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Home My WebLink AboutDRC-2019-001655 - 0901a068809bcff0UTAH DIVISION OF WASTE MANAGEMENT AND RADIATION CONTROL RML # UT1900479 ENERGY FUELS RESOURCES WHITE MESA MILL INSPECTION MODULE EM-01 SEMI-ANNUAL EFFLUENT MONITORING REPORT REPORTING PERIOD: July 1, 2016 through December 31, 2016 References: Utah Administrative Code R313-24-4; 10CFR40.65; Radioactive Materials License UT1900479; 10CFR20 Table II of Appendix B; NRC Regulatory Guide 4.14; 2007 License Renewal Application D Rc - Zo I 9 - 00 1 655 Inspector Russ Topham Date February 5, 2019 10CFR40.65(a)(1) requires the licensee to submit a report within 60 days after January 1 and July 1 of each year. The report must specify the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous six months of operation. 1. Did the licensee submit the report within 60 days of the end of the reporting period i.e., January 1st or July 1st? (10CFR40.65(a)(1)) Yes Z Non Comments: The Semi-Annual Effluent Monitoring Report for the 2nd half of 2016 for the White Mesa Mill was submitted on February 28, 2017 Page 1 of 8 2. Were the stack samples analyzed for U-nat, 230Th, 226Ra and 210Pb? (NRC Reg Guide 4.14) and Th- 228, Th-232 and Ra-228 (L.C. 11.9) Yes A No El Comments: South yellowcake dryer and bag house operated third and fourth quarters only. North yellowcake dryer and bag house not operated during the year. Grizzly operated only during the third quarter. Vanadium dryer and bag house not operated during the year. Stack sampling occurred only during quarters when the stack was operated. 3. Were site boundary effluent air samples analyzed for U-nat, 230Th, 226Ra arid 210Pb? (NRC Reg Guide 4.14) and Th-232 (L.C. 11.9) Yes [El No El 10CFR20 Appendix B Table 2 first paragraph states "The columns in Table 2 of this appendix captioned "Effluents," "Air," and "Water," are applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of sC 20.1302. The concentration values given in Columns 1 and 2 of Table 2 are equivalent to the radionuclide concentrations which, i f inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.05 rem (50 millirem or 0.5 millisieverts)." Comments: Sampling results were below ECLs for all analyzed isotopes at all monitoring locations for the last four quarters, and for the year. See the attached Particulate, Radon and Gamma Screening analysis for a summary of quarterly and annual data and a calculated dose at each of the high-volume air stations. Page 2 of 8 Th, 226•-• 4. Were the site boundary effluent air sample results within applicable limits for U-nat, 230 xa ana 210Pb? (10CFR20 Table II of Appendix B) 10CFR20 Table II of Appendix B. ECL's: U-nat .9.0E" pEi/m1 in air 230Th 2 0E14 liCi/m1 in air 226Ra 9.3E13 laCi/m1 in air 210Pb 6.0E13 µCi/m1 in air Yes E No 111 Comments: 5. Did the results of the effluent monitoring for this reporting period achieve the site's ALARA objective of 25% of the ECL's? (2007 License Renewal Application Vol. 1 Section 6.5; 10CFR20 Table II of Appendix B) 10CFR20 Table II of Appendix B. ECL's: .9.0E14 µCi/m1 in air.....25% = 2.0E14 µCi/m1 in air.....25% 9.3E13 µCi/ml in air.....25% 6.0E13 µCi/m1 in air.....25% = Yes E No 111 Comments: See the attached Particulate, Radon and Gamma Screening analysis for a summary of quarterly and annual data and a calculated dose at each of the high-volume air stations. The summary compares total dose to the mill's ALARA goal and to the annual 100 mrem exposure limit. U-nat 230Th 226Ra 210pb 2.25E14 1.1Ci/m1 in air = 5.15E15 tiCi/m1 in air = 2.33E13 µCi/ml in air 1.50E13 pCi/m1 in air Page 3 of 8 6. Were Gamma Measurements (Minus Background) Collected at each Monitoring Station? Comments: BHV-1 and BHV-5 exceed the gamma limits in 40CFR190 of 25 mrem but were less than the gamma limits in R313-15-301 (10CFR20.1301) of 100 mrem for the general public dose for the last four quarters. BHV-1 and BHV-5 both exceeded the 25 mrem for 2015. Need to monitor to see if they go back down in 2016. See the attached Particulate, Radon and Gamma Screening analysis for a summary of quarterly and annual data and a calculated dose at each of the high-volume air stations. 7. Were soil samples analyzed for U-nat, 226Ra and 210Pb? (NRC Reg Guide 4.14) Yes 0 No Z N/A Ej Comments: Soil sampling occurred during the first half of the year. 8. Were vegetation samples analyzed for 226Ra and 210Pb? (NRC Reg Guide 4.14) and U-Nat and Th- 232 (LC??) Yes 111 No Z Comments: Vegetation sampling occurred during the first half of the year. Page 4 of 8 9. Were radon samples (minus background) taken at Sample Stations BHV-1, BHV-2, BHV-4, BHV- 5, BHV-6, BHV-7 and BHV-8? (NRC Reg Guide 4.14) Yes L No El Comments: ECLs in 10 CFR 20 Appendix B Table 2 assume either no daughters present or 100% ingrowth. Calculated ECLs account for partial ingrowth using methodology in EPA 520/1-88-009 p. 2-20. Calculated ECLs result in maximum exposure of 25 mrem/yr vs. 50 mrem/yr using Table 2 value. Regulatory limit is 100 mrem/yr. See the attached Particulate, Radon and Gamma Screening analysis for a summary of quarterly and annual data and a calculated dose at each of the high-volume air stations. 10. Were radon samples analyzed for 222Rn9 (NRC Reg Guide 4.14) Yes No 0 Comments: 11. Were the 222R11 results within the calculated ECL's for the yearly average results for the last four quarters? Yes Z No El - Comments: See the attached Particulate, Radon and Gamma Screening analysis for a summary of quarterly and annual data and a calculated dose at each of the high-volume air stations. Page 5 of 8 License Condition 11.2.D requires the licensee to utilize lower limits of detection in accordance with Section 5 of the NRC Regulatory Guide 4.14, as amended, for analysis of effluent and environmental samples. 12. Were lower limits of detection (LLD) for analysis of stack effluent samples 10% or less of the limits found in 10CFR20 Table II of Appendix B for U-nat, 230Th, 226Ra and 210pb? (NRC Reg Guide 4.14) 10CFR20 Table II of Appendix B, ECL's: U-nat 9.0E14 tiCi/m1 10% = 9.0E15 uCi/ml 230Th 2.0E14 uCi/m1 10% = 2.0E15 1.1Ci/m1 226Ra 9 3E13 uCi/m1 10% = 9.3E14 µCi/ml 210pb 6.0E13 µCi/m1 10% = 6.0E14 tiCi/m1 Yes [E] No 0 Comments: LLDs in the analytical reports are called CRDL or RLs and they are identical to the numbers listed above. 13. Were lower limits of detection (LLD) for analysis of site boundary air effluents within the limits listed in NRC Regulatory Guide 4.14 Section 5 for U-nat, 230Th, 226Ra and 210Pb? (NRC Reg Guide 4.14) NRC Regulatory Guide 4.14 Section 5 LLD values (in air): 1.0E16 µCi/ml 1 0E16 uCi/m1 1 0E16 uCi/m1 2 0E15 uCi/m1 Yes KA No El Comments: The LLDs from documented in the analytical report are: U-nat 1E-16, Th-230 1E-16; Ra-226 1E-16 ,& Pb-210 2E-15 U-nat 230Th 226Ra 210pb Page 6 of 8 14. Were lower limits of detection (LLD) for analysis of site boundary soil samples within the limits listed in NRC Regulatory Guide 4.14 Section 5 for U-nat, 226Ra and 210pb? NRC Regulatory Guide 4.14 Section 5 LLD values (in soil): U-nat 2 0E7 µCi/g 226Ra 2 0E7 p.Ci/g 210pb 2 0E7 µCi/g Yes Z No 111 N/A 0 Comments: 15. Were lower limits of detection (LLD) for analysis of site boundary vegetation samples within the limits listed in NRC Regulatory Guide 4.14 Section 5 for 226Ra and 210pb? NRC Rqgulatory Guide 4.14 Section 5 LLD values (in vegetation): U-nat 2.0E7 tiCi/kg 226Ra 5 0E8 tiCi/kg 210pb 1 0E6 ',Xi/kg Yes 1E] No Z Comments: Page 7 of 8 7-77 /(,' (Date) i 2/7/6 I (Date) Reviewed By: Phil Goble Russ Topham Prepared By: (Print Name) (Signature) 13. Were lower limits of detection (LLD) for analysis of radon samples within the limits listed in NRC Regulatory Guide 4.14 Section 5 for 222Rn9 NRC Regulatory Guide 4.14 Section 5 LLD values for radon: 222Rn 2 OEI° j.tCilml (0.2pCi/L) Yes El No El Comments: White Mesa Environmental Protection Manual Section 1.4, STACK EMMISIONS MONITORING PROCEDURES, sub-section 1.0, INTRODUCTION, states, "These sampling methods are also consistent with guidance contained in the U.S. Nuclear Regulatory Commission's Regulatory Guide 4.14, "Radiological Effluent and Environmental Monitoring at Uranium Mills." 14. Were the yellowcake dryer and packaging stacks sampled in accordance with Regulatory Guide 4.14 Section 2.1.1? Quarterly samples at North Yellowcake Dryer and Yellowcake Baghouse for: U-nat Semi-annual samples at North Yellowcake Dryer and Yellowcake Baghouse for: 230Th 226Ra 210pb Yes El No 11] Comments: Stack sampling occurred during the first and third quarters only. The mill did not process ore during the 2nd and 4u' quarters of 2016. Page 8 of 8 Year Endin 31-Dec-16 PARTICULATE, RADON AND GAMMA SCREENING Quarter Ending Analysis of Annual Dose Constituent Location 31-Mar-16 30-Jun-16 30-Sep-16 31-Dec-16 Annual ECL Below ECL? mrem/yr L_ Ra di o a c tiv e P a r tic u la te s U NAT (pCi/mL) BHV-1 2 0E-16 .1E 1.1E- 5 9 E 16 8.5E-16 9.00E-14 Yes 0.47 BHV-2 7 0E-16 2.0E-16 4.2E-16 4.1E-16 4.3E-16 9.00E-14 Yes 0.24 BHV-4 5.0E 16 2.9E-15 6.2E-15 4.1E-15 3.4E-15 9.00E- 4 Yes 1.90 BHV-5 1 4E-15 3. E-15 7 1E-15 5.1E-15 4.4E-15 9.00E-14 Yes 2.43 BHV-6 7.0E-16 1,2E-14 6.9E-15 8,9E-15 7.1E-15 9.00E-14 Yes 3.96 BHV-7 8,0E-16 2.6E-15 1.6E-15 1.6E-15 9.00E-14 Yes 0 90 BHV-8 2.0E-16 1.1E-15 1.2E-15 1.2E-15 9.3E- 6 9 00E-14 Yes 0.51 230Th (pCilmL) BHV-1 3.0E-17 7.0E-17 8.7E-17 7.8E-17 6 6E-17 2.00E- 4 Yes 0.17 BHV-2 6.0E-18 3.0E-17 6.9E-17 1.9E-17 3,1E-17 2 00E 14 Yes 0.08 2.0E-17 5.0E-17 4.4E-16 3.0E-16 2.0E-16 2,00E-14 Yes 0 51 6.0E-16 4.0E-16 7.6E-16 6.6E-16 6.1E-16 2.00E-14 Yes 1.51 tšjJ 1.0E-16 1.0E-16 4.0E-16 3,3E-16 2.3E-16 2.00E-14 Yes 0.58 1.0E-16 9,0E-17 1.7E-16 1.2E-16 1.2E-16 2.00E-14 Yes 0.30 BHV-8 2.0E-17 1.0E-16 8.4E-17 6.0E-17 6.6E-17 2.00E-14 Yes 0.17 226Ra (pCi/mL) BHV-1 3,0E-16 9.0E-16 1.8E-16 1.3E-16 3,8E-16 9.00E-13 Yes 0.02 BHV-2 8.0E-17 3.0E-16 8.1E-17 5.0E-17 1.3E-16 9.00E-13 Yes 0.01 BHV-4 5.0E-17 4.0E-16 2.2E-15 4.8E-16 7.8E-16 9.00E-13 Yes 0.04 BHV-5 6.2E-15 6.0E-16 9.6E-16 2.2E-15 9.00E-13 Yes 0.12 BHV-6 9.0E-16 6.0E-15 7.2E-16 4.8E-16 2.0E-15 9.00E-13 Yes 0 11 BHV-7 1.0E-15 9.0E-16 4.1E-16 2.5E-16 6.4E-16 9.00E-13 Yes 0 04 BHV-8 3.0E-16 1,9E-15 3.3E-16 8.5E-17 6.5E-16 9.00E-13 Yes 0.04 210pb (pCi/mL) BHV-1 1,4E-14 9.6E-15 1.2E-14 2.2E-14 1.4E-14 6.00E-13 Yes 1.20 BHV-2 1.5E-14 1.3E-14 1.0E-14 2.1E-14 1.5E-14 6.00E-13 Yes 1.23 BHV-4 1.7E-14 8.8E-15 3.4E-16 .2.2E-14 1.2E-14 6.00E-13 Yes 1 00 BHV-5 2.3E-14 2.9E-16 1.5E-14 6.00E-13 Yes 1.24 BHV-6 1.7E-14 IIIEMEMIIIIBE{gM 2.1E-14 1.6E-14 6.00E-13 Yes 1.30 BHV-7 1.7E-14 1.5E-14 2.8E-15 1.5E-14 1.2E-14 6.00E-13 Yes 1.04 BHV-8 1.6E-14 1.1E-14 7.6E-15 1.4E-14 1.2E-14 6.00E-13 Yes 1 01 222Th (pCi/mL) BHV-1 2.0E-18 3,0E-18 9.5E-18 4.8E-18 4.8E-18 4.00E-15 Yes 0.06 BHV-2 4.0E-18 4.0E-18 5.2E-17 2.2E-18 1.6E-17 4.00E-15 Yes 0.19 BHV-4 2.0E-18 5.0E-18 7.1E-18 4,5E-18 4.7E-18 4.00E-15 Yes 0.06 BHV-5 6,0E-17 3.0E-18 3.0E-17 1.3E-17 2.7E-17 4.00E-15 Yes 0.33 BHV-6 1.0E-17 4.0E-18 9.5E-18 8.9E-18 4.00E-15 Yes 0.11 BHV-7 5.0E-18 3,0E-18 4,6E-18 4.00E-15 Yes 0 06 BHV-8 2.0E-18 2 OE 8 4.7E 8 2E 18 3.0E-18 4 00E- 5 Yes 0.04 IDi r e c t R a dia tio n v (mrem) BHV-1 5.7E+00 3 3E+00 5 0E+00 4 0E+00 1 8E+01 1.00E+02 Yes 18.00 jY 0.0E+00 1.9E+00 1.8E+00 4.8E+00 8.5E+00 1.00E+02 Yes 8.50 0.0E+00 0.0E+00 0.0E+00 1.2E+00 1.2E+00 1.00E+02 Yes 1.20 BHV-5 3.9E+00 2.4E+00 0.0E+00 2.1E+00 8.4E+00 1.00E+02 Yes 8.40 BHV-6 1.0E+00 0 0E+00 0 0E+00 4.0E-01 1 4E+00 1.00E+02 Yes 1.40 BHV-7 0.0E+00 0.0E+00 0.0E+00 4.3E+00 4.3E+00 1 00E+02 Yes 4.30 BHV-8 0.0E+00 1.0E+00 8.0E-01 1.8E+00 3.6E+00 1.00E+02 Yes 3:66 I Ra do n- 22 2 222Rn (pCi/L) BHV-1 5 4E+01 4.5E+01 4.7E+01 3.8E+01 4.6E+01 7.10E-02 Yes 0 10 BHV-2 4.8E+01 4.2E+01 4.2E+01 3.4E+01 4.1E+01 3 40E-01 Yes 0.03 HV-4 4 9E+01 3.7E+01 4.0E+01 3.5E+01 4.0E+01 5.00E-01 Yes 0.17 BHV 5 4.6E+01 4.3E+01 4.2E+01 3.6E+01 4 2E+01 1.43E+00 Yes 0.06 BHV-6 0.0E+00 1.9E+00 1.8E+00 4 8E+00 2.1E+00 8.30E-01 Yes 0.03 BHV-7 3.9E+00 2 4E+00 0 0E+00 2 1E+00 2.1E+00 1.12E+00 Yes 0 02 BHV-8 0.0E+00 0.0E+00 0.0E+00 4.3E+00 1.1E+00 7.10E-01 No 37 85 L'• g g (J) Estimated Dose Location Dose ALARA Goal ALARA Goal Met? Exposure Limit Compliant? Yes and BHV-1 20.01 25 Yes 100 Comparison BHV-2 10.28 25 Yes 100 Yes to BHV-4 4 88 25 Yes 100 Yes Screening BHV-5 14 09 25 Yes 100 Yes Values BHV-6 7.49 25 Yes 100 Yes (mrem/yr) BHV-7 6.65 25 Yes 100 Yes BHV-8 43.22 25 No 100 Yes o es: egu a ory Iimit is 100 mrem yr. Energy Fuels ALARA goal is not to maintain exposures below 25 mrem/yr ECLs are based on 50 mrem/yr except radon which uses 25 mrem/yr. ECLs for radon were calculated using distance and wind speed from assumed stack source to BHV stations. Calculated ECLs provide inclusion of ingrowth of daughters Annual values reflect averaging dose rates for the four quarters, except for gamma, which is the sum of four quarterly values.