Willow Creek Project - Semi-Annual Effluent and ... · survey report will be included in the 2nd half 2017 semi-annual effluent report which will be submitted in February 2018. Please

September 27, 2017

Attn: Document Control Desk, Director Office of Nuclear Material Safety and Safeguards Nuclear Regulatory Commission Washington, DC 20555-0001 Rockville, MD 20852-2738

Subject: License SUA-1314 Docket No. 040-08502 Willow Creek Project Semi-Annual Effluent and Environmental Monitoring Report

Dear Director:

@ uranium one··

In accordance with 10 CFR 40.65 and per license conditions 12.1 and 12.3 of Source Materials License SUA-1341, please find enclosed the Semi-Annual Effluent and Environmental Monitoring Report for the period of January 1 through June 30, 2017. The annual land use survey report will be included in the 2nd half 2017 semi-annual effluent report which will be submitted in February 2018.

Please contact me should you have any questions regarding this report.

;;leUL=~ Scott Schierman HSE Manager/RSC

Uranium One USA. Inc. A Member of the Uranium One Inc. Group of Companies

tel +1 307-234-8235 •fax +1 307-237-8235 907 N. Poplar Street,

Suite 260 Casper, Wyoming 82601

www.uranium1.com

Willow Creek ISR Project

License Number SUA-1341

Docket No.040-08502

First Half2017

Semi-Annual Report

January 01, 2017 through June 30, 2017

Table of Contents

1.0 Introduction ............................................................................................................................... 1

2.0 Operational Monitoring .............................................................................................................. 1

2.1 Activities Summary ........................................................................................................ 1

2.2 Excursion Well Status .................................................................................................... 1

2.3 Groundwater Injected and Recovered ............................................................................ 1

2.4 Injection Manifold Pressures ......................................................................................... 1

2.5 Summary of Mechanical Integrity Testing (MIT) Data ..................................................... 1

3. 0 Restoration ................................................................................................................................ 2

3.1 Christensen Ranch ........................................................................................................ 2

3.2 lrigaray ........................................................................................................................... 2

4.0 Environmental Monitoring .......................................................................................................... 2

4.1 Regional Ranch Wells .................................................................................................... 2

4.2 Surface Water Monitoring .............................................................................................. 3

4.3 Summary of Spills .......................................................................................................... 3

4.4 Soil Sampling ................................................................................................................. 3

4.5 Vegetation Sampling ...................................................................................................... 3

5.0 Air Monitoring ............................................................................................................................ 4 5.1 Dryer Stack Emissions ................................................................................................... 4 5.2 Environmental Airborne Radionuclides ......................................................................... .4 5.3 Environmental Radon Monitoring .................................................................................. .4 5.4 Environmental Gamma Radiation Monitoring ................................................................. 5 5.5 Effluent Released from Willow Creek Facilities .............................................................. 5

6.0 Public Dose ................................................................................................................................................ 5 7.0 Safety and Environmental Review Panel ................................................................................... 6 8.0 Other ......................................................................................................................................... 6

8.1 ALARA REVIEW ............................................................................................................ 6 8.2 Land Use Survey ........................................................................................... 7

Table of Appendices

Appendix A Tables

• Table 1 Groundwater Volumes Injected and Recovered • Table 2 Injection Manifold Pressures • Table 3 Regional Ranch Wells • Table 4 Surface Water Monitoring • Table 5 Soil Sampling • Table SA Vegetation Sampling • Table 6 Environmental Radon Monitoring • Table 7 Dryer Stack Emissions Testing Results • Table 8 Environmental Airborne Radionuclides • Table 9 Environmental Gamma Radiation Monitoring • Table 1 O SERP Summary

Appendix B ALARA Audit

1.0 INTRODUCTION

In accordance with Sections 12.1 and 12.3 of the Nuclear Regulatory Commission (NRC) Source License No. SUA-1341, Uranium One USA, Inc. hereby submits the 2014 SemiAnnual Effluent and Monitoring Report. This document summarizes the required operational and environmental monitoring activities conducted at the lrigaray (IR) and Christensen Ranch (CR) projects from January 1, 2016 through June 30, 2016.

2.0 OPERATIONAL MONITORING

2.1 Activities Summary

During the. report period, limited production operations occurred within Mine Units 7, 8, and 10. The operational plan for the remainder of 2017 involves sustaining a small uranium recovery bleed in mine units that are in a decreased production operation mode sufficient to maintain a cone of depression towards .the wellfields. During this downtime, wellfield maintenance work will proceed. Maintenance planned includes the 5-year mechanical integrity testing (MIT) of well casings in Mine Units 8 and 10 as per regulatory requirements.

2.2 Excursion Well Status

No wells were on excursion status during the reporting period from January 1, 2017 to June 30, 2017.

2.3 Groundwater Volumes Injected and Recovered

During this reporting period an overall wellfield bleed was maintained at 2.97%. A total of 752,570,983 gallons were injected and 775,581,820 gallons were recovered during this period. During the reporting period all mine units averaged at least at 1.0% bleed. The data is summarized by wellfield in Table 1 and is located in Appendix A of this report.

2.4 Injection Manifold Pressures

Injection manifold pressures at the CR project are limited to 140 psi during wellfield operations and 168 psi during maintenance tasks, as per License Condition 11.1. Injection manifold pressures are continuously logged by pressure chart recorders located in every wellfield module building. The data from these logs are summarized in Table 2 of Appendix A. Twice during the reporting period the manifold pressure in module 7-3 exceeded the 140 psi limit. The first event happened the week on January 1, 2017 (148 psi) and the second was the week of January 28, 2017 (146 psi). Both events were caused when an unexpected shut down in module 7-5 happened. The spikes in the recorded manifold pressure were brief and within seconds it returned to normal.

August 2017 2017 Semi-Annual Effluent And Monitoring Report Willow Creek Project

SUA-1341

2.5 Summary of Mechanical Integrity Testing (MIT}

During the report period, Mechanical Integrity Tests (MIT's) were completed on a total of 608 wells. The MIT's were completed using the "Two Packer Pressurized Test Method" approved in Permit No. 478. Of the total of 608 MIT's that were performed, there were sixteen (16) failures. Since the reporting period, two (2) of the wells that initially failed MIT have been repaired, retested and put back into production.

The MIT's were completed in the following area:

Location Mine Unit 8 Mine Unit 10

Number MIT's 596

12

Number Failures 15 (2 were repaired) 1

There were thirteen (13) wells in Mine Unit 8 that were grouted during the period of January 1, 2017 through June 30, 2017. The thirteen (13) wells that were grouted have not been (surface) abandoned as of June 30, 2017 as agreed to by Wyoming Department of Environmental Quality/ Land Quality Division (WDEQ/LQD). The well abandonment records are maintained on site.

3.0 Restoration

3.1 Christensen Ranch:

All groundwater restoration activities, including stabilization monitoring, · ended at Christensen Ranch Mine Units 2 through 6 on May 30, 2005. The results of all wellfield restoration were compiled into a report and submitted to the WDEQ and NRC on April 8, 2008. On October 23, 2012 in NRC's technical Evaluation Report (TER) listed their basis for denying restoration completeness. Uranium One submitted responses to NRC's TER concerns regarding groundwater restoration at Christensen Mine Units 2-6 were submitted for NRC review on September 11, 2015. WDEQ was provided a copy of Uranium One responses to NRC TER for review and comment on May 26, 2016.

3.2 lrigaray;

lrigaray groundwater restoration activities and stabilization monitoring were conducted from 1990 to 2002. The 'Wellfield Restoration Report lrigaray Mine" was submitted to the WDEQ in July of 2004. The WDEQ-LQD approved restoration of lrigaray Mine Units 1-9 via correspondence dated November 1, 2005. After an independent review, lrigaray restoration approval was received from the NRC in correspondence dated_September 20, 2006. The Final Decommissioning Report for lrigaray Mine Units 1-9 was submitted to NRC for review and approval on August 7, 2015. Uranium One was notified by NRC that ORAU would be conducted the review of this document and would be conducting confirmatory sampling during the July 2016 NRC inspection.

4.0 ENVIRONMENTAL MONITORING

4.1 Regional Ranch Wells

August 2017 2 2017 Semi-Annual Effluent And Monitoring Report

Willow Creek Project SUA-1341

Five stock watering and domestic water wells are located within two kilometers of Christensen Ranch mining area, and one is located near lrigaray. Routine quarterly groundwater samples were collected from these six regional ranch wells. The samples were analyzed for Uranium, Thorium-230, Radium-226, Lead-210 and Polonium-210 for both suspended and dissolved parameters. All parameters are in line with historical data presented in Table 5.23 of the SUA-1341 License Renewal Application. Sampling was consistent with the requirements of License Condition 11.3 and Section 5.8 of the License Renewal Application. This data is summarized in Table 3 of Appendix A.

4.2 Surface Water Monitoring

During the reporting period Surface Water samples were collected across the Willow Creek Project. Willow Creek is the only source of surface water present within and adjacent to the permit boundaries of both the IR and CR projects. Willow Creek is an ephemeral stream which was sampled on a quarterly basis. Three sample locations are designated at both project sites; upstream, downstream and within the permit boundary. The Powder River is also sampled annually at the Brubaker Ranch, which is approximately 4.5 miles downstream from its confluence with Willow Creek. Sample location IR-9 is located where Willow Creek meets up with the Powder River.

During the sampling period all regional wells that are sampled quarterly were below the 10 CFR Appendix B Table 2 Effluent Concentrations. Radionuclide levels for the 1s1 half of 2016 are consistent with historical values presented in Table 5.25 of the SUA-1341 License Renewal Application. Comparison of suspended radionuclide results is limited to data that has been collected since 2012 so historical data for these parameters are limited.

The surface water sampling for the first half 2017 is summarized in Table 4 of Appendix A

4.3 Summary of Spills

There was one reportable spill during the reporting period. Emails, written notifications, and summary reports were submitted to the NRC and WDEQ regarding these events and will not be duplicated in this report.

4.4 Soil Sampling

Annual soil sampling at the Willow Creek environmental locations occurred during the previous reporting period. The samples were taken from 5 locations at the lrigaray Project and 4 locations from the Christensen Project. Sampling locations coincide with air particulate stations and radon stations. The soil was analyzed for uranium, radium-226, lead-210, and thorium. This data is summarized in Table 5 located in Appendix A of this report.

4.5 Vegetation Sampling

August 2017 3 2017 Semi-Annual Effluent And Monitoring Report Willow Creek Project

SUA-1341

Annual vegetation sampling at the Willow Creek environmental locations occurred during June 9, 2017. Analytical results for the uranium values at sample location IR-3 are higher than historic values and are currently being evaluated and potentially re-sampled. Revised analytical results will be reported as part of the next semi-annual effluent report. Vegetation analytical results received to date are shown in Table SA of Appendix A. The samples were taken from 5 locations· at the lrigaray project and 4 locations at the Christensen Project. Comparing the vegetation results to historical averages as are presented in Table 5.15 of the SUA 1341 License Renewal Application indicate no upward trends were noted and all samples were within natural variances of the historical averages.

5.0 AIR MONITORING

5.1 Dryer Stack Emissions

The semi-annual Dryer Stack Emission testing was performed on May 17, 2017 by Western Environmental Services and Testing Services The sample collected in May 2017 during drying of Willow Creek materials shows a release rate of 0.020 lb/hr, which is in compliance with the WDEQ Air Quality Permit OP254 limit of 0.30 lb/hr. A summary of the total emissions is summarized in Table 7 of Appendix A.

Uranium One has included the quantities from stack emissions released for the reporting period for Th-230, Pb-210, Ra-226, and U-nat. These values are based on the operating times of the dryer and the stack testing performed by an outside entity.

5.2 Environmental Airborne Radionuclides

During dryer operations, continuous airborne radionuclide sampling is required at the five specified environmental air sampling locations at the IR project. The yellowcake dryer was in operation for approximately 232 hours during the second quarter of 2016. The stations used to monitor airborne radionuclides and are located as follows:

• IR-1 Downwind of Restricted Area • IR-3 Upwind of Restricted Area • IR-5 is located at Brubaker Ranch • IR-6 is the background location • IR-13 is the employee house trailer and is considered the maximally exposed

individual.

Air Particulate samples are collected weekly and then composited quarterly for analysis by an outside laboratory. The data for the first half 2017 are summarized in Table 8 of Appendix A.

5.3 Environmental Radon Monitoring

Radon gas is monitored continuously at the eight environmental air locations surrounding the lrigaray Project, and twelve locations surrounding the Christensen Ranch Project. Passive outdoor radon detectors are exchanged quarterly and sent to Landauer for analysis. The data is shown in Table 6 of Appendix A. Data is given as raw

August 2017 4 2017 Semi-Annual Effluent And Monitoring Report


data without subtracting the background location. Comparing the data to historical data presented in 5.11 and 5.12 of the SUA 1341 License Renewal Application the data is all below or within historical values.

Uranium One has received NRC approval of methodologies for quantifying radon release before implementation as per license condition 11.3 and these values will be reported for the 2nd half of 2017 semi-annual effluent report.

5.4 Environmental Gamma Radiation Monitoring

Passive gamma radiation is monitored continuously at six environmental air locations surrounding the lrigaray Project and at five locations surrounding the Christensen Ranch Project. Dosimeters are exchanged and analyzed quarterly by the Landauer Dosimetry Services, a NVLP accredited company. The gamma data is summarized in Appendix A Table 9. The data is consistent with the values presented in Tables 5.19 and 5.20 of the SUA 1341.

5.5 Effluent Released from Willow Creek Activities

As part of the 10 CFR 40.65 effluent monitoring requirements the licensee must specify the quantity of each of the principle radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous six months. Additionally, Uranium One is required under License Condition 11.3 to quantify the principal radionuclides from all point and diffuse sources. Under this license condition the method for estimating the quantity of radionuclides emitted from a facility needs to be verified by NRC before implementation. Uranium One received verification by the NRC for these estimations in June 2017 and will include this information for the second half 2017 semi-annual effluent report under this section.

6.0 PUBLIC DOSE

1 O CFR 20.1301 requires that each NRC licensee conduct their operations in a manner that the total effective dose equivalent {TEDE) to members of the public does not exceed 100 mrem in a year, and that the dose from external sources in any unrestricted area does not exceed 2 mrem in any hour.

Additionally, 10CFR 20.1302 require licensees to show compliance to these dose limits by:

1. Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed operation does not exceed the annual dose limit or;

2. Demonstrate

August 2017

A. The annual average concentration of radioactive material released in gaseous and liquid effluent at the boundary of the unrestricted area do not exceed the values specified in table 2 of appendix B

5 2017 Semi-Annual Effluent And Monitoring Report


8. If an individual were continuously present in an unrestricted. area, the dose from the external sources would not exceed 0.002 rem (0.02 mSv) in an hour and 0.05 rem (0.5 mSv) in a year.

Uranium One will demonstrate compliance to the public dose requirements by performing a dose assessment for the individual predicted to be the maximally exposed individual on an annual basis. Uranium One anticipates that the highest exposed individual would be operators staying in the man camps off shift. Operators working at Uranium One typically work four shifts of 12 hours and on four shifts off. This equates to a conservative three nights per week spent in workforce housing. For the year this equates to a total of 1872 hours spent in workforce housing.

Dose to individuals at the workforce housing are monitored through the use of Radtrak TrackEtch detectors, OSL environmental dosimeters, and airborne particulate sampling. The concentration is equated to dose using the following equation.

Where

D = DCF I CiFiTi i

D = annual dose (mrem/yr); DCF =dose conversion factor Ci = annual average concentration at the receptor location i; Fi = equilibrium factors for receptor location I used for radon; and Ti = occupancy time factor (fraction of year) for receptor location i

Dose conversion factors are established by taking effluent concentration limits in 1 O CFR 20 Appendix 8, Table 2, and using the annual dose limit of 1 OOmrem/yr. Taking the annual dose limit and dividing by the effluent concentration limit will provide the dose conversion factor. Dose conversion factors for radon will be calculated using the daughters present with the 100% equilibrium.

External gamma radiation will be determined through the use of Landauer environmental dosimeters. A dosimeter will be placed at each maximally exposed individual location. Dose will be assigned to each receptor.

Public Dose is calculated on an annual basis and will be included in the semi-annual effluent report submitted in February 2018.

7.0 SAFETY AND ENVIRONMENTAL EVAULATIONS

Per License Condition 9.4E Uranium One shall furnish, in an annual report to the NRC, a description of such changes, tests, or experiments, including a summary of the evaluations made by the safety and environmental evaluation panel (SERP). Uranium One completed one (1) SERP during the reporting period from January through June 2016. A summary of the SERPs findings for each evaluation can be found in Table 1 O of Appendix A.

August2017 6 2017 Semi-Annual Effluent And Monitoring Report Willow Creek Project

SUA-1341

8.0 Other

8.1 ALARA REVIEW

As required by License condition 12.3 the licensee shall submit the results of the annual review of the radiation protection program content and implementation performed in accordance with 10CFR20.1101(c). A copy of the 2016 ALARA audit is included in Appendix B of this semi-annual effluent.

8.2 Land Use Survey

The primary use of surrounding lands at both IR and CR project continues to be rural sheep and cattle ranching. Livestock actively graze these lands, but fencing prevents access to the evaporation ponds, plant sites, and wellfields.

The secondary use of surrounding lands continues to be petroleum production from wells dispersed throughout the region. The closest oil well at the CR project is located approximately one third of a mile west of the CR plant. The closest oil wells at the IR site are located approximately one half mile east of proposed MU 9 wellfield. Oil activities at and around the Willow Creek project for the first half of 2017 have been significantly reduced due to continued depressed oil prices.

Over the past several years (2001-2015) some additional interest has developed in the immediate areas of the IR and CR projects in the development of coal bed methane (CBM) gas. Several CBM wells are located within a half mile of Uranium facilities.

The nearest residence to the IR site is 4 miles to the north (the Brubaker Ranch) and the nearest residence to CR is the John Christensen Ranch located 3 miles southeast of the CR plant site. Both are ranch hou~ing with a population of six or less.

Land use surveys are conducted on an annual basis to verify the use of surrounding lands is consistent with previous assessments. These assessments are used in determining survey locations and which individuals may be potentially affected by Uranium One's activities. The Land Use Report will be included as part of the semiannual report submitted to NRC in February 2018.

August2017 7 2017 Semi-Annual Effluent And Monitoring Report Willow Creek Project

SUA-1341

APPENDIX A

Tables 1-10

August 2017 2017 Semi-Annual Effluent And Monitoring Report


Table 1

MU 5-2 Monthly Totals

Date

January 2017 Februarv 2017

March 2017 April 2017 May 2017 June 2017

Totals

MU 7 Monthly Totals

Date

January 2017 February 2017

March 2017 Aoril 2017 May 2017 June 2017

Totals

MU 8 Monthly Totals

Date

Januarv 2017 February 2017

March 2017

April 2017 May 2017 June 2017

Totals·

(

August 2017

Uranium One USA, Inc. Groundwater Volumes Injected and Recovered

Production Injection Bleed (gallons) (gallons) (gallons) Yo Bleed

250,560 0 250,560 100.0 % 108,560 0 108,560 100.0 % 277,680 0 277,680 100.0 % 264,960 0 264,960 100.0 % 403,040 0 403,040 100.0 % 322,560 0 322,560 100.0 %

1,627,360 0 1,627,360 100.0 %

Production Injection Bleed (gallons) (gallons) (gallons) Vo Bleed

14,774,337 13,625,551 1, 148,786 7.8 % 672,391 0 672,391 100.0 % 403,878 0 403,878 100.0 %

4,467,579 4,235,648 231,931 5.2 % 487,125 0 487, 125 100.0 % 291,874 0 291,874 100.0 %

21,097,184 17,861,199 3,235,985 15.3 %

Production Injection Bleed (gallons) (gallons) (gallons) Yo Bleed

73,916,114 72,906,833 1,009,281 1.4 % 50,549,488 50,182,288 367,200 0.7 % 45,070,081 44,243,918 826, 163 1.8 %

42,977,806 . 41,704,506 1,273,300 3.0 % 64,356,975 62,505,440 1,851,535 2.9 % 50,576,137 49,416,033 1, 160, 104 2.3 %

327,446,601 320,959,018 6,487,583 2.0 %

Page 1of20

1st Half 2017 Semi-Annual Effluent and Monitoring Report


Table 1

Date


March 2017 April 2017 May 2017 June 2017

Totals

Date


March 2017 Aoril 2017 Mav 2017 June 2017

Overall Totals

August 2017

Uranium One USA, Inc.

MU 1 O Monthly Totals Production Injection (gallons) (gallons)

48,553,817 45,412,740 68,860,660 67,267,233 73,481,510 71,771,582 74,009,814 72,420,765 91,783,831 89,751,462 68,721,043 67,126,984

425,410,675 413,750,766

Overall Monthly Totals Production Injection

(gallons) (gallons)

137,494,828 131,945, 124 120,191,099 117,449,521 119,233, 149 116,015,500 121,720, 159 118,360,919 157,030,971 152,256,902 119,911,614 116,543,017 775,581,820 752,570,983

Groundwater Volumes Injected and Recovered

Bleed (gallons) % Bleed

3,141,077 6.5 % 1,593,427 2.3 % 1,709,928 2.3 % 1,589,049 2.1 % 2,032,369 2.2 % 1,594,059 2.3 %

11,659,909 2.7 %

Bleed (gallons) % Bleed

5,549,704 4.0 % 2,741,578 2.3 % 3,217,649 2.7 % 3,359,240 2.8 % 4,774,069 3.0 % 3,368,597 2.8 %

23,010,837 3.0 %

Page 2 of 20



Table 2 Uranium One USA, Inc. Injection Manifold Pressures

Table 2 - Christensen Ranch Weekly Maximum Injection Pressures per Module Building

Week Ending 1/7/2017

1/14/2017 1/21/2017 1/28/2017 2/4/2017

2111/2017 2/18/2017 2/25/2017 3/4/2017

3/11/2017 3/18/2017 3/25/2017 4/1/2017 4/8/2017

4/15/2017 4/22/2017 4/29/2017 5/6/2017

5/13/2017 5/20/2017 5/27/2017 6/3/2017

6/10/2017 6/17/2017 6/24/2017 7/1/2017

August 2017

Mine Unit 7

Weekly Maximum injection Pressure (Maximum Permissible 140 psi)

Module 7-1 Module 7-2 Module 7-3 No Injection No Injection 148 No Injection No Injection 130 No Injection No Injection 137 No Injection No Injection 146 No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection 138 No Injection No Injection 120 No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection

Page 3 of 20

Module 7-4 Module 7-5 Module 7-6 No Injection 125 No Injection No Injection 133 No Injection No Injection 112 No Injection No Injection 136 No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection

75 No Injection No Injection 94 115 No Injection

No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection






1/14/2017 1/21/2017 1/28/2017 2/4/2017

2/11/2017 2/18/2017 2/25/2017 3/4/2017

3/11/2017 3/18/2017 3/25/2017 4/1/2017 4/8/2017

4/15/2017 4/22/2017 4/29/2017 5/6/2017

5/13/2017 5/20/2017 5/27/2017 6/3/2017

6/10/2017 6117/2017 6/24/2017 7/1/2017

August 2017

Mine Unit8


Module 8-1 Module 8-2 Module 8-3 137 125 125 133 120 122 132 105 106 138 127 125 132 125 124 115 110 111 165 127 125 134 No Injection 122 140 No Injection 124 140 No Injection 120 160 No Injection 115 125 No Injection 122 130 No Injection 115 131 125 125 135 130 125 115 124 100 130 121 125 136 121 125 126 124 115 137 120 105 130 121 100 128 122 100 130 No Injection 135 130 No Injection 125 135 No Injection 122 137 No Injection 115

Page 4 of 20

Module 8-4/5 Module 8-6 Module 8-7 120 90 135 107 93 135 102 85 124 95 90 135 115 100 133 100 90 125 113 98 137 117 75 131 130 84 133 136 101 127 126 80 135 130 100 120 130 110 121 130 123 125 126 124 130 101 105 122 138 130 133 130 121 135 131 124 136 130 119 135 125 115 130 126 120 135 135 124 137 135 135 140 126 117 . 135 135 120 133






1114/2017 1/21/2017 1/28/2017 2/4/2017

2/11/2017 2118/2017 2/25/2017 3/4/2017

3/11/2017 3/18/2017 3/25/2017 4/1/2017 4/8/2017

4/15/2017 4/22/2017 4/29/2017 5/6/2017

5/13/2017

5/20/2017

5/27/2017

6/3/2017

6110/2017 6/17/2017 6/24/2017 7/1/2017

August 2017

Mine Unit 8 (Cont.) and Mine Unit 5-2


Module 8-8 Module 8-9 Module 5-2 112 118 75 103 100 84 120 125 105 125 115 115 114 115 104 98 131 130 130 132 126 127 125 130 126 130

99 100 86 105 115 95 90 90 115 98 123 100 105 109 116 80 128 100 103 125 105 135 130 123 115 110

Page 5 of 20

No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection

No Injection

No Injection

No Injection

No Injection No Injection No Injection No Injection






1/14/2017 1/21/2017 1/28/2017 2/4/2017

2/11/2017 2/18/2017 2/25/2017 3/4/2017

3/11/2017 3/18/2017 3/25/2017 4/1/2017 4/8/2017

4/15/2017 4/22/2017 4/29/2017 5/6/2017

5/13/2017 5/20/2017 5/27/2017 6/3/2017

6/10/2017 6117/2017 6/24/2017 7/1/2017

August 2017

Mine Unit 10

Weekly Maximum injection Pressure {Maximum Permissible 140 psi)

Module 10-1 Module 10-2 Module 10-3 No Injection No Injection No Injection No Injection No Injection No Injection No Injection No Injection 65 No Injection No Injection 90 No Injection No Injection 80 No Injection 105 70

94 115 82 50 123 80 46 115 81 57 123 84 55 120 84 67 125 95 125 120 94 55 120 95 75 124 100 76 111 85 115 116 100 65 126 110 100 125 85 105 127 84 85 130 75 100 126 80 98 125 86 85 125 81 86 125 87 85 125 90

Page 6of20

Module 10-4 Module 10-5 Module 10-6 105 81 114 106 106 111 123 103 116 110 127 1420 110 115 125 106 111 80 119 116 99 120 105 110 122 120 110 118 115 122 119 124 123 100 125 122 100 118 121 120 115 120 125 85 120 110 105 125 124 135 127 115 115 120 125 105 121 125 100 120 120 ' 105 125 118 100 128 127 105 130 123 105 130 115 114 130 124 110 130



Table 3

Sam pie Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-210 (Suspended) Polonium-210 (Disolved) Polonium-210 (Suspended)

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-21 O (Suspended) Polonium-210 (Disolved) Polonium-210 (Suspended)

Sample Location

Radionuclide (

Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-21 O (Suspended) Polonium-210 (Disolved) Polonium-21 O (Suspended)

August 2017

Uranium One USA, Inc. Regional Ranch Wells

Christensen Ranch House #3 1st Q Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(µCi/ml) (±uCi/ml) Cone* (µCi/ml) (±uCi/mll Cone* 1.18E-08 NA 3.9 1.21 E-08 NA 4.0

ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA

1.00E-09 1.00E-10 1.7 5.00E-10 1.00E-10 0.8 ND NA NA 3.00E-10 1.00E-10 0.5 ND NA NA ND NA NA ND NA NA 1.40E-09 4.00E-10 14.0 ND NA NA ND NA NA ND NA NA ND NA NA

Christensen Ranch Ellendale #4 1st Q Uncertainty % of EFF 2nd Q Uncertainty % of EFF

(µCi/ml) (±uCi/ml) Cone* (µCi/ml) (±uCi/ml) Cone* 5.00E-10 NA 0.2 3.00E-10 NA 0.1

ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA

3.00E-10 1.00E-10 0.5 2.00E-10 1.00E-10 0.3 ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA

Christensen Ranch Willow Corral #32 1st Q Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(µCi/ml) (±uCi/ml) Cone* (µCi/ml) (±uCi/ml) Cone* ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA

3.00E-10 1.00E-10 0.5 4.00E-10 1.00E-10 0.7 ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA

Page 7 of 20



Table 3

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-21 O (Disolved) Lead-210 (Suspended) Polonium-21 O (Disolved) Polonium-21 O (Suspended)

Sam pie Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-21 O (Disolved) Lead-21 O (Suspended) Polonium-21 O (Disolved) Polonium-210 (Suspended)

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-210 (Suspended) Polonium-21 O (Disolved) Polonium-210 (Suspended)

August 2017

Uranium One USA, Inc. Regional Ranch Wells

1st Q (JJCi/ml)

ND ND ND ND ND ND ND ND ND ND

1st Q (JJCi/ml) 6.70E-09

ND ND ND

3.00E-10 5.00E-10

ND 2.00E-09

ND ND

1stQ (µCi/ml)

ND ND ND ND

6.00E-10 ND

1.60E-09 ND ND ND

Christensen Ranch First Artesian #1 Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(±µCi/ml) Cone* (JJCi/ml) (±µCi/ml) Cone* NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA

Christensen Ranch Middle Artesian Uncertainty % of EFF 2nd Q Uncertainty % of EFF

(±µCi/ml) Cone* (JJCi/ml) (±µCi/ml) Cone* NA 2.2 4.00E-09 NA 1.3 NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA

1.00E-10 0.5 5.00E-10 1.00E-10 0.8 1.00E-10 0.8 ND NA NA

NA NA ND NA NA 3.00E-10 20.0 1.20E-09 4.00E-10 12.0

NA NA ND NA NA NA NA ND NA NA

Christensen Ranch Del Gulch Lower #13 Uncertainty

(±JJCi/ml) NA NA NA NA

1.00E-10 NA

3.00E-10 NA NA NA

Page 8 of 20

% of EFF 2ndQ Uncertainty % of EFF Cone*

NA NA NA NA 1.0 NA

16.0 NA NA NA

(JJCi/ml) (±JJCi/ml) Cone* ND NA NA ND NA NA ND NA NA ND NA NA

3.00E-10 1.00E-10 . 0.5 ND NA NA ND NA NA ND NA NA ND NA NA

3.50E-09 8.00E-10 8.8



Table 3 Uranium One USA, Inc. Regional Ranch Wells

Sample Location 1stQ

Radionuclide (µCi/ml) Uranium (Disolved) ND Uranium (Suspended) ND Thorium-230 (Disolved) ND Thorium-230 (Suspended) ND Radium-226 (Disolved) ND Radium-226 (Suspended) ND Lead-210 (Disolved) ND Lead-21 O (Suspended) ND Polonium-210 (Disolved) ND Polonium-210 (Suspended) 1.10E-09

Uranium Thorium-230 Radium-226 Lead-210 Polonium-210

2.0E-10 µCi/ml 2.0E-1 O µCi/ml 2.0E-10 µCi/ml 1.0E-9 µCi/ml 1.0E-9 µCi/ml

ND= NON DETECTABLE NA= NOT APPLICABLE

*10 CFR 20 Appendix B Table 2 values

Uranium Thorium-230 Radium-226 Lead-210 Polonium-21 O

August 2017

3.0E-7 µCi/ml 1.0E-7 µCi/ml 6.0E-8 µCi/ml 1.0E-8 µCi/ml 4.0E-8 µCi/ml

Uncertainty (±1JCi/ml)

NA NA NA NA NA NA NA NA NA

6.00E-10

Page 9 of 20

lrigaray Willow #2 % of EFF 2ndQ Uncertainty % of EFF

Cone* (µCi/ml) (±1JCi/ml) Cone* NA NA NA NA NA NA NA NA NA 2.8

ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA ND NA NA

2.10E-09 6.00E-10 5.3



Table 4

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-21 O (Disolved) Lead-210 (Suspended) Polonium-210 (Disolved) Polonium-210 (Suspended)

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-210 (Suspended) Polonium-210 (Disolved) Polonium-21 O (Suspended)

Sam pie Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-210 (Suspended) Polonium-21 O (Disolved) Polonium-21 O (Suspended)

August 2017

Uranium One USA, Inc. Surface Water

1st Q (µCi/ml) 1.4E-08 6.0E-10

ND ND ND ND ND ND ND ND

1st Q , (µCi/ml) 4.3E-09

ND ND ND

4.0E-10 ND ND ND ND ND

1stQ (µCi/ml) 1.8E-08

ND ND ND


lrigaray-9 Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(±µCi/ml) Cone* (µCi/ml) (±µCi/ml) Cone* NA 4.5 6.7E-09 NA 2.2 NA 0.2 ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA

lrigaray-14 Uncertainty % of EFF 2ndQ Uncertainty % of EFF

C±uCi/ml) Cone* (µCi/ml) (±uCi/ml) Cone* NA 1.4 1.2E-09 NA 0.4 NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA

1.0E-10 0.7 5.0E-10 1.0E-10 0.8 NA NA 3.0E-10 1.0E-10 0.5 NA NA ND NA NA NA NA ND NA NA NA NA 6.0E-09 8.0E-10 15.0 NA NA 3.5E-09· 7.0E-10 8.8

lrigaray-17 Uncertainty % of EFF 2nd Q Uncertainty % of EFF

(±µCi/ml) Cone* (µCi/ml) (±11Ci/ml) Cone* NA 6.1 1.9E-08 NA 6.3 NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA

1.0E-10 0.3 ND NA NA NA NA ND NA NA NA NA 1.5E-09 4.0E-10 15.0 NA NA 1.1E-09 4.0E-10 11.0 NA NA 2.1E-09 5.0E-10 5.3 NA NA 5.4E-09 8.0E-10 13.5

Page 10 of 20



Table 4

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-210 (Suspended) Polonium-210 (Disolved) Polonium-210 (Suspended)

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-210 (Disolved) Lead-21 O (Suspended) Polonium-210 (Disolved) Polonium-210 (Suspended)

Sample Location

Radionuclide Uranium (Disolved) Uranium (Suspended) Thorium-230 (Disolved) Thorium-230 (Suspended) Radium-226 (Disolved) Radium-226 (Suspended) Lead-21 O (Disolved) Lead-21 O (Suspended) Polonium-210 (Disolved) Polonium-210 (Suspended)

August 2017

Uranium One U~A, Inc. Surface Water

1st Q (µCi/ml)

DRY DRY DRY DRY DRY DRY DRY DRY DRY DRY

1stQ (µCi/ml) 2.2E-08

ND ND ND


1st Q (µCi/ml) 1.5E-08

ND ND ND ND ND ND ND ND

1.2E-09

Christensen Ranch GS-01 Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(±uCi/ml) Cone* (µCi/ml) (±uCi/ml) Cone* NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA NA NA DRY NA NA

Christensen Ranch GS-03 Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(±uCi/ml) Cone* (µCi/ml) (±uCi/ml) Cone* NA 7.3 4.0E-08 NA 13.3 NA NA ND. NA NA NA NA ND NA NA NA NA ND NA NA

1.0E-.10 0.3 3.0E-10 1.0E-10 0.5 NA NA ND NA NA NA NA 1.8E-09 6.0E-10 18.0 NA NA ND NA NA NA NA 1.6E-09 4.0E-10 4.0 NA NA 7.0E-09 9.0E-10 17.5

Christensen Ranch CG-05 Uncertainty % of EFF

(±uCi/ml) Cone* NA 4.9 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA

7.0E-10 3.0

Page 11of20

2ndQ Uncertainty % of EFF (µCi/ml) (±uCi/ml) Cone* 4.6E-09 NA 1.5

ND NA NA ND NA NA ND NA NA ND NA NA

4.0E-10 1.0E-10 0.7 ND NA NA ND NA NA ND NA NA ND NA NA



Table 4 Uranium One USA, Inc. Surface Water

Sample Location 1stQ

Radionuclide (µCi/ml) Uranium (Disolved) ANNUAL Uranium (Suspended) ANNUAL Thorium-230 (Disolved} ANNUAL Thorium-230 (Suspended) ANNUAL Radium-226 (Disolved) ANNUAL Radium-226 (Suspended) ANNUAL Lead-210 (Disolved) ANNUAL Lead-210 (Suspended) ANNUAL Polonium-21 O (Disolved) ANNUAL Polonium-210 (Suspended) ANNUAL

Uranium Thorium-230 Radium-226 Lead-210 Polonium-210


ND = NON DETECTABLE NA= NOT APPLICABLE

*10 CFR 20 Appendix 8 Table 2 values

Uranium Thorium-230 Radium-226 Lead-210 Polonium-21 O

August 2017


Powder River (Annual) Uncertainty % of EFF 2ndQ Uncertainty % of EFF

(±µCi/ml) Cone* (µCi/ml) (±µCi/ml) Cone* NA NA 2.8E-09 NA 0.9 NA NA ND NA NA NA NA ND NA NA NA NA ND NA NA NA NA 2.0E-10 1.0E-10 0.3 NA NA 3.0E-10 1.0E-10 0.5 NA NA 1.1E-09 3.0E-10 11.0 NA NA 1.5E-09 5.0E-10 15.0 NA NA ND NA NA NA NA ND NA NA

Page 12 of 20



Table 5 Uranium One USA, Inc. Annual Soil

IRIGARA Y PROJECT CHRISTENSEN PROJECT IR-1 (Downwind of Restricted Area)

(µCi/g) Uncertainty

(±µCi/g) Uranium 7.60E-06 *NA Thorium-230 1.00E-06 3.00E-07 Radium-226 1.90E-06 2.00E-07 Lead-210 1.80E-06 4.00E-07

IR-3 (Upwind of Restricted Area)


(±uCi/al Uranium 1.23E-05 *NA Thorium-230 6.00E-07 2.00E-07 Radium-226 1.10E-06 2.00E-07 Lead-210 ND NA

IR-4 (North Road - Background)


C±uCi/al Uranium 7.00E-07 *NA Thorium-230 5.00E-07 2.00E-07 Radium-226 9.00E-07 2.00E-07 Lead-210 2.20E-06 7.00E-07

IR-5 (lrigaray Ranch - Nearest Resident)



IR-6 (Ridge Road S.E.)


(±µCi/a) Uranium 6.00E-07 *NA Thorium-230 4.00E-07 1.00E-07 Radium-226 6.00E-07 2.00E-07 Lead-210 ND NA

AS-1 (Table Mountain - Background)



AS-5A (CR Plant Upwind S.E.)



AS-5B (CR Plant Downwind N.W.)


(±µCi/g) Uranium 1.30E-06 *NA Thorium-230 7.00E-07 2.00E-07 Radium-226 1.30E-06 2.00E-07 Lead-210 ND NA

AS-6 (Christensen Ranch - Nearest Resident)


(±uCi/al Uranium 1.20E-06 *NA Thorium-230 9.00E-07 2.00E-07 Radium-226 1.00E-06 2.00E-07 Lead-210 2.10E-06 5.00E-07

RL's (µCi/g): Uranium = 2.0E-7 Thorium-230 = 2.0E-7 Radium-226 = 2.0E-7 Lead-21 O = 2.0E-7

Analyses performed by lnter-Mountian Labs (IML), Sheridan, Wyoming *The activity for uranium is a mathematical calculation based on a chemical analysis, therefore, no precision estimate (error) is given. The Inter-Mountain Lab reporting limit (RL) are based on the weight of the samples.

August 2017 Page 13 of 20



Table 5A Uranium One USA, Inc. Annual Vegetation

I RI GARAY PROJECT IR-1 (Downwind of Restricted Area)

(µCi/kg) Uncertainty

(±uCi/kal Uranium 3.4E-04 *NA Thorium-230 1.2E-05 3.0E-07 Radium-226 2.3E-05 2.0E-07 Lead-210 7.2E-05 4.0E-07

IR-3 (Upwind of Restricted Area)


(±µCilka) Uranium 6.0E-03 *NA Thorium-230 3.8E-06 3.2E-06 Radium-226 4.1E-06 2.1E-06 Lead-210 2.4E-04 1.8E-05

IR-4 (North Road - Background)


(±µCi/kg) Uranium 3.1E-05 *NA Thorium-230 2.9E-06 2.5E-06 Radium-226 9.2E-06 1.6E-06 Lead-210 2.7E-04 1.7E-05

IR-5 (lrigaray Ranch - Nearest Resident)


C±uCi/kg) Uranium 5.3E-04 *NA Thorium-230 ND NA Radium-226 2.0E-05 1.7E-05 Lead-210 9.8E-04 NA

IR-6 (Ridge Road S.E.)


(±µCi/kal Uranium 4.4E-05 *NA Thorium-230 ND NA Radium-226 9.7E-06 4.5E-06 Lead-210 1.7E-04 1.6E-05

CHRISTENSEN PROJECT AS-1 (Table Mountain - Background)


(±uCi/kal Uranium 2.2E-06 *NA Thorium-230 3.0E-07 6.0E-07 Radium-226 9.6E-06 1.7E-06 Lead-210 6.0E-05 9.8E-06

AS-5A (CR Plant Upwind S.E.)

(pCi/kg) Uncertainty

(±µCilka) Uranium 2.9E-06 *NA Thorium-230 3.8E-06 4.3E-06 Radium-226 1.7E-05 2.2E-06 Lead-210 7.9E-05 1.1E-05

AS-58 (CR Plant Downwind N.W.)


(±µCi/kal Uranium 1.6E-05 *NA Thorium-230 4.8E-06 5.5E-06 Radium-226 8.8E-06 2.3E-06 Lead-210 8.4E-05 1.2E-05

AS-6 (Christensen Ranch - Nearest Resident)


(±uCi/kg) Uranium ND *NA Thorium-230 9.0E-07 8.0E-07 Radium-226 1.1E-05 1.8E-06 Lead-210 1.9E-04 1.8E-05

LLD's (µCi/kg) Uranium = 2.0E-7 Thorium-230 = 2.0E-7 Radium-226 = 5.0E-8 Lead-21 O = 1.0E-6

Analyses performed by lnter-Mountian Labs (IML), Sheridan, Wyoming *The activity for uranium is a mathematical calculation based on a chemical analysis, therefore, no precision estimate (error) is given. The Inter-Mountain Lab reporting (LLD's) are based on the weight of the samples.




Table 6 Uranium One USA, Inc.

Location 1st

Quarter 2nd Quarter µCi/ml Uncertainty µCi/ml

IRIGARA Y PROJECT (2017) ±µCi/ml 2017

IR-1 (Downwind of Restricted Area) 2.40E+OO 6.00E-11 8.80E+OO

IR-3 (Upwind of Restricted Area)** 3.08E+01 5.00E-11 3.70E+01

IR-4 (North Road) 6.00E-01 6.00E-11 7.10E+OO

IR-5 (lrigaray Ranch) 3.00E-01 4.00E-11 2.40E+OO

IR-6 (Ridge Road - S.E. - Background) -1.60E+OO 6.00E-11 5.00E+OO

IR-13 (IR Employee House Trailer) 1.70E+OO 5.00E-11 5.80E+OO

IR-14 (IR Employee House Trailer inside) -2.10E+OO 5.00E-11 2.50E+OO

CHRISTENSEN PROJECT

AS-1 (Table Mountain - Background) 1.00E-01 5.00E-11 6.20E+OO

AS-5A (CR Plant Upwind S.E.) 3.00E+OO 5.00E-11 1.02E+01

AS-5B (CR Plant Downwind N.W) 1.00E-01 4.00E-11 2.60E+OO

AS-6 (Christensen Ranch) 8.40E+OO 5.00E-11 8.90E+OO

AS-7 (CR Employee House Trailer)* -1.70E+OO 4.00E-11 2.30E+OO

AS-8 (CR Employee House Trailer inside)* -1.70E+OO 4.00E-11 3.00E-01

AS-9 (Mine Unit 7) -2.70E+OO 4.00E-11 3.60E+OO

AS-10 (CR Wellfield Module 8-6) 6.70E+OO 4.00E-11 7.70E+OO

AS-11 (Water Tank) 6.50E+OO 4.00E-11 5.10E+OO

AS-12 (Mine Unit 10) 1.00E-01 4.00E-11 5.90E+OO

AS-13 (Substation) 1.80E+OO 1.80E+OO O.OOE+OO

AS-13 lost LLD = 0.06 pCi/I


Environmental Radon Monitoring

Location Uncertainty Average 10 CFRAPP B

±µCi/ml 2016 Table2

7.00E-11 5.60E+OO 1.00E-10

8.00E-11 3.39E+01 1.00E-10

7.00E-11 3.85E+OO 1.00E-10

5.00E-11 1.35E+OO 1.00E-10

9.00E-11 1.70E+OO 1.00E-10

4.00E-11 3.75E+OO 1.00E-10

4.00E-11 8.50E-01 1.00E-10

5.00E-11 3.15E+OO 1.00E-10

4.00E-11 6.60E+OO 1.00E-10

5.00E-11 1.35E+OO 1.00E-10

5.00E-11 8.65E+OO 1.00E-10

5.00E-11 3.00E-01 1.00E-10

5.00E-11 -7.00E-01 1.00E-10

5.00E-11 4.50E-01 1.00E-10

5.00E-11 7.20E+OO 1.00E-10

5.00E-11 5.80E+OO 1.00E-10

5.00E-11 3.00E+OO 1.00E-10

5.00E-11 9.00E-01 1.00E-10

1st Half 2017Semi-Annual Effluent and Monitoring Report


Table7

Time Total Particulates U308 Emissions lbs/hour (% limitl lbs

Jan-June, 2017 0.0021 3.6 0 0.0

Total 3.6 Pennlt Limit 0.30

Unat. Released Ci

1.40E-03 O.OOE+OO 1.40E-03


SUMMARY OF STACK EMISSIONS SURVEY RESULTS lrigaray Dryer and Packaging Circuit

Unat. Uncertainty Th-230 Released Th-230 Uncertainty Ci Ci Ci NA 5.94E-06 9.94E-07 NA 0.00E+OO

5.94E-06

Dryer Stack Emmlsslons Testing Results

Ra-226 Released Ra-226 Uncertainty Pb-21 O Released Pb-21 o Uncertainty Ci Ci Ci Ci

5.01E-06 4.28E-07 5.34E-05 5.64E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.01 E-06 5.34E-05

COMMENTS: YC Dryer ran for 1734 hours for the first half of 2017. These numbers are utilized to determine the re lase from the lrigaray YC drying and packaging operations for the above radionuclides.




Table 7 Uranium One USA, Inc. Dryer Stack Emmissions Testing Results

YC Dryer Stack Radionuclide Emissions

~Uranium .. ~ lOOE-11 ~-------------#------\--+---+---+-------------------"------'-'--ii . + Ra-226

...-Th-230

~Pb-210

:I.

August 2017

1981 1994 1995 1995 1996 1996 1997 19g) 1998 1998 199'J 199'J 2000 2001 HIST AVE 2011 2012 2012 2013 2013 2014 2014 2015 2015 2016 2016 2017

Page 3 of 3



Table 7

August 2017

0 .35

0.3

0 .25

0.2

0 .15

0.1

0 .05

0


YC Dryer Particulate Stack Emissions lbs/hr

Dryer Stack Emmission Testing Results

0.02

- Particulate 0.018

- uranium 0.016

0.014

0.012

0.01

0.008

0.006

0.004

0.002

0

198019941995199519961 996199719971998199819991999 20002001 HI ST 20112012 20122013 201320142014 201520152016 20162017 AVE

Page 2 of 3



Table 8

1st Quarter 2017 Data Uranium µCi/ml Th-230 µCi/ml Ra-226 µCi/ml

IR-1 Downwind 5.3E-15 O.OE+OO 2.4E-16

Uncertainty NA NIA 5.0E-17 %of Pt, App. B Effluent Limit 0.3% 0.0% 0.0%

IR-3 Upwind 1.1E-14 O.OE+OO O.OE+OO Uncertainty NA N/A NA %of Pt, App. B Effluent Limit 0.6% 0.0% 0.0%

IR-5 Brubaker Ranch 1.2E-15 . O.OE+OO 1.6E-16 Uncertainty NA 1.4E-16 6.9E-17 %of Pt, App. B Effluent Limit 0.1% 0.0% 0.0%

IR-6 Background 1.4E-15 1.7E-15 O.OE+OO Uncertainty NA NIA 1.3E-16 %of Pt, App. B Effluent Limit 0.1% 5.7% 0.0%

IR-13 Employee House Trailer 2.2E-15 O.OE+OO O.OE+OO Uncertainty NA N/A 5.7E-17 %of Pt, App. B Effluent Limit 0.1% 0.0% 0.0%

2017 Summary (Averages)

u Th-230 Ra-226 PB-210 (µCi/ml) (µCi/ml) (µCi/ml) (µCi/ml)

IR-1 6.7E-15 O.OE+OO 1.7E-16 1.9E-14 IR-3 7.1E-14 O.OE+OO O.OE+OO 1.5E-14 IR-5 8.3E-16 O.OE+OO 8.0E-17 1.3E-14 IR-6 9.9E-16 6.7E-16 O.OE+OO 2.2E-15

IR-13 1.8E-15 O.OE+OO O.OE+OO 1.1E-14

August2017


Pb-210 µCi/ml

2.9E-14 IR-1 Downwind 1.9E-15 Uncertainty

4.8% %of Pt, App. B Effluent Limit

2.1E-14 IR-3 Upwind 2.1E-15 Uncertainty


1.8E-14 IR-5 Brubaker Ranch 2.6E-15 Uncertainty


2.3E-15 IR-6 Background 1.9E-15 Uncertainty


1.3E-14 IR-13 Employee House Trailer 1.8E-15 Uncertainty


10 CFR Pt. 20, App. B, Effluent Limits (uCi/ml) Uranium= 1.95E-12 (50%D & 50%W) Th-230 = 3.0E-14 (Y) Ra-226 = 9.0E-13 (W) Pb- 210 = 6.0E-13 (D)

Page 19 of 20

Environmental Airborne Radionuclides

2nd Quarter 2017 Data Uranium µCi/ml Th-230 µCVml Ra-226 µCi/ml Pb-210 µCi/m

8.0E-15 O.OE+OO NA N/A

0.4% 0.0%

2.2E-14 O.OE+OO NA NA

1.1% 0.0%


0.0% 0.0%

5.8E-16 1.1E-16 NA 1.1E-15

0.0% 0.4%


0.1% 0.0%

Lab LLD's Uranium= 1.0E-16 Th-230 = 1.0E-16 Ra-226 = 1.0E-16 Pb-210 = 2.0E-15

1.0E-16 9.4E-15 6.BE-17 1.6E-15

0.0% 1.6%

0.0E+OO 9.2E-15 NA 1.3E-15

0.0% 1.5%

O.OE+OO 7.5E-15 NA 1.7E-15

0.0% 1.3%

O.OE+OO 2.0E-15 NA 1.1E-15

0.0% 0.3%

O.OE+OO 8.1E-15 NIA 1.5E-15

0.0% 1.4%

O or N/D =Non Detectable



Table 9 Uranium One USA, Inc.

Location 1st Quarter 2017 2nd Quarter 2017 Location Average 2017 mrem/quarter m rem/quarter mrem/quarter

IRIGARAY PROJECT

Control 46.7 39.1 NA IR-1 (Downwind of Restricted Area) 2.4 8.8 5.6

IR-3 (Upwind of Restricted Area) 30.8 37.0 33.9 IR-4 (North Road) 0.6 7.1 3.9

IR-5 (lrigaray Ranch) 0.3 2.4 1.4 IR-6 (Ridge Road S.E. - Background) -1.6 5.8 2.1 IR-13 (l.R. Employee House Trailer) 1.7 5.8 3.8

R-14 (l.R. Employee House Trailer inside -2.1 2.5 0.2 Quarterly Average 4i6 9.9 7.3

CHRISTENSEN PROJECT

AS-1 (Table Mountain - Background) 2 1.6 1.8 AS-5A(CR Plant Upwind S.E. ) 4.4 9.7 7.1

AS-5B (CR Plant Downwind N.W.) 2.4 10.2 6.3 AS-6 (Christensen Ranch ) 3.4 7.4 5.4

AS-7 (C.R. Employee House Trailer) -0.2 3.2 1.5 r-.s-8 (C.R. Employee House Trailer inside -7.0 0.3 -3.4

AS-9 (Mine Unit 7) -2.7 3.6 0.5 AS-10 (C.R. Wellfield Module 8-6) 6.7 7.7 7.2

AS-11 (Water Tank) 6.5 5.1 5.8 AS-12 (Mine Unit 10) 0.1 5.9 2.4 AS-13 (Substation)* 1.8 1.8 1.8

Quarterly Average 2.4 6.4 4.4 *Location AS-13 2nd quarter lost badge

August2017 Page 20 of20

Environmental Gamma Radiation Monitoring

Year to Date Total 2017 mrem/quarter

NA 11.2 67.8 7.7 2.7 4.2 7.5 0.4 7.3

3.6 14.1 12.6 10.8 3.0 -6.7 0.9 14.4 11.6 9.6 3.6 4.4



Table 10 Page of 1of1 Uranium One USA, Inc-Willow Creek Project 2016 Semi-Annual Effluent and Monitoring Report SERP Summary

SERP No. Date SERP Topic

SERP 17-01 2/28/17 Not Completed in progress

Well Stimulation Test Utilizing Air SERP 17-02 6/20/2017

Injection

August 2017

Evaluation Summary

Not Completed in Progress

Test to determine if air injection into the ore zone would improve uranium recovery while reducing reagent costs.

2017 Semi-Annual Effluent And Monitoring Report


Documents

Willow Creek Project - Semi-Annual Effluent and ... · survey report will be included in the 2nd half 2017 semi-annual effluent report which will be submitted in February 2018. Please