ML18065A185

Rancho Seco - Annual Radioactive Effluent Release Report for 2017

ML18065A185
Person / Time
Site:	Rancho Seco
Issue date:	02/20/2018
From:	Tallman D A Sacramento Municipal Utility District (SMUD)
To:	Cruz Z L Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
DPG 18-037
Download: ML18065A185 (20)

Text

" _ _: .. :~~-~:~=-:~ -.. -=-~ ---~---* <*. :"::;: February 20, 2018 DPG 18-037 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2017 Attention: Zahira Cruz In accordance with 10 CFR 50.36a(a)(2) and Rancho Seco Quality Manual (RSLBD-010), Appendix A, Section 1.5.2.4, we are submitting the Rancho Seco 2017 Annual Radioactive Effluent Release Report for the period of January 1 through December 31, 2017. If you or members of your staff have questions requiring additional information or clarification, please contact me at (916) 732-4893. Sincerely, ~+ Dan A. Tallman Manager, Rancho Seco Assets Enclosure (Rancho Seco NGS Annual Radioactive Effluent Release Report for 2017) Cc: NRG Region IV w/ Enclosure DPG Chron w/ Enclosure RIC 1 F.099 w/ Enclosure RIC 1 L.320 (Report only) Rancho Seco Nuclear Generating Station I 14440 Twin Cities Road I Herald, CA 95638-9799 I 916.452.3211 I smud.org ~Printed on Rccyc!ad Papar _J RANCHO SECO NUCLEAR GENERATING STATION LICENSE NUMBERS DPR-54 and SNM-2510 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2017 TABLE OF CONTENTS INTRODUCTION ........................................................................................................................................... 1 I. SUPPLEMENTAL INFORMATION .................................................................................................. 2 A. Regulatory Limits & Guidelines for Effluent Releases ......................................................... 2 B. Maximum Effluent Concentrations ...................................................................................... 3 C. Measurement Methods for Total Radioactivity .................................................................... 3 D. Batch Releases (via monitored pathways) .......................................................................... 4 E. Unplanned Releases ........................................................................................................... 4 F. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than 30 Days .................................................................................................................................... 4 II. ESTIMATION OF ERROR ............................................................................................................... 5 Ill. GASEOUS EFFLUENTS .................................................................................................................. 6 TABLE Ill-A: GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES .................................. 7 TABLE 111-8: GASEOUS EFFLUENTS -GROUND LEVEL RELEASES ......................................... 7 TABLE 111-C: GASEOUS EFFLUENTS-TYPICAL LOWER LIMITS OF DETECTION ................... 8 TABLE 111-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES .......................................................................................................................... 9 IV. LIQUID EFFLUENTS ...................................................................................................................... 10 TABLE IV-A: LIQUID EFFLUENTS -SUMMATION OF ALL RELEASES ..................................... 11 TABLE IV-8: LIQUID EFFLUENTS ................................................................................................ 12 TABLE IV-C: LIQUID EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTION ....................... 13 TABLE IV-D: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES ........................................................................................................................ 14 V. SOLID WASTE ............................................................................................................................... 15 TABLE V-A: Low-Level Radioactive Waste, Resins, Filters, and Evaporator Bottoms ................. 15 TABLE V-A: Low-Level Radioactive Waste, Dry Active Waste ...................................................... 15 TABLE V-A: Low-Level Radioactive Waste, Irradiated Components ............................................. 16 TABLE V-A: Low-Level Radioactive Waste, Other Waste ............................................................. 16 TABLE V-A: Low-Level Radioactive Waste, Sum of All Low-Level Waste Shipped from Site .................................................................................................................................... 17 ATTACHMENTS None RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 INTRODUCTION Rancho 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 Rancho Seco site was a pressurized water reactor supplied by Babcock and Wilcox. The rated capacity was 913 megawatts 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 on December 8, 1989. Transfer of the spent fuel rod assemblies from the Spent Fuel Pool into dry storage at 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 of the Rancho Seco property, except for the area associated with the Interim Onsite Storage Building (IOSB), from NRC license DPR-54 was approved on September 25, 2009. With the completion of Phase I of decommissioning, the facility was placed in a SAFSTOR-type condition awaiting a suitable disposal option for the low-level radioactive waste in storage in the IOSB. In 2014, the Class B & C radioactive waste stored in the IOSB was shipped to a suitable disposal facility in Texas. Phase II of decommissioning (the IOSB and surrounding area) began in 2015 and was completed in the first quarter of 2017. This Annual Radioactive Effluent Release Report (ARERR) provides a summary of gaseous and liquid effluent releases made from Rancho Seco during the period of January 1, 2017 through December 31, 2017. 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. Radioactive material handing during limited remediation activities associated with the Phase II decommissioning effort, as well as subsequent waste packaging activities were monitored with local air sampling as was the exhaust ventilation system. None of these portable air samples returned activity levels above MDA, eliminating the potential of radioactive material being released from the facility in gaseous effluents. Accordingly, there were no radioactive liquid or gaseous effluent releases made from Rancho Seco during the reporting period. One shipment of solid radioactive waste was made during the reporting period utilizing contract brokerage services This report has been prepared by SMUD to meet the requirements of Rancho Seco Quality Manual (RSQM), Appendix A, Section 1.5.2.4 and Offsite Dose Calculation Manual (ODCM) Revision 23, Step 6.10.1. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. Radiation doses associated with radioactive effluents in liquids and gasses would be calculated for a hypothetical individual who receives the maximum possible exposure at or beyond the applicable Site Boundary, had any releases occurred. Since there were no releases of radioactivity in gaseous and liquid effluents during this report period, the limits of 1 O CFR 20 were not exceeded, nor were the numerical guidelines of 10 CFR 50, Appendix I exceeded. A 40 CFR 190 dose evaluation is not required because radioactive effluent releases did not exceed twice the numerical guidelines of 10 CFR 50, Appendix I. 1 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 I. SUPPLEMENTAL INFORMATION A. Regulatory Limits & Guidelines for Effluent Releases 1. Gaseous Effluents a. Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.9.3): 1500 mrem/year to any organ b. Dose commitment to a member of the public at or beyond the Site Boundary for Gaseous Effluents from Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.9.4, numerical guidelines of 10 CFR 50, Appendix I): 7.5 mrem per calendar quarter to any organ 15 mrem per calendar year to any organ 2. Liquid Effluents a. The concentration of radioactive material in liquid effluents released beyond the Site Boundary for Liquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table 2, Column 2. b. Dose commitment to a member of the public at or beyond the Site Boundary for Liquid Effluents from radioactive materials in liquid effluents shall be limited to (numerical guidelines of 10 CFR 50, Appendix I): 1.5 mrem per calendar quarter to the total body 5 mrem per calendar quarter to any organ 3 mrem per calendar year to the total body 10 mrem per calendar year to any organ NOTE: The noble gas source term was removed when spent fuel transfer to the ISFSI was completed in August 2002. Reference to noble gases was completely removed from the ODCM. 2 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2017 B. Maximum Effluent Concentrations 1. Gaseous Effluents The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 (air) are not directly used in calculations for determining permissible gaseous effluent release rates. The annual dose limits of 1 O CFR 20 for unrestricted areas are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table 2, Column 1. ODCM Technical Requirement dose rate limits (mrem/yr) for gaseous effluents are provided to ensure that the dose rate from gaseous effluents at any time at the Site Boundary for Gaseous Effluents will be within the annual dose limits of 10 CFR 20 for unrestricted areas. These dose rate limits (listed above in part A) are used for determining permissible gaseous effluent release rates. 2. Liquid Effluents The concentration values listed in 10 CFR 20, Appendix B, Table 2, Column 2 are used in calculations to determine permissible liquid discharge flow rates. The most conservative Maximum Effluent Concentration (MEC) value for each radionuclide detected in the liquid effluent sample is used in the calculations. C. Measurement Methods for Total Radioactivity The methods listed below are examples should radioactive effluents be discharged. 1. Gaseous Effluents Liquid Scintillation (H-3) Gamma Spectroscopy (HPGe) Beta Proportional (Sr-90, gross beta) Alpha Proportional (gross alpha) 2. Liquid Effluents Gamma Spectroscopy (HPGe) Liquid Scintillation (H-3) Beta Proportional (Sr-90, gross beta) Alpha Proportional (gross alpha) NOTE: HPGe refers to Hyper-Pure Germanium 3 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 D. Batch Releases (via monitored pathways) Liquid Discharges Quarter 1 Quarter 2 Quarter 3 Number of batch releases 0 0 0 Total time period for batch releases (hours) N/A N/A N/A Maximum time period for a batch release (hours) N/A N/A N/A Average time period for a batch release (hours) N/A N/A N/A Minimum time period for a batch release (hours) N/A N/A N/A Average Plant Effluent Flow (cfs) N/A N/A N/A None E. Unplanned Releases Quarter 4 0 N/A N/A ' N/A N/A N/A This section describes unplanned releases of radioactivity in liquid and gaseous effluent. Gaseous None None F. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than 30 Days None 4 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 II. ESTIMATION OF ERROR The methods for establishing error estimates included review of applicable station procedures, inspection of 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 gaseous effluents, liquid effluents, and solid waste are assumed to be independent, and thus the total error is calculated according to the formula: Total Error = cr/ + a} + a3 2 . . . + cr / where: cri = relative error associated with component i Sources 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, grab sampling, counting, and calibration. Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, dose rate meter reading, computer program dose-to-curie calculation, sample volume measurement, gamma spec counting, gamma spec calibration, and waste volume determination. 5 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2017 Ill. GASEOUS EFFLUENTS Table Ill-A, Gaseous Effluents -Summation of All Releases, provides a detailed summary of gaseous effluent releases per quarter. This table summarizes releases of tritium and particulates with half-lives greater than 8 days. The methodology used to calculate the Percent of ODCM Technical Requirement limit is as follows: L [ ( 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 that category for that quarter (unitless). NOTE: Fi always equals 1.0 for H-3 because it is the only nuclide in the category. (Total Curies per category per quarter { 1 E + O~ µCi) \ C1

• Avg Rel Rate=---------------------~ ( # seconds in the quarter) X/Q = A default dispersion factor determined to be conservative when compared to the use of actual data (sec/m3). Dose Factor = The values derived for each nuclide i from NRC Regulatory Guide 1.109 (Ki, Li+1.1 Mi, or Raij). [Units in (mrem/yr)/(µCi/m3)] Dose Rate Limit = The Technical Requirement (i.e., Regulatory) limits for dose rate listed in Section 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 Ill-A is presented in Section II of this report. Table 111-B, Gaseous Effluents -Ground Level Releases, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data from continuous and batch releases are provided for particulates and tritium. Data reported for batch releases results only from unplanned releases. Table 111-C, Gaseous Effluents -Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in µCi/cc for various radionuclides. Table 111-D, Radiological Impact on Man Due to Gaseous Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Gaseous Effluents (actual doses will be assessed in the 2017 Annual REMP Report). The maximum calculated organ dose is listed for each quarter along with an annual total. The direct radiation dose results, based on monitoring badge dosimetry, are also listed. Presented in this table for each category is a comparison versus ODCM Technical Requirement dose limits with the exception of direct radiation measurements. 6 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 TABLE Ill-A: GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Quarter 3 A. Particulates 1. Particulates with half-lives>8 days Ci O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release Rate for period µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 3. Percent of Tech Req limit % N/A N/A N/A 4. Gross Alpha radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO B. Tritium 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release Rate for period µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 3. Percent of Tech Req limit % N/A N/A N/A TABLE 111-8: GASEOUS EFFLUENTS -GROUND LEVEL RELEASES Nuclides Released 1. Particulates None 2. Tritium None 7 Est. Total Quarter 4 Error,% O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO N/A RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 TABLE 111-C: GASEOUS EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES LLD (µCi/cc) 1. Tritium (H-3) 2.27 E-10 2. Particulates: Manganese-54 2.08 E-12 Cobalt-58 2.29 E-12 lron-59 5.89 E-12 Cobalt-60 3.11 E-12 Strontium-89 2.00 E-15 Strontium-90 5.00 E-15 Cesium-134 1.52 E-12 Cesium-137 1.88 E-12 Barium-140 3.06 E-12 Cerium-141 1.15 E-12 Cerium-144 3.69 E-12 8 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 TABLE 111-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS: 2017 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 YTD A. Tritium, Particulate 1. Maximum Organ Dose mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO N/A 2. Percent Tech Req limit % N/A N/A N/A N/A N/A B. Direct Radiation 1. Dose (Monitoring Badges)1 mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 2. Percent of Tech Req limit % N/A N/A N/A N/A N/A NOTE: No releases of gaseous radioactive effluent were made from Rancho Seco Nuclear Generating Station in 2017. 1 None of the Indicator stations indicate significant radiation attributable to facility operations. 9 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2017 IV. LIQUID EFFLUENTS Table IV-A, Liquid Effluents -Summation of All Releases, provides a detailed summary of liquid effluent releases per quarter. This table summarizes releases of fission and activation products, tritium, dissolved and entrained gases, and gross alpha radioactivity. Also listed is the volume of waste released prior to dilution and the volume of dilution water used during each quarter. The following methodology is used to calculate the Average Diluted Concentration and the Percent of ODCM Technical Requirement Limit in Table IV-A: % Tech Req Limit = f [ Ci ] i MECi where: n Ci = = = The total number of radionuclides identified The average diluted concentration of radionuclide i ( Total Release per Category per Quarter in µCi) (Total Release Volume (part Fin Table IV -A)in ml) The MEC of the i1h radionuclide, from 10 CFR 20, Appendix B, Table 2, The methodology used to calculate the estimated total error in Table IV-A is presented in Section II of this report. Table IV-8, 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 for dissolved and entrained gases. Tritium and gross alpha are not included in this table (they are listed in Table IV-A). Since no continuous releases of liquid radioactive effluent are made from RSNGS, data is provided only for batch

• releases. Table IV-C, Liquid Effluents -Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in µCi/ml for various radionuclides. Table IV-D, Radiological Impact on Man Due To Liquid Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Liquid Effluents (actual doses will be assessed in the 2015 Annual REMP Report). The maximum calculated total body dose and organ dose are listed for each quarter along with an annual total. A comparison versus ODCM Technical Requirement dose limits is also presented. 10 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 TABLE IV-A: LIQUID EFFLUENTS -SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error.% A. Fission & Activation Products 1. Total Release (not including tritium, gases, alpha) Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO N/A 2. Average diluted concentration during period µCi/ml 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 3. Percent of Tech Req limit % N/A N/A N/A N/A B. Tritium 1. Total Release Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO N/A 2. Average diluted concentration during period µCi/ml 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 3. Percent of Tech Req limit % N/A N/A N/A N/A C. Dissolved and Entrained Gases 1. Total Release Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO NIA 2. Average diluted concentration during period µCi/ml 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO D. Gross Alpha radioactivity 1. Total Release Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO N/A E. Volume of Waste Released (prior to dilution) Liters 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO NIA F. Volume of dilution water used during period Liters N/A N/A N/A N/A N/A 11 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2017 Nuclides Released 1. Fission and activation products (excluding tritium. gross alpha} None 2. Dissolved and entrained gases None TABLE IV-B: LIQUID EFFLUENTS NOTE: No releases of liquid radioactive effluent were made from Rancho Seco Nuclear Generating Station in 2017. 12

1. 2. RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 TABLE IV-C: LIQUID EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (µCi/ml) Tritium (H-3) Particulates: 2.60 E-06 Manganese-54 2.11 E-09 lron-59 3.71 E-09 Cobalt-57 2.12 E-09 Cobalt-58 1.93 E-09 Cobalt-60 1.98 E-09 Zinc-65 4.34 E-09 Strontium-90 5.00 E-10 Ruthenium-106 1. 79 E-08 Silver-110m1.94 E-09 Antimony-125 5.78 E-09 Cesium-1341.93 E-09 Cesium-1362.23 E-09 Cesium-1372.30 E-09 Barium-140 7.75 E-09 Cerium-141 3.60 E-09 Cerium-1441.59 E-08 13 A B. L RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 TABLE IV-D: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS: 2017 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 YTD Maximum Total Body Dose mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO Percent Tech Req limit % N/A N/A N/A N/A N/A Maximum Organ Dose mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO Percent Tech Req limit % N/A N/A N/A N/A N/A 14 RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 V. SOLID WASTE A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) Table V-A: Low-Level Waste ; . ,; Resins, Filters/and Volume* Curi~~(.Shipped Evaporator Bottoms Waste Class ft3 m3 . Curies A 0.00 E+OO 0.00 E+OO 0.00 E+OO 8 0.00 E+OO 0.00 E+OO 0.00 E+OO C 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO 0.00 E+OO Major Nuclides for the Above Table: None Dry Active Waste Volume Curies Shipped ;;;:t ¥ ,' ' i'> ;t; ' ' ,, . ' Waste Class ft3 m3 ,, Curies A 3.95 E+02 1.12 E+01 2.19 E-02 8 0.00 E+OO 0.00 E+OO 0.00 E+OO C 0.00 E+OO 0.00 E+OO 0.00 E+OO All 3.95 E+02 1.12 E+01 2.19 E-02 Major Nuclides for the Above Table: Ba-133; H-3 15 '

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 Table V-A: Low-Level Waste (continued) Irradiated Components Volume Curies Shipped ' . 't / **]e ;{';. Oi ic>',> Waste Class J; m3 *::ci:Jries A 0.00 E+OO 0.00 E+OO 0.00 E+OO B 0.00 E+OO 0.00 E+OO 0.00 E+OO C 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO 0.00 E+OO Major Nuclides for the Above Table: None .. ' ' *. Other Waste{ Volume* Curi,e,'s Shipped * ' "<,,_, Waste Class ft3 m3 Curies A 0.00 E+OO 0.00 E+OO 0.00 E+OO B 0.00 E+OO 0.00 E+OO 0.00 E+OO C 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO 0.00 E+OO Major Nuclides for the Above Table: None 16 ,.

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2017 Table V-A: Low-Level Waste (continued) i,; ; Sum of All Low-Level Volume Curies Shipped Waste Shipped from Site Waste Class . tt3 m3 Curies A 3.95 E+02 1.12 E+01 2.19 E-02 B 0.00 E+OO 0.00 E+OO 0.00 E+OO C 0.00 E+OO 0.00 E+OO 0.00 E+OO All 3.95 E+02 1.12 E+01 2.19 E-02 Major Nuclides for the Above Table: Ba-133; H-3 17