ML15093A059

Annual Radioactive Effluent Release Report for 2014

ML15093A059
Person / Time
Site:	Rancho Seco
Issue date:	03/23/2015
From:	Ronningen E T Sacramento Municipal Utility District (SMUD)
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
DPG 15-073
Download: ML15093A059 (22)

Text

Powering forward. Together.*SMUD7DPG 15-073March 23, 2015U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555Docket No. 50-312Rancho Seco Nuclear Generating StationLicense No. DPR-54ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2014Attention: Jack ParrottIn accordance with 10 CFR 50.36a(a)(2) and Rancho Seco Quality Manual (RSLBD-010), Appendix A, Section 1.5.3, we are submitting the Rancho Seco 2014 AnnualRadioactive Effluent Release Report for the period of January 1 through December 31,2014.If you or members of your staff have questions requiring additional information orclarification, please contact me at (916) 732-4817.Sincerely,Einar T. RonningenSuperintendent, Rancho Seco Assetscc with attachment: NRC, Region IV

Attachment:

Rancho Seco Annual Radioactive Effluent Release Report for 2014Rancho Seco Nuclear Generating Station 114440 Twin Cities Road I Herald, CA 95638-9799 1 1.209.333.2935 I smud.org 4 ~RANCHO SECONUCLEAR GENERATING STATIONLICENSE NUMBERS DPR-54 and SNM-2510ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE OF CONTENTSIN T R O D U C T IO N ........................................................................................................................................... 1I. SUPPLEMENTAL INFORMATION ............................................................................................ 2A. Regulatory Limits & Guidelines for Effluent Releases .......................................... 2B. Maximum Effluent Concentrations ........................................................................ 3C. Measurement Methods for Total Radioactivity ...................................................... 3D. Batch Releases (via monitored pathways) ............................................................. 4E .U nplanned R eleases ............................................................................................... 5F. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than3 0 D a y s ....................................................................................................................... 5II. ESTIMATION OF ERROR ...................................................................................................... 6III. GASEOUS EFFLUENTS ......................................................................................................... 7TABLE Ill-A: GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES ............................. 8TABLE Ill-B: GASEOUS EFFLUENTS -GROUND LEVEL RELEASES .................................... 9TABLE Ill-C: GASEOUS EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTION ............. 10TABLE III-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENTR E L E A S E S ............................................................................................................... 11IV .LIQ U ID E F F LU E N T S ...................................................................................................................... 12TABLE IV-A: LIQUID EFFLUENTS -SUMMATION OF ALL RELEASES ................................. 13TABLE IV-B: LIQUID EFFLUENTS .......................................................................................... 14TABLE IV-C: LIQUID EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTION ................... 15TABLE IV-D: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENTR E L E A S E S ............................................................................................................... 16V .S O LID W A S T E ............................................................................................................................... 17ATTACHMENTSNonei RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014INTRODUCTIONRancho Seco Nuclear Generating Station (RSNGS) Unit No. 1 is located in Sacramento County,California approximately 25 miles southeast of Sacramento and 26 miles north-northeast of Stockton.Rancho Seco Unit No. 1 began commercial operation on April 17, 1975. The single unit on the RanchoSeco site was a pressurized water reactor supplied by Babcock and Wilcox. The rated capacity was 913megawatts electrical. Because of a public vote on June 6, 1989, Sacramento Municipal Utility District(SMUD) shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations onDecember 8, 1989. Transfer of the spent fuel rod assemblies from the Spent Fuel Pool into dry storageat the Independent Spent Fuel Storage Installation (ISFSI) was completed on August 21, 2002.Radiological dismantlement of the nuclear facility was completed in December 2008 and the release ofthe Rancho Seco property, except for the area associated with the Interim Onsite Storage Installation(IOSB), from NRC license DPR-54 was approved on September 25, 2009. With the completion of PhaseI of decommissioning, the facility is in a SAFSTOR-type condition awaiting a suitable disposal option forthe low-level radioactive waste (LLRW) in storage in the IOSB. While in the SAFSTOR condition, theLLRW disposal facility in Andrews, TX became available and was deemed suitable by SMUD. During thereporting period, Phase II of decommissioning began when the inventory of LLRW previously storedonsite was shipped to that facility for disposal.This Annual Radioactive Effluent Release Report (ARERR) provides a summary of gaseous and liquideffluent releases made from Rancho Seco during the period of January 1 through December 31, 2014.This report also provides a summary of solid radioactive waste shipments during the reporting period.In the current condition, there are no radioactive liquids or liquid systems at the facility, and the remaininginventory of solid material is small and consists of some building surface contamination within the IOSB.The previously stored materials shipped during the reporting period had been packaged for disposal priorplacement into storage, and there was no need to process or otherwise handle the LLRW material prior toshipment off site. Accordingly, there were no radioactive liquid or gaseous effluent releases made fromRancho Seco during the reporting period. Any future decommissioning activities that present a potentialfor release of particulate material in gaseous effluents will be evaluated.This report has been prepared by SMUD to meet the requirements of Rancho Seco Quality Manual(RSQM), Appendix A, Section 1.5.3 and Offsite Dose Calculation Manual (ODCM) Revision 23, Step6.12. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. Radiation dosesassociated with radioactive effluents in liquids and gasses would be calculated for a hypotheticalindividual who receives the maximum possible exposure at or beyond the applicable Site Boundary, hadany releases occurred.Since there were no releases of radioactivity in gaseous and liquid effluents during this report period, thelimits of 10 CFR 20 were not exceeded, nor were the numerical guidelines of 10 CFR 50, Appendix Iexceeded. A 40 CFR 190 dose evaluation is not required because radioactive effluent releases did notexceed twice the numerical guidelines of 10 CFR 50, Appendix I.1 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014SUPPLEMENTAL INFORMATIONA. Regulatory Limits & Guidelines for Effluent Releases1. Gaseous Effluentsa. Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for Tritium andradioactive material in particulate form with half-lives greater than 8 days (ODCMTechnical Requirement 6.9.3):1500 mrem/year to any organb. Dose commitment to a member of the public at or beyond the Site Boundary for GaseousEffluents from Tritium and radioactive material in particulate form with half-lives greaterthan 8 days (ODCM Technical Requirement 6.9.4, numerical guidelines of 10 CFR 50,Appendix I):7.5 mrem per calendar quarter to any organ15 mrem per calendar year to any organ2. Liquid Effluentsa. The concentration of radioactive material in liquid effluents released beyond the SiteBoundary for Liquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table2, Column 2.b. Dose commitment to a member of the public at or beyond the Site Boundary for LiquidEffluents from radioactive materials in liquid effluents shall be limited to (numericalguidelines of 10 CFR 50, Appendix I):1.55310mrem per calendar quarter to the total bodymrem per calendar quarter to any organmrem per calendar year to the total bodymrem per calendar year to any organNOTE: The noble gas source term was removed when spent fuel transfer to the ISFSI wascompleted in August 2002. Reference to noble gases was completely removed from theODCM.2 4'RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014B. Maximum Effluent Concentrations1. Gaseous EffluentsThe concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 (air) are notdirectly used in calculations for determining permissible gaseous effluent release rates.The annual dose limits of 10 CFR 20 for unrestricted areas are the doses associated withthe concentrations of 10 CFR 20, Appendix B, Table 2, Column 1. ODCM TechnicalRequirement dose rate limits (mrem/yr) for gaseous effluents are provided to ensure thatthe dose rate from gaseous effluents at any time at the Site Boundary for GaseousEffluents will be within the annual dose limits of 10 CFR 20 for unrestricted areas. Thesedose rate limits (listed above in part A) are used for determining permissible gaseouseffluent release rates.2. Liquid EffluentsThe concentration values listed in 10 CFR 20, Appendix B, Table 2, Column 2 are used incalculations to determine permissible liquid discharge flow rates. The most conservativeMaximum Effluent Concentration (MEC) value for each radionuclide detected in the liquideffluent sample is used in the calculations.C. Measurement Methods for Total RadioactivityThe methods listed below are examples should radioactive effluents be discharged.1. Gaseous EffluentsLiquid Scintillation (H-3)Gamma Spectroscopy (HPGe)Beta Proportional (Sr-90, gross beta)Alpha Proportional (gross alpha)2. Liquid EffluentsGamma Spectroscopy (HPGe)Liquid Scintillation (H-3)Beta Proportional (Sr-90, gross beta)Alpha Proportional (gross alpha)NOTE: HPGe refers to Hyper-Pure Germanium3 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014D. Batch Releases (via monitored pathways)Liquid Discharges Quarter 1 Quarter 2 Quarter 3 Quarter 4a. Number of batch releases 0 0 0 0b. Total time period for batchreleases (hours) N/A N/A N/A N/Ac. Maximum time period for abatch release (hours) N/A N/A N/A N/Ad. Average time period for abatch release (hours) N/A N/A N/A N/Ae. Minimum time period for abatch release (hours) N/A N/A N/A N/Af. Average Plant Effluent Flow(cfs) N/A N/A N/A N/A4 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014E. Unplanned ReleasesThis section describes unplanned releases of radioactivity in liquid and gaseous effluent.GaseousNoneNoneF. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than 30 DaysNone5 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014I1. ESTIMATION OF ERRORThe methods for establishing error estimates included review of applicable station procedures, inspectionof sampling equipment, engineering estimates, statistical applications, review of calibration setpoint data,and communication with plant personnel. The various sources of error (s) in reported values of gaseouseffluents, liquid effluents, and solid waste are assumed to be independent, and thus the total error iscalculated according to the formula:/ 2 2 2 2Total Error = + C"2 + (3 + +where: ci = relative error associated with component iSources of error for gaseous effluents include fan error (flow), grab sampling, collection, filter efficiency,counting, and calibration.Sources of error for liquid effluents include collection container volume, dilution water flow rate, grabsampling, counting, and calibration.Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, dose ratemeter reading, computer program dose-to-curie calculation, sample volume measurement, gamma speccounting, gamma spec calibration, and waste volume determination.6 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014II1. GASEOUS EFFLUENTSTable Ill-A, Gaseous Effluents -Summation of All Releases, provides a detailed summary of gaseouseffluent releases per quarter. This table summarizes releases of tritium and particulates with half-livesgreater than 8 days. The methodology used to calculate the Percent of ODCM Technical Requirementlimit is as follows:Z [(Fi)(Avg Rel Rate)(X / Q)(Dose Factor)]% Tech Req Limit =(Dose Rate Limit) X 100%where:Fi = The fraction of the total number of Curies of nuclide i out of the total curies in thatcategory for that quarter (unitless).NOTE: Fj always equals 1.0 for H-3 because it is the only nuclide in the category.(Total Curies per category per quarterQI E + 06 CpCiAvg Rel Rate = C(# seconds in the quarter)X/Q = A default dispersion factor determined to be conservative when compared to the use ofactual data (sec/m3).Dose Factor = The values derived for each nuclide i from NRC Regulatory Guide 1.109 (Ki,Li+1.lMi, or Raij). [Units in (mrem/yr)/(pCi/m3)]Dose Rate Limit = The Technical Requirement (i.e., Regulatory) limits for dose rate listed inSection I of this report (mrem/yr).NOTE: Particulates with half-lives less than 8 days are not included in this calculation.The methodology used to calculate the Estimated Total Error (%) in Table III-A is presented in Section IIof this report.Table Ill-B, Gaseous Effluents -Ground Level Releases, provides a complete quarterly summary of theamount of radioactivity (Ci) released per radionuclide in each quarter. Data from continuous and batchreleases are provided for particulates and tritium. Data reported for batch releases results only fromunplanned releases.Table Ill-C, Gaseous Effluents -Typical Lower Limits of Detection, provides a listing of the typical lowerlimit of detection (LLD) concentrations in pCi/cc for various radionuclides.Table Ill-D, Radiological Impact on Man Due to Gaseous Effluent Releases, provides a summary ofcalculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundaryfor Gaseous Effluents (actual doses will be assessed in the 2014 Annual REMP Report). The maximumcalculated organ dose is listed for each quarter along with an annual total. The direct radiation doseresults, based on monitoring badge dosimetry, are also listed. Presented in this table for each category isa comparison versus ODCM Technical Requirement dose limits with the exception of direct radiationmeasurements.7 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE Ill-A: GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASESEst. TotalUnit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error, %A. Particulates1. Particulates with half-lives>8 days Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 N/A2. Average Release Rate for period pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+003. Percent of Tech Req limit % N/A N/A N/A N/A4. Gross Alpha radioactivity Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00B. Tritium1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 N/A2. Average Release Rate for period pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+003. Percent of Tech Req limit % N/A N/A N/A N/A8 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE Ill-B: GASEOUS EFFLUENTS -GROUND LEVEL RELEASESNuclides Released1. ParticulatesNone2. TritiumNone9 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE Ill-C: GASEOUS EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTIONRADIONUCLIDES LLD (wCi/cc)1. Tritium (H-3) 2.27 E-102. Particulates:Manganese-54 2.08 E-12Cobalt-58 2.29 E-12Iron-59 5.89 E-12Cobalt-60 3.11 E-12Strontium-89 2.00 E-15Strontium-90 5.00 E-15Cesium-134 1.52 E-12Cesium-137 1.88 E-12Barium-140 3.06 E-12Cerium-141 1.15 E-12Cerium-144 3.69 E-1210 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE III-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASESCALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:2014Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 AnnualA.1.2.B.1.2.Tritium, ParticulateMaximum Organ DosePercent Tech Req limitDirect RadiationDose (Monitoring Badges)1Percent of Tech Req limitmremmrem0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/A0.00 E+00N/ANOTE: No releases of gaseous radioactive effluent were made from Rancho Seco Nuclear GeneratingStation in 2014.None of the Indicator stations indicate significant radiation attributable to facility operations.11 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014IV. LIQUID EFFLUENTSTable IV-A, Liquid Effluents -Summation of All Releases, provides a detailed summary of liquid effluentreleases per quarter. This table summarizes releases of fission and activation products, tritium, dissolvedand entrained gases, and gross alpha radioactivity. Also listed is the volume of waste released prior todilution and the volume of dilution water used during each quarter.The following methodology is used to calculate the Average Diluted Concentration and the Percent ofODCM Technical Requirement Limit in Table IV-A:% Tech Req Limit = where: n = The total number of radionuclides identifiedC1 = The average diluted concentration of radionuclide i(Total Release per Category per Quarter in/pCi)(Total Release Volume (part F in Table IV -A) in ml)MECj = The MEC of the ith radionuclide, from 10 CFR 20, Appendix B, Table 2, Column 2The methodology used to calculate the estimated total error in Table IV-A is presented in Section II of thisreport.Table IV-B, Liquid Effluents, provides a complete quarterly summary of the amount of radioactivity (Ci)released per radionuclide in each quarter. Data is provided for fission and activation products, and fordissolved and entrained gases. Tritium and gross alpha are not included in this table (they are listed inTable IV-A). Since no continuous releases of liquid radioactive effluent are made from RSNGS, data isprovided only for batch releases.Table IV-C, Liquid Effluents -Typical Lower Limits of Detection, provides a listing of the typical lower limitof detection (LLD) concentrations in pCi/ml for various radionuclides.Table IV-D, Radiological Impact on Man Due To Liquid Effluent Releases, provides a summary ofcalculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundaryfor Liquid Effluents (actual doses will be assessed in the 2014 Annual REMP Report). The maximumcalculated total body dose and organ dose are listed for each quarter along with an annual total. Acomparison versus ODCM Technical Requirement dose limits is also presented.12 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE IV-A: LIQUID EFFLUENTS -SUMMATION OF ALL RELEASESEst. TotalUnit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error %A. Fission & Activation Products1. Total Release (not including tritium, gases, alpha) Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A2. Average diluted concentration during period pCi/ml 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+003. Percent of Tech Req limit % N/A N/A N/A N/AB. Tritium1. Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A2. Average diluted concentration during period pCi/ml 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+003. Percent of Tech Req limit % N/A N/A N/A N/AC. Dissolved and Entrained Gases1. Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A2. Average diluted concentration during period pCi/ml 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00D. Gross Alpha radioactivity1. Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/AE. Volume of Waste Released (prior to dilution) Liters 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/AF. Volume of dilution water used during period Liters N/A N/A N/A N/A N/A13

'SRSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE IV-B: LIQUID EFFLUENTSNuclides Released1. Fission and activation products(excluding tritium, gross alpha)None2. Dissolved and entrained gasesNoneNOTE: No releases of liquid radioactive effluent were made from Rancho Seco Nuclear GeneratingStation in 2014.14 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE IV-C: LIQUID EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTIONRADIONUCLIDES BATCH MODE: LLD (uCi/mI)1 Tritium (H-3) 2.60 E-062. Particulates:Manganese-54 2.11 E-09Iron-59 3.71 E-09Cobalt-57 2.12 E-09Cobalt-58 1.93 E-09Cobalt-60 1.98 E-09Zinc-65 4.34 E-09Strontium-90 5.00 E-10Ruthenium-106 1.79 E-08Silver-11Om 1.94 E-09Antimony-125 5.78 E-09Cesium-1 34 1.93 E-09Cesium-1 36 2.23 E-09Cesium-1 37 2.30 E-09Barium-140 7.75 E-09Cerium-141 3.60 E-09Cerium-144 1.59 E-0815 d 'l"RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014TABLE IV-D: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASESCALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:2014Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 AnnualA. Maximum Total Body Dose mrem 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00Percent Tech Req limit % N/A N/A N/A N/A N/AB. Maximum Organ Dose mrem 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00Percent Tech Req limit % N/A N/A N/A N/A N/A16 r RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 2014V. SOLID WASTEA. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)1. Type of Waste:Volume Total Est. Total(M3) Activity Error (%)(Curies)A. Spent Resins, filter sludges, 3.745E+01 1.68 E+02 N/Aevaporator bottoms, etc.B. Dry compressible waste, 0.00 E+00 0.00 E+00 N/Acontaminated equipment, etcC. Irradiated components, 7.86 E+01 1.0 E+04 N/Acontrol rods, etc.D. Other (primary metals, 0.00 E+00 0.00 E+00 N/Avalves, piping)2. Estimate of major nuclide composition Category A and Category B wasteCategory A Category BActivity Percentage Activity PercentageRadionuclide (Ci) (%) (Ci) (%)Am-241 2.84E-02 1.69E-02 NONEC-14 2.21 E+00 1.31E+00Cm-242 2.63E-10 1.56E-10Cm-244 3.58E-03 2.13E-03Co-60 2.72E+00 1.62E+00Cs-i 34 9.42E-02 5.59E-02Cs-137 1.03E+02 6.14E+01Fe-55 4.07E-01 2.42E-01H-3 1.38E-02 8.18E-03Nb-94 1.04E-02 6.15E-03Ni-63 5.85E+01 3.47E+01Pu-238 1.37E-02 8.11 E-03Pu-239 1.29E-02 7.69E-03Pu-241 3.56E-01 2.11 E-01Sr-90 6.41E-01 3.81E-01Tc-99 1.34E-02 7.95E-0317 I.,RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 20143. Estimate of major nuclide composition Category C and Category D wasteCategory CRadionuclideAm-241C-14Cm-242Cm-244Co-60Cs-137Fe-55Mn-54Nb-94Ni-59Ni-63Pu-238Pu-239Pu-241Sr-90Tc-99Zn-65Activity(Ci)2.14E-021.17E+018.67E-121.94E-033.02E+033.39E-031.74E+021.75E-051.85E-017.22E+016.76E+033.88E-033.61 E-037.62E-021.33E-027.47E-051.94E-09Percentage(%)2.13E-041.17E-018.64E-141.93E-053.01E+013.38E-051.73E+001.74E-071.84E-037.20E-016.74E+013.87E-053.60E-057.59E-041.33E-047.44E-071.94 E-11Activity(Ci)NONECategory DPercentage(%)18 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJANUARY -DECEMBER 20144. Solid Waste DispositionMode ofNumber of Shipments Transportation DestinationWaste Control Specialists LLC23 Highway Compact Waste FacilityAndrews, TX5. Type of Containera. All Shipments were Cask Shipments6. Solidification Agenta. NoneB. IRRADIATED FUEL SHIPMENTS (Disposition)Number of ShipmentsNone19