Text

Nine Mile Point, Units 1 and 2 - 2014 Radioactive Effluent Release Report
	ML15133A321
Person / Time
Site:	Nine Mile Point
Issue date:	05/01/2015
From:	Orphanos P M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NMP1L 3022
	Download: ML15133A321 (67)
	v • d • e

I'bExe!on Generation.10 CFR 50.36aTechnical SpecificationsNMP1L 3022May 1, 2015U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Nine Mile Point Nuclear Station, Units 1 and 2Renewed Facility Operating License Nos. DPR-63 and NPF-69NRC Docket Nos. 50-220 and 50-410

Subject:

2014 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2In accordance with 10 CFR 50.36a, and the Nine Mile Point Unit 1 (NMP1) and Nine Mile PointUnit 2 (NMP2) Technical Specifications, enclosed are the Radioactive Effluent Release Reportsfor NMP1 and NMP2 for the period of January through December 2014.The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21,Revision 1. During the reporting period, NMP1 and NMP2 did not exceed any 10 CFR 20, 10CFR 50, Technical Specification, or ODCM limits for gaseous or liquid effluents.Should you have questions regarding the information in this submittal, please contact ShaneHowe, Site Chemistry Environmental & Radwaste Manager, at (315) 349-5210.Sincerely,Peter M. OrphanosVice President, Nine Mile Point Nuclear StationExelon Generation Company, LLCPMO/BTV

Enclosures:

(1)Nine Mile Point Nuclear Station, Unit 1Radioactive Effluent Release Report, January -December 2014(2) Nine Mile Point Nuclear Station, Unit 2Radioactive Effluent Release Report, January -December 2014 Document Control DeskMay 1, 2015Page 2Cc: NRC Regional Administrator, Region 1NRC Project ManagerNRC Resident InspectorC. Graves, NRC Enclosure INine Mile Point Nuclear Station, Unit 1Radioactive Effluent Release Report, January -December 2014 x , .NINE MILE POINT NUCLEAR STATION -UNIT 1RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014SUPPLEMENTAL INFORM TIONFacility: Nine Mile Point Unit 1 Licensee: Nine Mile Point Nuclear Station, LLC1. TECHNICAL SPECIFICATION LIMITS/ODCM LimitsA. FISSION AND ACTIVATION GASES1. The dose rate limit of noble gases released in gaseous effluents from the site to areas atand beyond the site boundary shall be less than or equal to 500 mrem/year to the totalbody and less than or equal to 3000 mrem/year to the skin.2. The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit 1to areas at and beyond the site boundary shall be limited during any calendar quarter toless than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10mrad for beta radiation, and during any calendar year to less than or equal to 10milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.B. IODINES1. The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulateform with half-lives greater than eight days, released in gaseous effluents from the site toareas at and beyond the site boundary shall be less than or equal to 1500 mrem/year toany organ.2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and allradionuclides in particulate form with half-lives greater than eight days in gaseouseffluents released from Nine Mile Point Unit 1 to areas at and beyond the site boundaryshall be limited during any calendar quarter to less than or equal to 7.5 mrem to anyorgan, and during any calendar year to less than or equal to 15 mrem to any organ.C. TRITIUM AND PARTICULATES, HALF LIVES> 8 DAYS1. The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulateform with half-lives greater than eight days, released in gaseous effluents from the site toareas at and beyond the site boundary shall be less than or equal to 1500 mrem/year toany organ.2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and allradionuclides in particulate form with half-lives greater than eight days in gaseouseffluents released from Nine Mile Point Unit I to areas at and beyond the site boundaryshall be limited during any calendar quarter to less than or equal to 7.5 mrem to anyorgan, and during any calendar year to less than or equal to 15 mrem to any organ.Nine Mile Point Nuclear Station, LLCMay 1, 2015

~ImD. LIQUID EFFLUENTS1. The concentration of radioactive material released in.liquid effluents to unrestricted areasshall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B,Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. Fordissolved or entrained noble gases, the concentration shall be limited to 2E-04microcuries/ml total activity.2. The dose or dose commitment to a member of the public from radioactive materials inliquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limitedduring any calendar quarter to less than or equal to 1.5 mrem to the total body and to lessthan or equal to 5 mrem to any organ, and during any calendar year to less than or equalto 3 mrem to the total body and to less than or equal to 10 mrem to any organ.2. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITYDescribed below are the methods used to measure or approximate the total radioactivity and radionuclidecomposition in effluents.A. FISSION AND ACTIVATION GASESNoble gas effluent activity is determined by on-line gross activity monitoring (calibrated againstgamma isotopic analysis of a 4.OL Marinelli grab sample) of an isokinetic stack sample stream.B. IODINESIodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) ofcharcoal cartridges sampled from an isokinetic stack sample stream.C. PARTICULATESActivity released from the main stack is determined by gamma spectroscopic analysis (at leastweekly) of particulate filters sampled from an isokinetic sample stream and composite analysis ofthe filters for non-gamma emitters.D. TRITIUMTritium effluent activity is measured by liquid scintillation or gas proportional counting ofmonthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity ismeasured during purge and weekly when fuel is offloaded until stable tritium release rates aredemonstrated.E. EMERGENCY CONDENSER VENT EFFLUENTSThe effluent curie quantities are estimated based on the isotopic distribution in the CondensateStorage Tank water and the Emergency Condenser shell water. Actual isotopic concentrations arefound via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated byapplying scaling factors to release rates of gamma emitters and actual release rates are determinedfrom post off site analysis results. The activity of fission and activation gases released due to tubeleaks is based on reactor steam leak rates using offgas isotopic analyses.Nine Mile Point Nuclear Station, LLCMay 1, 2015 F. LIQUID EFFLUENTSIsotopic contents of liquid effluents are determined by isotopic analysis of a representativesample of each batch and composite analysis of non-gamma emitters. Tritium activity isestimated on the most recent analysis of the Condensate Storage Tank water. Initial release ratesof Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to release rates of gammaemitters and actual release rates are determined from post off site analysis results.G. SOLID EFFLUENTSIsotopic contents of waste shipments are determined by gamma spectroscopy analysis of arepresentative sample of each batch. Scaling factors established from primary composite sampleanalyses conducted off-site are applied, where appropriate, to find estimated concentration ofnon-gamma emitters. For low activity trash shipments, curie content is estimated by dose ratemeasurement and application of appropriate scaling factors.H. C-14The production of C-14 and the effluent dose consequences are estimates based on EPRImethodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power PlantGaseous Effluents, December 2010 and NUREG-00 16, Calculation of Releases of RadioactiveMaterials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code).3. METEOROLOGICAL DATAAn annual summary of hourly meteorological data collected over the previous year. This annualsummary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, winddirection, atmospheric stability, and precipitation (if measured), or in the form of joint frequencydistribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with theRadiological Effluent Release Report, the licensee is exercising the option of retaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request.Nine Mile Point Nuclear Station, LLCMay 1, 2015

....ISupplemental InformationATTACHMENT 1SUMMARY DATAPage 1 of 2Unit 1 X Unit 2 Reporting Period January -December 2014Liquid Effluents:ODCM Required Maximum Effluent Concentration (MEC) = 10 x 1OCFR20, Appendix B, Table 2, Column 2There were no batch discharges of liquid radwaste requiring use of MEC to determine allowable release rate.There were no Emergency Condenser Vent Liquid Discharges in 2014.Average MEC -pCi/ml (Qtr. 1) = NO RELEASES Average MEC -pCi/ml (Qtr. 3) = N LEASESAverage MEC -pCi/mI (Qtr. i) NO RELEASES Average MEC -pCi/mI (Qtr. 4) =N EESSAverage Energy (Fission and Activation gases -MeV):Qrtr. 1: Ey = N/A EP = N/AQrtr.2: Ev = N/A Ep = N/AQrtr. 3: Ey = NIA EP = N/AQrtr. 4: EV = N/A EP. = N/ALiquid: Radwaste EC VentNumber of Batch Releases 0 0Total Time Period for Batch Releases (hrs) 0 0.00Maximum Time Period for a Batch Release (hrs) 0 0.00Average Time Period for a Batch Release (hrs) 0 0.00Minimum Time Period for a Batch Release (hrs) 0 0.00Total volume of water used to dilute 1st 2nd 3rd 4ththe liquid effluent during releaseperiod (L) Radwaste N/A N/A N/A N/ATotal volume of water available to 1 st 2nd 3rd 4thdilute the liquid effluent during reportperiod (L) Radwaste 1.29E+11 1'32E+11 I 1.36E+11 1.30E+11Gaseous(Emergency Condenser Vent):Number of Batch Releases 0Total Time Period for Batch Releases (hrs) 0.00Maximum Time Period for a Batch Release (hrs) 0.00Average Time Period for a Batch Release (hrs) 0.00Minimum Time Period for a Batch Release (hrs) 0.00Gaseous (Primary Containment Purge):Number of Batch Releases 0Total Time Period for Batch Releases (hrs) 0.00Maximum Time Period for a Batch Release (hrs) 0.00Average Time Period for a Batch Release (hrs) 0.00Minimum Time Period for a Batch Release (hrs) 0.00Nine Mile Point Nuclear Station, LLCMay 1, 2015 Supplemental Information ATTACHMENT I Page 2 of 2SUMMARY DATAUnit 1 X Unit 2 Reporting Period January -December 2014Abnormal Releases:A. Liquids:Number of Releases 0ITotal Activity Released I NAB. Gaseous:I.Number of Releases 0ITotal Activity Released N/A CiIn August 2012, tritium was identified in ground water outside Unit 1. Subsequent investigations determined the source of tritium was EmergencyCondenser Vent discharges (during periodic testing, as well as past events). Per the ODCM, and through station procedures, the gaseous and liquideffluent releases to the environment via the Emergency Condenser pathway are analyzed and reported in the monthly effluent releases and reportedannually in the Radioactive Effluent Release Report (RERR).As a result of this discovery, the Unit 1 0DCM was revised (Revision 34) to require composite samples of discharges from the Reactor Building PerimeterDrain be collected and analyzed, and total curies reported in the RERR. Because this activity has been accounted for in previous RERRs, it is to bereported as a separate item, and not included in the liquid releases (Attachment 5).No tritium was detected in the Reactor Building Perimeter Drains during 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1A Gaseous Effluents -Summation of All Releases -Elevated and Ground LevelATTACHMENT 2Page 1 of 1Unit.1 X Unit 2 Reporting Period January -December 2014GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTALERROR %A. Fission & Activation Gases (111. Total Release2. Average Release RateB. lodines (1)1. Total Iodine- 1312. Average Release Rate for PeriodC. Particulates (1)1. Particulates with Half-lives>8 days2. Average Release Rate for Period3. Gross Alpha RadioactivityD. Tritium (1)1. Total Release2. Average Release Rate for PeriodE. Percent of Tech. Spec. LimitsFission and Activation GasesPercent of Quarterly Gamma Air DoseLimit (5 mR)Percent of Quarterly Beta Air Dose Limit(10 mrad)Percent of Annual Gamma Air Dose Limitto Date (10 mR)Percent of Annual Beta Air Dose Limit toDate (20 mrad)Percent of Whole Body Dose Rate Limit(500 mrem/yr)Percent of Skin Dose Rate Limit (3000mrem/yr)Tritium, lodines. and Particulates (withhalf-lives greater than 8 days)Percent of Quartedy Dose Limit (7.5mrem)Percent of Annual Dose Limit to Date (15mrem)Percent of Organ Dose Limit (1500mrem/yrCipCi/secCipCi/secCipCi/secCiCipCi/sec** -- -5.OOE+01** ** ** ** 50E01.60E-05 1.40E-05 8.51E-05 4.81 E-05 3OOE+012.03E-06 1.78E-06 1.01 E-05 6.11 E-061.31 E-04 1.96E-04 2.77E-04 2.40E-04 3.OOE+011.67E-05 2.50E-05 3.31 E-05 3.05E-05** * -**2.50E+014.99E+00 5.50E+00 6.68E+00 9.82E+00 5.00E+016.36E-01 6.99E-01 8.05E-01 1.25E+000.OOE+00 0.00E+00 0.OOE+00 0.00E+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.00E+00 0.OOE+001.53E-02 1.89E-02 4.68E-02 3.57E-027.67E-03 1.71 E-02 4.05E-02 5.84E-023.11E-04 3.80E-04 9.28E-04 7.09E-04(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1B GaseousEffluents -Elevated ReleasesATTACHMENT 3Page 1 of 2.Unit 1 X Unit 2 .Reporting Period January -December 2014GASEOUS EFFLUENTS -ELEVATED RELEASEContinuous Mode (2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-127Xenon-131mXenon-133Xenon-133mXenon-135Xenon-135mXenon-137Xenon-138lodines (1)Iodine-131Iodine-133Iodine-135Particulates (1)Strontium-89Strontium-90Cesium-134Cesium-137Cobalt-60Cobalt-58Manganese-54Barum-140Lanthanum-140Niobium-95Cerium-141Cerium-144Iron-59Cesium-136Chromium-51Zinc-65Iron-55Molybdenum-99Neodymium-147CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCi1.60E-05 i.40E-05 8.51E-05 4.81E-058.39E-04 1.03E-03 1.23E-03 1.56E-03** I ** I ** I **1.05E-05 2.OOE-06 1.51E-05 1.71 E-059.75E-05 1.75E-04 2.15E-04 2.06E-04** 1.88E-05 1.87E-05 1.68E-052*3iE-O5** **2.31 E-05 ...... 2.81E-05 *j4.12E+00 4.65E+00I 5.47E+00 8.99E+00Tritium (1)Ci(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit ofdetection of 1.OOE-04 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates, 1.OOE-12 pCi/ml for required lodines,and 1.OOE-06 pCi/ml for Tritium as required by the ODCM, has been verified.(2) Contributions from purges are included. There were no other batch releases during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1 BATTACHMENT 3Page 2 of 2Unit 1 X Unit 2 Reporting Period January -December 2014GASEOUS EFFLUENTS -ELEVATED RELEASEBatch Mode (2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-127Xenon-131mXenon-133Xenon-133mXenon-135Xenon-135mXenon-137Xenon-138lodines (1)Iodine-131Iodine-133Iodine-135Particulates (1)Strontium-89Strontium-90Cesium-134Cesium-137Cobalt-60Cobalt-58Manganese-54Barium-140Lanthanum-140Niobium-95Cerium-141Cerium-144Iron-59Cesium-136Chromium-51Zinc-65Iron-55Molybdenum-99Neodymium-147CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiI 3 ~ 3 ~ 3 ~ 3Tritium (1)Ci(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit ofdetection of 1.OOE-04 pCi/ml for required noble gases, 1.OOE-1i1 pCi/ml for required particulates, 1.OOE-12 pCi/ml for required lodines,and 1.OOE-06 pCi/ml for Tritium as required by the ODCM, has been verified.(2) Contributions from purges, if any, are included. There were no other batch releases during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1C GaseousEffluents -Ground ReleasesATTACHMENT 4Page 1 of 2Unit 1 X Unit 2 Reporting Period January -December 2014GASEOUS EFFLUENTS -GROUND LEVEL RELEASESGround level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.Continuous ModeNuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-127Xenon-131mXenon-133Xenon-133mXenon-135Xenon-135mXenon-137Xenon-138lodines (1)Iodine-131Iodine-133Iodine-135Particulates (1)Strontium-89Strontium-90Cesium-134Cesium-137Cobalt-60Cobalt-58Manganese-54Barium-140Lanthanum-140Niobium-95Cerium-141Cerium-144Iron-59Cesium-136Chromium-51Zinc-65Iron-55Molybdenum-99Neodymium-147CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCi8.69E-0i 8.44E-0i i.21E+00 8.27E-0iTritium (1)(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.Nine Mile Point Nuclear Station, LLCMay 1, 2015

-3Table 1 CATTACHMENT 4Page 2 of 2Unit 1 X Unit 2 Reporting Period January -December 2014GASEOUS EFFLUENTS -GROUND LEVEL RELEASESGround level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.Batch ModeNuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-127Xenon-1 31 mXenon-1 33Xenon-133mXenon-135Xenon-135mXenon-137Xenon-1 38lodines (1)Iodine-131Iodine-133Iodine-135Particulates (1)Strontium-89Strontium-90Cesium-134Cesium-137Cobalt-60Cobalt-58Manganese-54Barium-140Lanthanum-140Niobium-95Cerium-141Cerium-144Iron-59Cesium-136Chromium-51Zinc-65Iron-55Molybdenum-99Neodymium-147CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiIT2 3" t EE I 3"l *Tritium (1)Ci(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 2AATTACHMENT 5Page 1 of 2Unit 1 X Unit 2 Reporting Period January -December 2014LIQUID EFFLUENTS -SUMMATION OF ALL RELEASES (1)1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %A. Fission & Activation Products1. Total Release (not including Tritium,gases, alpha)2. Average diluted concentration duringreporting periodB. Tritium1 .Total release2. Average diluted concentration duringthe reporting periodC. Dissolved and Entrained Gases1. Total release2. Average diluted concentration duringthe reporting periodD. Gross Alpha Radioactivity1. Total releaseE. Volumes1. Prior to Dilution2. Volume of dilution water used duringrelease period3. Volume of dilution water availableduring reporting period -Cooling WaterF. Percent of Tech. Spec. LimitsPercent of Quarterly Whole Body DoseLimit (1.5 mrem)Percent of Annual Whole Body DoseLimit to Date (3 mrem)Percent of Quarterly Organ Dose Limit(5 mrem)Percent of Annual Organ Dose Limit toDate (10 mrem)Percent of 1OCFR20 ConcentrationLimitPercent of Dissolved or Entrained NobleGas Limit (2.OOE-04 pCi/ml)CipCi/mlCipCi/mlCipCi/mlNo Releases No Releases No Releases No ReleasesI5.OOE+01No Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No ReleasesjNoReleasesNo Releases No Releases No Releases No Releases5.OOE+01No Releases No Releases No Releases No Releases5.OOE+015.OOE+01Ci I No Releasesl No Releases No Releases I No ReleasesLitersLitersLitersNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No Releases1.29E+11 1.32E+11 1.36E+11 1.30E+11No Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No Releases5.OOE+015.OOE+015.OOE+01(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATable 2BATTACHMENT 5Page 2 of 2Unit I X Unit 2 Reporting Period January -December 2014LIQUID EFFLUENTS RELEASEDBatch Mode (1),(2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterNuclides ReleasedStrontium-89Strontium-90Cesium-134Cesium-137Iodine-131Cobalt-58Cobalt-60Iron-59Zinc-65Manganese-54Chromium-51Zirconium-95Niobium-95Molybdenum-99Barium-140Lanthanum-140Cerium-141Iodine-133Iron-55Cerium-144Cesium-136Copper-64Manganese-56Nickel-65Sodium-24CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesNo Releases No Releases No Releases No ReleasesDissolved or Entrained GasesTritium(1) No continuous mode release occurred during the report period as indicated by effluent sampling. There were no Radwaste BatchReleases.(2) Concentrations less than the lower limit of detection of the counting system used have been verified for sampled effluents. A lowerlimit of detection of 5.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/ml for required dissolved and entrainednoble gases and tritium, 5.OOE-08 pCi/ml for Sr-89/90, 1.OOE-06 pCi/ml for 1-131 and Fe-55, and 1.OOE-07 pCi/ml for gross alpharadioactivity, as identified in the ODCM, has been verified. Concentrations less than the lower limit of detection of the countingsystem used are indicated with a double asterisk.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 3ATTACHMENT 6Page 1 of 4Unit I X Unit 2 Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSAl. TYPE Volume Activity (1)(me) (Ci)Class ClassA B C A B Ca.1 Spent Resin (Dewatered) 9.91 E+00 O.OOE+00 O.OOE+00 7.79E+00 0.00E+00 O.OOE+00a.2 Filter Sludge O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+00 0.00E+00 0.00E+00a.3 Concentrated Waste O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Totals 9.91E+00 O.OOE+00 O.OOE+00 7.79E+00 O.OOE+00 O.OOE+00b.1 Dry Compressible Waste 1.16E+02 O.OOE+00 O.OOE+00 5.02E-02 O.OOE+00 O.OOE+00b.2 Dry Non-CompressibleWaste (Contaminated O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Equipment) I ITotals 1.16E+02 O.OOE+00 O.OOE+00 5.02E-02 O.OOE+00 O.OOE+00c to0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00Control Rods, etc.d. Other (to vendor for processing)d.1 Sewage sludge 1.63E+01 O.OOE+00 O.OOE+00 2.08E-05 O.OOE+00 O.OOE+001(l) The estimated total error is 5.OE+01 %.Nine Mile Point Nuclear Station, LLCMay 1, 2015

IITable 3ATTACHMENT 6Page 2 of 4Unit I X Unit 2 Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSAl. TYPE Container Package Solidification Agenta.1 Spent Resin (Dewatered) Poly Liner General Design Nonea.2 Filter Sludge N/A N/A N/Ab.1 Dry Compressible Waste Seavan General Design Noneb.2 Dry Non-CompressibleWaste (contaminated N/A N/A N/Aequipment)c. Irradiated Components, N/A N/A N/AControl Rodsd. Other (To vendor for processing)d.1 Sewage sludge Flexible shipping bag General Design None Table 3ATTACHMENT 6Page 3 of 4Unit I X Unit 2 Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSA2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)a. Spent Resins, Filter Sludges, Concentrated WasteNuclide Percent CuriesH-3 1.66% 1.32E-01C-14 2.05% 1.63E-01Fe-55 4.12% 3.27E-01Co-60 83.04% 6.59E+00Cs-137 6.25% 4.96E-01b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)Nuclide Percent CuriesCr-51 2.28% 1.14E-03Mn-54 2.63% 1.32E-03Fe-55 52.35% 2.63E-02Co-60 38.61% 1.94E-02Ni-63 1.33% 6.66E-04c. Irradiated Components, Control Rods: There were no shipments.Nuclide PercentN/A N/Ad. Other: (To vendor for processing)1. Dried Sewage Sludge shipped in "Flexible Shipping Bag"Nuclide Percent CuriesMn-54 3.76% 7.80E-07Co-60 90.56% 1.88E-05Cs-137 5.68% 1.18E-06Nine Mile Point Nuclear Station, LLCMay 1, 2015 bTable 3ATTACHMENT 6Page 4 of 4Unit I X Unit 2 Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSA3. SOLID WASTE DISPOSITIONNumber of Shipments Mode of Transportation Destination1 Hittman Transport Barnwell Processing Facility1 Hittman Transport Durateck Services, Inc (GRF)2 Hittman Transport Energy Solutions Services (CVRF)1 Hittman Transport Energy Solutions (Clive)B. IRRADIATED FUEL SHIPMENTS (Disposition)Number of Shipments Mode of Transportation Destination0 N/A N/AD. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIALSewage sludge with detectable quantities of plant-related nuclides was shipped from NMP to the treatment facility during 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 7Page 1 of 1Unit 1 X Unit 2 Reporting Period January -December 2014SUMMARY OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)The Unit 1 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period.REVISION XXPage # New/Amended Description of Change Reason For ChangeSection #REVISION XXNewlAmendedPage # Section # d Description of Change Reason For Change__ I ____ I ______ I _______Nine Mile Point Nuclear Station, LLCMay 1, 2015

-hATTACHMENT 8 Page 1 of 1Unit 1 X Unit 2 Reporting Period January -December 2014SUMMARY OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)There were no changes to the NMP1 Process Control Program (PCP) during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 jiATTACHMENT 9Page 1 of 1Unit 1 X Unit 2 Reporting Period January -December 2014SUMMARY OF NON-FUNCTIONAL MONITORSMonitor Dates Monitor was Cause and Corrective ActionsNon-FunctionalLiquid Radwaste January 1, 2014 to These monitors were intentionally allowed to exceed their quarterlyDischarge Monitors December 31, 2014 functional test and annual calibration frequency, as no discharges11 and 12 are planned or expected. This condition is allowed as long asblank flanges are installed in the discharge line, precluding anyunmonitored discharge. No liquid waste discharges wereperformed during 2014. This non-functionality is tracked inEquipment Status Log (ESL) 2006-0192.

)ATTACHMENT 10 Page 1 of 4Unit I X Unit 2 _ Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYIntroductionAn assessment of the radiation dose potentially received by a Member of the Public due to their activities insidethe site boundary from Nine Mile Point Unit 1 (NMPI) liquid and gaseous effluents has been conducted for theperiod January through December 2014.This assessment considers the maximum exposed individual and the various exposure pathways resulting fromliquid and gaseous effluents to identify the maximum dose received by a Member of the Public during theiractivities within the site boundary.Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observingthe educational displays or for picnicking and associated activities. Fishing also occurred near the shorelineadjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsiteactivity that resulted in the potential maximum dose received by a Member of the Public. Following September11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of thePublic at locations on site is also prohibited. Although fishing was not conducted during 2014, the annual doseto a hypothetical fisherman was still evaluated to provide continuity of data for the location.Dose PathwaysDose pathways considered for this evaluation included direct radiation, inhalation and external ground (shorelinesediment or soil doses). Other pathways, such as ingestion pathways, are not considered because they are eithernot applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of thepublic located off-site. In addition, only releases from the NMP1 stack and emergency condenser vent wereevaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicablesince swimming is prohibited at the NMP site.Dose to a hypothetical fisherman is received through the following pathways while standing on the shorelinefishing:* External ground pathway; this dose is received from plant related radionuclides detected in the shorelinesediment.* Inhalation pathway; this dose is received through inhalation of gaseous effluents released from the NMP1Stack and Emergency Condenser Vent." Direct radiation pathway; dose resulting from the operation of NMP1, Nine Mile Point Unit 2 (NMP2) andthe James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.Methodologies for Determining Dose for Applicable PathwaysExternal Ground (Shoreline Sediment) PathwayDose from the external ground (shoreline sediment) is based on the methodology in the NMP1 Offsite DoseCalculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that thehypothetical maximum exposed individual fished from the shoreline at all times.Nine Mile Point Nuclear Station, LLCMay 1, 2015

-lATTACHMENT 10Page 2 of 4Unit 1 X Unit 2 Reporting Period: January -December 20141 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYIThe total dose received by the whole body and skin of the maximum exposed individual during 2014 wascalculated using the following input parameters:* Usage Factor = 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months (fishing 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week, 39 weeks per year)* Density in grams per square meter = 40,000* Shore width factor = 0.3* Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6.* Fractional portion of the year = I (used average radionuclide concentration over total time period)" Average Cs-137 concentration = 1.05E-01 pCi/gThe total whole body and skin doses received by a hypothetical maximum exposed fisherman from the externalground pathway is presented in Table 1, Exposure Pathway Annual Dose.Inhalation PathwayThe inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP1 ODCM, as adaptedfrom Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximumexposed fisherman during 2014 calculated using the following input parameters for gaseous effluents releasedfrom both the NMPl Stack and Emergency Condenser Vent for the time period exposure is received:NMP 1 Stack:Variable FishermanX/Q (s/m3) 8.90E-06Inhalation dose factor Table E-7, Regulatory Guide 1. 109Annual air intake (m3/year) (adult) 8000Fractional portion of the year 0.0356H-3 (pCi/sec) 7.92 E+05C-14 (pCi/sec)2 2.75 E+05Fe-55 (pCi/sec) 1.17 E+00Co-58 (pCi/sec) 2.25 E+00Co-60 (pCI/sec) 2.47 E+011-131 (pCi/sec) 6.10 E+001-133 (pCi/sec) 1.58 E+02Cs- 137 (pCi/sec) 1.42 E+00Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 10 Page 3 of 4Unit 1 X Unit 2 __ Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY_NMPI Emergency Condenser Vent:Variable FishermanX/Q (s/rn3) 6.63E-06Inhalation dose factor Table E-7, Regulatory Guide 1.109Annual air intake (m3/year) (adult) 8000Fractional portion of the year 0.0356H-3 (pCi/sec) 1.21 E+05The maximum exposed fisherman is assumed to be present on site during the period of April throughDecember at a rate of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39 weeks per year equivalent to 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months for the year (fractionalportion of the year = 0.0356). Therefore, the Average Stack and Emergency Condenser Vent flow rates andradionuclide concentrations used to determine the dose are represented by second, third and fourth quartergaseous effluent flow and concentration values.2 C-14 release rate determined from NUREG-0016, "Calculation of Releases of Radioactive Materials inGaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code)," and EPRI Technical Report1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fishermanis presented in Table 1, Exposure Pathway Annual Dose.Direct Radiation PathwayThe direct radiation pathway is evaluated in accordance with the methodology found in the NMPI ODCM. Thispathway considers four components: direct radiation from the generating facilities, direct radiation from anypossible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion.The direct radiation pathway is evaluated by the use of high sensitivity environmental ThermoluminescentDosimeters (TLDs). Since fishing activities occur between April 1 and December 31, TLD data for the second,third, and fourth quarters of 2014 from TLDs placed in the general area where fishing once occurred were usedto determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. Thefollowing is a summary of the average dose rate and assumed time spent on site used to determine the total dosereceived:Variable FishermanAverage Dose Rate (mRem/hr) 5.47 E-03Exposure time (hours) 312Total doses received by the hypothetical maximum exposed fisherman from direct radiation is presented in Table1, Exposure Pathway Annual Dose.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 10Page 4 of 4Unit 1 X Unit 2 __ Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYIDose Received By A Hypothetical Maximum Exposed Member of the Public Inside the Site BoundaryDuring 2014The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid andgaseous effluents released from NMP1 during 2014:TABLE 1Exposure Pathway Annual DoseExposure Pathway Dose Type Fmrma(mrem)Whole Body 1.65 E-03External GroundSkin of Whole Body 1.92 E-03Whole Body 6.51 E-04Inhalation Maximum Organ Bone: 1.58 E-03Thyroid 6.50 E-04Direct Radiation Whole Body 0.47Based on these values the total annual dose received by a hypothetical maximum exposed Member of the Publicinside the site boundary is as follows:TABLE 2Annual Dose SummaryTotal Annual Dose for 2014 Fisherman(mrem)Total Whole Body 4.75 E-01Skin of Whole Body 1.92 E-03Maximum Organ Bone: 1.58 E-03Thyroid 6.50 E-04Nine Mile Point Nuclear Station, LLCMay 1, 2015 6ATTACHMENT 11 Page 1 of 5Unit 1 X Unit 2 Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYIntroductionAn assessment of radiation doses potentially received by the likely most exposed Member of the Public locatedbeyond the site boundary was conducted for the period January through December 2014 for comparison against the40 CFR 190 annual dose limits.The intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 1 (NMP1), as well as other nearbyuranium fuel cycle facilities, be considered. In this case, the effluents of NMP1, Nine Mile Point Unit 2 (NMP2)and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.40 CFR 190 requires the annual radiation dose received by Members of the Public in the general environment, as aresult of plant operations, be limited to:S< 25 mRem whole body* < 25 mRem any organ (except thyroid)* < 75 mRem thyroidThis evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating fromthe site as a result of the operation of the NMP 1, NMP2 and JAFNPP nuclear facilities.Dose PathwaysDose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents anddirect radiation from all nuclear operating facilities located on the Nine Mile Point site.Dose to the likely most exposed Member of the Public, outside the site boundary, is received through the followingpathways:* Fish consumption pathway; this dose is received from plant radionuclides that have concentrated in fish that isconsumed by a Member of the Public." Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated invegetation that is consumed by a Member of the Public." Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclidesin the shoreline sediment, which is used as a recreational area.* Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received throughexposure to gaseous effluents released from NMP1, NMP2 and JAFNPP operating facilities.* Direct Radiation pathway; radiation dose resulting from the operation ofNMPI, NMP2 and JAFNPP facilities(including the Independent Spent Fuel Storage Installations (ISFSI)).Methodologies for Determining Dose for Applicable PathwaysFish ConsumptionDose received as a result of fish consumption is based on the methodology specified in the NMP1 Off-Site DoseCalculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2014 is calculated fromactual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it isassumed that the most likely exposed Member of the Public consumes fish taken near the site discharge points.No radionuclides were detected in fish samples collected and analyzed during 2014; therefore, no dose wasreceived by the whole body and organs of the likely most exposed Member of the Public during 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11 Page 2 of 5Unit 1 X Unit 2 Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYVegetation ConsumptionDose received as a result of vegetation consumption is based on the methodology specified in the NMP I ODCM asadapted from Regulatory Guide 1.109. The dose for 2014 is calculated from actual analysis results ofenvironmental vegetation samples taken near the most exposed Member of the Public.No radionuclides were detected in vegetation samples collected and analyzed during 2014; therefore, no dose wasreceived by the whole body and organs of the likely most exposed Member of the Public during 2014.For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified inthe NMP 1 ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation isbased on the estimated concentration of C-14 in plant gaseous effluents.Shoreline SedimentDose received from shoreline sediment is based on the methodology in the NMPI ODCM as adapted fromRegulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Publicspends 67 hour7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months s/year along the shoreline for recreational purposes.No radionuclides were detected in shoreline sediment samples collected and analyzed during 2014; therefore nodose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.Dose Pathways Resulting From Gaseous EffluentsDose received by the likely most exposed Member of the Public due to gaseous effluents is calculated inaccordance with the methodology provided in the NMP1 ODCM, NMP2 ODCM, and the JAFNPP ODCM. Thesecalculations consider deposition, inhalation and ingestion pathways. The total sum of doses resulting from gaseouseffluents from NMP1, NMP2 and JAFNPP during 2014 provides a total dose to the whole body and maximumorgan dose for this pathway.Carbon-14 Dose Pathways Resulting from Gaseous EffluentsThe Carbon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseouswaste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 innuclear power plant 2014 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production andeffluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation ofCarbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. The following methodology was used inestimating C-14 gaseous release activity and dose components for the 2014 ARERR.EPRI methodology for estimating C-14 production rates in Boiling Water Reactors (BWRs):For BWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows: gaseous95% to 99%, liquid <0.5% and solid 1% to 5%. The report also states that -95% of C-14 in BWR gaseous wasteeffluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in thefood consumption cycle.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11 Page 3 of 5Unit I X Unit 2 __Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYFor NMPI and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the followingassumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based onthe number of Effective Full Power Days (EFPDs) for the period, (2) maximum C-14 activity from literaturevalues cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for gaseous releases fromliterature values also cited in EPRI Report 1021106.Equation 1 estimates the maximum annual production of C-14, PRmAx, for each BWR unit.PRMAX = 5.1 a MWT/ 1000 [Eq 1]Where:5.1 = BWR Normalized Production (Ci/GWt-yr)MWT MegaWatts Thermal (MWt)1000 Conversion Factor (MWt to GWt)Equation 2 estimates the C-14 activity released, A c-14, into the gaseous pathway during the time period for eachBWR unit.A c-14 PRq4,y

0.99

EFPD / 365, Ci (for timeperiod) [Eq 2]Where:PR " = maximum annual production rate of C-140.99 = fraction of C-14 in BWR gaseous pathway releases (maximumliterature value in EPRI Report 1021106; also Table 1)EFPD number of effective full power days for the unit during the timeperiod; e.g., quarterly or yearly (Table 1)365 number of days in a typical yearNine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11Page 4 of 5IUnit 1 X Unit 2 __ Reporting Period: January -December 2014IDOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYEquation 3 estimates the C-14 activity released in carbon dioxide form, A c-14, Co2, into the gaseous pathway duringthe time period for each BWR unit.A C-14, c02 = PR .fAv # 0.99 v 0.95

EFPD / 365, Ci (for time period) [Eq 3]Where:PR ftX = maximum annual production rate of C-140.99 = fraction of C-14 in BWR gaseous pathway releases (maximumliterature value in EPRI Report 1021106; also Table 1)0.95 fraction of C-14 as carbon dioxide in BWR gaseous pathwayreleases (typical literature value in EPRI Report 1021106; also Table 1)EFPD = number of effective full power days for the unit during the timeperiod, e.g. quarterly or yearly (Table 1)365 = conversion factor, 365 days in a typical average yearFor each BWR unit, the 2014 estimated C-14 activity releases (total and carbon dioxide chemical form) aresummarized in Table 1.Table 12014 BWR Estimated C-14 Gaseous ReleasesGaseous CO2 Form Max. Annual 2014 Total Release 2014 CO2 ReleaseBWR Release Release EFPD Operation Prod. RateFraction(s) Fraction(b) (Eq 1)363 EFPDNMP1 0.99 0.95 (99.4%) 9.44 Ci/yr 9.29 Ci 8.82 Ci318 EFPDNMP2 0.99 0.95 (87.1%) 20.34 Ci/yr(c) 17.54 Ci 16.67 CiJAFNPP 0.99 0.95 282 EFPD 10.84 Ci/yr 8.29 Ci 7.87 Ci(77.3%)(a) Maximum literature values from EPRI Report 1021106.(b) Typical value from EPRI Report 1021106.(c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal.As long as the core designs and power ratings are not significantly changed, the maximum annual production ratesand annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14gaseous release activity and dose components for the ARERR.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11Page 5 of 5Unit 1 X Unit 2 __ Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY IDirect Radiation PathwayDose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from thegenerating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and grounddeposition. This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector inorder to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the localmeteorology. During 2014, the closest residence and the critical downwind residence are at the same location.Table 2Dose Potentially Received by the Likely Most Exposed Member of the PublicOutside the Site Boundary During 2014Exposure Pathway Dose Type Dose (mrem)Fish and Vegetation Total Whole Body No DoseConsumption Total Maximum Organ No DoseTotal Whole Body No DoseShoreline SedimentTotal Skin of Whole Body No DoseTotal Whole Body 9.90 E-04Gaseous Effluents Thyroid 6.21 E-03(excluding C- 14)Maximum Organ Thyroid: 6.21 E-03Gaseous Effluent Total Whole Body 4.41 E-02(C-14) Maximum Organ Bone: 2.20 E-01Direct Radiation Total Whole Body 2.05Based on these values the maximum total annual dose potentially received by the likely most exposed Member ofthe Public during 2014 is as follows:* Total Whole Body: 2.09 E+00 mrem" Total Thyroid: 6.21 E-03 mrem" Maximum Organ: Bone: 2.21 E-01 mrem40 CFR 190 EvaluationThe maximum total doses presented in this attachment are the result of operations at the NMPI, NMP2 and theJAFNPP facilities. The maximum organ dose (Bone: 0.221 mrem), maximum thyroid dose (0.006 mrem) and themaximum whole body dose (2.09 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to themaximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 12Page 1 of 1Unit 1 X Unit 2 __ Reporting Period: January- December 20141 GROUNDWATER PROTECTION PROGRAM TRITIUM RESULTS SUMMARYIWell Identification # Samples Minimum MaximumNumber Collected Concentration (pCi/I) Concentration (pCi/I)GMX-MW1* 4 0 <404 <493MW-B119* 4 0 <404 <493MW-1 4 0 <404 <493MW-4 4 0 <404 <493MW-6 4 0 <404 <493MW-7 4 0 <404 <493MW-8 4 0 <404 <493MW-91 4 0 <404 <493MW-101 4 0 <404 <493MW-11 4 0 <404 <493MW-12 4 0 <404 <493MW-13 4 0 <404 <493MW-14* 4 0 <404 <493MW-15 4 0 <404 <493MW-16 4 0 <404 <493MW-17 4 0 <376 <493MW-18 4 0 <404 <493MW-19 4 0 <404 <493MW-20 4 0 <404 <493MW-21 4 0 <404 <493NMP2 MAT 23 4 0 <368 <488Notes:* -Control Location1 _ Sentinel well location2 _ NMP2 Groundwater Depression Cone-Samples collected from storm drain system which includes precipitationNine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 13Page 1 of 1Unit I X Unit 2 Reporting Period January -December 2014Off-Site Dose Calculation Manual (ODCM)There was no revision to the Off-Site Dose Calculation Manual for 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 14Page 1 of 1Unit 1 X Unit 2 Reporting Period January -December 2014Process Control Program (PCP)There were no changes to the Process Control Program in 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Nine Mile Point Nuclear Station, Unit 2Radioactive Effluent Release Report, January -December 2014 NINE MILE POINT NUCLEAR STATION -UNIT 2RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014SUPPLEMENTAL INFORMATIONFacijiy: Nine Mile Point Unit 2 LL t-.Nine Mile Point Nuclear Station, LLC1. TECHNICAL SPECIFICATION LIMITS/ODCM lTimitsA. FISSION AND ACTIVATION GASES1. The dose rate limit of noble gases released in gaseous effluents from the site to areas atand beyond the site boundary shall be less than or equal to 500 mrem/year to the totalbody and less than or equal to 3000 mrem/year to the skin.2. The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit Ito areas at and beyond the site boundary shall be limited during any calendar quarter toless than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10mrad for beta radiation, and during any calendar year to less than or equal to 10milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.B. IODINES1. The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulateform with half-lives greater than eight days, released in gaseous effluents from the site toareas at and beyond the site boundary shall be less than or equal to 1500 mrem/year toany organ.2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and allradionuclides in particulate form with half-lives greater than eight days in gaseouseffluents released from Nine Mile Point Unit 1 to areas at and beyond the site boundaryshall be limited during any calendar quarter to less than or equal to 7.5 mrem to anyorgan, and during any calendar year to less than or equal to 15 mrem to any organ.C. TRITIUM AND PARTICULATES, HALF LIVES> 8 DAYS1. The dose rate limit of Iodine-13 1, Iodine-133, Tritium and all radionuclides in particulateform with half-lives greater than eight days, released in gaseous effluents from the site toareas at and beyond the site boundary shall be less than or equal to 1500 mremryear toany organ.2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and allradionuclides in particulate form with half-lives greater than eight days in gaseouseffluents released from Nine Mile Point Unit 1 to areas at and beyond the site boundaryshall be limited during any calendar quarter to less than or equal to 7.5 mrem to anyorgan, and during any calendar year to less than or equal to 15 mrem to any organ.Nine Mile Point Nuclear Station, LLCMay 1, 2015 D. LIQUID EFFLUENTSI. The concentration of radioactive material released in liquid effluents to unrestricted areasshall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B,Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. Fordissolved or entrained noble gases, the concentration shall be limited to 2E-04microcuries/ml total activity.2. The dose or dose commitment to a member of the public from radioactive materials inliquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limitedduring any calendar quarter to less than or equal to 1.5 mrem to the total body and to lessthan or equal to 5 mrem to any organ, and during any calendar year to less than or equalto 3 mrem to the total body and to less than or equal to 10 mrem to any organ.2. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITYDescribed below are the methods used to measure or approximate the total radioactivity and radionuclidecomposition in effluents.A. FISSION AND ACTIVATION GASESNoble gas effluent activity is determined by on-line gross activity monitoring (calibrated againstgamma isotopic analysis of a 4.OL Marinelli grab sample) of an isokinetic stack sample stream.B. IODINESIodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) ofcharcoal cartridges sampled from an isokinetic stack sample stream.C. PARTICULATESActivity released from the main stack is determined by gamma spectroscopic analysis (at leastweekly) of particulate filters sampled from an isokinetic sample stream and composite analysis ofthe filters for non-gamma emitters.D. TRITIUMTritium effluent activity is measured by liquid scintillation or gas proportional counting ofmonthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity ismeasured during purge and weekly when fuel is offloaded until stable tritium release rates aredemonstrated.E. EMERGENCY CONDENSER VENT EFFLUENTSThe effluent curie quantities are estimated based on the isotopic distribution in the CondensateStorage Tank water and the Emergency Condenser shell water. Actual isotopic concentrations arefound via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated byapplying scaling factors to release rates of gamma emitters and actual release rates are determinedfrom post off site analysis results. The activity of fission and activation gases released due to tubeleaks is based on reactor steam leak rates using offgas isotopic analyses.Nine Mile Point Nuclear Station, LLCMay 1, 2015 F. LIQUID EFFLUENTSIsotopic contents of liquid effluents are determined by isotopic analysis of a representativesample of each batch and composite analysis of non-gamma emitters. Tritium activity isestimated on the most recent analysis of the Condensate Storage Tank water. Initial release ratesof Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to. release rates of gammaemitters and actual release rates are determined from post off site analysis results.G. SOLID EFFLUENTSIsotopic contents of waste shipments are determined by gamma spectroscopy analysis of arepresentative sample of each batch. Scaling factors established from primary composite sampleanalyses conducted off-site are applied, where appropriate, to find estimated concentration ofnon-gamma emitters. For low activity trash shipments, curie content is estimated by dose ratemeasurement and application of appropriate scaling factors.H. C-14The production of C-14 and the effluent dose consequences are estimates based on EPRImethodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power PlantGaseous Effluents, December 2010 and NUREG-0016, Calculation of Releases of RadioactiveMaterials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code).3. METEOROLOGICAL DATAAn annual summary of hourly meteorological data collected over the previous year. This annualsummary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, winddirection, atmospheric stability, and precipitation (if measured), or in the form ofjoint frequencydistribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with theRadiological Effluent Release Report, the licensee is exercising the option of retaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Supplemental Information ATTACHMENT 1 Page 1 of 2SUMMARY DATAUnit I Unit 2 X Reporting Period January -December 2014Liquid Effluents:ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20.1001 -20.2402, Appendix B, Table 2, Column 2Average MEC -pCi/ml (Qtr. 1) = NO RELEASE Average MEC -pCi/ml (Qtr. 3) = NO RELEASESAverage MEC -pCi/mI (Qtr.. 2) = [ .OO-oLJ Average MEC -pCi/mI (Qtr. 4) = NO REEASESAverage Energy (Fission and Activation gases -MEV):Qrtr. 1: Ey = 7.57E-01 EP = 2.94E-01Qrtr. 2: Ey = 1.59E-01 E3 = 2.53E-01Qrtr._3: Ey = N/A Ep = N/AQrtr. 4: Ey = N/A Ep = N/ALiquid:Number of Batch Releases 1Total Time Period for Batch Releases (hrs) 888.0Maximum Time Period for a Batch Release (hrs) 888.0Average Time Perod for a Batch Release (hrs) 888.0Minimum Time Period for a Batch Release 888.0Total volume of water used to dilute the liquid I 1st 2nd 3rd 4thduring the release period (L) N/A 4.73E+09 N/A N/AlTotal volume of water available to dilute the liquid ist 2nd 3rd 4theffluent during the report period (L) 1.24E+10 1.27E+10 1.36E+10 1.23E+1 0Gaseous (Emergency Condenser Vent) "Not applicable for Unit 2"Number of Batch Releases N/ATotal Time Period for Batch Releases (hrs) N/AMaximum Time Period for a Batch Release (hrs) N/AAverage Time Period for a Batch Release (hrs) N/AMinimum Time Period for a Batch Release N/AGaseous (Primary Containment Purge)Number of Batch Releases 13Total Time Period for Batch Releases (hrs) 72.4Maximum Time Period for a Batch Release (hrs) 6.0Average Time Period for a Batch Release (hrs) 5.6Minimum Time Period for a Batch Release (hrs) 2.8Nine Mile Point Nuclear Station, LLCMay 1, 2015 Supplemental InformationATTACHMENT 1SUMMARY DATAPage 2 of 2Unit 1 Unit 2 X Reporting Period January -December 2014Abnormal Releases:A. Liquids:Number of Releases 1ITotal Activity Released 2.24E-04 CiB. Gaseous:INumber of Releases 0Total Activity Released N/A CiNine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1A Gaseous Effluents -Summation of All Releases -Elevated and Ground LevelATTACHMENT 2Page 1 of 1Unit I Unit 2 X Reporting Period January -December 2014GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL1st 2nd 3rd 4th Est. TotalQuarter Quarter Quarter Quarter Error %A. Fission & Activation GasesI. Total Release2. Average Release RateB. lodines1. Total Iodine -1312. Average Release Rate for PeriodC. Particulates1. Particulates with Half-lives>8days2. Average Release Rate for Period3. Gross Alpha RadioactivityD. Tritium1. Total Release2. Average Release Rate for PeriodE. Percent of Tech. Spec. LimitsFission and Activation GasesPercent of Quarterly Gamma Air Dose Limit(5 mR)Percent of Quarterly Beta Air Dose Limit (10mrad)Percent of Annual Gamma Air Dose Limit toDate (10 mR)Percent of Annual Beta Air Dose Limit toDate (20 mrad)Percent of Whole Body Dose Rate Limit (500mrem/yr)Percent of Skin Dose Rate Limit (3000mrem/yr)Tritium, lodines. and Particulates (with half-lives qreater than 8 days)Percent of Quarterly Dose Limit (7.5 mrem)Percent of Annual Dose Limit to Date (15mrem)Percent of Organ Dose Limit (1500 mrem/yrCipCi/secCipCi/secCipCi/secCiCipCi/sec8.88E+00 4.89E-01 0.OOE+00 0 .OOE+001.14E+00 6.22E-02 0.OOE+00 0.OOE+005.33E-04 5.27E-05 3.22E-05 1 .57E-046.78E-05 6.70E-06 4.10E-06 2.OOE-055.49E-04 6.24E-04 2.60E-04 2.06E-046.98E-05 7.94E-05 3.31 E-05 2.62E-050.OOE+00 0.OOE+00 0.OOE+00 0.OOE+009.87E+00 5.75E+00 1- 29-E-+01 -T9 *91 E+0011.26E+00 7.32E-01 1.64E+00 1.26E+001.54E-02 1.58E-04 0.OOE+00 0.OOE+002.90E-04 1.37E-05 0.OOE+00 0.OOE+007.72E-03 7.80E-03 7.80E-03 7.80E-031.45E-04 1.52E-04 1.52E-04 1.52E-046.12E-04 9.76E-06 0.OOE+00 0.OOE+001.19E-04 1.30E-06 0.OOE+00 0.OOE+001.53E-01 2.35E-02 1.80E-02 2.97E-027.67E-02 8.84E-02 9.74E-02 1.12E-013.11E-03 4.70E-04 3.57E-04 6.02E-045.OOE+013.OOE+013.OOE+012.50E+015.OOE+01Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1B GaseousEffluents -Elevated ReleasesATTACHMENT 3Page 1 of 2unit I Unit 2 X Reporting Period January -December 2014GASEOUS EFFLUENTS -ELEVATED RELEASEContinuous Mode (2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-127Xenon-131mXenon-1 33Xenon-133mXenon-135Xenon-1 35mXenon-137Xenon-I38lodines (1)Iodine-131Iodine-133Iodine-135Particulates (1)Chromium-51Manganese-54Iron-55Iron-59Cobalt-58Cobalt-60Neodymium-147Zinc-65Strontium-89Strontium-90Niobium-95Zirconium-95Molybdenum-99Ruthenium-1 03Cesium-134Cesium-136Cesium-137Barium-140Lanthanum-140Cerium-141Cerium-144CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCi5.92E+00 4.89E-01 ....2.96E+00 ..4.96E-04 5.02E-05 [ 2.36E-05 j 9.26E-059.11E-03 3.15E-04 4.51E-04 1.06E-03** I ** I ** i **1.18E-04 1.75E-05 4.29E-06 1.17E-061i.02E-05 **i1.27E-05 8.77E-05 3.90E-05 4.06E-05S.04E-06** ** **8.03E00 3.89E+00 5.12E+00 8.15E+00::]Tritium (1)Ci(i) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of1,00E-04 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required lodines, 1.OOE-1 1pCi/ml for Sr-89/90 and 1.OOE-06 pCi/ml for Tritium, as required by the ODCM, has been verified.(2) Contributions from purges are included. There were no other batch releases during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 3Page 2 of 2Unit I Unit 2 X Reporting Period January -December 2014GASEOUS EFFLUENTS -ELEVATED RELEASEBatch Mode (2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-1 27Xenon-1 31 mXenon-1 33Xenon-133mXenon-135Xenon-135mXenon-1 37Xenon-1 38lodines (1)Iodine-131Iodine-133Iodine-135Particulates (1)Chromium-51Manganese-54Iron-55Iron-59Cobalt-58Cobalt-60Neodymium-147Zinc-65Strontium-89Stronium-90Niobium-95Zirconium-95Molybdenum-99Ruthenium-103Cesium-134Cesium-136Cesium-137Barium-140Lanthanum-140Cerium-141Cerium-144CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCi** T ** ** ** 1_________________ _________________ _________________ _________________ ITritium (11Ci(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of1.OOE-04 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required lodines, 1.00E-11pCi/ml for Sr-89/90 and 1.OOE-06 pCi/ml for Tritium, as required by the ODCM, has been verified.(2) Contributions from purges are included. There were no other batch releases during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1CATTACHMENT 4Page 1 of 2Unit I Unit 2 X Reporting Period January -December 2014GASEOUS EFFLUENTS -GROUND LEVEL RELEASESContinuous Mode (2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Argon-41Krypton-85Krypton-85mKrypton-87Krypton-88Xenon-127Xenon-131mXenon-133Xenon-1 33mXenon-135Xenon-135mXenon-137Xenon-1 38lodines (1)Iodine-131Iodine-133Iodine-135Particulates (11Chromium-51Manganese-54Iron-55Iron-59Cobalt-58Cobalt-60Neodymium-147Zinc-65Strontium-89Strontium-90Niobium-95Zirconium-95Molybdenum-99Ruthenium-103Cesium-134Cesium-136Cesium-137Barium-140Lanthanum-140Cerium-141Cerium-144CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCi3.65E-05 2.48E-06 f8.62E-06 6.45E-055.39E-04 3.45E-05 I _____I4.91iE-05** ** I ** I **.65E-05 3.87E-0 .60E-05 **1.87E-04 1.35E-04 5.90E-05i1.3i1E-06 i1.40E-06 i1.26E-06 2.70E-06i1.72E-04 3.1i0E-04 2.00E-04 i1.03E-047.85E-06 2.34E-0 ** **S.46E-06** **3.7E-0 ** **1.84E+00 I .86E+00 I.6E0 i77E+007.6E0 I* 77E00Tritium (1)(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of1.OOE-04 pCi/ml for required noble gases, 1.OOE-11 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required iodines, 1.00E -11 pCi/ml for Sr-89/90 and 1.OOE-06 pCi/ml for Tritium, as required by the ODCM, has been verified.(2) There were no batch releases from this path during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 1CATTACHMENT 4Page 2 of 2Unit I Unit 2 X Reporting Period January -December 2014GASEOUS EFFLUENTS -GROUND LEVEL RELEASESBatch ModeNuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterFission Gases (1)Ar-41Kr-85Kr-85mKr-87Kr-88Xe-127Xe-131mXe-133Xe-133mXe-135Xe-135mXe- 137Xe-138lodines (1)1-1311-1321-133Particulates (1)Cr-51Mn-54Fe-55Fe-59Co-58Co-60Nd-147Zn-65Sr-89Sr-90Nb-95Zr-95Mo-99Ru-103Cs- 134Cs-136Cs-137Ba-140La-140Ce-141Ce-144CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCi3** 3* **31 *Tritium (1)Ci(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double **.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 2AATTACHMENT 5Page 1 of 2Unit I Unit 2 X Reporting Period January -December 2014LIQUID EFFLUENTS -SUMMATION OF ALL RELEASES (1)1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %A. Fission & Activation Products1. Total Release (not including Tritium,gases, alpha)2. Average diluted concentration duringreporting periodB. Tritium1 .Total release2. Average diluted concentration during thereporting periodC. Dissolved and Entrained Gases1. Total release2. Average diluted concentration during thereporting periodD. Gross Alpha Radioactivity1. Total releaseE. Volumes1. Prior to Dilution2. Volume of dilution water used duringrelease period3. Volume of dilution water available duringreporting periodF. Percent of Tech. Spec. LimitsPercent of Quarterly Whole Body Dose Limit(1.5 mrem)Percent of Annual Whole Body Dose Limit toDate (3 mrem)Percent of Quarterly Organ Dose Limit (5mrem)Percent of Annual Organ Dose Limit to Date(10 mrem)Percent of 1OCFR20 Concentration Limit (2),(3)Percent of Dissolved or Entrained Noble GasLimit (2.OOE-04 pCi/ml)CipCi/mlCipCi/mlCipCi/mICiLitersLitersLitersNo Releases 2.24E-04 No Releases No ReleasesNo Releases 1.77E-1 1 No Releases No ReleasesNo Releases

No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesENo Releases _ No ReleasesjNo eleases]No Releases 5.10E+06 No Releases No ReleasesNo Releases 4.73E+09 No Releases No Releases1.24E+10 1.27E+10 1.36E+10 1.23E+100.00E+00 4.65E-04 0.00E+00 0.00E+000.00E+00 2.32E-04 0.OOE+00 0.00E+000.00E+00 7.28E-04 0.00E+00 0.00E+000.00E+00 3.64E-04 0.00E+00 0.00E+000.00E+00 5.89E-05 0.OOE+00 0.OOE+000.OOE+00 0.00E+00 0.00E+00 0.00E+005.00E+0115.O0E+015.OOE+015.00E+015.OOE+015.OOE+015.00E+01(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of5.00E-07 pCi/mI for required gamma emitting nuclides, 1.OOE-05 pCi/mI for required dissolved and entrained noble gases and tritium, 5.00E-08pCi/mI for Sr-89/90, 1.00E-06 pCi/ml for 1-131 and Fe-55, and 1.00E-07 pCi/ml for gross alpha radioactivity, as required by the Off-Site DoseCalculation Manual (ODCM), has been verified.(2) The percent of 10CFR20 concentration limit is based on the average concentration during the quarter.(3) Improved Technical Specifications limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times theconcentrations specified in 10CFR20.1001 -20.2402, Appendix B, Table 2, Column 2. Maximum Effluent Concentrations (MEC) numerically equalto ten times the 1OCFR20.1001 -20.2402 concentrations were adopted to evaluate liquid effluents.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 2BATTACHMENT 5Page 2 of 2Unit 1 Unit 2 X Reporting Period January -December 2014LIQUID EFFLUENTS RELEASEDBatch Mode (1),(2)Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th QuarterNuclides ReleasedStrontium-89Strontium-90Cesium-134Cesium-137Iodine-131Cobalt-58Cobalt-60Iron-59Zinc-65Manganese-54Chromium-51Zirconium-95Niobium-95Molybdenum-99Technetium-99mBarium-140Lanthanum-140Cerium-141Tungsten-187Arsenic-76Iodine-133Iron-55Neptunium-239Silver-11 OmCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases 2.24E-04 No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases ** No Releases No ReleasesNo Releases No Releases No ReleasesNo Releases ** NO Releases I No ReleasesGold-199Cerium-144Cesium-136Copper-64Dissolved or Entrained GasesTritium(1) No continuous mode release occurred during the report period as indicated by effluent sampling.(2) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of5.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/ml for required dissolved and entrained noble gases and tritium, 5.OOE-08pCi/ml for Sr-89/90, 1.OOE-06 pCi/ml for 1-131 and Fe-55, and 1.OOE-07 pCi/ml for gross alpha radioactivity, as identified in the ODCM, has beenverified.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 3ATTACHMENT 6Page 1 of 4Unit I Unit 2 X Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSAi. TYPE Volume Activity 01)(mi) (Ci)Class ClassA B C A B Ca.1 Spent Resins 7.51E+01 O.0OE+00 O.OOE+00 2.64E+02 O.OOE+00 O.OOE+00(Dewatered)a.2 Filter Sludge O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00a.3 Concentrated Waste O.OOE+0O O.OOE+00 O.OOE+00 O.O0E+00 O.OOE+00 O.OOE+00Totals 7.51 E+01 O.OOE+00 O.OOE+00 2.64E+02 O.OOE+00 O.OOE+00b.1 Dry, compressible waste 8.66E+02 O.OOE+00 O.OOE+00 1.72E+00 O.OOE+00 O.OOE+00b.2 Dry, non-compressible O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00waste (contaminatedequipment)Totals 8.66E+02 O.OOE+00 O.OOE+00 1.72E+00 O.OOE+00 O.OOE+00c. Irradiated Components, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00Control Rodsd. Other (to vendor for processing)d.1 Oilywaste 1.42E+01 O.0OE+00 O.OOE+00 1.62E-02 O.OOE+00 O.OOE+00(1) The estimated total error is 5.OOE+01%.Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 3ATTACHMENT 6Page 2 of 4Unit 1 Unit 2 X Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSAl. TYPE Container Packaae Solidification Aaenta.1 Spent Resin (Dewatered) Poly Liner General Design Nonea.2 Filter Sludge N/A N/A N/Ab.1 Dry Compressible Waste Seavan General Design Noneb.2 Dry, Non-Compressible N/A N/A N/AWastec. Irradiated Components, N/A N/A N/AControl Rodsd. Other (to vendor for processing)d.1 Oily waste_ 55 gallon drums General Design NoneNine Mile Point Nuclear Station, LLCMay 1, 2015 Table 3ATTACHMENT 6Page 3 of 4Unit I Unit 2 X Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSA2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)a. Spent Resins, Filter Sludges, Concentrated WasteNuclide Percent CuriesMn-54 5.59% 1.48E+01Fe-55 57.36% 1.52E+02Co-60 33.20% 8.78E+01Zn-65 2.60% 6.88E+00b. Dry, compressible waste, dry, non-compressible waste (contaminated equipment)Nuclide Percent CuriesCr_51 2.22% 3.82E-02Mn-54 4.87% 8.37E-02Fe-55 63.23% 1.09E+00Fe-59 1.03% 1.78E-02Co-60 24.61% 4.23E-01Zn-65 1.35% 2.33E-02c. Irradiated Components, Control Rods: There were no shipments.Nuclide PercentN/A N/Ad. Other (To Vendor for Processing)1, Oily Drums shipped in Pan SeavanNuclide Percent CuriesCr-51 2.23% 3.67E-04Mn-54 4.90% 8.05E-04Fe-55 63.22% 1.04E-04Fe-59 1.03% 1.70E-04Co-60 24.51% 4.03E-03Zn-65 !.37% 2.25E-04Nine Mile Point Nuclear Station, LLCMay 1, 2015 Table 3ATTACHMENT 6Page 4 of 4Unit 1 Unit 2 X Reporting Period January -December 2014SOLID WASTE AND IRRADIATED FUEL SHIPMENTSA3. SOLID WASTE DISPOSITIONNumber of Shipments Mode of Transportation Destination6 Hittman Transport Bamwell Processing Facility19 Hittman Transport Energy Solutions Services (CVRF)3 Hittman Transport Energy Solutions LLC (Clive)1 Hittman Transport Toxco, Inc2 Hittman Transport Bamwell Processing Facility5 Hittman Transport Energy Solutions Services (CVRF)B. IRRADIATED FUEL SHIPMENTS (Disposition): There were no shipments.Number of Shipments Mode of Transportation Destination0 N/A N/AD. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIALThere were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facilityduring the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 7Page 1 of 1Unit I Unit 2 X Reporting Period January -December 2014SUMMARY OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)The Unit 2 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period.REVISION XXPage # New/Amended Description of Change Reason for Change1* I I1* I I1~ I I1* I INine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 8Page 1 of 1Unit 1 Unit 2 X Reporting Period January -December 2014SUMMARY OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)There were no changes to the NMP2 Process Control Program (PCP) during the reporting period.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 9Page 1 of 1Unit 1 Unit 2 X Reporting Period January -December 2014SUMMARY OF NON-FUNCTIONAL MONITORSMonitor Dates Monitor was Cause and Corrective ActionsNon-Functional2LWS-CAB206, January 1, 2014 to No liquid waste discharges were performed during 2014, and therefore, these2LWS-FT330 & December 31, 2014 monitors were not returned to service. The discharge manual isolation valves,2LWS-FT331, 2LWS-V420 and 2LWS-V422, are locked closed during inoperable periods,Liquid Waste therefore, no inadvertent discharge can occur. Reference Equipment StatusDischarge Monitor Log (ESL) 2010-0243.2OFG-AT115, Offgas 2/22/14 -5/2/14 Monitor failed downscale, no cause was identified. Instrument passed nextCommon Hydrogen surveillance test.Monitor No action required with 2OFG-AT16A, Offgas Train A Hydrogen Monitor &2OFG-AT16B, Offgas Train B Hydrogen Monitor FUNCTIONAL.

ATTACHMENT 10Page 1 of 5IUnit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYIntroductionAn assessment of the radiation dose potentially received by a Member of the Public due to their activitiesinside the site boundary from Nine Mile Point Unit 2 (NMP2) liquid and gaseous effluents has been conductedfor the period January through December 2014.This assessment considers the maximum exposed individual and the various exposure pathways resulting fromliquid and gaseous effluents to identify the maximum dose received by a Member of the Public during theiractivities within the site boundary.Prior to September 11, 200 1, the public had access to the Energy Information Center for purposes of observingthe educational displays or for picnicking and associated activities. Fishing also occurred near the shorelineadjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was theonsite activity that resulted in the potential maximum dose received by a Member of the Public. FollowingSeptember 11, 2001 public access to the Energy Information Center has been restricted and fishing byMembers of the Public at locations on site is also prohibited. Although fishing was not conducted during 2014the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location.Dose PathwaysDose pathways considered for this evaluation included direct radiation, inhalation and external ground(shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered becausethey are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to amember of the public located off-site. In addition, only releases from the NMP2 Stack and Radwaste/ReactorBuilding Vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquideffluents is not applicable since swimming is prohibited at the NMIP site.Dose to a hypothetical fisherman is received through the following pathways while standing on the shorelinefishing:* External ground pathway; this dose is received from plant related radionuclides detected in the shorelinesediment.* Inhalation pathway; this dose is received through inhalation of gaseous effluents released from the NMP2Stack and Radwaste/Reactor Building Vent." Direct radiation pathway; dose resulting from the operation of Nine Mile Point Unit I (NMP 1), NMP2 andthe James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.Methodologies for Determining Dose for Applicable PathwaysExternal Ground (Shoreline Sediment) PathwayDose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite DoseCalculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed thatthe hypothetical maximum exposed individual fished from the shoreline at all times.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 10Page 2 of 5IUnit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYThe total dose received by the whole body and skin of the maximum exposed individual during 2014 wascalculated using the following input parameters:" Usage Factor = 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months (fishing 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week, 39 weeks per year)* Density in grams per square meter = 40,000* Shore width factor = 0.3* Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6.* Fractional portion of the year = 1 (used average radionuclide concentration over total time period)* Average Cs-137 concentration = 1.05E-01 pCi/gThe total whole body and skin doses received by a hypothetical maximum exposed fisherman from theexternal ground pathway is presented in Table 1, Exposure Pathway Annual Dose.Inhalation PathwayThe inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP2 ODCM, as adaptedfrom Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypotheticalmaximum exposed fisherman during 2014 calculated using the following input parameters for gaseouseffluents released from both the NMP2 Stack and Radwaste/Reactor Building Vent for the time periodexposure is received:NMP2 Stack:Variable FishermanX/Q (s/m3) 9.6 E-07Inhalation dose factor Table E-7, Regulatory Guide 1.109Annual air intake (m3/year) (adult) 8000Fractional portion of the year 0.0356H-3 (pCi/sec) 7.07 E+05C-14 (pCi/sec)2 5.90 E+05Mn-54 (pCi/sec) 9.96 E-01Fe-55 (pCi/sec) 4.82 E-01Co-60 (pCI/sec) 6.93 E+001-131 (pCi/sec) 7.76 E+001-133 (pCi/sec) 8.62 E+0lNine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 10Page 3 of 5Unit 1 -Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYINMP2 Radwaste/Reactor Building Vent:Variable FishermanX/Q (s/m3) 2.8 E-06Inhalation dose factor Table E-7, Regulatory Guide 1. 109Annual air intake (m3/year) (adult) 8000Fractional portion of the year 0.0356H-3 (pCi/sec) 4.83 E+05Mn-54 (pCi/sec) 2.32 E+00Fe-55 (pCi/sec) 8.22 E+00Co-58 (pCi/sec) 2.27 E-01Co-60 (pCi/sec) 2.60 E+01Zn-65 (pCi/sec) 9.91 E-011-131 (pCi/sec) 6.38 E-011-133 (pCi/sec) 6.11 E+001. The maximum exposed fisherman is assumed to be present on site during the period of Aprilthrough December at a rate of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39 weeks per year equivalent to 312 hour0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months sfor the year (fractional portion of the year = 0.0356). Therefore, the Average Stack andRadwaste/Reactor Building Vent flow rates and radionuclide concentrations used todetermine the dose are represented by second, third and fourth quarter gaseous effluent flowand concentration values.2. C-14 release rate determined from NUREG-0016, "Calculation of Releases of RadioactiveMaterials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code),"and EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power PlantGaseous Effluents."The total whole body dose and maximum organ dose received by the hypothetical maximum exposedfisherman is presented in Table 1, Exposure Pathway Annual Dose.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 10Page 4 of 5IUnit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY IDirect Radiation PathwayThe direct radiation pathway is evaluated in accordance with the methodology found in the NMP2 ODCM.This pathway considers four components: direct radiation from the generating facilities, direct radiation fromany possible overhead plume, direct radiation from ground deposition and direct radiation from plumesubmersion. The direct radiation pathway is evaluated by the use of high sensitivity environmentalThermoluminescent Dosimeters (TLDs). Since fishing activities occur between April 1 and December 31,TLD data for the second, third, and fourth quarters of 2014 from TLDs placed in the general area wherefishing once occurred were used to determine an average dose to the hypothetical maximum exposedfisherman from direct radiation. The following is a summary of the average dose rate and assumed time spenton site used to determine the total dose received:Variable FishermanAverage Dose Rate (mRem/hr) 5.47 E-03Exposure time (hours) 312Total Doses received by the hypothetical maximum exposed fisherman from direct radiation is presented inTable 1, Exposure Pathway Annual Dose.Dose Received By A Hypothetical Maximum Exposed Member of the Public Inside the Site BoundaryDurin2 2014The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquidand gaseous effluents released from NMP2 during 2014:TABLE 1Exposure Pathway Annual DoseFishermanExposure Pathway Dose Type (mrem)External Ground Whole Body 1.65 E-03Skin of Whole Body 1.92 E-03Whole Body 1.60 E-04Inhalation Maximum Organ Bone: 3.66 E-04Thyroid 1.72 E-04Direct Radiation Whole Body 0.47Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 10Page 5 of 5Unit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARYBased on these values, the total annual dose received by a hypothetical maximum exposed Member of thePublic inside the site boundary is as follows:TABLE 2Annual Dose SummaryFishermanTotal Annual Dose for 2014(mrem)Total Whole Body 4.75 E-01Skin of Whole Body 1.92 E-03Maximum Organ Bone: 3.66 E-04Thyroid 1.72 E-04Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11Page 1 of 5Unit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYIntroductionAn assessment of radiation doses potentially received by the likely most exposed Member of the Public locatedbeyond the site boundary was conducted for the period January through December 2014 for comparison against the40 CFR 190 annual dose limits.The intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 1 (NMP 1), as well as other nearbyuranium fuel cycle facilities, be considered. In this case, the effluents of NMP1, Nine Mile Point Unit 2 (NMP2)and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.40 CFR 190 requires the annual radiation dose received by Members of the Public in the general environment, as aresult of plant operations, be limited to:0 < 25 mRem whole body* < 25 mRem any organ (except thyroid)S< 75 mRem thyroidThis evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating fromthe site as a result of the operation of the NMP 1, NMP2 and JAFNPP nuclear facilities.Dose PathwaysDose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents anddirect radiation from all nuclear operating facilities located on the Nine Mile Point site.Dose to the likely most exposed Member of the Public, outside the site boundary, is received through the followingpathways:* Fish consumption pathway; this dose is received from plant radionuclides that have concentrated in fish that isconsumed by a Member of the Public." Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated invegetation that is consumed by a Member of the Public.* Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclidesin the shoreline sediment, which is used as a recreational area.* Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received throughexposure to gaseous effluents released from NMP1, NMP2 and JAFNPP operating facilities." Direct Radiation pathway; radiation dose resulting from the operation of NMP I, NMP2 and JAFNPP facilities(including the Independent Spent Fuel Storage Installations (ISFSI)).Methodologies for Determining Dose for Applicable PathwaysFish ConsumptionDose received as a result of fish consumption is based on the methodology specified in the NMP 1 Off-Site DoseCalculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2014 is calculated fromactual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it isassumed that the most likely exposed Member of the Public consumes fish taken near the site discharge points.No radionuclides were detected in fish samples collected and analyzed during 2014; therefore, no dose wasreceived by the whole body and organs of the likely most exposed Member of the Public during 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11Page 2 of 5Unit 1 Unit 2 X Reporting Period: January- December 2014IDOSES TO MEMBE RS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYVegetation ConsumptionDose received as a result of vegetation consumption is based on the methodology specified in the NMPI ODCM asadapted from Regulatory Guide 1.109. The dose for 2014 is calculated from actual analysis results ofenvironmental vegetation samples taken near the most exposed Member of the Public.No radionuclides were detected in vegetation samples collected and analyzed during 2014; therefore, no dose wasreceived by the whole body and organs of the likely most exposed Member of the Public during 2014.For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified inthe NMP1 ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation isbased on the estimated concentration of C-14 in plant gaseous effluents.Shoreline SedimentDose received from shoreline sediment is based on the methodology in the NMP1 ODCM as adapted fromRegulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Publicspends 67 hour7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months s/year along the shoreline for recreational purposes.No radionuclides were detected in shoreline sediment samples collected and analyzed during 2014; therefore nodose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.Dose Pathways Resulting From Gaseous EffluentsDose received by the likely most exposed Member of the Public due to gaseous effluents is calculated inaccordance with the methodology provided in the NMP 1 ODCM, NMP2 ODCM, and the JAFNPP ODCM. Thesecalculations consider deposition, inhalation and ingestion pathways. The total sum of doses resulting from gaseouseffluents from NMP1, NMP2 and JAFNPP during 2014 provides a total dose to the whole body and maximumorgan dose for this pathway.Carbon-14 Dose Pathways Resulting from Gaseous EffluentsThe Carbon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseouswaste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 innuclear power plant 2014 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production andeffluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation ofCarbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. The following methodology was used inestimating C-14 gaseous release activity and dose components for the 2014 ARERR.EPRI methodology for estimating C-14 production rates in Boiling Water Reactors (BWRs):For BWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows: gaseous95% to 99%, liquid <0.5% and solid 1% to 5%. The report also states that -95% of C-14 in BWR gaseous wasteeffluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in thefood consumption cycle.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11 Page 3 of 5Unit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY IFor NMP1 and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the followingassumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based onthe number of Effective Full Power Days (EFPDs) for the period, (2) maximum C-14 activity from literaturevalues cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for gaseous releases fromliterature values also cited in EPRI Report 1021106.Equation I estimates the maximum annual production of C-14, PRMAx, for each BWR unit.PRMAx = 5.1 v MWT / 1000 [Eq 1]Where:5.1 = BWR Normalized Production (Ci/GWt-yr)MWT = MegaWatts Thermal (MWt)1000 = Conversion Factor (MWt to GWt)Equation 2 estimates the C-14 activity released, A c-14, into the gaseous pathway during the time period for eachBWR unit.A c-14 PR lf4v o 0.99 a EFPD / 365, Ci (for time period) [Eq 2]Where:PR MAt = maximum annual production rate of C-140.99 = fraction of C-14 in BWR gaseous pathway releases (maximumliterature value in EPRI Report 1021106; also Table 1)EFPD number of effective full power days for the unit during the timeperiod; e.g., quarterly or yearly (Table 1)365 number of days in a typical yearNine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11Page 4 of 5Unit 1 Unit 2 X Reporting Period: January- December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARYEquation 3 estimates the C-14 activity released in carbon dioxide form, A c.14. Co2, into the gaseous pathway duringthe time period for each BWR unit.A C-14, C02 = PR m{Y

0.99

0.95 v EFPD / 365, Ci (for time period) [Eq 3]Where:PR MfA = maximum annual production rate of C-140.99 fraction of C-14 in BWR gaseous pathway releases (maximumliterature value in EPRI Report 1021106; also Table 1)0.95 fraction of C-14 as carbon dioxide in BWR gaseous pathwayreleases (typical literature value in EPRI Report 1021106; also Table 1)EFPD number of effective full power days for the unit during the timeperiod, e.g. quarterly or yearly (Table 1)365 conversion factor, 365 days in a typical average yearFor each BWR unit, the 2014 estimated C-14 activity releases (total and carbon dioxide chemical form) aresummarized in Table 1.Table 12014 BWR Estimated C-14 Gaseous ReleasesGaseous C02 Form Max. Annual 2014 Total Release 2014 CO2 ReleaseBWR Release Release EFPD Operation Prod. RateFraction(a) Fraction(b) (Eq I)363 EFPDNMP1 0.99 0.95 (99.4%) 9.44 Ci/yr 9.29 Ci 8.82 Ci318 EFPDNMP2 0.99 0.95 (87.1%) 20.34 Ci/yr(c) 17.54 Ci 16.67 CiJAFNPP 0.99 0.95 282 EFPD 10.84 Ci/yr 8.29 Ci 7.87 Ci(77.3%)(a) Maximum literature values from EPRI Report 1021106.(b) Typical value from EPRI Report 1021106.(c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal.As long as the core designs and power ratings are not significantly changed, the maximum annual production ratesand annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14gaseous release activity and dose components for the ARERR.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 11Page 5 of 5Unit 1 Unit 2 X Reporting Period: January -December 2014DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY IDirect Radiation PathwayDose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from thegenerating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and grounddeposition. This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector inorder to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the localmeteorology. During 2014, the closest residence and the critical downwind residence are at the same location.Table 2Dose Potentially Received by the Likely Most Exposed Member of the PublicOutside the Site Boundary During 2014Exposure Pathway Dose Type Dose (mrem)Fish and Vegetation Total Whole Body No DoseConsumption Total Maximum Organ No DoseTotal Whole Body No DoseShoreline SedimentTotal Skin of Whole Body No DoseTotal Whole Body 9.90 E-04Gaseous Effluents Thyroid 6.21 E-03(excluding C- 14)Maximum Organ Thyroid: 6.21 E-03Gaseous Effluent Total Whole Body 4.41 E-02(C-14) Maximum Organ Bone: 2.20 E-01Direct Radiation Total Whole Body 2.05Based on these values the maximum total annual dose potentially received by the likely most exposed Member ofthe Public during 2014 is as follows:" Total Whole Body: 2.09 E+00 mrem" Total Thyroid: 6.21 E-03 mrem* Maximum Organ: Bone: 2.21 E-01 mrem40 CFR 190 EvaluationThe maximum total doses presented in this attachment are the result of operations at the NMP1, NMP2 and theJAFNPP facilities. The maximum organ dose (Bone: 0.221 mrem), maximum thyroid dose (0.006 mrem) and themaximum whole body dose (2.09 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to themaximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 12Page 1 of IUnit 1 Unit 2 X Reporting Period: January -December 20141 GROUNDWATER PROTECTION PROGRAM TRITIUM RESULTS SUMMARYIWell Identification # Samples # Positive Samples Minimum MaximumNumber Collected Concentration (pCi/I) Concentration (pCi/I)GMX-MWl* 4 0 <404 <493MW-B119* 4 0 <404 <493MW-1 4 0 <404 <493MW-4 4 0 <404 <493MW-6 4 0 <404 <493MW-7 4 0 <404 <493MW-8 4 0 <404 <493MW-9' 4 0 <404 <493MW-101 4 0 <404 <493MW-11 4 0 <404 <493MW-12 4 0 <404 <493MW-13 4 0 <404 <493MW-14* 4 0 <404 <493MW-15 4 0 <404 <493MW-16 4 0 <404 <493MW-17 4 0 <376 <493MW-18 4 0 <404 <493MW-19 4 0 <404 <493MW-20 4 0 <404 <493MW-21 4 0 <404 <493NMP2 MAT 23 4 0 <368 <488Notes:* -Control Location-Sentinel well location2 _ NMP2 Groundwater Depression Cone3 _ Samples collected from storm drain system which includes precipitationNine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 13Page 1 of 1Unit 1 Unit 2 X Reporting Period January -December 2014Off-Site Dose Calculation Manual (ODCM)There was no revision to the Off-Site Dose Calculation Manual for 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015 ATTACHMENT 14Page 1 of 1Unit 1 Unit 2 X Reporting Period January -December 2014Process Control Proaram (PCP)There were no changes to the Process Control Program in 2014.Nine Mile Point Nuclear Station, LLCMay 1, 2015

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