A business of Merck KGaA, Darmstadt, GermanySIGI\AA-ALDRICH@ sigma-aldrich. com A business of Merck...

$: A business of Merck KGaA, Darmstadt, GermanySIGI\AA-ALDRICH@ sigma-aldrich. com A business of Merck KGaA, Darmstadt, Germany 3050 Spruce Street, St. Louis, MO 631 03 USA Tel: (800)$
SIGI\AA-ALDRICH@ sigma-aldrich. com

A business of Merck KGaA, Darmstadt, Germany 3050 Spruce Street, St. Louis, MO 631 03 USA

Tel: (800) 521-8956 (314) 771-5765 Fax: (800) 325-5052 (314) 771-5757

September 21, 2017

Peter J. Lee, Ph.D., CHP Materials Control, ISFSI and Decommissioning Branch U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352

RE: NRC License 24-16607-03, Final Status Survey report and request to terminate license

Dr. Lee:

Attached to this cover letter is a report entitled "FINAL STATUS DECONTAMINATION & DECOMMISSIONING SURVEY REPORT," prepared by DDES, LLC under contract with Sigma-Aldrich Manufacturing LLC (Sigma). This report concludes that the total effective dose equivalent (TEDE) from any potential radioactive materials in the specified areas of licensed activities was calculated to be:

• 3300 S Second Street Labs N1111, N1143, and N340- 6.17E-3 mrem/year for 14C • 3300 S Second Street Labs N1111, N1143, and N340- 1.61E-1 mrem/year for

125I • 2909 Laclede Ave Lab G 109 - 1.16E-4 mrem/year for 3 2P

Based on conclusions of this report, Sigma request that license 24-16607-03 be terminated.

Please contact me if you have concerns or questions regarding this license termination request or supporting report.

Sincerely,

.?1 /~}

/ 4J~:e~ /

Thomas K Spencer Radiation Safety Officer Sigma-Aldrich Manufacturing LLC

ATTACHMENT:

FINAL STATUS DECONTAMINATION & DECOMMISSIONING SURVEY REPORT

FINAL STATUS DECONTAMINATION & DECOMMISSIONING SURVEY REPORT

Sigma-Aldrich Manufacturing, LLC 3300 S Second Street and 2909 Laclede Avenue

St. Louis, Missouri

US NRC License #24-16607-03

Prepared for:

Sigma-Aldrich Manufacturing, LLC 3300 S Second Street St. Louis, MO 63118

Prepared by:

DOES, LLC 345 North Ave, 2nd Floor

Wakefield, MA 01880

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cces

AUGUST 3, 2017

1.0

2.0

3.0

4.0

5.0

6.0

7.0

8.0

1.1

2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8

3.1 3.2 3.3

8.1 8.2

fiNAL STATUS DECONTAMINATION & DECOMMISSIONING SURVEY REPORT

Sigma-Aldrich Manufacturing, LLC TABLE OF CONTENTS

EXECUTIVE SUMMARY .............................................................................................. 1

PURPOSE ........................................................................................................................................................... 1

FACILITY OPERATING HISTORY .................................................................................. 3

HISTORICAL SITE ASSESSMENT ............................................................................................................................... 3 LICENSE HISTORY ................................................................................................................................................ 3 RADIOACTIVE MATERIAL USE ................................................................................................................................ 3 POTENTIAL CONTAMINANTS ..•.•.....•.•..•••....•••••....••..•••..•••....•..••....••...•••..•..•...........•••..••••.....•••.....•••.•.....••......•••.... .4 OPERATIONAL RADIOLOGICAL SURVEYS .................................................................................................................. .4 SPILLS AND UNCONTROLLED RELEASE OF RADIOACTIVITY ........................................................................................... .4 POTENTIALLY IMPACTED FACILITIES AND lABORATORIES ............................................................................................ .4 NON-IMPACTED AREAS ........................................................................................................................................ 6

FACILITY REALEASE CRITERIA ..................................................................................... 6

DCGLs AND CLEANUP GoALs ............................................................................................................................. 6 DCGL DEVELOPMENT ......................................................................................................................................... 6

A LARA GOALS .................................................................................................................................................. 7

PROJECT MANAGEMENT AND ORGANIZATION .......................................................... 8

TRAINING ................................................................................................................. 8

ENVIRONMENTAL MONITORING PROGRAM .............................................................. 8

RADIOACTIVE WASTE MANAGEMENT ....................................................................... 8

SURVEY INSTRUMENTATION ..................................................................................... 9

INSTRUMENT CALIBRATION ••••....••••....•••.••••.....•.••...•...••••.••••.....••.•....•••......••.•....••••..••.....••••...•••.••...••••.....••••...•....•. 9 FUNCTIONAL CHECKS .••...•..•••...•..•......••••..•.....••.•....•....••••...•.•••.•....•.••••.....••••....••••..••.•...•••...••....••••.•••..•......•••.....•• 9

8.3 DETERMINATION OF COUNTING TIMES AND MINIMUM DETECTABLE CONCENTRATIONS ................................................... 9 8.3.1 STATIC COUNTING ........................................................................................................................................ 10 8.3.2 Ratemeter Scanning ............................................................................................................................... 10 8.3.3 Smear Counting ......................................................................................................................................... 11 8.4 RADIOLOGICAL INSTRUMENTATION SPECIFICATIONS ............................................................................................. 11

9.0 DATA QUALITY OBJECTIVES ..................................................................................... 12

10.0 CLASSIFICATION OF AREAS ...................................................................................... 12

10.1 CLASS 1 AREAS ................................................................................................................................................. 13 10.2 CLASS 2 AREAS ................................................................................................................................................. 13 10.3 CLASS 3 AREAS ................................................................................................................................................. 13 10.4 SURVEY UNITS ................................................................................................................................................. 14 10.5 SURFACE CONTAMINATION SCANS ....................................................................................................................... 14 10.6 TOTAL SURFACE ACTIVITY MEASUREMENTS ........................................................................................................... 15 10.6.1 Determining the Number of Samples ...................................................................................................... 15 10.6.2 Determination of the Relative Shift ......................................................................................................... 16 10.6.3 Determination of Acceptable Decision Errors .......................................................................................... 16 10.6.4 Determination of Number of Data Points (Sign Test) .............................................................................. 16 10.6.5 Determination of Sample Locations ......................................................................................................... 17

fiNAL STATUS DECONTAMINATION & DECOMMISSIONING SURVEY REPORT

Sigma-Aldrich Manufacturing, LLC TABLE OF CONTENTS

10.6.5.1 Determining Class 1 and 2 Sample Locations .............................................................................. 18 10.6.5.2 DETERMINING CLASS 3 SAMPLE LOCATIONS ................................................................................................... 18 10.7 REMOVABLE CONTAMINATION MEASUREMENTS .................................................................................................... 18

11.0 DECONTAMINATION ............................................................................................... 18

12.0 DATA QUALITY ASSESMENT AND INTERPRETATION OF SURVEY RESULTS ................. 19

12.1 PRELIMINARY DATA REVIEW ............................................................................................................................... 19 12.2 DETERMINING COMPLIANCE FOR BUILDING SURFACES AND STRUCTURES ..................................................................... 19 12.3 DANDO DOSE CALCULATIONS ............................................................................................................................. 19 12.4 DECOMMISSIONING REVIEW ............................................................................................................................... 20

13.0 QUALITY ASSURANCE SURVEYS ............................................................................... 20

APPENDIX A- INSTRUMENT CALIBRATION CERTIFICATES

APPENDIX B- MINIMUM DETECTABLE CONCENTRATION CALCLULATIONS

APPENDIX C- FACILITY MAPS

APPENDIX D- STATISTICAL DATA

APPENDIX E- SURVEY DATA STRUCTURES & SYSTEMS

APPENDIX F- TOTAL EFFECTIVE DOSE EQUIVALENT CALCULATION

APPENDIX G- QUALITY ASSURANCE DATA

APPENDIX H- SURVEY CODING SYSTEM

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Sigma-Aldrich Manufacturing LLC


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1.0 EXECUTIVE SUMMARY

1.1 Purpose

Final Status Survey Report St. Louis, MO

South 2"d Street and Laclede Avenue Decommissioning August 3, 2017

Sigma-Aldrich Manufacturing LLC (Sigma) commenced the decommissioning of its St. Louis, Missouri laboratories to terminate its United States Nuclear Regulatory Commission (NRC) License #24-16607-03 on July 24th 2017. This report covers the facilities located at 3300 S Second Street and 2909 Laclede Avenue, in St. Louis, Missouri. The Decontamination and Decommissioning (D&D) project was executed to comply with the requirements of the NRC standards for radioactive materials licensee termination. All decommissioning activities were performed under Decontamination Decommissioning and Environmental Services, LLC (DOES) Commonwealth of Massachusetts radioactive materials license #56-0623 with a reciprocity agreement in place from the NRC. Surveys and sampling were performed in accordance with the requirements of the DOES Radiation Safety Program.

The structures, systems, and surfaces of the interior of the affected laboratories were surveyed to demonstrate compliance with the established release criteria. The surveys were designed and executed using the guidance provided in NUREG 1757, "Consolidated Nuclear Materials Safety and Safeguards (NMSS) Decommissioning Guidance"; and NUREG 1575, "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM). The final status survey methods and techniques for the evaluation of potentially impacted radiological areas followed MARSSIM guidance to demonstrate compliance with the specified dose based decommissioning criteria. These methods ensure technically defensible data is generated to aid in determining whether or not these facilities meet the release criteria for unrestricted use.

The radionuclides of Carbon (14C), Hydrogen (3H), and Iodine (1251), Phosphorous, (32P) (33P), and Sulfur (35S) were used inside the laboratories N1111, N1143, and N340 at 3300 S Second Street. Only Phosphorous (32P) (33P) was used inside laboratory G109 at 2909 Laclede Avenue. ODES performed a radiological historic site assessment (HSA) in July of 2017, prior to decommissioning, that was based on NUREG 1575, MARSSIM. The nuclides of concern for each individual facility have been identified in Table 2-3.

Sigma retained DOES of Wakefield, Massachusetts to perform a characterization and final status survey of the facility. The guidance provided in NUREG-1757, V.1, "Consolidated Decommissioning Guidance, Decommissioning Process for Materials Licensees" (NRC 2006); NUREG-1757, V.2, "Consolidated Decommissioning Guidance, Characterization, Survey and the Determination of Radiological Criteria and NUREG 1575, (MARSSIM) was used to define the approach, methods, and techniques for the radiological D&D of potentially impacted areas of the affected facility.

Characterization and Final Status Surveys were designed to implement the protocols and guidance provided in MARSSIM to demonstrate compliance with the default screening values specified in NUREG 1757, Volume 1, Appendix B. These methods ensure technically defensible data is generated to aid in

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Final Status Survey Report

St. Louis, MO

South 2"d Street and Laclede Avenue Decommissioning

August 3, 2017

determining whether or not these facilities meet the release criteria for unrestricted use specified in U.S.

Nuclear Regulatory Commission (NRC), Title 10 Code Of Federal Regulations Parts 19-150 to provide

pertinent information for the decommissioning and unrestricted release of specified areas of the Sigma

licensed facilities 3300 S Second Street and 2909 Laclede Avenue in St. Louis, Missouri. Ultimately leading

to termination of Sigma's radioactive material license.

Based upon the results of the Final Status Survey, the facility meets the requirement for unrestricted

release based upon the following:

• All final scanning measurements at 3300 S Sceond Street were indistinguishable from

background except for one area of 12939 dpm/100cm2 that is discussed further in section 2.7.

• All final scanning measurements at 2909 Laclede Avenue were indistinguishable from background.

• All final static measurements at 3300 S Second Street were below the Derived Concentration

Guideline Level (DCGLw) of 3.7 E6 dpm/100cm2 for 14C and the Derived Concentration Guideline

Level (DCGLw) of 6.9 E5 dpm/100cm2 for 1251.

• The greatest final status survey structure contamination survey measurement from within the

labs at 3300 S Second Street was calculated at 908 dpm/100cm2 for 14C. The greatest final status

survey structure contamination survey measurement was calculated at 4431 dpm/100cm2 for 1251. None of the removable measurements obtained exceeded the removable contamination limit of 1000 dpm/100cm2•

• The greatest final status survey structure contamination survey measurement from within the

labs at 2909 Laclede Avenue was calculated at 44 dpm/100cm2 for 32P. None of the removable

measurements obtained exceeded the removable contamination limit of 1000 dpm/100cm2•

• The calculated total effective dose equivalent (TEDE) from any potential radioactive materials in

the specified areas within 3300 S Sceond Street laboratories were calculated to be 6.17E-3

mrem/year for 14C and 1.61E-1 mrem/year for 1251 based on the NRC DandO Version 2.4.0

default building occupancy scenario using the highest measured total contamination value for 14C and 1251 respectively.

• The calculated total effective dose equivalent (TEDE) from any potential radioactive materials in

the specified areas within 2909 Laclede Avenue were calculated to be 1.16E-4 mrem/year for 32P

based on the NRC DandO Version 2.4.0 default building occupancy scenario using the highest measured total contamination value for 32P.

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US NRC License #24-16607-03 . / '~

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2.0 FACILITY OPERATING HISTORY

2.1 Historical Site Assessment



DOES, LLC performed an HSA of the facilities in July of 2017. The HSA was designed to determine the existing radiological status of the facility. This included interviews with the site Radiation Safety Staff, review of the radioactive material license, application, amendments, and general surveys of the restricted areas.

2.2 License History

Sigma owns the 3300 S Second Street and 2909 Laclede facilities and operates the facilities under Radioactive Material License #24-16607-03 amendment #11. The NRC amended this license on June 8, 2016.

The radionuclides and quantities presented in Table 2-1 are authorized for use at Sigma facilities located at under License #24-16607-03. Authorized uses were for non-human use- research and development; and for persons authorized to receive licensed material pursuant to the terms and conditions of a specific license issued by the NRC.

Table 2-1 Authorized Radioactive Material

Nuclide Form Possession Limit

A. Hydrogen-3 Bound, Non-volatile 5 millicuries B. Carbon-14 Bound, Non-volatile 5 millicuries

c. Phosphorous-32 Bound, Non-volatile 5 millicuries D. Phosphorous-33 Bound, Non-volatile 5 millicuries E. lodine-125 Bound, Non-volatile 5 millicuries

2.3 Radioactive Material Use

The R&D facility in Building N is located at 3300 S Second Street St. Louis, Missouri. It consists of a 3-story building with 200,000 square feet of habitable space. Licensed radioactive materials were used in three contiguous laboratories in Building N. R&D laboratories N111, N1143 and N340 occupy a contiguous area inside the building. The total area for these laboratories is 620 ft2•

The Laclede Avenue R&D facility located at 2909 Laclede Avenue St. Louis, Missouri. It consists of a 4-story building with 120,000 square feet of habitable space. Licensed radioactive materials were used in laboratory G109 and occupies 610ft2 inside the building.

Sigma is the owner of the buildings that are currently licensed.

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2.4 Potential Contaminants

Table 2-2 lists the potential radioactive contaminants as identified by the HSA.

Table 2-2 Potential Contaminants

Radionuclide Half-Life Dispersible Form Half Life >120 Days

14( 5,730 years Yes Yes 3H 12.32 years Yes Yes 1251 60.14 days Yes No 32p 14.29 days Yes No 33p 25.40 days Yes No 355 87.40 days Yes No

2.5 Operational Radiological Surveys

Routine weekly and monthly surveys of radioactive material use/storage areas indicate removable contamination levels have been maintained at a level below the administrative operational level of 200 dpm/100 cm2 and direct measurements were at background levels.

2.6 Spills and Uncontrolled Release of Radioactivity

All spills were all within the affected laboratories. Minor spills were documented during the site's operational history and in all cases decontamination activities were successful in reducing levels of removable contamination below 1,000 dpm/100cm2

2.7 Potentially Impacted Facilities and Laboratories

Table 2-3 lists the laboratories/rooms that had been potentially impacted by the use of radioactive material and were evaluated against the decommissioning criteria. All of the isotopes with halflives less than 120 days historically used in Labs Nl111, N1143, and N340 have not been used in at least ten half-lives. Therefore they can be eliminated from the Nuclides of Concern. As a conservative measure, a gamma scan and static measurements was conducted on the Building N labs. Values obtained during gamma statics were used to determine dose compliance for 1251.

These labs did contain typical lab equipment, including benchtop shields, trays, ovens, glassware, analytical equipment, and chemicals. All large equipment was surveyed with a 100% scan and biased removable measurements. If results showed compliance with the administrative limits the item was disposed of as non-radioactive. Smaller items or items with areas that could not be adequately surveyed in a straightforward manner such as pipettes, distillation flasks, and tubing were disposed of as radioactive waste. Each chemical bottle had a 1 ml aliquot taken and

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St. Louis, MO South 2"d Street and Laclede Avenue Decommissioning

August 3, 2017

analyzed by Liquid Scintillation and surveyed on the exterior for contamination as well before being passed along to Sigma for disposal as non-radioactive waste.

In addition to the laboratory equipment, the lab was equipped with two fume hoods connected to an independent and filtered exhaust system, local unfiltered exhaust ventilation, and sinks that connect to a public sewer system. Each fume hood was scanned then, biased static and removable measurements were taken on any suspect surface, including exhaust entry points. The filters on the roof were removed and disposed of as radioactive waste while the duct and filter box was scanned and surveyed for removable and total contamination. The laboratory ventilation system was surveyed in a similar manner at both the inlets in the lab and exhaust on the roof. Results of the survey indicated that the exhaust system was not contaminated above administrative limits of 1,000 dpm/100cm2 removable and S,000/100cm 2 total. It was left in place.

An area of elevated contamination was identified on the base of one fume hood. This fixed contamination was approximately 100cm2• The hood base is constructed of asbestos so light decontamination techniques were employed such as cleaning with simple green. Fixed contamination could not be remediated below 12,939 dpm/100cm2• Removable contamination was at background levels. This measurement exceeded the administrative limit but is well below the DCGLw. After discussions between DDES and the Sigma RSO, it was decided to coat the hood base with a lockdown agent to prevent resuspension of the material and leave it in place.

Sink disposal of any radioactive material was expressly prohibited by Sigma policy. Nonetheless each sink was opened at the P-trap, a static measurement taken and a removable contamination wipe taken. All measurements were indistinguishable from background measurement levels.

At the 2909 Laclede Avenue facility, 32P and had been used in March 2017 inside the G109 lab. Therefore it was included in the survey. 33P use in G109 has surpassed the ten half-lives designation. The laboratory itself was nearly empty of all equipment and materials. There were some items left inside a refrigerator which were screened for the presence of 32P. Waste bins were surveyed as well. The single fume hood was scanned, static and removable measurements were taken on any suspect surface, including exhaust entry points. The sinks in the Laclede building had welded PVC joints so long cotton swabs were used to obtain trap samples and static measurements were taken on the drains.

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Table 2-3 Potentially Impacted Areas

Building Floor Laboratory/Room

Nuclides of Concern Survey Unit

Number Classification 3300 S Second Street 1 N1111 14C & 3H 1

3300 S Second Street 1 N1143 14C & 3H 1

3300 S Second Street 1 N340 14C & 3H 1

3300 S Second Street 1 Hallways 14C & 3H 3

3300 S Second Street 3 Rooftop Exhaust and

14C & 3H N/A Filters Boxes

2909 Laclede Ave 1 G109 32p 1

2909 Laclede Ave 1 Hallways 32p 3

2.8 Non-Impacted Areas

The following locations have not been impacted by radioactivity associated with activities based on information obtained during the HSA and inspection of the site.

• All Support and Office Areas • Unrestricted Laboratories

• Exterior of Buildings (Except for Rooftop Area adjacent to Filter Box Investigation)

3.0 FACILITY REALEASE CRITERIA

3.1 DCGLs and Cleanup Goals

DCGLs are radionuclide-specific concentration limits used during decommissioning to achieve the regulatory dose standard that permit the release of the property and termination of the license. The DCGL applicable to the average concentration over a survey unit is called the DCGLw and the DCGL applicable to limited areas of elevated concentrations within a survey unit is called the DCGLEMc {NRC 2006). These values were used as a guide to establish compliance with the site decommissioning criteria.

3.2 DCGL Development

The DCGL development analyses simulate the behavior of residual radioactivity over one year, a period during which peak annual doses from the radionuclides of primary interest would be expected to occur. DCGLs are developed for residual radioactivity that will result in 25 mrem per year dose to the average member of the critical group.

The NRC has published default screening values (DSVs) in NUREG 1757, Volume 1, Appendix B for commonly used radionuclides. These default screening values are based on 25 mrem/year. Table

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August 3, 2017

3-1 and Table 3-2 present the DCGLs based on 25 mrem and Sigma Decommissioning DCGL goals. 32P values are not provided in NUREG 1757, Volume 1, Appendix B so DandO Code Version 2.4.0 was used to determine the DCGL for 32P that would results in a dose of 25 mrem using the default parameters.

Table 3-1 Established DCGLw for Survey based on 25 mrem/yr

Isotope Total Removable (DPM/100 cm2) (DPM/100 cm2)

3H 1.2 X 108 1.2 X 107

14( 3.7 X 106 3.7 X 105

32p 9.5 X 106 9.5 X 105

1251 6.9 X 105 6.9 X 104

Table 3-2: Established Sigma Administrative Limit's for Survey DCGLw

Isotope Total Average * Removable (DPM/100 cm2) (DPM/100 cm2)

3H N/A 1,000 14( 5,000 1,000 32p 5,000 1,000 1251 5,000 1,000

* Not to exceed 15,000 dpm/100cm2 as a maximum for accessible areas.

The term derived concentration guideline levels (DCGLs) will be generically used to describe the established and administrative levels specified in Table 3-1 and Table 3-2. These release criteria are the basis for developing the derived concentration guideline levels (DCGLs) or release criteria for the project. DCGLw is the concentration limit if the residual activity is essentially evenly distributed over a large area.

Additionally, reasonable efforts were made to decontaminate any detectable contamination in compliance with As Low As Reasonably Achievable (ALARA) practices.

3.3 ALARA Goals

Sigma had selected ALARA goals based on their facility operational removable contamination limits combined with the administrative release criteria specified in their radioactive material handling procedures incorporated by reference into their radioactive material license from the

NRC.

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4.0 PROJECT MANAGEMENT AND ORGANIZATION

Sigma management supervised site decommissioning operations. ODES, LLC, a licensed decontamination and decommissioning services provider, was contracted to perform site characterization and final status survey activities under DOES LLC Commonwealth of Massachusetts Radioactive Material License 56-0623 with a Reciprocity Agreement in place with NRC Region Ill.

5.0 TRAINING

Sigma provided site safety training for DOES project employees prior to performing project activities. DOES, LLC performed project specific training health and safety training and radiation safety training for ODES personnel, as required by its Commonwealth of Massachusetts radioactive materials license conditions.

6.0 ENVIRONMENTAL MONITORING PROGRAM

The scope of this decommissioning project included the evaluation of four rooftop air handling systems. During investigation and removal of filters from the impacted systems an enclosure was built around the systems. The enclosure was ventilated through a HEPA system to ensure that particulates were not released to the environment. Further evidence of compliance with effluent air releases can be demonstrated with personnel air monitoring during operations. Air monitoring from inside the enclosure showed 3H concentrations of 2.34 x 10-10 llCi/mL and 14C of 1.68 x 10-11 1-lCi/mL. These concentrations are well below the most conservative limits for effluent release of air listed in 10 CFR Part 20 Appendix B Table 2 Column 1 of 1.00 x 10-7 llCi/mL for 3H and 3.00 x 10-9 J,.lCi/mL for 14C.

7.0 RADIOACTIVE WASTE MANAGEMENT

A small volume of radioactive waste was generated under this scope of work. Five cubic yards of Dry Active Waste (DAW) was generated during the decommissioning process. Also, there were three hazardous chemical bottles from the S Second Street laboratories that were determined to be impacted. In addition a number of sealed liquid and solid sources were disposed. Table 7-1 summarizes the waste generated under the decommissioning. Nonradioactive liquid scintillation vials were generated and disposed of by Sigma under their waste program.

In addition, the S Second Street facility had one liquid scintillation analyzer. This machine was serviced by the manufacturer, PerkinEimer, in order to remove the Ba-133 sealed source inside the machine. At the Laclede Avenue facility, one liquid scintillation analyzer was serviced by the manufacturer and had the sealed Ba-133 source removed. The manufacturer took possession of and is disposing of the sources.

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US NRC license #24-16607-03

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Table 7-1 Radioactive Waste Summary

Package Number Quantity Form Isotopes and Activities

Super Sack #1 4661bs. DAW 0.5 mCi 3H 0.5 mCi 14C NA NA


Super Sack #3 290 lbs. DAW 0.5 mCi 3H 0.5 mCi 14C NA NA


Super Sack #5 2221bs. DAW 0.5 mCi 3H 0.5 mCi 14C 0.01 mCi 32 P NA

Bucket B-1 1500 ml Liquid Waste 0.0007 mCi 3H NA NA NA

Bucket B-2 470 ml LSA Standards 0.0038 mCi 3H 0.002 mCi 14C NA NA

Bucket B-3 < 500g Sealed Sources 0.0007 mCi 0.0001 mCi 0.00005 mCi

0.1 mCi natu 226Ra 21op0 1291

770242605819 <500g Sealed Source 0.018 mCi

NA NA NA 133Ba

770242605819 <500g Sealed Source 0.018 mCi

NA NA NA 133Ba

8.0 SURVEY INSTRUMENTATION 8.1 Instrument Calibration

Portable field instruments were calibrated with National Institute of Standards and Technology (NIST) traceable sources for the nuclides of concern within the previous year. Instrument calibration sheets have been included in Appendix A.

8.2 Functional Checks

Functional checks for portable instrumentation were performed daily when in use. The background, source check, and field measurement count times for radiation detection instrumentation were validated daily to ensure that statistically valid data was obtained. Background readings were taken as part of the daily instrument check and compared with the acceptance range for instrument performance and site conditions.

8.3 Determination of Counting Times and Minimum Detectable Concentrations

Minimum counting times for background determinations and measurement of total and removable contamination were chosen to provide a minimum detectable concentration (MDC) that met the Final Status Survey Data Quality Objectives (DUOs). MDC calculations are presented in Appendix B. Instrumentation count times and scanning rates were determined using the following equations listed in Sections 8.3.1, 8.3.2 and 8.3.3 below:

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8.3.1 Static Counting

Static counting Minimum Detectable Concentration at a 95% confidence level was calculated using the following equation, which is an expansion of NUREG 1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions", (Strom & Stansbury, 1992):

Where: MDCstatic

Br tb

ts Etot

A

3+3.29 Br ·ts ·(1+~) tb

MDC static =-----'----A----t ·E ·---

s tot 100cm2

= minimum detectable concentration level in dpm/100cm2

= background count rate in counts per minute background count time in minutes

= sample count time in minutes = total detector efficiency for radionuclide emission of interest (includes

combination of instrument efficiency and 0.25 surface efficiency for beta emitters <400 keV max and 1.00 surface efficiency for gamma emitters) detector probe area in cm 2

8.3.2 Ratemeter Scanning

Scanning Minimum Detectable Concentration at a 95% confidence level was calculated using the following equation, which is a combination of MARSSIM equations 6-8, 6-9, and 6-10:

Where:

MDCscan

d'

bi

p

Etot

A

d'~(6i0) MDCscan = A

.JP . E tot . -1 O_O_c_m----=-2

= minimum detectable concentration level in dpm/100 cm2

= desired performance variable (1.38)

= background counts during the residence interval

= residence interval

= surveyor efficiency (0.5)

= total detector efficiency for radionuclide emission of interest (includes combination of instrument efficiency and 0.25 surface efficiency for beta emitters <400 keV max) and 0.50 surface efficiency for beta emitters >400keV max and 1.0 surface efficiency for gamma emitters

= detector probe area in cm 2

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8.3.3 Smear Counting

Smear counting Minimum Detectable Concentration at a 95% confidence level is calculated using the following equation, which is NUREG 1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions", (Strom & Stansbury, 1992):

Where: MDCsmear

Br tb

ts E

fs 3+3.29 B ·t ·(1+-)

r s f MDC smear = ____ .o__ _____ h_

t ·E s

= minimum detectable concentration level in dpm/smear = background count rate in counts per minute = background count time in minutes = sample count time in minutes = instrument efficiency for radionuclide emission of interest

8.4 Radiological Instrumentation Specifications

Field instruments were selected based on the DQOs in Section 9.0. Table 8-1 shows typical field instruments and associated efficiencies that were used for the Final Status Survey.

Table 8-1 Radiological Field Instruments

Detector Detector Detector Meter Window Typical Total Model Type Area Model Thickness Efficiency

Ludlum Alpha Beta Gas Flow 100 cm 2 Ludlum 0.8

12 %(14C)) 43-68 Proportional 2224 mg/cm2

Ludlum 43-37 Gas Flow Proportional 582 cm 2 Ludlum 0.4

13% (14C) Floor Monitor 2221 mg/cm 2

Perkin Elmer 2910 LSC 2" X 2" Tri-Carb N/A

92% (14C)

TR 55% (3H)

Ludlum Alpha Beta 100 cm 2

Ludlum 0.8 10%- (14C)

43-93 ' Scintillation 2224 mg/cm 2

Ludlum 19 Gamma Scintillation 1" X 1" Ludlum N/A N/A

GP13A Gamma Scintillation 100 cm 2 Electra 1A 0.8

25.5% (125 1) mg/cm 2

NOTES: These are approximate values based primarily on manufacturer's ratings. The sensitivities depend on background, count time, and other factors.

To assist with current planning activities, estimated scanning MDCs for the radionuclides of interest were obtained for field survey instruments by reviewing available information, and these values are listed in Table 8-2.

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St. Louis, MO


August 3, 2017

Table 8-2 Typical Operating Instrument Operating Parameters

Measurement Detector Meter Scan Count Background MDC Type Model Model Rate Time (cpm) (dpm/100cm2)

Surface Scans Ludlum 43- Ludlum 2

N/A 285 1,284 (14C} 68B 2221 in./sec.

Ludlum 43-

Surface Scans 37B Ludlum 4

N/A 740 441 (14C) Floor 2221 in./sec.

Monitor

Surface Scans Ludlum 43- Ludlum 2

N/A 235 2,317 (14C) 93 2224 in./sec.

Surface Scans Thermo Thermo 4

N/A 4540 1074 (1251) GP13A Electra in./sec.

Total Surface Ludlum 43- Ludlum N/A 1 Min 285 582 (14C)

Activity 68B 2221

T ota I Surface Ludlum 43- Ludlum N/A 1 Min 235 558(14C)

Activity 93 2224

T ota I Surface Thermo Thermo N/A 1 Min 4540 873 (1251)

Activity GP13A Electra

Removable Perkin Elmer N/A N/A 1 Min

10 (3H) 22 (3H) Activity 2910TR 15 (14C) 17 (14C)

The scanning MDCs presented in Table 8-2 are representative of those that reasonably can be expected to be obtained with currently available instruments under conditions typically encountered in the field. These values were obtained from reported values and scanning experience.

9.0 DATA QUALITY OBJECTIVES

The following identifies the DQOs used for the project radiological beta surveys:

• Static measurements were taken to achieve an MDC5tatic of 600 dpm/100cm2 •

• Scanning was conducted at a scan speed to achieve an MDCscan of 2,500 dpm/100cm2 for Beta.

• Removable contamination measurements had a MDC of 50 dpm/100cm 2 •

• Scenario A was used for the null hypothesis.

• Decision error and probability rates will be set to 0.05 for Type I and Type II errors.

10.0 CLASSIFICATION OF AREAS

MARSSIM dictates that all areas of the facility be categorized based on information revealed during the HSA. Each area will normally fall into one of four classes based on the potential for radioactive contamination. There were no areas inside the South 2nd Street or Laclede Avenue labs that were determined to be class 2 areas. Therefore some of the following is for informational purposes only,

• Class 1: impacted areas that, prior to remediation, are expected to have concentrations of residual radioactivity that exceed the DCGLw;

12



I . COli&

Final Status Survey Report St. louis, MO


• Class 2: impacted areas that, prior to remediation, are not likely to have concentrations of residual

radioactivity that exceed the DCGlw;

• Class 3: any impacted areas that have a low probability of containing residual radioactivity; and

• Non-impacted: areas without reasonable potential for radioactive contamination from licensed

or decommissioning activities.

Non-impacted areas are building surfaces or systems that do not have residual radioactivity present from

licensed activities. The following areas were classified as non-impacted:

• Unrestricted Laboratories

• Exterior of Buildings (Except for Rooftop Area adjacent to Filter Box Investigation)

Impacted areas are identified in Section 2.6 based on information obtained during the HSA. Each

impacted areas classification was confirmed by subsequent characterization and final status survey data.

Impacted areas are those areas that have potential residual radioactivity from licensed activities.

Impacted areas are subdivided into Class 1, Class 2 or Class 3 areas. Class 1 areas have the greatest

potential for contamination and therefore receive the highest degree of survey effort for the final status

survey using a graded approach, followed by Class 2, and then by Class 3. Impacted sub-classifications are

defined as follows:

10.1 Class 1 Areas

Areas with the highest potential for contamination, and meet the following criteria: (1) impacted; (2)

potential for delivering c;l dose above the release criterion; (3) potential for small areas of elevated activity;

and (4) insufficient evidence to support classification as Class 2 or Class 3.

10.2 Class 2 Areas

Areas that meet the following criteria: (1) impacted; (2) low potential for delivering a dose above the

release criterion; and (3) little or no potential for small areas of elevated activity.

10.3 Class 3 Areas

Areas that meet the following criteria: (1) impacted; (2) little or no potential for delivering a dose above

the release criterion; and (3) little or no potential for small areas of elevated activity.

The radiological status of the facility was determined by reviewing historical survey records, interviewing

Radiation Safety personnel, and performing characterization surveys during the implementation of the

Decommissioning Plan.

13



".-. CCEB

10.4 Survey Units



Survey units are geographical areas of specified size and shape for which a separate decision will be made

as to whether or not that area exceeds the regulatory limit. Areas within a survey unit will have a similar usage history and contamination potential and be contiguous areas of the same area classification. Areas of similar construction and composition were grouped together as survey units and tested individually

against the DCGLs and the null hypothesis to show compliance with the release criteria. Survey units were

of homogeneous in construction, contamination potential, and contamination distribution.

The number of discrete sampling locations needed to determine if a uniform level of residual radioactivity exists within a survey unit does not depend on the survey unit size. However, the sampling density should

reflect the potential for small elevated areas of residual radioactivity. Survey units were sized according to the potential for small elevated areas of residual radioactivity.

Recommended maximum survey unit sizes for from MARSSIM are provided in Table 10-1.

Table 1o-1- Recommended Maximum Survey Unit Size Limits

Type of Survey Unit Class 1 Class2 Class3

Structures Up to 100m2 100 m2 to 1,000 m2 No Limit

10.5 Surface Contamination Scans

Scanning is used to identify locations within the survey unit that exceed the investigation level.

These locations are marked and receive additional investigations to determine the concentration,

area, and extent of the contamination. Scanning surveys are designed to detect small areas of elevated activity that are not detected by the measurements using the systematic pattern. Floor

surfaces were scanned in main hallway areas and areas between rows including under shelving were potential contamination may be found. For this reason, the measurement locations and the number of total surface activity measurements were adjusted based on the sensitivity of the scanning technique. Table 10-2 summarizes the percentage of accessible building structural surfaces that were scanned based on classification.

Table 10-2 Scan Survey Coverage by Classification

Classification Recommended Scan Coverage Actual Coverage 1 100% 100%

3 Judgmental SO%

14



. co••



For the purposes of the Final Status Survey, Class 1 survey units received a scan survey of 100% of all floors and other horizontal surfaces and 100% scan of all vertical surfaces to a height of two (2) meters.

For the purposes of the Final Status Survey, Class 3 survey units received a scan survey of 50% of all floors and other horizontal surfaces and 50% scan of all vertical surfaces to a height of two (2) meters.

Scanning was performed by moving the probe over the subject surface at a distance of approximately 1.0 em or less at a rate less than the maximum scan rate necessary to achieve the specific MDCscan for the instrument. Areas of elevated activity that were detected during the scan surveys were marked and total and removable surface activity measurements taken. However, these total surface activity measurements are in addition to the static measurements required for the statistical test.

The derivation of scan and fixed MDCs will take into account instrument efficiencies (surface and detector), scan rates and distances over surfaces, surveyor efficiency, and minimum detectable count rate, using guidance in the MARSSIM (NRC 2000) and NUREG 1507 (Abelquist, et al. 1998).

The survey methodology specified in this section is consistent with the provisions of NUREG-1757, Volume 2 (NRC 2006) and with the guidance found in NUREG-1575, {MARSSJM) (NRC 2000).

10.6 Total Surface Activity Measurements

Total activity measurements were taken on building surfaces and system internals to the extent practical in impacted areas utilizing instrumentation of the best geometry based on the surface at the survey location. Locations of elevated activity identified and marked during the scan survey. Total surface activity measurements were taken at each determined sample location. Hand-held monitor count times were determined based on the MDCstatic of the applicable survey instrument.

10.6.1 Determining the Number of Samples

A minimum number of samples are needed to obtain sufficient statistical confidence that the conclusions drawn from the samples are correct. The number of samples will depend on the relative shift. Initial calculations have been performed to determine an estimated standard deviation and Lower Bound of the Gray Region (LBGR) for determination of the relative shift. Specific data was selected from areas that appear to meet the release criteria using the assumption that remedial actions will remove

locations greater than the DCGLw.

The survey design for surfaces and structures will be based on the Sign test. The minimum number of samples calculated using MARSSIM Equation 5-2 was 11 sample locations.

15





August 3, 2017

10.6.2 Determination of the Relative Shift

The number of required samples will depend on the ratio involving the activity level to be measured

relative to the variability in the concentration. The ratio to be used is called the Relative Shift, McrS and

is defined in MARSSIM as:

Where:

DCGL = derived concentration guideline level

LBGR concentration at the lower bound of the gray region. The LBGR is the average concentration to which the survey unit should be cleaned in order to have an acceptable probability of passing the test

crS an estimate of the standard deviation of the residual radioactivity in the survey unit

For the purpose of this plan, an estimated standard deviation will be pre-determined based on the

expected total activity levels at the time of the FSS. The LBGR will initially be set at one-half of the 14C DCGLw, one half of the 32P DCGLw, and one-half of the 1251 DCGLw.

10.6.3 Determination of Acceptable Decision Errors

A decision error is the probability of making an error in the decision on a survey unit by failing a unit

that should pass (~ decision error) or passing a unit that should fail (a decision error). MARSSIM uses

the terminology a and ~ decision errors; this is the same as the more common terminology of Type I

and Type II errors, respectively. The decision errors were set at 0.05 for Type I errors and 0.05 for Type II errors.

10.6.4 Determination of Number of Data Points (Sign Test)

The number of direct measurements for a particular survey unit, employing the Sign Test, is determined

from MARSSIM Table 5.5, which is based on the following equation (MARSSIM equation 5-2):

Where:

N = (z,_a + z,_f3 y 4(SignP- 0.5 )2

N = number of samples needed in the survey unit

16





Zl-a = percentile represented by the decision error a

Zl-~ = percentile represented by the decision error~

SignP = estimated probability that a random measurement will be less than the DCGL when the survey unit median is actually at the

LBGR

N = (1.645 + 1.645)2

= 11 4(0.998650- o.5Y

Note: SignP is determined from MARSSIM Table 5.4

MARSSIM recommends increasing the calculated number of measurements by 20% to ensure sufficient

power of the statistical tests and to allow for possible data losses. MARSSIM Table 5.5 values include an increase of 20% of the calculated value of 11 sample locations to 13 sample locations. However, MARSSIM relies on scanning data to identify any areas of contamination. Since this is not possible for 3H the number of samples has been increased by at least a factor of two in any area where

3H is a

contaminant of concern.

10.6.5 Determination of Sample Locations

Determination of Class 1 survey unit sample locations is accomplished by first determining sample spacing and then systematically plotting the sample locations from a randomly generated start location. The random starting point of the grid provides an unbiased method for obtaining measurement

locations to be used in the statistical tests.

Survey protocols for all areas are summarized in Table 10-3.

Table 10-3 Survey Sample Placement Overview

DCGLw Elevated

Survey Unit Classification Comparison Measurement Measurement Locations Comparison

Impacted Class 1 Yes N/A Systematic/Random Start

Class 2 N/A N/A Systematic/Random Start

Class 3 N/A N/A Judgmental

Non-Impacted None None None

17





10.6.5.1 Determining Class 1 and 2 Sample Locations

In Class 1 survey units, the sampling locations are established in a unique pattern beginning with the random start location and the determined sample spacing. After determining the number of samples

needed in the survey unit, sample spacing is determined from MARSSIM equation 5-S:

L = ~ for a square grid

Where:

L =sample spacing interval

A =the survey unit floor area

N =number of samples needed in the survey unit

Class 1 & 2 grid areas included walls to a height of 2 meters. Maps were generated for each survey unit's permanent surfaces included in the statistical tests. Maps are located in Appendix C. Random starting points are determined using computer-generated random numbers coinciding with the x and

y coordinates of the total survey unit. A grid is plotted across the survey unit surfaces based on the

random start point and the determined sample spacing. A measurement location is plotted at each

intersection of the grid plot. For the purposes of this report all survey units were considered Class 1 and Class 3 units. There were no Class 2 survey units included in this scope.

10.6.5.2 Determining Class 3 Sample Locations

Class 3 sample locations were performed using judgment in locations where high traffic would occur in each specific hallway and adjacent entrances to affected laboratories. These areas include, doors, light switches, floors and sinks.

10.7 Removable Contamination Measurements

Removable contamination measurements (smears) were collected on building surfaces and structures

at each total activity sample location to determine the potential removable contamination. Carbon (1 4C), Hydrogen (3H), and Phosphorous (32P) where applicable, contamination levels were evaluated

using removable contamination measurements (wipe test). This approach assumes that the removable portion is 10% of the total fixed contamination levels of 3H. An area of approximately 100 cm2 was wiped for each sample location.

11.0 DECONTAMINATION

Decontamination is the physical or chemical process of reducing and preventing the spread or potential exposure from contamination. Decontamination options include the use of commercially available materials and/or equipment that will effectively remove radioactive

18



I .-. OCI&!!!i

Final Status Survey Report St. louis, MO

South 2"d Street and laclede Avenue Decommissioning August 3, 2017

materials from surface areas so that the contamination can be collected and properly disposed. Only one type of decontamination technique was employed at the site. DOES used Simple Green and EZ Off to clean one area of elevated contamination.

12.0 DATA QUALITY ASSESMENT AND INTERPRETATION OF SURVEY RESULTS

The statistical guidance contained in Section 8 of MARSSIM was used to determine if areas are acceptable for unrestricted release and whether additional surveys or sample measurements were required.

12.1 Preliminary Data Review A preliminary data review was performed for each survey unit to identify any patterns, relationships or anomalies. Additionally, measurement data were reviewed and compared with the DCGLs and administrative limits to confirm the correct classification of survey units. All statistical calculations of average, standard deviations, minimum and maximum values are presented in Appendix D.

12.2 Determining Compliance for Building Surfaces and Structures Removable contamination measurements were compared directly to the applicable DCGLs. Additionally, all removable contamination measurements were compared to the applicable administrative limits to determine if an area required further examination. All of the smears collected during the final status surveys were less than the applicable administrative limits and significantly less than the established DCGLs for removable activity. Therefore, compliance was determined based on total activity measurements.

All total beta and gamma surface activity measurements were compared directly to the DCGL. Additionally, all total beta and gamma surface activity measurements were compared to the applicable administrative limits to determine if an area required further examination. All total surface activity measurement collected during final status surveys were less than the established DCGLs.

Therefore, the null hypothesis can be rejected and the survey units meet the release criteria and are suitable for release to unrestricted use. Total activity and removable contamination measurement results for all surface and structure survey units are provided in Appendix E.

12.3 DandO Dose Calculations To support the unrestricted release of the areas, dose calculations were completed using NRC DandO code Version 2.4.0. The dose was calculated using the maximum dpm static value of the unbiased final status survey to give a maximum potential dose resulting from any radioactive material that may not have been detected by the survey. It is important to

19


US NRC License #24-16607-03 . /"

\



August 3, 2017

recognize that this dose calculation assumes this level of contamination uniformly exists in all areas affected by the decommissioning and that this calculation is very conservative.

The total effective dose equivalent (TEDE) from any potential radioactive materials in the specified areas were calculated to be:

• 3300 S Second Street Labs N 1111, N 1143, and N340- 6.17E-3 mrem/year for 14C • 3300 S Second Street Labs N1111, N1143, and N340- 1.61E-1 mrem/year for 1251

• 2909 Laclede Ave Lab G109 -1.16E4 mrem/year for 32P

12.4 Decommissioning Review

ODES has reviewed all of the applicable data pertaining to the history of radioactive materials use at the facility as well as the static and removable contamination surveys completed at Building N Laboratories N1111, N1143, and N340 at 3300 S Second Street and Laboratory G109 at 2909 Laclede Ave in St. Louis, Missouri. It is our professional opinion that the areas surveyed and occupied by Sigma-Aldrich Manufacturing LLC meet the specified criteria for unrestricted release specified in the U.S. Nuclear Regulatory Commission, Title 10, Part 20 of the Code of Federal Regulations.

13.0 QUALITY ASSURANCE SURVEYS At least ten percent of the structural surface survey units were selected to be independently monitored to verify the reproducibility of the results recorded during final status surveys. The QA results demonstrate the data quality objectives have been met and the survey results are reproducible. QA sample data are provided in Appendix G.

20

Sigma-Aldrich Manufacturing LL(


Acronyms


South 2nd Street and Laclede Avenue Decommissioning August 3, 2017

\ . CCES

A LARA CFR D&D

DAW DCGLw DCGLEMC DQO DSV

HSA HVAC LBGR MARSSIM

MDC NIST NMSS NRC NUREG QAPP RAM RSC TEDE

ACRONYMS

As Low As Reasonably Achievable Code of Federal Regulations

Decontamination and Decommissioning Dry Active Waste

Derived Concentration Guideline Level

Elevated Measurement Exposure Concentration Data Quality Objective

Default Screening Value

Historical Site Assessment

Heating, Ventilation, Air Conditioning Lower Boundary of the Gray Region

Multi-Agency Radiation Survey and Site Investigation Manual Minimum Detectable Concentration

National Institute of Standards and Technology Nuclear Materials Safety and Safeguards

U.S. Nuclear Regulatory Commission

Nuclear Regulatory Commission Guidance Document Quality Assurance Project Plan

Radioactive Materials

Radiation Safety Committee Total Effective Dose Equivalent

1



References

I ' .

cces


St. Louis, MO


August 3, 2017

REFERENCES

10 CFR 20, Standards for Protection Against Radiation

10 CFR 20, Subpart E., Radiological Criteria For License Termination (L TR}

NUREG-1505, "A Nonparametric Statistical Methodology for the Design and Analysis of Final

Decommissioning Surveys"

NUREG 1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions"

NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM)

NUREG 1727, "NMSS Decommissioning Standard Review Plan," September 2000.

NUREG-1757, Volume 1," Consolidated NMSS Decommissioning Guidance"

NUREG 1757, Volume 2, "Consolidated NMSS Decommissioning Guidance"

U.S. Nuclear Regulatory Commission (NRC). Guidelines for the Decontamination of Facilities and

Equipment Prior to Release for Unrestricted Use or Termination of Byproduct, Source, or Special Nuclear Material Licenses; Policy and Guidance Directive FC 83-23, November 1983.

U.S. Nuclear Regulatory Commission (NRC). NUREG/CR-5512, Residual Radioactive Contamination from Decommissioning, October 1992.

Abelquist, et al. 1998, Minimum Detectable Concentrations With Typical Radiation Survey Instruments for Various Contaminants and Field Conditions, NUREG-1507. Abelquist, E., W. Brown, and G. Powers, U.S. Nuclear Regulatory Commission, Washington, D.C., June 1998.

NRC 1994, N UREG-1501. Background as a Residual Radioactivity Criterion for Decommissioning. Draft Report for Comment. U.S. Nuclear Regulatory Commission, Washington, D.C., August 1994.

NRC 1998. NUREG-1505, Rev. 1. A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys. U.S. Nuclear Regulatory Commission, Washington, D.C., September 1998.

1



\ r



APPENDIX A

Instrument Calibration Certificates

Designer and Manufacturer

SGientific an~~ndustrlal Instruments

w• '"= \'\ .... - LUDLUM MEASUREMENTS, INC __ f:tevhuui ~- •·nu:· ...1 By .. ' Jii>Tia.

CERT/F/CA TE OF GAL/BRAT/ON 501 Oall Street ~

www {(tdlutm..cam 325-235-5494 ~I!OtTJ.ID S~N-eelwaler. TX 79556, U SA CERT 114084.01

Customer

Mfg.

Mfg.

Cal. Dale

DOES LLC

l,_ll_Qium M~.iOI __ syrements, Inc.

Lud1Umt\il~'!l:>l1!!"JI1l6J1IS: 111<;:_

Model

Model

__ ....,...,1.:<-9-.;..A~,Q"-r-lL_ _________ Cal Due Dale

ORDER NO. 20310184/448629 '"~··--~----~-

Serial No. -~~OK.:J-5 __________ _

... --------··-------- 43-68 Serial No. fR 0 ll.f 5'03 1 ~-,tl.pr:1lL_ Cat. Interval Meterface

Check mark ~pplies to applicable instr. and/or detector lAW mfg. spec. T. 13 •F RH 52 % A It 704.0 mm Hg

0 New Instrument Instrument Received ~hin Toler. +-10% n 10-20% Out ofTol.

G2f Mechanical Ck. bZf Meter Zeroed 0 Background Subtract

O Requiring Repair 0 Other-See comments

G2f Input Sens. Linearity G6 F/S Resp. ck b2f Reset ck. b2f Window Operation b2f Geotropism G;;r Audio ck. Glf Alarm Setting ck. ~ Batt. ck.

[g'Caiibrated in accordance with LMI SOP 14.8 0 Calibrated in accordance with LMI SOP 14.9 Threshold

Instrument Volt Set Comments V Input Sens. __ 1'-'0'--- mV Oet. Oper. _Q~_~_r11ents . V at 10 mV Dial Ratio __ _jQQ_ __ = GZf HV Readout (2 points) Ref.llnst. ____ ------~0_0 __ __

COMMENTS: firmware: 261010 Calibrated with window in OUT position. Calibrated with 5' cable. 4 pi Eff. for Th230.,19,80Cdpm is:22.82% 2 pi EJ:f. for Th230.,10,100cpm is: 44.75% Bc~ckgro.mnd; l<::prn Reading: 4, 52lcpm Background: lcpm Reading: 4,521cpm

?_()()_0 ____ 1 ____ -----

4 pi Eff. for Tc99~22, 700dpm is:39.26% Background: 329cpm Reading: 9,242cpru

2 pi Eft. for Tc99~!4,200cpm is: 62.76~ OL checked but

Backgrcund: J29cpm Reading: 9,242cpm not set. 4 pi Ef!. foL SrY90~31,419dpm is:35.90% Background: 329cpm Reading: 1:,6lOcpm 4 pi Eff. for C14.,221,080dpm is:12.42% Background: 329cpm Reading: 27,791cpm

2 pi Eff. for SrY90~21,993cpm is:51.29% Background: 329cpm ReadJ.ng: l1,610cpm 2 pi Etf. for Cl4~110,840cpm is:24.77% Background: 329cpm Reading: 27,79lcpm

Aloha Voltaqc·:.wr; v [;..-r;, v:.-Jta e:l725 v Instrument ::~:rr<"lll!" set tof l\1nha Voltage. Gamma CalloraUon: GM detectors oos:t:one er end1cvfar to source except fOrM 44-~• "' wh:ch the front o robe laces source.

RANGEJMUL TJPLJER x1K ______ _

REFERENCE CAL POINT

INSTRUMENT REC'D "AS FOUND READING"

L)Q.~~-----

INSTRUMENT METER READING ..

10

x1K __ 1 OOkcpm ___ __ K!QQ ______ _ ----~()~ppm_

I.<W .. _______ ~-

llb.C. ... ~ loQ --------

.. lt_~----

)(1Q ___ x_1JL.

_xt ~~---------·-

- -- __ _1_Q152P.!'l1 4/<QPJ1L

. J.Ci:l ______ _

4o..a _ ______l_Q_(::I

Lt!LQ _______ _ ___ lqg

--l~Q __ -------------~--· ~..ll.J) ..-lb_O _

~.b.O 1"0

v

•uncertainty within± 10% C.F within ± 20% ----------------- ·----------------- _ .. A~_l,, Range{s) Calibrated Electronically

rnV

REFERENCE

CAL. POINT

INSTRUMENT RECEIVED

INSTRUMENT

METER READING'

REFERENCE

CAL. POINT

INSTRUMENT RECEIVED

INSTRUMENT

METER READING•

Digital Readout ___ _iQOkcpm

40Js~;p_l!l_

4kcgm_ ~QQ~Ell..

____ 199P...!Il_

~Q_If _...uu .. 3.ct~.L __ __3_11 ...... . _llQ_ ·---~~~--~--

l}

Log Scale ~----?.QQl<~.RITI

_ ____ 5()k~m 5kcpm

_ __5Q_QqQJII_ __ §Q_9PI'll.

..5:9JL __ _t(~f!'!>

..5o_ -~--L-__s____ __ ~l

~ crm Ludlum Measurements, Inc certifies thal the abovelnatrumen\ has been calibr&!od by standards tr&CIOabl& to the National Institute of Standerds all(! Te<:tmology, or to the calibration I8Cttlties of olh•r tnterruational Stan~ards Organizatron members. or have be&n derived !rom accepted values of nalur&l pnysrcat constants or have been denved by the ratio type of calibration tochntq'*' Th$ calibration system <:ontorms to tha requirements ot ANSIINCSL ZS<I0-1-1994 and ANSI N323-1978 I SOliE 17025 2005(El State of Texas Calibration lie&nse No. L0-1963

Reference Instruments and/or Sources: ca-137 SIN: U 059 0 2171CP O 2261CP 0 120 O 734 0 781 0 1131 01616 0 tS96 0 1909 0 191SCP 0 232412521

O 57HCO 0 5719CO Os0646 070897 073410 0 c662 0 G112 216SCP 0 S-394 0 8·1054 0 T10061 0 T10082 Neutron Am·241 Be 0 H04 Ra-226 0 Y1l62

G2f Alpha SIN Pu239:2928,Th230:E121495 G2f Beta SIN __ .-:.T-=.cl!~tii-EV,SrY90:4016 Gi:j Other

Gif m 500 SIN 2.891!5JL______ 0 Oscilloscope SIN _____ _ G:r Multimeter SIN ___ --:::.9-::.38:::.7'-'0"-'6'-"3'-'-7 ___ _

Calibrator Title Date /'J ap~L:-: .. _1 ]_ ___ _

QC'd By Title Date

This csrlificale shall not be reproctuced except in run. w11h3'l the wrolten approval of Ludlum Measurement•, Inc

FORM SC22A 1211212018 Pag~ _L ol

CUSTOMER


Scientific an~1

1ndustrial Instruments

ODES LLC

CERTIFICATE OF CAL/ BRA TION

------------· ···-------- . -------· Mfg. Ludlum Measurements, Inc. Model

LUDLUM MEASUREMENTS, INC. 501 Oak Street 0 10744 Dutchtown Road

325·235-5<194 865-392-4601

Sweetwater. TX 7955!;, U.S.A. KncurviJle, TN 37932, U.SA

ORDER NO. 20299548/442123

Senal No. 3 fJ i~ 53 Mfg. Ludlum M~asurements._lf1C___ Model Serial Nf!/? 3/2 'fi..;- -----·-

Cal Due Date 1 Year Meterface ___ 202-159 __ _

Check mark fi'flpplies to applicable mstr. and/or detector JAW mfg. spec.

O New Instrument Instrument Received ~hln Toter. +-10%

T. __ _:_75:o_ 'F RH. ___ _:.4.::.6 % All 705.0 mm Hg

blf Mechanical ck G2f Meter Zeroed ~ F/S Resp. ck G2f Reset ck.

G2f Judie ck. 0 Alarm Setting ck.

0 10-20% 0 Out of Tol. 0 Requiring Repair 0 Other-See comments

0 Background Subtract

Glj' Window Operation GZf Batt. ck. (Min. Volt) 4.4 VDC

G2f Input Sens_ Linearity

[Y3' Geotropism

[3"Calibrated tn a~orctance with LMI SOP 14.8 L" ':>~~ ~~t!

[]Calibrated In accordance with LMI SOP 14.9 ~~t!. ~~ _ Threshold L

Instrument Volt Se~!O\tl\'6 V Input Sensl!p~ mV Det. Opef:.oJ/Wtl~~f.) V a~ltt:S mV Dial Ratio /t'?Q = /0

GZf HV Readout (2 points) Ref.llnst. ___ ;::.;50"""0,__ __ #f'j V Ref.llnst. 2000 / ?7 lJ

COMMENTS: Peak Settings

High Voltage:748v Thr~shold Setting:642

Window Setting:40 Window Position:"IN"

Resolution for Csl37:9.5]~

Gross counts 900 100 ( lOmv) n/a "OUT" r.; u.

Instrument currently set tor G!\OSS COUNT$.

Fi::nw;a.re:26l0'72 Ovez-lodd checke~ b~t no~ so~.

Gamma Calibration GM detectors positioned perpendicular to source exc<tpt forM 44-9 in which the front of probe faces source

RANGE/MULTIPLIER x1K x1K x100

x100

-~--~----

REFERENCE CAL POINT

400kcpm 100kcpm

40kcpm

____ 1Qk~=p-'-'m'-------4kcpm

1kcpm 400cpm 100cpm

-----------·---

INSTRUMENT REC'D "AS FOUND READING"

----~--100

INSTRUMENT METER READING*

:1£!

v

·uncenalnty Within± 10% C.F. within± 20% ------·-- ALL Range(s) Calibrated Electronically

REFERENCE INSTRUMENT INSTRUMENT REFERENCE INSTRUMENT INSTRUMENT

mV

CAL. POINT RECEIVED METER READING* CAL. POINT RECEIVED METER READING•

Digital 400kcQm J:l'i$ 3f;:r Log

500kq~m q')Uc lfS"#I~ Readout Scale

_ _iQ_kcpm_ '') 50kcem p~ ~ 4kcm:n_ ----1-'- Skq~m ______!£/L.__ n::

_____ 4_99.~ I} If II 500q~m ~1!_0 ~g.. 40cQm 10 __ j_l! 50cpm s- --~--

Ludlum ~asurements lnc cert\f,O$ that the above- rr'ts:mmPnl h:t!<: been calibrated ny standards traceanle to the Nationallnshtute of Standards and Technology, or to ttte ca!rbration facrhties of o(her intematronal Slandatds Drgan:zar.•on members, or na,•e been dtmyeO !tom a:;:C{!,oled values or nahJtal ptlys;cat constants 01 havo been denved by thcr r~tto type of cahbra'tton tocnmquos Ti1e oahbrahon syst"m cortormsto tne reqwrements of ANSI/NCSL Z540·1·1994 ond ANSI N3?3-1978 State of Texas Calibration license No. L0-1963

Referencelnstrumentsand/orSources:cs-137SINQ059[J2171CP [Jn5tCP Qno Cn4 Qra• O•t:11 Ot616 Qt696 01s09 Qt9t6CP 023241252' 0S717CQ 0 5719CO 06(1646 070697 073410 0 ES52 c; G112 U 2168(;P 0 S-394 0 S-1()540 TH)081 11008l NeutronAm-241 Be 0 T-304 Ra-726 0 Y982

r.;y6ther JL~f; IJ.B.Jp..f .• 0 Alpha SIN ---------- 0 BelaS/N ___ _

~f, .. BrttrPr oate 2-f/Dv __ .. , __ c. __ _ Gl m 500 SIN L 130362 O Oscilloscope SIN

Calibrator ~ £.~ Title

Gl Multimeter SIN 784010~--'-1 __ _

QC'd By ~~· Title f- / tJ Pr \ ~---- Date '-\ T\,) 'D ,,A l2 Tn.,s ccn'tlcate $:halt not be reprodut:ed except' iull. ~out thfl wflt1cn approval Of Ludlum Measurement~, Inc FORM C22A 07125/201C P•ge __ ol k_

AC lnst 0 PaMed Diel~ctric (Hi-Pot) and Continuity Test. ---·~ On~_QFailed: .. . ... _

Desrgner and Manufacturer ot

Scienlifrc and Industrial Instruments

LUDLUM MEASUREMENTS, INC. 501 Oak Street 0 10744 Dutchtown Road

325 235-5494 865-392-4601

Sweetwater. TX 79556, U.SA Knoxville, TN 37932. U.S.A.

Bench Test Data For Detector

Detector 44-10 Serial No. ff( } /2 'f'i l Customer ODES LLC Order#. 20299548/442123

Counter 2221 Serial No. 36 i 0) J

Count Time ........~o~.c........--"6¢~~= .. ~----· Counter Input Sensitivity J t:J mv

Distance Source to Detector

High Voltage Background

Isotope ~ /itiiJ:! 1

Isotope ___ _ Size I. f1: Size

Isotope ___ _ Size

··-------··-,..----·-

_7po Itt 1 cot 71'0 171 CfJZ!

_i__~ lttf lo J)l j)O }t:;b 1/68 z. t)pp loti I !71 I '1>o -~_Q ______ !1177

7ooo lDJ I /I 112 ·-r·

loso. .. 1 ...... 2.1J.L_c---LLJ:l..~-~----I )/)O 228 11~1~-

__ jj)O 2'{Z.. I Ill 'l.tt •..

"' ·------~~----~'~"

.J.2Qa_ z9q /Z77b

-------···-·--·-·r--·

____ ........ . ..... ,.

'

,_ ... J ----"-----

Isotope ___ _ Size

""--

Signature --~--"'~~~----1~...-£-=~-~----------- Date 2 -f/Dv""/ h,

FORM C4A 0212612013 Page_l_ot~ • Serving The Nuclear Industry Since 1962 •

;YSOLUTIONS CALIBRATION CERTIFICATE

EnergySolutions Instrument Services 1570 Bear Creek Road Oak Ridge, TN 37830 Phone: (877) 462-4873 Email: !Sfsla!T!Q ..:m:;n:v~'ioluti~.illll

r This Certificate will be accompanied hy Calibration Charts or Readm<>s where appllcab c

CUSTOMER INFORMATION DETECTOR INFORMATION

Customer Name: DDES Manufacturer: Ludlum

Address: 345 North Ave., 2nd Floor, Wakefield, MA 01880 Detector Model: 43-93

Contact Name: Chris Kovalovsky Serial Number: 299637

Customer Purchase: Work Order Evaluation Method: Order Number: Credit Card Number: 2017-15430 Source

DETECTOR EVALUATION INFORMATION (Efficiencies determined with source on contact)

Source Nuclide Serial Number Activity (dpm) 2 Pi Emissions Net Response (cpm) 4 pi Eff(%)

Tb-230 119738 18,597 8,639/ min 3,682 19.8

Tc-99 099608 21,311 10,499/ min 2,990 14.0

SrY-90 129676 11,295 7,956/ min 2,530 22.4

C-14 010002 259,909 72,506/ min 10,616 4.1

INSTRUMENT INFORMATION DETECTOR INFORMATION

2 pi Eff{%)

42.6

28.5

31.8

14.6

Model Serial Number Due Date Background Operating Voltage Threshold

2224-1 271532 06/22/18 3cpm 800V Alpha (120 mV)

2224-1 271532 06/22/18 184 cpm soov Beta (3.5- 30 mY)

ATTACHMENTS "'

Voltage Plateau: .JvEs NO

COMMENTS LINEARITY TEST (Cross Count~<)

Calibrated with 5 ft. cable Count 1 (Toe) 3,080

Linearity test performed with Tc-99, #099608. Count 2 (Mid) 3,153 "··-~-

Calibrated in accordance with original equipment technical manual.

Count 3 (Heel) 3,289

Average J,174

Pass/ Fail PASS (+/-10% Tolerance)

. STATEMENT OF CERTIFJCA TION W c ~~m~y Uult the detector listed above wa~ evaluated for proper 0 Lion ri r · . SpccJIJcallons. We further ccrtiJY that our Calibmtion Measurement:': tra P b~ to :tpme~t and that 11 met all the Manufacturers published operating damage incurred durin!! shioment or usc of this detector). . cea e to e Nattonallnstitute of Standards and Technology. (We are not responsible for Detector

Certified By: ~~~.~--- ReviewedBy: ~~~ {. "'' '2-7.-/ 'Zi> I 7

... ...--~ Date;

Certification Date: 06/22/2017,. l *Certification Due (6 mo.): 12/22/2017 I

.... atJbrauon aue date ts dependent on users regulatOiy requtremems. J *Certification Due (12 mo.): 06/22/20IS

EnergySolutions Services, Inc 1570 Bear Creek Road

Phone: (877) 462-4873 Fax; (865) 220-!346

CALIBRATION CERTIFICATE

Oak Ridge, TN 37830 Email: [email protected] http://WWIN .energysolutions.com/

liS erh tcate w1 Tl. C 'fi ·n b e accompame y .a 1 ratton · db c rb · Ch arts or ea mgs w ere appltca c R d. h r hi

CUSTOMER INFORMATION INSTRUMENT INFORMATION

Customer Name: DOES Manufacturer: Ludlum

Address: 345 North Ave., 2nd Floor, Wakefield, MA Model: 2224-1 S.N. 271532

Contact Name: Chris Kovalovsky Probe: 43-93 S.N. 299637 Customer Work Order

PO No.: Credit Card Number: 2017-15430 Calibration Method: Source

Source Information

Isotope Source ID Certifcation Date Activity ( dpm) a Source Pu-239 071601 7/25/16 23.887 !3 Source Tc-99 099608 818196 21,311

Ludlum Model 43-93 High Voltage Plateau with crosstalk

Operating High Background Alpha Source Beta Source Crosstalk Efficiency Voltage Voltage AIQ_ha Beta Alpha Seta Alpha Beta a to 13 13 to a a 13

750 2 101 5,358 309 9 2,013 3.88% 0.37% 22.42% 8.97% 775 1 141 5,723 344 4 2,517 3.55% 0.13% 23.95% 11.15%

SET 800 3 173 5,969 510 11 3,184 . 5.65% 0.27% 24.98% 14.13% 825 5 234 6,146 1,092 7 3,713 13.97% 0.06% 25.71°/o 16.32%

STATEMENT OF CERTIFICATION We Certify that the instrument listed above was calibrated and inspected prior to shipment and that it met all the Manufacturers published operating specifications. We further certify that our Calibration Measurements are traceable to the National Institute of Standards and Technology. (We are not

responsible for damage incurred during shipment or use of this instrument}.

Calibrated 6y: ~~- Reviewed By: ~~-L~ Date: ~~"l-_~'24:.\"1 / I

Calibration Date: 6/22/2017 Calibration Due: 6/2212018

Page 1 011

ERG\ SOLUTIONS

EncrgySolutions Instrument Services 1570 Bear Creek Road Oak Ridge. TN 37830 Phone: (877) 462-4873 Email: I SFstafl<a _£n<.:rg.xsnhJJitms.cmn

h r bl


This Certificate will be accompanied by Calibration Chans or Readings w ere app'JCa c


Manufacturer: Ludlum Customer Name: DDES

Addre~:~: 345 North Ave., 2nd Floor, Wakefield, MA 01880 Model: 2124-1 Serial Number: 271532

Contact Name: Chris Kovalovsky Probe: N/A Serial Number: N/A

Customer Purchase Order I Work Order Calibration Method:

Number: Credit Card Number: 2017-15430

Electronic

INSTRUMENT CALIBRATION INFORMATION

Calibration Ratemeter Response (cpm) Calibration Time Tolerances Scaler Response

Instrument Standard (± 10% of Calibration Standard Values) (count~)

Range Value Standard Base {counts)

(com) As Found As Left Value (min.) ±2% As Found As Left

XI 200 180 200 l,OOOCPM 0.5 450-550 498 498

XI 500 460 500 l,OOOCPM I 900-1,100 996 996

Xl 800 730 800 l,OOOCPM 2 1.8K-2.2K 1,993 1,993

X 10 2,000 1,800 2,000 l,OOOCPM 5 4.SK- S.SK 4,985 4,985

X 10 5,000 4,600 s,ooo Scaler readout rolls over after 999,999

X 10 8,000 7,300 8,000

X 100 20,000 18,000 20,000

X 100 50,000 46,000 50,000

X 100 so,ooo 73,000 80,000

X 1000 200,000 180,000 200,000 Calibrated In accordance with OEM Technical Manual

X 1000 500,000 460.000 500,000

XIOOO llOO,OOO 730,000 800,000

. . . STATEMENT OF CERTIFICATION We Certtfy U1at the mstrumentlisted above wa J'b ed .- -We furtller certitY Ill . . . s ca ' rat and mspected pnor to Shipment and that it met I incurred dwinll ship~~~o~~~~~~~~~ ~taSUrc:ments nrc traccnble to the National lm:titute of Standards a~ ~~~ru;ufuct~;~~ published "P"':"';"o "i""';r;.,.,ti<>no.

1

ts msuumc.:m). no ogy. e are not responsrble for damage

nstrument

Calibrated Bv: ~2/_ Reviewed 8~·: M "11 ~ { • u,/2-'2.-, "lb ( 7 Calibration Date: 06/2212017 / "Calibration Due (6 mo.): I2/22/20l7

Onto: f

'catmrauon-aue ctate 1s oepenuenr on users reg Jl; *Calibration Due {12 mo.)· 06/Z2/ZOI8 u atory rcqutrements. • •

;\SOLUTIONS Page 2 of2

2224 1 Model:-=--=-Serial Number: 271532

Environmental Conditions M&TE

11130117 lD#: 3590 Cal Due:

Volt Meter ID#: 10380178 Cal Due: 11117117 Barometer

06/27/1'1 Thermometer II>#: 3590 Ca\ Due: 11/30/17 Pulser ID#: 120935 Cal Due:

Humidity ID#: 958670 Cal Due: 12/06/17 Temp: 24.3 ·c Press: 741 mmHg Humidity: 36.7 %

Special Test

BAT Check Sat( ...J) Unsat { ) Geotropism Sat ( ...J) Unsat ( )

LCD Display Chccl• Sat ( .Y) Unsat ( ) Audio Cbeck Sat ( ...J) Unsat ( )

Mechanical Zero Sat ( ...J) Unsat ( ) LowBATSet Sat ( -J) Unsat ( )

Reset Sat ( ..J) Unsat ( )

HV Analog Display Sat ( .J) Unsat ( ) As Found As Left

High Voltage Calibration(± 10%) Alpha Sensitivity= 121 mY Alpha Sensitivity = 120 m V

Voltage Tolerance As Found As Left Beta Sensitivity"'" 3.8 mV Beta Sensitivity = 3.5 m V

500 450-550 431 496 Beta Window= 29.6 mV Beta Window= 30.0 mV

1000 900-1,100 863 1,000 Beta Setpoints- Pul~>e1· counts detected at 3.5 mV ± 1 mV

1,500 1,350 - 1,650 1,295 and shut off at 30 mV for beta. For Alpha channel counts

1,501 detected at 120 m V and above.

H. V. Set With Detector Not Connected Overload to be 3et lvitb detector to be used

COMMENTS

Calibrated In accordance with OEM Technical Manual

See detector certificate for High Voltaj!e sening

*"' Calibrated with 5 ft. cable **

Instrument

Callbrnted By: ~-:&-:. ReviewedBy: ~Lt...~ I"

Date: t.t}2.:z./ '21)7'7 Calibration Date: 06/22/2017 tr:? * Calibration Due (6 mo.): 1212212017 \-au oration ouc aate 1s oepcnclent on users regUlatory requJreme:tEaJibration Due (12 mo.): 06/2212018


lia1 Scientific an~flndustrial

LUDLUM MEASUKt:IVII:.I'IIVJ ... - -1-501 Oak street ~

CERTIFICATE OF CALIBRATION 325-235-5494 celffi~sCo1 l!;i:il Instruments Sweetwater. TX 79556, U.S.A 20310634/448~?----

0RDER NO._.-----~-W\WJ.ludtums.com

DESLLC ----- --------S-en"alNo 3!)'l}tJ:J\ ---customer D --- ---- 2224 1 -x_: - ------- Model _______ .E.~-.!.------ -~- ) ·•f Ludlum MeasuJ~men~..J!l£.______

4.,

93 Serial No. _ 3 .;s._ :5. · LL.L. -~

·•• g. --~ Model .,.. 1 Ye~r Meterface -·· 202·783 Mfg

Ludlum MeasurementsJJ..J}S___.._ 5

A 18

Cal. Interval ______ _ · 0 t 2 - ~r- 702 0 mm Hg

25_Anr:11__ Cal Due a e RH 4s % All---'-~· Cal. Date -=-' T. ___ ___B_ •F --

,..,(. ~-~ppllcable instr. and/or detector lAW mfg. spec. 0 Raqu~ring Repair 0 Other-See comments ChecK mark roPP . rJ Within Toler. +-10% 0 10-20% 0 Out ofTol.

0 New Instrument Instrument Recewed kd-"- !\ Background Subtract Input Sens. Linearity . .

1 I< \0 Meter Zeroed .. - . Geotropism Gif Mechamca c . . r;;:r Window Operatton

rx F/S Resp. ck blf Reset cSI<.tt' k ~ Batt. ck M • n Alarm e tng C . 00 . 4 9 [i3 Audto ck· U D Calibrated in accordance WJth LMI SOP 1 · ~ ~ed in accordance with LMI SOP 14.8 · t mV 'b?~T~~~~~ -----------·---ld1Janorau

0 800 v at Commen s 800 v Input Sens. Comments mV D&t. per. ------- ---- ·

Instrument Volt Set -- ----·- -.... t/ 00 I 'S Q 1---- V Ref.!Jnst.__ 1000

~ HV Readout (2 points) Ref.llnst. ----5---

COMMENTS: . d .30 . cal'd with Sft cable s ·120mv Beta Sens:3.5mv Beta Wrn ow. mv · ~~hs:t t:n;~ulate light leak ; HV set with detector not connected : F_irmware:3_90092 39% Th230 SN:E121495 Size:19800dpm, Counts:4039cpm, Background:1cpm, 4p; ~:~~-98% Th230 sN:E121495 Slze:10100cpm, Counts:4039cpm, Background.1cpm, 2p · ·

0

Tc99 SN·S280 Size·9~200dpm Counts:24477cpm, Background:217cpm, 4pt Eff:26.03Yo . . . · 2 iEff"4161%

Tc99 SN:5280 Siz.e;56300cpm, Counts:24477cpm, Background.217cpm. P . · . · % SrY90 SN:S281 Size:88007dpm, counts:32940cpm. Background:217cpm. 4pt Eff:37 .18

0

SrY90 SN:5281 Size:G1604cpm. Counts:32940cpm. Background:217cpm. ~pi ~ff-;3~: 1 Vo c1 4 SN:1476 Slze:229767dpm, Counts:9734cpm, Background:217cpm, 4pt Eff:4. 4~ ~14 s~:~47R Si.z~114~8~&1lm ~oun~:9734~Pcillar~g~~~i&u~~H8/lW4.f..g1irrMh~c~~ front of prOlle races source.

amma a lbra iOn. M de ec os••one e en cu INSTRUMENT REC'D REFERENCE •

RANGEJMUL TIPLIER x1000

___ x100!L_ ____ _ x100 xJ()_O ___ _

_ !<1Q__ ___ _ x10 ___ _

x1

.... xJ -------

CAL POINT "AS FOUND READING

400kcpm 100kcpm

_ _____ 40kcp~m~---______ 1Qisf2_rn_. ______ _ _______ 4kCR!!!._ ________ _

____ 1kcQ_m'.!......-----

___ ...:4"'0'-"0""cp"'-J1"!-·-----~____ 100cpm_ ----·

---·-··-------

__ ......:7:&.£/)~a"-··--l&a .'C:€..-'<<2:...........-t&

_,l.t?Oa. ____ v

INSTRUMENT METER READING*

___ __/v.,{)..JL!i __ lc41 iL __ /1!2 <?

mV

____ ,__,._

·uncertainty within :t 10% C.F. within± 20% ALL Range(s) Calibrated Electronically

REFERENCE INSTRUMENT

CAL. POINT RECEIVED

Digital ~.!i.tii[o) Readout 400kcQm ___ 40kcpm - -;;;;-?' 'f!tL.i-__ J!:kcpm_ _:fit:[¢ _ _{_

400q~m _-f::.e:_J_ 4Dcpm - _}f___/_

_____ ,,._

INSTRUMENT METER READING•

.19'166tt) Log Scale

~:t_i'_L_5 -:3'19

--~--·-~-

__ tj {.'" -- -u /

REFERENCE

CAL POINT

INSTRUMENT INSTRUMENT RECEIVED METER READING•

Ludlum Measurements, Inc. centfies tnattne aoove instrument nae been calibrated by standards traceable !o the National Institute of Standards and TecllnOiogy, or to lhe cafibralion facililie• of other lntemauonaf Standards Organt.za1ion member c. ar have btten derived from aeectpted valuu of natural physical eonslants or have been derived by the ratio type of calibration techniques. The calibration system conforms to the reqt.rirom.,nts or ANSVNCSL ZS<t0-1-1 994 and ANSI N323-1978 ISO/IE 17025 :2005(E) State of Texas Calibration license No. l 0-1963

ReferencelnstrumentsandlorSources:cs-137SJN:[]05902171CP 0 225\CP 0120 0734 O 7al 01131 01816 01696 Q1909 Q191GCP 0232412521

5717CO S719CO 060646 070097 073410 n E552 C G112 :J 2168CP 0 S-394 S-1054 0 T10081 0 T10082 NeutronAm-241 Be 0 T-304 Ra-226 [] Y982

[] Other -----··-------~---Gi{ Multimeter SIN _____ 862503§l.Q_ ____ _

Calibraj9,_,_r ________ _ Date _;]._ 5:"~../f-/4~ /.7

Date

Th1s certrt•cate shall not be reproduced excepf in full, wllh.P"' the written approval o! lll~lum Mell<tl(l!menls. Inc

fORM :ICZZA llflZ/ZO!G ""9" _l.._ Of _q_ !.

AC Ins!. 0 Passed Dielectric (Hi-Pot) and Conti_·". trlty Test • --·--~- Onty _jJ faileo: __________ .--=-==--·-==-:=-=

115!1 www.ludlums.com

Designer and Manufacturer of

Scientific and Industrial Instruments

Customer ODES LLC

Detector 43-93

Counter 2224-1

Count Time 1Minute

Other """-~----~

Serial No.

Serial No.

Background

LUDLUM MEASUREMENTS, INC.JiiPJla 501 Oak Street ~

325·235·5494 !'AC§EDIT"iii) sweetwater, TX 79o50, U.S.A. CERT # 4084.01

Bench Test Data For Detector

ORDER N0. ___ 20_3_1_o_63_4_14_4_8_94_9 __

P(L5"5~'S""S:C) Alpha Input Sensitivity mV

Beta Input Sensitivity mV

------------ Beta Window --~--mv

------- Distance Source to Detector -~~

Isotope Isotope ~..Jtf:i_il Siz:e -~ {f~Q~ Size <-g-"2ftJO.?'.gp',.._,

Gas Proportional detector count rate decreased

Gas proportional detector count rate decreased

~ 10% after 15 hour static test using 39" cable.

:,;; 10% after 5 hour static test using 39" cable and alpha/beta counter.

Signature Jason Flores Date

FORM SC4B 1211212016 Page • Serving Th& Nuclear Industry Since 1962 •

ERG\SOLUTIONS

Energy.\"olulions Instrument Services 1570 Bear Cr<:ek Roa<l Oak Ridge. TN 37830 Phone: (R77) 4b2-4873 Email: 1~.E.gulh1 cm.:n.:ys,>lutiollsxnm

IS ert1 1cate WI Th. C .fi be accoJTipanied oy Cali ration Charts or Readings where applicable b b



Customer Name: DDES, LLC Manufacturer: Ludlum

Address: 345 North Ave., 2nd Floor, Wakefield, MA 01880 Detector Model: 43-37


Customer Purchas~e: Work Order Evaluation Method: Order Number: Credit Card Number: 20.17-15442 Source

DETECTOR EVALUATION INFORMATION

Net Response Efficiency(%) Source Nuclide Serial Number Activity {dpm) 2 Pi Emissions (cpm)

(4pi) (2pi)

Th-230 H9738 18,597 8,6391 min 3,650 19.6 42M~

Tc-99 099608 21,311 10,499/ min 5,275 24.8 50.2

C-14 010002 259,936 72,514/ min 34,881 13.4 48.1

SrY-90 101502 42,973 24,569/mln 16,594 38.6 67.5

Efficiencies determined with source on contact.

SCALER INFORMATION DETECTOR INI<'ORMAHON

Model Serial Number Oue Oate Background (cpm) Operating Voltage Threshold

2221 176956 10/18/17 16 (alpha) 1,400V (alpha) Alpha & Beta 4 m V

2221 176956 10/18/17 1,233 (beta) 1,900V (beta) (40 on display)

ATTACHMENTS

Voltage Plateau: -.J YES NO

COMMENTS Linearity Test (Gross Counts)

**Detectors calibrated with a 2221 may be used with any 2221 provided that the Heel 6,449 instrument Is in calibration and the specific detector parameters (High Voltage

Center 6,568 & Threshold) are entered into the 2221 prior to use. *" Toe 6,567

Detector has 1 Jayer of Mylar (0.4 mg I cm2 total). Average 6,508

Precision test performed with Tc-99, #099608.

Pass/Fail PASS (+1-10% Tolerance) Calibrated in accordance with original equipment technical manual. 5 minute backl!round performed. Calibrated with 5 foot cable.

STATEMENT OF CERTIFICATION

We CertifY that the detector listed above was evaluated for proper operation prior to shipment and that it met all the Manufacturers published operating specification.~. We funher certify that our Calibration Measurements are trnceable to the National Institute of Standards and Technology. ( W care not responsible for damage incurred during shipment or 11se of this detector). Detector

r;Mi~ctk~-Certified By: ~~:'· Reviewed By_: Date: 7/7/r"L v I * Certit"Jiaffc{n Due (6 mo.): Ql/0712018

Certification Date: 07/07/2017 * Certification Due (12 mo.): 07/07/2018 · canoratton aue aate IS aependent on users regulatory requirements.

BACKGROUND PLATEAU 43-37 S/N 318754 7-7-17 1000 0 1050 0 1100 0 lJ.50 3 1200 ].4

1250 5 1300 13 1350 10

Q-.;;;;1..;;.4 o:;...;o _ __.:;;l ..... JJ a fr'A q l'i50 12

1500 16 1550 27 1600 66 1650 158 1700 2B8 1750 520 1800 942 1850 1349

ALPHA PLATEAU Th-230 ID# 1l9738 18,600 DPM 900 0 950 0 1000 0 \_

1050 0 1100 7 1150 530 1200 2581 1250 3265 1300 3449 .1350 3647

(T4'""1=4.;..;o 2:;.........._...;:;3""""6 6"-"0 a 1/~ Ff 1450 3671 1500 3754

BETA PLATEAU Tc-99 ID# 099608 21,312 DPM 1400 17 1450 15 ].500 25 lSSO 166 1600 n8 1650 1802 1700 3169 1750 4535 1800 5612 1850 6448

(1900 ss9s) .be.r, 1950 6805 2000 7477

EnergySolutions Services, Inc. 1570 Bear Creek Road Oak Ridge, TN 37830 Phone: (877)462-4873 Email: ISFStaffa cncrgYsuluti<>IKcom

Th' c 'fi ·u b IS Crt! cate WI · db c rb · Ch eaccompame t>y a 1 ratwn arts or h r bl R d. ca mgs w ere appnca e

CALffiRATION CERTIFICATE


Customer Name: ODES Manufacturer: Thermo Sdentlflc

Address: 345 Nortb Ave., 2nd Floor, Wakefield, MA 01880 Model: Electra lA Serial Number: 18728

Contact Name: Chris Kovalovsky Probe: See probe cert Serial Number: See probe cert

Contract Purchase Order I Work Order Calibration Method: Number: Credit Card Number: 2017-15430 Electronic and Source

INSTRUMENT CALffiRATION INFORMATION

Instrument Calibration Instrument Response {cpm) Standard

Range Value Before After Comments (Auto Ranging) (cpm) Calibration Calibration

0-lK 200 201 201 Pulser: 120935 Cal Due: 06/27/17

0 -IK 500 501 501 DVM: 20380178 Cal Due: 11/17/17

0-IK 800 801 801 TempfPress: 3590 Cal Due: 11/30/17

IK -IOK 2,000 2,001 2,001 Humidity: 958670 Cal Due: 12106/17

JK -IOK 5,000 5,012 5,012 Temp: 24.3 4 C

JK -10K 8,000 8,020 8,020 Humidity: 36.7%

IOK -lOOK 20,000 20,000 20,000 Pressure: 741 mmHg

IOK-lOOK 50,000 50,100 50,100

lOK-lOOK 80,000 80,200 80,200 Audio: SAT Backlight: SAT

tOOK-1M 200,000 200,000 200,000 Batt. Check: SAT Overange: SAT

tOOK-1M 500,000 501,000 501,000

lOOK-1M 800,000 802,000 802,000 Calibrated in accordance witb OEM Technical Manual and Industry

All resdini!,S within ±HJ'i'o ui Standard \'alues &J!Piicable standards

METER CALIBRATION TESTS COMMENTS

Test 1-Software Version 20 Test 5, 6, 7 Dac Tests SAT

Test 2- Keypad Test SAT Test 8- Calibrate HV SAT See detector calibration sheet for detector specific information. Calibration

Test 3- Display Test SAT Test 9- HV Error Check SAT performed with dead time off.

Test 4- Option Switches SAT

STATEMENT OF CERTIFICATION We Certify that the instrument listed above was calibrated and inspected prior to shipment and that it met all the Manufacturers published operating specifications. We further certify that our Calibration Measurements are traceable to the National Institute of Standards and Technology. (We are not responsible for damage incurred during shipment or use of this instrument).

Instrument

~?k; ~~· Date:_V/~J'U:> l '1 Calibrated By: - Reviewed Bv:

Calibration Date: 0612.112.017 (/ Calibration Due: 06121/2018

EnergySolutions Services. Inc. 1570 Bear Creek Road Oak Ridge, TN 3 7830 Phone: (877)462-4873 Email: lil!~tt!.!l~!.E~~\!.ill!~~

This Certificate wil I b e accompanie db c rb · Ch y a 1 ration arts or R d' h r bl ea mgs w ere appllca e



Customer Name: DDES Manufacturer: Thermo Scientific

Address: 345 North Ave., 2nd Floor, Wakefield, MA 01880 Model: GP13A Serial Number: 9017

Contact Name: Chris Kovalovsky Calibration Method: Contract Purchase Order Work Order Electronic and Source Number: Credit Card Number: 2017-15430

DETECTOR PARAMETER SETUPS

Parameter As Found As Left Parameter As Found As Left Comments

0 4.3 4.2 8 Unit CPM Unit CPM Pulser: 120935 Cal Due; 06/1.7/17

1 Off Off A On On Temp/Press: 3590 Cal Due: Il/30/17

3 900V 900V b Off Off Humidity: 9S8670 Cal Due: 12/06/17

4 3.00 uA 3.00 uA c Auto Auto DVM: 20380178 Cal Due: 11117/17

5 0 uS 4 uS E lnt lnt Temp: 24.3 oc Humidity: 36.7 %

6 1.50V 2.40V F S66 S66 Pressure: 741 mmHg

7 60s 60s n Offm Offm **Detector specific parameters must be entered into instrument manually in the SUPERVISOR mode**

INSTRUMENT INFORMATION

Model Serial Number Calibration Due Date

Electra lA 18728 06/21118

USED FOR EFFICIENCY DETERMINATION AND HV PLATEAUING

EFFICIENCY DETERMINATION

Isotope I Serial # f Decayed Activity Source Counts Background Counts Net Counts 4 pi Effieiency in % {CPM) JCPM} (CPM) (Determined on contact)

1-129/ #040202/95,682 DPM 16,485 3,240 13,245 13.8

f:fflcicncy will! i-125 is 15.5'!/o per Ludlum tech documem (see link). f-l:fl5 efrl<:icncy Is L36 times the efficiency of 1-129 {13.7 X 1.86 = 25.5}. bttp!!I\HV\\.Iudlums.com/imal".""'awmJI!Jdf files/DifTerences in Efficiencies for lndinP.nclf

Cs-137/#010701/17,265 DPM 8,765 3,240 5,525 32.0

STATEMENT OF CERTIFICATION We CertifY that the instrument listed above was calibrated and inspected prior to shipment and that it met all the Manufacturers published operating specifications. We funh<.T cenify that our Calibration Mcasurcm<.:nts arc traceable to the National Institute of Standards and Technology. {We arc not responsible for damage incurred during shipment or use of this instrument). Instrument

~~Q_t· ~~ _, Reviewed Bv: ~(-u('2.l>n Calibrated Bv: Date:

Calibration Date: 06/21/2017 ~

Calibration Due: 06/Zl/2018 .

Thermo Scientific GP13A HIGH VOLTAGE PLATEAU DATA SHEET

Serial Number: 9017 HIGH VOLTAGE BACKGROUND (CPM) SOURCE (CPM)

840 3,010 8,270

850 3,040 10,800

860 3,070 13,700

870 3,060 15,100

880 3,170 15,400

890 3,180 15,800

900 (SET) 3,270 16,600

910 3,310 17,000

920 3,430 16,900

930 3,690 17,200

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N!A N/A N/A N/A N/A

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

N/A N/A N/A

Plateau performed with !129 Source# 040202 at 95,682 dpm at center of detector

Performed By: Date: ~,zl-17

ERGYSOLUTIONS

EnergySolutions Instrument Services 1570 Bear Creek Road Oak Ridge. TN 37830 Phone: (877) 462-4873

Email: .t!l.!.-""'~:.."''"""'"'"'-'""-'-"'-'--''~'-=~"''

is ertl cate WI Th c 'fi 'II b e accompanied by C l'b . Ch a 1 ration h arts or Rea mgs w ere applicab e

CALIDRATION CERTIFICATE


Customer Name: DDESLLC Manufacturer: Ludlum

Address: 345 North Ave., 2nd Floor, Wakefield, MA 01880 D~tector Model: 43-68


Customer Purchase: Work Order Evaluation Method: Order Number: Credit Card Number: 2017-15442 Source

DETECTOR EVALUATION INFORMATION

Net Response Efficiency(%)

Source Nuclide Serial Number Activity (dpm) 2 Pi Emissions (cpm)

(4pi) (2j>i)

Th-230 119738 18,597 8,639/min 4,079 21.9 47.2

Tc-99 099608 21,311 10,499 I min 5,366 25.2 51.1

C-14 010002 259,941 72,515/ min 36,901 14.2 50.9

SrY-90 101502 42,973 24,569/ min 16,669 38.8 67.8

Efficiencies determined with source on contact.

SCALER INFORMATION DETECTOR INFORMATION

Model Serial Number Due Date Background (cpm) Operating Voltage Threshold

2221 176956 10/18/17 6 (alpha) 1,400V (alpha) Alpha & Beta 4 m V

2221 176956 10/18/17 333 (beta) 1,800V (beta) (40 on display)

ATTACHMENTS

Voltage Plateau~ .J YES NO

COMMENTS Linearity Test (Gross Counts)

** Detectors calibrated with a 2221 may be used with any 2221 provided that the Heel 5,730 Instrument is In calibration and the specific detector parameters (High Voltage

Center 5,727 & Threshold) are entered into the 2221 prior to use.** Toe 5,640

Detector bas 1 layer of Mylar (0.4 mg I cm2 total). Average 5,699

Precision test performed wltb Tc99 #099608.

Pass/Fail PASS (+/-10% Tolerance) Calibrated in accordance with original equipment technical manual. 5 minute background performed. C1tllbrated with 5 foot cable.

STATEMENT OF CERTIFICATION

We CertifY that tile detec£or listl!d above was evaluated f<1r proper operation prior to shipment and that it met all tlrc Mllllufactut·crs published operating specifications. We further certify that our Calibration Me-asurements are traceable to the National Institute of Standards and Technology. (We are not responsible for damage incurred during shipment or use of this <letector). Detector

Certified By: ~~-- Reviewed By: tv\.~ l . Date: -d II I Ul l1 v * Certification Due (6 mo.): 01/07/2018

Certification Date: 07/0712017 * Certification Due (12 mo.): 07/07/2018 · Lauora!lon aue aatc ts dependent on users regulatory re UJrements. q

BACKGROUND PLATEAU 43-68 S/N 314505 7-7-17 1000 0 1050 0 1100 0 1150 4 ~200 0 1250 0 1.300 0 1350 2

a!;?lt~ (l,.400 D 1450 4

1500 10 1.550 25 1600 55 1650 85 1700 171

~75~ 309

(I so= 31U Je .. :/4-1850 374 1900 412

ALPHA PLATEAU Th-230 ID# 119738 18,600 DPM 1000 0 1050 3 1100 1042 1150 2668 1200 3552 1250 3887 1300 3998 1350 3984

< .... 1 .... 4 o..;o;.._--..;4:;.;o..;..o 1;;.-D a~ A t:t 1450 4045 1500 4035

BETA PLATEAU Tc-99 ID# 099608 21,312 DPM 1400 6 l.450 24 1500 355 1550 1156 1600 2304 1650 3728 1700 5032 1750 5775

(1800 5793) "tl! f-q 1850 6111 1900 6473 1950 6864

ERGVSOLVTIONS

EnergySol!llions Services, Inc. 1570 Bc.-ar Creek Road

Oak Ridge. TN 3 7830 Phone: (877)462-4873 Email: ISFSta!li.!!£n<.:rgysolutiuns.<:£ill

CALIBRATION CJ<:RTIFICATE

IS ert1 1cate wr Th. c "fi e accom_panr v ~a 1 m 1on . arts or ·edb c rb r Ch ea mas w ere appJJca R d. h r bt e


Customer Name: DDESLLC Manufacturer: Ludlum

Address: 345 North Ave., 2nd Floor, Wakefield, MA 01880 Modt>J: J9 Serial Number: 297439

Contact Name: Chris Kovalo,·sky Probe: N/A Serial Number: N/A

Customer Purchase I Work Order Calibration Method: Order Number: Credit Card Number: 2017-15455 Electronic And Source

INSTRUMENT CALIBRATION INFORMATION

Range Calibration

Tolerances lnttrument Rtsponse Comments

Standard (llR/hr)

Value (.u.Rihr) As Found As Left Calibrated in accordance with

(J.tRihr) (JtRihr) CP-IN-WI-211

5000 4,000 JlRlhr 3,600 • 4,400 3,850 3,900 Pulser: 101500 Cal Due: 04/19118

Black 2,500 pRlhr 2,250 - 2, 750 2,500 2,500 DVM: 20380178 Cal Due: lJ/17/17

1,000 JlRlhr 900- 1,100 1,000 1,000 Temp/Press: 3590 Cal Due: 11/30/17

400 J1Rihr 360-440 380 395 Humidity: 958670 Cal Due: 12/06/17

500 250 f1Rihr 225-275 240 250 I Temp: 24.7 °C

Black Humidity: 36.4 % Input cpm- 16,600 90- 110 94 98 Pressure: 743 mmHg

Input cpm = 33,200 f80- 220 187 200

250 Input cpm = 19,920 108- 132 112 120 Geotropism: SAT Over Range: SAT

Red

Input epm = 8,300 45-55 46 49 Batteries: SAT Mech. Zero: SAT

Input cpm = 6,640 36-44 38.1 40.0 F/S Response: SAT Audio: SAT

50 Input cpm = 4,150 22.5-27.5 23.8 25.0 Light: SAT Reset: SAT

Black

Input cpm = 1,660 9-11 9.4 9.9 Source: 0497H Cert. Due: 09/16/17

Input cpm = 3,320 18-22 19.1 20.0 High Voltage: As Found: 758V As Left: 758V

25 Red Input cpm = 1,992 10.8- LU 11.4 12.0 epmiJ,tRfhr:

Input cpm = 830 4.5-5.5 4.7 4.9 As Found: 173 As Left: 166

Precision ·rest- Reading 1: 395 pRlhr 2: 400 pR/hr 3: 390 JlR/hr Mean: 395 J1Rihr Precision Test: SAT

COMMENTS

Special Remarks: High Voltage: 758V cpm/JIR/hr: 166

STATEMENT OF CERTIFICATION We Certify that tlte instrument listed llbove was calibrated and inspected prior to shipment and that it met all the Manuiacturers published operating specilications. We furthercenity that our Calibration Measurements are traceable to the National Institute of Standards and Technology. (We arc not responsible for damage incum.>d during shipment or use of this instrument). Instrument

.Calibrated By: ~7L 7"" ,.,....,. Reviewed By: 'l?!//]./!4··1-~~ Date: 7//V/17 ,

* ¢efHfication Due (6 mo.): 01/13/2018 Certification Date: 07!1.3J201 7

"'Certification Due (12 mo.): 0711312018 uultmltton oue oate 1s oe enoent on users re uiato p g ryreq u1rements.


US NRC License #24-16607-03 / ' \ I



APPENDIX B

Minimum Detectable Concentration Calculations

DDES,LLC. Analytical Worksheet

Minimum Detectable Concentration (MDC) Static Count Calculations for Liquid Scintillation Counter (95% confidence level via MARSSIM method)

Where:

2 3+3.29.j(Rb)(T,+b)(l+Ts+b!Tb) MDC(dpm!lOOcm )= ( )( )

EfT T,+b Eff. = LSC total efficiency, Counter cpm!NlST Standard dpm

Rb = LSC background rate ( cpm)

T, •• = Sample count time (minutes)

Tb = Background count time (minutes)

Static Count MDC CakuJatiOns '" I Isotope Eff. R• Ts+b T• MDC (Static)

H-3 62% 14

C-14 96% 20

P-32 100% 19

Minimum Detectable Concentration (MDC) Static Count

Calculations for Hand-Held Monitors

(95% confidence level via MARSSlM method)

I 60 25

I 60 19

I 60 17

MDC(dpmll00cm2~ 3+3.29.j(Rb)(T,.b)(l+:;+biTb) 2

(EJ/'.)(T,+b }(probeareacm /I OOcm )

Where: Eff. = instrument efficiency (2n geometry)

Rb = Average background rate (cpm)

T,+h = Sample count time (minutes)

T b = Background count time (minutes)

P = Probe area (cm2)

Static Count MDC Calculations

I Eff. R• Ts+b Tb p

Isotope

Probe: 43-68

C-14 I 14"2% 345"3 I 10 126

Probe: 43-93

C-14 I 14"6% 210"8 I 10 100

P-32 I 31.8% 126 I 10 100

Ref MARSSIM NUREG-1575

dpm/100 cm2

dpm/100 em'

dpm/100 em'

MDC (Static)

3751 dpm/100cm2

3641 dpm/100 cm2

13!1 dpm/100 cm2

Appendix B

NUREG-1507 MDC Worksheet


Scan Minimum Detectable Concentration (MDC)


(Scan MDA per ~JJ~EG-1575, 1'41f!R~I507 methodology)

JP (s, )(s, )(I OO~m 2 )

Where:

p ~ surveyor efficiency, per MARSSIM (0.5)

E, ~ instrument efficiency (2n geometry)

surface efficiency, I for gammas and high energy betas> I Mev Emax

(e.g. P-32, Cl-36, S/Y-90, etc.). 0.5 for low energy betas

(e.g. C-14, P-33, S-35, Tc-99, Ca-45, etc), 0.25

A~ probe active area ( cm2)

And,

Where:

And,

Where:

And,

Where:

MDCR=S, (60sec/min)/isec

MDCR ~ Minimum detectable count rate ( cpm)

S, ~ source counts in time interval, i.

d' ~ 1.38 for 95% true positive scan detection rate,

per, MARSSIM, Table 6.5

B, ~ Background counts in interval, i

B, =(Pb)(i)(lmin/60sec)

Ph ~ probe background count rate ( cpm)

i ~ observation interval

Ref MARSSIM NUREG-1575 NUREG-1507

Appendix B

MDC Worksheet


Propagation of Error

The actual value of MDC (wheiJ t:jiap<tfsmoth I minute), at the 95% confidence level, is: MDC= ± 1.960MDC

E

O"MDC MDC

Because most (if not all) calibration labs do not report Ch ,we must compensate as shown b

mmc = MDC~(';J2

+(: )2

+( ;;)2

=MDC ~]2 +(O"A)2 +[~]2 Rb A Rc

aMTJc = Standard deviation of Minimum Detectable Concentration, dpm/1 00crn2

Background counts obtained

th = Background count time interval, minutes

Rb = Background count rate, minutes

a A= Standard deviation of calibration source activity as reported on certificate of traceability A= Source activity, dpm, as reported on certificate of traceability C, = Total net sample conts (minus background counts) obtained at the

calibration facility when determining instrument efficiency

t, = Calibration facility count time interval, minutes

~ = Calibration facility net count rate (CJU

Ref MARSSIM NUREG-1575

Appendix B

NUREG-1507 MDC Worksheet

Scan Minimum Detectable Concentration (MDC)



(Scan MDA per MARSSIM/NUREG-1575, NUREG-1507 methodology)

Specific Scan MDC calculat

Pb=

i=

Bi=

d'=

Si=

MDCR=

43-68

C-!4

345.3 cpm

I sec

5.76 counts

!38

3.31 counts

198.63 cpm

Scan MDC Calculations

Isotope

Probe: 43-68

C-14

Probe: 43-93

C-14

P-32

Ref MARSSIM NUREG- I 575 NUREG-1507

£; E,

14.2% 0.25

14.6% 0.25

31.8% 0.50

43-93

C-14

Pb= 210.8 cpm Pb=

t= I sec i=

Bi= 3.51 counts Bi=

d'= 138 d'=

Si = 2.59 counts Si=

MDCR= 155.20 cpm MDCR=

A MDC(Scan)

126 62801 dpm/100 cm2

100 60J3j dpm/100 cm2

100 13801 dpm/100 cm2

Appendix B

Propagation of Error

(dpm/100cm2)

± I 730

± 1 699

+ I 160

MDC Worksheet



Final Status Survey Report South 2"d Street and Laclede Avenue Decommissioning

August 3, 2017 APPENDIXC

Facility Maps

Room: Cherokee Lab N-1111, N-1143, N-340 31' X 20'

Survey Unit: Room N-1111, N-1143, N-340

Sigma Aldrich Cherokee Radiological Final Status Survey

DOES, LLC 345 North Ave

Wakefield, MA 01880

• /'-._

\ f -· cces

~

lf Room: Laclede Lab G-109

23'x26'6"

'

Survey Unit: Room G-109

• Sigma Aldrich Laclede ODES, LLC

/'-._

Radiological Final Status Survey 345 North Ave \ ( Wakefield, MA 01880 .,-.

cces

~

u L/ ~

~ Room: Cherokee Lab N-1111 Hallway

Class 3

Survey Unit: Room N-1111 Hallway Class 3

Sigma Aldrich Cherokee DOES, LLC '-....

Radiological Final Status Survey 345 North Ave \ ( Wakefield, MA 01880 -· 00&5




August 3, 2017 APPENDIX D

Statistical Data

3H Removable Activity dpm/100cm2

Mean 87

Standard Error 0.05

Median 80

Mode 71

Standard Deviation 25

Range 109

Maximum 157

Minimum 48

Count 38

P-32 Removable Activity dpm/100cm 2

Mean 0 Standard Error 0.05

Median 0 Mode -4

Standard Deviation 6 Range 22

Maximum 11 Minimum -11

Count 21

C-14 Removable Activity dpm/100cm2


Median 7 Mode 5

Standard Deviation 4 Range 21

Maximum 21 Minimum 0

Count 38

C-14 Total Contamination Measurements dpm/100cm2


Median 123

Mode 296 Standard Deviation 306

Range 1423 Maximum 908 Minimum -514

Count 38

P-32 Total Contamination Measurements dpm/100cm2

Mean -13

Standard Error 0.05

Median -16

Mode 44

Standard Deviation 31

Range 97

Maximum 44

Minimum -53

Count 21

Gamma Total Contamination Measurements dpm/100cm2

Mean -479

Standard Error 0.05

Median 608

Mode N/A Standard Deviation 3560

Range 16424

Maximum 4431

Minimum -11992

Count 38

Lab ID Srvey Unit Class Samples Type 1 Error Beta Relative Beta Locations

Type 2 Error STD DEV Shift Required

SIG-CHK-N-1111 SU-1 1 38 0.05 0.05 305.59 7264.12 14

SIG-LCD-G-109 SU-2 1 21 0.05 0.05 31.00 71613.32 14

SIG-CHK-N-1111 Class 3 SU-3 3 5 0.05 0.05 131.00 16944.13 Judgmental

SIG-LCD-G-109 Class 3 SU-4 3 3 0.05 0.05 11.00 201819.82 Judemental

.---------------------------------------------------------------------------

Lab ID

SIG-CHK-Gl


US NRC License #24-16607-03 / ' \ I


August 3, 2017 APPENDIX E

Survey Data Structures & Systems

\

Building: Cherokee

Survey Unit Description:

Survey Type: 0 -----------------·

Survey

Sigma Aldrich Cherokee and Laclede Site Radiological Survey Form

Survey Unit/Area: N-1111, N-1143, N-340 ----------------·-··-----· --

Final Status Survey

Equipment 0 Routine 0 Characterization

Page_1_of_4_ - ·-- ·-·-·-·-·-·---------·--

~ Final Status

Completed by~ William Valentine Date: 7/27/2017 Survey Entered by: William Valentine Date: 7/31/2017

lnstType· Ins!. SIN. Cal Due Date: MOC. BKG(cpm)

2221 290825 4119/18 13= 437 dpm/100cm2

lnst. 13= 263

#1 Probe Type: Probe SIN----·-- lnstEff: Count Time:

I 43-68 314505 13= 12.42% 1 min

lost Type: lnst SIN Cal Due Oate: MDC: BKG (cpm)

PKI LSA 416707 Dally Energy Dependent 3H= 14

lnst. 14C = 20

#2 ------Probe Type: Probe SIN lnst Elf Count Time:

NA NA Energy 1 min Dependent

lnstType: lnst SIN· Cal Due Date. MDC BKG (cpm) Electra 1A 18728 6/21/2018 Y= 952 dpm/100cm2 Y=2360

lnst. #3

----Probe Type. Probe SIN lnst Elf: ·-couiiiT1me:

GP13A 9017 Y= 25.5% 1 min

Comments:

Reviewed By:

Removable Activity- Cherokee Lab N-1111, N-1143, N-340 Removable Activity

Survey Code Number DPM 3H /100cm

2 DPM

14C /100cm

2 Result

SIG CHK N-1111, N-1143, N-340 F c 1 95 8 <1000

SIG CHK N-1111, N-1143, N-340 F M 2 69 14 <1000

SIG CHK N-1111, N-1143, N-340 F c 3 82 11 <1000 SIG CHK N-1111, N-1143, N-340 F M 4 74 6 <1000

SIG CHK N-1111, N-1143, N-340 F c 5 115 5 <1000

SIG CHK N-1111, N-1143, N-340 w D 6 88 5 <1000

SIG CHK N-1111, N-1143, N-340 w D 7 68 5 <1000

SIG CHK N-1111, N-1143, N-340 F c 8 66 9 <1000

SIG CHK N-1111, N-1143, N-340 F c 9 104 16 <1000

SIG CHK N-1111, N-1143, N-340 F c 10 103 5 <1000 SIG CHK N-1111, N-1143, N-340 F c 11 98 14 <1000

SIG CHK N-1111, N-1143, N-340 F c 12 57 7 <1000

SIG CHK N-1111, N-1143, N-340 w M 13 108 10 <1000

SIG CHK N-1111, N-1143, N-340 w M 14 107 7 <1000

SIG CHK N-1111, N-1143, N-340 F c 15 71 6 <1000

SIG CHK N-1111, N-1143, N-340 F c 16 50 8 <1000

SIG CHK N-1111, N-1143, N-340 F c 17 62 5 <1000

SIG CHK N-1111, N-1143, N-340 F c 18 113 10 <1000

SIG CHK N-1111, N-1143, N-340 F c 19 62 14 <1000

SIG CHK N-1111, N-1143, N-340 w D 20 77 7 <1000

SIG CHK N-1111, N-1143, N-340 w D 21 71 4 <1000

SIG CHK N-1111, N-1143, N-340 F c 22 67 3 <1000 SIG CHK N-1111, N-1143, N-340 F c 23 78 7 <1000

SIG CHK N-1111, N-1143, N-340 F c 24 48 21 <1000

SIG CHK N-1111, N-i143, N-340 F c 25 112 0 <1000

SIG CHK N-1111, N-1143, N-340 F c 26 122 1 <1000

SIG CHK N-1111, N-1143, N-340 w D 27 141 3 <1000

SIG CHK N-1111, N-1143, N-340 w M 28 106 9 <1000

SIG CHK N-1111, N-1143, N-340 w M 29 101 8 <1000

SIG CHK N-1111, N-1143, N-340 w M 30 75 2 <1000

SIG CHK N-1111, N-1143, N-340 w D 31 102 8 <1000

SIG CHK N-1111, N-1143, N-340 w D 32 70 15 <1000

SIG CHK N-1111, N-1143, N-340 w M 33 93 4 <1000

SIG CHK N-1111, N-1143, N-340 w D 34 61 5 <1000

SIG CHK N-1111, N-1143, N-340 w D 35 75 7 <1000

SIG CHK N-1111, N-1143, N-340 w D 36 67 7 <1000

SIG CHK N-1111, N-1143, N-340 w D 37 106 10 <1000

SIG CHK N-1111, N-1143, N-340 w D 38 157 8 <1000

Total Activity Cherokee Lab N-1111, N-1143, N-340 Total Beta Total Gamma

Survey Code Number GrossCPM DPM/100cm2 Result GrossCPM DPM/100cm2

Result

51G CHK N-1111, N-1143, N-340 F c 1 356 197 <DCGL 3220 1451 <DCGL

51G CHK N-1111, N-1143, N-340 F M 2 264 345 <DCGL 3040 2949 <DCGL

51G CHK N-1111, N-1143, N-340 F c 3 290 -268 <DCGL 3010 627 <DCGL

51G CHK N-1111, N-1143, N-340 F M 4 257 296 <DCGL 2020 -1051 <DCGL


51G CHK N-1111, N-1143, N-340 w D 6 297 190 <DCGL 5080 675 <DCGL







51G CHK N-1111, N-1143, N-340 w M 13 271 394 <DCGL 1800 -1914 <DCGL




51G CHK N-1111, N-1143, N-340 F c 17 274 -380 <DCGL 2840 -39 <DCGL







51G CHK N-1111, N-1143, N-340 F c 24 358 211 <DCGL 2320 -2078 <DCGL



51G CHK N-1111, N-1143, N-340 w D 27 359 627 <DCGL 3120 -7012 <DCGL






51G CHK N-1111, N-1143, N-340 w M 33 332 824 <DCGL 3160 3420 <DCGL


51G CHK N-1111, N-1143, N-340 w D 35 197 -514 <DCGL 1850 -11992 <DCGL 51G CHK N-1111, N-1143, N-340 w D 36 226 -310 <DCGL 2910 -7835 <DCGL 51G CHK N-1111, N-1143, N-340 w D 37 242 -197 <DCGL 2890 -7914 <DCGL


Q

0 0 0

8 :9 .8. 8. u, •

. cv· 0 C~Y 12 • . + + + .6'. . . . • + +

. G): ·G· :G G: G):

..

$ 1:o 1:5 2:o . 2:5 . 3:o ·

G 0 G G

Room: Cherokee Lab N-llll,N-1143, N-340 1'x20'

Spacing: 6'

Survey Unit: Room N-1111, N-1143, N-340

Sigma Aldrich Cherokee

Radiological Final Status Survey

0

DOES, LLC

345 North Ave Wakefield, MA 01880

0

0

G

G

• /,

f • oces

Sigma Aldrich Cherokee and Laclede Site Radiological Survey Form

Building: Cherokee Survey Unit/Area: N-1111 Hallway Class 3

Survey Unit Final Status Survey

Descf!E!ion: --Survey Type: 0 Equipment 0 Routine 0 Characterization

~'··----~---~~-~~-~---"'"'M>~-·

Survey Completed b:;£: William Valentine Date: Survey Entered by: William Valentine Date:

lnstlype: lnst SIN' Cal Due Date: MDC:

Page_1_ of_4_

ts:l Final Status

7/27/2017

7/31/2017

BKG(cpm)

2224-1 271532 6/22/2018 P= 364 dpm/100cm2

(3= 126 lnst. #1 Probe Type

,~~-~

Probe SIN: lnstEff Count lome:

43-93 299637 13= 14.6% 1 min

I lnst Type, lnst SiN Cal Due Date: MDC: BKG(cpm)

PKI LSA 416707 Daily Energy Dependent 3H = 14

lnst. 14C = 20

#2 -·*-~- ·---~-------~-- ·~----·-- 'Gaunt Time -~

Probe Type Probe SIN - -instEff ____________


lnst Type, lnst S/N, Cal Due Date MDC: BKG(cpm)

lnst. #3 Probe Type Probe SIN lnst Elf Countnme:

Comments:

Reviewed By:

Removable Activity- Laclede Lab N-1111 Hallway Class 3 Removable Activity

Survey Code Number DPM 3H /100cm2

DPM C-14/100cm2

Result

SIG CHK N-1111 Hallway Class 3 F c 1 95 2 <1000



SIG CHK N-1111 Hallway Class 3 5 M 4 51 3 <1000


Total Activity Cherokee Lab N-1111 Hallway Class 3 Total Beta

Survey Code Number Gross CPM DPM/100cm2

Result

SIG CHK N-1111 Hallway Class 3 F c 1 172 315 <DCGL



SIG CHK N-1111 Hallway Class 3 5 M 4 152 178 <DCGL


u

Room: Cherokee Lab N-1111 Hallway Class 3

Survey Unit: Room N-1111 Hallway Class 3

Sigma Aldrich Cherokee Radiological Final Status Survey


Wakefield, MA 01880

' \ ( -.a

oces

.. OOeS Sigma Aldrich Cherokee and Laclede Site

Radiological Survey Form

Building: Laclede Survey Unit/Area: G-109 Page_1_ of_4_ -~-·-----.--~~---- ·-------------------------Survey Unit

Final Status Survey Description:

~Survey Type: 0 Equipment 0 Routine 0 Characterization IS] Final Status ----··-··--···---·····----···--·----- ·----·--·-----------·-·----.. ·-·--------------------~---·---------··-----------------·--·

Survey Completed by: William Valentine Date: 7/27/2017 Survey Entered b}': William Valentine Date: 7/31/2017

lnstType lnst. SIN: Cal Due Date: MDC: BKG (cpm)

2224-1 271532 6/22/2018 (3= 364 dpm/100cm2

lnst. J3= 126

#1 ProbeType _________ 1-:----------------------Probe SiN

f--------------lnst Eft

1--c---.--------Count T1me:

43-93 299637 (3= 14.6% 1 min

---

lnstType: lnst SIN Cal Due Date MDC BKG (cpm)

PKILSA 416707 Daily Energy Dependent 3H= 14

lnst. 14C = 20

#2 f--.:o--Probe Type: Probe SiN Ins! Eft CountT1me:

NA NA Energy 1 min De~endent

lnstType: lnst SIN· Cal Due Date MDC BKG (cpm)

lnst. #3 Probe Type: Probe SIN

- -----------------------Ins! Eft. Count Time:

Comments:

ll

----- ------------------------ ----------------------------------------·-----------i

I Reviewed By I e ~4""'7:~L---=--'-I D_ate ~I ~~WJ....,L-~7~-----~

Removable Activity- Laclede Lab G-109 Removable Activity

Gross DPM P-32 Net DPM P-

Survey Code Number /100cm2

32/100cm2

Result

SIG LCD G-109 F c 1 21 2 <1000

SIG LCD G-109 F c 2 12 -7 <1000

SIG LCD G-109 F c 3 20 1 <1000

SIG LCD G-109 w D 4 29 10 <1000

SIG LCD G-109 w M 5 15 -4 <1000

SIG LCD G-109 F c 6 14 -5 <1000

SIG LCD G-109 F c 7 26 7 <1000

SIG LCD G-109 F c 8 25 6 <1000

SIG LCD G-109 w D 9 18 -1 <1000

SIG LCD G-109 D G 10 30 11 <1000 SIG LCD G-109 F c 11 15 -4 <1000

SIG LCD G-109 F c 12 17 -2 <1000

SIG LCD G-109 F c 13 18 -1 <1000

SIG LCD G-109 w D 14 23 4 <1000

SIG LCD G-109 w M 15 14 -5 <1000

SIG LCD G-109 w M 16 19 0 <1000

SIG LCD G-109 w D 17 8 -11 <1000

SIG LCD G-109 w D 18 13 -6 <1000

SIG LCD G-109 w D 19 24 5 <1000

SIG LCD G-109 w D 20 19 0 <1000

SIG LCD G-109 w M 21 17 4 <1000

Total Activity Laclede Lab G-109 Total Beta

Survey Code Number Gross CPM DPM/100cm2 Result

SIG LCD G-109 F c 1 112 -44 <DCGL

SIG LCD G-109 F c 2 124 -6 <DCGL

SIG LCD G-109 F c 3 129 9 <DCGL

SIG LCD G-109 w D 4 115 -35 <DCGL

SIG LCD G-109 w M 5 128 6 <DCGL

SIG LCD G-109 F c 6 133 22 <DCGL

SIG LCD G-109 F c 7 119 -22 <DCGL

SIG LCD G-109 F c 8 116 -31 <DCGL

SIG LCD G-109 w D 9 114 -38 <DCGL

SIG LCD G-109 D G 10 140 44 <DCGL

SIG LCD G-109 F c 11 109 -53 <DCGL

SIG LCD G-109 F c 12 140 44 <DCGL

SIG LCD G-109 F c 13 117 -28 <DCGL

SIG LCD G-109 w D 14 123 -9 <DCGL

SIG LCD G-109 w M 15 110 -50 <DCGL

SIG LCD G-109 w M 16 130 13 <DCGL

SIG LCD G-109 w D 17 109 -53 <DCGL

SIG LCD G-109 w D 18 121 -16 <DCGL

SIG LCD G-109 w D 19 111 -47 <DCGL

SIG LCD G-109 w D 20 127 3 <DCGL

SIG LCD G-109 w M 21 130 13 <DCGL

G

8

G

G .. J . . . . . .

~[ 2'

0):

G)

0

G G

(): 8

Pr :8 . . . . . . . . . . . . ... ·~.

@_ . . . . . . . ·cv 12

0 0

Room: Laclede Lab G-109 23'x26'6"

Spacing: 8'3"'

Survey Unit: Room G-109

Sigma Aldrich Laclede


8

0

G


Wakefield, MA 01880 -· cces

.. OOEiiS Sigma Aldrich Cherokee and Laclede Site


Building: Laclede Survey Unit/Area: G-109 Class 3 1-_--------------------------

Survey Unit . D ipf Fmal Status Survey escn 1on:

Survey Type: 0 Equipment 0 Routine 0 Characterization

Survey Completed by: William Valentine Date: Survey Entered bv: William Valentine Date:

Ins! Type: Ins! S/N: Cal Due Date: MDC:

Page_1_ of 4 -------

[2] Final Status

7/27/2017

7/31/2017

BKG (cpm)

2224-1 271532 6/22/2018 P= 364 dpm/100cm2

P= 126 lnst. #1 --·--·--·-··--------··-··· ·------------- >----------------------

Probe Type Probe-SIN-:-------------- lnst Eff Count Time:

43-93 299637 (3= 14.6% 1 min

--

Ins! Type: lnst SIN Cal Due Date· MDC BKG (cpm)

PKILSA 416707 Daily Energy Dependent 3H = 14

In st. 14C = 20

#2 Probe Type Probe SIN Ins! Eff: --~untTime:


lnst Type In st. SIN Cal Due Date· MDC: BKG (cpm)

Comments:

r----------------------------------------------------------1

------------------------------------------------------------------1

I Reviewed By: I Date

Removable Activity- Laclede Lab G-109 Class 3 Removable Activity



32/100cm2

Result

SIG LCD G-109 Class 3 F c 1 21 2 <1000

SIG LCD G-109 Class 3 F c 2 12 -7 <1000

SIG LCD G-109 Class 3 D M 3 20 1 <1000

Total Activity Laclede Lab G-109 Class 3 Total Beta

Survey Code Number GrossCPM DPM/100cm2

Result SIG LCD G-109 Class 3 F c 1 120 -19 <DCGL

SIG LCD G-109 Class 3 F c 2 124 -6 <DCGL

SIG LCD G-109 Class 3 D M 3 117 -28 <DCGL

s

Room: Laclede Lab G-109 Class 3 23'x26'6"

Survey Unit: Room G-109 Class 3



ODES, LLC 345 North Ave

Wakefield, MA 01880

" \ l '%,•_.--.

cces




August 3, 2017 APPENDIX F

Total Effective Dose Equivalent Calculation

DandO Building Occupancy Scenario Page I of2

DandD Building Occupancy Scenario

DandD Version: 2.4.0 Run Dateffime: 8/2/2017 2:27:53 PM Site Name: Sigma 3300 S Second Street Description: TEDE 14C Calculation for Labs Nllll, N1143, N340 FileName:C:\Users\Owner\DandD _Docs\Sigma S Second Street 14C.mcd

Options:

Implicit progeny doses NOT included with explicit parent doses Nuclide concentrations are distributed among all progeny Number of simulations: I 00 Seed for Random Generation: 8718721 Averages ofsampled values used for behavioral and metabolic type parameters Averages of sampled values not used for derived behavioral or metabolic parameters

External Pathway is ON Inhalation Pathway is ON Secondary Ingestion Pathway is ON

Initial Activities:

I I

Area of Nuclide Contamination

(m2)

jt4C II UNLIMITED

!Justification for concentration: Max Value

Site Specific Parameters:

General Parameters:

Correlation Coefficients:

Summary Results:

I Distribution

IJcoNSTANT(dpm/100 cm**2)

!!Value 9.08E+02

I I I

file:/1/C:/Users/Owner/DandD _ Docs/Sigma%20S%20Second%20Street%2014C _bid_ Sum... 8/2/2017

DandO Building Occupancy Scenario Page 2 of2

90.00% of the 100 calculated TEDE values are< 6.17£-03 mrem/year. The 95 °/o Confidence Interval for the 0.9 quantile value ofTEDE is 5.74£-03 to 6.72E-03 mrem/year

file:/ I /C:/Users/Owner/DandD _ Docs/Sigma%20S%20Second%20Street%20 14C _bid_ Sum... 8/2/2017



DandD Version: 2.4.0 Run Dateffime: 8/2/2017 2:34:48 PM Site Name: Sigma 3300 S Second Street Description: TEDE Calculation for 3300 S Second Street Laboratory FileName:C:\Users\Owner\DandD _Docs\Sigma S Second Street 125l.mcd

Options:

Implicit progeny doses NOT included with explicit parent doses Nuclide concentrations are distributed among all progeny Number of simulations: 100 Seed for Random Generation: 8718721 Averages of sampled values used for behavioral and metabolic type parameters Averages of sampled values not used for derived behavioral or metabolic parameters


Initial Activities:

: I


(m2)

\1251 II UNLIMITED

jJustification for concentration: Max Value


General Parameters:


Summary Results:

I Distribution

llcONSTANT(dpm/100 cm**2)

llvalue 4.43E+03

I I I

file:/1/C:/Users/Owner/DandD _ Docs/Sigma%20S%20Second%20Street%20 125I_bld _Sum... 8/2/2017

DandD Building Occupancy Scenario Page 2 of2

90.00% of the 100 calculated TEDE values are< 1.61£-01 mrem/year. The 95 °/o Confidence Interval for the 0.9 quantile value ofTEDE is 1.55£-01 to 1.68£-01 mrem/year

file:///C:/Users/Owner/DandD_Docs/Sigma%20S%20Second%20Street%20125I_bld_Sum... 8/2/2017

DandO Building Occupancy Scenario Page I of2


DandD Version: 2.4.0 Run Dateffime: 8/3/2017 10: 18:44 AM Site Name: Sigma 2909 Laclede Avenue Description: TEDE 32P Calculation for Lab G 109 FileN ame:C :\U sers\Owner\DandD _ Docs\Sigma Laclede A venue 32P .mcd

Options:

Implicit progeny doses NOT included with explicit parent doses Nuclide concentrations are distributed among all progeny Number ofsimulations: 100 Seed for Random Generation: 8718721 Averages of sampled values used for behavioral and metabolic type parameters Averages of sampled values not used for derived behavioral or metabolic parameters


Initial Activities:

I I


(m2)

j32P IIUNLIMITED

\Justification for concentration: Max Value


General Parameters:


Summary Results:

I Distribution

JJcoNSTANT(dpm/100 cm**2)

1\Value 4.40E+Ol

I J I

file:/1/C:/Users/Owner/DandD _Docs/Sigma%20Laclede%20Avenue%2032P _ b1d _Summary... 8/3/2017


90.00% of the 100 calculated TEDE values are< 1.16E-04 mrem/year. The 95 °/o Confidence Interval for the 0.9 quantile value of TEDE is 1.07E-04 to 1.27E-04 mrem/year

file:/1/C:/Users/Owner/DandD _Docs/Sigma%20Laclede%20Avenue%2032P _bld_Summary... 8/3/2017

Sigma-Aldrich Manufacturing


\ i


August 3, 2017 APPENDIXG

Quality Assurance Data

.. ooes Sigma Aldrich Cherokee and Laclede Site


Building: Laclede Survey Unit/Area: G-109 QC

Survey Unit Final Status Survey Description:

Survey Type: D Equipment D Routine D Characterization !-=-·--·-·· ..

Survey r-Ss>.ll1~_t~_d by: __ ~il_l~~!!l-~~-len~_!!e Date: Survey Enteredi:Jy William Valentine Date:

lnstType. Ins!. SIN. Cal Due Date· MDC:

Page _1_ of_4 _

[;23 Final Status

7/27/2017

7/31/2017

BKG (cpm)

2224-1 271532 6/22/2018 13= 364 dpm/1 00cm2

13= 126 lnst. #1 Probe Type Probe SIN: /nst Eft: Count Time.

43-93 299637 13= 14.6% 1 min

lnst Type lnst SIN Cal Due Date. MDC: BKG (cpm)

PKI LSA 416707 Daily Energy Dependent 3H = 14

lnst. 14C = 20

#2 ----·-------- --Probe Type Probe SIN lnst Eft. Count Time:

NA NA Energy 1 min i Dependent - - ---

lnst Type Ins!. SIN Cal Due Date: MDC:

I BKG (cpm)

lnst. #3

!-~----·--·,..-··-·-----Probe Type -Probe SIN ------rinstEft: Count Ti.me:

Comments:

f;-·---------··-·-------·---·-----·------------------------ -------!

l Reviewed By:

Removable Activity- Laclede Lab G-109 QC Removable Activity



32/100cm2

Result

SIG LCD G-109 QC F c 1 19 0 <1000

SIG LCD G-109 QC F c 2 18 -1 <1000

SIG LCD G-109 QC F c 3 17 -2 <1000

SIG LCD G-109 QC w D 4 27 8 <1000

SIG LCD G-109 QC w M 5 15 -4 <1000

SIG LCD G-109 QC F c 6 22 3 <1000

SIG LCD G-109 QC F c 7 20 1 <1000

SIG LCD G-109 QC F c 8 9 -10 <1000

SIG LCD G-109 QC w D 9 15 -4 <1000

SIG LCD G-109 QC D G 10 19 0 <1000 SIG LCD G-109 QC F c 11 20 1 <1000

SIG LCD G-109 QC F c 12 20 1 <1000

SIG LCD G-109 QC F c 13 21 2 <1000

SIG LCD G-109 QC w D 14 20 1 <1000

SIG LCD G-109 QC w M 15 22 3 <1000

SIG LCD G-109 QC w M 16 18 -1 <1000

SIG LCD G-109 QC w D 17 19 0 <1000

SIG LCD G-109 QC w D 18 21 2 <1000

SIG LCD G-109 QC w D 19 17 -2 <1000

SIG LCD G-109 QC w D 20 15 -4 <1000

SIG LCD G-109 QC w M 21 18 4 <1000

,....---------------------------- --------------

Total Activity Laclede Lab G-109 QC Total Beta

Survey Code Number GrossCPM DPM/100cm2

Result

SIG LCD G-109 QC F c 1 127 7 <DCGL

SIG LCD G-109 QC F c 2 110 -110 <DCGL


SIG LCD G-109 QC w D 4 125 -7 <DCGL

SIG LCD G-109 QC w M 5 126 0 <DCGL


SIG LCD G-109 QC F c 7 127 7 <DCGL



SIG LCD G-109 QC D G 10 122 -27 <DCGL





SIG LCD G-109 QC w M 15 115 -75 <DCGL







0

8

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(0: ·cq .8 . . . . . . . . . . . . ... ·r.r,.

81 . . . . .

cv· . . ·cv 12

0 G 0

Room: Laclede Lab G-109 QC 23'x26'6"

Spacing: 8'3"'

Survey Unit: Room G-109 QC



8

0

G

DOES, LLC

345 North Ave Wakefield, MA 01880 v-a

oces

Sigma-Aldrich Manufacturing


\ I


August 3, 2017 APPENDIX H

Survey Coding System

Sigma Aldrich Cherokee and Laclede Survey Coding

Sigma Aldrich- Building- Survey Unit- Surface- Material- Number

Example: SIG-LCD-G 109-F-C-1

Surface Codes:

F Floor

w Wall

D Door

B Bench

s Sink

H Hood

Material Codes:

M Metal

c Concrete

D Drywall

A Asbestos T Transite

Tomczak, Tammy

From: Sent: To: Subject: Attachments:

Lee, Peter Thursday, September 21, 2017 4:01PM Tomczak, Tammy FW: Final Status Survey Report and License termination request Sigma Aldrich 2nd Street and Laclede Final Status Survey Report Final Draft 09-21-17.pdf; FSS and License termination request 24-16607-03 2017-09-2l.docx

From: Tom Spencer [mailto:[email protected]] Sent: Thursday, September 21, 2017 2:35PM To: Lee, Peter <[email protected]> Cc: Cheryl Stipsits <[email protected]>; Brian Delmez <[email protected]> Subject: [Externai_Sender] Final Status Survey Report and License termination request

RE: License 24-16607-03

Dr. Lee,

I've attached two files to this email. One is a cover letter requesting license termination. The other is a final status survey report prepared by DDES, LLC.

As I mentioned in the cover letter, please contact me if you have any questions regarding the report or the license termination request.

Regards,

Tom Spencer R&D Principal Scientist Bio-Organic Production

D MilliporeSigma A subsidiary of Merck KGaA, Darmstadt, Germany

Sigma-Aldrich Corp I 3500 DeKalb St. I Saint Louis, MO I 63118 I USA Phone: +1 (314) 286-6600, x3186 I Fax: (314) 286-7826

Email: [email protected] I www.sigma-aldrich.com

This message and any attachment are confidential and may be privileged or otherwise protected from disclosure. If you are not the intended recipient, you must not copy this message or attachment or disclose the contents to any other person. If you have received this transmission in error, please notify the sender immediately and delete the message and any attachment from your system. Merck KGaA, Darmstadt, Germany and any of its subsidiaries do not accept liability for any omissions or errors in this message which may arise as a result of E-Mc;til-transmission or for damages resulting from any unauthorized changes of the

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