ML091490105

University of Arizona Nuclear Reactor Laboratory - Radiological Characterization Report

ML091490105
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Site:	05000113
Issue date:	05/20/2009
From:	Myers K Enercon Services
To:	Office of Nuclear Reactor Regulation, Univ of Arizona
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Download: ML091490105 (37)

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. ENERCON Excellence-Every project. Every day.

University of Arizona Nuclear Reactor Laboratory Radiological Characterization Report Nuclear Regulatory Commission Facility Operating License R-52 Prepared For:

University of Arizona I*THE UNIVERSITY

%. OF ARIZONA.

Prepared by:

ENERCON Murrysville, PA 4490 Old William Penn Hwy 2009 Prepared by: Date:

5/20/2009 Reviewed by:

- 5/20/2009 Dustin G. Miller, Health Physicist Approved by: Date:

5/20/2009 Corey D Aitt, Project Manager

ENERCON UA NRLCharacterization Report Rev. 0 Table of Contents ACRONYMS AND ABBREVIATIONS ......................................................................... ii

1. EXECUTIVE

SUMMARY

............................................................................... 1

2. INTRODUCTION ......................................................................................... 2 2.1 PROJECT BACKGROUND.......................................................................... 2 2.2 PURPOSE AND SCOPE .................................................................................. 3

3.

SUMMARY

OF TECHNICAL APPROACH........................................................... 4 3.1 RADIONUJCLIDES OF CONCERN................................................................... 4 3.2 RELEASE CRITERIA............................................................................... 4 3.3 SURVEY DESIGN .................................................................................. 5 3.4 SAMPLE IDENTIFICATION ........................................................................ 5 3.5 SURVEY INSTRUMENTATION..................................................................... 6 3.6 MINIMUM DETECTABLE CONCENTRATION..................................................... 7

4.

SUMMARY

OF RESULTS .............................................................................. 8 4.1 REACTOR CONTROL Room ...................................................................... 8 4.2 REACTOR Room .................................................................................. 8 4.3 EQUIPMENT STORAGE Room .................................................................... 9 4.4 SECOND FLOOR STORAGE Room................................................................ 9 4.5 TRITIUM SMEAR RESULTS ....................................................................... 9

4.6 BACKGROUND

RADIONUJCLIDE MEASUREMENTS................................................10

5. CONCLUSIONS ........................................................................................ 11 List of Tables Table .3-1 NRC License Termination Screening Levels for Surfaces 4 Table 3-2 Survey Instrumentation 6 Table 3-3 Instrumentation MDC 7 Table 4.1 Static Measurement Results - Reactor Control Room 8 Table 4.2 Static Measurement Results - Reactor Room 8 Table 4.3 Static Measurement Results - Equipment Storage Room 9 Table 4.4 Static Measurement Results - Second Floor Storage Room 9 Table 4.5 Tritium Smear Results - All Rooms 10 Table 4.6 Static Measurement Results -Non-Impacted Room I1I1 10 List of Appendices Appendix A - Site Maps Appendix B - UA Nuclear Reactor Laboratory Photographs Appendix C - Radiological Survey Results i

rENERCON UA NRL Characterization Report Rev. 0 List of Acronyms and Abbreviations DCGL Derived Concentration Guideline Level DPM Disintegrations per Minute DQO Data Quality Objectives FSS Final Status Survey MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration Nal Sodium Iodide NRC Nuclear Regulatory Commission NIST National Institute for Standards and Testing NRL Nuclear Reactor Laboratory NUREG Nuclear Regulatory Guide UA University of Arizona USNRC United States Nuclear Regulatory Commission ii

EN ERC N UA NRL Characterization Report Rev.

0

1. EXECUTIVE

SUMMARY

The University of Arizona is currently licensed by the Nuclear Regulatory Commission to operate its Nuclear Reactor Laboratory (NRL) until May 22, 2010. After this date, the University expects to defuel and decommission the NRL, thus terminating NRC license R-52.

The University has initiated development of a Decommissioning Plan in accordance with Chapter 17 of the Nuclear Regulatory Commission (NUREG -1537) Part 1 Guidance for Preparingand Reviewing Applicationsfor Licensing of Non-Power Reactors (NRC 1996). To support development of the Decommissioning Plan, site characterization activities were planned and conducted to assess the levels of radiological activity at the NRL.

The purpose of the characterization was to assess the current radiological status of the facility for the development of the Decommissioning Plan. This data will also be incorporated into the decision-making process for development of Final Status Survey (FSS) Data Quality Objectives (DQOs) and Derived Concentration Guidance Levels (DCGL's) for the NUREG 1575 Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) closeout of the University's Reactor License. Due to ongoing reactor operations, the scope of the characterization was limited to facility areas outside the reactor pit, its associated components and operations systems.

The survey was designed to determine whether or not elevated levels of radioactive material contamination were present in the radiologically impacted rooms of the NRL. In each radiologically impacted room, professional judgment was used to select locations that may have increased potential to be radiologically contaminated. These locations were then surveyed for total alpha, total beta, removable alpha, and removable beta. Additional sample locations were selected to investigate the presence of tritium 1. General area gamma radiation dose rates were also collected.

The radiological characterization surveys showed that there were no radiologically contaminated areas outside of the reactor pool that are greater than the potential release criteria.

1

SE N E R CON UA NRL Characterization Report Rev. 0

2. INTRODUCTION 2.1 Project Background The University of Arizona is currently licensed by the Nuclear Regulatory Commission to operate its Nuclear Reactor Laboratory (NRL) until May 22, 2010. After this date, the University expects to defuel and decommission the NRL, thus terminating NRC license R-52.

The University has initiated development of a Decommissioning Plan in accordance with Chapter 17 of the Nuclear Regulatory Commission (NUREG -1537) Part 1 Guidance for Preparingand Reviewing Applicationsfor Licensing of Non-Power Reactors (NRC 1996). To support development of the Decommissioning Plan, site characterization activities were planned and conducted to assess the levels of radiological activity at the NRL.

This report describes the purpose, scope and technical approach used during the characterization of the four rooms of the University of Arizona (UA) Nuclear Reactor Laboratory (NRL). These four rooms comprise the controlled area described in the Nuclear Regulatory Commission (NRC)

Reactor License R-52. The purpose of the characterization was to assess the current radiological status of the facility for the development of the Decommissioning Plan. This data will also be incorporated into the decision-making process for development of Final Status Survey (FSS)

Data Quality Objectives (DQO's) and Derived Concentration Guidance Levels (DCGL's) for the NUREG 1575 Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) closeout of the University's Reactor License. Due to ongoing reactor operations, the scope of the characterization was limited to facility areas outside the reactor pit, its associated components and operations systems. A more extensive evaluation will be required following shutdown of the UARR and completion of nuclear fuel removal activities.

The University of Arizona (UA) Research Reactor is a TRIGA pool-type reactor designed and constructed by General Atomic Division of General Dynamics Corporation. The reactor is located within the NRL on the 325 acre campus of the University of Arizona in Pima County Arizona in the city of Tucson. The University is about 65 miles north of the Mexican Border at Nogales, AZ, 110 miles south east of Phoenix, AZ and 120 miles from the western border of New Mexico. The campus is centrally located in the city of Tucson, Arizona, and is bounded roughly by East Speedway Boulevard, North Campbell Avenue, East Sixth Street, and North Park Avenue.

The NRL is located on the first floor of the north wing of the Engineering Building (Building 20) on the University's Main Campus as shown in Appendix A. The reactor core is located in a swimming pool type tank that is 21 feet deep and 6.5 feet in diameter, located below grade in Room 124. The tank contains approximately 5,000 gallons of demineralized water. The reactor fuel consists of standard stainless-steel clad TRIGA fuel elements, instrumented elements, and fuel followers for the control rods. The U-235 enrichment of the fuel is less than 20 percent.

Irradiated fuel is located either in the reactor core or in safe geometry storage racks in the reactor pool.

Four adjacent rooms in the Engineering Building are permanently established as the Reactor Laboratory and are designated a controlled access area. These are: Room 122, the Reactor 2

F ENERCON UA NRL Characterization Report Rev. 0 Control Room; Room 124, the Reactor Room; Room 124A, Equipment Storage and Experiment Setup Room; and Room 216, Second Floor Storage Room.

The reactor was constructed in 1958 and went into operation on December 6 th of that year. The licensed power was 10 kw thermal with operations of 30 kw possible for short times. The original core loading consisted of 61 aluminum-clad fuel elements and two additional aluminum-clad fuel elements were obtained and the facility was licensed to allow operations at 100 kw.

There is no history of major accidents or spills. In 1974, a crack was discovered in the cladding of a fuel element, however, there were no releases of long lived fission products or nuclear fuel from the fuel element.

2.2 Purpose and Scope

The data collected during this characterization will be utilized to support the development of radiological waste volume estimates; methodologies for removal and packaging of radiological waste; and disposal options for radioactively impacted materials generated during decommissioning activities conducted under NRC License R-52. This data will also be incorporated into the decision-making process for the development of Final Status Survey (FSS)

Data Quality Objectives (DQO's) and Derived Concentration Guidance Levels (DCGL's) for the NUREG 1575 MARSSIM closeout of the UA Reactor License.

The scope of the UA NRL characterization effort was limited to building surfaces, i.e. floors, walls, windows, storage pits, etc. The reactor was not intrusively characterized because it remains in operation; however, a component activation analysis was performed by modeling the neutron flux of the reactor and its effect on reactor components. This information can be found in the UA Decommissioning Plan. Subsurface soil contamination is not expected based upon facility operating history. Soil samples were not collected during this characterization effort because the reactor is currently operational.

3

UA NRL Characterization Report K, ENERCON Rev. 0

3.

SUMMARY

OF TECHNICAL APPROACH 3.1 Radionuclides of Concern Based upon facility operating history, tritium and beta/gamma emitting radionuclides are the radionuclides of concern identified for the characterization effort. Historical operational data and historical radiological survey data did not indicate that alpha emitting radionuclides are present in the NRL facility. Specifically, there has been no fuel leaks at the facility, no elevated radioactive material measurements from the resin in the demineralizer system, and no indications of alpha contamination on historical surveys. Alpha measurements were, however, collected simultaneously with beta/gamma measurements for informational purposes.

3.2 Release Criteria For the UA characterization effort, two sets of release criteria were considered. For the unrestricted release of building surfaces during the final status survey, USNRC License Termination Screening Levels were considered. For the unrestricted release of material and equipment prior to a final status survey, criteria from USNRC Regulatory Guide 1.86 were considered. The USNRC License Termination Screening Levels are listed in Table 3-1 below:

Table 3-1 NRC License Termination Screenine Levels for Surfaces Radionuclide Acceptable Screening Levels for Unrestricted Release (dpm/1OOcm 2)

Tritium (H-3) 1.2E+08 Carbon-14 3.7E+06 Manganese-54 3.2E+04 Iron-55 4.5E+06 Cobalt-60 7.1E+03 Nickel-63 1.8E+06 Technitium-99 1.3E+06 Cesium- 137 2.8E+04 The release criteria in USNRC Regulatory Guide 1.86 for the unrestricted release of materials and equipment is 5000 dpm/100cm 2 for all radionuclides listed in table 3-1. This criteria was considered when calculating the instrumentation counting sensitivities in Section 3.1.6.

Both release criteria bear consideration during evaluation of the data collected during the characterization effort for the development of the UA Decommissioning Plan. Comparison to the release criteria for building surfaces is important for remediation strategies and for developing the final status survey. The release criterion for material and equipment is important for estimating the quantity of material and equipment that will be disposed of as radioactive waste.

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ENERCON UA NRL Characterization Report Rev. 0 3.3 Survey Design The survey was designed to determine whether or not elevated levels of radioactive material contamination were present in the radiologically impacted rooms of the NRL. In each radiologically impacted room, professional judgment was used to select locations that may have increased potential to be radiologically contaminated. These locations were then surveyed for total alpha, total beta, removable alpha, and removable beta. Additional sample locations were selected to investigate the presence of tritium 1. General area gamma radiation dose rates were also collected.

Four rooms, 122, 124, 124 A and room 216, were identified as impacted rooms. Twenty-five (25) non-systemic, biased, random locations on the floors, walls, drains and drawers were identified in each of the impacted rooms. Smears were collected at these points for gross alpha/beta analysis.

In each of the identified locations in the impacted rooms, a static gross alpha/beta measurement was collected. In addition to the alpha/beta smears and static readings, a smear was collected for the evaluation of potential tritium contamination. This smear was collected in different locations that the static measurement and was analyzed using the University of Arizona Liquid Scintillation Counter using a UA RCO approved protocol.

The UA Systems and Industrial Engineering Department Administrative Office, Room 111, was selected to provide a reference of the background radiation that may be in the building materials at UA. It is located in the same building and is not associated with the physical activities conducted under any license held by UA for the possession and use of radioactive material. Five locations on the walls and floor Were selected by professional judgment. At each location, a smear was collected for gross alpha/beta analysis and a static gross alpha/beta measurement was collected. A general area exposure rate reading was also collected.

The status of these rooms at the time of the survey is documented in the photographs in Appendix B.

3.4 Sample Identification During the investigation, a consistent identification system was used to ensure both the uniqueness and clarity in evaluation location and an identification of data collected. This section describes the protocol that was employed in naming the evaluation locations. Each location was assigned a unique identifier that included:

• Room Number - identified by an R followed by the room number

" Building Surface o FL for Floor 5

ENERCON UA NRL Characterization Report Rev. 0 o NW for North Wall o SW for South Wall o EW for East Wall o WW for West Wall

• Unique Sequential Number This resulted in a unique identifier for each element evaluation in the following format in which:

" XXX is the three letter number combination designating the room where the evaluation was made.

" YY is the two letter designation for the surface on which the evaluation was made.

0 000 is a sequential number for the designated room.

RXXX-YY-000 3.5 Survey Instrumentation Radiological survey instrumentation was selected to ensure that sensitivities were sufficient to detect the expected radionuclides at the minimum detection requirements. The instrumentation was calibrated in accordance with approved procedures to NIST traceable standards. The calibration was checked daily using Th-230 and Tc-99 for alpha and beta/gamma measurements, respectively. A list of the survey instrumentation, along with the type of radiation detected, calibration sources, and the instrument use, is provided in Table 3-2.

Table 3-2 Survey Instrumentation Instrument Radiation Calibration Detector Type Detected Source Use Ludlum Model 2360 Ludlum Model 43-89 ZnS Alpha/Beta Th-230/Tc-99 Surface static coated Plastic Scintillator measurements (126 cm 2 area)

Ludlum Model 19 Internal Nal Gamma Cs- 137 General area exposure rates Ludlum Model 2929 Ludlum Model 43-10-1 Alpha/Beta Th-230/Tc-99 Swipe/smear I ZnS internal detector I I counting 6

ENERCON E UA NRL Characterization Report Rev. 0 3.6 Minimum Detectable Concentration The minimum detectable concentration (MDC) is the concentration of radioactivity that an instrument can be expected to detect at a 95 percent confidence level. For instruments performing direct measurements and for laboratory analyses, the MDC goal was 10-50% of applicable release criteria.

For static (direct) surface measurements, with conventional detectors, the MDC was calculated using the formula:

MDC (dpm/IOOcm )

2 !3+ 3.29 (RbXT Xl+T/Tb),

Variables:

Rb = Background count rate (cpm)

Tb = Background count time (min)

Td = Sample Run Time (min)

T, = Sample Count Time (min)

= Total Instrument Efficiency (MARSSIM section 6.6.1)

The data used to calculate the MDCs for the instrumentation used during the UA characterization effort are shown on the survey records in Appendix C. The a priori MDCs are listed in Table 3-3 below:

Table 3-3 Instrumentation MDC Instrument Detector Type Radiation Detected MDC CM)

Ludlum Model 2360 Ludlum Model 43-89 Alpha 154 Beta 1351 Ludlum Model 2929 Ludlum Model 43-10-1 Alpha 21 Beta 235 7

ENERCON UA NRL Characterization Report Rev. 0

4.

SUMMARY

OF RESULTS The following sections summarize the results of the radiological characterization effort. Per MARSSIM guidance all measurement results, whether positive, negative, or less than MDC, were included in the calculations of the mean, maximum, and standard deviation. The results are summarized by room, except for the removable tritium smears because they were collected as one group throughout the NRL.

The radiological survey records can be found in Appendix C.

4.1 Reactor Control Room The Reactor Control Room, Number 122, contained no elevated measurements of radioactive materials. The room was surveyed for total alpha, total beta, tritium, removable alpha, and removable beta. Table 4.1 below summarizes the total alpha and total beta results. Twenty-five (25) biased building surface locations were selected. In addition, five additional locations were selected, i.e. lights, trim, and window ledges, etc. All measurements, total and removable, were less than the calculated MDC for each respective measurement. Table 4.1 below summarizes the total alpha and total beta results.

Table 4.1 Static Measurement Results - Reactor Control Room Alpha (dpm/100cm 2) Beta (dpm/100cm2 )

1. Meas. Mean Max Std Dev Mean Max Std Dev 27 11 55 24 320 1369 438 4.2 Reactor Room The Reactor Room, Number 124, contained no elevated measurements of radioactive materials. The room was surveyed for total alpha, total beta, tritium, removable alpha, and removable beta. Table 4.2 below summarizes the total alpha and total beta results.

Table 4.2 Static Measurement Results - Reactor Room Alpha (dpm/100cm 2) Beta (dpm/100cm 2)

1. Meas. Mean Max Std Dev Mean Max Std Dev 29 24 111 35 253 2277 742 8

ItNll ENERCON UA NRIL Characterization Report Rev. 0 4.3 Equipment Storage Room The surfaces of the Storage Room, Room 124A, contained no elevated measurements of radioactive materials. The room was surveyed for total alpha, total beta, tritium, removable alpha, and removable beta. Table 4.3 below summarizes the total alpha and total beta results.

Elevated reading were measured for both the exposure rates and the static measurements, however, the results were attributed to shine from radioactive sources stored in this room.

Table 4.3 Static Measurement Results - Equipment Storage Room Alpha (dpm/100cm2 ) Beta (dpm/100cm 2 )

1. Meas. Mean Max Std Dev Mean Max Std Dev 25 37 111 42 2293 6899 1625 4.4 Second Floor Storage Room The Second Floor Storage Room, Number 216, contained no elevated measurements of radioactive materials. The room was surveyed for total alpha, total beta, tritium, removable alpha, and removable beta. Elevated exposure rates were measured and attributed to shine from the reactor below which also affected the static measurement results.

Table 4.4 below summarizes the total alpha and total beta results.

Table 4.4 Static Measurement Results - Second Floor Storage Room Alpha (dpm/1O0cm 2) Beta (dpm/1OOcm 2)

1. Meas. Mean' Max Std Dev Mean Max Std Dev 24 32 111 33 891 2772 910 4.5 Tritium Smear Results Smears for tritium were collected in Rooms 124, 124A, and 122. The smears were submitted to the UA Radiation Control Office for analysis. The smears were counted on a Packard Model 2800 Liquid Scintillation Counter. The highest smear result for tritium, 605 dpm/1OOcm2, was collected from Pit #1. The tritium smear results do not have natural and/or instrument induced backgrounds subtracted from the results. In addition, an MDC was not provided by the UA RCO for the tritium results.

Table 4.5 below summarizes the tritium results.

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jENERCON UA NRL Characterization Report Rev. 0 Table 4.5 Tritium Smear Results - All Rooms 2

Alpha (dpm/1OOcm )

1. Meas. Mean Max Std Dev 25 76 605 114 4.6 Background Radionuclide Measurements Surface measurements were collected in a non-impacted room to provide reference data on the natural background of the interior building surfaces at UA. Surface activity measurements were performed in an area where radioactive materials have not been used or suspected to be present based on historical knowledge. The non-impacted room that was chosen was the UA Engineering Department Administrative Office, Room 111. The results of the natural background measurements for the interior building surfaces at UA are presented in the Table 4-6 below.

Table 4.6 Static Measurement Results - Non-Impacted Room 111 Alpha (dpm/ 1OOcm 2 ) Beta (dpmr/100cm 2)

Area Mean Max Std Dev Mean Max Std Dev Floor -1 -1 N/A 296 296 N/A Walls 97.2 111 28 833 1784 889 All 78 111 50 726 1784 806 10

N milt, CUA NRL Characterization Report Rev. 0

5. CONCLUSIONS In conclusion, the radiological characterization surveys showed that there were no radiologically contaminated areas outside of the reactor pool that are greater than both release criteria stated in Section 3.1.2. Two measurements in Room 124A, Equipment and Storage Room, were greater than the material and equipment release criteria established in USNRC Regulatory Guide 1.86.

The measurements were 6164 and 6907 dpm/100 cm 2, compared to the release criteria of 5000 dpm!100 cm 2. Room 124A contained several radioactive sources which elevated the background radiation levels which skewed the results. The gamma radiation exposure rate measurements for this room verify this conclusion.

Almost all radiological measurements on the floors, walls, and equipment surfaces were less than the a prioriMDC in Section 3.1.6. Except for the two results for Room 124A mentioned above, measurement results greater than the MDC are a small fraction of the anticipated release criteria for building surfaces and may be attributed to radiation shine from the reactor core. Another factor that may attribute to measurements being greater than the MDC is the natural background radiation in the building materials. This is evident by the results of the measurements collected in the non-impacted room, Room 111.

The characterization data collected will be used, in conjunction with historical data, to support the UA Decommissioning Plan and subsequent final status surveys.

Since the facility remains in operation, a final characterization effort of the reactor pool and residual components should be performed once reactor operations have ceased and the nuclear fuel has been transferred off site. The radiologically impacted rooms of the NRL should be resurveyed in the event a radioactive material release is detected during the final year(s) of operation and subsequent off site nuclear fuel movement.

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ENERCON UA NRL Characterization Report Rev. 0 Appendix A Site Maps 12

0 ENERCON UA NRL Characterization Report Rev. 0 Location of UA NRL on the campus of The University of Arizona 13

UA NRL Characterization Report 0 ENERCON Rev. 0 LEGEND

=--] NRL IMPACTED AREAS FUM ROOM 164 NUC" CROMWRY LA3ORATOWi ROOM 163 Location of the NRL rooms in the Northwest Comer of the UA Engineering Building.

Room 216A/B is located directly above Room 124.

14

ENERCON UA NRL Characterization Report Rev. 0 Appendix B UA Nuclear Reactor Laboratory Photographs 15

UARR Room 122 Photographs Room 122 East Wall North End Room 122 South Wall Room 122 East Wall South End Room 122 West wall North End Room 122 North Wall Room 122 West Wall South End

UARR Room 124 Photographs Room 124 Reactor Bridge Room 124 Reactor Bridge looking northeast Room 124 North wall showing general exhaust fan Room 124 Double door access to/from outside North Wall Room 124 ceiling penetration into Room 216 Rm 124 East Wall

UARR Room 124 Photographs ealei Room 124 general exhaust fan on North wall Room 124 West Wall and ccess to vacuum pump pit Room 124 Radiography Tube Room 124 Vacuum Pump Pit Room 124 North Wall Room 124 Reactor Pool wall seen from vacuum pump pit

UARR Room 124 Photographs Room 124 South Wall - Long handle tools and vent Room 124 Storage Pits Room 124 South Wall East End Room 124 West Wall Emergency HEPA exhaust Room 124 South Wall West End Reactor Pool North side Neutron Beam and Demin Piping

UARR Room 124 Photographs Reactor Pool North side pool skimmer Reactor Wire and Cable Conduits SW comer of Reactor Reactor pool South Side Rm 124 PIT 2 - Carbon Rods Reactor Pool South side Rm 124 PIT 3 - MT

UARR Room 124 Photographs Rm. 124 PIT 6 - Shielded pig for old Co-60 source Rm 124 Pit No. I - Unirradiated fuel rods

UARR Room 124A Photographs Room 124A East Wall North End Room 124A West Wall North End Room 124A East Wall South End Room 124A West wall South End Room 124A North Wall

"ENERCON UA NRL Characterization Report Rev. 0 APPENDIX C Radiological Survey Reports 17

0 Purpose of RADIOLOGICA&RVEY REPORT Survey : Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona RoomNumber Rm I111 - Eng. Dept. Admin Surveyed by: Kurt Myers Reviewed By: Dustin Miller I u Nme Dfta'Wf. * .... m* Date: 2/4/2009 Ludlum M2360 248155 10/3/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 Cm2 Ludlum M2929 Ludlum M19 182671 3122/2009 Internal N/A N/A N/A N/A 11.5 uR/hr (gamma only) N/A Batch # N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Misc.

Remarks: All count times 0. 1 minute duration. exc 10 minutes. This room was surveyed for bac.

0 Purpose of RADIOLOGICJRVEY REPORT I': RoomNVumlber:

• i]I 0

Survey : Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona IRm 122 - Reactor Control Rm Surveyed by: Kurt Myers Reviewed By: Dustin Miller Instrument Probe.......A...........e.... ..... ........ Idpmj Date: 2/4/2009 Ludlum M2360 248155 10/3/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 2

15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 Cm Ludlum M2929 180832 5/17/2009 43-10-1 Ludlum M19 182671 3/22/2009 Internal N/A N/A N/A N/A 11.5 uR/hr (gamma only) NIA Batch# N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A N/A N/A N/A N/A NIA N/A N/A N/A NIA N/A Misc.

Remarks: All count times 0.1 minute duration. exc  : BKGD at 10 minutes. Sample locations measured from SW comer for floors and bottom left comer for walls.

1 FL001 11.5 1 0 -0.3 102 56.5 0 -1.1 300 130.6 2 2 FL002 9.5 10 0 -0.3 66 -85.8 0 -1.1 330 378.5 3 FL003 9.5 15.5 0 -0.3 50 -149.0 0 -1.1 290 47.9 4 FL004 2.7 10 0 -0.3 94 24.9 0 -1.1 310 213.2 5 FLOO5 2 6 0 -0.3 102 56.5 0 -1.1 320 295.9 6 NW006 Rad Monltors NE Comer 0 -0.3 96 32.8 0 -1.1 360 626.4 7 NW007 Window 0 -0.3 90 9.1 0 -1.1 310 213.2 8 NW008 7 6 0 -0.3 52 -141.1 0 -1.1 320 295.9 9 NW009 3 6.5 0 -0.3 96 32.8 0 -1.1 400 957.0 10 NW010 Computer Monitor 0 -0.3 70 -70.0 10 55.1 430 1205.0 11 EW011 15.5 6.5 0 -0.3 94 24.9 10 55.1 350 543.8 12 EW012 14.5 7.5 0 -0.3 90 9.1 0 -1.1 310 213.2 13 EW013 Window Sill (Middle) 0 -0.3 70 -70.0 0 -1.1 200 -695.9 14 IEW014 4 2.5 0 -0.3 102 56.5 0 -1.1 350 543.8 15 EW015 1.5 5.5 0 -0.3 84 -14.6 0 -1.1 280 -34.7 16 ww oi6 15.5 4.5 0 -0.3 82 -22.5 0 -1.1 360 626.4 17 WW017 12 7 0 -0.3 92 17.0 0 -1.1 310 213.2

RADIOLOGIC RVEY REPORT Purpose of Survey: Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona Room Numbe Rm 122 - Reactor Control Rm.

Surveyed by: Kurt Myers Reviewed By: Dustin Miller Seril Clibatio Prbe robe AraAphlh Apae.ta. kgd Bet . Bt Date: 2/4/2009 Ludlum M2360 248155 10/3/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 2

5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm Ludlum M2929 180832 Ludlum M19 182671 3/22/2009 Internal N/A NIA N/A N/A 11.5 uR/hr (gamma only) NIA Batch # N/A N/A NIA N/A N/A N/A N/A N/A N/A NIA N/A N/A RWP: N/A N/A N/A N/A N/A N/A NIA N/A NIA N/A NIA N/A Misc.

Remarks: All count times 0.1 minute duration. exc  : BKGD at 10 minutes. Sar e locations measured from SW comer for floors and bottom left comer for walls.

isIWW018 19 WWO19 7.5 4.8 6.5 6.5 1

0 2.4

-0.3 92 72 17.0

-62.1 0

10

-1.1 55.1 310 450 213.2 1370.2 i

20 WW020 1.5 5.3 0 -0.3 80 -30.4 10 55.1 290 47.9 21 SW021 12.5 6 0 -0.3 37 -200.4 10 55.1 330 378.5 22 sw 022 9 3.3 0 -0.3 96 32.8 0 -1.1 300 130.6 23 Sw 023 6 7 0 -0.3 72 -62.1 0 -1.1 350 543.8 24 sw024 1.5 7 0 -0.3 106 72.3 0 -1.1 360 626.4 25 SW 025 4.5 3 0 -0.3 50 -149.0 10 55.1 250 -282.6 26 CL 026 Vent 0 -0.3 70 -70.0 0 -1.1 310 213.2 27 CL 027 SW Light 0 -0.3 96 32.8 N/A N/A N/A N/A 28 CL 028 NE Light 0 -0.3 62 -101.6 N/ N/A N/A N/A_

29 CL 029 E Window Ledge 0 -0.3 54 -133.2 N/A N/A N/A N/A 30 CL 030 NW Window Top 0 -0.3 98 40.7 0 -1.1 240 -365.3 31 NIA N/A N/A N/A N/A N/A N/A N/A N/A 32 N/A N N/A N/A N/A N/A N/A N/A N/A 33 N/A N/A N/A N/A N/A N/A N/A N/A N/A 11/1 1 t%

34 NA N/Ai N/A !i!!~ii!N/A N/A N/A N/A N/A N/A N/A I N/A N/A I I N/A N/A I I

N/A N/A N/A N/A N/A N/A 34 jN/A N/A

RADIOLOGIC*RVEY REPORT Purpose of I I Survey : Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona I Room~ Num~ber Rm 124 - Reactor Room Surveyed by: Kurt Myers Reviewed By: Dustin Miller

_tC iAAlBB Beta &DA Date: 2/4/2009 Ludlum M2360 248155 1013/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 2

Ludlum M2929 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm Ludlum M19 182671 3/22/2009 Internal N/A N/A N/A N/A 11.5 uR/hr (gamma only) N/A Batch # N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Misc.

I. ).1 minute duration, except BKGD at 10 minutes. Sample locations measured from SW comer for floors and bottom left corner foi 1 INW001 25 5.5 0 -0.3 78 -38.3 0 -1.1 420 1122.3 2 NW002 21.5 7 0 -0.3 80 -30.4 0 -1.1 420 1122.3 3 NW 003 18 6.5 0 -0.3 95 28.9 0 -1.1 380 791.7 4 NW 004 15.5 3 0 -0.3 92 17.0 10 55.1 260 -200.0 5 NW 005 10.5 6 0 -0.3 80 -30.4 0 -1.1 370 709.1 6 EW ow 5.3 5.3 0 -0.3 70 -70.0 0 -1.1 240 -365.3 7 EW007 8.5 5.3 0 -0.3 72 -62.1 10 55.1 480 1618.2 8 EW008 12.5 4.5 0 -0.3 82 -22.5 10 55.1 240 -365.3 N 9 EW009 16.3 5 0 -0.3 88 1.2 10 55.1 240 -365.3 N 10 EW010 Handling Tools In Rack >6ft 0 -0.3 74 -54.2 10 55.1 450 1370.2 N 11 SWO11 Behind Cabinet SE Comer 0 -0.3 90 9.1 10 55.1 390 874.4 N 12 SW012 6 6 0 -0.3 94 24.9 0 -1.1 320 295.9 N 13 SWO13 11 7.5 0 -0.3 76 -46.2 0 -1.1 240 -365.3 N 14 SW014 19.5 7.5 0 -0.3 76 -46.2 0 -1.1 300 130.6 N 15 SW015 26 6 0 -0.3 72 -62.1 0 -1.1 330 378.5 N 16 WWI016 Window Sill Right 0 -0.3 104 64.4 10 55.1 280 -34.7 N 17 WW017 17 6 0 -0.3 94 24.9 0 -1.1 300 130.6 N

0 Purpose of RADIOLOGICeRVEY REPORT Survey: Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona IRoom Number: Rm 124 - Reactor Room Surveyed by: Kurt Myers Intrmet.6218 Clbaion Prob meAe lh Reviewed By:St&Bg Dustin e&Ef.Bt ApaMA Miller Date:

Number A Due Btgd tafmf Mom) 2/4/2009 Ludlum M2360 248155 10/3/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm 2 Ludlum M2929 180832 5/17/2009 Ludlum M19 182671 3/22/2009 Internal N/A N/A N/A N/A 11.5 uRlhr (gamma only) NIA Batch # N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A NIA N/A N/A NIA N/A N/A N/A N/A N/A N/A Misc.

Remarks: All count times 0. 1 minute duration. exc t BKGD at 10 minutes. Sample locations measured from SW comer for floors and 18 wwo18 15 8 0 -0.3 110 88.1 0 -1.1 210 -613.2 N/A I N/A Above Frisker 19 WWO19 7 6 0 -0.3 76 -46.2 10 55.1 290 47.9 I

20 WW 020 2 6.3 0 -0.3 78 -38.3 0 -1.1 200 -695.9 N/A 21 IFLO21 I 17 0 -0.3 84 -14.6 0 -1.1 220 -530.6 4 22 IFL022 Bridge at Lazy Susan Port 0 -0.3 128 159.3 0 -1.1 210 -613.2 4 23 FL023 25 14 0 -0.3 90 9.1 0 -1.1 290 47.9 Under Exp table 24 FL 024 Pit 3 Lid 0 -0.3 86 -6.7 10 55.1 320 295.9 5 25 FL025 13 1 0 -0.3 82 -22.5 0 -1.1 210 -613.2 4 26 CL 026 FAN 2 5.1 90 9.1 20 111.2 350 543.8 N/A N/A 27 CL027 HEPAL 0 -0.3 92 17.0 20 111.2 560 2279.3 N/A N/A 28 CL028 HEPAR 0 -0.3 84 -14.6 NI/A N/A N/A N/A N/A N/A 29 CL029 HEPA LEDGE 0 -0.3 76 -46.2 0 -1.1 320 295.9 N/A N/A, 30 CL 030 Crane 0 -0.3 86 -6.7 0 -1.1 290 47.9 N/A N/A 31 PIT 031 Pit1 0 -0.3 106 72.3 N/A N/A N/A N/A N/A N/A 32 PIT 032 Pit 2 0 -0.3 55 -129.2 N/A N/A IN/A I N/A N/A N/A 33 PIT 033 Pit3 0 -0.3 60 -109.5 N/A N/A N/A [ N/A N/A 34 P6T o34 Pit 4 0 -0.3 90 9.1 N/A N/A N/A N/A N/A N/A 34 IPrro34 PIt 4 0 -0.3 90 9.1 N/A N/A N/A N/A

0 Purpose of RADIOLOGIC* RVEY REPORT 1 1 Survey: Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona Room Numbe Rm 124 - Reactor Room Surveyed by: Kurt Myers Reviewed By: Dustin Miller

_________ Calib n P. BDate: 2/4/2009 Ludlum M2360 248155 1013/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 Cm2 Ludlum M2929 Ludlum M19 182671 3/22/2009 Internal NIA NIA NIA NIA 11.5 uR/hr (gamma only) N/A Batch # N/A N/A N/A N/A NIA N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A N/A N/A N/A N/A NIA NIA N/A N/A N/A N/A Misc.

- IA oily 35 PIT 035 Pit 5 10 I

1 -0.3 1 I

96 1 32.8 N/A N/A 36 PIT 036 Pit 6 1 0 1 -0.3 1 90 1 9.1 N/A N/A 37 Vacuum pump pit - pneumatic pump cage -1.1 26 -2133.9 N/A 2 38 Vacuum pump pit -Conduit below floor -1.1 29.0 -2109.1 NA 2 I

39 N/A N/A NI/A N/A 40 N/A N/A N/A N/A 41 N/A N/A N/A N/A 42 NIA N/A N/A N/A 43 N/A N/A N/A N/A 44 N/A N/A N/A N/A 45 N/A N/A N/A N/A 46 N/A N/A N/A N/A 47 N/A N/A N/A N/A 48 N/A N/A N/A N/A 49 NIA N/A I N/A N/A N/A N/A I.

• I-50 N/A N/A I N/A N/A N/A N/A 51 N/A N/A I N/A NIA N/A N/A

RADIOLOGIC*RVEY REPORT Survey: Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona Room Nu r Rm 124A - Equipment Storage Surveyed by: Kurt Myers Reviewed By: Dustin Miller lv , etagd U (dy Date: 2/4/2009 Ludlum M2360 248155 10/31/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A Ludlum M2929 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm2 Ludlum M19 182671 3/22/2009 Internal N/A N/A N/A N/A 11.5 uR/hr (gamma only) N/A Batch# N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A N/A N/A N/A N/A N/A N/A N/A NIA I N/A N/A Misc.

a h -

_____________________ I __________ .L A I

All count times 0. 1 minute duration. excent BKGD at 10C arnd hnttnm left rnrnrr fnr wnllQ I

1 NW 001 12.5 5.5 0 -0.3 55 -129.2 0 -1.1 490 1700.8 2 NW 002 10 5.5 0 -0.3 90 9.1 20 111.2 790 4180.2 3 NW 003 9.5 3 0 -0.3 86 -6.7 0 -1.1 500 1783.5 4 NW 004 5 5 0 -0.3 76 -46.2 0 -1.1 400 957.0 5 NW 005 3 5 0 -0.3 98 40.7 10 55.1 650 3023.1 6 EW006 2 5 0 -0.3 94 24.9 10 55.1 460 1452.9 7 EW 007 Storage Metal Shelf Middle 0 -0.3 90 9.1 0 -1.1 410 1039.7 8 EW 008 9 4 0 -0.3 48 -156.9 10 55.1 650 3023.1 9 EW 009 13.5 4 0 -0.3 92 17.0 20 111.2 600 2609.9 10 EW010 15.5 4.5 0 -0.3 82 -22.5 10 55.1 470 1535.5 11 SWO11 12 5.5 0 -0.3 104 64.4 0 -1.1 610 2692.6 12 SWO12 9 5 0 -0.3 108 80.2 0 -1.1 710 3519.0 13 SW013 Top of Meter Box 0 -0.3 96 32.8 0 -1.1 330 378.5 14 SWO14 6.5 5 0 -0.3 90 9.1 0 -1.1 490 1700.8 15 SWO15 Circuit Breaker Panel 0 -0.3 104 64.4 0 -1.1 380 791.7 16 WW 016 Sink 0 -0.3 96 32.8 10 55.1 350 543.8 17 WW017 3 5 0 -0.3 94 24.9 10 55.1 600 2609.9

0 Purpose of RADIOLOGIC*RVEY REPORT I1 Survey: Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona IRoom Number: Rm 124A - Equipment Storage Surveyed by: Kurt Myers seia Celbao Prb Are A lpha Reviewed KD By: Dustin Miller

.......- Beta MDAi u Number D Probe Date: 2/4/2009 Ludlum M2360 248155 10/312009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A Ludlum M2929 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm 2 Ludlum M19 182671 3/22/2009 Internal N/A N/A N/A N/A 11.5 uR/hr (gamma only) N/A Batch# N/A N/A N/A N/A N/A NIA NIA N/A NIA N/A N/A N/A RWP: N/A N/A N/A N/A N/A NIA N/A N/A N/A N/A N/A N/A Misc.

i V.- ,,,+ +4,*-,- 1 s measured from SW comer for floors and bottom left comer for walls.

1s IWW018 9 5.5 0 -0.3 94 24.9 0 -1.1 560 2279.3 19 WW019 13.5 5 0 -0.3 96 32.8 10 55.1 650 3023.1 20 WW 020 Front top of locker NW Comer 0 -0.3 54 -133.2 0 -1.1 320 295.9 I 21 FL021 2.5 16 1 2.4 86 -6.7 10 55.1 1030 6163.6 84 Asbestos Tile 22FL 022 2.5 6.5 0 -0.3 84 -14.6 20 111.2 500 1783.5 I 16 On Landing 23FL 023 10 10.5 0 -0.3 82 -22.5 0 -1.1 560 2279.3 10 24FL 024 7 7 0 -0.3 94 24.9 20 111.2 1120 6907.4 I 23 25 IFL025 3.5 2 n -n *q 24.9 10 55.1 420 1122.3 1 N/A 26 Top of Subcritical Assembly N/A N/A 369 27 Top of Shield Blocks N/A N/A 79 28 N/A N/A N/A N/A 29 N/A N/A N/A N/A 30 NIA N/A N/A N/A 31 NIA N/A N/A N/A I  ! I 32 NIA N/A N/A N/A N/A N/A 33 NIA N/A N/A N/A N/A N/A 34 N/A N/A N/A N/A I N/A I N/A

Purpose of RADIOLOGICJRVEY REPORT I

0 Survey : Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona Room Number IRm 216A/B - 2nd Floor Storage Surveyed by: Kurt Myers Reviewed By: Dustin Miller Insbu.e.. Number Due Date: 2/4/2009 Ludlum M2360 248155 10/3/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A Ludlum M2929 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm2 Ludlum M19 182671 3/22/2009 Internal N/A N/A NIA N/A 11.5 uR/hr (gamma only) N/A Batch # N/A N/A N/A N/A N/A N/A N/A NIA N/A N/A N/A NIA RWP: N/A NIA N/A N/A N/A N/A N/A N/A N/A N/A I N/A N/A Misc.

Remarks: All count times 0.1 minute duration 1 INWo01 13 6 0 -0.3 41 -184.6 10 55.1 430 1205.0 2 NW 002 9.75 3 0 -0.3 48 -156.9 20 111.2 380 791.7 3 NW 003 4.3 5.1 0 -0.3 39 -192.5 10 55.1 390 874.4 4 NWO04 2x4 0 -0.3 108 80.2 10 55.1 220 -530.6 5 NW005 HVPS 0 -0.3 126 151.4 10 55.1 270 -117.4 6 EW 006 Shelf 1 2.4 84 -14.6 0 -1.1 460 1452.9 7 EW 007 Shelf 0 -0.3 72 -62.1 10 55.1 160 -1026.4 8 EW008 15 4 0 -0.3 94 24.9 10 55.1 550 2196.7 9 EW 009 7 5 0 -0.3 106 72.3 0 -1.1 320 295.9 10 W010 6 Not given 0 -0.3 96 32.8 0 -1.1 410 1039.7 11 SWO11 10 6 0 -0.3 52 -141.1 0 -1.1 420 1122.3 12 SWO12 3.5 6 0 -0.3 76 -46.2 0 -1.1 390 874.4 13 SWO13 5.8 5 0 -0.3 80 -30.4 10 55.1 350 543.8 14 W014 Above Door 0 -0.3 78 -38.3 10 55.1 300 130.6 15 SWO15 10.5 5.5 0 -0.3 88 1.2 0 -1.1 620 2775.2 16 W 016 5.5 5.5 0 -0.3 84 -14.6 0 -1.1 550 2196.7 17 IWW07 Beneath table on E Wall 0 -0.3 96 32.8 NIA N/A N/A N/A

RADIOLOGIC*RVEY REPORT Purpose of Survey: Limited Characterization of the Nuclear Reactor Laboratory, University of Arizona Roo Nubr IRm 216A/ B - 2 nd Floor Storage Surveyed by: Kurt Myers Reviewed By: Dustin Miller Spta f Date: 2/4/2009 Ludlum M2360 248155 10/3/2009 43-89 126 0.2 0.178 154 284.2 0.121 1351 Time: N/A 2

Ludlum M2929 180832 5/17/2009 43-10-1 15 0.1 0.37 21 87.7 0.253 235 Smear Area 100 cm Ludlum M19 182671 3/22/2009 Internal N/A N/A N/A N/A 11.5 uR/hr (gamma only) N/A Batch# N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP: N/A N/A N/A N/A N/A N/A N/A N/A NIA NIA N/A N/A Misc.

a I 1=

Remarks: All count times 0.1 minute duration. except BKGD at 10 minutes. Sample locations measured from SW corner for floors and bottom left corner for walls.

18 IWW 018 13.3 5.5 0 -0.3 100 48.6 0 -1.1 330 378.5 I Rm 216A 19 WWo19 13 2.5 0 -0.3 88 1.2 10 55.1 550 2196.7 L 20 WW020 10 5 1 2.4 106 72.3 10 55.1 330 378.5 I 21 FL 021 3.5 16.5 0 -0.3 102 56.5 10 55.1 520 1948.8 I 22 FL022 5 2 0 -0.3 90 9.1 0 -1.1 350 543.8 23 1FL 023 2.5 from NW 13.3 0 -0.3 60 -109.5 0 1.1 380 791.7 I j

I 24.3+/-FL 024 3.3 9 0 -0.3 1 80 -30.4 j 10 j 55.1 j 41=0 1039.7

-4 25 IFL o25 10.5 4 1

0 I

-0.3 I

106 I

72.3 4

0 4-1.1 3202J95.9 I 26 iCL 026 0 -0.3 64 -93.7 27 CL 027 0 -0.3 72 -62.1 28 CL 028 0 -0.3 102 56.5 29 CL 029 0 -0.3 88 1.2 30 CL O3O 0 -0.3 82 -22.5 31 N/A N/A N/A N/A N/A N/A* N/A N/

32 NIA N/A N/A N/A N/A N/A N/A N/A 33 N/A N/A N/A N/A N/A i iiN/Ai N/A N/A N/A N/A N/A 34 INIA N/A 34 1N/A 1¶/A N/A N/A N/A

SENERCON UA NRL Characterization Report Rev. 0 Tritium Smear Results NRL Tritium Wipes Nuclear Reactor Laboratory Sample Collection Date: 2/3/2009 Sample Analysis Date: 2/4/2009,4/1/2009 Report Date: 4/3/2009 Counted on Packard Model 2800 LSC Count time =20 minutes Radionuclide(s) of interest: H-3 Sample Counting Results Number Description (dpm) 1 Reactor, SW Pool Wall near water level 42.04 2 Lazy Susan Port 36.35 3 R124 Floor West of Reactor 46.44 4 R124A Floor - Top of landing 72.19 5 R124 Floor - Wall south of reactor 84.61 6 R124 Wall - East 43.98 7 R124 Wall- North 34.67 8 R124 Floor - NW Corner under CAM 112.42 9 R124 Floor - SW Corner 39.97 10 R124 Reactor - SW corner 61.97 11 R124 - Storage Pit #3 33.25 12 R122 to R124 Door 165.85 13 R122 Control Panel 60.03 14 R124 to R122 Floor 53.82 15 R124A Floor - NW Corner 61.84 16 R 124A Floor - Center 33.89 17 R124A Floor - SW Corner 63.13 18 R124A Floor- E Corner 42.82 19 R214A - Top of sub-critical assembly 34.8 20 R124 - Storage Pit #1 605.43 21 R124 - Storage Pit #4 26.78 22 R124 - Sample Cave 27.81 23 Rm 216 Floor 48.77 24 Rm 216 Floor 49.03 25 Rm 216 Floor 36.61 18