ML22175A198

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Cimarron Environmental Response Trust Uranium Daughters in Groundwater
ML22175A198
Person / Time
Site: 07000925
Issue date: 06/24/2022
From: Lux J
Environmental Properties Management
To: Davis P, Robert Evans, James Smith
Document Control Desk, Office of Nuclear Material Safety and Safeguards, State of OK, Dept of Environmental Quality (DEQ)
References
Download: ML22175A198 (36)


Text

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environmental properties management, LLC June 24, 2022 Mr. James Smith U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Paul Davis Oklahoma Department of Environmental Quality 707 North Robinson Oklahoma City, OK 73101 Mr. Robert Evans U.S. Nuclear Regulatory Commission 1600 East Lamar Blvd; Suite 400 Arlington, TX 76011-4511 Re: Docket No. 07000925; License No. SNM-928 Cimarron Environmental Response Trust Uranium Daughters in Groundwater

Dear Sirs:

Solely as Trustee for the Cimarron Environmental Response Trust (CERT), Environmental Properties Management LLC (EPM) submits herein information on the potential presence of certain radionuclides in groundwater at the Cimarron site. This document is a revision of the May 2, 2022, submittal with the same title; it contains corrections in response to comments by the Oklahoma Department of Environmental Quality (DEQ).

In a letter dated August 11, 2021, the U.S. Nuclear Regulatory Commission (NRC) requested information regarding the potential presence of daughter radionuclides in groundwater. On November 23, 2021, EPM provided information on the daughters of U-235 and U-238 that may be present in groundwater.

EPM provided analytical results for groundwater samples collected in October (Attachments 1 and 2) to the NRC and the DEQ in a December 1, 2021 , email. EPM further discussed the presence (of lack thereof) of uranium daughters in groundwater at the Cimarron site.

In a letter dated January 19, 2022, the Oklahoma Department of Environmental Quality (DEQ) stated that the information provided by EPM in the December 1, 2021, email did not mention U-234 (as a daughter of uranium) and asked if it is reasonable to state that the U-234 was already present in the feedstock received by the facility.

The intent of this letter is to present a fuller explanation of our understanding regarding daughter radionuclides in site groundwater and to respond to the DEQ' s question regarding the source of the U-234 detected in site groundwater.

9400 Word Porkwoy

  • jlux@envpm.[Om

U-234 in the Uranium Feedstock Purified enriched uranium was received by the Cimarron facility as gaseous uranium hexafluoride (UF6). The ratio of uranium isotopes in the feedstock varied as the U-235 enrichment varied. Enrichment is expressed in terms of the weight percent (wt. %) of the mass of U-235 relative to the mass of all uranium isotopes. Attachment 3 presents the percentage of the total mass of uranium for all three uranium isotopes as enrichment increases.

As enrichment increases, the total activity per gram of total uranium increases. Attachment 3 shows that the activity per gram of 5% enriched uranium is over 31/2 times the activity per gram of natural uranium (0.711 wt. % U-235). Based on the specific activity of each uranium isotope, the activity percentage for each isotope was calculated.

The Cimarron facility received UF6 with a wide range of enrichment values. In 2017-2018, Enercon Services, Inc. evaluated the enrichment of groundwater in areas where the concentration of uranium exceeds the NRC criterion for groundwater. Enrichment values varied from 1.3 % in Burial Area #1 (BAI) to 2.9% in the W AA U>DCGL remediation area.

Looking at the graph in Attachment 3, at 1.3% enrichment, 100 pCi/g of total uranium activity in the feedstock would consist of approximately 60 pCi/g of U-234, 3 pCi/g of U-235, and 37 pCi/g of U-238. At 2.9% enrichment, 100 pCi/g of total uranium activity in the feedstock would consist of approximately 75 pCi/g of U-234, 4 pCi/g of U-235, and 21 pCi/g of U-238. This means that the feedstock received by the Cimarron facility contained U-234 at significantly higher activity concentrations than that of U-238, although the mass concentration of U-238 would have consistently been above 95% of the total uranium mass concentration.

Daughter Radionuclides in the Feedstock The fa_cility received chemically purified uranium, which means that when the UF6 was produced it did not contain any daughter isotopes. Attachment 4 presents the decay chains for U-235 and U-238. These charts provide the half-lives of each radionuclide in the decay chain. After seven half-lives, the activity of a daughter radionuclide would become essentially equal to the activity of the parent. The decay chain for U-235 indicates that only one week would be required for Th-231 to achieve the same activity as U-235, whereas it would take over two hundred thousand years for Pa-231 to achieve that activity.

The decay chain for U-238 indicates that approximately seven months would be required for Th-234 (and then only minutes for Pa-234) to reach equilibrium with U-238, but it would take most of two million years for U-234 to achieve that same activity. With the passage of only five decades, the activity concentration ofU-234 generated from the decay of U-238 would be far less than 0.01 % of the activity concentration of the U-238. Consequently, the only U-234 that could be present in groundwater (excluding naturally occurring uranium) is the U-234 that was received in the feedstock.

9400 Word Porkwoy

  • Konsos [ity, MO 6411 4405-642-5152
  • j!ux@envpm.com Poge2of5

If we assume that the licensed material was still on site for at least seven months after the production of the UF6, then the activity concentration of Th-234 and Pa-234 would be the same as the U-238, and the activity concentration of Th-231 would be the same as the U-235.

With a half-life of over 75,000 years, Th-230 would not achieve equilibrium with its parent U-234 for several hundred thousand years; hence, similar to the above description of U-234, the activity concentration of Th-230 generated from the decay of U-234 would be less than 0.01 % of the activity concentration of U-234.

Daughter Radionuclides in Groundwater It is important to understand that the presence of uranium in groundwater does not mean that its short-lived daughters are present in the groundwater. When uranium decays by alpha emission, the thorium daughters that are formed are chemically different from their uranium parent. Their presence in groundwater would be a function of the solubility of the thorium compound that is created. If the distribution coefficient (Kd) for the thorium compound that forms when uranium undergoes decay is significantly higher than that of the uranium compound, the thorium will sorb onto soil particles and no longer remain in solution.

The activity concentration of uranium in groundwater in the WAA U>DCGL remediation area has rarely exceeded 200 pCi/L total uranium since 2010. At 2.9% enrichment, 200 pCi/L total uranium would yield approximately 150 pCi/L U-234, 8 pCi/L U-235, and 42 pCi/L U-238. If the thorium and protactinium daughters were in equilibrium (in the groundwater) with the parent uranium isotopes, you would expect to have 8 pCi/L Th-231 and 42 pCi/L Th-234 and Pa-234 in the groundwater. With detection limits of 100 pCi/L for Th-231 and Pa-231, and 400 pCi/L for Th-234, none of these daughter isotopes could be detected.

Burial Area #1 is the only remediation area in which uranium activity concentrations are high enough that daughter radionuclides may be detected. Four monitor wells that were to be sampled during the 4 th quarter 2021 redox sampling event routinely yield over 700 pCi/L total uranium; two routinely yield over 1,600 pCi/L total uranium. At 1.3% enrichment, 1,600 pCi/L total uranium would yield approximately 960 pCi/L U-234, 48 pCi/L U-235, and 592 pCi/L U-238. If (in the groundwater) the thorium and protactinium daughters were in equilibrium with the parent uranium isotopes, you would expect to have 48 pCi/L Th-231, 592 pCi/L Th-234, and 592 pCi/L Pa-234 in the groundwater. Th-231 would not be detectable at 48 pCi/L, but both Th-234 and Pa-234 would be.

The half-life of Pa-234 is less than 2 minutes, and the groundwater samples were analyzed for thorium and protactinium twelve days after the sample was collected. If any groundwater sample contained over 100 pCi/L Th-234, the concentration of Pa-234 would have been above its detection limit. Attachments 1 and 2 show that none of the daughter radionuclides were detected in any of the groundwater samples, so no sample could have contained over 100 pCi/L Th-234.

9400 Word Porkwoy

  • Konsos City, MO 6411 4405-642-S152
  • ifux@envpm.com Poge J ofS

Conclusion None of the uranium daughters were detected in any of the groundwater samples submitted for isotopic analysis. The data demonstrates that the short-lived daughters of uranium can at most be present in groundwater at the Cimarron site at a small fraction of the concentration of the uranium parent radionuclides.

The uranium in recovered groundwater will be captured by ion exchange resin, and it is anticipated that the ion exchange resin will continue to adsorb uranium for several months between change-outs. The daughter radionuclides may be present in the ion exchange resin; even if the resin does not capture any of the daughter radionuclides, they will not be detectable in the effluent.

Please call me at (405) 642-5152, email me atjlux@envpm.com, or respond by written correspondence should you have questions or desire clarification.

Sincerely, y~

Jeff Lux, P .E.

Project Manager cc: Michael Broderick, Oklahoma Department of Environmental Quality NRC Public Document Room 9400 Word Porkwoy

  • j!ux@envpm.com Poge 4 off

ATTACHMENT I GEL LABORATORY REPORT NOVEMBER 11, 2021 9400 Word Porkwoy

  • j!ux@envpm.com

m~ *ILaboratories LLC PO Box30712 ChalleslOrl. SC29417 2040 S3vage Road Challeswr1. SC 29407 a member of The GEL Group INC P 843.556Jl171 F 843.766.1178 ge l.com November 11, 2021 Mr. Jeff Lux Environmental Properties Management, LLC 615 N. Hudson Suite 200 Oklahoma City, Oklahoma 73102 Re: Uranium Daughter Activities Evaluation Work Order: 559068

Dear Mr. Lux:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the following analytical results for the sample(s) we received on October 15, 2021. This original data report has been prepared and reviewed in accordance with GEL's standard operating procedures.

Test results for NELAP or ISO 17025 accredited tests are verified to meet the requirements of those standards, with any exceptions noted. The results reported relate only to the items tested and to the sample as received by the laboratory. These results may not be reproduced except as full reports without approval by the laboratory. Copies ofGEL's accreditations and certifications can be found on our website at www.gel.com.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4289.

Sincerely,

~~

Grace Bodiford for Julie Robinson Project Manager Purchase Order: 176069 Chain of Custody: 2021-059 Enclosures

Table of Contents Case Narrative .................................................................................... l Chain of Custody and Supporting Documentation ......................... 4 Laboratory Certification .................................................................... 7 Radiological Analysis ......................................................................... 9 Case Narrative .......................................................................... I 0 Sample Data Summary ............................................................ 14 Quality Control Summary ....................................................... 19

Case Narrative Page 1 of 22 SDG: 559068

CASE NARRATIVE for Burns & McDonnell Uranium Daughter Activities Evaluation SDG:559068 November 11, 2021 Laboratory Identification:

GEL Laboratories LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at GEL Laboratories LLC, Charleston, South Carolina on October 15, 2021 for analysis. The samples were delivered with proper chain of custody documentation and signatures. All sample containers arrived without any visible signs of tampering or breakage. There are no additional comments concerning sample receipt.

Items of Note There are no additional items of note concerning this SDG.

Sample Identification The laboratory received the following samples:

Laboratory ID Client ID 559068001 TMW-13 559068002 02W02 559068003 02W01 559068004 TMW-09 Case Narrative Sample analyses were conducted using methodology as outlined in GEL Laboratories, LLC (GEL) Standard Operating Procedures. Any technical or administrative problems during analysis, data review, and reduction are contained in the analytical case narratives in the enclosed data package.

Data Package The enclosed data package contains the following sections: Case Narrative, Chain of Custody, Cooler Receipt Checklist, Data Package Qualifier Definitions and data from the following fractions: Radiochemistry.

GEL Laboratories u.c PO Bax 30112 Charleston, sc 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gaI.com Page 2 of 22 SDG: 559068

This data package, to the best ofmy knowledge, is in compliance with technical and administrative requirements.

~~

Grace Bodiford for Julie Robinson Project Manager GEL Laboratories u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com Page 3 of22 SDG: 559068

Chain of Custody and Supporting Documentation Page 4 of 22 SDG: 559068

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0 CHAIN OF CUSTODY RECORD AND ANALYSIS REQUEST coc # : 2021-059 N SHIP TO: SHIP FROM: ANALYSIS REQUESTED N

Company Name: GEL Laboratories LLC VJ Address: 2040 Savage Road Environmental Properties Management v

C) Address: Charleston, SC 29407 100 North Highway 74

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0 Ol 0 Guthrie, OK 73044 a Contact Person: Julie Robinson

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!2 0\ I ATTEST THAT THE PROPER FIELD SAMPLING PROCEDURES WERE USED DURING THE Contact Person: Jeff Lux I") E 00 COLLECTION OF THESE SAMPLES. ~ I')' co

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CIMARRON FACILITY **---- s:: N WATER I-  ::>

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PRESERV. FILTERED

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TMW-13 10/13/2021 945 1 p 2L X HN03 y X TMW-13 10/13/2021 945 1 p 500ml X HN03 y X 02W02 10/13/2021 1125 1 p 2L X HN03 y X 02W02 10/13/2021 1125 1 p 500ml X HN03 y X 02W01 10/13/2021 1450 1 p 2L X HN03 y X 02W01 10/13/2021 1450 1 p 500ml X HN03 y X TMW-09 10/13/2021 1550 1 p 2L X HN03 y X TMW-09 10/13/2021 1550 1 p 500ml X HN03 y X Potential Hazardous Characteristics Sample Disposal Non-Haz D RCRA 0001,2&3, or 4 D RCRA Listed D Radioactive D Unknown 111 Disposal Lab 0 Return to Client 0 Holding pending further instructions PROJECT NAME: Uranium Daughter Activities Evaluation PO#: 176069 THIS SAMPLE MEETS ALL APPROPRIATE RADIOLOGICAL REQUIREMENTS: HP INITIAL: BA NOTES:

Distribution:

RELINQUISHED BY SAMPLER: DATE: TIME: RECEIVED BY: DATE: TIME:

Standard GEL EDD & GEL lab report in .pdf format to:

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  • jlux@envpm.com

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- jmaisler@enercon.com RELINQUISHED BY : DATE: TIM E: ~EDBY : DATE: TIME:

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- dhorne@burnsmcd.com PAGE 1 OF OOCUMENTCONTROtc

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SAMPLE RECEIPT & REVIEW FORM .,. . - -

Client: SDG/AR/COC/Wo!'k Order: S ~ 0 t (----:,( o '2._,. ii Received Ily: BE Date Received: IIj(

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Suspected Huwrd lnfonnntion i. *If Net Counts> IOOcpm on smnplcs not marked "radioactive". contact !he Radiation Safify Group for further investigation.

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Hazru-d Class Shipped: UNI/: I\

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rr UN29 I0. Is the Rndioactivc Shipment Su"*cy Compliant? Yes.,...,- No 7 B) Did the client designate the samples are ta b.:

received M r:idioactivc?

\ COC notation or radioactive stickers on comainers equal clieltl cle~ignation. Jl C) Did the RSO classify the samples :,s radioactivtl?

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Maximum Net Counts Obse,ved*' (Observed Counts -Ar.a Background Counts):

Cl:u;sificd u.~: R:td I Rad 2 Rud 3 . - p

(_y/,...,.,~) mRiHr COC notation or haznrd labels on containers equal client designation .

.; D) Did the client desil!lmle samples arc hazardous? .. .. .

If Dor Eis yes. select Hazards below.

E) Did the RSO identify possible haznrds? I\.-.:

PCB's Flammable Foreign Soil RCRA Asbestos Beryllium Snmplc Receipt Criteria z Cut11111c11ti/Qu:11ificrs (Required £or No11-Conron11dlc Items)

Circle Applic.:iblc: Scill'i broken O.tmagcd con1:.i incr Uaking contnincr Oth<!r (d~£Cribc)

Shipping containers reccivcc.l intact a11c.l 1 scab!?

\ Circle Applic.iblc: Cliclll conlacu:d and pro,ided COC COC cr..:-uh:d upon receipt

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F 2 Chain of custody c.lucumcnts inclltdcd with shipmenl? \ -

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Preservation Method: Wet Ice Ice Pncks Dry ice ;None J Other:

3 Samples requiring cold preservation within (0 < 6 <leg. C)?* \ *n111cmpcra1u1*es are recorded in Celsius \..-/ TEMP:

Daily check performed and passed 011 IR Tcmpcmtt:rc Device Scri<1I #:,.elRe.,2,.-,,2..,.1_____

4 temperature gun?

II' Sccond:uy Tcmper.iturc Device Serini II (If A~plicable):

Circle Applkabla: Seals- tl1*okc:n Damar,cd container U';tkin,s con1;.1.incr Other (describe) 5 Sample containers intact and sc.1led'/

\ Sample ID's nnd Containers Affeclcd:

Samples requiring chemical preservation 6 at proper pH?

\ If Prc:s:cn.11ion .Jddcd. Lot#:

lf-Y<s, are Encores or Soil Kits present for solids? Yes_ No_ NA_(lf ycs. t:ik{ to vo}:.* Freezer)

Do liquid VOA vials contni11 acid preservation? Yes_ No_ NA_(lf unknown,\sclcct No)

Du ony samples require Volatile 7

Analysis? Ar. liquid VOA vinls free orhcadspace?Ycs_ No_ NA_ f Sample ID's and containers .iffcctcd:

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!D's and te.,ts affected:

8 Samples received within holding time?

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Sample lD's urr CDC match ID's on !D's and conlaincrs affected:

9 bottles? \

Date & time on COC match date & time Circle Applicable: No dates on containers No times on coniainers coc missin~ i11fo Other (describe) 10 011 bo1tles? \ - I I

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Number of comaincrs received match Circle Applicable: No conlnincrcount 011 COC Other (describe) 11 number indicutcc.l on CDC'?

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Arc sample comainers idcntifiabk as 12 GEL provided bv use uf GEL labels? .

CDC form is properly signed in Circle Applicable: Nm relinquished Other (demibcl 13 relinquishcc.1/rccci vco.l ~clions?

Commcn1s (Use Continuation f'orm ir needed):

1 I PM (or PM Al review: Initials I\ HZJ _;- Date I D! JcS !"(., I l'ngc__lor_l___

Page 6 of22 SDG: 559068 GL-CHL-SR-001 Rev 7

Laboratory Certification Page 7 of 22 SDG: 559068

List of current GEL Certifications as of 11 November 2021 State Certification Alabama 42200 Alaska 17-018 Alaska Drinking Water SC000l2 Arkansas 88-0651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH-0169 DoD ELAP/ ISO 17025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P330-15-00283,P330-15-00253 Georgia SC00012 Georgia SOWA 967 Hawaii SC00012 Idaho SC00012 lllinois NELAP 200029 Indiana C-SC-01 Kansas NELAP E-10332 Kentucky SOW A 90129 Kentucky Wastewater 90129 Louisiana Drinking Water LA024 Louisiana NELAP 03046 (AI33904)

Maine 2019020 Maryland 270 Massachusetts M-SC0l2 Massachusetts PF AS Approv Letter Michigan 9976 Mississippi SC00012 Nebraska NE-OS-26-13 Nevada SC000122021-1 New Hampshire NELAP 2054 New Jersey NELAP SC002 New Mexico SC000l2 New York NELAP 11501 North Carolina 233 North Carolina SDW A 45709 No1ih Dakota R-158 Oklahoma 2019-165 Pennsylvania NELAP 68-00485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 Sanitation Districts ofL 9255651 South Carolina Chemistry 10120001 Tennessee TN 02934 TexasNELAP T104704235-21-19 Utah NELAP scooo 122021-36 Vermont VT87156 Virginia NELAP 460202 Washington C780 Page 8 of 22 SDG: 559068

Radiological Analysis Page 9 of22 SDG: 559068

Case Narrative Page 10 of22 SDG: 559068

Radiochemistry Technical Case Narrative Burns & McDonnell SDG #: 559068 Product: Alphaspec U, Liquid Analytical Method: DOE EML HASL-300, U-02-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 28 Analytical Batch: 2191040 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 559068001 TMW-13 559068002 02W02 559068003 02W01 559068004 TMW-09 1204943045 Method Blank (MB) 1204943046 55906800l(TMW-13) Sample Duplicate (DUP) 1204943047 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Product: Gammaspec, Gamma, Liquid Analytical Method: EPA 90 I. 1 Analytical Procedure: GL-RAD-A-013 REV# 27 Analytical Batch: 2186917 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 559068001 TMW-13 559068002 02W02 559068003 02W0I 559068004 TMW-09 1204934355 Method Blank (MB) 1204934356 55906800J(TMW-13) Sample Duplicate (DUP) 1204934357 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

Page 11 of 22 SDG: 559068

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Qualifier Information Client Qualifier Reason Analyte Sample Sample Results are considered a false positive due to UI Thorium-234 559068004 TMW-09 high peak-width.

Results are considered a false positive due to UI Thorium-231 559068001 TMW-13 interference.

Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.

Page 12 of 22 SDG: 559068

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Qualifier Definition Report for CMRN00 1 Burns & McDonnell Client SDG: 559068 GEL Work Order: 559068 The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria
    • Analyte is a Tracer compound U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOO.

UT Gamma Spectroscopy--Uncertain identification ReviewN alidation GEL requires all analytical data to be verified by a qualified data reviewer. In addition, all CLP-like deliverables receive a third level review of the fractional data package.

The following dJ~ validator verified the information presented in this data rep011:

Signature:

  • _).ll~-::1. {l /1J Name: Theresa Austin Date: 11 NOV 2021

Title:

Group Leader Page 13 of22 SDG: 559068

Sample Data Summary Page 14 of22 SDG: 559068

GELLABORATO~ESLLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company: Environmental Properties Address: Management, LLC 615 N. Hudson Suite 200 Oklahoma City, Oklahoma 73 102 Report Date: November 11 , 2021

Contact:

Mr. Jeff Lux Project: Uranium Daughter Activities Evaluation Client Sample ID: TMW-13 Project: CMRN00620 Sample ID: 559068001 Client ID: CMRN00J Matrix: Water Collect Date: 13-OCT-21 Receive Date: 15-OCT-21 Collector: Client Parameter Qualifier Result Uncertainty MDC TPU RL Units PF DF Analyst Date Time Batch Mtd.

Rad Alpha Spec Analysis Alphaspec U, Liquid "As Received" Uranium-233/234 602 +/-21.8 1.84 +/-130 1.00 pCi/L BVI 11/10/21 1131 2191040 I Uranium-235/236 38.4 +/-6.14 1.21 +/-10.2 1.00 pCi/L Uranium-238 364 +/-16.9 1.51 +/-79.3 1.00 pCi/L Rad Gamma Spec Analysis Gammaspec, Gamma, Liquid As Received" Protactinium-234 U 24.4 +/-30.3 71.2 +/-42.6 pCi/L MXRI 10/25/21 0845 2186917 2 Thorium-231 VI 0.000 +/-108 107 +/-110 pCi/L Thorium-234 u 80.3 +/-311 585 +/-314 pCi/L The following Analytical Methods were performed Method Description DOE EML HASL-300, U-02-RC Modified 2 EPA 9011 Surrogate/Tracer Recovery Test Batch ID Recovery% Acceptable Limits Uranium-232 Tracer Alphaspec U, Liquid "As Received" 2191040 30.1 (15%-125%)

Notes:

The MDC is a sample specific MDC.

TPU and Counting Uncertainty are calculated at the 95% confidence level ( 1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Mtd.: Method DL: Detection Limit PF: Prep Factor Le/LC: Critical Level RL: Repo1iing Limit MDA: Minimum Detectable Activity TPU: Total Propagated Uncertainty MDC: Minimum Detectable Concentration Page 15 of 22 SDG: 559068

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company: Environmental Properties Address: Management, LLC 615 N. Hudson Suite 200 Oklahoma City, Oklahoma 73102 Report Date: November 11, 2021

Contact:

Mr. Jeff Lux Project: Uranium Daughter Activities Evaluation Client Sample ID: 02W02 Project: CMRN00620 Sample ID: 559068002 Client ID: CMRN00l Matrix: Water Collect Date: 13-OCT-21 Receive Date: 15-OCT-21 Collector: Client Parameter Qualifier Result Uncertainty MDC TPU RL Units PF DF Analyst Date Time Batch Mtd.

Rad Alpha Spec Analysis Alphaspec U, Liquid "As Received" UraniLUn-233/234 418 +/-17.5 2.12 +/-88.9 1.00 pCi/L BVI 11 / 10/21 1131 2191040 I Uranium-235/236 38.2 +/-5.91 1.13 +/-9.93 1.00 pCi/L Uranium-238 309 +/-15.1 171 +/-66.1 1.00 pCi/L Rad Gamma Spec Analysis Gammaspec, Gamma, Liquid "As Received" Protactinium-234 U -14.5 +/-26.3 49.0 +/-31.8 pCi/L MXRl 10/25/21 0845 2186917 2 Thorium-231 U 2.05 +/-77.5 128 +/-77.5 pCi/L Thorium-234 U -247 +/-321 577 +/-344 pCi/L The following Analytical Methods were performed Method Description DOE EML HASL-300. U-02-RC Modified 2 EPA 901.1 Surrogate/Tracer Recovery Test Batch ID Recovery% Acceptable Limits Uranium-232 Tracer Alphaspec U, Liquid "As Received" 2191040 30.7 (15%-125%)

Notes:

The MDC is a sample specific MDC.

TPU and Counting Uncertainty are calculated at the 95% confidence level (l.96-sigma).

Column headers are defined as follows:

OF: Dilution Factor Mtd.: Method DL: Detection Limit PF: Prep Factor Le/LC: Critical Level RL: Repo1iing Limit MDA: Minimum Detectable Activity TPU: Total Propagated Uncertainty MDC: Minimum Detectable Concentration Page 16 of22 SDG: 559068

GEL LABO RA TORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company: Environmental Properties Address: Management, LLC 615 N. Hudson Suite 200 Oklahoma City, Oklahoma 73102 Report Date: November 11, 2021

Contact:

Mr. Jeff Lux Project: Uranium Daughter Activities Evaluation Client Sample ID: 02W0I Project: CMRN00620 Sample ID: 559068003 Client ID: CMRN00I Matrix: Water Collect Date: 13-OCT-21 Receive Date: 15-OCT-21 Collector: Client Parameter Qualifier Result Uncertainty MDC TPU RL Units PF DF Analyst Date Time Batch Mtd.

Rad Alpha Spec Analysis Alphaspec U, Liquid "As Received" Uranitun-233/234 1040 +/-35.3 3.22 +/-281 1.00 pCi/L BVI 11/10/21 1356 2191040 l Uranium-235/236 74.2 +/-10.5 1.15 +/-22.4 1.00 pCi/L Uranium-238 604 +/-26 .9 2.05 +/-164 1.00 pCi/L Rad Gamma Spec Analysis Gammaspec, Gamma, Liquid As Received" Protactinium-234 U 3.89 +/-38.5 79.2 +/-38.8 pCi/L MXRl 10/25/21 0846 2186917 2 Thorium-231 U 77.6 +/-145 109 +/-145 pCi/L Thorium-234 U -222 +/-322 559 +/-342 pCi/L The following Analytical Methods were performed Method Description DOE EML HASL-300, U-02-RC Modified 2 EPA 9011 Surrogate/Tracer Recovery Test Batch ID Recovery% Acceptable Limits Uranium-232 Tracer Alphaspec U, Liquid "As Received" 2191040 18.4 (15%-125%)

Notes:

The MDC is a sample specific MDC.

TPU and Counting Unce11ainty are calculated at the 95% confidence level (l.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Mtd.: Method DL: Detection Limit PF: Prep Factor Le/LC: Critical Level RL: Repo11ing Limit MDA: Minimum Detectable Activity TPU: Total Propagated Uncertainty MDC: Minimum Detectable Concentration Page 17 of 22 SDG: 559068

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company: Environmental Properties Address: Management, LLC 615 N. Hudson Suite 200 Oklahoma City, Oklahoma 73102 Report Date: November 11, 2021

Contact:

Mr. Jeff Lux Project: Uranium Daughter Activities Evaluation Client Sample ID: TMW-09 Project: CM.RN00620 Sample ID: 559068004 Client ID: CMRN00l Matrix: Water Collect Date: 13-OCT-2 l Receive Date: J5-OCT-21 Collector: Client Parameter Qualifier Resu lt Uncertainty MDC TPU RL Units PF OF Analyst Date Time Batch Mtd.

Rad Alpha Spec Analysis Alphaspec U, Liquid "As Received" Uranium-233/234 950 +/-29.3 1.97 +/-216 1.00 pCi/L BVI 11/10/21 1356 2191040 I Uranium-235/236 58.0 +/-8.08 1.61 +/-15.4 1.00 pCi/ L Uranium-238 660 +/-24.4 1.74 +/-151 1.00 pCi/L Rad Gamma Spec Analysis Gammaspec, Gamma, Liquid "As Received" Protactinium-234 u -13.4 +/-47.6 84.7 +/-50.4 pCi/L MXRl 10/25/21 0854 2186917 2 Thorium-231 u -8.39 +/-95 .9 165 +/-95.9 pCi/L Thorium-234 UI 0.000 +/-815 530 +/-843 pCi/L The following Analytical Methods were performed Method Description DOE EML HASL-300, U-02-RC Modified 2 EPA 901.1 Surrogate/Tracer Recovery Test Batch ID Recovery% Acceptable Limits Uranium-232 Tracer Alphaspec U, Liquid "As Received" 2191040 26.7 (15%-125%)

Notes:

The MDC is a sample specific MDC.

TPU and Counting Uncetiainty are calculated at the 95% confidence level ( 1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Mtd.: Method DL: Detection Limit PF: Prep Factor Le/LC: Critical Level RL: Repotiing Limit MDA: Minimum Detectable Activity TPU: Total Propagated Uncertainty MDC: Minimum Detectable Concentration Page 18 of22 SDG: 559068

Quality Control Summary Page 19 of 22 SDG: 559068

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summar.1: Report Date: November 11, 2021 Client: Environmental Properties Management, LLC Page 1 of 3 615 N. Hudson Suite 200 Oklahoma City, Oklahoma

Contact:

Mr. Jeff Lux

\Vorkorder: 559068 Parmname NOM Sample Qual QC Units RPO% REC% Range Anlst Date Time Rad Alpha Spec Batch 2191040 QC 1204943046 559068001 DUP Uranium-2331234 602 553 pCilL 8.45 (0%-20%) BVI 1111012113:56 Uncert: +l-21 .8 +l-20 .2 TPU: +l-130 +l-120 Uranium-2351236 38.4 32.7 pCi/L 16.2 (0%-20%)

Uncert: +l-6.14 +l-5.48 TPU: +l-10.2 +l-8.88 Uranium-238 364 339 pCi/L 7.03 (0%-20%)

Uncert: +l-16.9 +l-15.8 TPU: +l-79.3 +l-74.3 QC1204943047 LCS Uranium-233/234 26.0 pCilL BV1 11/10121 13 :56 Uncert: +l-2.57 TPU: +l-4.32 Uranium-2351236 1.39 pCi/L Uncert: +l-0.692 TPU: +l-0.716 Uranium-238 27.1 28.4 pCilL 105 (75%-125%)

Uncert: +l-2.67 TPU: +l-4.63 QC 1204943045 MB Uranium-2331234 u -0.0464 pCi/L BVl 11/1012113 :56 Uncert: +l-0.258 TPU: +l-0.258 Uranium-235/236 u 0.0245 pCi/L Uncert: +l-0.256 TPU: +l-0.256 Uranium-238 u 0.252 pCi/L Uncert: +l-0.351 TPU: +l-0.353 Rad Gamma Spec Batch 2186917 QC 1204934356 55906800 I DUP Protactinium-234 u 24.4 u -41.4 pCi/L 0 NIAMXRl 10/25/2111 :07 Uncert: +l-30.3 +l-45.0 TPU: +l-42.6 +l-68.1 Thorium-231 Ul 0.000 u 43.4 pCi/L 0 N IA Uncert: +l-108 +l-106 TPU: +l-110 +l-106 Thorium-234 u 80.3 u 241 pCi/L 0 NIA Uncert: +l-311 +l-430 TPU: +l-434 Page 20 of 22 SDG: 559068

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com QC Summary Workorder: 559068 Page 2 of 3 Parmname NOM Sample Qua[ QC Units RPO% REC3/4 Range Anlst Date Time Rad Gamma Spec Batch 2186917

+/-314 QC 1204934357 LCS Americium-241 1.09£+05 I.I 8E+05 pCi/L 109 (75%-125%) MXRI 10/25/2109: 15 Uncert: +/-2070 TPU: +/-11100 Cesium- 137 37800 39900 pCi/L 105 (75%-125%)

Uncert: +/-676 TPU: +/-3450 Cobalt-60 21400 22700 pCi/L 106 (75%-125%)

Uncert: +/-614 TPU: +/-2140 Protactinium-234 u 70.5 pCi/L Uncert: +/-1200 TPU: +/- 1210 Thorium-231 u 93.4 pCi/L Uncert: +/-990 TPU: +/-991 Thorium-234 u -1060 pCi/L Uncert: +/-2650 TPU: +/-2700 QC l 204934355 MB Protactinium-234 u 3.80 pCi/L MXR I I 0/25/2 108 :46 Uncert: +/-41.5 TPU: +/-41.7 Thorium-231 u 19.8 pCi/L Uncert: +/-45.4 TPU: +/-46.3 Thorium-234 u -185 pCi/L Uncert: +/-219 TPU: +/-238 Notes:

TPU and Counting Uncertainty are calculated at the 95% confidence level ( 1.96-sigma).

The Qualifiers in this report are defined as follows:

    • Analyte is a Tracer compound

< Result is less than value reported

> Result is greater than value reported BO Results are either below the MDC or tracer recovery is low FA Failed analysis.

H Analytical holding time was exceeded

.r See case narrative for an explanation J Value is estimated K Analyte present. Reported value may be biased high. Actual value is expected to be lower.

L Analyte present. Reported value may be biased low. Actual value is expected to be higher.

Page 21 of 22 SDG: 559068

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com QC Summary Workorder: 559068 Page 3 of 3 Parmname NOM Sample Qual QC Units RPO% REC% Range Anlst Date Time M M if above MDC and less than LLD M REMP Result > MDC/CL and < RDL N/A RPO or %Recovery limits do not apply .

NI See case narrative ND Analyte concentration is not detected above the detection limit NJ Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Q One or more quality control criteria have not been met. Refer to the applicable nmrntive or DER.

R Sample results are rejected u Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

UI Gamma Spectroscopy--Unce1tain identification UJ Gamma Spectroscopy--Uncertain identification UL Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias.

X Consult Case NmTative, Data Summary package, or Project Manager concerning this qualifier y Other specific qualifiers were required to properly define the results. Consult case narrative.

RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.

h Preparation or preservation holding time was exceeded NI A indicates that spike recovery limits do not apply when sample concentration exceeds spike cone. by a factor of 4 or more or %RPO not applicable.

    • Indicates analyte is a surrogate/tracer compound.

/\ The Relative Percent Difterence (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptence criteria when the sample is greater than five times (5X) the contract required detection limit (RL). ln cases where either the sample or duplicate value is less than 5X the RL a control limit of+/- the RL is used to evaluate the DUP result.

For PS, PSD, and SOIL T results, the values listed are the measured amounts, not final concentrations.

Where the analytical method has been pe1formed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.

Page 22 of22 SDG: 559068

ATTACHMENT 2 TABULATED DATA

SUMMARY

9400 Word Parkway* Kansas {ify, MO 64114 Tel 40S-o42-SIS2

  • jlux@envpm.com

Cimarron Environmental Response Trust Evaluation of Uranium Daughters in Groundwater Monitor Well Activity TMW13 02W02 02W01 TMW09 (pCi/L)

Result Uncertainty Qual DL Result Uncertainty Qual DL Result Uncertainty Qual DL Result Uncertainty Qual DL U238 364 16.9 1.51 309 15.1 1.71 604 26.9 2.05 660 24.4 1.74 Th234 80.3 311 U 585 247 321 U 577 222 322 U 559 0 815 UI 530 Pa234 24.4 30.3 U 71.2 14.5 26.3 U 49 3.89 38.5 U 79.2 13.4 47.6 U 84.7 U235 38.4 6.14 1.21 38.2 5.91 1.13 74.2 10.5 1.15 58 8.08 1.61 Th231 0 108 UI 107 2.05 77.5 U 128 77.6 145 U 109 13.4 47.6 U 84.7 U234 602 21.8 1.84 418 17.5 2.12 1040 35.3 3.22 950 29.3 1.97 The detection limit for Th234 is too high relative to the U238 activities to tell us anything but Th234 was never detected.

Pa234 was never detected, but the detection limit (that was never reached) was a small fraction of the U238 activity listed below.

Notes:

TMW13 Pa234 DL:U238 Ratio 02W02 Pa234 DL:U238 Ratio 02W01 Pa234 DL:U238 Ratio TMMW09 Pa234 DL:U238 Ratio 0.20 0.16 0.13 0.13 The detection limit for Th231 is too high relative to the U234 activities to tell us anything but Th231 was never detected.

ATTACHMENT 3 DISTRIBUTION OF URANIUM ISOTOPES IN ENRICHED URANIUM 9400 Word Parkway* Kansas {ify, MO 64114 Tel.- 40S-642-Slf2

  • jlux@envpm.com

ATTACHMENT 3 DISTRIBUTION OF URANIUM ISOTOPES IN ENRICHED URANIUM Enrichment Percent Total Mass Specific Activity

(% U-235 by Mass) U-234 U-235 U-238 (pCi/µg) 0.711 0.005 0.711 99.284 U234 6.19E+03 1 0.007 1 98.993 U235 2.14E+00 2 0.013 2 97.987 U238 3.30E01 3 0.019 3 96.981 5 0.031 5 94.969 Above Data from Determination of Conservative U235 Enrichment Levels for Groundwater at Cimarron Site Utilizing ICPMS Data Collected December 2016 Through 2nd Quarter 2017, Revision 0. Enercon Services, Inc. August 2017.

Isotopic Activity (pCi) per µg of Total Enrichment Total U Isotopic Percentage of Total Activity Uranium

(% U-235 by Mass) (pCi/µg)

U-234 U-235 U-238 U-234 U-235 U-238 0.711 31.0 1.5 32.8 65.2 47.4 2.3 50.2 1 43.3 2.1 32.7 78.1 55.5 2.7 41.8 2 80.5 4.3 32.3 117.1 68.7 3.7 27.6 3 117.6 6.4 32.0 156.0 75.4 4.1 20.5 5 191.9 10.7 31.3 233.9 82.0 4.6 13.4 U234 % Activity 85.0 80.0

% of Total Uranium Activity 75.0 70.0 65.0 60.0 55.0 50.0 45.0 40.0 0 1 2 3 4 5 6 Enrichment (% U235 by Mass)

ATTACHMENT 4 DECAY CHARTS FOR U-238 AND U-235 94/JIJ Word Parkway* /(onsos {ify, MO Ml 14 Tel: 40J-o42-SIS2

  • j/ux@envpm.com

rotactinium 1

Thorium 231 olonium 11 ead 07

Thorium horium 234 0 adon 2

lonium 4

ead 06 rcury