ML14125A098

Enclosure 1: Hatch Annual Radioactive Effluent Release Report for 2013

ML14125A098
Person / Time
Site:	Hatch
Issue date:	04/30/2014
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML14125A094	List: ML14125A097 ML14125A098 ML14125A099 ML14125A100 ML14125A101 NL-14-0659, Edwin I. Hatch, Units 1 & 2, Joseph M. Farley, Units 1 & 2, Vogtle, Units 1 & 2, Southern Nuclear Operating Company'S Submittal of Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manuals for 2013 NL-14-0659, Enclosure 1: Hatch Annual Radioactive Effluent Release Report for 2013 NL-14-0659, Enclosure 2: Farley Annual Radioactive Effluent Release Report for 2013 NL-14-0659, Enclosure 3: Vogtle Annual Radioactive Effluent Release Report for 2013 NL-14-0659, Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23 NL-14-0659, Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 29
References
NL-14-0659
Download: ML14125A098 (94)

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Edwin I. Hatch Nuclear PlantJoseph M. Farley Nuclear PlantVogtle Electric Generating PlantAnnual Radioactive Effluent Release Reports andOffsite Dose Calculation Manuals for 2013Enclosure 1Hatch Annual Radioactive Effluent Release Report for 2013 SOUTHERN COMPANYE. I. HATCH NUCLEAR PLANT- UNITS I AND 2NRC DOCKET NOS. 50-321 AND 50-366FACILITY OPERATING LICENSE NOS. DPR-57 AND NPF-5ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTFORJANUARY 1, 2013 TO DECEMBER 31, 2013Prepared by:.Reviewed by: t,,t/lA. £ enMCA SECTION1.01.11.1.11.1.21.21.31.3.11.41.4.11.51.61.71.81.9TITLELiquid EffluentsRegulatory RequirementsConcentration LimitsDose LimitsEffluent Concentration LimitMeasurements and Approximations of TotalRadioactivity for Liquid RadwasteTotal Radioactivity Determination for Liquid RadwasteMeasurements and Approximations of TotalRadioactivity for Groundwater Outfall -Y22N008ATotal Radioactivity Determination for GroundwaterOutfallsTotal Error EstimationLiquid Effluent Release DataRadiological Impact Due to Liquid ReleasesLiquid Effluents -Batch ReleasesLiquid Effluents -Continuous ReleasesPAGE21111224456777 SECTION1.102.02.12.1.12.1.22.1.32.22.2.12.2.22.2.2.12.2.2.22.2.2.32.2.32.32.42.52.63.03.13.1.13.1.2TITLELiquid Effluents -Abnormal ReleasesGaseous EffluentsRegulatory RequirementsDose Rate LimitsAir Doses Due to Noble Gases in Gaseous ReleasesDoses to a Member of the PublicMeasurements and Approximations of TotalRadioactivitySample Collection and AnalysisTotal Quantities of Radioactivity, Dose Ratesand Cumulative DosesFission and Activation GasesRadioiodine, Tritium and Particulate ReleasesGross Alpha ReleaseTotal Error EstimationGaseous Effluent Release DataRadiological Impact Due to Gaseous ReleasesGaseous Effluents -Batch ReleasesGaseous Effluents -Abnormal ReleasesSolid WasteRegulatory RequirementsSolid Radioactive Waste SystemReporting RequirementsPAGE72828282828292930303031313334343464646464ii zECT/ON3.24.04.14.25.05.15.26.07.07.17.1.17.1.27.27.2.17.2.27.37.3.17.3.2TITLESolid Waste DataDoses to Members of the Public Inside TheSite BoundaryRegulatory RequirementsDemonstration of ComplianceTotal Dose from Uranium Fuel Cycle (40 CFR 190)Regulatory RequirementsDemonstration of ComplianceMeteorological DataProgram DeviationsInoperable Liquid or Gaseous EffluentMonitoring InstrumentationRegulatory RequirementsDescription of DeviationsTanks Exceeding Curie Content LimitsRegulatory RequirementsDescription of DeviationsEffluent Sample Analysis Exceeding MinimumDetectable Concentration (MDC)Regulatory RequirementDescription of Deviation6569696974747475767676767676767777Vi

-SECTION8.08.18.29.09.19.2T/T/PA nTITI F IIIII ...77Changes to the Plant HatchOffsite Dose Calculation Manual (ODCM)Regulatory RequirementsDescription of ChangesMajor Changes to the Liquid, Gaseous orSolid Radwaste Treatment SystemsRegulatory RequirementsDescription of Major Changes7777787878vi TABLE LIST OF TABLES PAGE1-1A Liquid Effluents -Summation of All Releases 8Unit 1 (Quarters 1, 2, 3 and 4)1-1B Liquid Effluents -Summation of All Releases 9Unit 2 (Quarters 1, 2, 3 and 4)1-1C Liquid Effluents -Summation of All Releases 10Site (Quarters 1, 2, 3 and 4)1-2A Liquid Effluents -Unit I (Quarters 1, 2, 3 and 4) 111-2B Liquid Effluents -Unit 2 (Quarters 1, 2, 3 and 4) 141-2C Liquid Effluents -Site (Quarters 1, 2, 3 and 4) 171-3A Doses to a Member of The Public Due to Liquid 20Releases Unit I (Quarters 1, 2, 3 and 4)1-3B Doses to a Member of The Public Due to Liquid 21Releases Unit 2 (Quarters 1, 2, 3 and 4)1-4 Minimum Detectable Concentration -22Liquid Sample Analysis1-5A Liquid Effluents -Batch Release Summary 23Unit 11-5B Liquid Effluents -Batch Release Summary 24Unit 2vi rA VI IZT n I 1=4TAI /.-I 6A Liquid Effluents -Abnormal Release 25Summary Unit 11-6B Liquid Effluents -Abnormal Release 26Summary Unit 21-6C Liquid Effluents -Abnormal Release 27Summary Site2-1A Gaseous Effluents -Summation of All 35Releases -Unit I (Quarters 1, 2, 3 and 4)2-1 B Gaseous Effluents -Summation of All 36Releases -Unit 2 (Quarters 1, 2, 3 and 4)2-1C Gaseous Effluents -Summation of All 37Releases -Site (Quarters 1, 2, 3 and 4)2-2A Gaseous Effluents -Elevated Releases 38Unit I (Quarters 1, 2, 3 and 4)2-2B Gaseous Effluents -Elevated Releases 41Unit 2 (Quarters 1, 2, 3 and 4)2-2C Gaseous Effluents -Elevated Releases 44Site (Quarters 1, 2, 3 and 4)2-3A Gaseous Effluents -Ground Level Releases 47Unit I (Quarters 1, 2, 3 and 4)2-3B Gaseous Effluents -Ground Level Releases 49Unit 2 (Quarters 1, 2, 3 and 4)2-3C Gaseous Effluents -Ground Level Releases 51Site (Quarters 1, 2, 3 and 4)2-4A Air Doses Due to Noble Gases in Gaseous 54Releases -Unit I (Quarters 1, 2, 3 and 4)vi TAI I=I VZ T nP TA Al F-4ZpArI::2-4B Air Doses Due to Noble Gases in Gaseous 55Releases- Unit 2 (Quarters 1, 2, 3 and 4)2-5A Doses to a Member of the Public Due to 56Radioiodine, Tritium, and Particulates inGaseous Releases -Unit 1(Quarters 1, 2, 3 and 4)2-5B Doses to a Member of the Public Due to 57Radioiodine, Tritium, and Particulates inGaseous Releases -Unit 2(Quarters 1, 2, 3 and 4)2-6 Minimum Detectable Concentration -58Gaseous Sample Analyses2-7A Gaseous Effluents -Batch Release 59Summary Unit 12-7B Gaseous Effluents -Batch Release 60Summary Unit 22-8A Gaseous Effluents -Abnormal Release 61Summary Unit I2-8B Gaseous Effluents -Abnormal Release 62Summary Unit 22-8C Gaseous Effluents -Abnormal Release 63Summary Site3-1 Solid Waste and Irradiated Fuel Shipments 664-1 Doses to a Member of the Public Due to 70Activities Inside The Site Boundaryvii ATTACHMENTAPPENDIX $APPENDIX BADDENDUMTITI P10 A f2 =79Carbon-14Summary of GroundwaterProtection Program2012 Program Deviations8183viii 1.0 Liquid Effluents1.1 Regulatory Requirements1.1.1 Concentration LimitsThe concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS shall be limited to ten times the concentrationsspecified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclidesother than dissolved or entrained noble gases. For dissolved or entrained noblegases, the concentration shall be limited to 1 E-04 microcuries/ml total activity.1.1.2 Dose LimitsThe dose or dose commitment, to a MEMBER OF THE PUBLIC from radioactivematerials in liquid effluents released from each unit to UNRESTRICTED AREAS,shall be limited:a. During any calendar quarter, to less than or equal to 1.5 mrems to thewhole body and to less than or equal to 5 mrems to any organ, andb. During any calendar year, to less than or equal to 3 mrems to the wholebody and to less than or equal to 10 mrems to any organ.1.2 Effluent Concentration LimitECL values used in determining allowable liquid radwaste release rates andconcentrations, for principal gamma emitters, 1-131, tritium, Sr-89, Sr-90 andFe-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 practicalmonitor set points which can accommodate effluent releases at concentrationshigher 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 is1 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, theoverall ECL fraction is determined in accordance with 10 CFR Part 20,Appendix B.The method utilizing the ECL fraction to determine liquid radwaste release ratesand effluent radiation monitor set points is described in Subsection 1.3 of thisreport.1 The method utilizing the ECL fraction to determine the dose released fromgroundwater outfalls is described in Subsection 1.4 of this report.1.3 Measurements and Approximations of Total Radioactivity for LiquidRadwastePrior to the release of any tank containing liquid radwaste, following the requiredrecirculations, samples are collected and analyzed in accordance with theEdwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3.A sample from each tank planned for release is analyzed for principal gammaemitters, 1-131, and dissolved and entrained noble gases, by gammaspectroscopy. Monthly and quarterly composites are prepared for analysis byextracting aliquots from each sample taken from the tanks released.Liquid radwaste sample analyses are performed as described in Section 1.3.1.1.3.1 Total Radioactivity Determination for Liquid RadwasteMEASUREMENT1. Gamma Isotopic2. Dissolved or entrainednoble gas3. Tritium4. Gross Alpha5. Sr-89 & Sr-90FREQUENCYEach BatchEach BatchMonthlyCompositeMonthlyCompositeQuarterlyCompositeMETHODGamma Spectroscopywith computerized datareductionGamma Spectroscopywith computerized datareductionDistillation and liquidscintillation countingGas flow proportionalcountingChemical separationand gas flowproportional orscintillation countingChemical separationand liquid scintillationcounting6. Fe-55QuarterlyComposite2 Gamma isotopic measurements are performed in-house using germaniumdetectors with a resolution of 2 keV or lower. The detectors are shielded by fourinches of lead. A liquid radwaste sample is typically counted for 2000 secondsand a peak search of the resulting gamma ray spectrum is performed. Energyand net count data for all significant peaks are determined and a quantitativereduction or MDC calculation is performed to ensure that the MDC's are met forthe nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60,Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-141 and Ce-144). The quantitativecalculations, corrections for counting time, decay time, sample volume, samplegeometry, detector efficiency, baseline counts, branching ratio and MDCcalculations, are made based on the counts at the location in the spectrum wherethe peak for that radionuclide would be located, if present. Typically achievedliquid effluent sample analyses minimum detectable concentrations are reported inTable 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 ofsamples taken from tanks planned for release, in addition to the most currentsample 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 fractionfor these tanks. This ECL fraction is then used, with the appropriate safetyfactors, tolerance factors, and the expected dilution stream flow to calculatemaximum permissible release rate and a liquid effluent monitor setpoint. Themonitor setpoint is calculated to assure that the limits of the ODCM are notexceeded.A monitor reading in excess of the calculated setpoint will result in an automatictermination of the liquid radwaste discharge. Liquid effluent discharge is alsoautomatically terminated if the dilution stream flow rate falls below the minimumassured dilution flow rate used in the setpoint calculations and established as asetpoint on the dilution stream flow monitor.Radionuclide concentrations, safety factors, dilution stream flow rate, and theliquid effluent radiation monitor calibration factor, are entered into the computerand a pre-release printout is generated. If the release is not permissible,appropriate warnings will be displayed on the computer screen. If the release ispermissible, it is approved by a qualified Chemistry Technician. The pertinentinformation is transferred manually from the prerelease printout to a one-pagerelease permit, which is forwarded to Radwaste Operations. When the release iscompleted, the release permit is returned from Radwaste Operations to Chemistrywith the actual release data provided. These data are input into the computer anda post-release printout is generated. The post release printout contains the actualrelease rates, the actual release concentrations and quantities, the actual dilutionflow, and the calculated doses to a Member of the Public.3 1.4 Measurements and Approximations of Total Radioactivity for GroundwaterOutfalls -Y22NO03A/12B and Y22NO08ASamples are collected and analyzed in accordance with the Edwin I. HatchNuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3. Weekly,monthly and quarterly composites are prepared for analysis by extracting aliquotsfrom each outfall's automatic sampler, which collects a composite sample over aseven-day period. Sample analyses are performed as described in Section 1.4.1.1.4.1 Total Radioactivity Determination for Groundwater OutfallsMEASUREMENT1. Gamma Isotopic2. Tritium3. Gross Beta*4. Sr-89 & Sr-90**FREQUENCYWeekly CompositeWeekly CompositeQuarterlyCompositeQuarterlyComposite(as required)METHODGamma Spectroscopywith computerized datareductionDistillation and liquidscintillation countingChemical separationand gas flowproportional orscintillation countingChemical separationand gas flowproportional orscintillation counting* Gross Beta analysis is used for sample screening.** If the Gross Beta analysis yields a detectable value above background,a Sr-89/90 analysis will be performed.4 Gamma isotopic measurements are performed in-house using germaniumdetectors with a resolution of 2 keV or lower. The detectors are shielded by fourinches of lead. A weekly composite sample is typically counted to EnvironmentalMDC'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 aquantitative reduction or MDC calculation is performed to ensure that the MDC'sare met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59,Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-141 and Ce-144). Thequantitative calculations, corrections for counting time, decay time, samplevolume, sample geometry, detector efficiency, baseline counts, branching ratioand MDC calculations, are made based on the counts at the location in thespectrum where the peak for that radionuclide would be located, if present.Typically achieved liquid effluent sample analyses minimum detectableconcentrations 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 ofthe weekly composite sample, in addition to the most current sample analysisresults available for tritium, gross beta, Sr-89 and Sr-90, are used along with thecorresponding ECL values to determine the ECL fraction for these compositesamples. This ECL fraction is then used, with the appropriate safety factors,tolerance factors, and the expected dilution stream flow to calculate projecteddose released.Radionuclide concentrations, safety factors and dilution stream flow rate areentered into the computer and a pre-release printout is generated for each releaseperiod. When the release period is complete, the release permit is updated withthe actual release data collected during the release period. These data are inputinto the computer and a post-release printout is generated. The post releaseprintout contains the actual release rates, the actual release concentrations andquantities, the actual dilution flow, and the calculated doses to a Member of thePublic. Cumulative dose results are tabulated along with the percent of theODCM limit for each release period, for the current quarter and year.1.5 Total Error EstimationThe maximum error associated with volume and flow measurements, based uponplant calibration practice, is estimated to be + or -10%. The average errorassociated with counting is estimated to be less than + or -15%. Therefore, thetotal error estimation is + or -18%.5 1.6 Liquid Effluent Release DataRegulatory Guide 1.21, Tables 2A and 2B are found in this report as Table 1-1Afor Unit 1, Table 1-1 B for Unit 2 and Table 1-1C for the site; and Table 1-2A forUnit 1, 1-2B for Unit 2, and Table 1-2C for the site. Typical liquid minimumdetectable concentrations (MDC's) used for analyses are found in Table 1-4.The values for the four categories of Tables 1 -1A, 1-1 B, and 1-1C, arecalculated and the Tables completed as follows:1. Fission and activation products -The total release values (not includingtritium, gases, and alpha) are comprised of the sum of the measuredindividual radionuclide activities. This sum is for each batch released to theriver for the respective quarter.2. Tritium -The measured tritium concentrations in the monthly compositesamples are used to calculate the total release and average dilutedconcentration during each period.3. Dissolved and entrained gases -Concentrations of dissolved and entrainedgases in liquid effluents are measured by germanium spectroscopy using aone liter sample from each liquid radwaste batch. The measuredconcentrations are used to calculate the total release and the averagediluted concentration during the period. Radioisotopes of iodine in anyform are also determined during the isotopic analysis for each batch;therefore, a separate analysis for possible gaseous forms is not performedbecause it would not provide additional information.4. Gross alpha radioactivity -The measured gross alpha concentrations in themonthly composite samples are used to calculate the total release of alpharadioactivity.6 1.7 Radiological Impact Due to Liquid ReleasesDoses to a Member of the Public due to radioactivity in liquid effluents werecalculated in accordance with the Offsite Dose Calculation Manual. Results arepresented in Table 1-3A for Unit 1, and 1-3B for Unit 2, for all four quarters.1.8 Liquid Effluents -Batch ReleasesBatch Release information for Units 1 and 2 is summarized in the following tables:Unit 1 Liquid Batch Releases: Table 1-5AUnit 2 Liquid Batch Releases: Table 1-5B1.9 Liquid Effluents -Continuous ReleasesContinuous Release information is summarized in the following tables:Unit 1 Liquid Continuous Releases: Table 1-2AUnit 2 Liquid Continuous Releases: Table 1-2BHatch Site Conitinuous Releases: Table 1-2C1.10 Liquid Effluents -Abnormal ReleasesThere were no abnormal liquid releases for this reporting period.7 Table 1-1AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents -Summation Of All ReleasesUnit: 1Starting: 1-Jan- 2013 Ending: 31-Dec-2013Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterA. Fission And Activation Products1. Total Release (not includingtritium, gases, alpha) Curies 2.67E-03 6.63E-04 1. IOE-03 7.45E-042. Average diluted concentrationduring period uCi/mL 7.94E-09 2.79E-09 1.31E-09 2.87E-083. Percent of Applicable Limit % * * * *B. Tritium1. Total Release Curies 8.34E+00 5.17E+00 1.86E+01 8.01E-012. Average diluted Concentrationduring period uCi/mL 2.48E-05 2.17E-05 2.22E-05 3.08E-053. Percent of Applicable Limit %* * * *C. Dissolved and Entrained Gases1. Total Release Curies 4.17E-04 3.12E-05 1.OOE-04 6.91E-062. Average diluted Concentrationduring period uCi/mL 1.24E-09 1.31E-10 1.20E-10 2.66E-103. Percent of Applicable Limit % * * * *D: Gross Alpha Radioactivity1. Total Release Curies 7.97E-07 4.76E-06 O.OOE+00 O.OOE+00E: Waste Vol Release (Pre-Dilution) Liters 1.56E+06 1.17E+06 4.05E+06 9.10E+04F. Volume of Dilution Water Used Liters 3.36E+08 2.38E+08 8.35E+08 2.60E+07* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.8 Table 1-1BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents -Summation Of All ReleasesUnit: 2Starting: 1-Jan- 2013 Ending: 31-Dec-2013Units 1ST Quarter 2ND Quarter 3RD QuarterType of EffluentA. Fission And Activation Products1. Total Release (not includingtritium, gases, alpha)2. Average diluted concentrationduring period3. Percent of Applicable Limit4TH Quarter1.52E-033.33E-10CuriesuCi/mL9.05E-031.53E-092.19E-034.54E-101.32E-032.37E-10B. Tritium1. Total Release2. Average diluted Concentrationduring period3. Percent of Applicable LimitC. Dissolved and Entrained Gases1. Total Release2. Average diluted Concentrationduring period3. Percent of Applicable LimitD: Gross Alpha Radioactivity1. Total ReleaseE: Waste Vol Release (Pre-Dilution)F. Volume of Dilution Water UsedCuriesuCi/mLCuriesuCi/mLCuries9.95E+001.68E-068.19E-051.38E-110.O0E+005.34E+065.92E+097.83E+001.63E-064.48E-049.31E-1 13.79E-085.18E+064.82E+094.68E+008.40E-078.38E-051.50E-110.OOE+006.08E+065.57E+091.07E+002.33E-071.70E-043.72E-110.OOE+002.48E+064.58E+09LitersLiters* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.9 Table 1-ICHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents -Summation Of All ReleasesUnit: SiteStarting: 1-Jan- 2013 Ending: 31-Dec-2013Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterA. Fission And Activation Products1. Total Release (not includingtritium, gases, alpha) Curies 1.18E-02 2.85E-03 2.42E-03 2.27E-032. Average diluted concentrationduring period uCi/mL 1.88E-09 5.64E-10 3.77E-10 4.93E-103. Percent of Applicable Limit %* * * *B. Tritium1. Total Release Curies 1.85E+01 1.30E+01 2.32E+01 1.87E+002. Average diluted Concentrationduring period uCi/mL 2.95E-06 2.57E-06 3.62E-06 4.06E-073. Percent of Applicable Limit %* * * *C. Dissolved and Entrained Gases1. Total Release Curies 5.26E-04 4.80E-04 1.84E-04 1.77E-042. Average diluted Concentrationduring period uCi/mL 8.41E-11 9.49E-11 2.88E-11 3.85E-113. Percent of Applicable Limit %* * * *D: Gross Alpha Radioactivity1. Total Release Curies 8.25E-07 4.80E-06 O.OOE+00 O.OOE+00E: Waste Vol Release (Pre-Dilution) Liters 6.89E+06 6.35E+06 1.01E+07 2.57E+06F. Volume of Dilution Water Used Liters 6.26E+09 5.05E+09 6.41E+09 4.60E+09* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.10 Table 1-2AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Continuous Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedFission & Activation ProductsNo Nudides FoundUnitCuriesTritiumNo Nuclides FoundCuriesO.OOE+O0O.OOE+O0O.OOE+00O.OOE+0O0.OOE+000.OOE+000.OOE-t00O.OOE+000.OOE-i000.OOE+0OO.OOE+00O.OOE+OOO.OOE+O0O.OOE+00O.OOE+00O.OOE+OODissolved And Entrained GasesNo Nuclides FoundGross Alpha RadioactivityNo Nuclides FoundCuriesCuriesZeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.11 Table 1-2AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Batch Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedFission & Activation ProductsAs-76Co-57Co-58Co-60Cr-51Fe-55Fe-59Mn-54Mn-56Na-24Nb-97Sr-89Sr-90Sr-92Zn-65Au-199Cs-137La-140Sb-122Sb-124Zn-69MAg-110MTotal For PeriodUnitCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuries0.OOE+00O.OOE+004.38E-051.58E-039.87E-051.51E-042.33E-061.54E-040.OOE+008.85E-062.87E-043.70E-050.OOE+005. 12E-077.27E-050.OOE+001.88E-040.OOE+003.33E-072.01E-060.OOE+000.OOE+O00.OOE+004.57E-052.52E-040.OOE+001. 15E-040.OOE+005.99E-058.43E-077.52E-058.52E-061.89E-050.OOE-i000.OOE+002.44E-050.OOE+006.29E-050.OOE+000.OOE+000.COE+000.OOE+000.OOE+003.90E-075.38E-054.39E-040.OOE+000.OOE+00O.OOE+009.61E-051.56E-053.20E-042.09E-050.OOE+000.OOE+005.52E-074. 13E-050.OOE+001.O1E-042.54E-060.OOE+000.OOE+006.46E-062.99E-060.OOE+003.42E-051.52E-042.23E-055.73E-050.OOE+008.77E-057.76E-051.57E-066.88E-060.OOE+006.04E-070.OOE+002.69E-041.71lE-058.86E-060.OOE+000.OOE+000.OOE+007.29E-06Curies 3.92E-05 0.OOE+00 0.OOE+00 0.OOE+00Curies 2.67E-03 6.63E-04 1.10E-03 7.45E-04Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.12 Table 1-2AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid EffluentsUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Nuclides ReleasedTrtiumH-3UnitCuriesBatch Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter8.34E+00 5.17E+00 1.86E+01 8.01E-012.54E-04 6.14E-06 2.98E-06 5.54E-061.63E-04 2.51E-05 9.75E-05 1.38E-064.17E-04 3.12E-05 1.00E-04 6.91E-06Dissolved And Entrained GasesXe-133Xe-135Total For PeriodCuriesCuriesCuresCuriesGross Alpha RadioactivityG-Alpha7.97E-074.76E-06O.OOE+O0O.OOE+O0Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.13 Table 1-25Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Continuous ModeUnit 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterCuries O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0Curies 1.73E-02 2.09E-02 3.43E-02 1.11E-02Nuclides ReleasedFission & Activation ProductsNo Nuclides FoundTritiumH-3Dissolved And Entrained GasesNo Nudides FoundGross Alpha RadioactivityNo Nuclides FoundCuriesCuriesO.OOE+O0O.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.14 Table 1-2BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid EffluentsUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Batch ModeNuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterFission & Activation ProductsY-92 Curies 2.39E-05 5.67E-05 O.OOE+00 O.OOE+00As-76 Curies 1.72E-05 1.72E-05 O.OOE+00 3.79E-05Co-58 Curies 4.85E-04 7.33E-05 7.87E-05 9.OOE-05Co-60 Curies 2.97E-03 4.71E-04 2.84E-04 1.84E-04Cr-51 Curies 1.04E-03 5.85E-06 1.67E-05 1.76E-05Fe-55 Curies 7.57E-05 8.93E-05 O.OOE+00 1.73E-05Fe-59 Curies 3.37E-05 O.OOE+00 O.OOE+00 O.OOE+001-131 Curies 0.OOE+00 1.09E-06 6.20E-06 3.53E-051-133 Curies 1.68E-05 8.48E-06 1.08E-05 2.97E-05Mn-54 Curies 2.12E-03 2.53E-04 2.53E-04 1.13E-04Mn-56 Curies 2.40E-04 6.96E-05 5.72E-05 1.52E-04Na-24 Curies 7.17E-04 3.81E-04 2.27E-04 2.82E-04Nb-95 Curies 1.92E-05 9.89E-07 O.O0E+00 O.OOE+00Nb-97 Curies 1.55E-04 4.55E-04 2.41E-05 1.58E-05Sr-89 Curies 1.00E-04 6.02E-05 1.10E-04 4.55E-05Sr-91 Curies 3.08E-05 8.06E-06 O.OOE+00 8.32E-05Sr-92 Curies 1.58E-05 1.96E-06 O.OOE+00 1.69E-05Y-91M Curies 1.47E-05 3.77E-05 9.30E-06 1.40E-05Zn-65 Curies 3.79E-04 8.36E-05 1.43E-04 8.45E-05Zr-95 Curies 1.1OE-05 O.OOE+00 O.OOE+00 O.OOE+00Au-199 Curies O.OOE+00 O.OOE+00 2.21E-06 5.32E-06Ba-140 Curies O.OOE+O0 O.OOE+00 O.OOE+O0 4.50E-05Ce-141 Curies 7.56E-06 O.OOE+O0 O.OOE+O0 6.40E-06Cs-137 Curies 2.42E-04 3.61E-05 6.07E-05 1.59E-05La-140 Curies 7.96E-06 2.83E-05 3.62E-06 2.83E-05Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations. 15 Table 1-2BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Batch ModeNuclides ReleasedSb-124Sb-125Tc-99MZn-69MAg-iIOMTotal For PeriodUnit 1ST QuarterCuries 2.40E-04Curies 2.29E-05Curies 1.85E-05Curies 3.79E-05Curies 7.47E-06Curies 9.05E-032ND Quarter3.33E-060.00E+001.30E-052.71E-056.13E-062.19E-033RD Quarter0.OOE+00O.OOE+002.27E-059.16E-06O.OOE+001.32E-034TH QuarterO.OOE+00O.OOE+003.62E-051.62E-046.68E-061.52E-03TritiumH-3Curies9.93E+007.81E+004.65E+001.05E+00Dissolved And Entrained GasesKr-88Xe-133Xe-135Xe-133MXe-135MTotal For PeriodCuriesCuriesCuriesCuriesCuriesCuriesCuries1.25E-069.65E-067.10E-050.OOE+000.OOE+000.OOE+001.74E-042.75E-040.OOE+000.OOE+000.OOE+0O4.35E-054.04E-050.OOE+000.OOE+00O.OOE+003.39E-055.35E-052.6 1E-068.02E-058.19E-050.OOE+004.48E-043.79E-088.38E-050.OOE+0Q1.70E-040.OOE+00Gross Alpha RadioactivityG-AlphaZeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.16 Table 1-2CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Continuous Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedFission & Activation ProductsNo Nuclides FoundUnitCuriesCuriesTritium0.OOE+001. 73E-020.OOE+002.09E-020.OOE+003.43E-02O.OOE+001.11E-02H-3Dissolved And Entrained GasesNo Nuclides FoundGross Alpha RadioactivityNo Nuclides FoundCuriesCuries0.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.17 Table 1-2CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Batch ModeNuclides Released Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterFission & Activation ProductsY-92 Curies 2.39E-05 5.67E-05 O.OOE+00 O.OOE+00As-76 Curies 1.72E-05 1.72E-05 O.OOE+00 4.09E-05Co-57 Curies O.OOE+O0 O.OOE+O0 3.90E-07 O.OOE+OOCo-58 Curies 5.32E-04 1.19E-04 1.32E-04 1.24E-04Co-60 Curies 4.58E-03 7.23E-04 7.23E-04 3.36E-04Cr-51 Curies 1.13E-03 5.85E-06 1.67E-05 3.99E-05Fe-55 Curies 2.30E-04 2.04E-04 O.OOE+O0 7.46E-05Fe-59 Curies 3.61E-05 O.OOE+O0 O.OOE+O0 O.OOE+O01-131 Curies O.OOE+O0 1.09E-06 6.20E-06 3.53E-051-133 Curies 1.68E-05 8.48E-06 1.08E-05 2.97E-05Mn-54 Curies 2.28E-03 3.13E-04 3.49E-04 2.01E-04Mn-56 Curies 2.40E-04 7.05E-05 7.28E-05 2.29E-04Na-24 Curies 7.26E-04 4.56E-04 5.47E-04 2.84E-04Nb-95 Curies 1.92E-05 9.89E-07 0.00E+00 O.OOE+00Nb-97 Curies 4.42E-04 4.63E-04 4.50E-05 2.27E-05Sr-89 Curies 1.38E-04 7.91E-05 1.10E-04 4.55E-05Sr-90 Curies O.OOE+00 O.OOE+00 O.OOE+00 6.04E-07Sr-91 Curies 3.08E-05 8.06E-06 O.OOE+00 8.32E-05Sr-92 Curies 1.63E-05 1.96E-06 5.52E-07 1.69E-05Y-91M Curies 1.47E-05 3.77E-05 9.30E-06 1.40E-05Zn-65 Curies 4.56E-04 1.08E-04 1.85E-04 3.54E-04Zr-95 Curies 1.10E-05 O.OOE+00 O.OOE+00 O.OOE+00Au-199 Curies O.OOE+00 O.OOE+00 2.21E-06 2.24E-05Ba-140 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.50E-05Ce-141 Curies 7.56E-06 0.00E+00 0.00E+00 6.40E-06Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations. 18 Table 1-2CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid EffluentsUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Batch ModeNuclides ReleasedCs-137La-140Sb-122Sb-124Sb-125Tc-99MZn-69MAg-110MTotal For PeriodUnitCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuries1ST Quarter4.30E-047.96E-063.33E-072.42E-042.29E-051.85E-053.79E-055.85E-059.90E-052.83E-05O.OOE+003.33E-06O.OOE+001.30E-052.71E-056.13E-061.61E-046.16E-060.OOE+000.00E+000.OOE+002.27E-051.56E-050.OOE+002.48E-052.83E-050.00E+000.00E+000.00E+003.62E-051.69E-046.68E-062.27E-032ND Quarter 3RD Quarter 4TH Quarter1. 18E-02 2.85E-03 2.42E-03TritiumH-3Dissolved And Entrained GasesKr-88Xe-133Xe-135Xe-133MXe-135MTotal For PeriodGross Alpha RadioactivityG-AlphaCuries1.84E+011.30E+012.32E+011.86E+00CuriesCuriesCuriesCuriesCuriesCuriesCuries1.25E-062.91E-042.34E-040.00E+000.00E+000.00E+001.80E-043.OOE-040.00E+000.OOE+000.00E+004.65E-051.38E-040.00E+000.00E+00O.OOE+003.94E-055.49E-052.61E-068.02E-055.26E-048.25E-074.80E-044.80E-061.84E-040.00E+001.77E-04O.OOE+00Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.19 Table 1-3AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses to a member of the public due to Liquid ReleasesUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Cumulative Doses Per QuarterOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Lint5.OOE+005.OOE+005.OOE+005.OOE+005.OOE+005.OOE+001.50E+00UnitsmRemmRemmRemmRemmRemmRemmRem1ST Qtr 0/0 ODCM 2ND Qtr 0/o ODCM6.81E-04 1.36E-02 2.16E-04 4.31E-039.88E-04 1.98E-02 1.92E-04 3.85E-033.85E-04 7.71E-03 1.42E-04 2.84E-031.05E-03 2.09E-02 3.44E-04 6.87E-031.60E-04 3.19E-03 7.07E-05 1.41E-035.62E-05 1. 12E-03 3.81E-05 7.62E-047.65E-04 5.10E-02 2.47E-04 1.65E-023RD Qtr 0/o ODCM 4TH Qtr 0/o ODCM3.78E-04 7.56E-03 7.17E-05 1.43E-034.08E-04 8. 16E-03 1.78E-04 3.57E-033.15E-04 6.31E-03 9.37E-05 1.87E-036.72E-04 1.34E-02 1.69E-04 3.39E-031.90E-04 3.79E-03 1.OOE-05 2.OOE-041.32E-04 2.64E-03 4.30E-06 8.61E-055.02E-04 3.35E-02 9.79E-05 6.53E-03Cumulative Doses per YearOrgan ODCM LmtBone 1.OOE+01GI-Uli 1.OOE+01Kidney 1.OOE+01Liver 1.OOE+01Lung 1.OOE+01Thyroid 1.00E+01Total Body 3.OOE+00Units Year to Ending DatemRem 1.35E-03mRem 1.77E-03mRem 9.36E-04mRem 2.23E-03mRem 4.30E-04mRem 2.31E-04mRem 1.61E-03%/o ODCM1.35E-021.77E-029.36E-032.23E-024.30E-032.31E-035.37E-02ReceptorMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultLimitAnn Cum Organ Liq DoseAnn Cum Organ UIq DoseAnn Cum Organ Liq DoseAnn Cum Organ Liq DoseAnn Cum Organ Uq DoseAnn Cum Organ Uq DoseAnn Cum Tot Body Uq Dose20 Table 1-3BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses to a member of the public due to Liquid ReleasesUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Cumulative Doses Per QuarterOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Lmt5.OOE+005.OOE+005.OOE+005.OOE+005.OOE+005.OOE+001.50E+00UnitsmRemmRemmRemmRemmRemmRemmRem1ST Qtr 0/o ODCM 2ND Qtr9.57E-04 1.91E-02 1.72E-042.17E-03 4.34E-02 4.31E-046.08E-04 1.22E-02 1.62E-041.61E-03 3.22E-02 3.34E-042.18E-04 4.36E-03 8.95E-058.93E-05 1.79E-03 7.91E-051.16E-03 7.76E-02 2.55E-04%/ ODCM7.4-4E-038.62E-033.24E-036.69E-031.79E-031.58E-031.70E-023RD Qtr2.76E-042.95E-041.94E-044.51E-047.67E-058.76E-053.09E-04--/% ODCM 4TH Qtr5.52E-03 8.68E-055.89E-03 2.09E-043.87E-03 6.89E-059.02E-03 1.53E-041.53E-03 2.07E-051.75E-03 2.85E-042.06E-02 1.06E-040/6 ODCM1.74E-034.18E-031.38E-033.05E-034.14E-045.71E-037.04E-03Cumulative Doses per YearOrgan ODCM LmtBone 1.OOE+01GI-Lli 1.OQE+O1Kidney 1.OOE+01Liver 1.OOE+01Lung 1.OOE+01Thyroid 1.OOE+01Total Body 3.OOE+00Units Year to Ending DatemRem 1.49E-03mRem 3.10E-03mRem 1.03E-03mRem 2.55E-03mRem 4.05E-04mRem 5.41E-04mRem 1.83E-03%/o ODCM1.49E-023. IOE-021.03E-022.55E-024.05E-035.41E-036.11E-02ReceptorMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultMAX INDIVIDUAL LIQUID / AdultLimitAnn Cum Organ Liq DoseAnn Cum Organ Liq DoseAnn Cum Organ liq DoseAnn Cum Organ Liq DoseAnn Cum Organ Liq DoseAnn Cum Organ Uq DoseAnn Cum Tot Body Uq Dose21 Table 1-4E. I. HATCH NUCLEAR PLANT RADIOACTIVEEFFLUENT RELEASE REPORT- 2013MINIMUM DETECTABLE CONCENTRATIONS -LIQUID SAMPLE ANALYSESSTARTING: 1-Jan-2013 ENDING: 31-Dec-2013The values in this table represent a priori Minimum Detectable Concentrations(MDC) that are typically achieved in laboratory analyses of liquid radwastesamples.RADIONUCLIDE MDC UNITSMn-54 1.97E-08 uCi/mlFe-59 3.94E-08 uCi/mlCo-58 1.59E-08 uCi/mlCo-60 1.72E-08 uCi/mlZn-65 2.92E-08 uCi/mlMo-99 1.20E-07 uCi/mlCs-134 1.75E-08 uCi/mICs-137 1.62E-08 uCi/mICe-141 1.92E-08 uCi/mlCe-144 8.83E-08 uCi/ml1-131 1.43E-08 uCi/mlXe-135 1.03E-08 uCi/mlFe-55 2.34E-08 uCi/mlSr-89 1.44E-08 uCi/mlSr-90 8.50E-09 uCi/mlH-3 6.OOE-07 uCi/ml22 Table 1-5AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents -Batch Release SummaryUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Liquid Releases1. Number of batch releases2. Total time period for Batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch release6. Average stream flow during periodsof release of liquid effluent intoa flowing stream *UnitsMinutesMinutesMinutesMinutes1ST Quarter445.69E+031.65E+021.29E+028.70E+011.70E+042ND Quarter 3RD Quarter 4TH Quarter Year Totals32 119 3 1984.57E+03 1.53E+04 4.02E+02 2.60E+041.70E+02 1.73E+02 1.55E+02 1.73E+021.43E+02 1.29E+02 1.34E+02 1.31E+021.10E+02 2.20E+01 9.60E+01 2.20E+01( CFS )1.39E+041.83E+041.55E+031.27E+04* Data obtained from United States Geological Survey (USGS) website23 Table 1-5BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents -Batch Release SummaryUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Uquid Releases1. Number of batch releases2. Total time period for Batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch release6. Average stream flow during periodsof release of liquid effluent intoa flowing stream *UnitsMinutesMinutesMinutesMinutes1ST Quarter726.92E+031.30E+029.62E+017.70E+011.70E+042ND Quarter 3RD Quarter 4TH Quarter Year Totals49 38 9 1685.48E+03 3.95E+03 9.31E+02 1.73E+041.45E+02 1.25E+02 1.15E+02 1.45E+021.12E+02 1.04E+02 1.03E+02 1.03E+028.20E+01 6.70E+01 7.80E+01 6.70E+01( CFS )1.39E+041.83E+041.55E+031.27E+04* Data obtained from United States Geological Survey (USGS) website24 Table 1-6AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents -Abnormal Release SummaryUnit: 1Starting: l-Jan-2013 Ending: 31-Dec-2013Liquid Releases1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releasesUnits 1ST Quarter0MinutesMinutes(MinutesMinutes(Curies )0.OOE+000.00E+000.00E+000.00E+000.OOE+002ND Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+003RD Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+004TH Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00Year Totals0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+0025 Table 1-65Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents -Abnormal Release SummaryUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Units 1ST Quarter 2ND Quarter 3RD Quarter0 0 0Liquid Releases1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releasesMinutesMinutesMinutesMinutes(Curies )O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.00E+00 0.OOE+0O4TH Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00Year Totals0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+0026 Table 1-6CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents -Abnormal Release SummaryUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Liquid Releases1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releasesUnitsMinutesMinutesMinutesMinutes(Curies )1ST Quarter00.00E+000.OOE+000.OOE+000.OOE+000.OOE+002ND Quarter00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+003RD Quarter00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+004TH Quarter00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Year Totals00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+0027 2.0 Gaseous Effluents2.1 Regulatory RequirementsThe ODCM Specifications presented in this section are for Unit 1 and Unit 2.2.1.1 Dose Rate LimitsThe dose rate due to radioactive materials released in gaseous effluents from thesite to areas at and beyond the SITE BOUNDARY shall be limited to the following:a. For noble gases: Less than or equal to 500 mrems/yr. to the whole bodyand less than or equal to 3000 mrems/yr. to the skin and,b. For lodine-131, Iodine-1 33, tritium and for all radionuclides in particulateform with half-lives greater than 8 days: Less than or equal to 1500mrems/yr. to any organ.2.1.2 Air Doses Due To Noble Gases in Gaseous EffluentsThe air dose due to noble gases released in gaseous effluents, from each unit, toareas at and beyond the SITE BOUNDARY, shall be limited to the following:a. During any calendar quarter: Less than or equal to 5 mrads for gammaradiation and less than or equal to 10 mrads for beta radiation, andb. During any calendar year: Less than or equal to 10 mrads for gammaradiation and less than or equal to 20 mrads for beta radiation.2.1.3 Doses To A Member of the PublicThe dose to a MEMBER OF THE PUBLIC from Iodine-1 31, Iodine-1 33, tritium andall radionuclides in particulate form with half-lives greater than 8 days, in gaseouseffluents released from each unit, to areas at and beyond the SITE BOUNDARY,shall be limited to the following.a. During any calendar quarter: Less than or equal to 7.5 mrems to anyorgan.b. During any calendar year: Less than or equal to 15 mrems to any organ.28 2.2 Measurements and Approximations of Total RadioactivityWaste gas release at Plant Hatch is confined to four paths: main stack (alsocalled the offgas vent), Unit 1 reactor building vent, Unit 2 reactor building vent,and the recombiner building vent. Each of these four paths is continuouslymonitored for gaseous radioactivity.2.2.1 Sample Collection and AnalysisEach of the four gaseous effluent paths is equipped with an integrating-typesample collection device for collecting particulates and iodines. Unless requiredmore frequently under certain circumstances, samples are collected as follows:1. Noble gas samples are collected by grab sampling monthly.2. Tritium samples are collected by grab sampling monthly.3. Radioiodine samples are collected by pulling the sample stream through acharcoal cartridge over a 7-day period.4. Particulates are collected by pulling the sample stream through aparticulate filter over a 7-day period.5. The 7-day particulate filters above are analyzed for gross alpha activity.6. Quarterly composite samples are prepared from the particulate filterscollected over the previous quarter and the samples are analyzed for Sr-89and Sr-90.Sample analysis results and release flow rates from the four release points formthe basis for calculating released quantities of radionuclide-specific radioactivity,the dose rates associated with gaseous releases, and the cumulative doses forthe current quarter and year. This task is normally performed with computerassistance.The noble gas grab sample analysis results are used along with maximumexpected release flow rates from each of the four vents to calculate monitorsetpoints for the gaseous effluent monitors serving the four release points.Calculation of monitor setpoints is described in the ODCM. Typically achievedminimum detectable concentrations for gaseous effluents sample and analysesare reported in Table 2-6.For each release period, released radioactivity, dose rates, and cumulative dosesare calculated. Cumulative dose results are tabulated along with the percent ofthe ODCM limit for each release, for the current quarter and year.29 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative DosesThe methods for determining release quantities of radioactivity, dose rates, andcumulative doses follow:2.2.2.1 Fission and Activation GasesThe released radioactivity is determined using sample analysis results collectedas described above and the average release flow rates over the periodrepresented by the collected sample.Dose rates due to noble gases, radioiodines, tritium, and particulates arecalculated (with computer assistance). The calculated dose rates are compared tothe dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodine, tritium,and particulates. Dose rate calculation methodology is presented in the ODCM.Beta and gamma air doses due to noble gases are calculated for the location inthe unrestricted area with the potential for the highest exposure due to gaseousreleases. Air doses are calculated for each release period and cumulative totalsare kept for each unit for the calendar quarter and year. Cumulative air doses arecompared to the dose limits specified in ODCM 3.1.3. The current percent of theODCM limits are shown on the printout for each release period. Air dosecalculation methodology is presented in the ODCM.2.2.2.2 Radioiodine, Tritium and Particulate ReleasesReleased quantities of radioiodines are determined using the weekly samples andrelease flow rates for the four release points. Radioiodine concentrations aredetermined by gamma spectroscopy.Release quantities of particulates are determined using the weekly (filter) samplesand release flow rates for the four release points. Gamma spectroscopy is usedto quantify concentrations of principal gamma emitters.After each quarter, the particulate filters from each vent are combined, fused, anda strontium separation is performed. Since sample flows and vent flows arealmost constant over each quarterly period the filters from each vent can bedissolved together. Decay corrections are performed back to the middle of thequarterly 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 andused for release dose rate and dose calculations for a Member of the Public.30 Tritium samples are obtained monthly from each vent by passing the samplestream through a cold trap. The grams of water vapor/cubic foot is measuredupstream of the cold trap in order to alleviate the difficulties in determining watervapor collection efficiencies. The tritium samples are analyzed by an independentlaboratory and the results are furnished in uCi/ml of water. The tritiumconcentration in water is converted to the tritium concentration in air and this valueis input into the composite file of the computer and used in release, dose rate, andindividual dose calculations.Dose rates due to radioiodine, tritium and particulates are calculated for ahypothetical child exposed to the inhalation pathway at the location in theunrestricted 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 thedose rates from each release point are compared to the dose rate limits asdescribed in ODCM 3.1.2. Doses due to radioiodine, tritium and particulates arecalculated for the controlling receptor, which is described in the ODCM. Doses toa Member of the Public are calculated for each release period, and cumulativetotals are kept for each unit, for the current calendar quarter and year. Cumulativedoses are compared to the dose limits specified in ODCM 3.1.4. The currentpercent of ODCM limits are shown on the printout for each release period.2.2.2.3 Gross Alpha ReleaseThe gross alpha release is computed each month by counting the particulate filtersfor each week for gross alpha activity in a proportional counter. The four or fiveweeks' numbers are then recorded on a data sheet and the activity is summed atthe end of the month. The summed activity is then divided by the total monthlyvolume to determine the concentration. This concentration is input into thecomposite file of the computer and used for release calculations.2.2.3 Total Error EstimationThe total or maximum error associated with the effluent measurement will includethe cumulative errors resulting from the total process of sampling andmeasurement. Due to the difficulty with assigning error terms for each parameteraffecting the final measurement, detailed statistical evaluation of error is notsuggested. The objective is to obtain an overall estimate of the error associatedwith measurements of radioactive materials released in liquid and gaseouseffluents and solid waste.Estimated errors are associated with counting equipment calibration, countingstatistics, vent-flow rates, vent sample flow rates, non steady release rates,chemical yield factors and sample losses for such items as charcoal cartridges.31 Fission and activation total release was calculated from sample analysis resultsand release point flow rates.Statistical error 60%Counting equipment calibration 10%Vent flow rates 10%Non-steady release rates 20%TOTAL ERROR 65%1-131 releases were calculated from each weekly sample.Statistical error 60%Counting equipment calibration 10%Vent flow rates 10%Vent sample flow rates 10%Non-steady release rates 10%Losses from charcoal cartridges 10%TOTAL ERROR 64%Particulates with half-lives greater than 8 days releases were calculated fromsample analysis results and release point flow rates.Statistical error 60%Counting equipment calibration 10%Vent flow rates 10%Vent sample flow rates 10%Non-steady release rates 10%TOTAL ERROR 63%Total tritium releases were calculated from sample analysis results and releasepoint 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%32 Gross Alpha radioactivity was calculated from sample analysis results and releasepoint 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 DataRegulatory Guide 1.21 Tables 1A, 1B, and 1C are found in this report asTables 2-1A, 2-1B, 2-1C, 2-2A, ,2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data is presentedon a quarterly basis as required by Regulatory Guide 1.21 for all quarters.To complete table 2-1A, 2-1 B, and 2-1C, total release for each of the fourcategories (fission and activation gases, iodines, particulates, and tritium) wasdivided by the number of seconds in the quarter to obtain a release rate inuCi/second for each category for each quarter. However, the percent of theODCM limits are not applicable because we have no curie limits for gaseousreleases. Applicable limits are expressed in terms of dose. Noble gases arelimited 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, andparticulates were calculated as part of the pre-release and post-release permitson individual permits. No limits were exceeded for this reporting period.Gross alpha radioactivity is reported in Table 2-1A, 2-1 B, and 2-1C, as curiesreleased in each quarter.Limits for cumulative beta and gamma air doses due to noble gases are specifiedin ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A and 2-4B,along with percent of ODCM limits.Limits for cumulative doses to a Member of the Public due to radioiodine, tritiumand particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member ofthe Public doses are presented in Table 2-5A and 2-58, along with percent ofODCM limits.33 2.4 Radiological Impact Due to Gaseous ReleasesDose rates due to noble gas release were calculated for the site in accordancewith ODCM 3,1.2. Dose rates due to radioiodine, tritium, and particulates ingaseous releases were calculated in accordance with ODCM 3.1.2.These dose rates were calculated as part of the pre-release and post release onindividual release permits. No limits were exceeded for this reporting period.Cumulative air doses due to noble gas releases were calculated for each unit inaccordance with ODCM 3.1.3. These results are presented inTables 2-4A and 2-4B.Cumulative doses to a Member of the Public due to radioiodine, tritium andparticulates in gaseous releases were calculated for each unit in accordance withODCM 3.1.4. These results are presented in Tables 2-5A and 2-5B.Dose rates and doses were calculated using the methodology presented in theODCM.2.5 Gaseous Effluents -Batch ReleasesThere are no gaseous batch releases from Plant Hatch.2.6 Gaseous Effluents -Abnormal ReleasesThere were no unplanned or uncontrolled gaseous releases during this reportingperiod.34 Table 2-1AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Summation Of All ReleasesUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterA. Fission And Activation Gases1. Total Release Curies 2.50E+00 2.81E-01 1.06E+00 4.55E+002. Average Release rate for period uCi/sec 3.17E-01 3.56E-02 1.34E-01 5.77E-013. Percent of Applicable Limit %* * * *B. Radiolodines1. Total Iodine-131 Curies 9.31E-05 2.22E-05 6.66E-05 1.48E-042. Average Release rate for period uCi/sec 1.18E-05 2.81E-06 8.45E-06 1.88E-053. Percent of Applicable ULmit %* * * *C. Particulates1. Particulates ( Half-Lives > 8 Days ) Curies 1.98E-05 3.30E-05 5.37E-04 3.88E-052. Average Release rate for period uCi/sec 2.51E-06 4.18E-06 6.81E-05 4.915E-063. Percent of Applicable Limit %* * * *D. Tritium1. Total Release Curies 4.44E+00 3.81E+00 5.65E+00 2.21E+012. Average Release rate for period uCi/sec 5.63E-01 4.83E-01 7.16E-01 2.80E+003. Percent of Applicable Limit * * * *E. Gross Alpha1. Total Release Curies O.OOE+00 O.O0E+00 O.OOE+00 O.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.35 Table 2-1BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Summation Of All ReleasesUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Units 1ST Quarter 2ND Quarter 3RD QuarterType of EffluentA. Fission And Activation Gases4TH Quarter1. Total Release Curies 2.50E+00 2.79E-012. Average Release rate for period uCi/sec 3.17E-01 3.54E-023. Percent of Applicable Limit % * *B. Radioiodines1. Total Iodine-131 Curies 1.05E-04 3.20E-052. Average Release rate for period uCi/sec 1.33E-05 4.06E-063. Percent of Applicable Limit % *C. Particulates1. Particulates ( Half-Lives > 8 Days ) Curies 1.62E-05 2.51E-052. Average Release rate for period uCi/sec 2.06E-06 3.19E-063. Percent of Applicable Limit %* *D. Tritium1. Total Release Curies 3.26E+00 4.12E+002. Average Release rate for period uCi/sec 4.13E-01 5.23E-013. Percent of Applicable Umit * *E. Gross Alpha1. Total Release Curies O.OOE+00 O.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.361.06E+001.34E-015.95E-057.54E-063.03E-053.85E-065.54E+007.03E-010.OOE+001.19E+011.5 1E+001 .48E-G41.88E-053.66E-054.645E-062.24E+012.85E+000.OOE+00 Table 2-1CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Summation Of All ReleasesUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-20131ST Quarter 2ND Quarter 3RD Qu;Type of EffluentA. Fission And Activation GasesUnitsarter 4TH Quarter1. Total Release Curies 5.01E+00 5.60E-012. Average Release rate for period uCi/sec 6.35E-01 7.1OE-023. Percent of Applicable Limit %* *B. Radioiodines1. Total Iodine-131 Curies 1.98E-04 5.42E-052. Average Release rate for period uCi/sec 2.51E-05 6.87E-063. Percent of Applicable Limit % * *C. Particulates1. Particulates ( Half-Uves > 8 Days ) Curies 3.60E-05 5.81E-052. Average Release rate for period uCi/sec 4.56E-06 7.37E-063. Percent of Applicable Limit %* *D. Tritium1. Total Release Curies 7.70E+00 7.93E+002. Average Release rate for period uCi/sec 9.76E-O1 1.01E+003. Percent of Applicable Limit * *E. Gross Alpha1. Total Release Curies O.OOE+00 O.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.372.12E+002.69E-011.26E-041.60E-055.67E-047. 19E-051.12E+011.42E+000.00E+000.OOE+001.64E+012.09E+002.97E-043.76E-057.54E-059.561E-064.45E+015.65E+000.OOE+00 Table 2-2AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Elevated Level ReleasesUnit: 1Starting: 1-Jan- 2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedFission GasesUnit1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterAr-41 CuriesKr-85M CuriesXe-133 CuriesXe-135 CuriesTotal For Period Curies4.40E-011.69E-011.30E+005.92E-012.50E+007.60E-051.24E-042.00E-04Iodines1-1311-133Total For PeriodMn-54Co-60Sr-89Sr-90Cs-137Ba-140Ce-1441-131PTotal For PeriodCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuries0.OOE+000.00E+001.13E-011.67E-012.79E-012.00E-053.42E-055.42E-050.00E+000.00E+001.40E-055.86E-092.27E-081.08E-05O.OOE+00O.OOE+002.48E-050.OOE+002.12E-017.86E-016.02E-021.06E+005.20E-056.83E-051.20E-040.OOE+000.OOE+001.71E-054.86E-085.79E-081.04E-050.OOE+000.OOE+002.76E-051.11E+004.11E-012.69E+003.40E-014.55E+001 .26E-041 .O1E-042.27E-041.46E-088.22E-082.08E-056.40E-080.OOE+001.13E-051 .29E-071.83E-073.25E-050.OOE+000.OOE+009.41E-060.OOE+000.OOE+009.89E-060.OOE+000.OOE-i001.93E-05If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 38 Table 2-2AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Elevated Level ReleasesUnit: 1Starting: 1-Jan- 2013 Ending: 31-Dec-2013Continuous Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedTritiumHl-3UnitCuriesCuries3.69E-01O.OOE+0O4.16E-01O.OOE+0O4.43E-010.OOE+007. 19E-010.OOE+00Gross AlphaNo Nudides FoundIf Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 39 Nuclides ReleasedFission GasesNo Nuclides FoundlodinesNo Nuclides FoundParticulatesNo Nudides FoundTritiumNo Nuclides FoundGross AlphaNo Nuclides FoundUnitCuriesCuriesCuriesCuriesCuriesTable 2-2AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Elevated Level ReleasesUnit: 1Starting: 1-Jan- 2013 Ending: 31-Dec-2013Batch Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterO.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 40 Table 2-2BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Elevated Level ReleasesUnit: 2Starting: 1-Jan- 2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedFission GasesUnit1ST Quarter 2ND Quarter3RD Quarter 4TH QuarterNuclides ReleasedFission GasesAr-41 CuriesKr-85M CuriesXe-133 CuriesXe-135 CuriesTotal For Period CuriesIodines1-1311-133Total For PeriodMn-54Co-60Sr-89Sr-90Cs-137Ba-140Ce-144I-131PTotal For PeriodCuriesCuriesCuries4.40E-011.69E-011.30E+005.92E-012.50]E+006.96E-051. 19E-041.88E-040.OOE+000.OOE+005.82E-060.00E+000.OOE+007.76E-060.00 E+000.00E+001.13E-011.67E-012.79E-012.00E-053.42E-055.42E-050.OOE+000.OOE+001.40E-055.86E-092.27E-081.08E-050.OOE+000.OOE+002.48E-050.OOE+002.12E-017.86E-016.02E-021.06E+001.11E+004.11E-012.69E+003.40E-014.S5E+OO5.20E-05 1.26E-046.83E-05 1.01E-041.20E-04 2.27E-04CuriesCuriesCuriesCuriesCuriesCuries0.OOE+000.001E+001.7 1E-054.86E-085.79E-08l.G4E-050.OOE+000.OOE+002.76E-OS1.46E-088.22E-082.08E-056.40E-080.OOE+001.13E-051.29E-071.83E-073.25E-05Curies O.OOE+00Curies O.OOE+00Curies 1.36E-05If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 41 Table 2-21Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Elevated Level ReleasesUnit: 2Starting: 1-Jan- 2013 Ending: 31-Dec- 2013Continuous ModeNuclides ReleasedTritiumH-3UnitCuriesCuries1ST Quarter2.51E-012ND Quarter 3RD Quarter 4TH Quarter4.16E-01O.OOE+004.43E-010.OOE+007.19E-01O.OOE+00Gross AlphaNo Nudides FoundO.OOE+00If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 42 Nuclides ReleasedFission GasesNo Nudides FoundlodinesNo Nudides FoundParticulatesNo Nuclides FoundTritiumNo Nuclides FoundGross AlphaNo Nudides FoundUnitCuriesCuriesCuriesCuriesCuriesTable 2-2BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Elevated Level ReleasesUnit: 2Starting: 1-Jan- 2013 Ending: 31-Dec-2013Batch Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterO.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 43 Table 2-2CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Elevated Level ReleasesUnit: SiteStarting: 1-Jan- 2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedFission GasesNuclides ReleasedFission GasesAr-41Kr-85MXe-133Xe-135Total For PeriodUnitCuriesCuriesCuriesCuriesCuries1ST Quarter 2ND Quarter 3RD Quarter8.79E-013.39E-012.60E+001.18E+005.01E+000.00 E+000.00E+002.26E-013.33E-015.59E-014.OOE-056.85E-051.08E-04Iodines1-131 Curies 1.46E-041-133 Curies 2.42E-04Total For Period Curies 3.88E-040.OOE+004.23E-011.57E+001.20E-012.11E+001.04E-041.37E-042.41 E-040.OOE+000.OOE+003.4 1E-059.72E-081. 16E-072.08E-050.OOE+000.OOE+005.51E-054TH Quarter2.23E+008.21E-015.37E+006.81E-019.10E+002.52E-042.02E-044.54E-042.92E-081.64E-074.15E-051.28E-07O.OOE+002.25E-052.57E-073.67E-076.50E-05ParticulatesMn-54Co-60Sr-89Sr-90Cs-137Ba-140Ce-144I-131PTotal For PeriodCuriesCuriesCuriesCuriesCuriesCuriesCuries0.OOE+000.OOE+001. 52E-050.OOE+000.00E÷001.76E-050.OOE÷000.00E-i000.OOE+002.80E-051. 17E-084.55E-082.15E-050.OOE+00Curies 0.00E+00 0.00E+00Curies 3.29E-05 4.96E-05If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 44 Table 2-2CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Elevated Level ReleasesUnit: SiteStarting: 1-Jan- 2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedTritiumH-3UnitCuriesCuries1ST Quarter6.20E-012ND Quarter 3RD Quarter 4TH Quarter8.32E-01O.OOE+008.85E-010.OOE+001.44E+000.OOE+00Gross AlphaNo Nudides FoundO.OOE+00If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 45 Nuclides ReleasedFission GasesNo Nuclides FoundlodinesNo Nudides FoundParticulatesNo Nuclides FoundTritiumNo Nuclides FoundGross AlphaNo Nudides FoundUnitCuriesCuriesCuriesCuriesCuriesTable 2-2CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Elevated Level ReleasesUnit: SiteStarting: 1-Jan- 2013 Ending: 31-Dec-2013Batch Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterO.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 46 Table 2-3AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Ground Level ReleasesUnit: 1Starting: 1-3an-2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedUnit1ST Quarter2ND Quarter3RD Quarter4TH QuarterFission GasesXe-135CuriesCuries0.OOE+00O.00E+O01.27E-031.27E-032.53E-032.53E_030.OOE+00O.OOE+00Total For Periodlodines1-1311-133Total For PeriodParticulatesMn-54Co-58Co-60Zn-65Sr-89Curies 1.71E-05Curies 1.39E-05Curies 3.10E-05Curies 0.OOE+00Curies 0.00E+00Curies O.OOE+00Curies 0.OOE+00Curies 4.49E-07Curies 4.49E-072.16E-062.27E-064.42E-069.83E-071.07E-061.49E-061.50E-063.12E-068.17E-061.46E-056.18E-062.08E-0S9.90E-051.04E-041.50E-041,52E-044.90E-065.09E-042.24E-052.67E-062.51E-051.57E-061. 17E-061.89E-060.OOE+001.63E-066.27E-06Total For PeriodTritiumH-3Gross AlphaNo Nud ides FoundCuriesCuries4.07E+000.OOE+OO3.39E+000.OOE+005.21E+00O.OOE+002.13E+01O.OOE+00If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 47 Nuclides ReleasedFission GasesNo Nudides FoundlodinesNo Nudides FoundParticulatesNo Nudides FoundTritiumNo Nudides FoundGross AlphaNo Nudides FoundUnitCuriesCuriesCuriesCuriesCuriesTable 2-3AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Ground Level ReleasesUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Batch Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterO.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 48 Table 2-3BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Ground Level ReleasesUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedFission GasesXe- 133Unit1ST Quarter2ND Quarter 3RD Quarter4TH QuarterCuriesCuriesO.OOE+O00.00E+00Total For Periodlodines1-131 Curies 3.56E-051-133 Curies 4.26E-05Total For Period Curies 7.81E-05O.OOE+00O.OOE+001.20E-056.03E-061.81E-053.34E-070.OOE+003.34E-073.71E+00O.OOE+00O.OOE+007.49E-065.75E-061.32E-052.75E-060.OOE+002.75E-065.10E+007.34E+007.34E+002.23E-052.31E-054.53E-O54.14E-06O.OOE+004.14E-062.17E+01PartffiulatesSr-89I-131PCuries 1.86E-06Curies 7.89E-07Curies 2.65E-06Total For PeriodTritiumGross AlphaCuriesCuries3.01E+00O.OOE+O0No Nudides Found0.OOE+000.OOE+000.00E+00If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 49 Table 2-3BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Ground Level ReleasesUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Batch ModeNuclides ReleasedFission GasesNo Nuclides FoundIodinesNo Nuclides FoundParticulatesNo Nudides FoundUnitCuriesCuriesCuriesCuriesCuries1ST Quarter2ND Quarter 3RD Quarter 4TH Quarter0.OOE+000.OOE+000.OOE+000.OOE+000.00E+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00TritiumNo Nuclides FoundGross AlphaNo Nuclides FoundIf Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 50 Table 2-3CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Ground Level ReleasesUnit: SiteStarting: I-Jan-2013 Ending: 31-Dec-2013Continuous ModeNuclides ReleasedFission GasesXe-133Xe-135Total For PeriodUnit1ST Quarter2ND Quarter 3RD Quarter4TH QuarterCuriesCuriesCuries0.00E+000.OOE+00O.OOE+O00.OOE+001.27E-031.27E-030.OOE+002.53E-032.53E-037.34E+000.OOE+007.34E+00lodines1-1311-133Total For PeriodParticulatesMn-54Co-58Co-60Zn-65Sr-89I-131PTotal For PeriodCuries 5.26E-05Curies 5.65E-05Curies 1.09E-04Curies O.OOE+00Curies O.OOE+00Curies O.OOE+00Curies O.OOE+00Curies 2.31E-06Curies 7.89E-07Curies 3.10E-061.42E-058.30E-062.25E-059.83E-071.07E-061.49E-061.50E-063.45E-060.OOE+008.50E-062.2 1E-051. 19E-053.41E-059.90E-051.04E-041.50E-041.52E-047.64E-060.OOE+00S.12E-044.47E-052.57E-057.04E-051.57E-061. 17E-061.89E-060.OOE+005.77E-060.OOE+001.04E-OSTritiumH-3Curies7.08E+007.10E+001.03E+014.31E+01If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 51 Table 2-3CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Ground Level ReleasesUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Continuous Mode1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedGross AlphaNo Nuclides FoundUnitCuriesO.OOE+O0O.OOE+00O.OOE+00O.OOE+00If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 52 Table 2-3CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Ground Level ReleasesUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Batch ModeNuclides ReleasedFission GasesNo Nudides FoundlodinesNo Nudides FoundParticulatesNo Nudides FoundUnitCuriesCuriesCuriesCuriesCuries1ST QuarterO.OOE+O0O.OOE+O0O.OOE+O0O.OOE+00O.OOE+O0O.OOE+000.OOE+00O.OOE+0O0.OOE+000.OOE+0OO.OOE+O00.OOE+0O0.OOE+0O0.OOE+OO0.OOE+0OO.OOE+00O.OOE+00O.OOE+O0O.OOE+00O.OOE+002ND Quarter3RD Quarter 4TH QuarterTritiumNo Nuclides FoundGross AlphaNo Nudides FoundIf Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations. 53 Table 2-4AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Air Doses Due to Gaseous ReleasesUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Cumulative Doses Per QuarterType of Radiation ODCM LmntUnitsGamma AirBeta Air5.OOE+00 mRad1.OOE+01 mRad1ST Qtr1.45E-059.52E-06% ODCM2.90E-049.52E-052ND Qtr1.45E-061.41E-06% ODCM2.90E-051.41E-053RD Qtr % ODCM2.50E-06 5.OOE-053.51E-06 3.51E-054TH Qtr3.11E-051.68E-050/o ODCM6.22E-041.68E-04Cumulative Doses Per YearType of Radiation ODCM LmtGamma Air 1.O0E+01Beta Air 2.OOE+01UnitsmRadmRadYear to End Date %/o ODCM4.95E-05 4.95E-043.12E-05 1.56E-04ReceptorLimitSITE BOUNDARY / ChildMAX IND. AIRBORNE / ChildAnn Cum Gamma AirdoseAnn Cum Beta Airdose54 Table 2-4BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Air Doses Due to Gaseous ReleasesUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Cumulative Doses Per QuarterType of Radiation ODCM LmtUnitsGamma AirBeta Air5.OOE+00 mRad1.OOE+01 mRad1ST Qtr1 .45E-055.98E-06O/o ODCM2.90E-045.98E-052ND Qtr8.01E-076.86E-070/o ODCM1 .60E-056.86E-063RD Qtr 0/o ODCM1.21E-06 2.42E-051.81E-06 1.81E-054TH Qtr %/o ODCM7.19E-04 1.44E-022.06E-03 2.06E-02Cumulative Doses Per YearType of Radiation ODCM LmtGamma Air 1.OOE+01Beta Air 2.OOE+01Units Year to End Date % ODCM ReceptormRad 7.35E-04 7.35E-03 SITE BOUNmRad 2.06E-03 1.03E-02 SITE BOUNLimitDARY / ChildDARY / ChildAnn Cum Gamma AirdoseAnn Cum Beta Airdose55 Table 2-5AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous ReleasesUnit: 1Starting: 1-Jan-2013 Ending: 31-Dec-2013Cumulative Doses Per QuarterOrgan ODCM Lmt UnitsBone 7.50E+00 mRemGI-Ui 7.50E+00 mRemKidney 7.50E+00 mRemLiver 7.50E+00 mRemLung 7.50E+00 mRemThyroid 7.50E+00 mRemTotal Body 7.50E+00 mRemCumulative Doses per Year1ST Qtr2.08E-052.11E-032.11E-032.11E-032.11E-032.54E-032.11E-03%0/aOCM2.78E-042.82E-022.82E-022.82E-022.81E-023.38E-022.82 E-022ND Qtr6.42E-051.77E-031.77E-031.77E-031.77E-031.85E-031.77E-03% ODCM8.56E-042.37E-022.36E-022.36E-022.36E-022.46E-022.37E-023RD Qtr 0/o ODCM1.09E-03 1.46E-023.81E-03 5.09E-023.74E-03 4.99E-023.81E-03 5.08E-023.83 E-03 5.11E-024.01E-03 5.35E-023.80E-03 5.06E-024TH Qtr6.67E-051.11E-021.11E-021.11E-021.11E-021.17E-021.1 1E-020/o ODCM8.90E-041.48E-011.48E-011.48E-011.48E-011.56E-011.48E-01OrganBoneGI-UiKidneyLiverLungThyroidTotal BodyODcM Lint1.500E+011.500E+011.500E+01Units Year to Ending Date % ODCMmRem 1.246E-03 8.305E-03mRem 1.878E-02 1.252E-01mRem 1.870E-02 1.247E-01ReceptorMAX IND. AIRBORNE / ChildMAX IND. AIRBORNE / ChildMAX IND. AIRBORNE ChildLimitAnn Cum lod/Part AirdoseAnn Cum Iod/Part AirdoseAnn Cum Iod/Part Airdose1.500E+01 mRem1.500E+01 mRem1.500E+01 mRem1.500E+01 mRem1.877E-021.879E-022.007E-021.876E-021.251E-01 MAX IND. AIRBORNE Child1.252E-01 MAX IND. AIRBORNE Child1.338E-01 MAX IND. AIRBORNE Child1.251E-01 MAX IND. AIRBORNE ChildAnn Cum Iod/Part AirdoseAnn Cum lod/Part AirdoseAnn Cum Iod/Part AirdoseAnn Cum Iod/Part Airdose56 Table 2-5BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous ReleasesUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Cumulative Doses Per QuarterOrgan ODCM Lmt UnitsBone 7.50E+00 mRemGI-Lli 7.50E+00 mRemKidney 7.50E+00 mRemLiver 7.50E+00 mRemLung 7.50E+00 mRemThyroid 7.50E+00 mRemTotal Body 7.50E+00 mRemCumulative Doses per Year1ST Qtr3.04E-051.56E-031.56E-031.56E-031.56E-032.27E-031-56E-03%/ ODCM4.05E-042.08E-022.08E-022.08E-022.08E-023.02E-022.08E-022ND Qtr2.65E-051.92E-031.92E-031.92E-031.92E-032.15E-031.92E-03%/ ODCM2.57E-022.57E-022.57E-022.56E-022.87E-022,57E-023RD Qtr %/ ODCM5.80E-05 7.73E-G42.65E-03 3.53E-022.65E-03 3.53E-022.65E-03 3.53E-022.65E-03 3.53E-022.87E-03 3.83E-022.65E-03 3.53E-024TH Qtr8.13E-051.13E-021.13E-021.13E-021.13E-021.19E-021.13E-020/o ODCM1.07E-031.50E-011.50E-011.50E-011.50E-011.58E-011,50E-01OrganBoneGI-UiKidneyLiverLungThyroidTotal BodyODCM Lmt1.500E+011.500E+01Units Year to Ending DatemRem 1.949E-04mRem 1.739E-020/o ODCM1.299E-031.160E-01ReceptorMAX IND. AIRBORNE / ChildMAX IND. AIRBORNE / Child1.500E+01 mRem1.500E+01 mRem1.500E+01 mRem1.500E+01 mRem1.500E+01 mRem1.739E-021.739E-021.739E-021.9 16E-021.739E-021.160E-01 MAX IND. AIRBORNE / Child1.159E-01 MAX IND. AIRBORNE / Child1.159E-01 MAX IND. AIRBORNE / Child1.277E-01 MAX IND. AIRBORNE / Child1.160E-01 MAX IND. AIRBORNE / ChildLimitAnn Cum Iod/Part AirdoseAnn Cum Iod/Part AirdoseAnn Cum lod/Part AirdoseAnn Cum Iod/Part AirdoseAnn Cum Iod/Part AirdoseAnn Cum Iod/Part AirdoseAnn Cum Iod/Part Airdose57 TABLE 2-6E. I. HATCH NUCLEAR PLANT RADIOACTIVEEFFLUENT RELEASE REPORT -2013MINIMUM DETECTABLE CONCENTRATIONS -GASEOUS SAMPLE ANALYSESSTARTING: 1-Jan-2013 ENDING: 31-Dec-2013The values in this table represent a priori Minimum Detectable Concentrationlaboratory analyses of gaseous radwaste samples.(MDC) that are typically achieved inRADIONUCLIDEKr-87Kr-88Xe-1 33Xe-1 33mXe-1 35Xe-1381-1311-133Mn-54Fe-59Co-58Co-60Zn-65Mo-99Cs-1 34Cs-137Ce-141Ce-144Sr-89Sr-90H-3MDC2.94E-083.22E-082.30E-087.30E-088.73E-091.99E-071.34E-13*1.53E-1 3*1.62E-1 3*3.42E-1 3*1.30E-13*1.54E-1 3*2.54E-1 3*9.61 E-1 3*1.42E-1 3*1.28E-13*1.26E-13*5.64E-13*1.10E-166.70E-164.OOE-07UNITSuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/ccuCi/cc* Based on an estimated sample quantity of 4.078E+07 cc's.58 Table 2-7AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Batch Release SummaryUnit: 1Starting: 1-.Jan-2013 Ending: 31-Dec-2013Gaseous Releases1. Number of batch releases2. Total time period for batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch releaseUnits 1ST Quarter0MinutesMinutesMinutesMinutesO.OOE+00O.OOE+00O.OOE+00O.OOE+002ND Quarter 3RD Quarter0 0O.OOE+00 O.OOE+00O.OOE+00 O.OOE+00O.OOE+00 0.OOE+00O.OOE+00 O.OOE+004TH Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00Year Totals0O.OOE+00O.OOE+00O.OOE+00O.OOE+0059 Table 2-7BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Batch Release SummaryUnit: 2Starting: 1-Jan-2013 Ending: 31-Dec-2013Gaseous Releases1. Number of batch releases2. Total time period for batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch releaseUnits 1ST Quarter0MinutesMinutesMinutesMinutes))))0.OOE+000.OOE+000.OOE+000.OOE+002ND Quarter 3RD Quarter0 00.OOE+00 0.00E+000.00E+00 0.00E+00O.OOE+O0 O.OOE+00O.OOE+00 O.OOE+O04TH Quarter00.OOE+000.OOE+000.OOE+000.OOE+00Year Totals00.OOE+000.OOE+000.OOE+000.OOE+0060 Table 2-8AHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Abnormal Release SummaryUnit: 1Starting: 1-Jan-2013Ending: 31-Dec-2013Gaseous Releases1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A ReleaseS. Minimum Time For A Release6. Total activity for all releasesUnits 1ST Quarter02ND Quarter 3RD Quarter4TH QuarterYear TotalsMinutesMinutesMinutesMinutes( Curies )0.OOE+000.OOE+000.OOE+000.OOE+000.00 E+0000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+0000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+0061 Table 2-8BHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Gaseous Effluents -Abnormal Release SummaryUnit: 2Starting: 1-Jan-2013Ending: 31-Dec-2013Gaseous Releases1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releasesUnits 1ST Quarter0MinutesMinutesMinutesMinutes( Curies )0.00E+000.00E+000.00E+000.00E+000.00E+002ND Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+003RD Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+000.OOE+004TH Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00Year Totals0O.OOE+00O.OOF+00O.OOE+00O.OOE+00O.OOE+0062 Table 2-8CHatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents -Abnormal Release SummaryUnit: SiteStarting: 1-Jan-2013Ending: 31-Dec-2013Gaseous Releases1. Number of Releases2. Total Time For All Releases3. Maximum lime For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releasesUnits(Minutes( MinutesMinutesMinutes )(Curies )1ST Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+O0O.OOE+002ND Quarter0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+003RD Quarter0O.OOE+00O.OOE+00O.OOE+000.OOE+00O.OOE+004TH Quarter0O.OOE+00O.OOE+00O.OOE+000.OOE+00O.OOE+00Year Totals0O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+0063 3.0 Solid Waste3.1 Regulatory RequirementsThe Process Control Program (PCP) and the ODCM requirements presented inthis section are for Unit 1 and Unit 2 and are stated in part.3.1.1 Solid Radioactive Waste SystemPCP Section A.3.1 Solid Radioactive Waste System control states:The solid radwaste system shall be used in accordance with the PROCESSCONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastesand for the SOLIDIFICATION and packaging of other radioactive wastes, asrequired, to ensure that they meet requirements of 10 CFR Parts 20 and 71, priorto shipment of radioactive wastes from the site.3.1.2 Reporting RequirementsTechnical Specification 5.6.3 requires in part:The Radioactive Effluent Release Report covering the operation of the unit shallbe submitted in accordance with 10 CFR 50.36a. The report shall include asummary of the quantities of radioactive liquid and gaseous effluents and solidwaste released from the unit. The material provided shall be consistent with theobjectives outlined in the ODCM and the Process Control Program and inconformance 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 TechnicalSpecification 5.6.3, shall include a summary of the quantities of solid radwastereleased from the units as outlined in Regulatory Guide 1.21, "Measuring,Evaluating, and Reporting Radioactivity in Solid Wastes and Releases ofRadioactive Materials in Liquid and Gaseous Effluents from Light-Water-CooledNuclear Power Plants," Revision 1, June 1974, with data summarized on a 6month basis following the format of Appendix B thereof.64 For each type of solid radwaste shipped offsite during the report period, the reportshall include the following information:a. Container volume.b. Total curie quantity (specify whether determined by measurement orestimate).c. -Principal radionuclides (specify whether determined bymeasurement or estimate).d. Type of waste (such as spent resin, compacted dry waste,evaporator bottoms).e. Type of container (such as LSA, type A, type B, large quantity).f. Solidification agent (such as cement).Major changes to the solid radioactive waste treatment system shall be reported tothe Nuclear Regulatory Commission in the Radioactive Effluent Release Reportfor the period in which the evaluation was reviewed and accepted by the PRB.3.2 Solid Waste DataRegulatory Guide 1.21, Table 3 is found in this report as Table 3-1.65 TABLE 3-1E. I. HATCH NUCLEAR PLANT RADIOACTIVEEFFLUENT RELEASE REPORT- 2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTSUNIT 1 AND 2STARTING: 1-Jan-2013ENDING: 30-Jun-2013A Qr-I Irn 1AIA4ZTP QWIDD~flfl r)PITI= PrP RI PIAI (~p ipQ l~CVA [K.IM tirrorfintorlfiiaI1. Type of waste UNIT 6 month Est. Totalperiod ERROR %a. Spent resins, filter sludges, evaporator m_ 4.68E+01bottoms, etc. Ci 3.18E+01 1.T0 E 01b. Dry compressible waste, contaminated equip. m_ 8.80E+02etc. Ci 5.87E+00 2.00 E 01c. Irradiated components, control rods, m_Cid. Control Rod Drive Filters mCie. Other (describe) _Equip. etc. Ci2. Estimate of major nuclide composition (by type of waste)ISOTOPE PERCENT CURIESa.Fe-55 22.9 7.28E+00Co-60 44.9 1.43E+01Zn-65 5.8 1.84E+00Mn-54 9.7 3.08E+00Cs-137 5.3 1.68E+00Cr-51 1.3 4.26E-01Other 10.0 3.18E+00b.Fe-55 62.8 3.69E+00Co-60 15.6 9.15E-01Mn-54 4.59 2.70E-01Zn-65 2.13 1.25E-01Other 14.9 8.76E-01C.d.e.3. Solid Waste DispositionNumber of Shipments Mode of TransportationAll waste sent to processors N/AB. IRRADIATED FUEL SHIPMENTS (Disposition)Number of Shipments Mode of Transportation0 N/ADestinationN/ADestinationN/A66 TABLE 3-1E. I. HATCH NUCLEAR PLANT RADIOACTIVEEFFLUENT RELEASE REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTSUNIT 1 AND 2STARTING: 1-Jul-2013 ENDING: 31-Dec-2013A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)1. Type of waste UNIT 6 month Est. Totalperiod ERROR %a. Spent resins, filter sludges, evaporator m_ 3.89E+01bottoms, etc. Ci 2.86E+02 1.00 E 01b. Dry compressible waste, contaminated equip. m3 2.28E+02etc. Ci 1.41E+00 2.00 E 01c. Irradiated components, control rods, m_Cid. Control Rod Drive Filters m_Cie. Other (describe) mEquip. etc. Ci2. Estimate of major nuclide composition (by type of waste)ISOTOPE PERCENT CURIESa.Fe-55 20.5 5.85E+01Co-60 39.5 1.13E+02Zn-65 9.4 2.69E+01Mn-54 22.6 6.49E+01Cs-137 0.8 2.27E+00Cr-51 1.3 3.56E+00Other 5.9 1.69E+01b.Fe-55 62.8 8.86E-01Co-60 15.6 2.20E-01Mn-54 4.59 6.48E-02Zn-65 2.13 3.00E-02Other 14.9 2.10E-01C.d.e.3. Solid Waste DispositionNumber of Shipments Mode of TransportationAll waste sent to processors N/AB. IRRADIATED FUEL SHIPMENTS (Disposition)Number of Shipments Mode of Transportation0 N/ADestinationN/ADestinationN/A67 TABLE 3-1E. I. HATCH NUCLEAR PLANT RADIOACTIVEEFFLUENT RELEASE REPORT- 2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTSUNIT I AND 2STARTING: 1-Jan-2013ENDING: 30-Jun-2013TYPE CURIE QUANT PRINCIPAL BURIAL CONT NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATIONOF rrYi DET NUCLIDES/ AINER CONTAINERS EACH CONTAINER AGENTWASTE ERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINERCUBIC FEET(FT 3)Dewatered 31.8 Zn-65,Fe-55,Co-60 Carbon 9 195 LSA N/AResins Mn-54, Cr-51 Steel 14-210**STCLiners Cask/8-120(B)Shipping CaskDry 5.87 Fe-55,Co-60,Mn-54 B-25 55 95/ **STC N/AActive Waste Zn-65 Boxes/High See Note 2080 (B-25)14-210HIntegrity Cask/SealandsContainer* Note: The actual size and number of the containers may vary from the recorded values due to the use of differentcontainers by waste processors.** STC-Strong Tight ContainerTABLE 3-1E. I. HATCH NUCLEAR PLANT RADIOACTIVEEFFLUENT RELEASE REPORT- 2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTSUNIT 1 AND 2~TARTIN~P 1-JUL-2O1!~FNDINt: 31-DFC-2O1~TYPE CURIE QUANT PRINCIPAL BURIAL CONT NUMBER OF VOLUME OF TYPE SHIPMENT/ SOLIDIFICATIONOF rTY/ DET NUCLIDES/ AINER CONTAINERS EACH CONTAINER AGENTWASTE ERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINERCUBIC FEETIFT 3)Dewatered 285.8 Zn-65,Fe-55,Co-60 Carbon 8 195 14-210 DOT 7A N/AResins Mn-54 Steel Liners TYPE A CASK/(external)14-210 **STCDry 1.41 Fe-55,CO-60,Mn-54 B-25 14 90/ N/A2080 LSA ShipmentActive Waste Zn-65 BoxeslSea See NoteGeneral DesignLandBoxes (B-25)Containers* Note: The actual size and number of the containers mayvary from the recorded values due to the use of many differentcontainers bywaste processors for final disposal. All Plant Hatch Waste is sent to processors for processing and disposal.STC-Strong Tight Container68 4.0 Doses to Members of the Public Inside the Site Boundary4.1 Regulatory RequirementsODCM 7.2.2.3 states in part that the Radioactive Effluent Release Report shallalso include an assessment of the radiation doses from radioactive liquid andgaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside theSITE BOUNDARY during the report period; this assessment must be performed inaccordance with the ODCM.4.2 Demonstration of ComplianceThe locations of concern within the site boundary are the Roadside Park, theCamping Area, the Recreation Area, and the Visitors Center. Listed inTable 4-1 are: The distance and direction from a point midway between thecenter of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors forany releases from the Main Stack (elevated) and from the reactor building(ground level); and the estimated maximum occupancy factor for an individual andthe assumed age group of this individual.The source term is not listed in Table 4-1 .The source term is listed inTables 2-2A and 2-2B, for the elevated releases. Similarly the source term islisted in Tables 2-3A and 2-3B for the ground level releases.The maximum doses in units of mrem accumulated by an individual MEMBER OFTHE PUBLIC due to their activities inside the site boundary during the reportingperiod are presented in Table 4-1.69 Table 4-1Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses to a Member of the Public Due to Activities Inside the Site BoundaryUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Location Name:Distance (kilometers):Sector:Occupancy Factor:Age Group:Elevated ReleaseElevated ReleaseGround Level ReleaseGround Level ReleaseROADSIDE PARK1.18E+00WNW2.28E-04ChildNoble GasParticulate and RadioiodineNoble GasParticulate and RadioiodineX/Q (secWm3):X/Q (sec/m3):X/Q (sec/m3):X/Q (sec/m3):2.42E-082.37E-087.83E-067.OOE-06D/Q (m-2): 1.29E-09D/Q (m-2): 2.01E-08BoneLiverTotal BodyThyroidKidneyLungGI-UliSkinUnitsmRemmRemmRemmRemmRemm RemmRemmRem1ST Quarter4.34E-124.04E-094.04E-094.59E-094.04E-094.04E-094.04E-092.23E-122ND Quarter5.29E-114.10E-094. 1OE-094.24E-094.10E-094.11E-094.10E-096.04E-113RD Quarter5. l0E-091. lE-081. lE-081.12E-081.10E-081.17E-081.10E-085.99E-094TH Quarter6.82E-112.46E-082.46E-082.50E-082.46E-082.46E-082.46E-087.65E-11Year5.23E-094.38E-084.37E-084.51E-084.37E-084.45E-084.37E-086.13E-0970 Table 4-1Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses to a Member of the Public Due to Activities Inside the Site BoundaryUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Location Name:Distance (kilometers):Sector:Occupancy Factor:Age Group:Elevated ReleaseElevated ReleaseGround Level ReleaseGround Level ReleaseCAMPING AREA1.27E+00WNW5.48E-03ChildNoble GasParticulate and RadioiodineNoble GasParticulate and RadioiodineX/Q (sec/m3): 2.38E-08X/Q (sec/m3): 2.33E-08X/Q (sec/m3): 7.03E-06X/Q (sec/m3): 6.27E-06D/Q (m-2): 2.01E-08D/Q (m-2): 1.80E-08BoneLiverTotal BodyThyroidKidneyLungGI-UliSkinUnitsm Remm Remm RemmRemmRemmRemmRemmRem1ST Quarter2.07E-108.71E-088.71E-089.89E-088.71E-088.71E-088.70E-081.86E-102ND Quarter1.20E-098.84E-088.84E-089.12E-088.84E-088.86E-088.84E-081.37E-093RD Quarter1.10E-072.37E-072.37E-072.41E-072.37E-072.53E-072.37E-071.29E-074TH Quarter1.76E-095.30E-075.30E-075.40E-075.30E-075.3 1E-075.30E-072.OOE-09Year1.13E-079.43E-079.42E-079.71E-079.42E-079.59E-079.42E-071.33E-0771 Table 4-1Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses to a Member of the Public Due to Activities Inside the Site BoundaryUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Location Name:Distance (kilometers):Sector:Occupancy Factor:Age Group:Elevated ReleaseElevated ReleaseGround Level ReleaseGround Level ReleaseRECREATION AREA1.03E+00SSE2.37E-02ChildNoble GasParticulate and RadioiodineNoble GasParticulate and RadioiodineX/Q (sec/m3): 3.30E-08X/Q (sec/m3): 3.21E-08X/Q (sec/m3): 6.42E-06X/Q (sec/m3): 5.73E-06D/Q (m-2): 1.56E-09D/Q (m-2): 2.36E-08BoneLiverTotal BodyThyroidKidneyLungGI-UiSkinUnitsmRemm Remm Remm RemmRemmRemm Remm Rem1ST Quarter4.40E-103.44E-073.44E-073.91E-073.44E-073.44E-073.44E-072.74E-102ND Quarter6.40E-093.51E-073.51E-073.62E-073.51E-073.52E-073.51E-077.37E-093RD Quarter6.23E-071.12E-061.12E-061. 14E-061.12E-061.19E-061. 12E-067.31E-074TH Quarter8.21E-092.10E-062.10E-062.13E-062.10E-062.10E-062.10E-069.34E-09Year6.38E-073.92E-063.92E-064.03E-063.92E-063.98E-063.92E-067.48E-0772 Table 4-1Hatch Nuclear PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Doses to a Member of the Public Due to Activities Inside the Site BoundaryUnit: SiteStarting: 1-Jan-2013 Ending: 31-Dec-2013Location Name:Distance (kilometers):Sector:Occupancy Factor:Age Group:Elevated ReleaseElevated ReleaseGround Level ReleaseGround Level ReleaseVISITORS CENTER6.94E-01WSW4.57E-04ChildNoble GasParticulate and RadioiodineNoble GasParticulate and RadioiodineX/Q (sec/m3): 5.OOE-08X/Q (sec/m3): 4.97E-08X/Q (sec/m3): 1.87E-05X/Q (sec/m3): 1.72E-05D/Q (m-2): 2.26E-09D/Q (m-2): 5.47E-08BoneLiverTotal BodyThyroidKidneyLungGI-UliSkinUnitsmRemmRemmRemmRemmRemmRemmRemmRem1ST Quarter2.17E-111.99E-081.99E-082.26E-081.99E-081.99E-081.99E-081.14E-112ND Quarter2.87E-102.02E-082.02E-082.09E-082.02E-082.03E-082.02E-083.29E-103RD Quarter2.78E-085.68E-085.68E-085.78E-085.68E-086.05E-085.68E-083.27E-084TH Quarter3.69E-101.21E-071.21E-071.23E-071.21E-071.21E-071.21E-074.16E-10Year2.85E-082.18E-072.18E-072.25E-072.18E-072.22E-072.18E-073.34E-0873 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190)5.1 Regulatory RequirementsThe annual (calendar year) dose or dose commitment to any MEMBER OF THEPUBLIC due to releases of radioactivity and to radiation from uranium fuel cyclesources shall be limited to less than or equal to 25 mrems to the whole body or toany organ, except the thyroid, which shall be limited to less than or equal to75 mrems.5.2 Demonstration of ComplianceNo 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 inaccordance with the requirements of ODCM Section 5.1.3.74 6.0 Meteorological DataThe Radioactive Effluent Release Report, to be submitted by May 1 of each year,shall include an annual summary of hourly meteorological data collected over theprevious year. This annual summary may be either in the form of an hour-by-hourlisting of wind speed, wind direction, atmospheric stability, and precipitation (ifmeasured), on magnetic tape, or, in the form of joint frequency distributions ofwind speed, wind direction and atmospheric stability.In lieu of submission with the Radioactive Effluent Release Report, the licenseehas retained this summary of required meteorological data on site, in a file. It willbe provided to the NRC upon request.75 7.0 Program Deviations7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation7.1.1 Regulatory RequirementsODCM, Chapter 7, Section 7.2.2.6.2 states that the Radioactive EffluentRelease Report shall include deviations from the liquid and gaseous effluentmonitoring instrumentation operability requirements included in Sections 2.1.1and 3.1.1, respectively.7.1.2 Description of DeviationsThere was one deviation from the liquid and gaseous effluent monitoringinstrumentation operability requirements during this reporting period.Radioactive Liquid Effluent Monitoring Instrumentation channels were non-functional for >30 days. The unit two LRW instrumentation was declared OOS dueto the deferral of instrument calibration. There were no discharges performed fromthe unit for several months thus preventing instrument calibration. Theinstrumentation was OOS prior to 1/1/13 until 3/22/13 at which time it wascalibrated during discharge. (RAS 2-12-128)7.2 Tanks Exceeding Curie Content Limits7.2.1 Regulatory RequirementsODCM 7.2.2.6 states in part that the report shall include notifications ifthe contents within any outside temporary tank, for liquids, exceed thelimit of Technical Specification 5.5.8.b.7.2.2 Description of DeviationsThere were no outside temporary tanks, for liquids, that exceeded the limit ofTechnical Specification 5.5.8.b during this reporting period.76 7.3 Effluent Sample Analysis Exceeding Minimum Detectable Concentration(MDC)7.3.1 Regulatory RequirementsODCM 7.2.2.6 states in part that deviations from MDC(s) required in Table3-3 shall be included in the Radioactive Effluent Release Report.7.3.2 Description of DeviationThere were no deviations from MDC(s) required in Table 3-3 during this reportingperiod.8.0 Changes to the Plant Hatch Offsite Dose Calculation Manual (ODCM)8.1 Regulatory RequirementsPursuant to Technical Specification 5.5.1 and ODCM Section 7.2.2.5, licenseeinitiated changes shall be submitted to the NRC in the form of a complete, legiblecopy of the entire ODCM as part of or concurrent with the Radioactive EffluentRelease Report for the period of the report in which any change in the ODCM wasmade. Each change shall be identified by markings in the margin of the affectedpages, clearly indicating the area of the page that was changed, and shall indicatethe date (i.e., month and year) the change was implemented.8.2 Description of ChangesThere were two changes to the Hatch ODCM in 2013.1) Added Reference to Federal Guidance Report (FGR) 11, "Limiting Values ofIntake and Air Concentration and Dose Conversion Factors for RadionuclideInhalation, Submersion, and Ingestion," 1988.2) Section 10.2 updated definition of DOSE EQUIVALENT 1-131 to match thatin the Technical Specifications, Section1.1DOSE EQUIVALENT 1-131 shall be that concentration of 1-131EQUIVALENT (microcuries/gram) that alone would produce the sameCommittted 1-131 Effective Dose Equivalent as the quantity and isotopicmixture of 1-131, 1-132,1-133, 1-134, and 1-135 actually present. The doseconversion factors used for this calculation shall be those listed in FederalGuidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and AirConcentration and Dose Conversion Factors for Inhalation, Submersion,and Ingestion," 1988.77 9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems9.1 Regulatory RequirementsThe Radioactive Effluent Release Report shall include .... any major change toliquid, gaseous, or solid radwaste treatment systems pursuant to ODCMChapter 7, Section 7.2.2.7.9.2 Description of Major ChangesGaseous Radwaste SystemThere were no major changes to the gaseous radwaste system during thisreporting period.Solid Radwaste SystemThere were no major changes to the solid radwaste system during this reportingperiod.Liquid Radwaste SystemThere were no major changes to the liquid radwaste treatment system duringthis reporting period.78 SOUTHERN COMPANYE. I. HATCH NUCLEAR PLANTUNITS NO. 1 & 2ANNUAL REPORTJANUARY 1, 2013 -DECEMBER 31, 2013APPENDIX A79 Hatch Nuclear PlantAppendix ACARBON-14Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half-life. Nuclearweapons testing in the 1950s and 1960s significantly increased the amount of C-14 in theatmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal comparedto what has been distributed in the environment due to weapons testing and what is producedby natural cosmic ray interactions.As nuclear plants have improved gaseous waste processing systems and improved fuelperformance, the percentages of "principal radionuclides" in gaseous effluents have changed,and C-14 has become a larger percentage. "Principal radionuclides" are determined based onpublic dose contribution or the amount of activity discharged compared to other radionuclides ofthe 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 Effluentsand Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reportingC-14 as appropriate. In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclearpower plants will report C-14 amounts released and resulting doses to the maximally exposedmember of the public.Because C-14 is considered a hard-to-detect radionuclide which must be chemically separatedfrom the effluent stream before it can be measured, RG 1.21 provides the option of calculatingthe 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 inTechnical Report 1021106 (December 2010), "Estimation of Carbon-14 in Nuclear Power PlantGaseous Effluents." Evaluation of C-14 in radioactive liquid effluents is not required becausethe 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 be14.16 Curies (per unit). Approximately 95% of the C-14 released is in the form of 14CO2 and isincorporated into plants through photosynthesis. Ingestion dose results from this pathway. Theremaining 5% is estimated to be organic. Both the organic and inorganic forms of C-14contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is thehighest organ dose. Using the dose calculation methodology from the Hatch ODCM, theresulting bone dose to a child located at the controlling receptor location would be 1.59E-01mrem in a year which is 1.06% of the regulatory limit of 15 mrem per year (per unit) to anyorgan due to gaseous effluents. The resulting total body dose to a child located at thecontrolling receptor location would be 3.18E-02 mrem in a year which is 0.21% of the regulatorylimit of 15 mrem per year (per unit) total body dose due to gaseous effluents.80 SOUTHERN COMPANYE. I. HATCH NUCLEAR PLANTUNITS NO. I & 2ANNUAL REPORTJANUARY 1, 2013 -DECEMBER 31,2013APPENDIX B81 Appendix BSummary of Groundwater Protection ProgramNuclear Management Procedure NMP-EN-002 provides the methodology and criteria for implementationof the Radiological Groundwater Protection Program (GWPP) including evaluating hydrology andgeology, conducting a risk assessment, establishing and modifying on-site ground water monitoring,voluntary communications, corrective actions, reporting, and record keeping. Each program element ofNEI 07-07 "Industry Ground Water Protection Initiative -Final Guidance Document" is identified in thecorresponding procedure element.At Plant Hatch procedure 64CH-SAM-028-0 Releases Via Planned and Unplanned Routes: Samplingand Analysis procedure provides instructions for the sampling of groundwater sample wells, drainageoutfalls, STP effluent and drinking water deep wells for the Releases via Unplanned Routes (RVUR)sampling and analysis program.The Attachments to 64CH-SAM-028-0 contain the maps of the sampling points, the locations, collectionfrequency and the analyses required.On 13 Feb 2013 it was identified that the 1Y22-N008A collection tank at the discharge structureoverflowed. The overflow was caused by a malfunction of the permanently installed pump. The spill of>100 gallons impacted an area of 150 ft2 with an activity of approximately 6000pCi/L. The monthlygamma composite activity yielded 0 uCi/cc.82 SOUTHERN COMPANYE. I. HATCH NUCLEAR PLANTUNITS NO. 1 & 2ANNUAL REPORTJANUARY 1, 2013 -DECEMBER 31, 2013ADDENDUM83 ADDENDUM2012 Program DeviationsThis addendum is provided as an enhancement to the program deviations contained in the 2012Plant Radioactive Effluent Release Report describing inoperable liquid or gaseouseffluent monitoring instrumentation.Regulatory Requirements ODCM, Chapter 7, Section 7.2.2.6.2 states that the RadioactiveEffluent Release Report shall include deviations from the liquid and gaseous effluentmonitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1,respectively.Description of Deviations:There were two deviations from the liquid and gaseous effluent monitoringinstrumentation operability requirements during the Jan 1, 2012 -Dec 31,2012reporting period.Radioactive Liquid Effluent Monitoring Instrumentation channels were nonfunctional for >30 days.The Unit One LRW Effluent Flow Rate Measurement Device 1 G11 K023/R037 was out of service from7/30/12-10/01/12. The device was removed from service when the operator noticed a decrease indischarge flow to a rate below normal. A calibration check was performed on 10/1/2012. The flow ratedevice calibration deemed the instrument to be operable and it was returned to service. (RAS 1-12-227)Radioactive Liquid Effluent Monitoring Instrumentation channels were non-functional for >30days. The unit two LRW instrumentation was declared OOS due to the inability to performcalibration as there were no discharges performed during the specified time period. Theinstrumentation was OOS from 5/21/12 through the end of the year. (RAS 2-12-128)Page 84 of 503