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{{#Wiki_filter:Exelon Generation10 CFR 50.36a(a)(2)10 CFR 72.44 (d)(3)Technical Specification 6.9.1 .dRA-1 5-035April 30, 2015U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555 -0001Oyster Creek Nuclear Generating StationRenewed Facility Operating License No. DPR-16NRC Docket No. 50-219Independent Spent Fuel Storage FacilityNRC Docket No. 72-15 | |||
==Subject:== | |||
Annual Radioactive Effluent Release Report for 2014Enclosed with this cover letter is the Annual Radioactive Effluent Release Report for theperiod January 1 to December 31, 2014. This report includes the Oyster Creek NuclearGenerating Station Independent Spent Fuel Storage Facility.If any further information or assistance is needed, please contact John Renda,Chemistry Manager, at 609-971-2572.Sincerely,Jeff r 5staPlant Manage'r -Oyster Creek Nuclear Generating Station | |||
==Enclosure:== | |||
2014 Annual Radioactive Effluent Release Reportcc: Administrator, USNRC Region I (w/o attachment)USNRC Senior Project Manager, Oyster Creek (w/o attachment)USNRC Senior Resident Inspector, Oyster Creek (w/o attachment)Craig Stewart, American Nuclear InsurersA-1 vrjý 5 J-AExelon Generation(OAnnual Radioactive Effluent Release Report2014Oyster Creek Generating Station Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2014 through December 31, 2014EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTABLE OF CONTENTSSECTION PAGEEXECUTIVE SUMMARY 11. Introduction 32. Supplemental Information 4A Regulatory Limits 4B Effluent Concentration Limits 5C Average Energy 5D Measurements and Approximations of Total Radioactivity 5E Batch Releases 9F Abnormal Releases 9G Revisions to the ODCM 10H Radiation Effluent Monitors Out of Service More Than 30 Days 10I Releases from the Independent Spent Fuel Storage Facility 10J Program Deviations 11Appendix A -Effluent and Waste Disposal Summary 12Appendix B -Solid Waste and Irradiated Fuel Shipments 19Appendix C -Radiological Impact to Man 26Appendix D -Meteorological Data 29Appendix E -ODCM Revisions 103Appendix F -ERRATA 104ii Oyster Creek 2014 Annual Radioactive Effluent Release Report(Page Intentionally Left Blank)iii Oyster Creek 2014 Annual Radioactive Effluent Release ReportEXECUTIVE SUMMARYEffluents are strictly monitored to ensure that radioactivity released to the environment is aslow as reasonably achievable and does not exceed regulatory limits. Effluent control includesthe operation of monitoring systems, in-plant and environmental sampling and analysesprograms, quality assurance programs for the effluent and environmental programs, andprocedures covering all aspects of effluent and environmental monitoring.Both radiological environmental and effluent monitoring indicate that the operation of OysterCreek Generating Station (OCGS) does not result in significant radiation exposure to thepeople or the environment surrounding OCGS and is well below the applicable levels set by theNuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were liquid radioactive effluent releases during 2014 of concentrations of tritium too lowto detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution DischargeElimination System (NJPDES) permitted main condenser outfall. The releases were part ofnearly continuous pumping of groundwater at approximately 70 gpm containing low levels oftritium and no detectable gamma. Exelon and the State of New Jersey Department ofEnvironmental Protection (NJDEP) agreed to this remediation action instead of naturalattenuation to address concentrations of tritium in groundwater. Well 73 and supportingequipment and piping were installed to pump groundwater to the intake structure at the inlet ofthe main circulating water pumps. Provisions were established for both batch and continuousreleases of groundwater. Continuous releases occurred approximately 230 days in 2014. Thenearly continuous releases occurred from March 12, 2014 through December 31, 2014 with atotal of 2.31 E+07 gallons of groundwater pumped resulting in 1.74E-01 Ci of tritium released tothe discharge canal. The dose to the most limiting member of the public due to the release ofgroundwater was 8.28E-07 mrem.There were no liquid abnormal releases during 2014.There were two gaseous abnormal releases during 2014. During maintenance of the OldRadwaste Building exhaust fan EF-1 -17 the side panel was removed to access the fan whenpositive pressure was noted coming from the opening. The side panel was immediatelyreplaced and sealed. During maintenance of the New Radwaste Building exhaust fan HV-S-54A, two slits were identified in the expansion joint and repaired.The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), andparticulates to any individual due to gaseous effluents was 4.78E-01 mrem, which wasapproximately 3.19E+00 percent of the annual limit of 15 mrem. The majority of organ dosefrom gaseous effluents was due to C-14. The maximum calculated gamma air dose in theUNRESTRICTED AREA due to noble gas effluents was 1.62E-02 mrad, which was 1.62E-01percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limitof 10 mrad.For comparison, the background radiation dose averages approximately 300 mrem per year in theCentral New Jersey area, which includes approximately 200 mrem from naturally occurring radongas and 100 mrem from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposure1 Oyster Creek 2014 Annual Radioactive Effluent Release Reportis due to direct radiation. Based on offsite TLD readings, dose due to direct radiation from theISFSI was less than 1 mrem for 2014. Because it is a sealed unit, no radioactive material wasreleased.Comparison of environmental sampling results to iodine and particulate gaseous effluentsreleased, showed no radioactivity attributable to the operation of OCGS. Both elevated andground-level release paths were considered in this review, with total iodines released of5.29E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of3.33E-02 Ci.Joint Frequency Tables of meteorological data, per Stability Classification Category, as well asfor all stability classes, are included. All data was collected from the on-site MeteorologicalFacility. Data recoveries for the 380-foot data and the 33-foot data were 99.9 percent and 99.9percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for MeteorologicalFacility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.2 Oyster Creek 2014 Annual Radioactive Effluent Release ReportIntroductionIn accordance with the reporting requirements of Technical Specification 6.9.1.dapplicable during the reporting period, this report summarizes the effluent releasedata for OCGS for the period January 1, 2014 through December 31, 2014. Thissubmittal complies with the format described in Regulatory Guide 1.21,"Measuring, Evaluating and Reporting Radioactivity in Solid Wastes andReleases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974.Meteorological data was reported in the format specified in Regulatory Guide1.23, Revision 1, "Meteorological Monitoring Programs for Nuclear PowerPlants".All vendor results were received and included in the report calculations. Therefore the2014 report is complete.3 Oyster Creek 2014 Annual Radioactive Effluent Release Report2 Supplemental InformationOyster Creek Generating StationExelon Generation Company, LLCA. Regulatory Limits:LimitUnitsReceptorODCM and 10 CFR 50,Appendix I Design ObjectiveLimits1. Noble Gases:a. < 500mrem/yr Total Body< 3000 mrem/yrSkinb. <5*<10C. <10*<20mradmradmradmradAir GammaAir BetaAir GammaAir BetaTotal Body(Gamma)Skin (Beta)d. < 5 mrem< 15mrem2. lodines, Tritium, Particulates with Half Life > 8 days:a. < 1500 mrem/yr Any OrganODCM Control 3.11.2.1Quarterly air dose limitsODCM Control 3.11.2.2Yearly air dose limitsODCM Control 3.11.2.210 CFR 50, Appendix I,Section II.B.2(b)ODCM Control 3.11.2.1Quarterly dose limitsODCM Control 3.11.2.3Yearly dose limitsODCM Control 3.11.2.3ODCM Control 3.11.1.1Quarterly dose limitsODCM Control 3.11.1.2Yearly dose limitsODCM Control 3.11.1.2b. :< 7.5 mremAny OrganAny OrganC. _<15mrem3. Liquid Effluentsa. Concentration 10 CFR 20, Appendix B,Table 2 Column 2b. _<1.5< 5C. _<3<10mremmremmremmremTotal BodyAny OrganTotal BodyAny Organ4 Oyster Creek 2014 Annual Radioactive Effluent Release ReportB. Effluent Concentration Limits:Gaseous dose rates rather than effluent concentrations are used to calculatepermissible release rates for gaseous releases. The maximum permissible doserates for gaseous releases are defined in ODCM Controls 3.11.2.1.The Effluent Concentration Limit (ECL) specified in 10 CFR 20, Appendix B, Table2, Column 2 for identified nuclides, were used to calculate permissible release ratesand concentrations for liquid release per ODCM Controls 3.11..1.1. The total activityconcentration at the Route 9 bridge for all dissolved or entrained gases was limitedto < 2E-04 pjCi/ml.C. Average Energy ()E:The Oyster Creek ODCM limits the instantaneous dose equivalent rates due to therelease of noble gases to less than or equal to 500 mrem/year to the total body andless than or equal to 3000 mrem/year to the skin. The average beta and gammaenergies (-) of the radionuclide mixture in releases of fission and activation gasesas described in Regulatory Guide 1.21, "Measuring, Evaluating and ReportingRadioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid andGaseous Effluents from Light-Water-Cooled Nuclear Power Plant", may be used tocalculate doses in lieu of more sophisticated software. The Oyster Creekradioactive effluent program employs the methodologies presented in U.S. NRCRegulatory Guide 1.109 "Calculation of Annual Doses to Man from RoutineReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977. Therefore, average energy(-) as described in Regulatory Guide 1.21 is not applicable to Oyster Creek.D. Measurements and Approximations of Total Radioactivity:1. Fission and Activation GasesThe method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a gas Marinelli beaker. Airborne effluent gaseousactivity was continuously monitored and recorded in accordance with the OffSite Dose Calculation Manual (ODCM) Table 4.11.2.1.2-1. Additional grabsamples were taken from the stack Radioactive and Gaseous EffluentMonitoring System (RAGEMS) sample point and ground-level release samplepoints and analyzed at least monthly to determine the isotopic mixture of noblegas activity released for the month. If activity was found in the grab isotopicanalysis, the results are entered into Simplified Environmental EffluentDosimetry System (SEEDS) to calculate dose and dose rates. If no activity isdetected in the stack grab samples, post treatment or Off Gas IsotopicAnalysis data may be used.2. lodinesThe method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a charcoal cartridge. Iodine activity was continuouslysampled and analyzed in accordance with ODCM Table 4.11.2.1.2-1.Charcoal samples are taken from the stack RAGEMS sample point and5 Oyster Creek 2014 Annual Radioactive Effluent Release Reportground-level release sample points and analyzed at least weekly to determinethe total activity released from the plant based on the average vent flow ratesrecorded for the sampling period.3. Particulates (half-lives > 8 days)The method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a particulate filter (47 mm). Particulate activity wascontinuously sampled and analyzed in accordance with ODCM Table4.11.2.1.2-1. Particulate samples are taken from the stack RAGEMS samplepoint and ground-level release sample points and analyzed at least weekly todetermine the total activity released from the plant based on the average ventflow rates recorded for the sampling period.4. TritiumA. Gaseous EffluentsAir from stack and vent effluents was passed through a desiccantcolumn and distilled to remove the moisture collected. An aliquot of thewater from the distillate was analyzed for tritium using a liquidscintillation counter.B. Liquid EffluentsWater from liquid effluents was analyzed for tritium using a liquidscintillation counter.5. Gross AlphaGross alpha was measured by an off-site vendor for both the gas andliquid effluent composite samples.6. Hard-To-DetectsHard-To-Detects was measured by an off-site vendor for one set of gasmonthly composites. The analysis included Fe-55, 1-129, Ni-59, Ni-63,Tc-99, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241.Fe-55 and Ni-63 have been added to the routine monthly compositeanalysis schedule based on previous sample results for Hard-To-Detects.6 Oyster Creek 2014 Annual Radioactive Effluent Release Report7. Carbon-14 (C-14)The amount of C-14 (Ci) released was estimated using the guidance fromEPRI Technical Report 1021106, Estimation of Carbon-14 in Nuclear PowerPlant Gaseous Effluents. The C-14 was released primarily through the stack(97%) with a small amount (3%) released through plant vents. The activity inliquid effluents was determined to not be significant.The offsite dose from C-14 was calculated using SEEDS, which usesapproved ODCM methodologies. The resulting annual dose to a child fromgaseous releases of C-14 is about 4.53E-01 mrem to the bone.8. Liquid EffluentsGroundwater containing tritium was released during 2014. For continuousreleases, tritium and principal gamma emitters were determined for acomposite sample daily. The concentration of tritium is limited to ensureconcentrations were less than 200 pCi/I in the discharge canal. The gammaemitters were limited to less than detectable concentrations. Gross alpha andHard-to-detect analyses (Fe-55, Ni-63, Sr-89 and Sr-90) were determined formonthly composite samples for each type of release (batch or continuous).The leaks into the groundwater were reported in the 2009 Annual RadioactiveEffluent Release Report as abnormal releases. Estimates of the curies of thetritium releases were reported. Doses due to the release of the groundwaterto the discharge canal were included in the report. To ensure that amount ofactivity discharge is accurate and limiting, the activity and doses as a result ofdischarges during 2014 from the groundwater remediation project are includedin this report.9. Estimated Total Error PresentProcedure CY-AA-170-2100, Estimated Errors of Effluent Measurements,provides the methodology to obtain an overall estimate of the error associatedwith radioactive effluents.7 Oyster Creek 2014 Annual Radioactive Effluent Release Report10. Composite Samples and Lower Limit of Detection (LLD)Particulate air samples were composited monthly and analyzed for grossalpha, Sr-89, Sr-90, Fe-55 and Ni-63. Groundwater batch and continuousreleases were composited at least monthly and analyzed for gross alpha,Sr-89, Sr-90, Fe-55 and Ni-63. These composites are submitted to an offsitevendor laboratory for analysis. The ODCM required LLD for liquid andairborne releases are as follows:Liquid:Principal Gamma Emitters (Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Ce-141, Cs-134, Cs-137)Principal Gamma Emitters (Ce-144)Dissolved and Entrained GasesH-3Gross AlphaSr-89 and Sr-90Fe-55 and Ni-63AirbornePrincipal Gamma Emitters (Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138)H-31-1311-133Principal Gamma Emitters (Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141)Principal Gamma Emitters (Mo-99, Ce-144)Gross AlphaSr-89, Sr-90LLD5E-07 pCi/ml5E-06 pCi/ml1 E-05 pCi/ml1 E-05 pCi/ml1 E-07 pCi/ml5E-08 pCi/ml1E-06 pCi/mlLLD1E-04 pCi/ml1 E-06 pCi/ml1 E-12 pCi/ml1 E-1 0 pCi/ml1 E-1 I pCi/ml1E-10 pCi/ml1E-11 pCi/ml1E-1i1 pCi/ml8 Oyster Creek 2014 Annual Radioactive Effluent Release ReportE. Batch Releases:1. LiquThere were no batch releases of liquid effluents during 2014.2. GaseousThere were no batch releases of gaseous effluents during 2014.F. Abnormal Releases:There were no abnormal liquid releases during 2014.There were two abnormal gaseous releases during 2014.During the performance of Work Order C2031047, the side panel of exhaust fan EF-1-17 was removed to access the fan when positive pressure was noted coming fromthe opening. The side panel was immediately replaced and sealed. A tent hadbeen built around the work area but there was no HEPA filter in place to preventany releases from the fan from going to the atmosphere. Note that the exhaust fromEF-1 -17 is normally to the atmosphere but through the monitored stack effluentrelease point. Engineering performed a calculation to determine a release rate thatencompasses the maximum release rate through this opening.The following assumptions were made when calculating Curies released and dose:* Though the panel was off for less than 15 minutes, 15 minutes was used asthe release period.* The activity due to particulates identified from the sample at the time of therelease at the opening was released as a ground level release from theexhaust fan opening at the flow rate calculated by Engineering.Quarter Quarter QuarterUnits 123 Quarter 41 2 3Total Release Ci O.OOeO O.OOeO O.OOeO 1.29e-07Organ Dose mrem O.0Oe0 0.00e0 0.00e0 1.35E-07During the performance of Work Order R2227008, which is to perform an annualinspection of the New Radwaste (NRW) exhaust fan HV-S-54A, two slits werediscovered in the expansion joint. This is one of the exhaust fans for the NewRadwaste Building to the Main Stack. Note that the exhaust from HV-S-54A isnormally to the atmosphere but through the monitored stack effluent release point.Engineering performed a calculation to determine a release rate that encompassesthe maximum release rate for both slits. The activity to inspect the exhaust fan is anannual activity.The following assumptions were made when calculating Curies released and dose:* The exhaust fan has been leaking since the date of the last inspection untilthe time of the repair, 8/20/13 through 7/25/14.9 Oyster Creek 2014 Annual Radioactive Effluent Release Report" All of the activity due to particulates reported from the Main Stack wascoming from the New Radwaste Building and therefore being released as aground level release from the exhaust fan leaks at the flow rate calculatedby Engineering." HV-S-54A was in operation the entire time since the last inspection wasperformed.Quarter Quarter QuarterUnits 123 Quarter 41 2 3Total Release Ci 8.81 E-05 8.90E-05 2.41 E-05 O.OOeOOrgan Dose mrem 4.78E-04 4.63E-04 1.56E-04 0.000eG. Revisions to the ODCM:Revision 6 of the ODCM, CY-OC-170-301 was implemented 12/16/2014. A list ofthe major changes is included below. See the complete copy of CY-OC-170-301Revision 6 attached as part of this report." Meteorological data was updated resulting in changes to X/Q and D/Qvalues. These changes were also used to update the AySi, PySi and DFSidose factors.* Distances to the site boundary were updated.* AOG/NRW CCW Service Water Effluent was removed from Table4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis ProgramH. Radiation Effluent Monitors Out of Service More Than 30 DaysPer ODCM Control 3.3.3.10, "Radioactive Liquid Effluent MonitoringInstrumentation" and 3.3.3.11, Radioactive Gaseous Effluent MonitoringInstrumentation requires:With less than the minimum number of radioactive liquid/gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument toOPERABLE status within 30 days and, if unsuccessful, explain in the nextRadioactive Effluent Release Report why the inoperability was not corrected in atimely manner.The following is a discussion of instrumentation out of service for greater than 30days:1. There was no instrumentation out of service for greater than 30 days.1. Releases from the Independent Spent Fuel Storage Facility:The ISFSI is a closed system and the only exposure would be due to directradiation. This includes iodines, particulates, and noble gases. Based on offsite10 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for20.14. Because it is a sealed unit, no radioactive material was released.J. Program Deviations:1 .The groundwater remediation composite sampler was found with nocomposite collected from August 26, 2014 at 3:47 AM through August 26,2014 at 10:00 AM (approximately 6.25 hours). The composite sampler isrequired by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Samplingand Analysis Program and is set to obtain a composite sample once per hour.This issue occurred due to Operations starting the remediation pump per thesection of the procedure for by-passing the sample station. This issue wasentered into our Corrective Action Program (CAP) and corrective actions takenhave been documented per process.2. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was notcollected January 1, 2014 through November 13, 2014. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by Revision 5 of CY-OC-170-301, Offsite Dose Calculation Manualfor Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive LiquidWaste Sampling and Analysis Program and was required to be sampledweekly for principal gamma emitters and 1-131. This requirement wasremoved in Revision 6 of CY-OC-1 70-301. This issue occurred from theinclusion of this requirement in revision 4 of the ODCM due to amisunderstanding of the system flow path. It was believed that all servicewater exited the site from the same release point which was evident by thefact that the change paperwork included in the description of this change asbeing consistent with the practices at Oyster Creek and there was nomodification to the sampling schedule. The NRW and AOG Closed CoolingWater systems were reviewed as part of NRC Bulletin IE 80-10. At that timeNRW Closed Cooling Water system was determined to be a potentiallycontaminated system and was added to the sampling program for NRCBulletin IE 80-10. The sampling program for IE 80-10 requires all potentiallycontaminated systems to be sampled quarterly for gamma emitters. AOGClosed Cooling Water system was also reviewed but determined to not be apotentially contaminated system. Even though AOG was found not to be apotentially contaminated system, sampling is still performed quarterly forgamma emitters. The potential pathway for a release from NRW/AOG ServiceWater Effluent would be from a heat exchanger leak from the NRW ClosedCooling Water system into the Service Water side of the heat exchanger. Thesystem is designed to maintain the Service Water side of the heat exchangerat a higher pressure than the Closed Cooling Water side so that if any leakswould develop in the heat exchanger it would be Service Water leaking intothe Closed Cooling Water side. A review was performed for both NRW andAOG quarterly Closed Cooling Water samples for the time that the requiredsamples were not obtained and all samples were less than MDA for gammaemitters for that entire time period.11 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix AEffluent and Waste Disposal Summary12 Oyster Creek 2014 Annual Radioactive Effluent Release ReportLIST OF TABLESPAGETable A -1 Gaseous Effluents -Summary of All Releases 14Table A -2 Gaseous Effluents Release Point: Elevated Release 14Table A -3 Gaseous Effluents Release Point: Ground Level Releases 16Table A -4 Liquid Effluents -Summary of All Releases 17Table A -5 Liquid Release Point: Groundwater Remediation 1813 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-I: Gaseous Effluents- Summary Of All ReleasesPeriod: January 1, 2014 through December 31, 2014Unit: Oyster Creek1 1 1 Esto talA. Fission & Activation Gases Units Quarter II Quarter 21 Quarter3 Quarter 4 Error%I1. Total ReleaseCi1.95E+012.07E+011.45E+017.76E+00 I 25.00% I2. Average Release Rate for Periodfor Period I pCi/sec I 1.16E-03 I 8.05E-04 I 1.63E-03 I 6.32E-04* ODCM Limit is for combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.14 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-2: Gaseous Effluents Release Point: Elevated ReleasePeriod: January 1, 2014 through December 31, 2014Unit: Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gases Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci 1.90E+00 1.51 E+00 8.55E-01 4.38E-01 <LLD <LLD <LLD <LLDKr-87 Ci 3.24E+00 1.08E+00 2.39E+00 <LLD <LLD <LLD <LLD <LLDKr-88 Ci 2.13E+00 2.26E+00 5.80E-01 1.98E+00 <LLD <LLD <LLD <LLDXe-133 Ci 1.45E+00 1.70E+00 1.06E+00 5.25E-01 <LLD <LLD <LLD <LLDXe-135 Ci 5.96E+00 1.11E+01 8.71E+00 4.82E+00 <LLD <LLD <LLD <LLDXe-i 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-i 37 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-138 Ci 4.83E+00 1.71E+00 <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 1.95E+01 1.94E+01 1.36E+01 7.76E+00 <LLD <LLD <LLD <LLD2. lodines1-131 Ci 3.88E-04 6.18E-04 6,19E-04 7.03E-05 <LLD <LLD <LLD <LLD1-133 Ci 8.14E-04 1.76E-03 9.50E-04 5.20E-05 <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 1.20E-03 2.38E-03 1.57E-03 1.22E-04 <LLD <LLD <LLD <LLD3. ParticulatesSr-89 Ci 6.68E-04 1.57E-04 2.93E-04 6.45E-05 <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-1 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-137 Ci 1.92E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLDBa-140 Ci 1.13E-03 4.17E-04 7.12E-04 3.70E-04 <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci <LLD <LLD 7.77E-05 2.09E-05 <LLD <LLD <LLD <LLDMn-54 Ci 5.40E-04 4.16E-04 1.14E-03 3.98E-04 <LLD <LLD <LLD <LLDCo-58 Ci 2.41E-03 1.97E-03 3.96E-03 2.OOE-03 <LLD <LLD <LLD <LLDCo-60 Ci 3.04E-03 2.30E-03 5.01 E-03 1.88E-03 <LLD <LLD <LLD <LLDNi-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 2.46E-04 2.25E-04 3.52E-04 5.20E-05 <LLD <LLD <LLD <LLDAg-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 8.40E-04 7.41E-04 1.38E-03 2.36E-04 <LLD <LLD <LLD <LLDTotal for Period Ci 8.89E-03 6.23E-03 1.29E-02 5.02E-03 <LLD <LLD <LLD <LLD4. TritiumH-3 Ci 6.17E+00 9 80E+00 7449E+O0 4.40E+00 <LLD <LLD <LLD <LLD5. Gross AlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14 C-14 Ci 2.32E+00 2.33E+00 1.76E+00 1.98E--+00 <LLD <LLD <LLD <LLD15 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-3: Gaseous Effluent Release Point: Ground Level ReleasesPeriod: January 1, 2014 through December 31, 2014Unit: Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gases Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-135 Ci <LLD 1.34E+00 9.26E-01 <LLD <LLD <LLD <LLD <LLDXe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 38 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci <LLD 1.34E+00 9.26E-01 <LLD <LLD <LLD <LLD <LLD2. lodines j1-131 Ci <LLD 9.91E-07 1.30E-05 1.52E-06 <LLD <LLD <LLD <LLD1-133 Ci <LLD 4.86E-06 1.94E-06 <LLD <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal fOr Period Ci <LLD 5.85E-06 1.49E-05 1.52E-06 <LLD <LLD <LLD <LLD3. ParticulatesSr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-i 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-i 37 Ci 8.29E-07 8.38E-07 2.27E-07 <LLD <LLD <LLD <LLD <LLDBa-140 Ci 1.19E-05 1.20E-05 3.26E-06 <LLD <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci 6.72E-06 6.79E-06; 1.84E-06 <LLD <LLD <LLD <LLD <LLDMn-54 Ci 8.03E-06 8.12E-06 2.20E-06 <LLD <LLD <LLD <LLD <LLDCo-58 Ci 2.30E-05 2.36E-05 6.65E-06 7.76E-07 <LLD <LLD <LLD <LLDCo-60 Ci 2.81E-05 3.78E-05 1.94E-05 2.18E-06 <LLD <LLD <LLD <LLDNi-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 2.21E-06 2.24E-06 6.06E-07 <LLD <LLD <LLD <LLD <LLDAg-11Om Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 8.71 E-06 8.81 E-06 2.38E-06 <LLD <LLD <LLD <LLD <LLDAm-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 8.95E-05 1.OOE-04 3.66E-05 2.96E-06 <LLD <LLD <LLD <LLD4. Tritium PXH-3 Ci 2.66E-01 2.03E-01 4.40E-01 1.70E-01 <LLD <LLD <LLD <LLD5. GrossAlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14C-14 Ci 7.20E-02 7.21E-02 5.44E-02 6.13E-02 <LLD <LLD <LLD <LLD16 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-4: Liquid Effluents -Summary Of All ReleasesPeriod: January 1, 2014 through December 31, 2014 Unit: Oyster CreekEst. TotalA. Fission & Activation ProductsI Units IQuarter I Quarter 2 Quarter 3 Quarter 4Error %I1. iota! Release not includingtritium, gases, alphaCi<LLD<LLD<LLD<LLD 12 5. v/oI2. Average Diluted concentrationduring periodI Units IQuarter I Quarter 21 Quarter 3 Quarter 41 Eror ;I Ci I <LLD <LLD I <LLD <LLD I 25.00%I Liters I 1.04E+1114.85E+1 o 4.09E+112.19E+117 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-5: Liquid Release Point: Groundwater RemediationPeriod: January 1, 2014 through December 31, 2014Unit: Oyster CreekNuclidesReleased Continuous Mode Batch ModeFission & UnitActivation Quarter Quarter Quarter Quarter Quarter Quarter Quarter QuarterProducts 1 2 3 4 1 2 3 4Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-I 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-I 37 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCo-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCo-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDNi-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDNb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDBa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAg-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDA--133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 35 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDH-3 Ci 1,59E-02 I6.95E-02 15.85E-02 13.05E-021 <LLD I<LLD I<LLD I<LLDII,Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LD LD18 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix BSolid Waste and Irradiated Fuel Shipments19 Oyster Creek 2014 Annual Radioactive Effluent Release ReportA. Solid waste shipped offsite for burial or disposal (not irradiated fuel)1. Type of wasteTypes of Waste Total Total Period Est. TotalQuantity Activity Error%(mI) (Ci)a. Spent resins,filter sludges, evaporator bottom, etc 4.71 E+01 1.55E+02 2014 2.50E+01b. Dry compressible waste, contaminated equip, etc 5.61E+02 1.09E+0 2014 2.50E+01c. Irradiated components, control rods,etc 1.66E-01 4.24E+03 2014 2.50E+01d. Other 1.10E+02 5.06E-01 2014 2.50E+0120 Oyster Creek 2014 Annual Radioactive Effluent Release Report1. Estimate of Major Nuclide Composition (By Waste Type)Category A -Spent Resin, Filters, Sludges, Evaporator Bottoms, etc.Isotope Ij Waste Class AI Waste Class BI Waste Class CI Curies I Percent ICuries I PercentI (-iiripn I Pprri-Ant IH-3 5.13E-02 8.87E-02C-14 4.83E-02 8.35E-02Cr-51P-32Mn-54 3.05E+00 5.27E+00Fe-55 3.05E+01 5.27E+01Fe-59Co-57 1.78E-03 3.08E-03Co-58 1.46E-02 2.52E-02Co-60Ni-59Ni-63Zn-65Sr-89Sr-90Nb-95Tc-99Ag-11 OinSb-125Cs-1 34Cs-137Ce-144Pu-238Pu-239Pu-240Pu-241Am-241Cm-242Cm-243Cm-244Totals 5.78E+01 I .OOE+02I 9.72E+01 I .OOE+02 0 .OOE+00 10.00E+0Note: Grey fields are where results were not reported in the NRC Regulatory Guide 1.21 Report21 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCategory B -Dry Compressible Waste, Contaminated Equipment, etc.Isotope Waste Class ACuries PercentC-14 7.28E-06 6.70E-04P-32 6.1OE-05 5.61E-03Mn-54 3.67E-02 3.38E+00Fe-55 7.99E-01 7.35E+01Co-57 9.24E-05 8.50E-03Co-58 1.80E-03 1.66E-01Co-60 1.90E-01 1.75E+01Ni-63 6.93E-03 6.38E-01Zn-65 1.82E-02 1.67E+00Tc-99 Sb-1125 Sr-89 1.50E-04 1.38E-02Sr-90 1.89E-04 1.74E-02Cs-1 37 3.29E-02 3.03E+00Ce-144 5.00E-04 4.60E-02Pu-238 6.22E-06 5.72E-04Pu-239 1.90E-06 1.75E-04Pu-241 2.19E-04 2.02E-02Amn-241 7.52E-06 6.92E-04Cm-242 1.24E-06 1. 14E-04Cm-243 2.43E-06 2.24E-04Cm-244 2.43E-06 2.24E-04Totals 1.09E+00 1.OOE+0222 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCategory C -Irradiated components, control rods, etc.Isotope Waste Class CCuries PercentAbundanceH-3 1.06E-02 2.50E-04C-14 1.16E-01 2.73E-03Cr-51 6.22E-02 1.47E-03Mn-54 1.83E+01 4.31E-01Fe-55 4.77E+02 1.12E+01Fe-59 3.27E-02 7.71E-04Co-58 1.19E+00 2.81E-02Co-60 2.75E+03 6.48E+01Ni-59 2.92E-01 6.88E-03Ni-63 3.62E+01 8.53E-01Zn-65 2.83E-01 6.67E-03Sr-90 2.79E-05 6.58E-07Zr-95 1.37E+02 3.23E+00Nb-94 2.60E-03 6.13E-05Mo-93 2.91 E-05 6.86E-07Tc-99 3.32E-05 7.83E-07Sb-125 8.16E+02 1.92E+011-129 1.70E-09 4.01E-11Cs-137 4.52E-05 1.07E-06Ce-144 1.31E-07 3.09E-09Hf-1 81 9.68E-01 2.28E-02Ta-182 4.35E+00 1.03E-01U-235 3.97E-1 1 9.36E-1 3Np-237 9.79E-10 2.31 E-11Pu-238 1.35E-05 3.18E-07Totals 4.24E+03 1.OOE+0223 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCategory D -Other -Scrap MetalIsotope Waste Class ACuries PercentH-3 4.70E-01 9.28E+01C-14 2.42E-07 4.78E-05P-32 1.82E-06 3.59E-04Mn-54 1.23E-03 2.43E-01Fe-55 2.66E-02 5.25E+00Co-57 3.27E-06 6.46E-04Co-58 6.11E-05 1.21E-02Co-60 6.34E-03 1.25E+00Ni-63 2.30E-04 4.54E-02Zn-65 6.11E-04 1.21E-01Sr-85 5.73E-13 1.13E-10Sr-89 5.08E-06 1.OOE-03Sr-90 6.29E-06 1.24E-03Y-88 9.40E-08 1.86E-05Cd-109 8.87E-07 1.75E-04Sn-113 2.62E-08 5.17E-06Cs-137 1.33E-03 2.63E-01Ba-133 1.15E-05 2.27E-03Ce-1 39 3.82E-08 7.54E-06Ce-144 1.67E-05 3.30E-03Hg-203 8.55E-1 1 1.69E-08Pu-238 2.07E-07 4.09E-05Pu-239 6.30E-08 1.24E-05Pu-241 7.26E-06 1.43E-03Am-241 9.89E-06 1.95E-03Cm-242 4.16E-08 8.21E-06Cm-243 8.07E-08 1.59E-05Cm-244 8.06E-08 1.59E-05Totals 5.06E-01 1.OOE+02Note: Grey fields are where results were not reported in the NRC Regulatory Guide 1.21 Report2. Solid Waste (Disposition)Number of Shipments Mode of Transportation Destination9 Hittman Transport Co. Barnwell Disposal Facility16 Hittman Transport Co. Energy Solutions Services, Inc.B. Irradiated Fuel Shipments (disposition).There were no irradiated fuel shipments.24 Oyster Creek 2014 Annual Radioactive Effluent Release ReportC. Changes to the Process Control ProgramRevision 10 of the Process Control Program, RW-AA-1 00 was implemented August 26,2014. See the complete copy of RW-AA-1 00 Revision 10 attached as part of this report.25 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix CRadiological Impact to Man26 Oyster Creek 2014 Annual Radioactive Effluent Release ReportPer ODCM Administrative Control 6.2, an assessment of radiation doses to the likely mostexposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuelcycle sources (including doses from primary effluent pathways and direct radiation) for theprevious calendar year must be made to show conformance with 40 CFR Part 190,Environmental Radiation Protection Standards for Nuclear Power Operation. For purposes ofthis calculation the following assumptions were made:Gaseous" Nearest member of the public was W sector at 483 meters.* Actual 2014 meteorology and measured gaseous effluent releases were used.* All significant pathways were assumed to be present.* Occupancy factor was considered 22.8% (40 hours/week for 50 weeks).Ligqui* Doses calculated in the discharge canal at the Route 9 Bridge.* Fish, shellfish and shoreline pathways doses calculated.40 CFR Part 190 Compliance" Dosimetry measurements (minus average of control stations) measured direct radiation forthe nearest member of the public. The nearest member of the public for direct radiation isconsidered an individual that works in the warehouse west of the site. As a worker, theindividual is assumed to work 2,000 hours per year at this location. Note that for thewarehouse worker total dose calculations the full year (8760 hours) values for Iodine,Particulate, Carbon-14, Tritium and Liquid are used.* Nearest resident was at SE sector at 937 meters.* The highest calculated dose for gamma air dose and liquid total body were summed fortotal body dose.* The highest calculated dose for gamma air dose, child bone and liquid organ were summedfor organ dose.* The limits for Kr-85, 1-129, Pu-239 and other alpha-emitting transuranic radionuclides withhalf-lives greater than one year were not exceeded.The ODCM does not require total body doses to the population and average doses toindividuals in the population from gaseous effluents to a distance of 50 miles from the site to becalculated.27 Oyster Creek 2014 Annual Radioactive Effluent Release ReportA summary of gaseous and liquid radiation doses to most likely exposed MEMBER OF THEPUBLIC was as follows:Location % ofApplicable Estimated Age Distance Direction ApplicableEffluent Organ Dose Group (meters) (toward) Limit Limit UnitGamma -Noble Gas Air Dose 1.62E-02 All 405 E 1.62E-01 10 mradBeta -AirNoble Gas Dose 1.91 E-02 All 406 E 9.55E-02 20 mradTotal BodyNoble Gas (Gamma) 2.18E-03 All 972 ESE 4.36E-02 5 mremNoble Gas Skin (Beta) 4.86E-03 All 972 ESE 3.24E-02 15 mremIodine,Particulate, Bone 4.78E-01 Child 937 SE 3.19E+00 15 mremCarbon-14 &TritiumLiquid Total body 8.28E-07 All South Route 9 2.76E-05 3 mremLiquid Organ 8.28E-07E All Bridge 8.28E-06 10 mremDirect Radiation Total Body 5.09E+00 All 483 W 2.04E+01 25 mremDirect Radiation Total Body <LLD All 937 SE <LLD 25 mrem40 CFR Part 190 ComplianceWarehouse WorkerTotal Dose Total Body 5.09E+00 All 483 W 2.04E+01 25 mremnTotal Dose Bone 5.57E+00 All 483 W 2.23E+01 25 mremnTotal Dose Thyroid 5.09E+00 All 483 W 6.79E+00 75 mremnNearest ResidentTotal Dose Total Body 1.62E-02 All 937 SE 6.48E-02 25 mremTotal Dose Bone 4.94E-01 All 937 SE 1.98E+00 25 mremTotal Dose Thyroid 1.52h-O All 937 SE Z.1_E-02 75 mrem28 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix DMeteorological Data29 Oyster Creek 2014 Annual Radioactive Effluent Release ReportLIST OF METEOROLOGICAL DATA TABLESPAGETable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 31the Oyster Creek Generating Station, January -March, 2014Table D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 38the Oyster Creek Generating Station, January -March, 2014Table D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 45the Oyster Creek Generating Station, April -June, 2014Table D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 52the Oyster Creek Generating Station, April -June, 2014Table D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 59the Oyster Creek Generating Station, July -September, 2014Table D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 66the Oyster Creek Generating Station, July -September, 2014Table D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 73the Oyster Creek Generating Station, October- December, 2014Table D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 80the Oyster Creek Generating Station, October- December, 2014Table D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 87the Oyster Creek Generating Station, January -December, 2014Table D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 95the Oyster Creek Generating Station, January -December, 201430 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total00117005473692236281700002000055048201000544115172810512131019386647250Total0 83 15500 292Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:431 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7000000000000000007133414102244108408-12 13-18 19-24 > 240 0 0 00 0 0 02 0 0 05 0 0 00 0 0 00 0 0 01 0 0 02 0 0 05 2 0 04 1 0 00 0 0 06 0 0 05 5 0 04 3 0 07 2 0 00 0 0 00 0 0 0Total715841537721014171740Total0 58 41 1300 112Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:432 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 240 0 0 0 01 0 0 0 03 0 0 0 02 0 0 0 01 0 0 0 02 0 0 0 04 0 0 0 04 0 0 0 01 1 0 0 01 2 0 0 02 0 0 0 02 0 0 0 01 3 1 0 02 6 2 0 04 2 4 0 03 1 0 0 00 0 0 0 0Total0132124023225101040Total0 29 15'700 51Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:433 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-743832211112455450213233192557767131823313308-12 13-18 19-24 > 2417 0 0 033 2 0 016 4 0 013 0 0 01 0 0 00 0 0 03 0 0 01 0 0 06 0 0 012 15 0 07 1 0 05 0 0 013 5 0 021 19 0 025 5 0 040 0 0 00 0 0 0Total42706135579914341722416865780Total51 2622135100 577Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:434 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal1-3 4-7 8-12 13-18 19-24 > 243 14 2 0 0 04 13 0 0 0 03 27 2 1 0 08 10 5 0 0 05 2 0 0 0 02 1 0 0 0 00 8 1 0 0 02 6 9 1 0 05 15 11 12 0 05 16 40 11 0 010 34 6 0 0 010 28 3 0 0 09 34 3 1 0 013 49 27 1 0 013 46 22 0 0 011 17 13 0 0 00 0 0 0 0 0Total1917332373918437250414790814101033201442700 594Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:435 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -I Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Stable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection1-3 4-7N 8NNE 2NE 5ENE 2E 1ESE 2SE 2SSE 0S 2SSW 2SW 6WSW 13W 28WNW 11NW 7NNW 7Variable 01101003116614161315508-12 13-18 19-24 > 24o 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 0Total9353,1251381227442422120Total98 830000 181Hours of calm inHours of missingthis stability class:1wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:436 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal1-3 4-7 8-12 13-18 19-24 > 244 0 0 0 0 04 0 0 0 0 06 0 0 0 0 03 0 0 0 0 03 0 0 0 0 04 0 0 0 0 03 2 0 0 0 04 0 0 0 0 05 0 0 0 0 09 0 0 0 0 027 1 0 0 0 072 10 0 0 0 076 18 0 0 0 038 3 0 0 0 031 15 0 0 0 02 0 0 0 0 00 0 0 0 0 0Total4463345459288294414620291490000 340Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in8stability class: 0all stability classes:437 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal1-3 4-70000000000000000000000000000000000008-12 13-18 19-24 > 240 0 0 00 0 0 00 2 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 10 1 1 10 2 2 41 2 0 30 0 1 00 0 0 0Total002000000001386101749 21Hours of calm in this stability class:0Hours of missing wind measurements in this stabiHours of missing stability measurements in all slity class: 0tability classes:438 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph).WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7000000000000000008-12 13-18 19-24 > 241 0 0 01 0 0 00 4 3 00 0 1 10 0 0 00 0 0 01 0 0 00 1 0 00 1 0 00 0 2 01 1 0 00 3 2 20 1 2 42 9 3 41 10 4 52 4 3 00 0 0 0Total1072001112277182090Total008 34 20 16 78Hours of calm in this stability class: 0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:439 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotalWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total00300003121510787011890253164102132291500 10 45 47 30 15 147Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:440 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-1819-24 > 24 Total5381671020133413100175217426412513111710261801648352750538198142028283101924122411100228811263427010510000121101334321205880816016101372367313665102133990Total2 67 178218121 881Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:441 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total41151000402159172340361801006001333223141338385000720021012204303400817222344141827734341448984290Total3 30 69 19417767 540Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:442 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 240 2 8 8 10 1 1 0 02 1 2 0 02 2 5 0 01 4 0 0 01 3 2 0 02 3 3 1 02 6 0 1 35 4 2 2 01 5 1 1 14 2 6 5 51 4 9 2 51 3 16 8 30 7 21 23 20 6 18 23 00 4 10 9 10 0 0 0 0Total1926968101214112221315347240Total8 22 57 104 83 21 295Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:443 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total15114654111717101416101820140Total20 40 48 44 29 11 192Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in2stability class: 0all stability classes: 444 Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaTable D -3Period of Record: April -June 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-78-12 13-18 19-24 > 24 Total7313202428203455693145041833919423941321113175018000000001136000119001142153344762435816717223173230Total1 16931020 522Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:I45 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENE0100000027600 ii0 13E0155ESESESSESSSWSWWSWWWNW0 140000100056233530300233104437100050 1660 ii0 20090 110000054997NWNNWVariableTotal40 1120000000 130 1200003 97 32 140 146Hours of calm in thisHours of missing windstability class:measurements in this0stability class:all stability cl0asses:Hours of missing stability measurements in146 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENE1-3020014-7 8-12 13-18 19-24> 24 TotalEESESE000SSESSSWSWWSW0000000000000000000007832353241111W0WNWNWNNWVariable10105110Total5 28 11400 480es:Hours ofHours ofHours ofcalm inmissingmissingthis stability class: 0wind measurements in this stabilstability measurements in all stity class:ability class47 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3245725012001333404-7104483822920212887381016200qind Speed (in mph)8-12 13-181012335421515804510780000183229419000131019-24 > 240 00 00 00 00 00 00 00 04 01 00 00 00 00 00 00 00 0Total138659632202446533678162429330Total42 272129625 0 510Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in148 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total771155491419126613111651321010761016412616331920227000272114620122482010923221411203767672341343546141Total151 24862 1300 474Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:149 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3. 4-722232049971271410136000101000105176257008-12 13-18 19-24 > 240 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 0Total22333049107172420352060Total102630000 165Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:150 Table D -3Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotalWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total201210013111348945634150281010000000018496103021121001314569865401600 311Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in7stability class: 0all stability classes:151 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-70000000000000000000000000000000000Wind Speed (in mph)8-12 13-18 19-24 > 240 0 0 00 0 0 00 0 5 03 6 1 03 0 0 02 0 0 02 1 0 00 2 0 00 13 4 00 0 0 00 0 0 02 1 0 00 2 0 00 2 3 52 15 3 80 5 0 00 0 0 0Total005103232170032102850Total00 14 47 16 13 90Hours of calm in thisHours of missing windstability class:0measurements in this stalHours of missing stability measurements in allbility class: 0stability classes:152 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total011119131642122225204024014611303261860424249182010161126593190Total04 73 70 258 180Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:I53 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Unstable -380Ft-33Ft.Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total3059127111263415153053920131314201510561292090Total1 21 87 53 138 183Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in154 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-78-12111100210100000103 116 816 3311 2515 1415 1111 1910 415 374 242 144 35 54 105 177 100 013-18712137974929250788911019-24002301201637041191490> 240023062097320208450Total2216751345635377681931620293949430Total9 123282192108107821Hours of calm in this stability class:Hours of missingHours of missingwind measurements in thisstability measurements in0stability class: 0all stability classes:155 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 242 3 6 0 01 6 2 0 06 4 4 1 02 4 7 2 03 10 4 0 12 5 4 1 21 16 1 2 20 10 5 8 73 13 23 3 33 17 34 18 44 10 11 12 01 1 10 14 21 3 16 8 13 6 12 17 13 6 14 18 23 6 10 4 00 0 0 0 0Total14915171814233045763728293943240Total7 38 12016310825 461Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:156 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-700000011000200010200000102211020108-12 13-18 19-24 > 244 9 8 00 1 0 05 1 0 03 0 0 00 0 0 00 0 0 01 0 0 01 0 0 02 5 4 04 9 2 04 9 3 03 6 10 115 8 5 04 6 9 04 11 26 01 7 17 10 0 0 0Total23163003213171733182141280Total5 12 41 72 84 12 226Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in157 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in.mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 24 Total----- -----11640000001055468140----- ----- -----130000000048634150201812251935191126121429360Total10 33 56 73 446 222Hours of calm in this stability class:Hours of missingHours of missingwind measurements in thisstability measurements in0stability class: 0all stability classes:158 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total5516ý3719191252811345135000285224183612191941330000000001720000000195518452421362355223041392680Total0 16915600 344Hours of calm in this stability class: 0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:059 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-700100000010000000476126774437123971308-12 13-18 19-24 > 241 0 0 01 0 0 04 0 0 03 0 0 00 0 0 00 0 0 09 0 0 02 0 0 012 1 0 06 0 0 04 0 0 00 0 0 03 0 0 02 0 0 02 0 0 01 0 0 0o 0 0 0Total57111567166171011126119140Total2 ill49I00 163Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:060 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total001300311130101100339922931257547450Total6 58 25000 89Hours of calm in this stability class:0Hours of missing wind measurements in this stabiliHours of missing stability measurements in all staty class:bility cl0asses:061 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)4-7 8-12 13-181-361227289111617181113119121719005202370731617443243019-24 > 240 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0Total102251551716252035311921141624260Total43 236118500 402Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:062 Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Table D -5Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENE8 113430615 334 18 17E7278ESESESSESSSWSWWSWWWNWNW4 199151013815 590000003000000000030000000000000000000 2219 51 180718 3622 2110 127 219 1910 250 540 390 230 110 310 220 740 880 580 450 220 280 300 370 00 59142002NNWVariableTotal016603522070Hours of calm in this stability class:Hours of missingHours of missingwind measurements in thisstability measurements in2stability class: 0all stability classes: 063 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3520112266104-7 8-12 13-18 19-24 > 24 Total0011100033183000000000000000000000000000000000000000000000000000000000000005212222691523180 130 160 310 210 270 160 1317 10137036000Total1284000 168Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in1stability class: 0all stability classes:064 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNE.NEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total11010113117157514964622214141301012311715831506767251Total230000 437Hours of calm in this stability class:11Hours of missingHours of missingwind measurements in this stability class: 0stability measurements in all stability classes:065 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total000000001300000000Total000670 13Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:066 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total002105252103000010005000021151140061000710525417816410620Total00 31 45 110 87Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:067 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24N 0 0 4 1 0 0NNE 0 2 4 0 0 0NE 0 0 16 5 0 0ENE 0 4 16 8 0 0E 0 1 8 0 0 0ESE 0 3 9 0 0 0SE 0 1 15 4 0 0SSE 0 0 9 4 0 0S 0 0 2 9 3 0SSW 0 2 7 6 2 0SW 0 0 10 3 0 0WSW 0 0 1 1 0 0W 0 0 2 7 2 0WNW 0 0 3 5 0 0NW 0 0 13 7 1 0NNW 0 2 4 2 0 0Variable 0 0 0 0 0 0Total562128912201314171321182180Total0 15 1236280 208Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:068 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-1819-24 > 24 Total5171799111345211139497071734221818202021159161122101806833322429930352081011917064222214011426142040000715813002000002024471141005134703460804241323733450Total9 145278263ill 38 844Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:069 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable48345Ii8128211699433092141751968411764121402012100011018102111090771613132213161922371037941192331280Total10 50 1282219 495Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in070 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Stable -38OFt-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8:-12 13-18 19-24 > 24 Total10510021071010158511507001000010411566170201161154992019254021.1326280Total13 38 67 90 581 267Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in2stability class: 0all stability classes:071 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionWind Speed (in mph).8-12 13-18 19-24 > 24 Total1-3 4-7N1NNENEENEEESESESSESSSWSWWSW0113001030002110195443154425 17273003866916220002580 330 130 190 100009343 10 14WWNWNWNNWVariable5150094796311600 140 120 180 223 361 250 170 270 297 134 180000Total14 56 83 104304 291Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in1stability class:all stability cl0asses:072 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWW1-300000000000004-7 8-12 13-18 19-24 > 24 Total00000000000002411247889 129 113 264 330 210 220 320 42WNWNWNNW0004030350015000000070VariableTotal00 43 1030 161Hours of calm inHours of missingHours of missingthis stability class:wind measurements in thisstability measurements in0stability class: 0all stability classes:573 Table D -7Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESWind Speed (in mph)4-7 8-12 13-18 19-24 > 24 Total1-30000000000000000000000000052301394SSWSWWSWWWNW85647 144 110 110 210 16NWNNWVariableTotal00040101002000000500 50 51stability class:measurements in this0 103Hours of calm in thisHours of missing wind0stability class: 0all stability classes:Hours of missing stability measurements in574 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total812100040217415730Total1 23 27400 55Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in575 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total262616592101257182820314413030261961031913949113248150615738121031537262524393570102350Total49 2722452300 589Hours of calm in this stability class:1Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:576 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal156137115702518171520160148218207121024154841464984353204431002100311191515152022160140461435152318423467616571119776500 734Hours of calm inHours of missingthis stability class:wind measurements in this2stability class: 0all stability classes:Hours of missing stability measurements in577 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total12231203144517201817901100000011014122613620861333120315141929463123110Total1180000 204Hours of calm inHours of missingthis stability class:wind measurements in this3stability class: 0all stability classes:Hours of missing stability measurements in578 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7311120047516641333721700000000011341585308-12 13-18 19-24 > 240 0 0 0o o 0 0o 0 0 0o 0 0 0o 0 0 00 0 0 0o 0 o 0o 0 o 0o o 0 0o 0 0 00 0 0 0o o 0 0o 0 0 0o 0 0 0o 0 0 00 0 0 0Total31120048619681484526100Total302400000 342Hours of calm inHours of missingthis stability class:9wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:579 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7N 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0s 0SSW 0SW 0WSW 0W 0WNW 0NW 0NNW 0Variable 00000000000000000008-12 13-18 19-24 > 24o 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 1 00 0 0 00 0 0 0Total00000000000000100Total000101Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:580 Table D -8Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal0001000002026716003 16 105 34Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes: 581 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total00000012424109109000000000150001151020004220139371515312360Total02 28 51 346 121Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in582 Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Table D -8Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7N 0 5NNE 1 6NE 1 5ENE 1 2E 0 4ESE 1 2SE 0 4SSE 0 2S 1 1SSW 1 7SW 0 4WSW 1 4W 0 4WNW 0 4NW 0 5NNW 0 3Variable 0 08-12 13-18 19-24 > 2426 11 31 1623 15 18 106 14 16 31 1 3 34 3 0 03 2 0 011 2 2 06 15 21 32 8 5 27 12 11 617 19 6 19 25 7 025 23 14 219 29 43 1615 48 60 921 2 12 140 0 0 0Total89734511819471944474668ill137520Total7 62 19522924985 827Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:583 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total221013241549445127680191316101081252516172838321401026210161938381922553950001000231710116300463236231051636387769456810781310Total11 41 11625426335 720Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in1stability class: 0all stability classes:584 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total1953110412525121412706000000113201016311910338452964102525355642120Total2 16 52 93 10816 287Hours of calm in this stability class:0Hours of missingHours of missingwind measurements in this stability class: 0stability measurements in all stability classes:585 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotalWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total1100000102138561015100130000201440471840216300323107131691326392309 29 34 81 48 11 212Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in586 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -All Stabilities -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNW<0.5033211215214503440.5- 1.1-1 1.545 3420 2928 4923 2413 209 1813 2226 3238 4640 5567 76142 228234 331135 16388 16346 80Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total39 91 4440 77 4985 162 10436 148 14025 76 4824 76 4829 127 10831 87 9364 133 9444 146 11765 160 88139 157 83147 160 93120 234 144140 180 20395 139 8353 430 946 480 2212 103 336 665 2199 8363 6421 531 644 25104 65116 4969 18003182031134602216483610 3130 2570 4830 4920 2070 1830 3450 3710 5970 5940 4880 7930 10500 10160 9790 5350 8703Tot41 967 1370 1123 2153 1539872 394 236Hours of Calm ........ 45Hours of Variable Direction 2Hours of Valid Data .... 8750Hours of Missing Data ..10Hours in Period ...... .. 876087 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSector <0.50N 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0Sw 0WSW 0W 0WNW 0NW 0NNW 00.5- 1.1-1 1.50 00 00 00 00 10 00 00 00 00 00 00 00 00 00 00 0Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total0 13 6 11 8 0 14 21 19 112 41 50 212 31 27 01 39 36 10 23 67 200 4 38 262 1 18 440 13 17 80 16 24 120 14 23 191 16 42 201 8 43 350 26 71 490 15 29 150015000746103382721400000000218028242102010561196177110751325955619513818863Tot0 0 1 14 289 510 283135 84 30 1319Hours of Calm 0....... 0Hours of Variable Direction 0Hours of Valid Data .... 1319Hours of Missing Data ..10Hours in Period ...... .. 876088 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWiiDi]SecNNNNEENEEESESESSESSSWSWWSWWWNWNWNNWTot-idrection 0.5- 1.1- 1ctor <0.50 1 1.50 0 00 0 10 0 10 0 00 0 00 0 10 0 00 0 00 0 00 0 00 0 00 0 10 0 00 0 00 0 00 0 00 0 4Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... .......6-2444343101334623449Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 6912161991227664910921182721400524207931712891610111124027006713512915142000100111040214706.1- 8.1-8 100 00 00 04 00 00 00 01 01 03 01 00 05 03 02 00 020 0>10.000000000000000000Total19173043161746224327233540565535119 87 310 52410876089 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSector <0.50N 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0SW 00.5- 1.1-1 1.50 00 30 00 00 10 00 10 00 10 0o IWind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total2 42 18 82 91 41 31 100 31 31 23 64 41 46 102 52 712717176617142213111514372213WSWWWNWNWNNWTot0000000000010106377102531036100124100000000000 10 37 83 49 35 19 10 00 243Hours of Calm ..... ........ 0Hours of Variable Direction 0Hours of Valid Data .... 243Hours of Missing Data ..10Hours in Period ...... .. 876090 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWirDiiSecNNNNEENEEESESESSESSSWSWWSWWWNWNWNNWTotidrection 0.5- 1.1- 1-tor <0.50 1 1.51 5 72 0 120 2 180 5 70 1 20 3 90 0 40 1 40 3 40 1 40 2 40 2 100 1 120 6 80 2 120 2 153 36 132Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ...........6-2Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 612 3921 4128 7616 4912 228 1511 3510 456 425 198 2918 309 3415 4827 6032 45238 62910207910876026445761137111631251724273365363228303481721191855122831334911343471318119221496.1- 8.1-8 100 00 03 013 02 00 01 08 06 435 11 00 02 018 09 00 0>10.000000000000000000Total1261572151986446731121281266790106178220172493 312 132 98 5 0 207891 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirection 0.5- 1.1-Sector <0.50 1 1.5N 0 16 16NNE 0 11 9NE 1 15 25ENE 0 13 10E 1 7 10ESE 0 1 6SE 1 5 10SSE 0 12 19S 0 11 24SSW 0 11 25SW 0 11 25WSW 0 9 40W 0 12 31WNW 0 11 32NW 0 16 36NNW 1 21 19Tot 4 182 337Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total19 26 8 1210 12 5 040 39 21 212 28 20 145 8 5 411 7 2 113 29 16 119 29 25 945 79 25 1627 96 65 2926 89 37 344 80 14 542 73 11 137 115 49 2146 62 49 1934 44 15 18430 816 367 1550022601412281046657700000022613000100240 970 470 1450 990 460 280 780 1190 2180 2940 1920 1920 1740 2720 2340 1570 2392Hours of Calm ... ....... 4Hours of Variable Direction 1Hours of Valid Data .... 2397Hours of Missing Data ..10Hours in Period ...... .. 876092 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTotHours o0Hours ofHours olHours o0Hours ir0.5- 1.1- 1<0.50 1 1.51 17 90 4 41 3 50 2 40 2 31 2 10 4 72 4 90 8 120 10 130 15 190 22 340 18 571 11 39D 6 380 6 226 134 276f Calm ... ........f Variable Directionf Valid Data ....f Missing Data .n Period ... .......6213333119Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 66.1-88.1-10 >10.00 Total2 02 01 21 21 20 01 22 05 28 119 117 185 215 310 73 12 110507231087602910129841417274264ill131117814271893 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWirDi:SeNNN]NEEN]EES]SESSESSSýSWWS'WWNWNWNNWTotndrection 0.5- 1.1- 1ctor <0.50 1 1.51 7 2E 1 5 00 8 0E 1 3 30 3 31 3 10 4 03 9 02 16 51 18 134 39 275 109 1420 203 2312 107 834 64 773 17 2328 615 610Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... .......6-2000000204063253243210163Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 60300001001013120126.1- 8.1-8 100 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0>10.0000000000000000000Total1098765712273376289490218179531429351146510876094 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -All Stabilities -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTot<0.5000010000000000100.5- 1.1-1 1.52 61 62 65 53 84 55 123 41 64 70 11 61 22 15 53 5Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total7 25 349 40 5413 53 756 32 5613 33 4810 37 607 37 696 30 637 32 556 21 387 23 4110 37 385 29 403 22 306 34 576 30 576243785959388674616465464362746380619678202151541081088886968110660127 77 57 47785 48107 65122 8920 2515 468 1359 54145 78226 168135 131149 112184 126233 242289 300173 1362240882661052321477475762211867636953554125520035839952578956556060289710636092 42 85 121 515 815 977 1194 2137 16681188 8744Hours of Calm 6....... 6Hours of Variable Direction 0Hours of Valid Data .... 8750Hours of Missing Data ..10Hours in Period ...... .. 876095 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWirDirSecNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTotnd7ection 0.5- 1.1- 1$tor <0.50 1 1.50 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 0Hours of Calm ... ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... .......6-2Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1- 6.1-3 4 5 6 88.1-10 >10.00 Total00050002130002415400420000130012442001000000001110130007103232300045183561 8 13 45 32 26 1250012510876096 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at-380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in m/s)0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-1 1.5 2 3 4 5 6 8 10 >10.00 TotalWindDirectionSector <0.50N 0 0 0NNE 0 0 0NE 0 0 0ENE 0 0 0E 0 0 0ESE 0 0 0SE 0 0 0SSE 0 0 0S 0 0 0SSW 0 0 0SW 0 0 0WSW 0 0 0w 0 0 0WNW 0 0 0NW 0 0 0NNW 0 0 0Tot 0 0 0Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... ......0 10 10 12 122 117 103 140 40 10 11 20 10 10 00 20 2001010137572632687402200261786771134501490000955637145001200000.70261015152183714202615342320191934732015 64 77 111 68 44 3790037910876097 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirection 0.5- 1.1- 1Sector <0.50 1 1.5N 0 0 0NNE 0 0 0NE 0 0 0ENE 0 0 0E 0 0 0ESE 0 0 0SE 0 0 1SSE 0 0 0S 0 0 0SSW 0 0 0SW 0 0 0WSW 0 0 0W 0 0 0WNW 0 0 0NW 0 0 0NNW 0 0 0Tot 0 0 1Hours of Calm. .......Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... ......Wind Speed (in m/s).6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total0333143300111100242 6 2 13 3 0 19 14 11 315 15 15 611 11 1 013 9 1 06 19 8 30 14 13 80 3 8 192 6 8 85 11 4 80 6 8 154 2 14 231 9 9 226 17 16 248 4 10 1085 149 128 1510024000195038151436400010000070072316357111042592427403939362933598093386590065910876098 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTot<0. 5500.5- 1.1-1 1.5Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total0 0 1 2 10 19 28 35 24 320 1 2 5 18 23 22 36 49 380 1 2 4 32 40 34 51 73 480 0 1 2 16 26 16 35 74 600 0 0 7 18 25 17 9 13 210 0 1 7 19 26 12 9 8 20 2 4 2 16 35 24 15 30 80 0 1 2 10 31 34 18 26 240 0 1 1 9 20 34 48 47 120 1 1 2 9 15 19 35 70 530 0 1 3 9 13 22 39 28 150 0 1 3 20 12 14 28 36 250 0 1 3 14 16 24 32 48 290 0 0 3 10 17 27 30 57 540 0 1 4 17 32 25 42 62 960 1 2 4 16 25 36 19 49 340 6 20 54 243 375 388 481 694 55142223075243318796427917353561193216315305134871391641832841361431942893522393373Hours of Calm0Hours of Variable Direction0Hours of Valid Data .... 3373Hours of Missing Data ..10Hours in Period ...... .. 876099 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Wind Speed (in m/s)Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 TotalN 0 0 3 2 4 8 12 22 25 8 0 84NNE 0 0 1 2 10 16 7 14 20 1 0 71NE 0 0 0 3 11 12 15 15 16 6 8 86ENE 1 3 1 2 4 5 6 11 30 12 10 85E 0 0 0 1 6 7 13 7 5 4 2 45ESE 0 1 1 1 6 12 4 5 4 2 3 39SE 0 0 1 3 5 10 18 8 18 2 7 72SSE 0 0 1 1 3 14 10 11 14 24 28 106S 0 0 2 3 10 17 14 24 34 25 18 147SSW 0 1 3 1 3 10 20 40 110 89 52 329SW 0 0 0 0 5 6 19 23 56 76 43 228WSW 0 1 1 3 3 6 7 22 45 37 30 155W 0 0 1 0 6 7 9 21 61 48 7 160WNW 0 0 0 0 7 5 11 14 78 100 43 258NW 0 1 1 1 4 5 5 18 80 96 28 239NNW 0 0 1 1 7 9 10 8 45 28 3 112Tot 1 7 17 24 94 149 180 263 641 558 282 2216Hours of Calm ... ........ 1Hours of Variable Direction 0Hours of Valid Data .... 2217Hours of Missing Data ..10Hours in Period ...... .. 8760100 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWinDirSecNNNENEENEEESESESSESSSWSWWSWWWNWNWNNVTotndrection 0.5- 1.1- 1ctor <0.50 1 1.50 1 00 0 10 1 00 1 10 1 20 0 10 1 30 1 10 1 10 1 10 0 00 0 20 1 00 0 00 1 10 1 00 11 14Hours of CalmHours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... ......Wind Speed(in m/s).6-22.1- 3.1-3 40011311210441000194.1- 5.1-5 68 124 89 37 45 12 23 57 55 911 76 99 75 148 1212 134 56.1-838755138011161729313541228.1-10220010012810242626505339>10.0011000000411162818322811Total95222927161431295157891191051431569281 105 116 269 262150 1075201077108760101 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTotHoursHoursHours0.5- 1.1-<0.50 1 1.50 1 20 0 20 0 40 1 20 2 60 3 20 2 30 2 10 0 20 1 20 0 00 0 20 0 00 2 11 3 20 1 21 18 33of Calm .........of Variable Directiof Valid Data ...Wind Speed(in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 103 8 5 7 9 35 152 9 10 6 3 8 85 5 6 5 4 8 11 8 2 2 1 0 12 7 0 0 1 1 01 5 0 0 0 0 01 9 10 7 6 7 21 11 14 5 2 3 32 8 9 4 8 4 23 4 6 7 16 14 60 3 8 5 7 20 110 8 11 7 18 17 141 4 8 2 13 12 100 2 3 7 10 26 121 11 9 12 7 33 231 4 8 7 11 38 2524 106 109 83 116 226 1333on 0920>10. 0040000002219101012135Total894838181911474441606387607511510268 917Hours of Missing Data ..Hours in Period ..........108760102 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix EODCM RevisionsSee attached copy of CY-OC-1 70-301 Revision 6103 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix FERRATA104 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2013 ARERR1. A Program Deviation was not reported as required in the 2013 AnnualRadiological Effluent release Report in Section J. Program Deviations. A turbinebuilding (TB) effluent noble gas grab sample was not collected for July 2013.2. A Program Deviation was not reported as required in the 2013 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1, 2013 through December 31, 2013.3. An abnormal release was discovered in 2014 after the 2013 ARERR wassubmitted that was determined to impact the 2013 ARERR. There were multiplepages impacted by this abnormal release and all of the pages are included inthis errata section.105 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2013 through December 31, 2013EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16106 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportH. Radiation Effluent Monitors Out of Service More Than 30 DaysPer ODCM Control 3.3.3.10, "Radioactive Liquid Effluent MonitoringInstrumentation" and 3.3.3.11, "Radioactive Gaseous Effluent MonitoringInstrumentation" requires:With less than the minimum number of radioactive liquid/gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument toOPERABLE status within 30 days and, if unsuccessful, explain in the nextRadioactive Effluent Release Report why the inoperability was not corrected in atimely manner.The following is a discussion of instrumentation out of service for greater than 30days:1. The Offgas Building Exhaust Gaseous Effluent Radioactive Noble Gas Monitorwas out of service from 5/20/2013 through 8/9/2013. The monitor was taken outof service 5/20/2013 for failing the monitor functional test. The original issue forthe monitor failing the functional test was a faulty pushbutton on the alarm panelcausing the alarm not to function. Parts were ordered and replaced on6/18/2013 but the alarm still did not function as expected. After multipletroubleshooting attempts it was determined that the annunciator window cardwiring was the issue. After changing the wiring in the alarm panel, all alarmsresponded as expected. The functional test was reperformed 8/9/2013satisfactorily and the monitor was returned to service. This issue was enteredinto our Corrective Action Program (CAP) and corrective actions taken havebeen documented per process. All ODCM required compensatory measureswere met.1. Releases from the Independent Spent Fuel Storage Facility:The ISFSI is a closed system and the only exposure would be due to directradiation. This includes iodines, particulates, and noble gases. Based on offsiteTLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for2013. Because it is a sealed unit, no radioactive material was released.J. Program Deviations:1. The groundwater remediation composite sampler was found with no compositecollected on December 27, 2013. The composite sampler is required by ODCMTable 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.A manual sample was obtained per SP 10-003. Operations department wasnotified that composite sampler was not working and Operations secureddischarging from W-73 and Chemistry secured the composite sampler. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions taken have been documented per process.107 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportH. Radiation Effluent Monitors Out of Service More Than 30 DaysPer ODCM Control 3.3.3.10, "Radioactive Liquid Effluent MonitoringInstrumentation" and 3.3.3.11, Radioactive Gaseous Effluent MonitoringInstrumentation requires:With less than the minimum number of radioactive liquid/gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument toOPERABLE status within 30 days and, if unsuccessful, explain in the nextRadioactive Effluent Release Report why the inoperability was not corrected in atimely manner.The following is a discussion of instrumentation out of service for greater than 30days:1. The Offgas Building Exhaust Gaseous Effluent Radioactive Noble Gas Monitorwas out of service from 5/20/2013 through 8/9/2013. The monitor was taken outof service 5/20/2013 for failing the monitor functional test The original issue forthe monitor failing the functional test was a faulty pushbutton on the alarm panelcausing the alarm not to function. Parts were ordered and replaced on6/18/2013 but the alarm still did not function as expected. After multipletroubleshooting attempts it was determined that the annunciator window cardwiring was the issue. After changing the wiring in the alarm panel, all alarmsresponded as expected. The functional test was reperformed 8/9/2013satisfactorily and the monitor was returned to service. This issue was enteredinto our Corrective Action Program (CAP) and corrective actions taken havebeen documented per process. All ODCM required compensatory measureswere met.I. Releases from the Independent Spent Fuel Storage Facility:The ISFSI is a closed system and the only exposure would be due to directradiation. This includes iodines, particulates, and noble gases. Based on offsiteTLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for2013. Because it is a sealed unit, no radioactive material was released.J. Program Deviations:1. The groundwater remediation composite sampler was found with no compositecollected on December 27, 2013. The composite sampler is required by ODCMTable 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.A manual sample was obtained per SP 10-003. Operations department wasnotified that composite sampler was not working and Operations secureddischarging from W-73 and Chemistry secured the composite sampler. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions taken have been documented per process.2. A turbine building (TB) effluent noble gas grab sample was not collected for July2013. This sample is a requirement of Table 4.11.2.1.2-1, Radioactive GaseousWaste Sampling and Analysis Program, of CY-OC-170-301, ODCM for OysterCreek. The July sample was originally scheduled to be collected 7/5/13, but wasrescheduled to occur the following week so it could be collected in July. The108 Oyster Creek 2014 Annual Radioactive Effluent Release Reportsample was not rescheduled and tracked by the Chemistry Supervisoradequately, and a sample was not collected until the scheduled August sample8/1113. Historical data from July's TB RAGEMS low range monitor was trendedagainst the data from June and August with no discrepancies noted. There wereno isotopes identified in the Noble Gas Grab Samples from June and August.This issue was entered into our Corrective Action Program (CAP) and correctiveactions taken have been documented per process.3. The New Radwaste (NRVV)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2013 through December 31, 2013. TheNew Radwaste/Augmented Offgas Service Water Effluent sample was requiredby CY-OC-170-301, Offsite Dose Calculation Manual for Oyster CreekGenerating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling andAnalysis Program and was required to be sampled weekly for principal gammaemitters and 1-131. This issue occurred from the inclusion of this requirement inrevision 4 of the ODCM due to a misunderstanding of the system flow path. Itwas believed that all service water exited the site from the same release pointwhich was evident by the fact that the change paperwork included in thedescription of this change as being consistent with the practices at Oyster Creekand there was no modification to the sampling schedule. The NRW and AOGClosed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10.At that time NRW Closed Cooling Water system was determined to be apotentially contaminated system and was added to the sampling program forNRC Bulletin IE 80-10. The sampling program for IE 80-10 requires allpotentially contaminated systems to be sampled quarterly for gamma emitters.AOG Closed Cooling Water system was also reviewed but determined to not bea potentially contaminated system. Even though AOG was found not to be apotentially contaminated system sampling is still performed quarterly for gammaemitters. The potential pathway for a release from NRW/AOG Service WaterEffluent would be from a heat exchanger leak from the NRW Closed CoolingWater system into the Service Water side of the heat exchanger. The system isdesigned to maintain the Service Water side of the heat exchanger at a higherpressure than the Closed Cooling Water side so that if any leaks would developin the heat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were not obtainedand all samples were less than MDA for gamma emitters for that entire timeperiod.109 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportEXECUTIVE SUMMARYEffluents are strictly monitored to ensure that radioactivity released to the environment is aslow as reasonably achievable and does not exceed regulatory limits. Effluent control includesthe operation of monitoring systems, in-plant and environmental sampling and analysesprograms, quality assurance programs for the effluent and environmental programs, andprocedures covering all aspects of effluent and environmental monitoring.Both radiological environmental and effluent monitoring indicate that the operation of OysterCreek Generating Station (OCGS) does not result in significant radiation exposure to thepeople or the environment surrounding OCGS and is well below the applicable levels set by theNuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were liquid radioactive effluent releases during 2013 of concentrations of tritium too lowto detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution DischargeElimination System (NJPDES) permitted main condenser outfall. The releases were part ofnearly continuous pumping of groundwater at approximately 70 gpm containing low levels oftritium and no detectable gamma. Exelon and the State of New Jersey Department ofEnvironmental Protection (NJDEP) agreed to this remediation action instead of naturalattenuation to address concentrations of tritium in groundwater. Well 73 and supportingequipment and piping were installed to pump groundwater to the intake structure at the inlet ofthe main circulating water pumps. Provisions were established for both batch and continuousreleases of groundwater. Continuous releases occurred approximately 361 days in 2013. TheContinuous releases occurred from January 1, 2013 through December 27, 2013 with a total of3.50E+07 gallons of groundwater pumped resulting in 2.82E-01 Ci of tritium released to thedischarge canal. The dose to the most limiting member of the public due to the release ofgroundwater was 1.37E-06 mrem.There were no liquid abnormal releases during 2013.There was one gaseous abnormal release during 2013. During the annual inspection of theOld Radwaste Building exhaust fan connections to the main stack it was discovered that therewere three slits in the top boot connection of exhaust fan EF-1-16 and a bolt missing in theconnection of exhaust fan EF-1 -17.The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), andparticulates to any individual due to gaseous effluents was 4.93E-01 mrem, which wasapproximately 3.29E+00 percent of the annual limit of 15 mrem. The majority of organ dosefrom gaseous effluents was due to C-14. The maximum calculated gamma air dose in theUNRESTRICTED AREA due to noble gas effluents was 3.60E-03 mrad, which was 3.60E-02percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limitof 10 mrad.For comparison, the background radiation dose averages approximately 300 mrem per year in theCentral New Jersey area, which includes approximately 200 mrem from naturally occurring radongas and 100 mrem from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only110 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportEXECUTIVE SUMMARYEffluents are strictly monitored to ensure that radioactivity released to the environment is aslow as reasonably achievable and does not exceed regulatory limits. Effluent control includesthe operation of monitoring systems, in-plant and environmental sampling and analysesprograms, quality assurance programs for the effluent and environmental programs, andprocedures covering all aspects of effluent and environmental monitoring.Both radiological environmental and effluent monitoring indicate that the operation of OysterCreek Generating Station (OCGS) does not result in significant radiation exposure to thepeople or the environment surrounding OCGS and is well below the applicable levels set by theNuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were liquid radioactive effluent releases during 2013 of concentrations of tritium too lowto detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution DischargeElimination System (NJPDES) permitted main condenser outfall. The releases were part ofnearly continuous pumping of groundwater at approximately 70 gpm containing low levels oftritium and no detectable gamma. Exelon and the State of New Jersey Department ofEnvironmental Protection (NJDEP) agreed to this remediation action instead of naturalattenuation to address concentrations of tritium in groundwater. Well 73 and supportingequipment and piping were installed to pump groundwater to the intake structure at the inlet ofthe main circulating water pumps. Provisions were established for both batch and continuousreleases of groundwater. Continuous releases occurred approximately 361 days in 2013. TheContinuous releases occurred from January 1, 2013 through December 27, 2013 with a total of3.50E+07 gallons of groundwater pumped resulting in 2.82E-01 Ci of tritium released to thedischarge canal. The dose to the most limiting member of the public due to the release ofgroundwater was 1.37E-06 mrem.There were no liquid abnormal releases during 2013.There were two gaseous abnormal releases during 2013. During the annual inspection of theOld Radwaste Building exhaust fan connections to the main stack it was discovered that therewere three slits in the top boot connection of exhaust fan EF-1-16 and a bolt missing in theconnection of exhaust fan EF-1-17. During maintenance of the New Radwaste Buildingexhaust fan HV-S-54A, two slits were identified in the expansion joint and repaired.The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), andparticulates to any individual due to gaseous effluents was 4.94E-01 mrem, which wasapproximately 3.29E+00 percent of the annual limit of 15 mrem. The majority of organ dosefrom gaseous effluents was due to C-14. The maximum calculated gamma air dose in theUNRESTRICTED AREA due to noble gas effluents was 3.60E-03 mrad, which was 3.60E-02percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limitof 10 mrad.For comparison, the background radiation dose averages approximately 300 mrem per year in theCentral New Jersey area, which includes approximately 200 mrem from naturally occurring radongas and 100 mrem from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only111 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Reportexposure is due to direct radiation. Based on offsite TLD readings, dose due to direct radiationfrom the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive materialwas released.Comparison of environmental sampling results to iodine and particulate gaseous effluentsreleased, showed no radioactivity attributable to the operation of OCGS. Both elevated andground-level release paths were considered in this review, with total iodines released of 3.12E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.82E-02Ci.Joint Frequency Tables of meteorological data, per Stability Classification Category, as well asfor all stability classes, are included. All data was collected from the on-site MeteorologicalFacility. Data recoveries for the 380-foot data and the 33-foot data were 99.4 percent and 99.4percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for MeteorologicalFacility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.112 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Reportexposure is due to direct radiation. Based on offsite TLD readings, dose due to direct radiationfrom the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive materialwas released.Comparison of environmental sampling results to iodine and particulate gaseous effluentsreleased, showed no radioactivity attributable to the operation of OCGS. Both elevated andground-level release paths were considered in this review, with total iodines released of 3.12E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.84E-02Ci.Joint Frequency Tables of meteorological data, per Stability Classification Category, as well asfor all stability classes, are included. All data was collected from the on-site MeteorologicalFacility. Data recoveries for the 380-foot data and the 33-foot data were 99.4 percent and 99.4percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for MeteorologicalFacility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.113 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportE. Batch Releases:1. LiquThere were no batch releases of liquid effluents during 2013.2. GaseousThere were no batch releases of gaseous effluents during 2013.F. Abnormal Releases:There were no abnormal liquid releases during 2013.There was one abnormal gaseous release during 2013. During the performance ofWork Order R2205683, which is to perform an annual inspection of the stack padexhaust fans, three slits were discovered in the top boot of exhaust fan EF-1-16 anda bolt was missing from exhaust fan EF-1-17. These are the two exhaust fans forthe Old Radwaste Building to the Main Stack. One of these two exhaust fans is inoperation at all times to maintain a negative pressure in the Old Radwaste Building.At no times do both of these fans run simultaneously as each fans is designed toprovide 100% of the required flow. Engineering performed a calculation todetermine a release rate that encompasses the maximum release rate regardless ofwhich exhaust fan is in service. The activity to inspect the exhaust fans is anannual activity.The following assumptions were made when calculating Curies released and dose:* Both exhaust fans have been leaking since the date of the last inspectionuntil the time of the last repair, 7/29/12 through 7/25/13." All of the activity due to particulates reported from the Main Stack wascoming from the Old Radwaste Building and therefore being released as agroundlevel release from the exhaust fan leaks at the flow rate calculated byEngineering.Units Quarter Quarter Quarter Quarter 41 2 3Total Release Ci 4.94E-05 5.OOE-05 1.37E-05 O.OOE+00G. Revisions to the ODCM:There were no revisions to the ODCM during 2013.114 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportE. Batch Releases:1. LiuThere were no batch releases of liquid effluents during 2013.2. GaseousThere were no batch releases of gaseous effluents during 2013.F. Abnormal Releases:There were no abnormal liquid releases during 2013.There were two abnormal gaseous releases during 2013.During the performance of Work Order R2205683, which is to perform an annualinspection of the stack pad exhaust fans, three slits were discovered in the top bootof exhaust fan EF-1 -16 and a bolt was missing from exhaust fan EF-1 -17. Theseare the two exhaust fans for the Old Radwaste Building to the Main Stack. One ofthese two exhaust fans is in operation at all times to maintain a negative pressure inthe Old Radwaste Building. At no times do both of these fans run simultaneously aseach fans is designed to provide 100% of the required flow. Engineering performeda calculation to determine a release rate that encompasses the maximum releaserate regardless of which exhaust fan is in service. The activity to inspect theexhaust fans is an annual activity.The following assumptions were made when calculating Curies released and dose:* Both exhaust fans have been leaking since the date of the last inspectionuntil the time of the last repair, 7/29/12 through 7/25/13." All of the activity due to particulates reported from the Main Stack wascoming from the Old Radwaste Building and therefore being released as aground level release from the exhaust fan leaks at the flow rate calculatedby Engineering.Quarter Quarter QuarterUnits 1 1 2 1 3 Quarter 41 2 3Total Release Ci 4.94E-05 5.OOE-05 I 1.37E-05 O.00E+O0During the performance of Work Order R2227008, which is to perform an annualinspection of the New Radwaste (NRW) exhaust fan HV-S-54A, two slits werediscovered in the expansion joint. This is one of the exhaust fans for the NewRadwaste Building to the Main Stack. Note that the exhaust from HV-S-54A isnormally to the atmosphere but through the monitored stack effluent release point.Engineering performed a calculation to determine a release rate that encompassesthe maximum release rate for both slits. The activity to inspect the exhaust fan is anannual activity.The following assumptions were made when calculating Curies released and dose:115 Oyster Creek 2014 Annual Radioactive Effluent Release Report" The exhaust fan has been leaking since the date of the last inspection untilthe time of the repair, 8/20/13 through 7/25/14.* All of the activity due to particulates reported from the Main Stack wascoming from the New Radwaste Building and therefore being released as agroundlevel release from the exhaust fan leaks at the flow rate calculated byEngineering." HV-S-54A was in operation the entire time since the last inspection wasperformed.Units Quarter Quarter Quarter Quarter 41 2 3Total Release Ci 0.000e 0.OOeO 4.08E-05 9.00E-05G. Revisions to the ODCM:There were no revisions to the ODCM during 2013.116 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-I: Gaseous Effluents- Summary Of All ReleasesPeriod: January 1, 2013 through December 31, 2013Unit: Oyster Creek1 IEst° TotalA. Fission &Activation Gases j Units Quarter I IQuarter 2 Quarter 3 Quarter 4 Error %=_. -1. Total ReleaseCi2.06E+011.40E+017.04E+00 I 8.02E+00 I 25.00% I2. Average Release Rate for PeriodSULdI MWVOWC I %A I 0.10UU I.or-w ;.Oe'I-U12. Average Release Rate for Period I uCi/sec 1 1.12E+00 I 8.14E-01 4.90E-01 I 7.32E-0112. Percent of ODCM Limit* ODCM Limit is for combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.117 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-I: Gaseous Effluents -Summary Of All ReleasesPeriod: January 1, 2013 through December 31, 2013Unit: Oyster CreekY I I -A. Fission & Activation GasesESt. Iola,Quarter 4 Error %'. aI I L".J JD= I ,,,,5,,, I j.wJL_--, I ,2. Percent of ODCM Limit I % 56.67E-01 1* ODCM Limit is fkr combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.118 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-3: Gaseous Effluent Release Point: Ground Level ReleasesPeriod: January 1, 2013 through December 31, 2013Unit: Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gasei Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 33m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 35 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-i 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 38 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2. lodines1-131 Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD3. ParticulatesSr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-1 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-137 Ci 2.57E-07 2.59E-07 7.13E-08 <LLD <LLD <LLD <LLD <LLDBa-140 Ci 2.62E-05 2.65E-05 7.28E-06 <LLD <LLD <LLD <LLD <LLDLa-1 40 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci 5.30E-06 5.35E-06 1.47E-06 <LLD <LLD <LLD <LLD <LLDMn-54 Ci 4.78E-06 5.64E-06 1.22E-06 1.80E-05 <LLD <LLD <LLD <LLDCo-58 Ci 3.86E-06 1.33E-05 4.02E-06 3.51 E-07 <LLD <LLD <LLD <LLDCo-60 Ci 1.17E-05 2.86E-05 1.69E-05 8.87E-05 <LLD <LLD <LLD <LLDNi-63 Ci 2.74E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 7.96E-07 8.05E-07 2.21E-07 <LLD <LLD <LLD <LLD <LLDAg-1I0m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 2.09E-06 2.11E-06 5.81E-07 <LLD <LLD <LLD <LLD <LLDAm-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 8.24E-05 8.26E-05 3.18E-05 1.07E-04 <LLD <LLD <LLD <LLD4. TritiumH-3 Ci 2.88E-01 1.22E-01 2.93E-01 2.05E-01 <LLD <LLD <LLD I <LLD5. Gross AlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14 .....C-14 Ci 7.40E-02 7.49E-02 I 7.57E-02 17.57E-02 <LLD <LLD <LLD <LLD119 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-3: Gaseous Effluent Release Point: Ground Level ReleasesPeriod: January 1, 2013 through December 31, 2013Unit Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gase Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-I 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2. lodines1-131 Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Pedod Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD3. Particulates -Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-1 37 Ci 2.57E-07 2.59E-07 4.55E-07 8.47E-07 <LLD <LLD <LLD <LLDBa-140 Ci 2.62E-05 2.65E-05 1.28E-05 1.22E-05 <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci 5.30E-06 5.35E-06 4.58E-06 6.86E-06 <LLD <LLD <LLD <LLDMn-54 Ci 4.78E-06 5.64E-06 4.94E-06 2.62E-05 <LLD <LLD <LLD <LLDCo-58 Ci 3.86E-06 1.33E-05 1.47E-05 2.38E-05 <LLD <LLD <LLD <LLDCo-60 Ci 1.17E-05 2.86E-05 2.93E-05 1.16E-04 <LLD <LLD <LLD <LLDNi-63 Ci 2.74E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 7.96E-07 8.05E-07 125E-06 2.26E-06 <LLD <LLD <LLD <LLDAg-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 2.09E-06 2.11 E-06 4.62E-06 8.90E-06 <LLD <LLD <LLD <LLDAm-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 8.24E-05 8.26E-05 7.26E-05 l1.97E-04 <LLD <LLD <LLD <LLD4. Tritium LH-3 Ci 2.88E-01 1.22E-01 2.93E-01 2,05E-01 <LLD <LLD <LLD <LLD5. Gross AlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14C-14 Ci 7.40E-02 7.49E-02 7.57E-02 7.57E-02 <LLD <LLD <LLD <LLD120 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportLocation % ofApplicable Estimated Age Distance Direction ApplicableEffluent Organ Dose Group (meters) (toward) Limit Limit UnitGamma -Noble Gas Air Dose 3.60E-03 All 500 ESE 3.60E-02 10 mradBeta -AirNoble Gas Dose 8.44E-04 All 500 ESE 4.22E-03 20 mradTotal BodyNoble Gas (Gamma) 1.42E-03 All 937 SE 2.84E-02 5 mremNoble Gas Skin (Beta) 1.77E-03 All 972 ESE 1.18E-02 15 mremIodine,Particulate, Bone 4.93E-01 Child 937 SE 3.29E+00 15 mremCarbon-14 &TritiumLiquid Total body 1.37E-06 All South Route 9 4.57E-05 3 mremLiquid Organ 1.37E-06 All Bridge 1.37E-05 10 mremDirect Radiation Total Body 5.39E+00 All 483 W 2.16E+01 25 mremDirect Radiation Total Body <LLD All 937 SE <LLD 25 mrem40 CFR Part 190 ComplianceWarehouse WorkerTotal Dose JTotal Body 5.39E+00 All 483 W 2.16E+01 25 mremTotal Dose Bone 5.50E+00 All 483 W 2.20E+01 J 25 mremTotal Dose Thyroid 5.39E+00 All 483 W 7.19E+00 1 75 mremNearest ResidentTotal Dose Total BodyJ 3.60E-03 All 937 SE 1.44E-02 25 mremTotal Dose J Bone 4.97E-01 All 937 SE 1.99E+00 25 mremTotal Dose Thyroid 3.60E-03 All 937 SE 4.80h-03 75 m121 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportLocation % ofApplicable Estimated Age Distance Direction ApplicableEffluent Organ Dose Group (meters) (toward) Limit Limit UnitGamma -Noble Gas Air Dose 3.60E-03 All 500 ESE 3.60E-02 10 mradBeta -AirNoble Gas Dose 8.44E-04 All 500 ESE 4.22E-03 20 mradTotal BodyNoble Gas (Gamma) 1.42E-03 All 937 SE 2.84E-02 5 mremNoble Gas Skin (Beta) 1.77E-03 All 972 ESE 1.18E-02 15 mremIodine,Particulate, Bone 4.94E-01 Child 937 SE 3.29E+00 15 mremCarbon-14 &TritiumLiquid Total body 1.37E-06 All South Route 9 4.57E-05 3 mremLiquid Organ 1.37E-06 All Bridge 1.37E-05 10 mremDirect Radiation Total Body 5.39E+00 All 483 W 2.16E+01 25 mremDirect Radiation Total Body <LLD All 937 SE <LLD 25 mrem40 CFR Part 190 ComplianceWarehouse WorkerTotal Dose Total Body 5.39E+00 All 483 W 2.16E+01 25 mremTotal Dose Bone 5.50E+00 All 483 W 2.20E+01 25 mremTotal Dose Thyroid 5.39E+00 All 483 W 7.19E+00 75 mremNearest ResidentTotal Dose Total Body 3.60E-03 All 937 SE 1.44E-02 25 mremTotal Dose Bone 4.98E-01 All 937 SE 1.99E+00 25 mremTotal Dose Thyroid I3.E-03 All1 937 SE I4.80E-3 I7 mrem122 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2012 ARERR1. A Program Deviation was not reported as required in the 2012 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1, 2012 through December 31, 2012.123 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2012 through December 31, 2012EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16124 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2012 Annual Radioactive Effluent Release ReportJ. Program Deviations:1 A turbine building (TB) effluent noble gas grab sample was not collected forSeptember 2012. This sample is a requirement of Table 4.11.2.1.2-1,Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-1 70-301, ODCM for Oyster Creek. The September sample was originallyscheduled to be collected 8/31/12, but was rescheduled to occur the followingweek so it could be collected in September. The sample was not rescheduledand tracked by the Chemistry Supervisor adequately, and a sample was notcollected until the scheduled October sample 10/5/12. Historical data fromSeptember's TB RAGEMS low range monitor was trended against the datafrom August and October with no discrepancies noted. There were noisotopes identified in the Noble Gas Grab Samples from August and October.This issue was entered into our Corrective Action Program (CAP) andcorrective actions taken have been documented per process.2. The groundwater remediation composite sampler was found out of service forless than eight hours on October 19, 2012. The composite sampler isrequired by ODCM Table 4.11.1 .1 .1-1, Radioactive Liquid Waste Samplingand Analysis Program. There was enough sample in the composite samplerto perform the required analyses and the composite sampler was immediatelyreturned to service. This issue was entered into our Corrective ActionProgram (CAP) and corrective actions taken have been documented perprocess.125 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2012 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. A turbine building (TB) effluent noble gas grab sample was not collected forSeptember 2012. This sample is a requirement of Table 4.11.2.1.2-1,Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-170-301, ODCM for Oyster Creek. The September sample was originallyscheduled to be collected 8/31/12, but was rescheduled to occur the followingweek so it could be collected in September. The sample was not rescheduledand tracked by the Chemistry Supervisor adequately, and a sample was notcollected until the scheduled October sample 10/5/12. Historical data fromSeptember's TB RAGEMS low range monitor was trended against the datafrom August and October with no discrepancies noted. There were noisotopes identified in the Noble Gas Grab Samples from August and October.This issue was entered into our Corrective Action Program (CAP) andcorrective actions taken have been documented per process.2. The groundwater remediation composite sampler was found out of service forless than eight hours on October 19, 2012. The composite sampler isrequired by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Samplingand Analysis Program. There was enough sample in the composite samplerto perform the required analyses and the composite sampler was immediatelyreturned to service. This issue was entered into our Corrective ActionProgram (CAP) and corrective actions taken have been documented perprocess.3. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2012 through December 31, 2012. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by CY-OC-1 70-301, Offsite Dose Calculation Manual for OysterCreek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid WasteSampling and Analysis Program and was required to be sampled weekly forprincipal gamma emitters and 1-131. This issue occurred from the inclusion ofthis requirement in revision 4 of the ODCM due to a misunderstanding of thesystem flow path. It was believed that all service water exited the site from thesame release point which was evident by the fact that the change paperworkincluded in the description of this change as being consistent with thepractices at Oyster Creek and there was no modification to the samplingschedule. The NRW and AOG Closed Cooling Water systems were reviewedas part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Watersystem was determined to be a potentially contaminated system and wasadded to the sampling program for NRC Bulletin IE 80-10. The samplingprogram for IE 80-10 requires all potentially contaminated systems to besampled quarterly for gamma emitters. AOG Closed Cooling Water systemwas also reviewed but determined to not be a potentially contaminatedsystem. Even though AOG was found not to be a potentially contaminatedsystem sampling is still performed quarterly for gamma emitters. The potentialpathway for a release from NRWIAOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into theService Water side of the heat exchanger. The system is designed to126 Oyster Creek 2014 Annual Radioactive Effluent Release Reportmaintain the Service Water side of the heat exchanger at a higher pressurethan the Closed Cooling Water side so that if any leaks would develop in theheat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were notobtained and all samples were less than MDA for gamma emitters for thatentire time period.127 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2011 ARERR1. A Program Deviation was not reported as required in the 2011 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1,2011 through December 31, 2011.128 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2011 through December 31, 2011EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16129 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2011 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. During Augmented Off Gas (AOG) sample line pressue testing conductedFebruary 21, 2011, it was discovered that the sample line was not able tomaintain pressure due to the filter assembly not being tight. The filterassembly was tightened and the pressure test was completed SAT. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions implemented to ensure filter assemblies are tight when installed forsampling. The weekly sample results were evaluated against previous sampleresults for impact to sampling due to the assembly not being tight with noimpact identified.2. The groundwater remediation composite sampler was found out of service forless than one day on March 29, 2011. The composite sampler is required byODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and AnalysisProgram. There was enough sample in the composite sampler to perform therequired analyses and the composite sampler was immediately returned toservice.3. The groundwater remediation composite sampler was found out of service forfor approximately 4 hours on August 21, 2011. The composite sampler isrequired by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Samplingand Analysis Program. The composite sampler was immediately returned toservice and enough sample was collected in the composite sampler to performthe required analyses.130 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2011 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. During Augmented Off Gas (AOG) sample line pressue testing conductedFebruary 21, 2011, it was discovered that the sample line was not able tomaintain pressure due to the filter assembly not being tight. The filterassembly was tightened and the pressure test was completed SAT. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions implemented to ensure filter assemblies are tight when installed forsampling. The weekly sample results were evaluated against previous sampleresults for impact to sampling due to the assembly not being tight with noimpact identified.2. The groundwater remediation composite sampler was found out of service forless than one day on March 29, 2011. The composite sampler is required byODCM Table 4.11 .1 .1.1-1, Radioactive Liquid Waste Sampling and AnalysisProgram. There was enough sample in the composite sampler to perform therequired analyses and the composite sampler was immediately returned toservice.3. The groundwater remediation composite sampler was found out of service forfor approximately 4 hours on August 21, 2011. The composite sampler isrequired by ODCM Table 4.11.1.1.1.-1, Radioactive Liquid Waste Samplingand Analysis Program. The composite sampler was immediately returned toservice and enough sample was collected in the composite sampler to performthe required analyses.4. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2011 through December 31, 2011. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by CY-OC-1 70-301, Offsite Dose Calculation Manual for OysterCreek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid WasteSampling and Analysis Program and was required to be sampled weekly forprincipal gamma emitters and 1-131. This issue occurred from the inclusion ofthis requirement in revision 4 of the ODCM due to a misunderstanding of thesystem flow path. It was believed that all service water exited the site from thesame release point which was evident by the fact that the change paperworkincluded in the description of this change as being consistent with thepractices at Oyster Creek and there was no modification to the samplingschedule. The NRW and AOG Closed Cooling Water systems were reviewedas part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Watersystem was determined to be a potentially contaminated system and wasadded to the sampling program for NRC Bulletin IE 80-10. The samplingprogram for IE 80-10 requires all potentially contaminated systems to besampled quarterly for gamma emitters. AOG Closed Cooling Water systemwas also reviewed but determined to not be a potentially contaminatedsystem. Even though AOG was found not to be a potentially contaminatedsystem sampling is still performed quarterly for gamma emitters. The potentialpathway for a release from NRW/AOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into the131 Oyster Creek 2014 Annual Radioactive Effluent Release ReportService Water side of the heat exchanger. The system is designed tomaintain the Service Water side of the heat exchanger at a higher pressurethan the Closed Cooling Water side so that if any leaks would develop in theheat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were notobtained and all samples were less than MDA for gamma emitters for thatentire time period.132 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2010 ARERR1. A Program Deviation was not reported as required in the 2010 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1, 2010 through December 31, 2010.133 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2010 through December 31, 2010EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16134 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2010 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. Procedure 621.3.037, Turbine Building RAGEMS Noble Gas Monitor -Functional Test was not performed at the frequency required by ODCM Table4.3.3.11-1. The test was required to be performed by November 13, 2010 andwas completed on December 2, 2010.2. The groundwater remediation composite sampler was found out of service forless than one day on November 30, 2010. The composite sampler is requiredby ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling andAnalysis Program. A grab sample was taken as a compensatory measure andthe composite sample was immediately returned to service.3. On December 18, 2010 at 04:00 the stack monitor noble gas monitor countrate was discovered to be much lower than expected. A valve was found tobe out of position causing a dilution in the sample concentration. Based onthe stack monitor noble gas monitor readings, the valve had been open for 15hours. The valve was placed in the correct, closed position, immediately andthe count rate returned to normal.4. The stack sample line was discovered separated on April 7, 2010. A rootcause analysis concluded that the sample line was first separated aboutJanuary 1, 2006. The sample line was returned to service on April 20, 2010.135 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2010 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. Procedure 621.3.037, Turbine Building RAGEMS Noble Gas Monitor -Functional Test was not performed at the frequency required by ODCM Table4.3.3.11-1. The test was required to be performed by November 13, 2010 andwas completed on December 2, 2010.2. The groundwater remediation composite sampler was found out of service forless than one day on November 30, 2010. The composite sampler is requiredby ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling andAnalysis Program. A grab sample was taken as a compensatory measure andthe composite sample was immediately returned to service.3. On December 18, 2010 at 04:00 the stack monitor noble gas monitor countrate was discovered to be much lower than expected. A valve was found tobe out of position causing a dilution in the sample concentration. Based onthe stack monitor noble gas monitor readings, the valve had been open for 15hours. The valve was placed in the correct, closed position, immediately andthe count rate returned to normal.4. The stack sample line was discovered separated on April 7, 2010. A rootcause analysis concluded that the sample line was first separated aboutJanuary 1, 2006. The sample line was returned to service on April 20, 2010.5. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2010 through December 31, 2010. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by CY-OC-170-301, Offsite Dose Calculation Manual for OysterCreek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid WasteSampling and Analysis Program and was required to be sampled weekly forprincipal gamma emitters and 1-131. This issue occurred from the inclusion ofthis requirement in revision 4 of the ODCM due to a misunderstanding of thesystem flow path. It was believed that all service water exited the site from thesame release point which was evident by the fact that the change paperworkincluded in the description of this change as being consistent with thepractices at Oyster Creek and there was no modification to the samplingschedule. The NRW and AOG Closed Cooling Water systems were reviewedas part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Watersystem was determined to be a potentially contaminated system and wasadded to the sampling program for NRC Bulletin IE 80-10. The samplingprogram for IE 80-10 requires all potentially contaminated systems to besampled quarterly for gamma emitters. AOG Closed Cooling Water systemwas also reviewed but determined to not be a potentially contaminatedsystem. Even though AOG was found not to be a potentially contaminatedsystem sampling is still performed quarterly for gamma emitters. The potentialpathway for a release from NRW/AOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into theService Water side of the heat exchanger. The system is designed tomaintain the Service Water side of the heat exchanger at a higher pressurethan the Closed Cooling Water side so that if any leaks would develop in the136 Oyster Creek 2014 Annual Radioactive Effluent Release Reportheat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were notobtained and all samples were less than MDA for gamma emitters for thatentire time period.137 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2009 ARERR1. A Program Deviation was not reported as required in the 2009 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedSeptember 29, 2009 through December 31, 2009.138 Oyster Creek 2014 Annual Radioactive Effluent Release Report2009Annual Radioactive Effluent Release ReportOyster Creek Generating StationRevision 2Issued 2012139 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2009 through December 31, 2009EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16140 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2009 Annual Radioactive Effluent Release ReportThe maximum hypothetical calculated organ dose from iodines, tritium and particulates to anyindividual due to gaseous effluents was 3.38E-02 mrem, which was approximately 2.25E-01percent of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTEDAREA due to noble gas effluents was 4.55E-03 mrem, which was 4.55E-02 percent of theannual limit.For comparison, the background radiation dose averages approximately 300 mRem per year inthe Central New Jersey area, which includes approximately 200 mrem per year from naturallyoccurring radon gas and 100 mrem per year from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposurewould be due to direct radiation. This includes iodines, particulates and noble gases. Based onoffsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mRem for 2009.Because it is a sealed unit, no radioactive material was released.Additionally, comparison of environmental sampling results to iodine and particulate gaseouseffluents released, showed no radioactivity attributable to the operation of OCGS. Bothelevated and ground-level release paths were considered in this review, with total iodinesreleased of 1.78E-02 Ci and total particulates with half-lives greater than 8 days released of2.50E-02 Ci.Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stabilityclasses, are included. All data was collected from the on-site Meteorological Facility. Datarecoveries for the 380-foot data and the 33-foot data were 97.8 percent and 97.8 percent,respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facilitydata recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.141 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2009 Annual Radioactive Effluent Release ReportThe maximum hypothetical calculated organ dose from iodines, tritium and particulates to anyindividual due to gaseous effluents was 3.38E-02 mrem , which was approximately 2.25E-01percent of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTEDAREA due to noble gas effluents was 4.55E-03 mrem, which was 4.55E-02 percent of theannual limit.For comparison, the background radiation dose averages approximately 300 mRem per year inthe Central New Jersey area, which includes approximately 200 mrem per year from naturallyoccurring radon gas and 100 mrem per year from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposurewould be due to direct radiation. This includes iodines, particulates and noble gases. Based onoffsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mRem for 2009.Because it is a sealed unit, no radioactive material was released.Additionally, comparison of environmental sampling results to iodine and particulate gaseouseffluents released, showed no radioactivity attributable to the operation of OCGS. Bothelevated and ground-level release paths were considered in this review, with total iodinesreleased of 1.78E-02 Ci and total particulates with half-lives greater than 8 days released of2.50E-02 Ci.Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stabilityclasses, are included. All data was collected from the on-site Meteorological Facility. Datarecoveries for the 380-foot data and the 33-foot data were 97.8 percent and 97.8 percent,respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facilitydata recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.The New Radwaste (NRW)/Augmented Offas (AOG) Service Water Effluent sample was notcollected September 29, 2009 through December 31, 2009. The New Radwaste/AugmentedOffas Service Water Effluent sample was required by CY-OC-170-301, Offsite DoseCalculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive LiquidWaste Sampling and Analysis Program and was required to be sampled weekly for principalgamma emitters and 1-131. This issue occurred from the inclusion of this requirement inrevision 4 of the ODCM due to a misunderstanding of the system flow path. It was believedthat all service water exited the site from the same release point which was evident by the factthat the change paperwork included in the description of this change as being consistent withthe practices at Oyster Creek and there was no modification to the sampling schedule. TheNRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Water system was determined to be a potentiallycontaminated system and was added to the sampling program for NRC Bulletin IE 80-10. Thesampling program for IE 80-10 requires all potentially contaminated systems to be sampledquarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed butdetermined to not be a potentially contaminated system. Even though AOG was found not tobe a potentially contaminated system sampling is still performed quarterly for gamma emitters.The potential pathway for a release from NRW/AOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into the Service Water sideof the heat exchanger. The system is designed to maintain the Service Water side of the heatexchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would142 Oyster Creek 2014 Annual Radioactive Effluent Release Reportdevelop in the heat exchanger it would be Service Water leaking into the Closed Cooling Waterside. A review was performed for both NRW and AOG quarterly Closed Cooling Watersamples for the time that the required samples were not obtained and all samples were lessthan MDA for gamma emitters for that entire time period.143 Aw"w Exeton Generation.CY-OC-1 70-301Revision 6Page I of 140OFFSITE DOSE CALCULATION MANUALFOROYSTER CREEK GENERATING STATIONRevision of this document requires PORC approval and changes are controlled byCY-AA-1 70-3100122014 CY-OC-170-301Revision 6Page 2 of140TABLE OF CONTENTSINTRODUCTIONPART 1 -RADIOLOGICAL EFFLUENT CONTROLS1.03/4DEFINITIONSCONTROLS AND SURVEILLANCE REQUIREMENTS3/4.0 APPLICABILITY3/4.3 INSTRUMENTATION3/4.3.3.103/4.3.3.11RADIOACTIVE LIQUID EFFLUENT MONITORINGINSTRUMENTATIONRADIOACTIVE GASEOUS EFFLUENT MONTIORINGINSTRUMENTATION3/4.11 RADIOACTIVE EFFLUENTS3/4.11.1LIQUID EFFLUENTS3/4.11.1.13/4.11.1.23/4.11.1.33/4.11.23/4.11.2.13/4.11.2.23/4.11.2.33/4.11.2.43/4.11.33/4.11.43/4.123/4.12.13/4.12.23/4.12.33/4.12.4CONCENTRATIONDOSELIQUID WASTE TREATMENT SYSTEMGASEOUS EFFLUENTSDOSE RATEDOSE -NOBLE GASESDOSE -IODINE -131, IODINE -133, TRITIUM, ANDRADIONUCLIDES IN PARTICULATE FORMGASEOUS RADWASTE TREATMENT SYSTEMMARK I CONTAINMENTTOTAL DOSERADIOLOGICAL ENVIRONMENTAL MONITORINGMONITORING PROGRAMLAND USE CENSUSINTERLABORATORY COMPARISON PROGRAMMETEOROLOGICAL MONITORING PROGRAM122014 CY-OC-170-301Revision 6Page 3 of140BASES FOR SECTIONS 3.0 AND 4.03/4.3 INSTRUMENTATION3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORINGINSTRUMENTATION3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORINGINSTRUMENTATION3/4.11 RADIOACTIVE EFFLUENTS3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATION3/4.11.1.2 DOSE3/4.11.1.3 LIQUID RADWASTE TREATMENT3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSE RATES3/4.11.2.2 DOSE -NOBLE GAS3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM,AND RADIONUCLIDES IN PARTICULATE FORM3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM3/4.11.3 MARK I CONTAINMENT3/4.11.4 TOTAL DOSE3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAM3/4.12.2 LAND USE CENSUS3/4.12.3 INTERLABORATORY COMPARISON PROGRAM5.0 DESIGN FEATURES / SITE MAP6.0 ADMINISTRATIVE CONTROLS6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATINGREPORT (AREOR)6.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)6.3 RESPONSIBILITES122014 CY-OC-170-301Revision 6Page 4 of 140PART II -CALCULATIONAL METHODOLOGIES1.0 LIQUID EFFLEUNTS1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS1.2 LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION1.2.1 LIQUID EFFLUENT MONITORS1.2.2 SAMPLE RESULT SET POINTS1.2.3 ASSUMED DISTRIBUTION SET POINTS1.3 BATCH RELEASES1.4 CONTINUOUS RELEASES1.5 LIQUID EFFLUENT DOSE CALCULATION -10 CFR 501.5.1 MEMBER OF THE PUBLIC DOSE -LIQUID EFFLUENTS1.5.2 SHORELINE DEPOSIT DOSE1.5.3 SHORELINE DOSE EXAMPLE 11.5.3.1 SHORELINE DOSE EXAMPLE 21.5.4 INGESTION DOSE -LIQUID1.5.5 INGESTION DOSE CALCULATION EXAMPLE 11.5.5.1 INGESTION DOSE CALCULATION EXAMPLE 21.5.6 PROJECTED DOSE -LIQUID1.6 REPRESENTATIVE SAMPLES2 GASEOUS EFFLUENTS2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS2.2. GASEOUS EFFLUENT MONITOR SET POINT DETERMINATION2.2.1 PLANT VENT2.2.2 OTHER RELEASE POINTS2.2.3 RADIONUCLIDE MIX FOR SET POINTS2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATECALCULATIONS 10 CFR 202.3.1 SITE BOUNDARY DOSE RATE -NOBLE GASES2.3.1.1 TOTAL BODY DOSE RATE2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE2.3.1.3 SKIN DOSE RATE122014 CY-OC-170-301Revision 6Page 5 ofl1402.3.1.4 EXAMPLE SKIN DOSE RATE2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE ANDPARTICULATES2.3.2.1 METHOD -SITE BOUNDARY DOSE RATE -RADIOIODINE ANDPARTICULATES2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATECALCULATION2.4 NOBLE GAS EFFLUENT DOSE CALCULATION -10 CFR 502.4.1 UNRESTRICTED AREA DOSE -NOBLE GASES2.4.1.1 AIR DOSE METHOD2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION2.4.1.3 INDIVIDUAL PLUME DOSE METHOD2.5 RADIOIODINE PARTICULATE AND OTHER RADIONUCLIDES DOSECALCULATIONS -10 CFR 502.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES,ANDOTHER RADIONUCLIDES2.5.2 EXAMPLE CALCULATION -INHALATION OF RADIOIODINES,TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES2.5.3 INGESTION OF RADIOIODINES, PARTICULATES ANDOTHER RADIONUCLIDES2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGEAND VEGETATION -OTHER THAN TRITIUM2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THERADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION -OTHER THAN TRITIUM2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE ANDVEGETATION2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM INANIMAL FORAGE AND VEGETATION2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THERADIONUCLIDE IN MILK AND MEAT2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, ANDVEGETABLES2.5.3.8 EXAMPLE CALCULATION -DOSE FROM CONSUMPTION OFMILK, MEAT, AND VEGETABLES2.5.4 GROUND PLANE DEPOSITION IRRADIATION122014 CY-OC-170-301Revision 6Page 6 of 1402.5.4.12.5.4.22.5.4.32.5.4.4GROUND PLANE CONCENTRATIONEXAMPLE GROUND PLANE CONCENTRATION CALCULATIONGROUND PLANE DOSEEXAMPLE GROUND PLANE DOSE2.6PROJECTED DOSES -GASEOUS3 TOTAL DOSE TO MEMBERS OF THE PUBLIC -40 CFR 1903.1 EFFLUENT DOSE CALCULATIONS3.2 DIRECT EXPOSURE DOSE DETERMINATION4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMAPPRENDIX A -DERIVED DOSE FACTORS AND RECEPTOR LOCATIONSTable A-I:Table A-2:Table A-3:Table A-4:Table A-5:Dose Conversion Factors for Deriving Radioactive NobleGas Radionuclide-To-Dose Equivalent Rate FactorsNoble Gas Radionuclide-To-Dose Equivalent Rate FactorsAir Dose Conversion Factors for Effluent Noble GasLocations Associated with Maximum Exposure of a Member ofThe PublicCritical Receptor Noble Gas Dose Conversion FactorsAPPENDIX B -MODELING PARAMETERSTable B-I:Table B-2:OCGS Usage Factors for Individual Dose AssessmentMonthly Average Absolute Humidity g/m3APPENDIX C -REFERENCESTable C-1: REFERENCESAPPENDIX D -SYSTEM DRAWINGSFigure D-l-la:Figure D-1-1 b:Figure D-l-lc:Figure D-1-2:Figure D-2-1:Figure D-2-2:Figure D-2-3:Liquid Radwaste Treatment Chem Waste and FloorDrain SystemLiquid Radwaste Treatment -High Purity and EquipmentDrain SystemGroundwater Remediation SystemSolid Radwaste Processing SystemGaseous Radwaste Treatment -Augmented Offgas SystemVentilation SystemAOG Ventilation System122014 CY-OC-170-301Revision 6Page 7 of 140APPENDIX E -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -SAMPLETYPE AND LOCATIONTable E-1:Figure E-1:Figure E-2:Figure E-3:Figure E-4:REMP Sample LocationsOyster Creek Generating Station REMP Sample Locations within a1 Mile RadiusOyster Creek Generating Station REMP Sample Locations within a1 to 5 Mile RadiusOyster Creek Generating Station REMP Sample Locations over a 5Mile RadiusArea Plot Plan of Site122014 CY-OC-170-301Revision 6Page 8 of 140OYSTER CREEK GENERATING STATIONOFF SITE DOSE CALCULATION MANUALINTRODUCTIONThe Oyster Creek Off Site Dose Calculation Manual (ODCM) is an implementing document tothe Oyster Creek Technical Specifications. The previous Limiting Conditions for Operationsthat were contained in the Radiological Effluent Technical Specifications (RETS) are nowincluded in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts:Part I -Radiological Effluent Controls, and Part II -Calculational Methodologies.Part I includes the following:" The Radiological Effluent Controls and the Radiological Environmental MonitoringPrograms required by Technical Specifications 6.8.4" Descriptions of the information that should be included in the Annual Radioactive EffluentRelease Report and the Annual Radiological Environmental Operating Report requiredby Technical Specifications 6.9.1.d and 6.9.1.e, respectively.Part II describes methodologies and parameters used for:" The calculation of radioactive liquid and gaseous effluent monitoring instrumentationalarm/trip set points; and" The calculation of radioactive liquid and gaseous concentrations, dose rates, cumulativeyearly doses, and projected doses.Part II also contains a list and graphical description of the specific sample locations for theradiological environmental monitoring program (REMP), and the liquid and gaseous wastetreatment systems and discharge points.122014 CY-OC-170-301Revision 6Page 9 of140PART I -RADIOLOGICAL EFFLUENT CONTROLS1.0 DEFINITIONSThe following terms are defined so that uniform interpretation of these CONTROLS maybe achieved. The defined terms appear in capitalized type and are applicablethroughout these CONTROLS.1.1 OPERABLE -OPERABILITYA system, subsystem, train, component or device shall be OPERABLE or haveOPERABILITY when it is capable of performing its specified function(s). Implicitin the definition shall be the assumption that all necessary attendantinstrumentation, controls, normal and emergency electrical power sources,cooling or seal water, lubrication or other auxiliary equipment that are required forthe system, subsystem, train, component or device to perform its function(s) arealso capable of performing their related support function(s).A verification of OPERABILITY is an administrative check, by examination ofappropriate plant records (logs, surveillance test records) to determine that asystem, subsystem, train, component or device is not inoperable. Suchverification does not preclude the demonstration (testing) of a given system,subsystem, train, component or device to determine OPERABILITY.1.2 ACTIONACTION shall be that part of a CONTROL that prescribes remedial measuresrequired under designated conditions.1.3 CHANNEL CALIBRATIONA CHANNEL CALIBRATION shall be the adjustment, as necessary, of thechannel output such that it responds, with acceptable range and accuracy, toknown values of the parameter that the channel monitors. The CHANNELCALIBRATION shall encompass the entire channel, including equipmentactuation, alarm, or trip.1.4 CHANNEL CHECKA CHANNEL CHECK shall be a qualitative determination of acceptable operabilityby observation of channel behavior during operation. This determination shallinclude, where possible, comparison of the channel with other independentchannels measuring the same variable.122014 CY-OC-170-301Revision 6Page 10 of 1401.5 CHANNEL FUNCTIONAL TESTCHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal intothe channel to verify its proper response including, where applicable, alarm and/ortrip initiating actions.1.6 CONTROLThe Limiting Conditions for Operation (LCOs) that were contained in theRadiological Effluent Technical Specifications were transferred to the OFF SITEDOSE CALCULATION MANUAL (ODCM) and were renamed CONTROLS. Thisis to distinguish between those LCOs that were retained in the TechnicalSpecifications and those LCOs or CONTROLS that were transferred to theODCM.1.7 FREQUENCY NOTATIONThe FREQUENCY NOTATION specified for the performance of SurveillanceRequirements shall correspond to the intervals defined in Table 1.1.1.8 REPORTABLE EVENTA REPORABLE EVENT shall be any of those conditions specified Section 50.73to 10CFR Part 50.1.9 SOURCE CHECKSOURCE CHECK shall be the qualitative assessment of channel response whenthe channel sensor is exposed to a source of increased radioactivity.1.10 AUGMENTED OFF GAS SYSTEM (AOG)The AUGMENTED OFF GAS SYSTEM is designed and installed to holdup and/orprocess radioactive gases from the main condenser off gas system for thepurpose of reducing the radioactive material content of the gases before releaseto the environs.1.11 MEMBER (S) OF THE PUBLICMEMBER (S) OF THE PUBLIC shall include all persons who are notoccupationally associated with Exelon Generation and who do not normallyfrequent the Oyster Creek Generating Station site. This category does not includeemployees of the utility, its contractors, contractor employees, vendors, orpersons who enter the site to make deliveries, to service equipment, work on siteor for other purposes associated with plant functions. This category does includepersons who use portions of the site for recreational, occupational, or other122014 CY-OC-170-301Revision 6Page 11 of 140purposes not associated with the plant. An individual is not a member of thepublic during any period in which the individual receives an occupational dose.1.12 OFF SITE DOSE CALCULATION MANUAL (ODCM)The OFF SITE DOSE CALCULATION MANUAL (ODCM) shall contain themethodology and parameters used in the calculation of Off Site doses due toradioactive gaseous and liquid effluents, in the calculation of gaseous and liquideffluent monitoring Alarm/Trip Set points, and in the conduct of the RadiologicalEnvironmental Monitoring Program. The ODCM shall also contain (1) theRadioactive Effluent Controls and Radiological Environmental MonitoringPrograms required by Technical Specification Section 6.8.4 and (2) descriptionsof the information that should be included in the Annual Radioactive EffluentRelease Report AND Annual Radiological Environmental Operating Reportrequired by Technical Specification Sections 6.9.1.d and 6.9.1.e, respectively.1.13 PURGE-PURGINGPURGE or PURGING shall be the controlled process of discharging air or gasfrom a confinement and replacing it with air or gas.1.14 SITE BOUNDARYThe SITE BOUNDARY shall be the perimeter line around OCGS beyond whichthe land is neither owned, leased, nor otherwise subject to control by ExelonGeneration. The area outside the SITE BOUNDARY is termed OFF SITE orUNRESTRICTED AREA.1.15 OFF SITEThe area that is beyond the site boundary where the land is neither owned, leasednor otherwise subject to control by Exelon Generation. Can be interchanged withUNRESTRICTED AREA.1.16 UNRESTRICTED AREAAn UNRESTRICTED AREA shall be any area at or beyond the SITEBOUNDARY, access to which is not controlled by the licensee for purposes ofprotection of individuals from exposure to radiation and radioactive materials, orany area within the SITE BOUNDARY used for residential quarters or forindustrial, commercial, institutional, and/or recreational purposes. Can beinterchanged with OFF SITE.122014 CY-OC-170-301Revision 6Page 12 of 1401.17 DOSE EQUIVALENT 1-131DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (micro curies pergram), which alone would produce the same thyroid dose as the quantity andisotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. Thethyroid dose conversion factors used for this calculation shall be those listed inTable E-7 of Regulatory Guide 1.109, "Calculation of Annual Doses to Man fromRoutine Releases of Reactor Effluences for the Purpose of EvaluatingCompliance with 10CFR Part 40 Appendix I."1.18 DEPOSITION (D/Q)The direct removal of gaseous and particulate species on land or water surfaces.DEPOSITION is expressed as a quantity of material per unit area (e.g. m2).1.19 DOSE CONVERSION FACTOR (DCF)A parameter calculated by the methods of internal dosimetry, which indicates thecommitted dose equivalent (to the whole body or organ) per unit activity inhaled oringested. This parameter is specific to the isotope and the dose pathway. DOSECONVERSION FACTORS are commonly tabulated in units of mrem/hr perpicocurie/m3 in air or water. They can be found in Reg Guide 1.109 appendices.1.20 EFFLUENT CONCENTRATION (EC)The liquid and air concentration levels which, if inhaled or ingested continuouslyover the course of a year, would produce a total effective dose equivalent of 0.05rem. LEC refers to liquid EFFLUENT CONCENTRATION.1.21 ELEVATED (STACK) RELEASEAn airborne effluent plume whose release point is higher than twice the height ofthe nearest adjacent solid structure and well above any building wake effects soas to be essentially unentrained. Regulatory Guide 1.111 is the basis of thedefinition of an ELEVATED RELEASE. Elevated releases generally will notproduce any significant ground level concentrations within the first few hundredyards of the source. ELEVATED RELEASES generally have less doseconsequence to the public due to the greater downwind distance to the groundconcentration maximum compared to ground releases. All main stack releases atthe OCGS are ELEVATED RELEASES.1.22 FINITE PLUME MODELAtmospheric dispersion and dose assessment model which is based on theassumption that the horizontal and vertical dimensions of an effluent plume arenot necessarily large compared to the distance that gamma rays can travel in air.It is more realistic than the semi-infinite plume model because it considers the122014 CY-OC-170-301Revision 6Page 13 of 140finite dimensions of the plume, the radiation build-up factor, and the airattenuation of the gamma rays coming from the cloud. This model can estimatethe dose to a receptor who is not submerged in the radioactive cloud. It isparticularly useful in evaluating doses from an elevated plume or when thereceptor is near the effluent source.1.23 GROUND LEVEL (VENT) RELEASEAn airborne effluent plume which contacts the ground essentially at the point ofrelease either from a source actually located at ground elevation or from a sourcewell above the ground elevation which has significant building wake effects tocause the plume to be entrained in the wake and driven to the ground elevation.GROUND LEVEL RELEASES are treated differently than ELEVATEDRELEASES in that the X/Q calculation results in significantly higherconcentrations at the ground elevation near the release point.1.24 OCCUPATIONAL DOSEThe dose received by an individual in a RESTRICTED AREA or in the course ofemployment in which the individual's assigned duties involve exposure toradiation and to radioactive material from licensed and unlicensed sources ofradiation, whether in the possession of the licensee or other person. Occupationaldose does not include dose received from background radiation, as a patient frommedical practices, from voluntary participation in medical research programs, oras a member of the general public1.25 "OPEN DOSE"A routine effluent dosimetry computer program that uses Reg.Guides 1.109 and 1.111 methodologies.1.26 RAGEMS (RADIOACTIVE EMISSIONS MONITORING SYSTEM)A plant system that monitors gaseous effluent releases from monitored releasepoints. There is a RAGEMS system for the main stack (RAGEMS I) and one forthe turbine building (RAGEMS II). They monitor particulates, iodine's, and noblegases.1.27 SEMI-INFINITE PLUME MODELDose assessment model with the following assumptions. The ground isconsidered to be an infinitely large flat plate and the receptor is located at theorigin of a hemispherical cloud of infinite radius. The radioactive cloud is limitedto the space above the ground plane. The semi-infinite plume model is limited toimmersion dose calculations.1.28 SOURCE TERM122014 CY-OC-170-301Revision 6Page 14 of 140The activity release rate, or concentration of an actual release or potentialrelease. The common units for the source term are curies, curies per second, andcuries per cubic centimeter, or multiples thereof (e.g., micro curies).1.29 X/Q -("CHI over Q")The dispersion factor of a gaseous release in the environment calculated by apoint source Gaussian dispersion model. Normal units of X/Q are sec/m3.TheX/Q is used to determine environmental atmospheric concentrations bymultiplying the source term, represented by Q (in units of ýiCi/sec or Ci/sec).Thus, the plume dispersion, X/Q (seconds/cubic meter) multiplied by the sourceterm, Q (uCi/seconds) yields an environmental concentration, X (itCi/m3). X/Q isa function of many parameters including wind speed, stability class, release pointheight, building size, and release velocity.1.30 SEEDS (Simplified Effluent Environmental Dosimetry System)A routine effluent dosimetry computer program that uses Reg. Guides 1.109 and1.111 methodologies.TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION *NOTATION FREQUENCYS At least once per 12 hours.D At least once per 24 hours.W At least once per 7 days.M At least once per 31 days.Q At least once per 92 days.SA At least once per 184 days.A At least once per 366 days.R At least once per 18 months (550 days).1/24 At least once per 24 months (refueling cycle)S/U Prior to each reactor startup.P Prior to each radioactive release.N.A. Not applicable.* Each surveillance requirement shall be performed within the specified timeinterval with a maximum allowable extension not to exceed 25% of thesurveillance interval.122014 CY-OC-170-301Revision 6Page 15 of 1403/4 CONTROLS AND SURVEILLANCE REQUIREMENTS3/4.0 APPLICABILITYCONTROLS3.0.1 Compliance with the CONTROLS contained in the succeeding CONTROLS isrequired during the OPERATIONAL CONDITIONS or other conditions specifiedtherein; except that upon failure to meet the CONTROL, the associated ACTIONrequirements shall be met.3.0.2 Noncompliance with a CONTROL shall exist when the requirements of the CONTROLand associated ACTION requirements are not met within the specified time intervals.If the CONTROL is restored prior to expiration of the specified time intervals,completion of the ACTION requirements is not required.3.0.3 Except as provided in the associated ACTION requirements, when a CONTROL is notmet or the associated ACTION requirements cannot be satisfied, action shall beinitiated to place the unit into COLD SHUTDOWN within the following 30 hours.Where corrective measures are completed that permit operation under the ACTIONrequirements, the ACTION may be taken in accordance with the specified time limitsas measured from the time of failure to meet the CONTROL. Exceptions to theserequirements are stated in the individual CONTROLS.This CONTROL is not applicable in COLD SHUTDOWN or REFUELING.3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not bemade when the conditions of the CONTROLS are not met and the associatedACTION requires a shutdown if they are not met within a specified time interval. Entryinto an OPERATIONAL CONDITION or other specified condition may be made inaccordance with ACTION requirements when conformance to them permits continuedoperation of the facility for an unlimited period of time. This provision shall not preventpassage through or to OPERATIONAL CONDITIONS as required to comply withACTION requirements. Exceptions to these requirements are stated in the individualCONTROLS.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONSmay be returned to service under administrative control solely to perform testing todemonstrate its OPERABILITY or the OPERABILITY of other equipment. This is anexception to CONTROL 3.0.2 for the system returned to service under administrativecontrol to perform the testing required to demonstrate OPERABILITY.122014 CY-OC-1 70-301Revision 6Page 16 of 1403/4.0 APPLICABILITYSURVEILLANCE REQUIREMENTS4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS orother conditions specified for individual CONTROLS unless otherwise stated in anindividual Surveillance Requirement.4.0.2 Each Surveillance Requirement shall be performed within the specified surveillanceinterval with a maximum allowable extension not to exceed 25 percent of the specifiedsurveillance interval.4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval,defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITYrequirements for a CONTROL. The time limits of the ACTION requirements areapplicable at the time it is identified that a Surveillance Requirement has not beenperformed. The ACTION requirements may be delayed for up to 24 hours to permitthe completion of the surveillance when the allowed outage time limits of the ACTIONrequirements are less than 24 hours. Surveillance Requirements do not have to beperformed on inoperable equipment.4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable conditionshall not be made unless the Surveillance Requirement(s) associated with theCONTROLS have been performed within the applicable surveillance interval or asotherwise specified. This provision shall not prevent passage through or toOPERATIONAL CONDITIONS as required to comply with ACTION requirements.122014 CY-OC-170-301Revision 6Page 17 of 1403/4.3 INSTRUMENTATION3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONCONTROLS3.3.3.10 In accordance with Oyster Creek Technical Specifications 6.8.4.a.1, the radioactiveliquid effluent monitoring instrumentation channels shown in Table 3.3.3.10-1 shallbe OPERABLE with their Alarm/Trip set points set to ensure that the limits ofCONTROL 3.11.1.1 are not exceeded. The Alarm/Trip set points of these channelsshall be determined and adjusted in accordance with the methodology andparameters in the ODCM Part II section 1.2.1.APPLICABILITY: During all liquid releases via these pathways.ACTION:a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Tripset point less conservative than required by the above CONTROL, immediatelysuspend the release of radioactive liquid effluents monitored by the affectedchannel, or declare the channel inoperable, or change the set point so it isacceptably conservative, or provide for manual initiation of the Alarm/Tripfunction(s).b. With less than the minimum number of radioactive liquid effluent monitoringinstrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1. Make every reasonable effort to return the instrument to OPERABLEstatus within 30 days and, if unsuccessful, explain in the next Radioactive EffluentRelease Report pursuant to Technical Specification 6.9.1 .d why the inoperabilitywas not corrected in a timely manner.c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable. Report alldeviations in the Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at theFrequencies shown in Table 4.3.3.10-1.122014 CY-OC-1 70-301Revision 6Page 18 of 140TABLE 3.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSOPERABLEINSTRUMENT1. RADIOACTIVITY MONITORS PROVIDING ALARM ANDAUTOMATIC TERMINATION OF RELEASEa. Liquid Radwaste Effluent Line (DELETED)b. Turbine Building Sump No. 1-5 (DELETED)2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOTPROVIDING AUTOMATIC TERMINATION OF RELEASEa. Reactor Building Service Water System Effluent Line3. FLOW RATE MEASUREMENT DEVICESa. Liquid Radwaste Effluent Line (DELETED)b. Groundwater Remediation Release PathACTIONN/AN/A1N/A1N/AN/A112N/A115122014 CY-OC-170-301Revision 6Page 19 of 140TABLE 3.3.3.10-1 (Continued)TABLE NOTATIONSACTION 110ACTION 112ACTION 113ACTION 114With no channels OPERABLE, effluent releases via this pathway may continueprovided that:a. At least two independent samples are taken, one prior to discharge andone near the completion of discharge and analyzed in accordance withSURVEILLANCE REQUIREMENT 4.11.1.1.1.b. Before initiating a release, at least two technically qualified members ofthe Facility Staff independently verify the release rate calculations anddischarge line valving;Otherwise, suspend release of radioactive effluents via this pathway.With no channels OPERABLE, effluent releases via this pathway may continueprovided that, at least once per 24 hours, grab samples are collected andanalyzed for radioactivity at a limit of detection specified by Table 4.11.1.1.1-1.With no channel OPERABLE, effluent releases via the affected pathway maycontinue provided the flow is estimated with the pump curve or change in tanklevel, at least once per batch during a release.With no channel OPERABLE effluent may be released provided that beforeinitiating a release:a. A sample is taken and analyzed in accordance with SURVEILLANCEREQUIREMENT 4.11.1.1.1.b. Qualified personnel determine and independently verify the acceptablerelease rate.With no channel OPERABLE, effluent releases via this pathway may continueprovided the flow rate is estimated at least once per 4 hours during actualreleases. Pump performance curves may be used to estimate flow.ACTION 115122014 CY-OC-1 70-301Revision 6Page 20 of 140TABLE 4.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCEREQUIREMENTSaCHANNELCHECKSOURCE CHANNELCHECK CALIBRATIONCHANNELFUNCTIONALTESTINSTRUMENT1. RADIOACTIVITY MONITORS PROVIDING ALARM ANDAUTOMATIC TERMINATION OF RELEASEa. Liquid Radwaste Effluent Line (DELETED)b. Turbine Building Sump No. 1-5 (DELETED)N/AN/AN/AN/AN/AN/AN/AN/A2. RADIOACTIVITY MONITORS PROVIDING ALARM BUTNOT PROVIDING AUTOMATIC TERMINATION OF RELEASEa. Reactor Building Service Water System Effluent Line D3. FLOW RATE MEASUREMENT DEVICESa. Liquid Radwaste Effluent Line (DELETED)b. Groundwater Remediation Release pathMN/AN/AReN/ADfN/ARfN/AN/A122014 CY-OC-170-301Revision 6Page 21 of 140TABLE 4.3.3.10-1 (Continued)TABLE NOTATIONSa. Instrumentation shall be OPERABLE and in service except that a channel may be takenout of service for the purpose of a check, calibration, test or maintenance without declaringit to be inoperable.d. The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarmannunciation occurs if any of the following conditions exists:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a downscale failure.3. Instrument controls not set in operate mode.4. Instrument electrical power loss.e. The CHANNEL CALIBRATION shall be performed according to established calibrationprocedures.f. While actively discharging through this pathway.122014 CY-OC-170-301Revision 6Page 22 of 1403/4.3 INSTRUMENTATION3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONCONTROLS3.3.3.11 In accordance with Oyster Creek Technical Specifications 6.8.4.a. 1, the radioactivegaseous effluent monitoring instrumentation channels shown in Table 3.3.3.11-1shall be OPERABLE with their alarm/trip set points set to ensure that the limits ofCONTROL 3.11.2.1 are not exceeded. The alarm/trip set points of these channelsmeeting CONTROLS 3.11.2.1 shall be determined and adjusted in accordance withthe methodology and parameters in the ODCM Part II Section 2.2.APPLICABILITY: As shown in Table 3.3.3.11-1ACTION:a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/tripset point less conservative than required by the above CONTROL, immediatelysuspend the release of radioactive gaseous effluents monitored by the affectedchannel, or declare the channel inoperable, or change the set point so it isacceptably conservative.b. With less than the minimum number of radioactive gaseous effluent monitoringinstrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.11-1. Exert best efforts to return the instrument to OPERABLE status within 30 daysand, if unsuccessful, explain in the next Radioactive Effluent Release Reportpursuant to Technical Specification 6.9.1 .d why this inoperability was not correctedin a timely manner.c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable. Report alldeviations in the Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TESToperations at the frequencies shown in Table 4.3.3.11-1.122014 CY-OC-1 70-301Revision 6Page 23 of 140TABLE 3.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSINSTRUMENT OPERAE1. DELETED2. STACK MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) 1b. Iodine Sampler ic. Particulate Sampler 1d. Effluent Flow Measuring Device 1e. Sample Flow Measuring Device 13. TURBINE BUILDING VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) 1b. Iodine Sampler 1c. Particulate Sampler 1d. Effluent Flow Measuring Device 1e. Sample Flow Measuring Device 13LEa APPLICABILITY ALCTIONb,eb,eb,ebbbbbbb124127127122128123127127122128122014 CY-OC-170-301Revision 6Page 24 of 140TABLE 3.3.3.11-1(Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSINSTRUMENT OPERABLEa APPLICABILITY ACTION4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor 1 b 123b. Iodine Sampler 1 b 127c. Particulate Sampler 1 b 127d. Sample Flow Measuring Device 1 b 128122014 CY-OC-170-301Revision 6Page 25 of 140TABLE 3.3.3.11-1 (Continued)TABLE NOTATIONSa. Channels shall be OPERABLE and in service as indicated except that a channel may betaken out of service for the purpose of a check, calibration, test maintenance or samplemedia change without declaring the channel to be inoperable.b. During releases via this pathwaye. Monitor / sampler or an alternate shall be OPERABLE to monitor / sample Stack effluentwhenever the drywell is being purged.ACTION 122ACTION 123ACTION 124ACTION 127ACTION 128With no channel OPERABLE, effluent releases via this pathway may continueprovided the flow rate is estimated whenever the exhaust fan combination in thissystem is changed.With no channel OPERABLE, effluent releases via this pathway may continueprovided a grab sample is taken at least once per 48 hours and is analyzed forgross radioactivity within 24 hours thereafter or provided an alternate monitoringsystem with local display is utilized.With no channel OPERABLE, effluent releases via this pathway may continueprovided a grab sample is taken at least once per 8 hours and analyzed for grossradioactivity within 24 hours or provided an alternate monitoring system with localdisplay is utilized. Drywell purge is permitted only when the radioactive noblegas monitor is operating.With no channel OPERABLE, effluent releases via this pathway may continueprovided the required sampling is initiated with auxiliary sampling equipment assoon as reasonable after discovery of inoperable primary sampler(s).With no channel OPERABLE, effluent releases via the sampled pathway maycontinue provided the sampler air flow is estimated and recorded at least onceper day.122014 CY-OC-1 70-301Revision 6Page 26 of 140TABLE 4.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNEL MODES IN WHICHCHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCEINSTRUMENT CHECK CHECK CALIBRATION TEST REQUIREDa1. DELETED2. MAIN STACK MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qh bb. Iodine Sampler W N.A. N.A. N.A. bc. Particulate Sampler W N.A. N.A. N.A. bd. Effluent Flow Measuring Device D N.A. 1/24 Q be. Sample Flow Measuring Device D N.A. R Q b3. TURBINE BUILDING VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qi bb. Iodine Sampler W N.A. N.A. N.A. bc. Particulate Sampler W N.A. N.A. N.A. bd. Effluent Flow Measuring Device D N.A. 1/24 Q be. Sample Flow Measuring Device D N.A. R Q b122014 CY-OC-1 70-301Revision 6Page 27 of 140TABLE 4.3.3.11-1 (Continued)RADIOACTIVE'GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNELINSTRUMENT CHECKCHANNELSOURCE CHANNEL FUNCTIONALCHECK CALIBRATION TESTMODES IN WHICHSURVIELLANCE ISREQUIRED a4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor D M Rfb. Iodine Sampler W N.A. N.A.c. Particulate Sampler W N.A. N.A.d. Sample Flow Measuring Device D N.A. RQeN.A.N.A.N.A.bbbb122014 CY-OC-170-301Revision 6Page 28 of 140TABLE 4.3.3.11-1 (Continued)TABLE NOTATIONSa. Instrumentation shall be OPERABLE and in service except that a channel may be takenout of service for the purpose of a check calibration, test or maintenance withoutdeclaring it to be inoperable.b. During releases via this pathway.e. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarmannunciation occurs if any of the following conditions exist:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a downscale failure.3. Instrument controls not set in operate mode.4. Instrument electrical power loss.f. The CHANNEL CALIBRATION shall be performed according to established calibrationprocedures.h. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarmannunciation occurs if any of the following conditions exists:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a low count rate/monitor failure.3. Switch cover alarm shall be verified to alarm when the cover is opened; and clearwhen the cover is closed after the faceplate switches are verified in their correctpositions.The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarmannunciation occurs if any of the following conditions exists:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a low count rate/monitor failure.122014 CY-OC-170-301Revision 6Page 29 of 1403/4.11RADIOACTIVE EFFLUENTS3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATIONCONTROLS3.11.1.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.2 and 3, theconcentration of radioactive material, other than noble gases, in liquid effluent in thedischarge canal at the Route 9 bridge (See Figure E-4) shall not exceed theconcentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. Theconcentration of noble gases dissolved or entrained in liquid effluent in the dischargecanal at the Route 9 bridge shall not exceed 2E-4 microcuries/milliliter.APPLICABILITY: At all times.ACTION:a. In the event the concentration of radioactive material in liquid effluent released intothe Off Site area beyond the Route 9 bridge exceeds either of the concentrationlimits above, reduce the release rate without delay to bring the concentration belowthe limit.b. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the samplingand analysis program in Table 4.11.1.1.1-1.Alternately, pre-release analysis of batches(es) of radioactive liquid waste may be bygross beta or gamma counting provided a maximum concentration limit of 1 E-8gCi/ml in the discharge canal at the Route 9 bridge is applied.4.11.1.1.24.11.1.1.3The results of the radioactivity analyses shall be used in accordance with themethodology and parameters in the ODCM Part II Section 1.2 to assure that theconcentrations at the point of release are maintained within the limits of CONTROL3.11.1.1 and 3.11.1.2.The alarm or trip set point of each radioactivity monitoring channel in Table 3.3.3.10-1shall be determined on the basis of sampling and analyses results obtainedaccording to Table 4.11.1.1.1-1 and the set point method in ODCM Part 111.2.1 andset to alarm or trip before exceeding the limits of CONTROL 3.11.1.1.122014 CY-OC-170-301Revision 6Page 30 of 140TABLE 4.11.1.1.1-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMMinimum Lower LimitLiquid Release Type Sampling Analysis Type of Activity Analysis Detectiona (LLD)Frequency Frequency (P.Ci/ml)P pC Principal Gamma Emitters 5E-071. Batch WasteRelease Tanks Each Batchb Each Batch 1-131 5E-07M Dissolved and EntrainedOne Gases (Gamma Emitters) 1 E-05Batch/MbP M H-3 1 E-05Each Batchb Composited Gross Alpha 1 E-07P Q Sr-89, Sr-90 5E-08Each Batchb Composited Fe-55 1 E-06W Principal Gamma Emitters 5E-072. ContinuousRelease Grab W 1-131 5E-07a. Reactor Building Samplee-Service Water H-3 1 E-05EffluentGross Alpha 1E-07M(note f) CompositegFe-55 1 E-063. Groundwater uoush D Principal Gamma Emitters 5E-07Remediation Pathway ContinuoussteH-" E0Composite H-3 1 E-05a. ContinuousGross Alpha 1E-07M Sr-89, Sr-90 5E-08MCompositeg Fe-55 1 E-06Ni-63 1E-06b. Batch Release P P Principal Gamma Emitters 5E-07Tank Each Batchb Each Batch H-3 1E-05Gross Alpha 1 E-07P M Sr-89, Sr-90 5E-08Each Batchb Composited Fe-55 1E-06Ni-63 1 E-06122014 CY-OC-170-301Revision 6Page 31 of 140TABLE 4.11.1.1-1 (CONTINUED)TABLE NOTATIONSa. The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as thesmallest concentration of radioactive material in a sample that will yield a net count, abovesystem background, that will be detected with 95 percent probability with only 5 percentprobability of falsely concluding that a blank observation represents a "real" signal.The LLD is applicable to the capability of a measurement system under typical conditionsand not as a limit for the measurement of a particular sample in the radioactive liquid wastesampling and analyses program.For a particular measurement system, which may include radiochemical separation:LLD~ 4.66 | |||
* SbE | |||
* V | |||
* 2.22E6 | |||
* Y | |||
* exp(-kAt)Where:LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),Sb is the standard deviation of the background counting rate or of the counting rate of a blanksample as appropriate (counts per minute),E is the counting efficiency,V is the sample size (units of mass or volume),2.22E+6 is the number of disintegrations per minute per microcurie,Y is the fractional radiochemical yield, when applicable,Xk is the radioactive decay constant for the particular radionuclide, andAt is the elapsed time between the end of the sample collection and the time of counting.Analyses shall be performed in such a manner that the stated LLDs will be achieved underroutine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Ce-141, Cs-134, Cs-137; and an LLD of 5E-6 iýCi/ml shouldtypically be achieved for Ce-144.122014 CY-OC-170-301Revision 6Page 32 of 140TABLE 4.11.1.1.1-1 (CONTINUED)TABLE NOTATIONSOccasionally, background fluctuations, interfering radionuclides, or other uncontrollablecircumstances may render these LLD's unachievable.When calculating the LLD for a radionuclide determined by gamma ray spectrometry, thebackground may include the typical contributions of other radionuclides normally present inthe sample. The background count rate of a semiconductor detector (e.g. HPGe) isdetermined from background counts that are determined to be within the full width of thespecific energy band used for the quantitative analysis for the radionuclide.The principal gamma emitters for which the LLD specification will apply are exclusively thefollowing radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected andreported. Other peaks that are measurable and identifiable, together with the abovenuclides, shall be identified and reported. The LLD for Ce-144 is 5E-6 gCi/mL whereas theLLD for Mo-99 and the other gamma emitters is 5E-7 p.Ci/mL. Nuclides that are below theLLD for the analysis should not be reported.b. A batch release is the discharge of liquid wastes of a discrete volume. Before sampling foranalysis, each batch should be thoroughly mixed.c. In the event a gross radioactivity analysis is performed in lieu of an isotopic analysis before abatch is discharged, a sample will be analyzed for principal gamma emitters afterwards.d. A composite sample is one in which the quantity of liquid sampled is proportional to thequantity of liquid waste discharged and in which the method of sampling employed results ina specimen which is representative of the liquids released.e. Analysis may be performed after release.f. In the event a grab sample contains more than 5E-7 ýiCi/mL of 1-131 and principal gammaemitters or in the event the Reactor Building Service Water radioactivity monitor indicatesmore than 5E-7 gCi/mL radioactivity in the effluent, as applicable, sample the elevatedactivity effluent daily until analysis confirms the activity concentration in the effluent does notexceed 5E-7 ltCi/mL. In addition a composite sample must be made up for further analysisfor all samples taken when the activity was > 5E-7 itCi/mL.g. A composite sample is produced combining grab samples, each having a defined volume,collected routinely from the sump or stream being sampledh. Aliquot sampling shall be at least hourly to be representative of the quantities andconcentrations of radioactive materials in liquid effluent. Prior to analyses, all samples takenfor the composite shall be thoroughly mixed in order for the composite samples to berepresentative of the effluent release.122014 CY-OC-170-301Revision 6Page 33 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.1.2 DOSECONTROLS3.11.1.2 In accordance with Oyster Creek Technical Specifications 6.8.4.a.4 and 5, the doseor dose commitment to a MEMBER OF THE PUBLIC from radioactive materials inliquid effluents released to UNRESTRICTED AREAS (see Figure E-4) shall belimited:a. During any calendar quarter to less than or equal to 1.5 mrem to the Total Body andto less than or equal to 5 mrem to any body organ, andb. During any calendar year to less than or equal to 3 mrem to the Total Body and toless than or equal to 10 mrem to any body organ.APPLICABILITY: At all times.ACTION:a. With the calculated dose from the release of radioactive materials in liquid effluentsexceeding any of the above limits, prepare and submit to the Commission within 30days from the end of the quarter, pursuant to Technical Specification 6.9.2, aSpecial Report that identifies the cause(s) for exceeding the limit(s) and defines thecorrective actions that have been taken and/or will be taken to reduce the releasesand the proposed corrective actions to be taken to assure that subsequent releaseswill be in compliance with the above limits.b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarterand the current calendar year shall be determined in accordance with themethodology and parameters in the ODCM Part II Section 1.5 at least once per 31days in accordance with Technical Specification 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 34 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEMCONTROLS3.11.1.3 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.6, the liquidradwaste treatment system shall be OPERABLE and appropriate portions of thesystem shall be used to reduce releases of radioactivity when projected doses due tothe liquid effluent to UNRESTRICTED AREAS (see Figure E-4) would exceed 0.06mrem to the Total Body or 0.2 mrem to any organ in a 31 day period.APPLICABILITY: At all times.ACTION:a. With radioactive liquid waste being discharged without treatment and in excess ofthe above, prepare and submit to the Commission within 30 days, pursuant toTechnical Specification 6.9.2, a Special Report that includes the followinginformation:1. Explanation of why liquid radwaste was being discharged without treatment,identification of any inoperable equipment or subsystems, and the reason forthe inoperability,2. Action(s) taken to restore the inoperable equipment to OPERABLE status,and3. Summary description of action(s) taken to prevent a recurrence.b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall beprojected at least once per 31 days in accordance with the methodology andparameters in the ODCM Part II Section 1.5 in accordance with TechnicalSpecifications 6.8.4.a.5.4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstratedOPERABLE by meeting CONTROLS 3.11.1.1, 3.11.1.2, and 3.11.1.3.122014 CY-OC-170-301Revision 6Page 35 of 1403/4.11RADIOACTIVE EFFLUENTS3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSE RATECONTROLS3.11.2.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.5 and 7, thedose rate due to radioactive materials released in gaseous effluents in theUNRESTRICTED AREA (see Figure E-4) shall be limited to the following:a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less thanor equal to 3000 mrem/yr to the skin, andb. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form withhalf-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any bodyorgan.APPLICABILITY: At all times.ACTION:a. With the dose rate(s) exceeding the above limits, immediately restore the releaserate to within the above limit(s).b. If the gaseous effluent release rate cannot be reduced to meet the above limits, thereactor shall be in at least SHUTDOWN CONDITION within 48 hours unlesscorrective actions have been completed and the release rate restored to below theabove limit.SURVEILLANCE REQUIREMENTS4.11.2.1.14.11.2.1.2The dose rate due to noble gases in gaseous effluents shall be determined to bewithin the above limits in accordance with the methodology and parameters in theODCM Part II Section 2.3.1.The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides inparticulate form with half-lives greater than 8 days in gaseous effluents shall bedetermined to be within the above limits in accordance with the methodology andparameters in the ODCM Part II Section 2.3.2 by obtaining representative samplesand performing analyses in accordance with the sampling and analysis programspecified in Table 4.11.2.1.2-1.4,11.2.1.3 Dose rates due to tritium, Sr-89, Sr-90, and alpha-emitting radionuclides areaveraged over no more than 3 months and the dose rate due to other radionuclides isaveraged no more than 31 days.122014 CY-OC-1 70-301Revision 6Page 36 of 140TABLE 4.11.2.1.2-1: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMMinimum Lower LimitGaseous Release Sampling Analysis Type of Activity Detectiona- (LLD)Type Frequency Frequency Analysis (jiCi/ml)QQ H-3 1 E-06Grab SamplefM PrincipalM GammaGrab Sample Emittersb (Noble 1 E-04c,d,f Gases)W 1-131 1E-12Continuousf CharcoalSaplI-133 1E-10SampleW PrincipalStack; GammaTurbine Building Continuous Particulate EmittersbExhaust Vents; (particulates)Augmented Off gas MeBuilding VentContinuousf Composite Gross Alpha 1E-11ParticulateSampleQeContinuous Composite Sr-89, Sr-90 1E-11ParticulateSampleNoble Gas Noble Gases 1 E-06Continuous GammaRadioactivity122014 CY-OC-1 70-301Revision 6Page 37 of 140TABLE 4.11.2.1.2-1 (Continued)TABLE NOTATIONSa. The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as thesmallest concentration of radioactive material in a sample that will yield a net count, abovesystem background, that will be detected with 95 percent probability with only 5 percentprobability of falsely concluding that a blank observation represents a "real" signal.The LLD is applicable to the capability of a measurement system under typical conditionsand not as a limit for the measurement of a particular sample in the radioactive liquid wastesampling and analyses program.For a particular measurement system which may include radiochemical separation:LLD =4.66 | |||
* SbE | |||
* V | |||
* 2.22E6 | |||
* Y | |||
* exp(-kAt)Where:LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),Sb is the standard deviation of the background counting rate or of the counting rate of ablank sample as appropriate (counts per minute),E is the counting efficiency,V is the sample size (units of mass or volume),2.22E+6 is the number of disintegrations per minute per microcurie,Y is the fractional radiochemical yield, when applicable,k is the radioactive decay constant for the particular radionuclide, andAt is the elapsed time between the end of the sample collection and the time of counting.Analyses shall be performed in such a manner that the stated LLD's will be achieved underroutine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59,Co-58, Co-60, Zn-65, Cs-134, Cs-137, and Ce-141. Occasionally background fluctuations orother uncontrollable circumstances may render these LLD's unachievable.When calculating the LLD for a radionuclide determined by gamma ray spectrometry, thebackground may include the typical contributions of other radionuclides normally present inthe samples. The background count rate of a HpGe detector is determined from background122014 CY-OC-170-301Revision 6Page 38 of 140TABLE 4.11.2.1.2-1 (Continued)TABLE NOTATIONScounts that are determined to be within the full width of the specific energy band used for thequantitative analysis for that radionuclideb. The principal gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseousemissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, andCe-144 for particulate emissions. This list does not mean that only these nuclides are to beconsidered. Other gamma peaks that are identifiable, together with those of the abovenuclides, shall also be analyzed and reported in the Annual Radioactive Effluent ReleaseReport consistent with CONTROL 3.11.2.1. The LLD for Mo-99 and Ce-144 is 1E-10 ptCi/mlwhereas the LLD for other principal gamma emitting particulates is 1 E-1 1 jCi/ml.Radionuclides which are below the LLD for the analysis should not be reported.c. The noble gas radionuclides in gaseous effluent may be identified by taking a grab sample ofeffluent and analyzing it.d. In the event the reactor power level increases more than 15 percent in one hour and theStack noble gas radioactivity monitor shows an activity increase of more than a factor ofthree after factoring out the effect due to the change in reactor power, a grab sample of Stackeffluent shall be collected and analyzed.e. A composite particulate sample shall include an equal fraction of at least one particulatesample collected during each week of the compositing period.f. In the event a sample is collected for 24 hours or less, the LLD may be increased by a factorof 10.122014 CY-OC-170-301Revision 6Page 39 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.2.2 DOSE -NOBLE GASESCONTROLS3.11.2.2 In accordance with the Oyster Creek Technical Specification 6.8.4.a.5 and 8, the airdose due to noble gases released in gaseous effluents in the UNRESTRICTEDAREA (see Figure E-4) shall be limited to the following:a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation andless than or equal to 10 mrad for beta radiation and,b. During any calendar year: Less than or equal to 10 mrad for gamma radiation andless than or equal to 20 mrad for beta radiation.APPLICABILITY: At all times.ACTION:a. With the calculated air dose from radioactive noble gases in gaseous effluentsexceeding any of the above limits, prepare and submit to the Commission within 30days from the end of the quarter during which the release occurred, pursuant toTechnical Specification 6.9.2, a Special Report that identifies the cause(s) forexceeding the limit(s) and defines the corrective actions that have been taken toreduce the release and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the above limits.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendaryear for noble gases shall be determined in accordance with the methodology andparameters in the ODCM Part II Section 2.4.1 at least once per 31 days inaccordance with Technical Specification 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 40 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES INPARTICULATE FORMCONTROLS3.11.2.3 In accordance with Oyster Creek Technical Specification 6.8.4.a.5 and 9, the dose toa MEMBER OF THE PUBLIC from iodine-1 31, iodine-1 33, tritium, and allradionuclides in particulate form with half-lives greater than 8 days in gaseouseffluents released in the UNRESTRICTED AREA (see Figure E-4) shall be limited tothe following:a. During any calendar quarter: Less than or equal to 7.5 mrem to any body organand,b. During any calendar year: Less than or equal to 15 mrem to any body organ.APPLICABILITY: At all times.ACTION:a. With the calculated dose from the release of iodine-131, iodine-133 andradionuclides in particulate form with half-lives greater than 8 days, in gaseouseffluents exceeding any of the above limits, prepare and submit to the Commissionwithin 30 days, pursuant to Technical Specification 6.9.2, a Special Report thatidentifies the cause(s) for exceeding the limit and defines the corrective actions thathave been taken to reduce the releases and the proposed corrective actions to betaken to assure that subsequent releases will be in compliance with the abovelimits.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendaryear for iodine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologyand parameters in the ODCM Part II Section 2.5 at least once per 31 days inaccordance with Technical Specification 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 41 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEMCONTROLS3.11.2.4 The AUGMENTED OFF GAS SYSTEM shall be in operation to reduce releases ofradioactivity when the projected doses in 31 days due to gaseous effluent releases toareas at and beyond the SITE BOUNDARY (see Figure E-4) would exceed:a. 0.2 mrad to air from gamma radiation, orb. 0.4 mrad to air from beta radiation, orc. 0.3 mrem to any body organAPPLICABILITY: Whenever the main condenser steam jet air ejector is in operation exceptduring startup or shutdown with reactor power less than 40 percent of rated. Inaddition, the AUGMENTED OFF GAS SYSTEM need not be in operationduring end of cycle coast-down periods when the system can no longer functiondue to low off gas flow.ACTION:a. Every reasonable effort shall be made to maintain and operate charcoal absorbersin the AUGMENTED OFF GAS SYSTEM to treat radioactive gas from the maincondenser air ejectors.b. With gaseous radwaste from the main condenser air ejector system beingdischarged without treatment for more than 30 consecutive days and eitherCONTROL 3.11.2.1 or 3.11.2.4 exceeded, prepare and submit to the Commissionwithin 30 days from the end of the quarter during which release occurred, pursuantto Technical Specification 6.9.2, a Special Report that includes the followinginformation:1. Identification of any inoperable equipment or subsystems, and the reason forthe inoperability,2. Action(s) taken to restore the inoperable equipment to OPERABLE status,and3. Summary description of action(s) taken to prevent a recurrence.c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.122014 CY-OC-170-301Revision 6Page 42 of 140SURVEILLANCE REQUIREMENTS4.11.2.4.1 Operation of the Augmented Off gas System charcoal absorbers shall be verified byverifying the AOG System bypass valve, V-7-31, alignment or alignment indicationclosed at least once every 12 hours whenever the main condenser air ejector isoperating.4.11.2.4.2 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected atleast once per 31 days in accordance with the methodology and parameters in theODCM Part II Section 1.5 in accordance with Technical Specifications 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 43 of 1403/4.11RADIOACTIVE EFFLUENTS3/4.11.3 MARK I CONTAINMENTCONTROLS3.11.3.1 Venting or purging of the containment Drywell may be through normal ReactorBuilding Ventilation if the following requirements are met:APPLICABILITY:If the Station year-to-date radiological effluent releases (either iodine or noblegas) are less than 10% of the ODCM limit, then Standby Gas Treatment is NOTrequired for purging the contents of the Drywell.ACTION:a. If the Station year-to-date radiological effluent releases (either iodine or noble gas)are greater than 10% of the ODCM limit, then the Standby Gas Treatment Systemmust be used for purging the contents of the Drywell.SURVEILLANCE REQUIREMENTS4.11.3.1 The Standby Gas Treatment System is OPERABLE and available whenever thepurge system is in use.122014 CY-OC-170-301Revision 6Page 44 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.4 TOTAL DOSECONTROLS3.11.4.1 In accordance with Oyster Creek Technical Specifications 6.8.4.a. 10, the annual(calendar year) dose commitment to any MEMBER OFTHE PUBLIC due toradioactive material in the effluent and direct radiation from the OCGS in theUNRESTRICTED AREA shall be limited to less than or equal to 75 mrem to thethyroid or less than or equal to 25 mrem to the total body or any other organ.APPLICABILITY: At all timesACTION:a. With the calculated doses from the release of radioactive materials in liquid orgaseous effluents exceeding twice the limits of CONTROLS 3.11.1.2a, 3.11.1.2b,3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, perform an assessment to determinewhether the limits of CONTROL 3.11.4.1 have been exceeded. If such is the case,prepare and submit to the Commission within 30 days, pursuant to TechnicalSpecification 6.9.2, a Special Report that defines the corrective action to be takento reduce subsequent releases to prevent recurrence of exceeding the above limitsand includes the schedule for achieving conformance with the above limits. ThisSpecial Report shall include information specified in 10CFR20.2203. If theestimated dose(s) exceeds the above limits, and if the release condition resulting inviolation of 40 CFR Part 190 has not already been corrected, the Special Reportshall include a request for a variance in accordance with the provisions of 40 CFRPart 190. Submittal of the report is considered a timely request, and a variance isgranted until staff action on the request is complete.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determinedin accordance with SURVEILLANCE REQUIREMENT 4.11.1.2, 4.11.2.2, 4.11.2.3,and in accordance with the methodology and parameters in the ODCM Part II Section3.0 at least once per year.4.11.4.2 Cumulative dose contributions from direct radiation from the facility shall bedetermined in accordance with the methodology and parameters in the ODCM Part IISection 3.2. This requirement is applicable only under conditions set forth inCONTROL 3.11.4, ACTION a.122014 CY-OC-170-301Revision 6Page 45 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAMCONTROLS3.12.1. In accordance with Oyster Creek Technical Specifications 6.8.4.b, the radiologicalenvironmental monitoring program shall be conducted as specified in Table 3.12.1-1.For specific sample locations see Table E-1. Revisions to the non-ODCM requiredportions of the program may be implemented at any time. Non-ODCM samples arethose taken in addition to the minimum required samples listed in Table 3.12.1-1.APPLICABILITY: At all times.ACTION:a. With the radiological environmental monitoring program not being conducted asspecified in Table 3.12.1-1, prepare and submit to the Commission, in the AnnualRadiological Environmental Operating Report required by Technical Specification6.9. 1.e, a description of the reasons for not conducting the program as required andthe plans for preventing a recurrence.b. With the level of radioactivity as the result of plant effluents in an environmentalsampling medium at a specified location exceeding the reporting levels of Table3.12.1-2 when averaged over any calendar quarter, prepare and submit to theCommission within 60 days of the end of the quarter, pursuant to TechnicalSpecification 6.9.2, a Special Report that identifies the cause(s) for exceeding thelimit(s) and defines the corrective actions to be taken to reduce radioactive effluentsso that the potential annual dose* to a MEMBER OF THE PUBLIC is less than thecalendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. When morethan one of the radionuclides in Table 3.12.1-2 are detected in the samplingmedium, this report shall be submitted if:concentration (1) concentration (2) 1.0reporting level (1) reporting level (2)When radionuclides other than those in Table 3.12.1-2 are detected and are theresult of plant effluents, this report shall be submitted if the potential annual dose*to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater thanthe calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. This reportis not required if the measured level of radioactivity was not the result of planteffluents; however, in such an event, the condition shall be reported and describedin the Annual Radiological Environmental Operating Report pursuant to Section6.1.2.1.*The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLICshall be indicated in this report.122014 CY-OC-170-301Revision 6Page 46 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAMCONTROLS (Continued)ACTION: (Continued)C. If garden vegetation samples are unobtainable due to any legitimate reason, it isNOT ACCEPTABLE to substitute vegetation from other sources. The missedsample will be documented in the annual report, with no further actions necessary.If a permanent sampling location becomes unavailable, follow Table 3.12.1-1 TableNotation (1) to replace the location.d. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are notapplicable.SURVEILLANCE REQUIREMENTS4.12.1 The radiological environmental monitoring samples shall be collected pursuant toTable 3.12.1-1 from the specific locations given in Table E-1, and shall be analyzedpursuant to the requirements of Table 3.12.1-1, and the detection capabilitiesrequired by Table 4.12.1-1.122014 CY-OC-1 70-301Revision 6Page 47 of 140TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLE1. DIRECT RADIATION(2)NUMBER OF REPRESENTAIVESAMPLES ANDSAMPLE LOCATIONS(1)Routine monitoringstations with two or more dosimetersplaced as follows:SAMPLING AND TYPE AND FREQUENCYCOLLECTION FREQUENCY OF ANALYSISQuarterlyGamma dose quarterlyAn inner ring of stations one in eachmeteorological sector in the generalarea of the SITE BOUNDARY(At least 16 locations);An outer ring of stations, one in eachland-based meteorological sector inthe approximately 6- to 8-km range fromthe site (At least 14 locations); andAt least 8 stations to beplaced in special interest areas such aspopulation centers, nearby residences,schools, and in one or two areas toserve as control stations.122014 CY-OC-1 70-301Revision 6Page 48 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLE2. AIRBORNERadioiodine andParticulatesNUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)Samples from 5 locations:Three samples from close tothe SITE BOUNDARY in differentsectors of the highest calculatedannual average ground-level D/QOne sample from the vicinityof a community having the highestcalculated annual average ground-level D/Q; andOne sample from a control location,as for example 15-30 km distantand in the least prevalent winddirection (6)SAMPLING ANDCOLLECTION FREQUENCYContinuous sampleroperation with samplecollection weekly ormore frequently ifrequired by dustloadingTYPE AND FREQUENCYOF ANALYSISRadioiodine Canister:1-131 analysis weeklyParticulate SamplerGross beta radioacti-vity analysis follow-ing filter change3) ;Gamma isotopicanalysis(4)of composites (bylocation) quarterly122014 CY-OC-1 70-301Revision 6Page 49 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLE3. WATERBORNEa. Surfaceb. Ground(5)c. DrinkingNUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)One sample upstreamOne sample downstreamSamples from one or two sourcesif likely to be affected1 sample of each of 1 to 3 of thenearest water supplies that couldbe affected by its dischargeSAMPLING ANDCOLLECTION FREQUENCYTYPE AND FREQUENCYOF ANALYSISGrab sample weekly,Combine into monthlycomposite.Grab sample quarterlyGrab sample weekly,combine into a 2-weekcomposite if 1-131 analysisIs required; compositemonthly otherwiseGamma isotopic andtritium analysis(4)Gamma isotopic and tritiumanalysis,4)Gross beta, gammaisotopic and tritium analysismonthly (4)(7)One sample from a backgroundlocation122014 CY-OC-1 70-301Revision 6Page 50 of 140TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLENUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)SAMPLING ANDCOLLECTION FREQUENCYTYPE AND FREQUENCYOF ANALYSISd. SedimentOne sample from downstream area Semiannuallywith existing or potential recreationalvalueGamma isotopicanalysis(4) semiannually122014 CY-OC-1 70-301Revision 6Page 51 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLENUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)SAMPLING ANDCOLLECTION FREQUENCY4. INGESTIONa. Milk (6)No milking animalsIf milk animals are identified:Samples from milking animals inthree locations within 5km havingthe highest dose potential. If thereare none, then one sample frommilking animals in each of three areasbetween 5 an 8 km distant wheredoses are calculated to be greaterthan 1 mrem per year. One samplefrom milking animal at a controllocation 15 to 30 km distant andin the least prevalent wind directionOne sample of available speciesconsumed by man in plantdischarge canalOne sample of available speciesconsumed by man not influencedby plant dischargeSemimonthly when on pasture;monthly at other timesSemiannually,when availableTYPE AND FREQUENCYOF ANALYSISGamma isotopic (4) andIodine -131semimonthly whenanimals are on pasture;monthly at other timesGamma isotopicanalysis (4)on edible portionsb. Fish122014 CY-OC-1 70-301Revision 6Page 52 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLEc. ClamsNUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)One sample of available speciesconsumed by man within theinfluence of the facility discharge.SAMPLING ANDCOLLECTION FREQUENCYSemiannually,when availableTYPE AND FREQUENCYOF ANALYSISGamma isotopicanalysis (4)on edible portions.d. Vegetation (8)One sample of available speciesconsumed by man not influencedby plant discharge.3 samples of broad leafvegetation grown nearest eachof two different Off Site locations ofhighest predicted annual averagecombined elevated and ground levelrelease D/QMonthly duringgrowing seasonGamma isotopicanalysis (4) and 1-131 onedible portion.One sample of each of the similar broadleaf vegetation grown at least 15 to 30 km(9.3-18.6 miles) distant in the least prevalentwind direction.122014 CY-OC-170-301Revision 6Page 53 of 140TABLE 3.12.1-1 (Continued)TABLE NOTATIONSSpecific parameters of distance and direction sector from the centerline of the reactor, andadditional description where pertinent, are provided for each and every sample location inTable 3.12.1-1 and Table E-1. Deviations are permitted from the required sampling scheduleif specimens are unobtainable due to circumstances such as hazardous conditions, seasonalunavailability, malfunction of automatic sampling equipment, and other legitimate reasons. Ifspecimens are unobtainable due to sampling equipment malfunction, effort shall be made tocomplete corrective action prior to the end of the next sampling period. All deviations from thesampling schedule shall be documented in the Annual Radiological Environmental OperatingReport pursuant to CONTROL 6.1.2.4. It is recognized that, at times, it may not be possibleor practicable to continue to obtain samples of the media of choice at the most desiredlocation or time. In these instances suitable specific alternative media and locations may bechosen for the particular pathway in question and appropriate substitutions made within 30days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant toTechnical specification 6.19, submit in the next Radioactive Effluent Release Reportdocumentation for a change in the ODCM including revised figure(s) and table for the ODCMreflecting the new location(s) with supporting information identifying the cause of theunavailability of samples for the pathway and justifying the selection of the new location(s) forobtaining samples. This applies to changes/deletions/additions of permanent samplinglocations. This does not apply to one-time deviations from the sampling schedule. In thosecases, it is NOT ACCEPTABLE to substitute sample media from other sources. The missedsample will be documented in the annual report, with no further actions necessary.2 One or more instruments, such as pressurized ion chamber, for measuring and recordingdose rate continuously may be used in place of, or in addition to, integrating dosimeters. Thenumber of direct radiation monitoring stations has been reduced from the NUREG 1302recommendation due to geographical limitations; e.g., some sectors are over water and somesectors cannot be reached due to lack of highway access, therefore the number of dosimetershas been reduced accordingly.3 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours ormore after sampling to allow for radon and thoron daughter decay. If gross beta activity in airparticulate is greater than ten times the yearly mean of control samples, gamma isotopicanalysis shall be performed on the individual samples.4 Gamma isotopic analysis means the identification and quantification of gamma-emittingradionuclides that may be attributable to the effluents from the facility.5 Groundwater samples shall be taken when this source is tapped for drinking or irrigationpurposes in areas where the hydraulic gradient or recharge properties are suitable forcontamination. Extensive studies of geology and groundwater in the vicinity of the OCGS(Reference 21 and 31) have demonstrated that there is no plausible pathway for effluentsfrom the facility to contaminate offsite groundwater, including the local122014 CY-OC-1 70-301Revision 6Page 54 of 140drinking water supplies. Samples of groundwater, including local drinking water wells, arecollected in order to provide assurance to the public that these water resources are notimpacted.6 The purpose of this sample is to obtain background information. If it is not practical toestablish control locations in accordance with the distance and wind direction criteria, othersites which provide valid background data may be substituted7 1-131 analysis on each composite when the dose calculated for the consumption of the wateris greater than 1 mrem per year. If garden vegetation samples are unobtainable due to anylegitimate reason (see (1) above), it is NOT ACCEPTABLE to substitute vegetation from othersources. The missed sample will be documented in the annual report, with no further actionsnecessary.122014 CY-OC-170-301Revision 6Page 55 of 140TABLE 3.12.1-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS INENVIRONMENTAL SAMPLES -REPORTING LEVELSSurface and Airborne Fish Milk VegetationAnalysis Ground Particulate (pCi/Kg, (pCi/I) (pCi/Kg,Water(pCi/I) and Iodine wet) wet)(pCi/m3)H-3 20000*Mn-54 1000 30000Fe-59 400 10000Co-58 1000 30000Co-60 300 10000Zn-65 300 20000Zr-Nb-95 4001-131 2** 0.9 3 100Cs-134 30 10 1000 60 1000Cs-137 50 20 2000 70 2000Ba-La-140 200 300*For drinking water samples (this is the 40 CFR Part 141 value).If no drinking water pathway exists, a value of 30,000 pCi/L may be used.**If no drinking water pathway exists, a value of 20 pCi/L may be used.122014 CY-OC-1 70-301Revision 6Page 56 of 140TABLE 4.12.1-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLEANALYSIS(1I)(2) LOWER LIMITS OF DETECTION (LLD) (3)Surface and Air Vegetation Sediment Fish, ClamsAnalysis Ground Particulate (pCi/Kg, (pCi/Kg, dry) and CrabsWater and Air wet) (pCi/Kg, wet)(pCi/I) Iodine(pCi/m3)Gross Beta 4 0.01H-3 2000(4)Mn-54 15 130Fe-59 30 260Co-58, 60 15 130Zn-65 30 260Zr-95 30Nb-95 151-131 1(4) 0.07(5) 60Cs-134 15 0.05(6) 60 150 130Cs-137 18 0.06(6) 80 180 150La-140 15Ba-140 60(7)122014 CY-OC-1 70-301Revision 6Page 57 of 140TABLE 4.12.1-1 (Continued)TABLE NOTATIONS1. This list does not mean that only these nuclides are to be considered. Other peaks that areidentifiable, together with those of the above nuclides, shall also be analyzed and reported inthe Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.3.2. Required detection capabilities for dosimeters used for environmental measurements shall bein accordance with the recommendations of Regulatory Guide 4.13.3. The LLD is defined, for purposes of these CONTROLS as the smallest concentration ofradioactive material in a sample that will yield a net count, above system background, that willbe detected with 95% probability with only 5% probability of falsely concluding that a blankobservation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:LLD~ =4.66* SbE | |||
* V | |||
* 2.22 | |||
* Y | |||
* exp(-AýAt)Where:LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass orvolume,Sb is the standard deviation of the background counting rate or of the counting rate of a blanksample as appropriate, as counts per minute,E is the counting efficiency, as counts per disintegration,V is the sample size in units of mass or volume,2.22 is the number of disintegrations per minute per Pico curie,Y is the fractional radiochemical yield, when applicable,X is the radioactive decay constant for the particular radionuclide (sec1), andAt for environmental samples is the elapsed time between sample collection, or end of thesample collection period, and time of counting (sec).Typical values of E, V, Y, and At should be used in the calculation.122014 CY-OC-170-301Revision 6Page 58 of 140TABLE 4.12.1-1 (Continued)TABLE NOTATIONSIt should be recognized that the LLD is defined as an a priori (before the fact) limitrepresenting the capability of a measurement system and not as an a posteriori (after the fact)limit for a particular measurement. Analyses shall be performed in such a manner that thestated LLDs will be achieved under routine conditions. Occasionally, background fluctuations,unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollablecircumstances may render these LLDs unachievable. In such cases, the contributing factorsshall be identified and described in the Annual Radiological Environmental Operating Reportpursuant Technical Specification 6.9.1.e and Control 6.1.2.6.4.4. If no drinking water pathway exists, a value of 3000 pCi/L for tritium and 15 pCi/L for iodine-131 may be used.5. For the air iodine sample6. For the air particulate sample7. Ba-140 and La-140 are in equilibrium122014 CY-OC-170-301Revision 6Page 59 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.2 LAND USE CENSUSCONTROLS3.12.2 In accordance with the Oyster Creek Technical Specifications 6.8.4.b, a land usecensus shall be conducted and shall identify within a distance of 5 miles the location ineach of the 16 meteorological sectors of the nearest milk animal, the nearestresidence and the nearest garden* of greater than 500 ft2 producing broad leafvegetation. The census shall also identify within a distance of 3 miles the location ineach of the 16 meteorological sectors all milk animal and all gardens greater than 500square feet producing broadleaf vegetation.APPLICABILITY: At all times.ACTION:a. With a land use census identifying a location(s) that yields a calculated dose or dosecommitment greater than the values currently being calculated in SURVEILLANCEREQUIREMENT 4.11.2.3, identify the new location(s) in the next RadioactiveEffluent Release Report, pursuant to Control 6.2.2.4.b. With a land use census identifying a location(s) that yields a calculated dose or dosecommitment (via the same exposure pathway) 20 percent greater than at a locationfrom which samples are currently being obtained in accordance with CONTROL3.12.1, add the new location(s) to the radiological environmental monitoring programwithin 30 days. The sampling location(s), excluding the control station location,having the lowest calculated dose or dose commitment(s), via the same exposurepathway, may then be deleted from this monitoring. Pursuant to CONTROL 6.2.2.4,identify the new location(s) in the next Radioactive Effluent Release Report and alsoinclude in the report a revised figure(s) and table for the ODCM reflecting the newlocation(s).c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.12.2 The land use census shall be conducted during the growing season at least once per12 months using that information that will provide the best results, such as by door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.The results of the land use census shall be included in the Annual RadiologicalEnvironmental Operating Report pursuant to CONTROL 6.1.2.2.*Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed atthe SITE BOUNDARY in each of two different direction sectors with the highest predicted elevatedrelease D/Q's in lieu of the garden census. Controls for broadleaf vegetation sampling in Table3.12.1-1, Part 4.c shall be followed, including analysis of control samples.122014 CY-OC-1 70-301Revision 6Page 60 of 1403/412 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4,12.3 INTERLABORATORY COMPARISON PROGRAMCONTROLS3.12.3 In accordance with Oyster Creek Technical Specifications 6.8.4.b.3, analyses shall beperformed on radioactive materials supplied as part of an interlaboratory comparisonprogram which has been approved by the Commission.APPLICABILITY: At all times.ACTION:a. With analyses not being performed as required above, report the reason andcorrective actions taken to prevent a recurrence to the Commission in the AnnualRadiological Environmental Operating Report pursuant to CONTROL 6.1.2.6.3.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.12.3 A summary of the results obtained as part of the above-required InterlaboratoryComparison Program shall be included in the Annual Radiological EnvironmentalOperating Report pursuant to CONTROL 6.1.2.6.3.122014 CY-OC-1 70-301Revision 6Page 61 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.4 METEOROLOGICAL MONITORING PROGRAMCONTROLS3.12.4The meteorological monitoring instrumentation channels shown in Table 3.12.4.-Ishall be operable.APPLICABILITY: At all times.ACTION:a. With less than the minimum required instrumentation channels OPERABLE for morethan 7 days, initiate an Issue Report outlining the cause of the malfunction and theplans for restoring the instrumentation to OPERABLE status.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.TABLE 3.12.4-1METEOROLOGICAL MONITORING INSTRUMENTATIONINSTRUMENTELEVATIONMINIMUMINSTRUMENTOPERABLE1. Wind Speedab.C.380 feet150 feet33 feet1112. Wind Directia.b.C.3. ATa.b.on380 feet150 feet33 feet380-33150-3311111122014 CY-OC-1 70-301Revision 6Page 62 of 140BASES FOR SECTIONS 3.0 AND 4.0CONTROLS AND SURVEILLANCE REQUIREMENTSNOTE: The BASES contained in the succeeding pages summarize the reasons for theCONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS.3/4,3 INSTRUMENTATIONBASES3/4,3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONThe radioactive liquid effluent instrumentation is provided to monitor and control, asapplicable, the releases of radioactive materials in liquid effluents during actual orpotential releases of liquid effluents. The reactor service water system discharge lineradioactivity monitor initiates an alarm in the Control Room when the alarm set point isexceeded. The alarm/trip set points for these instruments shall be calculated andadjusted in accordance with the methodology and parameters in the ODCM to ensurethat the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. TheOPERABILITY and use of this instrumentation is consistent with the requirements ofGeneral Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONThe radioactive gaseous effluent instrumentation is provided to monitor and control, asapplicable, the releases of radioactive materials in gaseous effluents during actual orpotential releases of gaseous effluents. The alarm/trip set points for each of the noblegas monitors shall be calculated and adjusted in accordance with the methodologyand parameters in the ODCM. This will ensure the alarm/trip will occur prior toexceeding the limits of 10 CFR Part 20. The radioactive gas monitors for the stackeffluent and the Augmented Off gas Building exhaust ventilation have alarms whichreport in the Reactor Control Room. The OPERABILITY and use of thisinstrumentation is consistent with the requirements of General Design Criteria 60, 63,and 64 of Appendix A to 10 CFR Part 50.122014 CY-OC-170-301Revision 6Page 63 of 1403/4.11 RADIOACTIVE EFFLUENTSBASES3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATIONThis CONTROL is provided to ensure that the concentration of radioactive materialsreleased in liquid waste effluents to UNRESTRICTED AREAS will be less than theconcentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.This limitation provides additional assurance that the levels of radioactive materials inbodies of water in UNRESTRICTED AREAS will result in exposures within (1) theSection II.A design objectives of Appendix 1, 10 CFR Part 50, to a MEMBER OF THEPUBLIC and (2) the limits of 10 CFR Part 20.106(a) to the population. Theconcentration limit for dissolved or entrained noble gases is based upon theassumption that Xe-1 35 is the controlling radioisotope and its concentration limit in air(submersion) was converted to an equivalent concentration in water using themethods described in International Commission on Radiological Protection (ICRP)Publication 2.The value 1 E-8 is the limit for unidentified gross gamma or beta releases as per 10CFR 20 Appendix B, Table 2, Column 2 "any single radionuclide ... other than alpha orspontaneous fission ... half life greater than 2 hours". This provides operationalflexibility while providing reasonable assurance that dose will remain less than 0.1rem/yr.The required detection capabilities for radioactive materials in liquid waste samplesare tabulated in terms of the lower limits of detection (LLDs). Detailed discussion ofthe LLD, and other detection limits can be found in references 25, 26, and 27.Weekly grab samples for Service Water Effluent are composited for monthly tritiumand gross alpha analysis and quarterly Sr-89/90 and Fe-55 analysis if activity isdetected.While discharging groundwater via the continuous release remediation pathway, thecomposite sample will be analyzed daily for principal gamma emitters and tritium. Amonthly composite sample is analyzed for gross alpha, Sr-89/90, Fe-55, and Ni-63.While discharging groundwater via the batch release mode remediation pathway, agrab sample is collected from each tank and analyzed for principal gamma emittersand tritium, a composite sample is analyzed monthly for gross alpha, Sr-89/90, Fe-55,and Ni-63.Circulating Water Effluent is not included in Table 4.11.1.1.1-1, Radioactive LiquidWaste Sampling and Analysis Program since the Circulating Water is sampled as partof the Radiological Environmental Monitoring Program, Table 3.12.1-1, 3a,Waterborne, Surface downstream sample.122014 CY-OC-170-301Revision 6Page 64 of 1403/4.11.1.2 DOSEThis CONTROL is provided to implement the requirements of Sections II.A, Ill.A, andIV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forthin Section II.A of Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in liquid effluents toUNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dosecalculation methodology and parameters in the ODCM implement the requirements inSection III.A of Appendix I that conformance with the guides of Appendix I be shownby calculational procedures based on models and data, such that the actual exposureof a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to besubstantially underestimated. The equations specified in the ODCM for calculating thedoses due to the actual release rates of radioactive materials in liquid effluents areconsistent with the methodology provided in Regulatory Guide 1.109 and RegulatoryGuide 1.113.3/4.11.1.3 LIQUID RADWASTE TREATMENTThe OPERABILITY of the liquid radwaste treatment system ensures that this systemwill be available for use whenever liquid effluents require treatment prior to theirrelease to the environment. The requirement that the appropriate portions of thissystem be used, when specified, provides assurance that the releases of radioactivematerials in liquid effluents will be kept "as low as is reasonably achievable". ThisCONTROL implements the requirements of General Design Criterion 60 of AppendixA to 10 CFR Part 50 and the design objective given in Section IL.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of theliquid radwaste treatment system were specified as a suitable fraction of the dosedesign objectives set forth in Section II.A of Appendix 1, 10 CFR Part 50, for liquideffluents. Figure D-1-la, Liquid Radwaste Treatment Chem Waste and Floor DrainSystem and Figure D-1 -1 b, Liquid Radwaste Treatment -High Purity and EquipmentDrain System provides details of the Liquid Radwaste Treatment system.3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSE RATEThis CONTROL is provided to ensure that the dose at any time at and beyond theSITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the dosesassociated with the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column1. These limits provide reasonable assurance that radioactive material discharged ingaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in anUNRESTRICTED AREA either within or outside the SITE BOUNDARY, to annualaverage concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITEBOUNDARY, the occupancy of the individual will usually be sufficiently low to122014 CY-OC-170-301Revision 6Page 65 of 140compensate for any increase in the atmospheric diffusion factor above that for theSITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLICwith the appropriate occupancy factors shall be given in the ODCM. The specifiedrelease rate limits restrict, at all times, the corresponding gamma and beta dose ratesabove background to a MEMBER OF THE PUBLIC at or beyond the SITEBOUNDARY to less than or equal to 500 mrem/year to the total body or to less than orequal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times,the corresponding thyroid dose rate above background to a child via the inhalationpathway to less than or equal to 1500 mrem/year.The required detection capabilities for radioactive materials in liquid waste samplesare tabulated in terms of the lower limits of detection (LLDs). Detailed discussion ofthe LLD, and other detection limits can be found in references 25, 26 and 27.Tritium is sampled quarterly for gaseous effluents. Based on the consistency of thedata from the quarterly sampling, the sampling frequency is adequate.3/4.11.2.2 DOSE -NOBLE GASESThis CONTROL is provided to implement the requirements of Section II.B, III.A andIV.A of Appendix 1, 10 CFR Part 50. The CONTROL implements the guides set forth inSection II.B of Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in gaseous effluents willbe kept "as low as is reasonably achievable." The SURVEILLANCEREQUIREMENTS implement the requirements in Section III.A of Appendix I thatconformance with the guides of Appendix I be shown by calculational proceduresbased on models and data such that the actual exposure of a MEMBER OF THEPUBLIC through appropriate pathways is unlikely to be substantially underestimated.The dose calculation methodology and parameters established in the ODCM forcalculating the doses due to the actual release rates of radioactive noble gases ingaseous effluents are consistent with the methodology provided in Regulatory Guide1.109 and Regulatory Guide 1.111. The ODCM equations provided for determining theair doses at and beyond the SITE BOUNDARY are based upon the historical averageatmospheric conditions.3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES INPARTICULATE FORMThis CONTROL is provided to implement the requirements of Section II.C, III.A andIV.A of Appendix 1, 10 CFR Part 50. The CONTROLS are the guides set forth inSection II.C of Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in gaseous effluents toUNRERSTRICTED AREAS will be kept "as low as is reasonably achievable." TheODCM calculational methods specified in SURVEILLANCE REQUIREMENTSimplement the requirements in Section III.A of Appendix I that conformance with theguides of Appendix I be shown by calculational procedures based on models and data122014 CY-OC-170-301Revision 6Page 66 of 140such that the actual exposure of a MEMBER OF THE PUBLIC through appropriatepathways is unlikely to be substantially underestimated. The ODCM calculationalmethodology and parameters for calculating the doses due to the actual release ratesof the subject materials are consistent with the methodology provided in RegulatoryGuide 1.109, and Regulatory Guide 1.111. These equations also provide fordetermining the actual doses based upon the historical average atmosphericconditions. The release rate controls for iodine-1 31, iodine-1 33, tritium, andradionuclides in particulate form with half-life greater than 8 days are dependent onthe existing radionuclide pathways to man, in the areas at and beyond the SITEBOUNDARY. The pathways that were examined in the development of thesecalculations were: 1) individual inhalation of airborne radionuclides, 2) deposition ofradionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animals and meat producing animals grazewith consumption of the milk and meat by man, and 4) deposition on the ground withsubsequent exposure of man.3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEMThe OPERABILITY of the AUGMENTED OFF GAS TREATMENT SYSTEM (AOG)ensures that the system will be available for use whenever gaseous effluents requiretreatment prior to release to the environment. The requirement that the appropriateportions of these systems be used, when specified, provides reasonable assurancethat the releases of radioactive materials in gaseous effluents will be kept "as low as isreasonably achievable." This CONTROL implements the requirements of GeneralDesign Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives givenin Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the useof appropriate portions of the systems were specified as a suitable fraction of the dosedesign objectives set forth in Section II.B and II.C of Appendix 1, 10 CFR Part 50, forgaseous effluents. Figure D-2-1, Gaseous Radwaste Treatment -Augmented Off gasSystem, Figure D-2-2, Ventilation System provide details of the Augmented Off GasTreatment System and Figure D-2-3, AOG Ventilation System.3/4.11.4 TOTAL DOSEThis CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that havenow been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requiresthe preparation and submittal of a Special Report whenever the calculated doses fromplant radioactive effluents exceed 25 mrem to the total body or any organ, except thethyroid, which shall be limited to less than or equal to 75 mrem. It is highly unlikelythat the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of40 CFR Part 190 if the doses remain within twice the dose design objectives ofAppendix I, and if direct radiation doses from the unit, including outside storage tanks,etc. are kept small. The Special Report will describe a course of action that shouldresult in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed thatthe dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cyclesources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated toexceed the requirements of 40 CFR Part 190, the Special Report with a request for a122014 CY-OC-170-301Revision 6Page 67 of 140variance (provided the release conditions resulting in violation of 40 CFR Part 190have not already been corrected), in accordance with the provisions of 40 CFR Part190 and 10 CFR Part 20, is considered to be a timely request and fulfills therequirements of 40 CFR Part 190 until NRC staff action is completed. The varianceonly relates to the limits of 40 CFR Part 190, and does not apply in any way to theother requirements for dose limitation of 10 CFR Part 20, as addressed inCONTROLS 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OFTHE PUBLIC during any period in which he/she is engaged in carrying out anyoperation that is part of the nuclear fuel cycle.122014 CY-OC-170-301Revision 6Page 68 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORINGBASES3/4.12.1 MONITORING PROGRAMThe radiological environmental monitoring program required by this CONTROLprovides representative measurements of radiation and of radioactive materials inthose exposure pathways and for those radionuclides that lead to the highest potentialradiation exposures of MEMBERS OF THE PUBLIC resulting from the stationoperation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and thereby supplements the radiological effluent monitoring program byverifying that the measurable concentrations of radioactive materials and levels ofradiation are not higher than expected on the basis of the effluent measurements andthe modeling of the environmental exposure pathways. Guidance for this monitoringprogram is provided by the Radiological Assessment Branch Position onEnvironmental Monitoring, Revision 1, November 1979.The required detection capabilities for environmental sample analyses are tabulated interms of the lower limits of detection (LLDs). The LLDs required by Table 4.12.1-1 areconsidered optimum for routine environmental measurements in industriallaboratories. It should be recognized that the LLD is defined as an a priori (before thefact) limit representing the capability of a measurement system and not as an aposteriori (after the fact) limit for a particular measurement.Detailed discussion of the LLD, and other detection limits in references 25, 26, and 27.Site-specific research, which included the installation of a groundwatermonitoring well network, has demonstrated that the groundwater pathway is nota potential pathway to man from the OCGS. The surface water into which theOCGS discharges is a marine estuary containing saline water that is not used asdrinking water or irrigation water by man.3/4.12.2 LAND USE CENSUSThis CONTROL is provided to ensure that changes in the use of areas at and beyondthe SITE BOUNDARY are identified and that modifications to the radiologicalenvironmental monitoring program are made if required by the results of this census.The best information from the door-to-door survey, from aerial survey, from visualsurvey or consulting with local agricultural authorities shall be used. This censussatisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than 50 m2 (500 ft2) provides assurancethat significant exposure pathways via leafy vegetables will be identified andmonitored since a garden of this size is the minimum required to produce the quantity(26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumptionby a child. To determine this minimum garden size, the following assumptions weremade: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar tolettuce and cabbage), and 2) a vegetation yield of 2 kg/M2.122014 CY-OC-1 70-301Revision 6Page 69 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORINGBASES3/4.12.3 INTERLABORATORY COMPARISON PROGRAMThe requirement for participation in an approved Interlaboratory Comparison Programis provided to ensure that independent checks on the precision and accuracy of themeasurements of radioactive material in environmental sample matrices areperformed as part of the quality assurance program for environmental monitoring inorder to demonstrate that the results are valid for the purposes of Section IV.B.2 ofAppendix I to 10 CFR Part 50.5.05.0 DESIGN FEATURES / SITE MAP(Provided FOR INFORMATION ONLY. Technical Specifications are controlling.)5.1 Site map which will allow identification of structures and release points shall be asshown in Figure E-4.122014 CY-OC-170-301Revision 6Page 70 of 1406.0 ADMINISTRATIVE CONTROLS6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)6.1.1 In accordance with Oyster Creek Technical Specifications 6.9.1 .e, a routine radiologicalenvironmental operating report covering the operation of the unit during the previouscalendar year shall be submitted prior to May 1 of the following year.6.1.2 The Annual Radiological Environmental Operating Reports shall include:6.1.2.1 Summaries, interpretations, and an analysis of trends of the results of the radiologicalenvironmental surveillance activities (Radiological Environmental Monitoring Program -REMP) for the report period. This will include a comparison with preoperational studies,with operational controls (as appropriate), and with previous environmental surveillancereports, and an assessment of the observed impacts of the plant operation on theenvironment.6.1.2.2 The reports shall also include the results of land use censuses required by CONTROL3.12.2. If harmful effects or evidence of irreversible damage are detected by themonitoring, the report shall provide an analysis of the problem and a planned course ofaction to alleviate the problem.6.1.2.3 The Annual Radiological Environmental Operating Reports shall include summarizedand tabulated results similar in format to that in Regulatory Guide 4.8, December 1975 ofall the radiological environmental samples taken during the report period.6.1.2.4 Deviations from the sampling program identified in CONTROL 3.12.1 shall be reported.6.1.2.5 In the event that some individual results are not available for inclusion with the report,the report shall be submitted noting and explaining the reasons for the missing results.The missing data shall be submitted as soon as possible in a supplementary report.6.1.2.6 The reports shall also include the following:a. A summary description of the radiological environmental monitoringProgram;b. Map(s), covering sampling locations, keyed to a table giving distances and directionsfrom the reactor;c. The results of licensee participation in the Inter-laboratory ComparisonProgram, as required by CONTROL 3.12.3;d. Identification of environmental samples analyzed when the analysis instrumentationwas not capable of meeting the detection capabilities in Table 4.12.1-1.122014 CY-OC-1 70-301Revision 6Page 71 of 1406.2 ANNUAL ROUTINE RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)6.2.1 Routine radioactive effluent release reports covering the operation of the unit shall besubmitted prior to May 1 of each year and in accordance with the requirements of1OCFR50.36a and section IV.B.1 of 10CFR 50 Appendix I.6.2.2 The Radioactive Effluent Release Report shall include:6.2.2.1 A summary of the quantities of radioactive liquid and gaseous effluents and solid wastereleased from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating,and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials inLiquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision1, June 1974, with data summarized on a quarterly basis following the format ofAppendix B thereof.6.2.2.2 An annual summary of hourly meteorological data collected over the previous year. Thisannual summary may be in the form of joint frequency distributions of wind speed, winddirection, and atmospheric stability. Alternatively, summary meteorological data may beretained and made available to the NRC upon request.6.2.2.3 An assessment of the radiation doses due to the radioactive liquid and gaseouseffluents released from the unit or station during the previous calendar year. Thehistorical annual average meteorology or the meteorological conditions concurrent withthe time of release of radioactive materials in gaseous effluents (as determined bysampling frequency and measurement) shall be used for determining the gaseouspathway doses. The assessment of radiation doses shall be performed in accordancewith this OFF SITE DOSE CALCULATION MANUAL (ODCM).6.2.2.4 Identify those radiological environmental sample parameters and locations where it isnot possible or practicable to continue to obtain samples of the media of choice at themost desired location or time. In addition, the cause of the unavailability of samples forthe pathway and the new location(s) for obtaining replacement samples should beidentified. The report should also include a revised figure(s) and table(s) for the ODCMreflecting the new location(s).6.2.2.5 An assessment of radiation doses to the likely most exposed MEMBER OF THEPUBLIC from reactor releases and other nearby uranium fuel cycle sources (includingdoses from primary effluent pathways and direct radiation) for the previous calendaryear to show conformance with 40 CFR Part 190, Environmental Radiation ProtectionStandards for Nuclear Power Operation. The assessment of radiation doses shall beperformed in accordance with this OFF SITE DOSE CALCULATION MANUAL (ODCM)Part II Sections 1.5, 2.4, 2.5 and 3.2.6.2.2.6 The Radioactive Effluent Release Reports shall include the following information foreach class of solid waste (as defined by 10 CFR Part 61) shipped Off Site during thereport period (see Figure D-1-2):a. Total volume shippedb. Total curie quantity (specify whether determined by measurement or estimate),c. Principal radionuclides (specify whether determined by measurement or estimate),122014 CY-OC-170-301Revision 6Page 72 of 140d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporatorbottoms)6.2.2.7 Unplanned releases from the site to UNRESTRICTED AREAS of radioactive materialsin gaseous and liquid effluents on a quarterly basis.6.2.2.8 Changes to the PROCESS CONTROL PROGRAM (PCP)6.2.2.9 Changes to the OFF SITE DOSE CALCULATION MANUAL (ODCM) in the form of acomplete, legible copy of the ODCM.6.3 RESPONSIBILITIES:6.3.1 Chemistry / Radwaste -Responsible for:6.3.1.1 Implementing approval.6.3.1.2 Compliance with specifications regarding routine dose assessment.6.3.1.3 Radiological Environmental Monitoring Program6.3.1.4 Technical consultation and review6.3.2 Operations -Responsible for compliance with specifications regarding operation of theOCGS.6.3.3 Engineering -Responsible for compliance with specifications regarding set pointdetermination and implementation6.3.4 Radiological Engineering -Responsible for technical consultation and review.122014 CY-OC-170-301Revision 6Page 73 of 140PART II -CALCULATIONAL METHODOLOGIES1.0 LIQUID EFFLUENTS1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLSThe liquid effluent monitoring instrumentation and controls at Oyster Creek forcontrolling and monitoring normal radioactive material releases in accordance with theOyster Creek Radiological Effluent Technical Specifications are summarized as follows:Reactor Building Service Water Effluent -The Reactor Building Service Water EffluentLine Monitor provides an alarm function only for releases into the environment.Liquid radioactive waste flow diagrams are presented in Figures D-1-la, D-1-lb, and D-1-1c.1.2 LIQUID EFFLUENT MONITOR SET POINT DETERMINATIONPer the requirements of CONTROL 3.3.3.10, alarm set points shall be established forthe liquid monitoring instrumentation to ensure that the release concentration limits ofCONTROL 3.11.1.1 are met (i.e., the concentration of radioactive material released inliquid effluents to UNRESTRICTED AREAS at the U.S. route 9 bridge over thedischarge canal shall not exceed the concentrations specified in 10 CFR 20 AppendixB. Table 2, Column 2, for radionuclides and 2E-04 pCi/ml for dissolved or entrainednoble gases).1.2.1 LIQUID EFFLUENT MONITORSThe set points for the liquid effluent monitors at the Oyster Creek Generating Station aredetermined by the following equation:A F2 +BKGFLEC F IWhere:S = radiation monitor alarm set point (cpm)A = activity concentration (ptCi/ml) of sample in laboratory: A = Y.Cig = the primary conversion factor for the instrument -the ratio of effluent radiationmonitor counting rate to laboratory activity concentration in a sample of liquid (cpmper pCi/mL).F1 = flow in the batch release line (e.g. gal/min). Value not greater than the discharge lineflow alarm maximum set point.122014 CY-OC-170-301Revision 6Page 74 of 140F2. = flow in the discharge canal (e.g. gal/min). Value not less than the discharge canalminimum flow.BKG = Monitoring instrument background (cpm)FLEC = fraction or multiple of unrestricted area LEC in aqueous effluent based on sampleanalysis. FLEC is the ratio between the LECi and Ci. FLEC is unitless. Forexample: LEC for Co-60 is 3E-6 ýiCi/mL. If the concentration in a expected releaseis 6E-6 j.LCi/mL; then FLEC is 6E-6/3E-6 = 2.The term A represents the count rate of a solution having the same nuclideFLECdistribution as the sample and the LEC of that mixture.Ci = concentration of radionuclide i in effluent, i.e., in a liquid radwaste sample tank, inreactor building service water (pCi/mL).LEC, =the unrestricted area liquid effluent concentration (LEC) of radionuclide i, i.e., 10 CFR20, Appendix B, Table 2, Column 2 quantity for radionuclide i (p.Ci/mL).In the event gross radioactivity analysis alone is used to determine the radioactivity inan effluent stream or batch, FLEC is C/1E-8 (see 4.11.1.1.1),Where:C = the gross radioactivity concentration in effluent (ltCi/mL).1 E-8 = the unrestricted area LEC for unidentified radionuclides (jtCi/mL) from 4.11.1.1 .1.If the gross activity concentration, C, is below the lower limit of detection for grossactivity, the value, 1 E-8 j+/-Ci/mL, or the equivalent counting rate (cpm/mL) may besubstituted for the factor AFLECA = 1 E-8 ICi/mLFLEC1.2.2 SAMPLE RESULT SET POINTSUsually, when the concentration of specific radionuclides is determinable in a sample(s),i.e., greater than the LLD, the alarm/trip set point of each liquid effluent radioactivitymonitor is based upon the measurement of radioactive material in a batch of liquid to bereleased or in a continuous aqueous discharge.122014 CY-OC-170-301Revision 6Page 75 of 1401.2.3 ASSUMED DISTRIBUTION SET POINTSAlternatively, a radionuclide distribution that represents the distribution expected to be inthe effluent if the concentration were high enough to be detectable, i.e., greater than theLLD, may be assumed. The representative distribution may be based upon pastmeasurements of the effluent stream or upon a computed distribution.1.3 BATCH RELEASESA sample of each batch of liquid radwaste is analyzed for 1-131 and other principalgamma emitters or for gross beta or gross gamma activity before release. The result ofthe analysis is used to calculate the trip set point of the radioactivity monitor on theliquid radwaste effluent line to apply to release of the batch.1.4 CONTINUOUS RELEASESThe Reactor Building Service Water Effluent is sampled and analyzed weekly for 1-131,other principal gamma emitters. Results of analyses for the preceding week or for aperiod as long as the preceding 3 months are used to calculate the alarm/trip set pointof the corresponding effluent radioactivity monitor in order to determine a representativevalue. In each case, whether batch or continuous, the monitor alarm/trip set point maybe set at lower activity concentration than the calculated set point.1.5 LIQUID EFFLUENT DOSE CALCULATION -10 CFR 50Doses resulting from the release of radioiodines and particulates must be calculated toshow compliance with Appendix I of 1OCFR50. Calculations will be performed at leastmonthly for all liquid effluents as stated in SURVEILLANCE REQUIREMENT 4.11.1.2and SURVEILLANCE REQUIREMENT 4.11.1.3.1 to verify that the dose to MEMBERSOF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.1.2The maximum dose to an individual from radioiodines, tritium, and radioactiveparticulates with half-lives of greater than eight days in liquid effluents released tounrestricted areas is determined as described in Reg. Guide 1.109. Environmentalpathways that radioiodine, tritium, and particulates in liquid effluent follow to themaximally exposed MEMBER OF THE PUBLIC are assumed to be: exposure toshoreline deposits, ingestion of fish, and ingestion of shellfish. To assess compliancewith CONTROL 3.11.1.2, the dose due to radioactive iodine, tritium, and particulates inliquid effluent is calculated to a person at the Route 9 bridge who consumes fish andshellfish harvested at that location.122014 CY-OC-1 70-301Revision 6Page 76 of 1401.5.1 MEMBER OF THE PUBLIC DOSE -LIQUID EFFLUENTSCONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THEPUBLIC from radioactive materials in liquid effluents from Oyster Creek GeneratingStation to those listed in Table 1.5.1-1.TABLE 1.5.1-1 LIQUID PATHWAY DOSE LIMITSDuring Any Calendar Quarter During Any Calendar Year< 1.5 mrem to total body < 3.0 mrem to total body< 5.0 mrem to any organ < 10.0 mrem to any organPer the SURVEILLANCE REQUIREMENTS of 4.11.1.2, the following calculationmethods shall be used for determining the dose or dose commitment due to the liquidradioactive effluents from Oyster Creek. Applicable liquid pathways to man for OysterCreek include shoreline exposure, and ingestion of saltwater fish and shellfish. Thereceptor location is provided in Table A-4.1.5.2 SHORELINE DEPOSIT DOSEThe shoreline exposure pathway dose is calculated generally in the form (based onReg. Guide 1.109):Rapj = 110000 UapWM QiTiDaipj (1 -exp(-XiTb))FWhere:110000 = a constant that accounts for time and flow conversionsRapj = the annual dose to organ j (including the total body), through pathway p, to agegroup aUap = the age dependent usage factor for the specific pathway. Usage factors for shorelineexposure are residence time on the shoreline (hours). Usage factors are provided inReg. Guide 1.109 Table E-5. Usage factors specifically selected for Oyster Creek arepresented in Table B-I.W = the shore width factor. This adjusts the infinite plane gamma or beta dose factors forthe finite size and shape of the shoreline. Different factors apply to different bodies ofwater. A factor of 0.1 is used for OC for 'discharge canal bank'.M = the recirculation factor. The recirculation factor is a multiplier of 3.76 to account forrecirculation of discharge water back into the intake. Although this occursinfrequently, it is assumed to occur for each liquid release.122014 CY-OC-170-301Revision 6Page 77 of 140F = the flow rate in the discharge canal in cubic feet per secondQi = the activity of the ith isotope in the release in curiesTi = the half life of the ith isotope in daysDaipj =the age a, isotope i, pathway p, and organ j, specific dose conversion factor.Pathway, isotope, age, and organ specific dose factors are obtained from RegulatoryGuide 1.109 Appendix E, Tables E-6 through E-14Xi = the decay constant of the ith isotope in yearsTb = the long term buildup time, assumed to be 30 yearsNote: ki and Tb can use any time units as long as they are both the same. Notransit delay (Tp from Reg. Guide 1.109) is assumed.1.5.3 SHORELINE DOSE EXAMPLE 1The following provides an example of the liquid dose calculation:Initial parameters:Canal flow rate 1 E6 gpm (typical of normal full power operation)Release: 10,000 gallons of water at 1 E-3 LCi/ml Co-60Problem: calculate shoreline whole body doseUap = 67 (teenager) hoursW =0.1M = 3.76F = 2228 [1E6 gpm *3785 ml /gal/ (60 sec/min | |||
* 28316 ml/ft3) = 2228 CFS]Qi = 0.03785 Ci [1E-3uCi/ml | |||
* 10000gal | |||
* 3785ml/gal/1E6 uCi/Ci = 0.03785 Ci]Ti = 1920 [5.27 years*365 days/yr = 1.92E3 days)Mi = 1.31E-1 [0.693/(5.27yrs)]Tb = 30 yearsDaipj = 1.7E-8 mrem/hr / pCi/m2 Gamma dose factorCalculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotopeRapj = 110000-67.0.l*3.76 -0.03785" 1920* 1.7E- 8 * (I -exp(-1.3E -I | |||
* 30))2228 1Rapj =1.5 IE -3 mrem: teen: wholebody122014 CY-OC-1 70-301Revision 6Page 78 of 1401.5.3.1 SHORELINE DOSE EXAMPLE 2The following provides an example of the liquid dose calculation for groundwaterremediation discharge:Initial parameters:Canal flow rate 1 E6gpm (typical of normal full power operation)Release: 50 gpm for 7 days at 1 E-8 pCi/mI Co-60Problem: Calculate shoreline whole body doseUap = 67 (teenager) hoursW =0.1M = 3.76F = 2228 [1E6 gpm *3785 ml / gal / (60 sec/min | |||
* 28316 ml/ft3) = 2228 CFS]Qi = 1.91E-5 Ci [1E-08 pCi/ml*50gpm*7days*24hr/day*60 min/hr*3785ml/gal/1E+6 pCi/Ci]Ti = 1920 [5.27 years*365 days/yr = 1.92E+03 days)Xi = 1.31E-1 [0.693 /(5.27 yrs)]Tb = 30 yearsDaipj = 1.7E-8 mrem/hr / pCi/m2 External Dose factorCalculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotope67*0.1*376Rapj 110000 *37 -1.9 1E- 5"* 1920"* 1.7E -8"* (1- exp(-l1.31E -1*30))2228 jRapj = 7.60E- 7 mrem: teen: wholebody1.5.4 INGESTION DOSE -LIQUIDIngestion dose pathway calculations are similar to those for the shoreline dose,with minor changes in constants, removal of the shore width factor, and inclusion ofthe bioaccumulation factor:Rapj = 1100 UapMQiBipDaipjFWhere:Bip = the stable element bioaccumulation factor for pathway p for the ith isotopeNo transit delay is assumedPathway, isotope, age, and organ specific dose factors are obtained from RegulatoryGuide 1.109 Appendix E Tables E-7 through E-14. Bioaccumulation factors are122014 CY-OC-1 70-301Revision 6Page 79 of 140provided in Reg. Guide 1.109 Table A-1. Usage factors are provided in Reg. Guide1.109 Table E-5. Usage factors specifically selected for Oyster Creek are presented inTable B-1.The radionuclides included in the periodic dose assessment per the requirements ofCONTROL 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquidwaste samples collected and analyzed per the requirements of CONTROL 3/4.11 .1.1,Table 4.11.1.1.1-1.Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added tothe dose analysis at a frequency consistent with the required minimum analysisfrequency of Table 4.11.1.1.1-1.1.5.5 INGESTION DOSE CALCULATION EXAMPLE 1The following provides an example of the liquid dose calculation:Initial parameters:Canal flow rate 1 E6 gpm (typical of normal full power operation)Release: 10000 gallons of water at 1 E-3 .tCi/mL Co-60Problem: calculate teen whole body dose from saltwater fish ingestionRapj = 100 UapM QiBipDaipjFUap = 16 (teenager) KgM = 3.76F = 2228 [1E6 gpm *3785 ml/gal/(60 sec/min | |||
* 28316 ml/ft3) = 2228 CFS]Qi = 0.03785 Ci [1E-3uCi/mL | |||
* 10000gal | |||
* 3785mL/gal /1 E6 uCi/Ci = 0.03785 Ci]Bip = 100Daipj = 6.33E-6 mrem / pCiCalculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotopeRap ~10016*3. 76Rapj =I100 12 37 0.03785 *100 6.33E-62228 hRapj = 7.12 E -4 mrem *teen *wholebody122014 CY-OC-1 70-301Revision 6Page 80 of 1401.5.5.1 INGESTION DOSE CALCULATION EXAMPLE 2The following provides an example of the liquid dose calculation for ground waterremediation discharge:Initial parameters:Canal flow rate 1 E6 gpm (typical of normal full power operation)Release: 50 gpm for 7 days at 700,000 pCi/I H-3Problem: calculate teen whole body dose from saltwater fish ingestionRap] = 1100 Uap QiBipDaipjFUap = 16 (teenager) KgM = 3.76F = 2228 [1E6 gpm *3785 ml /gal /(60 sec/min | |||
* 28316 mlI/ft3) = 2228 CFS]Qi = 1.34 Ci [7E+5 pCi/l*50gpm*7days*24hr/day*60 min/hr*3.785 I/gall 1E+12 pCi/Ci]Bip = 0.90 (Regulatory Guide 1.109, Table A-I)Daipj = 1.06E-07 mrem / pCiCalculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotopeRapj =100 163.76 1.340.9 .06E-72228 iRapj = 3.80 E -6 mrem :teen : wholebody1.5.6 PROJECTED DOSE -LIQUIDThe projected doses in a 31 day period are equal to the calculated doses from thecurrent 31 day period.1.6 REPRESENTATIVE SAMPLESA sample should be representative of the bulk stream or volume of effluent from which itis taken. Prior to sampling, large volumes of liquid waste should be mixed in as short atime interval as practicable to assure that any sediments or particulate solids aredistributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks(collection or sample test tanks) should be capable of recirculating at a rate of not lessthan two tank volumes in eight hours. Minimum recirculation times and methods ofrecirculation are controlled by specific plant procedures.122014 CY-OC-170-301Revision 6Page 81 of 1402.0 GASEOUS EFFLUENTS2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLSThe gaseous effluent monitoring instrumentation and controls at Oyster Creek forcontrolling and monitoring normal radioactive material releases in accordance with theRadiological Effluent CONTROLS are summarized as follows:(1) Main StackThe main stack receives normal ventilation flow from the reactor building, newradwaste, old radwaste, process discharge flow from the augmented off gas system(AOG), condenser off gas flow if AOG is not in service, and normal ventilation flow fromportions of the turbine building, predominantly the condenser bay area. Reactor buildingand turbine building flow is not normally processed or filtered. Reactor Building flow maybe manually or automatically directed through the Standby Gas Treatment System(SBGTS) which has particulate and charcoal filtration. Off gas flow is processedthrough AOG or through a 30-minute delay pipe prior to release. Flow from the 'new'and 'old' radwaste buildings is HEPA filtered. Releases through the main stack aremonitored for noble gases using the RAGEMS I system and sampled for iodine,particulates and tritium. The plant stack is considered to be a true elevated releasepoint.(2) Turbine Building VentThe Turbine building vent is monitored for noble gases by the RAGEMS II system andsampled for iodine, particulates and tritium. It discharges on the west side of the turbinebuilding approximately at roof height and is considered to be a ground level release. Itventilates the turbine floor and other areas of the turbine building. Flow through thisrelease point is not filtered.(3) Feed Pump Room VentThe feed pump room vent is monitored by RAGEMS II. It discharges on the east side ofthe turbine building below roof height and is considered to be a ground level release. Itventilates the reactor feed pump room. Flow through this release point is not filtered.(4) Augmented Off Gas Building VentOff gas Building HVAC is released through a ground level release from the building. OffGas process flow is not released through the building ventilation, but is routed to thestack plant. A ventilation monitoring system monitors for noble gas and samples forparticulate and iodine.122014 CY-OC-1 70-301Revision 6Page 82 of 140(5) Isolation CondensersThe isolation condensers are a ground level release. The predominant isotope throughthis potential release point is tritium as a consequence of the forced evaporation ofcondensate transfer water when the isolation condensers are initiated. Releases areneither monitored nor is the release process flow sampled. Releases of tritium areevaluated based on liquid samples of the input and the volume used.Gaseous radioactive waste flow diagrams with the applicable, associated radiationmonitoring instrumentation controls are presented in Figures D-2-1 and D-2-2.2.2 GASEOUS EFFLUENT MONITOR SET POINT DETERMINATION2.2.1 PLANT VENTPer the requirements of CONTROL 3.3.3.11, alarm set points shall be established forthe gaseous effluent monitoring instrumentation to ensure that the release rate of noblegases does not exceed the limits of CONTROL 3.11.2.1, which corresponds to a doserate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year tothe skin. Based on a grab sample analysis of the applicable release (i.e., of the Stack,Off gas process flow, etc.), the radiation monitoring alarm set points may be establishedby the following calculation methods. A set point of a monitor of an elevated release,e.g., from the stack, may be calculated using the equation:s = 1.6 Z CiS=1.6~f Z (CiDFSi)+BgWhere:S = the alarm set point (cpm)h = primary conversion factor of the instrument -monitor response to activityconcentration of effluent being monitored, cpm/(pLCi/cm3). Each monitoring channelhas a unique response, h, which is determined by the instrument calibration.Ci = relative concentration of noble gas radionuclide i in effluent at the point ofmonitoring (gCi/cm3)1.06 = 500 mrem/year /472 (conversion of cfm to cc/sec)DFSi = factor converting elevated release rate of radionuclide i to total body doseequivalent rate at the location of potential exposure. Units are: mrem/(yr(jiCi/sec)).From Table A-I.f = flow of gaseous effluent stream being monitored, i.e., stack flow, vent flow, etc.(ft3/min)122014 CY-OC-1 70-301Revision 6Page 83 of 140BKG = Monitoring instrument background (cpm or mR/hr)2.2.2 OTHER RELEASE POINTSThe set point of a monitor of a ground-level or vent release, e.g., from the turbinebuilding vent or the AOG building, may be calculated with the equation:h CiS = 1.06 [h ]) + BkgWhere:DFVi = factor converting ground-level or vent release of radionuclide i to the total body doseequivalent rate at the location of potential exposure. Units are: mrem-m3/p.Ci-yearFrom Table A-I.X/Q = atmospheric dispersion from point of ground-level or vent release to the location ofpotential exposure (sec/m3) from Table 2.2.2-1.The atmospheric dispersion, X/Q, and the dose conversion factor, DFSi, depend uponlocal conditions. For the purpose of calculating radioactive noble gas effluent monitoralarm set points appropriate for the OCGS, the locations of maximum potential Off Siteexposure and the reference atmospheric dispersion factors applicable to the derivationof set points are given in Table 2.2.2-1.Symbols for this equation were defined in Section 2.2.1.TABLE 2.2.2-1 RECEPTOR LOCATIONS AND DISPERSION FOR GASEOUS MONITOR SETPOINTSDischarge Point Receptor Location Atm. DispersionSector Distance(m) (sec/mi3)Ground-levelor vent ENE 338 4.59 E-5Stack SW 229 N/A2.2.3 RADIONUCLIDE MIX FOR SET POINTSFor the purpose of deriving a set point, the distribution of radioactive noble gases in aneffluent stream may be determined in one of the following ways:122014 CY-OC-170-301Revision 6Page 84 of 1402.2.3.1 Preferably, the radionuclide distribution is obtained by gamma isotopic analysis ofidentifiable noble gases in effluent gas samples. Results of the analyses of one or moresamples may be averaged to obtain a representative spectrum.2.2.3.2 In the event a representative distribution is unobtainable from recent measurements bythe radioactive gaseous waste sampling and analysis program, it may be based uponpast measurements.2.2.3.3 Alternatively, the total activity concentration of radioactive noble gases may beassumed to be Xenon-1 33 as found in Reg Guide 1.97.2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS -10CFR 202.3.1 SITE BOUNDARY DOSE RATE -NOBLE GASESCONTROL 3.11.2.1a limits the dose rate at the SITE BOUNDARY due to noble gasreleases to < 500 mrem/yr, total body and < 3000 mrem/yr, skin. Radiation monitoralarm set points are established to ensure that these release limits are not exceeded.In the event any gaseous releases from the station results in an alarm set point (asdetermined in Section 2.2) being exceeded, an evaluation of the SITE BOUNDARYdose rate resulting from the release shall be performed.2.3.1.1 TOTAL BODY DOSE RATEThe total body dose equivalent rate from radioactive noble gases discharged from anelevated point (stack above building wake) is calculated with the equation:DG- i'siFrom a ground-level release (building vent) the total body dose equivalent rate is:DG= QiPYViQV,Where:DG = total body dose equivalent rate due to irradiation by radioactive noble gas (mrem/hr)Qi = average discharge rate of noble gas radionuclide i released during the averagingtime (p.Ci/hr)PyVi = factor converting time integrated ground-level concentration of noble gas nuclide ito total body dose mrem -m3. See Table A-2.pCi -secxX = atmospheric dispersion factor from the OCGS to the Off Site location of interestQV(sec/m3) from Table 2.3.1.3-1122014 CY-OC-170-301Revision 6Page 85 of 140PySi factor converting unit noble gas nuclide i stack release to total body dose at groundlevel received outdoors from the overhead plume (mrem/[tCi). See Table A-2The noble gas plume gamma-to-total body dose factors, PSi at designated locations arederived from meteorological dispersion data with the USNRC RABFIN softwarecomputer code or similar computer program implementing Reg Guide 1.109, AppendixB. The noble gas semi-infinite cloud gamma-to-total body dose factors, P',Vi, are derivedfrom Reg Guide 1.109, Revision 1, Table B-I, Column 5.2.3.1.2 EXAMPLE TOTAL BODY DOSE RATECalculate the dose from a release of 100 Ci of Xe1 33 in 1 hour from a ground levelreleaseDG = X QiPyViQV,X/Qv =4.59E-5 sec/m3 (Table 2.3.1.3-1)Qi 1 E8 gCi/hr [1 00Ci*1 E6 gCi/Ci]P'yVi 9.33E-6 mrem-m3 / ltCi-secDG = 4.59E-5Z 1E8*9.33E-6DG = 0.043 mrem /hr2.3.1.3 SKIN DOSE RATEThe dose equivalent rate to skin from radioactive noble gases is calculated by assuminga person at ground level is immersed in and irradiated by a semi-infinite cloud of thenoble gases originating in airborne effluent. It is calculated for each air effluentdischarge point with the equation:DB = X .Qi(SBi+1.11AyVi)Qwhere:DB dose rate to skin from radioactive noble gases (mrem/hr)X-- :=Atmospheric dispersions from gaseous effluent discharge point to ground-levellocation of interest (sec/m3) from Table 2.3.1.3-1.Qi discharge rate of noble gas radionuclide i (liCi/hr)122014 CY-OC-1 70-301Revision 6Page 86 of 140SBi = factor converting time integrated ground-level concentration of noble gas radionuclidei to skin dose from beta radiation mrem -m3 from Table A-2.pCi | |||
* secAyVi = factor for converting time integrated, semi-infinite concentration of noble gasradionuclide i to air dose from its gamma mrad -m from Table A-2.pCi | |||
* secThe noble gas beta radiation-to-skin-dose factors, SBj and the noble gas gamma-to-airdose factors, AyV1, are derived from Reg Guide 1.109, Revision 1, Table B-i, columns 3and 4 respectively. A tabulation of these factors used to compute noble gas-to-doseequivalent rate at 338 meters ENE for ground-level or vent and 544 meters SE for stackfrom the OCGS is in Table A-2.The dose equivalent rate is calculated with the meteorological dispersion data given inTable 2.3.1.3-1.TABLE 2.3.1.3-1 RECEPTOR LOCATIONS AND DISPERSION FOR SITE BOUNDARY DOSERATESDischarge Point Receptor Location Atm. DispersionSector Distance (m) (sec/m3)Ground Level ENE 338 4.59 E-5or VentStack SE 544 1.05 E-8Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the requirements of Regulatory Guide 1.109 may be used.Actual meteorological conditions concurrent with the release period or the default,annual average dispersion parameters as presented above may be used for evaluatingthe gaseous effluent dose rate.2.3.1.4 EXAMPLE SKIN DOSE RATECalculate the skin dose from a release of 100 Ci of Xel 33 in 1 hour from a ground levelrelease:xDB = -Qi(SBi + 1.llAyVi)QIX/Q =4.59 E-5 sec/m3Qi = 1E8 itCi/hrSBi = 9.71 E-6 mrem/ýtCi/ m3/secA'yVi = 1.12E-5 mrad/yr per p.Ci/m3122014 CY-OC-170-301Revision 6Page 87 of 140DB = 4.59E- 51 lE8(9.71E-6+ 1.11 *1.12E -5)DB = O. 102mrad / hr2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES2.3.2.1 METHOD -SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATESThe dose rate Off Site due to the airborne release of 1-131, 1-133, tritium, andparticulates with half-lives greater than 8 days is limited to no more than 1500 mrem/yrto any organ in CONTROL 3.11.2.1 b. Evaluation of compliance with CONTROL3.11.2.1 b is based on the sampling and analyses specified in TABLE 4.11.2.1.2-1.Since the dose rate cannot be resolved within less than the sample integration orcompositing time, the contribution of each radionuclide to the calculated dose rate willbe averaged no more than 3 months for H-3, Sr-89, Sr-90, and alpha-emittingradionuclides and no more than 31 days for other radionuclides. These are their usualsample integration or compositing times. The equation used to assess compliance ofradioiodine, tritium, and radioactive particulate releases with the dose rate limit is:11XDRp = 1E6- I RaDFAijaQe Xe iQeWhere:1 E6 = conversion pCi/jiCiDRp = the average dose rate to an organ via exposure pathway, p (mrem/yr).DFAija = inhalation dose factors due to intake of radionuclide i, to organ j age group a(mrem/pCi) from Reg. Guide 1.109 Appendix E.Ra = age group dependent inhalation respiratory rate (usage factor) m3/yr from Table B-1x= annual average relative airborne concentration at an Off Site location due to aQerelease from either the Stack or a vent, i.e. release point, e (sec/m3) from Table2.3.2.1-1.Qei = release rate of radionuclide i from release point, e during the period of interest(p.Ci/sec).For real-time meteorology and on an annual average basis, the location of themaximum ground-level concentration originating from a vent release will differ from themaximum ground-level concentration from a stack release. When assessing122014 CY-OC-1 70-301Revision 6Page 88 of 140compliance with CONTROL 3.11.2.1 b for tritium, iodine, and particulate, the airdispersion (X/Q) values are provided in Table 2.3.2.1-1.TABLE 2.3.2.1-1 LOCATION OF MAXIMUM EXPOSURE RE BY INHALATIONDischarge Point Receptor Location Atm. DispersionSector Distance (m) (sec/m3)Ground Levelor Vent ENE 338 4.59 E-5Stack SE 937 1.25 E-8Alternatively, inhalation exposure to effluent from the stack may be evaluated at the closesthypothetical individual located at:Stack SE 805 1.29 E-8Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the methods of Regulatory Guide 1.109, may be used.2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATIONCalculate the child thyroid dose rate from a release of 100 jtCi/hr of 1131 from aground level release:I17DRp = 1E6-YRaDFA~iaQeiXe QeRa = 3700 m3/yrDFAija = 4.39E-3 mrem/pCiQei = 0.028 ýtCi/sec [1 00tpCi/hr /3600 sec/hr = 0.02778]X/Qe = 4.59 E-5 sec/mi3DRp = IE6Z3700* 4.39E -3 | |||
* 0.028* 4.59E -5DRp = 20.9mrem / yr2.4 NOBLE GAS EFFLUENT DOSE CALCULATIONS -10 CFR 50Doses resulting from the release of noble gases must be calculated to show compliancewith Appendix I of 1 OCFR50. Calculations will be performed at least monthly for allgaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2 to verify thatthe dose to air is kept below the limits specified in CONTROL 3.11.2.2 and the dose toMEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL3.11.2.3.122014 CY-OC-170-301Revision 6Page 89 of 1402.4.1 UNRESTRICTED AREA DOSE -NOBLE GASESCONTROL 3.11.2.2 requires a periodic assessment of releases of noble gases toevaluate compliance with the quarterly air dose limits shown in Table 2.4.1-1.TABLE 2.4.1-1 ANNUAL AIR DOSE LIMITSDuring any calendar quarter During any calendar year_ 5 mrad gamma-air < 10 mrad gamma-air_ 10 mrad beta-air 20 mrad beta-airThe method used to calculate the air dose at the critical location due to noble gas isdescribed by the following equations. The limits are provided in CONTROL 3.11.2.2 forair dose Off Site due to gamma and beta radiations from effluent noble gas.2.4.1.1 AIR DOSE METHODFor Gamma Radiation:Dose Y = y AyVi -vQvi + A ySiQsii=1 QFor Beta RadiationDosep1 = I JAP~i~-eQeie =1 QWhere:Dose y =the gamma dose during any specified time period (mrad).Dose f3 =the beta dose during any specified time period (mrad).AyVj = the air dose factor due to ground level gamma emissions for each identified noblegas radionuclide, i; (mrad/yr per [tCi/m3). Table A-2AySi = the factor for air dose at ground level due to irradiation for an airborne plumeresulting from a Stack release (mrad per pCi), Table A-3.Ap3 = the air dose factor due to beta emissions for each identified noble gas radionuclide, i(mrad/yr per jiCi/m3). Table A-3X X =the annual average relative concentration for areas at or beyond the site boundary for--e --1Q Qreleases from either the Stack or ground vent at the critical location (sec/m3), Table2.4.1.1-1122014 CY-OC-170-301Revision 6Page 90 of 140Qvi = amount of radionuclide i released from vents (ljCi).Qsi = amount of radionuclide i released from the Stack (ltCi).Qei = amount of radionuclide i released from release point e(pLCi).Noble gases may be released from the ground level vents and stack. The quantity ofnoble gas radionuclides released will be determined from the continuous noble gasmonitors and periodic isotopic analyses. The maximum Off Site gamma radiation doserate to air from noble gases discharged from either the stack or from building ventsoccurs at 805 meters SE of the OCGS for the stack and 338 meters ENE of the OCGSfor building vents. Values of AySi depend upon the meteorological conditions and thelocation of exposure and are calculated using the NRC RABFIN code or similar one inaccordance with Reg. Guide 1.109, Appendix B, Section 1. AyVi and ABi are derivedfrom Reg. Guide 1.109, Table B-1 for a semi-infinite cloud, independent of meteorologyor location. Values of AySi, AyVi and ABi used to calculate the noble gas radiation doseto air at 805 meters SE of the OCGS for the stack and 338 meters ENE of the OCGS forbuilding vents are in Table A-3. Reference atmospheric dispersion from the OCGSto 805 meters SE for the stack and 338 meters ENE for building vents is given in Table2.4.1.1-1.TABLE 2.4.1.1-1 RECEPTOR LOCATIONS AND DISPERSION FOR AIR DOSEDischarge Point Receptor Location Atm. DispersionSector Distance (W) (sec/m3)Ground Level ENE 338 4.59 E-5or VentStack SE 805 1.29 E-8Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the requirements of Reg. Guide 1.109 may be used.2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATIONCalculate the gamma air dose from a release of 1 Ci per hour of Xe133 for 10 hoursfrom a ground level release and 10OCi per hour for 10 hours from an elevated release:Dose'y = AyVi-vQvi + AySiQsii1 QAyVi = 1.12E-5 mrad -m3 /Ci -secX/Q = 4.59 E-5 sec/mi3Qvi = 1E7 RCi [lCi/hr*10hrs*lE6 RCi/Ci]A7Si = 1.03E-1 2 mrad / jiCiQsi = 1E9 piCi [10OCi/hr*10hrs*lE6 tiCi/Ci]122014 CY-OC-170-301Revision 6Page 91 of 140nDose' = -1.12E-5*4.59E-5*1E7+1 .03E-12*IE9i=1Dose' =Z15.14E- 3 +1.03E- 3i=1Dosey = 6.17E -3mradNote how the ground level portion has a higher dose contribution per unit activity thanthe elevated portion.2.4.1.3 INDIVIDUAL PLUME DOSE METHODThe method for dose to an individual from noble gases is essentially identical with theair dose method except that different dose factors apply. Also, since dose to the skincombines the contribution from gamma and beta emissions, the gamma dose must beadded to the beta dose to obtain a total skin dose.For Total Body:Dose(t) = I PyVivQvi+ PY.SiQsi11 QFor SkinDose(s)= e Spi.-eQei + Dose(t)e 11 QWhere:Dose(t) =the total body dose during any specified time period (mrem).Dose(s) = the skin dose during any specified time period (mrem).PyVi = the plume dose factor due to ground level gamma emissions for each identifiednoble gas radionuclide, i; (mrad/yr per 4Ci/m3). Table A-5PYS, = the factor for plume dose at ground level due to irradiation for an airborne plumeresulting from a Stack release (mrad per jiCi), Table A-5.Spi = the skin dose factor due to beta emissions for each identified noble gasradionuclide, i (mrad/yr per p.Ci/m3) from Table A-5.122014 CY-OC-170-301Revision 6Page 92 of 140X X = the annual average relative concentration for areas at or beyond the site boundary forQ Qreleases from either the Stack or ground vent at the critical location (sec/m3) fromTable 2.5.1.Qvi = amount of radionuclide i released from vents (gCi).Qsi = amount of radionuclide i released from the Stack (ý Ci).Qei = amount of radionuclide i released from release point e (GtCi).122014 CY-OC-1 70-301Revision 6Page 93 of 1402.5 RADIOIODINE, PARTICULATE AND OTHER RADIONUCLIDES DOSECALCULATIONS -10 CFR 50Doses resulting from the release of radioiodines and particulates must be calculated toshow compliance with Appendix I of 1OCFR50. Calculations will be performed at leastmonthly for all gaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2and SURVEILLANCE REQUIREMENT 4.11.2.3 to verify that the dose to air is keptbelow the limits specified in CONTROL 3.11.2.2 and the dose to MEMBERS OF THEPUBLIC is maintained below the limits specified in CONTROL 3.11.2.3.The maximum dose to an individual from radioiodines, tritium, and radioactiveparticulates with half-lives of greater than eight days in gaseous effluents released tounrestricted areas is determined as described in Reg. Guide 1.109. Environmentalpathways that radioiodine, tritium, and particulates in airborne effluent follow to themaximally exposed MEMBER OF THE PUBLIC as determined by the annual land usesurvey and reference meteorology will be evaluated. The seasonality of exposurepathways may be considered. For instance, if the most exposed receptor has a garden,fresh and stored vegetables are assumed to be harvested and eaten during April throughOctober. Fresh vegetables need not be considered as an exposure pathway duringNovember through March. To assess compliance with CONTROL 3.11.2.3, the dosedue to radioactive iodine, tritium, and particulates in airborne effluent is calculated to aperson residing 972 meters ESE of the OCGS for ground-level or vent and 937 metersSE of the OCGS for stack. Reference atmospheric dispersion and deposition factors aregiven in Table 2.5-1.TABLE 2.5-1 DISPERSION FOR 10CFR50 DOSESDischarge Point Dispersion DepositionX/Q (sec/m3) D/Q(1/m2)Ground Levelor Vent 5.13 E-6 1.68 E-8Stack 1.25 E-8 2.39 E-9The environmental pathways of exposure to be evaluated are: inhalation, irradiation fromground deposition, and ingestion of milk (cow and goat are treated separately), meat,and vegetables. Eight organs are considered: Bone, Liver, Total Body, Thyroid, Kidney,Lung, GI-LLI (Gastro-Intestinal tract / Lower Large Intestine), and Skin. Four differentage groups are considered: Infants, Children, Teens, and Adults. Doses are calculated toa 'receptor' -a person who inhales the airborne activity and resides in a location withground deposition, and eats and drinks the foodstuffs produced. The maximally exposedindividual is conservatively assumed to reside at the location of the highest sum of theinhalation and ground plane doses, while eating and drinking foodstuffs transported fromthe locations that are highest for those pathways. Receptor locations are provided inTable A-4.Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the requirements of Reg Guide 1.109 may be used.122014 CY-OC-170-301Revision 6Page 94 of 1402.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHERRADIONUCLIDES.Dose from the inhalation pathway is generally in the form:Dja = RaT L-QiDFAi/aExp(-)uTr)iQWhere:Dja = the dose to the organ j (of eight) of age group a (of four)Ra = the respiration rate for age group a from Table B-1T = the duration of the release in fraction of a yearX = The atmospheric dispersion to the point of interest (the 'receptor') in sec/m3 fromTable 2.5-1Qi = The release rate of radionuclide i (pCi/sec)DFAija = The inhalation dose conversion factor (mrem per pCi) for radionuclide i to organ j ofage group a from Reg. Guide 1.109 Appendix E.Xi = decay constant of isotope i: 0.693/ Half life in yearsTr = plume transit time from release to receptor in yearsMi and Tr may be in any time units as long as they are the sameNote that a 'depleted X/Q' (dX/Q) is applicable to particulates only, which accounts forthe natural settling and lack of surface reflection of particulates to estimate thedownwind concentration accounting for these removal processes. Depleted X/Q will beslightly smaller than the X/Q. This is not used in the ODCM for simplicity. Using the X/Qis therefore slightly conservative compared to the dX/Q.122014 CY-OC-1 70-301Revision 6Page 95 of 1402.5.2 EXAMPLE CALCULATION -INHALATION OF RADIOIODINES, TRITIUM,PARTICULATES, AND OTHER RADIONUCLIDESCalculate the dose to child lung from inhalation from a ground level release of 100 pLCiof Co-60 in 10 hours. Plume transit decay time is ignored (exp(-AiTr)=1).Dja = RaT -- QiDFAijaDja = the dose to the organ j (of eight) of age group a (of four)Ra = 3700 m3/yrT = 0.00114 yrs [10 hrs / 8760 hrs / yr]X 5.13 E-6 sec/m3sQi = 2.78E3 pCi/sec [100 pCi | |||
* 1 E6 pCi/jiCi / (10 hrs*3600 sec hr)]DFAija =1.91 E-3 mrem / pCiDja = 3700* 0.00114* 5.13E- 6 *2.78E3 | |||
* 1.91E -3Dja = 1. 1 5E -4mrem2.5.3 INGESTION OF RADIOIODINES, PARTICULATES AND OTHER RADIONUCLIDESDose from the ingestion pathways is more complex and is broken out here into multiplesteps:2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE ANDVEGETATION -OTHER THAN TRITIUMThe concentration of a radionuclide in a foodstuff (other than tritium -see section2.5.3.3 for tritium) is dependent on the atmospheric deposition, the biological uptakeinto the food, various decay times (plume travel, harvest to table, etc.) and is generallyof the form:Where:Civ = the concentration (pCi/kg) of radionuclide i in vegetationQi = the release rate of isotope i in pCi/hrD =The atmospheric deposition to the point of interest (the 'receptor') in 1/M2 fromQTable 2.5-1.122014 CY-OC-170-301Revision 6Page 96 of 140Civ D Qi{r(l -EXP(-MEiTe)) + Biv(1 -EXP(-AiTb)) EXP(-ATh)EXP(--IiTr)Q Yv),Ei PMir = the retention coefficient for deposition onto vegetation surfaces (1.0 for iodines, 0.2for particulates)ki = the decay constant of radionuclide i; 0.693/half life in hoursXEi =the effective removal constant which is the sum of Xi + ?,w where Xw is theweathering constant, 0.0021/hrTe = duration of crop exposure during the growing season in hours. This is not the entireduration of the growing season, and is different for leafy vegetable andfruit/grain/vegetables. Provided in Table E-15 of Reg. Guide 1.109 or Table B-1.Yv = agricultural yield Kg of vegetation per m2, typically 0.7 kg/M2Biv = soil uptake concentration factor for transfer of the radionuclide i from the soil tothe vegetation through normal root uptake processes in pCi/kg in vegetation perpCi/Kg in soil. Values are provided in Reg. Guide 1.109 Table E-1.Tb = the length of time the soil is exposed to contaminated inputs -nominally 30years (2.63E5 hr)P = effective soil density in kg/mi2 normally 240 kg/M2Th = holdup time, the time the foodstuff is in transit between harvest andconsumption in hoursTr = plume transit time from release to receptor in hours2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE INANIMAL FORAGE AND VEGETATION -OTHER THAN TRITIUM.Calculate the forage and vegetation concentration from a ground level release of100 ptCi of Co-60 in 10 hours (plume transit time is ignored Tr=0, EXP(-XiTr)=I):Civ D Qi{ r(1 -EXP(-MiTe)) + Biv(1 -EXP(-).iTb)) EXP(_XiTh)EXP(_XiTr)QYvmEi P MD/Q = 1.67E-8 m2Qi = 1 E7 pCi/hr [100.pLCi | |||
* 1E6 pCi/iCi / 10 hr]r = 0.2Xi = 1.5E-5/hr [0.693 / (5.27yr | |||
* 8760 hr/yr)]XEi = 2.12E-3 /hr [1.5E-5 + 0.0021]Te = 720 hr [grass-cow-milk-man pathway value]122014 CY-OC-170-301Revision 6Page 97 of 140YvBivTbPTh= 0.7 kg/mr2= 9.4E-3= 2.63E5 hr= 240 kg/mr2= 24.1 hoursCiv = 1.67E -8 | |||
* 1E70.2* (1- EXP(-2.12E -3*720)) +{ EXP(-1.5E.-75**.O)9.4E -3 * (1 -EXP(-1.5E -5 | |||
* 2.63E5))1 240 | |||
* 1.5E -5Civ =1.67E-8*1E7{105Civ =1.67E-1{.0.2 * (1 -EXP (- 1.53))1.48E -39.4E -3 * (1 -EXP (-3+}EXP (-0 ).95))3.6E -3*1"Civ = 18.0 pCi / Kg2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATIONSince tritium is assumed to be released as tritiated water (HTO), the concentration oftritium in a foodstuff is dependent on atmospheric dispersion like a gas, rather thanparticulate deposition as for other radionuclides for foodstuff uptake. Further, theconcentration of tritium in food is assumed to be based on equilibrium between theconcentration of the tritium in the atmospheric water and the concentration of tritium inthe water in the food. Concentration of tritium in vegetation can be calculated generally inthe form (a plume transit decay term: EXP(-XiTr) is ignored since plume travel times arevery short compared to the half life):Ctv = 1000Qt x *0.75 | |||
* 0.5Q HWhere:Ctv= the concentration (pCi/kg) of tritium in vegetation1000 =g per kgQt = the release rate of the tritium in pCi/ sec122014 CY-OC-1 70-301Revision 6Page 98 of 140X/Q = the atmospheric dispersion at the vegetation point, sec/mr3 from Table 2.5-10.75 = the fraction of vegetation that is water0.5 = the effective ratio between the atmospheric water concentration and thevegetation concentrationH = the absolute humidity g/m3.Absolute humidity is seasonally dependent, varyingfrom as little as 1 in the winter to as much as 20 in the summer. Monthly averagevalues derived from historical data are provided in Table B-2.2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGEAND VEGETATION.Calculate the forage and vegetation concentration from a ground level release of100 1iCi of H-3 in 10 hours. Plume transit decay time is ignored (exp(-XiTr)=1):Ctv = I 000Qt X *0.75* 0.5Q HQt = 2778 pCi/sec [1 0OuCi | |||
* 1E6 pCi/uCi / (1 Ohrs*3600sec/hr)]X/Q = 5.13E-6 sec/m3H = 5 g/m3 (assumed for this example)Ctv = 2778 | |||
* 1000 *5.13E -6 | |||
* 0.75* 0.55Ctv = 1.07 pCi / kg2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEATMeat and milk animals are assumed to eat both pasture grass and stored feed. During afraction of the year, they may be assumed to be exclusively on stored feed, outside of thegrowing season. If using annual average release, the fraction of stored and fresh feedmust be accounted for with fractions, otherwise (as in this ODCM), the fresh pasturepathway is turned on or off depending on the growing season.The concentration of a radionuclide in the animal feed is calculated as follows:Civ = FpCis + (1 -Fp)Cis(l -Fs) + CipFs(l -Fp)Where:Fp = the growing season pasture factor: 1 if not growing season, 0 if in growing season122014 CY-OC-170-301Revision 6Page 99 of 140Fs = the fraction of the daily feed from fresh pasture from Table B-1 or Exhibit E-15 fromReg. Guide 1.109.Cip = the concentration in the fresh pasture feed (Civ from section 2.5.3.2 with Th = 0 forimmediate consumption)Cis = the concentration in stored feed (Civ from section 2.5.3.2 with Th = 90 days)The concentration in the milk is then based on this feed concentration:Cim = FmCivQfEXP (-)LiTf)Where:Cim = the concentration in milk pCi/IFm = the transfer coefficient of intake to concentration in the milk (dIl) from Reg. Guide1.109 Table E-1.Qf = feed intake rate Kg/d from Reg. Guide 1.109 Table E-3.2X = radionuclide i decay constant in 1/daysTf = transport time from milk production to consumption (2 days for milk)The Goat milk pathway may be similarly evaluated:Cim = FgCivQIfEP (-2iTf)Where:Fg = the transfer coefficient of intake to concentration in the milk (d/I) for goats fromReg. Guide 1.109 Table E-2.And for meat:CO = FfCivQJEXP (-XiTs)Where:Ff = the transfer coefficient of intake to concentration in the meat d/kg from Reg.Guide 1.109 Table E-1.Ts = the transport time from slaughter to consumption (20 days)122014 CY-OC-170-301Revision 6Page 100 of 1402.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILKAND MEATCalculate the concentration in cow milk from a ground level release of 100 liCi ofCo-60 in 10 hours. Plume transit decay time is ignored (exp(-XiTr)=l):Civ = FpCis + (l- Fp)Cis(1- Fs) + CipFs(l- Fp)Assume animals are on pasture and receive half of their food from stored feed.Cip = 18.0 pCi/kg as previously calculated in section 2.5.3.2Fp = 0Fs = 0.5Cis is calculated by applying a 90 day decay term to the Cip value previously calculated,since the previous decay correction was for 0 time as shown in 2.5.3.2.Cis = 18.0 * (exp(-0.693 | |||
* 90 /(5.27 | |||
* 365)))Cis = 17.4pCi / kgCiv is then:Civ =0*17.4+ (1-0)17.4 (1-0.5) +18.0 | |||
* 0.5 * (1-0)Civ = 17.7pCi/kgThe concentration in milk is given by:Cim = FmCivQEXP (-AiTf)Fm =1.OE-3 d/IQf = 50 Kg/dXi = 3.6E-4/d [0.693 / (5.27 yrs*365 days/yr)]Cim = .OE -3 | |||
* 17.7 | |||
* 50 | |||
* EXP(-3.6E -4 | |||
* 2)Cim = 0.88pCi/lThe concentration in meat given by:Cif = FfCivQJEXP (-tiTs )Ff =1.3E-2 d/kg122014 CY-OC-1 70-301Revision 6Page 101 of 140Qf = 50 Kg/dXi = 3.6E-4/dCf = 1.3E -2 | |||
* 17.7 | |||
* 50* EXP(-3.6E- 4 | |||
* 20)Cif = 11.5pCi / kg2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLESThe environmental pathway ingestion dose is the sum of the milk, meat, and vegetationingestion pathways. There are two separate pathways for vegetation: fresh leafyvegetables and a combination of fruits, non-leafy vegetables, and grains. These differonly in the decay and buildup processes applied to account for the environmentalexposure, and transportation delay decay represented by Te and Th as shown in section2.5.3.1. For long half-life isotopes (e.g. Co-60) the decay differences have little impact onthe dose.Dose from the environmental ingestion pathways is generally of the form:Dja = T DFiija[UavFgCiv+ UamCim + UafCif + UalFlCil]Where:Dja = the dose to organ j of age group a -mremT = fraction of year of release durationDFlija = the ingestion dose factor for isotope i to organ j for age group a -mrem/pCi from Reg.Guide 1.109 Appendix EUav = Ingestion rate (usage factor) for non-leafy vegetables, grains, and fruits for age groupa from Reg. Guide 1.109 Table E-5 or Table B-I.Fg = the fraction of vegetables, grains, and fruits from the location of interest : 0.76 in Reg.Guide 1.109.Civ = the concentration of isotope i in the vegetables, fruits, and grains calculated fromsection 2.5.3.2.Uam = Ingestion rate (usage factor) for milk for age group a: from Table B-1 or Reg. Guide1.109 Table E-5.Cim = the concentration of isotope i in milk calculated from section 2.5.3.5.Uaf = the ingestion rate for meat for age group a: from Table B-1 or Reg. Guide 1.109 TableE-5.122014 CY-OC-170-301Revision 6Page 102 of 140Cif = the concentration of isotope i in meat calculated from section 2.5.3.2.Ual = the ingestion rate for leafy vegetables for age group a: from Table B-1 or Reg. Guide1.109 Table E-5.FI = the fraction of annual leafy vegetable ingestion from the location of interest : 1.0 inReg. Guide 1.109.Cil = concentration of isotope i in the leafy vegetables for direct human consumption: Civcalculated from section 2.5.3.2 with Th=0.2.5.3.8 EXAMPLE CALCULATION -DOSE FROM CONSUMPTION OF MILK, MEAT, ANDVEGETABLESCalculate the ingestion dose to child whole body from a ground level release of 100gCi of Co-60 in 10 hours. Plume transit decay time is ignored (exp(-kiTr)=1):Dja = TZ DFIija[UavFgCiv + UamCim + UafCif + UalFlCil]Where:T = 0.00114 yr [10hrs / 8760 hrs/yr)DFlija = 1.56E-5 mrem/pCiUav = 520Fg = 0.76Civ = 17.6 [18.0*EXP(-X*60) using 60 day delay for ingestion]Uam = 330Cim = 0.88Uaf = 41Cif = 11.5Ual = 26FI =1Cil = 17.7Dja=.0011411.56E- 5[520*0.76* 17.6+330*0.88+41* 11.5 +26*1*17.7]Dja= .0011411.56E -5[6956+ 290+472+ 460]Dja = 1.45E -4mrem: child: wholebody2.5.4 GROUND PLANE DEPOSITION IRRADIATIONDose from ground plane deposition is estimated by determining the surface activityresulting from the release.122014 CY-OC-170-301Revision 6Page 103 of 1402.5.4.1 GROUND PLANE CONCENTRATIONThe ground surface activity is estimated as:Cig = D -(1- EXP(-2iTb))Q xiWhere:Cig = ground plane concentration of radionuclide i in pCi/mr2D = local atmospheric release deposition factor in 1/mi2 from Table 2.5-1Qi = release rate in pCi/secXi = radiological decay constant in 1/secTb = long term buildup time 30 years (9.46E8 sec)Note: Qi, Mi and Tb can utilize any time units as long as they are all the same2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATIONCalculate the ground plane concentration from a 100 jtCi release of Co-60 over 10hours from a ground level release point.Cig = D (1- EXP(-),iTb))Q xiD 1.67E-8 /mf2QQi = 2778 pCi/sec [100pCi/10hrs/3600sec/hr]ki = 4.17E-9/sec [0.693/(5.27yr*8760hr/yr*3600sec/hr)]Tb = 9.46E8 secCig=167E-8 2778Cig = 1.67E 8 (l EXP(-4.17E -9* 9.46E8))4.17E -99Cig = 1.09E4pCi / m2122014 CY-OC-170-301Revision 6Page 104 of 1402.5.4.3 GROUND PLANE DOSEAnnual dose from the ground plane deposition is of the form:Djg= 8760 | |||
* T | |||
* Sf CigDFGiWhere:Djg = the annual dose (mrem) from ground plane pathway (g) to the total body or skin (j)8760 = hours in a yearT = fraction of year release is in progressSf = shielding factor accounting for shielding from dwelling from Table B-1DFGij = Ground plane dose factor for skin or total body (j) for radionuclide i fromTable E-6 of Reg. Guide 1.109 in mrem/hr / pCi/m2.2.5.4.4 EXAMPLE GROUND PLANE DOSECalculate the ground plane Total Body dose from a 100 p.Ci release of Co-60 over 10hours from a ground level release point.Djg = 8760 | |||
* T | |||
* SfCigDFGijT = 0.00114 [10/8760]Sf = 0.7DFGij = 1.7E-8Cig = 1.09E4Djg = 8760* 0.00114 0.711.09E4 *1.7E- 8iDjg = 1.30E -3mremTotalB ody2.6 PROJECTED DOSES -GASEOUSThe projected doses in a 31 day period are equal to the calculated doses from thecurrent 31 day period.3.0 TOTAL DOSE TO MEMBERS OF THE PUBLIC -40 CFR 190The Radiological Environmental Monitoring Report (REMP) submitted by May 1st of eachyear shall include an assessment of the radiation dose to the likely most exposedMEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle122014 CY-OC-170-301Revision 6Page 105 of 140sources (including dose contributions from effluents and direct radiation from on-sitesources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of OysterCreek, the sources of exposure need only consider the Oyster Creek Generating Station.No other fuel cycle facilities would contribute significantly to the MEMBER OF THEPUBLIC dose for the Oyster Creek vicinity, however, both plant operation and ISFSIsources must be included in the dose assessment.To assess compliance with CONTROL 3.11.4, calculated organ and total body doses fromeffluents from liquid pathways and atmospheric releases as well as any dose from directradiation will be summed.As appropriate for demonstrating/evaluating compliance with the limits of CONTROL3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used forproviding data on actual measured levels of radiation and / or radioactive material andresultant dose to the MEMBER OF THE PUBLIC in the actual pathways of exposure.3.1 EFFLUENT DOSE CALCULATIONSFor purposes of implementing the surveillance requirements of CONTROL 3/4.11.4 andthe reporting requirements of Technical Specification 6.9.1 .d (ARERR), dose calculationsfor the Oyster Creek Generating Station may be performed using the calculation methodscontained within the ODCM; the conservative controlling pathways and locations from theODCM or the actual pathways and locations as identified by the land use census(CONTROL 3/4.12.1) may be used. Average annual meteorological dispersionparameters provided herein or meteorological conditions concurrent with the releaseperiod under evaluation may be used.3.2 DIRECT EXPOSURE DOSE DETERMINATIONAny potentially significant direct exposure contribution to off-site individual doses may beevaluated based on the results of environmental measurements (e.g., dosimeter) and/orby the use of radiation transport and shielding calculation methodologies.4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMThe operational phase of the Radiological Environmental Monitoring Program (REMP) isconducted in accordance with the requirements of CONTROL 3.12.1. The objectives ofthe program are:-To determine whether any significant increases occur in the concentration ofradionuclides in the critical pathways of exposure in the vicinity of Oyster Creek-To determine if the operation of the Oyster Creek Generating Station has resulted inany increase in the inventory of long lived radionuclides in the environment;-To detect any changes in the ambient gamma radiation levels; and-To verify that OCGS operations have no detrimental effects on the health and safety ofthe public or on the environment.The REMP sample locations are presented in Appendix E.122014 CY-OC-170-301Revision 6Page 106 of 140APPENDIX A -DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS122014 CY-OC-1 70-301Revision 6Page 107 of 140Table A-1 Dose Conversion Factors for Deriving Radioactive Noble GasRadionuclide-to-Dose Equivalent Rate Factors* IRadionuclide Factor DFSi for Factor DFVi forStack Release* Ground-level orVent Release**mrem-sec mrem-m3pCi-year pCi-yearKr83m 9.21E-10 7.56E-02Kr85m 1.46E-04 1.17E+03Kr85 2.58E-06 1.61 E+01Kr87 8.65E-04 5.92E+03Kr88 2.16E-03 1.47E+04Kr89 2.06E-03 1.66E+04Kr90 1.56E+04Xe131m 3.13E-05 9.15E+01Xe133m 2.50E-05 2.51E+02Xe133 2.15E-05 2.94E+02Xe135m 4.81E-04 3.12E+03Xe135 2.51E-04 1.81E+03Xe137 1.79E-04 1.42E+03Xe138 1.37E-03 8.83E+03Xe139 2.14E-04 5.02E+03Ar4l 1.67E-03 8.84E+03* Based on meteorology applicable at 229 meters SW of stack.** For exposure to a semi-infinite cloud of noble gas.122014 CY-OC-1 70-301Revision 6Page 108 of 140Table A-2 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors*Radionuclide PSi** PVi*** A7Vi*** SBi***mrem mrem-m3 mrad-m3 mrem-m3ýCi ýiCi-sec (Ki) ý.Ci-sec (Mi) jiCi-sec (Li)Kr83m 2.92E-17 2.40E-09 6.13E-07 -Kr85m 4.64E-12 3.71E-05 3.90E-05 4.63E-05Kr85 8.18E-14 5.11E-07 5.46E-07 4.25E-05Kr87 2.74E-11 1.88E-04 1.96E-04 3.09E-04Kr88 6.84E-1 1 4.67E-04 4.83E-04 7.52E-05Kr89 6.53E-1 1 5.27E-04 5.49E-04 3.21E-04Kr90 4.95E-04 5.17E-04 2.31E-04Xe131m 9.92E-13 2.90E-06 4.95E-06 1.51E-05Xe133m 7.94E-13 7.97E-06 1.04E-05 3.16E-05Xe133 6.83E-13 9.33E-06 1.12E-05 9.71E-06Xe135m 1.53E-11 9.90E-05 1.07E-04 2.26E-05Xe135 7.97E-12 5.75E-05 6.1OE-05 5.90E-05Xe137 5.69E-12 4.51E-05 4.79E-05 3.87E-04Xe138 4.34E-11 2.80E-04 2.92E-04 1.31 E-04Xe139 6.79E-12 --Ar4l 5.30E-11 2.81E-04 2.95E-04 8.54E-05* All of these dose factors apply out-of-doors.** Based on meteorology at 229 meters SW of effluent stack.* Derived from Reg Guide 1.109, Revision 1, Table B-1.122014 CY-OC-170-301Revision 6Page 109 of 140I Table A-3 Air Dose Conversion Factors for Effluent Noble GasRadionuclide AySi** AyVi*** Ap3i***mrad mrad-m3 mrad-m3pCi p.Ci-sec(M1) pCi-sec (Ni)Kr83m 1.33E-16 6.13E-07 9.14E-06Kr85m 6.89E-12 3.90E-05 6.25E-05Kr85 1.24E-13 5.46E-07 6.19E-05Kr87 4.13E-11 1.96E-04 3.27E-04Kr88 1.03E-10 4.83E-04 9.30E-05Kr89 9.82E-1 1 5.49E-04 3.37E-04Kr90 5.17E-04 2.49E-04Xel31 m 1.50E-12 4.95E-06 3.52E-05Xe133m 1.23E-12 1.04E-05 4.70E-05Xe133 1.03E-12 1.12E-05 3.33E-05Xel35m 2.31E-11 1.07E-04 2.35E-05Xe135 1.20E-11 6.1OE-05 7.81 E-05Xe137 8.59E-12 4.79E-05 4.03E-04Xel 38 6.51E-11 2.92E-04 1.51E-04Xe139 1.02E-11 -Ar4l 7.94E-11 2.95E-04 1.04E-04** Based on meteorology at 229 meters SW of effluent stack.*** Derived from Reg Guide 1.109, Revision 1, Table B-I.122014 CY-OC-1 70-301Revision 6Page 110 of 140Table A-4 Locations Associated with MaximumExposure of a Member of the Public*Effluent LocationDistance Direction(meters) (to)Liquid U.S. Route 9 Bridge at Discharge CanalAirborne Iodine and Particulates 937 SETritium 937 SENoble Gases 937 SEIrradiation by OCGS Site Boundary AllNoble Gas g Air Dose 937 SENoble Gas B Air Dose 937 SENote: the nearby resident experiencing the maximum exposure to airborne effluent fromthe Station is located 937 meters SE of the OCGS. The nearby resident (part-time)experiencing the maximum exposure to gamma radiation directly from the Station islocated 618 meters WSW of the OCGS. The most exposed member of the public isassumed to be exposed by irradiation from the OCGS, by inhaling airborne effluent, byirradiation by the airborne effluent, by irradiation by the airborne plume of the noble gas, byradionuclides deposited onto the ground, by irradiation by shoreline deposits, and byeating fish and shellfish caught in the discharge canal.*The age group of the most exposed member of the public is based on Reg. Guide 1.109,Revision 1.122014 CY-OC-170-301Revision 6Page 111 of 140Table A-5 Critical Receptor Noble Gas Dose Conversion Factors* IRadionuclide PySi** PyVi*** AyVi*** AySi** SBi***mrem mrem-m3 mrad-m3 mrad mrem-m3ýLCi gCi-sec(Ki) ptCi-sec(Mi) ptCi ýtCi-sec(Lj)Kr83m 4.61E-17 2.40E-09 6.13E-07 1.77E-14Kr85m 2.13E-12 3.71E-05 3.90E-05 3.16E-12 4.63E-05Kr85 3.38E-14 5.11E-07 5.46E-07 5.12E-14 4.25E-05Kr87 1.08E-11 1.88E-04 1.96E-04 1.63E-11 3.09E-04Kr88 2.76E-11 4.67E-04 4.83E-04 4.14E-11 7.52E-05Kr89 2.02E-11 5.27E-04 5.49E-04 3.03E-11 3.21E-04Kr9O 4.95E-04 5.17E-04 2.31E-04Xel31 m 5.05E-13 2.90E-06 4.95E-06 8.03E-13 1.51 E-05Xe133m 3.95E-13 7.97E-06 1.04E-05 6.50E-13 3.16E-05Xe133 3.88E-13 9.33E-06 1.12E-05 6.13E-13 9.71E-06Xe135m 5.82E-12 9.90E-05 1.07E-04 8.80E-12 2.26E-05Xel35 3.51E-12 5.75E-05 6.1OE-05 5.25E-12 5.90E-05Xe137 1.74E-12 4.51E-05 4.79E-05 2.64E-12 3.87E-04Xel38 1.72E-11 2.80E-04 2.92E-04 2.58E-11 1.31E-04Xel39 9.30E-13 -1.40E-12 -Ar4l 2.07E-11 2.81E-04 2.95E-04 3.1OE-11 8.54E-05* All of these dose factors apply out-of-doors.** Based on meteorology at 937 meters SE of effluent stack.Derived from Reg Guide 1.109, Revision 1, Table B-1122014 CY-OC-1 70-301Revision 6Page 112 of 140APPENDIX B -MODELING PARAMETERS122014 CY-OC-1 70-301Revision 6Page 113 of 140Table B-I- OCGS Usage Factors For Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorFraction Of Produce From Local Garden 7.6E-1Soil Density In Plow Layer (Kg/m2) 2.4E+2Fraction Of Deposited Activity Retained On Vegetation 2.5E-1Shielding Factor For Residential Structures 7.0E-1Period Of Buildup Of Activity In Soil (hr) 1.31 E+5Period of Pasture Grass Exposure to Activity (hr) 7.2E+2Period Of Crop Exposure to Activity (hr) 1.44E+3Delay Time For Ingestion Of Stored Feed By Animals (hr) 2.16E+3Delay Time For Ingestion Of Leafy Vegetables By Man (hr) 2.4E+1Delay Time For Ingestion Of Other Vegetables By Man (hr) 1.44E+3Transport Time Milk-Man (hr) 4.8E+1Time Between Slaughter and Consumption of Meat Animal (hr) 4.8E+2Grass Yield Wet Weight (Kg/mi2) 7.0E-1Other Vegetation Yield Wet-Weight (Kg/m2) 2.0Weathering Rate Constant For Activity on Veg. (hr-1) 2.1 E-3Milk Cow Feed Consumption Rate (Kg/day) 5.0E+1Goat Feed Consumption Rate (Kg/day) 6.0Beef Cattle Feed Consumption Rate (Kg/day) 5.0E+1Milk Cow Water Consumption Rate (L/day) 6.0E+1Goat Water Consumption Rate (L/day) 8.0Beef Cattle Water Consumption Rate (L/day) 5.0E+1Environmental Transit Time For Water Ingestion (hr) 1.2E+1Environmental Transit Time For Fish Ingestion (hr) 2.4E+1Environmental Transit Time For Shore Exposure (hr) 0Environmental Transit Time For Invertebrate Ingestion (hr) 2.4E+1122014 CY-OC-170-301Revision 6Page 114 of 140Table B-1 (Continued)OCGS Usage Factors for Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorWater Ingestion (L/yr)a. Adult 7.3E+2b. Teen 5.1E+2c. Child 5.1E+2d. Infant 3.3E+2Shore Exposure (hr/yr)a. Adult 1.2E+1b. Teen 6.7E+1c. Child 1.4E+1d. Infant 0Salt Water Sport Fish Ingestion (Kg/yr)a. Adult 2.1EE+1b. Teen 1.6E+1c. Child 6.9d. Infant 0Salt Water Commercial Fish Ingestion (Kg/yr)a. Adult 2.1E+1b. Teen 1.6E+1c. Child 6.9d. Infant 0Salt Water Invertebrate Ingestion (Kg/yr)a. Adult 5.0b. Teen 3.8c. Child 1.7d. Infant 0Irrigated Leafy Vegetable Ingestion (Kg/yr)a. Adult 6.4E+1b. Teen 4.2E+1c. Child 2.6E+1d. Infant 0122014 CY-OC-170-301Revision 6Page 115 of 140Table B-1 (Continued)OCGS Usage Factors for Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorIrrigated Other Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2b. Teen 6.3E+2c. Child 5.2E+2d. Infant 0Irrigated Root Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2b. Teen 6.3E+2c. Child 5.2E+2d. Infant 0Irrigated Cow and Goat Milk Ingestion (L/yr)a. Adult 3.1E+2b. Teen 4.0E+2c. Child 3.3E+2d. Infant 3.3E+2Irrigated Beef Ingestion (Kg/yr)a. Adult 1.1E+2b. Teen 6.5E+1c. Child 4.1E+1d. Infant 0Inhalation (m3/yr)a. Adult 8.0E+3b. Teen 8.0E+3c. Child 3.7E+3d. Infant 1.4E+3Cow and Goat Milk Ingestion (L/yr)a. Adult 3.1E+2b. Teen 4.01E+2c. Child 3.3E+2d. Infant 3.3E+2Meat Ingestion (Kg/yr)a. Adult 1.1E+2b. Teen 6.5E+1c. Child 4.1E+1d. Infant 0122014 CY-OC-1 70-301Revision 6Page 116 of 140Table B-1 (Continued)OCGS Usage Factors for Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorLeafy Vegetable Ingestion (Kg/yr)a. Adult 6.4E+1b. Teen 4.2E+1c. Child 2.6E+1d. Infant 0Fruits, Grains, & Other Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2b. Teen 6.3E+2c. Child 5.2E+2d. Infant 0122014 CY-OC-170-301Revision 6Page 117 of 140Table B-2 Monthly Average Absolute Humidity g/m3(derived from historical climatological data)Average AbsoluteMonth Humidity (q/m3)January 3.3February 3.3March 4.5April 6.1May 9.4June 12.8July 15.2August 15.6September 12.4October 7.9November 5.9December 3.8122014 CY-OC-170-301Revision 6Page 118 of 140APPENDIX C -REFERENCES122014 CY-OC-170-301Revision 6Page 119 of 140Table C-1 -REFERENCES1) Oyster Creek Updated Final Safety Analysis Report2) Oyster Creek Facility Description and Safety Analysis Report3) Oyster Creek Operating License and Technical Specifications4) NUREG 1302 "Off Site Dose Calculation Manual Guidance: Standard Radiological EffluentControls for Boiling Water Reactors" -Generic Letter 89-10, Supplement No. 1 ,April 19915) Reg Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases of radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" Rev.1, June 19746) Reg Guide 1.237) Reg Guide 1.978) Reg Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I", Rev 1,October, 19779) Reg Guide 1.111 "Methods for Estimating Atmospheric Transport and Dispersion ofGaseous Effluents in Routine Releases From Light-Water-Cooled Reactors", Rev. 1, July,197710) Reg Guide 4.8" Environmental Technical Specifications for Nuclear Power Plants"11) NRC Radiological Assessment Branch Technical Position, Rev 1, November 1979(Appendix A to NUREG1302)12) NUREG-001613) NUREG-013314) Licensing Application, Amendment 13, Meteorological Radiological Evaluation for theOyster Creek Nuclear Power Station Site.15) Licensing Application, Amendment 11, Question IV-8.16) Evaluation of the Oyster Creek Nuclear Generating Station to Demonstrate Conformanceto the Design Objectives of 1OCFR50, Appendix I, May, 1976, Tables 3-1017) XOQDOQ Output Files for Oyster Creek Meteorology, Murray and Trettle, Inc.122014 CY-OC-1 70-301Revision 6Page 120 of 14018) Hydrological Information and Liquid Dilution Factors Determination to Conform withAppendix I Requirements: Oyster Creek, correspondence from T. Potter, Pickard, Loweand Garrick, Inc. to Oyster Creek, July, 1976.19) Carpenter, J. J. "Recirculation and Effluent Distribution for Oyster Creek Site", Pritchard-Carpenter Consultants, Baltimore, Maryland, 1964.20) Nuclear Regulatory Commission, Generic Letter 89-01, "Implementation of ProgrammaticControls for Radiological Effluent Technical Specifications in the Administrative ControlsSection and Relocation of the Procedural Details of RETS to the ODCM or PCP", January,1989.21) Ground Water Monitoring System (Final Report), Woodward-Clyde Consultants, March,1984.22) Meteorology and Atomic Energy, Department of Energy, 1981.23) SEEDS Code Documentation through V & V of Version 98.8F (Radiological EngineeringCalculation No. 2820-99-005, Dated 3/23/99)24) Lynch, Giuliano, and Associates, Inc., Drawing Entitled, "Minor Subdivision, Lots 4 and4.01 Block 1001", signed 13 Sep 99.25) Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Positionfor Radiological Effluent and Environmental Measurements".26) NUREG/CR-4007 (September 1984).27) HASL Procedures Manual, HASL-300 (revised annually).28) Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental andRoutine Reactor Releases for the Purposes of Implementing Appendix I," April 197729) Reg. Guide 4.1330) 10CFR20, Appendix B, Table 2, Annual Limits on Intake (ALIs) and Derived AirConcentrations (DACs) of Radionuclides for Occupational Exposure; EffluentConcentrations; Concentrations for Release to Sewerage31) Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleet wideAssessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No.045136(18), September, 2006.32) Letter date April 23, 2013 from Murray and Trettel, Incorporated33) Letter dated January 10, 2013 titled "Meteorology and Dose Factor Update -ODCMRevision 6"122014 CY-OC-170-301Revision 6Page 121 of 140APPENDIX D -SYSTEM DRAWINGS122014 CY-OC-170-301Revision 6Page 122 of 140FIGURE D-1-la: LIQUID RADWASTE TREATMENT CHEM WASTE AND FLOOR DRAINSYSTEM.C>0D0 Fcc/)Cl)LO* V0 (0vcuC )..L-00)t0 Scu CL a.U -.4 cl°m .o_ C-Lo E122014 CY-OC-170-301Revision 6Page 123 of 140FIGURE D-1-lb: LIQUID RADWASTE TREATMENT -HIGH PURITY AND EQUIPMENTDRAIN SYSTEMI.-z0 z',,ICN.COC0~co a.WWL EU)~ C (0- .co M.-,-z"a.. o.,T1* I >"_ A8 --° -lE,o i-I 1 <0122014 CY-OC-1 70-301Revision 6Page 124 of 140FIGURE D-1-lc: GROUNDWATER REMEDIATION SYSTEMComposite Flow MonitorSampler122014 CY-OC-170-301Revision 6Page 125 of 140FIGURE D-1-2: SOLID RADWASTE PROCESSING SYSTEMProcessTemp ModWC-T-I A/ B/CFilterSludgeOption A122014 CY-OC-170-301Revision 6Page 126 of 140FIGURE D-2-1: GASEOUS RADWASTE TREATMENT -AUGMENTED OFF GAS SYSTEM122014 CY-OC-170-301Revision 6Page 127 of 140FIGURE D-2-2: VENTILATION SYSTEMOYSTI ER CREEKTUBVENT PATHSlae STACKICondV-7-31l1V- 1161~~IIiV 7s(1-6)CODN. RSI-I.-CEV-28-2TURBINE BUILDINGIIV.~-23-14V-29-21II U -STANDBY GAS TREATMENT SYSTEM V-28-19V-28-17 NV.RA7 Torus122014 CY-OC-1 70-301Revision 6Page 128 of 140Figure D-2-3 AOG Ventilation SystemHV-S-1O122014 CY-OC-1 70-301Revision 6Page 129 of 140APPENDIX E -RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM -SAMPLE TYPE AND LOCATIONAll sampling locations and specific information about the individual locations are given inTable E-1. Figures E-1, E-2 and E-3 show the locations of sampling stations with respect tothe site. Figure E-4 shows the site layout.122014 CY-OC-1 70-301Revision 6Page 130 of 140TABLE E-1: REMP SAMPLE LOCATIONS(1)1. Direct RadiationDOS -Inner Ring at or near site boundaryCode (miles) (degrees) Description1 0.4 219 SW of site at OCGS Fire Pond, Forked River, NJ51 0.4 358 North of site, on the access road to Forked RiverSite, Forked River, NJ52 0.3 333 NNW of site, on the access road to Forked RiverSite, Forked River, NJ53 0.3 309 NW of site, at sewage lift station on the accessroad to the Forked River Site, Forked River, NJ54 0.3 288 WNW of site, on the access road to Forked RiverSite, Forked River, NJ55 0.3 263 West of site, on Southern Area Stores securityfence, west of OCGS Switchyard, Forked River,NJ56 0.3 249 WSW of site, on utility pole east of Southern AreaStores, west of the OCGS Switchyard, ForkedRiver, NJ57 0.2 206 SSW of site, on Southern Area Stores accessroad, Forked River, NJ58 0.2 188 South of site, on Southern Area Stores accessroad, Forked River, NJ59 0.3 166 SSE of site, on Southern Area Stores accessroad, Waretown, NJ61 0.3 104 ESE of site, on Route 9 south of OCGS MainEntrance, Forked River, NJ62 0.2 83 East of site, on Route 9 at access road to OCGSMain Gate, Forked River, NJ63 0.2 70 ENE of site, on Route 9, between main gate andOCGS North Gate access road, Forked River, NJ64 0.3 42 NE of site, on Route 9 North at entrance toFinninger Farm, Forked River, NJ65 0.4 19 NNE of site, on Route 9 at Intake Canal Bridge,Forked River, NJ66 0.4 133 SE of site, east of Route 9 and south of theOCGS Discharge Canal, inside fence, Waretown,NJ112 0.2 178 S of site, along Southern access road, LaceyTownship, NJ122014 CY-OC-170-301Revision 6Page 131 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)1. Direct Radiation (Continued)DOS -Inner Ring at or near site boundaryCode113T1DOS45689(miles)0.30.4(dearees)90219DescriptionE of site, along Rt. 9 North, Lacey Township, NJSW of site, at OCGS Fire Pond, Lacey Township,NJ224647486873747578798284-Outer Ring at 6 -8 km4.6 213 SSW of Site, Garden State Parkway and Route554, Barnegat, NJ4.2 353 North of Site, Garden State Parkway Rest Area,Forked River, NJ2.1 13 NNE of site, Lane Place, behind St. Pius Church,Forked River, NJ2.3 177 South of site, Route 9 at the WaretownSubstation, Waretown, NJ2.0 230 SW of site, where Route 532 and the GardenState Parkway meet, Waretown, NJ1.6 145 SE of site, on Long John Silver Way, SkippersCove, Waretown, NJ5.6 323 NW of Site, on Lacey Road adjacent to UtilityPole BT 259 654.6 26 NNE of Site, Route 9 and Harbor Inn Road,Berkeley Township, NJ4.5 189 South of Site, Intersection of Brook and SchoolStreets, Barnegat, NJ1.3 266 West of site, on Garden State Parkway North atmile marker 71.7, Lacey Township, NJ1.8 108 ESE of site, on Bay Parkway, Sands PointHarbor, Waretown, NJ1.8 88 East of site, Orlando Drive and Penguin Court,Forked River, NJ2.0 71 ENE of site, Beach Blvd. and Maui Drive, ForkedRiver, NJ1.8 2 North of site, 1514 Arient Road, Forked River, NJ2.9 160 SSE of site, Hightide Drive and Bonita Drive,Waretown, NJ4.4 36 NE of site, Bay Way and Clairmore Avenue,Lanoka Harbor, NJ4.4 332 NNW of site, on Lacey Road, 1.3 miles west ofthe Garden State Parkway on siren pole, LaceyTownship, NJ122014 CY-OC-1 70-301Revision 6Page 132 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)1. Direct Radiation (continued)DOS -Outer Ring at 6 -8 km (continued)Code (miles) (degrees) Description85 3.9 250 WSW of site, on Route 532, just east of WellsMills Park, Waretown, NJ86 5.0 224 SW of site, on Route 554, 1 mile west of theGarden State Parkway, Barnegat, NJ98 1.6 318 NW of site, on Garden State Parkway at milemarker 73.0, Lacey Township, NJ99 1.5 310 NW of site, on Garden State Parkway at milemarker 72.8, Lacey Township, NJ100 1.4 43 NE of site, Yacht Basin Plaza South off LakdesideDr., Lacey Township, NJ101 1.7 49 NE of site, end of Lacey Rd., East, LaceyTownship, NJ102 1.6 344 NNW of site, end of Sheffield Dr., Barnegat Pines,Lacey Township, NJ103 2.4 337 NNW of site, Llewellyn Parkway, Barnegat Pines,Lacey Township, NJ104 1.8 221 SW of site, Rt. 532 West, before Garden StateParkway, Ocean Township, NJ105 2.8 222 SW of site, Garden State Parkway North, besidemile marker 69.6, Ocean Township, NJ106 1.2 288 NW of site, Garden State Parkway North, besidemile marker 72.2 Lacey Township, NJ107 1.3 301 NW of Site, Garden State Parkway North, besidemile marker 72.5, Lacey Township, NJ109 1.2 141 SE of site, Lighthouse Dr., Waretown, OceanTownship, NJ110 1.5 127 SE of site, Tiller Drive and Admiral Way,Waretown, Ocean Township, NJDOS -Special Interest11 8.2 152 SSE of site, 80th and Anchor Streets, HarveyCedars, NJ71 1.6 164 SSE of site, on Route 532 at the WaretownMunicipal Building, Waretown, NJ72 1.9 25 NNE of site, on Lacey Road at Knights ofColumbus Hall, Forked River, NJ122014 CY-OC-1 70-301Revision 6Page 133 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)1. Direct Radiation (continued)DOS -Special Interest (continued)Code (miles) (dearees) Description81 3.5 201 SSW of site, on Rose Hill Road at intersectionwith Barnegat Boulevard, Barnegat, NJ88 6.6 125 SE of site, eastern end of 3rd Street, BarnegatLight, NJ89 6.1 108 ESE of site, Job Francis residence, Island BeachState Park90 6.3 75 ENE of site, parking lot A-5, Island Beach StatePark92 9.0 46 NE of site, at Guard Shack/Toll Booth, IslandBeach State Park3 6.0 97 East of site, near old Coast Guard Station, IslandBeach State Park Special Interest AreaDOS -BackgroundC 24.7 313 NW of site, JCP&L office in rear parking lot,Cookstown, NJ14 20.8 2 North of site, Larrabee Substation on RandolphRoad, Lakewood, NJ2. Airborne -Radioiodines and ParticulatesAPT, AIO -At or near site boundary in highest DIQ Sectors20 0.7 95 East of site, on Finninger Farm on south side ofaccess road, Forked River, NJ66 0.4 133 SE of site, east of Route 9 and south of theOCGS Discharge Canal, inside fence, Waretown,NJ111 0.3 64 ENE of site, Finninger Farm property alongaccess road, Lacey Township, NJAPT, AIO -Special Interest71 1.6 164 SSE of site, on Route 532 at the WaretownMunicipal Building, Waretown, NJ72 1.9 25 NNE of site, on Lacey Road at Knights ofColumbus Hall, Forked River, NJ73 1.8 108 ESE of site, on Bay Parkway, Sands PointHarbor, Waretown, NJAPT, AIO -BackgoundC 24.7 313 NW of site, JCP&L office in rear parking lot,Cookstown, NJ122014 CY-OC-1 70-301Revision 6Page 134 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)2. Airborne -Radioiodines and Particulates (continued)APT, AIO -Backgound(continued)Code (miles) (dearees) Description3 6.0 97 East of site, near old Coast Guard Station, IslandBeach State Park Special Interest Area3. WaterborneSWA -Surface2324333.62.10.4SWA -Backgound94 20.0GW -GroundW-3C 0.4MW-24-3A 0.8DW -Drinking1s 0.164 ENE of site, Barnegat Bay off Stouts Creek,approximately 400 yards SE of "Flashing Light 1"101 East of site, Barnegat Bay, approximately 250yards SE of "Flashing Light 3"123 ESE of site, east of Route 9 Bridge in OCGSDischarge Canal198 SSW of site, in Great Bay/Little Egg Harbor112 ESE of site on Finninger Farm adjacent to Station35, Lacey Township, NJ97 E of site on Finninger Farm on South side ofaccess road, Lacey Township, NJ209 On-site southern domestic well at OCGS, ForkedRiver, NJ349 On-site northern domestic well at OCGS, ForkedRiver, NJ197 SSW of Site, on Route 532, at Ocean TownshipMUA Pumping Station, Waretown, NJ18 NNE of Site, off Boox Road at Lacey MUAPumping Station, Forked River, NJ353 N of Site, Trenton Ave. off Lacey Road LaceyTwp., MUA Pump Station, Forked River, NJ64 ENE of site, Barnegat Bay off Stouts Creek,approximately 400 yards SE of "Flashing Light 1"101 East of site, Barnegat Bay, approximately 250yards SE of "Flashing Light 3"123 ESE of site, east of Route 9 Bridge in OCGSDischarge Canal1N380.21.6DW -Backgound37 2.2393.5AQS -Sediment23 3.624332.10.4122014 CY-OC-170-301Revision 6Page 135 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)3. Waterborne (continued)AQS -BackgoundCode (miles) (dearees) Description94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor4. IngestionFISH -Fish930.1FISH -Backgound94 20.0CLAM -Clams23 3.6242.1CLAM -Backgound94 20.0CRAB -Crabs242 WSW of site, OCGS Discharge Canal betweenPump Discharges and Route 9, Forked River, NJ198 SSW of site, in Great Bay/Little Egg Harbor64 ENE of site, Bamegat Bay off Stouts Creek,approximately 400 yards SE of "Flashing Light 1"101 East of site, Barnegat Bay, approximately 250yards SE of "Flashing Light 3"198 SSW of site, in Great Bay/Little Egg Harbor123 ESE of site, east of Route 9 Bridge in OCGSDischarge Canal242 WSW of site, OCGS Discharge Canal betweenPump Discharges and Route 9, Forked River, NJ111 ESE of site, east of Route 9 and north of theOCGS Discharge Canal, Forked River, NJ133 SE of site, east of Route 9 and south of theOCGS Discharge Canal, inside fence, Waretown,NJ96 East of Site, on Finninger Farm319 NW of site, at "U-Pick" Farm, New Egypt, NJ33930.40.1VEG -Vegetation35 0.4661150.40.3VEG -Backgound36 23.1122014 CY-OC-1 70-301Revision 6Page 136 of 140SAMPLE MEDIUM IDENTIFICATION KEYAPT = Air ParticulateAIO = Air IodineVEG = VegetablesSWA = Surface WaterAQS = Aquatic SedimentCLAM = ClamsDW = Drinking WaterDOS = DosimeterFISH = FishCRAB =CrabGW = Ground Water(1) Samples may not be collected from some locations listed in this table, as longas the minimum number of samples listed in Table 3.12.1-1 is collected.122014 FIGURE E-1CY-OC-1 70-301Revision 6Page 137 of 140ENEOyster Creek Generating StationREMP Sample Locationswithin a I Mle Radius03 11.15 O 0.3 l" bDWe. 094t12122014 CY-OC-1 70-301Revision 6Page 138 of 140Oyster Creek Generating StationREMP Sample Locationswithin a 1 to 5 Mile RadiusDate: 08/27/12122014 CY-OC-1 70-301Revision 6Page 139 of 140FIGURE E-3.7fc) 2011 S,,bo()Oyster Creek Generating StationREMP Sample Locationsover a 5 Mile Radius5.5 2.75 0 &5 Ws5Date: 08127/12122014 CY-OC-1 70-301Revision 6Page 140 of 140FIGURE E-4AREA PLOT PLAN OF SITESITE MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVEGASEOUS AND LIQUID EFFLUENTSSite Boundary DistancesSectorSSSWSWWSWWWNWNWNNWDistance in metersSector348291229260239284364474NNNENEENEEESESESSEDistance in meters584621373338360491544395122014 Exeo eeRW-AA-100S Exeton Generation, Revision 10Page 1 of 12Level 3 -Information UsePROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES1. PURPOSE1.1. The purpose of the Process Control Program (PCP) is to:1.1.1. Establish the process and boundary conditions for the preparation of specificprocedures for processing, sampling, analysis, packaging, storage, and shipment ofsolid radwaste in accordance with local, state, and federal requirements. (CM-1)1.1.2. Establish parameters which will provide reasonable assurance that all Low LevelRadioactive Wastes (LLRW), processed by the in-plant waste process systemson-site OR by on-site vendor supplied waste processing systems, meet theacceptance criteria to a Licensed Burial Facility, as required by 10CFR Part 20,1 OCFR Part 61, 1 OCFR Part 71, 49CFR Parts 171-172, "Technical Position onWaste Form (Revision 1)" (1/91], "Low-Level Waste Licensing Branch TechnicalPosition on Radioactive Waste Classification" [5/83], and the Station TechnicalSpecifications, as applicable.1.1.3. Provide reasonable assurance that waste placed in "on-site storage" meets therequirements as addressed within the Safety Analysis Reports for the low levelradwaste storage facilities for dry and/or processed wet waste.2. TERMS AND DEFINITIONS2.1. Process Control Program (PCP): The program which contains the currentformulas, sampling, analysis, tests, and determinations to be made to ensure thatprocessing and packaging of solid radioactive waste based on demonstratedprocessing of actual or simulated wet solid wastes will be accomplished in such away as to assure the waste meets the stabilization criteria specified in 1 OCFR Parts20, 61 and 71, state regulations, and burial site requirements.2.2. Solidification: Liquid waste processed to either an unstable or stable form per10 CFR61 requirements. Waste solidified does not have to meet the 300-year freestanding monolith criteria. Approved formulas, samples and tests do not have tomeet NRC approval for wastes solidified in a container meeting stability criteria (e.g.High Integrity Container).2.3. Stabilization: Liquid waste processed to a "stable state" per 10CFR61Requirements. Established formulas, samples, and tests shall be approved by theNRC in order to meet solidification "stabilization" criteria. This processing method iscurrently not available, because the NRC recognizes that waste packed in a HighIntegrity Container meets the 300-year stabilization criteria. In the event that thisprocessing method becomes an acceptable method, then the NRC shall approve thestabilization formulas, samples, tests, etc. | |||
RW-AA-100Revision 10Page 2 of 122.4. Solidification Media: An approved media (e.g. Barnwell -vinyl ester styrene,cement, bitumen) when waste containing nuclides with greater than 5-year half livesis solidified in a container with activity greater than 1 micro curie/cc. Waste solidifiedin a HIC is approved by the commission meeting the 1 OCFR61 stabilization criteria,including 1% free standing liquids by volume when the waste is packaged to a"stable" form and < 0.5% when waste is packaged to an "unstable" form. Theformulas, sampling, analysis, and test do not require NRC approval, because theHIC meets the stability criteria.2.4.1. Solidification to an unstable or stable state is performed by vendors, whenapplicable. Liquid waste solidified to meet stabilization criteria (1OCFR61 and 01-91Branch Technical Requirements) shall have documentation available thatdemonstrates that the process is approved by the NRC or disposal facility.2.5. Dewatering: The process of removing fluids from liquid waste streams to produce awaste form that meets the requirements of 1OCFR Part 61 and applicable burial sitecriteria, <0.5% by volume when the waste is packaged to an "unstable" state, or_<1% by volume when the waste is packaged to a "stable" form.2.6. High Integrity Container (HIC): A disposable container that is approved to theRequirements of 10CFR61. The use of HIC's is an alternative to solidification orencapsulation in a steel container to meet burial stability. HIC's are used to packagedewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), ordry active waste.2.7. Liquid Waste Processing Systems: In-plant or vendor supplied processingsystems consisting of equipment utilized for evaporation, filtration, demineralization,dewatering, compression dewatering, solidification, or reverse osmosis (RO) for thetreatment of liquid wastes (such as Floor Drains, Chemical Drains and EquipmentDrain inputs).2.8. Incineration, RVR. and/or Glass Vitrification of Liquid or Solid: Dry or wetwaste processed via incineration and/or thermal processing where the volume isreduced by thermal means meets 1 OCFR61 requirements.2.9. Compaction: When dry wastes such as paper, wood, plastic, cardboard,incinerator ash, and etc. are volume reduced through the use of a compactor.I RW-AA-100Revision 10Page 3 of 122.10. Waste Streams: Consist of but are not limited to-Filter media (powdered, bead resin and fiber),-Filter cartridges,-Pre-coat body feed material,-Contaminated charcoal,-Fuel pool activated hardware,-Oil Dry absorbent material added to a container to absorb liquids-Fuel Pool Crud-Sump and tank sludges,-High activity filter cartridges,-Concentrated liquids,-Contaminated waste oil,-Dried sewage or wastewater plant waste,-Dry Active Waste (DAW): Waste such as filters, air filters, low activitycartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, andmetals, etc, which have become contaminated as a consequence of normaloperating, housekeeping and maintenance activities.-Other radioactive waste generated from cleanup of inadvertent contamination.2.11. Concentration Averaging: Concentration averaging is either: a) the mathematicalaveraging of waste concentrations, based on the size, geometry, type of radioactiveemission, and observed dose rates, or b) the combining of radioactive componentsin a single container and how their radioactivity may be averaged over the volume ofthe container. Concentration averaging is subject to constraints identified in theNRC's Branch Technical Position on Concentration Averaging and Encapsulationand may also be constrained by Agreement States or Disposal Facilities.2.12. Encapsulation: Encapsulation is the surrounding of a radioactive source orcomponent with a nonradioactive material. Encapsulation involves a radioactivecore surrounded by a non-radioactive matrix.2.13. Blending: The intentional mixing of different, but miscible waste streams (such asresins, filter media, etc.) from different batches or systems for the purpose ofoperational efficiency or ALARA. Blending applies to LLRW streams only. Theaddition of non-radioactive materials or fillers is not considered blending.3. RESPONSIBILITIES3.1. Implementation of this Process Control Program (PCP) is described in procedures ateach station and is the responsibility of the each site to implement. | |||
RW-AA-100Revision 10Page 4 of 124. MAIN BODY4.1. Process Control Program Requirements4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be madeprovided that the change is reported as part of the annual radioactive effluentrelease report, Regulatory Guide 1.21, and is approved by the Plant OperationsReview Committee (PORC).4.1.2. Changes become effective upon acceptance per station requirements.4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquidradwaste is solidified to a stable/unstable state.4.1.4. When processing liquid radwaste to meet solidification stability using a vendorsupplied solidification system:1. If the vendor has its own Quality Assurance (QA) Program, then the vendorshall ADHERE to its own QA Program and shall have SUBMITTED itsprocess system topical report to the NRC or agreement state.2. If the vendor does not HAVE its own Quality Assurance Program, then thevendor shall ADHERE to an approved Quality Assurance Topical Reportstandard belonging to the Station or to another approved vendor.4.1.5. The vendor processing system(s) is/are controlled per the following:1. A commercial vendor supplied processing system(s) may be USED for theprocessing of LLRW streams.2. Vendors that process liquid LLRW at the sites shall MEET applicable QualityAssurance Topical Report and Augmented Quality Requirements.4.1,6. Vendor processing system(s) operated at the site shall be OPERATED andCONTROLLED in accordance with vendor approved procedures or stationprocedures based upon vendor approved documents.4.1,7. All waste streams processed for burial or long term on-site storage shall MEET thewaste classification and characteristics specified in 1OCFR Part 61.55, Part 61.56,the 5-83 Branch Technical Position for waste classification, and the applicable burialsite acceptance criteria (for any burial site operating at the time the waste wasprocessed).4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, providedformal NRC approval has been RECEIVED for the transfer of waste. | |||
RW-AA-100Revision 10Page 5 of 124.2. General Waste Processing RequirementsNOTE: On-site resin processing involves tank mixing and settling,transferring to the station or vendor processing system via resinwater slurry or vacuuming into approved waste containers, and,when applicable, dewatering for burial.4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as,SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut DownCooling). These resins are then PROCESSED via the station or vendor processingsystem.4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitablecontainers for processing treatment. Water from these tanks may be SENT througha filter, demineralizer, concentrator or vendor supplied processing systems.4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodicallyDISCHARGED to the station or vendor processing system for onsite wastetreatment or PACKAGED in containers for shipment to offsite vendor for volumereduction processing.4.2.4. Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT toeither the site waste processing systems or vendor waste processing systems forfurther filtration, demineralization for plant re-use, or discharge.4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utilitysite personnel or by on-site vendors or will be PACKAGED and SHIPPED to anoff-site vendor low-level radwaste processing facility.4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:1. DAW will be COLLECTED and SURVEYED and may be SORTED forcompactable and non-compactable wastes.2. DAW may be packaged in containers to facilitate on-site pre-compactionand/or off-site vendor contract requirements.3. DAW items may be SURVEYED for release onsite or offsite when applicable.4. Contaminated filter cartridges will be PLACED into a HIC or will beENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsitewaste processor in drums, boxes or steel liners per the vendor site criteria forprocessing and disposal. | |||
RW-AA-100Revision 10Page 6 of 124.2.7. Filtering devices using pre-coat media may be USED for the removal of suspendedsolids from liquid waste streams. The pre-coat material or cartridges from thesedevices may be routinely REMOVED from the filter vessel and discharged to a FilterSludge Tank or Liner/HIC. Periodically, the filter sludge may be DISCHARGED tothe vendor processing system for waste treatment onsite or PACKAGED incontainers for shipment to offsite vendor for volume reduction processing.4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodicallyusing remote handling equipment and may then be PUT into a container forshipment or storage in the pool or loading the processed activated hardware into theDry Cask storage system.4.2.9. High Integrity Containers (HIC):1. For disposal at Barnwell, vendors supplying HIC's to the station shallPROVIDE a copy of the HIC Certificate of Compliance, which details specificlimitations on use of the HIC.2. For disposal at Clive or WCS, vendors supplying HIC's to the station shallPROVIDE a copy of the HIC Certificate of Conformance, which detailsspecific limitations on use of the HIC.3. Vendors supplying HIC's to the station shall PROVIDE a handling procedurewhich establishes guidelines for the utilization of the HIC. These guidelinesserve to protect the integrity of the HIC and ensure the HIC is handled inaccordance with the requirements of the Certificate of Compliance orCertificate of Conformance.4.2.10. Lubricants and oils contaminated as a consequence of normal operating andmaintenance activities may be PROCESSED on-site (by incineration, for oilsmeeting 10CFR20.2004 and applicable state requirements, or by an approvedvendor process) or SHIPPED offsite (for incineration or other acceptable processingmethod).4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areasmay be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities,Braidwood and Byron.4.2.12. Certain waste, including flowable solids from holding pond, oily waste separator,cooling tower basin and emergency spray pond, may be disposed of onsite underthe provisions of a 10CFR20.2002 permit. Specific requirements associated with thedisposal shall be incorporated into station implementing procedures. (CM-2) | |||
RW-AA-100Revision 10Page 7 of 124.2.13. Concentration averaging may be PERFORMED to combine LLRW having differentconcentrations of radionuclides to form a homogeneous mixture in accordance withthe guidance in the NRC's Branch Technical Position on Concentration Averagingand Encapsulation-1995:-For homogeneous waste types such as resins and filter media, theconcentration of the mixture for classification purposes may be based oneither the highest radionuclide concentration in any of the individual wastetypes contributing to the mixture or the volumetric or weight-averaged nuclideconcentrations in the mixture provided that the concentrations of theindividual waste type contributors to the mixture are within a factor of 10 ofthe average concentration of the resulting mixture. (NOTE: a designedcollection of homogeneous waste types (from different sources within afacility) is not considered 'mixing' and the concentration for classificationpurposes may be the average concentration of the combination).-For non-homogeneous waste types such as activated metals, cartridge filtersor components incorporating radioactivity in their design, the concentrationshould be determined from the total weight or displaced volume (excludingmajor void spaces) of the component. Mixtures of components in a disposalcontainer is permissible. Concentration averaging of a mixture of componentsof similar types can be performed in accordance with the NRC's BranchTechnical Position on Concentration Averaging and Encapsulation and anyState or Disposal Site specific requirements.4.2.14. Blending may be PERFORMED for routine LLRW such as resins and filter media inaccordance with the guidance in the NRC's Branch Technical Position onConcentration Averaging and Encapsulation as further clarified in SECY 2010-0043.The concentration of the mixture may be determined based on the total activity of allcomponents in the mixture divided by the total volume or mass of the mixture.Reasonable effort should be made to mix blended LLRW so that activity is evenlydistributed.4.2.15. Encapsulation may be PERFORMED for routine wastes such as filters, filtercartridges, or sealed sources centered in an encapsulated mass, in accordance withthe guidance in the NRC's Branch Technical Position on Concentration Averagingand Encapsulation. Classification may be based on the overall volume of the finalsolidified mass provided that;-The minimum solidified volume or mass should be reasonably difficult tomove by hand.-The maximum solidified volume or mass used for determiningconcentration for any single discrete source should be no more than 0.2m3 or 500Kg (typically 55-gallon drum).-The maximum amount of gamma-emitting radioactivity or radioactivematerial is <0.02 mrem/hr on the surface of the encapsulation over a 500-year decay period. | |||
RW-AA-100Revision 10Page 8 of 12The maximum amount of any radionuclide in a single encapsulation, whenaveraged over the waste and encapsulating media, does not exceed themaximum concentration limits for Class C waste.Written procedures should be established to ensure that the radiationsource(s) is reasonably centered (or distributed) within the encapsulatingmedia.All other disposal facility requirements for encapsulated material are met.4.3. Burial Site Requirements4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of49CFR171-172, 1OCFR61, 1OCFR71, and the acceptance criteria for the applicableburial site.4.4. Shippinq and Inspection Requirements4.4.1. All shipping/storage containers shall be INSPECTED, as required by stationprocedures, for compliance with applicable requirements (Department ofTransportation (DOT), Nuclear Regulatory Commission (NRC), station, on-sitestorage, and/or burial site requirements) prior to use.4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification qualityand/or dewatering requirements per the burial site, offsite vendor acceptance, orstation acceptance criteria, as applicable.4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that theapplicable processor's waste acceptance criteria are being met.4.4.4. Shipments sent for off site storage shall MEET the storage site's waste acceptancecriteria.4.5. Inspection and Corrective Action4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor,or site requirements shall be IDENTIFIED and TRACKED through the CorrectiveAction Program.4.5.2. Administrative controls for preventing unsatisfactory waste forms from beingreleased for shipment are described in applicable station procedures. If theprovisions of the Process Control Program are not satisfied, then SUSPENDshipments of defectively packaged radioactive waste from the site. (CM-1)4.5.3. If freestanding water or solidification not meeting program requirements is observed,then samples of the particular series of batches shall be TAKEN to determine thecause. Additional samples shall be TAKEN, as warranted, to ensure that nofreestanding water is present and solidification requirements are maintained. | |||
RW-AA-100Revision 10Page 9 of 124.6. Procedure and Process Reviews4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other thaneditorial/minor changes) shall be REVIEWED and APPROVED in accordance withthe station procedures, plant-specific Technical Specifications (Tech Spec),Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),as applicable, for the respective station and LS-AA-106. Changes to the LicenseesControlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of10CFR 50.59.4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required inthe Annual Radiological Effluent Release Report (ARERR). The RadwasteSpecialist shall ensure correct information is SUBMITTED to the ODCM programowner prior to submittal of the ARERR.4.6.3. Procedures shall be IMPLEMENTED as follows:-Station processes or other vendor waste processing/operating proceduresshall be technically reviewed and approved per RM-AA-102-1006.-Procedures related to waste manifests, shipment inspections, and containeractivity determinations are CONTROLLED by Radiation Protection StandardProcedures (RP-AA-600 Series).-Site waste processing IS CONTROLLED by site operating procedures.-Liquid processed by vendor equipment shall be PERFORMED in accordancewith vendor procedures.-The dewatering procedures implemented by Vendor for the purpose ofcompliance to the Process Control Program SHALL BE REVIEWED andAPPROVED in accordance with the plant specific TRM or ORM (eitherCurrent Technical Specifications (CTS) or Improved Technical Specifications(ITS), as applicable for the respective stations).4.7. Waste Types, Point of Generation, and Processing MethodMethods of processing and individual vendors may CHANGE due to changingfinancial and regulatory options. The table below is a representative sample. It isnot intended be all encompassing. | |||
RW-AA-100Revision 10Page 10 of 12AVAILABLE WASTEWASTE STREAM POINTS OF GENERATION POEING MEPROCESSING METHODSBead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to anReactor Water Cleanup, Blowdown, unstable/stable stateEquipment Drain, Chemical and Thermal ProcessingVolume Control Systems, Floor Drain,Maximum Recycle, Blowdown, Boric Free Release to a Land FillAcid Recycling System, VendorSupplied Processing Systems, andPortable Demin SystemPowdered Resin Systems -(Condensate System, Floor Dewatering, solidification to anDrain/Equipment Drain filtration, Fuel unstable/stable statePool) Thermal ProcessingConcentrated Waste Waste generated from Site Solidification to an unstable/stableEvaporators resulting typically from the stateFloor Drain and Equipment Drain Thermal ProcessingSystemsSludge Sedimentation resulting from various Dewatering, solidification to ansumps, condensers, tanks, cooling unstable/stable statetower, emergency spray pond, holding Thermal Processingpond, and oily waste separatorsEvaporation on-site or at an offsiteprocessorOn-site disposal per 1OCFR20.2002permitFilter cartridges Systems -Floor/Equipment Drains, Dewatering, solidification to anFuel Pool; cartridge filters are typically unstable/stable stategenerated from clean up activities Processed by a vendor for volumewithin the fuel pool, torus, etc reductionDry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Releasemetal, and etc. resulting from daily Compaction/Super-compactionplant activitiesThermal Processing by Incinerationor glass vitrificationSorting for Free ReleaseMetal melting to an ingotContaminated Oil Oil contaminated with radioactive Solidification unstable statematerials from any in-plant system. Thermal Processing by IncinerationFree Release for recyclingDrying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burialTreatment FacilitiesMetals See DAW See DAWIrradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packagingefficiencies RW-AA-100Revision 10Page 11 of 125. DOCUMENTATION5.1. Records of reviews performed shall be retained for the duration of the unit operatinglicense. This documentation shall contain:1. Sufficient information to support the change together with the appropriateanalyses or evaluations justifying the change, and2. A determination which documents that the change will maintain the overallconformance of waste products to Federal (1 OCFR61 and the BranchTechnical Position), State, or other applicable requirements, includingapplicable burial site criteria.6. REFERENCES6.1. Technical Specifications:6.1.1. The details contained in Current Tech Specs (CTS) or Improved TechnicalSpecifications (ITS), as applicable, in regard to the Process Control Program (PCP),are to be relocated to the Licensee Controlled Documents. Some facilities haveelected to relocate these details into the Operational Requirements Manual (ORM).Relocation of the description of the PCP from the CTS or ITS does not affect thesafe operation of the facility. Therefore, the relocation details are not required to bein the CTS or the ITS to provide adequate protection of the public health and safety.6.2. Writers' | |||
==References:== | |||
6.2.1. Code of Federal Regulations: 10 CFR Part 20, Part 61, Part 71, 49 CFRParts 171-1726.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive WasteClassification, May 19836.2.3. Technical Position on Waste Form (Revision 1), January 19916.2.4. USNRC Branch Technical Position on Concentration Averaging and Encapsulation,January 19956.2.5. Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in SolidWastes and Releases of Radioactive materials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants6.2.6. I.E. Circular 80.18, 1OCFR 50.59 Safety Evaluation for Changes to RadioactiveWaste Treatment Systems6.2.7. Amendment No. 202 to Facility Operating License No. NPF-1 1 and Amendment No.189 to Facility Operating License (FOL) No. NPF-18 for the LaSalle County Station(LSCS), Units 1 and 2 RW-AA-100Revision 10Page 12 of 126.2.8. NRC Branch Technical Position on Blending of Low-Level Radioactive Waste,SECY-10-00436.3. Users' | |||
==References:== | |||
6.3.1. Quality Assurance Program (QATR)6.3.2. LS-AA-106, Plant Operations Review Committee6.3.3. RM-AA-102-1006, Processing Vendor Documents6.3.4. RP-AA-600 Series, Radioactive Material/Waste Shipments6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report6.4. Station Commitments:6.4.1. Peach BottomCM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmittingTSCR 93-16 (Improved Technical Specifications). (Step 1.1.1,4.5.2)6.4.2. LimerickCM-2, T03896, 1OCFR20.2002 permit granted to Limerick via letter datedJuly 10, 1996. (Step 4.2.12)7. ATTACHMENTS -None}} | |||
Revision as of 17:29, 11 June 2018
| ML15132A140 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/30/2015 |
| From: | Dostal J P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| RA-15-035 | |
| Download: ML15132A140 (300) | |
Text
Exelon Generation10 CFR 50.36a(a)(2)10 CFR 72.44 (d)(3)Technical Specification 6.9.1 .dRA-1 5-035April 30, 2015U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555 -0001Oyster Creek Nuclear Generating StationRenewed Facility Operating License No. DPR-16NRC Docket No. 50-219Independent Spent Fuel Storage FacilityNRC Docket No. 72-15
Subject:
Annual Radioactive Effluent Release Report for 2014Enclosed with this cover letter is the Annual Radioactive Effluent Release Report for theperiod January 1 to December 31, 2014. This report includes the Oyster Creek NuclearGenerating Station Independent Spent Fuel Storage Facility.If any further information or assistance is needed, please contact John Renda,Chemistry Manager, at 609-971-2572.Sincerely,Jeff r 5staPlant Manage'r -Oyster Creek Nuclear Generating Station
Enclosure:
2014 Annual Radioactive Effluent Release Reportcc: Administrator, USNRC Region I (w/o attachment)USNRC Senior Project Manager, Oyster Creek (w/o attachment)USNRC Senior Resident Inspector, Oyster Creek (w/o attachment)Craig Stewart, American Nuclear InsurersA-1 vrjý 5 J-AExelon Generation(OAnnual Radioactive Effluent Release Report2014Oyster Creek Generating Station Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2014 through December 31, 2014EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTABLE OF CONTENTSSECTION PAGEEXECUTIVE SUMMARY 11. Introduction 32. Supplemental Information 4A Regulatory Limits 4B Effluent Concentration Limits 5C Average Energy 5D Measurements and Approximations of Total Radioactivity 5E Batch Releases 9F Abnormal Releases 9G Revisions to the ODCM 10H Radiation Effluent Monitors Out of Service More Than 30 Days 10I Releases from the Independent Spent Fuel Storage Facility 10J Program Deviations 11Appendix A -Effluent and Waste Disposal Summary 12Appendix B -Solid Waste and Irradiated Fuel Shipments 19Appendix C -Radiological Impact to Man 26Appendix D -Meteorological Data 29Appendix E -ODCM Revisions 103Appendix F -ERRATA 104ii Oyster Creek 2014 Annual Radioactive Effluent Release Report(Page Intentionally Left Blank)iii Oyster Creek 2014 Annual Radioactive Effluent Release ReportEXECUTIVE SUMMARYEffluents are strictly monitored to ensure that radioactivity released to the environment is aslow as reasonably achievable and does not exceed regulatory limits. Effluent control includesthe operation of monitoring systems, in-plant and environmental sampling and analysesprograms, quality assurance programs for the effluent and environmental programs, andprocedures covering all aspects of effluent and environmental monitoring.Both radiological environmental and effluent monitoring indicate that the operation of OysterCreek Generating Station (OCGS) does not result in significant radiation exposure to thepeople or the environment surrounding OCGS and is well below the applicable levels set by theNuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were liquid radioactive effluent releases during 2014 of concentrations of tritium too lowto detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution DischargeElimination System (NJPDES) permitted main condenser outfall. The releases were part ofnearly continuous pumping of groundwater at approximately 70 gpm containing low levels oftritium and no detectable gamma. Exelon and the State of New Jersey Department ofEnvironmental Protection (NJDEP) agreed to this remediation action instead of naturalattenuation to address concentrations of tritium in groundwater. Well 73 and supportingequipment and piping were installed to pump groundwater to the intake structure at the inlet ofthe main circulating water pumps. Provisions were established for both batch and continuousreleases of groundwater. Continuous releases occurred approximately 230 days in 2014. Thenearly continuous releases occurred from March 12, 2014 through December 31, 2014 with atotal of 2.31 E+07 gallons of groundwater pumped resulting in 1.74E-01 Ci of tritium released tothe discharge canal. The dose to the most limiting member of the public due to the release ofgroundwater was 8.28E-07 mrem.There were no liquid abnormal releases during 2014.There were two gaseous abnormal releases during 2014. During maintenance of the OldRadwaste Building exhaust fan EF-1 -17 the side panel was removed to access the fan whenpositive pressure was noted coming from the opening. The side panel was immediatelyreplaced and sealed. During maintenance of the New Radwaste Building exhaust fan HV-S-54A, two slits were identified in the expansion joint and repaired.The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), andparticulates to any individual due to gaseous effluents was 4.78E-01 mrem, which wasapproximately 3.19E+00 percent of the annual limit of 15 mrem. The majority of organ dosefrom gaseous effluents was due to C-14. The maximum calculated gamma air dose in theUNRESTRICTED AREA due to noble gas effluents was 1.62E-02 mrad, which was 1.62E-01percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limitof 10 mrad.For comparison, the background radiation dose averages approximately 300 mrem per year in theCentral New Jersey area, which includes approximately 200 mrem from naturally occurring radongas and 100 mrem from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposure1 Oyster Creek 2014 Annual Radioactive Effluent Release Reportis due to direct radiation. Based on offsite TLD readings, dose due to direct radiation from theISFSI was less than 1 mrem for 2014. Because it is a sealed unit, no radioactive material wasreleased.Comparison of environmental sampling results to iodine and particulate gaseous effluentsreleased, showed no radioactivity attributable to the operation of OCGS. Both elevated andground-level release paths were considered in this review, with total iodines released of5.29E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of3.33E-02 Ci.Joint Frequency Tables of meteorological data, per Stability Classification Category, as well asfor all stability classes, are included. All data was collected from the on-site MeteorologicalFacility. Data recoveries for the 380-foot data and the 33-foot data were 99.9 percent and 99.9percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for MeteorologicalFacility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.2 Oyster Creek 2014 Annual Radioactive Effluent Release ReportIntroductionIn accordance with the reporting requirements of Technical Specification 6.9.1.dapplicable during the reporting period, this report summarizes the effluent releasedata for OCGS for the period January 1, 2014 through December 31, 2014. Thissubmittal complies with the format described in Regulatory Guide 1.21,"Measuring, Evaluating and Reporting Radioactivity in Solid Wastes andReleases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974.Meteorological data was reported in the format specified in Regulatory Guide1.23, Revision 1, "Meteorological Monitoring Programs for Nuclear PowerPlants".All vendor results were received and included in the report calculations. Therefore the2014 report is complete.3 Oyster Creek 2014 Annual Radioactive Effluent Release Report2 Supplemental InformationOyster Creek Generating StationExelon Generation Company, LLCA. Regulatory Limits:LimitUnitsReceptorODCM and 10 CFR 50,Appendix I Design ObjectiveLimits1. Noble Gases:a. < 500mrem/yr Total Body< 3000 mrem/yrSkinb. <5*<10C. <10*<20mradmradmradmradAir GammaAir BetaAir GammaAir BetaTotal Body(Gamma)Skin (Beta)d. < 5 mrem< 15mrem2. lodines, Tritium, Particulates with Half Life > 8 days:a. < 1500 mrem/yr Any OrganODCM Control 3.11.2.1Quarterly air dose limitsODCM Control 3.11.2.2Yearly air dose limitsODCM Control 3.11.2.210 CFR 50, Appendix I,Section II.B.2(b)ODCM Control 3.11.2.1Quarterly dose limitsODCM Control 3.11.2.3Yearly dose limitsODCM Control 3.11.2.3ODCM Control 3.11.1.1Quarterly dose limitsODCM Control 3.11.1.2Yearly dose limitsODCM Control 3.11.1.2b. :< 7.5 mremAny OrganAny OrganC. _<15mrem3. Liquid Effluentsa. Concentration 10 CFR 20, Appendix B,Table 2 Column 2b. _<1.5< 5C. _<3<10mremmremmremmremTotal BodyAny OrganTotal BodyAny Organ4 Oyster Creek 2014 Annual Radioactive Effluent Release ReportB. Effluent Concentration Limits:Gaseous dose rates rather than effluent concentrations are used to calculatepermissible release rates for gaseous releases. The maximum permissible doserates for gaseous releases are defined in ODCM Controls 3.11.2.1.The Effluent Concentration Limit (ECL) specified in 10 CFR 20, Appendix B, Table2, Column 2 for identified nuclides, were used to calculate permissible release ratesand concentrations for liquid release per ODCM Controls 3.11..1.1. The total activityconcentration at the Route 9 bridge for all dissolved or entrained gases was limitedto < 2E-04 pjCi/ml.C. Average Energy ()E:The Oyster Creek ODCM limits the instantaneous dose equivalent rates due to therelease of noble gases to less than or equal to 500 mrem/year to the total body andless than or equal to 3000 mrem/year to the skin. The average beta and gammaenergies (-) of the radionuclide mixture in releases of fission and activation gasesas described in Regulatory Guide 1.21, "Measuring, Evaluating and ReportingRadioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid andGaseous Effluents from Light-Water-Cooled Nuclear Power Plant", may be used tocalculate doses in lieu of more sophisticated software. The Oyster Creekradioactive effluent program employs the methodologies presented in U.S. NRCRegulatory Guide 1.109 "Calculation of Annual Doses to Man from RoutineReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977. Therefore, average energy(-) as described in Regulatory Guide 1.21 is not applicable to Oyster Creek.D. Measurements and Approximations of Total Radioactivity:1. Fission and Activation GasesThe method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a gas Marinelli beaker. Airborne effluent gaseousactivity was continuously monitored and recorded in accordance with the OffSite Dose Calculation Manual (ODCM) Table 4.11.2.1.2-1. Additional grabsamples were taken from the stack Radioactive and Gaseous EffluentMonitoring System (RAGEMS) sample point and ground-level release samplepoints and analyzed at least monthly to determine the isotopic mixture of noblegas activity released for the month. If activity was found in the grab isotopicanalysis, the results are entered into Simplified Environmental EffluentDosimetry System (SEEDS) to calculate dose and dose rates. If no activity isdetected in the stack grab samples, post treatment or Off Gas IsotopicAnalysis data may be used.2. lodinesThe method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a charcoal cartridge. Iodine activity was continuouslysampled and analyzed in accordance with ODCM Table 4.11.2.1.2-1.Charcoal samples are taken from the stack RAGEMS sample point and5 Oyster Creek 2014 Annual Radioactive Effluent Release Reportground-level release sample points and analyzed at least weekly to determinethe total activity released from the plant based on the average vent flow ratesrecorded for the sampling period.3. Particulates (half-lives > 8 days)The method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a particulate filter (47 mm). Particulate activity wascontinuously sampled and analyzed in accordance with ODCM Table4.11.2.1.2-1. Particulate samples are taken from the stack RAGEMS samplepoint and ground-level release sample points and analyzed at least weekly todetermine the total activity released from the plant based on the average ventflow rates recorded for the sampling period.4. TritiumA. Gaseous EffluentsAir from stack and vent effluents was passed through a desiccantcolumn and distilled to remove the moisture collected. An aliquot of thewater from the distillate was analyzed for tritium using a liquidscintillation counter.B. Liquid EffluentsWater from liquid effluents was analyzed for tritium using a liquidscintillation counter.5. Gross AlphaGross alpha was measured by an off-site vendor for both the gas andliquid effluent composite samples.6. Hard-To-DetectsHard-To-Detects was measured by an off-site vendor for one set of gasmonthly composites. The analysis included Fe-55, 1-129, Ni-59, Ni-63,Tc-99, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241.Fe-55 and Ni-63 have been added to the routine monthly compositeanalysis schedule based on previous sample results for Hard-To-Detects.6 Oyster Creek 2014 Annual Radioactive Effluent Release Report7. Carbon-14 (C-14)The amount of C-14 (Ci) released was estimated using the guidance fromEPRI Technical Report 1021106, Estimation of Carbon-14 in Nuclear PowerPlant Gaseous Effluents. The C-14 was released primarily through the stack(97%) with a small amount (3%) released through plant vents. The activity inliquid effluents was determined to not be significant.The offsite dose from C-14 was calculated using SEEDS, which usesapproved ODCM methodologies. The resulting annual dose to a child fromgaseous releases of C-14 is about 4.53E-01 mrem to the bone.8. Liquid EffluentsGroundwater containing tritium was released during 2014. For continuousreleases, tritium and principal gamma emitters were determined for acomposite sample daily. The concentration of tritium is limited to ensureconcentrations were less than 200 pCi/I in the discharge canal. The gammaemitters were limited to less than detectable concentrations. Gross alpha andHard-to-detect analyses (Fe-55, Ni-63, Sr-89 and Sr-90) were determined formonthly composite samples for each type of release (batch or continuous).The leaks into the groundwater were reported in the 2009 Annual RadioactiveEffluent Release Report as abnormal releases. Estimates of the curies of thetritium releases were reported. Doses due to the release of the groundwaterto the discharge canal were included in the report. To ensure that amount ofactivity discharge is accurate and limiting, the activity and doses as a result ofdischarges during 2014 from the groundwater remediation project are includedin this report.9. Estimated Total Error PresentProcedure CY-AA-170-2100, Estimated Errors of Effluent Measurements,provides the methodology to obtain an overall estimate of the error associatedwith radioactive effluents.7 Oyster Creek 2014 Annual Radioactive Effluent Release Report10. Composite Samples and Lower Limit of Detection (LLD)Particulate air samples were composited monthly and analyzed for grossalpha, Sr-89, Sr-90, Fe-55 and Ni-63. Groundwater batch and continuousreleases were composited at least monthly and analyzed for gross alpha,Sr-89, Sr-90, Fe-55 and Ni-63. These composites are submitted to an offsitevendor laboratory for analysis. The ODCM required LLD for liquid andairborne releases are as follows:Liquid:Principal Gamma Emitters (Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Ce-141, Cs-134, Cs-137)Principal Gamma Emitters (Ce-144)Dissolved and Entrained GasesH-3Gross AlphaSr-89 and Sr-90Fe-55 and Ni-63AirbornePrincipal Gamma Emitters (Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138)H-31-1311-133Principal Gamma Emitters (Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141)Principal Gamma Emitters (Mo-99, Ce-144)Gross AlphaSr-89, Sr-90LLD5E-07 pCi/ml5E-06 pCi/ml1 E-05 pCi/ml1 E-05 pCi/ml1 E-07 pCi/ml5E-08 pCi/ml1E-06 pCi/mlLLD1E-04 pCi/ml1 E-06 pCi/ml1 E-12 pCi/ml1 E-1 0 pCi/ml1 E-1 I pCi/ml1E-10 pCi/ml1E-11 pCi/ml1E-1i1 pCi/ml8 Oyster Creek 2014 Annual Radioactive Effluent Release ReportE. Batch Releases:1. LiquThere were no batch releases of liquid effluents during 2014.2. GaseousThere were no batch releases of gaseous effluents during 2014.F. Abnormal Releases:There were no abnormal liquid releases during 2014.There were two abnormal gaseous releases during 2014.During the performance of Work Order C2031047, the side panel of exhaust fan EF-1-17 was removed to access the fan when positive pressure was noted coming fromthe opening. The side panel was immediately replaced and sealed. A tent hadbeen built around the work area but there was no HEPA filter in place to preventany releases from the fan from going to the atmosphere. Note that the exhaust fromEF-1 -17 is normally to the atmosphere but through the monitored stack effluentrelease point. Engineering performed a calculation to determine a release rate thatencompasses the maximum release rate through this opening.The following assumptions were made when calculating Curies released and dose:* Though the panel was off for less than 15 minutes, 15 minutes was used asthe release period.* The activity due to particulates identified from the sample at the time of therelease at the opening was released as a ground level release from theexhaust fan opening at the flow rate calculated by Engineering.Quarter Quarter QuarterUnits 123 Quarter 41 2 3Total Release Ci O.OOeO O.OOeO O.OOeO 1.29e-07Organ Dose mrem O.0Oe0 0.00e0 0.00e0 1.35E-07During the performance of Work Order R2227008, which is to perform an annualinspection of the New Radwaste (NRW) exhaust fan HV-S-54A, two slits werediscovered in the expansion joint. This is one of the exhaust fans for the NewRadwaste Building to the Main Stack. Note that the exhaust from HV-S-54A isnormally to the atmosphere but through the monitored stack effluent release point.Engineering performed a calculation to determine a release rate that encompassesthe maximum release rate for both slits. The activity to inspect the exhaust fan is anannual activity.The following assumptions were made when calculating Curies released and dose:* The exhaust fan has been leaking since the date of the last inspection untilthe time of the repair, 8/20/13 through 7/25/14.9 Oyster Creek 2014 Annual Radioactive Effluent Release Report" All of the activity due to particulates reported from the Main Stack wascoming from the New Radwaste Building and therefore being released as aground level release from the exhaust fan leaks at the flow rate calculatedby Engineering." HV-S-54A was in operation the entire time since the last inspection wasperformed.Quarter Quarter QuarterUnits 123 Quarter 41 2 3Total Release Ci 8.81 E-05 8.90E-05 2.41 E-05 O.OOeOOrgan Dose mrem 4.78E-04 4.63E-04 1.56E-04 0.000eG. Revisions to the ODCM:Revision 6 of the ODCM, CY-OC-170-301 was implemented 12/16/2014. A list ofthe major changes is included below. See the complete copy of CY-OC-170-301Revision 6 attached as part of this report." Meteorological data was updated resulting in changes to X/Q and D/Qvalues. These changes were also used to update the AySi, PySi and DFSidose factors.* Distances to the site boundary were updated.* AOG/NRW CCW Service Water Effluent was removed from Table4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis ProgramH. Radiation Effluent Monitors Out of Service More Than 30 DaysPer ODCM Control 3.3.3.10, "Radioactive Liquid Effluent MonitoringInstrumentation" and 3.3.3.11, Radioactive Gaseous Effluent MonitoringInstrumentation requires:With less than the minimum number of radioactive liquid/gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument toOPERABLE status within 30 days and, if unsuccessful, explain in the nextRadioactive Effluent Release Report why the inoperability was not corrected in atimely manner.The following is a discussion of instrumentation out of service for greater than 30days:1. There was no instrumentation out of service for greater than 30 days.1. Releases from the Independent Spent Fuel Storage Facility:The ISFSI is a closed system and the only exposure would be due to directradiation. This includes iodines, particulates, and noble gases. Based on offsite10 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for20.14. Because it is a sealed unit, no radioactive material was released.J. Program Deviations:1 .The groundwater remediation composite sampler was found with nocomposite collected from August 26, 2014 at 3:47 AM through August 26,2014 at 10:00 AM (approximately 6.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />). The composite sampler isrequired by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Samplingand Analysis Program and is set to obtain a composite sample once per hour.This issue occurred due to Operations starting the remediation pump per thesection of the procedure for by-passing the sample station. This issue wasentered into our Corrective Action Program (CAP) and corrective actions takenhave been documented per process.2. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was notcollected January 1, 2014 through November 13, 2014. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by Revision 5 of CY-OC-170-301, Offsite Dose Calculation Manualfor Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive LiquidWaste Sampling and Analysis Program and was required to be sampledweekly for principal gamma emitters and 1-131. This requirement wasremoved in Revision 6 of CY-OC-1 70-301. This issue occurred from theinclusion of this requirement in revision 4 of the ODCM due to amisunderstanding of the system flow path. It was believed that all servicewater exited the site from the same release point which was evident by thefact that the change paperwork included in the description of this change asbeing consistent with the practices at Oyster Creek and there was nomodification to the sampling schedule. The NRW and AOG Closed CoolingWater systems were reviewed as part of NRC Bulletin IE 80-10. At that timeNRW Closed Cooling Water system was determined to be a potentiallycontaminated system and was added to the sampling program for NRCBulletin IE 80-10. The sampling program for IE 80-10 requires all potentiallycontaminated systems to be sampled quarterly for gamma emitters. AOGClosed Cooling Water system was also reviewed but determined to not be apotentially contaminated system. Even though AOG was found not to be apotentially contaminated system, sampling is still performed quarterly forgamma emitters. The potential pathway for a release from NRW/AOG ServiceWater Effluent would be from a heat exchanger leak from the NRW ClosedCooling Water system into the Service Water side of the heat exchanger. Thesystem is designed to maintain the Service Water side of the heat exchangerat a higher pressure than the Closed Cooling Water side so that if any leakswould develop in the heat exchanger it would be Service Water leaking intothe Closed Cooling Water side. A review was performed for both NRW andAOG quarterly Closed Cooling Water samples for the time that the requiredsamples were not obtained and all samples were less than MDA for gammaemitters for that entire time period.11 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix AEffluent and Waste Disposal Summary12 Oyster Creek 2014 Annual Radioactive Effluent Release ReportLIST OF TABLESPAGETable A -1 Gaseous Effluents -Summary of All Releases 14Table A -2 Gaseous Effluents Release Point: Elevated Release 14Table A -3 Gaseous Effluents Release Point: Ground Level Releases 16Table A -4 Liquid Effluents -Summary of All Releases 17Table A -5 Liquid Release Point: Groundwater Remediation 1813 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-I: Gaseous Effluents- Summary Of All ReleasesPeriod: January 1, 2014 through December 31, 2014Unit: Oyster Creek1 1 1 Esto talA. Fission & Activation Gases Units Quarter II Quarter 21 Quarter3 Quarter 4 Error%I1. Total ReleaseCi1.95E+012.07E+011.45E+017.76E+00 I 25.00% I2. Average Release Rate for Periodfor Period I pCi/sec I 1.16E-03 I 8.05E-04 I 1.63E-03 I 6.32E-04* ODCM Limit is for combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.14 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-2: Gaseous Effluents Release Point: Elevated ReleasePeriod: January 1, 2014 through December 31, 2014Unit: Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gases Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci 1.90E+00 1.51 E+00 8.55E-01 4.38E-01 <LLD <LLD <LLD <LLDKr-87 Ci 3.24E+00 1.08E+00 2.39E+00 <LLD <LLD <LLD <LLD <LLDKr-88 Ci 2.13E+00 2.26E+00 5.80E-01 1.98E+00 <LLD <LLD <LLD <LLDXe-133 Ci 1.45E+00 1.70E+00 1.06E+00 5.25E-01 <LLD <LLD <LLD <LLDXe-135 Ci 5.96E+00 1.11E+01 8.71E+00 4.82E+00 <LLD <LLD <LLD <LLDXe-i 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-i 37 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-138 Ci 4.83E+00 1.71E+00 <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 1.95E+01 1.94E+01 1.36E+01 7.76E+00 <LLD <LLD <LLD <LLD2. lodines1-131 Ci 3.88E-04 6.18E-04 6,19E-04 7.03E-05 <LLD <LLD <LLD <LLD1-133 Ci 8.14E-04 1.76E-03 9.50E-04 5.20E-05 <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 1.20E-03 2.38E-03 1.57E-03 1.22E-04 <LLD <LLD <LLD <LLD3. ParticulatesSr-89 Ci 6.68E-04 1.57E-04 2.93E-04 6.45E-05 <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-1 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-137 Ci 1.92E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLDBa-140 Ci 1.13E-03 4.17E-04 7.12E-04 3.70E-04 <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci <LLD <LLD 7.77E-05 2.09E-05 <LLD <LLD <LLD <LLDMn-54 Ci 5.40E-04 4.16E-04 1.14E-03 3.98E-04 <LLD <LLD <LLD <LLDCo-58 Ci 2.41E-03 1.97E-03 3.96E-03 2.OOE-03 <LLD <LLD <LLD <LLDCo-60 Ci 3.04E-03 2.30E-03 5.01 E-03 1.88E-03 <LLD <LLD <LLD <LLDNi-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 2.46E-04 2.25E-04 3.52E-04 5.20E-05 <LLD <LLD <LLD <LLDAg-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 8.40E-04 7.41E-04 1.38E-03 2.36E-04 <LLD <LLD <LLD <LLDTotal for Period Ci 8.89E-03 6.23E-03 1.29E-02 5.02E-03 <LLD <LLD <LLD <LLD4. TritiumH-3 Ci 6.17E+00 9 80E+00 7449E+O0 4.40E+00 <LLD <LLD <LLD <LLD5. Gross AlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14 C-14 Ci 2.32E+00 2.33E+00 1.76E+00 1.98E--+00 <LLD <LLD <LLD <LLD15 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-3: Gaseous Effluent Release Point: Ground Level ReleasesPeriod: January 1, 2014 through December 31, 2014Unit: Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gases Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-135 Ci <LLD 1.34E+00 9.26E-01 <LLD <LLD <LLD <LLD <LLDXe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 38 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci <LLD 1.34E+00 9.26E-01 <LLD <LLD <LLD <LLD <LLD2. lodines j1-131 Ci <LLD 9.91E-07 1.30E-05 1.52E-06 <LLD <LLD <LLD <LLD1-133 Ci <LLD 4.86E-06 1.94E-06 <LLD <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal fOr Period Ci <LLD 5.85E-06 1.49E-05 1.52E-06 <LLD <LLD <LLD <LLD3. ParticulatesSr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-i 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-i 37 Ci 8.29E-07 8.38E-07 2.27E-07 <LLD <LLD <LLD <LLD <LLDBa-140 Ci 1.19E-05 1.20E-05 3.26E-06 <LLD <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci 6.72E-06 6.79E-06; 1.84E-06 <LLD <LLD <LLD <LLD <LLDMn-54 Ci 8.03E-06 8.12E-06 2.20E-06 <LLD <LLD <LLD <LLD <LLDCo-58 Ci 2.30E-05 2.36E-05 6.65E-06 7.76E-07 <LLD <LLD <LLD <LLDCo-60 Ci 2.81E-05 3.78E-05 1.94E-05 2.18E-06 <LLD <LLD <LLD <LLDNi-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 2.21E-06 2.24E-06 6.06E-07 <LLD <LLD <LLD <LLD <LLDAg-11Om Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 8.71 E-06 8.81 E-06 2.38E-06 <LLD <LLD <LLD <LLD <LLDAm-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 8.95E-05 1.OOE-04 3.66E-05 2.96E-06 <LLD <LLD <LLD <LLD4. Tritium PXH-3 Ci 2.66E-01 2.03E-01 4.40E-01 1.70E-01 <LLD <LLD <LLD <LLD5. GrossAlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14C-14 Ci 7.20E-02 7.21E-02 5.44E-02 6.13E-02 <LLD <LLD <LLD <LLD16 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-4: Liquid Effluents -Summary Of All ReleasesPeriod: January 1, 2014 through December 31, 2014 Unit: Oyster CreekEst. TotalA. Fission & Activation ProductsI Units IQuarter I Quarter 2 Quarter 3 Quarter 4Error %I1. iota! Release not includingtritium, gases, alphaCi<LLD<LLD<LLD<LLD 12 5. v/oI2. Average Diluted concentrationduring periodI Units IQuarter I Quarter 21 Quarter 3 Quarter 41 Eror ;I Ci I <LLD <LLD I <LLD <LLD I 25.00%I Liters I 1.04E+1114.85E+1 o 4.09E+112.19E+117 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable A-5: Liquid Release Point: Groundwater RemediationPeriod: January 1, 2014 through December 31, 2014Unit: Oyster CreekNuclidesReleased Continuous Mode Batch ModeFission & UnitActivation Quarter Quarter Quarter Quarter Quarter Quarter Quarter QuarterProducts 1 2 3 4 1 2 3 4Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-I 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-I 37 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCo-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCo-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDNi-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDNb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDBa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAg-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDA--133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 35 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDH-3 Ci 1,59E-02 I6.95E-02 15.85E-02 13.05E-021 <LLD I<LLD I<LLD I<LLDII,Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LD LD18 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix BSolid Waste and Irradiated Fuel Shipments19 Oyster Creek 2014 Annual Radioactive Effluent Release ReportA. Solid waste shipped offsite for burial or disposal (not irradiated fuel)1. Type of wasteTypes of Waste Total Total Period Est. TotalQuantity Activity Error%(mI) (Ci)a. Spent resins,filter sludges, evaporator bottom, etc 4.71 E+01 1.55E+02 2014 2.50E+01b. Dry compressible waste, contaminated equip, etc 5.61E+02 1.09E+0 2014 2.50E+01c. Irradiated components, control rods,etc 1.66E-01 4.24E+03 2014 2.50E+01d. Other 1.10E+02 5.06E-01 2014 2.50E+0120 Oyster Creek 2014 Annual Radioactive Effluent Release Report1. Estimate of Major Nuclide Composition (By Waste Type)Category A -Spent Resin, Filters, Sludges, Evaporator Bottoms, etc.Isotope Ij Waste Class AI Waste Class BI Waste Class CI Curies I Percent ICuries I PercentI (-iiripn I Pprri-Ant IH-3 5.13E-02 8.87E-02C-14 4.83E-02 8.35E-02Cr-51P-32Mn-54 3.05E+00 5.27E+00Fe-55 3.05E+01 5.27E+01Fe-59Co-57 1.78E-03 3.08E-03Co-58 1.46E-02 2.52E-02Co-60Ni-59Ni-63Zn-65Sr-89Sr-90Nb-95Tc-99Ag-11 OinSb-125Cs-1 34Cs-137Ce-144Pu-238Pu-239Pu-240Pu-241Am-241Cm-242Cm-243Cm-244Totals 5.78E+01 I .OOE+02I 9.72E+01 I .OOE+02 0 .OOE+00 10.00E+0Note: Grey fields are where results were not reported in the NRC Regulatory Guide 1.21 Report21 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCategory B -Dry Compressible Waste, Contaminated Equipment, etc.Isotope Waste Class ACuries PercentC-14 7.28E-06 6.70E-04P-32 6.1OE-05 5.61E-03Mn-54 3.67E-02 3.38E+00Fe-55 7.99E-01 7.35E+01Co-57 9.24E-05 8.50E-03Co-58 1.80E-03 1.66E-01Co-60 1.90E-01 1.75E+01Ni-63 6.93E-03 6.38E-01Zn-65 1.82E-02 1.67E+00Tc-99 Sb-1125 Sr-89 1.50E-04 1.38E-02Sr-90 1.89E-04 1.74E-02Cs-1 37 3.29E-02 3.03E+00Ce-144 5.00E-04 4.60E-02Pu-238 6.22E-06 5.72E-04Pu-239 1.90E-06 1.75E-04Pu-241 2.19E-04 2.02E-02Amn-241 7.52E-06 6.92E-04Cm-242 1.24E-06 1. 14E-04Cm-243 2.43E-06 2.24E-04Cm-244 2.43E-06 2.24E-04Totals 1.09E+00 1.OOE+0222 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCategory C -Irradiated components, control rods, etc.Isotope Waste Class CCuries PercentAbundanceH-3 1.06E-02 2.50E-04C-14 1.16E-01 2.73E-03Cr-51 6.22E-02 1.47E-03Mn-54 1.83E+01 4.31E-01Fe-55 4.77E+02 1.12E+01Fe-59 3.27E-02 7.71E-04Co-58 1.19E+00 2.81E-02Co-60 2.75E+03 6.48E+01Ni-59 2.92E-01 6.88E-03Ni-63 3.62E+01 8.53E-01Zn-65 2.83E-01 6.67E-03Sr-90 2.79E-05 6.58E-07Zr-95 1.37E+02 3.23E+00Nb-94 2.60E-03 6.13E-05Mo-93 2.91 E-05 6.86E-07Tc-99 3.32E-05 7.83E-07Sb-125 8.16E+02 1.92E+011-129 1.70E-09 4.01E-11Cs-137 4.52E-05 1.07E-06Ce-144 1.31E-07 3.09E-09Hf-1 81 9.68E-01 2.28E-02Ta-182 4.35E+00 1.03E-01U-235 3.97E-1 1 9.36E-1 3Np-237 9.79E-10 2.31 E-11Pu-238 1.35E-05 3.18E-07Totals 4.24E+03 1.OOE+0223 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCategory D -Other -Scrap MetalIsotope Waste Class ACuries PercentH-3 4.70E-01 9.28E+01C-14 2.42E-07 4.78E-05P-32 1.82E-06 3.59E-04Mn-54 1.23E-03 2.43E-01Fe-55 2.66E-02 5.25E+00Co-57 3.27E-06 6.46E-04Co-58 6.11E-05 1.21E-02Co-60 6.34E-03 1.25E+00Ni-63 2.30E-04 4.54E-02Zn-65 6.11E-04 1.21E-01Sr-85 5.73E-13 1.13E-10Sr-89 5.08E-06 1.OOE-03Sr-90 6.29E-06 1.24E-03Y-88 9.40E-08 1.86E-05Cd-109 8.87E-07 1.75E-04Sn-113 2.62E-08 5.17E-06Cs-137 1.33E-03 2.63E-01Ba-133 1.15E-05 2.27E-03Ce-1 39 3.82E-08 7.54E-06Ce-144 1.67E-05 3.30E-03Hg-203 8.55E-1 1 1.69E-08Pu-238 2.07E-07 4.09E-05Pu-239 6.30E-08 1.24E-05Pu-241 7.26E-06 1.43E-03Am-241 9.89E-06 1.95E-03Cm-242 4.16E-08 8.21E-06Cm-243 8.07E-08 1.59E-05Cm-244 8.06E-08 1.59E-05Totals 5.06E-01 1.OOE+02Note: Grey fields are where results were not reported in the NRC Regulatory Guide 1.21 Report2. Solid Waste (Disposition)Number of Shipments Mode of Transportation Destination9 Hittman Transport Co. Barnwell Disposal Facility16 Hittman Transport Co. Energy Solutions Services, Inc.B. Irradiated Fuel Shipments (disposition).There were no irradiated fuel shipments.24 Oyster Creek 2014 Annual Radioactive Effluent Release ReportC. Changes to the Process Control ProgramRevision 10 of the Process Control Program, RW-AA-1 00 was implemented August 26,2014. See the complete copy of RW-AA-1 00 Revision 10 attached as part of this report.25 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix CRadiological Impact to Man26 Oyster Creek 2014 Annual Radioactive Effluent Release ReportPer ODCM Administrative Control 6.2, an assessment of radiation doses to the likely mostexposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuelcycle sources (including doses from primary effluent pathways and direct radiation) for theprevious calendar year must be made to show conformance with 40 CFR Part 190,Environmental Radiation Protection Standards for Nuclear Power Operation. For purposes ofthis calculation the following assumptions were made:Gaseous" Nearest member of the public was W sector at 483 meters.* Actual 2014 meteorology and measured gaseous effluent releases were used.* All significant pathways were assumed to be present.* Occupancy factor was considered 22.8% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/week for 50 weeks).Ligqui* Doses calculated in the discharge canal at the Route 9 Bridge.* Fish, shellfish and shoreline pathways doses calculated.40 CFR Part 190 Compliance" Dosimetry measurements (minus average of control stations) measured direct radiation forthe nearest member of the public. The nearest member of the public for direct radiation isconsidered an individual that works in the warehouse west of the site. As a worker, theindividual is assumed to work 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per year at this location. Note that for thewarehouse worker total dose calculations the full year (8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />) values for Iodine,Particulate, Carbon-14, Tritium and Liquid are used.* Nearest resident was at SE sector at 937 meters.* The highest calculated dose for gamma air dose and liquid total body were summed fortotal body dose.* The highest calculated dose for gamma air dose, child bone and liquid organ were summedfor organ dose.* The limits for Kr-85, 1-129, Pu-239 and other alpha-emitting transuranic radionuclides withhalf-lives greater than one year were not exceeded.The ODCM does not require total body doses to the population and average doses toindividuals in the population from gaseous effluents to a distance of 50 miles from the site to becalculated.27 Oyster Creek 2014 Annual Radioactive Effluent Release ReportA summary of gaseous and liquid radiation doses to most likely exposed MEMBER OF THEPUBLIC was as follows:Location % ofApplicable Estimated Age Distance Direction ApplicableEffluent Organ Dose Group (meters) (toward) Limit Limit UnitGamma -Noble Gas Air Dose 1.62E-02 All 405 E 1.62E-01 10 mradBeta -AirNoble Gas Dose 1.91 E-02 All 406 E 9.55E-02 20 mradTotal BodyNoble Gas (Gamma) 2.18E-03 All 972 ESE 4.36E-02 5 mremNoble Gas Skin (Beta) 4.86E-03 All 972 ESE 3.24E-02 15 mremIodine,Particulate, Bone 4.78E-01 Child 937 SE 3.19E+00 15 mremCarbon-14 &TritiumLiquid Total body 8.28E-07 All South Route 9 2.76E-05 3 mremLiquid Organ 8.28E-07E All Bridge 8.28E-06 10 mremDirect Radiation Total Body 5.09E+00 All 483 W 2.04E+01 25 mremDirect Radiation Total Body <LLD All 937 SE <LLD 25 mrem40 CFR Part 190 ComplianceWarehouse WorkerTotal Dose Total Body 5.09E+00 All 483 W 2.04E+01 25 mremnTotal Dose Bone 5.57E+00 All 483 W 2.23E+01 25 mremnTotal Dose Thyroid 5.09E+00 All 483 W 6.79E+00 75 mremnNearest ResidentTotal Dose Total Body 1.62E-02 All 937 SE 6.48E-02 25 mremTotal Dose Bone 4.94E-01 All 937 SE 1.98E+00 25 mremTotal Dose Thyroid 1.52h-O All 937 SE Z.1_E-02 75 mrem28 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix DMeteorological Data29 Oyster Creek 2014 Annual Radioactive Effluent Release ReportLIST OF METEOROLOGICAL DATA TABLESPAGETable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 31the Oyster Creek Generating Station, January -March, 2014Table D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 38the Oyster Creek Generating Station, January -March, 2014Table D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 45the Oyster Creek Generating Station, April -June, 2014Table D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 52the Oyster Creek Generating Station, April -June, 2014Table D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 59the Oyster Creek Generating Station, July -September, 2014Table D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 66the Oyster Creek Generating Station, July -September, 2014Table D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 73the Oyster Creek Generating Station, October- December, 2014Table D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 80the Oyster Creek Generating Station, October- December, 2014Table D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 87the Oyster Creek Generating Station, January -December, 2014Table D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 95the Oyster Creek Generating Station, January -December, 201430 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total00117005473692236281700002000055048201000544115172810512131019386647250Total0 83 15500 292Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:431 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7000000000000000007133414102244108408-12 13-18 19-24 > 240 0 0 00 0 0 02 0 0 05 0 0 00 0 0 00 0 0 01 0 0 02 0 0 05 2 0 04 1 0 00 0 0 06 0 0 05 5 0 04 3 0 07 2 0 00 0 0 00 0 0 0Total715841537721014171740Total0 58 41 1300 112Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:432 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 240 0 0 0 01 0 0 0 03 0 0 0 02 0 0 0 01 0 0 0 02 0 0 0 04 0 0 0 04 0 0 0 01 1 0 0 01 2 0 0 02 0 0 0 02 0 0 0 01 3 1 0 02 6 2 0 04 2 4 0 03 1 0 0 00 0 0 0 0Total0132124023225101040Total0 29 15'700 51Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:433 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-743832211112455450213233192557767131823313308-12 13-18 19-24 > 2417 0 0 033 2 0 016 4 0 013 0 0 01 0 0 00 0 0 03 0 0 01 0 0 06 0 0 012 15 0 07 1 0 05 0 0 013 5 0 021 19 0 025 5 0 040 0 0 00 0 0 0Total42706135579914341722416865780Total51 2622135100 577Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:434 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal1-3 4-7 8-12 13-18 19-24 > 243 14 2 0 0 04 13 0 0 0 03 27 2 1 0 08 10 5 0 0 05 2 0 0 0 02 1 0 0 0 00 8 1 0 0 02 6 9 1 0 05 15 11 12 0 05 16 40 11 0 010 34 6 0 0 010 28 3 0 0 09 34 3 1 0 013 49 27 1 0 013 46 22 0 0 011 17 13 0 0 00 0 0 0 0 0Total1917332373918437250414790814101033201442700 594Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:435 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -I Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Stable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection1-3 4-7N 8NNE 2NE 5ENE 2E 1ESE 2SE 2SSE 0S 2SSW 2SW 6WSW 13W 28WNW 11NW 7NNW 7Variable 01101003116614161315508-12 13-18 19-24 > 24o 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 0Total9353,1251381227442422120Total98 830000 181Hours of calm inHours of missingthis stability class:1wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:436 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal1-3 4-7 8-12 13-18 19-24 > 244 0 0 0 0 04 0 0 0 0 06 0 0 0 0 03 0 0 0 0 03 0 0 0 0 04 0 0 0 0 03 2 0 0 0 04 0 0 0 0 05 0 0 0 0 09 0 0 0 0 027 1 0 0 0 072 10 0 0 0 076 18 0 0 0 038 3 0 0 0 031 15 0 0 0 02 0 0 0 0 00 0 0 0 0 0Total4463345459288294414620291490000 340Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in8stability class: 0all stability classes:437 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal1-3 4-70000000000000000000000000000000000008-12 13-18 19-24 > 240 0 0 00 0 0 00 2 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 10 1 1 10 2 2 41 2 0 30 0 1 00 0 0 0Total002000000001386101749 21Hours of calm in this stability class:0Hours of missing wind measurements in this stabiHours of missing stability measurements in all slity class: 0tability classes:438 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph).WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7000000000000000008-12 13-18 19-24 > 241 0 0 01 0 0 00 4 3 00 0 1 10 0 0 00 0 0 01 0 0 00 1 0 00 1 0 00 0 2 01 1 0 00 3 2 20 1 2 42 9 3 41 10 4 52 4 3 00 0 0 0Total1072001112277182090Total008 34 20 16 78Hours of calm in this stability class: 0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:439 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotalWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total00300003121510787011890253164102132291500 10 45 47 30 15 147Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:440 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-1819-24 > 24 Total5381671020133413100175217426412513111710261801648352750538198142028283101924122411100228811263427010510000121101334321205880816016101372367313665102133990Total2 67 178218121 881Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:441 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total41151000402159172340361801006001333223141338385000720021012204303400817222344141827734341448984290Total3 30 69 19417767 540Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:442 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 240 2 8 8 10 1 1 0 02 1 2 0 02 2 5 0 01 4 0 0 01 3 2 0 02 3 3 1 02 6 0 1 35 4 2 2 01 5 1 1 14 2 6 5 51 4 9 2 51 3 16 8 30 7 21 23 20 6 18 23 00 4 10 9 10 0 0 0 0Total1926968101214112221315347240Total8 22 57 104 83 21 295Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:443 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -March, 2014Oyster Creek AlphaPeriod of Record: January -March 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total15114654111717101416101820140Total20 40 48 44 29 11 192Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in2stability class: 0all stability classes: 444 Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaTable D -3Period of Record: April -June 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-78-12 13-18 19-24 > 24 Total7313202428203455693145041833919423941321113175018000000001136000119001142153344762435816717223173230Total1 16931020 522Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:I45 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENE0100000027600 ii0 13E0155ESESESSESSSWSWWSWWWNW0 140000100056233530300233104437100050 1660 ii0 20090 110000054997NWNNWVariableTotal40 1120000000 130 1200003 97 32 140 146Hours of calm in thisHours of missing windstability class:measurements in this0stability class:all stability cl0asses:Hours of missing stability measurements in146 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENE1-3020014-7 8-12 13-18 19-24> 24 TotalEESESE000SSESSSWSWWSW0000000000000000000007832353241111W0WNWNWNNWVariable10105110Total5 28 11400 480es:Hours ofHours ofHours ofcalm inmissingmissingthis stability class: 0wind measurements in this stabilstability measurements in all stity class:ability class47 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3245725012001333404-7104483822920212887381016200qind Speed (in mph)8-12 13-181012335421515804510780000183229419000131019-24 > 240 00 00 00 00 00 00 00 04 01 00 00 00 00 00 00 00 0Total138659632202446533678162429330Total42 272129625 0 510Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in148 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total771155491419126613111651321010761016412616331920227000272114620122482010923221411203767672341343546141Total151 24862 1300 474Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:149 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3. 4-722232049971271410136000101000105176257008-12 13-18 19-24 > 240 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 0Total22333049107172420352060Total102630000 165Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:150 Table D -3Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotalWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total201210013111348945634150281010000000018496103021121001314569865401600 311Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in7stability class: 0all stability classes:151 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-70000000000000000000000000000000000Wind Speed (in mph)8-12 13-18 19-24 > 240 0 0 00 0 0 00 0 5 03 6 1 03 0 0 02 0 0 02 1 0 00 2 0 00 13 4 00 0 0 00 0 0 02 1 0 00 2 0 00 2 3 52 15 3 80 5 0 00 0 0 0Total005103232170032102850Total00 14 47 16 13 90Hours of calm in thisHours of missing windstability class:0measurements in this stalHours of missing stability measurements in allbility class: 0stability classes:152 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total011119131642122225204024014611303261860424249182010161126593190Total04 73 70 258 180Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:I53 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Unstable -380Ft-33Ft.Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total3059127111263415153053920131314201510561292090Total1 21 87 53 138 183Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in154 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-78-12111100210100000103 116 816 3311 2515 1415 1111 1910 415 374 242 144 35 54 105 177 100 013-18712137974929250788911019-24002301201637041191490> 240023062097320208450Total2216751345635377681931620293949430Total9 123282192108107821Hours of calm in this stability class:Hours of missingHours of missingwind measurements in thisstability measurements in0stability class: 0all stability classes:155 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 242 3 6 0 01 6 2 0 06 4 4 1 02 4 7 2 03 10 4 0 12 5 4 1 21 16 1 2 20 10 5 8 73 13 23 3 33 17 34 18 44 10 11 12 01 1 10 14 21 3 16 8 13 6 12 17 13 6 14 18 23 6 10 4 00 0 0 0 0Total14915171814233045763728293943240Total7 38 12016310825 461Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:156 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-700000011000200010200000102211020108-12 13-18 19-24 > 244 9 8 00 1 0 05 1 0 03 0 0 00 0 0 00 0 0 01 0 0 01 0 0 02 5 4 04 9 2 04 9 3 03 6 10 115 8 5 04 6 9 04 11 26 01 7 17 10 0 0 0Total23163003213171733182141280Total5 12 41 72 84 12 226Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in157 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, April -June, 2014Oyster Creek AlphaPeriod of Record: April -June 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in.mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-34-7 8-12 13-18 19-24 > 24 Total----- -----11640000001055468140----- ----- -----130000000048634150201812251935191126121429360Total10 33 56 73 446 222Hours of calm in this stability class:Hours of missingHours of missingwind measurements in thisstability measurements in0stability class: 0all stability classes:158 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total5516ý3719191252811345135000285224183612191941330000000001720000000195518452421362355223041392680Total0 16915600 344Hours of calm in this stability class: 0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:059 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-700100000010000000476126774437123971308-12 13-18 19-24 > 241 0 0 01 0 0 04 0 0 03 0 0 00 0 0 00 0 0 09 0 0 02 0 0 012 1 0 06 0 0 04 0 0 00 0 0 03 0 0 02 0 0 02 0 0 01 0 0 0o 0 0 0Total57111567166171011126119140Total2 ill49I00 163Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes:060 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total001300311130101100339922931257547450Total6 58 25000 89Hours of calm in this stability class:0Hours of missing wind measurements in this stabiliHours of missing stability measurements in all staty class:bility cl0asses:061 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)4-7 8-12 13-181-361227289111617181113119121719005202370731617443243019-24 > 240 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0Total102251551716252035311921141624260Total43 236118500 402Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:062 Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Table D -5Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENE8 113430615 334 18 17E7278ESESESSESSSWSWWSWWWNWNW4 199151013815 590000003000000000030000000000000000000 2219 51 180718 3622 2110 127 219 1910 250 540 390 230 110 310 220 740 880 580 450 220 280 300 370 00 59142002NNWVariableTotal016603522070Hours of calm in this stability class:Hours of missingHours of missingwind measurements in thisstability measurements in2stability class: 0all stability classes: 063 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3520112266104-7 8-12 13-18 19-24 > 24 Total0011100033183000000000000000000000000000000000000000000000000000000000000005212222691523180 130 160 310 210 270 160 1317 10137036000Total1284000 168Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in1stability class: 0all stability classes:064 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNE.NEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total11010113117157514964622214141301012311715831506767251Total230000 437Hours of calm in this stability class:11Hours of missingHours of missingwind measurements in this stability class: 0stability measurements in all stability classes:065 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total000000001300000000Total000670 13Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:066 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total002105252103000010005000021151140061000710525417816410620Total00 31 45 110 87Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:067 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24N 0 0 4 1 0 0NNE 0 2 4 0 0 0NE 0 0 16 5 0 0ENE 0 4 16 8 0 0E 0 1 8 0 0 0ESE 0 3 9 0 0 0SE 0 1 15 4 0 0SSE 0 0 9 4 0 0S 0 0 2 9 3 0SSW 0 2 7 6 2 0SW 0 0 10 3 0 0WSW 0 0 1 1 0 0W 0 0 2 7 2 0WNW 0 0 3 5 0 0NW 0 0 13 7 1 0NNW 0 2 4 2 0 0Variable 0 0 0 0 0 0Total562128912201314171321182180Total0 15 1236280 208Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:068 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8-12 13-1819-24 > 24 Total5171799111345211139497071734221818202021159161122101806833322429930352081011917064222214011426142040000715813002000002024471141005134703460804241323733450Total9 145278263ill 38 844Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:069 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable48345Ii8128211699433092141751968411764121402012100011018102111090771613132213161922371037941192331280Total10 50 1282219 495Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in070 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Moderately Stable -38OFt-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableWind Speed (in mph)1-3 4-7 8:-12 13-18 19-24 > 24 Total10510021071010158511507001000010411566170201161154992019254021.1326280Total13 38 67 90 581 267Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in2stability class: 0all stability classes:071 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -6Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, July -September, 2014Oyster Creek AlphaPeriod of Record: July -September 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionWind Speed (in mph).8-12 13-18 19-24 > 24 Total1-3 4-7N1NNENEENEEESESESSESSSWSWWSW0113001030002110195443154425 17273003866916220002580 330 130 190 100009343 10 14WWNWNWNNWVariable5150094796311600 140 120 180 223 361 250 170 270 297 134 180000Total14 56 83 104304 291Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in1stability class:all stability cl0asses:072 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWW1-300000000000004-7 8-12 13-18 19-24 > 24 Total00000000000002411247889 129 113 264 330 210 220 320 42WNWNWNNW0004030350015000000070VariableTotal00 43 1030 161Hours of calm inHours of missingHours of missingthis stability class:wind measurements in thisstability measurements in0stability class: 0all stability classes:573 Table D -7Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionNNNENEENEEESESESSESWind Speed (in mph)4-7 8-12 13-18 19-24 > 24 Total1-30000000000000000000000000052301394SSWSWWSWWWNW85647 144 110 110 210 16NWNNWVariableTotal00040101002000000500 50 51stability class:measurements in this0 103Hours of calm in thisHours of missing wind0stability class: 0all stability classes:Hours of missing stability measurements in574 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total812100040217415730Total1 23 27400 55Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in575 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total262616592101257182820314413030261961031913949113248150615738121031537262524393570102350Total49 2722452300 589Hours of calm in this stability class:1Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:576 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal156137115702518171520160148218207121024154841464984353204431002100311191515152022160140461435152318423467616571119776500 734Hours of calm inHours of missingthis stability class:wind measurements in this2stability class: 0all stability classes:Hours of missing stability measurements in577 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total12231203144517201817901100000011014122613620861333120315141929463123110Total1180000 204Hours of calm inHours of missingthis stability class:wind measurements in this3stability class: 0all stability classes:Hours of missing stability measurements in578 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7311120047516641333721700000000011341585308-12 13-18 19-24 > 240 0 0 0o o 0 0o 0 0 0o 0 0 0o 0 0 00 0 0 0o 0 o 0o 0 o 0o o 0 0o 0 0 00 0 0 0o o 0 0o 0 0 0o 0 0 0o 0 0 00 0 0 0Total31120048619681484526100Total302400000 342Hours of calm inHours of missingthis stability class:9wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:579 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7N 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0s 0SSW 0SW 0WSW 0W 0WNW 0NW 0NNW 0Variable 00000000000000000008-12 13-18 19-24 > 24o 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 0 00 0 1 00 0 0 00 0 0 0Total00000000000000100Total000101Hours of calm in this stability class:0Hours of missing wind measurements in this stability class:0Hours of missing stability measurements in all stability classes:580 Table D -8Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7 8-12 13-18 19-24 > 24 TotalNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotal0001000002026716003 16 105 34Hours of calm in this stability class:0Hours of missing wind measurements in this stability class: 0Hours of missing stability measurements in all stability classes: 581 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total00000012424109109000000000150001151020004220139371515312360Total02 28 51 346 121Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in582 Oyster Creek 2014 Annual Radioactive Effluent Release ReportWind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Table D -8Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirection 1-3 4-7N 0 5NNE 1 6NE 1 5ENE 1 2E 0 4ESE 1 2SE 0 4SSE 0 2S 1 1SSW 1 7SW 0 4WSW 1 4W 0 4WNW 0 4NW 0 5NNW 0 3Variable 0 08-12 13-18 19-24 > 2426 11 31 1623 15 18 106 14 16 31 1 3 34 3 0 03 2 0 011 2 2 06 15 21 32 8 5 27 12 11 617 19 6 19 25 7 025 23 14 219 29 43 1615 48 60 921 2 12 140 0 0 0Total89734511819471944474668ill137520Total7 62 19522924985 827Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in0stability class: 0all stability classes:583 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total221013241549445127680191316101081252516172838321401026210161938381922553950001000231710116300463236231051636387769456810781310Total11 41 11625426335 720Hours of calm in this stability class:Hours of missing wind measurements in thisHours of missing stability measurements in1stability class: 0all stability classes:584 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October -December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in mph)WindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariable1-3 4-7 8-12 13-18 19-24 > 24 Total1953110412525121412706000000113201016311910338452964102525355642120Total2 16 52 93 10816 287Hours of calm in this stability class:0Hours of missingHours of missingwind measurements in this stability class: 0stability measurements in all stability classes:585 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, October- December, 2014Oyster Creek AlphaPeriod of Record: October -December 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWVariableTotalWind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total1100000102138561015100130000201440471840216300323107131691326392309 29 34 81 48 11 212Hours of calm inHours of missingthis stability class:wind measurements in this0stability class: 0all stability classes:Hours of missing stability measurements in586 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -All Stabilities -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNW<0.5033211215214503440.5- 1.1-1 1.545 3420 2928 4923 2413 209 1813 2226 3238 4640 5567 76142 228234 331135 16388 16346 80Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total39 91 4440 77 4985 162 10436 148 14025 76 4824 76 4829 127 10831 87 9364 133 9444 146 11765 160 88139 157 83147 160 93120 234 144140 180 20395 139 8353 430 946 480 2212 103 336 665 2199 8363 6421 531 644 25104 65116 4969 18003182031134602216483610 3130 2570 4830 4920 2070 1830 3450 3710 5970 5940 4880 7930 10500 10160 9790 5350 8703Tot41 967 1370 1123 2153 1539872 394 236Hours of Calm ........ 45Hours of Variable Direction 2Hours of Valid Data .... 8750Hours of Missing Data ..10Hours in Period ...... .. 876087 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSector <0.50N 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0Sw 0WSW 0W 0WNW 0NW 0NNW 00.5- 1.1-1 1.50 00 00 00 00 10 00 00 00 00 00 00 00 00 00 00 0Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total0 13 6 11 8 0 14 21 19 112 41 50 212 31 27 01 39 36 10 23 67 200 4 38 262 1 18 440 13 17 80 16 24 120 14 23 191 16 42 201 8 43 350 26 71 490 15 29 150015000746103382721400000000218028242102010561196177110751325955619513818863Tot0 0 1 14 289 510 283135 84 30 1319Hours of Calm 0....... 0Hours of Variable Direction 0Hours of Valid Data .... 1319Hours of Missing Data ..10Hours in Period ...... .. 876088 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Unstable -15OFt-33Ft Delta-T (F)Winds Measured at 33 FeetWiiDi]SecNNNNEENEEESESESSESSSWSWWSWWWNWNWNNWTot-idrection 0.5- 1.1- 1ctor <0.50 1 1.50 0 00 0 10 0 10 0 00 0 00 0 10 0 00 0 00 0 00 0 00 0 00 0 10 0 00 0 00 0 00 0 00 0 4Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... .......6-2444343101334623449Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 6912161991227664910921182721400524207931712891610111124027006713512915142000100111040214706.1- 8.1-8 100 00 00 04 00 00 00 01 01 03 01 00 05 03 02 00 020 0>10.000000000000000000Total19173043161746224327233540565535119 87 310 52410876089 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Unstable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSector <0.50N 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0SW 00.5- 1.1-1 1.50 00 30 00 00 10 00 10 00 10 0o IWind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total2 42 18 82 91 41 31 100 31 31 23 64 41 46 102 52 712717176617142213111514372213WSWWWNWNWNNWTot0000000000010106377102531036100124100000000000 10 37 83 49 35 19 10 00 243Hours of Calm ..... ........ 0Hours of Variable Direction 0Hours of Valid Data .... 243Hours of Missing Data ..10Hours in Period ...... .. 876090 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Neutral -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWirDiiSecNNNNEENEEESESESSESSSWSWWSWWWNWNWNNWTotidrection 0.5- 1.1- 1-tor <0.50 1 1.51 5 72 0 120 2 180 5 70 1 20 3 90 0 40 1 40 3 40 1 40 2 40 2 100 1 120 6 80 2 120 2 153 36 132Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ...........6-2Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 612 3921 4128 7616 4912 228 1511 3510 456 425 198 2918 309 3415 4827 6032 45238 62910207910876026445761137111631251724273365363228303481721191855122831334911343471318119221496.1- 8.1-8 100 00 03 013 02 00 01 08 06 435 11 00 02 018 09 00 0>10.000000000000000000Total1261572151986446731121281266790106178220172493 312 132 98 5 0 207891 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirection 0.5- 1.1-Sector <0.50 1 1.5N 0 16 16NNE 0 11 9NE 1 15 25ENE 0 13 10E 1 7 10ESE 0 1 6SE 1 5 10SSE 0 12 19S 0 11 24SSW 0 11 25SW 0 11 25WSW 0 9 40W 0 12 31WNW 0 11 32NW 0 16 36NNW 1 21 19Tot 4 182 337Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total19 26 8 1210 12 5 040 39 21 212 28 20 145 8 5 411 7 2 113 29 16 119 29 25 945 79 25 1627 96 65 2926 89 37 344 80 14 542 73 11 137 115 49 2146 62 49 1934 44 15 18430 816 367 1550022601412281046657700000022613000100240 970 470 1450 990 460 280 780 1190 2180 2940 1920 1920 1740 2720 2340 1570 2392Hours of Calm ... ....... 4Hours of Variable Direction 1Hours of Valid Data .... 2397Hours of Missing Data ..10Hours in Period ...... .. 876092 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTotHours o0Hours ofHours olHours o0Hours ir0.5- 1.1- 1<0.50 1 1.51 17 90 4 41 3 50 2 40 2 31 2 10 4 72 4 90 8 120 10 130 15 190 22 340 18 571 11 39D 6 380 6 226 134 276f Calm ... ........f Variable Directionf Valid Data ....f Missing Data .n Period ... .......6213333119Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 66.1-88.1-10 >10.00 Total2 02 01 21 21 20 01 22 05 28 119 117 185 215 310 73 12 110507231087602910129841417274264ill131117814271893 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Stable -150Ft-33Ft Delta-T (F)Winds Measured at 33 FeetWirDi:SeNNN]NEEN]EES]SESSESSSýSWWS'WWNWNWNNWTotndrection 0.5- 1.1- 1ctor <0.50 1 1.51 7 2E 1 5 00 8 0E 1 3 30 3 31 3 10 4 03 9 02 16 51 18 134 39 275 109 1420 203 2312 107 834 64 773 17 2328 615 610Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... .......6-2000000204063253243210163Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1-3 4 5 60300001001013120126.1- 8.1-8 100 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0>10.0000000000000000000Total1098765712273376289490218179531429351146510876094 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -All Stabilities -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTot<0.5000010000000000100.5- 1.1-1 1.52 61 62 65 53 84 55 123 41 64 70 11 61 22 15 53 5Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total7 25 349 40 5413 53 756 32 5613 33 4810 37 607 37 696 30 637 32 556 21 387 23 4110 37 385 29 403 22 306 34 576 30 576243785959388674616465464362746380619678202151541081088886968110660127 77 57 47785 48107 65122 8920 2515 468 1359 54145 78226 168135 131149 112184 126233 242289 300173 1362240882661052321477475762211867636953554125520035839952578956556060289710636092 42 85 121 515 815 977 1194 2137 16681188 8744Hours of Calm 6....... 6Hours of Variable Direction 0Hours of Valid Data .... 8750Hours of Missing Data ..10Hours in Period ...... .. 876095 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWirDirSecNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTotnd7ection 0.5- 1.1- 1$tor <0.50 1 1.50 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 0Hours of Calm ... ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... .......6-2Wind Speed (in m/s)2.1- 3.1- 4.1- 5.1- 6.1-3 4 5 6 88.1-10 >10.00 Total00050002130002415400420000130012442001000000001110130007103232300045183561 8 13 45 32 26 1250012510876096 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at-380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Speed (in m/s)0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-1 1.5 2 3 4 5 6 8 10 >10.00 TotalWindDirectionSector <0.50N 0 0 0NNE 0 0 0NE 0 0 0ENE 0 0 0E 0 0 0ESE 0 0 0SE 0 0 0SSE 0 0 0S 0 0 0SSW 0 0 0SW 0 0 0WSW 0 0 0w 0 0 0WNW 0 0 0NW 0 0 0NNW 0 0 0Tot 0 0 0Hours of Calm ........Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... ......0 10 10 12 122 117 103 140 40 10 11 20 10 10 00 20 2001010137572632687402200261786771134501490000955637145001200000.70261015152183714202615342320191934732015 64 77 111 68 44 3790037910876097 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Unstable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirection 0.5- 1.1- 1Sector <0.50 1 1.5N 0 0 0NNE 0 0 0NE 0 0 0ENE 0 0 0E 0 0 0ESE 0 0 0SE 0 0 1SSE 0 0 0S 0 0 0SSW 0 0 0SW 0 0 0WSW 0 0 0W 0 0 0WNW 0 0 0NW 0 0 0NNW 0 0 0Tot 0 0 1Hours of Calm. .......Hours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... ......Wind Speed (in m/s).6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total0333143300111100242 6 2 13 3 0 19 14 11 315 15 15 611 11 1 013 9 1 06 19 8 30 14 13 80 3 8 192 6 8 85 11 4 80 6 8 154 2 14 231 9 9 226 17 16 248 4 10 1085 149 128 1510024000195038151436400010000070072316357111042592427403939362933598093386590065910876098 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Neutral -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTot<0. 5500.5- 1.1-1 1.5Wind Speed (in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 10 >10.00 Total0 0 1 2 10 19 28 35 24 320 1 2 5 18 23 22 36 49 380 1 2 4 32 40 34 51 73 480 0 1 2 16 26 16 35 74 600 0 0 7 18 25 17 9 13 210 0 1 7 19 26 12 9 8 20 2 4 2 16 35 24 15 30 80 0 1 2 10 31 34 18 26 240 0 1 1 9 20 34 48 47 120 1 1 2 9 15 19 35 70 530 0 1 3 9 13 22 39 28 150 0 1 3 20 12 14 28 36 250 0 1 3 14 16 24 32 48 290 0 0 3 10 17 27 30 57 540 0 1 4 17 32 25 42 62 960 1 2 4 16 25 36 19 49 340 6 20 54 243 375 388 481 694 55142223075243318796427917353561193216315305134871391641832841361431942893522393373Hours of Calm0Hours of Variable Direction0Hours of Valid Data .... 3373Hours of Missing Data ..10Hours in Period ...... .. 876099 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Slightly Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWind Wind Speed (in m/s)Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 TotalN 0 0 3 2 4 8 12 22 25 8 0 84NNE 0 0 1 2 10 16 7 14 20 1 0 71NE 0 0 0 3 11 12 15 15 16 6 8 86ENE 1 3 1 2 4 5 6 11 30 12 10 85E 0 0 0 1 6 7 13 7 5 4 2 45ESE 0 1 1 1 6 12 4 5 4 2 3 39SE 0 0 1 3 5 10 18 8 18 2 7 72SSE 0 0 1 1 3 14 10 11 14 24 28 106S 0 0 2 3 10 17 14 24 34 25 18 147SSW 0 1 3 1 3 10 20 40 110 89 52 329SW 0 0 0 0 5 6 19 23 56 76 43 228WSW 0 1 1 3 3 6 7 22 45 37 30 155W 0 0 1 0 6 7 9 21 61 48 7 160WNW 0 0 0 0 7 5 11 14 78 100 43 258NW 0 1 1 1 4 5 5 18 80 96 28 239NNW 0 0 1 1 7 9 10 8 45 28 3 112Tot 1 7 17 24 94 149 180 263 641 558 282 2216Hours of Calm ... ........ 1Hours of Variable Direction 0Hours of Valid Data .... 2217Hours of Missing Data ..10Hours in Period ...... .. 8760100 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Moderately Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWinDirSecNNNENEENEEESESESSESSSWSWWSWWWNWNWNNVTotndrection 0.5- 1.1- 1ctor <0.50 1 1.50 1 00 0 10 1 00 1 10 1 20 0 10 1 30 1 10 1 10 1 10 0 00 0 20 1 00 0 00 1 10 1 00 11 14Hours of CalmHours of Variable DirectionHours of Valid Data ....Hours of Missing Data .Hours in Period ... ......Wind Speed(in m/s).6-22.1- 3.1-3 40011311210441000194.1- 5.1-5 68 124 89 37 45 12 23 57 55 911 76 99 75 148 1212 134 56.1-838755138011161729313541228.1-10220010012810242626505339>10.0011000000411162818322811Total95222927161431295157891191051431569281 105 116 269 262150 1075201077108760101 Oyster Creek 2014 Annual Radioactive Effluent Release ReportTable D -10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for theOyster Creek Generating Station, January -December, 2014Oyster Creek AlphaPeriod of Record: January -December 2014Stability Class -Extremely Stable -380Ft-33Ft Delta-T (F)Winds Measured at 380 FeetWindDirectionSectorNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTotHoursHoursHours0.5- 1.1-<0.50 1 1.50 1 20 0 20 0 40 1 20 2 60 3 20 2 30 2 10 0 20 1 20 0 00 0 20 0 00 2 11 3 20 1 21 18 33of Calm .........of Variable Directiof Valid Data ...Wind Speed(in m/s)1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-2 3 4 5 6 8 103 8 5 7 9 35 152 9 10 6 3 8 85 5 6 5 4 8 11 8 2 2 1 0 12 7 0 0 1 1 01 5 0 0 0 0 01 9 10 7 6 7 21 11 14 5 2 3 32 8 9 4 8 4 23 4 6 7 16 14 60 3 8 5 7 20 110 8 11 7 18 17 141 4 8 2 13 12 100 2 3 7 10 26 121 11 9 12 7 33 231 4 8 7 11 38 2524 106 109 83 116 226 1333on 0920>10. 0040000002219101012135Total894838181911474441606387607511510268 917Hours of Missing Data ..Hours in Period ..........108760102 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix EODCM RevisionsSee attached copy of CY-OC-1 70-301 Revision 6103 Oyster Creek 2014 Annual Radioactive Effluent Release ReportAppendix FERRATA104 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2013 ARERR1. A Program Deviation was not reported as required in the 2013 AnnualRadiological Effluent release Report in Section J. Program Deviations. A turbinebuilding (TB) effluent noble gas grab sample was not collected for July 2013.2. A Program Deviation was not reported as required in the 2013 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1, 2013 through December 31, 2013.3. An abnormal release was discovered in 2014 after the 2013 ARERR wassubmitted that was determined to impact the 2013 ARERR. There were multiplepages impacted by this abnormal release and all of the pages are included inthis errata section.105 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2013 through December 31, 2013EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16106 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportH. Radiation Effluent Monitors Out of Service More Than 30 DaysPer ODCM Control 3.3.3.10, "Radioactive Liquid Effluent MonitoringInstrumentation" and 3.3.3.11, "Radioactive Gaseous Effluent MonitoringInstrumentation" requires:With less than the minimum number of radioactive liquid/gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument toOPERABLE status within 30 days and, if unsuccessful, explain in the nextRadioactive Effluent Release Report why the inoperability was not corrected in atimely manner.The following is a discussion of instrumentation out of service for greater than 30days:1. The Offgas Building Exhaust Gaseous Effluent Radioactive Noble Gas Monitorwas out of service from 5/20/2013 through 8/9/2013. The monitor was taken outof service 5/20/2013 for failing the monitor functional test. The original issue forthe monitor failing the functional test was a faulty pushbutton on the alarm panelcausing the alarm not to function. Parts were ordered and replaced on6/18/2013 but the alarm still did not function as expected. After multipletroubleshooting attempts it was determined that the annunciator window cardwiring was the issue. After changing the wiring in the alarm panel, all alarmsresponded as expected. The functional test was reperformed 8/9/2013satisfactorily and the monitor was returned to service. This issue was enteredinto our Corrective Action Program (CAP) and corrective actions taken havebeen documented per process. All ODCM required compensatory measureswere met.1. Releases from the Independent Spent Fuel Storage Facility:The ISFSI is a closed system and the only exposure would be due to directradiation. This includes iodines, particulates, and noble gases. Based on offsiteTLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for2013. Because it is a sealed unit, no radioactive material was released.J. Program Deviations:1. The groundwater remediation composite sampler was found with no compositecollected on December 27, 2013. The composite sampler is required by ODCMTable 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.A manual sample was obtained per SP 10-003. Operations department wasnotified that composite sampler was not working and Operations secureddischarging from W-73 and Chemistry secured the composite sampler. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions taken have been documented per process.107 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportH. Radiation Effluent Monitors Out of Service More Than 30 DaysPer ODCM Control 3.3.3.10, "Radioactive Liquid Effluent MonitoringInstrumentation" and 3.3.3.11, Radioactive Gaseous Effluent MonitoringInstrumentation requires:With less than the minimum number of radioactive liquid/gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument toOPERABLE status within 30 days and, if unsuccessful, explain in the nextRadioactive Effluent Release Report why the inoperability was not corrected in atimely manner.The following is a discussion of instrumentation out of service for greater than 30days:1. The Offgas Building Exhaust Gaseous Effluent Radioactive Noble Gas Monitorwas out of service from 5/20/2013 through 8/9/2013. The monitor was taken outof service 5/20/2013 for failing the monitor functional test The original issue forthe monitor failing the functional test was a faulty pushbutton on the alarm panelcausing the alarm not to function. Parts were ordered and replaced on6/18/2013 but the alarm still did not function as expected. After multipletroubleshooting attempts it was determined that the annunciator window cardwiring was the issue. After changing the wiring in the alarm panel, all alarmsresponded as expected. The functional test was reperformed 8/9/2013satisfactorily and the monitor was returned to service. This issue was enteredinto our Corrective Action Program (CAP) and corrective actions taken havebeen documented per process. All ODCM required compensatory measureswere met.I. Releases from the Independent Spent Fuel Storage Facility:The ISFSI is a closed system and the only exposure would be due to directradiation. This includes iodines, particulates, and noble gases. Based on offsiteTLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for2013. Because it is a sealed unit, no radioactive material was released.J. Program Deviations:1. The groundwater remediation composite sampler was found with no compositecollected on December 27, 2013. The composite sampler is required by ODCMTable 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.A manual sample was obtained per SP 10-003. Operations department wasnotified that composite sampler was not working and Operations secureddischarging from W-73 and Chemistry secured the composite sampler. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions taken have been documented per process.2. A turbine building (TB) effluent noble gas grab sample was not collected for July2013. This sample is a requirement of Table 4.11.2.1.2-1, Radioactive GaseousWaste Sampling and Analysis Program, of CY-OC-170-301, ODCM for OysterCreek. The July sample was originally scheduled to be collected 7/5/13, but wasrescheduled to occur the following week so it could be collected in July. The108 Oyster Creek 2014 Annual Radioactive Effluent Release Reportsample was not rescheduled and tracked by the Chemistry Supervisoradequately, and a sample was not collected until the scheduled August sample8/1113. Historical data from July's TB RAGEMS low range monitor was trendedagainst the data from June and August with no discrepancies noted. There wereno isotopes identified in the Noble Gas Grab Samples from June and August.This issue was entered into our Corrective Action Program (CAP) and correctiveactions taken have been documented per process.3. The New Radwaste (NRVV)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2013 through December 31, 2013. TheNew Radwaste/Augmented Offgas Service Water Effluent sample was requiredby CY-OC-170-301, Offsite Dose Calculation Manual for Oyster CreekGenerating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling andAnalysis Program and was required to be sampled weekly for principal gammaemitters and 1-131. This issue occurred from the inclusion of this requirement inrevision 4 of the ODCM due to a misunderstanding of the system flow path. Itwas believed that all service water exited the site from the same release pointwhich was evident by the fact that the change paperwork included in thedescription of this change as being consistent with the practices at Oyster Creekand there was no modification to the sampling schedule. The NRW and AOGClosed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10.At that time NRW Closed Cooling Water system was determined to be apotentially contaminated system and was added to the sampling program forNRC Bulletin IE 80-10. The sampling program for IE 80-10 requires allpotentially contaminated systems to be sampled quarterly for gamma emitters.AOG Closed Cooling Water system was also reviewed but determined to not bea potentially contaminated system. Even though AOG was found not to be apotentially contaminated system sampling is still performed quarterly for gammaemitters. The potential pathway for a release from NRW/AOG Service WaterEffluent would be from a heat exchanger leak from the NRW Closed CoolingWater system into the Service Water side of the heat exchanger. The system isdesigned to maintain the Service Water side of the heat exchanger at a higherpressure than the Closed Cooling Water side so that if any leaks would developin the heat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were not obtainedand all samples were less than MDA for gamma emitters for that entire timeperiod.109 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportEXECUTIVE SUMMARYEffluents are strictly monitored to ensure that radioactivity released to the environment is aslow as reasonably achievable and does not exceed regulatory limits. Effluent control includesthe operation of monitoring systems, in-plant and environmental sampling and analysesprograms, quality assurance programs for the effluent and environmental programs, andprocedures covering all aspects of effluent and environmental monitoring.Both radiological environmental and effluent monitoring indicate that the operation of OysterCreek Generating Station (OCGS) does not result in significant radiation exposure to thepeople or the environment surrounding OCGS and is well below the applicable levels set by theNuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were liquid radioactive effluent releases during 2013 of concentrations of tritium too lowto detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution DischargeElimination System (NJPDES) permitted main condenser outfall. The releases were part ofnearly continuous pumping of groundwater at approximately 70 gpm containing low levels oftritium and no detectable gamma. Exelon and the State of New Jersey Department ofEnvironmental Protection (NJDEP) agreed to this remediation action instead of naturalattenuation to address concentrations of tritium in groundwater. Well 73 and supportingequipment and piping were installed to pump groundwater to the intake structure at the inlet ofthe main circulating water pumps. Provisions were established for both batch and continuousreleases of groundwater. Continuous releases occurred approximately 361 days in 2013. TheContinuous releases occurred from January 1, 2013 through December 27, 2013 with a total of3.50E+07 gallons of groundwater pumped resulting in 2.82E-01 Ci of tritium released to thedischarge canal. The dose to the most limiting member of the public due to the release ofgroundwater was 1.37E-06 mrem.There were no liquid abnormal releases during 2013.There was one gaseous abnormal release during 2013. During the annual inspection of theOld Radwaste Building exhaust fan connections to the main stack it was discovered that therewere three slits in the top boot connection of exhaust fan EF-1-16 and a bolt missing in theconnection of exhaust fan EF-1 -17.The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), andparticulates to any individual due to gaseous effluents was 4.93E-01 mrem, which wasapproximately 3.29E+00 percent of the annual limit of 15 mrem. The majority of organ dosefrom gaseous effluents was due to C-14. The maximum calculated gamma air dose in theUNRESTRICTED AREA due to noble gas effluents was 3.60E-03 mrad, which was 3.60E-02percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limitof 10 mrad.For comparison, the background radiation dose averages approximately 300 mrem per year in theCentral New Jersey area, which includes approximately 200 mrem from naturally occurring radongas and 100 mrem from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only110 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportEXECUTIVE SUMMARYEffluents are strictly monitored to ensure that radioactivity released to the environment is aslow as reasonably achievable and does not exceed regulatory limits. Effluent control includesthe operation of monitoring systems, in-plant and environmental sampling and analysesprograms, quality assurance programs for the effluent and environmental programs, andprocedures covering all aspects of effluent and environmental monitoring.Both radiological environmental and effluent monitoring indicate that the operation of OysterCreek Generating Station (OCGS) does not result in significant radiation exposure to thepeople or the environment surrounding OCGS and is well below the applicable levels set by theNuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were liquid radioactive effluent releases during 2013 of concentrations of tritium too lowto detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution DischargeElimination System (NJPDES) permitted main condenser outfall. The releases were part ofnearly continuous pumping of groundwater at approximately 70 gpm containing low levels oftritium and no detectable gamma. Exelon and the State of New Jersey Department ofEnvironmental Protection (NJDEP) agreed to this remediation action instead of naturalattenuation to address concentrations of tritium in groundwater. Well 73 and supportingequipment and piping were installed to pump groundwater to the intake structure at the inlet ofthe main circulating water pumps. Provisions were established for both batch and continuousreleases of groundwater. Continuous releases occurred approximately 361 days in 2013. TheContinuous releases occurred from January 1, 2013 through December 27, 2013 with a total of3.50E+07 gallons of groundwater pumped resulting in 2.82E-01 Ci of tritium released to thedischarge canal. The dose to the most limiting member of the public due to the release ofgroundwater was 1.37E-06 mrem.There were no liquid abnormal releases during 2013.There were two gaseous abnormal releases during 2013. During the annual inspection of theOld Radwaste Building exhaust fan connections to the main stack it was discovered that therewere three slits in the top boot connection of exhaust fan EF-1-16 and a bolt missing in theconnection of exhaust fan EF-1-17. During maintenance of the New Radwaste Buildingexhaust fan HV-S-54A, two slits were identified in the expansion joint and repaired.The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), andparticulates to any individual due to gaseous effluents was 4.94E-01 mrem, which wasapproximately 3.29E+00 percent of the annual limit of 15 mrem. The majority of organ dosefrom gaseous effluents was due to C-14. The maximum calculated gamma air dose in theUNRESTRICTED AREA due to noble gas effluents was 3.60E-03 mrad, which was 3.60E-02percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limitof 10 mrad.For comparison, the background radiation dose averages approximately 300 mrem per year in theCentral New Jersey area, which includes approximately 200 mrem from naturally occurring radongas and 100 mrem from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only111 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Reportexposure is due to direct radiation. Based on offsite TLD readings, dose due to direct radiationfrom the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive materialwas released.Comparison of environmental sampling results to iodine and particulate gaseous effluentsreleased, showed no radioactivity attributable to the operation of OCGS. Both elevated andground-level release paths were considered in this review, with total iodines released of 3.12E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.82E-02Ci.Joint Frequency Tables of meteorological data, per Stability Classification Category, as well asfor all stability classes, are included. All data was collected from the on-site MeteorologicalFacility. Data recoveries for the 380-foot data and the 33-foot data were 99.4 percent and 99.4percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for MeteorologicalFacility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.112 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Reportexposure is due to direct radiation. Based on offsite TLD readings, dose due to direct radiationfrom the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive materialwas released.Comparison of environmental sampling results to iodine and particulate gaseous effluentsreleased, showed no radioactivity attributable to the operation of OCGS. Both elevated andground-level release paths were considered in this review, with total iodines released of 3.12E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.84E-02Ci.Joint Frequency Tables of meteorological data, per Stability Classification Category, as well asfor all stability classes, are included. All data was collected from the on-site MeteorologicalFacility. Data recoveries for the 380-foot data and the 33-foot data were 99.4 percent and 99.4percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for MeteorologicalFacility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.113 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportE. Batch Releases:1. LiquThere were no batch releases of liquid effluents during 2013.2. GaseousThere were no batch releases of gaseous effluents during 2013.F. Abnormal Releases:There were no abnormal liquid releases during 2013.There was one abnormal gaseous release during 2013. During the performance ofWork Order R2205683, which is to perform an annual inspection of the stack padexhaust fans, three slits were discovered in the top boot of exhaust fan EF-1-16 anda bolt was missing from exhaust fan EF-1-17. These are the two exhaust fans forthe Old Radwaste Building to the Main Stack. One of these two exhaust fans is inoperation at all times to maintain a negative pressure in the Old Radwaste Building.At no times do both of these fans run simultaneously as each fans is designed toprovide 100% of the required flow. Engineering performed a calculation todetermine a release rate that encompasses the maximum release rate regardless ofwhich exhaust fan is in service. The activity to inspect the exhaust fans is anannual activity.The following assumptions were made when calculating Curies released and dose:* Both exhaust fans have been leaking since the date of the last inspectionuntil the time of the last repair, 7/29/12 through 7/25/13." All of the activity due to particulates reported from the Main Stack wascoming from the Old Radwaste Building and therefore being released as agroundlevel release from the exhaust fan leaks at the flow rate calculated byEngineering.Units Quarter Quarter Quarter Quarter 41 2 3Total Release Ci 4.94E-05 5.OOE-05 1.37E-05 O.OOE+00G. Revisions to the ODCM:There were no revisions to the ODCM during 2013.114 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportE. Batch Releases:1. LiuThere were no batch releases of liquid effluents during 2013.2. GaseousThere were no batch releases of gaseous effluents during 2013.F. Abnormal Releases:There were no abnormal liquid releases during 2013.There were two abnormal gaseous releases during 2013.During the performance of Work Order R2205683, which is to perform an annualinspection of the stack pad exhaust fans, three slits were discovered in the top bootof exhaust fan EF-1 -16 and a bolt was missing from exhaust fan EF-1 -17. Theseare the two exhaust fans for the Old Radwaste Building to the Main Stack. One ofthese two exhaust fans is in operation at all times to maintain a negative pressure inthe Old Radwaste Building. At no times do both of these fans run simultaneously aseach fans is designed to provide 100% of the required flow. Engineering performeda calculation to determine a release rate that encompasses the maximum releaserate regardless of which exhaust fan is in service. The activity to inspect theexhaust fans is an annual activity.The following assumptions were made when calculating Curies released and dose:* Both exhaust fans have been leaking since the date of the last inspectionuntil the time of the last repair, 7/29/12 through 7/25/13." All of the activity due to particulates reported from the Main Stack wascoming from the Old Radwaste Building and therefore being released as aground level release from the exhaust fan leaks at the flow rate calculatedby Engineering.Quarter Quarter QuarterUnits 1 1 2 1 3 Quarter 41 2 3Total Release Ci 4.94E-05 5.OOE-05 I 1.37E-05 O.00E+O0During the performance of Work Order R2227008, which is to perform an annualinspection of the New Radwaste (NRW) exhaust fan HV-S-54A, two slits werediscovered in the expansion joint. This is one of the exhaust fans for the NewRadwaste Building to the Main Stack. Note that the exhaust from HV-S-54A isnormally to the atmosphere but through the monitored stack effluent release point.Engineering performed a calculation to determine a release rate that encompassesthe maximum release rate for both slits. The activity to inspect the exhaust fan is anannual activity.The following assumptions were made when calculating Curies released and dose:115 Oyster Creek 2014 Annual Radioactive Effluent Release Report" The exhaust fan has been leaking since the date of the last inspection untilthe time of the repair, 8/20/13 through 7/25/14.* All of the activity due to particulates reported from the Main Stack wascoming from the New Radwaste Building and therefore being released as agroundlevel release from the exhaust fan leaks at the flow rate calculated byEngineering." HV-S-54A was in operation the entire time since the last inspection wasperformed.Units Quarter Quarter Quarter Quarter 41 2 3Total Release Ci 0.000e 0.OOeO 4.08E-05 9.00E-05G. Revisions to the ODCM:There were no revisions to the ODCM during 2013.116 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-I: Gaseous Effluents- Summary Of All ReleasesPeriod: January 1, 2013 through December 31, 2013Unit: Oyster Creek1 IEst° TotalA. Fission &Activation Gases j Units Quarter I IQuarter 2 Quarter 3 Quarter 4 Error %=_. -1. Total ReleaseCi2.06E+011.40E+017.04E+00 I 8.02E+00 I 25.00% I2. Average Release Rate for PeriodSULdI MWVOWC I %A I 0.10UU I.or-w ;.Oe'I-U12. Average Release Rate for Period I uCi/sec 1 1.12E+00 I 8.14E-01 4.90E-01 I 7.32E-0112. Percent of ODCM Limit* ODCM Limit is for combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.117 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-I: Gaseous Effluents -Summary Of All ReleasesPeriod: January 1, 2013 through December 31, 2013Unit: Oyster CreekY I I -A. Fission & Activation GasesESt. Iola,Quarter 4 Error %'. aI I L".J JD= I ,,,,5,,, I j.wJL_--, I ,2. Percent of ODCM Limit I % 56.67E-01 1* ODCM Limit is fkr combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.118 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-3: Gaseous Effluent Release Point: Ground Level ReleasesPeriod: January 1, 2013 through December 31, 2013Unit: Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gasei Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 33m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 35 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-i 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-1 38 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2. lodines1-131 Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD3. ParticulatesSr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-1 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-137 Ci 2.57E-07 2.59E-07 7.13E-08 <LLD <LLD <LLD <LLD <LLDBa-140 Ci 2.62E-05 2.65E-05 7.28E-06 <LLD <LLD <LLD <LLD <LLDLa-1 40 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci 5.30E-06 5.35E-06 1.47E-06 <LLD <LLD <LLD <LLD <LLDMn-54 Ci 4.78E-06 5.64E-06 1.22E-06 1.80E-05 <LLD <LLD <LLD <LLDCo-58 Ci 3.86E-06 1.33E-05 4.02E-06 3.51 E-07 <LLD <LLD <LLD <LLDCo-60 Ci 1.17E-05 2.86E-05 1.69E-05 8.87E-05 <LLD <LLD <LLD <LLDNi-63 Ci 2.74E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 7.96E-07 8.05E-07 2.21E-07 <LLD <LLD <LLD <LLD <LLDAg-1I0m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 2.09E-06 2.11E-06 5.81E-07 <LLD <LLD <LLD <LLD <LLDAm-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 8.24E-05 8.26E-05 3.18E-05 1.07E-04 <LLD <LLD <LLD <LLD4. TritiumH-3 Ci 2.88E-01 1.22E-01 2.93E-01 2.05E-01 <LLD <LLD <LLD I <LLD5. Gross AlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14 .....C-14 Ci 7.40E-02 7.49E-02 I 7.57E-02 17.57E-02 <LLD <LLD <LLD <LLD119 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportTable A-3: Gaseous Effluent Release Point: Ground Level ReleasesPeriod: January 1, 2013 through December 31, 2013Unit Oyster CreekNuclidesReleased Continuous Mode Batch Mode1. Fission gase Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter1 2 3 4 1 2 3 4Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-I 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDXe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2. lodines1-131 Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Pedod Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD3. Particulates -Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDSr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCs-1 37 Ci 2.57E-07 2.59E-07 4.55E-07 8.47E-07 <LLD <LLD <LLD <LLDBa-140 Ci 2.62E-05 2.65E-05 1.28E-05 1.22E-05 <LLD <LLD <LLD <LLDLa-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCr-51 Ci 5.30E-06 5.35E-06 4.58E-06 6.86E-06 <LLD <LLD <LLD <LLDMn-54 Ci 4.78E-06 5.64E-06 4.94E-06 2.62E-05 <LLD <LLD <LLD <LLDCo-58 Ci 3.86E-06 1.33E-05 1.47E-05 2.38E-05 <LLD <LLD <LLD <LLDCo-60 Ci 1.17E-05 2.86E-05 2.93E-05 1.16E-04 <LLD <LLD <LLD <LLDNi-63 Ci 2.74E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLDMo-99 Ci 7.96E-07 8.05E-07 125E-06 2.26E-06 <LLD <LLD <LLD <LLDAg-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDZn-65 Ci 2.09E-06 2.11 E-06 4.62E-06 8.90E-06 <LLD <LLD <LLD <LLDAm-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDTotal for Period Ci 8.24E-05 8.26E-05 7.26E-05 l1.97E-04 <LLD <LLD <LLD <LLD4. Tritium LH-3 Ci 2.88E-01 1.22E-01 2.93E-01 2,05E-01 <LLD <LLD <LLD <LLD5. Gross AlphaGross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD6. Carbon-14C-14 Ci 7.40E-02 7.49E-02 7.57E-02 7.57E-02 <LLD <LLD <LLD <LLD120 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportLocation % ofApplicable Estimated Age Distance Direction ApplicableEffluent Organ Dose Group (meters) (toward) Limit Limit UnitGamma -Noble Gas Air Dose 3.60E-03 All 500 ESE 3.60E-02 10 mradBeta -AirNoble Gas Dose 8.44E-04 All 500 ESE 4.22E-03 20 mradTotal BodyNoble Gas (Gamma) 1.42E-03 All 937 SE 2.84E-02 5 mremNoble Gas Skin (Beta) 1.77E-03 All 972 ESE 1.18E-02 15 mremIodine,Particulate, Bone 4.93E-01 Child 937 SE 3.29E+00 15 mremCarbon-14 &TritiumLiquid Total body 1.37E-06 All South Route 9 4.57E-05 3 mremLiquid Organ 1.37E-06 All Bridge 1.37E-05 10 mremDirect Radiation Total Body 5.39E+00 All 483 W 2.16E+01 25 mremDirect Radiation Total Body <LLD All 937 SE <LLD 25 mrem40 CFR Part 190 ComplianceWarehouse WorkerTotal Dose JTotal Body 5.39E+00 All 483 W 2.16E+01 25 mremTotal Dose Bone 5.50E+00 All 483 W 2.20E+01 J 25 mremTotal Dose Thyroid 5.39E+00 All 483 W 7.19E+00 1 75 mremNearest ResidentTotal Dose Total BodyJ 3.60E-03 All 937 SE 1.44E-02 25 mremTotal Dose J Bone 4.97E-01 All 937 SE 1.99E+00 25 mremTotal Dose Thyroid 3.60E-03 All 937 SE 4.80h-03 75 m121 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release ReportLocation % ofApplicable Estimated Age Distance Direction ApplicableEffluent Organ Dose Group (meters) (toward) Limit Limit UnitGamma -Noble Gas Air Dose 3.60E-03 All 500 ESE 3.60E-02 10 mradBeta -AirNoble Gas Dose 8.44E-04 All 500 ESE 4.22E-03 20 mradTotal BodyNoble Gas (Gamma) 1.42E-03 All 937 SE 2.84E-02 5 mremNoble Gas Skin (Beta) 1.77E-03 All 972 ESE 1.18E-02 15 mremIodine,Particulate, Bone 4.94E-01 Child 937 SE 3.29E+00 15 mremCarbon-14 &TritiumLiquid Total body 1.37E-06 All South Route 9 4.57E-05 3 mremLiquid Organ 1.37E-06 All Bridge 1.37E-05 10 mremDirect Radiation Total Body 5.39E+00 All 483 W 2.16E+01 25 mremDirect Radiation Total Body <LLD All 937 SE <LLD 25 mrem40 CFR Part 190 ComplianceWarehouse WorkerTotal Dose Total Body 5.39E+00 All 483 W 2.16E+01 25 mremTotal Dose Bone 5.50E+00 All 483 W 2.20E+01 25 mremTotal Dose Thyroid 5.39E+00 All 483 W 7.19E+00 75 mremNearest ResidentTotal Dose Total Body 3.60E-03 All 937 SE 1.44E-02 25 mremTotal Dose Bone 4.98E-01 All 937 SE 1.99E+00 25 mremTotal Dose Thyroid I3.E-03 All1 937 SE I4.80E-3 I7 mrem122 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2012 ARERR1. A Program Deviation was not reported as required in the 2012 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1, 2012 through December 31, 2012.123 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2012 through December 31, 2012EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16124 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2012 Annual Radioactive Effluent Release ReportJ. Program Deviations:1 A turbine building (TB) effluent noble gas grab sample was not collected forSeptember 2012. This sample is a requirement of Table 4.11.2.1.2-1,Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-1 70-301, ODCM for Oyster Creek. The September sample was originallyscheduled to be collected 8/31/12, but was rescheduled to occur the followingweek so it could be collected in September. The sample was not rescheduledand tracked by the Chemistry Supervisor adequately, and a sample was notcollected until the scheduled October sample 10/5/12. Historical data fromSeptember's TB RAGEMS low range monitor was trended against the datafrom August and October with no discrepancies noted. There were noisotopes identified in the Noble Gas Grab Samples from August and October.This issue was entered into our Corrective Action Program (CAP) andcorrective actions taken have been documented per process.2. The groundwater remediation composite sampler was found out of service forless than eight hours on October 19, 2012. The composite sampler isrequired by ODCM Table 4.11.1 .1 .1-1, Radioactive Liquid Waste Samplingand Analysis Program. There was enough sample in the composite samplerto perform the required analyses and the composite sampler was immediatelyreturned to service. This issue was entered into our Corrective ActionProgram (CAP) and corrective actions taken have been documented perprocess.125 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2012 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. A turbine building (TB) effluent noble gas grab sample was not collected forSeptember 2012. This sample is a requirement of Table 4.11.2.1.2-1,Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-170-301, ODCM for Oyster Creek. The September sample was originallyscheduled to be collected 8/31/12, but was rescheduled to occur the followingweek so it could be collected in September. The sample was not rescheduledand tracked by the Chemistry Supervisor adequately, and a sample was notcollected until the scheduled October sample 10/5/12. Historical data fromSeptember's TB RAGEMS low range monitor was trended against the datafrom August and October with no discrepancies noted. There were noisotopes identified in the Noble Gas Grab Samples from August and October.This issue was entered into our Corrective Action Program (CAP) andcorrective actions taken have been documented per process.2. The groundwater remediation composite sampler was found out of service forless than eight hours on October 19, 2012. The composite sampler isrequired by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Samplingand Analysis Program. There was enough sample in the composite samplerto perform the required analyses and the composite sampler was immediatelyreturned to service. This issue was entered into our Corrective ActionProgram (CAP) and corrective actions taken have been documented perprocess.3. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2012 through December 31, 2012. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by CY-OC-1 70-301, Offsite Dose Calculation Manual for OysterCreek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid WasteSampling and Analysis Program and was required to be sampled weekly forprincipal gamma emitters and 1-131. This issue occurred from the inclusion ofthis requirement in revision 4 of the ODCM due to a misunderstanding of thesystem flow path. It was believed that all service water exited the site from thesame release point which was evident by the fact that the change paperworkincluded in the description of this change as being consistent with thepractices at Oyster Creek and there was no modification to the samplingschedule. The NRW and AOG Closed Cooling Water systems were reviewedas part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Watersystem was determined to be a potentially contaminated system and wasadded to the sampling program for NRC Bulletin IE 80-10. The samplingprogram for IE 80-10 requires all potentially contaminated systems to besampled quarterly for gamma emitters. AOG Closed Cooling Water systemwas also reviewed but determined to not be a potentially contaminatedsystem. Even though AOG was found not to be a potentially contaminatedsystem sampling is still performed quarterly for gamma emitters. The potentialpathway for a release from NRWIAOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into theService Water side of the heat exchanger. The system is designed to126 Oyster Creek 2014 Annual Radioactive Effluent Release Reportmaintain the Service Water side of the heat exchanger at a higher pressurethan the Closed Cooling Water side so that if any leaks would develop in theheat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were notobtained and all samples were less than MDA for gamma emitters for thatentire time period.127 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2011 ARERR1. A Program Deviation was not reported as required in the 2011 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1,2011 through December 31, 2011.128 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2011 through December 31, 2011EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16129 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2011 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. During Augmented Off Gas (AOG) sample line pressue testing conductedFebruary 21, 2011, it was discovered that the sample line was not able tomaintain pressure due to the filter assembly not being tight. The filterassembly was tightened and the pressure test was completed SAT. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions implemented to ensure filter assemblies are tight when installed forsampling. The weekly sample results were evaluated against previous sampleresults for impact to sampling due to the assembly not being tight with noimpact identified.2. The groundwater remediation composite sampler was found out of service forless than one day on March 29, 2011. The composite sampler is required byODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and AnalysisProgram. There was enough sample in the composite sampler to perform therequired analyses and the composite sampler was immediately returned toservice.3. The groundwater remediation composite sampler was found out of service forfor approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on August 21, 2011. The composite sampler isrequired by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Samplingand Analysis Program. The composite sampler was immediately returned toservice and enough sample was collected in the composite sampler to performthe required analyses.130 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2011 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. During Augmented Off Gas (AOG) sample line pressue testing conductedFebruary 21, 2011, it was discovered that the sample line was not able tomaintain pressure due to the filter assembly not being tight. The filterassembly was tightened and the pressure test was completed SAT. Thisissue was entered into our Corrective Action Program (CAP) and correctiveactions implemented to ensure filter assemblies are tight when installed forsampling. The weekly sample results were evaluated against previous sampleresults for impact to sampling due to the assembly not being tight with noimpact identified.2. The groundwater remediation composite sampler was found out of service forless than one day on March 29, 2011. The composite sampler is required byODCM Table 4.11 .1 .1.1-1, Radioactive Liquid Waste Sampling and AnalysisProgram. There was enough sample in the composite sampler to perform therequired analyses and the composite sampler was immediately returned toservice.3. The groundwater remediation composite sampler was found out of service forfor approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on August 21, 2011. The composite sampler isrequired by ODCM Table 4.11.1.1.1.-1, Radioactive Liquid Waste Samplingand Analysis Program. The composite sampler was immediately returned toservice and enough sample was collected in the composite sampler to performthe required analyses.4. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2011 through December 31, 2011. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by CY-OC-1 70-301, Offsite Dose Calculation Manual for OysterCreek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid WasteSampling and Analysis Program and was required to be sampled weekly forprincipal gamma emitters and 1-131. This issue occurred from the inclusion ofthis requirement in revision 4 of the ODCM due to a misunderstanding of thesystem flow path. It was believed that all service water exited the site from thesame release point which was evident by the fact that the change paperworkincluded in the description of this change as being consistent with thepractices at Oyster Creek and there was no modification to the samplingschedule. The NRW and AOG Closed Cooling Water systems were reviewedas part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Watersystem was determined to be a potentially contaminated system and wasadded to the sampling program for NRC Bulletin IE 80-10. The samplingprogram for IE 80-10 requires all potentially contaminated systems to besampled quarterly for gamma emitters. AOG Closed Cooling Water systemwas also reviewed but determined to not be a potentially contaminatedsystem. Even though AOG was found not to be a potentially contaminatedsystem sampling is still performed quarterly for gamma emitters. The potentialpathway for a release from NRW/AOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into the131 Oyster Creek 2014 Annual Radioactive Effluent Release ReportService Water side of the heat exchanger. The system is designed tomaintain the Service Water side of the heat exchanger at a higher pressurethan the Closed Cooling Water side so that if any leaks would develop in theheat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were notobtained and all samples were less than MDA for gamma emitters for thatentire time period.132 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2010 ARERR1. A Program Deviation was not reported as required in the 2010 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedJanuary 1, 2010 through December 31, 2010.133 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2010 through December 31, 2010EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16134 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2010 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. Procedure 621.3.037, Turbine Building RAGEMS Noble Gas Monitor -Functional Test was not performed at the frequency required by ODCM Table4.3.3.11-1. The test was required to be performed by November 13, 2010 andwas completed on December 2, 2010.2. The groundwater remediation composite sampler was found out of service forless than one day on November 30, 2010. The composite sampler is requiredby ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling andAnalysis Program. A grab sample was taken as a compensatory measure andthe composite sample was immediately returned to service.3. On December 18, 2010 at 04:00 the stack monitor noble gas monitor countrate was discovered to be much lower than expected. A valve was found tobe out of position causing a dilution in the sample concentration. Based onthe stack monitor noble gas monitor readings, the valve had been open for 15hours. The valve was placed in the correct, closed position, immediately andthe count rate returned to normal.4. The stack sample line was discovered separated on April 7, 2010. A rootcause analysis concluded that the sample line was first separated aboutJanuary 1, 2006. The sample line was returned to service on April 20, 2010.135 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2010 Annual Radioactive Effluent Release ReportJ. Program Deviations:1. Procedure 621.3.037, Turbine Building RAGEMS Noble Gas Monitor -Functional Test was not performed at the frequency required by ODCM Table4.3.3.11-1. The test was required to be performed by November 13, 2010 andwas completed on December 2, 2010.2. The groundwater remediation composite sampler was found out of service forless than one day on November 30, 2010. The composite sampler is requiredby ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling andAnalysis Program. A grab sample was taken as a compensatory measure andthe composite sample was immediately returned to service.3. On December 18, 2010 at 04:00 the stack monitor noble gas monitor countrate was discovered to be much lower than expected. A valve was found tobe out of position causing a dilution in the sample concentration. Based onthe stack monitor noble gas monitor readings, the valve had been open for 15hours. The valve was placed in the correct, closed position, immediately andthe count rate returned to normal.4. The stack sample line was discovered separated on April 7, 2010. A rootcause analysis concluded that the sample line was first separated aboutJanuary 1, 2006. The sample line was returned to service on April 20, 2010.5. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluentsample was not collected January 1, 2010 through December 31, 2010. TheNew Radwaste/Augmented Offgas Service Water Effluent sample wasrequired by CY-OC-170-301, Offsite Dose Calculation Manual for OysterCreek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid WasteSampling and Analysis Program and was required to be sampled weekly forprincipal gamma emitters and 1-131. This issue occurred from the inclusion ofthis requirement in revision 4 of the ODCM due to a misunderstanding of thesystem flow path. It was believed that all service water exited the site from thesame release point which was evident by the fact that the change paperworkincluded in the description of this change as being consistent with thepractices at Oyster Creek and there was no modification to the samplingschedule. The NRW and AOG Closed Cooling Water systems were reviewedas part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Watersystem was determined to be a potentially contaminated system and wasadded to the sampling program for NRC Bulletin IE 80-10. The samplingprogram for IE 80-10 requires all potentially contaminated systems to besampled quarterly for gamma emitters. AOG Closed Cooling Water systemwas also reviewed but determined to not be a potentially contaminatedsystem. Even though AOG was found not to be a potentially contaminatedsystem sampling is still performed quarterly for gamma emitters. The potentialpathway for a release from NRW/AOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into theService Water side of the heat exchanger. The system is designed tomaintain the Service Water side of the heat exchanger at a higher pressurethan the Closed Cooling Water side so that if any leaks would develop in the136 Oyster Creek 2014 Annual Radioactive Effluent Release Reportheat exchanger it would be Service Water leaking into the Closed CoolingWater side. A review was performed for both NRW and AOG quarterly ClosedCooling Water samples for the time that the required samples were notobtained and all samples were less than MDA for gamma emitters for thatentire time period.137 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCorrections to 2009 ARERR1. A Program Deviation was not reported as required in the 2009 AnnualRadiological Effluent release Report in Section J. Program Deviations. The NewRadwaste/Augmented Offgas Service Water Effluent sample was not obtainedSeptember 29, 2009 through December 31, 2009.138 Oyster Creek 2014 Annual Radioactive Effluent Release Report2009Annual Radioactive Effluent Release ReportOyster Creek Generating StationRevision 2Issued 2012139 Oyster Creek 2014 Annual Radioactive Effluent Release ReportANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1, 2009 through December 31, 2009EXELON GENERATION COMPANY, LLCOYSTER CREEK GENERATING STATIONDOCKET NO. 50-219 (Oyster Creek Generating Station)DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)Submitted toThe United States Nuclear Regulatory CommissionPursuant toRenewed Facility Operating License DPR-16140 Oyster Creek 2014 Annual Radioactive Effluent Release ReportORIGINAL PAGE Oyster Creek 2009 Annual Radioactive Effluent Release ReportThe maximum hypothetical calculated organ dose from iodines, tritium and particulates to anyindividual due to gaseous effluents was 3.38E-02 mrem, which was approximately 2.25E-01percent of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTEDAREA due to noble gas effluents was 4.55E-03 mrem, which was 4.55E-02 percent of theannual limit.For comparison, the background radiation dose averages approximately 300 mRem per year inthe Central New Jersey area, which includes approximately 200 mrem per year from naturallyoccurring radon gas and 100 mrem per year from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposurewould be due to direct radiation. This includes iodines, particulates and noble gases. Based onoffsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mRem for 2009.Because it is a sealed unit, no radioactive material was released.Additionally, comparison of environmental sampling results to iodine and particulate gaseouseffluents released, showed no radioactivity attributable to the operation of OCGS. Bothelevated and ground-level release paths were considered in this review, with total iodinesreleased of 1.78E-02 Ci and total particulates with half-lives greater than 8 days released of2.50E-02 Ci.Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stabilityclasses, are included. All data was collected from the on-site Meteorological Facility. Datarecoveries for the 380-foot data and the 33-foot data were 97.8 percent and 97.8 percent,respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facilitydata recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.141 Oyster Creek 2014 Annual Radioactive Effluent Release ReportCORRECTED PAGE Oyster Creek 2009 Annual Radioactive Effluent Release ReportThe maximum hypothetical calculated organ dose from iodines, tritium and particulates to anyindividual due to gaseous effluents was 3.38E-02 mrem , which was approximately 2.25E-01percent of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTEDAREA due to noble gas effluents was 4.55E-03 mrem, which was 4.55E-02 percent of theannual limit.For comparison, the background radiation dose averages approximately 300 mRem per year inthe Central New Jersey area, which includes approximately 200 mrem per year from naturallyoccurring radon gas and 100 mrem per year from background radiation.The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposurewould be due to direct radiation. This includes iodines, particulates and noble gases. Based onoffsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mRem for 2009.Because it is a sealed unit, no radioactive material was released.Additionally, comparison of environmental sampling results to iodine and particulate gaseouseffluents released, showed no radioactivity attributable to the operation of OCGS. Bothelevated and ground-level release paths were considered in this review, with total iodinesreleased of 1.78E-02 Ci and total particulates with half-lives greater than 8 days released of2.50E-02 Ci.Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stabilityclasses, are included. All data was collected from the on-site Meteorological Facility. Datarecoveries for the 380-foot data and the 33-foot data were 97.8 percent and 97.8 percent,respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facilitydata recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.The New Radwaste (NRW)/Augmented Offas (AOG) Service Water Effluent sample was notcollected September 29, 2009 through December 31, 2009. The New Radwaste/AugmentedOffas Service Water Effluent sample was required by CY-OC-170-301, Offsite DoseCalculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive LiquidWaste Sampling and Analysis Program and was required to be sampled weekly for principalgamma emitters and 1-131. This issue occurred from the inclusion of this requirement inrevision 4 of the ODCM due to a misunderstanding of the system flow path. It was believedthat all service water exited the site from the same release point which was evident by the factthat the change paperwork included in the description of this change as being consistent withthe practices at Oyster Creek and there was no modification to the sampling schedule. TheNRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Water system was determined to be a potentiallycontaminated system and was added to the sampling program for NRC Bulletin IE 80-10. Thesampling program for IE 80-10 requires all potentially contaminated systems to be sampledquarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed butdetermined to not be a potentially contaminated system. Even though AOG was found not tobe a potentially contaminated system sampling is still performed quarterly for gamma emitters.The potential pathway for a release from NRW/AOG Service Water Effluent would be from aheat exchanger leak from the NRW Closed Cooling Water system into the Service Water sideof the heat exchanger. The system is designed to maintain the Service Water side of the heatexchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would142 Oyster Creek 2014 Annual Radioactive Effluent Release Reportdevelop in the heat exchanger it would be Service Water leaking into the Closed Cooling Waterside. A review was performed for both NRW and AOG quarterly Closed Cooling Watersamples for the time that the required samples were not obtained and all samples were lessthan MDA for gamma emitters for that entire time period.143 Aw"w Exeton Generation.CY-OC-1 70-301Revision 6Page I of 140OFFSITE DOSE CALCULATION MANUALFOROYSTER CREEK GENERATING STATIONRevision of this document requires PORC approval and changes are controlled byCY-AA-1 70-3100122014 CY-OC-170-301Revision 6Page 2 of140TABLE OF CONTENTSINTRODUCTIONPART 1 -RADIOLOGICAL EFFLUENT CONTROLS1.03/4DEFINITIONSCONTROLS AND SURVEILLANCE REQUIREMENTS3/4.0 APPLICABILITY3/4.3 INSTRUMENTATION3/4.3.3.103/4.3.3.11RADIOACTIVE LIQUID EFFLUENT MONITORINGINSTRUMENTATIONRADIOACTIVE GASEOUS EFFLUENT MONTIORINGINSTRUMENTATION3/4.11 RADIOACTIVE EFFLUENTS3/4.11.1LIQUID EFFLUENTS3/4.11.1.13/4.11.1.23/4.11.1.33/4.11.23/4.11.2.13/4.11.2.23/4.11.2.33/4.11.2.43/4.11.33/4.11.43/4.123/4.12.13/4.12.23/4.12.33/4.12.4CONCENTRATIONDOSELIQUID WASTE TREATMENT SYSTEMGASEOUS EFFLUENTSDOSE RATEDOSE -NOBLE GASESDOSE -IODINE -131, IODINE -133, TRITIUM, ANDRADIONUCLIDES IN PARTICULATE FORMGASEOUS RADWASTE TREATMENT SYSTEMMARK I CONTAINMENTTOTAL DOSERADIOLOGICAL ENVIRONMENTAL MONITORINGMONITORING PROGRAMLAND USE CENSUSINTERLABORATORY COMPARISON PROGRAMMETEOROLOGICAL MONITORING PROGRAM122014 CY-OC-170-301Revision 6Page 3 of140BASES FOR SECTIONS 3.0 AND 4.03/4.3 INSTRUMENTATION3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORINGINSTRUMENTATION3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORINGINSTRUMENTATION3/4.11 RADIOACTIVE EFFLUENTS3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATION3/4.11.1.2 DOSE3/4.11.1.3 LIQUID RADWASTE TREATMENT3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSE RATES3/4.11.2.2 DOSE -NOBLE GAS3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM,AND RADIONUCLIDES IN PARTICULATE FORM3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM3/4.11.3 MARK I CONTAINMENT3/4.11.4 TOTAL DOSE3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAM3/4.12.2 LAND USE CENSUS3/4.12.3 INTERLABORATORY COMPARISON PROGRAM5.0 DESIGN FEATURES / SITE MAP6.0 ADMINISTRATIVE CONTROLS6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATINGREPORT (AREOR)6.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)6.3 RESPONSIBILITES122014 CY-OC-170-301Revision 6Page 4 of 140PART II -CALCULATIONAL METHODOLOGIES1.0 LIQUID EFFLEUNTS1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS1.2 LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION1.2.1 LIQUID EFFLUENT MONITORS1.2.2 SAMPLE RESULT SET POINTS1.2.3 ASSUMED DISTRIBUTION SET POINTS1.3 BATCH RELEASES1.4 CONTINUOUS RELEASES1.5 LIQUID EFFLUENT DOSE CALCULATION -10 CFR 501.5.1 MEMBER OF THE PUBLIC DOSE -LIQUID EFFLUENTS1.5.2 SHORELINE DEPOSIT DOSE1.5.3 SHORELINE DOSE EXAMPLE 11.5.3.1 SHORELINE DOSE EXAMPLE 21.5.4 INGESTION DOSE -LIQUID1.5.5 INGESTION DOSE CALCULATION EXAMPLE 11.5.5.1 INGESTION DOSE CALCULATION EXAMPLE 21.5.6 PROJECTED DOSE -LIQUID1.6 REPRESENTATIVE SAMPLES2 GASEOUS EFFLUENTS2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS2.2. GASEOUS EFFLUENT MONITOR SET POINT DETERMINATION2.2.1 PLANT VENT2.2.2 OTHER RELEASE POINTS2.2.3 RADIONUCLIDE MIX FOR SET POINTS2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATECALCULATIONS 10 CFR 202.3.1 SITE BOUNDARY DOSE RATE -NOBLE GASES2.3.1.1 TOTAL BODY DOSE RATE2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE2.3.1.3 SKIN DOSE RATE122014 CY-OC-170-301Revision 6Page 5 ofl1402.3.1.4 EXAMPLE SKIN DOSE RATE2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE ANDPARTICULATES2.3.2.1 METHOD -SITE BOUNDARY DOSE RATE -RADIOIODINE ANDPARTICULATES2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATECALCULATION2.4 NOBLE GAS EFFLUENT DOSE CALCULATION -10 CFR 502.4.1 UNRESTRICTED AREA DOSE -NOBLE GASES2.4.1.1 AIR DOSE METHOD2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION2.4.1.3 INDIVIDUAL PLUME DOSE METHOD2.5 RADIOIODINE PARTICULATE AND OTHER RADIONUCLIDES DOSECALCULATIONS -10 CFR 502.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES,ANDOTHER RADIONUCLIDES2.5.2 EXAMPLE CALCULATION -INHALATION OF RADIOIODINES,TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES2.5.3 INGESTION OF RADIOIODINES, PARTICULATES ANDOTHER RADIONUCLIDES2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGEAND VEGETATION -OTHER THAN TRITIUM2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THERADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION -OTHER THAN TRITIUM2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE ANDVEGETATION2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM INANIMAL FORAGE AND VEGETATION2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THERADIONUCLIDE IN MILK AND MEAT2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, ANDVEGETABLES2.5.3.8 EXAMPLE CALCULATION -DOSE FROM CONSUMPTION OFMILK, MEAT, AND VEGETABLES2.5.4 GROUND PLANE DEPOSITION IRRADIATION122014 CY-OC-170-301Revision 6Page 6 of 1402.5.4.12.5.4.22.5.4.32.5.4.4GROUND PLANE CONCENTRATIONEXAMPLE GROUND PLANE CONCENTRATION CALCULATIONGROUND PLANE DOSEEXAMPLE GROUND PLANE DOSE2.6PROJECTED DOSES -GASEOUS3 TOTAL DOSE TO MEMBERS OF THE PUBLIC -40 CFR 1903.1 EFFLUENT DOSE CALCULATIONS3.2 DIRECT EXPOSURE DOSE DETERMINATION4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMAPPRENDIX A -DERIVED DOSE FACTORS AND RECEPTOR LOCATIONSTable A-I:Table A-2:Table A-3:Table A-4:Table A-5:Dose Conversion Factors for Deriving Radioactive NobleGas Radionuclide-To-Dose Equivalent Rate FactorsNoble Gas Radionuclide-To-Dose Equivalent Rate FactorsAir Dose Conversion Factors for Effluent Noble GasLocations Associated with Maximum Exposure of a Member ofThe PublicCritical Receptor Noble Gas Dose Conversion FactorsAPPENDIX B -MODELING PARAMETERSTable B-I:Table B-2:OCGS Usage Factors for Individual Dose AssessmentMonthly Average Absolute Humidity g/m3APPENDIX C -REFERENCESTable C-1: REFERENCESAPPENDIX D -SYSTEM DRAWINGSFigure D-l-la:Figure D-1-1 b:Figure D-l-lc:Figure D-1-2:Figure D-2-1:Figure D-2-2:Figure D-2-3:Liquid Radwaste Treatment Chem Waste and FloorDrain SystemLiquid Radwaste Treatment -High Purity and EquipmentDrain SystemGroundwater Remediation SystemSolid Radwaste Processing SystemGaseous Radwaste Treatment -Augmented Offgas SystemVentilation SystemAOG Ventilation System122014 CY-OC-170-301Revision 6Page 7 of 140APPENDIX E -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -SAMPLETYPE AND LOCATIONTable E-1:Figure E-1:Figure E-2:Figure E-3:Figure E-4:REMP Sample LocationsOyster Creek Generating Station REMP Sample Locations within a1 Mile RadiusOyster Creek Generating Station REMP Sample Locations within a1 to 5 Mile RadiusOyster Creek Generating Station REMP Sample Locations over a 5Mile RadiusArea Plot Plan of Site122014 CY-OC-170-301Revision 6Page 8 of 140OYSTER CREEK GENERATING STATIONOFF SITE DOSE CALCULATION MANUALINTRODUCTIONThe Oyster Creek Off Site Dose Calculation Manual (ODCM) is an implementing document tothe Oyster Creek Technical Specifications. The previous Limiting Conditions for Operationsthat were contained in the Radiological Effluent Technical Specifications (RETS) are nowincluded in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts:Part I -Radiological Effluent Controls, and Part II -Calculational Methodologies.Part I includes the following:" The Radiological Effluent Controls and the Radiological Environmental MonitoringPrograms required by Technical Specifications 6.8.4" Descriptions of the information that should be included in the Annual Radioactive EffluentRelease Report and the Annual Radiological Environmental Operating Report requiredby Technical Specifications 6.9.1.d and 6.9.1.e, respectively.Part II describes methodologies and parameters used for:" The calculation of radioactive liquid and gaseous effluent monitoring instrumentationalarm/trip set points; and" The calculation of radioactive liquid and gaseous concentrations, dose rates, cumulativeyearly doses, and projected doses.Part II also contains a list and graphical description of the specific sample locations for theradiological environmental monitoring program (REMP), and the liquid and gaseous wastetreatment systems and discharge points.122014 CY-OC-170-301Revision 6Page 9 of140PART I -RADIOLOGICAL EFFLUENT CONTROLS1.0 DEFINITIONSThe following terms are defined so that uniform interpretation of these CONTROLS maybe achieved. The defined terms appear in capitalized type and are applicablethroughout these CONTROLS.1.1 OPERABLE -OPERABILITYA system, subsystem, train, component or device shall be OPERABLE or haveOPERABILITY when it is capable of performing its specified function(s). Implicitin the definition shall be the assumption that all necessary attendantinstrumentation, controls, normal and emergency electrical power sources,cooling or seal water, lubrication or other auxiliary equipment that are required forthe system, subsystem, train, component or device to perform its function(s) arealso capable of performing their related support function(s).A verification of OPERABILITY is an administrative check, by examination ofappropriate plant records (logs, surveillance test records) to determine that asystem, subsystem, train, component or device is not inoperable. Suchverification does not preclude the demonstration (testing) of a given system,subsystem, train, component or device to determine OPERABILITY.1.2 ACTIONACTION shall be that part of a CONTROL that prescribes remedial measuresrequired under designated conditions.1.3 CHANNEL CALIBRATIONA CHANNEL CALIBRATION shall be the adjustment, as necessary, of thechannel output such that it responds, with acceptable range and accuracy, toknown values of the parameter that the channel monitors. The CHANNELCALIBRATION shall encompass the entire channel, including equipmentactuation, alarm, or trip.1.4 CHANNEL CHECKA CHANNEL CHECK shall be a qualitative determination of acceptable operabilityby observation of channel behavior during operation. This determination shallinclude, where possible, comparison of the channel with other independentchannels measuring the same variable.122014 CY-OC-170-301Revision 6Page 10 of 1401.5 CHANNEL FUNCTIONAL TESTCHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal intothe channel to verify its proper response including, where applicable, alarm and/ortrip initiating actions.1.6 CONTROLThe Limiting Conditions for Operation (LCOs) that were contained in theRadiological Effluent Technical Specifications were transferred to the OFF SITEDOSE CALCULATION MANUAL (ODCM) and were renamed CONTROLS. Thisis to distinguish between those LCOs that were retained in the TechnicalSpecifications and those LCOs or CONTROLS that were transferred to theODCM.1.7 FREQUENCY NOTATIONThe FREQUENCY NOTATION specified for the performance of SurveillanceRequirements shall correspond to the intervals defined in Table 1.1.1.8 REPORTABLE EVENTA REPORABLE EVENT shall be any of those conditions specified Section 50.73to 10CFR Part 50.1.9 SOURCE CHECKSOURCE CHECK shall be the qualitative assessment of channel response whenthe channel sensor is exposed to a source of increased radioactivity.1.10 AUGMENTED OFF GAS SYSTEM (AOG)The AUGMENTED OFF GAS SYSTEM is designed and installed to holdup and/orprocess radioactive gases from the main condenser off gas system for thepurpose of reducing the radioactive material content of the gases before releaseto the environs.1.11 MEMBER (S) OF THE PUBLICMEMBER (S) OF THE PUBLIC shall include all persons who are notoccupationally associated with Exelon Generation and who do not normallyfrequent the Oyster Creek Generating Station site. This category does not includeemployees of the utility, its contractors, contractor employees, vendors, orpersons who enter the site to make deliveries, to service equipment, work on siteor for other purposes associated with plant functions. This category does includepersons who use portions of the site for recreational, occupational, or other122014 CY-OC-170-301Revision 6Page 11 of 140purposes not associated with the plant. An individual is not a member of thepublic during any period in which the individual receives an occupational dose.1.12 OFF SITE DOSE CALCULATION MANUAL (ODCM)The OFF SITE DOSE CALCULATION MANUAL (ODCM) shall contain themethodology and parameters used in the calculation of Off Site doses due toradioactive gaseous and liquid effluents, in the calculation of gaseous and liquideffluent monitoring Alarm/Trip Set points, and in the conduct of the RadiologicalEnvironmental Monitoring Program. The ODCM shall also contain (1) theRadioactive Effluent Controls and Radiological Environmental MonitoringPrograms required by Technical Specification Section 6.8.4 and (2) descriptionsof the information that should be included in the Annual Radioactive EffluentRelease Report AND Annual Radiological Environmental Operating Reportrequired by Technical Specification Sections 6.9.1.d and 6.9.1.e, respectively.1.13 PURGE-PURGINGPURGE or PURGING shall be the controlled process of discharging air or gasfrom a confinement and replacing it with air or gas.1.14 SITE BOUNDARYThe SITE BOUNDARY shall be the perimeter line around OCGS beyond whichthe land is neither owned, leased, nor otherwise subject to control by ExelonGeneration. The area outside the SITE BOUNDARY is termed OFF SITE orUNRESTRICTED AREA.1.15 OFF SITEThe area that is beyond the site boundary where the land is neither owned, leasednor otherwise subject to control by Exelon Generation. Can be interchanged withUNRESTRICTED AREA.1.16 UNRESTRICTED AREAAn UNRESTRICTED AREA shall be any area at or beyond the SITEBOUNDARY, access to which is not controlled by the licensee for purposes ofprotection of individuals from exposure to radiation and radioactive materials, orany area within the SITE BOUNDARY used for residential quarters or forindustrial, commercial, institutional, and/or recreational purposes. Can beinterchanged with OFF SITE.122014 CY-OC-170-301Revision 6Page 12 of 1401.17 DOSE EQUIVALENT 1-131DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (micro curies pergram), which alone would produce the same thyroid dose as the quantity andisotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. Thethyroid dose conversion factors used for this calculation shall be those listed inTable E-7 of Regulatory Guide 1.109, "Calculation of Annual Doses to Man fromRoutine Releases of Reactor Effluences for the Purpose of EvaluatingCompliance with 10CFR Part 40 Appendix I."1.18 DEPOSITION (D/Q)The direct removal of gaseous and particulate species on land or water surfaces.DEPOSITION is expressed as a quantity of material per unit area (e.g. m2).1.19 DOSE CONVERSION FACTOR (DCF)A parameter calculated by the methods of internal dosimetry, which indicates thecommitted dose equivalent (to the whole body or organ) per unit activity inhaled oringested. This parameter is specific to the isotope and the dose pathway. DOSECONVERSION FACTORS are commonly tabulated in units of mrem/hr perpicocurie/m3 in air or water. They can be found in Reg Guide 1.109 appendices.1.20 EFFLUENT CONCENTRATION (EC)The liquid and air concentration levels which, if inhaled or ingested continuouslyover the course of a year, would produce a total effective dose equivalent of 0.05rem. LEC refers to liquid EFFLUENT CONCENTRATION.1.21 ELEVATED (STACK) RELEASEAn airborne effluent plume whose release point is higher than twice the height ofthe nearest adjacent solid structure and well above any building wake effects soas to be essentially unentrained. Regulatory Guide 1.111 is the basis of thedefinition of an ELEVATED RELEASE. Elevated releases generally will notproduce any significant ground level concentrations within the first few hundredyards of the source. ELEVATED RELEASES generally have less doseconsequence to the public due to the greater downwind distance to the groundconcentration maximum compared to ground releases. All main stack releases atthe OCGS are ELEVATED RELEASES.1.22 FINITE PLUME MODELAtmospheric dispersion and dose assessment model which is based on theassumption that the horizontal and vertical dimensions of an effluent plume arenot necessarily large compared to the distance that gamma rays can travel in air.It is more realistic than the semi-infinite plume model because it considers the122014 CY-OC-170-301Revision 6Page 13 of 140finite dimensions of the plume, the radiation build-up factor, and the airattenuation of the gamma rays coming from the cloud. This model can estimatethe dose to a receptor who is not submerged in the radioactive cloud. It isparticularly useful in evaluating doses from an elevated plume or when thereceptor is near the effluent source.1.23 GROUND LEVEL (VENT) RELEASEAn airborne effluent plume which contacts the ground essentially at the point ofrelease either from a source actually located at ground elevation or from a sourcewell above the ground elevation which has significant building wake effects tocause the plume to be entrained in the wake and driven to the ground elevation.GROUND LEVEL RELEASES are treated differently than ELEVATEDRELEASES in that the X/Q calculation results in significantly higherconcentrations at the ground elevation near the release point.1.24 OCCUPATIONAL DOSEThe dose received by an individual in a RESTRICTED AREA or in the course ofemployment in which the individual's assigned duties involve exposure toradiation and to radioactive material from licensed and unlicensed sources ofradiation, whether in the possession of the licensee or other person. Occupationaldose does not include dose received from background radiation, as a patient frommedical practices, from voluntary participation in medical research programs, oras a member of the general public1.25 "OPEN DOSE"A routine effluent dosimetry computer program that uses Reg.Guides 1.109 and 1.111 methodologies.1.26 RAGEMS (RADIOACTIVE EMISSIONS MONITORING SYSTEM)A plant system that monitors gaseous effluent releases from monitored releasepoints. There is a RAGEMS system for the main stack (RAGEMS I) and one forthe turbine building (RAGEMS II). They monitor particulates, iodine's, and noblegases.1.27 SEMI-INFINITE PLUME MODELDose assessment model with the following assumptions. The ground isconsidered to be an infinitely large flat plate and the receptor is located at theorigin of a hemispherical cloud of infinite radius. The radioactive cloud is limitedto the space above the ground plane. The semi-infinite plume model is limited toimmersion dose calculations.1.28 SOURCE TERM122014 CY-OC-170-301Revision 6Page 14 of 140The activity release rate, or concentration of an actual release or potentialrelease. The common units for the source term are curies, curies per second, andcuries per cubic centimeter, or multiples thereof (e.g., micro curies).1.29 X/Q -("CHI over Q")The dispersion factor of a gaseous release in the environment calculated by apoint source Gaussian dispersion model. Normal units of X/Q are sec/m3.TheX/Q is used to determine environmental atmospheric concentrations bymultiplying the source term, represented by Q (in units of ýiCi/sec or Ci/sec).Thus, the plume dispersion, X/Q (seconds/cubic meter) multiplied by the sourceterm, Q (uCi/seconds) yields an environmental concentration, X (itCi/m3). X/Q isa function of many parameters including wind speed, stability class, release pointheight, building size, and release velocity.1.30 SEEDS (Simplified Effluent Environmental Dosimetry System)A routine effluent dosimetry computer program that uses Reg. Guides 1.109 and1.111 methodologies.TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION *NOTATION FREQUENCYS At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.W At least once per 7 days.M At least once per 31 days.Q At least once per 92 days.SA At least once per 184 days.A At least once per 366 days.R At least once per 18 months (550 days).1/24 At least once per 24 months (refueling cycle)S/U Prior to each reactor startup.P Prior to each radioactive release.N.A. Not applicable.* Each surveillance requirement shall be performed within the specified timeinterval with a maximum allowable extension not to exceed 25% of thesurveillance interval.122014 CY-OC-170-301Revision 6Page 15 of 1403/4 CONTROLS AND SURVEILLANCE REQUIREMENTS3/4.0 APPLICABILITYCONTROLS3.0.1 Compliance with the CONTROLS contained in the succeeding CONTROLS isrequired during the OPERATIONAL CONDITIONS or other conditions specifiedtherein; except that upon failure to meet the CONTROL, the associated ACTIONrequirements shall be met.3.0.2 Noncompliance with a CONTROL shall exist when the requirements of the CONTROLand associated ACTION requirements are not met within the specified time intervals.If the CONTROL is restored prior to expiration of the specified time intervals,completion of the ACTION requirements is not required.3.0.3 Except as provided in the associated ACTION requirements, when a CONTROL is notmet or the associated ACTION requirements cannot be satisfied, action shall beinitiated to place the unit into COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.Where corrective measures are completed that permit operation under the ACTIONrequirements, the ACTION may be taken in accordance with the specified time limitsas measured from the time of failure to meet the CONTROL. Exceptions to theserequirements are stated in the individual CONTROLS.This CONTROL is not applicable in COLD SHUTDOWN or REFUELING.3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not bemade when the conditions of the CONTROLS are not met and the associatedACTION requires a shutdown if they are not met within a specified time interval. Entryinto an OPERATIONAL CONDITION or other specified condition may be made inaccordance with ACTION requirements when conformance to them permits continuedoperation of the facility for an unlimited period of time. This provision shall not preventpassage through or to OPERATIONAL CONDITIONS as required to comply withACTION requirements. Exceptions to these requirements are stated in the individualCONTROLS.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONSmay be returned to service under administrative control solely to perform testing todemonstrate its OPERABILITY or the OPERABILITY of other equipment. This is anexception to CONTROL 3.0.2 for the system returned to service under administrativecontrol to perform the testing required to demonstrate OPERABILITY.122014 CY-OC-1 70-301Revision 6Page 16 of 1403/4.0 APPLICABILITYSURVEILLANCE REQUIREMENTS4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS orother conditions specified for individual CONTROLS unless otherwise stated in anindividual Surveillance Requirement.4.0.2 Each Surveillance Requirement shall be performed within the specified surveillanceinterval with a maximum allowable extension not to exceed 25 percent of the specifiedsurveillance interval.4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval,defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITYrequirements for a CONTROL. The time limits of the ACTION requirements areapplicable at the time it is identified that a Surveillance Requirement has not beenperformed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permitthe completion of the surveillance when the allowed outage time limits of the ACTIONrequirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to beperformed on inoperable equipment.4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable conditionshall not be made unless the Surveillance Requirement(s) associated with theCONTROLS have been performed within the applicable surveillance interval or asotherwise specified. This provision shall not prevent passage through or toOPERATIONAL CONDITIONS as required to comply with ACTION requirements.122014 CY-OC-170-301Revision 6Page 17 of 1403/4.3 INSTRUMENTATION3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONCONTROLS3.3.3.10 In accordance with Oyster Creek Technical Specifications 6.8.4.a.1, the radioactiveliquid effluent monitoring instrumentation channels shown in Table 3.3.3.10-1 shallbe OPERABLE with their Alarm/Trip set points set to ensure that the limits ofCONTROL 3.11.1.1 are not exceeded. The Alarm/Trip set points of these channelsshall be determined and adjusted in accordance with the methodology andparameters in the ODCM Part II section 1.2.1.APPLICABILITY: During all liquid releases via these pathways.ACTION:a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Tripset point less conservative than required by the above CONTROL, immediatelysuspend the release of radioactive liquid effluents monitored by the affectedchannel, or declare the channel inoperable, or change the set point so it isacceptably conservative, or provide for manual initiation of the Alarm/Tripfunction(s).b. With less than the minimum number of radioactive liquid effluent monitoringinstrumentation channels OPERABLE, take the ACTION shown in Table3.3.3.10-1. Make every reasonable effort to return the instrument to OPERABLEstatus within 30 days and, if unsuccessful, explain in the next Radioactive EffluentRelease Report pursuant to Technical Specification 6.9.1 .d why the inoperabilitywas not corrected in a timely manner.c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable. Report alldeviations in the Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at theFrequencies shown in Table 4.3.3.10-1.122014 CY-OC-1 70-301Revision 6Page 18 of 140TABLE 3.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSOPERABLEINSTRUMENT1. RADIOACTIVITY MONITORS PROVIDING ALARM ANDAUTOMATIC TERMINATION OF RELEASEa. Liquid Radwaste Effluent Line (DELETED)b. Turbine Building Sump No. 1-5 (DELETED)2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOTPROVIDING AUTOMATIC TERMINATION OF RELEASEa. Reactor Building Service Water System Effluent Line3. FLOW RATE MEASUREMENT DEVICESa. Liquid Radwaste Effluent Line (DELETED)b. Groundwater Remediation Release PathACTIONN/AN/A1N/A1N/AN/A112N/A115122014 CY-OC-170-301Revision 6Page 19 of 140TABLE 3.3.3.10-1 (Continued)TABLE NOTATIONSACTION 110ACTION 112ACTION 113ACTION 114With no channels OPERABLE, effluent releases via this pathway may continueprovided that:a. At least two independent samples are taken, one prior to discharge andone near the completion of discharge and analyzed in accordance withSURVEILLANCE REQUIREMENT 4.11.1.1.1.b. Before initiating a release, at least two technically qualified members ofthe Facility Staff independently verify the release rate calculations anddischarge line valving;Otherwise, suspend release of radioactive effluents via this pathway.With no channels OPERABLE, effluent releases via this pathway may continueprovided that, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, grab samples are collected andanalyzed for radioactivity at a limit of detection specified by Table 4.11.1.1.1-1.With no channel OPERABLE, effluent releases via the affected pathway maycontinue provided the flow is estimated with the pump curve or change in tanklevel, at least once per batch during a release.With no channel OPERABLE effluent may be released provided that beforeinitiating a release:a. A sample is taken and analyzed in accordance with SURVEILLANCEREQUIREMENT 4.11.1.1.1.b. Qualified personnel determine and independently verify the acceptablerelease rate.With no channel OPERABLE, effluent releases via this pathway may continueprovided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actualreleases. Pump performance curves may be used to estimate flow.ACTION 115122014 CY-OC-1 70-301Revision 6Page 20 of 140TABLE 4.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCEREQUIREMENTSaCHANNELCHECKSOURCE CHANNELCHECK CALIBRATIONCHANNELFUNCTIONALTESTINSTRUMENT1. RADIOACTIVITY MONITORS PROVIDING ALARM ANDAUTOMATIC TERMINATION OF RELEASEa. Liquid Radwaste Effluent Line (DELETED)b. Turbine Building Sump No. 1-5 (DELETED)N/AN/AN/AN/AN/AN/AN/AN/A2. RADIOACTIVITY MONITORS PROVIDING ALARM BUTNOT PROVIDING AUTOMATIC TERMINATION OF RELEASEa. Reactor Building Service Water System Effluent Line D3. FLOW RATE MEASUREMENT DEVICESa. Liquid Radwaste Effluent Line (DELETED)b. Groundwater Remediation Release pathMN/AN/AReN/ADfN/ARfN/AN/A122014 CY-OC-170-301Revision 6Page 21 of 140TABLE 4.3.3.10-1 (Continued)TABLE NOTATIONSa. Instrumentation shall be OPERABLE and in service except that a channel may be takenout of service for the purpose of a check, calibration, test or maintenance without declaringit to be inoperable.d. The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarmannunciation occurs if any of the following conditions exists:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a downscale failure.3. Instrument controls not set in operate mode.4. Instrument electrical power loss.e. The CHANNEL CALIBRATION shall be performed according to established calibrationprocedures.f. While actively discharging through this pathway.122014 CY-OC-170-301Revision 6Page 22 of 1403/4.3 INSTRUMENTATION3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONCONTROLS3.3.3.11 In accordance with Oyster Creek Technical Specifications 6.8.4.a. 1, the radioactivegaseous effluent monitoring instrumentation channels shown in Table 3.3.3.11-1shall be OPERABLE with their alarm/trip set points set to ensure that the limits ofCONTROL 3.11.2.1 are not exceeded. The alarm/trip set points of these channelsmeeting CONTROLS 3.11.2.1 shall be determined and adjusted in accordance withthe methodology and parameters in the ODCM Part II Section 2.2.APPLICABILITY: As shown in Table 3.3.3.11-1ACTION:a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/tripset point less conservative than required by the above CONTROL, immediatelysuspend the release of radioactive gaseous effluents monitored by the affectedchannel, or declare the channel inoperable, or change the set point so it isacceptably conservative.b. With less than the minimum number of radioactive gaseous effluent monitoringinstrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.11-1. Exert best efforts to return the instrument to OPERABLE status within 30 daysand, if unsuccessful, explain in the next Radioactive Effluent Release Reportpursuant to Technical Specification 6.9.1 .d why this inoperability was not correctedin a timely manner.c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable. Report alldeviations in the Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TESToperations at the frequencies shown in Table 4.3.3.11-1.122014 CY-OC-1 70-301Revision 6Page 23 of 140TABLE 3.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSINSTRUMENT OPERAE1. DELETED2. STACK MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) 1b. Iodine Sampler ic. Particulate Sampler 1d. Effluent Flow Measuring Device 1e. Sample Flow Measuring Device 13. TURBINE BUILDING VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) 1b. Iodine Sampler 1c. Particulate Sampler 1d. Effluent Flow Measuring Device 1e. Sample Flow Measuring Device 13LEa APPLICABILITY ALCTIONb,eb,eb,ebbbbbbb124127127122128123127127122128122014 CY-OC-170-301Revision 6Page 24 of 140TABLE 3.3.3.11-1(Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSINSTRUMENT OPERABLEa APPLICABILITY ACTION4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor 1 b 123b. Iodine Sampler 1 b 127c. Particulate Sampler 1 b 127d. Sample Flow Measuring Device 1 b 128122014 CY-OC-170-301Revision 6Page 25 of 140TABLE 3.3.3.11-1 (Continued)TABLE NOTATIONSa. Channels shall be OPERABLE and in service as indicated except that a channel may betaken out of service for the purpose of a check, calibration, test maintenance or samplemedia change without declaring the channel to be inoperable.b. During releases via this pathwaye. Monitor / sampler or an alternate shall be OPERABLE to monitor / sample Stack effluentwhenever the drywell is being purged.ACTION 122ACTION 123ACTION 124ACTION 127ACTION 128With no channel OPERABLE, effluent releases via this pathway may continueprovided the flow rate is estimated whenever the exhaust fan combination in thissystem is changed.With no channel OPERABLE, effluent releases via this pathway may continueprovided a grab sample is taken at least once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and is analyzed forgross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter or provided an alternate monitoringsystem with local display is utilized.With no channel OPERABLE, effluent releases via this pathway may continueprovided a grab sample is taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for grossradioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or provided an alternate monitoring system with localdisplay is utilized. Drywell purge is permitted only when the radioactive noblegas monitor is operating.With no channel OPERABLE, effluent releases via this pathway may continueprovided the required sampling is initiated with auxiliary sampling equipment assoon as reasonable after discovery of inoperable primary sampler(s).With no channel OPERABLE, effluent releases via the sampled pathway maycontinue provided the sampler air flow is estimated and recorded at least onceper day.122014 CY-OC-1 70-301Revision 6Page 26 of 140TABLE 4.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNEL MODES IN WHICHCHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCEINSTRUMENT CHECK CHECK CALIBRATION TEST REQUIREDa1. DELETED2. MAIN STACK MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qh bb. Iodine Sampler W N.A. N.A. N.A. bc. Particulate Sampler W N.A. N.A. N.A. bd. Effluent Flow Measuring Device D N.A. 1/24 Q be. Sample Flow Measuring Device D N.A. R Q b3. TURBINE BUILDING VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qi bb. Iodine Sampler W N.A. N.A. N.A. bc. Particulate Sampler W N.A. N.A. N.A. bd. Effluent Flow Measuring Device D N.A. 1/24 Q be. Sample Flow Measuring Device D N.A. R Q b122014 CY-OC-1 70-301Revision 6Page 27 of 140TABLE 4.3.3.11-1 (Continued)RADIOACTIVE'GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNELINSTRUMENT CHECKCHANNELSOURCE CHANNEL FUNCTIONALCHECK CALIBRATION TESTMODES IN WHICHSURVIELLANCE ISREQUIRED a4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEMa. Radioactive Noble Gas Monitor D M Rfb. Iodine Sampler W N.A. N.A.c. Particulate Sampler W N.A. N.A.d. Sample Flow Measuring Device D N.A. RQeN.A.N.A.N.A.bbbb122014 CY-OC-170-301Revision 6Page 28 of 140TABLE 4.3.3.11-1 (Continued)TABLE NOTATIONSa. Instrumentation shall be OPERABLE and in service except that a channel may be takenout of service for the purpose of a check calibration, test or maintenance withoutdeclaring it to be inoperable.b. During releases via this pathway.e. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarmannunciation occurs if any of the following conditions exist:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a downscale failure.3. Instrument controls not set in operate mode.4. Instrument electrical power loss.f. The CHANNEL CALIBRATION shall be performed according to established calibrationprocedures.h. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarmannunciation occurs if any of the following conditions exists:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a low count rate/monitor failure.3. Switch cover alarm shall be verified to alarm when the cover is opened; and clearwhen the cover is closed after the faceplate switches are verified in their correctpositions.The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarmannunciation occurs if any of the following conditions exists:1. Instrument indicates measured levels above the alarm set point.2. Instrument indicates a low count rate/monitor failure.122014 CY-OC-170-301Revision 6Page 29 of 1403/4.11RADIOACTIVE EFFLUENTS3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATIONCONTROLS3.11.1.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.2 and 3, theconcentration of radioactive material, other than noble gases, in liquid effluent in thedischarge canal at the Route 9 bridge (See Figure E-4) shall not exceed theconcentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. Theconcentration of noble gases dissolved or entrained in liquid effluent in the dischargecanal at the Route 9 bridge shall not exceed 2E-4 microcuries/milliliter.APPLICABILITY: At all times.ACTION:a. In the event the concentration of radioactive material in liquid effluent released intothe Off Site area beyond the Route 9 bridge exceeds either of the concentrationlimits above, reduce the release rate without delay to bring the concentration belowthe limit.b. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the samplingand analysis program in Table 4.11.1.1.1-1.Alternately, pre-release analysis of batches(es) of radioactive liquid waste may be bygross beta or gamma counting provided a maximum concentration limit of 1 E-8gCi/ml in the discharge canal at the Route 9 bridge is applied.4.11.1.1.24.11.1.1.3The results of the radioactivity analyses shall be used in accordance with themethodology and parameters in the ODCM Part II Section 1.2 to assure that theconcentrations at the point of release are maintained within the limits of CONTROL3.11.1.1 and 3.11.1.2.The alarm or trip set point of each radioactivity monitoring channel in Table 3.3.3.10-1shall be determined on the basis of sampling and analyses results obtainedaccording to Table 4.11.1.1.1-1 and the set point method in ODCM Part 111.2.1 andset to alarm or trip before exceeding the limits of CONTROL 3.11.1.1.122014 CY-OC-170-301Revision 6Page 30 of 140TABLE 4.11.1.1.1-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMMinimum Lower LimitLiquid Release Type Sampling Analysis Type of Activity Analysis Detectiona (LLD)Frequency Frequency (P.Ci/ml)P pC Principal Gamma Emitters 5E-071. Batch WasteRelease Tanks Each Batchb Each Batch 1-131 5E-07M Dissolved and EntrainedOne Gases (Gamma Emitters) 1 E-05Batch/MbP M H-3 1 E-05Each Batchb Composited Gross Alpha 1 E-07P Q Sr-89, Sr-90 5E-08Each Batchb Composited Fe-55 1 E-06W Principal Gamma Emitters 5E-072. ContinuousRelease Grab W 1-131 5E-07a. Reactor Building Samplee-Service Water H-3 1 E-05EffluentGross Alpha 1E-07M(note f) CompositegFe-55 1 E-063. Groundwater uoush D Principal Gamma Emitters 5E-07Remediation Pathway ContinuoussteH-" E0Composite H-3 1 E-05a. ContinuousGross Alpha 1E-07M Sr-89, Sr-90 5E-08MCompositeg Fe-55 1 E-06Ni-63 1E-06b. Batch Release P P Principal Gamma Emitters 5E-07Tank Each Batchb Each Batch H-3 1E-05Gross Alpha 1 E-07P M Sr-89, Sr-90 5E-08Each Batchb Composited Fe-55 1E-06Ni-63 1 E-06122014 CY-OC-170-301Revision 6Page 31 of 140TABLE 4.11.1.1-1 (CONTINUED)TABLE NOTATIONSa. The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as thesmallest concentration of radioactive material in a sample that will yield a net count, abovesystem background, that will be detected with 95 percent probability with only 5 percentprobability of falsely concluding that a blank observation represents a "real" signal.The LLD is applicable to the capability of a measurement system under typical conditionsand not as a limit for the measurement of a particular sample in the radioactive liquid wastesampling and analyses program.For a particular measurement system, which may include radiochemical separation:LLD~ 4.66
- SbE
- V
- 2.22E6
- Y
- exp(-kAt)Where:LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),Sb is the standard deviation of the background counting rate or of the counting rate of a blanksample as appropriate (counts per minute),E is the counting efficiency,V is the sample size (units of mass or volume),2.22E+6 is the number of disintegrations per minute per microcurie,Y is the fractional radiochemical yield, when applicable,Xk is the radioactive decay constant for the particular radionuclide, andAt is the elapsed time between the end of the sample collection and the time of counting.Analyses shall be performed in such a manner that the stated LLDs will be achieved underroutine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Ce-141, Cs-134, Cs-137; and an LLD of 5E-6 iýCi/ml shouldtypically be achieved for Ce-144.122014 CY-OC-170-301Revision 6Page 32 of 140TABLE 4.11.1.1.1-1 (CONTINUED)TABLE NOTATIONSOccasionally, background fluctuations, interfering radionuclides, or other uncontrollablecircumstances may render these LLD's unachievable.When calculating the LLD for a radionuclide determined by gamma ray spectrometry, thebackground may include the typical contributions of other radionuclides normally present inthe sample. The background count rate of a semiconductor detector (e.g. HPGe) isdetermined from background counts that are determined to be within the full width of thespecific energy band used for the quantitative analysis for the radionuclide.The principal gamma emitters for which the LLD specification will apply are exclusively thefollowing radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected andreported. Other peaks that are measurable and identifiable, together with the abovenuclides, shall be identified and reported. The LLD for Ce-144 is 5E-6 gCi/mL whereas theLLD for Mo-99 and the other gamma emitters is 5E-7 p.Ci/mL. Nuclides that are below theLLD for the analysis should not be reported.b. A batch release is the discharge of liquid wastes of a discrete volume. Before sampling foranalysis, each batch should be thoroughly mixed.c. In the event a gross radioactivity analysis is performed in lieu of an isotopic analysis before abatch is discharged, a sample will be analyzed for principal gamma emitters afterwards.d. A composite sample is one in which the quantity of liquid sampled is proportional to thequantity of liquid waste discharged and in which the method of sampling employed results ina specimen which is representative of the liquids released.e. Analysis may be performed after release.f. In the event a grab sample contains more than 5E-7 ýiCi/mL of 1-131 and principal gammaemitters or in the event the Reactor Building Service Water radioactivity monitor indicatesmore than 5E-7 gCi/mL radioactivity in the effluent, as applicable, sample the elevatedactivity effluent daily until analysis confirms the activity concentration in the effluent does notexceed 5E-7 ltCi/mL. In addition a composite sample must be made up for further analysisfor all samples taken when the activity was > 5E-7 itCi/mL.g. A composite sample is produced combining grab samples, each having a defined volume,collected routinely from the sump or stream being sampledh. Aliquot sampling shall be at least hourly to be representative of the quantities andconcentrations of radioactive materials in liquid effluent. Prior to analyses, all samples takenfor the composite shall be thoroughly mixed in order for the composite samples to berepresentative of the effluent release.122014 CY-OC-170-301Revision 6Page 33 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.1.2 DOSECONTROLS3.11.1.2 In accordance with Oyster Creek Technical Specifications 6.8.4.a.4 and 5, the doseor dose commitment to a MEMBER OF THE PUBLIC from radioactive materials inliquid effluents released to UNRESTRICTED AREAS (see Figure E-4) shall belimited:a. During any calendar quarter to less than or equal to 1.5 mrem to the Total Body andto less than or equal to 5 mrem to any body organ, andb. During any calendar year to less than or equal to 3 mrem to the Total Body and toless than or equal to 10 mrem to any body organ.APPLICABILITY: At all times.ACTION:a. With the calculated dose from the release of radioactive materials in liquid effluentsexceeding any of the above limits, prepare and submit to the Commission within 30days from the end of the quarter, pursuant to Technical Specification 6.9.2, aSpecial Report that identifies the cause(s) for exceeding the limit(s) and defines thecorrective actions that have been taken and/or will be taken to reduce the releasesand the proposed corrective actions to be taken to assure that subsequent releaseswill be in compliance with the above limits.b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarterand the current calendar year shall be determined in accordance with themethodology and parameters in the ODCM Part II Section 1.5 at least once per 31days in accordance with Technical Specification 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 34 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEMCONTROLS3.11.1.3 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.6, the liquidradwaste treatment system shall be OPERABLE and appropriate portions of thesystem shall be used to reduce releases of radioactivity when projected doses due tothe liquid effluent to UNRESTRICTED AREAS (see Figure E-4) would exceed 0.06mrem to the Total Body or 0.2 mrem to any organ in a 31 day period.APPLICABILITY: At all times.ACTION:a. With radioactive liquid waste being discharged without treatment and in excess ofthe above, prepare and submit to the Commission within 30 days, pursuant toTechnical Specification 6.9.2, a Special Report that includes the followinginformation:1. Explanation of why liquid radwaste was being discharged without treatment,identification of any inoperable equipment or subsystems, and the reason forthe inoperability,2. Action(s) taken to restore the inoperable equipment to OPERABLE status,and3. Summary description of action(s) taken to prevent a recurrence.b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall beprojected at least once per 31 days in accordance with the methodology andparameters in the ODCM Part II Section 1.5 in accordance with TechnicalSpecifications 6.8.4.a.5.4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstratedOPERABLE by meeting CONTROLS 3.11.1.1, 3.11.1.2, and 3.11.1.3.122014 CY-OC-170-301Revision 6Page 35 of 1403/4.11RADIOACTIVE EFFLUENTS3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSE RATECONTROLS3.11.2.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.5 and 7, thedose rate due to radioactive materials released in gaseous effluents in theUNRESTRICTED AREA (see Figure E-4) shall be limited to the following:a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less thanor equal to 3000 mrem/yr to the skin, andb. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form withhalf-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any bodyorgan.APPLICABILITY: At all times.ACTION:a. With the dose rate(s) exceeding the above limits, immediately restore the releaserate to within the above limit(s).b. If the gaseous effluent release rate cannot be reduced to meet the above limits, thereactor shall be in at least SHUTDOWN CONDITION within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unlesscorrective actions have been completed and the release rate restored to below theabove limit.SURVEILLANCE REQUIREMENTS4.11.2.1.14.11.2.1.2The dose rate due to noble gases in gaseous effluents shall be determined to bewithin the above limits in accordance with the methodology and parameters in theODCM Part II Section 2.3.1.The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides inparticulate form with half-lives greater than 8 days in gaseous effluents shall bedetermined to be within the above limits in accordance with the methodology andparameters in the ODCM Part II Section 2.3.2 by obtaining representative samplesand performing analyses in accordance with the sampling and analysis programspecified in Table 4.11.2.1.2-1.4,11.2.1.3 Dose rates due to tritium, Sr-89, Sr-90, and alpha-emitting radionuclides areaveraged over no more than 3 months and the dose rate due to other radionuclides isaveraged no more than 31 days.122014 CY-OC-1 70-301Revision 6Page 36 of 140TABLE 4.11.2.1.2-1: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMMinimum Lower LimitGaseous Release Sampling Analysis Type of Activity Detectiona- (LLD)Type Frequency Frequency Analysis (jiCi/ml)QQ H-3 1 E-06Grab SamplefM PrincipalM GammaGrab Sample Emittersb (Noble 1 E-04c,d,f Gases)W 1-131 1E-12Continuousf CharcoalSaplI-133 1E-10SampleW PrincipalStack; GammaTurbine Building Continuous Particulate EmittersbExhaust Vents; (particulates)Augmented Off gas MeBuilding VentContinuousf Composite Gross Alpha 1E-11ParticulateSampleQeContinuous Composite Sr-89, Sr-90 1E-11ParticulateSampleNoble Gas Noble Gases 1 E-06Continuous GammaRadioactivity122014 CY-OC-1 70-301Revision 6Page 37 of 140TABLE 4.11.2.1.2-1 (Continued)TABLE NOTATIONSa. The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as thesmallest concentration of radioactive material in a sample that will yield a net count, abovesystem background, that will be detected with 95 percent probability with only 5 percentprobability of falsely concluding that a blank observation represents a "real" signal.The LLD is applicable to the capability of a measurement system under typical conditionsand not as a limit for the measurement of a particular sample in the radioactive liquid wastesampling and analyses program.For a particular measurement system which may include radiochemical separation:LLD =4.66
- SbE
- V
- 2.22E6
- Y
- exp(-kAt)Where:LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),Sb is the standard deviation of the background counting rate or of the counting rate of ablank sample as appropriate (counts per minute),E is the counting efficiency,V is the sample size (units of mass or volume),2.22E+6 is the number of disintegrations per minute per microcurie,Y is the fractional radiochemical yield, when applicable,k is the radioactive decay constant for the particular radionuclide, andAt is the elapsed time between the end of the sample collection and the time of counting.Analyses shall be performed in such a manner that the stated LLD's will be achieved underroutine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59,Co-58, Co-60, Zn-65, Cs-134, Cs-137, and Ce-141. Occasionally background fluctuations orother uncontrollable circumstances may render these LLD's unachievable.When calculating the LLD for a radionuclide determined by gamma ray spectrometry, thebackground may include the typical contributions of other radionuclides normally present inthe samples. The background count rate of a HpGe detector is determined from background122014 CY-OC-170-301Revision 6Page 38 of 140TABLE 4.11.2.1.2-1 (Continued)TABLE NOTATIONScounts that are determined to be within the full width of the specific energy band used for thequantitative analysis for that radionuclideb. The principal gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseousemissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, andCe-144 for particulate emissions. This list does not mean that only these nuclides are to beconsidered. Other gamma peaks that are identifiable, together with those of the abovenuclides, shall also be analyzed and reported in the Annual Radioactive Effluent ReleaseReport consistent with CONTROL 3.11.2.1. The LLD for Mo-99 and Ce-144 is 1E-10 ptCi/mlwhereas the LLD for other principal gamma emitting particulates is 1 E-1 1 jCi/ml.Radionuclides which are below the LLD for the analysis should not be reported.c. The noble gas radionuclides in gaseous effluent may be identified by taking a grab sample ofeffluent and analyzing it.d. In the event the reactor power level increases more than 15 percent in one hour and theStack noble gas radioactivity monitor shows an activity increase of more than a factor ofthree after factoring out the effect due to the change in reactor power, a grab sample of Stackeffluent shall be collected and analyzed.e. A composite particulate sample shall include an equal fraction of at least one particulatesample collected during each week of the compositing period.f. In the event a sample is collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, the LLD may be increased by a factorof 10.122014 CY-OC-170-301Revision 6Page 39 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.2.2 DOSE -NOBLE GASESCONTROLS3.11.2.2 In accordance with the Oyster Creek Technical Specification 6.8.4.a.5 and 8, the airdose due to noble gases released in gaseous effluents in the UNRESTRICTEDAREA (see Figure E-4) shall be limited to the following:a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation andless than or equal to 10 mrad for beta radiation and,b. During any calendar year: Less than or equal to 10 mrad for gamma radiation andless than or equal to 20 mrad for beta radiation.APPLICABILITY: At all times.ACTION:a. With the calculated air dose from radioactive noble gases in gaseous effluentsexceeding any of the above limits, prepare and submit to the Commission within 30days from the end of the quarter during which the release occurred, pursuant toTechnical Specification 6.9.2, a Special Report that identifies the cause(s) forexceeding the limit(s) and defines the corrective actions that have been taken toreduce the release and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the above limits.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendaryear for noble gases shall be determined in accordance with the methodology andparameters in the ODCM Part II Section 2.4.1 at least once per 31 days inaccordance with Technical Specification 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 40 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES INPARTICULATE FORMCONTROLS3.11.2.3 In accordance with Oyster Creek Technical Specification 6.8.4.a.5 and 9, the dose toa MEMBER OF THE PUBLIC from iodine-1 31, iodine-1 33, tritium, and allradionuclides in particulate form with half-lives greater than 8 days in gaseouseffluents released in the UNRESTRICTED AREA (see Figure E-4) shall be limited tothe following:a. During any calendar quarter: Less than or equal to 7.5 mrem to any body organand,b. During any calendar year: Less than or equal to 15 mrem to any body organ.APPLICABILITY: At all times.ACTION:a. With the calculated dose from the release of iodine-131, iodine-133 andradionuclides in particulate form with half-lives greater than 8 days, in gaseouseffluents exceeding any of the above limits, prepare and submit to the Commissionwithin 30 days, pursuant to Technical Specification 6.9.2, a Special Report thatidentifies the cause(s) for exceeding the limit and defines the corrective actions thathave been taken to reduce the releases and the proposed corrective actions to betaken to assure that subsequent releases will be in compliance with the abovelimits.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendaryear for iodine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologyand parameters in the ODCM Part II Section 2.5 at least once per 31 days inaccordance with Technical Specification 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 41 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEMCONTROLS3.11.2.4 The AUGMENTED OFF GAS SYSTEM shall be in operation to reduce releases ofradioactivity when the projected doses in 31 days due to gaseous effluent releases toareas at and beyond the SITE BOUNDARY (see Figure E-4) would exceed:a. 0.2 mrad to air from gamma radiation, orb. 0.4 mrad to air from beta radiation, orc. 0.3 mrem to any body organAPPLICABILITY: Whenever the main condenser steam jet air ejector is in operation exceptduring startup or shutdown with reactor power less than 40 percent of rated. Inaddition, the AUGMENTED OFF GAS SYSTEM need not be in operationduring end of cycle coast-down periods when the system can no longer functiondue to low off gas flow.ACTION:a. Every reasonable effort shall be made to maintain and operate charcoal absorbersin the AUGMENTED OFF GAS SYSTEM to treat radioactive gas from the maincondenser air ejectors.b. With gaseous radwaste from the main condenser air ejector system beingdischarged without treatment for more than 30 consecutive days and eitherCONTROL 3.11.2.1 or 3.11.2.4 exceeded, prepare and submit to the Commissionwithin 30 days from the end of the quarter during which release occurred, pursuantto Technical Specification 6.9.2, a Special Report that includes the followinginformation:1. Identification of any inoperable equipment or subsystems, and the reason forthe inoperability,2. Action(s) taken to restore the inoperable equipment to OPERABLE status,and3. Summary description of action(s) taken to prevent a recurrence.c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.122014 CY-OC-170-301Revision 6Page 42 of 140SURVEILLANCE REQUIREMENTS4.11.2.4.1 Operation of the Augmented Off gas System charcoal absorbers shall be verified byverifying the AOG System bypass valve, V-7-31, alignment or alignment indicationclosed at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the main condenser air ejector isoperating.4.11.2.4.2 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected atleast once per 31 days in accordance with the methodology and parameters in theODCM Part II Section 1.5 in accordance with Technical Specifications 6.8.4.a.5.122014 CY-OC-170-301Revision 6Page 43 of 1403/4.11RADIOACTIVE EFFLUENTS3/4.11.3 MARK I CONTAINMENTCONTROLS3.11.3.1 Venting or purging of the containment Drywell may be through normal ReactorBuilding Ventilation if the following requirements are met:APPLICABILITY:If the Station year-to-date radiological effluent releases (either iodine or noblegas) are less than 10% of the ODCM limit, then Standby Gas Treatment is NOTrequired for purging the contents of the Drywell.ACTION:a. If the Station year-to-date radiological effluent releases (either iodine or noble gas)are greater than 10% of the ODCM limit, then the Standby Gas Treatment Systemmust be used for purging the contents of the Drywell.SURVEILLANCE REQUIREMENTS4.11.3.1 The Standby Gas Treatment System is OPERABLE and available whenever thepurge system is in use.122014 CY-OC-170-301Revision 6Page 44 of 1403/4.11 RADIOACTIVE EFFLUENTS3/4.11.4 TOTAL DOSECONTROLS3.11.4.1 In accordance with Oyster Creek Technical Specifications 6.8.4.a. 10, the annual(calendar year) dose commitment to any MEMBER OFTHE PUBLIC due toradioactive material in the effluent and direct radiation from the OCGS in theUNRESTRICTED AREA shall be limited to less than or equal to 75 mrem to thethyroid or less than or equal to 25 mrem to the total body or any other organ.APPLICABILITY: At all timesACTION:a. With the calculated doses from the release of radioactive materials in liquid orgaseous effluents exceeding twice the limits of CONTROLS 3.11.1.2a, 3.11.1.2b,3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, perform an assessment to determinewhether the limits of CONTROL 3.11.4.1 have been exceeded. If such is the case,prepare and submit to the Commission within 30 days, pursuant to TechnicalSpecification 6.9.2, a Special Report that defines the corrective action to be takento reduce subsequent releases to prevent recurrence of exceeding the above limitsand includes the schedule for achieving conformance with the above limits. ThisSpecial Report shall include information specified in 10CFR20.2203. If theestimated dose(s) exceeds the above limits, and if the release condition resulting inviolation of 40 CFR Part 190 has not already been corrected, the Special Reportshall include a request for a variance in accordance with the provisions of 40 CFRPart 190. Submittal of the report is considered a timely request, and a variance isgranted until staff action on the request is complete.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determinedin accordance with SURVEILLANCE REQUIREMENT 4.11.1.2, 4.11.2.2, 4.11.2.3,and in accordance with the methodology and parameters in the ODCM Part II Section3.0 at least once per year.4.11.4.2 Cumulative dose contributions from direct radiation from the facility shall bedetermined in accordance with the methodology and parameters in the ODCM Part IISection 3.2. This requirement is applicable only under conditions set forth inCONTROL 3.11.4, ACTION a.122014 CY-OC-170-301Revision 6Page 45 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAMCONTROLS3.12.1. In accordance with Oyster Creek Technical Specifications 6.8.4.b, the radiologicalenvironmental monitoring program shall be conducted as specified in Table 3.12.1-1.For specific sample locations see Table E-1. Revisions to the non-ODCM requiredportions of the program may be implemented at any time. Non-ODCM samples arethose taken in addition to the minimum required samples listed in Table 3.12.1-1.APPLICABILITY: At all times.ACTION:a. With the radiological environmental monitoring program not being conducted asspecified in Table 3.12.1-1, prepare and submit to the Commission, in the AnnualRadiological Environmental Operating Report required by Technical Specification6.9. 1.e, a description of the reasons for not conducting the program as required andthe plans for preventing a recurrence.b. With the level of radioactivity as the result of plant effluents in an environmentalsampling medium at a specified location exceeding the reporting levels of Table3.12.1-2 when averaged over any calendar quarter, prepare and submit to theCommission within 60 days of the end of the quarter, pursuant to TechnicalSpecification 6.9.2, a Special Report that identifies the cause(s) for exceeding thelimit(s) and defines the corrective actions to be taken to reduce radioactive effluentsso that the potential annual dose* to a MEMBER OF THE PUBLIC is less than thecalendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. When morethan one of the radionuclides in Table 3.12.1-2 are detected in the samplingmedium, this report shall be submitted if:concentration (1) concentration (2) 1.0reporting level (1) reporting level (2)When radionuclides other than those in Table 3.12.1-2 are detected and are theresult of plant effluents, this report shall be submitted if the potential annual dose*to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater thanthe calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. This reportis not required if the measured level of radioactivity was not the result of planteffluents; however, in such an event, the condition shall be reported and describedin the Annual Radiological Environmental Operating Report pursuant to Section6.1.2.1.*The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLICshall be indicated in this report.122014 CY-OC-170-301Revision 6Page 46 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAMCONTROLS (Continued)ACTION: (Continued)C. If garden vegetation samples are unobtainable due to any legitimate reason, it isNOT ACCEPTABLE to substitute vegetation from other sources. The missedsample will be documented in the annual report, with no further actions necessary.If a permanent sampling location becomes unavailable, follow Table 3.12.1-1 TableNotation (1) to replace the location.d. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are notapplicable.SURVEILLANCE REQUIREMENTS4.12.1 The radiological environmental monitoring samples shall be collected pursuant toTable 3.12.1-1 from the specific locations given in Table E-1, and shall be analyzedpursuant to the requirements of Table 3.12.1-1, and the detection capabilitiesrequired by Table 4.12.1-1.122014 CY-OC-1 70-301Revision 6Page 47 of 140TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLE1. DIRECT RADIATION(2)NUMBER OF REPRESENTAIVESAMPLES ANDSAMPLE LOCATIONS(1)Routine monitoringstations with two or more dosimetersplaced as follows:SAMPLING AND TYPE AND FREQUENCYCOLLECTION FREQUENCY OF ANALYSISQuarterlyGamma dose quarterlyAn inner ring of stations one in eachmeteorological sector in the generalarea of the SITE BOUNDARY(At least 16 locations);An outer ring of stations, one in eachland-based meteorological sector inthe approximately 6- to 8-km range fromthe site (At least 14 locations); andAt least 8 stations to beplaced in special interest areas such aspopulation centers, nearby residences,schools, and in one or two areas toserve as control stations.122014 CY-OC-1 70-301Revision 6Page 48 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLE2. AIRBORNERadioiodine andParticulatesNUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)Samples from 5 locations:Three samples from close tothe SITE BOUNDARY in differentsectors of the highest calculatedannual average ground-level D/QOne sample from the vicinityof a community having the highestcalculated annual average ground-level D/Q; andOne sample from a control location,as for example 15-30 km distantand in the least prevalent winddirection (6)SAMPLING ANDCOLLECTION FREQUENCYContinuous sampleroperation with samplecollection weekly ormore frequently ifrequired by dustloadingTYPE AND FREQUENCYOF ANALYSISRadioiodine Canister:1-131 analysis weeklyParticulate SamplerGross beta radioacti-vity analysis follow-ing filter change3) ;Gamma isotopicanalysis(4)of composites (bylocation) quarterly122014 CY-OC-1 70-301Revision 6Page 49 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLE3. WATERBORNEa. Surfaceb. Ground(5)c. DrinkingNUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)One sample upstreamOne sample downstreamSamples from one or two sourcesif likely to be affected1 sample of each of 1 to 3 of thenearest water supplies that couldbe affected by its dischargeSAMPLING ANDCOLLECTION FREQUENCYTYPE AND FREQUENCYOF ANALYSISGrab sample weekly,Combine into monthlycomposite.Grab sample quarterlyGrab sample weekly,combine into a 2-weekcomposite if 1-131 analysisIs required; compositemonthly otherwiseGamma isotopic andtritium analysis(4)Gamma isotopic and tritiumanalysis,4)Gross beta, gammaisotopic and tritium analysismonthly (4)(7)One sample from a backgroundlocation122014 CY-OC-1 70-301Revision 6Page 50 of 140TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLENUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)SAMPLING ANDCOLLECTION FREQUENCYTYPE AND FREQUENCYOF ANALYSISd. SedimentOne sample from downstream area Semiannuallywith existing or potential recreationalvalueGamma isotopicanalysis(4) semiannually122014 CY-OC-1 70-301Revision 6Page 51 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLENUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)SAMPLING ANDCOLLECTION FREQUENCY4. INGESTIONa. Milk (6)No milking animalsIf milk animals are identified:Samples from milking animals inthree locations within 5km havingthe highest dose potential. If thereare none, then one sample frommilking animals in each of three areasbetween 5 an 8 km distant wheredoses are calculated to be greaterthan 1 mrem per year. One samplefrom milking animal at a controllocation 15 to 30 km distant andin the least prevalent wind directionOne sample of available speciesconsumed by man in plantdischarge canalOne sample of available speciesconsumed by man not influencedby plant dischargeSemimonthly when on pasture;monthly at other timesSemiannually,when availableTYPE AND FREQUENCYOF ANALYSISGamma isotopic (4) andIodine -131semimonthly whenanimals are on pasture;monthly at other timesGamma isotopicanalysis (4)on edible portionsb. Fish122014 CY-OC-1 70-301Revision 6Page 52 of 140TABLE 3.12.1-1(Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMEXPOSURE PATHWAYAND/OR SAMPLEc. ClamsNUMBER OF REPRESENTATIVESAMPLES ANDSAMPLE LOCATIONS(1)One sample of available speciesconsumed by man within theinfluence of the facility discharge.SAMPLING ANDCOLLECTION FREQUENCYSemiannually,when availableTYPE AND FREQUENCYOF ANALYSISGamma isotopicanalysis (4)on edible portions.d. Vegetation (8)One sample of available speciesconsumed by man not influencedby plant discharge.3 samples of broad leafvegetation grown nearest eachof two different Off Site locations ofhighest predicted annual averagecombined elevated and ground levelrelease D/QMonthly duringgrowing seasonGamma isotopicanalysis (4) and 1-131 onedible portion.One sample of each of the similar broadleaf vegetation grown at least 15 to 30 km(9.3-18.6 miles) distant in the least prevalentwind direction.122014 CY-OC-170-301Revision 6Page 53 of 140TABLE 3.12.1-1 (Continued)TABLE NOTATIONSSpecific parameters of distance and direction sector from the centerline of the reactor, andadditional description where pertinent, are provided for each and every sample location inTable 3.12.1-1 and Table E-1. Deviations are permitted from the required sampling scheduleif specimens are unobtainable due to circumstances such as hazardous conditions, seasonalunavailability, malfunction of automatic sampling equipment, and other legitimate reasons. Ifspecimens are unobtainable due to sampling equipment malfunction, effort shall be made tocomplete corrective action prior to the end of the next sampling period. All deviations from thesampling schedule shall be documented in the Annual Radiological Environmental OperatingReport pursuant to CONTROL 6.1.2.4. It is recognized that, at times, it may not be possibleor practicable to continue to obtain samples of the media of choice at the most desiredlocation or time. In these instances suitable specific alternative media and locations may bechosen for the particular pathway in question and appropriate substitutions made within 30days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant toTechnical specification 6.19, submit in the next Radioactive Effluent Release Reportdocumentation for a change in the ODCM including revised figure(s) and table for the ODCMreflecting the new location(s) with supporting information identifying the cause of theunavailability of samples for the pathway and justifying the selection of the new location(s) forobtaining samples. This applies to changes/deletions/additions of permanent samplinglocations. This does not apply to one-time deviations from the sampling schedule. In thosecases, it is NOT ACCEPTABLE to substitute sample media from other sources. The missedsample will be documented in the annual report, with no further actions necessary.2 One or more instruments, such as pressurized ion chamber, for measuring and recordingdose rate continuously may be used in place of, or in addition to, integrating dosimeters. Thenumber of direct radiation monitoring stations has been reduced from the NUREG 1302recommendation due to geographical limitations; e.g., some sectors are over water and somesectors cannot be reached due to lack of highway access, therefore the number of dosimetershas been reduced accordingly.3 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ormore after sampling to allow for radon and thoron daughter decay. If gross beta activity in airparticulate is greater than ten times the yearly mean of control samples, gamma isotopicanalysis shall be performed on the individual samples.4 Gamma isotopic analysis means the identification and quantification of gamma-emittingradionuclides that may be attributable to the effluents from the facility.5 Groundwater samples shall be taken when this source is tapped for drinking or irrigationpurposes in areas where the hydraulic gradient or recharge properties are suitable forcontamination. Extensive studies of geology and groundwater in the vicinity of the OCGS(Reference 21 and 31) have demonstrated that there is no plausible pathway for effluentsfrom the facility to contaminate offsite groundwater, including the local122014 CY-OC-1 70-301Revision 6Page 54 of 140drinking water supplies. Samples of groundwater, including local drinking water wells, arecollected in order to provide assurance to the public that these water resources are notimpacted.6 The purpose of this sample is to obtain background information. If it is not practical toestablish control locations in accordance with the distance and wind direction criteria, othersites which provide valid background data may be substituted7 1-131 analysis on each composite when the dose calculated for the consumption of the wateris greater than 1 mrem per year. If garden vegetation samples are unobtainable due to anylegitimate reason (see (1) above), it is NOT ACCEPTABLE to substitute vegetation from othersources. The missed sample will be documented in the annual report, with no further actionsnecessary.122014 CY-OC-170-301Revision 6Page 55 of 140TABLE 3.12.1-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS INENVIRONMENTAL SAMPLES -REPORTING LEVELSSurface and Airborne Fish Milk VegetationAnalysis Ground Particulate (pCi/Kg, (pCi/I) (pCi/Kg,Water(pCi/I) and Iodine wet) wet)(pCi/m3)H-3 20000*Mn-54 1000 30000Fe-59 400 10000Co-58 1000 30000Co-60 300 10000Zn-65 300 20000Zr-Nb-95 4001-131 2** 0.9 3 100Cs-134 30 10 1000 60 1000Cs-137 50 20 2000 70 2000Ba-La-140 200 300*For drinking water samples (this is the 40 CFR Part 141 value).If no drinking water pathway exists, a value of 30,000 pCi/L may be used.**If no drinking water pathway exists, a value of 20 pCi/L may be used.122014 CY-OC-1 70-301Revision 6Page 56 of 140TABLE 4.12.1-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLEANALYSIS(1I)(2) LOWER LIMITS OF DETECTION (LLD) (3)Surface and Air Vegetation Sediment Fish, ClamsAnalysis Ground Particulate (pCi/Kg, (pCi/Kg, dry) and CrabsWater and Air wet) (pCi/Kg, wet)(pCi/I) Iodine(pCi/m3)Gross Beta 4 0.01H-3 2000(4)Mn-54 15 130Fe-59 30 260Co-58, 60 15 130Zn-65 30 260Zr-95 30Nb-95 151-131 1(4) 0.07(5) 60Cs-134 15 0.05(6) 60 150 130Cs-137 18 0.06(6) 80 180 150La-140 15Ba-140 60(7)122014 CY-OC-1 70-301Revision 6Page 57 of 140TABLE 4.12.1-1 (Continued)TABLE NOTATIONS1. This list does not mean that only these nuclides are to be considered. Other peaks that areidentifiable, together with those of the above nuclides, shall also be analyzed and reported inthe Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.3.2. Required detection capabilities for dosimeters used for environmental measurements shall bein accordance with the recommendations of Regulatory Guide 4.13.3. The LLD is defined, for purposes of these CONTROLS as the smallest concentration ofradioactive material in a sample that will yield a net count, above system background, that willbe detected with 95% probability with only 5% probability of falsely concluding that a blankobservation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:LLD~ =4.66* SbE
- V
- 2.22
- Y
- exp(-AýAt)Where:LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass orvolume,Sb is the standard deviation of the background counting rate or of the counting rate of a blanksample as appropriate, as counts per minute,E is the counting efficiency, as counts per disintegration,V is the sample size in units of mass or volume,2.22 is the number of disintegrations per minute per Pico curie,Y is the fractional radiochemical yield, when applicable,X is the radioactive decay constant for the particular radionuclide (sec1), andAt for environmental samples is the elapsed time between sample collection, or end of thesample collection period, and time of counting (sec).Typical values of E, V, Y, and At should be used in the calculation.122014 CY-OC-170-301Revision 6Page 58 of 140TABLE 4.12.1-1 (Continued)TABLE NOTATIONSIt should be recognized that the LLD is defined as an a priori (before the fact) limitrepresenting the capability of a measurement system and not as an a posteriori (after the fact)limit for a particular measurement. Analyses shall be performed in such a manner that thestated LLDs will be achieved under routine conditions. Occasionally, background fluctuations,unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollablecircumstances may render these LLDs unachievable. In such cases, the contributing factorsshall be identified and described in the Annual Radiological Environmental Operating Reportpursuant Technical Specification 6.9.1.e and Control 6.1.2.6.4.4. If no drinking water pathway exists, a value of 3000 pCi/L for tritium and 15 pCi/L for iodine-131 may be used.5. For the air iodine sample6. For the air particulate sample7. Ba-140 and La-140 are in equilibrium122014 CY-OC-170-301Revision 6Page 59 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.2 LAND USE CENSUSCONTROLS3.12.2 In accordance with the Oyster Creek Technical Specifications 6.8.4.b, a land usecensus shall be conducted and shall identify within a distance of 5 miles the location ineach of the 16 meteorological sectors of the nearest milk animal, the nearestresidence and the nearest garden* of greater than 500 ft2 producing broad leafvegetation. The census shall also identify within a distance of 3 miles the location ineach of the 16 meteorological sectors all milk animal and all gardens greater than 500square feet producing broadleaf vegetation.APPLICABILITY: At all times.ACTION:a. With a land use census identifying a location(s) that yields a calculated dose or dosecommitment greater than the values currently being calculated in SURVEILLANCEREQUIREMENT 4.11.2.3, identify the new location(s) in the next RadioactiveEffluent Release Report, pursuant to Control 6.2.2.4.b. With a land use census identifying a location(s) that yields a calculated dose or dosecommitment (via the same exposure pathway) 20 percent greater than at a locationfrom which samples are currently being obtained in accordance with CONTROL3.12.1, add the new location(s) to the radiological environmental monitoring programwithin 30 days. The sampling location(s), excluding the control station location,having the lowest calculated dose or dose commitment(s), via the same exposurepathway, may then be deleted from this monitoring. Pursuant to CONTROL 6.2.2.4,identify the new location(s) in the next Radioactive Effluent Release Report and alsoinclude in the report a revised figure(s) and table for the ODCM reflecting the newlocation(s).c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.12.2 The land use census shall be conducted during the growing season at least once per12 months using that information that will provide the best results, such as by door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.The results of the land use census shall be included in the Annual RadiologicalEnvironmental Operating Report pursuant to CONTROL 6.1.2.2.*Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed atthe SITE BOUNDARY in each of two different direction sectors with the highest predicted elevatedrelease D/Q's in lieu of the garden census. Controls for broadleaf vegetation sampling in Table3.12.1-1, Part 4.c shall be followed, including analysis of control samples.122014 CY-OC-1 70-301Revision 6Page 60 of 1403/412 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4,12.3 INTERLABORATORY COMPARISON PROGRAMCONTROLS3.12.3 In accordance with Oyster Creek Technical Specifications 6.8.4.b.3, analyses shall beperformed on radioactive materials supplied as part of an interlaboratory comparisonprogram which has been approved by the Commission.APPLICABILITY: At all times.ACTION:a. With analyses not being performed as required above, report the reason andcorrective actions taken to prevent a recurrence to the Commission in the AnnualRadiological Environmental Operating Report pursuant to CONTROL 6.1.2.6.3.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.12.3 A summary of the results obtained as part of the above-required InterlaboratoryComparison Program shall be included in the Annual Radiological EnvironmentalOperating Report pursuant to CONTROL 6.1.2.6.3.122014 CY-OC-1 70-301Revision 6Page 61 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.4 METEOROLOGICAL MONITORING PROGRAMCONTROLS3.12.4The meteorological monitoring instrumentation channels shown in Table 3.12.4.-Ishall be operable.APPLICABILITY: At all times.ACTION:a. With less than the minimum required instrumentation channels OPERABLE for morethan 7 days, initiate an Issue Report outlining the cause of the malfunction and theplans for restoring the instrumentation to OPERABLE status.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.TABLE 3.12.4-1METEOROLOGICAL MONITORING INSTRUMENTATIONINSTRUMENTELEVATIONMINIMUMINSTRUMENTOPERABLE1. Wind Speedab.C.380 feet150 feet33 feet1112. Wind Directia.b.C.3. ATa.b.on380 feet150 feet33 feet380-33150-3311111122014 CY-OC-1 70-301Revision 6Page 62 of 140BASES FOR SECTIONS 3.0 AND 4.0CONTROLS AND SURVEILLANCE REQUIREMENTSNOTE: The BASES contained in the succeeding pages summarize the reasons for theCONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS.3/4,3 INSTRUMENTATIONBASES3/4,3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONThe radioactive liquid effluent instrumentation is provided to monitor and control, asapplicable, the releases of radioactive materials in liquid effluents during actual orpotential releases of liquid effluents. The reactor service water system discharge lineradioactivity monitor initiates an alarm in the Control Room when the alarm set point isexceeded. The alarm/trip set points for these instruments shall be calculated andadjusted in accordance with the methodology and parameters in the ODCM to ensurethat the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. TheOPERABILITY and use of this instrumentation is consistent with the requirements ofGeneral Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONThe radioactive gaseous effluent instrumentation is provided to monitor and control, asapplicable, the releases of radioactive materials in gaseous effluents during actual orpotential releases of gaseous effluents. The alarm/trip set points for each of the noblegas monitors shall be calculated and adjusted in accordance with the methodologyand parameters in the ODCM. This will ensure the alarm/trip will occur prior toexceeding the limits of 10 CFR Part 20. The radioactive gas monitors for the stackeffluent and the Augmented Off gas Building exhaust ventilation have alarms whichreport in the Reactor Control Room. The OPERABILITY and use of thisinstrumentation is consistent with the requirements of General Design Criteria 60, 63,and 64 of Appendix A to 10 CFR Part 50.122014 CY-OC-170-301Revision 6Page 63 of 1403/4.11 RADIOACTIVE EFFLUENTSBASES3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATIONThis CONTROL is provided to ensure that the concentration of radioactive materialsreleased in liquid waste effluents to UNRESTRICTED AREAS will be less than theconcentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.This limitation provides additional assurance that the levels of radioactive materials inbodies of water in UNRESTRICTED AREAS will result in exposures within (1) theSection II.A design objectives of Appendix 1, 10 CFR Part 50, to a MEMBER OF THEPUBLIC and (2) the limits of 10 CFR Part 20.106(a) to the population. Theconcentration limit for dissolved or entrained noble gases is based upon theassumption that Xe-1 35 is the controlling radioisotope and its concentration limit in air(submersion) was converted to an equivalent concentration in water using themethods described in International Commission on Radiological Protection (ICRP)Publication 2.The value 1 E-8 is the limit for unidentified gross gamma or beta releases as per 10CFR 20 Appendix B, Table 2, Column 2 "any single radionuclide ... other than alpha orspontaneous fission ... half life greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />". This provides operationalflexibility while providing reasonable assurance that dose will remain less than 0.1rem/yr.The required detection capabilities for radioactive materials in liquid waste samplesare tabulated in terms of the lower limits of detection (LLDs). Detailed discussion ofthe LLD, and other detection limits can be found in references 25, 26, and 27.Weekly grab samples for Service Water Effluent are composited for monthly tritiumand gross alpha analysis and quarterly Sr-89/90 and Fe-55 analysis if activity isdetected.While discharging groundwater via the continuous release remediation pathway, thecomposite sample will be analyzed daily for principal gamma emitters and tritium. Amonthly composite sample is analyzed for gross alpha, Sr-89/90, Fe-55, and Ni-63.While discharging groundwater via the batch release mode remediation pathway, agrab sample is collected from each tank and analyzed for principal gamma emittersand tritium, a composite sample is analyzed monthly for gross alpha, Sr-89/90, Fe-55,and Ni-63.Circulating Water Effluent is not included in Table 4.11.1.1.1-1, Radioactive LiquidWaste Sampling and Analysis Program since the Circulating Water is sampled as partof the Radiological Environmental Monitoring Program, Table 3.12.1-1, 3a,Waterborne, Surface downstream sample.122014 CY-OC-170-301Revision 6Page 64 of 1403/4.11.1.2 DOSEThis CONTROL is provided to implement the requirements of Sections II.A, Ill.A, andIV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forthin Section II.A of Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in liquid effluents toUNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dosecalculation methodology and parameters in the ODCM implement the requirements inSection III.A of Appendix I that conformance with the guides of Appendix I be shownby calculational procedures based on models and data, such that the actual exposureof a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to besubstantially underestimated. The equations specified in the ODCM for calculating thedoses due to the actual release rates of radioactive materials in liquid effluents areconsistent with the methodology provided in Regulatory Guide 1.109 and RegulatoryGuide 1.113.3/4.11.1.3 LIQUID RADWASTE TREATMENTThe OPERABILITY of the liquid radwaste treatment system ensures that this systemwill be available for use whenever liquid effluents require treatment prior to theirrelease to the environment. The requirement that the appropriate portions of thissystem be used, when specified, provides assurance that the releases of radioactivematerials in liquid effluents will be kept "as low as is reasonably achievable". ThisCONTROL implements the requirements of General Design Criterion 60 of AppendixA to 10 CFR Part 50 and the design objective given in Section IL.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of theliquid radwaste treatment system were specified as a suitable fraction of the dosedesign objectives set forth in Section II.A of Appendix 1, 10 CFR Part 50, for liquideffluents. Figure D-1-la, Liquid Radwaste Treatment Chem Waste and Floor DrainSystem and Figure D-1 -1 b, Liquid Radwaste Treatment -High Purity and EquipmentDrain System provides details of the Liquid Radwaste Treatment system.3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSE RATEThis CONTROL is provided to ensure that the dose at any time at and beyond theSITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the dosesassociated with the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column1. These limits provide reasonable assurance that radioactive material discharged ingaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in anUNRESTRICTED AREA either within or outside the SITE BOUNDARY, to annualaverage concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITEBOUNDARY, the occupancy of the individual will usually be sufficiently low to122014 CY-OC-170-301Revision 6Page 65 of 140compensate for any increase in the atmospheric diffusion factor above that for theSITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLICwith the appropriate occupancy factors shall be given in the ODCM. The specifiedrelease rate limits restrict, at all times, the corresponding gamma and beta dose ratesabove background to a MEMBER OF THE PUBLIC at or beyond the SITEBOUNDARY to less than or equal to 500 mrem/year to the total body or to less than orequal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times,the corresponding thyroid dose rate above background to a child via the inhalationpathway to less than or equal to 1500 mrem/year.The required detection capabilities for radioactive materials in liquid waste samplesare tabulated in terms of the lower limits of detection (LLDs). Detailed discussion ofthe LLD, and other detection limits can be found in references 25, 26 and 27.Tritium is sampled quarterly for gaseous effluents. Based on the consistency of thedata from the quarterly sampling, the sampling frequency is adequate.3/4.11.2.2 DOSE -NOBLE GASESThis CONTROL is provided to implement the requirements of Section II.B, III.A andIV.A of Appendix 1, 10 CFR Part 50. The CONTROL implements the guides set forth inSection II.B of Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in gaseous effluents willbe kept "as low as is reasonably achievable." The SURVEILLANCEREQUIREMENTS implement the requirements in Section III.A of Appendix I thatconformance with the guides of Appendix I be shown by calculational proceduresbased on models and data such that the actual exposure of a MEMBER OF THEPUBLIC through appropriate pathways is unlikely to be substantially underestimated.The dose calculation methodology and parameters established in the ODCM forcalculating the doses due to the actual release rates of radioactive noble gases ingaseous effluents are consistent with the methodology provided in Regulatory Guide1.109 and Regulatory Guide 1.111. The ODCM equations provided for determining theair doses at and beyond the SITE BOUNDARY are based upon the historical averageatmospheric conditions.3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES INPARTICULATE FORMThis CONTROL is provided to implement the requirements of Section II.C, III.A andIV.A of Appendix 1, 10 CFR Part 50. The CONTROLS are the guides set forth inSection II.C of Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in gaseous effluents toUNRERSTRICTED AREAS will be kept "as low as is reasonably achievable." TheODCM calculational methods specified in SURVEILLANCE REQUIREMENTSimplement the requirements in Section III.A of Appendix I that conformance with theguides of Appendix I be shown by calculational procedures based on models and data122014 CY-OC-170-301Revision 6Page 66 of 140such that the actual exposure of a MEMBER OF THE PUBLIC through appropriatepathways is unlikely to be substantially underestimated. The ODCM calculationalmethodology and parameters for calculating the doses due to the actual release ratesof the subject materials are consistent with the methodology provided in RegulatoryGuide 1.109, and Regulatory Guide 1.111. These equations also provide fordetermining the actual doses based upon the historical average atmosphericconditions. The release rate controls for iodine-1 31, iodine-1 33, tritium, andradionuclides in particulate form with half-life greater than 8 days are dependent onthe existing radionuclide pathways to man, in the areas at and beyond the SITEBOUNDARY. The pathways that were examined in the development of thesecalculations were: 1) individual inhalation of airborne radionuclides, 2) deposition ofradionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animals and meat producing animals grazewith consumption of the milk and meat by man, and 4) deposition on the ground withsubsequent exposure of man.3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEMThe OPERABILITY of the AUGMENTED OFF GAS TREATMENT SYSTEM (AOG)ensures that the system will be available for use whenever gaseous effluents requiretreatment prior to release to the environment. The requirement that the appropriateportions of these systems be used, when specified, provides reasonable assurancethat the releases of radioactive materials in gaseous effluents will be kept "as low as isreasonably achievable." This CONTROL implements the requirements of GeneralDesign Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives givenin Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the useof appropriate portions of the systems were specified as a suitable fraction of the dosedesign objectives set forth in Section II.B and II.C of Appendix 1, 10 CFR Part 50, forgaseous effluents. Figure D-2-1, Gaseous Radwaste Treatment -Augmented Off gasSystem, Figure D-2-2, Ventilation System provide details of the Augmented Off GasTreatment System and Figure D-2-3, AOG Ventilation System.3/4.11.4 TOTAL DOSEThis CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that havenow been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requiresthe preparation and submittal of a Special Report whenever the calculated doses fromplant radioactive effluents exceed 25 mrem to the total body or any organ, except thethyroid, which shall be limited to less than or equal to 75 mrem. It is highly unlikelythat the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of40 CFR Part 190 if the doses remain within twice the dose design objectives ofAppendix I, and if direct radiation doses from the unit, including outside storage tanks,etc. are kept small. The Special Report will describe a course of action that shouldresult in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed thatthe dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cyclesources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated toexceed the requirements of 40 CFR Part 190, the Special Report with a request for a122014 CY-OC-170-301Revision 6Page 67 of 140variance (provided the release conditions resulting in violation of 40 CFR Part 190have not already been corrected), in accordance with the provisions of 40 CFR Part190 and 10 CFR Part 20, is considered to be a timely request and fulfills therequirements of 40 CFR Part 190 until NRC staff action is completed. The varianceonly relates to the limits of 40 CFR Part 190, and does not apply in any way to theother requirements for dose limitation of 10 CFR Part 20, as addressed inCONTROLS 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OFTHE PUBLIC during any period in which he/she is engaged in carrying out anyoperation that is part of the nuclear fuel cycle.122014 CY-OC-170-301Revision 6Page 68 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORINGBASES3/4.12.1 MONITORING PROGRAMThe radiological environmental monitoring program required by this CONTROLprovides representative measurements of radiation and of radioactive materials inthose exposure pathways and for those radionuclides that lead to the highest potentialradiation exposures of MEMBERS OF THE PUBLIC resulting from the stationoperation. This monitoring program implementsSection IV.B.2 of Appendix I to 10CFR Part 50 and thereby supplements the radiological effluent monitoring program byverifying that the measurable concentrations of radioactive materials and levels ofradiation are not higher than expected on the basis of the effluent measurements andthe modeling of the environmental exposure pathways. Guidance for this monitoringprogram is provided by the Radiological Assessment Branch Position onEnvironmental Monitoring, Revision 1, November 1979.The required detection capabilities for environmental sample analyses are tabulated interms of the lower limits of detection (LLDs). The LLDs required by Table 4.12.1-1 areconsidered optimum for routine environmental measurements in industriallaboratories. It should be recognized that the LLD is defined as an a priori (before thefact) limit representing the capability of a measurement system and not as an aposteriori (after the fact) limit for a particular measurement.Detailed discussion of the LLD, and other detection limits in references 25, 26, and 27.Site-specific research, which included the installation of a groundwatermonitoring well network, has demonstrated that the groundwater pathway is nota potential pathway to man from the OCGS. The surface water into which theOCGS discharges is a marine estuary containing saline water that is not used asdrinking water or irrigation water by man.3/4.12.2 LAND USE CENSUSThis CONTROL is provided to ensure that changes in the use of areas at and beyondthe SITE BOUNDARY are identified and that modifications to the radiologicalenvironmental monitoring program are made if required by the results of this census.The best information from the door-to-door survey, from aerial survey, from visualsurvey or consulting with local agricultural authorities shall be used. This censussatisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than 50 m2 (500 ft2) provides assurancethat significant exposure pathways via leafy vegetables will be identified andmonitored since a garden of this size is the minimum required to produce the quantity(26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumptionby a child. To determine this minimum garden size, the following assumptions weremade: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar tolettuce and cabbage), and 2) a vegetation yield of 2 kg/M2.122014 CY-OC-1 70-301Revision 6Page 69 of 1403/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORINGBASES3/4.12.3 INTERLABORATORY COMPARISON PROGRAMThe requirement for participation in an approved Interlaboratory Comparison Programis provided to ensure that independent checks on the precision and accuracy of themeasurements of radioactive material in environmental sample matrices areperformed as part of the quality assurance program for environmental monitoring inorder to demonstrate that the results are valid for the purposes of Section IV.B.2 ofAppendix I to 10 CFR Part 50.5.05.0 DESIGN FEATURES / SITE MAP(Provided FOR INFORMATION ONLY. Technical Specifications are controlling.)5.1 Site map which will allow identification of structures and release points shall be asshown in Figure E-4.122014 CY-OC-170-301Revision 6Page 70 of 1406.0 ADMINISTRATIVE CONTROLS6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)6.1.1 In accordance with Oyster Creek Technical Specifications 6.9.1 .e, a routine radiologicalenvironmental operating report covering the operation of the unit during the previouscalendar year shall be submitted prior to May 1 of the following year.6.1.2 The Annual Radiological Environmental Operating Reports shall include:6.1.2.1 Summaries, interpretations, and an analysis of trends of the results of the radiologicalenvironmental surveillance activities (Radiological Environmental Monitoring Program -REMP) for the report period. This will include a comparison with preoperational studies,with operational controls (as appropriate), and with previous environmental surveillancereports, and an assessment of the observed impacts of the plant operation on theenvironment.6.1.2.2 The reports shall also include the results of land use censuses required by CONTROL3.12.2. If harmful effects or evidence of irreversible damage are detected by themonitoring, the report shall provide an analysis of the problem and a planned course ofaction to alleviate the problem.6.1.2.3 The Annual Radiological Environmental Operating Reports shall include summarizedand tabulated results similar in format to that in Regulatory Guide 4.8, December 1975 ofall the radiological environmental samples taken during the report period.6.1.2.4 Deviations from the sampling program identified in CONTROL 3.12.1 shall be reported.6.1.2.5 In the event that some individual results are not available for inclusion with the report,the report shall be submitted noting and explaining the reasons for the missing results.The missing data shall be submitted as soon as possible in a supplementary report.6.1.2.6 The reports shall also include the following:a. A summary description of the radiological environmental monitoringProgram;b. Map(s), covering sampling locations, keyed to a table giving distances and directionsfrom the reactor;c. The results of licensee participation in the Inter-laboratory ComparisonProgram, as required by CONTROL 3.12.3;d. Identification of environmental samples analyzed when the analysis instrumentationwas not capable of meeting the detection capabilities in Table 4.12.1-1.122014 CY-OC-1 70-301Revision 6Page 71 of 1406.2 ANNUAL ROUTINE RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)6.2.1 Routine radioactive effluent release reports covering the operation of the unit shall besubmitted prior to May 1 of each year and in accordance with the requirements of1OCFR50.36a and section IV.B.1 of 10CFR 50 Appendix I.6.2.2 The Radioactive Effluent Release Report shall include:6.2.2.1 A summary of the quantities of radioactive liquid and gaseous effluents and solid wastereleased from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating,and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials inLiquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision1, June 1974, with data summarized on a quarterly basis following the format ofAppendix B thereof.6.2.2.2 An annual summary of hourly meteorological data collected over the previous year. Thisannual summary may be in the form of joint frequency distributions of wind speed, winddirection, and atmospheric stability. Alternatively, summary meteorological data may beretained and made available to the NRC upon request.6.2.2.3 An assessment of the radiation doses due to the radioactive liquid and gaseouseffluents released from the unit or station during the previous calendar year. Thehistorical annual average meteorology or the meteorological conditions concurrent withthe time of release of radioactive materials in gaseous effluents (as determined bysampling frequency and measurement) shall be used for determining the gaseouspathway doses. The assessment of radiation doses shall be performed in accordancewith this OFF SITE DOSE CALCULATION MANUAL (ODCM).6.2.2.4 Identify those radiological environmental sample parameters and locations where it isnot possible or practicable to continue to obtain samples of the media of choice at themost desired location or time. In addition, the cause of the unavailability of samples forthe pathway and the new location(s) for obtaining replacement samples should beidentified. The report should also include a revised figure(s) and table(s) for the ODCMreflecting the new location(s).6.2.2.5 An assessment of radiation doses to the likely most exposed MEMBER OF THEPUBLIC from reactor releases and other nearby uranium fuel cycle sources (includingdoses from primary effluent pathways and direct radiation) for the previous calendaryear to show conformance with 40 CFR Part 190, Environmental Radiation ProtectionStandards for Nuclear Power Operation. The assessment of radiation doses shall beperformed in accordance with this OFF SITE DOSE CALCULATION MANUAL (ODCM)Part II Sections 1.5, 2.4, 2.5 and 3.2.6.2.2.6 The Radioactive Effluent Release Reports shall include the following information foreach class of solid waste (as defined by 10 CFR Part 61) shipped Off Site during thereport period (see Figure D-1-2):a. Total volume shippedb. Total curie quantity (specify whether determined by measurement or estimate),c. Principal radionuclides (specify whether determined by measurement or estimate),122014 CY-OC-170-301Revision 6Page 72 of 140d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporatorbottoms)6.2.2.7 Unplanned releases from the site to UNRESTRICTED AREAS of radioactive materialsin gaseous and liquid effluents on a quarterly basis.6.2.2.8 Changes to the PROCESS CONTROL PROGRAM (PCP)6.2.2.9 Changes to the OFF SITE DOSE CALCULATION MANUAL (ODCM) in the form of acomplete, legible copy of the ODCM.6.3 RESPONSIBILITIES:6.3.1 Chemistry / Radwaste -Responsible for:6.3.1.1 Implementing approval.6.3.1.2 Compliance with specifications regarding routine dose assessment.6.3.1.3 Radiological Environmental Monitoring Program6.3.1.4 Technical consultation and review6.3.2 Operations -Responsible for compliance with specifications regarding operation of theOCGS.6.3.3 Engineering -Responsible for compliance with specifications regarding set pointdetermination and implementation6.3.4 Radiological Engineering -Responsible for technical consultation and review.122014 CY-OC-170-301Revision 6Page 73 of 140PART II -CALCULATIONAL METHODOLOGIES1.0 LIQUID EFFLUENTS1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLSThe liquid effluent monitoring instrumentation and controls at Oyster Creek forcontrolling and monitoring normal radioactive material releases in accordance with theOyster Creek Radiological Effluent Technical Specifications are summarized as follows:Reactor Building Service Water Effluent -The Reactor Building Service Water EffluentLine Monitor provides an alarm function only for releases into the environment.Liquid radioactive waste flow diagrams are presented in Figures D-1-la, D-1-lb, and D-1-1c.1.2 LIQUID EFFLUENT MONITOR SET POINT DETERMINATIONPer the requirements of CONTROL 3.3.3.10, alarm set points shall be established forthe liquid monitoring instrumentation to ensure that the release concentration limits ofCONTROL 3.11.1.1 are met (i.e., the concentration of radioactive material released inliquid effluents to UNRESTRICTED AREAS at the U.S. route 9 bridge over thedischarge canal shall not exceed the concentrations specified in 10 CFR 20 AppendixB. Table 2, Column 2, for radionuclides and 2E-04 pCi/ml for dissolved or entrainednoble gases).1.2.1 LIQUID EFFLUENT MONITORSThe set points for the liquid effluent monitors at the Oyster Creek Generating Station aredetermined by the following equation:A F2 +BKGFLEC F IWhere:S = radiation monitor alarm set point (cpm)A = activity concentration (ptCi/ml) of sample in laboratory: A = Y.Cig = the primary conversion factor for the instrument -the ratio of effluent radiationmonitor counting rate to laboratory activity concentration in a sample of liquid (cpmper pCi/mL).F1 = flow in the batch release line (e.g. gal/min). Value not greater than the discharge lineflow alarm maximum set point.122014 CY-OC-170-301Revision 6Page 74 of 140F2. = flow in the discharge canal (e.g. gal/min). Value not less than the discharge canalminimum flow.BKG = Monitoring instrument background (cpm)FLEC = fraction or multiple of unrestricted area LEC in aqueous effluent based on sampleanalysis. FLEC is the ratio between the LECi and Ci. FLEC is unitless. Forexample: LEC for Co-60 is 3E-6 ýiCi/mL. If the concentration in a expected releaseis 6E-6 j.LCi/mL; then FLEC is 6E-6/3E-6 = 2.The term A represents the count rate of a solution having the same nuclideFLECdistribution as the sample and the LEC of that mixture.Ci = concentration of radionuclide i in effluent, i.e., in a liquid radwaste sample tank, inreactor building service water (pCi/mL).LEC, =the unrestricted area liquid effluent concentration (LEC) of radionuclide i, i.e., 10 CFR20, Appendix B, Table 2, Column 2 quantity for radionuclide i (p.Ci/mL).In the event gross radioactivity analysis alone is used to determine the radioactivity inan effluent stream or batch, FLEC is C/1E-8 (see 4.11.1.1.1),Where:C = the gross radioactivity concentration in effluent (ltCi/mL).1 E-8 = the unrestricted area LEC for unidentified radionuclides (jtCi/mL) from 4.11.1.1 .1.If the gross activity concentration, C, is below the lower limit of detection for grossactivity, the value, 1 E-8 j+/-Ci/mL, or the equivalent counting rate (cpm/mL) may besubstituted for the factor AFLECA = 1 E-8 ICi/mLFLEC1.2.2 SAMPLE RESULT SET POINTSUsually, when the concentration of specific radionuclides is determinable in a sample(s),i.e., greater than the LLD, the alarm/trip set point of each liquid effluent radioactivitymonitor is based upon the measurement of radioactive material in a batch of liquid to bereleased or in a continuous aqueous discharge.122014 CY-OC-170-301Revision 6Page 75 of 1401.2.3 ASSUMED DISTRIBUTION SET POINTSAlternatively, a radionuclide distribution that represents the distribution expected to be inthe effluent if the concentration were high enough to be detectable, i.e., greater than theLLD, may be assumed. The representative distribution may be based upon pastmeasurements of the effluent stream or upon a computed distribution.1.3 BATCH RELEASESA sample of each batch of liquid radwaste is analyzed for 1-131 and other principalgamma emitters or for gross beta or gross gamma activity before release. The result ofthe analysis is used to calculate the trip set point of the radioactivity monitor on theliquid radwaste effluent line to apply to release of the batch.1.4 CONTINUOUS RELEASESThe Reactor Building Service Water Effluent is sampled and analyzed weekly for 1-131,other principal gamma emitters. Results of analyses for the preceding week or for aperiod as long as the preceding 3 months are used to calculate the alarm/trip set pointof the corresponding effluent radioactivity monitor in order to determine a representativevalue. In each case, whether batch or continuous, the monitor alarm/trip set point maybe set at lower activity concentration than the calculated set point.1.5 LIQUID EFFLUENT DOSE CALCULATION -10 CFR 50Doses resulting from the release of radioiodines and particulates must be calculated toshow compliance with Appendix I of 1OCFR50. Calculations will be performed at leastmonthly for all liquid effluents as stated in SURVEILLANCE REQUIREMENT 4.11.1.2and SURVEILLANCE REQUIREMENT 4.11.1.3.1 to verify that the dose to MEMBERSOF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.1.2The maximum dose to an individual from radioiodines, tritium, and radioactiveparticulates with half-lives of greater than eight days in liquid effluents released tounrestricted areas is determined as described in Reg. Guide 1.109. Environmentalpathways that radioiodine, tritium, and particulates in liquid effluent follow to themaximally exposed MEMBER OF THE PUBLIC are assumed to be: exposure toshoreline deposits, ingestion of fish, and ingestion of shellfish. To assess compliancewith CONTROL 3.11.1.2, the dose due to radioactive iodine, tritium, and particulates inliquid effluent is calculated to a person at the Route 9 bridge who consumes fish andshellfish harvested at that location.122014 CY-OC-1 70-301Revision 6Page 76 of 1401.5.1 MEMBER OF THE PUBLIC DOSE -LIQUID EFFLUENTSCONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THEPUBLIC from radioactive materials in liquid effluents from Oyster Creek GeneratingStation to those listed in Table 1.5.1-1.TABLE 1.5.1-1 LIQUID PATHWAY DOSE LIMITSDuring Any Calendar Quarter During Any Calendar Year< 1.5 mrem to total body < 3.0 mrem to total body< 5.0 mrem to any organ < 10.0 mrem to any organPer the SURVEILLANCE REQUIREMENTS of 4.11.1.2, the following calculationmethods shall be used for determining the dose or dose commitment due to the liquidradioactive effluents from Oyster Creek. Applicable liquid pathways to man for OysterCreek include shoreline exposure, and ingestion of saltwater fish and shellfish. Thereceptor location is provided in Table A-4.1.5.2 SHORELINE DEPOSIT DOSEThe shoreline exposure pathway dose is calculated generally in the form (based onReg. Guide 1.109):Rapj = 110000 UapWM QiTiDaipj (1 -exp(-XiTb))FWhere:110000 = a constant that accounts for time and flow conversionsRapj = the annual dose to organ j (including the total body), through pathway p, to agegroup aUap = the age dependent usage factor for the specific pathway. Usage factors for shorelineexposure are residence time on the shoreline (hours). Usage factors are provided inReg. Guide 1.109 Table E-5. Usage factors specifically selected for Oyster Creek arepresented in Table B-I.W = the shore width factor. This adjusts the infinite plane gamma or beta dose factors forthe finite size and shape of the shoreline. Different factors apply to different bodies ofwater. A factor of 0.1 is used for OC for 'discharge canal bank'.M = the recirculation factor. The recirculation factor is a multiplier of 3.76 to account forrecirculation of discharge water back into the intake. Although this occursinfrequently, it is assumed to occur for each liquid release.122014 CY-OC-170-301Revision 6Page 77 of 140F = the flow rate in the discharge canal in cubic feet per secondQi = the activity of the ith isotope in the release in curiesTi = the half life of the ith isotope in daysDaipj =the age a, isotope i, pathway p, and organ j, specific dose conversion factor.Pathway, isotope, age, and organ specific dose factors are obtained from RegulatoryGuide 1.109 Appendix E, Tables E-6 through E-14Xi = the decay constant of the ith isotope in yearsTb = the long term buildup time, assumed to be 30 yearsNote: ki and Tb can use any time units as long as they are both the same. Notransit delay (Tp from Reg. Guide 1.109) is assumed.1.5.3 SHORELINE DOSE EXAMPLE 1The following provides an example of the liquid dose calculation:Initial parameters:Canal flow rate 1 E6 gpm (typical of normal full power operation)Release: 10,000 gallons of water at 1 E-3 LCi/ml Co-60Problem: calculate shoreline whole body doseUap = 67 (teenager) hoursW =0.1M = 3.76F = 2228 [1E6 gpm *3785 ml /gal/ (60 sec/min
- 28316 ml/ft3) = 2228 CFS]Qi = 0.03785 Ci [1E-3uCi/ml
- 10000gal
- 3785ml/gal/1E6 uCi/Ci = 0.03785 Ci]Ti = 1920 [5.27 years*365 days/yr = 1.92E3 days)Mi = 1.31E-1 [0.693/(5.27yrs)]Tb = 30 yearsDaipj = 1.7E-8 mrem/hr / pCi/m2 Gamma dose factorCalculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotopeRapj = 110000-67.0.l*3.76 -0.03785" 1920* 1.7E- 8 * (I -exp(-1.3E -I
- 30))2228 1Rapj =1.5 IE -3 mrem: teen: wholebody122014 CY-OC-1 70-301Revision 6Page 78 of 1401.5.3.1 SHORELINE DOSE EXAMPLE 2The following provides an example of the liquid dose calculation for groundwaterremediation discharge:Initial parameters:Canal flow rate 1 E6gpm (typical of normal full power operation)Release: 50 gpm for 7 days at 1 E-8 pCi/mI Co-60Problem: Calculate shoreline whole body doseUap = 67 (teenager) hoursW =0.1M = 3.76F = 2228 [1E6 gpm *3785 ml / gal / (60 sec/min
- 28316 ml/ft3) = 2228 CFS]Qi = 1.91E-5 Ci [1E-08 pCi/ml*50gpm*7days*24hr/day*60 min/hr*3785ml/gal/1E+6 pCi/Ci]Ti = 1920 [5.27 years*365 days/yr = 1.92E+03 days)Xi = 1.31E-1 [0.693 /(5.27 yrs)]Tb = 30 yearsDaipj = 1.7E-8 mrem/hr / pCi/m2 External Dose factorCalculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotope67*0.1*376Rapj 110000 *37 -1.9 1E- 5"* 1920"* 1.7E -8"* (1- exp(-l1.31E -1*30))2228 jRapj = 7.60E- 7 mrem: teen: wholebody1.5.4 INGESTION DOSE -LIQUIDIngestion dose pathway calculations are similar to those for the shoreline dose,with minor changes in constants, removal of the shore width factor, and inclusion ofthe bioaccumulation factor:Rapj = 1100 UapMQiBipDaipjFWhere:Bip = the stable element bioaccumulation factor for pathway p for the ith isotopeNo transit delay is assumedPathway, isotope, age, and organ specific dose factors are obtained from RegulatoryGuide 1.109 Appendix E Tables E-7 through E-14. Bioaccumulation factors are122014 CY-OC-1 70-301Revision 6Page 79 of 140provided in Reg. Guide 1.109 Table A-1. Usage factors are provided in Reg. Guide1.109 Table E-5. Usage factors specifically selected for Oyster Creek are presented inTable B-1.The radionuclides included in the periodic dose assessment per the requirements ofCONTROL 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquidwaste samples collected and analyzed per the requirements of CONTROL 3/4.11 .1.1,Table 4.11.1.1.1-1.Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added tothe dose analysis at a frequency consistent with the required minimum analysisfrequency of Table 4.11.1.1.1-1.1.5.5 INGESTION DOSE CALCULATION EXAMPLE 1The following provides an example of the liquid dose calculation:Initial parameters:Canal flow rate 1 E6 gpm (typical of normal full power operation)Release: 10000 gallons of water at 1 E-3 .tCi/mL Co-60Problem: calculate teen whole body dose from saltwater fish ingestionRapj = 100 UapM QiBipDaipjFUap = 16 (teenager) KgM = 3.76F = 2228 [1E6 gpm *3785 ml/gal/(60 sec/min
- 28316 ml/ft3) = 2228 CFS]Qi = 0.03785 Ci [1E-3uCi/mL
- 10000gal
- 3785mL/gal /1 E6 uCi/Ci = 0.03785 Ci]Bip = 100Daipj = 6.33E-6 mrem / pCiCalculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotopeRap ~10016*3. 76Rapj =I100 12 37 0.03785 *100 6.33E-62228 hRapj = 7.12 E -4 mrem *teen *wholebody122014 CY-OC-1 70-301Revision 6Page 80 of 1401.5.5.1 INGESTION DOSE CALCULATION EXAMPLE 2The following provides an example of the liquid dose calculation for ground waterremediation discharge:Initial parameters:Canal flow rate 1 E6 gpm (typical of normal full power operation)Release: 50 gpm for 7 days at 700,000 pCi/I H-3Problem: calculate teen whole body dose from saltwater fish ingestionRap] = 1100 Uap QiBipDaipjFUap = 16 (teenager) KgM = 3.76F = 2228 [1E6 gpm *3785 ml /gal /(60 sec/min
- 28316 mlI/ft3) = 2228 CFS]Qi = 1.34 Ci [7E+5 pCi/l*50gpm*7days*24hr/day*60 min/hr*3.785 I/gall 1E+12 pCi/Ci]Bip = 0.90 (Regulatory Guide 1.109, Table A-I)Daipj = 1.06E-07 mrem / pCiCalculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotopeRapj =100 163.76 1.340.9 .06E-72228 iRapj = 3.80 E -6 mrem :teen : wholebody1.5.6 PROJECTED DOSE -LIQUIDThe projected doses in a 31 day period are equal to the calculated doses from thecurrent 31 day period.1.6 REPRESENTATIVE SAMPLESA sample should be representative of the bulk stream or volume of effluent from which itis taken. Prior to sampling, large volumes of liquid waste should be mixed in as short atime interval as practicable to assure that any sediments or particulate solids aredistributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks(collection or sample test tanks) should be capable of recirculating at a rate of not lessthan two tank volumes in eight hours. Minimum recirculation times and methods ofrecirculation are controlled by specific plant procedures.122014 CY-OC-170-301Revision 6Page 81 of 1402.0 GASEOUS EFFLUENTS2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLSThe gaseous effluent monitoring instrumentation and controls at Oyster Creek forcontrolling and monitoring normal radioactive material releases in accordance with theRadiological Effluent CONTROLS are summarized as follows:(1) Main StackThe main stack receives normal ventilation flow from the reactor building, newradwaste, old radwaste, process discharge flow from the augmented off gas system(AOG), condenser off gas flow if AOG is not in service, and normal ventilation flow fromportions of the turbine building, predominantly the condenser bay area. Reactor buildingand turbine building flow is not normally processed or filtered. Reactor Building flow maybe manually or automatically directed through the Standby Gas Treatment System(SBGTS) which has particulate and charcoal filtration. Off gas flow is processedthrough AOG or through a 30-minute delay pipe prior to release. Flow from the 'new'and 'old' radwaste buildings is HEPA filtered. Releases through the main stack aremonitored for noble gases using the RAGEMS I system and sampled for iodine,particulates and tritium. The plant stack is considered to be a true elevated releasepoint.(2) Turbine Building VentThe Turbine building vent is monitored for noble gases by the RAGEMS II system andsampled for iodine, particulates and tritium. It discharges on the west side of the turbinebuilding approximately at roof height and is considered to be a ground level release. Itventilates the turbine floor and other areas of the turbine building. Flow through thisrelease point is not filtered.(3) Feed Pump Room VentThe feed pump room vent is monitored by RAGEMS II. It discharges on the east side ofthe turbine building below roof height and is considered to be a ground level release. Itventilates the reactor feed pump room. Flow through this release point is not filtered.(4) Augmented Off Gas Building VentOff gas Building HVAC is released through a ground level release from the building. OffGas process flow is not released through the building ventilation, but is routed to thestack plant. A ventilation monitoring system monitors for noble gas and samples forparticulate and iodine.122014 CY-OC-1 70-301Revision 6Page 82 of 140(5) Isolation CondensersThe isolation condensers are a ground level release. The predominant isotope throughthis potential release point is tritium as a consequence of the forced evaporation ofcondensate transfer water when the isolation condensers are initiated. Releases areneither monitored nor is the release process flow sampled. Releases of tritium areevaluated based on liquid samples of the input and the volume used.Gaseous radioactive waste flow diagrams with the applicable, associated radiationmonitoring instrumentation controls are presented in Figures D-2-1 and D-2-2.2.2 GASEOUS EFFLUENT MONITOR SET POINT DETERMINATION2.2.1 PLANT VENTPer the requirements of CONTROL 3.3.3.11, alarm set points shall be established forthe gaseous effluent monitoring instrumentation to ensure that the release rate of noblegases does not exceed the limits of CONTROL 3.11.2.1, which corresponds to a doserate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year tothe skin. Based on a grab sample analysis of the applicable release (i.e., of the Stack,Off gas process flow, etc.), the radiation monitoring alarm set points may be establishedby the following calculation methods. A set point of a monitor of an elevated release,e.g., from the stack, may be calculated using the equation:s = 1.6 Z CiS=1.6~f Z (CiDFSi)+BgWhere:S = the alarm set point (cpm)h = primary conversion factor of the instrument -monitor response to activityconcentration of effluent being monitored, cpm/(pLCi/cm3). Each monitoring channelhas a unique response, h, which is determined by the instrument calibration.Ci = relative concentration of noble gas radionuclide i in effluent at the point ofmonitoring (gCi/cm3)1.06 = 500 mrem/year /472 (conversion of cfm to cc/sec)DFSi = factor converting elevated release rate of radionuclide i to total body doseequivalent rate at the location of potential exposure. Units are: mrem/(yr(jiCi/sec)).From Table A-I.f = flow of gaseous effluent stream being monitored, i.e., stack flow, vent flow, etc.(ft3/min)122014 CY-OC-1 70-301Revision 6Page 83 of 140BKG = Monitoring instrument background (cpm or mR/hr)2.2.2 OTHER RELEASE POINTSThe set point of a monitor of a ground-level or vent release, e.g., from the turbinebuilding vent or the AOG building, may be calculated with the equation:h CiS = 1.06 [h ]) + BkgWhere:DFVi = factor converting ground-level or vent release of radionuclide i to the total body doseequivalent rate at the location of potential exposure. Units are: mrem-m3/p.Ci-yearFrom Table A-I.X/Q = atmospheric dispersion from point of ground-level or vent release to the location ofpotential exposure (sec/m3) from Table 2.2.2-1.The atmospheric dispersion, X/Q, and the dose conversion factor, DFSi, depend uponlocal conditions. For the purpose of calculating radioactive noble gas effluent monitoralarm set points appropriate for the OCGS, the locations of maximum potential Off Siteexposure and the reference atmospheric dispersion factors applicable to the derivationof set points are given in Table 2.2.2-1.Symbols for this equation were defined in Section 2.2.1.TABLE 2.2.2-1 RECEPTOR LOCATIONS AND DISPERSION FOR GASEOUS MONITOR SETPOINTSDischarge Point Receptor Location Atm. DispersionSector Distance(m) (sec/mi3)Ground-levelor vent ENE 338 4.59 E-5Stack SW 229 N/A2.2.3 RADIONUCLIDE MIX FOR SET POINTSFor the purpose of deriving a set point, the distribution of radioactive noble gases in aneffluent stream may be determined in one of the following ways:122014 CY-OC-170-301Revision 6Page 84 of 1402.2.3.1 Preferably, the radionuclide distribution is obtained by gamma isotopic analysis ofidentifiable noble gases in effluent gas samples. Results of the analyses of one or moresamples may be averaged to obtain a representative spectrum.2.2.3.2 In the event a representative distribution is unobtainable from recent measurements bythe radioactive gaseous waste sampling and analysis program, it may be based uponpast measurements.2.2.3.3 Alternatively, the total activity concentration of radioactive noble gases may beassumed to be Xenon-1 33 as found in Reg Guide 1.97.2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS -10CFR 202.3.1 SITE BOUNDARY DOSE RATE -NOBLE GASESCONTROL 3.11.2.1a limits the dose rate at the SITE BOUNDARY due to noble gasreleases to < 500 mrem/yr, total body and < 3000 mrem/yr, skin. Radiation monitoralarm set points are established to ensure that these release limits are not exceeded.In the event any gaseous releases from the station results in an alarm set point (asdetermined in Section 2.2) being exceeded, an evaluation of the SITE BOUNDARYdose rate resulting from the release shall be performed.2.3.1.1 TOTAL BODY DOSE RATEThe total body dose equivalent rate from radioactive noble gases discharged from anelevated point (stack above building wake) is calculated with the equation:DG- i'siFrom a ground-level release (building vent) the total body dose equivalent rate is:DG= QiPYViQV,Where:DG = total body dose equivalent rate due to irradiation by radioactive noble gas (mrem/hr)Qi = average discharge rate of noble gas radionuclide i released during the averagingtime (p.Ci/hr)PyVi = factor converting time integrated ground-level concentration of noble gas nuclide ito total body dose mrem -m3. See Table A-2.pCi -secxX = atmospheric dispersion factor from the OCGS to the Off Site location of interestQV(sec/m3) from Table 2.3.1.3-1122014 CY-OC-170-301Revision 6Page 85 of 140PySi factor converting unit noble gas nuclide i stack release to total body dose at groundlevel received outdoors from the overhead plume (mrem/[tCi). See Table A-2The noble gas plume gamma-to-total body dose factors, PSi at designated locations arederived from meteorological dispersion data with the USNRC RABFIN softwarecomputer code or similar computer program implementing Reg Guide 1.109, AppendixB. The noble gas semi-infinite cloud gamma-to-total body dose factors, P',Vi, are derivedfrom Reg Guide 1.109, Revision 1, Table B-I, Column 5.2.3.1.2 EXAMPLE TOTAL BODY DOSE RATECalculate the dose from a release of 100 Ci of Xe1 33 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from a ground levelreleaseDG = X QiPyViQV,X/Qv =4.59E-5 sec/m3 (Table 2.3.1.3-1)Qi 1 E8 gCi/hr [1 00Ci*1 E6 gCi/Ci]P'yVi 9.33E-6 mrem-m3 / ltCi-secDG = 4.59E-5Z 1E8*9.33E-6DG = 0.043 mrem /hr2.3.1.3 SKIN DOSE RATEThe dose equivalent rate to skin from radioactive noble gases is calculated by assuminga person at ground level is immersed in and irradiated by a semi-infinite cloud of thenoble gases originating in airborne effluent. It is calculated for each air effluentdischarge point with the equation:DB = X .Qi(SBi+1.11AyVi)Qwhere:DB dose rate to skin from radioactive noble gases (mrem/hr)X-- :=Atmospheric dispersions from gaseous effluent discharge point to ground-levellocation of interest (sec/m3) from Table 2.3.1.3-1.Qi discharge rate of noble gas radionuclide i (liCi/hr)122014 CY-OC-1 70-301Revision 6Page 86 of 140SBi = factor converting time integrated ground-level concentration of noble gas radionuclidei to skin dose from beta radiation mrem -m3 from Table A-2.pCi
- secAyVi = factor for converting time integrated, semi-infinite concentration of noble gasradionuclide i to air dose from its gamma mrad -m from Table A-2.pCi
- secThe noble gas beta radiation-to-skin-dose factors, SBj and the noble gas gamma-to-airdose factors, AyV1, are derived from Reg Guide 1.109, Revision 1, Table B-i, columns 3and 4 respectively. A tabulation of these factors used to compute noble gas-to-doseequivalent rate at 338 meters ENE for ground-level or vent and 544 meters SE for stackfrom the OCGS is in Table A-2.The dose equivalent rate is calculated with the meteorological dispersion data given inTable 2.3.1.3-1.TABLE 2.3.1.3-1 RECEPTOR LOCATIONS AND DISPERSION FOR SITE BOUNDARY DOSERATESDischarge Point Receptor Location Atm. DispersionSector Distance (m) (sec/m3)Ground Level ENE 338 4.59 E-5or VentStack SE 544 1.05 E-8Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the requirements of Regulatory Guide 1.109 may be used.Actual meteorological conditions concurrent with the release period or the default,annual average dispersion parameters as presented above may be used for evaluatingthe gaseous effluent dose rate.2.3.1.4 EXAMPLE SKIN DOSE RATECalculate the skin dose from a release of 100 Ci of Xel 33 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from a ground levelrelease:xDB = -Qi(SBi + 1.llAyVi)QIX/Q =4.59 E-5 sec/m3Qi = 1E8 itCi/hrSBi = 9.71 E-6 mrem/ýtCi/ m3/secA'yVi = 1.12E-5 mrad/yr per p.Ci/m3122014 CY-OC-170-301Revision 6Page 87 of 140DB = 4.59E- 51 lE8(9.71E-6+ 1.11 *1.12E -5)DB = O. 102mrad / hr2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES2.3.2.1 METHOD -SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATESThe dose rate Off Site due to the airborne release of 1-131, 1-133, tritium, andparticulates with half-lives greater than 8 days is limited to no more than 1500 mrem/yrto any organ in CONTROL 3.11.2.1 b. Evaluation of compliance with CONTROL3.11.2.1 b is based on the sampling and analyses specified in TABLE 4.11.2.1.2-1.Since the dose rate cannot be resolved within less than the sample integration orcompositing time, the contribution of each radionuclide to the calculated dose rate willbe averaged no more than 3 months for H-3, Sr-89, Sr-90, and alpha-emittingradionuclides and no more than 31 days for other radionuclides. These are their usualsample integration or compositing times. The equation used to assess compliance ofradioiodine, tritium, and radioactive particulate releases with the dose rate limit is:11XDRp = 1E6- I RaDFAijaQe Xe iQeWhere:1 E6 = conversion pCi/jiCiDRp = the average dose rate to an organ via exposure pathway, p (mrem/yr).DFAija = inhalation dose factors due to intake of radionuclide i, to organ j age group a(mrem/pCi) from Reg. Guide 1.109 Appendix E.Ra = age group dependent inhalation respiratory rate (usage factor) m3/yr from Table B-1x= annual average relative airborne concentration at an Off Site location due to aQerelease from either the Stack or a vent, i.e. release point, e (sec/m3) from Table2.3.2.1-1.Qei = release rate of radionuclide i from release point, e during the period of interest(p.Ci/sec).For real-time meteorology and on an annual average basis, the location of themaximum ground-level concentration originating from a vent release will differ from themaximum ground-level concentration from a stack release. When assessing122014 CY-OC-1 70-301Revision 6Page 88 of 140compliance with CONTROL 3.11.2.1 b for tritium, iodine, and particulate, the airdispersion (X/Q) values are provided in Table 2.3.2.1-1.TABLE 2.3.2.1-1 LOCATION OF MAXIMUM EXPOSURE RE BY INHALATIONDischarge Point Receptor Location Atm. DispersionSector Distance (m) (sec/m3)Ground Levelor Vent ENE 338 4.59 E-5Stack SE 937 1.25 E-8Alternatively, inhalation exposure to effluent from the stack may be evaluated at the closesthypothetical individual located at:Stack SE 805 1.29 E-8Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the methods of Regulatory Guide 1.109, may be used.2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATIONCalculate the child thyroid dose rate from a release of 100 jtCi/hr of 1131 from aground level release:I17DRp = 1E6-YRaDFA~iaQeiXe QeRa = 3700 m3/yrDFAija = 4.39E-3 mrem/pCiQei = 0.028 ýtCi/sec [1 00tpCi/hr /3600 sec/hr = 0.02778]X/Qe = 4.59 E-5 sec/mi3DRp = IE6Z3700* 4.39E -3
- 0.028* 4.59E -5DRp = 20.9mrem / yr2.4 NOBLE GAS EFFLUENT DOSE CALCULATIONS -10 CFR 50Doses resulting from the release of noble gases must be calculated to show compliancewith Appendix I of 1 OCFR50. Calculations will be performed at least monthly for allgaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2 to verify thatthe dose to air is kept below the limits specified in CONTROL 3.11.2.2 and the dose toMEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL3.11.2.3.122014 CY-OC-170-301Revision 6Page 89 of 1402.4.1 UNRESTRICTED AREA DOSE -NOBLE GASESCONTROL 3.11.2.2 requires a periodic assessment of releases of noble gases toevaluate compliance with the quarterly air dose limits shown in Table 2.4.1-1.TABLE 2.4.1-1 ANNUAL AIR DOSE LIMITSDuring any calendar quarter During any calendar year_ 5 mrad gamma-air < 10 mrad gamma-air_ 10 mrad beta-air 20 mrad beta-airThe method used to calculate the air dose at the critical location due to noble gas isdescribed by the following equations. The limits are provided in CONTROL 3.11.2.2 forair dose Off Site due to gamma and beta radiations from effluent noble gas.2.4.1.1 AIR DOSE METHODFor Gamma Radiation:Dose Y = y AyVi -vQvi + A ySiQsii=1 QFor Beta RadiationDosep1 = I JAP~i~-eQeie =1 QWhere:Dose y =the gamma dose during any specified time period (mrad).Dose f3 =the beta dose during any specified time period (mrad).AyVj = the air dose factor due to ground level gamma emissions for each identified noblegas radionuclide, i; (mrad/yr per [tCi/m3). Table A-2AySi = the factor for air dose at ground level due to irradiation for an airborne plumeresulting from a Stack release (mrad per pCi), Table A-3.Ap3 = the air dose factor due to beta emissions for each identified noble gas radionuclide, i(mrad/yr per jiCi/m3). Table A-3X X =the annual average relative concentration for areas at or beyond the site boundary for--e --1Q Qreleases from either the Stack or ground vent at the critical location (sec/m3), Table2.4.1.1-1122014 CY-OC-170-301Revision 6Page 90 of 140Qvi = amount of radionuclide i released from vents (ljCi).Qsi = amount of radionuclide i released from the Stack (ltCi).Qei = amount of radionuclide i released from release point e(pLCi).Noble gases may be released from the ground level vents and stack. The quantity ofnoble gas radionuclides released will be determined from the continuous noble gasmonitors and periodic isotopic analyses. The maximum Off Site gamma radiation doserate to air from noble gases discharged from either the stack or from building ventsoccurs at 805 meters SE of the OCGS for the stack and 338 meters ENE of the OCGSfor building vents. Values of AySi depend upon the meteorological conditions and thelocation of exposure and are calculated using the NRC RABFIN code or similar one inaccordance with Reg. Guide 1.109, Appendix B, Section 1. AyVi and ABi are derivedfrom Reg. Guide 1.109, Table B-1 for a semi-infinite cloud, independent of meteorologyor location. Values of AySi, AyVi and ABi used to calculate the noble gas radiation doseto air at 805 meters SE of the OCGS for the stack and 338 meters ENE of the OCGS forbuilding vents are in Table A-3. Reference atmospheric dispersion from the OCGSto 805 meters SE for the stack and 338 meters ENE for building vents is given in Table2.4.1.1-1.TABLE 2.4.1.1-1 RECEPTOR LOCATIONS AND DISPERSION FOR AIR DOSEDischarge Point Receptor Location Atm. DispersionSector Distance (W) (sec/m3)Ground Level ENE 338 4.59 E-5or VentStack SE 805 1.29 E-8Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the requirements of Reg. Guide 1.109 may be used.2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATIONCalculate the gamma air dose from a release of 1 Ci per hour of Xe133 for 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />sfrom a ground level release and 10OCi per hour for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> from an elevated release:Dose'y = AyVi-vQvi + AySiQsii1 QAyVi = 1.12E-5 mrad -m3 /Ci -secX/Q = 4.59 E-5 sec/mi3Qvi = 1E7 RCi [lCi/hr*10hrs*lE6 RCi/Ci]A7Si = 1.03E-1 2 mrad / jiCiQsi = 1E9 piCi [10OCi/hr*10hrs*lE6 tiCi/Ci]122014 CY-OC-170-301Revision 6Page 91 of 140nDose' = -1.12E-5*4.59E-5*1E7+1 .03E-12*IE9i=1Dose' =Z15.14E- 3 +1.03E- 3i=1Dosey = 6.17E -3mradNote how the ground level portion has a higher dose contribution per unit activity thanthe elevated portion.2.4.1.3 INDIVIDUAL PLUME DOSE METHODThe method for dose to an individual from noble gases is essentially identical with theair dose method except that different dose factors apply. Also, since dose to the skincombines the contribution from gamma and beta emissions, the gamma dose must beadded to the beta dose to obtain a total skin dose.For Total Body:Dose(t) = I PyVivQvi+ PY.SiQsi11 QFor SkinDose(s)= e Spi.-eQei + Dose(t)e 11 QWhere:Dose(t) =the total body dose during any specified time period (mrem).Dose(s) = the skin dose during any specified time period (mrem).PyVi = the plume dose factor due to ground level gamma emissions for each identifiednoble gas radionuclide, i; (mrad/yr per 4Ci/m3). Table A-5PYS, = the factor for plume dose at ground level due to irradiation for an airborne plumeresulting from a Stack release (mrad per jiCi), Table A-5.Spi = the skin dose factor due to beta emissions for each identified noble gasradionuclide, i (mrad/yr per p.Ci/m3) from Table A-5.122014 CY-OC-170-301Revision 6Page 92 of 140X X = the annual average relative concentration for areas at or beyond the site boundary forQ Qreleases from either the Stack or ground vent at the critical location (sec/m3) fromTable 2.5.1.Qvi = amount of radionuclide i released from vents (gCi).Qsi = amount of radionuclide i released from the Stack (ý Ci).Qei = amount of radionuclide i released from release point e (GtCi).122014 CY-OC-1 70-301Revision 6Page 93 of 1402.5 RADIOIODINE, PARTICULATE AND OTHER RADIONUCLIDES DOSECALCULATIONS -10 CFR 50Doses resulting from the release of radioiodines and particulates must be calculated toshow compliance with Appendix I of 1OCFR50. Calculations will be performed at leastmonthly for all gaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2and SURVEILLANCE REQUIREMENT 4.11.2.3 to verify that the dose to air is keptbelow the limits specified in CONTROL 3.11.2.2 and the dose to MEMBERS OF THEPUBLIC is maintained below the limits specified in CONTROL 3.11.2.3.The maximum dose to an individual from radioiodines, tritium, and radioactiveparticulates with half-lives of greater than eight days in gaseous effluents released tounrestricted areas is determined as described in Reg. Guide 1.109. Environmentalpathways that radioiodine, tritium, and particulates in airborne effluent follow to themaximally exposed MEMBER OF THE PUBLIC as determined by the annual land usesurvey and reference meteorology will be evaluated. The seasonality of exposurepathways may be considered. For instance, if the most exposed receptor has a garden,fresh and stored vegetables are assumed to be harvested and eaten during April throughOctober. Fresh vegetables need not be considered as an exposure pathway duringNovember through March. To assess compliance with CONTROL 3.11.2.3, the dosedue to radioactive iodine, tritium, and particulates in airborne effluent is calculated to aperson residing 972 meters ESE of the OCGS for ground-level or vent and 937 metersSE of the OCGS for stack. Reference atmospheric dispersion and deposition factors aregiven in Table 2.5-1.TABLE 2.5-1 DISPERSION FOR 10CFR50 DOSESDischarge Point Dispersion DepositionX/Q (sec/m3) D/Q(1/m2)Ground Levelor Vent 5.13 E-6 1.68 E-8Stack 1.25 E-8 2.39 E-9The environmental pathways of exposure to be evaluated are: inhalation, irradiation fromground deposition, and ingestion of milk (cow and goat are treated separately), meat,and vegetables. Eight organs are considered: Bone, Liver, Total Body, Thyroid, Kidney,Lung, GI-LLI (Gastro-Intestinal tract / Lower Large Intestine), and Skin. Four differentage groups are considered: Infants, Children, Teens, and Adults. Doses are calculated toa 'receptor' -a person who inhales the airborne activity and resides in a location withground deposition, and eats and drinks the foodstuffs produced. The maximally exposedindividual is conservatively assumed to reside at the location of the highest sum of theinhalation and ground plane doses, while eating and drinking foodstuffs transported fromthe locations that are highest for those pathways. Receptor locations are provided inTable A-4.Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") thatimplements the requirements of Reg Guide 1.109 may be used.122014 CY-OC-170-301Revision 6Page 94 of 1402.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHERRADIONUCLIDES.Dose from the inhalation pathway is generally in the form:Dja = RaT L-QiDFAi/aExp(-)uTr)iQWhere:Dja = the dose to the organ j (of eight) of age group a (of four)Ra = the respiration rate for age group a from Table B-1T = the duration of the release in fraction of a yearX = The atmospheric dispersion to the point of interest (the 'receptor') in sec/m3 fromTable 2.5-1Qi = The release rate of radionuclide i (pCi/sec)DFAija = The inhalation dose conversion factor (mrem per pCi) for radionuclide i to organ j ofage group a from Reg. Guide 1.109 Appendix E.Xi = decay constant of isotope i: 0.693/ Half life in yearsTr = plume transit time from release to receptor in yearsMi and Tr may be in any time units as long as they are the sameNote that a 'depleted X/Q' (dX/Q) is applicable to particulates only, which accounts forthe natural settling and lack of surface reflection of particulates to estimate thedownwind concentration accounting for these removal processes. Depleted X/Q will beslightly smaller than the X/Q. This is not used in the ODCM for simplicity. Using the X/Qis therefore slightly conservative compared to the dX/Q.122014 CY-OC-1 70-301Revision 6Page 95 of 1402.5.2 EXAMPLE CALCULATION -INHALATION OF RADIOIODINES, TRITIUM,PARTICULATES, AND OTHER RADIONUCLIDESCalculate the dose to child lung from inhalation from a ground level release of 100 pLCiof Co-60 in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Plume transit decay time is ignored (exp(-AiTr)=1).Dja = RaT -- QiDFAijaDja = the dose to the organ j (of eight) of age group a (of four)Ra = 3700 m3/yrT = 0.00114 yrs [10 hrs / 8760 hrs / yr]X 5.13 E-6 sec/m3sQi = 2.78E3 pCi/sec [100 pCi
- 1 E6 pCi/jiCi / (10 hrs*3600 sec hr)]DFAija =1.91 E-3 mrem / pCiDja = 3700* 0.00114* 5.13E- 6 *2.78E3
- 1.91E -3Dja = 1. 1 5E -4mrem2.5.3 INGESTION OF RADIOIODINES, PARTICULATES AND OTHER RADIONUCLIDESDose from the ingestion pathways is more complex and is broken out here into multiplesteps:2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE ANDVEGETATION -OTHER THAN TRITIUMThe concentration of a radionuclide in a foodstuff (other than tritium -see section2.5.3.3 for tritium) is dependent on the atmospheric deposition, the biological uptakeinto the food, various decay times (plume travel, harvest to table, etc.) and is generallyof the form:Where:Civ = the concentration (pCi/kg) of radionuclide i in vegetationQi = the release rate of isotope i in pCi/hrD =The atmospheric deposition to the point of interest (the 'receptor') in 1/M2 fromQTable 2.5-1.122014 CY-OC-170-301Revision 6Page 96 of 140Civ D Qi{r(l -EXP(-MEiTe)) + Biv(1 -EXP(-AiTb)) EXP(-ATh)EXP(--IiTr)Q Yv),Ei PMir = the retention coefficient for deposition onto vegetation surfaces (1.0 for iodines, 0.2for particulates)ki = the decay constant of radionuclide i; 0.693/half life in hoursXEi =the effective removal constant which is the sum of Xi + ?,w where Xw is theweathering constant, 0.0021/hrTe = duration of crop exposure during the growing season in hours. This is not the entireduration of the growing season, and is different for leafy vegetable andfruit/grain/vegetables. Provided in Table E-15 of Reg. Guide 1.109 or Table B-1.Yv = agricultural yield Kg of vegetation per m2, typically 0.7 kg/M2Biv = soil uptake concentration factor for transfer of the radionuclide i from the soil tothe vegetation through normal root uptake processes in pCi/kg in vegetation perpCi/Kg in soil. Values are provided in Reg. Guide 1.109 Table E-1.Tb = the length of time the soil is exposed to contaminated inputs -nominally 30years (2.63E5 hr)P = effective soil density in kg/mi2 normally 240 kg/M2Th = holdup time, the time the foodstuff is in transit between harvest andconsumption in hoursTr = plume transit time from release to receptor in hours2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE INANIMAL FORAGE AND VEGETATION -OTHER THAN TRITIUM.Calculate the forage and vegetation concentration from a ground level release of100 ptCi of Co-60 in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> (plume transit time is ignored Tr=0, EXP(-XiTr)=I):Civ D Qi{ r(1 -EXP(-MiTe)) + Biv(1 -EXP(-).iTb)) EXP(_XiTh)EXP(_XiTr)QYvmEi P MD/Q = 1.67E-8 m2Qi = 1 E7 pCi/hr [100.pLCi
- 1E6 pCi/iCi / 10 hr]r = 0.2Xi = 1.5E-5/hr [0.693 / (5.27yr
- 8760 hr/yr)]XEi = 2.12E-3 /hr [1.5E-5 + 0.0021]Te = 720 hr [grass-cow-milk-man pathway value]122014 CY-OC-170-301Revision 6Page 97 of 140YvBivTbPTh= 0.7 kg/mr2= 9.4E-3= 2.63E5 hr= 240 kg/mr2= 24.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />sCiv = 1.67E -8
- 1E70.2* (1- EXP(-2.12E -3*720)) +{ EXP(-1.5E.-75**.O)9.4E -3 * (1 -EXP(-1.5E -5
- 2.63E5))1 240
- 1.5E -5Civ =1.67E-8*1E7{105Civ =1.67E-1{.0.2 * (1 -EXP (- 1.53))1.48E -39.4E -3 * (1 -EXP (-3+}EXP (-0 ).95))3.6E -3*1"Civ = 18.0 pCi / Kg2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATIONSince tritium is assumed to be released as tritiated water (HTO), the concentration oftritium in a foodstuff is dependent on atmospheric dispersion like a gas, rather thanparticulate deposition as for other radionuclides for foodstuff uptake. Further, theconcentration of tritium in food is assumed to be based on equilibrium between theconcentration of the tritium in the atmospheric water and the concentration of tritium inthe water in the food. Concentration of tritium in vegetation can be calculated generally inthe form (a plume transit decay term: EXP(-XiTr) is ignored since plume travel times arevery short compared to the half life):Ctv = 1000Qt x *0.75
- 0.5Q HWhere:Ctv= the concentration (pCi/kg) of tritium in vegetation1000 =g per kgQt = the release rate of the tritium in pCi/ sec122014 CY-OC-1 70-301Revision 6Page 98 of 140X/Q = the atmospheric dispersion at the vegetation point, sec/mr3 from Table 2.5-10.75 = the fraction of vegetation that is water0.5 = the effective ratio between the atmospheric water concentration and thevegetation concentrationH = the absolute humidity g/m3.Absolute humidity is seasonally dependent, varyingfrom as little as 1 in the winter to as much as 20 in the summer. Monthly averagevalues derived from historical data are provided in Table B-2.2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGEAND VEGETATION.Calculate the forage and vegetation concentration from a ground level release of100 1iCi of H-3 in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Plume transit decay time is ignored (exp(-XiTr)=1):Ctv = I 000Qt X *0.75* 0.5Q HQt = 2778 pCi/sec [1 0OuCi
- 1E6 pCi/uCi / (1 Ohrs*3600sec/hr)]X/Q = 5.13E-6 sec/m3H = 5 g/m3 (assumed for this example)Ctv = 2778
- 1000 *5.13E -6
- 0.75* 0.55Ctv = 1.07 pCi / kg2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEATMeat and milk animals are assumed to eat both pasture grass and stored feed. During afraction of the year, they may be assumed to be exclusively on stored feed, outside of thegrowing season. If using annual average release, the fraction of stored and fresh feedmust be accounted for with fractions, otherwise (as in this ODCM), the fresh pasturepathway is turned on or off depending on the growing season.The concentration of a radionuclide in the animal feed is calculated as follows:Civ = FpCis + (1 -Fp)Cis(l -Fs) + CipFs(l -Fp)Where:Fp = the growing season pasture factor: 1 if not growing season, 0 if in growing season122014 CY-OC-170-301Revision 6Page 99 of 140Fs = the fraction of the daily feed from fresh pasture from Table B-1 or Exhibit E-15 fromReg. Guide 1.109.Cip = the concentration in the fresh pasture feed (Civ from section 2.5.3.2 with Th = 0 forimmediate consumption)Cis = the concentration in stored feed (Civ from section 2.5.3.2 with Th = 90 days)The concentration in the milk is then based on this feed concentration:Cim = FmCivQfEXP (-)LiTf)Where:Cim = the concentration in milk pCi/IFm = the transfer coefficient of intake to concentration in the milk (dIl) from Reg. Guide1.109 Table E-1.Qf = feed intake rate Kg/d from Reg. Guide 1.109 Table E-3.2X = radionuclide i decay constant in 1/daysTf = transport time from milk production to consumption (2 days for milk)The Goat milk pathway may be similarly evaluated:Cim = FgCivQIfEP (-2iTf)Where:Fg = the transfer coefficient of intake to concentration in the milk (d/I) for goats fromReg. Guide 1.109 Table E-2.And for meat:CO = FfCivQJEXP (-XiTs)Where:Ff = the transfer coefficient of intake to concentration in the meat d/kg from Reg.Guide 1.109 Table E-1.Ts = the transport time from slaughter to consumption (20 days)122014 CY-OC-170-301Revision 6Page 100 of 1402.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILKAND MEATCalculate the concentration in cow milk from a ground level release of 100 liCi ofCo-60 in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Plume transit decay time is ignored (exp(-XiTr)=l):Civ = FpCis + (l- Fp)Cis(1- Fs) + CipFs(l- Fp)Assume animals are on pasture and receive half of their food from stored feed.Cip = 18.0 pCi/kg as previously calculated in section 2.5.3.2Fp = 0Fs = 0.5Cis is calculated by applying a 90 day decay term to the Cip value previously calculated,since the previous decay correction was for 0 time as shown in 2.5.3.2.Cis = 18.0 * (exp(-0.693
- 90 /(5.27
- 365)))Cis = 17.4pCi / kgCiv is then:Civ =0*17.4+ (1-0)17.4 (1-0.5) +18.0
- 0.5 * (1-0)Civ = 17.7pCi/kgThe concentration in milk is given by:Cim = FmCivQEXP (-AiTf)Fm =1.OE-3 d/IQf = 50 Kg/dXi = 3.6E-4/d [0.693 / (5.27 yrs*365 days/yr)]Cim = .OE -3
- 17.7
- 50
- EXP(-3.6E -4
- 2)Cim = 0.88pCi/lThe concentration in meat given by:Cif = FfCivQJEXP (-tiTs )Ff =1.3E-2 d/kg122014 CY-OC-1 70-301Revision 6Page 101 of 140Qf = 50 Kg/dXi = 3.6E-4/dCf = 1.3E -2
- 17.7
- 50* EXP(-3.6E- 4
- 20)Cif = 11.5pCi / kg2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLESThe environmental pathway ingestion dose is the sum of the milk, meat, and vegetationingestion pathways. There are two separate pathways for vegetation: fresh leafyvegetables and a combination of fruits, non-leafy vegetables, and grains. These differonly in the decay and buildup processes applied to account for the environmentalexposure, and transportation delay decay represented by Te and Th as shown in section2.5.3.1. For long half-life isotopes (e.g. Co-60) the decay differences have little impact onthe dose.Dose from the environmental ingestion pathways is generally of the form:Dja = T DFiija[UavFgCiv+ UamCim + UafCif + UalFlCil]Where:Dja = the dose to organ j of age group a -mremT = fraction of year of release durationDFlija = the ingestion dose factor for isotope i to organ j for age group a -mrem/pCi from Reg.Guide 1.109 Appendix EUav = Ingestion rate (usage factor) for non-leafy vegetables, grains, and fruits for age groupa from Reg. Guide 1.109 Table E-5 or Table B-I.Fg = the fraction of vegetables, grains, and fruits from the location of interest : 0.76 in Reg.Guide 1.109.Civ = the concentration of isotope i in the vegetables, fruits, and grains calculated fromsection 2.5.3.2.Uam = Ingestion rate (usage factor) for milk for age group a: from Table B-1 or Reg. Guide1.109 Table E-5.Cim = the concentration of isotope i in milk calculated from section 2.5.3.5.Uaf = the ingestion rate for meat for age group a: from Table B-1 or Reg. Guide 1.109 TableE-5.122014 CY-OC-170-301Revision 6Page 102 of 140Cif = the concentration of isotope i in meat calculated from section 2.5.3.2.Ual = the ingestion rate for leafy vegetables for age group a: from Table B-1 or Reg. Guide1.109 Table E-5.FI = the fraction of annual leafy vegetable ingestion from the location of interest : 1.0 inReg. Guide 1.109.Cil = concentration of isotope i in the leafy vegetables for direct human consumption: Civcalculated from section 2.5.3.2 with Th=0.2.5.3.8 EXAMPLE CALCULATION -DOSE FROM CONSUMPTION OF MILK, MEAT, ANDVEGETABLESCalculate the ingestion dose to child whole body from a ground level release of 100gCi of Co-60 in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Plume transit decay time is ignored (exp(-kiTr)=1):Dja = TZ DFIija[UavFgCiv + UamCim + UafCif + UalFlCil]Where:T = 0.00114 yr [10hrs / 8760 hrs/yr)DFlija = 1.56E-5 mrem/pCiUav = 520Fg = 0.76Civ = 17.6 [18.0*EXP(-X*60) using 60 day delay for ingestion]Uam = 330Cim = 0.88Uaf = 41Cif = 11.5Ual = 26FI =1Cil = 17.7Dja=.0011411.56E- 5[520*0.76* 17.6+330*0.88+41* 11.5 +26*1*17.7]Dja= .0011411.56E -5[6956+ 290+472+ 460]Dja = 1.45E -4mrem: child: wholebody2.5.4 GROUND PLANE DEPOSITION IRRADIATIONDose from ground plane deposition is estimated by determining the surface activityresulting from the release.122014 CY-OC-170-301Revision 6Page 103 of 1402.5.4.1 GROUND PLANE CONCENTRATIONThe ground surface activity is estimated as:Cig = D -(1- EXP(-2iTb))Q xiWhere:Cig = ground plane concentration of radionuclide i in pCi/mr2D = local atmospheric release deposition factor in 1/mi2 from Table 2.5-1Qi = release rate in pCi/secXi = radiological decay constant in 1/secTb = long term buildup time 30 years (9.46E8 sec)Note: Qi, Mi and Tb can utilize any time units as long as they are all the same2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATIONCalculate the ground plane concentration from a 100 jtCi release of Co-60 over 10hours from a ground level release point.Cig = D (1- EXP(-),iTb))Q xiD 1.67E-8 /mf2QQi = 2778 pCi/sec [100pCi/10hrs/3600sec/hr]ki = 4.17E-9/sec [0.693/(5.27yr*8760hr/yr*3600sec/hr)]Tb = 9.46E8 secCig=167E-8 2778Cig = 1.67E 8 (l EXP(-4.17E -9* 9.46E8))4.17E -99Cig = 1.09E4pCi / m2122014 CY-OC-170-301Revision 6Page 104 of 1402.5.4.3 GROUND PLANE DOSEAnnual dose from the ground plane deposition is of the form:Djg= 8760
- T
- Sf CigDFGiWhere:Djg = the annual dose (mrem) from ground plane pathway (g) to the total body or skin (j)8760 = hours in a yearT = fraction of year release is in progressSf = shielding factor accounting for shielding from dwelling from Table B-1DFGij = Ground plane dose factor for skin or total body (j) for radionuclide i fromTable E-6 of Reg. Guide 1.109 in mrem/hr / pCi/m2.2.5.4.4 EXAMPLE GROUND PLANE DOSECalculate the ground plane Total Body dose from a 100 p.Ci release of Co-60 over 10hours from a ground level release point.Djg = 8760
- T
- SfCigDFGijT = 0.00114 [10/8760]Sf = 0.7DFGij = 1.7E-8Cig = 1.09E4Djg = 8760* 0.00114 0.711.09E4 *1.7E- 8iDjg = 1.30E -3mremTotalB ody2.6 PROJECTED DOSES -GASEOUSThe projected doses in a 31 day period are equal to the calculated doses from thecurrent 31 day period.3.0 TOTAL DOSE TO MEMBERS OF THE PUBLIC -40 CFR 190The Radiological Environmental Monitoring Report (REMP) submitted by May 1st of eachyear shall include an assessment of the radiation dose to the likely most exposedMEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle122014 CY-OC-170-301Revision 6Page 105 of 140sources (including dose contributions from effluents and direct radiation from on-sitesources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of OysterCreek, the sources of exposure need only consider the Oyster Creek Generating Station.No other fuel cycle facilities would contribute significantly to the MEMBER OF THEPUBLIC dose for the Oyster Creek vicinity, however, both plant operation and ISFSIsources must be included in the dose assessment.To assess compliance with CONTROL 3.11.4, calculated organ and total body doses fromeffluents from liquid pathways and atmospheric releases as well as any dose from directradiation will be summed.As appropriate for demonstrating/evaluating compliance with the limits of CONTROL3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used forproviding data on actual measured levels of radiation and / or radioactive material andresultant dose to the MEMBER OF THE PUBLIC in the actual pathways of exposure.3.1 EFFLUENT DOSE CALCULATIONSFor purposes of implementing the surveillance requirements of CONTROL 3/4.11.4 andthe reporting requirements of Technical Specification 6.9.1 .d (ARERR), dose calculationsfor the Oyster Creek Generating Station may be performed using the calculation methodscontained within the ODCM; the conservative controlling pathways and locations from theODCM or the actual pathways and locations as identified by the land use census(CONTROL 3/4.12.1) may be used. Average annual meteorological dispersionparameters provided herein or meteorological conditions concurrent with the releaseperiod under evaluation may be used.3.2 DIRECT EXPOSURE DOSE DETERMINATIONAny potentially significant direct exposure contribution to off-site individual doses may beevaluated based on the results of environmental measurements (e.g., dosimeter) and/orby the use of radiation transport and shielding calculation methodologies.4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMThe operational phase of the Radiological Environmental Monitoring Program (REMP) isconducted in accordance with the requirements of CONTROL 3.12.1. The objectives ofthe program are:-To determine whether any significant increases occur in the concentration ofradionuclides in the critical pathways of exposure in the vicinity of Oyster Creek-To determine if the operation of the Oyster Creek Generating Station has resulted inany increase in the inventory of long lived radionuclides in the environment;-To detect any changes in the ambient gamma radiation levels; and-To verify that OCGS operations have no detrimental effects on the health and safety ofthe public or on the environment.The REMP sample locations are presented in Appendix E.122014 CY-OC-170-301Revision 6Page 106 of 140APPENDIX A -DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS122014 CY-OC-1 70-301Revision 6Page 107 of 140Table A-1 Dose Conversion Factors for Deriving Radioactive Noble GasRadionuclide-to-Dose Equivalent Rate Factors* IRadionuclide Factor DFSi for Factor DFVi forStack Release* Ground-level orVent Release**mrem-sec mrem-m3pCi-year pCi-yearKr83m 9.21E-10 7.56E-02Kr85m 1.46E-04 1.17E+03Kr85 2.58E-06 1.61 E+01Kr87 8.65E-04 5.92E+03Kr88 2.16E-03 1.47E+04Kr89 2.06E-03 1.66E+04Kr90 1.56E+04Xe131m 3.13E-05 9.15E+01Xe133m 2.50E-05 2.51E+02Xe133 2.15E-05 2.94E+02Xe135m 4.81E-04 3.12E+03Xe135 2.51E-04 1.81E+03Xe137 1.79E-04 1.42E+03Xe138 1.37E-03 8.83E+03Xe139 2.14E-04 5.02E+03Ar4l 1.67E-03 8.84E+03* Based on meteorology applicable at 229 meters SW of stack.** For exposure to a semi-infinite cloud of noble gas.122014 CY-OC-1 70-301Revision 6Page 108 of 140Table A-2 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors*Radionuclide PSi** PVi*** A7Vi*** SBi***mrem mrem-m3 mrad-m3 mrem-m3ýCi ýiCi-sec (Ki) ý.Ci-sec (Mi) jiCi-sec (Li)Kr83m 2.92E-17 2.40E-09 6.13E-07 -Kr85m 4.64E-12 3.71E-05 3.90E-05 4.63E-05Kr85 8.18E-14 5.11E-07 5.46E-07 4.25E-05Kr87 2.74E-11 1.88E-04 1.96E-04 3.09E-04Kr88 6.84E-1 1 4.67E-04 4.83E-04 7.52E-05Kr89 6.53E-1 1 5.27E-04 5.49E-04 3.21E-04Kr90 4.95E-04 5.17E-04 2.31E-04Xe131m 9.92E-13 2.90E-06 4.95E-06 1.51E-05Xe133m 7.94E-13 7.97E-06 1.04E-05 3.16E-05Xe133 6.83E-13 9.33E-06 1.12E-05 9.71E-06Xe135m 1.53E-11 9.90E-05 1.07E-04 2.26E-05Xe135 7.97E-12 5.75E-05 6.1OE-05 5.90E-05Xe137 5.69E-12 4.51E-05 4.79E-05 3.87E-04Xe138 4.34E-11 2.80E-04 2.92E-04 1.31 E-04Xe139 6.79E-12 --Ar4l 5.30E-11 2.81E-04 2.95E-04 8.54E-05* All of these dose factors apply out-of-doors.** Based on meteorology at 229 meters SW of effluent stack.* Derived from Reg Guide 1.109, Revision 1, Table B-1.122014 CY-OC-170-301Revision 6Page 109 of 140I Table A-3 Air Dose Conversion Factors for Effluent Noble GasRadionuclide AySi** AyVi*** Ap3i***mrad mrad-m3 mrad-m3pCi p.Ci-sec(M1) pCi-sec (Ni)Kr83m 1.33E-16 6.13E-07 9.14E-06Kr85m 6.89E-12 3.90E-05 6.25E-05Kr85 1.24E-13 5.46E-07 6.19E-05Kr87 4.13E-11 1.96E-04 3.27E-04Kr88 1.03E-10 4.83E-04 9.30E-05Kr89 9.82E-1 1 5.49E-04 3.37E-04Kr90 5.17E-04 2.49E-04Xel31 m 1.50E-12 4.95E-06 3.52E-05Xe133m 1.23E-12 1.04E-05 4.70E-05Xe133 1.03E-12 1.12E-05 3.33E-05Xel35m 2.31E-11 1.07E-04 2.35E-05Xe135 1.20E-11 6.1OE-05 7.81 E-05Xe137 8.59E-12 4.79E-05 4.03E-04Xel 38 6.51E-11 2.92E-04 1.51E-04Xe139 1.02E-11 -Ar4l 7.94E-11 2.95E-04 1.04E-04** Based on meteorology at 229 meters SW of effluent stack.*** Derived from Reg Guide 1.109, Revision 1, Table B-I.122014 CY-OC-1 70-301Revision 6Page 110 of 140Table A-4 Locations Associated with MaximumExposure of a Member of the Public*Effluent LocationDistance Direction(meters) (to)Liquid U.S. Route 9 Bridge at Discharge CanalAirborne Iodine and Particulates 937 SETritium 937 SENoble Gases 937 SEIrradiation by OCGS Site Boundary AllNoble Gas g Air Dose 937 SENoble Gas B Air Dose 937 SENote: the nearby resident experiencing the maximum exposure to airborne effluent fromthe Station is located 937 meters SE of the OCGS. The nearby resident (part-time)experiencing the maximum exposure to gamma radiation directly from the Station islocated 618 meters WSW of the OCGS. The most exposed member of the public isassumed to be exposed by irradiation from the OCGS, by inhaling airborne effluent, byirradiation by the airborne effluent, by irradiation by the airborne plume of the noble gas, byradionuclides deposited onto the ground, by irradiation by shoreline deposits, and byeating fish and shellfish caught in the discharge canal.*The age group of the most exposed member of the public is based on Reg. Guide 1.109,Revision 1.122014 CY-OC-170-301Revision 6Page 111 of 140Table A-5 Critical Receptor Noble Gas Dose Conversion Factors* IRadionuclide PySi** PyVi*** AyVi*** AySi** SBi***mrem mrem-m3 mrad-m3 mrad mrem-m3ýLCi gCi-sec(Ki) ptCi-sec(Mi) ptCi ýtCi-sec(Lj)Kr83m 4.61E-17 2.40E-09 6.13E-07 1.77E-14Kr85m 2.13E-12 3.71E-05 3.90E-05 3.16E-12 4.63E-05Kr85 3.38E-14 5.11E-07 5.46E-07 5.12E-14 4.25E-05Kr87 1.08E-11 1.88E-04 1.96E-04 1.63E-11 3.09E-04Kr88 2.76E-11 4.67E-04 4.83E-04 4.14E-11 7.52E-05Kr89 2.02E-11 5.27E-04 5.49E-04 3.03E-11 3.21E-04Kr9O 4.95E-04 5.17E-04 2.31E-04Xel31 m 5.05E-13 2.90E-06 4.95E-06 8.03E-13 1.51 E-05Xe133m 3.95E-13 7.97E-06 1.04E-05 6.50E-13 3.16E-05Xe133 3.88E-13 9.33E-06 1.12E-05 6.13E-13 9.71E-06Xe135m 5.82E-12 9.90E-05 1.07E-04 8.80E-12 2.26E-05Xel35 3.51E-12 5.75E-05 6.1OE-05 5.25E-12 5.90E-05Xe137 1.74E-12 4.51E-05 4.79E-05 2.64E-12 3.87E-04Xel38 1.72E-11 2.80E-04 2.92E-04 2.58E-11 1.31E-04Xel39 9.30E-13 -1.40E-12 -Ar4l 2.07E-11 2.81E-04 2.95E-04 3.1OE-11 8.54E-05* All of these dose factors apply out-of-doors.** Based on meteorology at 937 meters SE of effluent stack.Derived from Reg Guide 1.109, Revision 1, Table B-1122014 CY-OC-1 70-301Revision 6Page 112 of 140APPENDIX B -MODELING PARAMETERS122014 CY-OC-1 70-301Revision 6Page 113 of 140Table B-I- OCGS Usage Factors For Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorFraction Of Produce From Local Garden 7.6E-1Soil Density In Plow Layer (Kg/m2) 2.4E+2Fraction Of Deposited Activity Retained On Vegetation 2.5E-1Shielding Factor For Residential Structures 7.0E-1Period Of Buildup Of Activity In Soil (hr) 1.31 E+5Period of Pasture Grass Exposure to Activity (hr) 7.2E+2Period Of Crop Exposure to Activity (hr) 1.44E+3Delay Time For Ingestion Of Stored Feed By Animals (hr) 2.16E+3Delay Time For Ingestion Of Leafy Vegetables By Man (hr) 2.4E+1Delay Time For Ingestion Of Other Vegetables By Man (hr) 1.44E+3Transport Time Milk-Man (hr) 4.8E+1Time Between Slaughter and Consumption of Meat Animal (hr) 4.8E+2Grass Yield Wet Weight (Kg/mi2) 7.0E-1Other Vegetation Yield Wet-Weight (Kg/m2) 2.0Weathering Rate Constant For Activity on Veg. (hr-1) 2.1 E-3Milk Cow Feed Consumption Rate (Kg/day) 5.0E+1Goat Feed Consumption Rate (Kg/day) 6.0Beef Cattle Feed Consumption Rate (Kg/day) 5.0E+1Milk Cow Water Consumption Rate (L/day) 6.0E+1Goat Water Consumption Rate (L/day) 8.0Beef Cattle Water Consumption Rate (L/day) 5.0E+1Environmental Transit Time For Water Ingestion (hr) 1.2E+1Environmental Transit Time For Fish Ingestion (hr) 2.4E+1Environmental Transit Time For Shore Exposure (hr) 0Environmental Transit Time For Invertebrate Ingestion (hr) 2.4E+1122014 CY-OC-170-301Revision 6Page 114 of 140Table B-1 (Continued)OCGS Usage Factors for Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorWater Ingestion (L/yr)a. Adult 7.3E+2b. Teen 5.1E+2c. Child 5.1E+2d. Infant 3.3E+2Shore Exposure (hr/yr)a. Adult 1.2E+1b. Teen 6.7E+1c. Child 1.4E+1d. Infant 0Salt Water Sport Fish Ingestion (Kg/yr)a. Adult 2.1EE+1b. Teen 1.6E+1c. Child 6.9d. Infant 0Salt Water Commercial Fish Ingestion (Kg/yr)a. Adult 2.1E+1b. Teen 1.6E+1c. Child 6.9d. Infant 0Salt Water Invertebrate Ingestion (Kg/yr)a. Adult 5.0b. Teen 3.8c. Child 1.7d. Infant 0Irrigated Leafy Vegetable Ingestion (Kg/yr)a. Adult 6.4E+1b. Teen 4.2E+1c. Child 2.6E+1d. Infant 0122014 CY-OC-170-301Revision 6Page 115 of 140Table B-1 (Continued)OCGS Usage Factors for Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorIrrigated Other Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2b. Teen 6.3E+2c. Child 5.2E+2d. Infant 0Irrigated Root Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2b. Teen 6.3E+2c. Child 5.2E+2d. Infant 0Irrigated Cow and Goat Milk Ingestion (L/yr)a. Adult 3.1E+2b. Teen 4.0E+2c. Child 3.3E+2d. Infant 3.3E+2Irrigated Beef Ingestion (Kg/yr)a. Adult 1.1E+2b. Teen 6.5E+1c. Child 4.1E+1d. Infant 0Inhalation (m3/yr)a. Adult 8.0E+3b. Teen 8.0E+3c. Child 3.7E+3d. Infant 1.4E+3Cow and Goat Milk Ingestion (L/yr)a. Adult 3.1E+2b. Teen 4.01E+2c. Child 3.3E+2d. Infant 3.3E+2Meat Ingestion (Kg/yr)a. Adult 1.1E+2b. Teen 6.5E+1c. Child 4.1E+1d. Infant 0122014 CY-OC-1 70-301Revision 6Page 116 of 140Table B-1 (Continued)OCGS Usage Factors for Individual Dose AssessmentEffluent Ingestion Parameters Usage FactorLeafy Vegetable Ingestion (Kg/yr)a. Adult 6.4E+1b. Teen 4.2E+1c. Child 2.6E+1d. Infant 0Fruits, Grains, & Other Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2b. Teen 6.3E+2c. Child 5.2E+2d. Infant 0122014 CY-OC-170-301Revision 6Page 117 of 140Table B-2 Monthly Average Absolute Humidity g/m3(derived from historical climatological data)Average AbsoluteMonth Humidity (q/m3)January 3.3February 3.3March 4.5April 6.1May 9.4June 12.8July 15.2August 15.6September 12.4October 7.9November 5.9December 3.8122014 CY-OC-170-301Revision 6Page 118 of 140APPENDIX C -REFERENCES122014 CY-OC-170-301Revision 6Page 119 of 140Table C-1 -REFERENCES1) Oyster Creek Updated Final Safety Analysis Report2) Oyster Creek Facility Description and Safety Analysis Report3) Oyster Creek Operating License and Technical Specifications4) NUREG 1302 "Off Site Dose Calculation Manual Guidance: Standard Radiological EffluentControls for Boiling Water Reactors" -Generic Letter 89-10, Supplement No. 1 ,April 19915) Reg Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases of radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" Rev.1, June 19746) Reg Guide 1.237) Reg Guide 1.978) Reg Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I", Rev 1,October, 19779) Reg Guide 1.111 "Methods for Estimating Atmospheric Transport and Dispersion ofGaseous Effluents in Routine Releases From Light-Water-Cooled Reactors", Rev. 1, July,197710) Reg Guide 4.8" Environmental Technical Specifications for Nuclear Power Plants"11) NRC Radiological Assessment Branch Technical Position, Rev 1, November 1979(Appendix A to NUREG1302)12) NUREG-001613) NUREG-013314) Licensing Application, Amendment 13, Meteorological Radiological Evaluation for theOyster Creek Nuclear Power Station Site.15) Licensing Application, Amendment 11, Question IV-8.16) Evaluation of the Oyster Creek Nuclear Generating Station to Demonstrate Conformanceto the Design Objectives of 1OCFR50, Appendix I, May, 1976, Tables 3-1017) XOQDOQ Output Files for Oyster Creek Meteorology, Murray and Trettle, Inc.122014 CY-OC-1 70-301Revision 6Page 120 of 14018) Hydrological Information and Liquid Dilution Factors Determination to Conform withAppendix I Requirements: Oyster Creek, correspondence from T. Potter, Pickard, Loweand Garrick, Inc. to Oyster Creek, July, 1976.19) Carpenter, J. J. "Recirculation and Effluent Distribution for Oyster Creek Site", Pritchard-Carpenter Consultants, Baltimore, Maryland, 1964.20) Nuclear Regulatory Commission, Generic Letter 89-01, "Implementation of ProgrammaticControls for Radiological Effluent Technical Specifications in the Administrative ControlsSection and Relocation of the Procedural Details of RETS to the ODCM or PCP", January,1989.21) Ground Water Monitoring System (Final Report), Woodward-Clyde Consultants, March,1984.22) Meteorology and Atomic Energy, Department of Energy, 1981.23) SEEDS Code Documentation through V & V of Version 98.8F (Radiological EngineeringCalculation No. 2820-99-005, Dated 3/23/99)24) Lynch, Giuliano, and Associates, Inc., Drawing Entitled, "Minor Subdivision, Lots 4 and4.01 Block 1001", signed 13 Sep 99.25) Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Positionfor Radiological Effluent and Environmental Measurements".26) NUREG/CR-4007 (September 1984).27) HASL Procedures Manual, HASL-300 (revised annually).28) Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental andRoutine Reactor Releases for the Purposes of Implementing Appendix I," April 197729) Reg. Guide 4.1330) 10CFR20, Appendix B, Table 2, Annual Limits on Intake (ALIs) and Derived AirConcentrations (DACs) of Radionuclides for Occupational Exposure; EffluentConcentrations; Concentrations for Release to Sewerage31) Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleet wideAssessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No.045136(18), September, 2006.32) Letter date April 23, 2013 from Murray and Trettel, Incorporated33) Letter dated January 10, 2013 titled "Meteorology and Dose Factor Update -ODCMRevision 6"122014 CY-OC-170-301Revision 6Page 121 of 140APPENDIX D -SYSTEM DRAWINGS122014 CY-OC-170-301Revision 6Page 122 of 140FIGURE D-1-la: LIQUID RADWASTE TREATMENT CHEM WASTE AND FLOOR DRAINSYSTEM.C>0D0 Fcc/)Cl)LO* V0 (0vcuC )..L-00)t0 Scu CL a.U -.4 cl°m .o_ C-Lo E122014 CY-OC-170-301Revision 6Page 123 of 140FIGURE D-1-lb: LIQUID RADWASTE TREATMENT -HIGH PURITY AND EQUIPMENTDRAIN SYSTEMI.-z0 z',,ICN.COC0~co a.WWL EU)~ C (0- .co M.-,-z"a.. o.,T1* I >"_ A8 --° -lE,o i-I 1 <0122014 CY-OC-1 70-301Revision 6Page 124 of 140FIGURE D-1-lc: GROUNDWATER REMEDIATION SYSTEMComposite Flow MonitorSampler122014 CY-OC-170-301Revision 6Page 125 of 140FIGURE D-1-2: SOLID RADWASTE PROCESSING SYSTEMProcessTemp ModWC-T-I A/ B/CFilterSludgeOption A122014 CY-OC-170-301Revision 6Page 126 of 140FIGURE D-2-1: GASEOUS RADWASTE TREATMENT -AUGMENTED OFF GAS SYSTEM122014 CY-OC-170-301Revision 6Page 127 of 140FIGURE D-2-2: VENTILATION SYSTEMOYSTI ER CREEKTUBVENT PATHSlae STACKICondV-7-31l1V- 1161~~IIiV 7s(1-6)CODN. RSI-I.-CEV-28-2TURBINE BUILDINGIIV.~-23-14V-29-21II U -STANDBY GAS TREATMENT SYSTEM V-28-19V-28-17 NV.RA7 Torus122014 CY-OC-1 70-301Revision 6Page 128 of 140Figure D-2-3 AOG Ventilation SystemHV-S-1O122014 CY-OC-1 70-301Revision 6Page 129 of 140APPENDIX E -RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM -SAMPLE TYPE AND LOCATIONAll sampling locations and specific information about the individual locations are given inTable E-1. Figures E-1, E-2 and E-3 show the locations of sampling stations with respect tothe site. Figure E-4 shows the site layout.122014 CY-OC-1 70-301Revision 6Page 130 of 140TABLE E-1: REMP SAMPLE LOCATIONS(1)1. Direct RadiationDOS -Inner Ring at or near site boundaryCode (miles) (degrees) Description1 0.4 219 SW of site at OCGS Fire Pond, Forked River, NJ51 0.4 358 North of site, on the access road to Forked RiverSite, Forked River, NJ52 0.3 333 NNW of site, on the access road to Forked RiverSite, Forked River, NJ53 0.3 309 NW of site, at sewage lift station on the accessroad to the Forked River Site, Forked River, NJ54 0.3 288 WNW of site, on the access road to Forked RiverSite, Forked River, NJ55 0.3 263 West of site, on Southern Area Stores securityfence, west of OCGS Switchyard, Forked River,NJ56 0.3 249 WSW of site, on utility pole east of Southern AreaStores, west of the OCGS Switchyard, ForkedRiver, NJ57 0.2 206 SSW of site, on Southern Area Stores accessroad, Forked River, NJ58 0.2 188 South of site, on Southern Area Stores accessroad, Forked River, NJ59 0.3 166 SSE of site, on Southern Area Stores accessroad, Waretown, NJ61 0.3 104 ESE of site, on Route 9 south of OCGS MainEntrance, Forked River, NJ62 0.2 83 East of site, on Route 9 at access road to OCGSMain Gate, Forked River, NJ63 0.2 70 ENE of site, on Route 9, between main gate andOCGS North Gate access road, Forked River, NJ64 0.3 42 NE of site, on Route 9 North at entrance toFinninger Farm, Forked River, NJ65 0.4 19 NNE of site, on Route 9 at Intake Canal Bridge,Forked River, NJ66 0.4 133 SE of site, east of Route 9 and south of theOCGS Discharge Canal, inside fence, Waretown,NJ112 0.2 178 S of site, along Southern access road, LaceyTownship, NJ122014 CY-OC-170-301Revision 6Page 131 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)1. Direct Radiation (Continued)DOS -Inner Ring at or near site boundaryCode113T1DOS45689(miles)0.30.4(dearees)90219DescriptionE of site, along Rt. 9 North, Lacey Township, NJSW of site, at OCGS Fire Pond, Lacey Township,NJ224647486873747578798284-Outer Ring at 6 -8 km4.6 213 SSW of Site, Garden State Parkway and Route554, Barnegat, NJ4.2 353 North of Site, Garden State Parkway Rest Area,Forked River, NJ2.1 13 NNE of site, Lane Place, behind St. Pius Church,Forked River, NJ2.3 177 South of site, Route 9 at the WaretownSubstation, Waretown, NJ2.0 230 SW of site, where Route 532 and the GardenState Parkway meet, Waretown, NJ1.6 145 SE of site, on Long John Silver Way, SkippersCove, Waretown, NJ5.6 323 NW of Site, on Lacey Road adjacent to UtilityPole BT 259 654.6 26 NNE of Site, Route 9 and Harbor Inn Road,Berkeley Township, NJ4.5 189 South of Site, Intersection of Brook and SchoolStreets, Barnegat, NJ1.3 266 West of site, on Garden State Parkway North atmile marker 71.7, Lacey Township, NJ1.8 108 ESE of site, on Bay Parkway, Sands PointHarbor, Waretown, NJ1.8 88 East of site, Orlando Drive and Penguin Court,Forked River, NJ2.0 71 ENE of site, Beach Blvd. and Maui Drive, ForkedRiver, NJ1.8 2 North of site, 1514 Arient Road, Forked River, NJ2.9 160 SSE of site, Hightide Drive and Bonita Drive,Waretown, NJ4.4 36 NE of site, Bay Way and Clairmore Avenue,Lanoka Harbor, NJ4.4 332 NNW of site, on Lacey Road, 1.3 miles west ofthe Garden State Parkway on siren pole, LaceyTownship, NJ122014 CY-OC-1 70-301Revision 6Page 132 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)1. Direct Radiation (continued)DOS -Outer Ring at 6 -8 km (continued)Code (miles) (degrees) Description85 3.9 250 WSW of site, on Route 532, just east of WellsMills Park, Waretown, NJ86 5.0 224 SW of site, on Route 554, 1 mile west of theGarden State Parkway, Barnegat, NJ98 1.6 318 NW of site, on Garden State Parkway at milemarker 73.0, Lacey Township, NJ99 1.5 310 NW of site, on Garden State Parkway at milemarker 72.8, Lacey Township, NJ100 1.4 43 NE of site, Yacht Basin Plaza South off LakdesideDr., Lacey Township, NJ101 1.7 49 NE of site, end of Lacey Rd., East, LaceyTownship, NJ102 1.6 344 NNW of site, end of Sheffield Dr., Barnegat Pines,Lacey Township, NJ103 2.4 337 NNW of site, Llewellyn Parkway, Barnegat Pines,Lacey Township, NJ104 1.8 221 SW of site, Rt. 532 West, before Garden StateParkway, Ocean Township, NJ105 2.8 222 SW of site, Garden State Parkway North, besidemile marker 69.6, Ocean Township, NJ106 1.2 288 NW of site, Garden State Parkway North, besidemile marker 72.2 Lacey Township, NJ107 1.3 301 NW of Site, Garden State Parkway North, besidemile marker 72.5, Lacey Township, NJ109 1.2 141 SE of site, Lighthouse Dr., Waretown, OceanTownship, NJ110 1.5 127 SE of site, Tiller Drive and Admiral Way,Waretown, Ocean Township, NJDOS -Special Interest11 8.2 152 SSE of site, 80th and Anchor Streets, HarveyCedars, NJ71 1.6 164 SSE of site, on Route 532 at the WaretownMunicipal Building, Waretown, NJ72 1.9 25 NNE of site, on Lacey Road at Knights ofColumbus Hall, Forked River, NJ122014 CY-OC-1 70-301Revision 6Page 133 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)1. Direct Radiation (continued)DOS -Special Interest (continued)Code (miles) (dearees) Description81 3.5 201 SSW of site, on Rose Hill Road at intersectionwith Barnegat Boulevard, Barnegat, NJ88 6.6 125 SE of site, eastern end of 3rd Street, BarnegatLight, NJ89 6.1 108 ESE of site, Job Francis residence, Island BeachState Park90 6.3 75 ENE of site, parking lot A-5, Island Beach StatePark92 9.0 46 NE of site, at Guard Shack/Toll Booth, IslandBeach State Park3 6.0 97 East of site, near old Coast Guard Station, IslandBeach State Park Special Interest AreaDOS -BackgroundC 24.7 313 NW of site, JCP&L office in rear parking lot,Cookstown, NJ14 20.8 2 North of site, Larrabee Substation on RandolphRoad, Lakewood, NJ2. Airborne -Radioiodines and ParticulatesAPT, AIO -At or near site boundary in highest DIQ Sectors20 0.7 95 East of site, on Finninger Farm on south side ofaccess road, Forked River, NJ66 0.4 133 SE of site, east of Route 9 and south of theOCGS Discharge Canal, inside fence, Waretown,NJ111 0.3 64 ENE of site, Finninger Farm property alongaccess road, Lacey Township, NJAPT, AIO -Special Interest71 1.6 164 SSE of site, on Route 532 at the WaretownMunicipal Building, Waretown, NJ72 1.9 25 NNE of site, on Lacey Road at Knights ofColumbus Hall, Forked River, NJ73 1.8 108 ESE of site, on Bay Parkway, Sands PointHarbor, Waretown, NJAPT, AIO -BackgoundC 24.7 313 NW of site, JCP&L office in rear parking lot,Cookstown, NJ122014 CY-OC-1 70-301Revision 6Page 134 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)2. Airborne -Radioiodines and Particulates (continued)APT, AIO -Backgound(continued)Code (miles) (dearees) Description3 6.0 97 East of site, near old Coast Guard Station, IslandBeach State Park Special Interest Area3. WaterborneSWA -Surface2324333.62.10.4SWA -Backgound94 20.0GW -GroundW-3C 0.4MW-24-3A 0.8DW -Drinking1s 0.164 ENE of site, Barnegat Bay off Stouts Creek,approximately 400 yards SE of "Flashing Light 1"101 East of site, Barnegat Bay, approximately 250yards SE of "Flashing Light 3"123 ESE of site, east of Route 9 Bridge in OCGSDischarge Canal198 SSW of site, in Great Bay/Little Egg Harbor112 ESE of site on Finninger Farm adjacent to Station35, Lacey Township, NJ97 E of site on Finninger Farm on South side ofaccess road, Lacey Township, NJ209 On-site southern domestic well at OCGS, ForkedRiver, NJ349 On-site northern domestic well at OCGS, ForkedRiver, NJ197 SSW of Site, on Route 532, at Ocean TownshipMUA Pumping Station, Waretown, NJ18 NNE of Site, off Boox Road at Lacey MUAPumping Station, Forked River, NJ353 N of Site, Trenton Ave. off Lacey Road LaceyTwp., MUA Pump Station, Forked River, NJ64 ENE of site, Barnegat Bay off Stouts Creek,approximately 400 yards SE of "Flashing Light 1"101 East of site, Barnegat Bay, approximately 250yards SE of "Flashing Light 3"123 ESE of site, east of Route 9 Bridge in OCGSDischarge Canal1N380.21.6DW -Backgound37 2.2393.5AQS -Sediment23 3.624332.10.4122014 CY-OC-170-301Revision 6Page 135 of 140TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)3. Waterborne (continued)AQS -BackgoundCode (miles) (dearees) Description94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor4. IngestionFISH -Fish930.1FISH -Backgound94 20.0CLAM -Clams23 3.6242.1CLAM -Backgound94 20.0CRAB -Crabs242 WSW of site, OCGS Discharge Canal betweenPump Discharges and Route 9, Forked River, NJ198 SSW of site, in Great Bay/Little Egg Harbor64 ENE of site, Bamegat Bay off Stouts Creek,approximately 400 yards SE of "Flashing Light 1"101 East of site, Barnegat Bay, approximately 250yards SE of "Flashing Light 3"198 SSW of site, in Great Bay/Little Egg Harbor123 ESE of site, east of Route 9 Bridge in OCGSDischarge Canal242 WSW of site, OCGS Discharge Canal betweenPump Discharges and Route 9, Forked River, NJ111 ESE of site, east of Route 9 and north of theOCGS Discharge Canal, Forked River, NJ133 SE of site, east of Route 9 and south of theOCGS Discharge Canal, inside fence, Waretown,NJ96 East of Site, on Finninger Farm319 NW of site, at "U-Pick" Farm, New Egypt, NJ33930.40.1VEG -Vegetation35 0.4661150.40.3VEG -Backgound36 23.1122014 CY-OC-1 70-301Revision 6Page 136 of 140SAMPLE MEDIUM IDENTIFICATION KEYAPT = Air ParticulateAIO = Air IodineVEG = VegetablesSWA = Surface WaterAQS = Aquatic SedimentCLAM = ClamsDW = Drinking WaterDOS = DosimeterFISH = FishCRAB =CrabGW = Ground Water(1) Samples may not be collected from some locations listed in this table, as longas the minimum number of samples listed in Table 3.12.1-1 is collected.122014 FIGURE E-1CY-OC-1 70-301Revision 6Page 137 of 140ENEOyster Creek Generating StationREMP Sample Locationswithin a I Mle Radius03 11.15 O 0.3 l" bDWe. 094t12122014 CY-OC-1 70-301Revision 6Page 138 of 140Oyster Creek Generating StationREMP Sample Locationswithin a 1 to 5 Mile RadiusDate: 08/27/12122014 CY-OC-1 70-301Revision 6Page 139 of 140FIGURE E-3.7fc) 2011 S,,bo()Oyster Creek Generating StationREMP Sample Locationsover a 5 Mile Radius5.5 2.75 0 &5 Ws5Date: 08127/12122014 CY-OC-1 70-301Revision 6Page 140 of 140FIGURE E-4AREA PLOT PLAN OF SITESITE MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVEGASEOUS AND LIQUID EFFLUENTSSite Boundary DistancesSectorSSSWSWWSWWWNWNWNNWDistance in metersSector348291229260239284364474NNNENEENEEESESESSEDistance in meters584621373338360491544395122014 Exeo eeRW-AA-100S Exeton Generation, Revision 10Page 1 of 12Level 3 -Information UsePROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES1. PURPOSE1.1. The purpose of the Process Control Program (PCP) is to:1.1.1. Establish the process and boundary conditions for the preparation of specificprocedures for processing, sampling, analysis, packaging, storage, and shipment ofsolid radwaste in accordance with local, state, and federal requirements. (CM-1)1.1.2. Establish parameters which will provide reasonable assurance that all Low LevelRadioactive Wastes (LLRW), processed by the in-plant waste process systemson-site OR by on-site vendor supplied waste processing systems, meet theacceptance criteria to a Licensed Burial Facility, as required by 10CFR Part 20,1 OCFR Part 61, 1 OCFR Part 71, 49CFR Parts 171-172, "Technical Position onWaste Form (Revision 1)" (1/91], "Low-Level Waste Licensing Branch TechnicalPosition on Radioactive Waste Classification" [5/83], and the Station TechnicalSpecifications, as applicable.1.1.3. Provide reasonable assurance that waste placed in "on-site storage" meets therequirements as addressed within the Safety Analysis Reports for the low levelradwaste storage facilities for dry and/or processed wet waste.2. TERMS AND DEFINITIONS2.1. Process Control Program (PCP): The program which contains the currentformulas, sampling, analysis, tests, and determinations to be made to ensure thatprocessing and packaging of solid radioactive waste based on demonstratedprocessing of actual or simulated wet solid wastes will be accomplished in such away as to assure the waste meets the stabilization criteria specified in 1 OCFR Parts20, 61 and 71, state regulations, and burial site requirements.2.2. Solidification: Liquid waste processed to either an unstable or stable form per10 CFR61 requirements. Waste solidified does not have to meet the 300-year freestanding monolith criteria. Approved formulas, samples and tests do not have tomeet NRC approval for wastes solidified in a container meeting stability criteria (e.g.High Integrity Container).2.3. Stabilization: Liquid waste processed to a "stable state" per 10CFR61Requirements. Established formulas, samples, and tests shall be approved by theNRC in order to meet solidification "stabilization" criteria. This processing method iscurrently not available, because the NRC recognizes that waste packed in a HighIntegrity Container meets the 300-year stabilization criteria. In the event that thisprocessing method becomes an acceptable method, then the NRC shall approve thestabilization formulas, samples, tests, etc.
RW-AA-100Revision 10Page 2 of 122.4. Solidification Media: An approved media (e.g. Barnwell -vinyl ester styrene,cement, bitumen) when waste containing nuclides with greater than 5-year half livesis solidified in a container with activity greater than 1 micro curie/cc. Waste solidifiedin a HIC is approved by the commission meeting the 1 OCFR61 stabilization criteria,including 1% free standing liquids by volume when the waste is packaged to a"stable" form and < 0.5% when waste is packaged to an "unstable" form. Theformulas, sampling, analysis, and test do not require NRC approval, because theHIC meets the stability criteria.2.4.1. Solidification to an unstable or stable state is performed by vendors, whenapplicable. Liquid waste solidified to meet stabilization criteria (1OCFR61 and 01-91Branch Technical Requirements) shall have documentation available thatdemonstrates that the process is approved by the NRC or disposal facility.2.5. Dewatering: The process of removing fluids from liquid waste streams to produce awaste form that meets the requirements of 1OCFR Part 61 and applicable burial sitecriteria, <0.5% by volume when the waste is packaged to an "unstable" state, or_<1% by volume when the waste is packaged to a "stable" form.2.6. High Integrity Container (HIC): A disposable container that is approved to theRequirements of 10CFR61. The use of HIC's is an alternative to solidification orencapsulation in a steel container to meet burial stability. HIC's are used to packagedewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), ordry active waste.2.7. Liquid Waste Processing Systems: In-plant or vendor supplied processingsystems consisting of equipment utilized for evaporation, filtration, demineralization,dewatering, compression dewatering, solidification, or reverse osmosis (RO) for thetreatment of liquid wastes (such as Floor Drains, Chemical Drains and EquipmentDrain inputs).2.8. Incineration, RVR. and/or Glass Vitrification of Liquid or Solid: Dry or wetwaste processed via incineration and/or thermal processing where the volume isreduced by thermal means meets 1 OCFR61 requirements.2.9. Compaction: When dry wastes such as paper, wood, plastic, cardboard,incinerator ash, and etc. are volume reduced through the use of a compactor.I RW-AA-100Revision 10Page 3 of 122.10. Waste Streams: Consist of but are not limited to-Filter media (powdered, bead resin and fiber),-Filter cartridges,-Pre-coat body feed material,-Contaminated charcoal,-Fuel pool activated hardware,-Oil Dry absorbent material added to a container to absorb liquids-Fuel Pool Crud-Sump and tank sludges,-High activity filter cartridges,-Concentrated liquids,-Contaminated waste oil,-Dried sewage or wastewater plant waste,-Dry Active Waste (DAW): Waste such as filters, air filters, low activitycartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, andmetals, etc, which have become contaminated as a consequence of normaloperating, housekeeping and maintenance activities.-Other radioactive waste generated from cleanup of inadvertent contamination.2.11. Concentration Averaging: Concentration averaging is either: a) the mathematicalaveraging of waste concentrations, based on the size, geometry, type of radioactiveemission, and observed dose rates, or b) the combining of radioactive componentsin a single container and how their radioactivity may be averaged over the volume ofthe container. Concentration averaging is subject to constraints identified in theNRC's Branch Technical Position on Concentration Averaging and Encapsulationand may also be constrained by Agreement States or Disposal Facilities.2.12. Encapsulation: Encapsulation is the surrounding of a radioactive source orcomponent with a nonradioactive material. Encapsulation involves a radioactivecore surrounded by a non-radioactive matrix.2.13. Blending: The intentional mixing of different, but miscible waste streams (such asresins, filter media, etc.) from different batches or systems for the purpose ofoperational efficiency or ALARA. Blending applies to LLRW streams only. Theaddition of non-radioactive materials or fillers is not considered blending.3. RESPONSIBILITIES3.1. Implementation of this Process Control Program (PCP) is described in procedures ateach station and is the responsibility of the each site to implement.
RW-AA-100Revision 10Page 4 of 124. MAIN BODY4.1. Process Control Program Requirements4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be madeprovided that the change is reported as part of the annual radioactive effluentrelease report, Regulatory Guide 1.21, and is approved by the Plant OperationsReview Committee (PORC).4.1.2. Changes become effective upon acceptance per station requirements.4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquidradwaste is solidified to a stable/unstable state.4.1.4. When processing liquid radwaste to meet solidification stability using a vendorsupplied solidification system:1. If the vendor has its own Quality Assurance (QA) Program, then the vendorshall ADHERE to its own QA Program and shall have SUBMITTED itsprocess system topical report to the NRC or agreement state.2. If the vendor does not HAVE its own Quality Assurance Program, then thevendor shall ADHERE to an approved Quality Assurance Topical Reportstandard belonging to the Station or to another approved vendor.4.1.5. The vendor processing system(s) is/are controlled per the following:1. A commercial vendor supplied processing system(s) may be USED for theprocessing of LLRW streams.2. Vendors that process liquid LLRW at the sites shall MEET applicable QualityAssurance Topical Report and Augmented Quality Requirements.4.1,6. Vendor processing system(s) operated at the site shall be OPERATED andCONTROLLED in accordance with vendor approved procedures or stationprocedures based upon vendor approved documents.4.1,7. All waste streams processed for burial or long term on-site storage shall MEET thewaste classification and characteristics specified in 1OCFR Part 61.55, Part 61.56,the 5-83 Branch Technical Position for waste classification, and the applicable burialsite acceptance criteria (for any burial site operating at the time the waste wasprocessed).4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, providedformal NRC approval has been RECEIVED for the transfer of waste.
RW-AA-100Revision 10Page 5 of 124.2. General Waste Processing RequirementsNOTE: On-site resin processing involves tank mixing and settling,transferring to the station or vendor processing system via resinwater slurry or vacuuming into approved waste containers, and,when applicable, dewatering for burial.4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as,SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut DownCooling). These resins are then PROCESSED via the station or vendor processingsystem.4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitablecontainers for processing treatment. Water from these tanks may be SENT througha filter, demineralizer, concentrator or vendor supplied processing systems.4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodicallyDISCHARGED to the station or vendor processing system for onsite wastetreatment or PACKAGED in containers for shipment to offsite vendor for volumereduction processing.4.2.4. Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT toeither the site waste processing systems or vendor waste processing systems forfurther filtration, demineralization for plant re-use, or discharge.4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utilitysite personnel or by on-site vendors or will be PACKAGED and SHIPPED to anoff-site vendor low-level radwaste processing facility.4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:1. DAW will be COLLECTED and SURVEYED and may be SORTED forcompactable and non-compactable wastes.2. DAW may be packaged in containers to facilitate on-site pre-compactionand/or off-site vendor contract requirements.3. DAW items may be SURVEYED for release onsite or offsite when applicable.4. Contaminated filter cartridges will be PLACED into a HIC or will beENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsitewaste processor in drums, boxes or steel liners per the vendor site criteria forprocessing and disposal.
RW-AA-100Revision 10Page 6 of 124.2.7. Filtering devices using pre-coat media may be USED for the removal of suspendedsolids from liquid waste streams. The pre-coat material or cartridges from thesedevices may be routinely REMOVED from the filter vessel and discharged to a FilterSludge Tank or Liner/HIC. Periodically, the filter sludge may be DISCHARGED tothe vendor processing system for waste treatment onsite or PACKAGED incontainers for shipment to offsite vendor for volume reduction processing.4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodicallyusing remote handling equipment and may then be PUT into a container forshipment or storage in the pool or loading the processed activated hardware into theDry Cask storage system.4.2.9. High Integrity Containers (HIC):1. For disposal at Barnwell, vendors supplying HIC's to the station shallPROVIDE a copy of the HIC Certificate of Compliance, which details specificlimitations on use of the HIC.2. For disposal at Clive or WCS, vendors supplying HIC's to the station shallPROVIDE a copy of the HIC Certificate of Conformance, which detailsspecific limitations on use of the HIC.3. Vendors supplying HIC's to the station shall PROVIDE a handling procedurewhich establishes guidelines for the utilization of the HIC. These guidelinesserve to protect the integrity of the HIC and ensure the HIC is handled inaccordance with the requirements of the Certificate of Compliance orCertificate of Conformance.4.2.10. Lubricants and oils contaminated as a consequence of normal operating andmaintenance activities may be PROCESSED on-site (by incineration, for oilsmeeting 10CFR20.2004 and applicable state requirements, or by an approvedvendor process) or SHIPPED offsite (for incineration or other acceptable processingmethod).4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areasmay be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities,Braidwood and Byron.4.2.12. Certain waste, including flowable solids from holding pond, oily waste separator,cooling tower basin and emergency spray pond, may be disposed of onsite underthe provisions of a 10CFR20.2002 permit. Specific requirements associated with thedisposal shall be incorporated into station implementing procedures. (CM-2)
RW-AA-100Revision 10Page 7 of 124.2.13. Concentration averaging may be PERFORMED to combine LLRW having differentconcentrations of radionuclides to form a homogeneous mixture in accordance withthe guidance in the NRC's Branch Technical Position on Concentration Averagingand Encapsulation-1995:-For homogeneous waste types such as resins and filter media, theconcentration of the mixture for classification purposes may be based oneither the highest radionuclide concentration in any of the individual wastetypes contributing to the mixture or the volumetric or weight-averaged nuclideconcentrations in the mixture provided that the concentrations of theindividual waste type contributors to the mixture are within a factor of 10 ofthe average concentration of the resulting mixture. (NOTE: a designedcollection of homogeneous waste types (from different sources within afacility) is not considered 'mixing' and the concentration for classificationpurposes may be the average concentration of the combination).-For non-homogeneous waste types such as activated metals, cartridge filtersor components incorporating radioactivity in their design, the concentrationshould be determined from the total weight or displaced volume (excludingmajor void spaces) of the component. Mixtures of components in a disposalcontainer is permissible. Concentration averaging of a mixture of componentsof similar types can be performed in accordance with the NRC's BranchTechnical Position on Concentration Averaging and Encapsulation and anyState or Disposal Site specific requirements.4.2.14. Blending may be PERFORMED for routine LLRW such as resins and filter media inaccordance with the guidance in the NRC's Branch Technical Position onConcentration Averaging and Encapsulation as further clarified in SECY 2010-0043.The concentration of the mixture may be determined based on the total activity of allcomponents in the mixture divided by the total volume or mass of the mixture.Reasonable effort should be made to mix blended LLRW so that activity is evenlydistributed.4.2.15. Encapsulation may be PERFORMED for routine wastes such as filters, filtercartridges, or sealed sources centered in an encapsulated mass, in accordance withthe guidance in the NRC's Branch Technical Position on Concentration Averagingand Encapsulation. Classification may be based on the overall volume of the finalsolidified mass provided that;-The minimum solidified volume or mass should be reasonably difficult tomove by hand.-The maximum solidified volume or mass used for determiningconcentration for any single discrete source should be no more than 0.2m3 or 500Kg (typically 55-gallon drum).-The maximum amount of gamma-emitting radioactivity or radioactivematerial is <0.02 mrem/hr on the surface of the encapsulation over a 500-year decay period.
RW-AA-100Revision 10Page 8 of 12The maximum amount of any radionuclide in a single encapsulation, whenaveraged over the waste and encapsulating media, does not exceed themaximum concentration limits for Class C waste.Written procedures should be established to ensure that the radiationsource(s) is reasonably centered (or distributed) within the encapsulatingmedia.All other disposal facility requirements for encapsulated material are met.4.3. Burial Site Requirements4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of49CFR171-172, 1OCFR61, 1OCFR71, and the acceptance criteria for the applicableburial site.4.4. Shippinq and Inspection Requirements4.4.1. All shipping/storage containers shall be INSPECTED, as required by stationprocedures, for compliance with applicable requirements (Department ofTransportation (DOT), Nuclear Regulatory Commission (NRC), station, on-sitestorage, and/or burial site requirements) prior to use.4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification qualityand/or dewatering requirements per the burial site, offsite vendor acceptance, orstation acceptance criteria, as applicable.4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that theapplicable processor's waste acceptance criteria are being met.4.4.4. Shipments sent for off site storage shall MEET the storage site's waste acceptancecriteria.4.5. Inspection and Corrective Action4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor,or site requirements shall be IDENTIFIED and TRACKED through the CorrectiveAction Program.4.5.2. Administrative controls for preventing unsatisfactory waste forms from beingreleased for shipment are described in applicable station procedures. If theprovisions of the Process Control Program are not satisfied, then SUSPENDshipments of defectively packaged radioactive waste from the site. (CM-1)4.5.3. If freestanding water or solidification not meeting program requirements is observed,then samples of the particular series of batches shall be TAKEN to determine thecause. Additional samples shall be TAKEN, as warranted, to ensure that nofreestanding water is present and solidification requirements are maintained.
RW-AA-100Revision 10Page 9 of 124.6. Procedure and Process Reviews4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other thaneditorial/minor changes) shall be REVIEWED and APPROVED in accordance withthe station procedures, plant-specific Technical Specifications (Tech Spec),Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),as applicable, for the respective station and LS-AA-106. Changes to the LicenseesControlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of10CFR 50.59.4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required inthe Annual Radiological Effluent Release Report (ARERR). The RadwasteSpecialist shall ensure correct information is SUBMITTED to the ODCM programowner prior to submittal of the ARERR.4.6.3. Procedures shall be IMPLEMENTED as follows:-Station processes or other vendor waste processing/operating proceduresshall be technically reviewed and approved per RM-AA-102-1006.-Procedures related to waste manifests, shipment inspections, and containeractivity determinations are CONTROLLED by Radiation Protection StandardProcedures (RP-AA-600 Series).-Site waste processing IS CONTROLLED by site operating procedures.-Liquid processed by vendor equipment shall be PERFORMED in accordancewith vendor procedures.-The dewatering procedures implemented by Vendor for the purpose ofcompliance to the Process Control Program SHALL BE REVIEWED andAPPROVED in accordance with the plant specific TRM or ORM (eitherCurrent Technical Specifications (CTS) or Improved Technical Specifications(ITS), as applicable for the respective stations).4.7. Waste Types, Point of Generation, and Processing MethodMethods of processing and individual vendors may CHANGE due to changingfinancial and regulatory options. The table below is a representative sample. It isnot intended be all encompassing.
RW-AA-100Revision 10Page 10 of 12AVAILABLE WASTEWASTE STREAM POINTS OF GENERATION POEING MEPROCESSING METHODSBead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to anReactor Water Cleanup, Blowdown, unstable/stable stateEquipment Drain, Chemical and Thermal ProcessingVolume Control Systems, Floor Drain,Maximum Recycle, Blowdown, Boric Free Release to a Land FillAcid Recycling System, VendorSupplied Processing Systems, andPortable Demin SystemPowdered Resin Systems -(Condensate System, Floor Dewatering, solidification to anDrain/Equipment Drain filtration, Fuel unstable/stable statePool) Thermal ProcessingConcentrated Waste Waste generated from Site Solidification to an unstable/stableEvaporators resulting typically from the stateFloor Drain and Equipment Drain Thermal ProcessingSystemsSludge Sedimentation resulting from various Dewatering, solidification to ansumps, condensers, tanks, cooling unstable/stable statetower, emergency spray pond, holding Thermal Processingpond, and oily waste separatorsEvaporation on-site or at an offsiteprocessorOn-site disposal per 1OCFR20.2002permitFilter cartridges Systems -Floor/Equipment Drains, Dewatering, solidification to anFuel Pool; cartridge filters are typically unstable/stable stategenerated from clean up activities Processed by a vendor for volumewithin the fuel pool, torus, etc reductionDry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Releasemetal, and etc. resulting from daily Compaction/Super-compactionplant activitiesThermal Processing by Incinerationor glass vitrificationSorting for Free ReleaseMetal melting to an ingotContaminated Oil Oil contaminated with radioactive Solidification unstable statematerials from any in-plant system. Thermal Processing by IncinerationFree Release for recyclingDrying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burialTreatment FacilitiesMetals See DAW See DAWIrradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packagingefficiencies RW-AA-100Revision 10Page 11 of 125. DOCUMENTATION5.1. Records of reviews performed shall be retained for the duration of the unit operatinglicense. This documentation shall contain:1. Sufficient information to support the change together with the appropriateanalyses or evaluations justifying the change, and2. A determination which documents that the change will maintain the overallconformance of waste products to Federal (1 OCFR61 and the BranchTechnical Position), State, or other applicable requirements, includingapplicable burial site criteria.6. REFERENCES6.1. Technical Specifications:6.1.1. The details contained in Current Tech Specs (CTS) or Improved TechnicalSpecifications (ITS), as applicable, in regard to the Process Control Program (PCP),are to be relocated to the Licensee Controlled Documents. Some facilities haveelected to relocate these details into the Operational Requirements Manual (ORM).Relocation of the description of the PCP from the CTS or ITS does not affect thesafe operation of the facility. Therefore, the relocation details are not required to bein the CTS or the ITS to provide adequate protection of the public health and safety.6.2. Writers'
References:
6.2.1. Code of Federal Regulations: 10 CFR Part 20, Part 61, Part 71, 49 CFRParts 171-1726.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive WasteClassification, May 19836.2.3. Technical Position on Waste Form (Revision 1), January 19916.2.4. USNRC Branch Technical Position on Concentration Averaging and Encapsulation,January 19956.2.5. Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in SolidWastes and Releases of Radioactive materials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants6.2.6. I.E. Circular 80.18, 1OCFR 50.59 Safety Evaluation for Changes to RadioactiveWaste Treatment Systems6.2.7. Amendment No. 202 to Facility Operating License No. NPF-1 1 and Amendment No.189 to Facility Operating License (FOL) No. NPF-18 for the LaSalle County Station(LSCS), Units 1 and 2 RW-AA-100Revision 10Page 12 of 126.2.8. NRC Branch Technical Position on Blending of Low-Level Radioactive Waste,SECY-10-00436.3. Users'
References:
6.3.1. Quality Assurance Program (QATR)6.3.2. LS-AA-106, Plant Operations Review Committee6.3.3. RM-AA-102-1006, Processing Vendor Documents6.3.4. RP-AA-600 Series, Radioactive Material/Waste Shipments6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report6.4. Station Commitments:6.4.1. Peach BottomCM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmittingTSCR 93-16 (Improved Technical Specifications). (Step 1.1.1,4.5.2)6.4.2. LimerickCM-2, T03896, 1OCFR20.2002 permit granted to Limerick via letter datedJuly 10, 1996. (Step 4.2.12)7. ATTACHMENTS -None