Text

University of Arizonas - Post-Shutdown Radiological Characterization Report
	ML102930034
Person / Time
Site:	05000113
Issue date:	10/13/2010
From:	Williams J; Univ of Arizona
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML102930034 (56)
	v • d • e

Nuclear Reactor Laboratory Engineering Building (20)

P. O. Box 210020 Tucson, Arizona 85721-0020 THE UNIVERSITY OF ARTUCSONARIZONA.

TUCSON ARIZONA John G. Williams, Director E-mail: jgw@engr.arizona.edu Voice: (520) 621-9729 FAX: (520) 621-8096 October 13, 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 10 CFR 50.82(b)

Re: University of Arizona's Post-shutdown Radiological Characterization Report This letter provides the University of Arizona's post-shutdown radiological characterization report.

Our letter of May 21, 2009, provided the initial Radiological Characterization Report (ADAMS Accession Number ML091490105) for our reactor decommissioning. In our RAI response dated March 26, 2010 (ADAMS ML100920089), the University of Arizona committed "to submit a completed radiological characterization report to NRC review and approval prior to initiating decommissioning activities" after we had shut the reactor down. The attached is that report.

If you require further information please contact Robert Offerl supervisor, at (520) 621-6205 or rofferlegemail.arizona.edu.

I declare under penalty of perjury that the foi is true and correct. Executed on October 6, 201 e, Arizona's reactor

/

egoing 0.

N John G. Williams, Director University of Arizona Research Reactor Attachment University of Arizona Post Shutdown Radiological Characterization Report Cc(w/o attachment):

Ms. Linh Tran, U.S. Nuclear Regulatory Commission Mr. Patrick Isaac, U.S. Nuclear Regulatory Commission Dr. Leslie Tolbert, Vice President for Research, University of Arizona Acting Director Arizona Research Laboratories Aooo~

0 0e 0O 0O

,0 0

0 0

University of Arizona Nuclear Reactor Laboratory Post Shutdown 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 Prepared by:

Reviewed by:

Approved by:

Dustin G. Miller Health Physicist Gerald E. Williams, PE Sr. Technical Specialist Corey E.

eWitt Project Manager Date:

Date:

10/12/2010 10/12/2010 10/12/2010

E ENERC0N Post Shutdown Characterization Report UA Nuclear Reactor Laboratory ORevision 0

Table of Contents A CRON YM S AN D ABBREVIATION S.....................................................................................................

ii 1.0 EX EC U TIV E SU M M A R Y.............................................................................................................

1 2.0 IN T R O D U C T IO N...........................................................................................................................

2 0

2.1 PURPOSE AND SCOPE..................................................................................................... 2 2.2 PROJECT BACKGROUND............................................................................................. 2 3.0

SUMMARY

OF TECHNICAL APPROACH............................................................................. 4 0

3.1 RADIONUCLIDES OF CONCERN....................................................................................... 4 3.2 RELEASE CRITERIA 4

3.3 SURVEY OBJECTIVE AND DESIGN.................................................................................

5 3.4 SAM PLE IDENTIFICATION..............................................................................................

5 0

3.5 SURVEY INSTRUM ENTATION........................................................................................... 6 4.0

SUMMARY

OF RESULTS AND OBSERVATIONS..............................................................

8 4.1 CONCRETE AND SUBSURFACE SOILS............................................................................

8 4.2 W ALL AND FLOOR SCANS.............................................................................................

9 4.3 SUBSURFACE CONCRETE AND EQUIPMENT SCANS......................................................

10 4.4 STORAGE PIT RESULTS AND INVENTORY 1..............................

4.5 MEASUREMENT OF NEUTRON BEAM PORT IN VAN DE GRAAFF ROOM....................... 12 4.6 PREVIOUS CHARACTERIZATION RESULTS.................................................................... 13 5.0 C O N C L U SIO N S...........................................................................................................................

17

List of Tables Table 3-1 NRC License Termination Screening Levels for Surfaces 4

Table 3-2 Survey Instrumentation 6

Table 3-3 Instrumentation scan MDCs 7

Table 4.1 Soil and Concrete Results Summary 8

Table 4.2 Static Measurement Results - Reactor Control Room 14 Table 4.3 Static Measurement Results - Reactor Room" 14 Table 4.4 Static Measurement Results - Equipment Storage Room 14 Table 4.5 Static Measurement Results - Second Floor Storage Room 15 Table 4.6 Tritium Smear Results - All Rooms 15 Table 4.7 Static Measurement Results - Non-Impacted Room 111 16 List of Appendices Appendix A.- Site Drawings Appendix B - Laboratory Data Package Appendix C - Radiological Survey Data Appendix D - Storage Pit and NRL Inventory

f£)

EENERCON Post Shutdown Characterization Report

l UA Nuclear Reactor Laboratory Revision 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 MDA Minimum Detectable Activity MDC Minimum Detectable Concentration Nal Sodium Iodide NRC Nuclear Regulatory Commission NRL Nuclear Reactor Laboratory 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 VPP Vacuum Pump Pit 0

0 0

0 o

ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 1.0 EXECUTIVE

SUMMARY

The University of Arizona was licensed by the Nuclear Regulatory Commission to operate its Nuclear Reactor Laboratory (NRL) TRIGA Reactor until May 22, 2010. The reactor was shut down for the final time at precisely 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months on Tuesday, May 18, 2010.

The University expects to defuel and decommission the NRL, thus terminating NRC license R-52. A Decommissioning Plan was developed in accordance with Chapter 17 of the Nuclear Regulatory Commission Guidance (NUREG-1537) Part 1 Guidance for Preparing and Reviewing Applications for Licensing of Non-Power Reactors (NRC 1996).

To support development of the Decommissioning Plan, site characterization activities were planned and conducted in February 2009 to assess the radiological status of the NRL.

Due to ongoing reactor operations at that time, the scope of the characterization was limited to facility areas outside the reactor tank, its associated components and operating systems.

The purpose of the characterization described in this report was to assess the radiological status of the facility after the final shutdown of the reactor, to verify assumptions in the Decommissioning Plan and to meet license condition commitments to the NRC to complete additional characterization activities prior to initiation of site decommissioning activities. This post shutdown characterization survey consisted of radiological scan surveys and subsurface soil collection.

It was designed to provide additional information on the post-shutdown radiological status of the NRL rooms and soil surrounding the reactor pool to meet NRC license commitments for additional site characterization prior to initiating site decommissioning activities. The subsurface soil data was to be used to verify assumptions made within the Decommissioning Plan on waste volumes and site decommissioning strategies; however, due to breach of an undocumented sewer line, the subsurface soil collection effort was discontinued with no soil collected lower than 10 feet below the reactor room floor surface.

Analytical results from subsurface soil samples were below laboratory minimum detectable concentrations. Radiological surface scans measurements were all below NRC default release criteria listed in Section 3.2.

The data from both characterization efforts, along with the WMG Activation Analysis provides sufficient data to demonstrate that the radiological status of the NRL has been adequately characterized.

One key piece of information discovered during the characterization effort was the location of the sanitary sewer pipe directly west of the reactor tank. The line will either need to be relocated prior to or monitored during dismantlement to ensure radioactive materials are not accidently transported through this preferential pathway.

0

0 E NENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0

2.0 INTRODUCTION

2.1 Purpose and Scope

This report describes the purpose, scope and technical approach used during the post shutdown characterization of the four rooms and the subsurface soil of the University of Arizona (UA) Nuclear

Reactor Laboratory (NRL).

The University of Arizona's TRIGA reactor at the Nuclear Research Laboratory was shut down for the final time at precisely 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months on Tuesday, May 18, 2010. The report also summarizes the characterization results and provides a set of conclusions based on the results.

The purpose of the characterization described in this report was to assess the radiological status of the 0

facility after the final shutdown of the reactor and to verify assumptions in the Decommissioning Plan.

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 development of Final Status Survey (FSS) Data Quality Objectives (DQO's) for the closeout of the University's Reactor License using guidance from NUREG 1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM).

2.2 Project Background 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 387-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 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.

The NRL is located on the first floor of the north wing of the Engineering Building (Building 20) on the University's Main Campus. The reactor core is located in a swimming pool type tank that is 21 feet deep 2

E N E R C 0 N Post Shutdown Characterization Report

UA Nuclear Reactor Laboratory Revision 0 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 Control Room; Room 124, the Reactor Room; Room 124A, Equipment Storage and Experiment Setup Room; and Room 216, Second Floor Storage Room.

The University expects to defuel and decommission the NRL, thus terminating NRC license R-52. The University submitted to the NRC on May 22, 2009 a Decommissioning Plan developed using guidance from Chapter 17 of the Nuclear Regulatory Commission Guidance (NUREG-1537) Part 1 Guidance for Preparing and Reviewing Applications for Licensing of Non-Power Reactors (NRC 1996).

To support development of the Decommissioning Plan in early 2009, site characterization activities were planned and conducted to assess the levels of radiological activity at the NRL. Due to ongoing reactor operations at that time, the scope of the characterization was limited to facility areas outside the reactor tank, its associated components and operations systems. An activation analysis was performed on the reactor internals and tank to establish a basis of assumptions to be used to develop the DP for the reactor dismantlement.

03 0

0 0

0

0 0

0O 0

0 0

A¶j ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 3.0

SUMMARY

OF TECHNICAL APPROACH 3.1 Radionuclides of Concern Based upon facility operating history, tritium and other 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 the presence of alpha emitting radionuclides in the NRL facility. Specifically, there have 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 collected during the characterization effort in 2009 simultaneously with beta/gamma measurements for informational purposes.

Because the 2009 characterization effort indicated no presence of alpha contamination, alpha measurements were not collected during the post shutdown characterization effort.

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 Screening Levels for Surfaces Acceptable Screening Levels for Radionuclide Unrestricted Release (dpm/100cm2)

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/100cm2 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 4

ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 release criterion for material and equipment is important for estimating the quantity of material and equipment that will be disposed of as radioactive waste.

3.3 Survey Objective and Design The post shutdown characterization effort focused on scan measurements of the four NRL rooms and three vertical coring locations of the soil surrounding the reactor pool. Data collected during the boring and scanning characterization will be utilized to support decisions on appropriate volumes of radiological waste; methodologies for removal and packaging of radiological waste; and disposal techniques and locations of radioactively impacted materials associated with activities conducted under NRC License R-52.

The objective of the core boring was to determine the presence of horizontal neutron activation in soils surrounding the reactor tank; bounding of activation if present; and identification and bounding of any radionuclides that would be indicative of reactor pool leakage within soil adjacent the Reactor tank (i.e.,

Tritium, Cobalt-60). Based upon the WMG Activation Analysis (May 2009), Co-60 soil activation is expected in the soil directly adjacent to the core midplane at concentrations less than 0.05 pCi/g and in soils directly beneath the reactor pedestal at the axial center line at concentrations less than 12 pCi/g. The vertical coring was initiated to bound the axial soil activation and to verify that activation products were not present through leaching in soils adjacent to the reactor tank. The planned vertical coring was not designed to access the soils directly beneath the reactor pedestal.

Scanning data was used to determine if any radioactive material was present in the balance of the licensed facility. The scan data will be incorporated into the decision-making process for development of Final Status Survey Plan (FSSP) for the NRL facility.

3.4 Sample Identification 0During the subsurface soil 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 0

a unique identifier that included the sample location and the depth interval of the sample measured from the top of the concrete floor.

Boring locations were numbered sequentially using a two digit number, e.g., 01, 02, 03, and 04. The sample interval was measured from the hanging concrete floor surface and designated the depth interval 0of the sample with two 3 digit numbers representing inches. For example, a sample collected from 5

0 5

0

E NE R C0N Post Shutdown Characterization Report Ir,,C UA Nuclear Reactor Laboratory Revision 0 Location Number 1 with a sample interval of 3 feet to 4 feet would be designated as Sample Number 01-036-048.

3.5 Survey Instrumentation The instruments selected for the wall and floor scans had a Minimum Detectable Concentration (MDC) well below the release criteria specified in Section 3.2. The MDC is the concentration of radioactivity that an instrument can be expected to detect at a 95 percent confidence level. For instruments performing direct and/or scan measurements, the MDC goal is 10 to 50% of the applicable release criteria.-

Information used to calculate the MDC for instrumentation used during this characterization effort was

documented on a radiation survey form and is included as Appendix C.

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

MDC (dprn/100cm2) = 3+ 3.29V(RbXTsX1 Ts / Tb)

SL (TsX )

j

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) 0 The MDCscan for beta-gamma measurements is calculated by determining the Minimum Detectable Count Rate (MDCR). The MDCR is determined by first determining the minimum detectable net source counts

using Formula 6-8 in the MARSSIM as below.

Minimum number of detectable source counts:

si = d'bi7

Where:

d' = value from Table 6.5 in the MARSSIM for applicable true and false positive rates bi = Number of background counts in a given time interval

The MDCR is calculated from Formula 6-9 in the MARSSIM:

060

Minimum detectable count rate: MDCR = si i

Where:

i = Observed time interval Finally, applying the detection efficiency correction resulted in an MDCsca, in standardized units (DPMI100-cm 2) from this formula:

6

0

0 0O 0

0 0

ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 Scan MDC:

MDCSC~sca MDCR

probearea 100cm 2

Where:

8i = Instrument efficiency F, = Surface efficiency probearea = total area of the detector face in cm2 p = Surveyor efficiency (value from a range between 0.5 and 0.75)

Note: The value for p was developed in Draft NUREG/CR-6364 and NUREG-1507. It is a percentage estimate of the likelihood a surveyor will reliably detect an elevated count rate.

The typical a priori MDCs for beta/gamma radiation for the selected instruments used in this characterization effort are listed in the Table below and are recorded on the Radiological Survey form in Appendix C:

Instrumentation Scan MDC Instrument and Detector Serial Probe 2-pi BKGD OIy MiDCscan Number Area Efficiency (cpm)

(dpm/100 cm 2)

Ludlum Model 2360 w/Model 185776 with 126 cm2 32%

257 850 43-68 Gas Proportional Probe PR094759 Ludlum Model 2221 with Model 172056 with 43-37 Gas Proportional Large PR147970 584 cm 2 45%

1421 337 Area Probe 7

0 S

S 0

0 0

0, ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 4.0

SUMMARY

OF RESULTS AND OBSERVATIONS 4.1 Concrete and Subsurface Soils The subsurface soils around the reactor tank were investigated by utilizing a RAMSET limited access direct push rig. Three planned boring locations within the reactor room were marked and the concrete floor cored to permit access to underlying soils. Approximately 3 feet of void space exists below the concrete floor and the underlying soil surface. During the drilling activities, an unknown sanitary sewer line was encountered and breached by the RAMSET at a depth of approximately 9 feet below the reactor room floor at boring locations 1 and 4. The 5" line is located approximately 2.5 feet west of the reactor tank and runs south to north. The drilling activities were discontinued following this breach and borings were not initiated at location's 2 and 3. Boring locations are shown in Appendix A, Site Drawings, page A-1. Soil samples were collected continuously to a depth of approximately 9-10 feet at two locations 1 and 4. Samples were collected from the concrete core, the soil surface layer and the bottoms of each boring location. The samples were sent to Teledyne Brown Engineering for Gross Alpha, Gross Beta, Gamma Spectroscopy, and Tritium analyses. The results, as summarized in Table 4.1 below, did not indicate the presence of radioactive material from the operation of the UARR within the concrete floor or within soil underneath the reactor room floor. The complete laboratory report is included as Appendix B.

Table 4.1 Soil/Concrete Analysis Results Summary Results shown in picocuries per gram (pCi/g)

Analysis No. of No. Samples Standard Procedure Radionuclide Samples

>MDC Mean Minimum Maximum Deviation Gross a/P Alpha 6

5 4.5E+00 3.9E+00 5.3E+00 5.2E-01 Gross ca/0 Beta 6

6 3.4E+O1 3.OE+01 3.7E+01 2.5E+00 Liquid Scint Tritium 6

0 1.5E-01

-2.3E-01 1.4E+00 6.OE-01 Gamma Spec Co-58 6

0

-1.3E-02

-3.4E-02 1.2E-02 1.7E-02 Gamma Spec Co-60 6

0

-8.3E-03

-4.2E-02 4.9E-02 3.2E-02 Gamma Spec Cs-137 6

0 9.8E-03

-3.1E-02 3.3E-02 3.OE-02 Gamma Spec Eu-152 6

0 8.1E-03

-3.6E-02 8.5E-02 4.5E-02 Gamma Spec Eu-154 6

0 8.3E-03

-2.3E-02 5.5E-02 3.4E-02 Gamma Spec Mn-54 6

0 1.2E-02

-2.9E-02 5.4E-02 3.4E-02 Gamma Spec Ag-110m 6

0

-1.9E-02

-6.OE-02 8.6E-03 2.9E-02 Gamma Spec K-40 6

6 2.2E+01 2.OE+01 2.9E+01 3.2E+00 Gamma Spec Th-228 6

6 6.8E-01 5.1E-01 8.9E-01 1.4E-01 Gamma Spec Th-232 6

6 7.6E-01 6.2E-01 8.6E-01 1.1E-01 NOTE: Samples with results greater than MDC (i.e., Gross Alpha, Gross Beta, K-40, Th-228, and Th-230) are indicative of natural background values. Negative values are due to the subtraction of instrument background from the gross results per laboratory procedures.

8

00 0

0 0

0 0 ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 4.2 Wall and Floor Scans The accessible walls of the four NRL rooms were scanned to a height of 2 meters with a scan rate of 1 probe width per second. The accessible floor areas were also scanned at a rate of 1 probe width per second. As shown in the table in Section 3.5, all Instrument MDCs were less than 10% of the release criteria listed in Section 3.2 except for Co-60. The C-60 scan MDC was less than 30% of the MDC for this radionuclide, which is still within the desired MDC range of 10-50% of the release criteria. All scan measurement values (floors and walls), except Room 124A, were less than the a priori MDC values.

Room 124A, the Equipment and Storage Room, currently houses a subcritical assembly that will be removed during the planned reactor defueling activities.

This assembly contributes to background radioactivity in this room which was evident during both radiological characterization efforts. Even with this assembly present, radiological scans within this room were still a small fraction of the release criteria for Co-60; therefore, the data supports the assertion that radiological activity consequences within this room are low.

Room 124 Sub-critical Assembly In addition to the walls, other structures, including elevated pipe runs, the jib crane, long handled tools, lead bricks and ventilation ductwork were scanned for radiological activity. Vertical and horizontal pipes exterior surfaces were surveyed on the south and east walls of the reactor room. No elevated activity was located on the surfaces of these pipes. The crane boom was surveyed and possessed no radioactivity above background. Long handled tools used to support reactor operations were surveyed and found to exhibit some radioactivity. It is expected that these tools will be resurveyed during decommissioning and 9

10 ENERCON Post Shutdown Characterization Report W

UA Nuclear Reactor Laboratory Revision 0 disposed accordingly. Lead bricks stored along the eastern wall of the reactor room were surveyed and possessed no radioactivity above background. The room is ventilated through a 500-cfm squirrel cage

blower on the northern wall and a HEPA exhaust on the western wall of the reactor room This exhaust point features one HEPA filter. During this effort, the HEPA filter was removed and surveyed. Minor radioactivity above background was found on the HEPA filter which would be most likely attributable to 0radon. Horizontal surfaces on the ductwork interior behind the HEPA filter and the ductwork exterior were scanned for radiological activity and none was identified above background.

4.3 Subsurface Concrete and Equipment Scans

Scans were also conducted beneath the reactor room floor via the vacuum pump pit (VPP). Accessible concrete and equipment beneath the western reactor room floor was scanned. Additionally, the accessible portions of the reactor tank were also scanned. No elevated activity was found on accessible surfaces,

equipment and pipes beneath the reactor room floor.

0 0

.~

0 0

N,:

VPP Looking North VPP - Looking North. West Side of Pit 0

0 0

0 VPP View to East. Outer Wail of Reactor Tank VPP Looking North - Reactor to Right 01 0

l

C)ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 4.4 Storage Pit Results and Inventory

Six storage pits are located east of the reactor tank. Each pit is approximately 8" in diameter and 6 feet deep.

Each pit was opened and scanned for radiological activity during this characterization effort.

Radiological impacted materials are still stored in the Pits 1 and 3. A complete inventory of remaining

materials stored in these pits is available in Appendix D. Pits 1 and 3 still contain instrumented and 0demountable fuel elements in addition to graphite core elements. It is expected that these elements will be removed as part of the planned defueling activities.

Storage Pits 1 and 3 had elevated levels of radioactivity directly attributable to the presence of the fuel elements. Storage Pit 2 is empty, but did exhibit elevated radioactivity most likely due to its close proximity to the fuel elements stored in Pits 1

and

3. Storage Pits 4-6 were empty and scans did not indicate radioactivity above normal background

levels.

0 0

Room 124 Storage Pits. Pit 1 is the far right pit.

0 0

0 11 0

10 ENERCON Post Shutdown Characterization Report W

UA Nuclear Reactor Laboratory Revision 0 04.5 Measurement of Neutron Beam Port in Van de Graaff Room 0Room 20B is a subterranean room located directly north of the NRL and accessed through the Engineering Building basement. It is not associated with the NRL license R-52; however, it does possess 0a penetration along its southern wall that was constructed to house a recessed beam port to support experiments in conjunction with a Van de Graaff Proton Accelerator. The beam port is approximately 2-3" in diameter and runs perpendicular towards to bottom of the reactor tank. The general area radiation levels in room 20B are elevated due to the presence of a Co-60 sealed source. Surveys conducted at the beam port using a Ludlum Model 19 Micro-R meter were at typical NRL background levels. The bags of metal plugs shielded the detector from the sealed source.

The beam port is sealed with a wooden plug. Following several unsuccessful efforts to remove the plug intact, the effort was discontinued. No records indicate that this port construction was ever completed or 0that the feature was ever used for actual experiments.

0 0

0

Room 20 - View of Opening to Neutron Beam Tube 00 0

0 12 0

0 0

0 0 ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 R

0 - N-of Material Room 20 - Neutron Beam Tube Behind the Bags of Shielding Material 4.6 Previous Characterization Results The following sections summarize the results of the initial radiological characterization effort that was submitted in conjunction with the UA Decommissioning Plan to the NRC in May 2009.

The initial 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. General area gamma radiation dose rates were also collected.

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.

13

0 0

90

0 0

E N E R C 0 N Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 4.6.1 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 biased building surface locations were selected. In addition, five additional locations were selected, i.e. lights, trim, and window ledges.

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 Number of Alpha (dpm/100cm 2)

Beta (dpm/100cm 2)

Measurements Mean Max Std Dev Mean Max Std Dev 27 11 55 24 320 1369 438 4.6.2 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 Number of Alpha (dpm/1OOcm 2)

Beta (dpm/1OOcm 2)

Measurements Mean I

Max Std Dev Mean Max Std Dev 29 24 111 35 253 2277 742 4.6.3 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 readings 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 - Equ'pment Storage Room Number of Alpha (dpm/100cm 2)

Beta (dpm/100cm 2)

Measurements Mean Max Std Dev Mean Max Std Dev 25 37 111 42 2293 6899 1625 14

0 0

0 00O 0

f1 ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 4.6.4 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 Number of Alpha (dpm/100cm 2)

Beta (dpm/1OOCm 2)

Measurements Mean I

Max Std Dev Mean Max Std Dev 24 32 111 33 891 2772 910 4.6.5 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/100cm 2, 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.

Table 4.5 Tritium Smear Results - All Rooms Number of Alpha (dpm/100cm 2)

Measurements Mean Max Std Dev 25 76 605 114 4.6.6 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.

15

i" ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 0

S0 0

'0

'0 10 0

0 0

0 9

10

0 0O 10 Table 4.6 Static Measurement Results - Non-Impacted Room 111 Al ha (dpm/100cm 2)

Beta (dpm/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 NOTE: Negative values are due to the subtraction of instrument background from the gross results per laboratory procedures.

16

rENERCON Post Shutdown Characterization Report

O UA Nuclear Reactor Laboratory Revision 0 0

5.0 CONCLUSION

S The Post Shutdown Characterization results support the assumptions in the Decommissioning Plan regarding the radiological status of the NRL. The radiological characterization scan surveys and the subsurface soil sample analytical results demonstrated that there were no new radiological impacts from the final year of operation and that in general; the NRL is minimally impacted outside of the reactor tank by the operations of the UARR over the past 51 years.

The information obtained from both characterization efforts, along with the WMG Activation

O Analysis provides sufficient data to demonstrate that it is unlikely that significant quantities of residual radioactivity have gone undetected in the NRL. Analytical results from all subsurface soil samples adjacent the reactor tank and concrete NRL floor samples were less than the laboratory MDCs for contaminants of concern.

In addition, all radiological scan measurements on the floor and wall surfaces were less than the a priori MDCs listed in Section 3.5. All instrument MDCs were significantly less than the release criteria stated in Section 3.1.2.Due to the breach of an undocumented sewer line 0adjacent the reactor tank, all subsurface coring efforts were discontinued at the request of the University.

S0 Soils beneath the sewer line and in area surrounding the reactor tank are currently not readily accessible. The measurements performed to date and site operating history support the

assumption that no radiological spills have impacted soil surrounding the reactor tank. Any 0

subsurface soil impacts will be bounded by the limits of radiation transport of core neutrons, as calculated in the WMG Activation Analysis and Component Characterization (WMG 2009).

Minimal activation of the surrounding soils was estimated in the WMG 2009 report using the boundary fluxes of the ANISN models and a standard concrete material composition. The boundary fluxes extend outward up to eight (8) inches from the outer wall of the reactor tank.

The activation of the reactor components and surrounding soils is the primary source of residual radioactivity at the NRL. The extent of the residual radioactivity that is expected to require remediation is visually shown on the drawing on page A-2, NRL activated areas. In addition, some equipment in the NRL, i.e. long handled tools and demountable fuel elements, had elevated radiological readings, however, this equipment will be properly removed during decommissioning through either transfer of ownership to the DOE or sent to a licensed disposal facility.

17

ENERCO N Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 One key piece of data discovered during the characterization effort was the placement of the sanitary sewer pipe. Even though it caused the subsurface sampling to be halted, it is important to know that a preferential pathway is located in close proximity to the reactor tank. The location of the sewer pipe may directly affect the decommissioning of the reactor tank. The line will either need to be relocated or monitored during dismantlement to ensure radioactive materials are not transported through this preferential pathway.

00 0

0 0

01

0 0

S 0

0 S

S 0

0 0

0 0i ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 Appendix A Site Drawings

0 0

0 9

0 0

0 ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 NRL Impacted Rooms and Boring Locations 4%

LEGEND WM

=

NRL IMPACTED AREAS 0

BORING LOCATION SL P40OM 0"4

-ifuw fUNA POWM ROOM 124 ROROM ROOM 1 rm I.49MRTOWY ROOM in ROOM U

-01C

/

ROOM 164 NUCLEAR aE.PWV UL4ORATORY ROOM 1IU Note: Locations 02 and 03 were not used due to breach of sewer line. See report for details.

A-1

0 0

0 0 ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 NRL Activated Areas ROOM 124 (SOUTH WAW ACCE88 TO-VACUUM PUMP PIT FSTORAGE PITS REFLECTOR CORE 7 5,

UI I

ESliMATED AREA OF ACTIVATED ESTIMATED AREA Of ACTIVATED REACTOR INTERNALS, CONCRETE AND SOIL SOIL I CALICHE LZ A-2

S0

,S S0 SO S0 SQ S

SO S0 S

SS S

tENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 Appendix B Laboratory Data Package

0 0

'0 0.0 0

0 0

0 0.0

'0 0

0 0

.0

'0 10 0

0, AM P

TELEDYNE BROWN ENGINEERING, INC.

A Teledyne Technologies Company 2508 Quality Lane Knoxville, TN 37931-3133 865-690-6819 Work Order #: L43255 Enercon September 14, 2010 This report shall not be reproduced or distributed except in its entirety.

0 1*

Table of Contents C a se N a rra tive.............................................................................................................

3 A nalytical R esults................................................................................................

6 SQ C R e s u lts....................................................................................................................

14 S a m p le R e ce ipt.............................................................................................................

2 1 0

0 0

0;0 0

0 0

'0 0

0 0

0

.0

0 fj TELEDYNE P' !

BROWN ENGINEERING, INC.

ATeledyne Technologies Company 2508 Quality Lane Knoxville, TN 37931-3133 Corey Dewitt Enercon 4490 Old William Penn Highway Murrysville PA 15668

O Case Narrative - L43255 EN005-3EUOFA-10 09/14/2010 10:34 Sample Receipt 0

The following-samples were received on-August 10, 2010 in good condition, unless otherwise noted.

0

e Cross Reference Table Client ]ID Laboratory ID Station ID(if applicable) 01-000-004 L43255-1 01-042-090 L43255-2 01-090-108 L43255-3 04-000-012 L43255-4 04-044-066 L43255-5 04-108-120 LA3255-6 Sample Analysis Instruments used for all analyses were in calibration.

Standard solutions used in analyses were National Institute of Standards and Technology (NIST) traceable.

0Analytical Method Cross Reference Table Radiological Parameter TBE Knoxville Method Reference Method GR-A TBE-2008 EPA 900.0 GR-B TBE-2008 EPA 900.0 Gamma Spectrometry TBE-2007 EPA 901.1 H-3 TBE-2003 00 011 O

Case Narative I of 4 e0

0 0

AIW TELEDYNE BROWN ENGINEERING, INC.

A Teledyne Technologies Company 2508 Quality Lane Knoxville, TN 37931-3133 Case Narrative - L43255 EN005-3EUOFA-10 09/14/2010 10:34 Special Considerations Revision:

Cs-137 added to the gamma library Gamma Spectroscopy Quality Control Quality control samples were analyzed as WG10375.

Duplicate Sample Duplicates were analyzed for the following samples. All duplicate results were within acceptance limits, unless otherwise noted.

Client ID Laboratory ID L43316-1 QC Sample #

WG10375-1 MW-GPI-5 GR-A Quality Control Quality control samples were analyzed as WG10356.

Method Blank All blanks were within acceptance limits, unless otherwise noted.'

Laboratory Control Sample All laboratory control samples were within acceptance limits, unless otherwise noted.

Laboratory Control Sample Duplicate All laboratory control samples duplicate results were within acceptance limits, unless otherwise noted.

Case Narrative 2 of 4

0 TELEDYNE P"'!

BROWN ENGINEERING, INC.

A Teledyne Technologies Company 2508 Quality Lane Knoxville, TN 37931-3133 Case Narrative - L43255

EN00S-3EUOFA-10 09/14/2010 10:34 0

GR-B Quality Control 0

Quality control samples were analyzed as WG10356.

O Method Blank 0

All blanks were within acceptance limits, unless otherwise noted.

O Laboratory Control Sample All laboratory control samples were within acceptance limits, unless otherwise noted.

Laboratory Control Sample Duplicate All laboratory control samples duplicate results were within acceptance limits, unless otherwise noted.

H-__3 Quality Control Quality control samples were analyzed as WGI0410.

Method Blank All blanks were within acceptance limits, unless otherwise noted.

0 Laboratory Control Sample O

All laboratory control samples were within acceptance limits, unless otherwise noted.

Duplicate Sample Duplicates were analyzed for the following samples. All duplicate results were within acceptance limits, unless otherwise noted.

Client ID Laboratory ID QC Sample #

W-K LA3248-1 WG10410-3 Case Narrative 3 of 4

0 0

0i 0

0 S

0 0

0 0,

0

,7*

TELEDYNE BROWN ENGINEERING, INC.

A Teledyne Technologies Company 2508 Quality Lane Knoxville, TN 37931-3133 Case Narrative - L43255 EN005-3EUOFA-10 09/14/2010 10:34 Certification This is to certify that Teledyne Brown Engineering - Environmental Services, located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct.

Keith Jeter Operations Manager Case Narrative 4 of 4

0 0

0 00 0

0 0

0; 0

ANALYTICAL RESULTS

09/14/10 10:54 BROWN ENGINEERING, INC.

A Teledyne Technologies Company L43255 REVISED Enercon Corey Dewitt EN005-3EUOFA-10 Sep. 14, 2010 Sample ID: 01-000-004 Collect Start: 08/03/2010 00:00 Matrix:

Solids (SD)

Station:

Collect Stop:

Volume:

==

Description:==

location 01 concrete Receive Date: 08/10/2010

% Moisture:

0.98 LIMS Number:

L43255-1 So# Activity Uncertainty Run~h Aliquot Aliquot Reference Count T Count fCount Radionuclide S

Conc 2 Sigma MDC Units Volume Units Date I

Date Time Units Flag Values 3R-A 1 2008 4.51E+00 3.47E+00 3.96E+00 pCi/g 1.2054 g dry 1 08/18/101 50 1

M I U I GR-B 2008 3.43E+01 2.82E+00 1.96E+00 pCi/g 1.2054 g dry 1 08/18/101 50 M

I

_+

I fI-3 2003

.OOE+00 7.39E-01 1.22E+00 pCi/g 2.87 g wet 1 08/28/101 20 M

IU

_-40-2007 1.99E+01 1.80E+00 6.47E-01 pCi/g 164.85 g dry 08/03/10 00:00 1 08/20/101 6000 Sec

+

Yes

+

MIN-54 1 2007 1 -2.93E-02 4.91E-02 8.19E-02 pCi/g 1

164.85 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec U

No CO-58 2007 1 -3.38E-02 5.22E-02 8.68E-02 pCi/g I

164.85 g dry 108/03/10 00:00 1 08/20/101 6000 See IU I_

INo I O-60 2007 1 2.11E-03 4.37E-02 8.22E-02 pCi/g 164.85 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec U

No AG-110M 2007

-1.29E-02 3.44E-02 6.12E-02 pCi/g 164.85 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec U

No OB-124 2007 5.3 IE-02 5.15E-02 9.32E-02 pCi/g I

164.85 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec U I No I ICS-137 2007 3.01E-02 4.36E-02 8.52E-02 pCi/g T

164.85 g dry 108/03/10 00:00 1 08/20/101 6000 1 See UI I No I LA-140 2007 3.81E-02 8.42E-02 1.88E-01 pCi/g I

164.85 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec UI I No I

_U-152 2007

-1.61E-02 1.26E-01 1.96E-01 pCig1 164.85 gdry 08/03/10 00:00 I 08/20/101 6000 1 Sec U

I No I 2007 I -3.68E-03 I 7.26E-02 1.29E-01 pCi/g 164.85 gdry 08/03/10 00:00 1 08/20/101 6000 1 Sec U

I No I 11-228 2007 6.31E-01 1.07E-01

1. 14E-01 I pCi/g I _

164.85 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec

+ I Yes

-232 2007 I 8.59E-01 2.09E-01 5.15E-01 pCi/g T

164.85 1 g dry 108/03/10 00:00 1 08/20/101 6000 "1 Sec 1 +

I Yes Flag Values U

=

Compound/Analyte not detected (<MDC) or less than 3 sigma No = Peak not identified in gamma spectrum

+

=

Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)

Yes = Peak identified in gamma spectrum U*

=

Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 3 sigma

- - - Unless otherwise noted, the analytical results reported High

=

Activity concentration exceeds customer reporting value are related only to the samples tested in the condition they Spec

=

MDC exceeds customer technical specification are received by the lab L

=

Low recovery H

=

High recovery MDC -Minimum Detectable Concentration Bolded text indicates reportable value.

Page I of 6

04115BROWN ENGINEERING, INC.

09/14/10 10:54 A Teledyne Technologies Company L43255 Enercon Corey Dewitt EN005-3EUOFA-10 REVISED Sep. 14, 2010 Sample ID: 01-042-090 Collect Start: 08/03/2010 00:00 Matrix:

Soil (S)

Station:

Collect Stop:

Volume:

==

Description:==

location 01 soil 3.5-7.5 Receive Date: 08/10/2010

% Moisture:

8.23 LIMS Number:

L43255-2 Activity Uncertainty Run Aliquot Aliquot Reference 1 Count Count I Count Radionuclide SOp#

Conc 2 Sigma MDC Units Volume Units Date Date Time Units Flag Values

-R-A 2008 4.42E+00 2.92E+00 3.15E+00 pCi/g 1.3756 [g dry 1

1 08/19/101 50 1

M I + I GR-B 2008 3.71E+01 2.90E+00 1.94E+00 pCi/g 1.3756 g dry 1

08/19/101 50 M

I + I I

I H-3 2003

-2.30E-01 9.30E-01 1.55E+00 pCi/g 2.25 g wet 1108/28/101 20 1M IU I K-40 2007 2.16E+01 1.91E+00 18.37E-01 pCi/g 1

1 171.75 g dry 108/03/10 00:00 1 08/20/101 6000 Sec I++ I Yes I MN-54 2007 5.45E-02 4.83E-02 9.56E-02 pCi/g 171.75 g dry 08/03/10 00:00 1 08/201101 6000 1 See IU I

No CO-58 2007 1 -1.30E-02 5.24E-02 9.13E-02 pCi/g 171.75 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec I U I No

0-60 2007 1 4.95E-02 4.72E-02 9.90E-02 pCi/g 171.75 g dry 08/03/10 00: 00 1 08/20/101 6000 1 See U I No I

ýG-110M 2007

-5.98E-02 4.36E-02 6.84E-02 pCi/g 171.75 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec I UI No I ISB-124 2007

-6.37E-03 5.19E-02 8.15E-02 pCi/g 171.75 g dry 08/03/10 00:00 08/20/101 6000 See U

I No I IS-137 2007 2.19E-02 4.36E-02 8.33E-02 pCi/g 171.75 gdry 08/03/10 00:00 1 08/20/101 6000 1 Sec U I No I rA-140 2007

-9.87E-04 1.04E-01 2.03E-01 pCi/g 171.75 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec I U I

No

_U-152 2007

-3.60E-02 1.23E-01 1.98E-01 pCi/g 171.75 g dry 08/03/10 00:00 1 08/20/101 6000 1 Sec U

I No

ýU-154 2007 5.48E-02 7.14E-02 1.31E-01 pCi/g 171.75 g dry 08/03/10 00:00 08/20/101 6000 1 Sec I U I

No SH-228 2007 7.38E-01 1.69E-01 1.28E-01 pCi/g 171.75 g dry 08/03/10 00:00 1 08/20/101 6000 Sec

_+ I Yes "H-232 1 2007 8.39F-01 2.20E-01 5.51E-01 pCi/g 171.75 gdry 08/03/10 00:00 1 08/20/101 6000 1 Sec

+

Yes Flag Values U

=

Compound/Analyte not detected (<MDC) or less than 3 sigma No = Peak not identified in gamma spectrum

+

=

Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)

Yes = Peak identified in gamma spectrum U*

=

Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 3 sigma

- - - Unless otherwise noted, the analytical results reported High

=

Activity concentration exceeds customer reporting value are related only to the samples tested in the condition they Spec

=

MDC exceeds customer technical specification are received by the lab L

=

Low recovery -

H

=

High recovery MDC - Minimum Detectable Concentration Bolded text indicates reportable value.

Page 2 of 6

~VI oeooy1Ro

-0 oe

&At

0 o-oo o0re*ooo 09/14/10 10:54

-BROWN ENGINEERING, INC.

A Teledyne Technologies Company L43255 REVISED Enercon Corey Dewitt EN005-3EUOFA-10 Sep. 14, 2010 Sample ID: 01-090-108 Collect Start: 08/03/2010 00:00 Matrix:

Soil (S)

Station:

Collect Stop:

Volume:

==

Description:==

location 01 soil 7.5-9.0 Receive Date: 08/10/2010

% Moisture:

5.74 LIMS Number:

L43255-3 Sop#

Activity Uncertainty I

Run Aliquot Aliquot Reference Count Count Count Radionuclide SOP#

Cone 2 Sigma MDC Units

n, Volume Units Date

] Date Time Units Flag Values R-A 2008 3.94E+00 I 2.50E+00 I 2.65E+00 pCi/g 1.4742 g dry 1 08/19/101 50 1

M I + I II GR-B 2008 3.34E+01 2.48E+00 1.61E+00 pCi/g 1.4742 g dry 1 08/19/101 50 1 M

+

I

+

-3 2003 8.56E-03 8.25E-01 1.36E+00 pCi/g 2.57 1 gwet I

08/28/101 20 M

I U 1

-40 2007 1 2,03E+01 1.63E+00 5.32E-01 pCi/g 192.42 g dry 108/03/10 00:00 1 08/24/101 6000 1 Sec I+ I Yes I MN-54 2007 1 3.25E-02 4.37E-02 7.72E-02 pCi/g 192.42 g dry I 08/03/10 00:00 08/24/101 6000 1 See I U I No 1 C0-58 2007

-2.54E-02 4.3 IE-02 6.73E-02 pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec I U No 0-60 2007

-2.12E-02 1 4.24E-02 1 6.42E-02 pCi/g 1

192.42 g dry 08/03/10 00:00 08/24/101 6000 Sec

[TU I No AG-110M 2007

-1.07E-02 3.85E-02 I 6.30E-02 pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 1 See UI I

No SB-124 2007

-2.23E-02 5.80E-02 7.66E-02 pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec IU I

No CS-137 2007 3.30E-02 4.25E-02 7.54E-02 pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec UI I

No LA-140 2007

-4.82E-02 1.00E-01 1.43E-01 pCi/g 192.42 g dry 08/03/10 00:00 108/24/101 6000 1Sec IU INo EU-152 2007 8.47E-02 1.33E-01 g1.77E-01 pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 1 See U

I No EU-154 2007 4.82E-02 5.84E-02 1.01E-01 pCi/g 192.42 g dry 08/03/10 00:00 08/24/101 6000 1 See IU I

No TH-228 2007 5.09E-01 1.18E-01 1.19E-01 I pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 1 See I + I Yes I TH-232 1 2007 6.24E-01 1.59E-01 2.42E-01 pCi/g 192.42 g dry 08/03/10 00:00 1 08/24/101 6000 I Sec I + I Yes I Flag Values U

=

Compound/Analyte not detected (<MDC) or less than 3 sigma No = Peak not identified in gamma spectrum

+

=

Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)

Yes = Peak identified in gamma spectrum U*

=

Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 3 sigma

- - - Unless otherwise noted, the analytical results reported High, =

Activity concentration exceeds customer reporting value are related only to the samples tested in the condition they Spec

=

MDC exceeds customer technical specification are received by the lab L

=

Low recovery H

=

High recovery MDC - Minimum Detectable Concentration Bolded text indicates reportable value.

Page 3 of 6

BROWN ENGINEERING, INC.

09/14/1010:54 A Teledyne Technologies Company L43255 REVISED Enercon Corey Dewitt EN005-3EUOFA-10 Sep. 14, 2010 Sample ID: 04-000-012 Collect Start: 08/03/2010 00:00 Matrix:

Solids (SD)

Station:

Collect Stop:

Volume:

==

Description:==

location 04 concrete Receive Date: 08/10/2010

% Moisture:

2.63 LIMS Number:

L43255-4 Activity I Uncertainty Run Aliquot Aliquot Reference Count Count Count Radionuclide SOP#

Conc 2 Sigma MDC Units Volume Units Date Date Time Units Flag Values R-A 2008 4.70E+00 3.2613E+00 3.58E+00 pCi/g

.8729 gdry 1

108/19/101 50 M

IUI I

_R-A 2008 3.41E+01 3.13E+00 2.35E+00 pCi/g I

.8729 g dry 1

08/19/101 50 1

M

+

2003

-2.32E-01 8.83E-0 1 1.47E+00 pCi/g 2.37 gwet 1 08/28/101 20 M

IU I

_-40 2007 2.09E+01 2.41E+00 5.32E-01 pCi/g 256.16 g dry 08/03/10 00:00 1 08/20/101 6688 1 See I++

I Yes Mv1N-54 2007 2.97E-02 4.43E-02 8.17E-02 pCi/g 256.16 g dry 08/03/10 00:00 1 08/20/101 6688 See I U No

O-58 2007 1.15E-02 4.92E-02 8.60E-02 pCi/g 256.16 gdry 08/03/10 00:00 08/20/101 6688 1 See I U I

No 1

O-60 2007

-9.89E-03 4.03E-02 6.20E-02 pCi/g 256.16 gdry 08/03/10 00:00 1 08/20/101 6688 See IUI No

_G-110M 2007 8.61E-03 4.15E-02 6.83E-02 pCi/g 256.16 gdry 08/03/10 00:00 1 08/20/101 6688 1 See U I_

I NoI 3B-124 2007

-1.30E-02 4.89E-02 7.06E-02 pCi/g 256.16 g dry 08/03/10 00:00 1 08/20/101 6688 1 Sec U I No I

,S-137 2007

-3.10E-02 4.62E-02 6.65E-02 pCi/g 256.16 gdry T08/03/10 00:00 1 08/20/101 6688 1 Sec U I No I

,A-140 2007 I 2.12E-02 1.35E-01 2.27E-01 pCi/g 256.16 gdry 108/03/10 00:00 1 08/20/101 6688 1 See IHU j No

-U-152 2007 1 3.46E-02 1.39E-01 2.11E-01 pCi/g V

256.16 gdry 108/03/10 00:00 1 08/20/101 6688 1 See UI No EU-154 2007 I -1.81E-02 7.61E-02 1.28E-01 pCi/g I

256.16 g dry

_08/03/10 00:00

_08/20/101 6688 1See IU I

No rH-228 2007 I 7.30E-01 1.36E-01 1.39E-01 pCi/g I

256.16 g dry 108/03/10 00:00 1 08/20/101 6688 1 See

+ I Yes I TH-232 2007 I 6.69E-01 2.13E-01 2.04E-01 pCi/g I

I 256.16 g dry I 08/03/10 00:00 I 08/20/101 6688 1 See I + I Yes I Flag Values U

=

Compound/Analyte not detected (<MDC) or less than 3 sigma No Peak not identified in gamma spectrum

+

=

Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)

Yes = Peak identified in gamma spectrum U*

=

Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 3 sigma

- - - Unless otherwise noted, the analytical results reported High

=

Activity concentration exceeds customer reporting value are related only to the samples tested in the condition they Spec

=

MDC exceeds customer technical specification are receied by the lab L

=

Low recovery are received by the lab H

=

High recovery MDC -Minimum Detectable Concentration Bolded text indicates reportable value.

Page 4 of 6

BROWN ENGINEERING, INC.

09/14/10 10:54 A Teledyne Technologies Company L43255 Enercon EN005-3EUOFA-10 REVISED Sep. 14, 2010 Corey Dewitt Sample ID: 04-044-066 Collect Start: 08/03/2010 00:00 Matrix:

Soil (S)

Station:

Collect Stop:

Volume:

==

Description:==

location 04 soil 3.75-5.5 Receive Date: 08/10/2010

% Moisture:

11.69 LIMS Number:

L43255-5 Sop#

Activity Uncertainty C

Run Aliquot Aliquot Reference Count Count Count Radionuclide Cone 2 Sigma MD Units Volume I Units Date Date Time Units Flag Values KR-A 2008 5.29E+00 3.66E+00 4.02E+00 pCi/g 1.1755 gdry 1

108/19/101 50, 1

M IUI I

I 3R-B 2008 2.95E+01 2.66E+00 1.96E+00 pCi/g 1

1 1.1755 g dry 1

108/19/101 50 1 M I+

I I

2003 1.35E+00 1.03E+00 1.59E+00 pCi/g 1

1 2.2 g wet 1

1 08/28/101 20 1 M IUI I

K-40 2007 1 2.08E+01 1.82E+00 5.23E-01 pCi/g 166.39 1g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec I+I Yes MN-54 2007 1 -2.53E-02 4.29E-02 6.46E-02 pCi/g 166.39 g dry 08/03/10 00:00 08/24/101 6000 1 Sec U

No C0-58 2007 1 2.36E-04 5.12E-02 8.34E-02 pCi/g 166.39 g dry 08/03/10 00:00 1 08/24/10 6000 1 Sec U

No C0-60 2007 1 -4.24E-02 4.85E-02 6.63E-02 pCi/g 166.39 g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec U

No AG-110M 2007

-4.71E-02 4.41E-02 6.41F,-02 pCi/g 166.39 g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec U

I No SB-124 2007

-1.15E-02 5.74E-02 8.31E-02 pCi/g I

166.39 g dry 08/03/10 00:00 08/24/101 6000 1 Sec U

No CS-137 2007 3.08E-02 4.66E-02 8.20E-02 pCi/g I

166.39 1g dry 08/03110 00:00 08/24/101 6000 1 Sec U

I No LA-140 2007 1 -3.78E-02 1.12E-01 i.72E-01 pCi/g I

166.39 1

gdry 08/03/10 00:00 08/24/101 6000 1 Sec U

I No EU-152 2007 1 7.23E-03 1.46E-01 1.83E-01 pCi/g I

166.39 g dry 08/03/10 00:00 1 08/24/101 6000 1 Sec U

I No EU-154 2007 1 -7.84E-03 6.67E-02 I 1.11E-01 pCi/g 166.39 gdry 08/03/10 00:00 1 08/24/101 6000 1 Sec I3U I

No I TH-228 2007 I 5.83E-01 1.29E-01 1 1.30E-01 pCi/g I

166.39 gdry 08/03/10 00:00 1 08/24/101 6000 1 See I + I I Yes I

[I'--232 I

2007 6.88E-01 1.75E-01 I 2.74E-01 I pCi/g I

166.39 g dry 08/03/1000:00 1 08/24/101 6000 I Sec I + I I Yes Flag Values U

Compound/Analyte not detected (<MDC) or less than 3 sigma

+

=

Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)

U*

=

Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 3 sigma High

=

Activity concentration exceeds customer reporting value Spec

=

MDC exceeds customer technical specification L

=

Low recovery H

=

High recovery Bolded text indicates reportable value.

Page 5 of 6 No = Peak not identified in gamma spectrum Yes = Peak identified in gamma spectrum

- - - Unless otherwise noted, the analytical results reported are related only to the samples tested in the condition they are received by the lab MDC - Minimum Detectable Concentration

09/14/10 10:541 "BROWN ENGINEERING, INC.

A Teledyne Technologies Company L43255 REVISED Corey Dewitt EN005-3EUOFA-10 Sep. 14, 2010 Sample ID: 04-108-120 Collect Start: 08/03/2010 00:00 Matrix:

Soil (S)

Station:

Collect Stop:

Volume:

==

Description:==

location 04 soil 9-10 Receive Date: 08/10/2010

% Moisture:

13.90 LIMS Number:

L43255-6 S Activity Uncertainty Run Aliquot Aliquot Reference Count Count Count1 Radionuclide SOP#

Cone 2 Sigma MDC Units Volume Units Date Date Time Units Flag Values GR-A 2008 3.90E+00 3.40E+00 4.05E+00 pCi/g I

1 1.1543 1g dry 1

1 08/19/101 50 1

M I U I

GR-B 2008 3.50E+01 2.85E+00 1.97E+00 pCi/g 1.1543 1g dry 08/19/101 50 M

I + I I

H-3 2003

-4.72E-03 9.10E-01 1.50E+00 I pi/g 2.33 1g wet 1

1 08/28/101 20 1

M I U I

I-40 2007 2.85E+01 2.37E+00 7.78E-01 pCi/g 158.06 1g dry 108/03/10 00:00 1 08/24/101 6000 Sec I +

I Yes I IMN-54 2007 9.78E-03 4.70E-02 7.99E-02 pCi/g 158.06 g dry 108/03/10 00:00 08/24/101 6000 1 Sec I U I

No 1 CO-58 2007 1 -1.83E-02 5.46E-02 8.75E-02 pCi/g I

158.06 gdry 08/03/10 00:00 08/24/101 6000 1 Sec I U I No 1 CO-6 0 2007 1 -2.78E-02 6.27E-02 9.42E-02 pCi/g I

158.06 g dry 108/03/10 00:00 1 08/24/101 6000 1 See U

No AG-110M 2007 8.18E-03 4.63E-02 7.93E-02 pCi/g 158.06 g dry 108/03/10 00:00 1 08/24/101 6000 1 Sec U

I No SB-124 2007

-6.72E-02 7.14E-02 8.69E-02 pCi/g 158.06 g dry I 08/03/10 00:00 1 08/24/101 6000 1 Sec I U I No CS-137 2007

-2.59E-02 5.06E-02 8.12E-02 pCi/g 158.06 gdry 108/03/10 00:00 08/24/101 6000 1 Sec IU I No LA-140 2007

-1.99E-02 1.69E-01 2.75E-01 pCi/g 158.06 gdry 08/03/10 00:00 1 08/24/101 6000 1 See U

I No EU-152 2007

-2.61E-02 1.18E-01 1.92E-01 pCi/g 158.06 gdry 108/03/10 00:00 1 08/24/101 6000 1 See U

I No I EU-154 2007

-2.33E-02 6.87E-02 1.1OE-01 pCi/g 158.06 gdry 08/03/10 00:00 1 08/24/101 6000 1 Sec IU I No I TH-228 2007 8.92E-01 1.13E-01 1.13E-01 pCi/g 158.06 1 gdry 108/03/10 00:00 1 08/24/101 6000 1 Sec

+ I Yes I TH-232 2007 8.62E-01 1.75E-01 2.$3E-01 pCi/g 158.06 1g dry 108/03/10 00:00 1 08/24/101 6000 -1 See

+

I Yes Flag Values U

=

Compound/Analyte not detected (<MDC) or less than 3 sigma

+

=

Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)

U*

=

Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 3 sigma High

=

Activity concentration exceeds customer reporting value Spec

=

MDC exceeds customer technical specification L

=

Low recovery H

=

High recovery Bolded text indicates reportable value.

Page 6 of 6 No = Peak not identified in gamma spectrum Yes = Peak identified in gamma spectrum

- - - Unless otherwise noted, the analytical results reported are related only to the samples tested in the condition they are received by the lab MDC - Minimum Detectable Concentration

0 0

0 0*CREUT 0

0 0

0 0e 0I

QC Summary Report for L43255 BROWN ENGINEERING EN005-3EUOFA-10 A Te*edy r'ne techntoSes CompanV 09/01/2010 14:36 GAMMA Duplicate Summary TBE Sample ID Radionuclide Matrix Count Date/Time Oriainal Result DUP Result Units RPD Ran_*e Oualifier P/F WG10375-1 All non-detects.

WG 08/18/2010 18:19

<30 U

NE L43316-1 GAMMA Associated Samples for Sample #

Client ID L43255-1 01-000-004 L43255-2 01-042-090 L43255-3 01-090-108 L43255-4 04-000-012 L43255-5 04-044-066 L43255-6 04-108-120 WG10375

+

U P

F NE Positive Result Compound/analyte was analyzed, peak not identified and/or not detected above MDC

< 5 times the MDC are not evaluated Nuclide not detected Spiking level < 5 times activity Pass Fail Not evaluated Page 1

....- 0 &***weoooeo~oooee *0 *0 0*

eo0o*

0-0o

**W'

VO QC Summary Report for L43255 BROWN ENGINEERING EN005-3EUOFA-10 A Teledyne Thchnofjes Company 09/01/2010 14:36 GR-A Method Blank Summary TBE Sample ID Radionuclide Matrix Count Date/Time Blank Result Units Qualifier PEX WG10356-1 GR-A WO 08/18/2010 16:38

<6.840E-01 pCi/Total U

P LCS Sample Summary TBE Sample ID Radionuclide Matrix Count Date/Time Spike Value LCS Result Units Spike Recovery Range Qualifier P/F WG10356-2 GR-A WO 08/18/2010 17:28 3.11E+01 3.330E+01 pCi/Total 107.2 70-130

+

P Spike ID:

244CM-062609-1 Spike Cone:

3.11E+O I Spike Vol:

1.OOE+00 LCSD Sample Summary TBE Sample ID Radionuclide Matrix Count Date/Time Spike Value LCSD Result Units RPD Qualifier P/F WG10356-3 GR-A WO 08/18/2010 18:19 3.11E+01 3.400E+01 pCi/Total 2.1

+

P WG10356-2 Spike ID:

244CM-062609-1 Spike Cone:

3.11E+01 Spike Vol:

1.00E+00

+

U P

F NE Positive Result Compound/analyte was analyzed, peak not identified and/or not detected above MDC

< 5 times the MDC are not evaluated Nuclide not detected Spiking level < 5 times activity Pass Fail Not evaluated Page 2

QC Summary Report for L43255 BROWN ENGINEERINOG EN005-3EUOFA-10 A Preledyne rchnobtol*s compcfn 09/01/2010 14:36 GR-A GR-A Associated Samples for Sample #

Client ID L43255-1 01-000-004 IA3255-2 01-042-090 L43255-3 01-090-108 L43255-4 04-000-012 L43255-5 04-044-066 L43255-6 04-108-120 WG10356

+

U P

F NE Positive Result Compound/analyte was analyzed, peak not identified and/or not detected above MDC

< 5 times the MDC are not evaluated Nuclide not detected Spiking level < 5 times activity Pass Fail Not evaluated Page 3

.: 0 1O -W 1 01.0-OOO * *00 oo1 0OOe-

* *0

oo0*:*...

0...

....,0 0*

QC Summary Report for L43255

,BR Q.WýENGNEERING EN005-3EUOFA-10 A 'rNetdyne r7tednofoies Company 09/01/2010 14:36 GR-B Method Blank Summary TBE Sample ID Radionuclide Matrix Count Date/Time Blank Result Units Qualifier P

WG10356-1 GR-B WO 08/18/2010 16:38

< 1.OOOE+00 pCi/Total U

P LCS Sample Summary TBE Sample ID Radionuclide Matrix Count Date/Time Spike Value LCS Result Units Spike Recovery Ranne Oualifier P/F WG10356-2 GR-B WO 08/18/2010 17:28 3.80E+01 3.530E+01 pCi/Total 92.8 70-130

+

P Spike ID:

137CS-060208-1 Spike Conc:

3.80E+01 Spike Vol:

1.00E+00 LCSD Sample Summary TBE Sample ID Radionuclide Matrix Count Date/Time Spike Value LCSD Result Units RPD Qualifier P/F WG10356-3 GR-B WO 08/18/2010 18:19 3.80E+01 3.640E+01 pCi/Total 3.1

+

P WG10356-2 Spike ID:

137CS-060208-1 Spike Conc:

3.80E+01 Spike Vol:

1.OOE+00

+

U P

F NE Positive Result Compound/analyte was analyzed, peak not identified and/or not detected above MDC

< 5 times the MDC are not evaluated Nuclide not detected Spiking level < 5 times activity Pass Fail Not evaluated Page 4

QC Summary Report for L43255.

BROWN ENGINEERING EN005-3EUOFA-10 A

Orldyne rhosie Campany 09/01/2010 14:36 GR-B GR-B Associated Samples for Sample #

Client ID L43255-1 01-000-004 L43255-2 01-042-090 L43255-3 01-090-108 L43255-4 04-000-012 L43255-5 04-044-066 L43255-6 04-108-120 WG10356 U

P F

NE Positive Result Compound/analyte was analyzed, peak not identified and/or not detected above MDC

< 5 times the MDC are not evaluated Nuclide not detected Spiking level < 5 times activity Pass Fail Not evaluated Page 5

QC Summary Report for L43255 BROW.VN ENGINEERINýG EN005-3EUOFA-10 A reledyne Tecthroo*ies Company 09/01/2010 14:36 H-3 Method Blank Summary TBE Sample ID Radionuclide Matrix Count Date/Time Blank Result Units Oualifier P/F WG10410-1 H-3 WO 08/28/2010 00:00

< 3.480E+00 pCi/Total U

P LCS Sample Summary TBE Sample ID Radionuclide Matrix Count Date/Time Spike Value LCS Result Units Spike Recovery Ranue Oualifier P/F WG10410-2 H-3 WO 08/28/2010 00:20 2.52E+02 2.610E+02 pCi/Total 103.4 70-130

+

P Spike ID:

3H-041706-1 Spike Conc:

5.05E+02 Spike Vol:

5.OOE-01 Duplicate Summary TBE Sample ID Radionuclide Matrix Count Date/Time Original Result DUP Result Units RPD Ranae Qualifier P/F WG10410-3 H-3 S

08/28/2010 00:41

< 1.330E+00

< 1.320E+00 pCi/g Wet

<50 NE L43248-1 H-3 Associated Samples for Sample #

Client ID L43255-1 01-000-004 L43255-2 01-042-090 L43255-3 01-090-108 L43255-4 04-000-012 L43255-5 04-044-066 L43255-6 04-108-120 WG10410

+

U P

F NE Positive Result Compound/analyte was analyzed, peak not identified and/or not detected above MDC

< 5 times the MDC are not evaluated Nuclide not detected Spiking level < 5 times activity Pass Fail Not evaluated Page 6

0 0

0 SAMPLE RECEIPT

A Work Plan for the Core Boring and Scanning Characterization of the Nuclear Reactor Laboratory University of Arizona Chain of Custody Record ENERCON Services. Inc.

4490 Old William Penn Highway Murnwille, PA15668 A

Laboratory Contacto t1 4 )Ja g

DQte COCka:

No :

Laboratoryf-

.rUWA Fly 24)733-87.,..

4)325-6383 Phone:

Carrier.

i.-,

Page ofL.L.

Address:.

Anayis TumaroundTime ENERCON JobCharge No.

Circle OneU r4td a

77 5

7Days, 4D~ays,ZiMays, 30 Days, Phone:

Sampling Evolution

Description:

FAXsampe.

SI

Grab or Compos*te Su

.,,f;,.

£;a I Project:Mb.S Liquid E

Samplo Sample Sample Sampleldentification Da Time T atrix i1 *

,Sample Specific Notes:

01-MIS

-C-S"

"/IX, C r

-:*h,.

c.,,-,.

ol - t4'e1-o1O

_xt_:

4-a=a4-,e^ ol S,,.

7. S"

-oo

-151A 65 1YK Iso-I-Iq

,'-r--.L S

-S I -

(- C¢.,c,+w-o14 sail S7)7-i

1.

7 A

Sod 10 preservationUsed: I

Ice,

= HCI, 3 5

NA r

6"=

Hazard Identification: Circle One Sample Disposition: Circle One Non-Hazard Flammable Skin Inrtant PoisonB Unknown rRetumtoClient DisposalbyLao Archivefor Mot ks /Da.y (circleone)

Special I yltructions/QC Reqrements & Comments:

Relinquiby:b~,,,

~Dt/m R

raby.

Compar 7 -

6 ae/ie nquishly:

Company.

It byTime

.Company Date/Time:

Relinquished by:

Company.

DateB / TimeFeevd by.

Company Date I Time:

00 B-2 July 14, 2010

08/31/10 09:28 O3R #:

SR24881 OClient:

Enercon Services, Inc.

nitiated By: RCHARLES Init Date: 08/11/10 Recei Teledyne Brown Enginee Sample Receipt Verification/Varin 55Pe 23 Project #:

EN005-3EUOFA-10 LIMS #L43255 7e Date:

08/11/10 Notification of Variance Person Notified:

Contacted By:

Notify Date:

Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment 1

Shipping container custody seals present NA and intact.

2 Sample container custody seals present NA and intact.

3 Sample containers received in good N

condition 01-000-004 Bottle arrived broken on the bottom.

4 Chain of custody received with samples Y

1: 5 All samples listed on chain of custody Y

received 6

Sample container labels present and Y

legible.

7 Information on container labels y

correspond with chain of custody 8

Sample(s) properly preserved and in NA

appropriate container(s) 9 Other (Describe)

NA For Hazardous Materials Only:

10 Paperwork shows TBE and shippers name, NA address and phone number 11 Paperwork shows sample quantity NA information 0

.00 0

0

,0 0

0 0

0 0

0

!ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 APPENDIX C Radiological Survey Data

RADIOLOGICAL SURVEY REPORT P

hPurpose of Survey I

Post-Shutdown Characterization: University of Arizona Nuclear Reactor Laboratory I

Rooms 122, 124, 124A, 216, 216A Date:

8/5/2010 N/A Ludlum M2360 185776 40089 43-68 126 N/A N/A N/A 257 0.32 1936 Time:

Ludlum M2221 172056 39950 43-37 584 NIA N/A N/A 1421 0.45 698 Smear Are 100 CM2 Ludlum M3 39894 44-9 15.5 PRI69296 NWA N/A N/A 100 0.17 N/A Batch #

N/A N/A N/A NIA 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 NIA Surface Efficiency 0.5

.1 I

a =

I

=

Remarks: All scan rates at 1 probe width per second. Model 2221 with 43-37 used for floor scans.

and Storage Pit scans. Background measurements used for MDC calculations were collected from I Model 2360 with 43-68 used for wall scans. Model 3 with 44-9 used for equipment 1 Floor Scan:

Room 216A 2 Floor Scan:

Room 216 3 Floor Scan:

Room 122 4 Floor Scan:

Room 124 5 Wall Scan:

Room 216A N & E 6 Wall Scan:

Room 216A W & S 7 Wall Scan:

Room 216 N & E 8 Wall Scan:

Room 216 W & S 9 Wall Scan:

Room 122 N Wall 10 Wall Scan:

Room 122 E Wall 11 Wall Scan:

Room 122 W Wall 12 Wall Scan:

Room 122 S Wall 13 Wall Scan:

Room 124 N Wall 14 Wall Scan:

Room 124 S Wall 15 Wall Scan:

Room 124 E Wall 16 Wall Scan:

Room 124 W Wall 17 Scans:

Room 124 A 18 Storage Pit #1 1778 1750 1850

-21 55

<MDC 1706 1650 1750

-43 33

<MDC 1477 1400 1500

-59 18

<MDC 1539 1450 1550

-68 8

<MDC 520 450 550

-347 149

<MDC 356 350 450

-30 466

<MDC 551 500 600

-253 243

<MDC 367 350 450

-84 412

<MDC 398 250 450

-734 258

<MDC 309 250 350

-293 203

<MDC 293 250 350

-213 283

<MDC 330 275 375

-273 223

<MDC 320 250 350

-347 149

<MDC 303 250 350

-263 233

<MDC 414 350 450

-317 179

<MDC 314 250 350

-317 179

<MDC 414 500 1200 427 3899 See Report 100 100 4000 0

148008 See Report c - loose alpha 13

- loose beta

- direct reading 5/1/2008, Rev. 0 B-1

RADIOLOGICAL SURVEY REPORT Purposef 0surTey Post-Shutdown Characterization: University of Arizona Nuclear Reactor Laboratory I

S SReviewed Bv:

Rooms 122, 124, 124A, 216, 216A Date:

8/5/2010 Ludlum M2360 185776 40089 43-68 126 N/A N/A N/A 257 0.32 1936 Time:

N/A Ludlum M2221 172056 39950 43-37 584 N/A N/A N/A 1421 0.45 698 Smear Area 100 cm2 Ludlum M3 39894 44-9 15.5 PR169296 N/A N/A N/A 100 0.17 N/A Batch #

N/A NIA NIA N/A N/A N/A N/A N/A N/A N/A N/A N/A RWP N/A NIA NIA N/A NIA N/A N/A N/A NIA N/A N/A N/A Surface Efficiency

0.5 Remarks

All scan rates at 1 probe width per second. Model 2221 with 43-37 used for floor scans. Model 2360 with 43-68 used for wall scans. Model 3 with 44-9 used for equipment

--,A Q ---

D;+

12 1

ý"

f--, ~ANTh(

-n 1 -,l+;-

1 4,-r V^^-

1 1 1 rr, TT RATI 1'.

+l.1tA f-~ fA)F-A1 I/Ad-OI 19 Storage Pit #2 20 Storage Pit #3 21 Storage Pit #4 22 Storage Pit #5 23 Storage Pit #6 24 Long Handle Tools 25 Lead Bricks 26 Rm 124 Ventillation System - HEPA 27 Rm 124 Ventillation System - Pre-fllter 28 Rm 124 Ventillation System - Duct Work 29 Crane Boom 30 N/A 31 N/A 32 N/A 33 N/A 34 N/A 35 NA 36 NiA 100 100 1200 0

41746 See Report 100 100 4000 0

148008 See Report 100 100 200 0

3795 See Report 100 100 100 0

0 See Report 100 100 100 0

0 See Report 100 100 500 0

15180 See Report 100 100 100 0

0 See Report 100 100 200 0

3795 See Report 100 100 200 0

3795 See Report 100 100 100 0

0 See Report 100 100 100 0

0 See Report

,I a - loose alpha 1 - loose beta 0 - direct reading 5/1/2008, Rev. 0 B-1

0 0

9 0

0 0

0 S

0 0

0 S

0 0

E ENERCON Post Shutdown Characterization Report UA Nuclear Reactor Laboratory Revision 0 APPENDIX D Storage Pit and NRL Inventory

0 O

O 0

0 O

0 0

0 L

NUCLEAR REACTOR LABORATORY

UNIVERSITY OF ARIZONA A.

Pit InventoryA RI zoNA instrumentea ruel eiement

10208 8/5/2010 4000 cpm maximum reading within the pit Demountable fuel element 1

2898 containing 14 uranium 8/5/2010 slugs, 5 carbon spacers, and a Plexiglas plug 16 graphite core fuel elements 0.5 mR/hr 8/5/2010 Pit # 2 is emp t.

1200 c ~m maximum reading within the p2it Nine (9) graphite core fuel 3000 cpm maximum reading eInts radioactivity 8/5/2010 within thepit elements found within thepit One empty demountable fuel No element/experiment tube found

______________________found ic4

.. t T 4 is empty. I UU cpm maximum reading within tne pit Pit #t 5 is empty. 100 cpm maximum reading within the pit

'it*

F t 1* 6 cont1a1I~

u1 e eavy mo1untu g SLa111 kp g) Ilul e11 oI Co source.

Source~

was remo1ve in 2008. 100 epm maximum reacting within the pit Room 124A File Cabinet, TopPrawer Used Reuter-Stokes BF 3 Proportional Counter, Model RS-Pl-1624-102, Ser # R1903 No radioactivity detected 10/14/08 Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-204A-MG3, Ser # K249 detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-204A-MG3, Ser # K257 detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-204A-MG3, Ser # K260 detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RS-P1-624-102, Ser#R1840 detected 1

updated 8/5/2010

R L NUCLEAR REACTOR LABORATORY

UNIVERSITY OF ARIZONA Pit Inventory A.

ARIZONA Invst Iy Objeict RadiociviyT eak dae.'

Used G.E. y-Compensated Neutron Chamber, Cat. No.

5467870 G 11, Ser # 4072982 No radioactivity detected 10/14/08 0

0 0

0 Used G.E. Proportional No Counter, Cat. No. 5478906 G radioactivity 10/14/08 1, Ser # 4131049 detected Used Westinghouse No RELIATRON WL 6937 tube, radioactivity 10/14/08 stamped # 82206 detected Plastic spacers for No Platicspaersforradioactivity 10/14/08 demountable fuel element detected detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-7A, Ser # N688 detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-7A, Ser # H462 detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-7A, Ser # K478 detected Used Reuter-Stokes BF 3 No Proportional Counter, Model radioactivity 10/14/08 RSN-7A, Ser # E1315 detected Depleted uranium pellets, Bag 10/14/08 "A"

Depleted uranium pellets, Bag 10/14/08 "B"

Depleted uranium pellets, Bag 1/40 Small cardboard box containing two Reuter-Stokes No neutron counter tubes, Model radioactivity 10/14/08 RSN-48, Serial # D892 and found D882.

Room "

AmmI-;24A oC1-Plastic baggie of Coleman 10/14/08 lantern mantels (thorium)

Ammo Can # 2 is empty Nothing exposed in Room 124A 2

updated 8/5/2010

0 0

0 NUCLEAR REACTOR LABORATORY - UNIVERSITY OF ARIZONA Pit Inventory ARIZONA Fission Chamber RSN-OA 10

K491 n

deece 10/14/08 Fission Chamber RSN-10A n n eetd 1/40

M2632 nn eetd 1/40 Westinghouse Reliatron Tube WL 6376 Fission chamber, Serial # 80803, labeled to contain 1.72 g 231U, -30 ptCi 137CS on 2/10(?)/76 by George Nelson 2.1 mr/hr 10/14/08 Co-60 Irradiation Source 10/14/08

[S254]

Co-60 Irradiation Source 10/14/08

[S395], formerly [S20]

3 updated 8/5/2010

v t e Letter Sequence Request
TAC:ME2989, (Open)
Initiation Request, Request, Request Acceptance Administration Questions 14 June 2010 Answers 26 March 2010 14 July 2010 Results Approval Other: ML110120042
MONTHYEAR2010-03-26 [Table View]

ML102930034

Text

SUMMARY

SUMMARY

SUMMARY

2.0 INTRODUCTION

2.1 Purpose and Scope

SUMMARY

SUMMARY

5.0 CONCLUSION

Description:

0.5 Remarks

Navigation menu

Search