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Home My WebLink AboutDRC-2019-005411 - 0901a06880a7186fUTAH DIVISION OF WASTE MANAGEMENT AND RADIATION CONTROL RML # UT1900479 ENERGY FUELS RESOURCES WHI1E MESA MILL INSPECTION MODULE EM-01 SEMI-ANNUAL EFFLUENT MONITORING REPORT REPORTING PERIOD: January 1, 2018 through June 30, 2018 ,DRC-201,-0054 References: Utah Administrative Code R313-24-4; 10CFR40.65; Radioactive Materials License UT1900479, Amendments 7 and 8; 10CFR20 Table II of Appendix B; NRC Regulatory Guide 4.14; 2007 License Renewal Application Inspector Heather Mickel son Date May 23, 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 No 111 Comments: The Semi-Annual Effluent Monitoring Report for the 1st half of 2018 for the White Mesa Uranium Mill was dated August 29, 2018 and was received by the DWMRC on August 31, 2018. 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 (RML UT 1900479 Amendment 7 L.C. 11.9) Yes Z No fl Comments: Stack sampling occurred only during the quarters when the stack operated. The South Yellowcake Dryer and the Yellowcake Packaging Baghouse operated in the 2na quarter of 2018 and both were sampled during the second quarter. The Grizzly Baghouse operated sporadically during the first half of 2018. Its operation was limited to a few hours when the mill was processing Sequoyah Fuels materials. This limited operation did not allow the mill to perform a stack test on the Grizzly Baghouse. The North Yellowcake Dryer, Vanadium Dryer, and Vanadium Baghouse were not operated during the first half of 2018 and the radioisotopes in their effluents were not evaluated. Page 1 of 7 3. Were site boundary effluent air samples analyzed for U-nat, 23°Th, 226Ra and 210Pb? (NRC Reg Guide 4.14) and Th-232 (RML UT 1900479 Amendment 7 L.C. 11.9) Yes El No LiJ Comments: The airborne radionuclide concentrations were obtained from locations to the North (BHV-1, BHV-2, and BHV-8), East (BHV-5 and BHV-7), and South (BHV-4). BHV-1 and BHV-8 serve as surrogates for the nearest residents. BHV-6 measures the impacts to the White Mesa Ute community, which is south of the mill. 4. Were the site boundary effluent air sample results within applicable limits for U-nat, 226Ra and 210Pb? (10CFR20 Table II of Appendix B) 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 § 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)." Radioisotope Effluent Concentration Limit (pCi/m1 in air) U-nat 9E-14 232Th 4E15 230Th 2E14 226Ra 9E13 210pb 6E13 Yes El No Comments: The quarterly measured dose and the calculated annual dose for the measured radioactive particulates (Unat, 230Th, 226Ra, 210pb, and 232,,, h) for this quarterly sampling event and the three preceding sampling events are below the ECLs. A summary of the calculated doses is attached. Page 2 of 7 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) Radioisotope ALARA Limit (tiCi/m1 in air) ALARA Limit (mrem) U-nat 2E14 25 232Th 1E15 25 230Th 5E-15 25 13 226Ra 2E 25 210pb 2E-13 25 Yes Z Comments: The quarterly measured dose and the calculated annual dose for the measured radioactive particulates 2307h, 226Ra, 210pb d 232r (Unat, , an n) A summary of the calculated doses is attached. The estimated dose from the combined radioisotopes (particulates, gamma, and 222) at each high- volume air station is listed in the attached table. The largest estimated dose was measured at BHV-1 at 12.28 mrem/yr, which is less than the ALARA goal of 25 mrem/yr. 6. Were Gamma Measurements (Minus Background) Collected at each Monitoring Station? Yes Z No I=) Comments: Gamma measurements for BHV-1, BHV-2, BHV-4, BHV-5, BHV-6, BHV-7, and BHV-8 were less than the ECL. The largest gamma measurement was at BHV-1 with a dose of 10.20 mrem/yr. 7. Were soil samples analyzed for U-nat, 226Ra and 210Pb? (NRC Reg Guide 4.14) Yes ID No 111 N/A Comments: Soil samples were not collected for this effluent report. Soil samples will be collected with the July to December 2018 effluent report. Page 3 of 7 8. Were vegetation samples analyzed for 226Ra and 210Pb? (NRC Reg Guide 4.14) and U-Nat and Th-232? Yes Z No III Comments: Two vegetation samples were collected during this evaluation period. They were collected on April 26, , 210 2018 and June 20, 2018. The samples were analyzed for 226Ra Pb, U-Nat and Th-232. The measured radioisotopes were comparable to previous vegetation samples. 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 El No1=1 Comments: 10. Were radon samples analyzed for 222? (NRC Reg Guide 4.14) Yes Z No 111 Comments: The ECLs in 10 CFR 20 Appendix B Table 2 assume either no daughters present or 100% ingrowth. Th 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. The Regulatory limit is 100 mrem/yr. 11. Were the 222Rn results within the calculated ECL's for the yearly average results for the last four quarters? Yes CI No Z Comments: The sample location BHV-1 had an annual 222RI1 greater than the ECL. It is noted that the Field Blank sample, which is stored in the field office has a higher reading than the samples. 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 4 of 7 License Condition 1 1.2.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, 232Th, 2"Th, 226Ra and 210Pb? (NRC Reg Guide 4.14) Radioisotope U-nat 232Th 230Th 226Ra 210pb LLD (µCi/m1 in air) 9E15 4E16 2E15 9E14 6E14 Yes IZI No 0 Comments: LLDs in the analytical reports are called RRDL and are identical to the numbers listed above, except for 230Th RRDL that is listed as 3E-1 5 on the laboratory sheets. 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 21 r 0., b (NRC Reg Guide 4.14) Radioisotope U-nat 232Th 230Th 226Ra 210pb LLD (ACi/m1 in air) 1E16 Not Listed 1E16 1E16 2E15 Yes Z No 0 Comments: The LLDs documented in the analytical report are: 1.0E-1 6 for U-nat; Not listed for 232Th; 1.0E-1 6 for n 1.0E-16 226Ra, and 2.0E-1 5 for 21°Pb. Page 5 of 7 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? Radioisotope LLD (µCi/g in soil ) U-nat 2E7 226Ra 2E7 210pb 2E7 Yes 111 No D N/A Z Comments: Soil samples were not collected for this effluent report. The soil samples will be collected with the July to December 2018 effluent report. 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? Radioisotope LLD (µCilg in vegetation ) U-nat 2E7 226Ra 5E8 210pb 1 E6 Yes Z No Z Comments: The laboratory supplied RL were equivalent to NRC Regulatory Guide 4.14 values. The MDC were all greater than the LLD. Measurements were all orders of magnitude greater than the LLD or the MDC. 16. Were lower limits of detection (LLD) for analysis of radon samples within the limits listed in NRC Regulatory Guide 4.14 Section 5 for 222? Radioisotope LLD (µCi/m1) 222R11 2E1° (0.2pCi/1) Yes Z No Comments: Energy Fuels Resources used alpha-track high sensitivity detectors. The above LLD is not applicable for alpha-track detectors. The effective reporting limit is 0.6 pCi/1 based on information supplied by Energy Fuels Resources. The MDC for alpha track-etch passive detectors is approximately 8.2 x 10-11 microcurie/ml (0.082 pCi/l) based on a 12-month sampling period (Technical Basis Document to Support the Revision of Regulatory Guide 4.14, Revision 1, "Radiological Effluent and Environmental Monitoring at Uranium Mills. (Final Report, Feb 2014, Oak Ridge Associated Universities). Page 6 of 7 Prepared By: Heather Mickelson (Print Name) Reviewed By: Phil Goble (Print Name) (Signature) 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." 17. Were the yellowcake dryer and packaging stacks sampled in accordance with Regulatory Guide 4.14 Section 2.1.1? Yes Z No Comments: The stack sampling occurred during the quarters that the equipment was operational. The stack sampling followed EPA Method #'s 1, 5, and 17, which ensured that sampling was isokinetic, representative, and adequate to determine the release rates and concentrations of the radioisotopes. The radioisotopes evaluated were: U-Nat, 228Tn, 230Th, 232Th, 210ph, 226Ra, and 228Ra. wit64.(adic) 517-412-01 (Date) (Date) Page 7 of 7 Year Endin 30-Jun-18 PARTICULATE, RADON AND GAMMA SCREENING Quarter Ending Analysis of Annual Dose Constituent Location 30-Sep-17 31-Dec-17 31-Mar-18 30-Jun-18 Annual ECL Below ECL? mrem/yr I Ra dio a c tiv e Pa rtic u la te s I Cilai BHV-1 ,' 6.0E-16 ••.2.4E15 ,S, 1.9E-16 8.0E-16 1.8E- 5 :.- ' 9E-14 Yes 0.55 ,i,BHV-2 !.2.0E-.16 6.0E-16 - 6.7E 17 3.8E-16 3.1E-16 : - 9E-14 Yes 0.17 -•ERV-4 2.5E-15 ••!.1.0.E14 ,„ ,6,8E-16 1.5E-15 31E-15 . 9E-14 Yes 2.04 HV-5 ,..2.7E-15 .1.4E-14 7.1E-16 2,6E,15 5 E-15 9E-14 Yes 2.78 BHV:6 3.5E-15 .1 .4E- 4 1 E-15 3.0E-15 4E- 5 E 14 Yes 3.01 BHV-7 1.2E-15 4.6E-15 4.1E-16 1.6E15 2 0E-15 9E-14 Yes 1.08 BHV-8 1:::•.6.0E-16 2-. E- 5 2:3E46 • 9.4E-16 1 2E-15 9E- 4 Yes 0.65 • r, ,BHV-1 - 6.0E-17 5.0E17 .5.3E-17 - 1.2E-16 7.1E-17 E-14 Yes 0.18 HV- f 2.0E-17 0E-17 „- ::4E,1- 4'.6E,-;17 2 E-17 E- 4 Yes 0.07 BHV-4 . 30E16 :.0E-16 1.2E 6 , 8.2E-17 1.6E-1 2E 14 Yes 0.44 13FIV- ' 2:0E716 4.0E-16 -17E-16 -2.4E-16 2 5E-16 2E 4 Yes 0.63 Bf-W-6 1-2.0E-16 4.0E-16 1 1E- 6 9.7E- 7 - 2 OE-16 E- 4 Yes 0.50 ' BHV-7 l• 6.0E-17 ••: 2.0E- , '':1'.2E16 2.2E-16 1 5E16 '''''• .2E-14 Yes 0.38 8HV-8 8.0E -17 5.0E-17 , 5.8E717 „1,2E-16 . 7.7E-17 2E-14 Yes 0.19 a BHV-1 : 1.0E16 '7.0E-17 -9:2E-17 -2.5E-16 ''' 1.3E-16 • - 9E-13 Yes 0.01 BHV-2 ' 5.0E-17 5.0E-17 • 4.0E- 7 1.2E-16 6.5E-17 9E-13 Yes 0.00 BHV-4 . ;• 2:0E7.16 H.2.0E-16 e5.7E-17 37E-17 • 1.2E-16 • 9E-13 Yes 0.01 BHV-5 • 2.0E-16 '3.0E-16 .5E16 5.9E-16 3.1E16 9E-13 Yes 0.02 BFIV-6 • 1%0E-16 1.0E-17 :. :1..1E-16 :.•KOE-16 OE-17 9E 13 Yes 0.00 BHV-7 1,:0E-16 1.0E-1 2,6E16 3E- 6 .1 5E.16 9E 1 Yes 0.01 BHV-8 1:0E,16 .5. E-17 8 3E-17 3 0E-16 ,, 1.3E71_6 , „ •-',, 9E713 Yes 0.01 -, FIf-2/6Pla• BHV-1 1.2E-14 1.8E-14 1.5E-14 •.. 1.2E-14 "1.4c14 ' 6E13 Yes 1.19 BHV-2 -1.3E-14 • 2.0E-14 :1.2E-14 ,•0E-14 14E44 ' E-13 Yes 1.21 10.4 1.6B14 ..2.2E-14 "1.4E- 4 1.1E-14 1.',6E14 ,•,', • . 6E,1 Yes 1.31 .r.i ' •-• '',i'll.tei/mL) t5 BHV- 1.6E-14 1.6E-14 1.4E-14 1 2E-14 1.5E- 4 6E-13 Yes 1.21 HV-6 •1••1::9E-14 2.0E- 4 1: E 4 1-2E-14 1.7E,..14 6E. la Yes 1.38 BI-IV-7 1.9E-14 2.1E-14 1 8E 4 .2E- 4 1. E-14 6E43 Yes 1.46 .BHV-8 1.2E-14 1.7E-14 -1.3E-14 88E715 -1 3E-14 6E-18 Yes 1.06 BHV-1 .:•.8.0E-18 1,0E-17 IIEW 9,3E-18 8.2E-18 . " 4E715 Yes 0.10 BHV-2 ", 4.0E-18 O.0E-18 5.3E-18 1.5E-17 . E:18 .4&15. Yes 0.10 4:0E-18 ,2,0E-17 - ' 4,0E-1$ 1,2E-1,7 1.0E-17 4E-15 Yes 0.13 BHVi•5 •: 4.0E-18 E-17 2.0E-17 9.4E-18 : .. 1,1E-17 .4E15 Yes 0.14 ' . BHV-6 1.0E-17 . 1.0E- 7 9.0E-1 1.4E-17 1.1E-17 '4E-15 Yes 0.13 BHV-7 4.0E 8 1.0E-1•V',..:! 8 7E-18 1.7B17 9 9E-18 .4E1 Yes 0.12 BHV-8 2.0E 8 7.0E-18 5.1E-18 ' &SEA 8 5.7E-18 4E-15 Yes 0.07 Di r e c t R a dia tio n I Y (mrem) SHV-1- 1.30 7.90 1.00 0.00 10.20 100 Yes 10.20 -SHY-2 1.40 2.90 0.10 2.20 6.60 100 Yes 6.60 0.00 0.40 0.00 0.70 1.10 100 Yes 1.10 B1-11/-5 0.00 4.00 2.00 1.20 7.20 100 Yes 7.20 ,f3HV-6 1-31:1\70 0.00 2.80 0.00 0.00 2.80 100 Yes 2.80 0.70 0.00 0.00 0.00 0.70 100 Yes oio BHV-8 0.00 Z50 0.00 0.00 2.50 100 Yes 2.50 Ra do n -22 2 I 222Rn (pCi/L) BHV,1 0.06 0 17 0.80 0.05 0.27 0.1 No 0.05 BHV-2 0.00 0.06 0.CH3 0.00 0.02 0.3 Yes 13.06 BHV-4 0.00 0.30 0.25 0.03 0.15 0.5 Yes 0.07 HV 0.08 0.54 0.41 0.24 0.32 1 Yes 0.07 BHV=6 0.00 0.27 0.14 0.08 0.12 0.8 Yes 0.06 B W7 0.06 0.11 0.14 0.08 0.10 1 Yes 0.04 V-8 0.00 0.25 0.17 0.00 0.11 0.7 Yes 3.70 Su mm a ry I Estimated Dose and Comparison to Screening Values (mrem/yr) Location Dose ALARA Goal ALARA Goal Met? Exposure Lirnit Compliant? BHV-1 12 28 25 Yes 100 Yes BHV-2 8.22 25 Yes 100 Yes . ---a- •Elliv-4 5.09 25 Yes 100 Yes : .8HV,-5 12.04 25 Yes 100 Yes BHV-6 7.89 25 Yes 100 Yes •,BHV-7 3.79 25 Yes 100 Yes BHV-8 8.17 25 Yes 100 Yes Notes: Regulatory limit is 100 mrem/yr. Energy Fuels' ALARA goa 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.