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NASA Glenn Research Center Building 140 Cyclotron Vault Final Status Survey Report

The National Aeronautics and Space Administration

John H. Glenn Research Center Lewis Field

Cleveland, OH

Revision 0 March 31, 2017

Work Performed Under NASA Glenn Research Center

Radioactive Materials License No. 34-00507-16

Prepared:

Field Services Manager Date: 3/31/17

Reviewed:

Dave Culp

Project Manager Date: 4/17/17

Approved:

Dustin G. Miller, CHP

NASA GRC

Radiation Safety Officer Date: Chris Blasio, CHP, CIH

Prepared by: Chase Environmental Group, Inc.

200 Sam Rayburn Parkway Lenoir City, TN 37771

NASA Glenn Research Center Lewis Field March 31, 2017

Building 140 Cyclotron VaultFinal Status Survey Report

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TABLE OF CONTENTS

1.0 INTRODUCTION.................................................................................................. 1 2.0 FACILITY DESCRIPTION ................................................................................. 2 3.0 SITE OPERATING HISTORY ............................................................................ 4 4.0 LEIDOS CHARACTERIZATION SUMMARY ................................................ 4 5.0 NUCLIDES OF CONCERN ................................................................................. 8 6.0 RELEASE CRITERIA .......................................................................................... 8 7.0 SCENARIO AND CRITICAL GROUP .............................................................. 9 8.0 DERIVED CONCENTRATION GUIDELINE LEVELS (DCGL) ................ 10 9.0 SURVEY INSTRUMENTATION ...................................................................... 13

9.1 Instrument Calibration ........................................................................................ 13 9.2 Functional Checks .............................................................................................. 13 9.3 Efficiency Determination ................................................................................... 13 9.4 Minimum Detectable Concentrations ................................................................. 13

9.4.1 Static Counting............................................................................................ 14 9.4.2 Ratemeter Scanning - Surface ..................................................................... 14 9.4.3 Ratemeter Scanning – Volumetric .............................................................. 15 9.4.4 Smear Counting .......................................................................................... 21

9.5 Instrumentation Specifications ........................................................................... 22 9.6 Datalogging ........................................................................................................ 23

10.0 CYCLOTRON REMOVAL ................................................................................ 24 11.0 REMEDIATION .................................................................................................. 25 12.0 FINAL STATUS SURVEYS ............................................................................... 25

12.1 Background Determination ................................................................................ 25 12.2 Data Quality Objectives ..................................................................................... 25 12.3 Area Classifications ............................................................................................ 26

12.3.1 Non-Impacted Area ..................................................................................... 26 12.3.2 Impacted Areas ........................................................................................... 26

12.4 Survey Units ....................................................................................................... 27 12.5 Surface Scans ..................................................................................................... 28 12.6 Total Surface Activity Measurements ................................................................ 29 12.7 Dose Rate Measurements ................................................................................... 29 12.8 Number of Samples ............................................................................................ 30

12.8.1 Determination of the Relative Shift ............................................................ 30 12.8.2 Determination of Acceptable Decision Errors ............................................ 31 12.8.3 Number of Data Points for Surface Activity (Sign Test) ............................ 31 12.8.4 Number of Data Points for Volumetric Activation (WRS Test) ................. 31

12.9 Sample Locations ............................................................................................... 32 12.10 Removable Surface Activity Measurements ...................................................... 33 12.11 Surveys of Building Mechanical System Internals ............................................ 34 12.12 Survey Investigation Levels ............................................................................... 34

13.0 SURVEY DOCUMENTATION ......................................................................... 34 14.0 SURVEY RESULTS ............................................................................................ 35

14.1 Volumetric Scan Results .................................................................................... 35 14.2 Surface Scan Results .......................................................................................... 35



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14.3 Total Surface Activity Results ........................................................................... 35 14.4 Removable Surface Activity Results .................................................................. 36 14.5 Systems Survey Results ..................................................................................... 36 14.6 Dose Rate Measurement Results ........................................................................ 36 14.7 Locations of Elevated Activity ........................................................................... 36

15.0 INTERPRETATION OF SURVEY RESULTS ................................................ 37 15.1 Data Validation .................................................................................................. 37 15.2 Preliminary Data Review ................................................................................... 37

15.2.1 Surface Activity Data Review .................................................................... 38 15.2.2 Volumetric Activity Data Review .............................................................. 40

15.3 Determining Compliance for Surface Activity .................................................. 41 15.4 Determining Compliance for Volumetric Activity ............................................ 41

16.0 MECHANICAL SYSTEM SURVEY DATA ANALYSIS ............................... 42 17.0 QUALITY ASSURANCE SURVEY RESULTS ............................................... 42 18.0 ALTERNATE SCENARIO ANALYSIS ........................................................... 43

18.1 Beam Tube Analysis .......................................................................................... 43 18.1.1 Beam Tube Descriptions ............................................................................. 44 18.1.2 Survey Protocol ........................................................................................... 45 18.1.3 Background ................................................................................................. 46 18.1.4 Dose Modeling ............................................................................................ 47

18.2 Soil Scenario Analysis ....................................................................................... 48 18.3 Recycling and Re-use Scenarios ........................................................................ 49

18.3.1 Volume Considerations ............................................................................... 50 18.3.2 Activity Concentrations .............................................................................. 52 18.3.3 NUREG 1640 Processing Dose Conversion Factors .................................. 53 18.3.4 NUREG 1640 Disposal Dose Conversion Factors ..................................... 53 18.3.5 Processing Dose Calculations ..................................................................... 54 18.3.6 Disposal Dose Calculations ........................................................................ 55 18.3.7 Results ......................................................................................................... 56 18.3.8 Alternate Scenario Conclusions .................................................................. 56

19.0 SUMMARY .......................................................................................................... 57 20.0 REFERENCES ..................................................................................................... 58

TABLES Table 4-1: Cyclotron Vault Concrete Core Results Summary (Leidos 2011) .................... 5 Table 4-2: Decay-Corrected Concrete Core Results Summary .......................................... 5 Table 5-1: Concrete Radionuclide Distributions ................................................................ 8 Table 8-1: Surface Activity Screening Values .................................................................. 10 Table 8-2: Removable Activity Contribution to Total Dose ............................................ 12 Table 8-3: Summary of DCGLs ........................................................................................ 12 Table 9-1: NaI Detector Response (cpm per μR/hr) for Eu-152 in Concrete ................... 18 Table 9-2: NaI Scan MDC: Concrete, 10,000 cpm bkg, 5 in/sec @ 2” distance .............. 19 Table 9-3: NaI Scan MDC: Concrete, 7,000 cpm bkg, 5 in/sec @ 2” distance ................ 19 Table 9-4: NaI Detector Response (cpm per μR/hr) for Co-60 in 1” Steel ...................... 20



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Table 9-5: NaI Scan MDC for 1” Steel Plate, 10,000 cpm bkg, 5 in/sec @ 2” Distance . 20 Table 9-6: NaI Scan MDC for 1” Steel Plate, 7,000 cpm bkg, 5 in/sec @ 2” Distance ... 21 Table 9-7: Instrumentation Specifications ........................................................................ 22 Table 9-8: Typical Instrument Operating Parameters ....................................................... 23 Table 10-1: Cyclotron Components Shipped for Disposal ............................................... 24 Table 12-1: Building Structural Survey Units .................................................................. 28 Table 12-2: Building Systems Survey Units ..................................................................... 28 Table 12-3: Survey Investigation Levels .......................................................................... 34 Table 14-1: Locations of Elevated Activity ...................................................................... 37 Table 15-1: Structural Surfaces - Surface Activity Scan Results ..................................... 38 Table 15-2: Structural Surfaces - Total Beta Surface Activity Summary ........................ 38 Table 15-3: Structural Surfaces - Removable Surface Activity Summary ....................... 39 Table 15-4: Structural Surfaces - Removable H-3 Activity Summary ............................. 39 Table 15-5: Systems - Total Beta Surface Activity Summary .......................................... 39 Table 15-6: Systems - Removable Surface Activity Summary ........................................ 39 Table 15-7: Systems - Removable H-3 Surface Activity Summary ................................. 39 Table 15-8: Structural Surfaces – Gamma Scan Results .................................................. 40 Table 15-9: Structural Surfaces – Dose Rate Summary ................................................... 40 Table 15-10: Structural Surfaces - Total Surface Activity Dose Calculations ................. 41 Table 15-11: Structural Surfaces - Volumetric Activity Dose Calculations ..................... 42 Table 17-1: QA Survey Locations .................................................................................... 42 Table 17-2: QA - Total Beta Surface Activity Summary ................................................. 43 Table 17-3: QA - Removable Surface Activity Summary ................................................ 43 Table 17-4: QA - Removable H-3 Activity Summary ...................................................... 43 Table 17-5: QA - Dose Rate Summary ............................................................................. 43 Table 18-1: Beam Tube and Beam Dump Information .................................................... 44 Table 18-2: Beam Tube Gamma Scan Summary Statistics .............................................. 46 Table 18-3: Beam Tube Background Measurements ........................................................ 47 Table 18-4: Beam Tube Mass and Activity Calculations ................................................. 48 Table 18-5: Soil Dose Modeling Geometry ...................................................................... 49 Table 18-6: Activated Concrete Mass Calculations .......................................................... 51 Table 18-7: Activated Steel Mass Calculations ................................................................ 52 Table 18-8: Activated Steel Mass Calculations ................................................................ 53 Table 18-9: NUREG 1640 Processing Dose Conversion Factors .................................... 53 Table 18-10: NUREG 1640 Steel Disposal Dose Conversion Factors ............................. 54 Table 18-11: NUREG 1640 Concrete Disposal Dose Conversion Factors ...................... 54 Table 18-12: Concrete Road Building Dose Calculations ................................................ 54 Table 18-13: Steel Scrap Yard Dose Calculations ............................................................ 55 Table 18-14: Concrete Disposal Calculations ................................................................... 55 Table 18-15: Concrete Disposal Leachate Dose Calculations .......................................... 55 Table 18-16: Steel Scrap Disposal Calculations ............................................................... 55 Table 18-17: Steel Scrap Disposal Leachate Dose Calculations ...................................... 56



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FIGURES Figure 2-1: Facility Floor Plan ............................................................................................ 3 Figure 4-1: Concrete Boring Locations with Eu-152 Concentrations (pCi/g) .................... 6 Figure 4-2: Subsurface Soil Sample Locations and Results ............................................... 7

APPENDICES

Appendix A ‐ Site Satellite Photo Appendix B ‐ Facility Layout Appendix C ‐ DSV Dose Modeling DandD Reports Appendix D ‐ Instrument Calibration Records Appendix E ‐ MicroshieldTM Output Reports for MDC Calculations Appendix F ‐ 4-Plots Graphs: Volumetric Activity Scans Appendix G ‐ 4-Plots Graphs: Surface Activity Scans Appendix H ‐ Structural Surfaces Final Status Survey Results Appendix I ‐ Systems Final Status Survey Results Appendix J ‐ Dose Rate Survey Results Appendix K ‐ Final Status Survey Location Maps Appendix L ‐ Quality Assurance Survey Results Appendix M ‐ Beam Tube Identification Map Appendix N ‐ Beam Tube 4-Plots Appendix O ‐ Beam Tube Activity Calculations and MicroshieldTM Output Reports Appendix P ‐ Soil Analysis RESRAD Output Reports



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ACRONYMS

ALARA As Low As Reasonably Achievable DCF Dose Conversion Factor DCGL Derived Concentration Guideline Level DQO Data Quality Objective DOT Department of Transportation DSV Default Screening Value EPA US Environmental Protection Agency FSS Final Status Survey GRC Glenn Research Center H0 Null Hypothesis HA Alternative Hypothesis MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NASA National Aeronautics and Space Administration NIST National Institute of Standards and Technology NRC U.S. Nuclear Regulatory Commission RWP Radiation Work Permit TEDE Total Effective Dose Equivalent



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1.0 INTRODUCTION

The National Aeronautics and Space Administration (NASA) has decided to decommission Building 140, a radioactive material usage location under their byproduct Nuclear Regulatory Commission (NRC) license number 34-00507-16. The facility contained a 69-inch cyclotron within a shielded vault and various support areas. NASA contracted with Chase Environmental Group, Inc. (Chase) through Pinnacle Construction and Development Corporation (Pinnacle) to remove the cyclotron and decommission areas that are impacted for activation products; i.e., the vault and beam tubes. Based on gamma spectroscopy results from concrete core and structural steel samples collected during facility characterization, inner portions of the concrete vault contain detectable levels of Co-60, Eu-152, Eu-154, and Na-22 while structural steel and beam tubes contain detectable levels of Co-60. Additionally, one subsurface soil sample outside the vault had detectable Eu-152 at a small fraction of the soil screening value. Upon completion of the decommissioning process and unrestricted release of the facility, the building will be demolished and disposed along with surrounding soils. The cyclotron was located within a vault below grade at the NASA Glenn Research Center (GRC), Lewis Field in Cleveland, OH adjacent to the Cleveland Hopkins International Airport. The facility was constructed by General Electric in the late 1940’s and early 1950’s. The facility was turned over to NASA (NACA at that time) for operation in 1955. The cyclotron was permanently shut down in 1990 and the facility is currently in a possession only status on the NASA GRC limited scope specific license. The unshielded 69” cyclotron was moved out of the cyclotron vault on February 24, 2017 and then disassembled and removed as radioactive waste from February 27 to March 3, 2017. Cyclotron removal and final status surveys (FSS) were performed under Work Execution Packages (WEP) developed per NASA’s AD-01(CYC) Rev 1, Creation, Revision, Approval, and Cancellation of GRC Cyclotron Decommissioning Project Plans, Procedures, and Documents. The cyclotron removal was performed according to WEP-16-001, Cyclotron Removal Only while final status surveys were performed under the survey plan contained in WEP-16-002, Building 140 Radiological Survey Only (Plan). The Plan was developed using the guidance provided in NUREG-1757, “Consolidated NMSS Decommissioning Guidance” and NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM); and provided the approach, methods, and techniques for radiological survey of impacted areas. These methods ensure technically defensible data were generated to aid in determining compliance with the criteria for unrestricted use specified in 10 CFR 20 Subpart E.



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Final Status surveys of the vault were conducted from March 3 to March 8, 2017. Final status surveys were designed using the guidance provided in MARSSIM to demonstrate compliance with the release criteria for unrestricted use specified in 10 CFR 20.1402. Additionally, for building structures with potential volumetric activation products, a site-specific dose model was developed and the scenario analyses of NUREG 1640 Volume 1 “Radiological Assessments for Clearance of Equipment and Materials from Nuclear Facilities,” were used to develop an upper bound of potential doses from plausible future scenarios. This report presents sufficient data to support the conclusion that the facility meets the release criteria. Final status surveys demonstrate that building structures included in the scope of this report meet the release criteria and are suitable for unrestricted release. Based on the building occupancy scenario, the Total Effective Dose Equivalent (TEDE) to an average member of the critical group is less than 5.6 mrem/year (approximately 22% of the release criterion of 25 mrem/yr). Additionally, alternate scenario analysis for recycling, renovation, and disposal demonstrate that potential doses are much less than 1 mrem/yr.

2.0 FACILITY DESCRIPTION

The cyclotron vault has a footprint of approximately 2,000 square feet and is shown in Figure 2-1. The Cyclotron Vault (shaded green) and the embedded beam tubes and beam dumps (shaded red) are within the scope of this report. There are other various rooms located within the NASA controlled area that were surveyed for unrestricted release by NASA contractor, Leidos. Facility layout drawings are in Appendix B.



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Figure 2-1: Facility Floor Plan

The vault is below grade and has twelve-inch thick reinforced concrete external walls on the north, east, and west sides. Access to the vault is via one of the two shield rooms to the east. The shield rooms (personnel access and equipment access) are designed with watertight steel doors that allowed the rooms to be filled with water for shielding during operation. The beam tubes and dumps are embedded in reinforced concrete walls, with some portions embedded in soils. Most of the south wall is thicker reinforced concrete (6 ft thick) with embedded beam tubes that were used to support neutron therapy conducted in the therapy room. The vault contains a perimeter trench that is approximately 18 inches wide and 16-18 inches deep. The perimeter trench is connected to a pit on the north wall that connects to a utility chase. The utility pit is 60 inches deep from floor level. The cyclotron was located within a 24-inch to 26-inch deep pit that also connects to the utility pit. The vault is fitted with a 10-ton double girder manual bridge crane with rails running east and west. The large room east of the shield room is fitted with a removable equipment hatch to accommodate transfer of large items into or out of the facility.



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The facility exterior consists of an earthen berm/shield covering the structure. A stairwell, mechanical room, equipment hatch, and various ventilation shafts are visible on the surface.

3.0 SITE OPERATING HISTORY

The cyclotron was constructed by GE in the 1940’s and 1950’s and was first operated in 1955. The cyclotron was upgraded in the 1970’s from a 60” to a 69” cyclotron. The facility was also upgraded several times to include neutron therapy and additional spacing. NASA operated the facility and cyclotron for research until 1990. NASA contracted Leidos to support decommissioning of the facility. Leidos personnel have supported NASA with facility characterization and removal of activated and radioactively contaminated equipment and materials except for the cyclotron magnets, coils and vacuum tank; embedded piping; overhead crane; and building structures. Some activation products at the facility became licensed by the NRC in 2009, coincidentally with implementation of the Energy Policy Act of 2005 that redefined byproduct material to include certain accelerator-produced materials. Some historical activities took place at the cyclotron facility that caused the associated incidental activated materials to become byproduct materials that are required to be licensed. However, incidental activation products associated with the therapy room and associated beam tubes are not considered byproduct material under the Energy Policy Act. These structures became activated during use of the cyclotron beam for research of the efficacy of neutron teletherapy as a cancer treatment modality, an activity that is specifically excluded from the definition of byproduct material.

4.0 LEIDOS CHARACTERIZATION SUMMARY

Leidos conducted characterization in 2010-2011 and provided a summary report of this characterization in 2016.

4.1 Surface Activity Measurements

Leidos surveyed generally accessible areas of the vault. Four discrete locations had elevated beta-gamma surface activity up to 118,000 dpm/100 cm2 total and 1,473 dpm/100 cm2 removable. Locations of elevated surface activity were subsequently remediated by Leidos.

4.2 Concrete Activation Measurements

Concrete vault structures contain detectable activation products from cyclotron operation. The concentrations of detectable activation products in building structural concrete core samples are summarized in the tables below and are



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compared to the NRC soil default screening values (DSV) contained in NUREG 5512, Volume 3, Table 6.91 as a qualitative comparison only.

Table 4-1: Cyclotron Vault Concrete Core Results Summary (Leidos 2011)

Nuclide No. of

Samples % of Positive

Activity Results Concentration (pCi/g)

Maximum Average Co-60 119 34% 1.38 0.42 Eu-152 119 98% 4.97 1.45 Eu-154 119 2% 0.30 0.30 Na-22 119 3% 0.26 0.21

Table 4-2: Decay-Corrected Concrete Core Results Summary

Nuclide Soil DSV

(pCi/g)

Maximum Concentration

Average Concentration Fraction of

Distribution Based on Average (pCi/g)

% of Soil DSV

(pCi/g)% of Soil DSV

Co-60 3.8 0.63 17% 0.19 5% 0.13 Eu-152 8.7 3.66 42% 1.07 12% 0.72 Eu-154 8.0 0.18 2.3% 0.18 2.3% 0.12 Na-22 4.3 0.05 1.2% 0.04 1.0% 0.03

Concrete boring locations within the Cyclotron Vault are shown in Figure 4-1 with the maximum Eu-152 concentrations in pCi/g listed for each location (not decay-corrected).



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Figure 4-1: Concrete Boring Locations with Eu-152 Concentrations (pCi/g)

The Leidos characterization concrete sample with the highest result of 4.97 pCi/g Eu-152 (3.66 pCi/g Eu-152 decay-corrected) is within an area identified by Chase as being the area of highest response on a 2” x 2” sodium iodide detector (after cyclotron removal) and is representative of the highest concrete activity concentration in the vault. Additionally, the averages of the decay-corrected characterization activity concentrations present an upper bound of the average concentrations within the vault because the locations were selected judgmentally based on areas with the highest potential for activation.

4.3 Metal Activation Measurements

A total of ten metal samples consisting of carbon steel, copper, and aluminum were judgmentally collected from piping systems and other equipment for gamma spectroscopy analysis. The results of these analyses were decay corrected and used to determine nuclide distributions for shipping and disposal of the cyclotron. Structural steel samples are also used to determine the nuclide distribution for dose modeling associated with release of remaining building structures; Co-60 is the only nuclide of concern for remaining metal.



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4.4 Soil Activation Measurements

In 2010-2011, Leidos conducted gamma walkover surveys and collected a total of 30 surface soil samples on a systematic triangular grid pattern. The samples were analyzed for activation products by gamma spectroscopy. No elevated exposure rates or cyclotron related radionuclides were identified.

In 2015, Leidos collected subsurface soil samples adjacent to the cyclotron vault walls and ceiling for gamma spectroscopy analysis. All results were less than the detection sensitivity of the analysis except one boring along the west wall at a depth interval of 18’-24’ that had detectable levels of Eu-152 at less than 1 pCi/g. For comparison, the soil screening value for Eu-152 is 8.7 pCi/g. This location corresponds with the direction of a historical beam line. Chase conducted gamma scans of the interior wall at this location after removal of the cyclotron and could not distinguish this area from nearby areas where subsurface soil samples did not contain detectable activation products. The maximum subsurface soil sample result was 0.93 pCi/g Eu-152 (11% of the DSV) at the 21’- 22’ depth interval with a decreasing trend at deeper and at shallower intervals. A diagram showing the results is presented below.

Figure 4-2: Subsurface Soil Sample Locations and Results

Based on soil sample results at a very small fraction of the screening value, soil surface and subsurface soils are considered non-impacted for decommissioning. However, because Eu-152 was detected, potential future doses from activation products in soils are conservatively modeled as part of the alternate scenario analysis in Section 18.0.



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5.0 NUCLIDES OF CONCERN

Contaminants include activation products from cyclotron operations. Short lived radioisotopes have been mathematically eliminated from concern as they have had sufficient time to decay since shutdown. Leidos collected and analyzed concrete and metal samples from within the vault. The detected radionuclides in concrete include Co-60, Eu-152, Eu-154, and Na-22. Co-60 is the only nuclide of concern for remaining steel structures. Small quantities of H-3 can be produced in the cooling water system. Although not considered a nuclide of concern, confirmatory H-3 smears were collected during the final status survey.

5.1 Concrete Radionuclide Distribution

The distribution of radionuclides was established by determining the average of decay-corrected results of each nuclide detected in concrete core samples during characterization. The concrete distribution is presented below.

Table 5-1: Concrete Radionuclide Distributions

Nuclide Average Activity

Concentration (pCi/g)

Fraction of Distribution

Co-60 0.19 0.13 Eu-152 1.07 0.72 Eu-154 0.18 0.12 Na-22 0.04 0.03

5.2 Steel Radionuclide Distribution

Co-60 was the only nuclide detected in steel samples during characterization. Typically, steel samples are analyzed to quantify the activation products by gamma spectroscopy. Gamma spectroscopy can easily identify common activation products in steel such as Co-60 because it is a strong gamma emitter. However, two activation products, Fe-55 and Ni-63, do not emit gammas suitable for detection by gamma spectroscopy. Due to the low energy of the emissions and low dose conversion factors, Fe-55 and Ni-63 are insignificant contributors to dose compared to Co-60. For the same activity concentration, Co-60 contributes more than five orders of magnitude higher dose than Ni-63 or Fe-55. Therefore, Ni-63 and Fe-55 are not included in dose modeling calculations and Co-60 is the only nuclide of concern.

6.0 RELEASE CRITERIA

The radiological release criteria are those specified in 10 CFR 20 Subpart E. Specifically the facility being released under this decommissioning effort was surveyed in accordance with the guidance contained in MARSSIM to demonstrate



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compliance with the criteria of 10 CFR 20.1402, “Radiological Criteria for Unrestricted Use.”

“A site will be considered acceptable for unrestricted use if the residual radioactivity that is distinguishable from background radiation results in a TEDE to an average member of the critical group that does not exceed 25 mrem (0.25 mSv) per year, including that from groundwater sources of drinking water, and the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA). Determination of the levels which are ALARA must take into account consideration of any detriments, such as deaths from transportation accidents, expected to potentially result from decontamination and waste disposal.”

7.0 SCENARIO AND CRITICAL GROUP

For conservatism, the building occupancy scenario of NUREG/CR-5512 and its associated default critical group (full-time adult males in light industry) is used for release of this facility.

In addition to the building occupancy scenario, the information contained in NUREG 1640 “Radiological Assessments for Clearance of Equipment and Materials from Nuclear Facilities” was used to develop an upper bound of potential future doses from alternate scenarios. These alternate scenarios include potential future disposition of materials for renovation, demolition, recycling or disposal. NUREG 1640 provides detailed assessments of the doses from various scenarios involving recycling and disposal of contaminated concrete and steel, and provides simple dose conversion factors that can conservatively be applied to the building structures in the cyclotron vault to develop an upper bound of potential future doses from residual licensed materials. The recycling scenario evaluates the doses from crushing and rubblizing reinforced concrete at a recycling facility and cutting structural steel at a scrapyard. This bounds the potential doses from any future scenario involving maintenance, dismantlement or demolition of remaining building structures.

For soils, a resident farmer scenario is conservatively used to bound potential future doses to members of the public.



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8.0 DERIVED CONCENTRATION GUIDELINE LEVELS (DCGL)

NASA plans to demolish the building and dispose of potentially activated portions in a landfill, so a demolition and disposal scenario is most appropriate for the site. However, for conservatism, DCGLs are based on an occupancy scenario to ensure that any potential future use is evaluated. Additionally, demolition, recycling, and disposal scenarios are evaluated as alternate scenarios to demonstrate that occupancy is the most limiting. Section 18.0 addresses alternate scenario analyses.

The Derived Concentration Guideline Level (DCGL) is the surface or volumetric activity concentration that could result in a dose equal to the release criterion (the modeled dose to an occupant working in an area that contains residual radioactivity equal to the DCGL would be 25 mrem/yr TEDE). Due to the presence of various activation products in concrete, the determination of DCGLs is much more complex than simply directly applying screening values. As a result, two sets of DCGLs are applicable for this project, a DCGLsurface and DCGLvolumetric. The DCGLsurface is applied to surface contamination, and is equal to the default screening value (DSV) for the most restrictive radionuclide, Co-60. For locations inside the cyclotron room that are likely to be activated, the DCGLvolumetric is an external dose rate combined with a conservative removable contamination limit to bound the dose contribution from internal sources.

8.1 Surface DCGLs

The NRC has published DSVs for common radionuclides in NUREG-1757, Volume 1, Appendix B. These DSVs were calculated using NRC-approved DandD, version 2.1 software under default conditions. DSVs were calculated using DandD v2.1 with an input total surface activity of 1 dpm/100 cm2 and accepting the default parameter values of the building occupancy scenario. Copies of the dose model output reports are presented in Appendix C. A summary of the DSVs is provided in the table below.

Table 8-1: Surface Activity Screening Values

Nuclide Half-Life mrem/yr per dpm/100 cm2

DSV0F0F

1 (dpm/100 cm2)

Co-60 5.3 years 3.55E-3 7.1E3 Eu-152 13.6 years 1.97E-3 1.3E4 Eu-154 8.6 years 2.18E-3 1.1E4 Na-22 2.6 years 2.62E-3 9.5E3

1 DSVs were determined for each nuclide by dividing the release criterion of 25 mrem/yr by the output of the dose model in mrem/yr per dpm/100 cm2.



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For conservatism and convenience, the limiting Co-60 DSV was chosen as the gross beta DCGL and was applied to surface contamination measurements. An important assumption of the DandD dose model is that removable surface contamination is 10% of the total surface contamination. Therefore, removable contamination measurements shall not exceed 10% of the total surface contamination limit.

8.2 Volumetric DCGLs

The DSVs described above assume surface contamination at a depth not to exceed 1 cm and are therefore not appropriate for volumetric contamination that exists from activation of building structural surfaces. Volumetric contamination can be modeled using RESRAD-BUILD software. However, modeling of volumetric contamination presents challenges due to the conservative nature of the dose model, the difficulty in obtaining sufficient sample data to determine the actual radionuclide distribution, and the heterogeneous nature of activation of concrete and steel structures. Dose modeling is typically performed when the dose cannot be directly measured in the field. In the case of volumetrically activated concrete, almost all dose to the receptor is from the external component because the activation products are not available for inhalation or ingestion. The external component of dose can be directly measured, therefore the approach to dose modeling consists of performing direct radiation measurements to ensure external doses are less than 24 mrem/yr and demonstrating through modeling that the internal dose contribution is less than 1 mrem/yr.

The external dose limit equivalent to 24 mrem/yr is easily calculated using the occupancy assumption of the building occupancy scenario as follows:

hour

μrem 10.3

mrem

μrem 1,000

hours 2,340

year

year

mrem 24

The internal dose limit is met by establishing a removable surface activity limit that would result in 1 mrem/yr internal dose. The DandD software reports internal dose components for each nuclide, based on the assumption that 10% of the total surface activity is removable. Therefore, an input of 1 dpm/100 cm2 total activity yields DandD output that includes internal exposure in mrem/yr per 0.1 dpm/100 cm2 of removable surface activity. Calculations of the removable surface activity limit for each nuclide of concern are presented in the table below.



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Table 8-2: Removable Activity Contribution to Total Dose

Nuclide

Annual Internal Dose1F1F

2 (mrem per 0.1 dpm/100 cm2)

Removable Activity Equivalent to 1 mrem/yr

Internal Dose 2F2F

3 (dpm/100 cm2) Inhalation Ingestion Total

Co-60 4.87E-4 2.93E-5 5.16E-4 1.94E2 Eu-152 5.12E-4 7.32E-6 5.19E-4 1.93E2 Eu-154 6.54E-4 1.06E-5 6.65E-4 1.50E2 Na-22 1.60E-5 1.17E-5 2.77E-5 3.61E3

The most conservative removable activity limit (Eu-154, 150 dpm/100 cm2) is used as the removable surface activity DCGL.

8.3 Summary of DCGLs

DCGLs were determined using the most limiting nuclide. The following table summarizes all project DCGLs.

Table 8-3: Summary of DCGLs

Type of Activity DCGLTotal DCGLRemovable 3F3F

4 Surface 7,100 dpm/100 cm2 710 dpm/100 cm2

Volumetric 10 µrem/hr 150 dpm/100 cm2

8.4 Materials and Equipment

The radiological release limits for surface contaminated materials and equipment under the NASA radioactive materials license are:

5,000 dpm/100 cm2 total surface contamination (averaged over 1 m2) 15,000 dpm/100 cm2 max total surface contamination (limited to 100 cm2) 1,000 dpm/100 cm2 removable surface contamination

Structural concrete and steel materials may contain volumetric activation products and are therefore not suitable for release using the surface contamination limits. Any materials that exhibited an increase in the audible count rate on a 2” x 2” sodium iodide detector were removed and disposed as radioactive waste or analyzed for release under the alternate scenario analysis described in Section 18.0.

2 Annual doses are obtained from the DandD modeling reports presented in Appendix C. 3 The removable activity equivalent to 1 mrem/yr is determined by dividing 0.1 dpm/100 cm2 by the total annual internal dose per 0.1 dpm/100 cm2 in mrem/yr. 4 Because the volumetric removable DCGL is more limiting than the surface DCGL, the volumetric DCGL is applied to all measurements.



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9.0 SURVEY INSTRUMENTATION

9.1 INSTRUMENT CALIBRATION

Laboratory and portable field instruments were calibrated within the previous year with National Institute of Standards and Technology (NIST) traceable sources to radiation emission types and energies to provide detection capabilities similar to the nuclides of concern. Portable instrument calibration records are included as Appendix D. NASA maintains calibration records for the Tennelec smear counter.

9.2 FUNCTIONAL CHECKS

Functional checks were performed at least daily when in use. The background, source check, and field measurement count times for radiation detection instrumentation were specified by procedure to ensure measurements were statistically valid. Background readings were taken as part of the daily instrument check and compared with the acceptance range for instrument and site conditions. Daily functional checks of the liquid scintillation counter consisted of performing the instrument’s automatic quality assurance protocol that utilizes H-3 and C-14 sources as well as a background standard.

9.3 EFFICIENCY DETERMINATION

ISO 7503-1 methods were used to determine field concentrations for final status data and calculation of resultant doses from residual radioactivity. MARSSIM protocols for building structures use ISO-7503-1 methodology that takes into account the texture of the surface and the 2π detector efficiency. Under MARSSIM, the default surface efficiency for beta emitters with maximum energies less than 400 keV is conservatively set at 0.25. For total surface activity measurements, the results were corrected using the Tc-99 2-pi surface emission rate and a surface efficiency of 0.25. For smear counting, 4π efficiencies were used.

9.4 MINIMUM DETECTABLE CONCENTRATIONS

Minimum counting times for background determinations and counting times for measurement of total and removable contamination were chosen to provide minimum detectable concentrations (MDC) that meet the data quality objectives. NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM) instrumentation performance protocols were used. MARSSIM equations relative to building surfaces have been modified to convert to units of



Page 14 of 58

dpm/100 cm2. Count times and scanning rates for surface contamination are determined using the following equations:

9.4.1 Static Counting

Static counting MDC at a 95% confidence level is 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”, Table 3.1 (Strom & Stansbury, 1992):

2100

)1(29.33

cm

AEt

t

ttB

MDC

tots

b

ssr

static

Where:

MDCstatic = minimum detectable concentration (dpm/100 cm2) Br = background count rate (counts per minute) tb = background count time (minutes) ts = sample count time (minutes)

Etot = total detector efficiency for radionuclide emission of interest (cpm/dpm)

A = detector probe area (cm2)

A typical beta MDCstatic calculation for the Ludlum Model 43-68 gas flow proportional detector is shown below:

2dpm/100cm 215,1

100

126)1.0)(5.0(

5.0

5.01)5)(.500(29.33

STATICMDC

9.4.2 Ratemeter Scanning - Surface

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

2100

60'

cm

AEp

ibd

MDC

tot

i

scan



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Where:

MDCscan = minimum detectable concentration (dpm/100 cm2) d’ = desired performance variable (1.38) bi = background counts during the residence interval (counts) i = residence interval (seconds) p = surveyor efficiency (0.5)

Etot = total detector efficiency for radionuclide emission of interest (cpm/dpm)

A = detector probe area (cm2)

A typical MDCscan calculation for the Ludlum 43-37 gas flow proportional detector is shown below:

sec 262.0 inch20

sec

cm2.54

inchcm 13.3 i

counts 55.6sec60

minute

minute

counts 1500 sec 262.0 b i

2dpm/100cm 959,1

100

5841.05.0

262.0

6055.638.1

SCANMDC

9.4.3 Ratemeter Scanning – Volumetric

The method used in MARSSIM (presented in Section 6 of NUREG-1507) to calculate soil scanning sensitivity is used to determine a conservative estimate of the scan MDC for volumetric activity. The calculation is performed in four steps:

1. Determine a minimum detectable audible count rate (MDCRsurveyor) of a 2” x 2” NaI detector associated with the scan rate and background count rate (cpm)

2. Determine the detector response for the gamma energies associated with the radionuclide distribution (cpm per µR/hr)

3. Determine the minimum detectable exposure rate associated with the MDCRsurveyor (µR/hr)

4. Determine scan MDC by correlating the minimum detectable exposure rate to an activity concentration (pCi/g)



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The MDC is dependent upon the geometry of the source, the scan distance from the source, and the scan rate. Example calculations for concrete and steel are provided below.

9.4.3.1 Concrete

An example calculation for Eu-152 in concrete at a scan rate of 5 in/sec at a distance of 5 cm is provided below.

Step 1: Determine MDCRsurveyor The number of source counts required for a specific time interval is given by MARSSIM Equation 6-8:

ii bds '

where: d’ is the performance factor based on required true and false positives rates (1.38), and bi is the number of background counts in the observation interval

Assuming a scan rate of 5 in/s and a 22 in diameter source 4F4F

5, the source remains under the detector for 4.4 seconds (e.g. I = 4.4 s) and the background count rate for the 2” x 2” NaI detector is 10,000 cpm. The value for bi and si is then calculated:

7334.460

000,10ib counts/interval

counts 4.3773338.1 is

The scan minimum detectable count rate is then calculated using MARSSIM equation 6-9:

)/60( isMDCR i

where: MDCR is the Minimum Detectable Count Rate

cpm 510)4.4/60(4.37 MDCR

5 MARSSIM methodology for calculating soil scan sensitivity includes modeling a cylindrical volume of soil 15 cm thick with a 56 cm (22 inch) diameter.



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The MDCRsurveyor is calculated assuming a surveyor efficiency of 0.5 using MARSSIM equation 6-10:

cpm 5.0

MDCRMDCRsurveyor

cpm 7215.0

510surveyorMDCR

Step 2: Determine Detector Response (cpm per µR/hr) For the corresponding minimum detectable exposure rate to be determined for the detector and radionuclide distribution, it is necessary to run Microshield™ and determine the count rate to exposure rate ratio (cpm per µR/hr) considering each of the gamma emissions and their contribution to the total exposure rate for the nuclide. Microshield™ software was used to determine the net exposure rate produced by a concentration of 1 pCi/g Eu-152 activity in the concrete. The following factors were considered in the modeling:

1 pCi/g Eu-152 (input as 2.35E-6 Ci/cm3)

Dimensions of source: radius equal to 28 cm

Depth of source: 20 cm 5F5F

6

Location of dose point: Centered 5 cm above the source, as this position is consistent with the average height of the NaI scintillation detector (center of the detector) above the concrete surfaces during scanning

Density of concrete: 2.35 g/cm3 The modeling code performed the calculations and determined a total exposure rate with buildup for a Eu-152 activity concentration of 1 pCi/g. Microshield™ also provided the exposure rates for a number of gamma energies associated with the source term inputs. The MicroshieldTM output report is presented in Appendix E. This data was used to weight the cpm per µR/hr value at each energy by the fractional exposure rate to estimate an overall cpm per µR/hr value specific to the source term as presented in NUREG-1507 Table 6.3. The MicroshieldTM code only considers primary gamma energies when evaluating the buildup from scattered photons, therefore the NaI detector response will be greater (more

6 The concrete is activated to an 8 in depth based on Leidos characterization concrete core sample results.



Page 18 of 58

sensitive) in the field than is calculated here because the detector is more efficient at detecting lower energy scattered photons, resulting in a conservative estimate of the scan MDC. The results of these calculations are shown in the table below.

Table 9-1: NaI Detector Response (cpm per μR/hr) for Eu-152 in Concrete

Energy (MeV)

2” x 2” NaI Detector Count Rate

(cpm per R/hr) 6F6F

7

Exposure RateR/hr

With Buildup7F7F

8

Weighted Count Rate (cpm per

R/hr) 0.015 2,200 3.28E-04 1 0.04 8,880 3.89E-03 43 0.05 11,800 1.35E-03 20 0.1 9,840 1.05E-02 130 0.2 4,230 9.00E-03 48 0.3 2,520 5.57E-02 176 0.4 1,700 1.82E-02 39 0.5 1,270 2.10E-03 3 0.6 1,010 1.91E-02 24 0.8 710 1.07E-01 95 1 540 3.21E-01 217

1.5 350 2.51E-01 110

Totals 7.99E-01 905

Step 3: Determine the Minimum Detectable Exposure Rate The minimum detectable exposure rate is calculated by dividing the MDCRsurveyor count rate by the count rate to exposure rate ratio for the detector.

hrRhrRpercpm

cpmRateExposureDetectableMinimum /80.0

/905

721

Step 4: Determine Scan MDC (pCi/g)

The scan MDC can be derived by the ratios of the minimum detectable exposure rate to the calculated exposure rate provide by Microshield™.

gpCigpCiperhrR

hrRMDCScanConcrete /1

//799.0

/80.0

7 Values for energies presented are from NUREG-1507 Table 6.3. 8 Values for energies presented are from page E.4 “Results - Dose Point # 2 - (0,25,0) cm.



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To determine the detection sensitivity for the total activity concentration, the sum of the weighted average MDC for each nuclide is calculated. The results of these calculations for 8” thick activated concrete is presented in the table below.

Table 9-2: NaI Scan MDC: Concrete, 10,000 cpm bkg, 5 in/sec @ 2” distance

Nuclide µR/hr

per pCi/g cpm per µR/hr

MDC (pCi/g)


Weighted MDC (pCi/g)

Co-60 1.84E+00 440 0.89 0.13 0.11 Eu-152 7.99E-01 905 1.00 0.72 0.72 Eu-154 9.51E-01 715 1.06 0.12 0.13 Na-22 1.62E+00 849 0.52 0.03 0.01

Total 0.98

While the MDC associated with a background of 10,000 cpm was conservatively used for FSS planning, the actual background rate was 7,000 cpm. For comparison, the associated MDC is presented in the table below.

Table 9-3: NaI Scan MDC: Concrete, 7,000 cpm bkg, 5 in/sec @ 2” distance

Nuclide µR/hr


MDC (pCi/g)


Weighted MDC

(pCi/g) Co-60 1.84E+00 440 0.74 0.13 0.10 Eu-152 7.99E-01 905 0.83 0.72 0.60 Eu-154 9.51E-01 715 0.89 0.12 0.11 Na-22 1.62E+00 849 0.44 0.03 0.01

Total 0.82

9.4.3.2 Steel

An example MDC calculation for Co-60 in steel at a scan rate of 5 in/sec at a distance of 5 cm is provided below.

For steel structures, such as crane girders, the same method is used as was used for concrete, except that parameter values applicable to steel were used. Microshield™ software was used to determine the net exposure rate produced by a concentration of 1 pCi/g Co-60 in steel. The following factors were considered in the modeling:

1 pCi/g Co-60 (input as 7.86E-6 Ci/cm3)

Dimensions of source: radius equal to 28 cm

Depth of source: 2.5 cm

Location of dose point: Centered 5 cm above the source, as this position is consistent with the average height of the NaI scintillation



Page 20 of 58

detector (center of the detector) above the steel surfaces during scanning

Density of steel: 7.86 g/cm3

The modeling code performed the calculations and determined a total exposure rate with buildup of 0.471 µR/hr for a Co-60 activity concentration of 1 pCi/g. The MicroshieldTM output report is presented in Appendix E. Calculation of the detector response in cpm per µR/hr specific to the source term is presented in the table below.

Table 9-4: NaI Detector Response (cpm per μR/hr) for Co-60 in 1” Steel

Energy (MeV)

2” x 2” NaI Detector Count Rate

(cpm per R/hr) 8F8F

9

Exposure RateR/hr With

Buildup9F9F

10

Weighted Count Rate (cpm per

R/hr)

0.6938 1,010 2.13E-05 0.05 1.1732 540 2.22E-01 255 1.3325 350 2.49E-01 185

Totals 4.71E-01 440

The minimum detectable exposure rate is calculated by dividing the MDCRsurveyor count rate by the count rate to exposure rate ratio for the detector.

hrRhrRpercpm

cpmRateExposureDetectableMinimum /64.1

/440

721

The scan MDC is derived by the ratio of the minimum detectable exposure rate to the calculated exposure rate provide by the Microshield™.

gpCigpCiperhrR

hrRMDCScanSteel /49.3

//471.0

/64.1

Table 9-5: NaI Scan MDC for 1” Steel Plate, 10,000 cpm bkg, 5 in/sec @ 2” Distance

Nuclide µR/hr


MDC (pCi/g)

Co-60 4.71E-01 440 3.49

For comparison, the MDC associated the actual background rate is presented in the table below.

9 Values for energies presented are from NUREG-1507 Table 6.3. 10 Values for energies presented are from page E.10 “Results - Dose Point #2 - (0,7.5,0) cm.



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Table 9-6: NaI Scan MDC for 1” Steel Plate, 7,000 cpm bkg, 5 in/sec @ 2” Distance

Nuclide µR/hr


MDC (pCi/g)

Co-60 4.71E-01 440 2.91

9.4.4 Smear Counting

Smear counting MDC 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”, Table 3.1 (Strom & Stansbury, 1992):

Et

t

ttB

MDCs

ssr

smearb

)1(29.33

Where:

MDCsmear = minimum detectable concentration level in dpm/smear

Br = background count rate in counts per minute

tb = background count time in minutes

ts = sample count time in minutes

E = instrument efficiency for radionuclide emission of interest

A typical beta static MDC calculation for the Tennelec gas flow proportional smear counter is shown below:

2dpm/100cm 31)25.0)(1(

1

11)1)(1(29.33

smearMDC

The liquid scintillation counter was setup to count samples in three channels as described in Section 12.10. The MDC calculation for each LSC channel using conservative parameters is shown below.

dpm 35)60.0)(1(

1

11)1)(15(29.33

H MDC SMEAR 3



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dpm 33)80.0)(1(

1

11)1)(25(29.33

MDCC SMEAR 14

cpm 36)1)(1(

1

11)1)(50(29.33

MDC3 Channel SMEAR

Because the counting efficiency is different for each LSC measurement depending on quench characteristics, and in consideration of the errors associated with wipe counting (i.e., area wiped, wiping pressure, etc.), the a priori estimates of smear MDCs calculated above are applied to all removable contamination measurements.

9.5 INSTRUMENTATION SPECIFICATIONS

The specifications and operating parameters for the radiation detection instrumentation used for final status surveys are summarized in the tables below.

Table 9-7: Instrumentation Specifications

Meter Model

Detector Type

Detector Model

Detector Area (cm2)

Detector Width (cm)

Typical Efficiency

Use

Ludlum 2241-3

Gas Flow Proportional

Ludlum 43-37

584 13.3 10% Scans, Direct Measurements

Ludlum 2241-3

Gas Flow Proportional

Ludlum 43-68

126 8.8 10% Scans, Direct Measurement

Ludlum 2241

2” x 2” Sodium Iodide

Ludlum 44-10

N/A N/A N/A Gamma Scans

Tennelec Gas Flow

Proportional Counter

N/A N/A N/A 25% Airborne and

Removable Activity

LSC Liquid

Scintillation N/A N/A N/A

60% (H-3) 80% (C-14) 95% (open)

Hard to Detect Removable Activity

Bicron MicroRem

Tissue Equiv. Gamma

Scintillation N/A N/A N/A N/A

External Dose Rate Measurements



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Table 9-8: Typical Instrument Operating Parameters

Measurement Type

Detector Model

Maximum Scan Rate

(in/s)

Count Time

(s)

Bkg. Time

(s)

Maximum Background

(cpm)

MDC

(dpm/100cm2)

Surface Scans (Beta)

Ludlum 43-68

5 N/A N/A 500 3,223

Surface Scans (Beta)

Ludlum 43-37

20 N/A N/A 1,500 1,959

Total Surface Activity (Beta)

Ludlum 43-68

N/A 30 30 500 1,215

Total Surface Activity (Beta)

Ludlum 43-37

N/A 6 6 1,500 1,027

Volumetric Scans (Gamma)

Ludlum 44-10

5 in/s @ 2” height

N/A 60 7,000 0.82 pCi/g (concrete)

2.91 pCi/g (steel) Hard-to-Detect

Removable Activity

LSC N/A 60

sec. 60

sec.

15 (H-3) 25 (C-14) 50 (open)

35 (H-3) 33 (C-14) 38 (open)

Removable Activity (Beta)

Tennelec N/A 60 60 1 31

9.6 DATALOGGING

Structural surface scans and static measurements were performed using datalogging instrumentation. While scanning, in addition to the surveyor listening to the audible output, integrated counts were recorded. Logged data were downloaded and processed using data management software to perform data analyses and reporting. Reporting includes graphical (4-plot) presentation of scan data as well as summary statistics functions. The 4-Plot is described in the NIST e-Handbook of Statistical Methods that can be found at the following link: (http://www.itl.nist.gov/div898/handbook/index.htm). A 4-plot consists of the following: A run sequence plot presents logged data in chronological order, providing

a time history of the survey data.

A lag plot checks whether a data set or time series is random or not. Random data should not exhibit any identifiable structure in the lag plot. Non-random structure in the lag plot indicates that the underlying data are not random.

A histogram plot graphically summarizes the distribution of a univariate data set, showing center (i.e., the location) of the data, spread (i.e., the scale) of the data, skewness of the data, presence of outliers, and presence of multiple modes.



Page 24 of 58

A probability plot is a goodness-of-fit test used to verify the distributional model. The normal probability plot is a graphical technique for assessing whether or not a data set is approximately normally distributed. The data are plotted against a theoretical normal distribution in such a way that the points should form an approximate straight line. Departures from this straight line indicate departures from normality.

10.0 CYCLOTRON REMOVAL

Chase subcontractor Barnhart Crane and Rigging disassembled and removed the cyclotron. NASA provided the necessary training and health physics oversight to disassemble all items as required for movement, packaging, and/or characterization. NASA issued a Radiation Work Permit (RWP) and provided health physics coverage as the millwright workers disassembled and removed the cyclotron. Radioactive materials were transported via approved carriers and manifested by qualified shippers to Alaron Nuclear Services in Wampum, PA for transloading from truck to rail for transport to the US Ecology disposal site in Grand View, ID. Chase provided a qualified Hazmat shipper to oversee loading and provided all packaging materials and prepared the packages for transport over public highways in accordance with appropriate US Department of Transportation (DOT) regulations. Shipping papers reflect that Chase is the shipper and NASA is the generator. None of the packages were Class 7.

Table 10-1: Cyclotron Components Shipped for Disposal

Truck Number

Package Description Weight

(lb) Volume

(ft2) Activity (mCi)

1 Upper Yoke 136,200 272 0.084 2 Vertical Yoke 1 55,800 112 0.245 3 Upper Pole and Vacuum Tank 37,000 138 1.680 4 Upper Coil 28,700 90 0.083 5 Vertical Yoke 2 55,800 112 0.098 6 Lower Coil 28,700 90 0.063

7 Lower Pole 38,000 65 0.809 Cooling Coil 2,200 27 0.055

8 Lower Yoke 135,000 272 0.224 9 B25 Box of Misc. Parts 7,000 96 0.468

Totals 524,400 1,274 3.808



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After the cyclotron was removed, Chase performed the scanning portion of the final status survey protocol (surface activity scans with a gas flow detector and volumetric scans with a 2” x 2” sodium iodide detector). Where elevated activity was identified, the boundary of the elevated area was marked. Sodium iodide scans were performed to detect elevated activity as a result of activation based on the audible response. These areas were then evaluated for compliance with the dose rate criterion with a MicroRem meter and smears. A surface activity static measurement and smear were also taken at the location. These surveys indicated that remediation was not necessary, so the survey results were used as final status data.

11.0 REMEDIATION

Remediation of building structures was not necessary.

12.0 FINAL STATUS SURVEYS

Final status surveys were performed to demonstrate that residual radioactivity in each survey unit satisfies the predetermined criteria for release for unrestricted use. Final status surveys were conducted using the Data Quality Objective (DQO) process. Final status surveys consisted of scan surveys, total direct surveys, dose rate measurements and removable contamination measurements as discussed further in this section.

12.1 BACKGROUND DETERMINATION

The use of reference background areas or paired background comparisons is not necessary for beta surface contamination measurements. The background rate for NaI and MicroRem detectors were determined in an area non-impacted for activation, and of similar construction in the corridor north and east of the cyclotron vault.

12.2 DATA QUALITY OBJECTIVES

The following is a list of the major data quality objectives (DQOs) for the survey design described in the Plan:

Static measurements will be taken to achieve an MDCstatic of less than 20% of DCGL.

Scanning will be conducted at a rate to achieve an MDCscan of less than 50% of the DCGL.

Removable surface activity measurements will be conducted to achieve an MDCsmear of less than 50% of the DCGL.

Individual measurements will be made to a 95% confidence interval.



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Decision error probability rates will initially be set at 0.05 for both and .

The null hypothesis (H0) and alternative hypothesis (HA) are that of NUREG-1505 scenario A:

H0 is that the survey unit does not meet the release criteria

HA is that the survey unit meets the release criteria

Characterization and remedial action support surveys will be conducted under the same quality assurance criteria as final status surveys such that the data may be used as final status survey data to the maximum extent possible.

12.3 AREA CLASSIFICATIONS

Areas were classified based on Leidos facility characterization.

12.3.1 Non-Impacted Area

Non-impacted areas are areas without residual licensed radioactivity and are not surveyed during final status surveys. Non-impacted areas include:

Areas outside the project limits (outside the cyclotron vault)

Surface and subsurface soils of outside grounds

12.3.2 Impacted Areas

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:

Class 1 Area: Areas with the highest potential for contamination, and meet the following criteria: (1) impacted; (2) potential for delivering a 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.

Class 2 Area: 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.

Class 3 Area: 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.

Initial area classifications are as follows:

Class 1

Cyclotron Vault Lower Surfaces (< 2 meter height)



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Beam Tubes / Embedded Pipes

Class 2

Cyclotron Vault Upper Surfaces (>2-meter height) 10F10F

11

12.4 SURVEY UNITS

A survey unit is a geographical area of specified size and shape for which a separate decision is made whether or not that area meets the release criteria. A survey unit is a portion of a building or site that is surveyed, evaluated, and released as a single unit. 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.

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 building structures, based on floor area, is as follows:

Class 1: up to 100 m2

Class 2: 100 m2 to 1000 m2

Class 3: no limit

The vault floor area exceeds the recommended size limit for a Class 1 area, but consists of a single room. To be more consistent with the dose model assumptions and to use a single systematic grid pattern, the vault lower surfaces are considered a single Class 1 survey unit; however, to ensure an adequate sample density, the number of samples required for a Class 1 survey unit was doubled.

11 Area classifications are based on the limiting type of radioactivity – surface or volumetric. The classification of lower surfaces is based on surface activity and classification of upper surfaces is based on volumetric activity. Upper surfaces do not have a potential for residual surface activity because any activities involving dispersible forms of radioactivity involved small quantities and were only conducted at floor level. Additionally, there is no history of airborne radioactivity events.



Page 28 of 58

Table 12-1: Building Structural Survey Units Survey Unit Class Description Comments

1101 1 Lower Vault

Surfaces < 2m height, exceeds recommended size – number of samples doubled.

1201 2 Upper Vault

Surfaces > 2m height

BRA1 N/A Background Reference

Area

The background reference area was selected in an area outside the cyclotron room near concrete surfaces, yet away from the potentially activated portions of the vault.

Table 12-2: Building Systems Survey Units

Survey Unit Description DR01 Drain System VE01 Ventilation System BT01 Beam Tubes and Dumps

12.5 SURFACE 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. For Class 1 areas, scanning surveys are designed to detect small areas of elevated activity that are not detected by the measurements using the systematic pattern. The percentage of accessible building structural surfaces scanned based on classification is:

Class 1: 100% Class 2: 50%

For Class 2 areas, the surfaces to be scan surveyed were those with the highest potential to contain residual radioactivity.

All survey units (i.e., Cyclotron Vault and beam tubes/embedded pipes) were scanned using a 2” x 2” NaI detector for volumetric activation. The detector was positioned to maintain a distance of approximately 2 inches from the center of the detector to the surface being scanned. Additionally, horizontal surfaces and lower wall surfaces in the Cyclotron Vault were scanned with a gas flow proportional detector for surface contamination at a distance of approximately 0.25 inches. 100% of accessible vault floor and lower surfaces were scanned for volumetric activity. Scans of upper walls and the ceiling focused on the concrete beams and wall areas closest to the cyclotron as well as any metal equipment or appurtenances that have a higher activation potential than concrete. Additionally, these ceiling and wall 2” x 2” NaI detector scans included 100% of accessible steel structures that were present during cyclotron operation. Elevated gamma scan results identified on floor surfaces indicate neutron beam loss and therefore,



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mirrored measurements were conducted on the ceiling surfaces as part of the judgmental Class 2 scans.

12.6 TOTAL SURFACE ACTIVITY MEASUREMENTS

Direct surveys (static measurements) for total surface activity 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. Additionally, locations of elevated activity identified and marked during the scan survey received static measurements.

Field measurements were converted to activity concentrations using the following equation:

2

2

100

)(dpm/100cmActivity

cm

AE

cpmcpm

total

backgroundsample

where:

cpmsample = sample count rate in counts per minute cpmbackground = background count rate in counts per minute

Etot = total detector efficiency for radionuclide emission of interest

A = active area of the detector in cm2

12.7 DOSE RATE MEASUREMENTS

Dose rate measurements were performed with a tissue equivalent Bicron MicroRem meter. This instrument was selected due to the flat energy response. Because the Bicron is a ratemeter, an average of ten instantaneous rates was determined at each location by covering the meter and recording the measurement observed when it is uncovered (this is a relatively unbiased method to obtain an average).

Dose rate measurements were taken of building surfaces in the cyclotron room and in a background reference area. The background reference area was selected outside the cyclotron room near concrete surfaces, yet away from the activated structures. Dose rate measurements were taken at each cyclotron room calculated sample location, at areas of elevated activity identified during scans, and in the background reference area. At each location, a measurement was taken at 1 m from the surface to determine the dose rate at the midpoint of a receptor. Additionally, a one-minute count was performed at each location using a 2” x 2” sodium iodide detector at a distance of 2 inches from the surface, consistent with the scan distance.



Page 30 of 58

12.8 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 depends on the Relative Shift (the ratio of the concentration to be measured relative to the statistical variability of the contaminant concentration).

The minimum number of samples is obtained from MARSSIM tables or calculated using equations in Section 5 of MARSSIM.

12.8.1 Determination of the Relative Shift

The number of required samples depends 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, /S and is defined in MARSSIM as:

SS

LBGRDCGL

/

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

S = an estimate of the standard deviation of the residual radioactivity in the survey unit

The preliminary calculations from the Plan are provided below:

Surface Activity (Static Measurements):

6.3000,1

550,3100,7/

S

Volumetric Activity (Dose Rates):

5.22

510/

S

Since MARRSIM Tables 5.3 and 5.5 do not include relative shifts above 3 and the number of samples required decreases with an increasing relative shift, the relative shift for structural surface activity was conservatively set at 3.



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12.8.2 Determination of Acceptable Decision Errors

A decision error is the probability of making an error in the decision on a survey unit by passing a unit that should fail (α decision error) or failing a unit that should pass (β decision error). The decision errors are 0.05 for both α and β errors.

12.8.3 Number of Data Points for Surface Activity (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):

2

211

5.04

SignP

ZZN

Where:

N = number of samples needed in the survey unit

Z1- = 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

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. The following calculations were made to determine this number:

115.0998650.04

645.1645.12

2

N

Z1-α and Z1-β are equal to 1.645 using the error rate of 0.05 from MARSSIM Table 5.2. SignP is equal to 0.998650 from MARSSIM Table 5.4. Adding an additional 20% to account for data losses resulted in a value of 14. Therefore, the determined number of samples per survey unit for planning purposes is 14. For vault lower surfaces, the number of samples required was doubled to ensure an adequate sample density while maintaining a consistent systematic grid pattern.

12.8.4 Number of Data Points for Volumetric Activation (WRS Test)

The number of direct measurements for a survey unit and the background reference area, employing the WRS Test, is determined from MARSSIM Table 5.3, which is based on the following equation (MARSSIM equation 5-1):



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2

211

5.03

rP

ZZN

Where:

N = number of samples needed in the survey unit and in the background reference area



Pr = probability that a random measurement from the survey unit exceeds a random measurement from the background reference area by less than the DCGL when the survey unit median is equal to the LBGR above background.

Note: Pr is determined from MARSSIM Table 5.1

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 5.3 values include an increase of 20% of the calculated value. The following calculations were made to determine this number:

175.0961428.03

645.1645.12

2

N

Z1-α and Z1-β are equal to 1.645 using the error rate of 0.05 from MARSSIM Table 5.2. Pr is equal to 0.961428 from MARSSIM Table 5.1. Adding an additional 20% to account for data losses resulted in a value of 21. This number is the total number of measurements for the survey unit and background reference area combined. Therefore, the determined number of samples for the survey unit and for the background reference area for planning purposes is 11. Because the number of samples required for surface activity measurements is higher than the number required for volumetric activity, dose rate measurements were taken at the same locations as surface activity measurements for consistency.

12.9 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. Class 1 survey units have the highest potential for small areas



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of elevated activity, so the areas between measurement locations may be adjusted to ensure that these areas can be detected by scanning techniques.

Similar systematic spacing methods are used for Class 2 survey units. The use of a systematic grid allows the decision-maker to draw conclusions about the size of the potential areas of elevated activity based on the area between measurement locations.

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 5-8:

grid square afor N

AL

Where:

L = sample spacing interval

A = the survey unit area

N = number of samples needed in the

survey unit

Maps were generated of the survey unit’s permanent surfaces included in the statistical tests (floors, walls, ceilings, etc.). A random starting point was determined using computer-generated random numbers coinciding with the x and y coordinates of the total survey unit. A square grid pattern was plotted across the survey unit surfaces based on the random start point and the determined sample spacing. A measurement location was plotted at each intersection of the grid plot.

12.10 REMOVABLE SURFACE ACTIVITY MEASUREMENTS

Removable surface activity measurements (smears) were collected by wiping an area of approximately 100 cm2 on structural surfaces and in ventilation and drain systems. Removable beta surface activity was determined using cloth disc smears and were counted on a Tennelec smear counter. Additionally, an adjacent LSC disc smear was collected to quantify low energy beta emitters that may not be detected in Tennelec. The LSC was set up for three channels with background subtraction at the following energies:

Channel 1 (3H dpm): 0 – 18.6 keV Channel 2 (14C dpm): 18.6 – 156 keV Channel 3 (cpm): 156 – 2,000 keV

Channel 3 results were used to measure beta emissions with energies above C-14 and H-3 emissions.



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12.11 SURVEYS OF BUILDING MECHANICAL SYSTEM INTERNALS

Surveys of various building system components were performed in the cyclotron vault. Survey design for these systems is out of the scope of MARSSIM. For the purposes of identifying potential residual contamination within these systems, the following survey protocol was established. Surveys of ventilation exhausts consisted of beta and gamma scan surveys, total activity measurements, and removable contamination measurements of accessible ventilation exhaust points and at locations of potential collection/buildup. Removable contamination surveys of the internal surfaces of drains were collected, since scan surveys and static measurements are not practical due to their small geometry. Beam tube and beam dump internal surveys consisted of scans for activation products using 2” x 2” sodium iodide detectors as described in Section 18.1.

12.12 SURVEY INVESTIGATION LEVELS

Investigation levels are used to flag locations that require special attention and further investigation to ensure areas are properly classified and adequate surveys are performed. These locations are marked and receive additional investigations to determine the concentration, area, and extent of the contamination. The survey investigation levels for each type of measurement are listed by classification in the table below.

Table 12-3: Survey Investigation Levels

Survey Unit Classification

Flag Direct Measurement or Sample Result

When:

Flag Scanning Measurement Result When:

Flag Removable Measurement Result

When:

Class 1 >50% of DCGL >MDC > 100 dpm/100 cm2 Class 2 >25% of DCGL >MDC > 75 dpm/100 cm2

13.0 SURVEY DOCUMENTATION

Survey packages were developed for each survey area that contained specific survey instructions. Survey package preparation and completion were approved by the Chase PM or designee to ensure all survey requirements and Data Quality Objectives (DQOs) were met. As applicable, each survey package contained:

Survey unit number Maps of the survey unit surfaces Overview maps detailing survey locations and placement methodology General survey requirements



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Instrument requirements with associated Minimum Detectable Concentrations (MDCs), count times and scan rates

Survey Instruction Sheets Percentage of surface requiring scan surveys Number of measurements required Additional specific survey instructions Survey Data Sheets Sampling protocols Chain of Custody Forms Signature of Preparer, Surveyor and Reviewer

14.0 SURVEY RESULTS

14.1 VOLUMETRIC SCAN RESULTS

Sodium iodide scans were performed to detect areas of elevated activity as a result of activation based on the audible response. Four areas on the floor in and around the cyclotron pit and two locations on the north and south walls had elevated surface exposure rates and were marked for investigation, including judgmental measurements. Volumetric scan data was datalogged and used to develop 4-Plot graphs. 4-Plots of volumetric scan data conducted with a 2” x 2” sodium iodide detector are provided in Appendix F.

14.2 SURFACE SCAN RESULTS

Surface scans were performed using gas flow proportional instruments to detect areas of elevated activity based on the audible response. The same areas as described above for sodium iodide detector scans were identified except that the identified areas were smaller due to the lower efficiency of gas flow detectors for gamma emissions. Surface scan data was datalogged and used to develop 4-Plot graphs. 4-Plots of surface scan data conducted with a gas flow proportional detector are provided in Appendix G.

14.3 TOTAL SURFACE ACTIVITY RESULTS

Direct surveys (static measurements) for total surface activity were taken on building surfaces inside the vault (survey units 1101 and 1201) using gas flow proportional detectors. Static measurements were taken in impacted areas at each identified sample location. Scaler count times were determined to achieve the detection sensitivities stated in the DQOs. Field measurements were converted to an activity concentration using the equation described in Section 12.6 of this report. The results of total surface activity measurements are presented in Appendix H.



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14.4 REMOVABLE SURFACE ACTIVITY RESULTS

Removable surface activity measurements were collected by wiping an area of approximately 100 cm2 on structural surfaces. Samples were then counted for one minute on NASA’s Tennelec. Additionally, Chase counted smears from each sample location on a liquid scintillation counter. The results of removable surface activity measurements are presented in Appendix H.

14.5 SYSTEMS SURVEY RESULTS

Ventilation and drain systems were surveyed for removable surface activity measurements by wiping an area of approximately 100 cm2 for the ventilation duct inlets and with cotton swabs for drains. Samples were then counted for one minute on NASA’s Tennelec. Ventilation ducts were also surveyed Additionally, Chase counted smears from each sample location on a liquid scintillation counter.

Direct surveys (static measurements) for total surface activity were taken in the two duct inlets inside the vault using gas flow proportional detectors. Scaler count times were determined to achieve the detection sensitivities stated in the DQOs. Field measurements were converted to an activity concentration using the equation described in Section 12.6 of this report.

The results of removable activity measurements in the drain and ventilation systems are presented in Appendix I.

14.6 DOSE RATE MEASUREMENT RESULTS

Dose rate measurement results from the background reference area and the cyclotron room are presented in Appendix J.

14.7 LOCATIONS OF ELEVATED ACTIVITY

Scanning identified four areas on the floor in and around the cyclotron pit and two locations on the north and south walls with elevated surface exposure rates. Each area received judgmental measurements at the location within the elevated area with the highest detector response. The results of these measurements are provided in the table below.



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Table 14-1: Locations of Elevated Activity

Survey Unit

Sample Locations

Surface (ft2)

Surface Activity Volumetric Activity Total

(dpm/100 cm2)Removable

(dpm/100 cm2) NaI

(cpm) Dose Rate (µRem/hr)

1101 J1 Floor (14)

1,138 1.97 15,765 7.0

1101 J2 Floor (20)

2,526 -1.97 16,664 7.9

1101 J3 Floor (19)

1,221 1.97 16,187 7.1

1101 J4 Floor (67)

1,472 1.97 19,623 9.3

1101 J5 Wall (5)

1,656 13.76 10,264 6.0

1101 J6 Wall (5)

1,405 1.97 15,525 7.1

A map showing areas of elevated activity is presented in Appendix K with the Final Status Survey Locations.

15.0 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 are needed.

15.1 DATA VALIDATION

Field data were reviewed and validated to ensure:

Completeness of forms and that the type of survey was correctly assigned to the survey unit.

The MDCs for measurements meet the established data quality objectives; independent calculations were performed for a representative sample of data sheets and survey areas.

Instrument calibrations and daily functional checks were performed accurately and at the required frequency.

15.2 PRELIMINARY DATA REVIEW

A preliminary data review was performed for each survey unit to identify any patterns, relationships, or potential anomalies. Additionally, measurement data



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were reviewed and compared with the DCGLs and investigation levels to identify areas of elevated activity and confirm the correct classification of survey units.

The following preliminary data reviews were performed for each survey unit:

Calculations of the survey unit mean, median, maximum, minimum, and standard deviation for each type of reading.

Comparison of the actual standard deviation to the assumed standard deviation used for calculating the number of measurements to ensure a sufficient number of samples have been obtained.

Comparison of survey data with applicable investigation levels.

Descriptions of the preliminary data review are provided below. Judgmental measurement data at areas of elevated activity is conservatively included in the statistical summaries.

15.2.1 Surface Activity Data Review

4-Plot data of surface activity scan data are presented in Appendix G. The gas flow detector 4-Plots indicate that all scan results in survey units 1101 and 1201 are less than the investigation levels. Both 1101 and 1201 have a bimodal distribution likely due to differences between areas with higher levels of activation and areas of lower levels of activation and differences in concrete for floor and wall surfaces. The bimodal distribution for 1201 is more pronounced, as would be expected. BRA1 shows a bimodal distribution due to differences in unpainted floor and painted wall surfaces.

Summary statistics of surface activity results are provided in the tables below. Locations are shown in Appendix K.

Table 15-1: Structural Surfaces - Surface Activity Scan Results

Survey Unit

Scan Count Time (sec)

Mean MedianStandard Deviation

Min. Max.

(dpm/100 cm2) 1101 9,439 30 0 543 -1,328 3,099 1201 10,435 -52 -110 535 -1,550 2,656

Table 15-2: Structural Surfaces - Total Beta Surface Activity Summary

Survey Unit

# of Sample

Locations

Total Surface Activity (dpm/100 cm2) Investigation

Level

Any Result Exceeding

Investigation Level? Mean MDC

Standard Deviation

Min. Max.

1101 35 553 991 704 -435 2,526 3,550 NO 1201 14 207 991 250 -368 736 1,775 NO



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Table 15-3: Structural Surfaces - Removable Surface Activity Summary

Survey Unit

# of Sample

Locations

Removable Surface Activity (dpm/100 cm2) Investigation

Level



Standard Deviation

Min. Max.

1101 35 1 20 5 -6 18 100 NO 1201 14 3 20 5 -6 10 75 NO

Table 15-4: Structural Surfaces - Removable H-3 Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

1101 35 7 35 7 0 28 100 NO 1201 14 3 35 5 0 19 75 NO

Table 15-5: Systems - Total Beta Surface Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

VE01 2 -8 1,007 204 -153 136 3,550 NO

Table 15-6: Systems - Removable Surface Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

DR01 2 0 20 3 -2 2 100 NO VE01 2 2 20 6 -2 6 100 NO

Table 15-7: Systems - Removable H-3 Surface Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

DR01 2 25 35 8 19 31 100 NO VE01 2 5 35 6 0 9 100 NO



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15.2.2 Volumetric Activity Data Review

4-Plot data of volumetric activity scan data are presented in Appendix F. It is important to note that the background count rate is not subtracted from this data. The gamma scan 4-Plots indicate that both 1101 and 1201 have a bimodal distribution due to differences between areas with higher levels of activation and areas of lower levels of activation; this effect is more pronounced than gas flow detector results due to the higher detection efficiency of the NaI detector for gamma emissions. Survey Unit 1101 wall surfaces were surveyed first and have less variability than floor surfaces. The crane and watertight steel doors were surveyed last with lower results than concrete surfaces due to the shielding effect of the steel. BRA1 has an approximate normal distribution.

Summary statistics of volumetric activity scan results are provided in the table below.

Table 15-8: Structural Surfaces – Gamma Scan Results

Survey Unit

Scan Count Time (sec)

Mean MedianStandard Deviation

Min. Max.

(gross cpm) 11F11F

12 1101 9,632 10,259 10,020 2,588 1,680 22,6201201 13,171 9,361 9,720 1,924 2,160 14,460

BRA1 862 7,010 7,020 728 4,800 9,420

Table 15-9: Structural Surfaces – Dose Rate Summary

Survey Unit

# of Sample

Locations

Dose Rate @ 1m (µRem/hr) Investigation

Level


Investigation Level? Mean

Standard Deviation

Min. Max.

1101 35 6.5 1.1 4.6 9.3 10.0 NO 1201 14 6.6 0.7 5.8 8.1 7.5 YES

BRA1 15 5.0 0.6 3.6 5.8 N/A N/A

Beam tube and beam dump volumetric activity measurements are described in Section 18.1.

12 Background is not subtracted from measurement results; instead, summary statistics from the background reference area are also presented in the table.



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15.3 DETERMINING COMPLIANCE FOR SURFACE ACTIVITY

Survey Unit 1201 had two locations (#8 and #13) over the investigation level of 7.5 µRem/hr without background subtraction. Because restrictive ILs are assigned for Class 2, background is not subtracted, and results are a small fraction of DCGL, no action required.

Because all surface activity measurements are less than the DCGL and an adequate number of samples were taken, all survey units pass the Sign Test for surface activity.

The results of the data quality assessment and calculations of dose from residual surface activity are presented in the table below.

Table 15-10: Structural Surfaces - Total Surface Activity Dose Calculations

Survey Unit

Standard Deviation

(dpm/100 cm2)

# Samples Required

# of Samples

Adequate # of

Samples?

Mean (dpm/100 cm2)

Calculated Annual TEDE(mrem/yr) 12F12F

13

1101 704 11 35 YES 553 1.9

1201 250 11 14 YES 207 0.7

Maximum: 1.9 The TEDE to an average member of the critical group from surface activity is 1.9 mrem/yr which is less than 8% of the release criterion of 25 mrem/yr.

15.4 DETERMINING COMPLIANCE FOR VOLUMETRIC ACTIVITY

For volumetric activity, the Wilcoxon Rank Sum (WRS) test is used to evaluate external dose rate measurements. The highest dose rate measurement of any location inside the cyclotron room (9.3 µRem/hr) is less than the DCGL (10 µRem/hr) above the lowest dose rate measurement in the background reference area (3.6 µRem/hr), so the survey unit will pass the Wilcoxon Rank Sum (WRS) test. All removable activity results were less than the removable DCGL of 150 dpm/100cm2. The results of the data quality assessment and calculations of the dose based on external dose rate measurements are presented in Table 12 5.

13 The TEDE is calculated by dividing the survey unit mean by the DCGL and then multiplying by 25 mrem/yr.



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Table 15-11: Structural Surfaces - Volumetric Activity Dose Calculations

Survey Unit

Standard Deviation

(µRem/hr)

# Samples Required

# of Samples

Adequate # of

Samples?

Mean (µRem/hr)

Corrected Mean Dose

Rate 13F13F

14 (µRem/hr)

1101 1.1 18 35 YES 6.5 1.5

1201 0.7 9 14 YES 6.6 1.6

BRA1 0.6 9 15 YES 5.0 N/A

The mean dose rate in the cyclotron room is 1.6 µR/hr above background which equates to 3.7 mrem per year from external exposures assuming occupancy of 2,340 hours. Considering that there is no measureable removable radioactivity, the TEDE to an average member of the critical group from volumetric activation products is 3.7 mrem/yr which is less than 15% of the release criterion of 25 mrem/yr.

16.0 MECHANICAL SYSTEM SURVEY DATA ANALYSIS

All gamma scan measurements, and total and removable surface activity measurements were compared directly to the investigation levels to determine if an area required further examination. All measurements were less than the investigation levels, therefore all systems meet the release criteria and are suitable for release for unrestricted release.

17.0 QUALITY ASSURANCE SURVEY RESULTS

Quality assurance surveys consisted of re-performing the FSS protocol for building structural surfaces to achieve a minimum of 5% duplication of scans, dose rate measurements, static measurements, and smears. QA surveys were implemented by re-performing judgmentally selected survey locations as survey unit QA01. The locations of QA survey measurements are presented in the table below.

Table 17-1: QA Survey Locations

QA Survey Location FSS Location QA01-1 1101-25 QA01-2 1101-12 QA01-3 1201-3

14 The mean dose rate from BRA1 is subtracted.



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All QA survey results were similar to FSS data and the conclusions were the same as those based on the initial surveys. QA survey results are presented in Appendix L and are summarized in the tables below.

Table 17-2: QA - Total Beta Surface Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

QA01 3 252 965 511 -290 724 1,775 NO

Table 17-3: QA - Removable Surface Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

QA01 3 -2 20 0 -2 -2 100 NO

Table 17-4: QA - Removable H-3 Activity Summary

Survey Unit

# of Sample

Locations


Level



Standard Deviation

Min. Max.

QA01 3 9 35 9 0 18 100 NO

Table 17-5: QA - Dose Rate Summary

Survey Unit

# of Sample

Locations

Dose Rate @ 1m (µRem/hr) Investigation

Level


Investigation Level? Mean

Standard Deviation

Min. Max.

QA01 3 6.5 0.5 6.1 7 7.5 NO

18.0 ALTERNATE SCENARIO ANALYSIS

18.1 BEAM TUBE ANALYSIS

Beam tube internals are not subject to occupancy scenarios and are outside the scope of MARSSIM; therefore, Chase surveyed the internal surfaces of beam tubes and modeled the activity concentrations for recycling and re-use scenario dose assessments. Chase used conservative assumptions for each step of the



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process such that the calculated results are overestimated and the actual Co-60 concentration in beam tubes is believed to be much lower.

18.1.1 Beam Tube Descriptions

Each beam line was assigned a unique number from 1-13 as shown in Appendix M. Each section of beam line was also assigned a descriptor before the number to indicate if the section was a beam tube or a beam dump. BT = Beam Tube, BD = Beam Dump. (i.e., BT8 and BD8 are the beam tube and beam dump in beam line 8). All beam line centers are at a 49” height from the floor to coincide with height of the cyclotron beam, except beam line 5 which exits the vault at a height of 77” and angles upward into the Therapy Room. Beam tube/dump sections and dimensions are provided in the table below. Some of the beam tubes have been removed; in these cases, the material is identified as concrete.

Table 18-1: Beam Tube and Beam Dump Information

Item Material ID 14F14F

15

(in) WT 15F15F

16

(in) Length

(ft) Comments

BT1A Steel 8 0.375 24.5 No history of usage BT1B Steel 8 0.375 9.2 None BD2 Steel 8 0.375 4.9 None BD3 Steel 8 0.375 4.8 None

BD4 Stainless

Steel 4 0.25 7.3 None

BT5A Concrete 9 N/A 7.1 Beam tube removed BT5B Concrete 9 N/A 8.8 Beam tube removed BT5C Steel 11.5 N/A 2.9 None

BT6 Concrete 14 N/A

8.4 14”D Concrete on Vault side, 44” long steel on Therapy Room side Steel 11.5 1.25

BT7 Stainless


BT8 Stainless

Steel

2.75 0.125 6.9

43.75” long on Vault side 39” long on Therapy Room side 6.25 0.375

BD8 Steel 6 0.25 4.5 None BT9 Concrete 6.75 N/A 6.5 Beam tube removed BD9 Steel 6 0.25 4.5 None

BT10 Stainless

Steel 2.75 0.125 6.8 None

BD10 Steel 6 0.25 4.5 None BT11 Stainless 2.75 0.125 6.7 None

15 ID = Inside Diameter 16 WT = Wall Thickness



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Item Material ID 14F14F

15

(in) WT 15F15F

16

(in) Length

(ft) Comments

Steel BD11 Steel 6 0.25 4.5 None

BT12 Stainless


BD12 Steel 6 0.25 4.5 None BT13 Steel 18 16F16F

17 0.5 6.1 None

18.1.2 Survey Protocol

Chase performed gamma scans and static measurements of the internal surfaces of the beam tubes for dose modeling to estimate the activity concentration. The internal surface of each beam line was scanned starting at the opening closest to the vault and scanning outward from the vault. Chase scanned at maximum rate of 1” per second with the detector centered in the beam tube. At specific locations within the tube, Chase obtained one-minute static measurements for dose modeling calculations. 4-Plots of beam tube scan data are provided in Appendix N and summary statistics are provided in the table below. It is important to note that background was not subtracted from this scan data. There appear to be higher background levels in beam tubes that are embedded in soils vs. embedded in concrete. This results in an overestimation of the activity concentration in these sections of piping when conservative background values based on piping embedded in concrete are applied to static measurements taken at these locations. The higher detector response in soils can be seen on the run sequence plots for BT1A, BT1B, BD-2, BD-3, and BD8-BD12. BT1A and BT1B are embedded in 12-inch thick concrete at the ends and soils in between; the run sequence plot shows a lower detector response at the ends where the piping is embedded in concrete and a higher response in the middle where the piping is embedded in soil. Similarly, BD-2, BD-3, and BD8-BD12 are embedded in concrete at the beginning of the run plot and demonstrate a higher detector response where the dumps are embedded in soils. For comparison, BD-4 is embedded in concrete and demonstrates a lower detector response than beam dumps that are embedded in soils.

17 BT13 is not technically a beam tube; it is 18” square and previously had beam tubes within it, for consistency of the survey protocol, it is referred to as a beam tube.



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Table 18-2: Beam Tube Gamma Scan Summary Statistics

Survey Unit

Count Mean Median

Standard Deviation

Min. Max.

(gross cpm) BT1A 379 9,072 9,720 2,175 3,120 12,240BT1B 235 7,567 8,760 2,759 2,760 11,460BD2 91 8,554 8,820 2,133 4,800 12,480BD3 79 8,170 8,520 1,810 4,440 10,980BD4 175 6,456 5,160 3,085 3,360 15,540

BT5A 101 10,144 9,540 2,023 6,780 15,720BT5B 114 8,457 8,400 907 5,460 10,920BT5C 54 5,506 5,490 1,702 2,820 9,420 BT6 152 17,967 11,310 11,271 6,900 41,160BT7 210 19,108 14,550 13,413 4,800 43,680BT8 163 14,602 14,760 2,224 9,780 20,460BD8 78 7,150 6,540 2,004 4,320 11,880BT9 85 8,876 8,640 1,142 6,720 12,000BD9 91 6,597 6,180 1,781 4,080 11,160BT10 115 13,567 13,860 1,677 9,720 17,160BD10 94 8,954 8,460 2,554 4,680 14,220BT11 173 13,608 13,680 1,396 8,880 16,980BD11 108 8,556 7,920 2,630 4,440 13,380BT12 107 9,713 9,900 1,496 6,000 13,680BD12 107 8,071 7,440 2,759 3,780 12,840BT13 79 14,976 15,360 1,891 9,900 18,660

18.1.3 Background

Because the background level within the beam tubes is lower than the ambient background due to the shielding effect of the tube and surrounding concrete, subtracting the ambient background would result in an underestimation of the residual radioactivity. Therefore, Chase obtained static measurements from two embedded drain pipes located in the pit adjacent to the Skylight Room. These embedded steel pipes have an internal diameter of 8 inches and are of the same construction as Beam Tube 1. Static measurements were taken at the opening as well as at locations 1 ft, 2 ft, 3 ft, and 4 ft within the pipes. The average of these background measurements at each distance were subtracted from beam tube measurements taken at the same distance.



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Table 18-3: Beam Tube Background Measurements Distance

(ft) Measurement Result (gross cpm)

Pipe 1 Pipe 2 Average 0 6,044 6,221 6,133 1' 2,170 2,341 2,256 2' 3,808 4,222 4,015 3' 4,250 4,527 4,389 4' 5,408 5,497 5,453

Emissions due to activation of surrounding concrete were not subtracted; any contribution to the detector response is conservatively assumed to be from activation of the beam tube steel. Chase collected a sample of steel from BT6 (the location of highest external dose rate) and a sample of the adjacent concrete surrounding the beam tube. NASA analyzed the sample and obtained results of 28.4 pCi/g Co-60 in the steel sample and 11.3 pCi/g Eu-152 in the concrete sample, indicating that Eu-152 concentrations in the concrete surrounding the beam tube steel is approximately 40% of the Co-60 concentration in the beam tube steel. The dose per pCi/g is low in thin-walled piping due to wall thickness – this results in magnification of the errors associated with the application of conservative backgrounds and results in gross overestimation of the concentration of Co-60 in these thin-walled tubes. There appear to be higher background levels in beam tubes that are embedded in soils. However, no attempt was made to quantify this higher background and any detector response from soil activity is assumed to be from Co-60 activation of the beam tube steel.

18.1.4 Dose Modeling

Chase used the 2” x 2” NaI static measurement data to estimate the Co-60 activity concentration in the beam tubes. Chase modeled each tube geometry in MicroshieldTM software using an annular cylinder geometry with internal dose points. The geometry of each beam tube was input and dose points centered at various lengths along the tube were modeled for a Co-60 concentration of 1 pCi/g. The results were used to develop scaling factors for calculation of the activity concentration associated with the static measurements. MicroshieldTM output reports are presented in Appendix O.

The results of each static measurement were corrected for the background level at the appropriate distance within the pipe (distance from either end) and converted to pCi/g Co-60 using the results of the MicroshieldTM modeling. Where the distance within the tube is greater than 4 ft from an end, the 4 ft background level



Page 48 of 58

is used. Beam tube static measurements and MDC calculations are presented in Appendix O. Calculations of the beam tube mass and weighted average activity concentration are provided in the table below.

Table 18-4: Beam Tube Mass and Activity Calculations

Item ID (in)

WT (in)

Length (ft)

A (ft2)

lb/ft2 Mass (lb)

Average (pCi/g)

Fraction of Mass

WeightedAverage (pCi/g)

BT1A 8 0.375 24.5 51.3 15.3 784.7 6.2 0.19 1.2

BT1B 8 0.375 9.2 19.3 15.3 294.7 4.0 0.07 0.3

BD2 8 0.375 4.9 10.3 15.3 156.9 9.6 0.04 0.4

BD3 8 0.375 4.8 10.0 15.3 153.7 9.0 0.04 0.3

BD4 4 0.25 7.3 7.6 11.2 85.6 6.2 0.02 0.1

BT5C 11.5 1.25 2.9 8.7 51.1 445.9 1.9 0.11 0.2

BT6 11.5 1.25 3.7 11.1 51.1 568.9 18.5 0.14 2.6

BT7 4 0.25 8 8.4 11.2 93.8 34.4 0.02 0.8

BT8 2.75 0.125 3.6 2.6 5.6 14.5 51.7 0.00 0.2

BT8 6.25 0.375 3.3 5.4 16.5 89.0 15.1 0.02 0.3

BD8 6 0.25 4.5 7.1 10.2 72.1 11.6 0.02 0.2

BD9 6 0.25 4.5 7.1 10.2 72.1 10.2 0.02 0.2

BT10 2.75 0.125 6.8 4.9 5.6 27.4 46.0 0.01 0.3

BD10 6 0.25 4.5 7.1 10.2 72.1 13.6 0.02 0.2

BT11 2.75 0.125 6.7 4.8 5.6 27.0 45.6 0.01 0.3

BD11 6 0.25 4.5 7.1 10.2 72.1 12.3 0.02 0.2

BT12 6 0.375 7.3 11.5 16.5 189.1 10.4 0.05 0.5

BD12 6 0.25 4.5 7.1 10.2 72.1 12.2 0.02 0.2

BT13 18 0.5 6.1 36.6 20.4 746.6 15.7 0.18 2.9

Total 4,038.3 Total 11.6

18.2 SOIL SCENARIO ANALYSIS

Even though soils are considered non-impacted, Chase used existing soil characterization data to model potential doses from scenarios involving soils that had results above MDC. Chase analyzed the potential dose to a member of the public using RESRAD software for the following two scenarios:

Scenario 1: The site is left as-is. Scenario 2: The site is excavated and spread on the ground surface to an

average 6” depth.



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Compliance with the unrestricted release criteria is demonstrated using a dose model developed with RESRAD v.6.5 dose modeling software. RESRAD default parameter values were retained, except for contaminated zone geometry, to establish a dose rate in mrem/yr. The source concentration for the intact model is conservatively assumed to be higher than the maximum of all the sample results (1 pCi/g). The source concentration for the excavated and spread model is conservatively assumed to be 0.25 pCi/g using a 3:1 mixing factor with clean soils. RESRAD inputs are summarized in the tables below. RESRAD output reports are presented in Appendix P.

Table 18-5: Soil Dose Modeling Geometry

Scenario Eu-152 (pCi/g)

CZ Area (m2)

CZ Depth

(m)

CoverDepth

(m)

Length Parallel

to Aquifer(m)

RESRAD 6.5 File

Dose 17F17F

18 (mrem/yr)

Intact 1 4 2 5 2 NASA_1 9.8E-28

Excavated and

Spread 0.25 213 0.15 0 14.6 NASA_3 0.76

The results of dose modeling using these conservative assumptions are a very small fraction of the unrestricted release criterion, such that a more refined model is not necessary to demonstrate compliance. The calculated dose to an average member of the critical group is less than 1 mrem/yr. Even though the full extent of residual radioactivity was not completely bound, the conservatism of the dose model compensates for the uncertainty. Because residual radioactivity is at a low concentration and limited to a shallow depth relative to groundwater, groundwater contamination is not of concern.

18.3 RECYCLING AND RE-USE SCENARIOS

The results of gamma spectroscopy analysis of reinforced concrete and steel samples were used to model the resultant doses from removal, recycling, and disposal of activated structures after unrestricted release of the facility. These analyses are in addition to the dose evaluations based on the building occupancy scenario.

Extensive work has been performed by the NRC in NUREG 1640 to assess potential doses resulting from recycling and disposal of scrap metal and concrete released from nuclear facilities. This work was performed in support of

18 The maximum annual dose from RESRAD 7.0 output reports.



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developing clearance criteria for release of a variety of recyclable materials including steel, copper, concrete, and aluminum scrap, as well as direct reuse of equipment. Assessments include all phases of recycling processes including transportation, refining, waste product disposal, utilization of recycled metal in consumer goods, and land disposal. The goal of the analysis was to identify realistic critical groups resulting from clearance of equipment and materials from NRC licensed facilities and to calculate dose factors for the average member of each critical group.

NUREG 1640 Chapter 3 discusses recycling and disposal of steel. A variety of exposure scenarios associated with steel recycling are analyzed in NUREG 1640. Steel recycling scenarios include handling and processing; including processing of scrap in the scrap yard, handling of slag, and processing of baghouse dust; emissions of airborne effluents from the furnace; transportation, including hauling of slag, baghouse dust, and steel products; various product use scenarios such as the use of cement made from steel slag in road construction; landfill disposal; and consumption of groundwater infiltrated by leachate.

NUREG 1640 Chapter 6 discusses recycling and disposal of concrete rubble. The assessments address eight scenarios that depict exposures resulting from handling and processing of cleared concrete rubble, transportation of the rubble, use of recycled concrete in road construction, landfill disposal of concrete rubble, and infiltration of well water by leachate from landfills containing concrete rubble. The analyses utilize data on concrete recycling and disposal, as currently practiced in the United States, and on contemporary U.S. work practices and living habits.

18.3.1 Volume Considerations

It is important to note that NUREG 1640 was developed to assess doses resulting from continuous material recycling and disposal (i.e., a continuous feed stream) as opposed to one-time recycling or disposal of a small amount of concrete rubble or steel scrap.

Concrete NUREG 1640 assumes all the cleared concrete rubble from a commercial nuclear power plant during one year is processed at a single location or disposed in a single landfill. The amount of concrete rubble cleared is estimated at 281,000 metric tons for a boiling water reactor and 143,000 metric tons for a pressurized water reactor. All rubble is assumed to be cleared and recycled uniformly over a period of 1.7 years. NUREG 1640 uses probabilistic analysis, so a single value of the volume used for the dose assessment is not available. Therefore, a conservatively low deterministic volume of concrete is assumed for correction of the DCFs for this analysis. Using the conservative assumption that the lowest estimated amount of cleared scrap (143,000 metric tons) is uniformly cleared over



Page 51 of 58

a two-year period, the annual amount of cleared scrap would be 71,500 metric tons. The vault interior floor dimensions are approximately 40 ft by 50 ft and the ceiling height is approximately 20 ft. The quantity of vault materials for the interior 1 ft layer was conservatively calculated to support dose modeling (characterization core sampling determined that activation was detectable to an approximate 8inch depth). The concrete density is assumed to be 150 lb/ft3. For simplicity and conservatism, the volume of doors, trenches and structural irregularities are not subtracted. Calculations of potentially activated concrete are presented in the table below.

Table 18-6: Activated Concrete Mass Calculations

Vault Condition

InteriorLength

(ft)

InteriorWidth

(ft)

InteriorHeight

(ft)

Interior Volume

(ft3)

Volume 18F18F

19 (ft3)

Mass (MT)

19F19F

20 Intact 50 40 20 40,000 N/A N/A

0-1 ft Removed 52 42 22 48,048 8,048 547

There are less than 550 metric tons of potentially activated concrete; this is less than 1 % of the 71,500 metric tons conservatively assigned to NUREG 1640 DCFs. Therefore, a correction is applied to account for volume differences between the model volume assumptions and the volume of potentially activated concrete in the vault.

Steel NUREG 1640 scrap volume assumptions assume all the cleared steel scrap from a commercial nuclear power plant during one year is processed by a single scrap dealer or disposed in a single landfill. The amount of steel scrap cleared is estimated at 14,657 to 19,374 metric tons for a boiling water reactor and 19,754 to 23,592 metric tons for a pressurized water reactor. All scrap is assumed to be cleared and recycled uniformly over a period of 1.7 years. Using the conservative assumption that the lowest estimated amount of cleared scrap (14,657 metric tons) is uniformly cleared over a two-year period, the annual amount of cleared scrap would be about 7,328 metric tons. Calculations of potentially activated steel are provided in the table below.

19 The materials volume is the interior volume with the inner 1 ft of concrete removed less the interior volume of the intact vault. 20 One metric ton (MT) is 2205 lb.



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Table 18-7: Activated Steel Mass Calculations

Item Comments Mass (MT)

20F20F

21 Crane Girders and

Hoist 80 ft girders at 162 lb per linear ft, 0.5 MT for hoist 6.4

Equipment Door 12 ft x 20 ft x 1.5 inch thick steel 6.7 Personnel Door 12 ft x 20 ft x 1.5 inch thick steel 0.7

Rebar, Deck Supports, Misc.

Rebar mass is 5% of concrete mass, doubled to include deck supports and misc. metal in the vault

54.7

Beam Tubes See Table 18-4 for calculation 1.8 Total 70.3

There are less than 71 metric tons of potentially activated steel at the site; this is less than 1 % of the 7,328 tons conservatively assumed. Therefore, a correction is applied to account for volume differences between the model volume assumptions and the amount of potentially activated steel in the cyclotron room.

18.3.2 Activity Concentrations

Chase developed conservative assumptions regarding the average activity concentrations of steel and concrete materials for recycling and disposal dose calculations.

Concrete The averages of the Leidos characterization decay-corrected concrete sample activity concentrations present an upper bound of the average concentrations within the vault because the locations were selected judgmentally based on areas with the highest potential for activation. Therefore, these average concentrations presented in Table 4-2 are used for recycling and disposal dose calculations

Steel Chase calculated a weighted average concentration of remaining steel materials that are potentially activated. The activity concentrations of the crane and doors are based on decay-corrected Leidos characterization data, the activity concentration of rebar and miscellaneous metal items is based on 2.5 times the average Eu-152 concentration in concrete,21F21F

22 and beam tube activity concentration is based on the calculations presented in Table 18-4.

21 The density of concrete is 150 lb/ft3. One metric ton (MT) is 2205 lb. 22 This ratio is based on the steel sample adjacent concrete sample results described in Section 18.1.3.



Page 53 of 58

Table 18-8: Activated Steel Mass Calculations

Item Mass (MT)

22F22F

23

Fraction of Mass

Co-60 Activity(pCi/g)

Weighted Average Co-60 Activity

(pCi/g) Crane Girders and Hoist 6.4 0.08 4 0.3

Equipment & Personnel Doors 7.4 0.11 0.3 0.1 Rebar, Deck Supports, Misc. 54.7 0.78 2.7 2.1

Beam Tubes 1.8 0.03 11.6 0.3 2.8

18.3.3 NUREG 1640 Processing Dose Conversion Factors

NUREG 1640 provides nuclide-specific dose conversion factors (DCFs) to relate surface and volumetric radioactivity concentrations to an annual dose to an average member of the critical group in mrem/yr. NUREG 1640 Table 2.1 lists the nuclide-specific critical groups and associated DCFs for all NUREG 1640 recycling and disposal scenarios (the most conservative nuclide-specific DCFs for each material).

Table 18-9: NUREG 1640 Processing Dose Conversion Factors

Nuclide Concrete Mass-Based DCF Steel Mass-Based DCF mrem/yr per pCi/g

Critical Group mrem/yr per pCi/g

Critical Group

Co-60 1.07 Road Building 0.19 Scrap Yard Eu-152 0.44 Road Building --- --- Eu-154 0.52 Road Building --- --- Fe-55 --- --- 0.0000017 Scrap Yard Na-22 0.89 Road Building --- --- Ni-63 --- --- 0.0000017 Scrap Yard

18.3.4 NUREG 1640 Disposal Dose Conversion Factors

NUREG 1640 Appendix F provides tables of the dose conversion factors for each steel pathway. For steel disposal scenarios, the dose to disposal workers and the dose to the public from leachate are considered.

23 The density of concrete is 150 lb/ft3. One metric ton (MT) is 2205 lb.



Page 54 of 58

Table 18-10: NUREG 1640 Steel Disposal Dose Conversion Factors

Nuclide

Most Conservative Worker DCF

Most Conservative Leachate DCF

mrem/yr per pCi/g

Critical Group mrem/yrper pCi/g

Critical Group

Co-60 0.15 Industrial Disposal 1.9E-6 Municipal Leachate Fe-55 0 N/A 3.6E-17 Municipal Leachate Ni-63 0 N/A 7.0E-16 Municipal Leachate

NUREG 1640 Appendix I provides tables of the dose conversion factors for each concrete pathway. For concrete disposal scenarios, the dose to disposal workers and the dose to the public from leachate are considered.

Table 18-11: NUREG 1640 Concrete Disposal Dose Conversion Factors

Nuclide

Most Conservative Worker DCF

Most Conservative Leachate DCF

mrem/yr per pCi/g

Critical Group mrem/yr per pCi/g

Critical Group

Co-60 0.41 Industrial Disposal 2.1E-8 Municipal Leachate Eu-152 0.18 Industrial Disposal 0 N/A Eu-154 0.20 Industrial Disposal 0 N/A Na-22 0.35 Industrial Disposal 5.6E-39 Industrial Leachate

18.3.5 Processing Dose Calculations

The doses from recycling and re-use scenarios were calculated using the average activity concentration of each nuclide and the quantity of materials.

The estimated doses from vault demolition and recycling are presented in the tables below.

Table 18-12: Concrete Road Building Dose Calculations



DCF (mrem/yr per

pCi/g)

Dose Using NUREG 1640 Volume Assumptions

(mrem/yr)

Volume-Corrected Dose

(mrem/yr)

Co-60 0.19 1.07 0.2 1.6E-03 Eu-152 1.07 0.44 0.5 3.6E-03 Eu-154 0.18 0.52 0.1 7.1E-04 Na-22 0.04 0.89 0.0 2.7E-04

Total 6.2E-3



Page 55 of 58

Table 18-13: Steel Scrap Yard Dose Calculations



DCF (mrem/yr per

pCi/g)


(mrem/yr)


(mrem/yr)

Co-60 2.8 0.19 0.53 5.1E-3

18.3.6 Disposal Dose Calculations

The estimated doses from disposal of concrete structures from the vault are presented in the tables below.

Table 18-14: Concrete Disposal Calculations



DCF (mrem/yr per

pCi/g)


(mrem/yr)


(mrem/yr)

Co-60 0.19 0.41 0.1 6.0E-04 Eu-152 1.07 0.18 0.2 1.5E-03 Eu-154 0.18 0.20 0.0 2.8E-04 Na-22 0.04 0.35 0.0 1.1E-04

Total 2.5E-3

Table 18-15: Concrete Disposal Leachate Dose Calculations



DCF (mrem/yr per

pCi/g)


(mrem/yr)


(mrem/yr)

Co-60 0.19 2.1E-8 4.0E-09 3.1E-11 Eu-152 1.07 0 0.0E+00 0.0E+00 Eu-154 0.18 0 0.0E+00 0.0E+00 Na-22 0.04 5.6E-39 2.2E-40 1.7E-42

Total 3.1E-11 The estimated doses from disposal of steel structures from the vault are presented in the tables below.

Table 18-16: Steel Scrap Disposal Calculations



DCF (mrem/yr per

pCi/g)


(mrem/yr)


(mrem/yr)

Co-60 2.8 0.15 0.42 4.0E-3



Page 56 of 58

Table 18-17: Steel Scrap Disposal Leachate Dose Calculations



DCF (mrem/yr per

pCi/g)


(mrem/yr)


(mrem/yr)

Co-60 2.8 1.9E-6 5.3E-6 5.1E-8

18.3.7 Results

The dose resulting from recycling or disposal of concrete was bounded using the volumetric-based DCFs. For the volumetric-based analysis, the volumetric activity concentration associated with the MDC was used (based on modeling of the activity concentration at the minimum detectable concentration of the gamma scanning technique – refer to calculation of volumetric scan MDC). NUREG 1640 mass-based dose calculations are presented in the tables above. Both corrected and uncorrected doses are presented to demonstrate that modeled doses are acceptable, even without applying the volume correction.

18.3.8 Alternate Scenario Conclusions

Dose modeling indicates vault materials can be safely demolished and recycled without exceeding public dose limits. Alternate scenario dose modeling using NUREG 1640 demonstrates that potential future doses to an average member of the critical group for recycling or disposal of the concrete/steel are much less than 1 mrem/yr. Additionally, recycling scenarios include rubblization of materials at a processor – an operation that bounds potential future uses of the structural materials inside the cyclotron room.

Calculations of the average activity concentration and quantity of materials are conservative due to the reasons listed below.

Conservative source volume assumptions were used (higher than actual); the volume of utility trenches, doors, etc. were not subtracted in the volume calculation

The ceiling and upper structures have lower activation levels than the floor and lower structures due to proximity of the cyclotron and beam. Only floor and lower structure sample results are used to determine the average concentrations

Judgmental samples at highest locations identified during characterization surveys are included in calculation of average concentration.

Conservative NUREG 1640 volume assumptions (lower than actual)



Page 57 of 58

19.0 SUMMARY

The cyclotron and associated components were removed from the facility. All data presented in this report demonstrates that the facility meets release criterion for unrestricted use. Structural surfaces and system removable activities were below the established DCGL of 150 dpm/100 cm2. In the same manner, total activities present on structural surfaces were found to yield annual doses to a member of the critical group in the order of 1.9 mrem/yr (<8% of the release criterion of 25 mrem/yr established in 10 CFR 20.1402).

The average measured background was 5.0 µrem/hr. The average dose rate within the cyclotron vault was 6.6 µrem/hr. Assuming an occupancy of 2,340 hr/yr, the total effective dose equivalent to an average member of the critical group was calculated to be 3.7 mrem/yr (<15% of the release criterion of 25 mrem/yr established in 10 CFR 20.1402).

Alternate scenario analyses (with results less than 1 mrem/yr per scenario) demonstrate that the occupancy scenario is the limiting scenario.

Even under the assumptions of the conservative analysis performed, an upper bound of potential doses to an average member of the critical group is less than 5.6 mrem/yr. This dose was conservatively determined by adding together the dose calculated from surface activity and the dose calculated from volumetric activity, even though there is overlap in the dose calculations (volumetric activity detected by surface activity measurements is included in the dose calculations for surface activity as well as in the dose calculations for volumetric activity). Based solely on potential dose averted, further action is not consistent with the ALARA principle.

ALARA is further supported by the occupational risks associated with removal, movement, packaging, transport, processing and disposal along with the risks associated with the restoration of remediated areas for future use of the space.



Page 58 of 58

20.0 REFERENCES

1. US Nuclear Regulatory Commission 10 CFR 20, “Standards For Protection Against Radiation”

2. NASA Glenn Research Center Building 140 Cyclotron Vault Radiological Survey Work Execution Plan

3. NASA radioactive materials license number 34-00507-16

4. NUREG-1505, Revision 1, “A Nonparametric Statistical Methodology for the Design and Analysis of Final Decommissioning Surveys," June 1998

5. NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions,” June 1998

6. NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM)

7. NUREG 1640, Volumes 1 & 2, “Radiological Assessments for Clearance of Equipment and Materials from Nuclear Facilities,” June, 2003

8. NUREG-1757, Volume 1, Rev. 2 “Consolidated NMSS Decommissioning Guidance: Decommissioning Process for Materials Licensees,” September, 2006

9. NUREG-1757, Volume 2, Rev. 1 “Consolidated NMSS Decommissioning Guidance: Characterization, Survey, and Determination of Radiological Criteria,” September, 2006

10. NUREG/CR-5512 Volume 1, “Residual Radioactive Contamination from Decommissioning: Technical Basis for Translating Contamination Levels to Annual Total Effective Dose Equivalent,” October 1992.

11. NUREG/CR-5512 Volume 3, “Residual Radioactive Contamination from Decommissioning: Parameter Analysis,” October 1999.

12. Characterization Summary Report, NASA GRC Cyclotron Facility, May, 2016

13. EUR 19151, “Evaluation of the Radiological and Economic Consequences of Decommissioning Particle Accelerators,” March 1999

NASA Glenn Research CenterCyclotron Vault

Final Status Survey Report

Page: A.1 of A.1Building: 140 Facility Location Map

AutoCAD SHX Text

N

AutoCAD SHX Text

Building 140 Cyclotron Vault



Page: B.1 of B.1Building: 140 Facility Layout

Beam Tubes

Survey Area

AutoCAD SHX Text

(TUNNEL)

AutoCAD SHX Text

Cyclotron Vault

AutoCAD SHX Text

Neutron Therapy Room

AutoCAD SHX Text

Shield Room

AutoCAD SHX Text

Skylight Room

AutoCAD SHX Text

Hot Storage Room

AutoCAD SHX Text

Walk Way

AutoCAD SHX Text

Instrument Room

AutoCAD SHX Text

Sump

AutoCAD SHX Text

Building 49

AutoCAD SHX Text

N

DandD Building Occupancy Scenario

DandD Version: 2.1.0 Run Date/Time: 8/27/2007 11:06:19 AM Site Name: N/A Description: DSV Determination FileName:C:\Documents and Settings\Dave Culp\My Documents\Co-60 DSV.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 used for behavioral type parameters

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

Initial Activities:

Chain Data:

Number of chains: 1

Chain No. 1: 60Co Nuclides in chain: 1

Initial Concentrations:Note: All reported values are the upper bound of the symmetric 95% confidence interval for the 0.9 quantile value

Model Parameters:

General Parameters:

NuclideArea of

Contamination (m2)Distribution

60Co UNLIMITED CONSTANT(dpm/100 cm**2)

Justification for concentration: DSV Determination Value 1.00E+00

NuclideChain

PositionHalf Life

First Parent

Fractional Yield

Second Parent

Fractional Yield

Ingestion CEDE Factor (Sv/Bq)

Inhalation CEDE Factor (Sv/Bq)

Surface Dose Rate

Factor

((Sv/d)/(Bq/m2))

15 cm Dose Rate

Factor

((Sv/d)/(Bq/m3))

60Co 1 1.93E+03 7.28E-09 5.91E-08 2.03E-10 6.26E-12

NuclideSurface Concentration

(dpm/100 cm**2)

60Co 1.00E+00


Building 140 Cyclotron Vault Final Status Survey Report

Page C.1 of C.12

Parameter Name Description Distribution

To:Time In BuildingThe time in the building during the occupancy period

CONSTANT(hr/week)

Default value used Value 4.50E+01

Tto:Occupancy PeriodThe duration of the occupancy exposure period

CONSTANT(days)


Vo:Breathing RateThe average volumetric breathing rate during building occupancy for an 8-hour work day

CONSTANT(m**3/hr)


RFo*:Resuspension Factor

Effective resuspension factor during the occupancy period = RFo * Fl

DERIVED(1/m)

Default value used

GO*:Ingestion Rate

Effective secondary ingestion transfer rate of removable surface activity from building surfaces to the mouth during building occupancy = GO * Fl

DERIVED(m**2/hr)

Default value used

Tstart:Start Time The start time of the scenario in days CONSTANT(days)


Tend:End Time The ending time of the scenario in days CONSTANT(days)


dt:Time Step Size The time step size CONSTANT(days)


Pstep:Print Step SizeThe time steps for the history file. Doses will be written to the history file every n time steps

CONSTANT(none)


AOExt:External Exposure Area

Minimum surface area to which occupant is exposed via external radiation during occupancy period

CONSTANT(m**2)


AOInh:Inhalation Exposure Area

Minimum surface area to which occupant is exposed via inhalation during occupancy period

CONSTANT(m**2)


AOIng:Secondary Ingestion Exposure Area

Minimum surface area to which occupant is exposed via secondary ingestion during occupancy period

CONSTANT(m**2)


AO:Exposure AreaMinimum surface area to which occupant is exposed during the occupancy period

DERIVED(m**2)

Default value used

Fl:Loose FractionFraction of surface contamination available for resuspension and ingestion

CONSTANT(none)

Default value used Value 1.00E-01

Rfo:Loose Resuspension Factor

Resuspension factor for loose contamination CONTINUOUS LOGARITHMIC(1/m)

Default value used Value Probability

9.12E-06 0.00E+00

1.10E-04 7.67E-01

1.46E-04 9.09E-01

1.62E-04 9.50E-01

1.85E-04 9.90E-01

1.90E-04 1.00E+00

GO:Loose Ingestion The secondary ingestion transfer rate of loose removable surface activity from

Rate building surfaces to the mouth during building occupancy

Default value used

CONSTANT(m**2/hr)

Value 1.10E-04



Page C.2 of C.12

Correlation Coefficients:

None

Summary Results:

90.00% of the 100 calculated TEDE values are < 3.55E-03 mrem/year . The 95 % Confidence Interval for the 0.9 quantile value of TEDE is 3.50E-03 to 3.61E-03 mrem/year

Detailed Results:Note: All reported values are the upper bound of the symmetric 95% confidence interval for the 0.9 quantile value

Concentration at Time of Peak Dose:

Pathway Dose from All Nuclides (mrem)

Radionuclide Dose through All Active Pathways (mrem)

Dose from Each Nuclide through Each Active Pathway (mrem)


(dpm/100 cm**2)

60Co 9.37E-01

All Pathways Dose

External InhalationSecondary Ingestion

3.61E-03 3.09E-03 4.87E-04 2.93E-05

NuclideAll Pathways

Dose

60Co 3.61E-03

All Nuclides 3.61E-03

Nuclide External InhalationSecondary Ingestion

60Co 3.09E-03 4.87E-04 2.93E-05



Page C.3 of C.12


DandD Version: 2.1.0 Run Date/Time: 8/27/2007 11:10:30 AM Site Name: N/A Description: DSV Determination FileName:C:\Documents and Settings\Dave Culp\My Documents\Eu-152 DSV.mcd

Options:



Initial Activities:

Chain Data:

Number of chains: 1

Chain No. 1: 152Eu Nuclides in chain: 2


Model Parameters:

NuclideArea of


152Eu UNLIMITED CONSTANT(dpm/100 cm**2)


NuclideChain

PositionHalf Life

First Parent

Fractional Yield

Second Parent

Fractional Yield



Surface Dose Rate

Factor

((Sv/d)/(Bq/m2))

15 cm Dose Rate

Factor

((Sv/d)/(Bq/m3))

152Eu 1 4.87E+03 1.75E-09 5.97E-08 9.53E-11 2.78E-12

152Gd 2 3.94E+16 1 0.2792 4.34E-08 1.01E-06 0.00E+00 0.00E+00


(dpm/100 cm**2)

152Eu 1.00E+00

152Gd 0.00E+00



Page C.4 of C.12

General Parameters:



CONSTANT(hr/week)



CONSTANT(days)



CONSTANT(m**3/hr)




DERIVED(1/m)

Default value used

GO*:Ingestion Rate


DERIVED(m**2/hr)

Default value used








CONSTANT(none)




CONSTANT(m**2)




CONSTANT(m**2)




CONSTANT(m**2)



DERIVED(m**2)

Default value used


CONSTANT(none)





9.12E-06 0.00E+00

1.10E-04 7.67E-01

1.46E-04 9.09E-01

1.62E-04 9.50E-01

1.85E-04 9.90E-01

1.90E-04 1.00E+00



Page C.5 of C.12


None

Summary Results:







GO:Loose Ingestion Rate

The secondary ingestion transfer rate of loose removable surface activity from building surfaces to the mouth during building occupancy

CONSTANT(m**2/hr)



(dpm/100 cm**2)

152Eu 9.74E-01

152Gd 8.82E-16

All Pathways Dose


2.03E-03 1.51E-03 5.12E-04 7.32E-06

NuclideAll Pathways

Dose

152Eu 2.03E-03

152Gd 8.00E-18



152Eu 1.51E-03 5.12E-04 7.32E-06

152Gd 0.00E+00 7.84E-18 1.64E-19



Page C.6 of C.12


DandD Version: 2.1.0 Run Date/Time: 8/27/2007 11:14:10 AM Site Name: N/A Description: DSV Determination FileName:C:\Documents and Settings\Dave Culp\My Documents\Eu-154 DSV.mcd

Options:



Initial Activities:

Chain Data:

Number of chains: 1

Chain No. 1: 154Eu Nuclides in chain: 1


Model Parameters:

General Parameters:

NuclideArea of


154Eu UNLIMITED CONSTANT(dpm/100 cm**2)


NuclideChain

PositionHalf Life

First Parent

Fractional Yield

Second Parent

Fractional Yield



Surface Dose Rate

Factor

((Sv/d)/(Bq/m2))

15 cm Dose Rate

Factor

((Sv/d)/(Bq/m3))

154Eu 1 3.21E+03 2.58E-09 7.73E-08 1.02E-10 3.04E-12


(dpm/100 cm**2)

154Eu 1.00E+00



Page C.7 of C.12



CONSTANT(hr/week)



CONSTANT(days)



CONSTANT(m**3/hr)




DERIVED(1/m)

Default value used

GO*:Ingestion Rate


DERIVED(m**2/hr)

Default value used








CONSTANT(none)




CONSTANT(m**2)




CONSTANT(m**2)




CONSTANT(m**2)



DERIVED(m**2)

Default value used


CONSTANT(none)





9.12E-06 0.00E+00

1.10E-04 7.67E-01

1.46E-04 9.09E-01

1.62E-04 9.50E-01

1.85E-04 9.90E-01

1.90E-04 1.00E+00



Default value used

CONSTANT(m**2/hr)

Value 1.10E-04



Page C.8 of C.12


None

Summary Results:








(dpm/100 cm**2)

154Eu 9.62E-01

All Pathways Dose


2.26E-03 1.59E-03 6.54E-04 1.06E-05

NuclideAll Pathways

Dose

154Eu 2.26E-03



154Eu 1.59E-03 6.54E-04 1.06E-05



Page C.9 of C.12


DandD Version: 2.1.0 Run Date/Time: 8/27/2007 11:27:05 AM Site Name: N/A Description: DSV Determination FileName:C:\Documents and Settings\Dave Culp\My Documents\Na-22 DSV.mcd

Options:



Initial Activities:

Chain Data:

Number of chains: 1

Chain No. 1: 22Na Nuclides in chain: 1


Model Parameters:

General Parameters:

NuclideArea of


22Na UNLIMITED CONSTANT(dpm/100 cm**2)


NuclideChain

PositionHalf Life

First Parent

Fractional Yield

Second Parent

Fractional Yield



Surface Dose Rate

Factor

((Sv/d)/(Bq/m2))

15 cm Dose Rate

Factor

((Sv/d)/(Bq/m3))

22Na 1 9.50E+02 3.10E-09 2.07E-09 1.82E-10 5.45E-12


(dpm/100 cm**2)

22Na 1.00E+00



Page C.10 of C.12



CONSTANT(hr/week)



CONSTANT(days)



CONSTANT(m**3/hr)




DERIVED(1/m)

Default value used

GO*:Ingestion Rate


DERIVED(m**2/hr)

Default value used








CONSTANT(none)




CONSTANT(m**2)




CONSTANT(m**2)




CONSTANT(m**2)



DERIVED(m**2)

Default value used


CONSTANT(none)





9.12E-06 0.00E+00

1.10E-04 7.67E-01

1.46E-04 9.09E-01

1.62E-04 9.50E-01

1.85E-04 9.90E-01

1.90E-04 1.00E+00



Default value used

CONSTANT(m**2/hr)

Value 1.10E-04



Page C.11 of C.12


None

Summary Results:








(dpm/100 cm**2)

22Na 8.78E-01

All Pathways Dose


2.62E-03 2.60E-03 1.60E-05 1.17E-05

NuclideAll Pathways

Dose

22Na 2.62E-03



22Na 2.60E-03 1.60E-05 1.17E-05



Page C.12 of C.12

Safety and Ecology Corporation 2800 Solway Road, Knoxville, TN 37931

SEC PROCEDURE # SEC-IS-422 Rev 2

Calibration Certificate

Calibration Certificate for 2241,Serial # 215484, Bar Code# ,Property# Chase133

Date: 02102117 Date Last Cal. Expires: 10/20117 Technician: Carl Hall

Location: 999999. Reason For Calibration: Short Cycled

MODEL: 500-2

MODEL:

EQUIPMENT USED DURING CALIBRATION

SERIAL#: 132896

SERIAL#:

CAL. DUE: 06120117

CAL DUE:

AS FOUND DATA

High Voltage

(+/- 10% tolerance)

500 V:

1000 V:

1500 V:

AS FOUND Instrument Condition: SAT AS LEFT Instrument Condition: SAT

_\ New Batteries?

Battery Check: SAT

AS FOUND AS LEFT

High Voltage High Voltage AS FOUND HV Setting: 950 v AS LEFT HV Setting:

NIA NIA

NIA NIA AS FOUND THRESHOLD: 10 mV AS LEFT THRESHOLD:

NIA NIA

REPRODUCIBILITY x.1 or x1 Scale:

x1 or x10 Scale:

x10 or x100 Scale:

x100 or x1000 Scale:

N/A

NIA

N/A K

NIA K

NIA

NIA

NIA K

NIA K

NIA

NIA

NIA K

NIA K

;~ Are the Individual Counts Within 10% of the Average?

'" Fast I Slow Response Switch Functions Properly?

DIGITAL SCALER AF 250:

AF 2500:

AF 25K:

AF 250K:

Push Buttons: SAT

Comments: Married as a set with:

Audio Response: SAT

250 % ERR: 0.00% AL250: AF % ERR: 0.00%

2500 % ERR: 0.00% AL 2500: AF % ERR: 0.00%

25 K % ERR: 0.00% AL25K: AF K %ERR: 0.00%

250 K % ERR: 0.00% AL 250K: AF K %ERR: 0.00%

'V Is the As Found Data Within 20% of the Set Point?

Lamp: SAT Audio/Divide: SAT

Model: 44-10 Serial#: PR360145

V Does Instrument Meet Final Acceptance Criteria?

'~- Calibration Sticker Attached?

Bar Code#:

Page 1 of 1

21212017

950 v

10 mV



Page D.1 of D.22

Safety and Ecology Corporation SEC PROCEDURE# SEC-IS-415 Rev 3

2800 Solway Road, Knoxville, TN 37931


Calibration Certificate for 44-10,Serial # PR360145, Bar Code# ,Property# Chase168

Date: 02/02/17

Location: 999999,

Date Last Cal. Expires: 10/20/17 Technician: Carl Hall

Reason For Calibration: Short Cycled

MODEL: 2241

MODEL:


SERIAL#: 215484 CAL DUE: 02/02/18

SERIAL#: CAL DUE:

NIST TRACEABLE SOURCES USED

Page 1.of 1

21212017

SOURCE ISOTOPE ACTIVITY 2TT ASSAY DATE

99CS250-0288

Efficiency from Last Calibration: 0.70 %

AS FOUND DATA

AS FOUND Instrument Condition: SAT

HV: 950 V

Center: 100458

Background: 3316

4 TT Probe Efficiency: Cs-137 0.723

Cs-137 6.0658 uCi 1/3/2017

HV From Last Calibration: 950 V Calibration Threshold: 10 mV

1 MINUTE COUNTS (CPM) AS LEFT DATA after repair of HV adjust

AS LEFT Instrument Condition: SAT

HV: 950 V

Center: 100458

Background: 3316

4 TT Probe Efficiency: Cs-137 .0.72o/o.

"AF" in the AL Efficiency fields means to refer to the AF Efficiencies in the AS FOUND DATA Section

-~ Is the As Found Efficiency Within 20% of the efficiency from the last cal.? - ~

Reproducibility: lsotope:Cs-137 100365 10037 4 100481 Average: 100407 ~' Are the individual counts within 10% of the average?

~ Jf Asf oond efficiency (even ;;fter repair}~ \\•ah in 10% of i~ fust caiibnin'l>li~nd unifOlll)ity is <10%. the technicialimay NIA the Plateau riata and proceedtG c~!S. -Gepmetry .;, Na I ~~~re 4 1/2" ~sQWl:e, .Ali~ prob~ll«'in contact with surfaceUQ)Gs$ O{llerwise S!)e<:ified, .. . . . .

PLATEAU AND SET POINT DATA {CPMl High Voltage Source Response Background

N/A

Comments: Married as a set with: Model: 2241

Calibrated to a 15' cable.

v CENTER Background 4 TT Efficiency

Cs-137

Serial#: 215484 Bar Code#:

-~ Does Instrument Meet Final Acceptance Criteria? ~ Calibration Sticker Attached?

~:"rument is Due For ~ext Cali

7br~ 02/02/I~.

Performed by: __ ~ __ ;;.,,. ...... ==~=-.,,c.=------- Reviewed by:~ -Printed Name: Carl Hall

Date:,.:?-..Z-/?

llHllHllHll!I



Page D.2 of D.22

SEC INSTRUMENTATION SERVICES 10512 Lexington Drive Suite 200 Knoxville, TN 37932

SEC Corporate 2800 Solway Road Knoxville, TN 37931

Model 2241-3 CALIBRATION FORM Serial number : 267138 Customer Name : Chase

Previous due date : 6/5/2016 P.O Number: Date: 5/4/2016 Technician : Carl Hall

Reason For Calibration : Probe needed repair

INSTRUMENT(S) USED DURING CALIBRATION Model Number: 500-2 I Serial Number: 132896 I Calibration Due date:

Model Number: I Serial Number: I Calibration Due date:

Instrument Condition Threshold Battery Indicator

As Found I As Left As Found I As Left SAT

OK I OK 4.0 I 4.0

SCA/RATE Switch

Set Voltage High Voltage Range SAT

Detector# As Found As Left As Found As Left

1 1674 1675 SAT SAT

2 1798 1800 SAT SAT

3 1225 1250 SAT SAT Reproducability 4 1275 1275 SAT SAT x.1 or x1 Scale

250 I 250 I Digital Scaler x1 or x10 Scale

Target As Found %Error As Left o/oError 2500 I 2500 I

6/15/2016

250

2500 250 250 O.OOo/o 250 0.00% x10 or x100 Scale

2,500 2,501 0.04o/o 2,501 0.04o/o 25,000 25,013. 0.05°/o 25,013 0.05o/o 250,000 250,130 0.05% 250, 130 0.05o/o

OK Is the As Found Data within 20o/o of the set point? OK Are the individual counts within 10% of the average? OK Fast I Slow response switch functions properly? OK Does Instrument meet final Acceptance Criteria? OK Calibration sticker attached?

Married with:

Comments:

1675V 1800V 1250V 1275V

Instrument calibrated per SEC-IS-423.

5 foot cable used for the 43-68

DET 1 DET2 DET3 DET4

Model: Model: Model: Model:

43-68 43-37 43-68 43-37

25K I 25K I 25K x100 or x1000 Scale

250K I 250K I 250K

OK Audio Response OK Push Buttons OK RESET OK Audio Switch OK Light

Serial Number: Serial Number: Serial Number: Serial Number:

PR285699 PR286832 PR285699 PR286832



Page D.3 of D.22

Safety and Ecology Corporation sEc PROCEDURE #


SEC·IS-417 Rev 4


Page 1 of 1

51412016

Calibration Certificate for 43-68,Serial # PR285699, Bar Code# ,Property# Chase79 Date: 05/04/16

Location: 102624,


Reason For Calibration: Due and Repair

EQUIPMENT USED DURING CALIBRATION MODEL: 2241-3 SERIAL#: 267138 CAL DUE 05/04/17


Efficiencies from last calibration

Pu-239: 23.31 o/o Tc-99: 27.77 o/o

Th-230: 22.37 o/o

SrY-90: 41.06 o/o

SOURCE

5744-06

5746-06

5747-06

5748-06

AS FOUND DATA AS FOUND Instrument Condition: SAT Calibration Setpoints

HV (Alpha): 1225 v HV (Beta): 1675 v Threshold:

ISOTOPE

Sr-90

Tc-99

Pu-239

Th-230

ACTIVITY 2rr ASSAY DATE

16834 dpm 11,811 cpm 1/1/2016

31900 dpm 20,000 cpm 1/1/2016

25798 dpm 13,099 cpm 1/1/2016

34899 dpm 17,700 cpm 1/1/2016


AS LEFT DATA after repair, HV adjust or Plateau

4mV HV (Alpha): 1250 V HV (Beta): 1675 v Threshold: 4 mV

Back Alpha Beta AF 4 nEfficiencies Back A!nlli! Beta AL 4 TT Efficiencies

ground: 0 CPM

Pu-239: 4596 CPM

Tc-99: N/A

Th-230: 5788 CPM

SrY-90: N/A

~ Is the As Found Data within 20°/o of the efficiency from the last cal.?

187

N/A 8077

N/A 5869

CPM

CPM

CPM

ground: 0 CPM 187 CPM

Pu-239: 5132 CPM N/A Tc-99: N/A 8077 CPM

Th-230: 6203 CPM N/A

SrY-90: N/A 5869 CPM


Reproducibility: Isotope: ~ 5888 5842 5857 Average: 5862.3 ~ Are the individual counts within 10% of the average?

-

Alpha Source: Th-230

Response Background

HV CPM CPM

Ach. A ch. Net 4rr Elf.

N/A r --

I --

I --

l I -

2 Pi Efficiencies:

-------

PLATEAU DATA Beta Source: Tc~99

Response Background

HV CPM CPM

B ch. B ch. Net 4rr Elf. -

N/A j

-1 -

-

I -

__ I ____

Comments: Married as a set with: Model: 2241-3 Serial #: 267138 Bar Code#:

Calibrated with plastic spacers attached. DET 1 111675V, DET 3 a 1250V. Replaced damaged mylar and broken string. Increased high voltage due to improve efficiencies.

~ Does Instrument Meet Final Acceptance Criteria? ~ Calibration Sticker Attached?

Date Instrument is Due For Next Calibration:

Performed by:_~Z9~---~----~-=-~------ ~ s--'f-/t Reviewed by: ___________ Date: __ _

Printed Name: Carl Hall 11m 1m 11111111J 1H[J 1m11



Page D.4 of D.22

Safety and Ecology Corporation sEc PROCEDURE#


SEC-IS-417 Rev 4

Page 1 of 1

51412016 Calibration Certificate

Calibration Certificate for 43-37,Serial # PR286832, Bar Code #,Property# Chase101 Date: 05/04/16

Location: 999999,


Reason For Calibration: Due and Repair ·---




Pu-239:

Tc-99:

Th-230:

20.01 %

24.49 o/o 18.02 %

SrY-90: 39.42 %

SOURCE

5744-06

5746-06

5747-06

5748-06


ISOTOPE

Sr-90

Tc-99

Pu-239

Th-230

----


16834 dpm 11,811 cpm 1/1/2016

31900 dpm 20,000 cpm 1/1/2016

25798 dpm 13,099 cpm 1/1/2016

34899 dpm 17,700 cpm 1/1/2016


AS LEFT DATA after repair. HV adjust or Plateau

HV (Alpha): 1275 v HV (Beta): 1800V Threshold: 4mV HV (Alpha): 1275 V HV (Beta): 1800 v Threshold: 4mV

Alpha Beta AF 4 rrEfficiencies Back Alpha Beta AL 4 TT Efficiencies Back ground: 6 CPM

Pu-239: 4011 CPM

Tc-99: N/A

Th-230: 5128 CPM

SrY-90: N/A

[] Is the As Found Data within 20% of the efficiency from the last cal.?

512 CPM

N/A 6815 CPM

N/A 5944 CPM

Reproducibility: Isotope: [sr-9o ) 6340 6418 6375 Average:

ground: 8 CPM 704 CPM Pu-239: 4996 CPM N/A

Tc-99: N/A 8129 CPM Th-230: 6016 CPM N/A

SrY-90: N/A 6393 CPM


6377.7 ~ Are the individual counts within 10o/o of the average?


Response Background PLATEAU DATA Beta Source: Tc-99

Response Background

HV CPM CPM

lfilDhlll N/A

A ch. A ch. Net 4rr Elf.

=+= =r-·_ -~ Pu-239

2 Pi Efficiencies: ~~]}:;~§:~,~%'

Comments: Married as a set with: Model: 2241-3

HV CPM CPM

(Beta) B ch. B ch. Net 4rr Elf.

------+-"' =~~ --+---[ ±-

Th-230 SrY-90

~~t~1%~ IK~~t:l:'Z%%~ --- -----


Calibrated with plastic spacers attached. DET 2111800V, DET 4 a 1275V. Replaced damaged mylar.



Performed by:_~&=-""'-~-·-·==--~SL.-- Reviewed by: ___ ~ _______ Date: <; ''-{-(~ Prlnted Name: Carl Hall llfllll~ll![Jllillllllllil



Page D.5 of D.22

SEC INSTRUMENTATION SERVICES 10512 Lexington Drive

Suite 200 Knoxville, TN 37932

C-14 SOURCE CALIBRATION FORM Probe Model Number : 43-68 Customer Name : Chase Environmental

Probe Serial Number : PR285699 Technician : Carl Hall --------Date of Calibration : 5/4/2016

Instruments used during calibration Model Number: 2241-3 Serial Number: 26.7138 Calibration Due Date: I Model Number: Serial Number: Calibration Due Date: I

NIST Traceable Sourcei-'('""s.._) "'us.::.e::cd::....:..,: ----~~~..,.A"'"c'""'ti"'v"'ity'+"s)'----~---~---~ Source S/N Emission Rate 2 Pi cpm) uCi 4Pi dpm) Assay Date

1> C-14 DX 295 432 25,920 0.0305405 67,800 5/3/1994

Instrument condition : Sat -----High Voltage: __ 1-'-67-'5 __

Background: ---'-18"-7'---

C-14 Count: 8243 -----

2rr Efficiency: 31.0.8% ----~

4rr Efficiency: 11.88% '-----~

Calibration sticker attached? Yes ---'-"-'----

Comments: Married as a set with : Model: 2241-3 Serial # : Calibrated with plastic standoffs attached.

~e instrument is due for next calibratio.n ·~: ::::::;2:::::::~~~~ Performed by: ~ ? ~ Reviewed by:_ . Date: Printed Name : Carl Hall

Entered in computer inventory by: __________ Date :

5/4/2017

267138



Page D.6 of D.22



C-14 SOURCE CALIBRATION FORM Probe Model Number: 43-37

---'-.:....:-'---- Customer Name : Chase Environmental

Probe Serial Number : PR286832 Technician : Carl Hall -------~

Date of Calibration · 5/4/2016 Instruments used during calibration

Model Number: 2241-3 Serial Number: 267138 Calibration Due Date:I 5/4/2017 Model Number: Serial Number: . Calibration Due Date:!

NIST Traceable Sources used : Activity(s) ;:.>.::L..::.::..::.;::....:.., _______ ...:..;;:..::..:.=.+=.I.----~---~---~ Source S/N Emission Rate 2 Pi ( cpm uCi 4Pi dpm

1 > C-14 DX 295 432 25,920 0.0305405 67,800

Instrument condition : __ .:::S.:::at:___ High Voltage: ---'1"'8"'0.::.0 __

Background: __ .:...70:...4:___

C-14 Count: _ _.:9:.:3:.:.7.::.9 __

2rr Efficiency:'-. _3::..3.:...·c.:4..:..7..:..%=-..; 4 rr E ffic ie n cy: --'1~2_,-'7-'-!1""%'--'

Calibration sticker attached? Yes __ .:..=.;:..__

Assay Date

5/3/1994

Comments : Married as a set with : Model: 2241-3 Serial # : Calibrated with plastic standoffs attached.

c;,: .. Date instrurr1ent is due for next calibration : I 5/4/2017 I Performed by : ~ ( ~ Reviewed by:--=-"=::::.. ___ Date : Printed Name : Carl Hall 7

Entered in computer inventory by:---------Date:

267138



Page D.7 of D.22




Previous due date: 5/4/2017 P.O Number: Date: 8/24/2016 Technician : Carl Hall

Reason For Calibration : Short Cycled

INSTRUMENT(S) USED DURING CALIBRATION Model Number: 500·2 I Serial Number: 132896 I Calibration Due date:




OK I OK 4.1 I 4.0

SCA/RATE Switch



1 1616 1675 SAT SAT

2 1691 1800 SAT SAT

6/20/2017

3 1214 1275 SAT SAT Reproducability 4 1316 1350 SAT SAT

Digital Scaler Target As Found %Error As Left %Error

250 250 0.00% 250 O.OOo/o 2,500 2,500 0.00% 2,500 O.OOo/o

25,000 25,008 0.03% 25,008 0.03°/o 250,000 250,081 0.03o/o 250,081 0.03%

OK Is the As Found Data within 20% of the set point? OK Are the individual counts within 10%) of the average? OK Fast I Slow response switch functions properly? OK Does Instrument meet final Acceptance Criteria? OK Calibration sticker attached?

Married with:

Comments:

1675V 1800V 1275V 1350V

Instrument calibrated per SEC-IS-423.




43-68 43-37 43-68 43-37

x.1 or x1 Scale

250 I 250 I 250

x1 or x10 Scale

2500 I 2500 I 2500 x10 or x100 Scale

25K I 25K I 25K x100 or x1000 Scale

250K I 250K I 250K

OK Audio Response OK Push Buttons OK RESET

OK Audio Switch OK Light

Serial Number: Serial Number: Serial Number: Serial Number:

PR216394 PR178300 PR216394 PR178300



Page D.8 of D.22

Safety and Ecology Corporation SEC PROCEDURE#


SEC-IS-417 Rev 4



Location: 999999, ----------



EQUIPMENT USED DURING CALIBRATION MODEL: 2241-3 SERIAL#: 253351 CAL DUE ----

NIST TRACEABLE SOURCES USED SOURCE ISOTOPE ACTIVITY 2rr

Page 1 of 1

812412016

08/24/17

ASSAY DATE ---

Efficiencies from last calibration 5744-06 Sr-90 16834 dpm 11,811 cpm 1/1/2016

Pu-239: 22.09% 5746-06 Tc-99 31900 dpm 20,000 cpm 1/1/2016

Tc-99: 25.21 % 5747-06 Pu-239 25798 dpm 13,099 cpm 1/1/2016

Th-230: 20.29 Ofo 5748-06 Th-230 34899 dpm 17,700 cpm 1/1/2016

SrY-90: 34.54 Ofo


HV (Alpha): 1275 v HV (Beta): 1675 v Threshold: 4mV



HV (Alpha): 1275 v HV (Beta): 1675 v Threshold: 4mV

Back Alpha Beta AF 4 TTEfficiencies Back Afolli! Beta AL 4 TI Efficiencies

ground: 1 CPM

Pu-239: 4944 CPM

Tc-99: N/A

Th-230: 5770 CPM

SrY-90: N/A

[~ Is the As Found Data within 20o/o of the efficiency from the last cal.?

191 CPM

N/A i ~,. 1-9: 1:~0;.;;1 ·--<~·-,....,-~

7661 CPM I:, 23;42°/o_"" -1 ~-7···-cY·";-·~~

N/A [:-_.19.53o/o' l f;-,.,>·;---,..~

5748 CPM ::: :3a:o.~ 0!o l

Reproducibility: Isotope: -~~r-90 . 5769 5742 5723 Average:

ground: CPM 191 CPM Pu-239: 4944 CPM N/A ;- :~9-'.,t69fo]

Tc-99: N/A 7661 CPM /23,4?%1 Th-230: 5770 CPM N/A :_1_~:~-~o/0:·:1

SrY-90: N/A 5748 CPM .::·33;'(f1 % j


5744.7 ~ Are the individual counts within 10% of the average?

jJf .. ii1~·~-S:_FO\iri'd ·data· (Ei~~·n:·~~~-~ i:ePaJ~j iS-:WUii~_- 10%-0f'ih6:1~~t"Ca·11b;ai1ciO>ih6rlthe :_t6_i:~_Oi~ikf{rii~)i''N/A J:i1~1~~~-·Qa1~.:~·n_d :ij_c>.diiSCifi-.lp'.CO'rlillfGil_i~: ;-:(i~_OID:eiiX.· of_ S'O~;:ce:-;·_fiJ~friO:~'lJ_-~_c,~·. :.~x4ap,---1gas_proportto11a1 p_robes "'-,1/6"_.frof(I (!'Urface_unlfi!ss_olf}efl.-visa· specifi_ed. • · · · · · · · · ·


Response Background

HV CPM CPM

(Alpha)

N/A

A ch. A ch. Net 4rr Elf. -~---

PLATEAU DATA Beta Source: Tc-99 Response Background

HV CPM CPM

~ N/A

B ch. B ch. Net 4rr Elf.

L---

-~

Pu-239

2 Pi Efficiencies: [:'37:743·;

i ---,

--1 J

_Tc-99 37;353

Th-230

:fa.59% i SrY-90

[47·:~~%_:·! ----

Comments: Married as a set with: Model: 2241-3 Serial#: 253351 Bar Code#:

DET 1 11=1675V, DET 3 a= 1275V. Calibrated with plastic spacers attached.


Performed by:

Printed Name:

Date Instrument is Due For Next Calibration: i08/i4j1'ic·~---.

Carl Hall

Reviewed by:~ ~

Date: f-·)__~/-/~

Ill lilm lllllll I lllll!I 11111111

I



Page D.9 of D.22



C-14 SOURCE CALIBRATION FORM Probe Model Number: 43-68 Customer Name : Chase Environmental -----Probe Serial Number: PR216394

Date of Calibration : 8/24/2016 Technician: Carl Hall ----"""'--"=----

Instruments used during calibration Model Number: 2241-3 Serial Number: 253351 Calibration Due Date: I 8/24/2017

Model Number: Serial Number: Calibration Due Date: I

NIST Traceable Source(s) used : Activity(s) .-'--~-----------__._.~-------~---~

Source S/N Emission Rate 2 Pi cpm) uCi 4Pi (dpm) Assay Date

1> C-14 DX 295 432 25,920 0.0305405 67,800 5/3/1994

Data Instrument condition : Sat

----,=,,--High Voltage: 1675 -----

Background: 191 -----

C-14 Count: 7906 -----

2rr Efficiency: 29.76% -----4IT Efficiency: 11.38% -----

Calibration sticker attached? Yes -----

Comments : Married as a set with : Model: 2241-3 Serial # : 253351 Calibrated with plastic standoffs attached.

~F~in ent is due for nex_t calibration: Performed by:-~~~....,.~--'---- Reviewed by;_:,;;...~::::.._ _____ Date: Printed Name : Carl Hal

8/24/2017 It-)_•/-/(,.




Page D.10 of D.22



SEC-IS-417 Rev 4



Location: 999999,



EQUIPMENT USED DURING CALIBRATION MODEL: 2241-3 SERIAL#: 253351



Pu-239: 18.88 o/o

Tc-99: 22.31 o/o Th-230: 17.19 o/o

SrY-90: 30,62 %

SOURCE.

5744-06

5746-06

5747-06

5748-06

ISOTOPE

Sr-90

Tc-99

Pu-239

Th-230

ACTIVITY

16834 dpm

31900 dpm

25798 dpm

34899 dpm

CAL DUE

2rr

11,811 cpm

20,000 cpm

13,099 cpm

17,700 cpm

Page 1 of 1

8/2412016

08/24/17

ASSAY DATE

1/1/2016

1/1/2016

1/1/2016

1/1/2016




HV (Alpha): 1350 v HV (Beta): 1800 v Threshold: 4mV HV (Alpha): 1350 v HV (Beta): 1800 v Threshold: 4mV

Alpha Beta AF 4 rrEfficiencies Back Alpha Beta AL 4 rr Efficiencies Back ground: 3 CPM

Pu-239: 4503 CPM

Tc-99: N/A

Th-230: 5590 CPM

SrY-90: N/A

~ Is the As Found Data within 20% of the efficiency from the last cal.?

850 CPM i ::1'1,4.4.010.· :i N/A •... ~;+, •• J

7643 CPM L-:~1_-:~-~~---1 N/A ;·: __ .-1_f)~Q.1_%:._:i

5603 CPM i -28~23%·---_ l ~

Reproducibility: Isotope: ~~ 5621 5582 5611 Average:

ground: 3 CPM 850 CPM Pu-239: 4503 CPM N/A

"·:·-""-"'''' _---]

t!:~44o/o J Tc-99: N/A 7643 CPM : :-2_1 ;2e%~l

Th-230: 5590 CPM N/A · 11;.01% i SrY-90: N/A 5603 CPM 2a:23%·i


5604.7 ~ Are the individual counts within 10o/o of the average?

fif'ih0: AiF_o~:n~f ~i_a -(~~-~n- arterrepaJrj-i_S-WithYO :10% Of "lli-~)aSf :c_iiiib-ia·11ru;;:th·;~- ihe"'i·e~ti_Oi"Ci~ri; rl~Y:"f·i?A:Pl~ie~u--O~ia ·an:d -90\1i_~SCiiY-tO.-c-o_m-;ne_Oi~.:::_GeometrY-~i(SOU-rc_e;;;;·fi_U-sh ~:~~-{ta,~;- -e~cepi··: 1g"a$-prt;Jportfonal_ Probes·:: 118-JfQm surface unless otherwtsi;i specified. • ·• · · ·


Response Background PLATEAU DATA Beta Source: Tc-99

Response Background

HV

ffi!J1!IBl N/A

CPM CPM

A ch. A ch. Net 4TT Eff.

2 Pi Efficiencies: Pu·23_!l__

: 34.35o/o 0 '··---·

Tc-99 -----.. ----, 33.97%


Th-230

~1.-56% !

Serial#: 253351

HV

N/A

CPM CPM

B ch. B ch. Net 4rr Eff.

Bar Code#:

DET 2 r.. = 1800V, DET 4 a= 1350V. Calibrated with plastic spacers attached.


Date Instrument is Due For Next Calibration: .08/24/17

Carl Hall

. ~~- y-2~-/{,, Reviewed by: ~Date:

7 1111-im1111~-111~1m1111111111111m <~ Performed by: &~

Printed Name:



Page D.11 of D.22



C-14 SOURCE CALIBRATION FORM Probe Model Number : 43-37 -----Probe Serial Number : PR178300

Date of Calibration : 8/24/2016

Customer Name : Chase Environmental

Technician : Carl Hall ------=--~

Instruments used during calibration Model Number: 2241-3 Serial Number: 253351 Calibration Due Date: I 8/24/2017


NIST Traceable Source(s) used : Activity(s) r-'-~------~------"-+~-------:-~---~

Source S/N Emission Rate 2 Pi ( cpm) uCi 4Pi ( dpm) Assay Date

1>C-14 DX295 432 25,920 0.0305405 67,800 5/3/1994

Instrument condition : Sat -----c==----H i g h Voltage: 1800 -----Background: 850 -----C-14 Count: 8369. -----

2rr Efficiency: 29.01% ---,--,...,...,-4 rr Efficiency: 11.09% -----



~le instrument is due for next calibration : Performed by: ~~ Reviewed by: -"":;;;<'~:'.:::====~Date : Printed Name : ---t-~c"°a-r~I ~H""a"'11 "--t"""

8/24/2017 J· l "/ -/t;,.




Page D.12 of D.22




Previous due date: 6/8/2016 P.0 Number: Date : 8/24/2016 Technician : Carl Hall

Reason For Calibration : Short Cycled

INSTRUMENT(S) USED DURING CALIBRATION

Model Number: 500-2 I Serial Number: 132896 I Calibration Due date:




OK I OK 4.0 I 4.0

SCA/RATE Switch



1 1704 1700 SAT SAT

2 1779 1775 SAT SAT·

6/20/2017

3 1129 1125 SAT SAT Reproducability

4 1277 1275 SAT SAT

Digital Scaler Target As Found %Error As Left %Error

250 250 0.00% 250 0.00% 2,500 2,500 0.00% 2,500 0.00%1

25,000 25,010 0.04% 25,010 0.04%1 250,000 250, 101 0.04% 250, 101 0.04°/o

OK Is the As Found Data within 20% of the set point?

OK Are the individual counts within 10% of the average?

OK Fast I Slow response switch functions properly?

OK Does Instrument meet final Acceptance Criteria?

OK Calibration sticker attached?

Married with: 1700V 1775V 1125V

Comments: 1275V Instrument calibrated per SEC-IS-423.




Date instrument is du


x.1 or x1 Scale

250 I 250 I 250

x1 or x10 Scale

2500 I 2500 I 2500

x1 O or x100 Scale 25K I 25K I 25K

x100 or x1000 Scale

250K I 250K I 250K

OK Audio Response

OK Push Buttons OK RESET

OK Audio Switch

OK Light

43-68 Serial Number: PR190903 43-37 Serial Number: PR265548 43-68 Serial Number: PR190903 43-37 Serial Number: PR265548



Page D.13 of D.22



SEC-IS-417 Rev 4

Page 1 of 1

812412016 Calibration Certificate

Calibration Certificate for 43-68,Serial # PR190903, Bar Code# ,Property# Chase48 Date: 08124116

Location: 999999,


Reason For Calibration: Repair

EQUIPMENT USED DURING CALIBRATION MODEL: 2241-3 SERIAL#; 253363 CAL DUE 08124117



Pu-239: 19.19% Tc-99: 25.80 %

Th-230: 17.30 %

SrY-90: 39.81 O/o

SOURCE

5744-06

5746-06

5747-06

5748-06


ISOTOPE

Sr-90

Tc-99

Pu-239

Th-230

ACTIVITY

16834 dpm

31900 dpm

25798 dpm

34899 dpm

2n ASSAY DATE

11.811 cpm 11112016

20.000 cpm

13.099 cpm

17, 700 cpm

11112016

11112016

11112016



HV (Alpha): 1125 V HV (Beta): 1700 V Threshold: 4 mV HV (Alpha): 1125 V HV (Beta): 1700 v Threshold: 4 mV

Back ground:

Alpha

0 CPM

Beta

0

NIA 0

NIA 0

AF 4 rrEfficiencies CPM

Back ground:

Alpha

2 CPM

Beta

201

NIA 7626

NIA 6402

AL 411 Efficiencies

CPM

Pu-239:

Tc-99;

Th-230:

SrY-90:

0 CPM

NIA

0 CPM

NIA

LJ Is the As Found Data within 20% of the efficiency from the last cal.?

CPM

CPM

Reproducibility : Isotope: ~O 6439 6386 6411 Average:

Pu-239: 4707 CPM Tc-99: NIA CPM

Th-230: 5250 CPM

SrY-90: NIA CPM


6412.0 ~ Are the individual counts within 10% of the average?

iir~:4S·.F·o~~d ·Ciata:(ev~n .. anar r~Pt;1rl.i.s ''JJJihJn· 1§o/&-of ·.th~Jas~· .c.~lfufai16n;- then the '1~~hni'Ci~o-rnay NiA P1ate~·u:.oa1~ ~ild"9'b.··~i~ecit1y· 1o·com~en1~--, ... Gi3"0ll)eti-Y'Of ·~ourc~:·;;;~·nuS,h .. iri~'S'~rt~~e. '&f~p·1 :gas proportfona\ probe.s "'. 1/8" fro~ sUria_ce·unless o.lh£l.f,Wise sp'1;1cified.

Alpha Source: Th~230

Response Background

HV CPM CPM

(Alpha) . A ch. A ch. Net 4TT Eff.

NIA

__ , ' _ _J

_!'u-239

2 Pi Efficiencies: [ 35~92% '1

PLATEAU DATA

Tc-99

$7.13%

Comments: Married as a set with: Model: 2241-3 Serial#: 253363

DET 1 Beta= 1700V, DET 3 Alpha= 1125V. Calibrated with plastic spacer.s installed.

Beta Source: Tc-99

Response Background

HV CPM CPM

(Beta) B ch.

NIA I

I B ch. Net 4TT Elf.

---1- i

' ~

,-1 --

i_ __ i -'--·

SrY-90

[52,$Q%'

Bar Code#:



Performed by:_._~-~-<-~· '-.~0':::::~~~t'S"""~---Printed Name: Carl Hail

Reviewed~ (i-J...-t-lv Date: __ _

llll llllllrnl Ill llllll 111111111



Page D.14 of D.22



C-14 SOURCE CALIBRATION FORM Probe Model Number : 43-68 -----Probe Serial Number : PR190903

Date of Calibration : 8/24/2016


Technician : Carl Hall ---------Instruments used during calibration

Model Number: 2241-3 Serial Number: 253363 Calibration Due Date: I 8/24/2017


NIST Traceable Source(s used : Activity(s) .--'-~------~----....c-t~-----------~

Source S/N Emission Rate 2 Pi cpm) uCi 4Pi (dpm) Assay Date

1> C-14 DX 295 432 25,920 0.0305405 67,800 5/3/1994

Instrument condition : Sat --=..,---High Voltage: 1700 -----

Background: 201 -----C-14 Count: 7848 -----

2TT Efficiency: 29.50% ----~ 4TT Efficiency: 11.28% -----'-'-



8/ 4/2017

~ Date: -~/~~-----

f ·l.-f-/ b

Date: ----------



Page D.15 of D.22

Safety and Ecology Corporation sEc PROCEDURE #


SEC-IS-417 Rev 4


Calibration Certificate for 43-37,Serial # PR265548, Bar Code # ,Property# Chase47 Date Last Cal. Expires: 06/08/16 Technician: Carl Hall

Page 1of1

812412016

Date: 08/24/16

Location: 999999, Reason For Calibration: Due and Repair




Pu-239: 18.28 o/o

Tc-99: 22.98 % Th-230: 16.48 %

SrY-90: 34.00 %

SOURCE

5744-06

5746-06

5747-06

5748-06


ISOTOPE

Sr-90

Tc-99

Pu-239

Th-230


16834 dpm 11,811 cpm 1/1/2016

31900 dpm 20,000 cpm 1/1/2016

25798 dpm 13,099 cpm 1/1/2016

34899 dpm 17,700 cpm 1/112016

AS LEFT lnStrument Condition: SAT


HV (Alpha): 1275 v HV (Beta): 1775 v Threshold: 4mV HV (Alpha): 1275 v HV (Beta): 1775 v Threshold: 4mV

Back Alpha

ground: 0 CPM

Pu-239: 0 CPM

Tc-99: N/A

Th-230: 0 CPM

SrY-90: N/A

D Is the As Found Data within 20o/o of the efficiency from the last cal.?

Beta AF 4 nEfficiencies

0 CPM

N/A ~Q-j)p_o/0 -.-_--i

0 CPM ~-····-·c-1 ! .0.00% I

NIA i"---c-"-" - ·1 ' 0.0~~"1

0 CPM ;_-,Or(H)% -_l

Back Alpha Beta AL 4 TT Efficiencies

ground: 4 CPM 947 CPM Pu-239: 4391 CPM N/A _17,~0-~~io -:1

Tc-99: NIA 8054 CPM :.:;:2~;_-~8~] Th-230: 5299 CPM NIA 1~.t7°/oj SrY-90: NIA 6075 CPM :-:30-;4:6o/o-]


Reproducibility : Isotope: iSr-90 6041 6092 6060 Average: 6064.3 ~ Are the individual counts within 10% of the average?

'.1f"i_he- ~S-FciUQ<l" d~ia-(·eV~n--a~e-f rep~if j i·~wiii1iri' 1-oo/~ Ot the -1~$t- ca1ihr~ti~n_:":th-en ul~--i·e_Chrii-ci~n- riiaY:NiA_P~aie_~u--~~i~-_ 1nd·-go'dir_ecUftO'.C_omrn;;n1S'. :;c;;e·~me1r;;'_Of'SQU~ce·~ :ii_U_~~:-'°_:-: --~:urt~_ce;-:e~C(iP-t · ;9as-proportj_QJ!al_probe_!>'°-1f8~from_stJJf~ce1m_!essolherwls_Ei_specifi_ed, " _-,_-_-, ::::· -----_.- -_.- ,_-._ -.--:,-:-:-.: .>·;-,<- · .. :;:--, -__·.--- "


Response Background

HV CPM CPM

PLATEAU DATA Beta Source: Tc-99

Response Background

HV CPM CPM

(Alpha)

N/A

Ach. A ch. Net 4TT Elf. (Beta) B ch. B ch. Net 4rr Elf.

Pu-239

2 Pi Efficiencies: !' _3_3:49-o/o _( Tc-99

35~54°/o


Th-230

'29.92%~

Serial #: 253363

DET 2 Beta= 1775V, DET 4 Alpha= 1275V. Calibrated with plastic spacers installed.

N/A

--~, --

!

SrY-90

f-'43.42% "l

I

1--' i--

--!

--,

Bar Code#:


Date Instrument is Due For Next Calibration: [0~~411"7 ___ .. , .. ]

Printed Name: Carl Hall

Reviewed by: ~ /

r· v1.f/; Date: __ _

11111mm 1111111111rn11111111m1

Performed by:~



Page D.16 of D.22



C-14 SOURCE CALIBRATION FORM Probe Model Number: 43-37

Probe Serial Number: PR265548 Date of Calibration : 8/24/2016


Technician : Carl Hall

Instruments used during calibration Model Number: 2241-3 Serial Number: 253363 Calibration Due Date: I 812412017


NIST Traceable Source<"("'s,__) "'us::..e:..;d"-": ----~-~~A""c"'ti-"vi"'tyc+(s'-'----~---~--~ Source SIN Emission Rate 2 Pi (cpm) uCi 4Pi (dpm) Assay Date

1 > C-14 DX 295 432 25,920 0.0305405 67,800 5/3/1994

Instrument condition : Sat -----High Voltage: __ 1_7_7c..5 __

Background: __ 9"-4'-'7 __

C-14 Count: 8505 -----

2rr Efficiency: 29.16% -----4rr Efficiency: 11.15% -----

Calibration sticker attached? Yes --"-'-''----


Performed by : Printed Name :

~d~t is due for next calibration: I 812412017 I (~~ Reviewed by: ~ Date:

Carl Hall _/_,,,.~------

Entered in computer inventory by: Date : ----------



Page D.17 of D.22


SEC PROCEDURE # SEC-IS-422 Rev 2



Date: 02/24/17 Date Last Cal. Expires: 11/04/17 Technician: Carl Hall

Location: 102624, Reason For Calibration: Short Cycled

MODEL: 500-2

MODEL:


SERIAL#: 132896

SERIAL#:

CAL. DUE: 06/20/17

CAL DUE:

AS FOUND DATA AS FOUND Instrument Condition: SAT

High Voltage AS FOUND AS LEFT


D New Batteries?

Battery Check: SAT

{+/· 10o/o tolerance) High Voltage High Voltage AS FOUND HV Setting: 950 v AS LEFT HV Setting:

500 V:

1000 V:

1500 V:

REPRODUCIBILITY

DIGITAL SCALER

N/A N/A

N/A N/A AS FOUND THRESHOLD: 10.0 mV AS LEFT THRESHOLD:

N/A N/A

x.1 or x1 Scale:

x1 or x1 O Scale:

x10 or x100 Scale:


N/A

N/A

N/A K

N/A K

N/A

N/A

NIA K

N/A K

N/A

N/A

N/A K

N/A K

~ Are the Individual Counts Within 10o/o of the Average?

&ZJ Fast I Slow Response Switch Functions Properly?

Audio Response: · SAT

AF 250: 250 0/o ERR: O.OOo/o AL 250: AF o/o ERR: 0.00%>

AF 2500: 2500 0/o ERR: O.OOo/o AL 2500: AF o/o ERR: 0.00°/o

AF 25K: 25 K 0/o ERR: 0.00% AL25K: AF K % ERR: O.OOo/o

AF 250K: 250 K % ERR: 0.00°/c, AL250K: AF K % ERR: 0.00%

~ Is the As Found Data Within 20% of the Set ~oint?

Push Buttons: SAT


Lamp: SAT

Serial#: PR360170

Audio/Divide: SAT

Bar Code#:

Printed Name: Carl Hall

~ Does Instrument Meet Final Acceptance Criteria?

~ Calibration Sticker Attached?

Date Instrument is Due For Next Calibration: :-------02124/18-'

Reviewed b~ _____ Date2;.2f-"/ 7 ~ 1111111111111n11111rnm

Page 1 of 1

212412017

950 v

10.0 mV



Page D.18 of D.22


2800 Solway Road, Knoxville, TN 37931 Page 1 of 1

Calibration Certificate 212412017


Date: 02/24/17

Location: 102624,




MODEL: 2241

MODEL:

SOURCE

99CS250-0288

Efficiency from Last Calibration: 0. 70 %

AS FOUND DATA


HV: 950 V

Center: 101482

Background: 3329

4 TT Probe Efficiency: Cs-137 0.73o/o

SERIAL#: 196627

SERIAL#:

CAL DUE: 02/24/18

CAL DUE:


ISOTOPE ACTIVITY 2rr ASSAY DATE

Cs-137 6.0658 uCi 1/3/2017


1 MINUTE COUNTS (CPMl AS LEFT DATA after repair of HV adjust


HV: 950 V

Center: 101482

Background: 3329

4 rr Probe Efficiency: Cs-137 0,73o/o


~ Is the As Found Efficiency Within 20% of the efficiency from the last cal.?

Reproducibility: lsotope:Cs~137 101830 100875 101179 Average: 101295 ~ Are the individual counts within 10o/o of the average?

• If As Found Efficiency (even after repair). Is within 1oo/~ Of ihe lasl cB1ibrat.lon and uniformity is <1'0%,· the tech11ician may NtA the Plateau ·oatB and.proceed tO 'commenls, Geometry"' Nal probes are 4 112" from source, AU other probes are in con la ct with surface unless othe!Wlse specified,

-~~-- -

PLATEAU AND SET POINT DATA ICPMl High Voltage Source Response Background

N/A



v


Performed by:

Printed Name:

CENTER Background 4 TT Efficiency

Cs-137



Date..;? zf:/) llll lllllllllllllillllllllllllllllll



Page D.19 of D.22


SEC PROCEDURE# SEC-IS-422 Rev 2



Date: 02/24/17 Date Last Cal. Expires: 11/04/17 Technician: Carl Hall

Location: 102624,

MODEL: 500-2

MODEL:



SERIAL#: 132896

SERIAL#:

CAL. DUE: 06/20/17

CAL DUE:

AS FOUND DATA AS FOUND Instrument Condition: SAT AS LEFT Instrument Condition: SAT

0 New Batteries?

Battery Check: SAT

High Voltage AS FOUND AS LEFT

Page 1 of 1

212412017

{+/~ 10o/o tolerance) High Voltage High Voltage AS FOUND HV Setting: 900 V AS LEFT HV Setting: 900 V

500 V: N/A N/A

1000 V: N/A N/A AS FOUND THRESHOLD: 10.4 mV AS LEFT THRESHOLD: 10.0 mV

1500 V:

REPRODUCIBILITY

DIGITAL SCALER

N/A N/A - --- -- -------

x.1 or x1 Scale:

x1 or x10 Scale:

x1 O or x100 Scale:


N/A

N/A

N/A K

N/A K

N/A

N/A

N/A K

N/A K

~ Are the Individual Counts Within 10% of the Avera9e?

~ Fast I Slow Response Switch Functions Properly?

Audio Response: SAT ---------

N/A

N/A

N/A K

N/A K

-- ---------------

AF 250: 250 0/o ERR: O.OOo/o AL 250: AF 0/o ERR: 0.00°/o

AF 2500: 2500 o/o ERR: O.OOo/o AL 2500: AF o/o ERR: O.OOo/o

AF 25K: 25 K o/o ERR: O.OOo/o AL 25K: AF K -0/o ERR: 0.00%

AF 250K: 250 K o/u ERR: O.OOo/o AL 250K: AF K o/o ERR: O.OOo/o

~ Is the As Found Data Within 20% of the Set Point?

Push Buttons: SAT Lamp: SAT Audio/Divide: SAT

Comments: Married as a set with: Model: 44~10 Serial#: PR360155



(~-~--:-:---- ~~:trument is Due For Next Calibration: 02/24/18

Bar Code#:

Performed by: ~ Reviewed bq::~·-,,.._ ________ Date;,?;.?Y-/ 7 Printed Name: Carl Hall / lllfllllllJlllJllllllllllll



Page D.20 of D.22


2800 Solway Road, Knoxville, TN 37931 Page 1 of 1

Calibration Certificate 212412017


Date: 02/24/17

Location: 102624,




MODEL: 2241

MODEL:

SOURCE

99CS250-0288

Efficiency from Last Calibration: 0.73%

AS FOUND DATA


HY: 900 V

Center: 99964

Background: 3394

4 TT Probe Efficiency: Cs-137 o.12°1o

SERIAL#: 196624

SERIAL#:


ISOTOPE ACTIVITY

Cs-137 6.0658 uCi

CAL DUE: 02/24/18

CAL DUE:

2rr ASSAY DATE

1/3/2017


1 MINUTE COUNTS ICPMl AS LEFT DATA after repair of HV adjust


HY: 900 V

Center: 99964

Background: 3394

4 rr Probe Efficiency: Cs-137 -0.72%


~ Is the As Found Efficiency Within 20% of the efficiency from the last cal.?

Reproducibility: lsotope:Cs-137 100001 100078 99346 Average: 99808 ~Are the Individual counts within 10o/o of the average?

~ If As Found Efficiency (even after repair) is within 10% oflrie' Jasi 'c.91ibrallon arid uniformity Is <10"1~. the t~chnician maY NIA the Pia le au Data and proceed to .Comments, .Geometfy = Na.·1 .probes are 4 1/2" from source. AU other probes are In contact wlth surface unless otherwise specilled.

PLATEAU AND SET POINT DATA (CPMl High Voltage Source Response Background

N/A

----------



CENTER Background 4 n Efficiency

v Cs-137

Serial #: 196624 Bar Code#:


Performed by:

Printed Name:

?~ D~te ~~strument is Due For Next Calibration: p_2_/~~/1~----

C~ - .? , qp Review•dr--

car1 Hall

Date:;?-;U/(7

lill lllllllllllilllllllllllllilll!lllll



Page D.21 of D.22

Safety and Ecology Corporation 2800 Solway Road Knoxville, TN 37931


SEC PROCEDURE# ICAL Rev 0

Page 1 of 1

811512016

Calibration Certificate for MICRO REM,Serial # C790F, Bar Code# ,Property# Chase160 Date: 08/15/16

Location: 999999,

Date Last Cal. Expires: Technician: Thomas Thompson

Reason For Calibration: Due for Calibration


MODEL MP-2 SERIAL#: 314 CAL DUE: 06/28117

MODEL 87V SERIAL#: 92560066 CAL DUE: 02/19/17

MODEL SERIAL#: CAL DUE:

NIST TRACEABLE SOURCES USED SOURCE ISOTOPE ACTIVITY

KR-4097 Cs-137 75.55678 mCi

AS FOUND DATA

Physical Cond UNSA Geotropism: SAT Bat. Check SAT

As Found

Speaker Check

As Left

OK

5.09

-4.32

High Voltage High Voltage Indicated in OK Band

+5 Volt Power Supply (4.5 to 5.5V)

-5 Volt Power Supply (-3.74 to -5.06 V)

CALIBRATION DATA Scale

I 0.1

1· --·-- ·-----

1

I 10

L_1~0

I

Precision

1000

.. -- . Scale X1000

-- ---

HVAL Exposure Rate

uR/HR {MR/HR) -· .. 5 .... <Pulsed = TO)

10 (Pulsed =TO)

15 (Pulsed =TO)

50 (.05)

100 (.1)

150 (.15)

500 (0.5) ·- -- --

1000 (1.0)

1500 (1.5)

5000 (5) .. ., - -

10000 (10)

15000 (15) -~---.,··--·-

50000 (50) - . _____ ,,,, 100000 (100)

150000 (150) - .

Exposure Rate 100000 (100)

Comments: Replaced battery holder board part number 942001 o.

OK

5.093

-4.33

Instrument Reading As Found As Left

5.1 5

10.2 10

15.3 15

60 50

115 100

170 155

400 500

800 1000

1300 1500 -- --

4000 5000 - ----·

8500 10000 - ·--

14000 16000

40000 48000

90000 100000

145000 150000 ---------

As Found Mean Value 90000.00

90000.00 90000.00

90000.00

N/A

----------ASSAY DATE

3/9/2016

Percent l;rror As Found As Left

·--·--2.00 0.00

2.00 0.00 '""" -

2.00 0.00

20.00 0.00 ·-

15.00 0.00

13.33 3.33

-20.00 0.00 ·----

-20.00 0.00 --- ---13.33 0.00

-20.00 0.00

-15.00 0.00

-6.67 6.67 -

-20.00 -4.00 ... --

-10.00 0.00

-3.33 0.00

o/o Dev 0.00

0.00

0.00

~ Does lnstrumen~effiii~ e nee Criteria? ~ Calibration Sticker Attached? Next Calibration Due Date: [ollf15!17i ·· ':'j

Performed by: ,. Reviewed by~~ Date: WJ/f £ Printed Name:



Page D.22 of D.22

MicroShield 8.01Microsoft (8.00-0000)

Date By Checked

Filename Run Date Run Time Duration8 in Concrete Co-60.msd November 29, 2016 4:16:26 PM 00:00:00

Project InfoCase Title Cyclotron Activation

Description 1 pci/g Co-60; 1", 2", and 4" above 8" Concrete SlabGeometry 8 - Cylinder Volume - End Shields

Source DimensionsHeight 20.0 cm (7.9 in)Radius 28.0 cm (11.0 in)

Dose PointsA X Y Z#1 0.0 cm (0 in) 22.5 cm (8.9 in) 0.0 cm (0 in)#2 0.0 cm (0 in) 25.0 cm (9.8 in) 0.0 cm (0 in)#3 0.0 cm (0 in) 30.0 cm (11.8 in) 0.0 cm (0 in)

ShieldsShield N Dimension Material DensitySource 4.93e+04 cm³ Concrete 2.35Air Gap Air 0.00122

Source Input: Grouping Method - Actual Photon EnergiesNuclide Ci Bq µCi/cm³ Bq/cm³Co-60 1.1576e-007 4.2832e+003 2.3500e-006 8.6950e-002

Buildup: The material reference is SourceIntegration Parameters

Radial 20Circumferential 10

Y Direction (axial) 10

Results - Dose Point # 1 - (0,22.5,0) cm

Energy (MeV) Activity (Photons/sec)Fluence RateMeV/cm²/secNo Buildup

Fluence RateMeV/cm²/secWith Buildup

Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6938 6.987e-01 2.417e-05 5.149e-05 4.667e-08 9.942e-081.1732 4.283e+03 3.128e-01 5.716e-01 5.590e-04 1.022e-031.3325 4.283e+03 3.751e-01 6.612e-01 6.508e-04 1.147e-03Totals 8.567e+03 6.879e-01 1.233e+00 1.210e-03 2.169e-03

Results - Dose Point # 2 - (0,25,0) cm

Energy (MeV) Activity (Photons/sec) Fluence RateMeV/cm²/sec

Fluence RateMeV/cm²/sec

Exposure RatemR/hr

Exposure RatemR/hr



Page E.1 of E.12

No Buildup With Buildup No Buildup With Buildup0.6938 6.987e-01 2.120e-05 4.413e-05 4.093e-08 8.520e-081.1732 4.283e+03 2.721e-01 4.861e-01 4.862e-04 8.687e-041.3325 4.283e+03 3.255e-01 5.612e-01 5.647e-04 9.736e-04Totals 8.567e+03 5.976e-01 1.047e+00 1.051e-03 1.842e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6938 6.987e-01 1.627e-05 3.287e-05 3.142e-08 6.346e-081.1732 4.283e+03 2.066e-01 3.591e-01 3.693e-04 6.417e-041.3325 4.283e+03 2.465e-01 4.137e-01 4.277e-04 7.177e-04Totals 8.567e+03 4.532e-01 7.728e-01 7.970e-04 1.359e-03



Page E.2 of E.12


Date By Checked

Filename Run Date Run Time Duration8 in Concrete Eu-152.msd November 29, 2016 3:58:29 PM 00:00:00


Description 1 pci/g Eu-152; 1", 2", and 4" above 8" Concrete SlabGeometry 8 - Cylinder Volume - End Shields




Source Input: Grouping Method - Standard IndicesNumber of Groups: 25

Lower Energy Cutoff: 0.015Photons < 0.015: Included

Library: GroveNuclide Ci Bq µCi/cm³ Bq/cm³Eu-152 1.1576e-007 4.2832e+003 2.3500e-006 8.6950e-002







Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.015 6.509e+02 3.950e-06 4.090e-06 3.388e-07 3.508e-070.04 2.534e+03 7.006e-04 9.739e-04 3.098e-06 4.307e-060.05 6.337e+02 3.409e-04 5.628e-04 9.081e-07 1.499e-060.1 1.218e+03 2.791e-03 7.776e-03 4.270e-06 1.190e-05



Page E.3 of E.12

0.2 3.210e+02 1.991e-03 5.841e-03 3.515e-06 1.031e-050.3 1.158e+03 1.249e-02 3.386e-02 2.370e-05 6.423e-050.4 2.692e+02 4.313e-03 1.083e-02 8.404e-06 2.110e-050.5 2.416e+01 5.279e-04 1.244e-03 1.036e-06 2.442e-060.6 1.816e+02 5.121e-03 1.141e-02 9.997e-06 2.226e-050.8 7.626e+02 3.228e-02 6.592e-02 6.139e-05 1.254e-041.0 1.833e+03 1.065e-01 2.040e-01 1.964e-04 3.760e-041.5 9.936e+02 1.030e-01 1.758e-01 1.732e-04 2.958e-04

Totals 1.058e+04 2.701e-01 5.182e-01 4.863e-04 9.355e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.015 6.509e+02 3.697e-06 3.823e-06 3.171e-07 3.279e-070.04 2.534e+03 6.322e-04 8.786e-04 2.796e-06 3.886e-060.05 6.337e+02 3.067e-04 5.048e-04 8.170e-07 1.345e-060.1 1.218e+03 2.490e-03 6.871e-03 3.809e-06 1.051e-050.2 3.210e+02 1.768e-03 5.098e-03 3.120e-06 8.998e-060.3 1.158e+03 1.106e-02 2.937e-02 2.097e-05 5.572e-050.4 2.692e+02 3.807e-03 9.355e-03 7.418e-06 1.823e-050.5 2.416e+01 4.649e-04 1.071e-03 9.125e-07 2.103e-060.6 1.816e+02 4.500e-03 9.795e-03 8.784e-06 1.912e-050.8 7.626e+02 2.825e-02 5.638e-02 5.373e-05 1.072e-041.0 1.833e+03 9.292e-02 1.739e-01 1.713e-04 3.205e-041.5 9.936e+02 8.915e-02 1.490e-01 1.500e-04 2.506e-04

Totals 1.058e+04 2.354e-01 4.422e-01 4.240e-04 7.986e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.015 6.509e+02 3.059e-06 3.159e-06 2.624e-07 2.710e-070.04 2.534e+03 5.047e-04 7.006e-04 2.232e-06 3.098e-060.05 6.337e+02 2.437e-04 3.998e-04 6.492e-07 1.065e-060.1 1.218e+03 1.958e-03 5.328e-03 2.995e-06 8.151e-060.2 3.210e+02 1.380e-03 3.883e-03 2.436e-06 6.853e-060.3 1.158e+03 8.595e-03 2.219e-02 1.630e-05 4.208e-050.4 2.692e+02 2.948e-03 7.030e-03 5.745e-06 1.370e-050.5 2.416e+01 3.588e-04 8.023e-04 7.043e-07 1.575e-060.6 1.816e+02 3.463e-03 7.314e-03 6.760e-06 1.428e-050.8 7.626e+02 2.163e-02 4.190e-02 4.114e-05 7.969e-051.0 1.833e+03 7.082e-02 1.288e-01 1.305e-04 2.374e-041.5 9.936e+02 6.734e-02 1.096e-01 1.133e-04 1.844e-04

Totals 1.058e+04 1.792e-01 3.279e-01 3.231e-04 5.925e-04



Page E.4 of E.12


Date By Checked

Filename Run Date Run Time Duration8 in Concrete Eu-154.msd November 29, 2016 4:13:30 PM 00:00:00


Description 1 pci/g Eu-154; 1", 2", and 4" above 8" Concrete SlabGeometry 8 - Cylinder Volume - End Shields






Library: GroveNuclide Ci Bq µCi/cm³ Bq/cm³Eu-154 1.1576e-007 4.2832e+003 2.3500e-006 8.6950e-002







Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.015 3.269e+02 1.984e-06 2.054e-06 1.702e-07 1.762e-070.04 8.717e+02 2.410e-04 3.350e-04 1.066e-06 1.482e-060.05 2.214e+02 1.191e-04 1.966e-04 3.173e-07 5.238e-070.1 1.733e+03 3.972e-03 1.107e-02 6.077e-06 1.693e-05



Page E.5 of E.12

0.2 2.925e+02 1.815e-03 5.323e-03 3.203e-06 9.395e-060.4 3.056e+01 4.897e-04 1.230e-03 9.541e-07 2.396e-060.5 9.274e+00 2.026e-04 4.776e-04 3.977e-07 9.375e-070.6 3.455e+02 9.742e-03 2.169e-02 1.901e-05 4.235e-050.8 1.670e+03 7.069e-02 1.444e-01 1.345e-04 2.746e-041.0 1.318e+03 7.660e-02 1.466e-01 1.412e-04 2.703e-041.5 1.671e+03 1.732e-01 2.957e-01 2.914e-04 4.975e-04

Totals 8.490e+03 3.371e-01 6.271e-01 5.982e-04 1.117e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.015 3.269e+02 1.856e-06 1.920e-06 1.592e-07 1.647e-070.04 8.717e+02 2.175e-04 3.022e-04 9.617e-07 1.337e-060.05 2.214e+02 1.072e-04 1.764e-04 2.855e-07 4.699e-070.1 1.733e+03 3.543e-03 9.779e-03 5.421e-06 1.496e-050.2 2.925e+02 1.611e-03 4.646e-03 2.844e-06 8.201e-060.4 3.056e+01 4.322e-04 1.062e-03 8.422e-07 2.070e-060.5 9.274e+00 1.784e-04 4.112e-04 3.503e-07 8.072e-070.6 3.455e+02 8.560e-03 1.863e-02 1.671e-05 3.637e-050.8 1.670e+03 6.187e-02 1.235e-01 1.177e-04 2.349e-041.0 1.318e+03 6.681e-02 1.250e-01 1.231e-04 2.304e-041.5 1.671e+03 1.500e-01 2.506e-01 2.523e-04 4.216e-04

Totals 8.490e+03 2.933e-01 5.341e-01 5.207e-04 9.512e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.015 3.269e+02 1.536e-06 1.586e-06 1.318e-07 1.361e-070.04 8.717e+02 1.736e-04 2.410e-04 7.678e-07 1.066e-060.05 2.214e+02 8.514e-05 1.397e-04 2.268e-07 3.722e-070.1 1.733e+03 2.787e-03 7.583e-03 4.263e-06 1.160e-050.2 2.925e+02 1.258e-03 3.539e-03 2.220e-06 6.245e-060.4 3.056e+01 3.347e-04 7.982e-04 6.522e-07 1.555e-060.5 9.274e+00 1.377e-04 3.079e-04 2.703e-07 6.045e-070.6 3.455e+02 6.588e-03 1.391e-02 1.286e-05 2.715e-050.8 1.670e+03 4.737e-02 9.177e-02 9.010e-05 1.745e-041.0 1.318e+03 5.092e-02 9.259e-02 9.386e-05 1.707e-041.5 1.671e+03 1.133e-01 1.843e-01 1.906e-04 3.102e-04

Totals 8.490e+03 2.229e-01 3.952e-01 3.959e-04 7.041e-04



Page E.6 of E.12


Date By Checked

Filename Run Date Run Time Duration8 in Concrete Na-22.msd November 29, 2016 4:21:37 PM 00:00:00


Description 1 pci/g Na-22; 1", 2", and 4" above 8" Concrete SlabGeometry 8 - Cylinder Volume - End Shields




Source Input: Grouping Method - Actual Photon EnergiesNuclide Ci Bq µCi/cm³ Bq/cm³Na-22 1.1576e-007 4.2832e+003 2.3500e-006 8.6950e-002







Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.0008 5.352e+00 1.838e-09 1.903e-09 6.634e-09 6.870e-090.511 7.701e+03 1.734e-01 4.061e-01 3.404e-04 7.971e-041.2745 4.281e+03 3.518e-01 6.279e-01 6.170e-04 1.101e-03Totals 1.199e+04 5.253e-01 1.034e+00 9.574e-04 1.898e-03




Exposure RatemR/hr

Exposure RatemR/hr



Page E.7 of E.12

No Buildup With Buildup No Buildup With Buildup0.0008 5.352e+00 1.720e-09 1.778e-09 6.208e-09 6.420e-090.511 7.701e+03 1.527e-01 3.496e-01 2.997e-04 6.861e-041.2745 4.281e+03 3.056e-01 5.333e-01 5.359e-04 9.353e-04Totals 1.199e+04 4.583e-01 8.829e-01 8.356e-04 1.621e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.0008 5.352e+00 1.423e-09 1.469e-09 5.137e-09 5.305e-090.511 7.701e+03 1.178e-01 2.617e-01 2.313e-04 5.136e-041.2745 4.281e+03 2.317e-01 3.934e-01 4.063e-04 6.900e-04Totals 1.199e+04 3.495e-01 6.551e-01 6.375e-04 1.204e-03



Page E.8 of E.12


Date By Checked

Filename Run Date Run Time Duration1 in Steel Co-60.msd November 29, 2016 5:09:58 PM 00:00:00


Description 1 pci/g Co-60; 1", 2", and 4" above 1" Steel SlabGeometry 8 - Cylinder Volume - End Shields



ShieldsShield N Dimension Material DensitySource 6157.522 cm³ Iron 7.86Air Gap Air 0.00122








Exposure RatemR/hr

No Buildup

Exposure RatemR/hr





Exposure RatemR/hr

Exposure RatemR/hr



Page E.9 of E.12

No Buildup With Buildup No Buildup With Buildup0.6938 8.733e-02 6.421e-06 1.105e-05 1.240e-08 2.133e-081.1732 5.354e+02 8.001e-02 1.241e-01 1.430e-04 2.218e-041.3325 5.354e+02 9.482e-02 1.434e-01 1.645e-04 2.487e-04Totals 1.071e+03 1.748e-01 2.675e-01 3.075e-04 4.706e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr




Page E.10 of E.12


Date By Checked

Filename Run Date Run Time Duration2 in Steel Co-60.msd November 29, 2016 5:12:19 PM 00:00:00


Description 1 pci/g Co-60; 1", 2", and 4" above 2" Steel SlabGeometry 8 - Cylinder Volume - End Shields



ShieldsShield N Dimension Material DensitySource 1.23e+04 cm³ Iron 7.86Air Gap Air 0.00122








Exposure RatemR/hr

No Buildup

Exposure RatemR/hr





Exposure RatemR/hr

Exposure RatemR/hr



Page E.11 of E.12

No Buildup With Buildup No Buildup With Buildup0.6938 1.747e-01 7.039e-06 1.343e-05 1.359e-08 2.593e-081.1732 1.071e+03 9.183e-02 1.591e-01 1.641e-04 2.844e-041.3325 1.071e+03 1.102e-01 1.860e-01 1.912e-04 3.227e-04Totals 2.142e+03 2.020e-01 3.452e-01 3.553e-04 6.071e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


NASA Glenn Research CenterLewis FieldMarch 31, 2017


Page E.12 of E.12



Page F.1 of F.3

Figure F.1: 140-1101 Gamma Scan 4-Plot



Page F.2 of F.3

Figure F.2: 140-1201 Gamma Scan 4-Plot



Page F.3 of F.3

Figure F.3: 140-BRA1 Gamma Scan 4-Plot



Page G.1 of G.3

Figure G.1: 140-1101 Beta Scan 4-Plot



Page G.2 of G.3

Figure G.2: 140-1201 Beta Scan 4-Plot



Page G.3 of G.3

Figure G.3: 140-BRA1 Beta Scan 4-Plot

NASA Glenn Research Center

Lewis Field

March 31, 2017



Page H.1 of H.3

Date: 3/8/2017

Source Alpha/ Total/ Bkgd Area MDC

Check Beta Removable Counts Sample Bkg. (cm2) (dpm/100cm

2)

Gross Net Activity Gross Net Activity

Counts cpm (dpm/100cm2) Counts cpm (dpm/100cm

2)

1 136 -20 -167 <MDC 0.00 -0.5 -1.97 <MDC 0 0 0 <MDC Concrete Wall

2 133 -26 -217 <MDC 1 0.5 1.97 <MDC 9 3 0 <MDC Concrete Floor

3 124 -44 -368 <MDC 0 -0.5 -1.97 <MDC 13 0 0 <MDC Concrete Floor

4 168 44 368 <MDC 1 0.5 1.97 <MDC 0 14 3 <MDC Concrete Floor


6 153 14 117 <MDC 0 -0.5 -1.97 <MDC 28 4 2 <MDC Concrete Floor




10 142 -8 -67 <MDC 2 1.5 5.90 <MDC 1 3 0 <MDC Concrete Wall

11 158 24 201 <MDC 0 -0.5 -1.97 <MDC 13 0 0 <MDC Concrete Wall


13 263 234 1,957 2 1.5 5.90 <MDC 0 3 1 <MDC Concrete Floor








21 228 164 1,372 0 -0.5 -1.97 <MDC 8 12 0 <MDC Concrete Wall




25 148 4 33 <MDC -1 -1.5 -5.90 <MDC 0 4 0 <MDC Concrete Floor


27 179 66 552 <MDC 2 1.5 5.90 <MDC 12 1 1 <MDC Concrete Wall



J1 214 136 1,138 1 0.5 1.97 <MDC 8 6 0 <MDC Concrete Floor

J2 297 302 2,526 0 -0.5 -1.97 <MDC 10 3 2 <MDC Concrete Floor



J5 245 198 1,656 4 3.5 13.76 <MDC 1 0 2 <MDC Concrete Wall

J6 230 168 1,405 1 0.5 1.97 <MDC 11 0 1 <MDC Concrete Wall

Unit-3

SAT 8/24/2017

LSC (dpm/100cm2)

H-3 C-14 NotesOpen

1 10 100Beta Removable

Location

Total Beta Surface Activity Removable Beta Surface Activity

Notes Notes

25.44% 100%

9912241-3 / 253351

SAT 4/20/2017

25% 0.5 0.5 126Beta Total 14643-68 / PR216394

37.95%

Tennelec / 13000675

Description

Radiological Survey Record

Building: 140 Survey Unit: 1101

Reviewed: Dustin Miller

Project: NASA Cyclotron

Surveyor: Jay Gluck/ Tyler Hillis Notes: FSS

20

Instrument / Serial #Cal. Due

Instrument

Efficiency

Surface

Efficiency

Count Time (min)

Detector / Serial #

5


Lewis Field

March 31, 2017



Page H.2 of H.3

Date: 3/8/2017



2)



2)


2 164 36 301 <MDC 3 2.5 9.83 <MDC 1 6 0 <MDC Concrete Ceiling



5 140 -12 -100 <MDC 0 -0.5 -1.97 <MDC 2 2 2 <MDC Concrete Wall

6 166 40 335 <MDC 0 -0.5 -1.97 <MDC 1 0 0 <MDC Concrete Ceiling

7 165 38 318 <MDC -1 -1.5 -5.90 <MDC 0 0 0 <MDC Concrete Ceiling








5 25.44%

Location

Total Beta Surface Activity Removable Beta Surface Activity LSC (dpm/100cm2)

Notes Notes H-3 C-14 Open Notes

Tennelec / 13000675SAT 4/20/2017 Beta Removable

Unit-3

0.5

100% 1

126 991

2010 100

Cal. Due

43-68 / PR21639437.95% 25% 0.5

2241-3 / 253351SAT 8/24/2017

Description


Project: NASA Cyclotron Building: 140 Survey Unit: 1201

Surveyor: Jay Gluck/ Tyler Hillis Reviewed: Dustin Miller Notes: FSS

Instrument

Efficiency

Surface

Efficiency

Count Time (min)

Detector / Serial #

Beta Total 146

Instrument / Serial #


Lewis Field

March 31, 2017



Page H.3 of H.3

Date: 3/8/2017



2)



2)

1 98 -104 -837 <MDC N/A N/A N/A N/A N/A N/A N/A N/A Concrete Wall


3 153 6 48 <MDC N/A N/A N/A N/A N/A N/A N/A N/A Concrete Floor













Location

Total Beta Surface Activity Removable Beta Surface Activity LSC (dpm/100cm2)

Notes Notes H-3 C-14 Open Notes

9652241-3 / 267138

SAT 8/24/2017

N/A N/A N/A N/A N/AN/A N/AN/A N/A

0.5 0.5

N/A N/A

126


43-68 / PR28569939.45% 25%

Description

N/A


Project: NASA Cyclotron Building: 140 Survey Unit: BRA1

Surveyor: Stefan Herold Reviewed: Dustin Miller Notes: FSS

Instrument

Efficiency

Surface

Efficiency

Count Time (min)

Detector / Serial #

Beta Total 150


Lewis Field

March 31, 2017



Page I.1 of I.1

Date: 3/8/2017 Time:



2)



2)

1 154 16 136 <MDC 0 -1 -1.97 <MDC 0 6 0 <MDC Ventillation - East

2 137 -18 -153 <MDC 2 2 5.90 <MDC 9 1 1 <MDC Ventillation - West

3 N/A N/A N/A N/A 1 1 1.97 <MDC 19 0 3 <MDC Cooling Water Outlet

4 N/A N/A N/A N/A 0 -1 -1.97 <MDC 31 2 0 <MDC Cooling Water Inlet

Description

10 100Removable

SAT 8/24/2017

LSC (dpm/100cm2)

H-3 C-14 Notes

Beta Total 146

Open

1Beta

Location

Total Surface Activity Removable Surface Activity

Notes Notes

43-68 / PR21639437.35% 1,007

2241-3 / 253351

SAT 4/20/2017

25% 0.5 0.5 126

Tennelec / 13000675

Unit-3 19.795 25.44% 100%


Instrument

Efficiency

Surface

Efficiency

Count Time (min)

Detector / Serial #


Building: 140 Survey Unit: VE01 and DR01

Reviewed: Dustin Miller

Project: NASA Cyclotron

Surveyor: Jay Gluck/ Tyler Hillis Notes: FSS



Page J.1 of J.3

Source Alpha/ Total/ Bkgd Area MDCCheck Beta Removable CPM or Dose Sample Bkg. (cm2) (dpm/100cm2)

1 2 3 4 5 6 7 8 9 10

1 3/7/2017 9,562 6 5 5 6 7 8 7 5 7 6

2 3/7/2017 7,692 4 4 4 7 6 4 3 3 4 7

3 3/7/2017 7,661 6 6 8 6 4 3 4 5 7 5

4 3/7/2017 8,033 5 7 8 6 4 4 3 4 4 5

5 3/7/2017 8,737 5 6 7 8 6 5 6 7 6 5

6 3/7/2017 8,930 4 6 4 8 8 8 6 5 6 7

7 3/7/2017 10,373 5 6 8 6 7 6 5 6 7 8

8 3/7/2017 10,300 5 6 5 7 10 8 5 6 7 8

9 3/7/2017 9,504 5 8 7 5 6 7 5 7 5 7

10 3/7/2017 9,420 6 5 5 5 6 6 5 6 5 8

11 3/7/2017 10,393 5 4 5 5 8 9 6 7 6 7

12 3/7/2017 9,555 4 5 5 4 6 7 6 5 5 4

13 3/7/2017 19,161 7 10 8 7 12 10 10 7 10 7

14 3/7/2017 11,996 8 5 6 7 6 4 7 8 10 10

15 3/7/2017 9,551 7 5 6 8 7 6 8 9 8 6

16 3/7/2017 9,648 5 7 5 4 4 6 8 6 9 8

17 3/7/2017 12,649 5 6 6 8 11 7 6 6 10 12

18 3/7/2017 15,975 7 10 9 10 11 9 8 8 7 12

19 3/7/2017 10,118 7 7 8 7 6 5 6 5 7 5

20 3/7/2017 10,085 5 6 7 5 4 4 5 6 5 10

21 3/7/2017 15,608 7 6 6 6 7 7 8 6 8 10

22 3/7/2017 12,155 6 6 6 5 7 5 4 5 3 5

23 3/7/2017 14,959 8 8 8 8 7 6 7 7 7 5

24 3/7/2017 13,573 8 7 9 7 6 5 7 8 7 6

25 3/7/2017 8,761 4 4 5 6 6 7 8 5 4 4

26 3/7/2017 10,086 6 5 5 5 6 7 7 5 7 6

27 3/7/2017 11,788 6 6 4 7 6 8 11 7 6 7

28 3/7/2017 12,531 7 7 6 7 8 5 7 6 5 7

29 3/8/2017 10,066 6 5 6 4 7 6 6 4 6 6

Location DateNaI Static

(cpm)

Bicron Instantaneous Measurements (µRem/hr) @ 1 meter

N/A N/A Instant Instant N/A N/A

1 N/A N/A

SAT 8/15/2017 N/A N/A 7Bicron/C790F

6,84344-10/PR360145

N/A N/A 12241/215484

SAT 2/2/2018 N/A N/A

Instrument / Serial #Cal. Due Efficiency

Equilibrium Factor

Count Time (min)Detector / Serial #

Surveyor: Jay Gluck/Tyler Hillis Reviewed: Dustin Miller Notes: FSS. NaI 2x2 background readings in CPM. Bicron Readings in REM/hr.


Project: NASA Cyclotron Building: 140 Survey Unit: 140-1101



Page J.2 of J.3


1 2 3 4 5 6 7 8 9 10

1 3/7/2017 9,956 5 6 7 5 10 10 7 6 6 7

2 3/7/2017 10,123 10 8 7 6 6 5 8 5 5 7

3 3/7/2017 9,909 5 6 7 8 7 7 5 5 4 4

4 3/7/2017 9,968 4 7 7 5 6 8 6 6 5 7

5 3/7/2017 10,588 7 7 6 8 5 5 6 7 7 7

6 3/7/2017 11,300 7 5 7 8 5 7 8 4 5 6

7 3/7/2017 11,001 7 7 5 6 7 8 7 7 7 5

8 3/7/2017 10,645 7 6 7 5 6 8 10 10 12 10

9 3/7/2017 10,675 6 7 6 7 4 7 6 5 6 8

10 3/7/2017 10,268 5 6 4 5 4 7 8 8 6 7

11 3/7/2017 11,277 7 7 7 9 6 6 5 4 7 7

12 3/7/2017 11,810 6 8 7 8 6 7 8 5 4 5

13 3/7/2017 11,799 7 8 6 7 8 9 6 6 9 12

14 3/7/2017 10,515 6 7 5 6 7 4 5 10 7 4


(cpm)



1 N/A N/A


6,84344-10/PR360145

N/A N/A 12241/215484

SAT 2/2/2018 N/A N/A


Equilibrium Factor




Project: NASA Cyclotron Building: 140 Survey Unit: 140-1201



Page J.3 of J.3


1 2 3 4 5 6 7 8 9 10

1 3/7/2017 6,188 4 4 3 4 5 4 5 5 4 4

2 3/7/2017 6,167 4 4 4 4 5 4 4 5 5 6

3 3/7/2017 6,735 3 4 3 3 3 4 4 4 4 4

4 3/7/2017 6,960 5 4 4 6 7 10 7 6 5 4

5 3/7/2017 7,186 6 6 7 5 4 4 4 5 6 4

6 3/7/2017 7,601 4 4 5 5 4 4 6 4 3 4

7 3/7/2017 7,977 4 3 4 4 4 5 7 5 6 6

8 3/7/2017 7,277 7 6 5 5 5 4 6 5 6 8

9 3/7/2017 7,274 6 7 6 6 5 4 5 4 4 6

10 3/7/2017 7,515 7 6 5 5 6 6 6 6 5 4

11 3/7/2017 7,514 6 5 5 4 5 6 5 8 6 5

12 3/7/2017 7,667 5 5 4 7 6 5 7 6 5 4

13 3/7/2017 7,841 5 6 5 6 6 6 7 5 6 5

14 3/7/2017 7,559 4 4 4 3 4 6 5 8 7 6

15 3/7/2017 7,527 5 5 4 6 7 4 5 5 4 5


(cpm)



1 N/A N/A


6,84344-10/PR360145

N/A N/A 12241/215484

SAT 2/2/2018 N/A N/A


Equilibrium Factor




Project: NASA Cyclotron Building: 140 Survey Unit: 140-BRA1

22

19

12

9

2

28(5')

23

18

13

8

3

27(5')

24

17

14

7

4

25

16

15

6

5

29(5')

11(5')

10(5')

20(5')

21(5')26(5')

1(5')

J1

J2

J3

J4

J5

J6



Page: K.1 of K.4Building: 140 Survey Unit: 1101

Random Start Location

Spacing = 11ft

(#) = Height on Wall

Elevated Gamma Count RateArea: 12k to 18k cpm

AutoCAD SHX Text

Cyclotron Vault

AutoCAD SHX Text


AutoCAD SHX Text

N

1

14(6')

10

7

2

13(6')

11

6

3

12(3.9')

5(3.9')

4(3.9')

9(10')

1(10')

8(10')



Page: K.2 of K.4Building: 140 Survey Unit: 1201

Random Start LocationSpacing = 18 ft(#) = Height Down TheWall From Ceiling

AutoCAD SHX Text

Ceiling

AutoCAD SHX Text

Cyclotron Vault

AutoCAD SHX Text


AutoCAD SHX Text

Shield Room

AutoCAD SHX Text

N

1415

13

1112

910

8

67

4(Lower Square Meter)5(Upper Square Meter)

3

1(Upper Square Meter)2(Lower Square Meter)



Page: K.3 of K.4Building: 140 Survey Unit: BRA1

Location of measurementwas in the center of thegrid drawn by NASA.

AutoCAD SHX Text

(209)

AutoCAD SHX Text

4

AutoCAD SHX Text

Skylight Room

AutoCAD SHX Text

N



Page: K.4 of K.4Building: 140 Survey Unit: DR01 and VE01

AutoCAD SHX Text

Vent #1

AutoCAD SHX Text

Vent #2

AutoCAD SHX Text

Drain #1

AutoCAD SHX Text

Drain #2

AutoCAD SHX Text


AutoCAD SHX Text

Shield Room

AutoCAD SHX Text

Walk Way

AutoCAD SHX Text

N


Lewis Field

March 31, 2017



Page L.1 of L.2

Date: 3/8/2017



2)



2)

1 132 -36 -290 <MDC 0 -0.5 -1.97 <MDC 18 5 3 <MDC Duplicate for Survey Unit 1101 Location 25

2 195 90 724 <MDC 0 -0.5 -1.97 <MDC 0 9 0 <MDC Duplicate for Survey Unit 1101 Location 12

3 170 40 322 <MDC 0 -0.5 -1.97 <MDC 8 6 0 <MDC Duplicate for Survey Unit 1201 Location 3


Project: NASA Cyclotron Building: 140 Survey Unit: QA01

Surveyor: Stefan Herold Reviewed: Dustin Miller Notes: Quality Assurance duplication measurements for locations listed in description.

Instrument

Efficiency

Surface

Efficiency

Count Time (min)

Detector / Serial #

Beta Total 150


43-68 / PR285699

Tennelec / 13000675SAT 4/20/2017 Beta Removable

39.45% 25% 0.5 0.5 126 9652241-3 / 267138

SAT 5/4/2017

19.79Unit-3

5 25.44% 100% 1 10 100

Location

Total Surface Activity Removable Surface Activity LSC (dpm/100cm2)

Notes Notes H-3 C-14 Open Notes Description


Lewis Field

March 31, 2017



Page L.2 of L.2

Date: 3/8/2017


Check Beta Removable CPM or Dose Sample Bkg. (cm2) (dpm/100cm

2)

1 2 3 4 5 6 7 8 9 10

1 3/7/2017 9,562 6 5 5 4 3 5 10 11 7 14 Duplicate for Survey Unit 1101 Location 25



Description

Surveyor: Stefan Herold Reviewed: Dustin Miller Notes: FSS. NaI 2x2 background readings in CPM. Bicron Readings in mREM/hr.


Project: NASA Cyclotron Building: 140 Survey Unit: 140-QA01


Equilibrium

Factor

Count Time (min)

Detector / Serial #

N/A N/A2241/199624

SAT 2/24/2017 N/A N/A 6,72644-10/PR360155

Bicron/C790F

N/A N/A 1 1


(cpm)


N/A N/A Instant Instant N/A N/ASAT 8/15/2017 N/A N/A 5



Page: M.1 of M.1Building: 140 Beam Tube Identification

Beam TubesNotes:BT5A and BT6 are in line with each other. BT5Ais above BT6.BT5B and BT5c are in the ceiling of the NeutronTherapy Room.

AutoCAD SHX Text

BT1A

AutoCAD SHX Text

(TUNNEL)

AutoCAD SHX Text

Cyclotron Vault

AutoCAD SHX Text


AutoCAD SHX Text

Shield Room

AutoCAD SHX Text

Skylight Room

AutoCAD SHX Text

Hot Storage Room

AutoCAD SHX Text

Walk Way

AutoCAD SHX Text

Instrument Room

AutoCAD SHX Text

Sump

AutoCAD SHX Text

BD2

AutoCAD SHX Text

BT1B

AutoCAD SHX Text

BD3

AutoCAD SHX Text

BD4

AutoCAD SHX Text

BT5B (In Ceiling)

AutoCAD SHX Text

BT5A and BT6

AutoCAD SHX Text

BT7

AutoCAD SHX Text

BT8

AutoCAD SHX Text

BT9

AutoCAD SHX Text

BT10

AutoCAD SHX Text

BT11

AutoCAD SHX Text

BT12

AutoCAD SHX Text

BT13 (Square)

AutoCAD SHX Text

BD8

AutoCAD SHX Text

BD9

AutoCAD SHX Text

BD10

AutoCAD SHX Text

BD11

AutoCAD SHX Text

BT5C (Vertical)

AutoCAD SHX Text

BD12

AutoCAD SHX Text

N



Page N.1 of N.21

Figure N.1: Beam Tube 1A 4-Plot



Page N.2 of N.21

Figure N.2: Beam Tube 1B 4-Plot



Page N.3 of N.21

Figure N.3: Beam Dump 2 4-Plot



Page N.4 of N.21




Page N.5 of N.21




Page N.6 of N.21

Figure N.6: Beam Tube 5A 4-Plot



Page N.7 of N.21

Figure N.7: Beam Tube 5B 4-Plot



Page N.8 of N.21

Figure N.8: Beam Tube 5C 4-Plot



Page N.9 of N.21

Figure N.9: Beam Tube 6 4-Plot



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Page N.21 of N.21


ModeluR/hr per

pCi/gcpm per uR/hr

Steel 1' 7,045 2,256 4,790 8S 1.461 430 8 0.4Steel 6' 2" 10,169 5,453 4,717 8S 1.555 430 7 0.4Steel 12' 3" 10,098 5,453 4,646 8S 1.555 430 7 0.4Steel 18' 5" 9,877 5,453 4,425 8S 1.555 430 7 0.4Steel 23' 6" 4,099 2,256 1,844 8S 1.461 430 3 0.4Steel 1' 4,085 2,256 1,830 8S 1.461 430 3 0.4Steel 4' 7" 9,884 5,453 4,432 8S 1.556 430 7 0.4Steel 8' 2" 3,884 2,256 1,629 8S 1.461 430 3 0.4Steel 1' 6,006 2,256 3,751 8S 1.461 430 6 0.4Steel 2' 6" 9,981 4,015 5,966 8S 1.532 430 9 0.4Steel 3' 11" 10,986 2,256 8,731 8S 1.461 430 14 0.4Steel 1' 6,159 2,256 3,904 8S 1.461 430 6 0.4Steel 2' 5" 9,229 4,015 5,214 8S 1.532 430 8 0.4Steel 3' 11" 10,432 2,256 8,177 8S 1.461 430 13 0.4

Stainless Steel 1' 7,570 2,256 5,315 4SS 1.070 430 12 0.5Stainless Steel 3' 8" 5,005 4,015 990 4SS 1.090 430 2 0.5Stainless Steel 6' 3" 4,589 2,256 2,334 4SS 1.070 430 5 0.5

Concrete 1' 10,193 2,256 7,938 --- --- --- --- ---Concrete 4' 7" 8,618 5,453 3,166 --- --- --- --- ---Concrete 8' 2" 13,669 2,256 11,414 --- --- --- --- ---Concrete 1' 8,098 2,256 5,843 --- --- --- --- ---Concrete 4' 5" 8,369 5,453 2,917 --- --- --- --- ---Concrete 7' 9" 10,370 2,256 8,115 --- --- --- --- ---

Steel 1' 3,491 2,256 1,236 11S 3.450 428 1 0.2Steel 1' 11" 6,507 2,256 4,252 11S 3.450 428 3 0.2

Concrete 1' 10,895 2,256 8,640 --- --- --- --- ---Concrete 4' 2" 9,180 5,453 3,728 --- --- --- --- ---

Steel 5' 6" 9,195 4,389 4,807 11S 1.870 428 6 0.3Steel 6' 6" 17,688 4,015 13,673 11S 3.450 428 9 0.2Steel 7' 6" 32,677 2,256 30,422 11S 3.450 428 21 0.2Steel 8' 4" 36,504 6,133 30,372 11S 1.870 428 38 0.3

Stainless Steel 1' 13,337 2,256 11,082 4SS 1.070 430 24 0.5Stainless Steel 4' 5,586 5,453 134 4SS 1.120 430 0 0.5Stainless Steel 7' 38,549 2,256 36,294 4SS 1.070 430 79 0.5Stainless Steel 1' 16,232 2,256 13,977 3SS 0.574 430 57 1.0Stainless Steel 3' 6" 16,263 4,015 12,248 3SS 0.608 430 47 1.0Stainless Steel 5' 11" 11,962 2,256 9,707 6.3SS 1.490 430 15 0.4

Steel 1' 5,899 2,256 3,644 6S 1.050 430 8 0.6Steel 2' 3" 8,110 4,015 4,095 6S 1.080 430 9 0.5Steel 3' 5" 10,310 2,256 8,055 6S 1.050 430 18 0.6

Concrete 1' 10,586 2,256 8,331 --- --- --- --- ---Concrete 3' 3" 8,092 4,015 4,077 --- --- --- --- ---Concrete 5' 6" 8,299 2,256 6,044 --- --- --- --- ---


Beam Tube Number

Length (feet)

Material DistanceStatic Count (gross cpm)

Bkg (cpm)

net cpmActivity (pCi/g)

MDC (pCi/g)

MicroShieldTM

Dose Modeling Results

BT1A 24' 6"

BT1B 9' 2"

BD2 4' 11"

BD3 4' 10.5"

BD4 7' 3"

BT5A 9' 2"

BT5B 8' 9"

BT5C 2' 11"

BT6 8' 5"

BT7 8'

BT8 6' 11"

BD8 4' 5"

BT9 6' 6"

BD9 4' 5"



Page O.1 of O.16

ModeluR/hr per

pCi/gcpm per uR/hr

Stainless Steel 1' 15,707 2,256 13,452 3SS 0.574 430 54 1.0Stainless Steel 3' 5" 13,943 4,389 9,555 3SS 0.608 430 37 1.0Stainless Steel 5' 10" 13,856 2,256 11,601 3SS 0.574 430 47 1.0





Steel 1' 5,832 2,256 3,577 6S 1.050 430 8 0.6Steel 2' 3" 7,980 4,015 3,965 6S 1.080 430 9 0.5Steel 3' 5" 11,346 2,256 9,091 6S 1.050 430 20 0.6Steel 1' 15,692 2,256 13,437 18SQ 1.730 429 18 0.3Steel 3' 1" 16,131 4,389 11,743 18SQ 1.940 429 14 0.3Steel 5' 2" 13,303 2,256 11,048 18SQ 1.730 429 15 0.3

BKG 1 BKG 2 AVG MDCRSteel 0 6,044 6,221 6,133 250Steel 1' 2,170 2,341 2,256 152Steel 2' 3,808 4,222 4,015 202Steel 3' 4,250 4,527 4,389 212Steel 4' 5,408 5,497 5,453 236

MicroShieldTM

Dose Modeling Results Activity (pCi/g)

MDC (pCi/g)

Material DistanceStatic Count (gross cpm)

Bkg (cpm)

net cpm

BT10 6' 10"

Beam Tube Number

Length (feet)

BD10 4' 5"

BT11 6' 9"

BD11 4' 5"

BKG1

BT12 7' 4"

BD12 4' 5"

BT13 6' 1.5"



Page O.2 of O.16


Date By Checked

Filename Run Date Run Time DurationNASA 3SS.msd March 22, 2017 8:45:17 PM 00:00:00

Project InfoCase Title NASA Beam Tubes

Description 3SS - 2.75" Diameter Stainless SteelGeometry 11 - Annular Cylinder - Internal Dose Point

Source DimensionsHeight 304.8 cm (10 ft 0.0 in)

Inner Cyl Radius 3.493 cm (1.4 in)Inner Cyl Thickness 0.0 cm (0 in)

Source 0.318 cm (0.1 in)

Dose PointsA X Y Z#1 0.0 cm (0 in) 0.0 cm (0 in) 0.0 cm (0 in)#2 0.0 cm (0 in) 30.48 cm (1 ft) 0.0 cm (0 in)#3 0.0 cm (0 in) 60.96 cm (2 ft) 0.0 cm (0 in)#4 0.0 cm (0 in) 121.92 cm (4 ft) 0.0 cm (0 in)#5 0.0 cm (0 in) 152.4 cm (5 ft 0.0 in) 0.0 cm (0 in)#6 0.0 cm (0 in) 182.88 cm (6 ft) 0.0 cm (0 in)

ShieldsShield N Dimension Material Density

Cyl. Radius 1.375 in Air 0.00122Source 135.481 in³ Iron 7.86



Library: GroveNuclide Ci Bq µCi/cm³ Bq/cm³Co-60 1.7450e-008 6.4566e+002 7.8600e-006 2.9082e-001

Buildup: The material reference is SourceIntegration ParametersRadial 10

Circumferential 10Y Direction (axial) 20

Results - Dose Point # 1 - (0,0,0) in



Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6 1.053e-01 5.684e-06 6.526e-06 1.109e-08 1.274e-081.0 6.457e+02 6.037e-02 6.698e-02 1.113e-04 1.235e-041.5 6.457e+02 9.304e-02 1.009e-01 1.565e-04 1.698e-04

Totals 1.291e+03 1.534e-01 1.679e-01 2.678e-04 2.932e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6 1.053e-01 1.123e-05 1.280e-05 2.193e-08 2.499e-08

1 of 2 3/31/2017 3:02 PM



Page O.3 of O.16

1.0 6.457e+02 1.191e-01 1.312e-01 2.195e-04 2.418e-041.5 6.457e+02 1.832e-01 1.974e-01 3.082e-04 3.321e-04

Totals 1.291e+03 3.023e-01 3.286e-01 5.277e-04 5.740e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.291e+03 3.076e-01 3.355e-01 5.370e-04 5.861e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.291e+03 3.190e-01 3.478e-01 5.568e-04 6.076e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.291e+03 3.196e-01 3.485e-01 5.579e-04 6.086e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.291e+03 3.190e-01 3.478e-01 5.568e-04 6.076e-04

2 of 2 3/31/2017 3:02 PM



Page O.4 of O.16


Date By Checked

Filename Run Date Run Time DurationNASA 4SS.msd March 22, 2017 4:59:20 PM 00:00:00


Description 4SS - 4" Diameter Stainless SteelGeometry 11 - Annular Cylinder - Internal Dose Point















Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 3.818e+03 2.717e-01 3.159e-01 4.741e-04 5.517e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


1 of 2 3/31/2017 3:04 PM



Page O.5 of O.16

1.0 1.909e+03 2.074e-01 2.444e-01 3.823e-04 4.505e-041.5 1.909e+03 3.248e-01 3.690e-01 5.465e-04 6.208e-04

Totals 3.818e+03 5.323e-01 6.134e-01 9.289e-04 1.071e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 3.818e+03 5.401e-01 6.259e-01 9.424e-04 1.093e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 3.818e+03 5.524e-01 6.403e-01 9.640e-04 1.118e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 3.818e+03 5.506e-01 6.386e-01 9.609e-04 1.115e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 3.818e+03 5.524e-01 6.403e-01 9.640e-04 1.118e-03

2 of 2 3/31/2017 3:04 PM



Page O.6 of O.16


Date By Checked

Filename Run Date Run Time DurationNASA 6S.msd March 22, 2017 8:56:36 PM 00:00:00


Description 6S - 6" Diameter SteelGeometry 11 - Annular Cylinder - Internal Dose Point















Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.615e+03 2.720e-01 3.161e-01 4.746e-04 5.521e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


1 of 2 3/31/2017 3:05 PM



Page O.7 of O.16

1.0 2.807e+03 2.036e-01 2.388e-01 3.752e-04 4.401e-041.5 2.807e+03 3.184e-01 3.603e-01 5.357e-04 6.061e-04

Totals 5.615e+03 5.220e-01 5.991e-01 9.109e-04 1.046e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.615e+03 5.369e-01 6.205e-01 9.370e-04 1.084e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.615e+03 5.421e-01 6.287e-01 9.460e-04 1.098e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.615e+03 5.412e-01 6.280e-01 9.445e-04 1.097e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.615e+03 5.421e-01 6.287e-01 9.460e-04 1.098e-03

2 of 2 3/31/2017 3:05 PM



Page O.8 of O.16


Date By Checked

Filename Run Date Run Time DurationNASA 6.3SS.msd March 22, 2017 9:22:58 PM 00:00:00


Description 6SS - 6" Diameter Stainless SteelGeometry 11 - Annular Cylinder - Internal Dose Point















Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 8.928e+03 3.679e-01 4.495e-01 6.417e-04 7.850e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


1 of 2 3/31/2017 3:05 PM



Page O.9 of O.16

1.0 4.463e+03 2.738e-01 3.400e-01 5.047e-04 6.268e-041.5 4.463e+03 4.348e-01 5.150e-01 7.316e-04 8.665e-04

Totals 8.928e+03 7.086e-01 8.551e-01 1.236e-03 1.493e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 8.928e+03 7.278e-01 8.850e-01 1.270e-03 1.545e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 8.928e+03 7.331e-01 8.944e-01 1.279e-03 1.562e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 8.928e+03 7.321e-01 8.937e-01 1.277e-03 1.561e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 8.928e+03 7.331e-01 8.944e-01 1.279e-03 1.562e-03

2 of 2 3/31/2017 3:05 PM



Page O.10 of O.16


Date By Checked

Filename Run Date Run Time DurationNASA 8Sb.msd March 16, 2017 9:22:49 PM 00:00:00


Description 8S - 8" Diameter SteelGeometry 11 - Annular Cylinder - Internal Dose Point






Cyl. Radius .333 ft Air 0.00122Source .685 ft³ Iron 7.86






Results - Dose Point # 1 - (0,0,0) ft



Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.129e+04 3.676e-01 4.492e-01 6.413e-04 7.844e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


1 of 2 3/31/2017 3:08 PM



Page O.11 of O.16

1.0 5.643e+03 2.689e-01 3.328e-01 4.956e-04 6.135e-041.5 5.643e+03 4.267e-01 5.039e-01 7.179e-04 8.478e-04

Totals 1.129e+04 6.956e-01 8.367e-01 1.214e-03 1.461e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.129e+04 7.233e-01 8.775e-01 1.262e-03 1.532e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.129e+04 7.304e-01 8.904e-01 1.274e-03 1.555e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.129e+04 7.307e-01 8.912e-01 1.275e-03 1.556e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.129e+04 7.304e-01 8.904e-01 1.274e-03 1.555e-03

2 of 2 3/31/2017 3:08 PM



Page O.12 of O.16


Date By Checked

Filename Run Date Run Time DurationNASA 11S.msd March 22, 2017 9:04:16 PM 00:00:00


Description 11S - 11.5" Diameter SteelGeometry 11 - Annular Cylinder - Internal Dose Point















Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6 4.671e+00 2.143e-05 3.764e-05 4.184e-08 7.348e-081.0 2.863e+04 2.619e-01 4.161e-01 4.827e-04 7.671e-041.5 2.863e+04 4.483e-01 6.568e-01 7.542e-04 1.105e-03

Totals 5.727e+04 7.101e-01 1.073e+00 1.237e-03 1.872e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6 4.671e+00 4.038e-05 7.010e-05 7.881e-08 1.368e-07

1 of 2 3/31/2017 3:07 PM



Page O.13 of O.16

1.0 2.863e+04 4.910e-01 7.694e-01 9.050e-04 1.418e-031.5 2.863e+04 8.365e-01 1.208e+00 1.407e-03 2.032e-03

Totals 5.727e+04 1.328e+00 1.977e+00 2.312e-03 3.450e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6 4.671e+00 4.220e-05 7.387e-05 8.236e-08 1.442e-071.0 2.863e+04 5.148e-01 8.145e-01 9.490e-04 1.501e-031.5 2.863e+04 8.799e-01 1.283e+00 1.480e-03 2.158e-03

Totals 5.727e+04 1.395e+00 2.097e+00 2.430e-03 3.660e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.727e+04 1.412e+00 2.132e+00 2.460e-03 3.719e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.727e+04 1.414e+00 2.134e+00 2.463e-03 3.724e-03




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 5.727e+04 1.412e+00 2.132e+00 2.460e-03 3.719e-03

2 of 2 3/31/2017 3:07 PM



Page O.14 of O.16


Date By Checked

Filename Run Date Run Time DurationCase1 March 22, 2017 9:31:46 PM 00:00:00

Project InfoCase Title NASA Cyclotron

Description 18SQ - 18" SquareGeometry 13 - Rectangular Volume

Source DimensionsLength 1.27 cm (0.5 in)Width 304.8 cm (10 ft 0.0 in)Height 45.72 cm (1 ft 6.0 in)

Dose PointsA X Y Z#1 24.13 cm (9.5 in) 22.86 cm (9.0 in) 0.0 cm (0 in)#2 24.13 cm (9.5 in) 22.86 cm (9.0 in) 30.48 cm (1 ft)#3 24.13 cm (9.5 in) 22.86 cm (9.0 in) 60.96 cm (2 ft)#4 24.13 cm (9.5 in) 22.86 cm (9.0 in) 121.92 cm (4 ft)#5 24.13 cm (9.5 in) 22.86 cm (9.0 in) 152.4 cm (5 ft 0.0 in)#6 24.13 cm (9.5 in) 22.86 cm (9.0 in) 182.88 cm (6 ft)

ShieldsShield N Dimension Material DensitySource 1080.0 in³ Iron 7.86Air Gap Air 0.00122





X Direction 10Y Direction 20Z Direction 20

Results - Dose Point # 1 - (9.5,9,0) in



Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.029e+04 1.168e-01 1.513e-01 2.037e-04 2.642e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup0.6 8.396e-01 6.617e-06 9.402e-06 1.292e-08 1.835e-081.0 5.147e+03 7.491e-02 9.812e-02 1.381e-04 1.809e-04

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1.5 5.147e+03 1.208e-01 1.494e-01 2.032e-04 2.514e-04Totals 1.029e+04 1.957e-01 2.475e-01 3.413e-04 4.322e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.029e+04 2.185e-01 2.782e-01 3.810e-04 4.859e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.029e+04 2.283e-01 2.932e-01 3.982e-04 5.119e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.029e+04 2.290e-01 2.943e-01 3.994e-04 5.139e-04




Exposure RatemR/hr

No Buildup

Exposure RatemR/hr


Totals 1.029e+04 2.283e-01 2.932e-01 3.982e-04 5.119e-04

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NASA Glenn Research Center Lewis Field Building 140 Cyclotron Vault

Final Status Survey Report Page P.1 of P.36