.OOE'-oo 0.00&#xa3;...00 2 . .53&#xa3;*05 (1.00&#xa3;+00 HI6E*06 O.OOE"'OO 0.001:.. 00 0.001:.+00 lRDQuat'tef 31l1f..{l!i 2.411:.115 2EE-OS g.ln*OS :UHf-OS 2.,\HE-OS 
*U30E-OS 6.441'-05 L9OE-QS L66N14 Q.OOf....oo Ul6E-05 2,16.&#xa3;-04 535E-05 536E-05 1.94E,05 ],7ll<l:-05 2,27I:-OS 4,.&11:*05 4.JS;E-05 L7::1f-OS 9,fiH..fJ4 4TH Qual'tet O.OOf ..OO O.OOf"OO 0.00f..00 0,001'+00 0.00f"'.]C>
O.OOE+OO O.ooE"OO O.OOE"OO O.IXlf"OO 0.00&#xa3;.00 0.00f ...00 O.C<JE* 'JO O.fJlllhoo 
...oo 0.1):1&#xa3;"00 0,(;,.:1&#xa3; 
.. 00 0.001'''00 Q.OOf..,JO 0.1.)01:"00 0.1:<< .. 00 o.r<<....oo O.ooe-oo O.OOE+OO T.rtal FOt' Period CUries D,OOE+OO in tili.s td ble indicdtes tr1<lt no WdS present..t levels. See T .. bIe 1-4 fortypk.dl minin:fr.iim detectcJble corlCem:rdtlons.,
Table 1-2.8 Hatch Nuclear EFFLUENT RELEASE REPORT Liquid Unit:: 2 Starting:
1-Jan-2010 Ending: 31-Dec-10l0 aatchMode Nudides Released TriUom H-3 Ullit CI.lI1es t.STQIW'W IH.t.lf"OO 
'9.92E-Dl 3RDQualUt 4.54E1-00 o..OOE+OO DilSOllIed AmI Enttaii'led Gties Total foot Period Ca.tlfS CUrieil 0.00&#xa3; .. 00 O.OOE+OO 0.00&#xa3;+0&#xa3;1 1.4!!E..o.5 2.C3f-4JtS 1!1E-llS 9.21f-!l5 2.3!lE-tl4 131&#xa3;-04 0.00&#xa3;"00 O.OOf+Ofl o.OO!'+oo GroIi$S Alpha RadIoadiV'lty (,,,,... O.OOf..OO Hl9E*117 3.69E-D7 B.OOhOO Zeroes in this tdOie indk",tes; m..t flO rllld'iic...cti'llity prec-ent "t lewis. See T .. ble 1-4 tbr 1:\1-0:""" minirw",," detectclb!e COI1ICe>"iVdt'Q1S.
Table. I-X Hatch Nuclear RADIOACTIVE EFFLUENT RElEA.SE REPORT -Liquid Unit: starting:
I-Jan-2010 E.nding:
Continuous Mode Nudides Released Flulen
* Adi'vatioft PtomUD St*89 To'" for Period Unlt CWieJI 3.071:-4>5 3"07f..oS lNDQWIrtet S.12f-4>:S 5.1lf-GS lAD Qllarter 3.54E-05 3.Me-DS 4TH Qualter 3.9iE-ff.. 
].971:-116 Trltiwm H-3 "U5E*02 "l.611f"{)2 6.33E-{}1 2.11lE-1l2 DltJOfw!d And fllbaifted GtiIi!S NQ NrJdl/llo:;S FOdM (tI:'iIeS.
0.00&#xa3; .. 00 O.fAlE"OO IH10f"00 IiJlIJE ...OO Gloss Rllldloadlvlty No Nu(j\(je; Fut.."'ld 
(".rileS.
0.00&#xa3;-00 0.r.>'Jf.400 O.OOE-OO 0.00&#xa3; .. 00 Zeroes in this 1A!:4e indic..tes tr.cIt no radO<tc:tivity 
'NilS l)fe'Sent itt  ieYeis, SEe T..hle 1-4 for typ-lc.il minimllJm detertdble CClf\CE!I"I!J
..tions.
Table I-X Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEA-liE REPORT -Uquid Unib Starting:
I-Jan-2010 Ending:
Batch Mode Nuclides Released Uftft 1ST Qmu1i!t' Fl:.Urioo
* At:ti\IlIiaaa Ptodl.idS 
';"92 CUIle!; O.OOE+<JO CurieS O.oof..oo c>>-sa Cl.Ille!i O.oof+OO C!>-6>:1 O.OOE+OO Fe--55 Curie'!. O,ooE+OO H31 O.OOf..oo H33 Cur'>!!lS O.oof+<lO Mn-54 CUIle!; 0.00&#xa3;0+00 Mr)-56 CUIie'!. O.OOE+fJO tia-24 O.OOE+fJO NIH!S O.ooE..oo Nti-97 CUIie'!. O,ooE+OO 5II-S9 CIJfie'!.
O.OOE+OO 511*91 O.OOE+<JO 
'"'*92 Cu!'iies O.l)JE..oo Y"91M CI.Iflie$
O.ooE+'JO Zll-&5 CUl1S O.OOE+OO Al.>-l99 wieS 0.001':+00 Cs,.1l6 (".l&#xa5;les CI.OOf+(lO C!.J;\e; O.OOf+OO la-!410 Curt<'!$ O.OOE+OO Tc-99M tLOOE+<lO Z,)-i>9M CUft<'!$ O.ooE..oo OJXlE..
U12*(III lJilJf*04 lU1E-07 t..77f-Ul 2.94f-OS 329E-05 2,15&#xa3;*04 3 Jil1f-O'l O,ooE+1.lO 
;L99'E-OS O,OOE+oo 0.001':"00 0.001:,,00 2.5lf..1)5 1.33f-06 O.OOf"";}O 5..QSH14 0.00&#xa3;+00 0.001:"'00 UOf..1)5 1.14&#xa3;-03 lRD QuilI1et ]011:*05 1.'l1f-05 2:93&#xa3;-05 L5&E-04 7.321:*05 2.9U-OS 41.131:-05 7 . .89&#xa3;*05 L9N,-OS 2. 17E-(II1 O.OOE"OO UI&E*06 2.16t-(II1 5.38.&#xa3;*05 5.36f*06 7.351'*1)5 l.94f-05 O.OOE+OO 3.70&#xa3;*05 1.17f-04 "'ME-OS '1.351:-05 L71:f..OS 1.2!J&#xa3;-Q3 41lf QUarbtt O.OOf. ....)O O.OOf+oo O.i)X"OO O.((IE..;.OO O.OOE+OO 0.00&#xa3;:+00 O.OOf ...oo 0.001: ...')0 O.CoOE+'JO 0.001:..00 0.00&#xa3;:"00 O'c(JE... OC, 1),00E....00 0,00&#xa3;:"'00 O.{)X+OO O.OOf"'OO 0.00[400 O.OOf-OO o.ooe..oo O.OOE+OO O.fltlE+OO (1.1;.)&#xa3;+00 0-001:+00 Total Fot Period CUries D.OQf+OO Zer.:::.e!>
in this tal:ie indkdtes t!'idt no Wd.$  IeYels. See Tdbie 1-4 for ty:;.i::d!
minimum detett.tble COOCel'ltl'.r!.?Ms.
Tablel-2C Hatch Nuclear Plant RADlOAcnve EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
I-lan-2010 Ending:
Batch Mode r+udides Released Unit 1STQUar'bU 3M QIlatbY" 4TH QUarter Tliliillfl Ii*) CIXleS uJ)Jf--OO L.12E-+t.ll L54E+Ol ()j'Xlf+OD ANI ffttNIth!td GDes xe-BJ xe-US Total fOt Period Cu"" O.OOf.+OO O.OOf+OD 1.07E-GS 3.5SE-QS '9.2LE-oS L39E-t<4 3.31&#xa3;-04 1i.D>Jf.oo D.D>Jf+OO O.OOE+OO Groll. AfptIIli RadlOactiwity CIl!I'Iei O.OOE"'OO 6.21f.1)7 1.+:::E-OO D.OOE+OO Zeroes in this indicc1te5 N no r.diodctivity
_ pneS!!l1t c;;t deteo:t.c:hie levels.. See T..ble 1-4 for ty;>"ol minim,,"m detect:tble cl:ll'ICerb
..1i::m., 18 Table 1-3A Hatm Nuclear RADIOACTIVE EFflUENT RELEASE REPORT -Doses to a member of the public due to Liquid Unit: starting:
I-Jan-2010 Ending:
Cumulative Doses Per Quarter Orgill" OOCMLmt UIlIIs 1ST 'MiDDeN 2NDQtt %OOCM 3IIDQtt 4THQtt 'MiDOCM BI.'.Ir!e 5.00E+00 rnRero OJH1E+OO 13.001:+00 UllE*{f3 3.76fAlfl S..3OE-fH 1.06E-02 O.OCf+OO 0.00&#xa3;+00 GHi S.OOE"'OO mRero O.lllJf+OO 0.001:+00 2.ZSf-'J4 4.5CE..()3 1.1:4E*04 2A91HJ3 O.OCE+OO O.OC>E+{(l lCl1ney 5.00E+00 mRflnl 0.001:+00 OlJOE+1l!J 9.49E.(J4 L9OI:-i)2 .lZU;..f)4 I.L41E-CO O.OOf+OO 0.00'1:+00 LiYer S.OOE"OO mReYl O.OC*+OO O.lJOE+OO Z.EOE*03 5.3c*-1}2 8.atf*04 UiOE-Q2 O.OOf+OO 0.00&#xa3;+00 LLe\Q S.r)JE+OO mRif'!l O.OIIE+OO O'<:lOE+OO 3.Ei7E*{j4 7.34e-03 1.S6E-04 3.13H13 O.OIIE+OO O.OCIE+OO Thyl'Okl mRero O.OIIE+OO 0.001:+00 7.00E*(J5 1.58E-1}3 7.46f-05 Lo49E*Q] O.OOE+oo Q.OOE+oo 1.51JE+OO mRero O.OIIE+\))
IJ.IJGE+OO 1.nf-03 UIlf-tl1 5.53f-04 3Ai9f-((2 O.OIIE+OO 0.0CIE+00 Cumulative Doses per Veal' Orgill. ODCM Lmt Unils Year to ElIding Date %ODCM Limit BciIe 1.00E+01 It)Rero 2.41E-<)3 2.o4lE-02 
'I'W( INDMDUAL liQUID I MtII Ali/li Cum 0\1.:111)
I..i:q Dose GH.i II'tRero l.SOE..IJf J.5OE'03 MAX lNDMDUAl liQUID l Mull. Anl\ Cutr, 0I9i11fl liq Dose Kidflli!'l' l.IXlE"'Ol rYlRem 1.:17E-03 127&#xa3;-02 MAX lNDMDUAl UQUID f At.1vIt Arm Cum 0I9GfI uq Dose LOOE ..m mRenl 3.45E*{)3 
.1.0451:-02 .MJ\X INDMDUAl liqUID r Mull Arm (1,,'0  tiiq r:>ai:e Lt.ri9 u:...jf..m mRflnI S.23E./J4 5.231:-03 MI\:( INI>MDUAl liQUID I Ad:III Afln Cwm 0I9i!1i1 tiiq Dose TI1&#xa5;l'Oi:1 1.00E-"0l 
/fiReI'll 1.5oCE-*J4 151E-0:3 MAX lNDMDUM. UQUlD I M:JII Arm Cum Dtgilil I.kl Oose T etal fiot:ly 3.00E"'OO mRero 2.32E.{JJ 7J'SE-Q2 MAX INI)fJlDUAl UQUlD .. Arm Clltn Tot ilO:Iy lJq Table 1-3B Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a member of t:be public due to Liquid Unit: Starii.ng: 1-)an-2010 Ending:
Cumulative Doses Per Quarter Otgall BctIe GHJli lJ&#xa5;a' LurH;i Tl!vlltltl TotalllodY ODCMLmt 5.00e..oo S.f)JE+OO 5.00e..oo 5.00e..oo 5.0:111:.. 00 5.Ollli:"OO 1.9JE+OO Ullib IJllRem mRml mRem ffrRem mReiTI mRem mRem 1STQtr S.3n..Q6 lASE-06 S.!!BE-07 5.!!BE*Ol 5.88&#xa3;-07 5.!!BE*Ol 7.42&#xa3;*07 I.07E..(J4 2.saE-(15 1.UlE..(J5 
!.Hlf-05 1.18&#xa3;-(15 
!..18E-05 4.S>5fA'J5 2NDQtr 1.51iE-(J$
1.70E..(JS l.lJE-(J$
2.ZfJE*'J5 9.93E..(J6 1.21E-<JS 1.78E-05 ,*,OOCM 3.llE-M HIE-M 2.61E-M 4A1E-M 1.9!lE*[)4 2AlE-04 U!lE-1)3 ].IU)Qtr 1.26E-IM 1.25*f.-IM 9.11E-1l5 1.881:-6'1 S.3&E-05 2.fI3E-C'4 1.4O"f.6'1 2;52&#xa3;*03 2.50&#xa3;-03 USE-03 3.761.:-113 Inn-OJ 5.JSE*OJ 9.JIE*Q3 4TH Itl:lSE*07 4jjOE..Q7 3.ttlE-O]
3.L6E*07 3.l6E-07 3.t6E-07 3.42E..Q7 1.1!f.lE*(15 9.roE..Q6.
0.121.:..(16 6.32E*()6 f..32E..(16 0.321.:*':16 l.2'SN1S Cumulativ1!
Doses. Year Orpll Booe GHJi liwlr ll.ID9 Tl!vrol:!
ODCM Lmt 1.00f"'Ol UY.JE+Ol UX1E ..Ol 1.00f...Q1 I.O(lf .. Ql HI.lf.Ql 3.1:..1&#xa3;,;,00 Ullib ItlRerrI mRem mRem mRelu InRem IYII?.ero irlRem Year 10 Elldillg Date 1.4Sf*M 1.44E-M !.07f..(J4 
:UIE-M i).-44E-1J5 1.81E..(J4 1.59E-M ,*,ODCM L4$E*OJ 1.44&#xa3;-OJ UIJE-1l3 2.llE-ro 0.4-4&#xa3;-04 UHf-OJ 52l!iE-03 lltea!pblr M"-X INDMDUAL UQuro I Aaf.llt MAl( INDl'lIDUAL UQUJD f AI'.Jllft MAl( INDMDUAI.
llQUlD I MIlt M"-X INDMDUAl UQuro .. Mult MAl( INDMDUAl UQUID I M ..!l1 MAl( INOl'.'lDUIiL UQUlD f A..'''ull M"-X INDMDUAL UQUID l A:11.l1t Limit Arm cmn Uq .t:\C6e Mn Cl:m t:l\'9i11!l *Oose Mn CIJ'tll Uq !:lase Mn Cldl\ f..v9i1>1l uq f:i!:!!ie Ann CIil\tU o,gi!ln l.iq f:i!:!!ie Mil Clltll Anll CI..""l Tot Ilal'y Table 1-4 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT -2010 MINIMUM DETECTABLE CONCENTRA T/ONS -LIQUID SAMPLE ANAL YSES STARTING:
1-Jan-2010 ENDING: 31-Dec-2010 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples. RADIONUCLIDE Mn-54 Fe-59 Co-5B Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 1-131 Xe-135 Fe-55 Sr-B9 Sr-90 H-3 MDC UNITS 1.97E-OB uCi/ml 3.94E-OB uCi/ml 1.59E-OB uCi/ml 1.72E-OB uCi/ml 2.92E-OB uCilrnl 1.20E-07 uCi/ml 1.75E-OB uCi/ml 1.62E-OB uCi/rnl 1.92E-OB uCi/ml B.B3E-OB uCi/ml 1.43E-OB uCi/ml 1.03E-OB uCilml 2.34E-OB uCilml 1.44E-OB uCi/rnl B.5OE-09 uCi/ml 6.00E-07 uCi/ml Table I-SA Hatd'l RADIOA.C'tIVE EJllF1UDIT REL:fASE ePORT -staffing:
l-Jan-Z01O E ..
31-Dec-:KI10 L I'iUmb!':f c! bi'rtd1 Unlb 3R:D QUIIIItiItf 
....,T<<.rds 0 Jq; 51 0 % 2. 1$1 I3M!I'I r I\ItntJtr::!i i-!I.mE,.!D S.1SE+III 'J'.!lIlt'H:E !tOOEtOO 3L Iob.'<imum 
!:'.II"ne peOOd f,or' 3i Gmt! I MJ1lltir:s 11!JE,..*!12 J.7'rd:t02 ll.coetOO 
: 4. I:'iIrni!':
pcrt:.d f'af a t:atrh { I\Itnl.ltr.:&#xa3; i !l.mE+OO 1,.::!SE,..m l...l!iE+02 U.ooftOO i.::!SE+ljJ 
: 5. I'IIIrAtrLm I:'iIrni!':
peI'!a:I f'af II t:.1tt:'.h I MntJtr:j; !l.U,..OO 
!LlI)E+Ol 
!J..ooEi'OO 8.:IDEtOL 
: 6. 1'bi!I' durtnQ c! Ii:t kJA:! d!J!Wt lntn i1 I'klwI\fIQ
* 10:5 ) Z.16E1"l)i 35LE+l)i U1E,.04 ;:; .:'S!iFt*
0:-1 
'!r'J..t:
Ir, the Table 1-58 Hatch Nuclear RAOIOACTIVE EffLUENT RELEASE REPORT -liquid Effluents 
-Batch Release Unit: starting:
1-Jan-2010 Units lSTQUiWter lNOQuaftet lRD Qti.at1:eI 4THQuaftet Year Totals 1. Number or C ., 34 0 41 1. TotaiIlimE!
perk:::d fill' Batal ( MhlUtf!!1j ) O..o.1E+OO 6.OClE"'02 3.71E"03 O.OOE+OO ,4,40E...0] 1. MaXlnlllm time pettld Vet a I!J<i!tdl; release ) O.o.1E-+<..lO U4E..OZ L25E"'02 O.OOE"'OO I.!'iE""02 4.11.$". time !I)I'!tIOd fOr ill batd! ( ) O.o.1E+OO 9.S5E4!-Ol 1.09E+Q2 0.00&#xa3;....0(;* LD7E"'02 5. Miniftlilfil trne pef)oo I'ct a tatch re1ea!ie ( Mir#Jtf!!1j ) O.o.1E+OO B.4iJE"'Cl 7.3f.lf401 O.OOE...OO 7.3OE ...01 Ii. Ioverage sb'eam fI<:tAJ rl reft>..ase at Iiq;Jid etI'kIent lmo a 11I:M'1rtg stteam .. ( CPS 2.76f4{14 3.51E""M 1.J2E",04 3.55E+03 1.!}3f+Q4 tPJs tat 1ft l1he Station P'atametf1S Tabfe 1-6A Hatch Nudear RADIOACTIVE EFFlUENT RELEASE REPORT -Liquid Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending: 31-0ec-2010 UIIiib lSTQwIrter 2HD QUarter lRD QlUlrter 4TH QUarter YearTabls 
: t. Nuftlbet ciI' 0 0 0 0 0 2_ TCJtaIlilf'le fa M ( MifllUti!s ) 0.ooE4oo 0.00E400 {).J)JE...OO C<.I:*JE"")o 
{j.00E---00 ], IJ,axilfllJf'!l TIJ'11e f(jf A ( Mm.Jti!s ) O.ooE+OO O.ooE"OO 1).!):lE...OO O.l)(IE...')o 0.00["'00 
: 4. Average Ttme: n::.t A (, ) O.OOE"'oo 0.00["'00 0.1):1&#xa3; ...00 O.OOE-OO {).OOE...OO S. IJ2fliI111bffi Tiitne f(jf A (
O.OOE'"00 O.oof"'OI) 0.00[...00 r:)'cOE....oo O. ar:tivily I'br all (
O.OOE"'OO O.CJX"'OO O.ooE"'OO 0.00&#xa3;...00 u.OOE*OO Table 1-68 Hatch Nudear RADIOACTIVE EFFLUENT RELEASE REPORT -liquid Effluents -Abnormal Release Unit: Starting:
1-Jan-201O Ending: 31-0ec-2010 UnitS 2ND QUarter lRDQuatIs 4TH Qtaalter YeatTotats 
: 1. I'twnt:er af 0 a 0 a 0 2. TIltilIi TIme f<l( R*ear.es ) O.OOE4-00 D.00E400 O.OOE"'OO O.OOf...oo D.ool:+OD 
: 3. MaXlrrllJfIl TIJ!lIi! FOf A ( Mil'!i.ut*es)
OJ)JE'HlO O.OOE+OO 0.00E+00 D.oo&#xa3;+OO IJ.OOI:+OD 
: 4. A\o'eI. T1frle fut A lteIaase ( ) O.OOE+OO O.l):J&#xa3;"OO 0.*00&#xa3;:"'00 0.00f+00 ftOOE ....OO 5.,
T!iiIle FOf A Release ( Minutes ) O.ooE+OO O.OOE+OO 0.00&#xa3;"'00 D.OOf+oo D.ooE+OO Ii, loti!!! aa:tilo'il'( I'i:lf all ( Curies ) O.ooE"'OO 0.00f"'00 D.OOE+OO O.OOf+OO 0.001:+00 Table 1-6(: Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -liquid Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending: 31-0ec-2010 Unib 1ST Quaftet' 2ND QoiN'tItl!;t 4TH Quarttit' YMrTcblls 
: 1. NU(I:)I:W or (I 0 (I 0 0 2. TIlI.ailI TIme fa M Releases Mlndtes ) O.ooE...OO 0.00f ...00 D.OOE ...OO D.OOE+OO O.OOE....oo 3. Maxiit'llllfl T\0'1'!1!l ft.If A Reil!!iil!i@ ( MIrilutI'!S j O.ooE+OO O.OOE+OO .n.OOE"OO D.OO&#xa3;*OO [)J.MlE41D 
", l"Ime IiOi' A ': MlnllJtes ) o.ooe.oo 0.00f .. 00 O.ooE"'OO D.OOE ...OO {HOE+00 !L Milnill)1.I!tn TIfflJe ft.If A Release ( MlnllJtl!!S ) O.ooE*OO O.ooE+OO O.ooE"OO 0.00&#xa3;*00 D.OOE+OO &. TIlI.ailI i'lI::tMl';
Itlf all ( Cut1es) O.ooE*OO 0.00f ...00 ,o.C<lE+OI)
D.I:(JE4-oo O.OOE ....oo Gaseous Effluents Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2. 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: 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, For lodine-131, lodine-133, 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. 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: 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 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. Doses To A Member of the Public The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-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. During any calendar quarter: Less than or equal to 7.5 mrems to any organ. During any calendar year: Less than or equal to 15 mrems to any organ.
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. 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: Noble gas samples are collected by grab sampling monthly. Tritium samples are collected by grab sampling monthly. Radioiodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period. Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period. The 7-day particulate filters above are analyzed for gross alpha activity. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the samples are analyzed for Sr-89 and Sr-90. Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, the dose rates associated with gaseous releases, and the cumulative doses for the current quarter and year. This task is normally performed with computer assistance.
The noble gas grab sample analysis results are used along with maximum expected release flow rates from each of the four vents to calculate monitor setpoints for the gaseous effluent monitors serving the four release points. Calculation of monitor setpoints is described in the ODCM. Typically achieved minimum detectable concentrations for gaseous effluents sample and analyses are reported in Table 2-6. For each release period, released radioactivity, dose rates, and cumulative doses are calculated.
Cumulative dose results are tabulated along with the percent of the ODCM limit for each release, for the current quarter and year. 28 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow: 2.2.2. 1 Fission and 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 aDCM 3.1.2 for noble gases, radioiodine, tritium, and particulates.
Dose rate calculation methodology is presented in the aDCM. 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 aDCM 3.1.3. The current percent of the aDCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the aDCM. 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 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.
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 aDCM 3.1.2 Doses due to radioiodine, tritium and particulates are calculated for the controlling receptor, which is described in the aDCM. 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 aDCM 3.1.4. The current percent of aDCM 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 Error Estimation 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.
Fission and activation total release was calculated from sample analysis results and release point flow rates. Statistical error Counting equipment calibration Vent flow rates Non-steady release rates TOTAL ERROR 1-131 releases were calculated from each weekly sample. Statistical error Counting equipment calibration Vent flow rates Vent sample flow rates Non-steady release rates Losses from charcoal cartridges TOTAL ERROR 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% !\Jon-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%
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 1 A, 18, and 1 C are found in this report as Tables 2-1A, 2-18, 2-1C, 2-2A, ,2-28, 2-2C, 2-3A, 2-38, 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, 2-18, and 2-1 C, total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each category for each quarter. However, the percent of the ODCM limits are not applicable because we have no curie limits for gaseous releases.
Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2. Dose rates due to noble gas releases, and due to radioiodine, tritium, and particulates were calculated as part of the pre-release and post-release permits on individual permits. No limits were exceeded for this reporting period. Gross alpha radioactivity is reported in Table 2-1A, 2-18, and 2-1C, as curies released in each quarter. Limits for cumulative beta and garnma air doses due to noble gases are speci'fied in ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A and 2-48, 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 2-58, along with percent of ODCM limits.
2.4 Radiological Impact Due to Gaseous Releases Dose rates due to noble gas release were calculated for the site in accordance with aDCM 3.1.2. Dose rates due to radioiodine, tritium, and particulates in gaseous releases were calculated in accordance with aDCM 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 aDCM 3.1 .3. These results are presented in Tables 2-4A and 2-48. 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 aDCM 3.1.4. These results are presented in Tables 2-5A and 2-58. Dose rates and doses were calculated using the methodology presented in the aDCM. 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.
Tabfe 2-1A Hatch Nuclear Plant RADIOACTIVE EFFlUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Unit! Starting:
l-Jan-2010 Of fftlluelllt UnHs 1STQUat'W lRO QIIiItlet A. fiDiOf!I ArId AdivatlOft GalleS 1. T01aI Ri!le:ase 
:L Re1ie!iIse r.!iIe fcf 3. d Limit B. R.adIoil.lolllrle:t 
: 1. TOlfali iodIne-131 
: 2. liMe rCJ pt!fiQ'l ],
timlt c:. ftwtlClflllltes 
: 1. Par1J(lJlate; ( Halr*lives. 
':> a Days) :L AYter. tate fo{ 
: 3. Per{,.efllt d ApJ:jic.atlle L'mIt D. TI1t1ut11l 
: 1. Tbtili! Reie!lse 1. A\'i!tage RI:'!'iea!>!! 
:t.
d limit E. GlOSS AIpIlIa 1. Totat Reie!lse 1. AYErt;ge Re!ea!illl tale f1:f pt!fiO:!
* Applicable dre 6.781:...00 1.4ZE..01 :U6E....01 Bll!E-01 l.f&#xa5;.If"OO 2.7.11E"'00 
'Ni " (!.VieS L19f-1)4j 32\.OE*04 2.27HIS 4.19HlS 2.51E-DS '" " * 
;UBE-05 SA2E-OS 7. Lfi,ises:.
2]71:-06 
...% 1.76E...02 5J.l4E... OO 
..1::1!jses:.
2.Z3E... m 639E-01 7.OC1[*01 
% * "... Ci.II'!eS 0.00&#xa3;+00 o.ooe..OO O.C-lE ...OO t.t:J,Ises:.
0.00&#xa3;:..00 o.oct'+OO OJXIE+OO in mf1TlS of dose. See Tdbles 2-4A.-2--48, 2-5A. 2-58 of this report. 4TH Quarblr 2.47E+01 l.13E+OO .. LJIlE-j)4 1.14E-DS .. -4.86C-I)S 
: 6. Hi7E*(l6 " 4.32E-OO 5.4flE-lil DJ)QE+OO O.OJE+>JO Table 2.-18 Hatch Nudcear RAOIOACTIVE EFFLUENT RElEASE REPORT -Gaseous Effluents 
-Summation Of All Unit: starting:
1-Jan-2010 Ending: 31-Dec-2010 l'fCM! of&#xa3;1IIUent A. fiHbI AIId Adtatiofl 1. Total 
: 1. A...e:ragt? !aIle fet' 3. Pett:el1t ct Applall1e lliIt'lit B..Radioilldlne!!l 
: 1. 
!'ate fa 3. Per,rent d AppIGll1e lliIt'lit C. ttattic:uhllt!!S 
: 1. Pal1loJIates ( 
". il Days) 1. &sect;ate f!ii' perJ:'!d 3. F'ef<ellt d Appicai1e Ulillt D. Tritium 1. Total R*!ease 2. A...e:rage Reiease tet period 3. 1':1 AppiGli1e 12lllit E. Gnm. AJpIlla 1. T<1taI Re!ea5.e 1. AVi!i!I:. 
!IlIte fer peril:la Unfts Cur,es 
% CUi\eS 
% CurieS tKs CUi\eS 1STQtwter l.47E.Q1 1.81E...OO * :LSf,f-Q4 3ol$E-05 " "lti1E-05 5.92E-Oli
* 3.9SE+,OO 5J.12f-Ol 
.. 0.001.:"":10 O.():Jf"'f:lO litO Qu.wIet ),.42E...Ol 1.OOE+OO * !_51E-Q4 L92'E-OS 4111)&#xa3;-05 iU&E-Oli " 4.36&#xa3;+00 ,5.S3f-Ol
* O.l)]E...oo O.OOE+OO 3RDQuarw 2.16E...01 1.14E...00 .. 2.27E-04 2*.SS,E-OS 8.n,f..(l<S 1.04I:-IJ5 7.4aE....00 9.-1IJ;E-iil
* O.ooE"'oo a.OOE ...OO oint Quarter 2.47E+O! 3.13E..00
* 1.93E*04 2.45E-iiS 
.. S.m:'-415 7.232E-Oli " B.71E ..oo UIE...OO O.llOE ..O.OOE ..'I< AppIk:.oible limits <:Ire E!:qJres:seci in terms of dose. See T<tbles 2-4B, i-SA,. 2.-58 of this repent. 35 Tab1e2-1C Hatch Nuclear RADIOACTIVE EFFLUENT RElEASE REPORT .. Gaseous Effluents 
-Summation Of All Unit: Sta mug: 1-Jan-2010 Ending: 31-0ec-2010 Type Of Elllltent Unfts 1STQortet 2N D QIJ.ilitet 1RDQUilrte
.. 4ntQWIIter A. FiHIoI!I And Adi"atloft Gases 1. TO".at Rl!lea5e ClEi<!S 2.15E+01 2.84E .. Ol 4.32E+01 4.I;.4E+01 
: 2. A_1lIge !'!!te r(Y p!1!"ru uG/se::
3BJE..OO 5.48E..00 62liE..00 1. Petc..ellt d Api:jiGltlie Uil1If B. RadloiodiMs 
: 1. Total 131 (U!l.i!5 435E*04 4111&#xa3;*04 4.19&#xa3;*(>4 3.31E-J:>4 
: 2. A'iffilI9Cl Re!ea5e rate fu t:e'fOJ 1.IJ/5eL 552f-OS ,:LiCf-OS 5.44f-05 ".IS'E-I}S 
: 1. Perom1 d AppiGltlie l.Sl1it % C. I'llII'liwIllltei 
: 1. pamwlilte5 ( 
',. 8 Day,; ) CWl1!S U13&#xa3;*0'! 1.54&#xa3;-1)4 LOfE*!)4 2. A'/f:'Ja"e fat.! bf peOOd IJCiiseo: ,Ui9f-05 1 JOE-l)S 1. 96E.r,6 L34Of*Q5 1, P,;"a!ftt cr ApPicat#e titr<t % D. Trithift'l 
: 1. Td.al Rl!lea!ie (lEi<!S LOOE..02 9.4<:1&#xa3;"00 UOE"01 LlOf.. Ol 2. A..er1ll9'l Re!ealle 'i!!te ref ohiseo: 2.2aE.;.(]
1 U9E..00 L6SE ..00 LOSE +00 % 1. PeKl'!Ill d ltpt:liCllt#e Llnit E. Gross AJ,pba 1. TC?.2JI ReJea<.e O.l)JE+(]O 0.00&#xa3;+00 O.OOE*OO D.OOE ...iJO 2. Aver1llge 
,<lie r:x uGjseo: O.OJE*OO O.OOE+OO 0.00E+(!)
O.ooE+(1O 
., Appllcdble Ii mits "ore e:.:pressed in ref1llS of dose. See T..hies 2-4.A. 2-48, 2-5A.. 2-58 of this report.
Tabk!: 2-2A Hatch Nude.... Plant RADIOACTIVE EFFLUENT RELEASE REPORT -GaseQus Effluents 
-Elevated level Unit: Starting:
I-Jan-2010 Ending:
Continuous Mode Nudides Released Fitlklt! GaN!i Ar41 Kt-R'iH II"HJ.? Xe-13] Xe-llSM Xe-13.5 Xe-11!i Total Fot Period lOdiMll H31 H33 Tat/II For Petlod UtiJIt CUries CUries CUries ClJrIes {:Carles CUries O.lr'll!!!
Qlrite!J)
CiJf!E!S curieS CUriel 1STQmNter OJ:Df+OO 7.16&#xa3;-01 1.10&#xa3;+00 6.00E-Ol UlDE+OO 2.131:+00 6..11&#xa3;+00 Ui6f-04 2.SOf-04 4A6E...Q4 lNOQuilrtet ILJSE-tH 2.2Jf+OO 1.2&1:+00 3.S2*E+&#xa3;!J l.94E+-:JO 4.BHOO 1.421:+IU 
: 3. 15E..()4 1.-42E..()4 4.SH...Q4 lItO QtlaI1Jet' 2.57&#xa3;.(11 5.41&#xa3;-01 2.351:'+00 6.mtE-Ol 2.6JE+DH 2.7'9f+OO 1.lSEHH 4TH Qwutet O.(tOf+OO L07E+OO 2.89&#xa3;:+00 O.OC*+OO 4.19&#xa3;:+00 2.67E+OO 1.39E+Ol :LlIiE+IU 2.41&#xa3;+01 1..54E-1}4 2.33E-1>1 3.81&#xa3;-04 1.16f..()4 L63*E..()4 2.18&#xa3;-04 If Not Detected, l'Wdide is Not Report:ed.
Zeroes In this ub!!i! ;ndiC6tes th.rt no rddiOclCti*lty W<:tS present ..t dete::t:i:ttE lewIs., See T& 2-6 for WpiCdI minimum detec.'t:itE concentr.mOilS. 37 D.-131 Ta.ble2-2A Hatch Nudear RADIOACTIVE EFFLUENT RELEASE REPORT -Ga:saous Effluents 
-Elevated Level Unit: Starting:
1-Jao-2010 Ending: :U-Dec-2010 Continuous Mode Nuclides Released PlI1:iaIIatti Mn-54 eo-ss (j)<6I) SI*tl9 s.r.9I) Bi*HII H31P Totat For Perielll Tl'ltblm 1i*3 Grosl AIpI'la N<r Nlldkie!.
fi:lIlfld Uftit Ci.l'b!!!'.
Oanes 1ST QlI.iIIUr 1.13&#xa3;-07 0.001':+'30 
.11.70&#xa3;-08 LBf*D5 l.GlE-oa 3.131:-08 
..q.13f-Ofi U2f-08 1.581:-05 o.34E*0l O.OOE"'OO 2ND QINIrter O.ooE ..
O.ll!JE ..OO 3. 11f-l15 .5 ..3!!.E-{)!I 1.31 E-{}7 l..5..qE-OS 5.27&#xa3;-00 4.6U-05 7.3Of-Ol O.OOf+OO 3RD Quarter IHlOE.. oo OJlOE"oo D.OOf.. oo 4. Hf4}5 -4. 71 E-oi 3.9JE-07 2.56E-C,S 1i.000..OO 6.731-(15 L12E"OO O.OOf..oo 4TH Quartet O.OOf+oo 2.51E-08 6.1CE..();!l 
: 2. 64E-{}S Z.11E.fJ7 2.0ze-07 1.7HE-05 2.S!1E-OO 
...."71-1:15 U9E..oo !:'.OOf..*JO If Not Detected, tfudide is NO!; Reported.
Zeroes;n thls t:tble indiCd'teS th.tt no IN..:I$ pni!sent at levels. See T dble 2-6 for typiCc!1 minimum roncentrdtions.
Tabte2-2A Hatch Nuclear Pbnt RADIOACTIVE EFFLUENT REtE ASE REPORT -Gaseous Effluents 
-Elevated Level Unit: Starting:
I-Jan-2010 Ending:
BatmMode Nuclides Released Fis!Jllan GaleS '40 tJI.<</ideS f't'Icl&#xa5;.1 UnK CUlleS 1ST QWIttJ!t O.l)J&#xa3;+OO lHD Quartet 0.00&#xa3;... 00 lRDQuartet O.OJE....*JO 4nI QUaIt:et O.OOE...OO [odlRes '(0 NudideS FoIA'K! (u{J<i!S O.oo&#xa3;+<JO O.ooE"oo O.OOE ...'JO O.lXIE*OO Partl!:blates No NudideS FollOO CUlie!. 0.cX1&#xa3;...00 O.IJiJE"'OO O.OOE"OO &.IJiJE"OO Trit.ium No Nudil1e!;
Fot.ftl O.ooE"oo O.I:<IE"OO O.C"lf""JO 0.(0)&#xa3;"00 GrossAipba No NudideS FoLJfl'j CU1ieS 0.00&#xa3;"00 0.00f...00 O.ooE+oo D.OOE"'OO If Not Deted:Ed, tfwdide is Not R.eport.ed.
Zeroes 1n this t:lble ;odicdtes thdt no fddioactivity WdS present dt  levels. See T dble 2-6 fc.. t)'piccl minimum detectdh1e-cOIlcentJ.rtIDns, 39 Table 2-18 Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents 
-Elevated Level Unit: Starting:
I-Jan-2010 Ending:
Continuous Mode Nuclides Released fission Gillses ,1\1-41 Kt-SSM YJ'-87 xe-1J3 xe-n5M xe-1J5 xe-US Total For PeriOd IodiDes H3L H33 TOUI For Ul\lt Curie;; Curie> CUrie> Curie> Curie;; CUnes Curie> CUries CUriei 1STQttMtet O_OOEHXI El.uJE-I.ll 2JlOE+OO 3.SliE+00 fi.J.!!E-I.ll 4..56E+00 2.94f+00 1..47&#xa3;+01 2.18E*fYI 3.35E*04 5_S:U-04 2.BIE*r.J1 IU!lE*{}l 
: 2. 23 E+OO 1.2&E+JX) 3.52E+00 1.94&#xa3;+00 Ji.lJE+OJ lRD Quam. 2.S7E-I.ll 6AIE-0l 2.8SE+!ltJ 6.C<!'IE-I.ll 2.67E+0:1 2.79&#xa3;+00 1.1&E+01 1....1&#xa3;+01 1.UiEHll LOJif-M 1.l9f-&4 2.l3E-04 1. SJiE-!J4 2.:nE-l>'J 3.iii 7&#xa3;-04 4THQUaFtet r.J.OCE:+OO 1.07E+OO 2.SI;E+OO O.OCt:+OO Ji.ll;E+OO 2.67E+OO 1.39E+Ol 1.47&#xa3;+01 1.lEC-M 1.f.i3E-!)04 2.. 78E-D4 If NotDetect.ed, ""..:elide i!> Not Reported.
Zeroes in '&is t:tble 'ndiu.es thdt no rd!!lCl:fctiv'ty W<lS present <It detectable levels. See T dble 2-6 fur typic..1 minimum detectable coocentrdtions.
40  

H-3 Tabie2-18 Hatch Nudear Phmt RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Efevated Level Unit: starting:
i-Jan-2010 Ending:
Continuous Mode NtJdides Released PartiallllteS MI1-54 (0.56 C!>-60 5(-89 1-131P Total For Pel'h!Id Tritium Eiross Alp_ rio Nudk1es n:wnlo'J Unit CuI'!es CUfIe5 Ct.IIies Cufiies CUtIle!; CUriel Ct.IIies 1ST QIIioIftB 339H17 O.lXlf+OO VHf*07 2.541:-05 2.18f-oll 7.71'E-00 UI3f-05 iL12E-oa ::UJE-OS l.05E..OO 0.00&#xa3;;*00 2ND QlIMtet O.OOE+oo O.llOE+OO O.OOf"'OO 
.2.42f-!ltS 
: 4. HiE-Ga 1.311:-1)'1 L4/i.f-(llS O.ooE"'OO 
:UOf.-05 5.8ef-IJ1 O.ooE"OO lRDQUlI12t G.OOE"'oo O.OOf.o.OO O.OOE*OO ".HE*IiS 4.71E-1)I9 3.9Jf-{Ji' 2.561.:-05 O.OOf"'oo 6.7:Jf..OS 1.12E"00 O.oof"OO 4TH Quillrter 0.1:<<*00 2.51E-1)8 6.10E-1)8 2J:i4E-DS 2.17E-07 2.0lE..o7 1.711&#xa3;-1)5 2 * .59E-OS "'-41'&#xa3;-05 1.19E"'OO O.[JIJf ...oo if Not Detected, Nudide is Not Reported.
Zeroes:n this tdbIE indiUiteS that* no rodiOdctiVrty Wd5 present at detectitble levels. See T dOle 2-6 f<< typiU:il1 minimum detett.:t:.1E-concentr.roons, 42 Table 2-28 Hatch Nuclea!' RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents -Elevated Level Unit: Starting:
i-Jan'" 2010 Ending:
Batch Mode Nuclides Released FtuiGft Gatti f40 Nudk:le; 1'01.11\11 Ullit CU;:-es 1STQwItef 0.001:+00 lifO QIIl:IIrt.er OJXlE+OO :IRQ QuIIIrter 0.00f+00 4'TM Qilarllet 0.00&#xa3;+':10 
[odlMll rw fi)1lI\d O.OOfTOO o.ooe.oo Q.OOE+OO 0.00["00 Pal'lkslatl!!i Fro Fourid O.OOE...OO 0.00[ .. 00 0.00f+00 O.OOE*OO No tilidid!!!i Fot;rld O.ooE+OO 0.00&#xa3;+00 D.COE"OO O.OOE"'oo GlOB AJpblll No HIJdK1es fO!lIld O.OOE...;m 0.00&#xa3;+00 O.OOE.QC*
IH1(lE"'OO If Not Detected.
tt""oitie is Not Reported.
Zeroes in tr.s 1nditdtes that no r..aiOdctivity WdS p"'es.em dt levels. See T dbIe 2-6 fa" typil::dl minimum coocentrciltions.
Table Hatch Nuclear RADIOACTIVE EFflUENT RELEASE REPORT -Gaseous Effluents 
-Elevated level Releases Unit: starting:
1-Jao-2016 Ending:
Continuous Mode Nuclides Released FissIoft GaI8 1Ir"'H Kf*B5M 1Il-87 Xe-UJ :Ke-1JSM :Ke-135 :Ke-138 Total 'or Period Illidiftes H31 H3l Tcllld fQr PeIiI':Id Uflil ('Jl.lrIes O.Jries Curies Curies CuI1es Curies Curies Qarlle.& Cl..II1ie:!. CUries 1ST Quartet Q_OOiE+oo L31:+E.oo 2.12E+00 4.00f.+00 1.+1*&#xa3;+00 cL17E+00 5117E+00 2.15&#xa3;+01 3J14E-1M 6.15E-Q4.
9.99E-114 lffDQU!1er 5.&2E-01 1.68E+lAl "1.46&#xa3;+00 2.51f+00 7.04f+00 3.881:+00 8.17E+OO 2.141!+O1 
<4.1S'E-604 2.71lt-604 6.19E-G4 lRDQuartef S.HE*f.H UB:E.OO 5.70f+OtJ 1.22&#xa3;+00 5.351:+00 5.57&#xa3;+00 2.3bE+tt1 4.32&#xa3;+1:11 3.OI!-E-604 7.15&#xa3;-114 41M Quarter O.OI:E+OO 2.14E+OO 5.1\lf+OO (l.otf:+oo a.39E+OO 5.*+00 2.7J'l:+ltl 4.141:+01 3.2SE-(H s..S6E-04 if Not DetKted. N"dide is Nat Reported.
Zeroes 1n 'd)-s tdble lndic:dteS that 00 ,<tdiOdcti'l:ty W.:IS prESent.:lt levels. See T2-6 fol' typiC4' minimum detE<'t.i!l:tie cooCl!ntrdtions.
H-3 Table 2-2C Hatch Nuclear RADIOACTIVE EFflUENT RELEA.SE REPORT -Gaseous Effluents 
-Elevated Level Unit: Starting:
i-Jan-2010 Ending:
Continuous Hode Nudides Released Partkatates MI)'54 co-sa Cc.-60 Sf-90 Ba-14l> HJ!P Total fOI Period Ti'HiLlIn Grou AJpIla No Nudk:le!i.
fUIJOO U!tft. Curies Ctt!eS CUlte!I CUriIes Cwte!l CUries CUI\'eS 1ST QtI.IItM -!32f-07 OJ):lE+iJQ LS8f-07 3h7E-05 3.29f*as V:l9f*07 UI5e-t15 1..62f*(l7 S.1.1&#xa3;-05 1.69E...OO O.OOE*OO O.OOf....
o.rJlJE"'oo 5.541:-1)5 
: 9. 55,f-O!! 2.62E-I)7 3.ooE-oS S.27t-flll 8,S8E-05 132&#xa3;...00 O.I')!)f..oo lRDQUlrlet ItOOf+OO 0.00f ...00 v.!)JE+OO S.27E-Cl5 9:41E-09 7.871:*D7 5.1l1:-liS 0.00&#xa3;+00 1.35&#xa3;-04 2.l-4E.00 
{} .Dt]f 4THQUatlet O.OOE ..OO 5.Q2E*oa L22f-07 5.Z9E**j)5 
-4.34f-Oi 4.04fA)7 3.55E..f6 S.l!lE-1)S I..!JSE-OS 2.3flE....{IC' D.OOE ..OO If Not Detected, trudide is Not REj.1OIted.
ZI:!roes in  t.lble lndiCdtes th.rt no tadiOdCti..,;ty 
"".itS present <It levels. See T..ble 2-6 fa"typiCdI minimum cOficentrations.
Table 2-2C Hatch Nuclear ptant RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Elevated Level Unit: Starting:
I-Jan-2010 Ending:
Batch Mode Nuclides Released Fission GaIllS No l\Iudi!.l!e!l fi::J,"'o(!
Uftit Curies O.OOf+OO lHDQWIfle O.ooE"OO lRDQ_rter 0.001:+00 4TH Qualtet D.OOE ..OO lodmes r.f.l Nudklie!i F'C1tir1l!
cooe; OJY.IE+OO (UXlE..OO O.OOf....OO 0.0>3f..tlO Partiallateli cooe; 0.00f""'1ll 0.00f.... 00 0.001:.... 00 O.OOf,,'J!)
Trithlm No Nudi<:le!i fi::JtJOO (ules o.ooe"',)o O.!JtJE"OO 0.001: .. 00 f.}.C(lf+OO Grosl AIpIiIa He Nudkle!. Fi:rurll!
Curies O.ooE+OO O.Ilt'\E ..OO 0.00&#xa3;; .. 00 u.l)JE .. OO If Not Dl!1iI!Cted, N:...dkle is Nat: Reported.
Zeroes in th"s t:tbte 'ndic..tes thi.t nDrddiCl:lCtiv:ty 
"'dS present.itt detlact.iible levels. See T .. ble 2-6 fQf typh:.. 1 minimum detKt:t!>ie concentr.roons.
Tabfe 2-3A Hatch Nuclear RADIOACTIVE EFfLUENT RELE.ASE REPORT -Gaseous Effluents 
-Ground level Unit: 'itarting:
I-J<l0-2010 E.nding:
CoOOI'lUOUS Mode Nuclides Released FiYiOfI GiIos 
...M Ufljl Curies 1ST QtliarIer OllOf+OJ 2ND QtliarIer Qf.lOE+oo 3RD Qllartet O.OOE+[::OJ 4THQuaIter O.OOf'+OO IOdIBes HH HB Total For Period UJtles CutII!Js Curies l.25f-{lS CLOOE+oo 1.2StH)S Uii'E*QS ].421:-05 4.84E..(I5 Ul!E..&#xa3;14 1.491:-&4 2.;ltlE..ffi 2.00f-QS 4*.281:-05 Plilltiflilliites Mr;.$4 Co-f&#xa3;t 51:-89 Sr*!lO Total For PedOCl CUI'Ie; WIle; Cii/tII!Js CutII!Js Curies 2.76&#xa3;*(16 0.001'+00 3.27E-f.J6 Q1JOf+OO 1.031:-06 2.14E..(16 USE*Ofi. 3.3'1E*Ofi. (LOOHOO 1.421:-06 0.001:'+00 
.).1:101:+00 
"'.1.I7E..(16 O.OOE+OO 4.871:-06 Q.OOE+{l(]
O.I.lr,E-l-OO 1.B7E-06 1.52f*10 3.811:-06 Trititlm H-l Curle! 1.751:+02 
'UIE+CtJ '1.4t'E+Cl(]
3.BE+C>J Gross Alpila No NucLr:le:;
fCtlfld Curies Q.OOf+OJ 0.00&#xa3;+0.1 0.001:+00 O.'U+tlO If Not Detected, Il.iclide is Not REpOIted.
Zefoesin tiible AndiGrte$
th.It no T..ble 2-6 fa typic..1 minimum detlKt:cible concentr..tions.
WdS present <It det.ect:.;,ble levels.
Tabte2-3A Hatch Nuclear Plant RADIOACTIVE EFflUENT RELEASE REPORT -2010 Gaseous Effluents 
-Ground Level Releases Unit: Starting:
I-Jan-2010 Ending:
BatchHocie Nudides Released RmonGaies No t.UCIil.'les fcUld UfIit Ullies lNDQuarl.
3RDQWlrter 0.001:+00 4TH Quattet 0.00E+00 IodI_ No lIIuctiOllS uJriel lJ'oOE+OO lHlOE+OJ a.Wf&#xa5;..i.l O.lJOE+*oo Pactlalllllb!:!l 11<.) Nuckles kJurtl CUlies OllOf.+tI1 
').OOE+OO O.OOE+()'l O.OCf'+OO TI'ltI:IJm No Iluctdei UJriti!s O.iYJf+OO 0.001:+00 0.001:+00 O.OOE+f:"l Gto$sAlptt,a tIt;. Nuckles fUir,o CUllI!ii O.OOE+OO O.ooE-I-Cl:l O.,:IOf+OO O.OOE+OO If NotDe'!li!C"..ed.
f.il..dide is Not R.epo;!rt@d.
ZefOo.'i!S kn 6:5 tdble jooic..tes thdt no radiructill'ty W<lS present ",t detKt.oble-lev-els, See T"ble 2:-&#xa3; for tvoic..1 minimum detect.ble cOfIa!ntrdtions.
Table2-3B Hatch Nuclear RAOIDACTIVE EfflUENT RELEASE REPORT -Gaseous Effluents 
-Ground level Unit: Starting:
I-lan-2010 Ending:
Continuous Mode Nuclides Released fbsiGft Gases Nuckle\ fU.md lodines Hl1 Hll Total r<< Period PlllltiC1llillleiS MF",$>! SH}9 Sr*90 H31P Total for Period Ttttklm GronA/pita 
!lie. F4UCidei Frul1id Unit Curle! wries wrle! Curies CAJrl!!!;
Curle! CUrie! Ulril!S (lilies OJrIe! ClJrie!;
OJJOI:+OO 3.B4E*05 ].T3E-':l5 1.561:-05 2.55E-<ll 9.7OE.Q6 O.OOf+OO 3.B!lE.Q7 1.031:-05 2.9(1f,+00 OJ)OfH[I 0.00&#xa3;+00 4.7iJf*QS 0.11E-05 1.081:-04 f.JJ:1Of+OO 9.f.Qf..(.l6 0.00&#xa3;+00 (LOOf+OO 9.6Of-06 3]7E+1>3 0.001:+00 
:SRD QiIiIrtet (I.OOE+oo 7.28E*'llS UYlE*Q4 2,51f-04 11OOE+OO 1.%E*05 2.92&#xa3;-07 .:J.OOE+OO 1.491:-05 o.3SE+OO O.OOE+C-!l 4THQuattet O.Ol:f::+C>J l.91E.(J4 1.75f-Q4 lJ.OOE+[)1) 
!.20E-05 O.OOf+OO 2.76E-(l7 1.23f-05 1.5:!f+OO O.OOf+W if Not Detected, Nudide is Nat Reported.
Zeroes;n this tdbleindic..tes r.h..t no r.i!diOdCtiv:ty w"'s present <It detect;,hle Ie..'els.
See T",ble 2:-6 for tvDicdl minimum COflcentrdtions.
Table 2-38 Hatch Nudeal' RADIOACTIVE EFfLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
t-Jan-2010 Endingi:
aatcnMode Nuclides Released Unft 1ST QII\i!IItU lNDQwrt8 lRDQuartet 4TH fitilOft GuelI tk} Nuclides /'>ootid CUries O.\lOf+OO (LOOE+OO 0.00E+00 O.IJ!J*:+OO lodInes tk> NiJlCfrle; 
/'>0000 Curies QjXlHOO (HlOHOO OJ1I}E+L"(J 
'lOOE+ll(1 Paltlallat.es 
.>>0 IhlCl:del f*wfld CUtli!s (LOOf+OO 01lOE+OO O.OOf+t(J O.o:lCE+OO Tri'tflIlM tlO U<<1ides /'>oofld Curlei O.o:IOf+OO 0001:'+00 Q,OOE+OO 0.':0:+00 GtoHAlpIIA t.ID N<<1:del /'>oolld 0Jtlei I.VJOf+OO 0.01:'1:+00 0.001:+00 a.OOE+OO D' Not Detected, N\.idide is Not R!!pO!tl!!d, Zeroes In this 't,ible lndic.oteS thd!: no ;ddiOdctiv'ty WdS present ..t detect:..ble levels.. See T dble 2-6 f.rM. t')'Pk..1 minimum detec:tDl:>le conc.entrdtions.
Table Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Ga:seous Effluents 
-Ground Level Unit: Starting:
l-Jan-2010 Ending:
Continuous Mode Nuclides Released fillion GUes No N..:1iI:I!!S tJ:ldiftes 
[-131 Total Fot PeriOd Paltic:ufates Mfl.5<I (0.60 SHl*9 I*HIP Total Fot Peticd Tl'itlllm H-J GtoaAlplla tto 1I'iJCk1es Ullit C<lrlei Ciltles GJril!!i Cllril!!i C"riI!!i G.Jrles Curies CLII'Ites Curies CUries 1ST Qv.iIftet' O.OOE+OO S,!)jf-aS 3.73E-<l5 B.81E-oS 3mE-06 i:LOOE+OO L3OE.{/S O.oCIE+OJ 3.88E.{/7 1.6ft-oS 1.78&#xa3;+02 O.OOf+-I)[J 1ft'DQtwtw 
'JllOf+OO 6.25E..Q5 7.9I!!f . ..Q5 1.4l:E-04 2.14E-06 L9SE.Q6 1.19E.{fS QJ.1Of+oo 
-3.00f+00 1.701:-05 OOClE+oo lRDQUartef O.OOf+[lQ 1.21E-64 2.1t5E..(J4 4.061:-04 D.nOHoo 0.00&#xa3;+00 Ui<SE..Q5 1.92E-<l7 ilOOf+W 1.97E-05 1.00E+OI a.o!lf+OO 4'TH QINItter (HJre+t()
9.9SE.{/!;
2.UIE*Q4 3.1111:-04 1.52E*1!i 2.76&#xa3;-07 1.61E-05 UJ1E+OI If Not Det.ed:ed, !'+.;dide is Not Reported.
Zeroes in th's t:!hIe indlc...tes thdt no r..diOotcti
..';t>f \'i'dS pt'es.ent dt levels. Se!1! T dhle 2-6 fer typlc...1 minimum detKt:dble coocentr..tians.
Table 2-3C Hat<:h Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground level Unit: Site Starting:
l-.lan-lOlO Ending: ;U-Dec-2010 BatchMcde Nuclides Released fIssioft G.ases No Nuctdl!S f{)uoo UI\iI Curies 1STQwIter OME+oo 2ND Qu.ttter 0,00&#xa3;+00 lRDQua..... {lool:+oo 4THQuamr O.OOE+OIJ 10lIl_
Curle; OJ:lOE+OO 000&#xa3;+00 O.OOE+C&#xa5;l O.OOE+OO ParticulallH No fhJCk1el fcuoo {".uriel (tOC!f+OO 0.00E+00 0.00E+00 0.0&#xa3;'&#xa3;:+1);]
Tritfwft No N.xliJes FwOO Curies OJlO!'+oo (tOOE+OO O.OOE+t()
O.*Jre+lJO Grou AlpIt:a No 't",:1iJes foooo Cu!ies o .OOE +OJ (Loof+OO 0.001:+0<3 O.OOE+t1J If Not Detected, is. Not Reported.
Zeroes;n tT.is t4b!e inrlu.es th.:.t no rddiQ:lCtiv;ty W"S pl'esent .itt detect.rble lelfe!s..
See T dble 2-6 fe.' tfPiCdI minimum deted:i.hle 
;:OOOl!ntl
..tions..
Table Hatch Nudeai' RADIOACTIVE EFFLUENT RElEASE REPORT Air Doses Due to Gaseous Unib Starting:
I-Jan-lOW Ending: 31-Dec-2010 Cumul.ative Doses Per Qu.lJrter TJpe Gi!!lnma Air IJ.eIa lilt ODCMlml 51JOf"OO LOOf+Ol unitS fI1I'l.aa rrlRail 1STQtr 6.67E-05 S.05f-t:5 
..,. ODCM 1.37f4JJ 5.05f414 2NDQtt i.ME-04 L12f*04 'lMoOOCM L!9E-Ol L12E-0l lRDQft J.25E-{)4 1.DIE*"J"I 
'lMo ODCM 6.SQH!.l Vllf-Ol 4THQtt 3.75f-(lol 2.22E-{)4 
'li400DCM 7."I9f-l})
2.D!:,-!)J Cumulative Doses Per Year Type or ItilclaUOII Beta ODeM I.mt u.JE+O! 2.WE .. lU Unlb mRl'td 1flRl'td YIlIM to I!ftd Date S.85E*oq 9.l2E..(J3 2.93E-<l) SITE IiOJNC\l\JtY I 0i1h1 MJV( IND. AIRBORNE eNid UHf .AIIn Cum Gamma AiiII:IO!ill' Mil Cum Bea.AlrdQ!ie Table 2-48 Hatch Nuclear RADIOACTIVE EFFLUENT RElEASE REPORT -Air Doses Due to Gaseous Unit: Starting:
1-Jan-101O Ending: 31-0ec-2010 Cumulative Doses Per Qua.rter Type cf RatfiatJ.oo Gammalllr 
!\eta Alr aDeM Latl LOOf+Ol lMll mRali1 mRilil iSTQtt LZ1E-{)l l.O]E-{)l 
%0001 2.*m:-D3 U17E-{)3 2ND Ott Ui4E-!)q UZE*!)q %OOCN :t2<.lE-l:ll 1.12E-03 3RDQIr ].25E"(>> 
%ODCM iL<;Of-03 2.011:-03 4THQtr 3.751:,,(>>
2.22E*64 'MoODCM 7.4I'l'E-ID 2.22f-OJ Cumulative Doses Per Vear Tn-of lilMfiatlol!l Gamffr.a Air BetiI Ait OIXMLmt 1.00&#xa3;...1.11 2.00&#xa3;+01 lMltl mftild rnftild Yeat to !ltd Dile 91l4E*()!I iL.2f..()!I %OOCM 9.B'lE-<J3 3.21E""J3 SITE OOUNDARY l CI'lM MAX RID. AIREl)1l;NE 
.. Child Umit Culll (".amwliI Mn Cum Beta JlJrdOiiE!
Table2-5A Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses To A Mecmber Of The public Due To Radioiodines, Tritium, and Particulates in Gaseous Unit: Starting:
1-Jan-lOlO Ending:
Cumulative Doses Per Quarter BcfIe CiH.I'I 1G:l!'rlry llv<!t loog Tl'IytOl'I T<<iJlh"Y OOCMLmt 7.5(1[..00 1.5Cf"OO 7.5!:If"00 7.5(1[.. 00 750E"'OI:'
7.SQE""XI 7.5'(1&#xa3;+00 Units ntRl!!fIl rf1Ran mRem mRan mRem AiR<!!l'l 15TQtr 5.421"-<15 9.09[-<12 9.09&#xa3;>Q2 9JEE.(JZ 9Jl!lE.(I2 
: 9. 14E-<l1: 9.091:-<12 
%OOCM 7.23&#xa3;-04 1.211"+00 1.211"+00 1.211:+00 1.211"+00 1.11E+OCI 1.211"+00 2ND 1.OU:..04 
:.t26E"::lJ 1.2DE-(lJ 2:.2DE-(!l 1.:!sHll 3.16E.(I3 2.2'6E.(lJ 
%OOCM DSE*I.B 3.DIE.(JZ 3.01[-02 3.011".(12 3.011"-02 3.01&#xa3;..(12 JIU) U9E-ll4 1.2'.lE-03 2.:MlE-!)3 2.:J:q[-03 2.291"-1)3 3.40E-l'l3 2.29[-03 %ODCM 1.51!E-ID 3.06f-02 J.06f-02 3.00f-02 3.05E-IJ2 4..54E-02 J.06f-IJ2 4TII 9.-461:-05 U4E-03 LME-OJ 1.64&#xa3;-03 Hi4f*Ol 1.22ND 1.64f*0l %OOCM L2flf-O) 2.161:-02 1.lSf*02 ::tIBE-02:
2.1BE*0l :L97f-02 2.J9[-02 Cumulative Doses per Year Otgall Bene GHlti Kl:IllI!y llv<!t lU'lQ Total &Jdy ODCMLmt 1500E+Ol 1.5ooE+01 
!.500E+O.L 1.500E+Ol l.SooHDl 1.5001'...01 15OOE+01 UIIIb ml!.ern mRem mRem mIl.e!rl m:R<!!tl 1fJb'!m Year to Endillg Date $.fi,91NH 9.1(H,E-IJ2 9.104f-02 9.704E-(*2 9.7!llf-02 l.002:Nl1 9.704f-02 
%ODCM :l..;ffl,lE-ol 6 . .;ffl,9f..(H 1.i*.;ffl,9E-ol 5 * .;ffl,9E-ol 6."I69f-ol 6.679E-Ot 
!i.'!1OE-ol Rl'!i:'lI!JIbfr WD. AIRBORNE I Ctrliltl ,.a.AX mo. AIRBORNE I Cilid "'.AX ItUl. AIRBORtlE}
C!MId MAX. It4D. ,MRElORNE ,I Chdd MAX mo. AiRBORNE l Chid MAli IND ..A!RBOIlNE f Cllild MAX um. A!RfIOruIE I (lIlId limit Mil CI:m iod./Part .a.irruse Am, Clltlt kld"/Part Ali'tnse Mil CIJIl, b..1,/Patt .a.itoos.!
Mil CllIfl\
Air'!lo';,e Anrl Cwm tc.:llPart AlI'I:tlse Mil CllIfll. too/Part .a.itOOse Atlf)
Zoo/Part AltdIlse Table2-5B Hatch Nuclear RADIOACTIVE EFR.UENT RELEASE REPORT -Doses To A Member Of The Public Due To Radioiodines., Tritium, and Particulates in Gaseous Unit: Starting:
l-Jan-2010 Ending; Cumulative Doses Per Quarter O,.n Bone (;1-U" Liw!r LUl19 TIlotm<<J TOOlI i'.a1'f CIDOIl..lllt 7.SOf+OO 7.50&#xa3;+00 7.5QE"l1O 7.51JE ..OO 7.5OE..OO 1.5>jf .. OO 7.5I,lE ..OO UnftS II'IRM'! rnRM'! RlRern B,Rern /r,Rern mRfflI mRl!m lSTQtt 1.43E..(l4 1.52E*03 1.S2E..a3 1.511'*03 1.511'-03 2.SSE003 LS2f-<J3 %ODCM U'lf.. 03 2..D2E-02 2.02f-02 2.021;-02 
:,Um-02 1.441:-112 2.D2f-02 2NDQb' 1.'l1f*{14 UJ!7E-OJ.
1.96E'*Q3 L"16E-m i.96E..a3 
".",21'.. (1] I.9n..al %ODCN l.6SNll :2.62&#xa3;*02 2.62E..aZ 2.621:.02 2.62&#xa3;-<J2 3.B9f..oZ 2.62E-02 lRDQIr 3.Z3E4J4 3.31f..n3 3.31E..n3 3.31E..n3 4.BJE-!}3 3.34E-rn %ODCM -t.";!!:'!):!
4.*1111:-02 4.411E-1)2 4 . .iJIE-I)2 (j.44E-fl2 .iJ.45f.'{;2 4THQIr 1.801:>04 .Hl:l!c-03 3.9::!E*03 3.'!Ilf-ID 
:HltE-03 5.43f-lll 3512&#xa3;-00 %ODC:M 1AOI'*03 5.m*02 5.UE-02 "'.221"-01 5.211"01 7.24HIl 5.m-O:! Cumulative Doses per Veal' OtgaA IlI!lrl/o GH . .iI! Kllr.ey Ltver OOCMl..lllt 1.5001'+01 1.5OOE+01 1.5OOErOl l.500E+OL units mftern rn,1I.em {j\,Rem Yl/IIIIt 10 EMmg Date 7.f!:6JE-IJ>'I Ul71f-l)l L011E-ll'1 1.1i7Df-G2 
%OIKM 242f-<J) 7. 141E-t!2 1.1l9E-t!1 7.132f-t!2 Rea!pI:Or I",JI.>: IND. A!RfORt.IE J Chjd MAX IrID .;lJROOltI'lE I' Clli.Id MAX IND, A!RB04tNE ICMa MAX 100. AlROOII.HE i Ctild Umit Ann 
!.OO!'Part AlrtlO!IIl!
Ann Cum iOO,Ipalt AnI'! Cidn Eod)Palt All'do!iIe NrJ'o Clltll. 50dJPatt Lu'lQ Th-,roi:J T<<aISOOy l.5ooE+Ol l.500f+Ol l.SOOE"-Ol tYlJ1:,;,m mRem 1.{)69<E*1)2 1.57&E-02 1.1}74E-02 7.l1BE*O:!
HISIE-Gt 7. LS9E..(J2 MAX trID. AIRfORt.IE I C1li1d MAX IND. A!ROOII.HE" ChlI.::t MAXINO. MROCHt.'IIE I (Ilid "'nn lod)Part Mn CIlc1'l 50dJPalt hI'or, iOO,IPart TABLE 2-6 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT -2010 MINIMUM DETECTABLE CONCENTRATIONS 
-GASEOUS SAMPLE ANALYSES STARTING:
1-Jan-2010 ENDING: 31-Dec-2010 The values in this table represent a priori Minimum Detectable Concentration (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples. RADIONUCLIDE Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 1-131 1-133 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 Sr-89 Sr-90 H-3 MDC UNITS 2.94E-08 uCi/cc 3.22E-08 uCi/cc 2.30E-08 uCi/cc 7.30E-08 uCi/cc 8.73E-09 uCilcc 1.99E-07 uCilcc 1.34E-13*
uCi/cc 1.53E-13*
uCi/cc 1.62E-13*
uCi/cc 3.42E-13*
uCi/cc 1.30E-13*
uCi/cc 1.54E-13*
uCi/cc 2.54E-13*
uCilcc 9.61 E-13* uCi/cc 1.42E-13*
uCi/cc 1.28E-13*
uCi/cc 1.26E-13*
uCi/cc 5.64E-13*
uCi/cc 1.10E-16 uCi/cc 6.70E-16 uCi/cc 4.00E-07 uCi/cc
* Based on an estimated sample quantity of 4.o 78E+O 7 cc's.
Table 2-7A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Gaseous Effluents 
-Batch Release Unit: Starting:
l-Jan-l.Ol0 Ending: 31-l)ec-2010 UAitS 1STQuarteI 2ND Quart<< lRD QUarter 4TH Qlaatter YearrTotal!l 
: 1. l'ilumbet at bilOCh (} (J (} 0 0 2. Total! I'i$ll!!!
perIOd tor biltdl ( MItWte> ) 0.00&#xa3;:.. 00 D.OO&#xa3;:+OO 1).00&#xa3;:+00 o.ooe..oo O.ooE...oI) 
: l. MaldWI!.IM time perbd fa a IbatdI release MilWtes ) OJllf-OO 0.00[+00 0.00&#xa3;..00 0.00E+00 O.OOE...a1) 
: 4. "..era<fII" time lIf'fiOO lot a tli!tdl ( MlIIIltes ) OJ,JE..OO O.OOE"OO IHJoJE400 f).OOf.!)!)
O.ooE+OO 5. MiflIIH!.II}l 
!:nIl!! IIf'fIOO r<< a t:aU:h release Mili!Utes O.ooe+OO O.OOf+OO 0.00[+00 DJXIE""JO O.OOE...aD Table 2-78 Hatch Nudear RADIOACTIVE EFFlUENT RELEASE REPORT -Gaseous EffIuents-Batch Release Unit: Starting:
1-1,a0-1010 Ending: 31-Dec-10l0 GaMoIIr. ReIi!Mel Units 1STQwrt.et lNDQWMter 
]RDQvane.
4TH QII/IIlteI-YarTotIihl 
: 1. NilI'!l1:et of b1Ilt:1i <el!iases 
'3 0 a 0 0 1. TdIaI tl<lw! petilA1 b tatdl teJeases ( MIO:>Jtei)
O.ooE"OO 0.00&#xa3;...00 ft.OOf ..OO 0.00f...00 O.OOf"'-Ov 
: 3. !'+,aldmum 1l1'llf!!
pi!OOd I\Y a bail:.b rs8it!ill! ( Mlrvtltei ) 0.1),11:"'00 O.OOf ..O() O.OOE*OO O.OOE...oo O.OOE.-QO 
: 4. A\If!I'ag;!:
till\'!) il@floo Pot a Mtdl ( Mlr.:<Itei ) O.OOE"'OO 0.00&#xa3; .. 00 0<.00f ..00 O.OOE...OO IHlOE.-QO S. Mlttlll'llil!
IJme petlOO l'aa balrh 1'!!!Iea!ill! ( MW<\Itei ) O.ooE+OO 0.00&#xa3;""00 I).OOE"'OO i).!lOE"'JO l:).OOE"OO Table 2-8A Hatch Nuclea.. RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-AbnOl"DlaI Release Unit: Startinq:
1-Jan-2010 Ending: .31-Dec-2010 GIUeOU:!I ReJeates UliR:i.i 1ST QIItattf!r lHDQwttter 
:JRDQUII..w YearT_1s 1, (I a a 0 Tim! r-'t Nt \ Mil1oJlei\ ) O,(Xlf"'OO 0.00[...00 0.00E,.00 IJ.OOf",JO 0.001'+00 
: l. Maltimlltll 
,.me For A Rall!a!>e ( MkllJtes ) o,00"....00 O.OOE"OO Q,OOE....OO 0.00E .. 00 Ii.OOE+OO 
: 4. Aver. 'Ime Fa A Ile!t'iaIJl! ( MloJulei\ ) O.OOE+OO O.OOE ....oo D.OOE..oo O.orJE...oo 0.001'-+00 5.. 
,.me For A ( MltllJlei\ ) 0.001:+00 O.OOE....OO O.OOf"OO O.(()f"(H)
IfJXlE+QO f.}, TotaS activity fi:l1' all (CIl1l'le!.)
O.OOE*H1O O.OOf+OO 1i.00f .. 00 0.00[..00 O.OOf+OO 0 Tabk2-8B Hittch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Gaseous Effluents Abnormal Release Unit: Starting:
l-Jan-2010 Ending:
G_RIlJealieI UNti 1STQUatW lHDQWItb!t lRDQUIrlIiII' 4TH Qultrtet Year TOIiIIts 0 0 I} 0 IJ :l Tataii 11m!! for AI Ri!Iei!.!i.E!!i ( Mll1!Jtes ) 0.001:+00 O.OOE"OO 6.00f..OO IMXlf ..OO 0.00[+00 J_
T.me for A Reli!iI!iIe ( Mlroutei ) CUXlE"OO O.OOE+OO O.llfX"OO 0.001:+00 O.OOE..oo 4, A.'1!!fagt! n::.t A fl.e!eal.le: ( ) o.ooe..oo O.OOE ..OO O.ooe ...OO O.OOE ...OO 0.00["'00 5., M<iillmll!ll1l T;t);e for A RlI!P.a!.e ( Miroutei ) 0.0:11:...00 O.ooE"OO 1),000*HlD O.OOE+OO O.ooE+OO 6. T.:J'laII ao:tlvlty I\:)f all (Curil!<> ) o.ooe..oo O.I7JE...OO O.OOE..OO li.OOE..oo O.ooE.oO Table 2-8C Hatch Nudeal' RADIOACTIVE EFflUENT REl.&#xa3;ASE REPORT -Gaseous Effluents 
-lI,bnormal Release Unit: Starting:
I-J..n-2010 Ending:
G..-ReIelUes Unib 1ST Quartet' lHDQIWtet 4TH Quartet V_Talala L ()f Re\ease!'i a a 0 0 0 :;t TOIili TIlne fef M FieI_ ( MifI>Jtei ) 0.00&#xa3;+00 0.00f'''00 0.00f"00 O.OOf'+(lO j).*ooE..O{) 1. Ma.:lrrtllf!l nne f'QI: A Release ( MiIllutes ) OJ))f+ao 0.00f' ..00 O.OOE+OO IHI'JE"OO IH(lE...oo rill'll!:
F.;:.; A Rl!!If9se ( M,/1;lJtei)
O,ooE"'OO Q,OOf'..oo O.OOE"OO O.l):lE...OO O,OOE+{m 5.
rime Rlr A ReiE\ase ( MiIl'lltei ) O.ooE..oo 0.00&#xa3;+00 0.00&#xa3;....00 D.OOf"oo D,OOE+{lC< 
: 6. TOIal i!l:tMty f\::\f all (Cutles ) 0,00&#xa3;"00 0.1>>)&#xa3;"00 O.t1(1f.+OO I),OOE"OO 0.00&#xa3;+00 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.
For each type of solid radwaste shipped offsite during the report period, the report shall include the following information: Container volume. Total curie quantity (specify whether determined by measurement or estimate). Principal radionuclides (specify whether determined by measurement or estimate). Type of waste (such as spent resin, compacted dry waste, evaporator bottoms). Type of container (such as LSA, type A, type B, large quantity). 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. Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.
TABLE E. I. HATCH NUCLEAR RADIOACTIVE EFFLUENT RELEASE REPORT -SOLID WASTE AND IRRADIATED FUEL UNIT 1 AND 2 STARTING:
ENDING: 30-Jun-2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1. Type of waste UNIT 6 month period Est. Total ERROR % a. Spent resins, filter sludges, evaporator m 3 3.65 E+01 bottoms, etc. Ci 7.35 E+01 1.00 E 01 b. Dry compressible waste, contaminated equip. rna 1.02 E+03 etc. Ci 5.72 E+01 2.00 E 01 c. Irradiated components, control rods, m 3 Ci d. Control Rod Drive Filters m" Ci e. Other (describe) m;j Equip. etc. Ci 2. Estimate of major nuclide composition (by type of waste) ISOTOPE PERCENT CURIES a.Fe-55 36.9 2.71 E+01 Co-60 28.7 2.11 E+01 Zn-65 4.9 3.57E+00 Mn-54 11.3 8.32 E+OO Cr-51 0.3 2.28 E-01 Other 18.0 1.32E+01 b.Fe-55 62.8 3.59E+01 i Co-60 15.6 8.92E+00 Mn-54 4.59 2.63E+00 Zn-65 2.13 1.22E+00 Other 14.9 8.53E+00 c. d. e. I I ..3. Solid Waste DIspoSition Number of Shipments Mode of Transportation Destination All waste sent to processors NI A N/A IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination N/A N/A 65  
: 1. Type of waste UNIT 6 month period Est. Total ERROR % a. Spent resins, filter sludges, evaporator m" 4.71 E+01 bottoms, etc. Ci 6.81 E+01 1.00 E 01 b. Dry compressible waste, contaminated equip. m 3 3.28 E+02 etc. Ci 1.33 E-01 2.00 E 01 c. Irradiated components, control rods, m 3 Ci d. Control Rod Drive Filters m;$ Ci e. Other (describe) m 3 Equip. etc. Ci TABLE 3-1 E. I. HATCH NUCLEAR RADIOACTIVE EFFLUENT RELEASE REPORT -SOLID WASTE AND IRRADIATED FUEL UNIT 1 AND 2 STARTING:
1-Jul-2010 ENDING: 31-Dec-2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) I I I I 2. Estimate of major nuclide composition (by type of waste) ISOTOPE PERCENT CURIES a.Fe-55 33.3 2.27 E+01 Co-60 32.8 2.23 E+01 Zn-65 5.1 3.50 E+OO Mn-54 13.3 9.09 E+OO Cr-51 1.2 8.47 E-01 Other 14.2 9.66 E+OO b.Fe-55 62.8 2.06 E-02 Co-60 15.6 6.08 E-03 Mn-54 4.59 2.82 E-03 Zn-65 2.13 2.82 E-03 Other 14.9 2.00 E-02 c. d. e. 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination All waste sent to processors NI A N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination o N/A N/A I TABLE E. I. HATCH NUCLEAR RADIOACTIVE EFFLUENT RELEASE REPORT -SOLID WASTE AND IRRADIATED FUEL UNIT 1 AND STARTING:
1-Jan-2010 ENDING:
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 (FT31 Dewatered 73.5 Zn-65,Fe-55,Co-60 Carbon Steel 7 195 14-210 Cask NfA Resins Mn-54 Liners
* See Note (External)
Dry 57.2 Fe*55,Co-60,Mn-54 B-25fHigh 400 90 B-25 Boxes, Sea NfA Active Waste Zn-65 Integrity Liner
* See Note land Containers 14-210 "STC Shipping Cask 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. ** STC-Strong Tight Container TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT -2010 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND STARTING:
1-JUL-2010 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 I CUBIC FEET (FT3) Dewalered 68.1 Zn-65,Fe.55,Co-60 Carbon Steel 9 195 14-210 CASK! NlA Resins Mn-54 Liners
* See Note (External)
Dry 1.33E-Ol Fe-55,CO-60,Mn-54 B-25lHigh 121 90 825 Boxes, Sea N/A Active Waste Zn-65 Integrity Liner
* See Note land Containers 14-210 STC Shiooino Cask
* Note: The actual type, size and number of the containers may vary from the recorded values due to the use of different sized containers to ship wastes to processor.
4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part that the Radioactive Effluent Release Report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with the ODCM. 4.2 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 2-2B, for the elevated releases.
Similarly the source term is listed in Tab/es 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.
Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -Ooses to a Member of the Public Due to Activities Inside the Site Unit: starting:
l-Jan-2010 Ending: 31-Dec-2010 lOt:atiOfI NUIe: DIstaIK.'e sector:: O<<:upaacy fadtlr.
Elevated ll.I!!Iea!ie Gro..nt'l Le;,'e! l.ro..dld l&#xa3;,teI Bu..e U..er TotalllOOiy ThYfOi:J Kldfl'!y lllillQ GH.lI s.jf) RQADSIDE PARK U8E+OO WNW 2.281:-<14 Odd Not;:je Gas aoo f4Otti! Gas ililtl RaaiOiiti!lil'll'!
UIlIIt$ 1ST QWIrter' 1I1Rilfll 1.441:-11 WlRem UIZE-Ol II'IRem LIJZE-Ol mRI!m LOZE-Ol rllRem Ull'f:Hi7 InReta U)ZE-Ol rnRern LolZE-07 WlRIlfll 1..l4E*l1 XlQ (secJmJ):
2.42E'-<lB.
XlQ (sedmJ:" 2.l7fAl8 (S!!C/mJ l: 7.IBI:....16 }flQ (set:{mJ);
7.00E-<l6 2ND QlIIIIIl1et 3R:O Quatbit' 7.42E-11 3.181:-11 4.W..(19 Ust-09 4.W-09 t>_1'ff-09 S.Jfjf-(19 7.rot-09 4.fXlE-09 fdSf-09 *UOE-Q9 iU6H.t9 4.6ElE*(l'i' tu4E-Q>{l B.DIE-H fid'i'ff-12 DlQ (m.2);
DJQ (m-2):
4TH: QWIfb!t Yf!illt 1.37E-l1 1.34E-10 6.0\1E..$
1.19E..o7 6.09E-09 1.19E..(I7 7.34&#xa3;-09 6.0\1E-09 U9E-Q7 6.10E-tJ9 U'llE*{J7 6.09fA19 1.19E",17 5.33E-12 l.OltHO Table 4-1 Hatch Nuclear RADIOACTIVE EFFLUENT RElE4SE REPORT -Doses to a Member of the Public Due to A.c.tivities Inside the Site Unit: Starting:
1-Jao-2010 Ending:
l.oa1ttIoA DJDIWIl Sec:Wr: O<xDpillIICY I'ac:tDr.
AoeGroupr Elevate:!
flc.'!e llvl:!' T Qtill i!OO", TIl'ifOij Kt:lr'!ey Lu.>fl9 GI-lJI CAMP!lKi AAfA 1.27E+QO WNW 5.48E.(J)
Chl'd NoI:4e Gi!!l PaJ1;;(tJate and NlltleGu PartiCulate and UlIIb 1ST QItlt.lt.
mRl!fll 7..77f-lQ mRl!m 2.191:-00 mRem 2..19E..05 11'1Refl1 UOH.15 mRell1 U9HJ5 mRefl1 :U9f-05 rMRstT. 2.19&#xa3;-05 rnRem 7.84f*1!.l XiQ (!i<<ifnl): 
!.38E..oo XiQ ';SE!JmJ):
2.33E-CIj XiQ ($ii!!r;:}mJ):
7.D3f-OO (SE!Jlnl):
D.27E..oo 2NDQwatter 11m QItltrtet 1.'JI7E{J9 l.2Of-(tg UilE.(I7 1.33E*07 UilE.(I7 LllE*07 1.161':<17 UiiiE*01 l.OlE.(I7 L3;!.f*07 l.Cl2E-Ol Ul1E*lJl U3E*07 2. 16f*1J9 J.StE-tO D.lQ (;lf1>-:?).
O/Q (m-2):
4TH QwIttef YeilIr 7.00&#xa3;*10 4.64[4J9 DiE*a7 2.515E..Q6 D1E.Q7 2.5l5E-<l6 1.S!lE-tl7 l.ME""'" 1.3ZHI7 2.S6E-OO 1.32E*07 2.S6E*06 D1E*O] 2.S6E..(J6 
!>.95E*lO 4.::rn:<l9 Table 4-1 Hatch Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a Member of the Public Due to Activities Inside the Site Unit: starting:
I-Jan-lOlO Ending: 31-Dec-201O 
*DI$flIInc:e (ldlomel.u):
sector: 
,..:.tor:
Age Group:
G<<luIId le'.f!l Q()UfId t.eYeI Booe Uver Tl',yroi;l Ki:llle)'
ll:ll19 GH.il RECREA TlON AREA 1.I:13E-+OO 55&#xa3; 2.S7E'(}2 (hM Notte PaltUi.1lle aoo Notte PaAJ(wle at'lll Ul!litt lSTQvamIr InRl!m L5f1E-O&#xa3;I mRi!Jll ItiiSHI'Ii mRm li.7Of-Oli mRt!fl1 M5N16 mRall E1iSf-D5 mRm B.I.iSE-OO rflR<::m !.2Sf-C/9 XlQ (5l!4'rnll:
3.301:*00 XlQ (S!!!'/ntl):
3.21E*00 (S!!!'/ml j:6.42E.Q6 X/Q 5.73E*06 2NDQiilillrter 
:JRDQu<ilkr 8.Ii,tjE.09 1.93f.tll! 
-4.111E.(I]
5.ZlE-U7 4.IHE.(l7 5.23f.o] 4.6Of..(J]
6S1f-U7 4.1)11'..(J7 5*.24E-07 4.031'..(17 S.2'j;f-07 4.IHE*G7 5.:131'-07 9.78&#xa3;-(19 8.161:-10 O/Q (m-2}: 1.51if:-D9 OlQ (m-2}: l_lliE-ff.j 4TH Qt.t.IIts Yen 1.:Mf-09 "U8f*O]
5.111E..(J]
1.01E-05 6.25E-(}7 1.04NI5 S.I9f..(J7 UJi&#xa3;-05 5.l!)1'..(J1 1.01E-05 1.01E,.(j5 6.55E-1O Table4-! Hatch Nuclear EFFLUENT RELE4SE REPORT -Doses to a Member of the Public Due to .Activities Insjde the Site Unit: 5tartingll-Jan-2010 Ending: 31-Dec-2010 OlstalKll!! oc.cupalilq' Elevate]
Grotilfid I.iffii!l Citt'lufld I.iffii!l 600e UIItlt TtJ"..a1 .Il<<ly Th'ftl.'ltj ICtIr'ley Gr*Ll! 9J:n VlSrrollS Cfl'fTER WS'N 4.57E.(14 Chl:J: t'IOI:4e Gas Pal'tltWte aM t'IOI:4e C.as Pan"::JJate aM Units 15TQW14tS mRem 7291:*U mRMri 5i11E*01 II)Rem 5.01&#xa3;*07 fl1Rem 5JJ:l;f-Q1 mRem S.t.l1E-07 mRj!flj 5JJ U'.(i7 f!*,f:'.s11 
!LiHNJ7 mRem 537f*11 X,iQ (!iIl:'CimJ):
S.OOE*OO X,IQ (s.!!/"r,3):
4.97E-ilI>
X,iQ (s.!!/mJ):
1.B7E.(JS X,iQ 2ND Quarter 3RO Quarter 4.00E*11}
L51f*iO 2.:UE-ilI> 
].G3E*OO 2.31ECOO 3.!J3f-o!J 2.64E-'ll8 339&#xa3;*08 2.31E-08 H)3E*OO 2.32E..()jj .Ul4f*OO 2.31E*OO Hi2t*OO +.34E-1O J.28f-U D/Q (m-21:
DlQ (m-2):
4TH QlW"b!I Year 6.73f-U 1I..'11E-1O 3.00E-!Jf.I 5.ME*1)7 3.0010-(16 S.6iIE-(J7 3.61E-<l8 6.04E*01 ;3,I))f-oB 5.&1E-07 3.l))E.(JB 5.84E-{l7 3.00Ec(la 5.&11"-07 2.&41:-11 5.47E-10 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 5.1 Regulatory Requirements The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to less than or equal to 75mrems. 5.2 Demonstration of 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 Meteorological Data 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 Monitoring Instrumentation From 5/18/10 to 6/30/10 2G 11 N355 Yokogawa Discharge G PM and Totalizer Recorder was inop for greater than 30 days. CR 2010106507 was generated on 5/18/10 due to a failed surveillance.
Work order 21 00741101 performed repairs and satisfied the surveillance on 6/30/2010.
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.
Description of Deviations There were no deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements during this reporting period. Tanks Exceeding Curie Content Limits Regulatory Requirements aDeM 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.B.b. Description of Deviations There were no outside temporary tanks, for liquids, that exceeded the limit of Technical Specification 5.5.B.b during this reporting period. Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) Regulatory Requirements aDeM 7.2.2.6 states in part that deviations from MDe(s) required in Table 3-3 shall be included in the Radioactive Effluent Release Report. Description of Deviation There were no deviations from MDe(s) required in Table 3-3 during this reporting period. Changes to the Plant Hatch Off site Dose Calculation Manual (ODeM) There were no changes to the aDCM in 2010. Regulatory Requirements Pursuant to Technical Specification 5.5.1 and aDCM 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 aDCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the aDCM 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.
Description of Changes There were no changes in 2010. Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems Regulatory Requirements The Radioactive Effluent Release Report shall include. . .. any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to ODCM Chapter 7, Section 7.2.2.7. Description of 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.
SOUTHERN E. I. HATCH NUCLEAR UNITS NO. 1 & ANNUAL JANUARY 1, 2010 -DECEMBER 31,2010 APPENDIX A Release of Radioactive RHR Service Water for 2010 The following historical information is provided to create a perspective for the release of radioactivity during the year 2010 relative to the RHR Service Water System. In 1996, the analysis of samples from the Unit 1 RHR "8" 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 !lCi and 25.6 JlCi. On August 23,1996 repairs were made to a Ap instrument in an effort to stop the in leakage 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 1 OCFR50.59 Evaluation titled "Unit 1 RHR Service Water: Release of Contaminated Water.1I 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 1 OCFR50.36a 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 U1 RHR 118" 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. 8ased on this it was determined that one of the outermost tubes (tube 1-1) was definitely leaking. 1\10 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.
The conservative decision was made to plug the leaker as well as the eight surrounding tubes. After plugging the tubes a hydrostatic pressure test was conducted at 300 psi and the Heat Exchanger was inspected for signs of leakage. No leakage was noted at this time. The Heat Exchanger was deconned, closed up and placed back in service. The Chemistry Department has sampled and monitored the activity during the operation of the Heat Exchanger.
The only radionuclide found in the RHRSW samples for 2010 was on 4/26/10 when the total concentration released was 1.49E-8 JlCi/ml. As shown in the following table, the highest concentrations were found in 1997, when the total concentration released was 1.21 E-5 JlCi/ml. 3.16E-7 4.9SE-7 2.49E-7 2.S3E-7 1.19E-7 4.94E-6 1.12E-6 2.27E-8 2.82E-7 1.99E-7 2.06E-6 7.96E-8 2.24E-7 1.06E-6 C&-.134 2.10E-7 Cs..137 4.43E-7 3.78E-8 1.24E-7 2.76E-8 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. aDCM 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 1.0E-4 )lCi/ml. The following discussion is based on a release duration of 1 minute, a release volume 4,000 gallons, a total dilution of only 10,000 gallons, and the radionuclide concentrations 1997. This is a very conservative estimate, since credit for the additional dilution provided the circulating water flume was not taken into consideration and the activity from 1997 higher with more radionuclides.
The sum of the ratios of the concentration of each in the mixture to its effluent concentration limit (ECl) was 1.15. The sum of the ECl must be less than ten <<10) to ensure that the concentration limit for the mixture is exceeded.
As can be seen, the sum is much less that ten. (1 OCFR20 Appendix 8 states the sum of the fractions of the nuclides divided by their effluent concentration limits (ECls) be less than one. Further NRC guidance, Technical Specifications, and the aDCM allow 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 10CRF20 limits.} aDCM 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 aDCM 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-lU, 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.
aDCM 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. 1 OCFR20.1302 (b)(l) 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 aDCM section 2.1.2. 10CFR20.1501 (a}(2}(ii) 
& (iii) requires the licensee to evaluate the concentration or quantities of radioactive materials and the potential radiological hazard, respectively.
The concentrations and quantity of the radioactive materials in the release was evaluated by sampling and analysis as discussed above. The potential radiological hazard was also evaluated by performance of the dose calculations, which would be a result of the release, as discussed above in the assessment of aDeM section 2.1.3. This release does not constitute a Licensee Event Report (lER) based on the following.
10CFR 50.73 (A)(2)(VIII)(8) requires the licensee to report any liquid effluent release which exceeds 20 times the applicable concentration specified in 10CFR20, Appendix 8, Table 2, column 2, at the point of entry into the receiving waters (Le., unrestricted area). This is justified as discussed above in the assessment of aDCM section 2.1.3; it can be seen that the concentrations are much less that the applicable limits. Design Criterion 64 in Appendix A to 1 OCFR50 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.
Compliance with Appendix I to 1 OCFR50 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 concemed 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.S.4.j and implemented by ODCM section S.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 10CFRSO.S9 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.
SOUTHERN E. I. HATCH NUCLEAR UNITS NO. 1 & ANNUAL JANUARY 1, 2010 -DECEMBER 31,2010 APPENDIX B Hatch Nuclear Plant Appendix B CARBON-14 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of "principal radionuclides" in gaseous effluents have changed, and C-14 has become a larger percentage. "Principal radionuclides" are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21), "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate.
In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants will report C-14 amounts released and resulting doses to the maximally exposed member of the public. Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation.
The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.
At Plant Hatch, the quantity of C-14 released in gaseous effluents in 2010 was estimated to be 14.16 Curies (per unit). Approximately 95% of the C-14 released is in the form of 14C02 and is incorporated into plants through photosynthesis.
Ingestion dose results from this pathway. The remaining 5% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Hatch ODeM, the resulting bone dose to a child located at the controlling receptor location would be 1.59E-01 mrem in a year which is 1.06% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents.
The resulting total body dose to a child located at the controlling receptor location would be 3.18E-02 mrem in a year which is 0.21 % of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents Edwin I. Hatch Nuclear Joseph M. Farley Nuclear Vogtle Electric Generating Annual Radioactive Effluent Release Reports for Enclosure Farley Annual Radioactive Effluent Release Report for SOUTHERN NUCLEAR OPERATING COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 FARLEY NUCLEAR UNIT NO. LICENSE NO. ANNUAL RADIOACTIVE EFFLUENT RELEASE CALENDAR YEAR SECTION 1.0 1.1 1.1.1 1.1.2 1.2 1.3 1.3.1 1. 3.2 1.4 1.5 1.6 1.7 2.0 2.1 2.1.1 2.1.2 2.1.3 2.2 2.2.1 FARLEY NUCLEAR ANNUAL RADIOACTIVE RELEASE TITLE LIQUID EFFLUENTS of Total Gaseous of Total Regulatory Requirements Concentration Limits Dose Limits Effluent Concentration Limit (ECL) Measurements and Approximation Total Radioactivity Determination Total Error Estimation Liquid Effluents 
-Release Data Radiological Impact Due to Liquid Releases Liquid Effluents Batch Releases Liquid Effluents 
-Abnormal Releases GASEOUS EFFLUENTS Regulatory Requirements Dose Rate Limits Air Doses Due to Noble Gases in Doses to a Member of the Public Measurements and Approximation Sample Collection and Analysis SECTION 2.2.2 2.2.2.1 2.2.2.2 2.2.2.3 2.2.3 2.3 2.4 2.5 2.6 3.0 3.1 3.1.1 3.1. 2 3.2 4.0 4.1 4.2 FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TITLE PAGE Total Quantities of Radioactivity, Dose 28 Rates and Cumulative Doses Fission and Activation Gases 29 Radioiodine, Tritium and Particulate 29 Releases Gross Alpha Release 30 Total Error Estimation 30 Gaseous Effluent Release Data 31 Radiological Impact Due to Gaseous 32 Releases Gaseous Effluents 
-Batch Releases 32 Gaseous Effluents 
-Abnormal Releases 32 SOLID WASTE 59 Regulatory Requirements 59 Solid Radioactive Waste System 59 Reporting Requirements 59 Solid Waste Data 59 DOSES TO MEMBERS OF THE PUBLIC 62 INSIDE THE SITE BOUNDARY Regulatory Requirements 62 Demonstration of Compliance 62 SECTION 5.0 5.1 5.2 6.0 7.0 7.1 7.1.1 7.1.2 7.2 7.2.1 7.2.2 7.3 7.3.1 7.3.2 8.0 8.1 8.2 FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TITLE PAGE TOTAL DOSE FROM URANIUM FUEL 67 CYCLE (40CFR190)
Regulatory Requirements 67 Demonstration of Compliance 67 METEOROLOGICAL DATA 67 PROGRAM DEVIATIONS 67 Inoperable Liquid or Gaseous Effluent 67 Monitoring Instrumentation Regulatory Requirements 67 Description of Deviations 68 Effluent Sample Analysis Exceeding 68 Minimum Detectable Concentration (MDC) Regulatory Requirements 68 Description of Deviations 68 Incorrect Compositing of Liquid 68 or Gaseous Effluent Samples Regulatory Requirements 68 Description of Deviations 69 CHANGES TO THE PLANT FARLEY ODCM 69 Regulatory Requirements 69 Description of Changes 69 SECTION 9.0 9.1 9.2 App.A FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TITLE PAGE MAJOR CHANGES TO LIQUID, SOLID RADWASTE TREATMENT Regulatory Requirements GASEOUS, SYSTEMS Description of Major Changes Appendix A, Carbon-14 Supplement OR for 2010 70 70 70 71 FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents 
-Summation of All Releases, Unit 1 (Quarters 1,2, 3 and 4) 5 1-1B Liquid Effluents 
-Summation of All Releases, Unit 2 (Quarters 1,2, 3 and 4) 6 1 1C Liquid Effluents 
-Summation of All Releases, Site (Quarters 1,2, 3 and 4) 7 1 2A Liquid Effluents, 3 and 4) Unit 1 (Quarters 1,2, 8 1-2B Liquid Effluents, 3 and 4) Unit 2 (Quarters 1,2, 11 1 2C Liquid Effluents, 3 and 4) Site (Quarters 1,2, 15 1-3A Doses to a MEMBER OF THE PUBLIC Due to Liquid Releases, Unit 1 (Quarters 1,2,3 and 4) 19 1 3B Doses to a MEMBER OF THE PUBLIC Due to Liquid Releases, Unit 2 (Quarters 1,2,3 and 4) 20 1-4 Minimum Detectable Concentration Liquid Sample Analyses -21 I-SA Liquid Effluents Summary, Unit 1 -Batch Release 22 l-SB Liquid Effluents Summary, Unit 2 Batch Release 23 TABLE 1 6A 1 6B 2 1A 2-1B 2-1C 2 2A 2-2B 2 2C 2-3A 2-3B 2 3C FARLEY NUCLEAR ANNUAL RADIOACTIVE RELEASE LIST OF TABLES Liquid Effluents Summary, Unit 1 Abnormal Release Liquid Effluents Summary, Unit 2 Abnormal Release Gaseous Effluents 
-Summation of All Releases, Unit 1 (Quarters 3 and Gaseous Effluents 
-Summation All Releases, Unit 2 (Quarters 3 and Gaseous Effluents 
-Summation All Releases, Site (Quarters 3 and Gaseous Effluents 
-Mixed Level Releases, Unit 1 (Quarters 3 and 4) Gaseous Effluents Level Releases, Unit 3 and 4) Gaseous Effluents Level Releases, Site 3 and 4) Gaseous Effluents Level Releases, Unit 3 and 4) Gaseous Effluents Level Releases, Unit 3 and 4) Gaseous Effluents Level Releases, Site 3 and 4) Mixed Mode 2 (Quarters 1,2, Mixed Mode (Quarters 1,2, Ground 1 (Quarters 1,2, Ground 2 (Quarters 1,2, Ground (Quarters 1,2, PAGE 24 25 33 34 35 36 39 41 44 46 48 FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 2-4A Air Doses Due to Noble Gases in Gaseous Releases, Unit 1 (Quarters 1,2, 3 and 4) 50 2-4B Air Doses Due to Noble Gases in Gaseous Releases, Unit 2 (Quarters 1,2, 3 and 4) 51 2-5A Doses to a MEMBER OF THE PUBLIC Due to Radioiodines, Tritium, and Particulates in Gaseous Releases, Unit 1 (Quarters 1,2,3 and 4) 52 2 5B Doses to a MEMBER OF THE PUBLIC Due to Radioiodines, Tritium, and Particulates in Gaseous Releases, Unit 2 (Quarters 1,2,3 and 4) 53 2 6 Minimum Detectable Concentration Gaseous Effluent Analyses -54 2-7A Gaseous Effluents Summary, Unit 1 -Batch Release 55 2-7B Gaseous Effluents Summary, Unit 2 -Batch Release 56 2-SA Gaseous Effluents Summary, Unit 1 -Abnormal Release 57 2-SB Gaseous Effluents Summary, Unit 2 -Abnormal Release 58 3-1 Solid Waste and Irradiated Fuel Shipments 60 4-1 Doses to a MEMBER OF THE PUBLIC Due to Activities Inside the Site Boundary, Site 63 1.0 LIQUID This section contains applicable aDCM limits for liquid effluents as well as the quantities of radioactive liquid effluents released during 2010. 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 aDCM 2.4 are presented to show conformance with the limits of aDCM 2.1.3. 1.1 Regulatory Requirements 1.1.1 Concentration Limits Technical Specifications 5.5.4.b and 5.S.4.c state that the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see aDCM Figure 10-1) shall be limited at all times to ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-04 uCi/ml total activity.
1.1.2 Dose Limits Technical Specifications S.S.4.d and 5.S.4.e state that the dose or dose commitment to a MEMBER aF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see aDCM 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 IOCFR20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases in liquid radwaste, the ECL is 1.0E 04 uCi/ml total activity.
For gross alpha in liquid radwaste, the ECL is 2.0E-09 uCi/ml. Furthermore, for all the above radionuclides, or categories of radioactivity, the overall ECL fraction is determined in accordance with 10CFR Part 20, Appendix B. -1 1.3 Measurements and Approximation of Total Radioactivity The radionuclides listed below are considered when evaluating liquid effluents:
MN-54 FE 59 CS CO-58 CO-60 ZN-65 SR-89 SR-90 1.3.1 Total Radioactivity Determination Batch Releases:
Representative pre-release grab samples are obtained and analyzed in accordance with ODCM Table 2-3. Isotopic analyses are performed using the computerized pulse height analysis system utilizing high resolution germanium detectors.
Isotopic values thus obtained are used for release rate calculations as specified in the ODCM. Only those nuclides that are detected are used in the calculations.
All Strontium and Iron-55 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis.
Gross beta and gross alpha determinations are made using 2 pi gas flow proportional counters.
Tritium determinations are made using liquid scintillation techniques.
Dissolved gases are determined employing grab sampling techniques and then counting on the pulse height analyzer.
The sample analyses results are used along with the ECL values to determine the ECL fraction for the planned release. The ECL fraction is then used, with the appropriate safety factors, and the expected dilution stream flow, to calculate the maximum permissible release rate and a liquid effluent monitor setpoint.
The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded.
A monitor reading in excess of the calculated setpoint will result in automatic termination of the liquid radwaste discharge.
Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibration factors are used by the computer to generate a pre-release printout.
If the release is not permissible, appropriate warnings will be displayed on the computer screen and on the printout.
If the release is permissible, it is approved by a Chemistry Technician.
The release permit is transferred from the Chemistry Department to the Operations Department for release. When the release is completed, the actual release data are provided to the Chemistry Department.
These release data, including release rate and release duration, are input into the computer and a post-release printout is generated.
This printout contains the actual release rates, radionuclide concentrations and quantities, dilution flow, and calculated doses to an individual. -2 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 2010 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, I-lB, and 1 lC; 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 2010 Doses to a Member of the Public due to Liquid Releases:
Table 1-3A Unit 2 2010 Doses to a Member of the Public due to Liquid Releases:
Table 1-3B -3 1.6 Liquid Effluents 
-Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables: Unit 1 2010 Liquid Effluents Batch Release Summary: Table 1-5A Unit 2 2010 Liquid Effluents 
-Batch Release Summary: Table 1 5B 1.7 Liquid Effluents 
-Abnormal Releases There were no abnormal releases during 2010. Abnormal release information for Units 1 and 2 is summarized in the following tables: Unit 1 2010 Liquid Effluents 
-Abnormal Release Summary: Table 1-6A Unit 2 2010 Liquid Effluents 
-Abnormal Release Summary: Table 1-6B -4 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Summation of All Unit: Starting:
l-lan-2010 Ending:
Type of Effluent Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) Curies 2.41E-03 5.63E-03 2.17E-03 3.42E-02 2. Average diluted concentration during period uCi/mL 1.60E-IO 3.26E-IO 1.28E-1O 2.79E-09 3. Percent of Applicable Limit % * * *
* B. Tritium 1. Total Release Curies 2.21E+02 1.52E+02 2.21E+02 1.95E+Ol 2. Average diluted Concentration during period uCi/mL 1.46E-05 8.79E-06 1.30E-05 1.59E-06 3. Percent of Applicable Limit % * * *
* C. Dissolved and Entrained Gases 1. Total Release Curies 5.03E-04 1.02E-04 2.03E-03 1. 16E-04 2. Average diluted Concentration during period uCi/mL 3.33E-ll 5.90E-12 1. 19E-IO 9.45E-12 3. Percent of Applicable Limit % ** *
* D: Gross Radioactivity 
--_._..... 1. Total Release Curies 1. 13E-05 4.04E-06 5.93E-06 3.27E-06 E: Waste Vol Release (Pre-Dilution)
Liters 7.59E+07 7.17E+07 7.22E+07 5.43E+07 F. Volume of Dilution Water Used Liters 1.50E+1O l.72E+lO 1.70E+I0 1.22E+I0
* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report. -5 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Summation of All Unit: Starting:
1-Jan-2010 Ending:
Type of Effluent A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) 2. Average diluted concentration during period 3. Percent of Applicable Limit B. Tritium 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit C. Dissolved and Entrained Gases 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit D: Gross Radioactivity 
: 1. Total Release E: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used Units Curies uCi/mL % Curies uCi/mL % Curies uCi/mL % Curies Liters Liters 1ST Quarter 4.37E-03 2.61E-IO
* 2.03E+02 1.21E-OS
* S.67E-04 3.3SE-ll
* O.OOE+OO 7.38E+07 1.67E+IO 2ND Quarter l.S7E-02 1.2SE-09
* 3.7SE+Ol 2.97E-06
* 1.01E-04 8.04E-12
* 4.91E-06 S.47E+07 1.26E+I0 3RD Quarter 1.24E-02 7.0SE-1O
* 1.16E+02 6.62E-06
* 2.23E-03 1.27E-1O
* 2.06E-06 7.16E+07 1.7SE+I0 4TH Quarter 2.10E-02 1.30E-09
* 6.44E+Ol 3.99E-06
* 7.S2E-04 4.66E-ll
* 6.18E-06 6.78E+07 1.61E+I0
* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report. -6 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Summation of All Unit: Starting:
1-Jan-2010 Ending:
Type of Effluent A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) 2. Average diluted concentration during period 3. Percent of Applicable Limit Units Curies uCi/mL % 1ST Quarter 6.7BE-03 2.13E-1O
* 2ND Quarter 2. 13E-02 7.14E-IO
* 3RD Quarter 1.46E-02 4.22E-IO
* 4TH Quarter S.52E-02 1.94E-09
* 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit Curies uCi/mL % 4.24E+02 1.33E-OS
* l.B9E+02 6.33E-06
* 3.37E+02 9.74E-06
* 8.39E+Ol 2.9SE-06
* C. Dissolved and Entrained Gases 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit Curies uCi/mL % 1.07E-03 3.36E-ll
* 2.03E-04 6.BOE-12
* 4.26E-03 1.23E-IO
* 8.68E-04 3.0SE-ll
* D: Gross Radioactivity 
: 1. Total Release Curies 1.13E-OS B.9SE-06 7.99E-06 9.46E-06 E: Waste Vol Release (Pre-Dilution)
Liters l.S0E+OB 1.26E+OB 1.44E+08 1.22E+08 F. Volume of Dilution Water Used Liters 3.17E+I0 2.97E+I0 3.4SE+IO 2.B3E+I0
* Applicable Ii mits are expressed in terms of dose. See Tables 1-3A and 1-38 of this report. -7 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission It Activation Products Sr-89 Total For Period Units Curies Curies 1ST Quarter 7.37E-04 2ND Quarter O.OOE+OO O.OOE+OO 3RD Quarter O.OOE+OO O.OOE+OO 4TH Quarter O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. -8 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter Fission & Activation Products Be-7 Y-88 Y-91 As-76 Br-84 Co-57 Co-58 Co-60 Cr-S1 Fe-55 Fe-59 I-131 Mn-S4 Nb-9S Nb-97 Ni-S6 Sr-89 Sr-90 Zn-6S Zr-9S Cs-137 Eu-1S4 Pm-149 Pr-144 Rh-10S Ru-103 Sb-122 Curies Curies Curies CUries Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.71E-OS 1.06E-06 8.SSE-OS 9.04E-04 O.OOE+OO 2.71E-04 O.OOE+OO O.OOE+OO 9.06E-06 1.l1E-06 1.46E-06 O.OOE+OO 7.30E-OS S.S7E-06 2.21E-04 O.OOE+OO 1.41E-OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2ND Quarter O.OOE+OO 7.72E-07 9.S8E-OS 3.20E-OS O.OOE+OO O.OOE+OO 1.17E-03 1.l1E-03 3.4SE-OS 7.92E-04 3.41E-OS O.OOE+OO 1.44E-OS 1.74E-OS S.31E-06 2. 18E-OS S.2SE-OS O.OOE+OO 2.56E-04 O.OOE+OO S.37E-06 O.OOE+OO 2.69E-DS O.OOE+OO O.OOE+OO O.OOE+OO 7.83E-06 3RD Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.71E-04 4.91E-04 2. 13E-OS l.S2E-04 O.OOE+OO 1.62E-07 O.OOE+OO 7.46E-06 O.OOE+OO 6.70E-07 O.OOE+OO O.OOE+OO 1.6SE-OS O.OOE+OO 4.73E-OS O.OOE+OO O.OOE+OO O.OOE+OO 4.3SE-06 O.OOE+OO O.OOE+OO 4TH Quarter S.37E-06 1.2SE-06 O.OOE+OO O.OOE+OO 4.70E-06 2.4SE-06 S.SOE-03 1.67E-03 6.86E-04 3.43E-04 1.06E-06 O.OOE+OO 2.6SE-OS 3.S8E-04 O.OOE+OO 3.47E-OS O.OOE+OO O.OOE+OO 1.68E-04 1.8SE-04 1.14E-OS 3. 13E-06 O.OOE+OO 4.03E-04 2.8SE-04 7.82E-07 O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. -9 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Sb-l24 Curies O.OOE+OO 9.B4E-06 O.OOE+OO 2.l0E-OS Sb-l2S Curies 6.66E-OS 9.77E-OS 1.3lE-04 4.03E-04 Sn-113 Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.l4E-06 Te-l29 Curies O.OOE+OO O.OOE+OO O.OOE+OO 9.37E-OS Ag-lOBM Curies B.4SE-07 l.06E-06 O.OOE+OO O.OOE+OO Ag-ll0M Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.S9E-Q6 Sn-117M Curies O.OOE+OO O.OOE+OO 4.30E-07 2.67E-06 Te-l2SM Curies O.OOE+OO 1.BSE-03 9.30E-04 2.39E-02 Te-129M Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.9SE-OS Total For Period Curies 1.67E-03 S.63E-03 2.17E-03 3.42E-02 Tritium H-3 Curies 2.21E+02 1.S2E+02 2.2lE+02 1.9SE+Ol Dissolved And Entrained Gases Ar-4l Curies 1.4lE-06 1.BSE-06 O.OOE+OO 1.36E-06 Xe-133 Curies 4.99E-04 9.99E-OS 2.02E-03 1.12E-04 Xe-13S Curies O.OOE+OO O.OOE+OO 1.07E-06 2.7BE-06 Xe-13lM Curies O.OOE+OO O.OOE+OO 1.SBE-OS O.OOE+OO Xe-l33M Curies 2.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies S.03E-04 1.02E-04 2.03E-03 1.16E-04 See Table 1-4 for typical minimum detectable concentrations.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -10 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission Ie. Activation Products Sr-89 Total For Period Units Curies Curies 1ST Quarter 7.06E-04 7.06E-04 2ND Quarter O.OOE+OO O.OOE+OO 3RD Quarter O.OOE+OO O.OOE+OO 4TH Quarter O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
11 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Fission It Activation Products Y-88 Y-93 Y-9S As-76 Br-84 Co-58 Co-60 Cr-Sl Cu-64 Fe-55 Fe-59 1-133 Mn-S4 Mn-S6 Na-24 Nb-9S Nb-97 Ni-S6 Rb-86 Sr-89 Sr-90 Sr-92 Zn-65 Zr-9S Zr-97 Ba-140 Cd-US Units 

1ST Quarter S.41E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.24E-04 1.6SE-03 O.OOE+OO O.OOE+OO 2.00E-04 O.OOE+OO 1.64E-06 1.06E-OS 1.48E-06 1.SSE-OS S.48E-06 2.43E-06 O.OOE+OO O.OOE+OO 1.90E-04 9.76E-06 O.OOE+OO S.23E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2ND Quarter O.OOE+OO O.OOE+OO O.OOE+OO 1.81E-06 4.81E-06 2.28E-03 2.72E-03 S.4SE-04 1.26E-06 2. 14E-03 1.04E-04 O.OOE+OO 9.44E-OS O.OOE+OO O.OOE+OO 3.64E-04 l.S9E-06 3.34E-OS O.OOE+OO 1.46E-OS O.OOE+OO 1.26E-08 8.34E-04 1.86E-04 O.OOE+OO 4.3SE-06 O.OOE+OO 3RD Quarter 4TH Quarter O.OOE+OO O.OOE+OO O.OOE+OO 2.48E-OS S.42E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.30E-04 3.40E-03 1.l6E-03 1.71E-03 2.78E-06 2.33E-04 O.OOE+OO O.OOE+OO 3.48E-04 3.48E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.l2E-06 1.29E-OS 4.11E-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.86E-OS 3.78E-OS 1.24E-04 3.44E-06 8. 12E-06 4.91E-06 1.23E-OS O.OOE+OO 8.28E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.01E-04 1.92E-04 1.39E-OS 6.26E-OS 4.97E-07 O.OOE+OO O.OOE+OO 1.99E-OS 1.22E-06 O.OOE+OO See Table 1-4 for typical minimum detectable concentrations.
Zeroes in this table indicates that no radioactivity was present at detectable levels. 12 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-lan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Cs-137 Curies 1.07E-04 S.04E-05 2.43E-04 1.53E-04 Eu-154 Curies O.OOE+OO 6.71E-OS O.OOE+OO O.OOE+OO Nd-147 CUries O.OOE+OO O.OOE+OO O.OOE+OO 2. 13E-06 Pr-146 Curies 6.65E-06 O.OOE+OO O.OOE+OO O.OOE+OO Rh-10S Curies O.OOE+OO 2.0SE-04 O.OOE+OO 1.09E-04 Rh-106 Curies O.OOE+OO O.OOE+OO 3.44E-06 O.OOE+OO Ru-103 Curies O.OOE+OO O.OOE+OO O.OOE+OO 4.07E-07 Ru-106 Curies O.OOE+OO O.OOE+OO 3.44E-06 O.OOE+OO Sb-124 Curies O.OOE+OO 4.7SE-05 1.24E-06 1.05E-04 Sb-125 Curies 7.69E-04 7.24E-04 2.03E-03 1.42E-03 Sn-1l3 Curies 5.07E-07 1.4SE-06 O.OOE+OO 1.35E-06 Tc-99M Curies 2.56E-06 O.OOE+OO O.OOE+OO 7.26E-07 Te-127 Curies 4.09E-05 O.OOE+OO O.OOE+OO O.OOE+OO Te-129 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.90E-05 Te-132 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.69E-07 Ag-10SM Curies 3.90E-06 O.OOE+OO 4.79E-07 4.30E-06 Ag-llOM Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-OS In-115M Curies O.OOE+OO O.OOE+OO 1.27E-06 O.OOE+OO Sn-U7M Curies O.OOE+OO 5.04E-06 3.25E-06 O.OOE+OO Te-125M Curies O.OOE+OO 5.34E-03 7.S3E-03 1.29E-02 Total For Period Curies 3.66E-03 1.S7E-02 1.24E-02 2.10E-02 Tritium H-3 Curies 2.03E+02 3.75E+01 1.16E+02 6.44E+01 See Table 1-4 for typical minimum detectable concentrations.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -13 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Dissolved And Entrained Gases Ar-41 Curies 7.63E-06 2.SSE-06 O.OOE+OO O.OOE+OO Kr-SSM Curies 4.SSE-07 O.OOE+OO 4.49E-07 O.OOE+OO Xe-133 Curies S.49E-04 9.SSE-OS 2.22E-03 7.S2E-04 Xe-13S Curies 1.02E-06 O.OOE+OO 3.S2E-07 O.OOE+OO Xe-13SM Curies S.41E-06 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies S.67E-04 1.01E-04 2.23E-03 7.S2E-04 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. 
-14 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission It Activation Products Sr-89 Total For Period Units Curies Curies 1ST Quarter 1.44E-03 1.44E-03 2ND Quarter O.OOE+OO O.OOE+OO 3RDQuarter O.OOE+OO O.OOE+OO 4TH Quarter O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. 
-15 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &. Activation Products Be-7 Curies O.OOE+OO O.OOE+OO O.OOE+OO S.37E-06 Y-88 Curies S.41E-07 7.72E-07 O.OOE+OO 1.2SE-06 Y-91 Curies O.OOE+OO 9.S8E-OS O.OOE+OO O.OOE+OO Y-93 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.48E-OS Y-9S Curies O.OOE+OO O.OOE+OO S.42E-06 O.OOE+OO As-76 Curies O.OOE+OO 3.38E-OS O.OOE+OO O.OOE+OO Br-84 Curies 1.71 E-OS 4.81E-06 O.OOE+OO 4.70E-06 Co-S7 Curies 1.06E-06 O.OOE+OO O.OOE+OO 2.4SE-06 Co-S8 Curies 2.09E-04 3.44E-03 9.00E-04 8.91E-03 Co-60 Curies 2.SSE-03 3.83E-03 1.6SE-03 3.39E-03 Cr-S1 Curies O.OOE+OO S.80E-04 2.41E-OS 9.20E-04 Cu-64 Curies O.OOE+OO 1.26E-06 O.OOE+OO O.OOE+OO Fe-SS Curies 4.71E-04 2.93E-03 S.00E-04 6.91E-04 Fe-S9 Curies O.OOE+OO 1.38E-04 O.OOE+OO 1.06E-06 1-131 Curies O.OOE+OO O.OOE+OO 1.62E-07 O.OOE+OO 1-133 Curies 1.64E-06 O.OOE+OO O.OOE+OO 2. 12E-06 Mn-S4 Curies 1.97E-OS 1.09E-04 1.29E-OS 6.76E-OS Mn-S6 Curies 1.4SE-06 O.OOE+OO O.OOE+OO O.OOE+OO Na-24 Curies 1.SSE-OS O.OOE+OO O.OOE+OO 1.86E-OS Nb-9S Curies 6.S9E-06 3.81E-04 4.S3E-OS 4.82E-04 Nb-97 Curies 3.88E-06 6.90E-06 3.44E-06 S.12E-06 Ni-S6 Curies O.OOE+OO S.S2E-OS S.S8E-06 4.69E-OS Rb-86 Curies O.OOE+OO O.OOE+OO O.OOE+OO S.28E-06 Sr-89 Curies 2.63E-04 6.72E-OS O.OOE+OO O.OOE+OO Sr-90 Curies l.S3E-OS O.OOE+OO O.OOE+OO O.OOE+OO Sr-92 Curies O.OOE+OO 1.26E-OS O.OOE+OO O.OOE+OO Zn-6S CUries 7.44E-04 1.09E-03 2. 18E-04 3.60E-04 See Table 1-4 for typical minimum detectable concentrations.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -16 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Zr-9S Zr-97 Ba-140 Cd-11S Cs-137 Eu-1S4 Nd-147 Pm-149 Pr-144 Pr-146 Rh-l0S Rh-106 Ru-l03 Ru-l06 Sb-122 Sb-124 Sb-12S Sn-l13 Tc-99M Te-127 Te-129 Te-132 Ag-l08M Ag-110M In-115M Units Curies Curies Curies Curies Curies Curies CUries Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.21E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.6SE-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.36E-04 S.07E-07 2.S6E-06 4.09E-OS O.OOE+OO O.OOE+OO 4.74E-06 O.OOE+OO O.OOE+OO 2ND Quarter 1.86E-04 O.OOE+OO 4.35E-06 O.OOE+OO S.S7E-OS 6.71E-08 O.OOE+OO 2.69E-OS O.OOE+OO O.OOE+OO 2.08E-04 O.OOE+OO O.OOE+OO O.OOE+OO 7.83E-06 S.74E-OS 8.21E-04 1.48E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.06E-06 O.OOE+OO O.OOE+OO 3RD Quarter 1.39E-05 4.97E-07 O.OOE+OO 1.22E-06 2.90E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.3SE-06 3.44E-06 O.OOE+OO 3.44E-06 O.OOE+OO 1.24E-06 2. l6E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.79E-07 O.OOE+OO 1.27E-06 4TH Quarter 2.48E-04 O.OOE+OO 1.99E-05 O.OOE+OO 1.64E-04 3. 13E-06 2.13E-06 O.OOE+OO 4.03E-04 O.OOE+OO 3.94E-04 O.OOE+OO l.l9E-06 O.OOE+OO O.OOE+OO 1.26E-04 1.82E-03 7.49E-06 7.26E-07 O.OOE+OO 1.23E-04 2.69E-07 4.30E-06 2.47E-OS O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. 
-17 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-lan-2010 Ending:
Batch Mode Nuclides Released Sn-117M Te-125M Te-129M Total For Period Iritium H-3 And Entrained Ar-41 Kr-85M Xe-133 Xe-135 Xe-131M Xe-133M Xe-135M Total For Period Units Curies Curies Curies Curies Curies Curies Curies Curies Curies CUries Curies Curies Curies 1ST Quarter O.OOE+OO O.OOE+OO O.OOE+OO 5.33E-03 4.24E+02 9.04E-06 4.5SE-07 1.0SE-03 1.02E-06 O.OOE+OO 2.63E-06 8,41E-06 1.07E-03 2ND Quarter 2.13E-02 1.89E+02 4,40E-06 O.OOE+OO 1.99E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3RD Quarter 1.46E-02 3.37E+02 O.OOE+OO 4,49E-07 4.24E-03 1.4SE-06 1.S8E-05 O.OOE+OO O.OOE+OO 2.03E-04 4TH Quarter 5.52E-02 8.39E+Ol 1.36E-06 O.OOE+OO 8.64E-04 2.78E-06 O.OOE+OO O.OOE+OO O.OOE+OO 8.68E-04 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations. 
-18 Table 1-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Doses to a member of the public due to Liquid Releases Unit: 1 Starting:
1-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr o/oODCM 2ND Qtr o/oODCM 3RD Qtr o/oODeM 4TH Qtr o/oODCM Bone S.OOE+OO mRem 2.61E-03 5.21E-02 1.12E-03 2.25E-02 4.S1E-04 9.61E-03 1.1SE-02 2.30E-Ol GI-Lli 5.00E+OO mRem 3.33E-03 6.67E-02 S.S3E-03 l.17E-Ol 4.1SE-03 S.36E-02 4.76E-02 9.S1E-Ol Kidney 5.00E+OO mRem 2.61E-03 5.23E-02 5.l0E-03 1.02E-Ol 3.97E-03 7.94E-02 4.64E-02 9.2SE-Ol Liver 5.00E+OO mRem 2.71E-03 5,42E-02 2.S0E-03 5.00E-02 2.6SE-03 S.36E-02 4.S6E-03 9.l3E-02 Lung 5.00E+OO mRem 2.97E-03 S.94E-02 2.62E-03 5.2SE-02 3.l4E-03 6.2SE-02 2.9SE-03 S.97E-02 Thyroid 5.00E+OO mRem 2.S9E-03 5.1SE-02 2.1SE-03 4.36E-02 2.S4E-03 S.OSE-02 3.67E-03 7.33E-02 Total Body 5.00E+OO mRem 2.76E-03 5.53E-02 2.l9E-03 4.3SE-02 2.56E-03 S.12E-02 1.9SE-03 3.96E-02 Total Body 1.50E+OO mRem 2.76E-03 l.S4E-Ol 2.19E-03 1.46E-Ol 2.S6E-03 l.71E-Ol 1.9SE-03 1.32E-Ol Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date o/oODCM Receptor Limit Bone 1.00E+Ol mRem 1.57E-02 l.S7E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+Ol mRem 6.09E-02 6.09E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+Ol mRem S.SlE-02 S.SlE-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 1.25E-02 1.25E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+Ol mRem 1.17E-02 1.17E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 1.10E-02 1.1OE-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.00E+Ol mRem 9,49E-03 9,49E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+OO mRem 9,49E-03 3.16E-Ol Maximum Individual Liquid Liquid Effluent TB Annual -19 Table 1-38 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2010 Doses to a member of the public due to Liquid Releases Unit: 2 Starting:
l-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr o/oODCM 2NDQtr o/oODCM 3RD Qtr o/oODCM 4TH Qtr o/oODCM Bone S.OOE+OO mRem 2.69E-03 S.3BE-02 2.BBE-03 S.76E-02 2.94E-03 S.B7E-02 4.2BE-03 B.S6E-02 GI-Lli S.OOE+OO mRem 3.46E-03 6.93E-02 l.l0E-02 2.21E-Ol 1.23E-02 2.46E-Ol 1.BOE-02 3.S9E-Ol Kidney S.OOE+OO mRem 2.29E-03 4.59E-02 9.0SE-03 l.B1E-Ol 1.1SE-02 2.29E-Ol 1.6BE-02 3.36E-Ol Liver S.OOE+OO mRem 2.49E-03 4.9BE-02 l.B9E-03 3.79E-02 2.46E-03 4.92E-02 2.43E-03 4.B6E-02 Lung S.OOE+OO mRem 6.2SE-03 1.2SE-Ol 4.63E-03 9.26E-02 9.93E-03 1.99E-Ol 7.23E-03 1.4SE-Ol Thyroid 5.00E+OO mRem 2.20E-03 4.40E-02 1.04E-03 2.07E-02 l.B7E-03 3.74E-02 l.B3E-03 3.66E-02 Total Body S.OOE+OO mRem 2.S3E-03 S.06E-02 1.OSE-03 2.10E-02 1.7SE-03 3.S0E-02 1.44E-03 2.B9E-02 Total Body l.S0E+OO mRem 2.S3E-03 1.69E-Ol 1.OSE-03 6.99E-02 1.7SE-03 l.l7E-Ol 1.44E-03 9.63E-02 Cumulative Doses per Year Organ ODCM Lmt Units Year to Endins Date o/oODCM Limit Bone 1.00E+Ol mRem 1.2BE-02 1.2BE-Ol Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+Ol mRem 4.4BE-02 4.4BE-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+Ol mRem 3.96E-02 3.96E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 9.27E-03 9.27E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+01 mRem 2.BOE-02 2.BOE-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 6.94E-03 6.94E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.00E+Ol mRem 6.77E-03 6.77E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+OO mRem 6.77E-03 2.26E-Ol Maximum Individual Liquid Liquid Effluent TB Annual -20 TABLE Joseph M. Farley Nuclear ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -MINIMUM DETECTABLE CON.CENTRATION 
-LIQUID SAMPLE The values in this table represent a Minimum Detectable Concentrations ) that are ly achieved in laboratory analyses of liquid radwaste samples. Nuclide MDC(uCi/ML)
MN-54 CO-58 FE-59 CO-60 1. ZN-65 MO-99 1-131 CS-134 CS 137 CE-141 CE 144 1. -21 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Batch Release Unit: Starting:
l-lan-2010 Ending:
Liquid Releases 1. Number of batch releases 2. Total time period for Batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release S. Minimum time period for a batch release 6. Average stream flow during periods of release of liquid effluent a flowing stream Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals -( Minutes) ( Minutes) ( Minutes) ( Minutes) (CFS) 79 1.00E+04 1.SOE+02 1.27E+02 1.0SE+02 6.66E+OS 76 9.S7E+03 1.40E+02 1.26E+02 8.40E+Ol 2.S4E+OS 92 1.23E+04 1.93E+02 1.34E+02 1.03E+02 8.47E+04 85 332 1.0SE+04 4.24E+04 1.4SE+02 1.93E+02 1.23E+02 1.28E+02 1.02E+02 8.40E+Ol 1.16E+05 2.78E+05 Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant. -22 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT .. Liquid Effluents 
.. Batch Release Unit: Starting:
1-Jan-2010 Ending:
Liquid Releases 1. Number of batch releases 2. Total time period for Batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release 5. Minimum time period for a batch release 6. Average stream flow during periods of release of liquid effluent a flowing stream Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals -( Minutes) ( Minutes) ( Minutes) ( Minutes) (CFS) 109 1.19E+04 1.80E+02 1.10E+02 7.80E+01 6.66E+OS 73 8.02E+03 1.61E+02 1.10E+02 2.00E+00 2.54E+OS 9S 1.0SE+04 1.44E+02 1.10E+02 9.00E+01 8.47E+04 98 37S 9.93E+03 4.04E+04 1.31E+02 1.80E+02 1.01E+02 1.08E+02 7.S0E+Ol 2.00E+00 1.16E+OS 2.78E+OS Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant. 23 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 0 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO -24 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 2. Total Time For All Releases ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO -25 0 2.0 GASEOUS EFFLUENTS This section contains applicable ODeM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2010. 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 ODeM 3.4.2 to show conformance with the limits of ODeM 3.1.3, and the offsite organ doses to a member of the public calculated in accordance with ODeM 3.4.3 to show conformance with ODeM 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: 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 For Iodine-131, Iodine 133,tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr. to any organ. 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases Technical Specifications 5.5.4.e and 5.5.4.h state that the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODeM Figure 10-1) shall be limited to the following: 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 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. 
-26 2.1.3 Doses to a Member of the Public Technical Specifications S.S.4.e and S.S.4.i state that the dose to a MEMBER OF THE PUBLIC from 1-131, I 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: During any calendar quarter: Less than or equal to 7.5 mrem to organ, During any calendar year: Less than or equal to 15 mrem to 2.2 Measurements and Approximation of Total Radioactivity The following noble gases are considered in evaluating gaseous effluents:
KR-87 XE KR-88 XE-13S XE-133M The following radioiodines and radioactive materials in particulate form are specifically considered in evaluating gaseous effluents:
MN-54 FE-59 I CO-58 CO-60 ZN-65 SR-89 SR-90 H -
2.2.1 Sample collection and Analysis Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height 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 iculates, 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 radioact materials collected on the filters. Part filters are then analyzed for gross alpha and strontium as required.
All gross alpha, Sr-89 and SR 90 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis.
Batch Releases:
The processing of batch type releases (from Containment when in batch mode, or Waste Gas Decay Tanks) is analogous to continuous releases, except that the release is not commenced until samples have been obtained and analyzed.
Containment Purge batch releases were commenced at FNP beginning in 2006 in order to take advantage of additional decay time for short lived radionuclides.
Typically achieved minimum detectable concentrations for gaseous effluent sample analyses are reported in Table 2-6. 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, rates, and cumulative doses -28 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 part are calculated (with computer assistance).
The calculated dose rates are compared to the dose rate limits spec in ODCM 3.1.2 for noble gases, radioiodine, tritium, and particulates.
Dose rate calculation methodology is presented in the ODCM. Beta and gamma doses due to noble gases are calculated for the location in the unrestricted area with the 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 Part Releases Released quantities of radioiodines are determined using the weekly samples and release flow rates for the applicable release points. Radioiodine concentrations are determined by gamma spectroscopy.
Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the applicable release points. Gamma spectroscopy is used to quantify the concentrations of principal gamma emitters.
After each , 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 compos 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. 
-29 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. highest concentration calculated for any of these weeks is used for the monthly value. This value is input into the composite file of the computer and used for release calculations.
2.2.3 Total Error Estimation The maximum errors associated with monitor readings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedure are collectively estimated to be: Fission Activation Gases Iodine Particulates 75% 60% 50% The average error associated with counting is estimated to be: Fission Activation Gases Iodine Particulates 19% 28% 20% -30 2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables lA, 1B and 1C are found in this report as Tables 2 lA, 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 aDCM 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 aDCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in aDCM 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 release permits. No limits were exceeded for this reporting period. Gross alpha radioactivity is reported in Tables 2 lA, 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 aDCM limits. Limits for cumulative doses to an individual due to radioiodines, tritium and particulates are specif in aDCM 3.1.4. Cumulative individual doses are presented in Tables 2 SA and 2 5B along with percent of aDCM limits. -31 2.4 Radiological Impact Due to Gaseous Releases The air doses due to noble gases and doses to a Member of the Public due to radioiodines, tritium and particulates in gaseous effluents for Units 1 and 2 are provided in the following tables in order to show conformance with the limits of ODCM 3.1.3 and ODCM 3.1.4: Unit 1 2010 Air Doses Due to Noble Gases in Gaseous Releases:
Table 2-4A Unit 2 2010 Air Doses Due to Noble Gases in Gaseous Releases:
Table 2-4B Unit 1 2010 Doses to a Member of the Public Due to Radioiodines, and Particulates in Gaseous Releases:
Table 2 Unit 2 2010 Doses to a Member of the Public Due to Radioiodines, and Particulates in Gaseous Releases:
Table 2.5 Gaseous Effluents Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables: Unit 1 2010 Gaseous Effluents 
-Batch Release Summary: Table 2-7A Unit 2 2010 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 2010. Abnormal release information for Units 1 and 2 is summarized in the following Unit 1 2010 Gaseous Effluents 
-Abnormal Release Summary: Table Unit 2 2010 Gaseous Effluents 
-Abnormal Release Summary: Table 2 -32 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Unit: Starting:
1-Jan-2010 Ending:
Type of Effluent Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter A. Fission And Activation Gases 1. Total Release Curies 6.39E+OO 2.6SE+Ol 7.43E+OO 1.94E+OO 2. Average Release rate for period uCi/sec S.lOE-Ol 3.36E+OO 9.42E-Ol 2.46E-Ol 3. Percent of Applicable Limit % * * *
* B. Radioiodines 
: 1. Total Iodine-131 Curies 1.03E-04 1.69E-OS 1.10E-OS l.77E-OS 2. Average Release rate for period 3. Percent of Applicable Limit uCi/sec % 1.30E-OS
* 2.l4E-06
* 1.39E-06
* 2.2SE-06
* C. Particulates 
: 1. Particulates ( Half-Lives>
S Days) Curies 1.96E-06 1.66E-07 S.04E-09 2.72E-06 2. Average Release rate for period uCi/sec 2.49E-07 2.llE-OS 6.39E-l0 3.4SE-07 3. Percent of Applicable Limit % * * *
* D. Tritium 
: 1. Total Release Curies 2.3SE+Ol 3.1SE+Ol 9.11E+OO 2.72E+OO 2. Average Release rate for period 3. Percent of Applicable Limit uCi/sec% 2.9SE+OO
* 3.99E+OO
* 1.16E+OO
* 3.4SE-Ol
* E. Gross 
: 1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO -33 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Unit: Starting:
l-lan-2010 Ending:
Type of Effluent Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter A. Fission And Activation Gases 1. Total Release Curies l.S9E+OO 3.62E+OO 3. 13E+OO 2.6SE-Oi 2. Average Release rate for period uCi/sec 2.02E-Oi 4.60E-Oi 3.97E-Ol 3.36E-02 3. Percent of Applicable Limit % * * *
* B. Radioiodines 
: 1. Total Iodine-131 Curies O.OOE+OO 3.11E-OS O.OOE+OO 2.S2E-09 2. Average Release rate for period uCi/sec O.OOE+OO 3.9SE-09 O.OOE+OO 3.SSE-i0 3. Percent of Applicable Limit % * * *
* C. Particulates 
: 1. Particulates ( Half-Lives>
S Days) Curies 1.34E-OS 9.46E-07 2.S9E-OS O.OOE+OO 2. Average Release rate for period uCi/sec 1.70E-09 1.20E-07 3.66E-09 O.OOOE+OO 
: 3. Percent of Applicable Limit % * * *
* 1. Total Release Curies 2.56E+OO 1.15E+Ol 2.72E+Oi 3.40E+OO 2. Average Release rate for period uCi/sec% 3.24E-Ol l.4SE+OO 3.46E+OO 4.32E-Ol 3. Percent of Applicable Limit * * *
* E. Gross 
: 1. Total Release Curies 1.llE-OS O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec 1.40E-09 O.OOE+OO O.OOE+OO O.OOE+OO *Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-48, 2-SA, 2-58 of this report. -
Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Unit: Starting:
1-Jan-2010 Ending:
Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases 1. Total Release Curies 7.97E+OO 3.0lE+Ol 1.06E+Ol 2.2lE+OO 2. Average Release rate for period uCi/sec 1.01E+OO 3.B2E+OO 1.34E+OO 2.BOE-Ol 3. Percent of Applicable Limit % * * *
* B. Radioiodines 
: 1. Total Iodine-13l Curies 1.03E-04 1.69E-05 1.1OE-OS l.77E-OS 2. Average Release rate for period uCi/sec 1.30E-OS 2.lSE-06 l.39E-06 2.2SE-06 3. Percent of Applicable Limit % * * *
* C. Particulates 
: 1. Particulates ( Half-Lives>
B Days) Curies 1.9BE-06 1.llE-06 3.39E-OB 2.72E-06 2. Average Release rate for period uCi/sec 2.51E-07 1.4lE-07 4.30E-09 3.45E-07 3. Percent of Applicable Limit % * * *
* D. Tritium 1. Total Release Curies 2.6lE+Ol 4.29E+Ol 3.64E+Ol 6.12E+OO 2. Average Release rate for period uCi/sec% 3.31E+OO S.44E+OO 4.6lE+OO 7.77E-Ol 3. Percent of Applicable Limit * * *
* E. Gross 
: 1. Total Release Curies 1.llE-OB O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec 1.40E-09 O.OOE+OO O.OOE+OO O.OOE+OO
* Applicable limits are expressed in terms of dose. See Tables 2-4A/ 2-48/ 2-5A/ 2-58 of this report. -35 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission Gases Ar-41 Xe-133 Xe-135 Total For Period Iodines Total For Period Units Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 4.74E+OO 1.12E+OO 8.46E-02 5.94E+OO 1.03E-04 4. 16E-04 3.59E-04 2ND Quarter 2.26E+01 3.45E-01 3.59E+OO 2.65E+01 1.69E-05 9.45E-05 8.22E-07 3RD Quarter 7.06E+OO 2.37E-01 1.26E-01 7.43E+OO 1.1OE-05 5.98E-05 7.89E-07 4TH Quarter 1.79E+OO 3.28E-03 2. 16E-04 1.79E+OO 1.77E-05 1.60E-06 O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations. 
-36 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Particulates Be-7 Curies 6.83E-07 O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.89E-08 Co-58 Curies 9.36E-07 2.79E-09 2.79E-09 6.86E-08 Co-60 Curies 3.33E-07 8.68E-l0 2.24E-09 1.43E-07 Zn-65 Curies 1.42E-09 O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.63E-07 Sr-89 Curies 9.51E-09 1.63E-07 O.OOE+OO O.OOE+OO Sr-90 Curies O.OOE+OO O.OOE+OO O.OOE+OO 6.39E-09 Zr-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO 8.90E-07 Nb-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.08E-06 Cs-137 Curies O.OOE+OO O.OOE+OO O.OOE+OO 4.27E-08 Eu-155 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.95E-07 Total For Period Curies 1.96E-06 1.66E-07 5.04E-09 2.71E-06 Tritium H-3 Curies 2.17E+Ol 3.15E+Ol 9.11E+OO 2.72E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations. 
-37 1-131 H-3 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Fission Gases Ar-41 Xe-131M Xe-133 Xe-135M Xe-135 Total For Period lodines Total For Period Particulates Co-5B Co-60 Total For Period Tritium Gross Alpha No Nuclides Found Units Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 3.29E-Ol O.OOE+OO 1.07E-Ol O.OOE+OO 7.SBE-03 4.44E-Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.B1E+OO O.OOE+OO 2ND Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3RD Quarter 4.42E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1. llE-05 4.S3E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4TH Quarter 6.20E-02 1.5BE-03 B.S9E-02 SAlE-OS O.OOE+OO 1.49E-Ol S.04E-08 S.04E-OS 7. 13E-09 3. llE-09 1.02E-OS 1.3BE-03 O.OOE+OO If Not Detected l Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations. 
-38 Table 2-28 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Gaseous Effluents 
-Mixed Mode Level Releases Unit: 2 Starting:
l-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.12E+00 3.59E+00 2.97E+00 O.OOE+OO Total For Period Curies 1.12E+OO 3.S9E+OO 2.97E+OO O.OOE+OO Iodines 1-131 Curies O.OOE+OO 7.32E-09 O.OOE+OO O.OOE+OO 1-133 Curies O.OOE+OO 2.62E-08 O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO 3.3SE-08 O.OOE+OO O.OOE+OO Particulates Cr-51 Curies O.OOE+OO 1.95E-07 O.OOE+OO O.OOE+OO Mn-54 Curies O.OOE+OO 1.03E-07 O.OOE+OO O.OOE+OO Fe-59 Curies O.OOE+OO 3.66E-08 O.OOE+OO O.OOE+OO Co-58 Curies O.OOE+OO 1.12E-07 O.OOE+OO O.OOE+OO Co-60 Curies O.OOE+OO 1.08E-07 O.OOE+OO O.OOE+OO Sr-89 Curies 1.34E-08 3.90E-07 O.OOE+OO O.OOE+OO Sr-90 Curies O.OOE+OO 1.86E-09 2.89E-08 O.OOE+OO Total For Period Curies 1.34E-08 9.46E-07 2.89E-08 O.OOE+OO Tritium H-3 Curies 2.54E+OO 1.15E+Ol 2.66E+Ol 1.63E+OO Gross Alpha G-Alpha Curies 1.llE-08 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.11E-08 O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes See Table 2-6 for typical minimum detectable concentrations.
in this table indicates that no radioactivity was present at detectable levels. -39 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 4.6SE-01 2,4SE-04 1.65E-01 2.6SE-01 Xe-133M Curies O.OOE+OO 4.16E-04 O.OOE+OO O.OOE+OO Xe-133 Curies 1.67E-03 3.20E-02 O.OOE+OO O.OOE+OO Xe-135 Curies O.OOE+OO 5.27E-05 O.OOE+OO O.OOE+OO Xe-127 Curies O.OOE+OO O.OOE+OO O.OOE+OO 7.37E-OS Total For Period Curies 4.70E-01 3.27E-02 1.6SE-01 2.6SE-01 Iodines I-131 Curies O.OOE+OO 2.3SE-OS O.OOE+OO 2.S2E-09 Total For Period Curies O.OOE+OO 2.3BE-OB O.OOE+OO 2.B2E-09 Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies l.S4E-02 O.OOE+OO 6,40E-01 l.77E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations. 
-40 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies S.86E+OO 2.62E+Ol loOOE+Ol 1.79E+OO Xe-133 Curies lo12E+OO 3.45E-Ol 2.37E-Ol 3.28E-03 Xe-13S Curies 8.46E-02 3.S9E+OO lo26E-Ol 2.16E-04 Total For Period Curies 7.06E+OO 3.01E+01 1.04E+01 1.79E+OO Iodines 1-131 Curies lo03E-04 lo69E-OS 1.10E-OS lo77E-OS 1-133 Curies 4.16E-04 9.45E-05 S.98E-05 1.60E-06 1-13S Curies 3.59E-04 8.22E-07 7.89E-07 O.OOE+OO Total For Period Curies 8.77E-04 1.12E-04 7.16E-05 1.93E-05 See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -41 Table 2-2C Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Particulates Be-7 Curies 6,S3E-07 O,OOE+OO O,OOE+OO O,OOE+OO Cr-51 Curies O,OOE+OO 1.95E-07 O,OOE+OO O,OOE+OO Mn-54 Curies O,OOE+OO 1.03E-07 O,OOE+OO 1.S9E-OS Fe-59 Curies O,OOE+OO 3,66E-OS O,OOE+OO O,OOE+OO Co-5S Curies 9,36E-07 1.15E-07 2,79E-09 6,86E-OS Co-60 Curies 3,33E-07 1.09E-07 2,24E-09 1,43E-07 Zn-65 Curies 1.42E-09 O,OOE+OO O,OOE+OO O.OOE+OO Rb-S6 Curies O,OOE+OO O,OOE+OO O,OOE+OO 1.63E-07 Sr-S9 Curies 2.29E-OS 5,52E-07 O,OOE+OO O.OOE+OO Sr-90 Curies O.OOE+OO 1.S6E-09 2.S9E-OS 6.39E-09 Zr-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO S.90E-07 Nb-95 Curies O.OOE+OO O.OOE+OO O,OOE+OO 1.0SE-06 Cs-137 Curies O,OOE+OO O.OOE+OO O,OOE+OO 4,27E-OS Eu-155 Curies O.OOE+OO O.OOE+OO O,OOE+OO 2,95E-07 Total For Period Curies 1.98E-06 1.11E-06 3.39E-08 2.71E-06 Tritium H-3 Curies 2,42E+01 4.29E+01 3.57E+Ol 4,35E+OO Gross Alpha G-Alpha Curies 1.llE-08 O,OOE+OO O.OOE+OO O,OOE+OO Total For Period Curies 1.11E-08 O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations. 
-42 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 7.97E-Ol 2.48E-04 L6SE-Ol 3.27E-Ol Xe-131M Curies O.OOE+OO O.OOE+OO O.OOE+OO LS8E-03 Xe-133M Curies O.OOE+OO 4. 16E-04 O.OOE+OO O.OOE+OO Xe-133 Curies L09E-Ol 3.20E-02 O.OOE+OO 8.S9E-02 Xe-13SM Curies O.OOE+OO O.OOE+OO O.OOE+OO S.41E-OS Xe-13S Curies 7.58E-03 S.27E-OS LllE-OS O.OOE+OO Xe-127 Curies O.OOE+OO O.OOE+OO O.OOE+OO 7.37E-OS Total For Period Curies 9.13E-01 3.27E-02 1.6SE-01 4.1SE-01 lodines 1-131 Curies O.OOE+OO 2.38E-08 O.OOE+OO S.32E-08 Total For Period Curies O.OOE+OO 2.3SE-OS O.OOE+OO S.32E-OS Particulates Co-58 Curies O.OOE+OO O.OOE+OO O.OOE+OO 7. 13E-09 Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.11E-09 Total For Period Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-OS Tritium H-3 Curies L83E+OO O.OOE+OO 6.40E-Ol l.77E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -43 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission Gases No Nuclides Found Units Curies 1ST Quarter O.OOE+OO 2ND Quarter O.OOE+OO 3RDQuarter O.OOE+OO 4TH Quarter O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -44 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents 
-Ground Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Fission No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -45 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
l-lan-2010 Ending:
Continuous Mode Nuclides Released Fission Gases No Nuclides Found Units Curies 1ST Quarter O.OOE+OO 2ND Quarter O.OOE+OO 3RD Quarter O.OOE+OO 4TH Quarter O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -46 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Fission Gases No Nuclides Found Units Curies 1ST Quarter O,OOE+OO 2ND Quarter O.OOE+OO 3RD Quarter O.OOE+OO 4TH Quarter O,OOE+OO Iodines No Nuclides Found Curies O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found CUries O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -47 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
l-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission Gases No Nuclides Found Units Curies 1ST Quarter O.OOE+OO 2ND Quarter O.OOE+OO 3RDQuarter O.OOE+OO 4TH Quarter O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected l Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -48 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Fission Gases No Nuclides Found Units Curies 1ST Quarter O.OOE+OO 2ND Quarter O.OOE+OO 3RD Quarter O.OOE+OO 4TH Quarter O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO See Table 2-6 for typical minimum detectable concentrations.
If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. -49 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Air Doses Due to Gaseous Unit: Starting:
l-Jan-2010 Ending:
Cumulative Doses Per Quarter Type of Radiation Gamma Air Beta Air ODCM Lmt S.OOE+OO 1.00E+Ol Units mRad mRad Cumulative Dos es Per Year Type of Radiation Gamma Air Beta Air ODCM Lmt 1.00E+Ol 2.00E+Ol Units mRad mRad lSTQtr 1.64E-03 6.21E-04 %ODCM 3.27E-02 6.21E-03 2NDQtr 7.44E-03 2.8SE-03 %ODCM 1.49E-Ol 2.8SE-02 3RDQtr 2.26E-03 8. 13E-04 %ODCM 4.S2E-02 8. 13E-03 4TH Qtr S.91E-04 2. llE-04 %ODCM 1.18E-02 2.11E-03 Year to End Date %ODCM Receptor Limit 1.19E-02 4.S0E-03 1.19E-Ol 2.2SE-02 Site Boundary SSE Mixed Mode R Site Boundary SSE Mixed Mode R Air Dose Gamma Annual Air Dose Beta Annual -50 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Air Doses Due to Gaseous Unit: Starting:
1-Jan-2010 Ending:
Cumulative Doses Per Quarter Type of Radiation ODCM Lmt Units Gamma Air S.OOE+OO mRad Beta Air 1.00E+Ol mRad Cumulative Doses Per Year Type of Radiation ODCM Lmt Units Gamma Air 1.00E+Ol mRad Beta Air 2.00E+Ol mRad lSTQtr 5.06E-04 1.78E-04 %ODCM 1.01E-02 1.78E-03 2ND Qtr 1.14E-03 4.0SE-04 %ODCM 2.29E-02 4.0SE-03 3RD Qtr 9.98E-04 3.S2E-04 %ODCM 2.00E-02 3.S2E-03 4TH Qtr 8ASE-OS 2.98E-OS %ODCM 1.69E-03 2.98E-04 Year to End Date 2.73E-03 9.6SE-04 %ODCM 2.73E-02 4.82E-03 Receptor Site Boundary SSE Mixed Mode R Site Boundary SSE Mixed Mode R Limit Air Dose Gamma Annual Air Dose Beta Annual -51  
--Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Unit: Starting:
1-Jan-2010 Ending:
Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr %ODCM 2NDQtr %ODCM 3RDQtr %ODCM 4TH Qtr %ODCM Bone 7.50E+OO mRem 9.S0E-06 1.31E-04 2.9SE-06 3.97E-OS S.19E-07 1.09E-OS S.4SE-06 7.26E-OS GI-Lli 7.S0E+OO mRem 3.01E-03 4.02E-02 2.SSE-03 3.4SE-02 S.OOE-04 6.67E-03 3.06E-04 4.0SE-03 Kidney 7.50E+OO mRem 3.02E-03 4.03E-02 2.S9E-03 3.4SE-02 S.02E-04 6.69E-03 3.06E-04 4.0SE-03 Liver 7.S0E+OO mRem 3.02E-03 4.03E-02 2.SSE-03 3.4SE-02 S.OlE-04 6.6SE-03 3.06E-04 4.07E-03 Lung 7.S0E+OO mRem 3.01E-03 4.02E-02 2.SSE-03 3.4SE-02 S.OOE-04 6.67E-03 3.04E-04 4.06E-03 Thyroid 7.S0E+OO mRem S.02E-03 6.70E-02 2.92E-03 3.90E-02 7.20E-04 9.61E-03 6.2SE-04 S.33E-03 Total Body 7.S0E+OO mRem 3.02E-03 4.02E-02 2.SSE-03 3.4SE-02 S.01E-04 6.6SE-03 3.06E-04 4.07E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date %ODCM Receptor Limit Bone 1.S00E+Ol mRem 1.904E-OS 1.270E-04 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli l.S00E+Ol mRem 6.404E-03 4.269E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney 1.S00E+Ol mRem 6.416E-03 4.277E-02 Gas Controlling Receptor Iodine/Part Dose Annual Liver l.S00E+Ol mRem 6.4llE-03 4.274E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung l.S00E+Ol mRem 6.401E-03 4.267E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid l.S00E+Ol mRem 9.293E-03 6.19SE-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body l.S00E+Ol mRem 6.407E-03 4.271E-02 Gas Controlling Receptor Iodine/Part Dose Annual -52 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Unit: Starting:
2010 Ending:
Cumulative Doses Per Quarter Organ ODCM Lmt Units 1ST Qtr %ODCM 2ND Qtr o/oODCM 3RDQtr o/oODCM 4TH Qtr o/oODCM Bone 7.50E+OO mRem 1.63E-07 2.17E-06 6.37E-06 8,49E-OS 1.21E-OS 1.61E-04 1.69E-l0 2.26E-09 GI-Lli 7.50E+OO mRem 3,43E-04 4.58E-03 9.33E-04 1.24E-02 3.03E-03 4.04E-02 4.66E-04 6.21E-03 Kidney 7.S0E+OO mRem 3,43E-04 4.58E-03 9.33E-04 1.24E-02 3.03E-03 4.04E-02 4.66E-04 6.21E-03 Liver 7.50E+OO mRem 3.43E-04 4.58E-03 9.33E-04 1.24E-02 3.03E-03 4.04E-02 4.66E-04 6.21E-03 Lung 7.50E+OO mRem 3.43E-04 4.58E-03 9.33E-04 1.24E-02 3.03E-03 4.04E-02 4.66E-04 6.21E-03 Thyroid 7.S0E+OO mRem 3.43E-04 4.58E-03 9.34E-04 1.24E-02 3.03E-03 4.04E-02 4.66E-04 6.21E-03 Total Body 7.S0E+OO mRem 3,43E-04 4.S8E-03 9.34E-04 1.24E-02 3.03E-03 4.04E-02 4.66E-04 6.21E-03 Cumulative Doses per Year Organ ODCM Lmt Units Year to Ending Date o/oODCM Receptor Limit Bone l.S00E+Ol mRem 1.862E-OS 1.241E-04 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli l.S00E+Ol mRem 4.769E-03 3.180E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney 1.500E+Ol mRem 4.769E-03 3.179E-02 Gas Controlling Receptor Iodine/Part Dose Annual Liver 1.500E+Ol mRem 4.769E-03 3.179E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung l.S00E+Ol mRem 4.769E-03 3.179E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid l.S00E+Ol mRem 4.769E-03 
: 3. 180E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body l.S00E+Ol mRem 4.772E-03 3.182E-02 Gas Controlling Receptor Iodine/Part Dose Annual -
TABLE Joseph M. Farley Nuclear ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -MINIMUM DETECTABLE CONCENTRATIONS 
-GASEOUS EFFLUENT The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples. Nuclide MDC(uCi/ML)
Nuclide MDC{uCi/ML)
MN-54 4.17E-14 KR-87 4.64E-OS CO-58 7.65E-14 KR-SS 7.46E-OS FE-59 2.53E-14 XE-133 4.71E OS CO-60 6.01E-14 XE-133M 1.42E-07 ZN-65 2.40E-13 XE-135 1.58E-OS MO-99 4.46E-13 XE-138 1.21E-07 CS-134 S.17E-14 1-131 5.95E-14 CS-137 6.95E-15 1-133 8.96E-14 CE-141 CE-144 
-54 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Batch Release Unit: Starting:
1-Jan-2010 Ending:
Gaseous Releases 1. Number of batch releases 2. Total time period for batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release S. Minimum time period for a batch release Units ( Minutes) ( Minutes) ( Minutes) ( Minutes) 1ST Quarter 76 4.38E+03 5.63E+02 5.76E+01 5.00E+00 2ND Quarter 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3RD Quarter 8 3.92E+03 7.59E+02 4.89E+02 2.31E+02 4TH Quarter Year Totals 18 102 2.02E+03 1.03E+04 6.84E+02 7.59E+02 1.12E+02 1.01E+02 6.00E+00 5.00E+00 -55 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Batch Release Unit: Starting:
1-Jan-2010 Ending:
Gaseous Releases 1. Number of batch releases 2. Total time period for batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release 5. Minimum time period for a batch release Units ( Minutes) ( Minutes) ( Minutes) ( Minutes) 1ST Quarter 102 8.31E+03 1.05E+03 8.15E+01 4.00E+OO 2ND Quarter 8 2.73E+03 4.13E+02 3.41E+02 2.67E+02 3RDQuarter 38 2.31E+03 2.90E+02 6.08E+01 6.00E+OO 4TH Quarter Year Totals 65 213 3.14E+03 1.65E+04 2.68E+02 1.05E+03 4.83E+01 7.74E+01 2.00E+OO 2.00E+OO -56 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Abnormal Release Unit: Starting:
l-lan-2010 Ending:
Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 0 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO -57 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending:
Gaseous Releases Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 0 2. Total Time For All Releases ( Minutes):
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes):
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes):
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes):
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) : O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 58 3.0 SOLID WASTE 3.1 Regulatory Requirements 3.1.1Solid Radioactive Waste System FNP-O-M-30 step B.3.1 states that the radwaste solidification system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of radioactive wastes from the site. 3.1.2 Reporting Requirements FNP-0-M-30 step B.3.1 states that the Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specifications 5.6.2 and 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 Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," Revision 2, June 2009, with data summarized on an annual basis following the format of Table A-3 thereof. 3.2 Solid Waste Data Regulatory Guide 1.21 Revision 2 Table A-3 is found in the report as Table 3-1. -59 TABLE Joseph M. Farley Nuclear ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -SOLID RADIOACTIVE WASTE SHIPPED FOR PROCESSING OR DISPOSAL Starting 0l-Jan-2010 Ending 31-Dec-2010 I Dry Active Waste Volume Curies Shipped m;j ft;j Waste Class A 1.87E+04 5.31 E+02 3.72E-01 B O.OOE+OO O.OOE+OO O.OOE+OO I O.OOE+OO O.OOE+OO O.OOE+OO I IC ALL 1.87E+04 5.31 E+02 3.72E-01 I I Resins, Filters, and Evaporator Bottoms Volume Curies Shipped Waste Class ft;j m;j ! A O.OOE+OO O.OOE+OO O.OOE+OO B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides for the Above Table: Waste Class A I\J/A Waste Class B N/A Waste Class C N/A ALL N/A Major Nuclides for the Above Table: Waste Class Nb-95 27.431% Zr-95 18.303% Co-60 6.889% Cr-51 6.008% Be-7 1.223% Sb-125 1 .122% Waste Class N/A Waste Class N/A Nb-95 27.431% Zr-95 18.303% Co-60 6.889% Cr-51 6.008% Be-7 1.223% Sb-125 1 .122% Major Nuclides for the Above Table: Waste Class A N/A Waste Class B N/A Waste Class C N/A ALL N/A Fe-55 17.517% Co-58 10.116% l\Ji-63 5.202% Zn-65 2.096% H-3 1.078% Fe-55 17.517% Co-58 10.116% Ni-63 5.202% Zn-65 2.096% H-3 1.078% Irradiated Components Volume Curies Shipped Waste Class fe m;j A O.OOE+OO O.OOE+OO O.OOE+OO B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO O.OOE+OO I Other Waste Volume Curies Shipped I Waste Class tr' m" IA 2.85E+02 8.07E+00 2.40E-04 I B O.OOE+OO O.OOE+OO O.OOE+OO ! IC O.OOE+OO O.OOE+OO O.OOE+OO I ALL 2.85E+02 8.07E+00 2.40E-04 Major Nuclides for the Above Waste Class A Waste Class B Waste Class C NIALL TABLE 3-1 Joseph M. Farley Nuclear ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -SOLID RADIOACTIVE WASTE SHIPPED FOR PROCESSING OR DISPOSAL Starting 0l-Jan-2010 Ending 31-Dec-2010 (Continued)
I I Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ff m" A 1.90E+04 5.39E+02 3.72E-01 B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO ALL 1.90E+04 5.39E+02 3.72E-01 Major Nuclides for the Above Table: Waste Class Nb-95 27.413% Co-60 6.884% Be-7 1.222% Waste Class B N/A Waste Class C N/A Nb-95 27.413% Co-60 6.884% Be-7 1.222% Zr-95 18.291% Fe-55 17.506% Co-58 10.1 09% Cr-51 6.004% Ni-63 5.198% Zn-65 2.095% H-3 1.142% Sb-125 1 .122% Zr-95 18.291 % Fe-55 17.506% Co-58 10.109% Cr-51 6.004% Ni*63 5.198% Zn-65 2.095% H-3 1.142% Sb*125 1 .122%
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 2010 using the methods described in ODCM 6.2 and is included in this section as Table 4 1.
Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a Member of the Public Due to Activities Inside the Site Unit: Starting:
1-Jan-2010 Ending:
Location Name: Visitor Center Distance (kilometers):
3.06E-Ol Sector: N Occupancy Factor: 1.37E-03 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3):
1.04E-04 Ground Level Release Particulate and Radioiodine X/Q (sec/m3):
1.04E-04 D/Q (m-2): 4.S0E-07 Mixed Mode Release Noble Gas X/Q (sec/m3):
S.SOE-06 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3):
S.SOE-06 D/Q (m-2): 6.20E-OS Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Bone mRem 3.23E-08 9.3SE-09 2.73E-09 1.23E-08 S.67E-OS Liver mRem 1.0SE-OS 1,lOE-OS 1, l1E-OS 2.42E-06 3.51E-OS Total Body mRem 1.0SE-OS 1,lOE-OS 1.l1E-OS 2.42E-06 3.S0E-OS Thyroid mRem 1.1SE-OS 1, 13E-OS 1.12E-OS 2.S3E-06 3.68E-OS Kidney mRem 1,OSE-OS 1.lOE-OS 1.l1E-OS 2.42E-06 3.S1E-OS Lung mRem 1.0SE-OS 1.lOE-OS 1, l1E-OS 2.42E-06 3.S0E-OS GI-Ui mRem 1.0SE-OS 1.lOE-OS 1.l1E-OS 2.42E-06 3.S0E-OS NG Total Body mRem 2.27E-OS 9.lOE-OS 3.46E-OS 7.17E-06 l.SSE-04 Whole Body Dose mRem 3.32E-OS 1,02E-04 4.S6E-OS 9.S9E-06 1.91E-04 Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a Member of the Public Due to Activities Inside the Site Unit: Starting:
I-Jan-2010 Ending:
Location Name: Distance (kilometers):
Sector: Occupancy Factor: Age Group: Ground Level Release Ground Level Release Mixed Mode Release Mixed Mode Release Bone Liver Total Body Thyroid Kidney Lung GI-Lli NG Total Body Whole Body Dose Service Water Pond 9.66E-Ol N 7.S7E-03 Child Noble Gas X/Q (sec/m3):
4.74E-OS Particulate and Radioiodine X/Q (sec/m3):
4.74E-OS Noble Gas X/Q (sec/m3):
9.7SE-07 Particulate and Radioiodine X/Q (sec/m3):
9.7SE-07 Units 1ST Quarter 2ND Quarter 3RD Quarter D/Q (m-2):
D/Q (m-2):
4TH Quarter Year 2.92E-OS 1.2SE-07 l.S0E-06 2.1SE-OS l.S0E-06 2.1SE-OS l.S7E-06 2.26E-OS l.S0E-06 2. 16E-OS 1.S0E-06 2.1SE-OS l.S0E-06 2.1SE-OS 4.39E-06 9.52E-OS S.S9E-06 1.17E-04 mRem mRem mRem mRem mRem mRem mRem mRem mRem 7.1SE-OS 6.S1E-06 6.50E-06 7.27E-06 6.S1E-06 6.S0E-06 6.50E-06 1.39E-OS 2.04E-OS 2.11E-OS 6.77E-06 6.77E-06 6.92E-06 6.77E-06 6.77E-06 6. 77E-06 S.S7E-OS 6.2SE-OS 3.61E-09 6.77E-06 6.77E-06 6.S7E-06 6.77E-06 6.77E-06 6.77E-06 2.12E-OS 2.79E-OS Table Joseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a Member of the Public Due to Activities Inside the Site Unit: Starting:
1-Jan-2010 Ending:
Location Name: River Water Discharge 
-Air Distance (kilometers):
1.64E+OO Sector: N Occupancy Factor: 1.14E-02 Age Group: Child Ground Level Release Noble Gas X/Q (sec/m3):
1.63E-OS Ground Level Release Particulate and Radioiodine X/Q (sec/m3):
1.63E-OS D/Q (m-2): 4.SSE-08 Mixed Mode Release Noble Gas X/Q (sec/m3):
7.0SE-07 Mixed Mode Release Particulate and Radioiodine X/Q (sec/m3):
7.0SE-07 D/Q (m-2): 1.39E-08 Units 1ST Quarter 2ND Quarter 3RDQuarter 4TH Quarter Year Bone mRem S,48E-08 1.61E-OS 3.06E-09 2.21E-08 9.61E-08 Liver mRem 7.06E-06 7.36E-06 7.37E-06 1.63E-06 2.34E-OS Total Body mRem 7.06E-06 7.36E-06 7.37E-06 1.63E-06 2.34E-OS Thyroid mRem 7.S9E-06 7.S3E-06 7,4SE-06 1.70E-06 2,46E-OS Kidney mRem 7.06E-06 7.36E-06 7.37E-06 1.63E-06 2.34E-OS Lung mRem 7.06E-06 7.36E-06 7.37E-06 1.63E-06 2.34E-OS GI-Lli mRem 7.06E-06 7.36E-06 7.37E-06 1.63E-06 2.34E-OS NG Total Body mRem l.S1E-OS 6.07E-OS 2.31E-OS 4.7SE-06 1.04E-04 Whole Body Dose mRem 2.22E-OS 6.S0E-OS 3.04E-OS 6,40E-06 1.27E-04 -65 Table loseph M Farley Nuclear RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a Member of the Public Due to Activities Inside the Site Unit: Starting:
1-lan-2010 Ending:
Location Name: Distance (kilometers):
Sector: Occupancy Factor: Age Group: Ground Level Release Ground Level Release Mixed Mode Release Mixed Mode Release Bone Liver Total Body Thyroid Kidney Lung GI-Lli NG Total Body Whole Body Dose New Construction Activity 3.22E-Ol 5 2.28E-Ol Adult Noble Gas X/Q (sec/m3):
1.8SE-04 Particulate and Radioiodine X/Q (sec/m3):
6.66E-05 Noble Gas X/Q (sec/m3):
2,42E-06 Particulate and Radioiodine X/Q (sec/m3):
2.23E-06 Units 1ST Quarter 2ND Quarter 3RD Quarter D/Q (m-2): 9.26E-OS D/Q (m-2): 9.26E-OS D/Q (m-2): S.66E-09 D/Q (m-2): 8.66E-09 4TH Quarter Year 2.99E-07 5.99E-07 1.1SE-04 1.24E-03 1.1SE-04 1.24E-03 1.19E-04 1.26E-03 1.1SE-04 1.24E-03 1.1SE-04 1.24E-03 1.15E-04 1.24E-03 3.28E-04 6.06E-03 4,43E-04 7.30E-03 mRem mRem mRem mRem mRem mRem mRem mRem mRem 1.13E-lO 6.6SE-OS 6.6SE-OS 6.6SE-OS 6.6SE-OS 6.6SE-OS 6.6SE-OS O.OOE+OO 6.6SE-OS 2.17E-07 5.33E-04 S.33E-04 S.39E-04 S.33E-04 S.33E-04 S.33E-04 4.1SE-03 4.68E-03 S.32E-OS S.27E-04 S.27E-04 S.31E-04 S.27E-04 S.27E-04 S.27E-04 l.S8E-03 2.UE-03 -66 TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190) Regulatory Requirements Technical Specification 5.5.4.j states that the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem (as stated in ODCM 5.1). With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM 2.1.3, 3.1.3, or 3.1.4, calculations shall be made according to ODCM 5.2 methods to determine whether the above (ODCM 5.1) limits have been exceeded (as stated in ODCM 5.1.2) . Demonstration of Compliance Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded during 2010, no calculations were required. 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. PROGRAM DEVIATIONS Inoperable Liquid or Gaseous Effluent 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. 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 two effluent monitoring equipment deviations during 2010. an 12 16 09, the Unit 1 Waste Monitor Tank#2 flow indicator was declared inoperable (CR2010100515) and was out of service over 30 days on 1/15/2010.
Per aDCM 2.1.1.2, this instrument should have been repaired within 30 days or explained in the Radioactive Effluent Release Report. an 11-26 09, the U1 service water dilution flow transmitter was declared inoperable (CR2009115154) and was out of service over 30 days on 1/25/2010.
Per aDCM 2.1.1.21 this instrument should have been repaired within 30 days or explained in the Radioactive Effluent Release Report. The repair on this transmitter is currently on hold pending required design modifications (CR2009115239). Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) 7.2.1 Regulatory Requirements aDCM 7.2.2.6 states in part that the report shall include deviations from the MDC requirements included in aDCM Tables 2 3 and 3-3. 7.2.2 Description of Deviations There were no deviations during 2010. Incorrect Compositing of Liquid or Gaseous Effluent Samples 7.3.1 Regulatory Requirements aDCM 7.2.2.6 states in part that the report shall include deviations from composite sampling requirements included in aDCM Tables 2-3 and 3-3. -68 7.3.2 Description of Deviations There were no deviations during 2010. 8.0 CHANGES TO THE PLANT FARLEY ODCM 8.1 Regulatory Requirements Pursuant to Technical Specification s.s.l.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 was one change to the ODCM during 2010. The Radiological Environmental Monitoring Program (REMP) control sample location for milk, 0714 -Weir Dairy, is no longer able to provide milk samples. This location was removed from the ODCM Table 4-4, REMP Locations, and Figure 4-3, Sampling Locations, o 20 miles. There is no available replacement location at this time. -69 MAJOR CHANGES TO LIQUID, GASEOUS, OR SOLID RADWASTE TREATMENT SYSTEMS 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 the period in which the change was implemented.
The discussion of each change shall include the information specified in PCP B.4.1. Description of Major Changes On 4-16-2010 a change to the Process Control Program, 30 Version 17 was approved by the PRB. This change updated guidance for annual reporting of solid waste based on Regulatory Guide 1.21, Revision 2. The change also included corrections to several Technical Specification references to reflect the appropriate sections of the current Technical Specifications.
This revision did not result in a change to waste forms produced at FNP. -
Farley Nuclear Plant Appendix A CARBON-14 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of "principal radionuclides" in gaseous effluents have changed, and C-14 has become a larger percentage. "Principal radionuclides" are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21), "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate.
In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants will report 14 amounts released and resulting doses to the maximally exposed member of the public. Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation.
The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.
At Plant Farley, the quantity of C-14 released in gaseous effluents in 2010 was estimated to be 9.28 Curies (per unit). Approximately 30% of the C-14 released is in the form of 14C02 and is incorporated into plants through photosynthesis.
Ingestion dose results from this pathway. The remaining 70% is estimated to be organic. Both the organic and inorganic forms ofC-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Farley ODCM, the resulting bone dose to a child located at the controlling receptor location would be 4.IIE-01 mrem in a year which is 2.74% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents.
The resulting total body dose to a child located at the controlling receptor location would be 8.21E-02 mrem in a year which is 0.54% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents. 
-71 Edwin I. Hatch Nuclear Joseph M. Farley Nuclear Vogtle Electric Generating Annual Radioactive Effluent Release Reports for Enclosure Vogtle Annual Radioactive Effluent Release Report for SOUTHERN NUCLEAR VOGTLE ELECTRIC GENERATING PLANT -UNITS 1 AND NRC DOCKET NOS. 50-424 AND FACILITY OPERATING LICENSE NOS. NPF-68 AND ANNUAL RADIOACTIVE EFFLUENT RELEASE JANUARY 1, 2010 TO DECEMBER Page 1 of 87 VOGTLE ELECTRIC GENERATING RADIOACTIVE EFFLUENT RELEASE REPORT -TABLE OF SECTION TITLE PAGE 1.0 1.1 1.1.1 1.1.2 1.2 1.3 1.3.1 1.3.2 1.4 1.5 1.6 1.7 Table 1-1A Table 1-1B Table 1-1C Table 1-2A liquid Effluents Regulatory Requirements Concentration limits Dose Limits Effluent Concentration limit (ECl) Measurements and Approximations of Total Radioactivity Total Radioactivity Determination Total Error Estimation liquid Effluent Release Data Radiological Impact Due to liquid Releases liquid Effluents 
-Batch Releases liquid Effluents 
-Abnormal Releases Liquid Effluents 
-Summation of All Releases Unit (Quarters 1,2,3, and 4) liquid Effluents 
-Summation of All Releases Unit (Quarters 1,2,3, and 4) liquid Effluents 
-Summation of All Releases Site 1,2,3, and 4) Liquid Effluents 
-Summation of All Releases Unit (Quarters 1,2,3, and 4) Page 2 of Table 1-28 Liquid Effluents 
-Summation of All Releases Unit (Quarters 1,2,3, and 4) Table 1-2C Liquid Effluents 
-Summation of All Releases Site 1,2,3, and 4) Table 1-3A Doses to a Member of the Public Due to Liquid Unit 1 (Quarters 1,2,3, and 4) Table 1-38 Doses to a Member of the Public Due to Liquid Unit 2 (Quarters 1,2,3, and 4) Table 1*3C Doses to a Member of the Public Due to Liquid Site (Quarters 1,2,3, and 4) Table 1-4 Minimum Detectable Liquid Sample Analysis Table 1-5A Liquid Effluents 
-Batch Release Summary Unit 1 Table 1-58 Liquid Effluents 
-Batch Release Summary Unit 2 Table 1-5C Liquid Effluents 
-Batch Release Summary Site Table 1-6A Liquid Effluents 
-Abnormal Release Summary Unit 1 Table 1-68 Liquid Effluents 
-Abnormal Release Summary Unit 2 Table 1-6C Liquid Effluents 
-Abnormal Release Summary Site 2.0 Gaseous Effluents 2.1 Regulatory Requirements 2.1.1 Dose Rate Limits 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 2.1.3 Doses to a Member of the Public 2.2 Measurements and Approximations of Total Radioactivity Page 3 ofS7 Sample Collection and Analysis 36 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 37 Fission and Activation Gases 37 Radioiodines, Tritium and Particulate Releases 37 Gross Alpha Release 37 Total Error Estimation 38 Gaseous Effluent Release Data 39 Radiological Impact Due to Gaseous Releases 40 Gaseous Effluents 
-Batch Releases 40 2.6 Gaseous Effluents 
-Abnormal Releases 40 Table 2-1A Gaseous Effluents 
-Summation of All Releases -Unit 1 (Quarters 1,2,3, and 4) 42 Table 2-1B Gaseous Effluents 
-Summation of All Releases -Unit 2 (Quarters 1,2,3, and 4) 43 Table 2-1C Gaseous Effluents 
-Summation of All Releases -Site (Quarters 1,2,3, and 4) 44 Table 2-2A Gaseous Effluents 
-Mixed Mode Releases Unit 1 (Quarters 1,2,3, and 4) 45 Table 2-2B Gaseous Effluents 
-Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 47 Table 2-2C Gaseous Effluents 
-Mixed Mode Releases Site (Quarters 1,2,3, and 4) 49 Page 4 of 87 Table 2-3A Gaseous Effluents 
-Ground Level Releases Unit 1 (Quarters 1,2,3, and 4) 51 Table 2-3B Gaseous Effluents 
-Ground Level Releases Unit 2 (Quarters 1,2,3, and 4) 53 Table 2-3C Gaseous EtUuents -Ground Level Releases Site (Quarters 1,2,3, and 4) 55 Table 2-4A Air Doses Due to Noble Gases in Gaseous Releases Unit 1 (Quarters 1,2,3, and 4) 57 Table 2-4B Air Doses Due to Noble Gases in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 58 Table 2-4C Air Doses Due to Noble Gases in Gaseous Releases Site (Quarters 1,2,3, and 4) 59 Table 2-5A Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit 1 (Quarters 1,2,3, and 4) 60 Table 2-5B Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit 2 (Quarters 1,2,3, and 4) 61 Table 2-5C Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Site (Quarters 1,2,3, and 4) 62 Table 2-6 Minimum Detectable Concentrations Gaseous Sample Analyses 63 Table 2-7A Gaseous Effluents 
-Batch Release Summary Unit 1 64 Page 5 of87 Table 2-7B Gaseous Effluents 
-Batch Release Summary Unit 2 Table 2-7C Gaseous Effluents 
-Batch Release Summary Site Table 2-8A Gaseous Effluents 
-Abnormal Release Summary Unit 1 Table 2-8B Gaseous Effluents 
-Abnormal Release Summary Unit 2 Table 2-8C Gaseous Effluents 
-Abnormal Release Summary Site Solid Waste Regulatory Requirements Solid Radioactive Waste System Reporting Requirements 3.2 Solid Waste Data Table 3-1 Solid Waste and Irradiated Fuel Shipments Doses to Members of the Public Inside the Site Boundary Regulatory Requirements 4.2 Demonstration of Compliance Table 4-1 Doses to a Member of the Public Due to Activities the Site Boundary Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Demonstration of Compliance Meteorological Data Program Deviations Inoperable Liquid or Gaseous Effluent Instrumentation Regulatory Requirement Page 6 of87 7.1.2 Description of Tanks Exceeding Curie Content Limits Regulatory Requirements Description of Deviations Changes to the Vogtle Electric Generating Plant Dose Calculation Manual (ODCM) Regulatory Requirements Description of Changes Major Changes to Liquid, Gaseous, or Solid Treatment Systems Regulatory Requirements Description of Major Changes 10.0 Corrections to Previous Reports APPENDIX A VEGP Carbon-14 Attachment 1 Revised Previous Reports Page 7 of87 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 IlCi/ml total activity.
1.1.2 Dose Limits The dose or dose comrnitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited as follows: 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 During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 rnrems 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 1 E-04 IlCilml total activity.
For gross alpha in liquid radwaste, the ECl is 2 E-09 IlCi/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 87 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 METHOD Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction. 
: 2. Dissolved or entrained Each Gamma Spectroscopy noble with computerized data reduction 
: 3. Tritium Distillation and liquid scintillation counting Gross Alpha Monthly Gas flow proportional Composite counting 5. Sr-89 & Sr-90 Chemical separation and gas flow proportional or scintillation counting 6. Quarterly Chemical separation and liquid scintillation counting Page 9 of 87 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 (Le., 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 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 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 87 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 Counting Equipment Calibration Tank Volumes and System Flow Rates TOTAL ERROR 10% 10% 20% 24.5% b. Total Tritium release was calculated from sample analysis results and release point volumes. Sampling and statistical errors Counting equipment calibration Tank volumes and system flow rate TOTAL ERROR 10% 10% 20% 24.5% c. Dissolved and entrained gases were calculated from sample analysis results and release point volumes. Sampling and statistical error Counting equipment calibration Tank volumes and system flow rate TOTAL ERROR 20% 10% 20% 30% d. Gross alpha radioactivity was calculated 
'from sample analysis results and release point volumes. Sampling and statistical error Counting EqUipment calibration Tank volumes and system flowrates TOTAL ERROR 10% 10% 20% 24.5% Page 11 of 87 Total Error Estimation cont'd 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% 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% Gross alpha, Sr-89, Sr-90, Fe-55 and H-3 radioactivity has an additional error associated with sample compositing.
Compositing sample 5% Liquid Effluent Release Data Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Tables 1-1A, 1-1B, 1-1C, 1-2A, 1-2B and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters. 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. 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. Liquid Effluents 
-Abnormal Releases There were no abnormal liquid releases during 2010. Page 12 of 87 Table l-lA Vogtle Electric Generating Plant Liquid Effluents 
-Summation of All Releases Unit: 1 Starting:
1-Jan-2010 Ending: 31-Dec-2010 Type of Effl Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) Curies 1.00E-02 1.2SE-02 4.94E-03 9.99E-03 2. Average diluted concentration during period uCi/mL 1.01E-OS S.97E-09 1.92E-09 2.S9E-09 3. Percent of Applicable Limit % * *
* B. Tritium 1. Total Curies 3,4SE+02 7.67E+01 3.S7E+01 1.64E+02 2. Average diluted Concentration during period uCi/mL 3.S1E-04 3.SSE-OS 1.S0E-OS 4.74E-OS 3. Percent of Applicable Limit % * *
* C. Dissolved and Entrained Gases 1. Total Curies 4.10E-01 S.09E-04 O.OOE+OO 2.S7E-03 2. Average diluted Concentration during period uCi/mL 4.14E-07 2.3SE-10 O.OOE+OO 7,4SE-10 3. Percent of Applicable Limit % * *
* D: Gross Alpha Radioactivity 
: 1. Total Curies 6,46E-06 2.21E-06 O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution)
Liters 4.S1E+07 4.30E+07 4.19E+07 2.S2E+07 F. Volume of Dilution Water Used Liters 9.91E+OS 2.14E+09 2.SSE+09 3,46E+09 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-38 of this report. Page 13 of 87 Table 1-18 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Liquid Effluents 
-Summation Of All Releases Unit: 2 Starting:
l-Jan-2010 Ending: 31-Dec-2010 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Ouarter 4TH Quarter A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) Curies 7.23E-03 S.S6E-03 1.1SE-03 1.S3E-04 2. Average diluted concentration during period uCi/MI 7.21E-09 2.S6E-09 4.74E-10 6.0SE-ll 3. Percent of Applicable Limit % * *
* 8. Tritium 1. Total Curies 2.3SE+02 2.90E+01 6.94E+OO 9.S0E-01 2. Average diluted Concentration during period uCi/mL 2.37E-04 1.49E-OS 2.S6E-06 3.26E-07 3. Percent of Applicable Limit % * *
* C. Dissolved and Entrained Gases 1. Total Curies 1.96E-01 2,47E-04 O.OOE+OO O.OOE+OO 2. Average diluted Concentration during period uCi/mL 1.9SE-07 1.27E-10 O.OOE+OO O.OOE+OO 3. Percent of Applicable Limit % * *
* D: Gross Alpha Radioactivity 
: 1. Total Curies O.OOE+OO 1.02E-06 O.OOE+OO 2.00E-07 E: Waste Vol Release (Pre-Dilution)
Liters 2.67E+07 2.2SE+07 1.77E+07 1.46E+07 F. Volume of Dilution Water Used Liters 1.00E+09 1.9SE+09 2.43E+09 3.00E+09 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-36 of this report. Page 14 of 87 Table 1-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Liquid Effluents 
-Summation Of All Releases Unit: Site Starting:
1-Jan-2010 Ending: 31-Dec-2010 Type of Units 1ST Ouarter 2ND Ouarter 3RD Quarter 4TH Quarter A. Fission And Activation Products 1. Total Release (not tritium, gases, alpha) Curies 1.73E-02 1.84E-02 6.09E-03 
: 2. Average diluted during period uCijmL 8.66E-09 4,49E-09 1. 22E-09 
: 3. Percent of Applicable Limit % * *
* B. Tritium 1. Total Curies S.86E+02 1.06E+02 4.S7E+01 1.6SE+02 2. Average diluted during period uCijmL 2.94E-04 2.S8E-OS 9. 13E-06 
: 3. Percent of Applicable Limit % * *
* C. Dissolved and Entrained Gases 1. Total Curies 6.06E-01 7.56E-04 O.OOE+OO 2.S7E-03 2. Average diluted Concentration during period uCi/mL 3.04E-07 1.8SE-l0 O.OOE+OO 3.99E-10 3. Percent of Applicable Limit % * *
* D: Gross Alpha Radioactivity 
: 1. Total Curies 6.46E-06 3.23E-06 O.OOE+OO 2.00E-07 E: Waste Vol Release (Pre-Dilution)
Liters 7.18E+07 6.SSE+07 S.96E+07 3.98E+07 F. Volume of Dilution Water Used Liters 1.99E+09 4.09E+09 S.OlE+09 6,46E+09 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-36 of this report. Page 15 of87 Table 1-2A Vogtle Electric Generating RADIOAC11VE EFFLUENT RELEASE REPORT -Liquid Unit: Startina:
l-lan-201g Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Ouarter 3 RD Ouarter 4TH Ouarter fission It Activation C..o-57 Olripc; 1.RnF-nn nnnF+nn n.nnF+nn RR4F-nn Co-58 Curies 2.66E-03 7. 72E-04 9. 13E-04 6.7SE-04 Co-60 Curies 6.63E-04 2.66E-04 4.3SE-04 6.74E-04 Cr-S1 Curies O.OOE+OO O.OOE+OO O.OOE+OO lA6E-04 Fe-55 Curies 2.89E-03 8.02E-04 9. 14E-04 1.29E-03 1-131 Curies 2A3E-04 S.20E-OS O.OOE+OO 1.43E-04 1-133 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.88E-OS Mn-54 Curies 3.26E-06 2.28E-OS 3.72E-OS 1.39E-OS Nb-9S Curies O.OOE+OO 8.21E-07 O.OOE+OO O.OOE+OO 5r-89 Curies 9.01E-04 7. 14E-OS 4.87E-06 O.OOE+OO 5r-90 Curies 6.89E-OS S.12E-06 1.lSE-06 O.OOE+OO W-187 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.06E-OS Ba-141 Curies 6.66E-OS O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 Curies 1.84E-OS 4.S4E-07 l.40E-OS 2.76E-OS Cs-137 Curies 2.69E-04 3.03E-OS SA8E-OS S.98E-OS Eu-1S2 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.6SE-OS 5b-12S Curies 2.2SE-03 6.0SE-04 2.S6E-03 6.8SE-03 Tc-99M Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.01E-OS Te-132 Curies S.84E-06 O.OOE+OO O.OOE+OO O.OOE+OO Te-125M Cucies Q.OOE+OO l.JJE-Q3 Q.OOI;+QQ O.QQE+QQ Total For Period Curies 1.00E-02 3.96E-03 4.94E-03 9.99E-03 Tritium H-3 Curies 3A8E+02 7.66E+01 3.86E+Ol 1.64E+02 *Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations Page 16 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending: 31-Dec-2010 Batch Mode Nuclides Released Dissolved And Entrained Gases Kr-8SM Xe-133 Xe-13S Xe-131M Xe-133M Total For Period Gross Alpha Radioactivity G-Alpha Units Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 1.09E-OS 3.99E-01 7.21E-04 7.83E-03 2.24E-03 4.10E-Ol 6.46E-06 2ND Quarter O.OOE+OO 4.66E-04 O.OOE+OO 4.29E-OS O.OOE+OO S.09E-04 2.21E-06 3RD Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4TH Quarter O.OOE+OO 2.S7E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.S7E-03 O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 17 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: 1 Starting:
1-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Fission & Activation Products Fe-55 Total For Period Units Curies Curies 1ST Quarter O.OOE+OO O.OOE+OO 2ND Quarter 8.84E-03 8.84E-03 3RD Quarter O.OOE+OO O.OOE+OO 4TH Quarter O.OOE+OO O.OOE+OO Tritium H-3 Curies 4.19E-02 8.28E-02 1.12E-01 6.83E-02 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 18 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-1an-2010 Ending: 31-Dec-2010 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission It Activation Products Co-57 Curies S.S2E-06 O.OOE+OO O.OOE+OO O.OOE+OO Co-58 Curies 1.28E-03 2.83E-04 1.37E-04 1.23E-OS Co-60 Curies 7.33E-04 9.96E-05 2.13E-04 9A7E-OS Fe-55 Curies 3.54E-03 2.23E-05 6.32E-OS 1.31E-OS 1-131 Curies 1.16E-04 3.69E-05 O.OOE+OO O.OOE+OO Mn-54 Curies 3.30E-05 O.OOE+OO 8.S0E-06 3.91E-06 Sr-89 Curies 1.16E-04 O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 Curies 5.31E-06 O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 Curies 1.03E-04 O.OOE+OO O.OOE+OO O.OOE+OO Eu-152 Curies 1.65E-05 O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 Curies 1.28E-03 2.70E-04 7.28E-04 S.8SE-OS Te-132 Curies 6.01E-06 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 7.23E-03 7.11E-04 1.lSE-03 1.83E-04 Tritium H-3 Curies 2.38E+02 2.89E+01 6.86E+OO 9.14E-01 Dissolved And Entrained Gases Xe-133 Curies 1.91E-01 2,47E-04 O.OOE+OO O.OOE+OO Xe-135 Curies 4.29E-05 O.OOE+OO O.OOE+OO O.OOE+OO Xe-131M Curies 3.55E-03 O.OOE+OO O.OOE+OO O.OOE+OO Xe-133M Curies 1.29E-03 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.96E-01 2.47E-04 O.OOE+OO O.OOE+OO *Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 19 of8?
Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Gross Alpha Radioactivity G-Alpha Curies O.OOE+OO 1.02E-06 O.OOE+OO 2.00E-07 Page 20 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
l-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission 8t Activation Products Fe-SS Total For Period Tritium H-3 Units Curies Curies Curies 1ST Quarter O.OOE+OO O.OOE+OO 3. 14E-02 2ND Quarter 4.8SE-03 4.8SE-03 3.09E-02 3RD Quarter O.OOE+OO O.OOE+OO 7.84E-02 4TH Quarter O.OOE+OO O.OOE+OO 6.SSE-02 Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nuclides FOl.lnd Curies Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 21 of 87 Table 1-2C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2010 Liquid Effluents Unit: Site Starting:
1-Jan-2010 Ending: 31-Dec-2010 Batch Mode NuClides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission &. Activation Products Co-57 Co-58 Co-60 Cr-S1 Fe-55 1-131 1-133 Mn-S4 Nb-9S Sr-89 Sr-90 W-187 Sa-14l Cs-134 Cs-137 Eu-1S2 Sb-12S Tc-99M Te-132 Te-12SM Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 7.33E-06 3.94E-03 1.40E-03 O.OOE+OO 6.44E-03 3.S9E-04 O.OOE+OO 3.62E-OS O.OOE+OO 1.02E-03 7.42E-OS O.OOE+OO 6.66E-OS 1.84E-OS 3.73E-04 1.6SE-OS 3.S2E-03 O.OOE+OO 1.19E-OS O.OOE+OO O.OOE+OO 1.0SE-03 3.66E-04 O.OOE+OO 8.2SE-04 8.89E-OS O.OOE+OO 2.28E-OS 8.21E-07 7.l4E-OS S.12E-06 O.OOE+OO O.OOE+OO 4.S4E-07 3.03E-OS O.OOE+OO 8.7SE-04 O.OOE+OO O.OOE+OO 1.33E-03 O.OOE+OO 1.0SE-03 6.48E-04 O.OOE+OO 9.78E-04 O.OOE+OO O.OOE+OO 4.S7E-OS O.OOE+OO 4.87E-06 1.1SE-06 O.OOE+OO O.OOE+OO 1.40E-OS S.48E-OS O.OOE+OO 3.29E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.84E-06 6.87E-04 7.68E-04 1.46E-04 1.31E-03 1.43E-04 3.88E-OS 1.79E-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.06E-OS O.OOE+OO 2.76E-OS S.98E-OS 2.6SE-OS 6.91E-03 1.01E-OS O.OOE+OO O.OOE+OO Total For Period CUries 1.73E-02 4.67E-03 6.09E-03 1.02E-02 Tritium H-3 Curies S.86E+02 1.06E+02 4.SSE+Ol 1.6SE+02 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 22 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending: 31-Dec-2010 Batch Mode Nuclides Released Dissolved And Entrained Gases Kr-8SM Xe-133 Xe-13S Xe-131M Xe-133M Total For Period Gross Alpha Radioactivity G-Alpha Units Curies Curies Curies Curies Curies Curies Curies 1ST Quarter 1.09E-OS S.90E-01 7.64E-04 1.14E-02 3.S3E-03 6.06E-Ol 6.46E-06 2ND Quarter O.OOE+OO 7. 13E-04 O.OOE+OO 4.29E-OS O.OOE+OO 7.S6E-04 3.23E-06 3RD Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4TH Quarter O.OOE+OO 2.S7E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.S7E-03 2.00E-07 Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 23 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Unit: Starting:
1-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Fe-55 Curies O.OOE+OO 1.37E-02 O.OOE+OO g.OOE+OO Total For Period Curies O.OOE+OO 1.37E-02 O.OOE+OO O.OOE+OO Tritium H-3 Curies 7.32E-02 1.14E-01 1.90E-01 1.34E-01 Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6[055 Alpha Badioactillil&#xa5; No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 24 of87 Table 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2010 Doses to a member of the public due to Liquid Releases Unit: 2 Starting:
I-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses per Quarter Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body ODCM 5.00E+OO 5.00E+OO 5.00E+OO 5.00E+OO 5.00E+OO 5.00E+OO 1.S0E+OO Units mRem mRem mRem mRem mRem mRem mRem 1ST Qtr 4.79E-03 9.27E-03 9.37E-03 1.13E-02 1.3SE-02 8.78E-03 1.08E-02 %ODCM 9.57E-02 1.8SE-01 1.87E-01 2.26E-01 2.69E-01 1.76E-O1 7.20E-01 2ND Otr 1.64E-03 2.95E-03 2.41E-03 3. 19E-03 4.02E-03 2. 13E-03 2.S0E-03 %ODCM 3.29E-02 5.90E-02 4.81E-02 6.37E-02 8.0SE-02 4.27E-02 1.67E-01 3RD Qtr 5.21E-04 1.S8E-03 1.21E-03 1.67E-03 6.91E-03 9.89E-04 1.48E-03 %ODCM 1.04E-02 3. 17E-02 2.43E-02 3.34E-02 1.38E-01 1.98E-02 9.8SE-02 4TH Qtr 8.26E-04 6.37E-03 5. 18E-03 5.91E-03 2.12E-02 5.06E-03 S.63E-03 %ODCM 1.65E-02 1.27E-01 1.04E-01 1.18E-01 4.24E-01 1.01E-01 3.7SE-01 Cumulative Doses per Year Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body ODCM 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 3.00E+OO Units mRem mRem mRem mRem mRem mRem mRem Year to Ending Date 7.78E-03 2.02E-02 1.82E-02 2.21E-02 4.S6E-02 1.70E-02 2.04E-02 O/oODCM 7.78E-02 2.02E-01 1.82E-01 2.21E-Ol 4.S6E-Ol 1.70E-Ol 6.80E-01 Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Maximum Individual Liquid Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent Organ Annual Liquid Effluent TB Annual Page 25 of 87 Table 1-38 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2010 Doses to a member of the public due to Liquid Releases Unit: 2 Starting:
l-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses per Quarter Organ ODCM Units 1ST Qtr o/oODCM 2ND Qtr o/oODCM 3RD Qtr o/oODCM 4TH Qtr o/oODCM Bone S.OOE+OO mRem 1.10E-03 2.20E-02 6.S7E-04 1.37E-02 1.70E-OS 3.40E-04 1.37E-06 2.73E-OS GI-Lli S.OOE+OO mRem 6.20E-03 1.24E-Ol 1.12E-03 2.24E-02 3.74E-04 7ASE-03 SA2E-OS 1.0SE-03 Kidney S.OOE+OO mRem 6.l0E-03 1.22E-O 1 7.7SE-04 1.SSE-02 1.99E-04 3.99E-03 3.32E-OS 6.64E-04 Liver S.OOE+OO mRem 6.S2E-03 1.36E-Ol 1.2SE-03 2.49E-02 2.02E-04 4.0SE-03 3.41E-OS 6.81E-04 Lung S.OOE+OO mRem S.S9E-03 1.72E-Ol 1.64E-03 3.28E-02 1.88E-03 3.7SE-02 l.S7E-04 3. 13E-03 Thyroid S.OOE+OO mRem S.93E-03 1.l9E-Ol S.30E-04 1.66E-02 1.99E-04 3.98E-03 3.31E-OS 6.62E-04 Total Body 1.S0E+OO mRem 6.4SE-03 4.32E-Ol S.S9E-04 S.92E-02 2.06E-04 1.37E-02 3.4SE-OS 2.30E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date &deg;/oODCM ReceRtor Limit Bone 1.00E+Ol mRem 1.S1E-03 1.81E-02 Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli 1.00E+Ol mRem 7.7SE-03 7.7SE-02 Maximum Individual Liquid Liquid Effluent Organ Annual Kidney 1.00E+Ol mRem 7.l0E-03 7.l0E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem S.31E-03 S.31E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+Ol mRem 1.23E-02 1.23E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 6.99E-03 6.99E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+OO mRem 7.61E-03 2.S4E-Ol Maximum Individual Liquid Liquid Effluent TB Annual Page 26 of 87 Table 1-3C Vogtle Electric Generating Plant RADIOAcnYE EFFLUENT RELEASE REPORT -2010 Doses to a member of the public due to Liquid Releases Unit: Site Starting:
l-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses per Quarter Organ Bone GI-Lli Kidney Liver Lung Thyroid Total Body ODCM S.OOE+OO 5.00E+OO S.OOE+OO S.OOE+OO 5.00E+OO S.OOE+OO loSOE+OO Units mRem mRem mRem mRem mRem mRem mRem 1ST Qtr S.B9E-03 loS5E-02 lo5SE-02 1.B1E-02 2.21E-02 lo47E-02 lo73E-02 o/oODCM 1.1BE-Ol 3.10E-Ol 3.09E-Ol 3.63E-Ol 4.41E-Ol 2.94E-Ol 1.1SE+OO 2ND Qtr 2.33E-03 4.07E-03 3.1BE-03 4.43E-03 S.67E-03 2.97E-03 3.39E-03 o/oODCM 4.66E-02 B.14E-02 6.36E-02 B.B7E-02 lo13E-Ol S.93E-02 2.26E-Ol 3RD Qtr S.3BE-04 1.96E-03 1.41E-03 1.B7E-03 B.79E-03 1.19E-03 lo68E-03 o/oODCM 1.0BE-02 3.92E-02 2.B2E-02 3.7SE-02 1. 76E-Ol 2.3BE-02 1.12E-Ol 4TH Qtr B.27E-04 6.42E-03 S.22E-03 S.94E-03 2.14E-02 S.09E-03 S.66E-03 &deg;/oODCM 1.6SE-02 1.2BE-Ol 1.04E-Ol 1.19E-Ol 4.27E-Ol 1.02E-Ol 3.7BE-Ol Cumulative Doses per Year Organ ODCM Units Year to Ending o/oODCM ReceRtor Limit Bone 1.00E+Ol mRem 9.SBE-03 9.SBE-02 Maximum Individual Liquid liquid Effluent Organ Annual GI-Lli loOOE+Ol mRem 2.79E-02 2.79E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Kidney loOOE+Ol mRem 2.S3E-02 2.S3E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 3.04E-02 3.04E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Lung loOOE+Ol mRem 5.79E-02 S.79E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 2.40E-02 2.40E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 3.00E+OO mRem 2.BOE-02 9.34E-Ol Maximum Individual Liquid Liquid Effluent TB Annual Page 27 of 87 Table 1-4 Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -MINIMUM DETECTABLE CONCENTRATIONS 
-LIQUID SAMPLE Starting:
1-Jan-2010 Ending: 31-Dec-2010 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples. RADIONUCUDE MDC UNITS Mn-54 2.73E-OS f.LCijml Fe-59 S.33E-OS f.L Ci/ml Co-5S 3.7SE-OS f.LCi/ml Co-60 6.76E-OS f.L Ci/ml Zn-65 1.32E-07 f.LCi/ml Mo-99 4.31E-07 f.LCi/ml Cs-134 3.06E-OS f.L Ci/ml Cs-137 4.51E-OS f.LCi/ml Ce-141 6.99E-OS f.L Ci/ml Ce-l44 2.95E-07 f.L Ci/ ml I-131 5.97E-OS f.LCijml Xe-133 9.11E-OS f.LCi/ml Xe-135 4.27E-OS f.LCi/ml Fe-55 1.00E-06 f.LCijml Sr-S9 5.00E-OS f.LCi/ml Sr-90 7.00E-09 f.LCijml H-3 2.00E-06 f.LCi/ml Gross Alpha 7.00E-OS f.LCijml Page 28 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Batch Release Unit: Starting:
l-lan-2010 Ending:
Liquid Releases units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of batch releases 23 15 12 16 66 2. Total time period for Batch releases ( Minutes) 5.28E+03 2.75E+03 1.98E+03 5.32E+03 1.53E+04 3. Maximum time period for a batch ( Minutes) 3.67E+02 3.49E+02 2.75E+02 8.76E+02 8.76E+02 4. Average time period for a batch ( Minutes) 2.30E+02 1.83E+02 1.65E+02 3.32E+02 2.32E+02 5. Minimum time period for a batch ( Minutes) 5.70E+01 6.10E+01 6.00E+01 5.50E+01 5.50E+01 6. Average stream flow during periods of release of liquid effluent a flowing stream * ( CFS ) 19,898 8,134 6,415 5,218 *Average river f10wrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle. Page 29 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Batch Release Unit: Starting:
1-1an-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of batch releases 9 4 2 1 16 2. Total time period for Batch releases ( Minutes) 2.66E+03 1.1OE+03 3.51E+02 6.60E+01 4.18E+03 3. Maximum time period for a batch ( Minutes ) 3.72E+02 3.40E+02 2.69E+02 6.60E+01 3.72E+02 4. Average time period for a batch ( Minutes) 2.96E+02 2.75E+02 1.76E+02 6.60E+01 2.61E+02 5. Minimum time period for a batch ( Minutes ) 1.65E+02 2.22E+02 8.20E+01 6.60E+01 6.60E+01 6. Average stream flow during periods of release of liquid effluent into a flowing stream * ( CFS ) 19,898 8,134 6,415 5,218 9,911 *Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle. Page 30 of87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Batch Release Unit: Starting:
1-Jan-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of batch releases 32 19 14 17 82 2. Total time period for Batch releases ( Minutes) 7.94E+03 3.85E+03 2.33E+03 5.38E+03 1.95E+04 3. Maximum time period for a batch ( Minutes) 3.72E+02 3.49E+02 2.75E+02 8.76E+02 8.76E+02 4. Average time period for a batch ( Minutes) 2.48E+02 2.02E+02 1.66E+02 3.17E+02 2.38E+02 5. Minimum time period for a batch ( Minutes) 5.70E+01 6.10E+01 6.00E+01 5.50E+01 5.50E+01 6. Average stream flow during of release of liquid ( CFS ) 19,898 8,134 6,415 5,218 9,911 into a flowing stream* *Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle. Page 31 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 0 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average TIme For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 32 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Abnormal Release Unit: Starting:
l-Jan-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 0 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 33 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Liquid Effluents 
-Abnormal Release Unit: Starting:
l-)an-2010 Ending:
Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 0 0 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. Total activity for all releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 34 of 87 2.0 Gaseous Effluents Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2. 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: 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, For lodine-131 , for lodine-133, 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. 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: 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 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. Doses to a Member of the Public The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-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. During any calendar quarter: Less than or equal to 7.5 mrems to any organ. During any calendar year: Less than or equal to 15 mrems to any organ. Page 35 of87 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 five paths: plant vents (Unit 1 and Unit 2), the condenser air ejector, the steam packing exhauster systems (Unit 1 and Unit 2), and the Radwaste Processing Facility.
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 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. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and the steam packing exhauster system vents. 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 aDeM 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 36 of87 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 2.2.2.1 2.2.2.2 2.2.2.3 The methods for determining release quantities of radioactivity, dose rates, and cumulative doses are as follows: 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 aDCM 3.1.2 for noble gases, radioiodines, tritium, and particulates.
Dose rate calculation methodology is presented in the aDCM. 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 aDCM 3.1.3. Current percent of the aDCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the aDCM. 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 3-70f 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 aDCM 3.1.4. Current percent of aDCM limits are shown in this report for each release period. 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 37 of 87 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. 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% 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 38 of87 2.3 2.2.3 Total Error Estimation cont'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% 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% Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found in this report as Tables 2-1A, 2-1B, 2-1C, 2-2A, 2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data are presented on a quarterly basis as required by Regulatory Guide 1.21. To complete table 2-1A, and 2-1 B, the total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in IlCi/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 ODeM 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. G ross alpha radioactivity is reported in Table 2-1 A, and 2-1 B as cu ries 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 39 of87 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-SA, and 2-S8 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 2-48. 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-SA and 2-58. 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 was one abnormal release during this period. On 10/12/2010, after reviewing Waste Gas Decay Tank pressures, an Operator found that the in service tank GDT #2 pressure had lowered from the day shift to the night shift round by 25 psig after isolation.
HP/Chemistry review of the Unit 2 Plant Vent Monitor trends show that radiation levels increased when Waste Gas was placed on recirculation and levels decreased after closure of the flow path. Even though the levels were elevated, the entire release was monitored out of the plant vent stack. Furthermore, none of the radiation monitors for this flow path went into alarm at the time of the release nor subsequently.
The Operators were directed to shutdown Waste Gas Processing to allow Chemistry to obtain a sample. Waste Gas Decay Tank #2 was sampled on 10/12/2010 at 045S. Release permit G-201 01 011-281-8 was generated to account for this unplanned release. There Page 40 of 87 were no limits exceeded and there was no reason for the NRC to be not notified.
The duration of this release was 355 minutes, from 10/11/2010 at 1750 to 10/11/2010 at 2345. A volume of 1 .02E+03 ft3 was released.
The release was attributed to two factors: 1) A diaphragm valve (21902U4162) was not fully closed during recirculation of a waste gas decay tank because of the travel stop repositioning over time. Travel stop drift is common in high vibration systems for this model of Hills-McCanna diaphragm valve 2) The gas trap for a phase separator did not function properly.
Remedial actions include (1) reevaluating the manufacturer's suggestion not to perform maintenance the Hills-McCanna diaphragm valve, (2) re-adjusting the diaphragm valve to close completely, (3) revising procedures to address the repositioning of travel stops for diaphragm valves over time, (4) using a medium strength "thread locker" that is more suitable for the size of the travel stop bolt, it will prevent innate travel stop repositioning while allowing for readjustment without a special tool (5) additionally, a step should will be included to match mark the valve stem after performance of the travel stop repositioning section. The system operating procedure will be changed to provide an adequate warning of gas trap design and installation shortcomings, refurbish the Armstrong gas trap 21902Z6003.
RADIONUCLIDES RELEASED:
Radionuclide Released Estimated Activity (IlCi/cc)
Kr-85 1.88E-02 Xe-135m 7.54E-04 Xe-133 5.51E-02 Xe-133m 4.72E-04 TOTAL 7.51 E-02 There was no calculated dose to the public as a result of this release. Page 41 of8?
Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Type of Effluent A. Fission And Activation Gases 1. Total Release 2. Average Release rate for period 3. Percent of Applicable Limit B. Radioiodines 
: 1. Total Iodine-13l 
: 2. Average Release rate for period 3. Percent of Applicable Limit C. Particulates 
: 1. Particulates ( Half-Lives 
> S 2. Average Release rate for period 3. Percent of Applicable Limit D. Tritium 1. Total Release 2. Average Release rate for period 3. Percent of Applicable Limit E. Gross All!ha 1. Total Release 2. Average Release rate for period Unit: Starting:
l-Jan-2010 Units 1ST Quarter Curies uCi/sec % Curies uCi/sec % Curies uCi/sec % Curies uCi/sec % Curies uCi/sec 1.00E-Ol 1.27E-02
* 7. l3E-06 9.0SE-07
* 7.47E-OS 9.47E-09
* 4.SSE+OO 6.l6E-Ol
* Ending: 31-Dec-2010 2ND Quarter 1.46E-Ol 1.SSE-02
* O.OOE+OO O.OOE+OO
* 9.73E-OS 1.23E-OS
* 3.27E+OO 4. l4E-Ol
* O.OOE+OO O.OOE+OO 3RD Quarter 4TH Quarter 6.S1E-Ol S.66E-02 S.63E-02 7.1SE-03 *
* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *
* 1.47E-07 1.31E-07 1.S7E-OS 1.6SSE-OS 
*
* 7.76E+OO 3.46E+OO 9.S4E-Ol 4.3SE-Ol *
* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-SA, 2-SB of this report. Page 42 ofS7 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Unit: Starting:
1-Jan-2010 Ending:
Type of Effl uent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases 1. Total Release Curies 1.92E+02 S.96E+OO 6.77E+OO 1.19E+Ol 2. Average Release rate for period uCi/sec 2.44E+Ol 7.S7E-Ol 8.58E-Ol l.S1E+OO 3. Percent of Applicable Limit % * * *
* B. Radioiodines 
: 1. Total Iodine-131 Curies 4.41E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec S.S9E-OS O.OOE+OO O.OOE+OO O.OOE+OO 
: 3. Percent of Applicable Limit % * * *
* C. Particulates 
: 1. Particulates ( Half-Lives>
8 Curies 6.S1E-08 1.54E-08 O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec 8.26E-09 1.96E-09 O.OOE+OO O.OOOE+OO 
: 3. Percent of Applicable Limit % * * *
* D. Tritium 1. Total Release Curies 7.22E+OO 5.16E+OO 2.84E+OO 1.13E+OO 2. Average Release rate for period uCi/sec 9.16E-Ol 6.SSE-Ol 3.60E-Ol 1.43E-O1 3. Percent of Applicable Limit % * * *
* E. Gross AI 1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-46, 2-5A, 2-56 of this report. Page 43 of 87 Table Vogtle Electric Generating RADIOACllVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Summation Of All Unit: Site Starting:
1-Jan-2010 Ending: 31-Dec-2010 Type of Effluent Units 1ST Ouarter 2ND Ouarter 3RD guarter 4TH Quarter A. Fission And Activation Gases 1. Total Release Curies 1.92E+02 6.11E+OO 7.45E+OO 1.20E+OI 2. Average Release rate for period uCi/sec 2.44E+Ol 7.75E-Ol 9.45E-Ol 1.52E+OO 3. Percent of Applicable Limit % * * *
* B. Radioiodines 
: 1. Total Iodine-131 Curies 4.48E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec S.68E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3. Percent of Applicable Limit % * * *
* C. Particulates 
: 1. Particulates ( Half-Lives>
8 Curies 1.40E-07 1. 13E-07 1.47E-07 1.31E-07 2. Average Release rate for period uCi/sec 1. 77E-08 1.43E-08 1.87E-08 1.658E-08 
: 3. Percent of Applicable Limit % * * *
* D. Tritium 1. Total Release Curies 1.2IE+OI 8.43E+OO l.06E+OI 4.58E+OO 2. Average Release rate for period uCi/sec% l.S3E+OO 1.07E+OO 1.34E+OO S.8lE-Ol 3. Pprrpnt of Annlirl'lhlp limit * * *
* E. Gross Alpha 1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-SA, 2-5B of this report. Page 44 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines 1-131 1-133 1-135 Total For Period Curies Curies Curies Curies 7. 13E-06 2.B1E-05 3.79E-05 7.31E-OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-B9 Sr-90 Total For Period Curies Curies Curies O.OOE+OO 7.47E-OB 7.47E-08 O.OOE+OO 9.73E-OB 9.73E-08 B.04E-OB 6.69E-OB 1.47E-07 1.31E-07 O.OOE+OO 1.31E-07 Tritium H-3 Curies 4.74E+OO 2.77E+OO 3.1BE+OO 3.20E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 45 of87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Xe-133 Total For Period Curies Curies Curies 9.96E-02 7.26E-04 1.00E-Ol 1.41E-Ol 4.90E-03 1.46E-Ol 6.8lE-Ol 1.0SE-04 6.81E-Ol S.S6E-02 1.03E-03 S.66E-02 Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies l.l2E-Ol S.OOE-Ol 4.S8E+OO 2.S8E-Ol Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 46 of 87 1-131 H-3 Nuclides Released Fission Gases Kr-85M Xe-133 Xe-135 Total For Period Iodines Total For Period Particulates Sr-S9 Sr-90 Total For Period Tritium Gross Alpha No Nuclides Found Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
1-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Units Curies Curies Curies Curies Curies Curies Curies Curies Curies 1ST Quarter S.29E-Ol 3.21E+Ol 3.41E+OO 3.64E+Ol 7.59E-06 7.S9E-06 4.62E-OS 1.S9E-OS 6.S1E-08 6.16E+OO O.OOE+OO 2ND Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.54E-08 1.S4E-08 4.27E+OO O.OOE+OO 3RD Quarter 4TH Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 47 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
l-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.46E+OO 1.28E+OO 6.77E-01 8.S0E-01 Kr-85 Curies O.OOE+OO O.OOE+OO O.OOE+OO 5.43E-01 Xe-131M Curies 2.21E+OO O.OOE+OO O.OOE+OO 2. 18E-02 Xe-133M Curies 1.91E+OO O.OOE+OO 2.1SE-02 4.79E-02 Xe-133 Curies 1.40E+02 4.46E+OO S.84E+OO 1.03E+01 Xe-13S Curies 3.78E-01 2.19E-01 2.23E-01 1.S8E-O 1 Total For Period Curies 1.46E+02 S.96E+00 6.77E+00 1.19E+Ol lodines 1-131 Curies 2.37E-04 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 2.37E-04 O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 9.SSE-01 8.90E-01 1.26E+OO 1.13E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 48 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Site Starting:
l-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Kr-B5M Curies B.29E-01 O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 Curies 3.21E+01 O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 Curies 3.41E+OO O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 3.64E+Ol O.OOE+OO O.OOE+OO O.OOE+OO Iodines 1-131 Curies 1.47E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1-133 Curies 2.B1E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1-135 Curies 3.79E-05 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period CUries 8.07E-OS O.OOE+OO O.OOE+OO O.OOE+OO Particulates Sr-B9 Curies 4.62E-OB O.OOE+OO B.04E-OB 1.31E-07 Sr-90 Curies 9.36E-OB 1. 13E-07 6.69E-OB O.OOE+OO Total For Period Curies 1.40E-07 1.13E-07 1.47E-07 1.31E-07 Tritium H-3 Curies 1.09E+01 7.04E+OO 4.75E+OO 3.20E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 49 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Mixed Mode Level Unit: Starting:
l-Jan-2010 Ending: 31-Dec-2010 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.56E+OO 1.42E+OO 1.36E+OO 9.06E-01 Kr-85 Curies O.OOE+OO O.OOE+OO O.OOE+OO 5.43E-01 Xe-131M Curies 2.21E+OO O.OOE+OO O.OOE+OO 
: 2. 18E-02 Xe-133M Curies 1.91E+OO O.OOE+OO 2.15E-02 4.79E-02 Xe-133 Curies 1.40E+02 4,47E+OO 5.84E+OO 1.03E+01 Xe-135 Curies 3.78E-01 2. 19E-Ol 2.23E-Ol 1.58E-01 Total For Period Curies 1.46E+02 6.11E+00 7.4SE+00 1.20E+Ol lodines 1-131 Curies 2.37E-04 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 2.37E-04 O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 1.07E+OO 1.39E+OO 5.84E+OO 1.39E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 50 of 87 Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Gaseous Effluents 
-Ground Level Releases Unit: 1 Starting:
1-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO gai:l:icillatas No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 51 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
1-Jan-2010 Ending: 31-Dec-2010 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Aigha No NUclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 52 of87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: starting:
l-Jan-2010 Ending:
Continuous Mode Nuclides Released Fission Gases No Nuclides Found Units Curies 1ST Quarter O.OOE+OO 2ND Quarter O.OOE+OO 3RD Quarter O.OOE+OO 4TH Quarter O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 53 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1. 29E-Ol O.OOE+OO O.OOE+OO O.OOE+OO Xe-131M Curies 1.81E-Ol O.OOE+OO O.OOE+OO O.OOE+OO Xe-133M Curies 1.S0E-Ol O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 Curies 9.39E+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-13S Curies 2.62E-02 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period CUries 9.88E+00 O.OOE+OO O.OOE+OO O.OOE+OO Iodines 1-131 Curies 1.96E-04 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.96E-04 O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 1.0SE-Ol O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 54 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Site Starting:
1-Jan-2010 Ending: 31-Dec-2010 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 55 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Ground Level Unit: Starting:
1-Jan-2010 Ending:
Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 1.29E-O1 O.OOE+OO O.OOE+OO O.OOE+OO Xe-131M Curies 1.81E-01 O.OOE+OO O.OOE+OO O.OOE+OO Xe-133M Curies 1.S0E-01 O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 Curies 9.39E+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-13S Curies 2.62E-02 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 9.88E+00 O.OOE+OO O.OOE+OO O.OOE+OO Iodines 1-131 Curies 1.96E-04 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 1.96E-04 O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 1.0SE-01 O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 56 ofS7 Table 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Air Doses Due to Gaseous Release Unit: Starting:
I-Jan-2010 Ending:
Cumulative Doses Per Quarter Type of Radiation ODCM Units Gamma Air S.OOE+OO mRad Beta Air 1.00E+Ol mRad Cumulative Doses Per Year Type of Radiation ODCM Unit Gamma Air 1.00E+Ol mRad Beta Air 2.00E+Ol mRad 1ST Qtr 1.36E-OS 4.80E-06 Year to End O/oODCM 2ND Qtr O/oODCM 3RD Qtr 2.71E-04 1.93E-OS 3.8SE-04 4.80E-OS 6.86E-06 6.86E-OS 010 ODCM ...:,.R:.;:e:,.;:c:,:e.a::p.=.;to::;,:r
_________ 1.33E-04 1.33E-03 Site Boundary I Child 4.70E-OS 2.3SE-04 Site Boundary I Child O/oODCM 4TH Qtr &deg;/oODCM 1.8SE-03 7.S7E-06 1.S1E-04 3.27E-04 2.69E-06 2.69E-05 Limit Air Dose Gamma Annual 1.21 Air Dose Beta Annual 1.21 Page 57 cf87 Table 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Air Doses Due to Gaseous Release Unit: 2 Starting:
1-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses Per Quarter Type of Radiation ODCM Units Gamma Air S.OOE+OO mRad Beta Air 1.00E+01 mRad Cumulative Doses Per Year Type of Radiation ODCM Unit Gamma Air 1.00E+01 mRad Beta Air 2.00E+01 mRad 1ST Qtr 1.36E-03 3.47E-03 Year to End %ODCM 2ND Qtr %ODCM 3RD Qtr %ODCM 4TH Qtr %ODCM 2.71E-02 2.04E-04 4.0SE-03 1.29E-04 2.SSE-03 1.74E-04 3.4SE-03 3.47E-02 1.3SE-04 1.3SE-03 1.31E-04 1.31E-03 2.22E-04 2.22E-03 0/0 ODCM ...;.R.:;.:e:..;:c;::;ea:;.pt;:.:o:...::.r
_________ Limit 1.S6E-03 1.S6E-02 Site Boundary I Child Air Dose Gamma Annual 1.21 3.96E-03 1.9SE-02 Site Boundary I Child Air Dose Beta Annual 1.21 Page 58 of 87 Table 2-4C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Air Doses Due to Gaseous Release Unit: Starting:
l-lan-2010 Ending:
Cumulative Doses Per Quarter Type of Radiation ODCM Units Gamma Air S.OOE+OO mRad Beta Air 1.00E+Ol mRad Cumulative Doses Per Year Type of Radiation ODCM Unit Gamma Air 1.00E+Ol mRad Beta Air 2.00E+Ol mRad 1ST Qtr 1.37E-03 3.48E-03 Year to End o/oODCM 2ND Qtr o/oODCM 2.74E-02 2.23E-04 4.47E-03 3.48E-02 1.4SE-04 1.4SE-03 o/oODCM Receptor 3RD Qtr 2.22E-04 1.64E-04 &deg;/oODCM 4TH Qtr o/oODCM 4.43E-03 1.82E-04 3.63E-03 1.64E-03 2.2SE-04 2.2SE-03 Limit 2.00E-03 2.00E-02 Site Boundary / Child Air Dose Gamma Annual 1.21 4.01E-03 2.01E-02 Site Boundary / Child Air Dose Beta Annual 1.21 Page 59 of87 Table 2-SA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 1 Starting:
l-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses Per Quarter Organ ODCM Units 1ST gtr &deg;/oODCM 2ND gtr o/oODCM 3RD gtr %ODCM 4TH gtr % ODCM Bone 7.50E+OO mRem 3.0lE-06 4.0lE-05 3.86E-06 5.l5E-OS 2.7SE-06 3.67E-OS 1.54E-07 2.0SE-06 GI-Lli 7.S0E+OO mRem 1.0SE-04 1.40E-03 7.07E-OS 9.43E-04 1.68E-04 2.24E-03 7.47E-05 9.96E-04 Kidney 7.50E+OO mRem 1.05E-04 1.40E-03 7.06E-05 9.42E-04 1.68E-04 2.24E-03 7.47E-05 9.96E-04 Liver 7.S0E+OO mRem l.05E-04 1.40E-03 7.06E-OS 9.42E-04 1.68E-04 2.24E-03 7.47E-05 9.96E-04 Lung 7.S0E+OO mRem 1.0SE-04 1.40E-03 7.06E-OS 9.42E-04 1.68E-04 2.24E-03 7.47E-05 9.96E-04 Thyroid 7.50E+OO mRem 1.l8E-04 1.S8E-03 7.06E-OS 9.42E-04 1. 68E-04 2.24E-03 7.47E-05 9.96E-04 Total Body 7.S0E+OO mRem 1.06E-04 1.41E-03 7.l6E-OS 9.SSE-04 1.68E-04 2. 24E-03 7.47E-05 9.96E-04 Cumulative Doses per Year Organ ODCM Units Year to Ending Date o/oODCM Limit Bone 1.500E+Ol mRem 9.773E-06 6.5l5E-05 Maximum Individual/Child Iodine/Part Dose Annual 1.2 GI-Lli 1.500E+Ol mRem 4.l8lE-04 2.787E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Kidney l.S00E+Ol mRem 4. l80E-04 2.787E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Liver 1.500E+Ol mRem 4.l80E-04 2.787E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Lung 1.500E+Ol mRem 4.l80E-04 2.787E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Thyroid 1.S00E+Ol mRem 4.31SE-04 2.876E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Total Body 1.S00E+Ol mRem 4.204E-04 2.803E-03 Maximum Individual/Child Iodine/Part Dose Annual 1.2 Page 60 of8?
Table 2-58 Vogtle Electric Generating Plant RADIOAcnVE EFFLUENT RELEASE REPORT -2010 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 2 Starting:
1-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses Per Quarter Orsan ODCM Units 1ST gtr %ODCM 2ND gtr %ODCM 3RD gtr %ODCM 4TH gtr %ODCM Bone 7.S0E+OO mRem S.47E-06 7.29E-OS 6.12E-07 8.16E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO GI-Lli 7.S0E+OO mRem 1.38E-04 1.8SE-03 1. 12E-04 1.49E-03 6. 14E-OS 8. 18E-04 2.44E-OS 3.2SE-04 Kidney 7.S0E+OO mRem 1.4SE-04 1.93E-03 1. 12E-04 1.49E-03 6.14E-OS 8. 18E-04 2.44E-OS 3.2SE-04 Liver 7.S0E+OO mRem 1.42E-04 1.90E-03 1. 12E-04 1.49E-03 6. 14E-OS 8. 18E-04 2.44E-OS 3.2SE-04 Lung 7.50E+OO mRem 1. 38E-04 1.84E-03 1. 12E-04 1.49E-03 6.14E-OS 8. 18E-04 2.44E-OS 3.2SE-04 Thyroid 7.S0E+OO mRem 1.SSE-03 2.06E-02 1. 12E-04 1.49E-03 6.14E-OS 8. 18E-04 2.44E-OS 3.2SE-04 Total Body 7.S0E+OO mRem 1.41E-04 1.88E-03 1. 12E-04 1.49E-03 6. 14E-OS 8. 18E-04 2.44E-OS 3.2SE-04 Cumulative Doses per Year Organ ODCM Units Year to Ending Date %ODCM Receptor Limit Bone 1.S00E+Ol mRem 6.081E-06 4.0S4E-OS Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 GI-Lli 1.S00E+Ol mRem 3.3S9E-04 2.239E-03 Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 Kidney 1.S00E+Ol mRem 3.42SE-04 2.283E-03 Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 Liver 1.S00E+Ol mRem 3.397E-04 2.26SE-03 Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 Lung 1.S00E+Ol mRem 3.3SSE-04 2.237E-03 Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 Thyroid l.S00E+Ol mRem 1.743E-03 
: 1. 162E-02 Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 Total Body l.S00E+Ol mRem 3.382E-04 2.2SSE-03 Maximum Individual 
/ Child Iodine/Part Dose Annual 1.21 Page 61 of 87 Table 2-5C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2010 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting:
l-Jan-2010 Ending: 31-Dec-2010 Cumulative Doses Per Quarter Organ ODCM Units 1ST gtr %ODCM 2ND gtr %ODCM 3RD gtr %ODCM 4TH gtr %ODCM Bone 7.S0E+OO mRem 8.48E-06 1. 13E-04 4.47E-06 S.96E-OS 2.7SE-06 3.67E-OS l.S4E-07 2.0SE-06 GI-Lli 7.S0E+OO mRem 2.43E-04 3.2SE-03 1.82E-04 2.43E-03 2. 29E-04 3.0SE-03 9.91E-OS 1.32E-03 Kidney 7.50E+OO mRem 2.S0E-04 3.33E-03 1.82E-04 2.43E-03 2. 29E-04 3.0SE-03 9.91E-OS 1.32E-03 Liver 7.S0E+OO mRem 2.47E-04 3.30E-03 1.82E-04 2.43E-03 2.29E-04 3.0SE-03 9.91E-OS 1.32E-03 Lung 7.S0E+OO mRem 2.43E-04 3.24E-03 1.82E-04 2.43E-03 2.29E-04 3.0SE-03 9.91E-OS 1.32E-03 Thyroid 7.S0E+OO mRem 1.66E-03 2.22E-02 1.82E-04 2.43E-03 2.29E-04 3.0SE-03 9.91E-OS 1.32E-03 Total Body 7.S0E+OO mRem 2.46E-04 3.29E-03 1.83E-04 2.4SE-03 2.30E-04 3.06E-03 9.91E-OS 1.32E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date %ODCM Recel!tor Limit Bone l.S00E+Ol mRem l.S8SE-OS 1.0S7E-04 Maximum Individual/Child Iodine/Part Dose Annual GI-Lli l.S00E+Ol mRem 7.S40E-04 S.027E-03 Maximum Individual/Child Iodine/Part Dose Annual Kidney l.S00E+Ol mRem 7.60SE-04 S.070E-03 Maximum Individual/Child Iodine/Part Dose Annual Liver l.S00E+Ol mRem 7.S77E-04 S.OS2E-03 Maximum Individual/Child Iodine/Part Dose Annual Lung l.S00E+Ol mRem 7.S3SE-04 S.023E-03 Maximum Individual/Child Iodine/Part Dose Annual Thyroid l.S00E+Ol mRem 2.17SE-03 1.4S0E-02 Maximum Individual/Child Iodine/Part Dose Annual Total Body l.S00E+Ol mRem 7.S86E-04 S.OS8E-03 Maximum Individual/Child Iodine/Part Dose Annual Page 62 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -MINIMUM DETECTABLE CONCENTRATIONS 
-GASEOUS SAMPLE Starting:
1-Jan-2010 Ending: 31-Dec-2010 RADIONUCUDE MDC UNITS Kr-S7 l.S2E-OS f.lCi/ml Kr-SS 2.s3E-OS f.lCi/ml Xe-133 2.0sE-OS f.lCi/ml Xe-133m S.63E-OS f.l Ci/ ml Xe-13s 7.12E-OS f.lCi/ml Xe-13S l.OsE-07 f.lCijml 1-131 7.93E-1s*
f.l Ci/ ml Mn-s4 3.94E-14*
f.l Ci/ ml Fe-59 2.4sE-14*
f.lCi/ml Co-ss l.39E-14*
f.lCi/ml Co-60 l.7sE-14*
f.lCi/ml Zn-6s 2.S2E-14*
f.lCi/ml Mo-99 9.s7E-14*
f.lCi/ml Cs-134 l.12E-14*
f.lCi/ml Cs-137 S.71E-1S*
f.lCi/ml Ce-141 S.62E-1S*
f.l Ci/ ml Ce-144 2.77E-14*
f.l Ci/ ml Sr-S9 l.OOE-13 f.lCi/ml Sr-90 l.OOE-13 f.l Ci/ ml H-3 9.00E-OS f.l Ci/ml Gross Alpha 1.00E-13 f.l Ci/ml
* Based on an estimated sample volume of S.7E+OS ml. Page 63 of8?
Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Batch Release Unit: Starting:
1-Jan-2010 Ending:
Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of batch releases 24 25 24 26 99 2. Total time period for batch releases ( Minutes) 2.39E+03 3.17E+03 1.07E+04 1.46E+03 1.77E+04 3. Maximum time period for a batch ( Minutes) 9.37E+02 7.10E+02 4.55E+03 1.16E+02 4.55E+03 4. Average time period for a batch ( Minutes) 9.95E+Ol 1.27E+02 4.46E+02 5.62E+Ol 1.79E+02 5. Minimum time period for a batch ( Minutes) 2.40E+Ol 3.00E+Ol 2.30E+Ol 1.60E+Ol 1.60E+Ol Page 64 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Batch Release Unit: Starting:
1-Jan-2010 Ending:
Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of batch releases 64 24 21 28 137 2. Total time period for batch releases ( Minutes) S.91E+04 3.90E+04 2.24E+04 1.8SE+04 1.39E+OS 3. Maximum time period for a batch ( Minutes) S.7SE+03 9.09E+03 4.76E+03 3.27E+03 9.09E+03 4. Average time period for a batch ( Minutes) 9.24E+02 1.63E+03 1.07E+03 6.61E+02 1.02E+03 S. Minimum time period for a batch ( Minutes) 2.00E+OO 6.00E+OO 1.00E+Ol 1.40E+01 2.00E+OO Page 65 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Batch Release Unit: Starting:
1-lan-2010 Ending:
Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of batch releases 88 49 45 54 236 2. Total time period for batch releases ( Minutes) 6.15E+04 4.22E+04 3.31E+04 2.00E+04 1.57E+05 3. Maximum time period for a batch ( Minutes) 5.75E+03 9.09E+03 4.76E+03 3.27E+03 9.09E+03 4. Average time period for a batch ( Minutes) 6.99E+02 8.62E+02 7.37E+02 3.70E+02 6.65E+02 5. Minimum time period for a batch ( Minutes) 2.00E+OO 6.00E+OO 1.00E+Ol 1.40E+Ol 2.00E+OO Page 66 of8?
Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Abnormal Release Unit: Starting:
1-Jan-2010 Ending:
Gaseous Releases 1. Number of Releases Units 1ST Quarter 0 2ND Quarter 0 3RD Quarter 0 4TH Quarter 0 Year Totals 0 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. Minimum Time For A Release 6. Total activity for all releases A. Fission And Activation Products ( Minutes) ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. Total Release (not inciudinQ tritium, gases, alpha) 2. Average diluted concentration during period 3. Percent of Applicable Limit Curies uCi/mL % 7.23E-03 7.2iE-09
* S.S6E-03 2.S6E-09
* 1.iSE-03 4.74E-i0
* 1.S3E-04 6.0SE-ll
* B. Tritium 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit Curies uCi/mL % 2.3SE+02 2.37E-04
* 2.90E+Oi 1.49E-OS
* 6.94E+OO 2.S6E-06
* 9.S0E-Oi 3.26E-07
* C. Dissolved and Entrained Gases 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit Curies uCi/mL % 1.96E-Oi 1.9SE-07
* 2.47E-04 1.27E-i0
* O.OOE+OO O.OOE+OO
* O.OOE+OO O.OOE+OO
* Page 67 of 87  

Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Abnormal Release Unit: Starting:
1-1an-2010 Ending:
Gaseous Releases 1. Number of Releases Units 1ST Quarter 0 2ND Quarter 0 3RD Quarter 0 4TH Quarter 1 Year Totals 1 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 3.SSE+02 3. Maximum Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO 3.SSE+02 3.SSE+02 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 3.SSE+02 5. Minimum Time For A Release 6. Total activity for all releases A. Fission And Activation Products ( Minutes) ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 2.17E+OO 3.55E+02 2.17E+OO 1. Total Release (not includinQ tritium, gases, alpha) 2. Average diluted concentration during period 
: 3. Percent of Applicable Limit Curies uCi/mL % 1.73E-02 8.66E-09
* 1.84E-02 4.49E-09
* 6.09E-03 1.22E-09
* 1.02E-02 1.S7E-09
* B. Tritium 1. Total Release 2. Average diluted Concentration Curies 5.86E+02 1.06E+02 4.57E+Ol 1.65E+02 during period 
: 3. Percent of Applicable Limit uCi/mL % 2.94E-04
* 2.58E-OS
* 9. 13E-06
* 2.SSE-OS
* C. Dissolved and Entrained Gases 1. Total Release 2. Average diluted Concentration during period 3. Percent of Applicable Limit Curies uCi/mL % 6.06E-Ol 3.04E-07
* 7.56E-04 1.85E-l0
* O.OOE+OO O.OOE+OO
* 2.S7E-03 3.99E-l0
* Page 68 of 87 Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Gaseous Effluents 
-Abnormal Release Unit: Starting:
I-Jan-2010 Ending:
Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 1. Number of Releases 0 0 0 1 1 2. Total Time For All Releases ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 3.55E+02 3. Maximum Time For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 3.55E+02 4. Average Time For A Release ( Minutes) O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 3.55E+02 5. Minimum Time For A Release ( Minutes ) O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 3.55E+02 6. Total activity for ali releases ( Curies) O.OOE+OO O.OOE+OO O.OOE+OO 2. 17E+OO 2.17E+OO Page 69 of 87 Solid Waste Regulatory Requirements The aDCM requirements presented in this section are stated in part for Unit 1 and Unit 2. 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. 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. Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1. Page 70 of87 Type of Waste Unit 6 month Period Est. Total Error, % a. Spent Resins, Filter sludges, evaporator Bottoms, etc m" Ci N/A N/A b. Dry Compressible Waste, Contaminated Equipment, etc m j Ci 475* 5.36 10% c. Irradiated components, control rods, etc m 3 Ci NONE N/A d. Other (describe)
Secondary Side Resin (SGBD) m J Ci NONE N/A *As Shipped 50 m j as disposed of. 2. Estimate of major nuclide composition (by type of waste). Type of Nuclide Percentage waste N/A %a. N/A % N/A % %b. H-3 31.780 Ni-63 % 18.979 Co-60 % 10.722 C-14 % 16.195 Fe-55 % 7.692 Others 14.632 N/A %c. N/A % N/A % D N/A % N/A % N/A % Table Vogtle Electric Generating RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -SOUD WASTE AND IRRADIATED FUEL Units 1 and Page 10f4 JANUARY 1, 2010 THROUGH JUNE 30, 2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Non Irradiated Fuel) 1. Type of waste I I 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination I CaskffractorlTrailer Energy Solutions, Oak Ridge, TN 8 TractorlTrailer Energy Solutions, Oak Ridge, TN Page 71 ofS7 TABLE Vogtle Electric Generating RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -SOLID WASTE AND IRRADIATED FUEL Units 1 and Page 20f4 JANUARY 1, 2010 THROUGH JUNE 30, 2010 B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Sbipments Mode of Transportation Destination NONE ADDITIONAL INFORMATION REQUIRED BY ODCM: Shi Ipments S ent D'lrec tl Iy t 0 D'Isposa Shipment No, Waste Class Type Container Shipping Class Solidification Agent Volume NONE Shi lpments to a W t P as e rocessor Shipment No, Waste Class Type Container Shipping Class Solidification Agent Processor RVRS-lO-OO 1 A IP-l LSA-I NONE Energy Solutions RVRS-IO-002 A IP-l Limited Quantity NONE Energy Solutions RVRS-1O-003 A IP-l LSA-I NONE Energy Solutions RVRS-IO-004 A IP-l LSA-I NONE Energy Solutions
* RVRS-1O-005 I A IP-l Limited Quantity NONE Energy Solutions i RVRS-IO-006 A IP-l LSA-I NONE Energy Solutions RVRS-1O-007 A IP-l Limited Quantity NONE Energy Solutions RVRS-1O-008 A IP-ll LSA-II NONE Energy Solutions RVRS-1O-009 A IP-l LSA-I NONE Energy Solutions Page 72 of87 TABLE Vogtle Electric Generating RADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -SOLID WASTE AND IRRADIATED FUEL Units 1 and Page 3 of4 lUL Y 1, 2010 THROUGH DECEMBER 31, 2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 1 T Lypeo f t. was e Type of Waste Unit 6 month Est. Total Period Error, % a. Spent Resins, Filter sludges, evaporator Bottoms, etc m j Ci 3.115* 6.25 25% b. Dry Compressible Waste, Contaminated Equipment, etc m 5 Ci 270.143* 1.8 25% c. Irradiated components, control rods, etc m" Ci d. Other (describe)
Secondary Side Resin (SGBD) **GIC Program m j Ci 112.418* 7.38E-2 25%
* As Shipped 2. Estimate of major nuclide composition (by type of waste). I Type of waste Nuclide Percentage 
: a. N/A N/A N/A % % % b. H-3 Ni-63 Co-60 C-14 Fe-55 Others % % % % % 31.780 18.979 10.722 16.195 7.692 14.632 c. N/A N/A N/A % % % D N/A N/A N/A % 
% % 3. Solid Waste Disposition I Number of Shipments Mode of Transportation Destination I 1 CasklTractorlTrailer Energy Solutions, Oak Ridge, TN 1 CaskITractorlTrailer Energy Solutions, Kingston, TN 18 TractorlTrailer Energy Solutions, Oak Ridge, TN 16 TractorlTrailer Energy Solutions, Oak Ridge, TN Page 73 ofB7 B. TABLE Vogtle Electric Generating RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -SOLID WASTE AND IRRADIATED FUEL Units 1 and Page 40f4 July 1, 2010 THROUGH December 31, 2010 I I I Mode of Trans ortation Destination Additional Information Required by ODCM: Sh'Ipments , S ent D' I D'ISpOS al lreCtly to Shipment No, Waste Class Type Container Shipping Class Solidification Agent Volume NONE Sh'Ipments to a W aste P rocessor Shipment No, Waste Class Type Container Shipping Class Solidification Agent Processor RVRS-IO-O 1 0 A IP-l LSA-I NONE Energy Solutions RVRS-IO-Oll
* A IP-l (SGBD) Limited Quantity NONE Energy Solutions RVRS-IO-O 12 A IP-l LSA-I NONE Energy Solutions RVRS-1O-0l3
* A IP-l (SGBD) Limited Quantity NONE Energy Solutions RVRS-1O-0l4 A IP-l Limited Quantity NONE Energy Solutions RVRS-IO-OI5 A IP-l Limited Quantity NONE Energy Solutions RVRS-1O-0l6 A IP-I Limited Quantity NONE Energy Solutions RVRS-I0-017 A IP-I Limited Quantity NONE Energy Solutions RVRS-IO-OI8
* A IP-I (SGBD) Limited Quantity NONE Energy Solutions RVRS-1O-019
* A IP-I (SGBD) Limited Quantity NONE Energy Solutions RVRS-1O-020 A IP-I LSA-I NONE Energy Solutions RVRS-1O-021
* A IP-I (SGBD) Limited Quantity NONE Energy Solutions RVRS-1O-022 A IP-I LSA-I NONE Energy Solutions I RVRS-IO-023 A IP-I Limited Quantity NONE Energy Solutions I RVRS-1O-024
* A IP-I (SGBD) Limited Quantity NONE Energy Solutions RVRS-IO-025 A IP-I Limited Quantity NONE Energy Solutions
* Stearn Generator Blow Down resin goes to Energy Solutions for final Evaluation and release. Page 74 ofS7 4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part: liThe 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 ( Le., specific activity, exposure time, and location) shall be included in the report". 4.2 Demonstration of Compliance The location of concem within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.
There will be no radiation dose at this location due to radioactive liquid effluents.
Delineated in Table 4-1 for this location are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents.
Listed in this table are distance and direction from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the plant vent (mixed mode) and from the turbine building (ground level), and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.
The source term is listed in Tables 2-2A, and 2-2B for the mixed mode releases.
Similarly, it is listed in tables 2-3A and 2-3B for the ground level releases.
The maximum doses in units of mrem to a MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period are presented in Table 4-1. Page 75 of 87 Location Na Distance Occupancy Age Ground Level Ground Level Mixed Mode Mixed Mode Total NG Total Whole Body Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT Doses to a Member of the Public Due to Activities Inside the Site Unit: Starting:
l-Jan-2010 Ending:
Visitor's Center Receptor 4,47E-Ol SE 4.S7E-04 Child Noble Gas Particulate and Radioiodine Noble Gas Particulate and RadiOiodine Units 1ST Quarter mRem 2,46E-09 mRem 1.33E-07 mRem 1.33E-07 mRem 4.31E-07 mRem 1.34E-07 mRem 1.32E-07 mRem 1.32E-07 mRem 9.06E-07 mRem 1.04E-06 X/Q (sec/m3):
S.93E-06 X/Q (sec/m3):
S.S8E-06 X/Q (sec/m3):
7.12E-07 X/Q (sec/m3):
6.74E-07 D/Q (m-2): 2.28E-08 D/Q (m-2): S.77E-09 2ND Quarter 3RD Quarter 4TH Quarter Year 1.11E-1O 9.80E-08 9.80E-08 9.80E-08 9.80E-OS 9.S0E-OS 9.S0E-OS 1.4SE-07 2,46E-07 6.66E-ll 1.23E-07 1.23E-07 1.23E-07 1.23E-07 1.23E-07 1.23E-07 1.46E-07 2.69E-07 7.67E-13 S.33E-08 S.33E-08 S.33E-08 S.33E-OS S.33E-OS S.33E-OS 1.17E-07 1.70E-07 2.64E-09 4.07E-07 4.07E-07 7.0SE-07 4.0SE-07 4.07E-07 4.07E-07 1.32E-06 1.72E-06 Page 76 of 87 Location Distance Occupancy Age Ground Level Ground Level Ground Level Mixed Mode Mixed Mode Total NG Total Whole Body Table Vogtle Electric Generating RADIOACTIVE EFFLUENT RELEASE REPORT -Doses to a Member of the Public Due to Activities Inside the Site Unit: starting:
1-Jan-2010 Ending:
Units 3&4 Construction 4.83E-Ol SW 2.37E-Ol Adult Noble Gas Particulate and Radioiodine Particulate and Radioiodine Noble Gas Particulate and Radioiodine Units 1ST Quarter mRem 1.S1E-OS mRem 1.S1E-OB mRem 1.81E-OB mRem 1.S1E-OS mRem 1.81E-08 mRem 1.81E-08 mRem 1.81E-OS mRem 1.80E-07 mRem 1.9SE-07 X/Q (sec/m3):
1.B1E-OS X/Q (sec/m3):
6.93E-06 X/Q (sec/m3):
6.96E-06 X/Q (sec/m3):
9.7SE-07 X/Q (seC/m3):
9.17E-07 2ND Quarter 3RDQuarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D/Q (m-2): 2.BBE-OB D/Q (m-2): 2.BSE-OS D/Q (m-2): 7.14E-09 4TH Quarter Year O.OOE+OO 1.B1E-OB O.OOE+OO 1.S1E-OS O.OOE+OO 1.S1E-OS O.OOE+OO 1.81E-08 O.OOE+OO 1.81E-OS O.OOE+OO 1.S1E-OB O.OOE+OO 1.81E-08 O.OOE+OO 1.S0E-07 O.OOE+OO 1.9SE-07 Page 77 of87 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Requirements aDCM 5.1 states in part that the annual (calendar year) dose or dose commitment to any MEMBER aF 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 No dose limits stated in aDCM 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 aDCM Section 5.1.3. 6.0 Meteorological Data aDCM 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 aDCM 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 78 of87 7.1.2 Description of Deviations The inoperability of liquid and gaseous effluent monitors not corrected within the specified time for this reporting period is detailed below: The river water dilution flow instrumentation, AFQI-7620 and 7620A, were determined to be inoperable and not corrected within the specified time requirement of aDCM Section 2.1.1. Condition reports 2009108845,2009108949,2009110546 and 2009110718 document the events of inoperability.
The requirements of aDCM Action 40 have been implemented.
This inoperability was not corrected within the specified time requirement because of equipment obsolescence.
Design change work order C091733601 was scheduled to correct this issue. This work was completed on 10/20/10.
This instrumentation is returned to service. AFT-0014, waste gas system effluent flow rate measure device, was determined to be inoperable and not corrected within the specified time requirement of aDCM Section 3.1 .1 . Condition report 2009106923 documented the events of inoperability.
The requirements of aDCM Action 46 have been implemented.
This inoperability was not corrected within the specified time requirement because of operational issues. Repair of this equipment requires a simultaneous outage of the waste gas systems for both operating units. Design change work order A091273901 is scheduled to correct this issue following the Unit 1 refueling outage. 1 FT-0021, Steam Generator Slowdown Effluent Line flow rate measurement device, was determined to be inoperable and not corrected within the specified time requirement of aDCM Section 2.1.1. Condition report 2009104981 was written following unsuccessful channel calibration surveillance of this equipment under wa 1081301301.
The requirements of aDCM Action 40 have been implemented.
This inoperability was not corrected within the specified time requirement because of equipment obsolescence.
Design change work order 1090935601 was scheduled to correct this issue. Page 79 of 87 This work was completed on 08/02/10.
1 FT-0021 has been returned to service. 1 RE-12444A, Plant vent effluent wide range monitor, was determined to be inoperable and not corrected within the specified time requirement of aDCM Section 3.1.1. Condition report 2010105339 was written due to failure of the skid sample pump. The requirement of aDCM Action Statement 51 was not required due to alternate monitor 1 RE-12442A being continuously operable.
The inoperability was not corrected within the specified time requirement because a safety related pump assembly had to be used. This part had to be ordered. This work was completed on 08/03/10.
1 RE-12444A is returned to service. 2RE-12444C, Plant vent noble gas activity monitor, was determined to be inoperable and not corrected within the specified time requirement of aDCM Section 3.1.1 . Condition report 2009100357 was written following unsuccessful channel calibration surveillance under wa 2090065101.
The requirements of aDCM Actions 47 and 48 have not been required due to alternate monitor 1 RE-12442C being continuously operable.
The inoperability was not corrected within the specified time requirement because of equipment obsolescence.
wa 2090065101 documents efforts to procure replacement parts. This work was completed on 12108/10.
2RE-12444C has been returned to service. Page 80 of87 7.2 Tanks Exceeding Curie Content Limits Regulatory Requirements aDeM 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. Description of Deviations Limits for outdoor liquid hold-up tanks used for radioactive liquids not exceeded during this reporting Limits for the gas storage tanks were not exceeded during this Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) Regulatory Requirements aDeM 7.2.2.5 states in part that changes to the aDeM 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 aDeM 4.1.1.2.3 or changes to dose calculation locations as required by aDeM 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 aDeM 4.1.2. Page 81 of 87 8.2 Description of Changes Changes were made to the Vogtle Electric Generating Plant ODCM for the period January 1,2010 through December 31,2010. Revision 27 in October 2010. 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.
Revision 27, October 2010 The following were revised to provide the option of recording the local effluent radiation monitor (if functional) on a scheduled frequency rather than sampling radioactive effluents when remote effluent radiation monitor indication is not available in the control room. Table 2-1 Radioactive Liquid Effluent Monitoring Instrumentation, Action 37, Action 38, Action 39. Table 3-1 Radioactive Gaseous Effluent Monitoring Instrumentation, Action 45, Action 47, Action 48, Action 51. Also, in Section 3.3.6, Setpoints for Particulate and Iodine Monitors, the reference to ARE-13256 was deleted. This monitor was in the Dry Active Waste (DAW) Building and was removed when the building was removed during construction of Units 3 and 4. Page 82 of 87 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 2010 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 2010 assessment period. Solid Radwaste System There were no major changes to the solid radwaste systems in the 2010 assessment period. Page 83 of 87 10.0 Corrections to Previous Reports From a 2009 Assessment, the following 2 errors were noted: 1 )The 2009 Annual Radioactive Release Report section 7.1.2.d. states that Unit 2 RE-12444C Plant vent noble gas activity monitor was determined to be inoperable and not corrected within the specified time requirement of aDCM section 3.1.1. The requirements of aDCM Actions 47 and 48 were not required due to the alternate monitor being continuously operable.
The annual report stated the alternate monitor as Unit 1 RE-12442C instead of Unit 2 RE-12442C and the CR states from the control room log the alternate monitor was 2 12442. The statement was corrected to say, "The requirements of aDCM Action Statements 47and 48 were not required due to alternate monitor Unit 2 12442C being continually operable." 2) During the review of the Annual Radioactive Release Report for 2008 Table 3A-Gaseous Effluents-Ground Level Releases for Unit ane the first quarter Batch mode contains a Tritium value with a No Nuclides Found as the Nuclide released.
The amount released and nuclide is correctly identified in Table 2-3C for Unit: Site. Table2-3A Gaseous Effluents 
-Ground Level Releases for Unit 1 has been corrected to identify H-3 as the isotope. The affected pages, in their entirety are included in Attachment 1 for this report. Revision bars reflect the changes made. Page 84 of8?
Vogtle Electric Generating Plant Appendix A CARBON-l 4 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount ofC-14 in the atmosphere.
Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of "principal radionuclides" in gaseous effluents have changed, and C-14 has become a larger percentage. "Principal radionuclides" are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21), "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate.
In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants will report C-14 amounts released and resulting doses to the maximally exposed member of the public. Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation.
The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.
At Plant Vogtle, the quantity of C-14 released in gaseous effluents in 2010 was estimated to be 12.08 Curies (per unit). Approximately 30% of the C-14 released is in the form of 14C02 and is incorporated into plants through photosynthesis.
Ingestion dose results from this pathway. The remaining 70% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Vogtle ODCM, the resulting bone dose to a child located at the controlling receptor location would be 8,46E-02 mrem in a year which is 0.56% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents.
The resulting total body dose to a child located at the controlling receptor location would be 1.69E-02 mrem in a year which is 0.11 % of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.
Page 85 of87 ATTACHMENT 1 2009 Annual Radioactive Release Report section 7.1.2.d. 2RE-12444C, Plant vent noble gas activity monitor, was determined to be inoperable and not corrected within the specified time requirement of ODCM Section 3.1 .1 . Condition report 2009100357 was written following unsuccessful channel calibration surveillance under WO 20900651 OJ. The requirements of ODCM Actions 47 and 48 have not been required due to alternate mon itor 2RE-12442C being continuously operable.
The inoperability was not corrected within the specified time requirement because of equipment obsolescence.
WO 2090065101 documents efforts to procure replacement parts. Repair is scheduled for spring 2010. Page 77 01'80 ATTACHMENT 1 Table 2-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT 2008 Gaseous Effluents 
-Ground Level Releases Nuclides Released Unit: 1 Starting:
1-Jan-2008 Ending: 31-Dee-2008 Batch Mode Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Xe-133 Curies 1.76E-02 O.OOE+OO O.OOE+OO O.OOE+OO lodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Pflrtieulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H*3 Curies 9.03E-02 O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
Page 49 of 76 Edwin I. Hatch Nuclear Joseph M. Farley Nuclear Vogtle Electric Generating Annual Radioactive Effluent Release Reports for Enclosure Farley Offsite Dose Calculation Manual -Version OFFSITE DOSE CALCULATION JOSEPH M. FARLEY NUCLEAR Version 24 (January 2010) Tom Moorer Environmental Affairs, Chemistry, and Radiological Services Manager Tom Moorer  

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9-21 ................................................ 9-22 ................................................ 9-23 ................................................9-24 ................................................9-25 ................................................ 9-26 ................................................ 9-27 ................................................ 9-28 ................................................9-29 ................................................ 9-30 ................................................ 9-31 ................................................9-32 ................................................ 9-33 ................................................ 9-34 ................................................9-35 ................................................9-36 ................................................ 9-37 ................................................ 9-38 ................................................ 9-39 ................................................ 9-40 ................................................ 9-41 ................................................ 9-42 ................................................ 10-1 ................................................ 10-2 ................................................ 10-3 ................................................10-4 ................................................10-5 ................................................ 10-6 ................................................10-7 ................................................ iii Version 24 01/10 FNP-ODCM TABLE OF CONTENTS DIS'rRIBUTION LIST ........................................................................................................................... EFFECTIVE PAGE LiST..................................................................................................................... TABLE OF CONTENTS..................................................................................................................... LIST OF TABLES ............................................................................................................................LIST OF FIGURES .............................................................................................................................REFERENCES
...................................................................................................................................CHAPTER 1: INTRODUCTION 
..................................................................................................... CHAPTER 2: LIQUID EFFLUENTS 
............................................................................................... 2.1 LIMITS OF OPERATION 
.......................................................................................................2.1.1 Liquid Effluent Monitoring Instrumentation ControL ...................................................... 2.1.2 Liquid Effluent Concentration Control. .......................................................................... 2.1.3 Liquid Effluent Dose ControL ...................................................................................... 2.1.4 Liquid Radwaste Treatment System Control .............................................................. 2.1.5 MAJOR CHANGES TO LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS .2.2 LIQUID RADWASTE TREATMENT SYSTEM ..................................................................... 2.3 LIQUID EFFLUENT MONITOR SETPOINTS 
...................................................................... 2.3.1 General Provisions Regarding Setpoints 
................................................................... 2.3.2 Setpoints for Radwaste System Discharge Monitors ................................................. 2.3.3 Setpoints for Monitors on Normally Low-Radioactivity Streams ................................ 2.4 LIQUID EFFLUENT DOSE CALCULATIONS 
.................................................................... 2.4.1 Calculation of Dose ................................................................................................... 2.4.2 Calculation of ................................... 
'" ................................................................. 2.4.3 Calculation of CF iv ..................................................................................................... 2.5 LIQUID EFFLUENT DOSE PROJECTIONS 
...................................................................... 2.5.1 Thirty-One Day Dose Projections 
.............................................................................. 2.5.2 Dose Projections for Specific Releases ..................................................................... 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS ................................................................. iv Version 24 01/10  

CHAPTER 3: GASEOUS EFFLUENTS 
.........................................................................................3.1 LIMITS OF OPERATION 
.......................................................................................................3.1.1 Gaseous Effluent Monitoring Instrumentation Control .................................................. 3.1.2 Gaseous Effluent Dose Rate Control ........................................................................... 3.1.3 Gaseous Effluent Air Dose Control .............................................................................. Control on Gaseous Effluent Dose to a MEMBER OF THE PUBLIC ......................... GASEOUS RADWASTE TREATMENT SYSTEM Control ......................................... MAJOR CHANGES TO THE GASEOUS RADIOACTIVE WASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SySTEM ....................... 3.2 GASEOUS RADWASTE TREATMENT SYSTEM ............................................................... 3.3 GASEOUS EFFLUENT MON ITOR SETPOINTS 
................................................................ 3.3.1 General Provisions Regarding Noble Gas Monitor Setpoints 
..................................... 3.3.2 Setpoint for the Final Noble Gas Monitor on Each Release Pathway ........................ 3.3.3 Setpoints for Noble Gas Monitors on Effluent Source Streams .................................. 3.3.4 Determination of Allocation Factors, AG .................................................................... 3.3.5 Setpoints for Noble Gas Monitors with Special Reguirements 
................................... 3.3.6 Setpoints for Particulate and Idoine Monitors ............................................................ 3.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 
................................................... 3.4.1 Dose Rates at and Beyond the Site Boundary .......................................................... 3.4.2 Noble Gas Air Dose at or Beyond Site Boundary ...................................................... 3.4.3 Dose to a Member of the Public at or Beyond Site Boundary ................................... 3.4.4 Dose Calculations to Support Other Requirements 
................................................... 3.5 GASEOUS EFFLUENT DOSE PROJECTS ......................................................................... 3.5.1 Thirty-One Day Dose Projections 
.............................................................................. 3.5.2 Dose Projections for Specific Releases ..................................................................... 3.6 DEFINITIONS OF GASEOUS EFFLUENT TERMS ............................................................. Version 24 01/10 FNp*ODCM CHAPTER 4: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ......................... 
.4.1 LIMITS OF OPERATION 
........................................................................................................ 4.1.1 Radiological Environmental Monitoring 
........................................................................ 4.1.2 Land Use Census ......................................................................................................... 4.1.3 Interlaboratory Comparison Program ........................................................................... 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 
....................................... CHAPTER 5: TOTAL DOSE DETERMINATIONS 
......................................................................... 5.1 LIMIT OF OPERATION 
........................................................................................................... 5.1.1 Applicability 
.................................................................................................................. 5.1.2 Actions ......................................................................................................................... 5.1.3 Surveillance Requirements 
.......................................................................................... 5.1.4 Basis .............................................................................................................................5.2 DEMONSTRATION OF COMPLIANCE 
.................................................................................. CHAPTER 6POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARy .......................................................... 6.1 REQUIREMENT FOR CALCULATION 
................................................................................... 6.2 CALCULATIONAL METHOD .................................................................................................. CHAPTER 7: REPORTS ............................................................................................................... 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ................................ 7.1.1 Requirement for Report ................................................................................................ 7.1 .2 Report Contents ........................................................................................................... 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT ................................................................... 7.2.1 Requirement for Report ................................................................................................ 7.2.2 Report Contents ........................................................................................................... 7.3 MONTHLY OPERATING REPORT ........................................................................................ 7.4 SPECIAL REPORTS .............................................................................................................. Version 24 01/10 FNP-ODCM CHAPTER 8: METEOROLOGICAL MODELS ............................................................................... 8.1 ATMOSPHERIC DiSPERSiON 
...............................................................................................8.1.1 Ground-Level Releases ................................................................................................ 8.1.2 Elevated Releases ....................................................................................................... 8.1.3 Mixed-Mode Releases .................................................................................................. 8.2 RELATIVE DEPOSITION 
....................................................................................................... 8.2.1 Ground-Level Releases ................................................................................................ 8.2.2 Elevated Releases ....................................................................................................... 8.2.3 Mixed-Mode Releases .................................................................................................. 8.3 ELEVATED PLUME DOSE FACTORS ................................................................................... 8.4 METEOROLOGICAL SUMMARy ........................................................................................... CHAPTER 9: METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUENT PATHWAY DOSE FACTORS, RaiPj .*......*......***....**.*...*.***....*..*......****.....*.*..**.**....** 9.1 INHALATION PATHWAY FACTOR ........................................................................................ 9.2 GROUND PLANE PATHWAY FACTOR ................................................................................. 9.3 GARDEN VEGETATION PATHWAY FACTOR ...................................................................... 9.4 GRASS-COW-MILK PATHWAY FACTOR. ............................................................................. 9.5 GRASS-GOAT-MILK PATHWAY FACTOR ............................................................................ 9.6 GRASS-COW-MEAT PATHWAY FACTOR ............................................................................ CHAPTER 10: DEFINITIONS OF EFFLUENT CONTROL TERMS .............................................. 10.1 TERMS SPECIFIC TO THE ODCM .................................................................................... 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS 
.............................................. vii Version 24 01/10  

Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table LIST OF TABLES Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Surveillance Requirements Radioactive Liquid Waste Sampling and Analysis Program Applicability of Liquid Monitor Setpoint Methodologies Parameters for Calculation of Doses Due to Liquid Effluent Releases Element Transfer Factors Adult Ingestion Dose Factors Site-Related Ingestion Dose Factors, Ai't Radioactive Gaseous Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation Requirements Radioactive Gaseous Waste Sampling and Analysis Program Applicability of Gaseous Monitor Setpoint Methodologies Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Dose Factors for Exposure to Direct Radiation from Noble Gases in Elevated Finite Plume Attributes of the Controlling Receptor R aipj for Ground Plane Pathway, All Age Groups Raipj for Inhalation Pathway, Child Age Group RaiPj for Cow Meat Pathway, Child Age Group R aipj for Garden Vegetation Pathway, Child Age Group Radiological Environmental Monitoring Program Reporting Levels for Radioactivity Concentrations in Samples Values for the Minimum Detectable Concentration Radiological Environmental Monitoring Locations viii Version 24 01/10  

Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Onsite Groundwater Monitoring Locations Attributes of MEMBER OF THE PUBLIC Receptor Locations Inside Site Boundary Terrain Elevation Above Plant Site Grade Annual Average (X/O) for Mixed Mode Releases Annual Average (X/O) for Ground-Level Releases Annual Average (0/0) for Mixed Mode Releases Annual Average (0/0) for Ground-Level Releases Miscellaneous Parameters for the Garden Pathway Miscellaneous Parameters for the Grass-Cow-Milk Pathway Miscellaneous Parameters for the Grass-Goat-Milk Pathway Miscellaneous Parameters for the Grass-Cow-Meat Pathway Individual Usage Factors Stable Element Transfer Data Inhalation Dose Factors for the Infant Age Group Inhalation Dose Factors for the Child Age Group Inhalation Dose Factors for the Teenager Age Group Inhalation Dose Factors for the Adult Age Group Ingestion Dose Factors for the Infant Age Group Ingestion Dose Factors for the Child Age Group Ingestion Dose Factors for the Teenager Age Group Ingestion Dose Factors for the Adult Age Group External Dose Factors for Standing on Contaminated Ground ix Version 24 01/10 FNp*ODCM LIST OF FIGURES Page Figure 2-1 LIQUID RADWASTE TREATMENT SYSTEM (Typical of Both Units) Figure 2-2 Steam Generator Blowdown System (Typical of Both Units) Figure 2-3 Liquid Discharge Pathways Figure 3-1 Schematic Diagram of the Routine Release Sources and Points (Typical of Both Units) Figure 4-1 Airborne Sampling Locations, 0-5000 feet Figure 4-2 Indicator II (Community)
Sampling Locations for Radiation Figure 4-3 Airborne Sampling Locations, 0-20 miles Figure 4-4 Water Sampling Locations Figure 4-5 Onsite Groundwater Monitoring Locations Figure 8-1 Vertical Standard Deviation of Material in a Plume (O"z) Figure 8-2 Terrain Recirculation Factor (Kr) Figure 8-3 Plume Depletion Effect for Ground-Level Releases Figure 8-4 Plume Depletion Effect for 30-Meter Releases Figure 8-5 Plume Depletion Effect for 60-Meter Releases Figure 8-6 Plume Depletion Effect for 1 OO-Meter Releases Figure 8-7 Relative Deposition for Ground-Level Releases Figure 8-8 Relative Deposition for 30-Meter Releases Figure 8-9 Relative Deposition for 60-Meter Releases Figure 8-10 Relative Deposition for 100-Meter (or Greater) Releases Figure 10-1 Site Map for Effluent Controls x Version 24 01/10  

REFERENCES J. S. Boegli, RR Bellamy, W. L. Britz, and R L. Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, October 1978. "Calculation of Annual Doses to Man form Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Regulatory Guide 1.109, March 1976. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1," U.S. NRC Regulatory Guide 1.109, Revision 1, October 1977. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, "U.S. NRC Regulatory Guide 1.111, March 1976. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC Regulatory Guide 1.111, Revision 1, July 1977. "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"U.S. NRC Regulatory Guide 1.113, April 1977. Joseph M. Farley Nuclear Plant Units 1 and 2 Final Safety Analysis Report, Alabama Power Company. Joseph M. Farley Nuclear Plant Units 1 and 2 Environmental Report -Operating License Stage, Alabama Power Company. T. E. Young, T. S. Bohn, and W. Serrano, "Technical Evaluation Report for the Evaluation of ODCM Revision 7 for Joseph M. Farley Nuclear Plant, Units 1 and 2," EGG-PHY.8674, dated August 1989, transmitted by NRC letter dated November 9, 1989. W. M. Jackson, "Survey Report of Chattahoochee River Water Use Downstream of Farley Nuclear Plant Liquid Effluent Discharge," dated July 19, 1990. J. E. Till and H. R Meyer, eds., Radiological Assessment, U.S. NRC Report NUREG/CR-3332, 1983. L. A. Currie, Lower Limit of Detection:
Definition and Elaboration of a Proposed Position of Radiological Effluent and Environmental Measurements, U.S. NRC Report NUREG/CR-4007, 1984. "Radiological Assessment Branch Technical Position," U.S. Nuclear Regulatory Commission, Revision 1, November 1979. U.S. DOE Report PNL-5484. D. C. Kocher, "Radioactive Decay Data Tables," U.S. DOE Report DOEITIC-11026, 1981. Version 24 01/10 Internal Memorandum.
J. E. Garlington to D. N. Morey, Alabama Power Company, June 4, 1990. W. W. Meinke and T. H. Essig, "Offsite Dose Calculation Manual Guidance:
Standard Radiological Effluent Controls for Pressurized Water Reactors," NUREG-1301, April 1991. {Joseph M. Farley Nuclear Plant Technical Specifications, Units 1 and 2.} {Code of Federal Regulations, 10 CFR 50.4, "Written Communications."} {Code of Federal Regulations, 10 CFR 50.72, "Immediate Notification Requirements for Operating Nuclear Power Reactors."} {Code of Federal Regulations, 10 CFR 50.73, "Licensee Event Report System."} {Joseph M. Farley Nuclear Plant Technical Requirements Manual (TRM).} Version 24 01/10  

CHAPTER 1 INTRODUCTION The Offsite Dose Calculation Manual is a supporting document of the Technical Specifications.
As such, it describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents, and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm setpoints.
In addition, it contains the following: The controls required by the Technical Specifications, governing the effluent and radiological environmental monitoring Schematics of liquid and gaseous radwaste effluent treatment systems, which include designation of release points to UNRESTRICTED AREAS. A list and maps indicating the specific sample locations for the Environmental Monitoring Specifications and descriptions of the information that must be included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by the Technical Specifications.
The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations.
Changes in the calculational methods or parameters will be incorporated into the ODCM in order to ensure that it represents current methodology in all applicable areas. Any computer software used to perform the calculations described will be maintained current with the ODCM. Equations and methods used in the ODCM are based on those presented in NUREG-0133 (Reference 1), in Regulatory Guide 1.109 (References 2 and 3), in Regulatory Guide 1.111 (References 4 and 5), and in Regulatory Guide 1.113 (Reference 6). Version 24 01/10  

CHAPTER LIQUID 2.1 LIMITS OF OPERATION The following Liquid Effluent Controls implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10. 2.1.1 Liguid Effluent Monitoring Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits specified in Section 2.1.2 are not exceeded.
The alarm/trip setpoints of these channels shall be determined in accordance with Section 2.3. 2.1.1.1 Applicability This limit applies at all times. 2.1.1.2 Actions With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint to a conservative value. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Section 7.2 why this inoperability was not corrected in a timely manner. This control does not affect shutdown requirements or MODE changes. 2.1.1.3 Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST (COT) operations at the frequencies shown in Table 2-2. 2-1 Version 24 01/10 2.1.1.4 Basis The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 2.3 to ensure that the alarm/trip will occur prior to exceeding the limits of Section 2.1.2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 2-2 Version 24 01/10  

Radioactive Liquid Effluent Monitoring Instrumentation Instrument OPERABILITY Requirements a Minimum Channels OPERABLE ACTION 1. Gross Radioactivity Monitors Providing Automatic Termination of Release a. Liquid Radwaste Effluent Line (RE-18) 1 28 b. Steam Generator Blowdown Effluent Line (RE-23B) 1 29 2. Flowrate Measurement Devices a. Liquid Radwaste Effluent Line 1) Waste Monitor Tank No.1 1 30 2) Waste Monitor Tank No.2 1 30 b. Discharge Canal Dilution Line (Service Water) 1 30 c. Steam Generator Blowdown Effluent Line 1 30 a. All requirements in this table apply to each unit. 2-3 Version 24 01/10  

Table 2*1 (contd) Notation for Table 2-1 -ACTION Statements ACTION 28 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release: At least two independent samples are analyzed in accordance with Section 2.1.2.3, and At least two technically qualified members of the Facility Staff independently verify the discharge line valving and Verify the manual portion of the computer input for the release rate calculations performed on the computer, or Verify the entire release rate calculations if such calculations are performed manually.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 29 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab samples are analyzed for gross radioactivity (beta or gamma) at a MINIMUM DETECTABLE CONCENTRATION no higher than 1 x 10.7 /lCi/mL. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01/lCi/gram DOSE EQUIVALENT 1-131. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 /lCi/gram DOSE EQUIVALENT 1-131. ACTION 30 -With the number of channels OPERABLE Jess than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that the flowrate is estimated at least once per 4 hours during actual releases.
Pump curves may be used to estimate flow. Version 24 01/10  

Table 2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT Surveillance Requirements d CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION CHANNEL OPERATIONAL TEST 1. Gross Radioactivity Monitors Providing Automatic Termination of Release a. Liquid Radwaste Effluent Line (RE-18) Db P Rb Qa b. Steam Generator Blowdown Effluent Line (RE-23B) D M Rb Qa 2. Flowrate Measurement Devices a. Liquid Radwaste Effluent Line 1 ) Waste Monitor Tank No.1 DC NA R NA 2) Waste Monitor Tank No.2 DC NA R NA b. Discharge Canal Dilution Line (Service Water) DC NA R Q c. Steam Generator Blowdown Effluent Line DC NA R NA a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section 10.2): The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists: Instrument indicates measured levels above the alarm/trip setpoint; Loss of control power; or Instrument controls loss of instrument power. The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: Instrument indicates a downscale failure; or Instrument controls not set in operate mode. Version 24 01/10  

Table 2-2 (cont'd) Notation for Table 2-2 b. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurements assurance activities with NIST. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. c. CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. d. All requirements in this table apply to each unit. 2-6 Version 24 01/10  

2.1.2 Liquid Effluent Concentration Control In accordance with Technical Specifications 5.5.4.b and 5.5.4.c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 10-1) 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 x 10-4 IlCilmL total activity.
2.1.2.1 Applicability This limit applies at all times 2.1.2.2 Actions With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the limits stated in Section 2.1.2, immediately restore the concentration to within the stated limits. This control does not affect shutdown requirements or MODE changes. 2.1.2.3 Surveillance Requirements The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 2-3. The results of radioactive analyses shall be used with the calculational methods in Section 2.3 to assure that the concentration at the point of release is maintained within the limits of Section 2.1.2. 2.1 .2.4 Basis This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section ILA design objectives of Appendix 1,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.1301 to the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2 (1959). The resulting concentration of 2 x 10-4 was then multiplied by the ratio of the effluent concentration limit for Xe-135, stated in Appendix B, Table 2, Column 1 of 10 CFR 20 (paragraphs 20.1001 to 20.2401), to the I\t1PC for Xe-135, stated in Appendix B, Table II, Column 1 of 10 CFR 20 (paragraphs 20.1 to 20.601), to obtain the limiting concentration of 1 x 10-4 Il Ci/mL. 2-7 Version 24 01/10  

Table 2-3 Radioactive Liquid Waste Sampling and Analysis Program Sampling and Analysis Requirementsa,b MINIMUM DETECTABLE Minimum CONCENTRATION Liquid Sampling Analysis Type of Activity (MDC)Release Type FREQUENCY FREQUENCY Analysis A. Waste Tanks Producin;:, BATCH RELEASES PRINCIPAL GAMMA EMITTERS 5 E-7 P P Each BATCH Each BATCH 1-131 1 E-6 Dissolved and P M Entrained Gases All One BATCH/M (Gamma Emitters) 1 E-5 H-3 1 E-5 P M Each BATCH COMPOSITE Gross Alpha 1 E-7 Sr-89, Sr-90 5 E-8 P Q Each BATCH COMPOSITE Fe-55 1 E-6 B. CONTINUOUS RELEASES c PRINCIPAL GAMMA EMITTERS 5 E-7 D W Grab Sample COMPOSITE 1-131 1 E-6 Dissolved and Steam M Entrained Gases Generator Grab Sample M (Gamma Emitters) 1 E-5 Blowdown H-3 1 E-5 D M Grab Sample COMPOSITE Gross Alpha 1 E-7 Sr-89, Sr-90 5 E-8 D Q Grab Sample COMPOSITE Fe-55 1 E-6 PRINCIPAL GAMMA Turbine EMITTERS 5 E-7 Building p d W Sump Grab Sample COMPOSITE H-3 1 E-5 2-8 Version 24 01/10  

Table 2-3 (contd) Notation for Table 2-3 a. All requirements in this table apply to each unit. Deviation from the MDC requirements of this table shall be reported in accordance with Section 7.2. b. Terms printed in all capital letters are defined in Chapter 10. c. Sampling will be performed only if the effluent will be discharged to the environment. 
: d. Samples will be taken prior to or during each discharge.
2-9 Version 24 01/10  

2.1.3 Liquid Effluent Dose Control In accordance with Technical Specifications S.S.4.d and S.S.4.e, 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 Figure 10-1) shall be limited: a. During any calendar quarter to less than or equal to 1.S mrem to the total body and to less than or equal to S 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. 2.1.3.1 Applicability These limits apply at all times. 2.1.3.2 Actions With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the limits of Section 2.1.3, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR SO.4, a Special Report which identifies the cause(s) for exceeding the limit(s);
defines the corrective actions to be taken to reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits of Section 2.1.3. This control does not affect shutdown requirements or MODE changes. 2.1.3.3 Surveillance Requirements At least once per 31 days, cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined, for each unit, in accordance with Section 2.4. 2.1.3.4 Basis This control is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part SO. The limits stated in Section 2.1.3 implement the guides set forth in Section II.A of Appendix I. The ACTIONS stated in Section 2.1.3.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in Section 2.4 implement the requirements in Section III.A of Appendix I, which state that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in Section 2.4 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109 (Reference 
: 3) and Regulatory Guide 1.113 (Reference 6). 2-10 Version 24 01/10  

This control applies to the release of liquid effluents from each unit at the site. The liquid effluents from shared LIQUID RADWASTE TREATMENT SYSTEMS are to be proportioned between the units. 2.1.4 Liquid Radwaste Treatment System Control In accordance with Technical Specification 5.5.4.f, the LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the system shall be used to reduce radioactivity in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 10-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ of a MEMBER OF THE PUBLIC in 31 days. 2.1.4.1 Applicability This limit applies at all times. 2.1.4.2 Actions With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not in operation, prepare and submit to the Nuclear Regulatory Commission within 30 days pursuant to 10 CFR 50.4, a Special Report which includes the following information: Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reason for inoperability, Action(s) taken to restore the inoperable equipment to OPERABLE status, and c. Summary description of action(s) taken to prevent a recurrence.
This control does not affect shutdown requirements or MODE changes. 2.1.4.3 Surveillance Requirements Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with Section 2.5, during periods in which the LIQUID RADWASTE TREATMENT SYSTEMs are not being fully utilized.
The LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE: by meeting the controls of Sections 2.1.2 and 2.1.3, or by operating the LIQUID RADWASTE TREATMENT SYSTEM equipment for at least 15 minutes at least once per 92 days unless the LIQUID RADWASTE TREATMENT SYSTEM equipment has been utilized to process radioactive liquid effluents during the previous 92 days. Version 24 01/10  

2.1.4.4. Basis The OPERABILITY ofthe LIQUID RADWASTE TREATMENT SYSTEM ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the UNRESTRICTED AREAS. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the LIQUID RADWASTE TREATMENT SYSTEM were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. MAJOR CHANGES TO LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS Licensee initiated MAJOR CHANGES TO LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS: Shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented, in accordance with Section 7.2.2.7. Shall become effective upon review by the Plant Review Board and approval by the Vice President-Plant. Version 24 01/10  

2.2 LIQUID RADWASTE TREATMENT The Farley Nuclear Plant is located on the west bank of the Chattahoochee River approximately 35 river miles above the point where it empties into Lake Seminole.
There are two pressurized water reactors on the site. Each unit is served by a completely separate LIQUID RADWASTE TREATMENT SYSTEM that is illustrated schematically in Figure 2-1. However. both units share a common demineralizer bed system for processing liquids prior to release from the site. As shown in Figure 2-2. the Steam Generator Blowdown System is a separate entity. Liquid discharge pathways are shown in Figure 2-3. All liquid radwastes treated by the LIQUID RADWASTE TREATMENT SYSTEM are collected in 5.000-gallon Waste Monitor Tanks for sampling and analysis prior to release. Prior to sampling.
each waste monitor tank is recirculated for a minimum of two tank content volumes. to ensure that a representative sample can be taken from the tank. Releases from the waste monitor tanks are routed to the Service Water discharge line (which provides dilution prior to release to the UNRESTRICTED AREA). and thence to the Chattahoochee River. The Service Water discharge line also receives input from the Cooling Tower Blowdown and the Turbine Building Sump. Although no significant quantities of radioactivity are expected in the steam generator blowdown processing system, this effluent pathway is monitored as a precautionary measure. The monitors serving this pathway provide for automatic termination of release in the event that radioactivity is detected above predetermined levels. Like the LIQUID RADWASTE TREATMENT SYSTEMs, the Steam Generator Blowdown Systems discharge to the Service Water discharge line. One potential release pathway. the Turbine Building Sump discharge.
is not monitored during release. but is sampled regularly during discharges.
Sampling and analysis of releases via this pathway must be sufficient to ensure that the liquid effluent dose limits specified in Section 2.1.3 are not exceeded.
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Waste Holdup Tank Waste Evaporator Package Floor Drain Tank Disposable Demlnerallzer System Chemical Drain Tank Waste Monitor Tank 2 Waste Evaporator Condensate 1-------.....1 Tank Laundry and Hot Shower Tank (Unit 1 Only) Waste Monitor Tank 1 Discharge Structure Via Service Water 112RE018 Figure 2*1 LIQUID RADWASTE TREATMENT SYSTEM (TYPICAL OF BOTH UNITS) 2-14 Version 24 01/10  

S/G B Surge Tank r-l 1/2RE23ATo Main Condenser L..-_-( B l---....I Discharge Structure S/G Monitor 1/2RE23B Discharge Figure 2-2 Steam Generator Blowdown System (Typical of Both Units) 2-15 Version 24 01/10  

Unit 2 Service Water Unit 1 Service Water Tr Train A Train B inA Train B 1RE018 Cooling Tower Blowdown Radwaste Discharge Steam Generator Blowdown 1RE23B Turbine Building Sump To River 2RE018 2RE23B Figure 2-3. Liquid Discharge Pathways 2-16 Version 24 01/10  

2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2.3.1 General Provisions Regarding Setpoints Liquid monitor setpoints calculated in accordance with the methodology presented in this section will be regarded as upper bounds for the actual high alarm setpoints.
That is, a lower value for the high alarm setpoint may be established or retained on the monitor, if desired. Intermediate level setpoints should be established at an appropriate level to give sufficient warning prior to reaching the high alarm setpoint.
If no release is planned for a particular pathway, or if there is no detectable activity in the planned release, the monitor setpoint should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inadvertent release occur. Two basic setpoint methodologies are presented below. For radwaste system discharge monitors, setpoints are determined to assure that the limits of Section 2.1.2 are not exceeded.
For monitors on streams that are not expected to contain significant radioactivity, the purpose of the monitor setpoints is to cause an alarm on low levels of radioactivity, and to terminate the release where this is possible.
Section 2.1.1 establishes the requirements for liquid effluent monitoring instrumentation.
Table 2-4 lists the monitors for which each of the setpoint methodologies is applicable.
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Table 2-4 Applicability of Liquid Monitor Setpoint Methodologies Liquid Radwaste Discharge Monitors Setpoint Method: Section 2.3.2 Unit 1 or Unit 2 Waste Monitor Tanks Release Type: Monitor: 1 RE-018 I Unit 1 or Unit 2 Steam Generator Blowdown Release Type:
Monitor: 1 RE-023 B I 2RE-023 Normally Low-Radioactivity Streams with Termination or Diversion upon Alarm Farley Nuclear Plant has no liquid effluent streams in this category.
Normally Low-Radioactivity Streams with Alarm Only Farley Nuclear Plant has no liquid effluent streams in this category.
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2.3.2 Setpoints for Radwaste System Discharge Monitors 2.3.2.1 Overview of Method LIQUID RADWASTE TREATMENT SYSTEM effluent line radioactivity monitors are intended to provide alarm and automatic termination of release prior to exceeding the limits specified in Section 2.1.2 at the pOint of release of the diluted effluent into the UNRESTRICTED AREA. Therefore, their alarm/trip setpoints are established to ensure compliance with the following equation (equation adapted from Addendum to Reference 1): c*J-=-...::.-..."..<
TF .C EeL (2.1)F+J where: C ECL the Effluent Concentration Limit corresponding to the mix of radionuclides in the effluent being considered for discharge, in JlCi/mL. c the setpoint, in JlCi/ml, of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to dilution and subsequent release. The setpoint represents a concentration which, if exceeded, could result in concentrations exceeding the limits of Section 2.1.2 in the UNRESTRICTED AREA. f the effluent flowrate at the location of the radioactivity monitor, in gpm. F the dilution stream f10wrate which can be assured prior to the release point to the UNRESTRICTED AREA, in gpm. A predetermined dilution flowrate must be assured for use in the calculation of the radioactivity monitor setpoint.
TF the tolerance factor selected to allow flexibility in the establishment of a practical monitor setpoint which could accommodate effluent releases at concentrations higher than the ECl values stated in 10 CFR 20, Appendix S, Table 2, Column 2; the tolerance factor must not exceed a value of 10. While equation (2.1) shows the relationships of the critical parameters that determine the setpoint, it cannot be applied practically to a mixture of radionuclides with different Effluent Concentration Limits (ECls). For a mixture of radionuclides, equation (2.1) is satisfied in a practicable manner based on the calculated ECl fraction of the radionuclide mixture and the dilution stream f10wrate that can be assured for the duration of the release (F d), by calculating the maximum permissible effluent flowrate (f m) and the radioactivity monitor setpoint (c). The setpoint method presented below is applicable to the release of only one tank of liquid radwaste per reactor unit at a given time. Liquid releases must be controlled administratively to ensure that this condition is met; otherwise, the setpoint method may not ensure that the limits of Section 2.1.2 are not exceeded. Version 24 01/10  

2.3.2.2 Setpoint Calculation Steps Step Determine the radionuclide concentrations in the liquid waste being considered for release in accordance with the sampling and analysis requirements of Section 2.1.2. To ensure that sample analyses are based on samples that are representative of the waste being sampled. the liquid volume must be mixed thoroughly prior to sampling.
Mixing may be accomplished by any method that has been demonstrated to achieve sufficient mixing for representative sampling.
The Waste Monitor Tanks are recirculated for a minimum of two tank content volumes prior to sampling.
The Service Water discharge line is assumed to be well mixed. so that no additional mixing is required prior to sampling.
The total concentration of the liquid waste is determined by the results of all required analyses on the collected sample, as follows: LC; =C a + Lc. +C f +C 1 + LC g (2.2) g where: C a the gross concentration of alpha emitters in the liquid waste, not less than that measured in the most recent applicable composite sample. C s the concentration of strontium radioisotopes (Sr-89 or Sr-90) in the liquid waste, not less than that measured in the most recent applicable composite sample. the concentration of Fe-55 in the liquid waste, not less than that measured in the most recent applicable composite sample. the concentration of H-3 in the liquid waste, not less than that measured in the most recent applicable composite sample. C g the concentration of gamma emitter g in the liquid waste as measured by gamma ray spectroscopy performed on the sample for the release under consideration.
The C g term will be included in the analysis of each waste sample; terms for gross concentrations of alpha emitters, Sr-89, Sr-90, Fe-55, and tritium will be included in accordance with the sampling and analysis program required for the waste stream (see Section 2.1.2). For each analysis, only radionuclides identified and detected above background for the given measurement should be included in the calculation.
When using the alternate setpoint methodology of step 5.b, the historical maximum values of C a , C s , Cf. and C t shall be used. Step Determine the required dilution factor for the mix of radionuclides detected in the waste. Version 24 01/10  

Measured radionuclide concentrations are used to calculate ECl fractions.
The ECl fractions are used along with a safety factor to calculate the required dilution factor; this is the minimum ratio of dilution flowrate to waste flowrate that must be maintained throughout the release to ensure that the Effluent Concentration Limits of Section 2.1.2 are not exceeded at the point of discharge into the UNRESTRICTED AREA. The required dilution factor, RDF, is calculated as the sum of the dilution factors required for gamma emitters (RDFy) and for non-gamma-emitters (RDFny): RDF = [2: + [(SFXTF)]
i ECL i (2.3) = RDF'y + RDFny (2.4) (2.5) where: the measured concentration of radionuclide i as defined in step 1, in IlCifmL. The C a , C s , C I , and C t terms will be included in the calculation as appropriate.
the ECl for radionuclide i from 10 CFR Part 20, Appendix S, Table 2, Column 2 (except for noble gases as discussed below). In the absence of information regarding the solubility classification of a given radionuclide in the waste stream, the solubility class with the lowest ECl shall be assumed. For dissolved or entrained noble gases, the concentration shall be limited to 1 x 10-4 IlCifmL. For gross alpha, the ECl shall be 2 x 10 .9 Il Ci/ml; if specific alpha-emitting radionuclides are measured, the ECl for the specific radionuclide(s) should be used. SF the safety factor selected to compensate for statistical fluctuations and errors of measurement.
The value for the safety factor must be between o and 1. A value of 0.5 is reasonable for liquid releases; a more precise value may be developed if desired. TF the tolerance factor (as defined in Section 2.3.2.1).
Step 3: Determine the release-specific assured dilution stream flowrate.
Determine the dilution stream flowrate that can be assured during the release period, designated F d. Version 24 01/10  

If simultaneous radioactive releases are planned from the same reactor unit, the unit's dilution stream must be allocated among all the simultaneous releases, whether or not they are monitored during release. Normally, only the Waste Monitor Tank and Steam Generator Blowdown effluents need be considered, unless there is detectable radioactivity in one of the normally low-radioactivity streams (see Table 2-4), or in the Turbine Building Sump. Allocation of the dilution stream to multiple release paths is accomplished as follows: (2.6) where: F dp = the dilution flowrate allocated to release pathway p, in gpm. AFp the dilution allocation factor for release pathway p. AFp may be assigned any value between 0 and 1 for each active release pathway, under the condition that the sum of the AFp for all active release pathways for each unit does not exceed 1. [Note: Because the two units have separate dilution streams, the two units do not affect each other with respect to dilution allocation.]
the assured minimum dilution flow for the unit, in gpm. If more precise allocation factor values are desired, they may be determined based on the relative radiological impact of each active release pathway; this may be approximated by multiplying the RDF of each effluent stream by its respective planned release flowrate, and comparing these values. If only one release pathway for a given reactor unit contains detectable radioactivity, its AFp may be assigned the value of 1, making F dp equal to F d* For the case where RDF s; 1, the planned release meets the limits of Section 2.1.2 without dilution, and may be released with any desired effluent flowrate and dilution flowrate.
Step Determine the maximum allowable waste discharge flowrate.
For the case where RDF > 1, the maximum permissible effluent discharge flowrate for this release pathway, fmp (in gpm), is calculated as follows: _ F dp (2.7)imp -(RDF -1) For the case RDF s; 1, equation (2.7) is not valid. However, as discussed above, when RDF s; 1, the release may be made at full discharge pump capacity; the radioactivity monitor setpoint must still be calculated in accordance with Step 5 below. NOTE Discharge flowrates are actually limited by the discharge pump capacity.
When the calculated maximum permissible release flowrate exceeds the pump capacity, the release may be made at full capacity.
Discharge flowrates less than the pump capacity must be achieved by throttling if this is available; if throttling is not available, the release may not be made as planned. Version 24 01/10 FNp*ODCM NOTE If, at the time of the planned release, there is detectable radioactivity due to plant operations in the dilution stream, the diluting capacity of the dilution stream is diminished. (In addition, sampling and analysis of the other radioactive effluents affecting the dilution stream must be sufficient to ensure that the liquid effluent dose limits specified in the controls of Section 2.1.3 are not exceeded.)
Under these conditions, equation (2.7) must be modified to account for the radioactivity present in the dilution stream prior to the introduction of the planned release: where: the measured concentration of radionuclide i in release pathway r that is contributing to radioactivity in the dilution stream. the effluent discharge f10wrate of release pathway r. If the entire dilution stream contains detectable activity due to plant operations, whether or not its source is identified, f r= F d , and C ir is the concentration in the total dilution system. This note does not apply: a) if the RDF of the planned release is 1; or b) if the release contributing radioactivity to the dilution stream has been accounted for by the assignment of an allocation factor. Step Determine the maximum radioactivity monitor setpoint concentration.
Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the limits of Section 2.1.2 will not be exceeded.
Because the radioactivity monitor responds primarily to gamma radiation, the monitor setpoint c p for release pathway p (in jlCi/mL) is based on the concentration of gamma emitters in the waste stream, as follows: where: an adjustment factor which will allow the setpoint to be established in a practical manner to prevent spurious alarms while allowing a margin between measured concentrations and the limits of Section 2.1.2. Step If the concentration of gamma emitters in the effluent to be released is sufficient that the high alarm setpoint can be established at a level that will prevent spurious alarms, Ap should be calculated as follows: Ap _l_xADF==_l_x (Fdp +fa p) (2.10)RDF RDF f ap where: Version 24 01/10  

ADF the assured dilution factor. fap the anticipated actual discharge flowrate for the planned release (in gpm), a value less than f mp. The release must then be controlled so that the actual effluent discharge flowrate does not exceed fap at any time. Step 5.b. Alternatively, Ap may be calculated as follows: A = ADF-RDFny (2.11) P RDF y Step 5.c. Evaluate the computed value of Ap as follows: If Ap ;::: 1, calculate the monitor setpoint, cpo However, if c p is within about 10 percent of C g , it may be impractical to use this value of Cp. This situation indicates that measured concentrations are approaching values which would cause the limits of Section 2.1.2 to be exceeded.
Therefore, steps should be taken to reduce potential concentrations at the point of discharge; these steps may include decreasing the planned effluent discharge flowrate, increasing the dilution stream f1owrate, postponing simultaneous releases, and/or decreasing the effluent concentrations by further processing the liquid planned for release. Alternatively, allocation factors for the active liquid release pathways may be reassigned.
When one or more of these actions has been taken, repeat Steps 1-5 to calculate a new radioactivity monitor setpoint.
If Ap < 1, the release may not be made as planned. Consider the alternatives discussed in the paragraph above, and calculate a new setpoint based on the results of the actions taken. Version 24 01/10 FNP-ODCM 2.3.2.3 Use of the Calculated Setpoint The setpoint calculated above is in the units IlCi/mL. The monitor actually measures a count rate that includes background, so that the calculated setpoint must be converted accordingly:
c* c . E + B (2.8a)p p p the monitor setpoint as a count rate. the monitor calibration factor, in count rate/(IlCi/mL).
Monitor calibration data for conversion between count rate and concentration may include operational data obtained from determining the monitor response to stream concentrations measured by liquid sample analysis. the monitor background count rate. In all cases, monitor background must be controlled so that the monitor is capable of responding to concentrations in the range of the setpoint value. The count rate units of E p , and Bp in equation (2.8a) must be the same (cpm or cps). 2.3.3 Setpoints for Monitors on Normally Low-Radioactivity Streams Radioactivity in these streams (listed in Table 2-4 above) is expected to be at very low levels, generally below detection limits. Accordingly, the purpose of these monitors is to alarm upon the occurrence of significant radioactivity in these streams, and to terminate or divert the release where this is possible.
2.3.3.1 Normal Conditions When radioactivity in one of these streams is at its normal low level, its radioactivity monitor setpoint should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inadvertent release occur. 2.3.3.2 Conditions Requiring an Elevated Setpoint Under the following conditions, radionuclide concentrations must be determined and an elevated radioactivity monitor setpoint determined for these pathways: For streams that can be diverted or isolated, a new monitor setpoint must be established when it is desired to discharge the stream directly to the dilution water even though the radioactivity in the stream exceeds the level which would normally be diverted or isolated. Version 24 01/10}}