ML12264A064

University of Michigan - Ford Nuclear Reactor Final Disposition of Fnr Storage Ports

ML12264A064
Person / Time
Site:	University of Michigan
Issue date:	09/18/2012
From:	Driscoll M University of Michigan
To:	Document Control Desk, NRC/FSME
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Download: ML12264A064 (226)

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O SEH University of Michigan Occupational Safety & Environmental Health Campus Safety Services Building Occupational Safety & 1239 Kipke Drive, Ann Arbor, MI 48109-1010 Environmental lealtth Phone: 734 647-1143

• Fax: 734 763-1185 September 18, 2012 Document Control Room U.S. Nuclear Regulatory Commission Two White Flint North 11545 Rockville pike (Mail Code: 03H8)

Rockville, Maryland 20852-2738 RE: University of Michigan - Ford Nuclear Reactor Final Disposition of FNR Storage Ports Docket 50-2 / License R-28 Decommissioning Branch:

Please find enclosed a draft copy of the Final Disposition of the Below-Grade Storage Ports report to be used in conjunction with the Final Status Survey (FSS) of the University of Michigan - Ford Nuclear Reactor (License R-28 / Docket 50-2). A final copy of this report will be submitted along with the final FSS report.

Thank you for your time, effort, and consideration with respect to your review of this FSS-related document. Please do not hesitate to contact me at OSEH / Radiation Safety Service

[(734) 647-2251] should you have any questions or comments regarding this draft copy of the Final Disposition of the FNR Storage Ports report.

Sincerely, Mark L. Driscoll Director / Radiation Safety Officer Radiation Safety Service / OSEH MLD/mld NRCFNRD&DFSSQAPlan09l712.doc cc: Terry Alexander, Executive Director, OCS Robert Blackburn, Manager, Laboratory Operations, MMPP Theodore Smith, FNR Project Manager, NRC Headquarters (Mailstop T-8F5)

FNR Decommissioning Files

Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT DRAFT Ford Nuclear Reactor Facility Final Disposition of the Storage Ports February 24, 2012 Submitted By:

FNR Decommissioning Project Director Date Final Approval:

Chairman, Decommissioning Review Committee Date 1

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4Ford Nuclear Reactor Revision: 00, DRAFT Storage Ports - Final Disposition Table of Contents E xecutive Sum mary ........................................................................................................................ 3 Description of the Storage Ports Construction and Use ............................................................. 5 Characterization of the Storage Ports ....................................................................................... 9 Characterizationof Storage PortInternal Contamination.................................................... 9 Determination of DCGLsfor the Neutron Activated Soil aroundStorage Port 1................ 10 Characterizationof Neutron Activated Soil around Storage Port 1..................................... 13 Characterizationof Neutron Activated Concrete aroundStorage Port No. 1 ..................... 15 Storage Port and Contaminated Soil Removal Activity .......................................................... 17 Removal of Storage Port Vent Lines ...................................................................................... 18 Removal of Storage Ports and Concrete Support Wall ........................................................ 19 Final Status Confirm ation Surveys .......................................................................................... 20 FreeRelease Survey of Sections of Storage Ports Remaining in the FNR Wall ................... 22 Soil and Concrete Survey andAnalysis aroundStorage PortNo. 1 ................................... 23 FinalStatus Survey Conclusion............................................................................................ 25 NRC Confirm ation Surveys ...................................................................................................... 25 Appendices under Separate Cover ............................................................................................. 27 A Pre-Removal Internal Characterization of the Storage Ports B Analytical Data for Activated Soil Characterization around Storage Port No. 1 C Pre-Excavation Soil Analysis around Storage Port No. 1 D Analysis of Concrete Support Wall around Storage Port No. 1 Eberline Analytical E Storage Port Vent Lines Survey Data Sheet F Radiological Survey and Swipe Analysis for Storage Port Ends Remaining in FNR Wall G Radiological Survey Report of Excavation Zone Former Storage Port No. 1 Location H Analytical Data for Final Status Survey of Soil Located Behind the Section of Support Wall Removed I Analytical Data for Final Status Survey of Soil Located Behind the Section of Support Wall Removed J Analytical Results from Eberline Analytical for Final Status Survey of the Soil under the Former Storage Port No. I K ORISE Confirmation Samples Collected by NRC 2

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Wi Storage Ports Ford Nuclear Reactor

- Final Disposition R

Revision: 00, DRAFT Executive Summary Fifty storage ports extended through the west wall of the first floor of the reactor and were designed for and used to store beam port plugs, collimators or other equipment from the beam ports. The storage ports were also used to store items with elevated dose readings. The storage ports consisted of forty-two 6" and eight 8" schedule 40 carbon steel pipes that extended 8'- 10" into the soil; terminating into an 8" thick concrete wall providing structural support for the pipes ends. The storage ports were arranged in three levels.

Of specific interest was Storage Port No. I that was used to store two large pu238 Be sources from approximately November 1971 to February 2003 when they were relocated to another U-M facility in preparation for decommissioning the reactor facility. These Pu 238Be sources were capable of producing approximately 1.7E+8 neutrons sec-1 which would be spread in all directions. The other ports were used for storing materials that would not produce a neutron flux capable of activating surrounding soil materials. Therefor the primary areas of concern during the remediation efforts were from:

• Contaminated surfaces and debris inside the storage ports from reactor equipment

" Activated soils surrounding Storage Port No. I

• Concrete surfaces that may have been within the radius of influence from the Pu23Be sources in Storage Port No. 1 and become partially activated During November/December 2008 excavation activity was undertaken to expose the storage ports to facilitate their removal. Activities involved:

• Installation of sheet piling to establish the northern, western and southern limits of the approximately 10' by 52' excavation.

" Excavation from the ground surface down to the bottom of the east/west running storage port pipes at a depth of approximately 13'. All excavated soil from storage ports 4 through 50 was stockpiled for re-use in backfilling the excavation zone. Soil from around storage ports I through 3 was removed for disposal.

" The seventeen one inch vent lines and 50 six and eight inch storage ports were cut and removed in a controlled manner.

• The concrete support wall around Storage Port Nos. I through 3 was cut and removed from the excavation for disposal.

With the excavation completed and the storage ports all removed, the project moved into a final status survey mode to confirm the ability to backfill and close the site. This involved radiological surveys of the excavation zone where the pu238 Be sources had been stored in Storage Port No. 1, confirmation soil samples of the area under the former Storage Port No. I and to the west of the area where the concrete support wall had been removed, and confirmation of the remaining concrete support wall. In addition, all of the storage port ends remaining in the wall into the FNR facility were surveyed for free release to allow them to remain in place.

The surveys and analytical work performed on remaining soil and the concrete support wall have not identified contamination remaining in the excavation associated with the operation of the storage ports, in particular Storage Port No. 1 that had been used to house high level neutron sources in the form of Pu 238Be. The final status survey supports the conclusion that all remedial 3

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Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT activity has been adequately completed to comply with the Default Screening Values of Table 6.91 in NUREG 5512.

On Monday, March 25, 2009 the NRC visited the FNR facility to conduct confirmatory sampling of the storage port soil and concrete for their independent analysis. The NRC radiological analyses of the soil concurred with the analyses conducted by the FNR staff and Eberline Analytical. The excavation was subsequently backfilled.

4 E:\Storage Port Final Report draft.doc

Description of the Storage Ports Construction and Use Fifty storage ports extended through the west wall of the first floor of the reactor and were designed for and used to store beam port plugs, collimators or other equipment from the beam ports. The storage ports were also used to store items with elevated dose readings. The storage ports consisted of forty-two 6" and eight 8" schedule 40 (1/4" wall thickness) carbon steel pipes that extended 8'-10" into the soil; terminating into an 8" thick, 10'-9" tall concrete wall providing structural support for the pipes ends. The storage ports were arranged in three levels with the top and bottom levels aligned vertically and the middle level staggered horizontally between adjacent pairs. The configuration resulted in 17 storage ports in the top row, 17 storage ports in the middle row, and 16 storage ports in the bottom row. The storage ports are numbered one through fifty going from south to north and top to bottom (see Figure 1).

oooooo 11 14119 2 98 42 44 48 5 0 62236 Figure 1, Storage Ports numbering system starting with no. 1 to the south and ending with no. 50 to the north (note they are shown stacked here only for convenience of illustration)

Each storage port had a V" vent line attached near the end of the pipe to provide for air passage into or out of the storage port as the tight fitting beam port plugs, collimators or other equipment were inserted or withdrawn. With the exception of the storage ports at the north and south ends, the vents lines from three storage ports (one each from the top, middle, and bottom rows) were connected to a common vent line using "Y" fittings, and increasing from 2inch pipe at the lowest storage port to 1 inch pipe at the upper storage port (see Figures 2 and 3). The common vent line then turned horizontal and ran parallel to and 3'-6" above the upper storage port to return through the west wall of the reactor building for connection to the Stack 2 exhaust system.

The north and south end upper and lower storage ports were connected to common vent lines and run into the west wall of the facility in a similar manner.

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WFord Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT

-T>'r',cAL Vf~A~rjJA/L LAYO~-Ir 4

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Figure 2, Typical Vent Line Layout for the Storage Ports Figure 3, Storage Ports under Construction - view from NW looking toward SE The entire installation of storage ports was buried along the west wall of the reactor building, running south to north 48'. The vent lines were located approximately 7'-10" below ground surface, the top row of storage ports were located approximately 10'-2" below ground surface, and the bottom row of storage ports were located approximately 12'- 10" below ground surface.

(See Figures 4 through 7) 6 E:\Storage Port Final Report draft.doc

iFord Nuclear Reactor Revision: 00, DRAFT Storage Ports - Final Disposition Figure 4, Plan view of Storage Port design (January 1958)

Figure 5, Storage Ports under Construction - view from NE corner looking toward SW and showing location of Storage Port No. 1 7

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Ford Nuclear Reactor Revision: 00, DRAFT Storage Ports - Final Disposition Figure 6, Plan view of Storage Port design (January 1958)

Figure 7, Section view of Storage Port design looking from north to south (January 1958) 8 E:\Storage Port Final Report draft.doc

WFord Nuclear Reactor Ports - Final Disposition Revision: 00, DRAFT Storage Characterization of the Storage Ports The 50 storage ports were designed for and used to store beam port plugs, collimators or other equipment from the beam ports as well as items with elevated dose readings. Of specific interest was Storage Port No. 1 that was used to store two large Pu238Be sources from approximately November 1971 to February 2003 when they were relocated to another U-M facility in preparation for decommissioning the reactor facility. These Pu 238Be sources were capable of producing approximately 1.7E+8 neutrons sec1 (from the paper work provided by Monsanto with the sources) which would be spread 47r from the source in all directions such that at 8 cm from the source, neutron flux in air would be approximately 6E+5 neutrons cm2 sec . The other ports were used for storing materials that would not produce a neutron flux capable of activating surrounding soil materials. Therefor the primary areas of concern during the remediation efforts were from:

" Contaminated surfaces and debris inside the storage ports from reactor equipment

" Activated soils surrounding Storage Port No. I

• Concrete surfaces that may have been within the radius of influence from the pu238Be sources in Storage Port No. 1 and become partially activated Characterizationof Storage PortInternal Contamination To determine internal contamination of the ports, survey work was performed using one minute static gamma measurements at approximately 9" intervals from the entrance to the back of each of the storage ports using a Ludlum 44-10 2" by 2" Nal detector (serial no. 24815). The detector was placed in a 6" or 8" cradle specifically constructed to center the Nal detector in each 6" or 8" storage port. The detector was then connected using a 20' R-59 cable to a Ludlum 2221 Scaler Ratemeter (serial no. 218602). The gross count measurements for each storage port are summarized in Table I below with additional data and plots of gross gamma counts as a function of position for each storage port provided in Appendix A (separate binder).

From these measurements, the following observations were made:

• Storage Port No. 1: The activation of the carbon steel wall of by the pu238Be sources yielded a peak activity approximately 2' in from the end of the storage port. This agreed with operational knowledge that the Pu238Be sources were stored approximately one to two feet from the end of the storage port. Removable activity was found at one survey point.

• Storage Port No. 10: The high gamma measurement at the end indicated that there was a piece of activated metal stored at the very end of the storage port and that piece of metal potentially had a high specific activity. Subsequent visual inspection by camera did not identify a source of the elevated measurements. Removable activity was found at three survey points.

• Storage Port No. 48: The high gamma measurement V' from the end indicated that there may be a piece of activated metal that required removal. Subsequent visual inspection by camera did not identify a source of the elevated measurements. Removable activity was found at three survey points.

" Storage Port No. 12, 13, 26, 29-49: Removable activity was found at various survey points.

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Ford Nuclear Reactor bStorage Ports - Final Disposition Revision: 00, DRAFT Table 1, Storage Port pre-removal survey results summary Port Highest Gross CPM Highest Smear in Port Highest Gross CPM During Highest Smear in Number During Scan dpml/100cm2 Number Scan dpm/100cm2 Port 1 2400@ 8 ft 121 Port 26 1200 @ 7 ft 45 Port 2 600 @ 10 ft <MDA Port 27 300-350 <MDA Port 3 300-350 <MDA Port 28 300-350 <MDA Port 4 300-350 <MDA Port 29 1000 @ 6.5 ft 33 Port 5 586 @ 5 ft <MDA Port 30 300-350 1220 Port 6 800 @ 5.5 ft <MDA Port 31 300-350 37 Port 7 300-350 <MDA Port 32 1300 @ 10 ft 205 Port 8 300-350 <MDA Port 33 1400 @ 5 ft 71 Port 9 300-350 <MDA Port 34 300-350 5.80 a only Port 10 52,000 @ 9 ft 96 Port 35 3000 @ 8 ft 83 Port 11 300-350 <MDA Port 36 3000@ 8 ft 343 Port 12 400-450 73 Port 37 300-350 31 Port 13 1000 @ 5 ft 1078 Port 38 600 @ 7 ft 60 Port 14 300-350 <MDA Port 39 300-350 140 Port 15 300-350 <MDA Port 40 370 @ 10 ft 31 Port 16 300-350 <MDA Port 41 1700 @ 6 ft, 600 @ 9 ft 79 Port 17 400-450 <MDA Port 42 500-600 all 92 Port 18 300-350 <MDA Port 43 4300 @ 6ft 73 Port 19 300-350 <MDA Port 44 300-350 22 Port 20 1000 4-10 ft <MDA Port 45 1100 @ 9 ft 690 Port 21 300-350 <MDA Port 46 300-500 all 119 Port 22 300-350 <MDA Port 47 300-350 25 Port 23 300-350 <MDA Port 48 1300-9200 @ 10 ft 217 Port 24 300-350 <MDA Port 49 5000 @ 10 ft 58 Port 25 300-350 <MDA Port 50 400-700 all <MDA No feasible method could be identified that would allow characterization of the small diameter vent lines in order to leave them in place. Based on the need to remove the vent lines and the three storage ports with elevated measurements, it was determined the most expeditious route was to remove all storage ports for disposal Determinationof DCGLs for the Neutron Activated Soil around Storage Port 1 Soil samples were collected north of the storage port area in November 2008 to determine a background concentration for the isotopes of concern in the soil near Storage Port No. I that may have become activated due to proximity to the Pu238Be sources. Using a 2 inch diameter dual tube direct push soil sampler, three samples were collected from a depth of 8 feet to 12 feet below the surface (the approximate depth of the storage ports) at a point north of Storage Port No. 50. The soil samples were collected in acetate liners and processed following ASTM (2005)

C 999, Soil Sample Preparationfor the Determination of Radionuclides. The material from the three acetate tubes was dried for two days at 110 degrees C until reaching a constant weight.

The sample material from the three samples was combined into one sample, UM2008-11-06-01.

The sample was split then into two portions using an ELLE sample splitter and 186 grams of 10 E:\Storage Port Final Report drafi.doc

i i Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT sample material from the first split was sent to Oregon State University for determination of the content of the soil using Instrumental Neutron Activation Analysis (INAA) (refer to the following site for information:

http://serc.carleton.edu/research education/geochemsheets/techniques/INAA.html).

The purpose of the Oregon State University analyses was two-fold: first to determine the elemental composition of the soil, and second to give an indication of what radio-isotopes might stand out given exposure to a higher neutron flux rate. In addition it was suspected that certain other elements of possible concern may be present in the soil at levels not detected by the Oregon State University analyses; in particular, tin, molybdenum, and certain of the rare earth elements (REE). Gerhard Erdtmann, Neutron Activation Tables, 1976 was consulted based on the Oregon State University results and the suspect elements to determine what additional radioisotopes might have been produced by neutron activation of the soil. Only those radio-isotopes with a half-life greater than 100 days and absorption cross section of milli-barns or larger were considered in the analysis as others would be present at levels approximately IOE-9 pCi/g or lower.

It was necessary to make reasonable assumptions about the suspect elements concentrations in the soil in order to calculate an estimated activity for their neutron activation products. Since it is known that the REE elements, with the exceptions of europium and cerium, behave geochemically in a predictable way', their behavior can be used to estimate the concentration of REEs of interest based on those that were detected in the Oregon State University analyses and the commonly accepted REE pattern in the upper continental crust (UCC) as reported by Taylor and McLennan 2 .

Based on this analysis, the elemental concentration of metal with activation potential and the subsequent significant activation radionuclides and their estimated concentrations are listed in Table 2.

Table 2, Metals in soil with activation potential from Storage Port 1 Activity Target Natural Activation isotope % Activation Cross Half Life (d-Element Concentration Radionuclide abundance Section (barn) days, a-years)

Activation by Thermal Neutrons Iron 15325 gtg/g Fe-55 5.8 2.25 2.7 a Eu-152 47.8 5900 12.4 a Europium 0.60 gtg/g Eu-154 52.2 390 8.5 a Cobalt 5.O0ig/g Co-60 100 37.2 5.272 a Cesium 0.92 ig/g Cs-134 100 29 2.06 a Barium 292 jig/g Ba-133 0.095 8.5 10.4 a La-137 0.193 7.25 60,000 a Cerium 26 jig/g Ce-139 0.26 1.1 137.5 d 1Cornell University, Geol. 655 Isotope Geochemistry,Lecture 7, Spring 2003, GEOCHRONOLOGY III,THE SM-ND SYSTEM 2 Taylor and McLennan, The Continental Crust: its Composition and Evolution, Blackwell Scientific Publications, 1985, Table 2.15 Chemical composition of the upper continental crust, p.46 11 E:\Storage Port Final Report drafi.doc

Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Chromium 5.0 jig/g None2 Antimony 0.53 [tg/g None2 Hafnium 0.0044 jig/g None2 - -

Neodymium 13 gtg/g Sm- 151 5.62 1.2 93 a Ni-59 67.88 4.6 75,000 a Nickel 12 ltg/g Ni-63 3.66 14.2 100 a Rubidium 42 jtg/g None2 - -

Scandium 4.7 ýLg/g None2 Strontium 202 jtg/g None2 - -

Tantalum 310 p//g Ta-182 99.998 21 115 d 2

Terbium 349 jig/g None - -

Zinc 48 tig/g Zn-65 48.9 0.78 243.7 d Zirconium 160 lt*/g Zr-93 17.11 260 x 10-3 1.5 x 106 a Sn-113 0.96 1.15 115.1 d Sn-119m 24.03 16 x 10-3 245 d Sn-121m 32.85 1 x 10-3 50 a Tin 5.5 ltg/g Sn-123 4.72 180 x 10-3 129.2 d Sm-145 3.1 0.7 340 d Sm-151 7.4 102 93 a Samarium 4.5 pig/g Eu-155 22.8 5.5 4.96 a Gadolinium 3.8 jtg/g Gd-153 0.2 1100 241.5 d Lutetium 0.32 Atg/g Lu-177m 2.6 7 161 d Activation by Fast Neutrons Iron 15325 ltg/g Mn-54 5.8 82.5 X 10.' 312.5 d Barium 292 jtg/g Cs- 134 2.42 Hafnium 0.0044 jtg/g La-137 0.17 2.2 x 10-3 1.37 a Nickel 12 gtg/g Co-60 4.4 x 10-3 5.272 a Terbium 349 tgg/g Th-158 100 3.2 x 103 150 a 3

Molybdenum 1.5 gig/g Tc-99 23.78 130 x10 2.15 x 10' a Tin 5.5 gtg/g Sb-125 5.8 134 x 10"i 2.77 a No activation product with a half-life of greater than 100 day or an absorption cross section smaller than millibarn.

The concentration of activity formed in the soil from a given element by activation of the Where:

CP gýC,- "g0.6023.

i1xl0* *%- Id/

neutrons from the Pu 238Be source is described by the activation equation:

X 6

• MWgi1mole 2... Buildup TIt j Decay

" Cpg/g is the concentration of the element in the soil surrounding the storage port

" a% is the abundance of the isotope of the radionuclide to be measured

" MWis the atomic weight of the element 0¢ is the neutron flux from the pu238Be source

" a-* is the cross section for the corresponding reaction 238Be source

" iirradiation is the length of time the soil was exposed to neutrons from the Pu

" tdecay is the length of time after the irradiation the soil decayed before being excavated

• T112 is the half-life of the activation product 12 E:\Storage Port Final Report draft.doc

fFord Nuclear Reactor Revision: 00, DRAFT Storage Ports - Final Disposition 1,000 grams of sample material from the first split was placed into a 500 ml wide mouth Nalgene bottle and analyzed using the U-M high purity germanium (HPGe) detector. The HPGe was calibrated using a 2.09 g cm-3 epoxy, 500 ml Nalgene, multi-nuclide standard (Am-241 - 60 keV through Y-99 1836 keV). This sample analysis allows a determination of the isotopic concentration of the above nuclides to less than 25% of the concentration (pCi g-') that is equivalent to 25 mren yf' for various radio nuclides listed in Table 6.91 of NUREG 5512 Vol 3 (1999), Residual Radioactive Contaminationfrom Decommissioning - ParameterAnalysis. This sample serves as background for the analyses of the soil around Storage Port No. 1; results are shown in Tables 3 and 4. Analytical reports are available in Appendix B (separate binder).

Table 3, Nuclides of Concern in soil surrounding Storage Port No. 1 EPA Consultation Conenraton(p~ g1)Trigger (p~ g'1) Typical MDA (pCi g-)

equivalent to 25 mrem for (p'i g) for 50,000 second I for Residual Soil analysis yr Contamination Mn-54 13.9 69 3 x 10-2 Fe-55 9,350 269,000 N/A Co-60 3.68 4 3 x 10-2 Ba-133 5 x 10-2 Cs-134 5.36 16 3 x 10-2 Eu-152 8.66 4 5 x 10-2 Eu-154 8.0 5 5 x 10-2 Table 4, Background soil analysis (sample no. UM2008-11-06-01) for Storage Port Area Minimum Default Screening Identified Measured Detectable Values (pCi/ g-)

Radionuclide Concentration (pCi g-1) Activity (pCi 9-1)

Mn-54 Not Identified 1.77 x 10" 13.9 Fe-55 Not Identified Not Detectable 9,350 Co-60 Not Identified 1.76 x 10.2 3.68 Ba-133 Not Identified 2.73 x 10-2 Cs-134 Not Identified 1.90 x 10-2 5.36 Eu-152 Not Identified 2.88 x 10-2 8.66 Eu-154 Not Identified 2.05 x 10.2 8.0 Characterizationof Neutron Activated Soil aroundStorag-e Port1 In September 2008 three soil samples were collected along Storage Port No. 1, approximately 1.5' from the end of the pipe where the Pu 238Be sources had been stored. The purpose of these samples was to compare them to the radio-isotopes of concern identified in Tables 3 and 4 to determine if the soil had activation products that exceeded the Default Screening Values, requiring removal.

Using a 2 inch diameter dual tube direct push soil sampler, three sample tubes were collected at the two locations along Storage Port No. I from a depth of 8 feet to 12 feet below the surface.

The soil from the third set of tubes (the approximate depth of the storage ports) was collected for analysis. The sample material from the two geo-probes was identified as sample numbers UM2008-11-20-01 and UM2008-11-20-02. In addition, a 6" hole was hand dug directly over 13 E:\Storage Port Final Report draft.doe

Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT and down to Storage Port No. 1 where sample number UM2008-12-18-01 was collected. All samples were processed following ASTM (2005) C 999, Soil Sample Preparationfor the Determinationof Radionuclides. The material was dried for two days at 110 degrees C until reaching a constant weight. 1,000 grams of sample material from each was placed into 500 ml wide mouth Nalgene bottles and analyzed using the U-M high purity germanium (HPGe) detector calibrated using a 2.09 g cm-3 epoxy, 500 ml Nalgene, multi-nuclide standard (Am-241

- 60 keV through Y-99 1836 keV). Results shown in Table 5 indicate soil activation products from thearePuin238Be reports source Cmaterial Appendix (separatethatbinder).

had been stored in the Storage Port No. 1. Analytical Table 5, Pre-excavation soil samples collected at Storage Port No. 1 Identified Measured Concentration Minimum Detectable Default Screening Radionuclide (pCi g rto Activity (pCi g-l) Values - Table 3 (PC/ g-l)

Sample No. UM2008-11-20-02: Dual Tube sample 1.5' from end of Storage Port No. 1, along south side of port, depth at 8' to -11' [calculated unity factor of 0.031 Mn-54 1.31 x 10.2 1.30 x 10-2 13.9 Fe-55 1.6 9,350 Co-60 2.52 x 10.2 2.34 x 10.2 3.68 Ba-133 Not Identified 3.06 x 10.2 Cs-134 Not Identified 2.14 x 10.2 5.36 Eu-152 0.257 4.08 x 10.2 8.66 Eu-154 Not Identified 2.63 x 10. 8.0 Sample No. UM2008-11-20-01: Dual Tube sample 1.5' from end of Storage Port No. 1, along center line of port, depth at 8' to -12' [calculated unity factor of 0.041 Mn-54 Not Identified 1.96 x 10-2 13.9 Fe-55 1.6 9,350 Co-60 2.42 x 10-2 2.05 x 10-2 3.68 Ba-133 Not Identified 3.02 x 10.2 Cs-134 Not Identified 2.11 x 10-2 5.36 Eu-152 0.194 3.78 x 10" 1 8.66 Eu-154 Not Identified 2.53 x 10"2 8.0 Sample No. UM2008-12-18-01: Hand dug soil from within 6 inches of Storage Port No. 1 - [calculated unity factor of 0.371 Mn-54 <MDA 2.2 x 10-2 13.9 Fe-55 2.9 9,350 Co-60 0.462 2.61 x 10.2 3.68 Ba-133 Not Identified 3.19 x 10.2 Cs-134 2.77 x 10.2 1.59 x 10.2 5.36 Eu-152 2.08 6.37 x 10". 8.66 Eu-154 < MDA 5.35 x 10' 8.00 Because the radionuclides are in a mixture, a sum-of-fractions calculation was performed on the samples to determine if the 25 mrem/yr equivalent had been exceeded in the soil. As shown in Table 5, the calculated unity factors ranged from 0.03 to 0.37. The samples indicate some activation of soil particles surrounding Storage Port No. 1 but not to the extent the soil exceeds the Default Screening Values of Table 6.91 in NUREG 5512.

3 Fe-55 Estimated by activation calculation bases upon measured Cu- 152 and Co-60 concentrations 14 E:\Storage Port Final Report draft.doc

Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Because the default screening values are based on an assumption that there is at least a 1 meter separation between the activated soil and groundwater, a determination was made that the separation does exist. Based on data collected from a monitoring well located approximately 200' south of the storage port location, the groundwater zone was 25' (7.7 m) below the depth of Storage Port No. 1.

8-4, , '- Y Figure 8, Depth to Groundwater Determination Characterizationof Neutron Activated Concrete aroundStorage PortNo. 1 Samples of the concrete from the wall supporting the west end of Storage Port No. 1 were collected to analyze for isotopes that may have been activated by the storage of the Pu 238Be sources approximately 1.5' from the end of the storage port. Two samples from the wall were collected after the storage port had been removed. The first was a circular pattern 12" diameter from the centerline of the storage port (UM2009-02-26-01) and the second was a circular pattern 18" diameter from the centerline (UM2009-03-04091). In each sample collection, a clean, 1" rotor-hammer bit was used to drill a series of holes approximately 7" deep in a circular pattern around the centerline of the storage port (see Figure 9).

15 E:\Storage Port Final Report draft.doe

Figure 9, Concrete sampling around Storage Port 1 to check for activation products Fines from the drilling operation were collected in a clean "Minute Man Vacuum" purchased specifically for the project. The fines were collected in a paper filter bag from which they were removed for analysis. A total of approximately 1.5 gallons of material were collected for each set of sample drill holes. The samples were submitted to Eberline Analytical for characterization and the results are shown in Table 6. Analytical data sheets are in Attachment D.

Table 6, Characterization of concrete around Storage Port No. 1 end cap (Analysis performed by Eberline)

Default Screening Identified Measured Concentration Minimum Detectable Values - Table 3 Radionuclide (pCi g'-) Activity (pCi g-1) (pCi/ g')

Sample No. UM2009-02-26-01: Concrete wall 12" from centerline of Storage Port No. 1

[calculated unity factor of 0.37]

Mn-54 <MDA 1.74 x 10' 13.9 Fe-55 1.48 11.4 9,350 Co-60 2.75 x 10"' 9.66 x 10-2 3.68 16 E:\Storage Port Final Report draft.doc

Ford Nuclear Reactor Revision: 00, DRAFT Storage Ports - Final Disposition Ag-108m 1.32 x 10-2 9.07 x 10-2 Ba-133 6.89 x 10-2 1.02 x 10"_

Cs-134 9.35 x 10-3 1.05 x 10"' 5.36 Eu-152 1.73 3.94 x 10"' 8.66 Eu-154 7.48 x 10-" 2.88 x 10l' 8.0 Eu-155 3.23 x 10-' 2.09 x 10' 282 Sample No. UM2009-03-04-01: Concrete wall 18" from centerline of Storage Port No. 1

[calculated unity factor of 0.1]

Mn-54 2.33 x 10"' 1.43 x 10-' 13.9 Fe-55 <MDA 10.5 9,350 Co-60 8.9 x 10.2 8.18 x 10.2 3.68 Ag-108m 1.28 x 102 6.94 x 10.2 Ba-133 <MDA 7.56 x 10".

Cs-134 3.59 x 10-2 8.61 x 10-2 5.36 Eu-152 4.94 x 10"' 6.03 x 10-' 8.66 Eu-154 4.89 x 10.2 2.18 x 10"' 8.0 Eu-155 8.28 x 10.2 1.76 x 10-1 282 Results of the analysis indicate some activation of the concrete from the Pu 2aBe neutron source but at levels below the Default Screening Values. Because the radionuclides are in a mixture, a sum-of-fractions calculation was performed on the samples to determine if the 25 mrem/yr equivalent had been exceeded in the concrete. Calculated sample unity factors were 0.37 and 0.1. The samples indicate some activation of concrete particles surrounding Storage Port No. I but not to the extent the concrete exceeds the Default Screening Values of Table 6.91 in NUREG 5512. A decision was made to cut the concrete section of the wall from around Storage Port No.

1 for disposal.

Storage Port and Contaminated Soil Removal Activity During November/December 2008 excavation activity was undertaken to expose the storage ports to facilitate their removal. Activities involved:

• Installation of sheet piling to establish the northern, western and southern limits of the approximately 10' by 52' excavation (the eastern limit of the excavation was established by the western wall of the building) as shown on figure 10.

• Excavation from the ground surface down to the bottom of the east/west running storage port pipes at a depth of approximately 13'. All excavated soil from storage ports 4 through 50 was stockpiled for re-use in backfilling the excavation zone. Soil from around storage ports I through 3 was removed for disposal.

" The seventeen one inch vent lines and 50 six and eight inch storage ports were cut and removed in a controlled manner.

" The concrete support wall around Storage Port Nos. 1 through 3 was cut and removed from the excavation for disposal.

17 E:\Storage Port Final Report draft.doc

OW Ford Nuclear Reactor Storage Ports - Final Disposition Figure 10, Storage Port excavation zone Removal of Storage Port Vent Lines Seventeen 1" vent lines running from the west ends of the storage ports, in an easterly direction back to and through the wall of the FNR facility were removed on December 10, 2008 using a band saw. A cardboard tray was placed under each cut line to contain pipe shavings from the band saw operation. The shavings were placed in a radioactive materials slurry/piping drum for proper disposal.

Following the cutting operation the pipes were wipe sampled at each end, and then taped to seal the openings. The pipes were then placed in the FNR radioactive material area inside FNR and eventually sent for proper disposal. All wipe samples measured below Lc levels. The cardboard tray was checked using a frisker probe Model 44-142, serial no. PR249243, and wipe samples collected and analyzed on a Tenelec Series 5, serial no. 2161, measured below Lc levels. Refer to Appendix E for the survey data sheet.

18 E:\Storage Port Final Report draft.doe

Figure 11, Cutting vent lines from the storage ports Removal of Storaze Ports and Concrete Support Wall In December 2008 all 50 storage ports were uncovered, cut, and removed from the excavation zone. The storage ports were moved inside the FNR building for processing and ultimately disposed as low level radioactive waste in a controlled manner. As anticipated from the preliminary soil sampling activities, the soil immediately surrounding Storage Port No. 1 exhibited low-level soil activation from the pu238 Be sources that had been stored in the storage port. The soil and concrete in a cube approximately 40-inches on a side or approximately 37 cubic feet was removed in a controlled manner and disposed as radioactive waste.

19 E:\Storage Port Final Report draft.doc

Figure 11, Cutting Storage Ports Figure 12, Concrete support wall section removed Final Status Confirmation Surveys With the excavation completed and the storage ports all removed, the project moved into a final status survey mode to confirm the ability to backfill and close the site. This involved radiological surveys of the excavation zone where the pu238Be sources had been stored in Storage Port No. 1, confirmation soil samples of the area under the former Storage Port No. 1 and to the west of the area where the concrete support wall had been removed, and confirmation of the remaining concrete support wall. In addition, all of the storage port ends remaining in the wall into the FNR facility were surveyed for free release to allow them to remain in place. The NRC then made a site visit and collected samples of the soil and concrete to confirm the analysis in order to allow backfilling of the excavation. Figure 13 identifies the sample locations.

20 E:\Storage Port Final Report draft.doc

Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Al 3

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jrovit6st sroxAA4 eoA7 0joo R 01 c . r,0-Figure 13, Final Status Survey sample locations for Storage Port No. 1 21 E:\Storage Port Final Report draft.doc

Figure 14, Storage port excavation ready for final survey work Free Release Survey of Sections of Storage Ports Remaining in the FNR Wall To determine the ability to free-release and leave in the wall the remaining sections of storage ports that could not be removed, survey work was performed using one minute static gamma measurements at two locations on each pipe end. The survey was performed using a Ludlum 44-1 Nal detector, serial no. PR249243, on January 9, 2009. Swipe samples were also collected and analyzed for alpha and beta using a Tenelec S5-XLB, serial no. 2161. The measurements for each storage port are summarized in Table 7 below with survey data sheets provided in Appendix F (separate binder).

The survey results indicate the pipe ends can all be free-released and left in the wall of the FNR.

The ends were plugged and capped to prevent soil infiltration to the FNR facility during backfill of the excavation.

22 E:\Storage Port Final Report draf.doc

Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Table 7, Final Status Survey of Storage Port pipe-ends remaining in FNR wall Port Highest Gross CPM Highest Smear in Port Highest Gross CPM Highest Smear2 in Number During Scan dpm/1 00cm 2 Number During Scan dpm/ 100cm Port 1 <MDA <MDA Port 26 <MDA <MDA Port 2 <MDA <MDA Port 27 <MDA <MDA Port 3 <MDA <MDA Port 28 <MDA <MDA Port 4 <MDA <MDA Port 29 <MDA <MDA Port 5 <MDA <MDA Port 30 <MDA <MDA Port 6 <MDA <MDA Port 31 <MDA <MDA Port 7 <MDA <MDA Port 32 <MDA <MDA Port 8 <MDA <MDA Port 33 <MDA <MDA Port 9 <MDA <MDA Port 34 <MDA <MDA Port 10 <MDA <MDA Port 35 <MDA <MDA Port 11 <MDA <MDA Port 36 <MDA <MDA Port 12 <MDA <MDA Port 37 <MDA <MDA Port 13 <MDA <MDA Port 38 <MDA <MDA Port 14 <MDA <MDA Port 39 <MDA <MDA Port 15 <MDA <MDA Port 40 <MDA <MDA Port 16 <MDA <MDA Port 41 <MDA <MDA Port 17 <MDA <MDA Port 42 <MDA <MDA Port 18 <MDA <MDA Port 43 <MDA <MDA Port 19 <MDA <MDA Port 44 <MDA <MDA Port 20 <MDA <MDA Port 45 <MDA <MDA Port 21 <MDA <MDA Port 46 <MDA <MDA Port 22 <MDA <MDA Port 47 <MDA <MDA Port 23 <MDA <MDA Port 48 <MDA <MDA Port 24 <MDA <MDA Port 49 <MDA <MDA Port 25 <MDA <MDA Port 50 <MDA <MDA Soil and Concrete Survey and Analysis aroundStoraze PortNo. 1 On April 13, 2009 a survey of the soil and concrete support wall around the former location of Storage Port No. 1 was conducted using a Ludlum Model 19 MicroR Meter, serial no. 101763.

All measurements were at or below the background levels as determined through measurements at the north end of the excavation zone. Appendix G (separate binder) is the Radiological Survey Report for this effort.

Following removal of the section of concrete support wall from the south end, up through Storage Port No. 3 including the concrete around Storage Port No. 1, a sample of the cut edge of the remaining concrete was collected and analyzed to determine residual activation products.

The sample was collected using a diamond grinder with a new diamond wheel to grind the concrete surface. Dust from the grinding was collected in a clean Minuteman vacuum designated specifically for sample collection. The sample was processed and analyzed using the U-M high purity germanium (HPGe) detector calibrated using a 2.09 g cm 3 epoxy, 500 ml Nalgene, multi-nuclide standard (Am-241 - 60 keV through Y-99 1836 keV). The samples are compared to the activation products identified in the concrete prior to removal. Table 8 below provides results of that analysis and the analytical data is in Appendix H (separate binder).

23 E:\Storage Port Final Report drafi.doc

Ford Nuclear Reactor Storage Ports - Final Disposition Table 8, Final Status Survey Characterization of concrete support wall remaining in the excavation zone Post-Removal Default Screening Identified Pre-Removal Measured Measured Minimum Detectable Values - Table 3 Radionuclide Concentration (pCi g*1) Concentration (pCig1) Activity (pCi g-) (pCi! g-)

Sample No. UM2009-04-24-01: Edge of remaining concrete wall at centerline of removed Storage Port No. 1 Mn-54 <MDA <MDA 3.72 x 10" 13.9 Fe-55 1.48 <MDA 11.4 9,350 Co-60 2.75 x 10-' <MDA 5.84 x 10.2 3.68 Ag-108m 1.32 x 10-2 <MDA 2.9 x 10-2 Ba-133 6.89 x 10-2 <MDA 7.88 x 10"'

Cs-134 9.35 x 10.' <MDA 1.05 x 10l 5.36 Eu-152 1.73 8.58 x 10-2 7.26 x 102 8.66 Eu-154 7.48 x 10.2 <MDA 5.83 x 10.2 8.0 Eu-155 3.23 x 10' ND ND 282 Following removal of the support wall section for Storage Port No. I the soil behind the wall was analyzed to determine if the soil was impacted by the neutron flux from the former pu238Be sources stored in the vicinity. The soil sample was collected using a clean flat scoop using ASTM D5633 (2004) methodology. The sample was processed following ASTM (2005) C 999, Soil Sample Preparationfor the Determination of Radionuclides. The material was dried for two days at 110 degrees C until reaching a constant weight. 1,000 grams of sample material from each was placed into 500 ml wide mouth Nalgene bottles and analyzed using the U-M high purity germanium (HPGe) detector calibrated using a 2.09 g cm-3 epoxy, 500 ml Nalgene, multi-nuclide standard (Am-241 - 60 keV through Y-99 1836 keV). Table 9 below provides results of that analysis and the analytical data is in Appendix I (separate binder).

Table 9, Final Status Survey soil sample from behind support wall for Storage Port No. 1 Identified Radionuclide Measured Concentration (pCi g-1) 4 Minimum Detectable (pci Activity (pCi g-I)

I Values -Screening Default Val Table3 i/s-l)

Sampe (pi N. ~ M~tiity g1)(pCi g-1)

Sample No. UM2009-03-25-02: Soil from behind support wall for Storage Port No. 1 Mn-54 <MDA 2.4 x 10"' 13.9 Fe-55 <MDA 9,350 Co-60 <MDA 3.7 x 10.2 3.68 Ba-133 <MDA 5.36 x 10.2 Cs-134 <MDA 5.23 x 10.2 5.36 Eu-152 <MDA 5.29 x 10-1 8.66 Eu-154 <MDA 4.4 x 10'2 8.0 The only original soil remaining from around Storage Port No. 1 was the bottom of the excavation, approximately 20" below the former storage port, and the south wall of the excavation approximately 22" from the former storage port. The soil from the top, north, and east sides was removed. Soil samples were collected from these locations using a clean flat scoop. The samples were processed and sent to Eberline Analytical for final status survey determination of final closure of the excavation. Figure 13 above shows the sample locations 4 Fe-5 5 Estimated by activation calculation bases upon measured Cu- 152 and Co-60 concentrations 24 E:\Storage Port Final Report draft.doc

1. Ford Nuclear Reactor Storage Ports - Final Disposition and orientation with the former storage port. Table 10 below provides results of that analysis and the analytical data is in Appendix J (separate binder).

Table 10, Final Status Survey Soil samples from around the former Storage Port No. 1 (Eberline Analytical)

Identified Measured Concentration Minimum Detectable Default Screening Radionuclide (pCi g-) 5 Activity (pCi g-1) Values - Table 3 Sample No. UM2009-02-06-02: Soil on floor of excavation directly under former Pu "Be source in Storage Port No. 1 [calculated unity factor of 0.081 Mn-54 <MDA 5.36 x 10-2 13.9 Fe-55 <MDA 3.87 9,350 Co-60 7.64 x 10-2 6.51 x 102 3.68 Ba- 133 Not Identified Not Identified Cs-134 <MDA 5.38 x 10-2 5.36 Eu-152 5.1 x 10-' 3.58 x 10"' 8.66 Eu-154 <MDA 1.77 x 10' 8.0 Sample No. UM2009-02-06-04: Soil on south wall of excavation directly adjacent to former Pu mBe source in Storage Port No. 1 Mn-54 <MDA 1.11 x 10-I 13.9 Fe-55 <MDA 4.16 9,350 Co-60 <MDA 1.58 x 10-' 3.68 Ba-133 Not Identified Not Identified Cs-134 <MDA 1.00 x 10"1 5.36 Eu-152 <MDA 1.00 8.66 Eu-154 <MDA 2.99 x 10l' 8.0 Because the radionuclides are in a mixture, a sum-of-fractions calculation was performed on the samples to determine if the 25 mrem/yr equivalent had been exceeded in the soil. As shown in Table 10, the calculated unity factor for the soil under the former pu238Be sources was 0.08, indicating the remaining soils in the excavation do not exceed the Default Screening Values of Table 6.91 in NUREG 5512.

Final Status Survey Conclusion The surveys and analytical work performed on remaining soil and the concrete support wall have not identified contamination remaining in the excavation associated with the operation of the storage ports, in particular Storage Port No. I that had been used to house high level neutron sources in the form of Pu 238Be. The final status survey supports the conclusion that all remedial activity has been adequately completed to comply with the Default Screening Values of Table 6.91 in NUREG 5512.

NRC Confirmation Surveys On December 11, 2008, the decommissioning branch of the NRC conducted an inspection of activities at the FNR facility. The NRC inspection team consisted of Senior Health Physicist Bill Snell and staff Health Physicist Jeremy Tapp. The purpose of the inspection was to determine 5Fe-55 Estimated by activation calculation bases upon measured Cu- 152 and Co-60 concentrations 25 E:\Storage Port Final Report draft.doc

0 i Ford Nuclear Reactor Storage Ports - Final Disposition whether the decommissioning activities were conducted safely and in accordance with NRC requirements. Specifically, the two inspectors evaluated decommissioning activities and radioactive waste management. The primary activity observed during the inspection was the removal of the underground storage ports and associated vent lines. The inspectors determined that the University of Michigan was effectively completing decontamination and dismantlement activities along with adequate calibration of survey equipment and completion of associated documentation. In an NRC inspection report dated December 23, 2008, the NRC noted that no radiological concerns were identified during facility tours and observations of work in progress.

On Monday, March 25, 2009 the NRC visited the FNR facility to conduct confirmatory sampling of the storage port soil and concrete for their independent analysis. The NRC radiological analyses of the soil concurred with the analyses conducted by the FNR staff and Eberline Analytical. The excavation was subsequently backfilled. Table 11 below provides results of the NRC confirmation sampling and the data sheets are provided in Appendix K (separate binder).

Table 11, NRC confirmation sampling/analytical through ORISE Identified Measured Minimum Detectable Default Screening Radionuclide Concentration (pCi g-1) 6 Concentration (pCi g-1) Values - Table 3 Sample No. UOM-09-1-01: Soil sample from area of former Storage Port No. 1 Fe-55 0.03 2.4 9,350 Co-60 0.03 0.03 3.68 Eu-152 0.02 0.03 8.66 Sample No. UOM-09-1-02: Soil sample from area of former Storage Port No. 1 Fe-55 0.07 2.4 9,350 Co-60 0.01 0.03 3.68 Eu-152 0.06 0.04 8.66 Sample No. UOM-09-1-03: Concrete support wall sample Fe-55 0.07 2.3 9,350 Co-60 0.04 0.05 3.68 Eu-152 0.08 0.06 8.66 6 Fe-55 Estimated by activation calculation bases upon measured Cu-I152 and Co-60 concentrations 26 E:\Storage Port Final Report draft.doe

1. i Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Appendices under Separate Cover A Pre-Removal Internal Characterization of the Storage Ports B Analytical Data for Activated Soil Characterization around Storage Port No. 1 C Pre-Excavation Soil Analysis around Storage Port No. I D Analysis of Concrete Support Wall around Storage Port No. 1 Eberline Analytical E Storage Port Vent Lines Survey Data Sheet F Radiological Survey and Swipe Analysis for Storage Port Ends Remaining in FNR Wall G Radiological Survey Report of Excavation Zone Former Storage Port No. 1 Location H Analytical Data for Final Status Survey of Soil Located Behind the Section of Support Wall Removed I Analytical Data for Final Status Survey of Soil Located Behind the Section of Support Wall Removed J Analytical Results from Eberline Analytical for Final Status Survey of the Soil under the Former Storage Port No. 1 K ORISE Confirmation Samples Collected by NRC 27 E:\Storage Port Final Report draft.doc

Ford Nuclear Reactor Storage Ports - Final Disposition Appendix A Pre-Removal Internal Characterization of the Storage Ports 28 E:\Storage Port Final Report drafi.doc

Appendix B Analytical Data for Activated Soil Characterization around Storage Port No. 1 29 E:\Storage Port Final Report draft.doc

Ford Nuclear Reactor i 0 Storage Ports - Final Disposition Revision: 00, DRAFT Appendix C Pre-Excavation Soil Analysis around Storage Port No. 1 30 E:\Storage Port Final Report draft.doc

OFord Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Appendix D Analysis of Concrete Support Wall around Storage Port No. 1 Eberline Analytical 31 E:\Storage Port Final Report draft.doc

WFord Nuclear Reactor Ports - Final Disposition Revision: 00, DRAFT Storage Appendix E Storage Port Vent Lines Survey Data Sheet 32 E:\Storage Port Final Report draft.doc

Ow Ford Nuclear Reactor Ri Storage Ports - Final Disposition Revision: 00, DRAFT Appendix F Radiological Survey and Swipe Analysis for Storage Port Ends Remaining in FNR Wall 33 E:\Storage Port Final Report draft.doc

Appendix G Radiological Survey Report of Excavation Zone Former Storage Port No. 1 Location 34 E:\Storage Port Final Report draft.doc

Appendix H Analytical Data for Final Status Survey of Concrete Support Wall Remaining in Excavation 35 E:\Storage Port Final Report draft.doc

OFord Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Appendix I Analytical Data for Final Status Survey of Soil Located Behind the Section of Support Wall Removed 36 E:\Storage Port Final Report draft.doc

oFord Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Appendix J Analytical Results from Eberline Analytical for Final Status Survey Of the Soil under the Former Storage Port No. 1 37 E:\Storage Port Final Report drafi.doc

1. Ford Nuclear Reactor Storage Ports - Final Disposition Revision: 00, DRAFT Appendix K ORISE Confirmation Samples Collected by NRC 38 E:\Storage Port Final Report drafi.doc

APPENDIX A UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

Ford Nuclear Reactor Decommissioning Project Storage Port Characterization Surveys The following surveys were performed using a Ludlum 2221 meter (Serial No. 218802) and a 2" x 2" Nal probe (Ludlum 4410; Serial No. 242815)

Removable activity surveys (disc smeam) were also peiformed at each point whenever practical. Removable activity smears were counted on a L-2929 counter.

Survey Method: The Nal probe was placed onto a circular jig (see attafched photos). The jig ensured the probe remained centered within the storage port. The jig was attached to a string. The j*xobe was inserted into the storage port and measurements were taken at one foot (1-ft.) increments.

Survey point #1 represents the first measurement as the probe breaks the plane of the storage point. The August, 2006 measurements have elevated counts at the first port due to high exposure rates from staged radioactive materials on the Beam Port Floor (BPF).

Since exposure rates were elevated by radioactive materials in the areas surrounding the Storage Ports, corresponding graphs do not plot Pt #1 for the August, 2006 characterization surveys. Although the May, 2007 survey data show less elevated exposure rates for Pt. #1, statistics also exclude Pt. #1 to be consistent with the August, 2006 survey statistics.

Gross Gamma (cpm) vs Depth into Storsae Port Position (feet into Dort)

L D". Remowvabe

( ,dk& Surey Log Adivt port 1 2 3 4 5 S 7 S 9 10 11 12 13 Pton) PL) Stormy 04M No. Detlecw 1 4649 4904 4897 4886 5098 5064 5130 55781 8986 20 20581 14651 11696 9296 6053 172007 2007-0997 Y 2 5249 4754 4847 4785 4708 4761 4463 4686 4977 5377 52 5549 5027 49631 M17007 2007-0998 N 3 20700 6768 5 5219 5209 5004 5131 5311 5953 736 6065 698 8348 *1010 8/21/2006 20064013 N 4 21232 580 5433 52511 5113 50401 4985 5015 52731 5386 5711 535 5172 5300 277 77 1120o 2006"03U4 N 5 17429 5261 5204 5126 5116 5247 5292 5030 5342 5147 5013 5027 5042 5154 114 113=0011 2008-N470 N 6 16368 6776 5596 5248 5273 4920 5057 5081 5241 5471 5535 5332 5124 53 481 89oo0 2006-047 not surveyed 7 21008 6206 5550 5353 5189 5250 5156 5081 5323 5287 5359 5488 5121 536 302 81281200 2008-0468 not surveyed S 19735 5734 5510 5317 5106 5017 5175 5321 5267 5451 5850 5350 5041 535 259 2120048 2006-0469 not suveyed 9 2106 68005 5901 5728 5350 5532 5517 5623 5879 625 6368 6103 5512 5814 324 &WAN200 200M-071 not survyed 10 68 5706 83 582 5272 5303 524 5688 3 105 15106 23606 71422 14071 1677 5/17/2007 2007-0o9 Y 11 21228 5926 5541 5553 5296 5070 5234 5221 5336 5866 5662 5599 5206 "69 27442006 2006-0473 nOt SUrvey 12 20019 5935 5814 5579 5722 5766 5827 6013 6331 6913 7324 7434 7991 637 814 80osN 2008-0472 not eWwyed 13 22436 7342 6583 5894 65130 816 81540 6414 6017 5719 5729 5825 5362 6 537 613=011 2006-0474 not aurveyed 114 24569 5605 5587 5311 5203 5137 5557 5354 5354 5369 5427 5281 5002 537 130 o1206M 2006-0475 not uVeysd 15 18088 5469 5376 5439 5384 5129 5150 4964 5238 5027 5064 5032 5264 5213 173 W3012006 200.04976 not urveyed 16 27251 5631 5241 5199 5268 5328 5252 5131 5202 51261 5213 51061 5352 5256 141 13434200112006-0477 notZufveye 117 27156 52 5599 5461 5635 559 51597 5569 84 63611 65 56831 607 53 31 W=2006 2006*47 not surveyd 18 27724 5711 5410 5075 5125 5`149 5068 5014 5047 5166 5156 5236 5281 5203 1194 830N6 2006-0479 not urveysd 19 32823 5451 5040 5152 5208 5039 5114 5118 5198 5107 5126 5110 5090 5146 109 SAMOS00 2006-0492 roteurveire 20 35160 5613 5039 4942 5290 5594 57321 5677 5559 567 5710 5802 5795 56 233 11*3o10 20o6o493 not surved 21 33633 5609 4980 5094 5078 4869 5140 5089 5056 5159 5207 52633 5069 513 131 83120o 2008-N494 not surve 22 42950 58!55 4988 4777 4817 4866 491 5039 5047 5051 5067 5125 5182 5066 276 31/2006 2006045 not urmyed 23 43985 5299 4628 4557 4923 4877 4794 4834 4931 5041 5219 5258 5202 4947 2538 3lrAoos 20o6-"" not surveed 24 42749 7809 5631 5106 5058 5062 4958 4979 5076 51521 5112 5181 5057 5349 794 8131200 2006-04v7 not sunwpyd 25 6050 5636 482 4547 4649 4395 4617 4555 469 47591 4613 4923 482 4741 321 /r17/2007 2W07-1000 N 26 4879 4485 4486 463 4830 50971 5378 5218 573082191 50 5395 5399 52 547 517S207 2007-1001 N 27 5198 4708 4758 466 45991 459 46171 4818 481 48 4897 49 4963 4770 14 1 5/17/2007 2007-1002 N 1 of 2

Ford Nuclear Reactor Decommissioning Project Storage Port Characterization Surveys Gross Gamma (cpm) vs Depth into Storae Port Position (feet into port) I I *I - --

Removable 112 Av ers.. Stand. Dow. Survey Log Obtttd7 Part 3 4 5i 61I7 8 B 10 11 12 Pt PIn) I PLt.4) Survey Dobs No.

28 5634 4848 4729 4488 48 4 453 466 496 4792 4768 477 4790 12t 1712o7 2007-100o N 29 5702 47691 4720 4000 4794 4843 4998 4023 5057 509 5209 5239 22 /172007 2007-1004 N 30 5235 4747 4888 4738 4542 4627 4758 4763 4735 4902 5000 4801 12 5117/2007 2007-1005 N 31 5383 5146 5213 4957 5011 52945528520655246 5516 5476 5295 1S 5/1712007 2007-1006 N 32 5100 4844 4894 5101 4879 5142 5072 5426 58141 6372 627 5689 64 511712007 2007-1007 N 33 5524 4012 4794 485 5129 5887 5327 5174 5221 5037 4984 4780 324 511M07o 2007-100o N 34 6153 5020 4815 4005 4905 5004 5179 5275 5418 5500 5140 5068 226 5n*17,207 2oo7-100e N 38 633 565 695 6524 656 7129 880 6271 6426 606 546 5610 633 5/207 2007-1010 N 38 6538 4834 4702 5125 5401 5247 5654 5396 5583 5773 578 5248 341 170A07 2007-1011 Y 37 6381 4722 4712 4640 4808 4798 5006 4081 5220 5224 5321 5316 2 511S2007I 2007-1025 N 38 7306 4902 4813 4603 5036 5248 5362 5425 5450 5407 5443 5508 6 5/112007 2007-1024 N 39 825358255247 5254 5135 5262 5271 529152505540 54135330 218 MI1BO007 2007-1023 N 40 7482 4784 4955 49991 4960 4977 5708 5540 5525 5328 5186 5005 2* 5/162007 2007-1022 N 41 8923 5100 5170 5034 5439 5300 5625 5525 5706 5536 5525 5252 Z2 5M1OW2007 2007-1021 N 42 853 54761 5303 5134 5002 5280 835 5326 5208 536 5365 5103 152 5S/182007 2007-1020 N 43 7128 51531 5044 4921 4934 5049 5015 5038 4954 4961 5344 4984 14W 8121/207 2007-0 o37 Y 44 8479 5381 4910 4585 4730 4725 4736 4791 5023 4800 4927 4917 212 512112007 2007-1036 N 48 7727 5420 5466 5179 5024 5031 5162 5240 4938 5212 5027 5012 205 512112007 2007-1030 Y 48 11016 7470 6062 5392 5233 5319 5300 5451 4049 5092 5071 4936 723 5/212007 2007-1040 Y 47 8747 4933 4404 4731 4707 48124 4947 5091 4973 503M 46 5102 1* 512112007 2007-1041 Y 48 7889 5782 5474 5893 6407 5874 5750 50421 6312 6553 695 9954 1211 51211207 2007-1042 Y 48 11100 5707 5309 5186 5274, 507 5199 54791 649 6400 610 7789- 7 51211007 2007-1043 Y 50 17208 50171 4807 4605 46161 4550 47421 47861 488 498 5000 5034- 181 I2M1107 2007-1044 Y 2 of 2

FNR Storage Port #1: Nal Gross Gamma vs Depth 25000 20000 115000 E

.E 0 10000 z

5000 0

0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth into Port (ft)

Surveyed: 5-17-2007

FNR Storage Port #2: Nal Gross Gamma vs Depth 8000 7500 7000 .

6500 E

C.

V E

E- 6000 zl*-ý 5000.

4500 4000 I- I I~ I -- I.- ~ -I I- I 0 1 2 3 4 5 6 7 8 .9 10 11 12 13 14 Depth Into Port'(1)

Surveyed: 5-17-2007

FNR Storage Port #3: Nal Gross Gamma vs Depth 9000 8500 8000 7500 i

E 7000.

E E

E 6500 W

09 2 6000

-z 5500 5000 4500 4000 0 1 2 3 4 5 6 7 8 9 10 11 12. 13 14 Depth into Port (ft)

Surveyed: 8-21-2006

FNR Storage Port #4: Nal Gross Gamma vs Depth 8000o - p*Pt,

1. 1 = 21232 c*pm (Dueto High Background-on BPF)

-7500 7000 6500 0.

U.

E

,E 6000 U) 0 Z 5500 50001 4500 4000 .. . i 0- 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port-(ft)

Surveyed: 8-21-2006

FNR Storage Port #5: Nal Gross Gamma vs Depth 8000 Pt #1 = 17,429 cpm (Due to High Background an BPF).

7500 7000

'--6506 a.. o

{U E

E 600

.Co 0

-M 5500 z

5000 -

4500 4000 0 1 2 3' 4 .5 6 7 8 9 10 11 .12 13 14 Depth into Port (ft)

Surveyed: &-30-2006

FNR Storage Port #6: Nal Gross Gamma vs Depth 8000 Pt. #1 = 16,368 cpm (Due to High Background on BPF) 7500 7000 E 6500 0.

E A' 6000 5000 _,,_

4500 50001 0 1 2 3 4 5 6 7 8 9 10 11 12. 13 14 Depth into Port (ft)

Surveyed: 08-29-2006

FNR Storage Port,#7: Nal Gross Gamma vs Depth 8000.

PL #1 21,008 cpm (Due to High Background on BPF) 7500 7000 E65o a.

E E

' 6000 0

z*.5500 --

5000 4500 4000.

0 1 2 3 4 -5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 08-29-2006

FNR Storage Port'#8: Nal Gross Gamma vs Depth 000Pt,# = 19735'cpm (Due'to High'Background on BPF) 7500 7000 E

C. 6500 E

E 6000 1; 5500-Z 50

-4500 4000.

0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth into Port (ft)

Surveyed: 08-29-2006

FNR Storage Port #9: Nal Gross-Gamma vs Depth 8000 Pt.R.#I :21:;066 cpm (Due-to High Background'on BPF) 7500--

7000

6500

E E

6000

-w 0

I-5500 z

5000 4500 4000" 0 1 2 3 4 5 6 7 8 9 i0 11 12 13 14 Depth Into Port (ft)

Surveyed: 08-30-2006.

FNR Storage Port #10: Nal Gross Gamma vs Depth 80000 70000 60000 AE EL 50000 0.

c E

E m 40000 0

0 0

-R.30000 20000 10000 0

0 1 2 3 4 5 6 7 8 9 10 11 12. 13 14 Depth into Port (ft)

Surveyed. 05-17-2007

FNR Storage Port #11: Nal Gross Gamma vs Depth 8000 7500 7000' 6500 U

E

• E 6000 to 5500 5000 4500 4000

.0 1 2 :3 4 5 6 7 8 9 10 11 12 13 14 Depth into Port (ft)

Surveyed: 08-30-2006

FNR Storage Port #12: Nal Gross Gamma vs Depth 8500 8000 7500 7000 6500 7j.

U, 6000 5500 5000 4500 4000 0 1 3 A2 5 6 7 8 9 10 11 12 13 14 DepthInto Port (ft)

Surveyed: 08-30-2006

FNR Storage Port #13: Nal Gross Gamma vs Depth 8000 7500 7000 E 6500 E

,E 6000

'0L j 5500 z

5000 4500 4000 0 1 2 3 4 5 6 7 8 9 10 1.1 12 13 14 Depth into Port (ft)

Surveyed: 08-30-2006

FNR Storage Port #14: Nal Gross Gamma vs Depth 8000 Pt.#1 = 24,569repM (Due to High Background on BPF) 17500 7000 a.

0 6500 E

2 6000 0 K,*.

• - 5500 z

5000 4500.

4000 4.....

0 2 .4 6 8 10 12 14 Depth into Port (ft)

Surveyed: 08-30-2006

FNR Storage Port #15: Nal Gross Gamma vs Depth 8000 800 1"* Pt. #1= 16,088 cPM (Due to High Background on BPF).

7500, 7000 6500

'U 6000 5500 5000 4500 7 4000 0 1 .2 3 4 5 6 7 8 9 10 11 12 13 14 Depth into Port (ft)

Surveyed: 08-30-2006'

FNR Storage Port #16: Nal Gross Gamma vs Depth 7500 7000 E

c.

U 6500 E

E 6000

?A z 5500 5000 4500 4000 0 1 2 3' 4 :5 6 .7 8 9 10 '11 12 13 14 Depth into Port (ft)

Surveyed: 08-30-2006

FNR Storage Port #17: Nal Gross Gamma vs Depth 8000 -

Pt. #1 = 270156 cpm (Due to High Background on BPF) 7500 7000 E 6500-E S

66000, 0

• @ 5500 z

15000 4500

-4000" I 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth into Port (ft)

Surveyed: 08-30-2006

FNR Storage-Port #18: Nal Gross Gamma vs Depth 8000

( PDHg t #1 27B7r24acpm

,(Due t~o.High* Backg*0bund~on BPF) 7500 7000 E

6500 E

E 2 '6000

-- ý5500 z

5oo0 4500 4000 4 I I I I I I I I 0 1 2 3 4 5: 6 7 8 9 10 11 12 13 14 Depth Into Port (ff)

Surveyed: 08-30-2006

FNR Storage Port #19: Nal Gross Gamma vs Depth 8000 7500 7000 E.

0. .6500 EU E

6000 27

U

!5500 5000 4500 4000 0 1 2 3 4 5 6 7 8ý 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed:: 08-31-2006

FNR Storage Port#20: Nal Gross Gamrma vs Depth 58000 7500 7000 6500 E,

E 6000 5500 5000 4500 4000 0 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port'(ft)

Surveyed: 08-31-2006

I FNR Storage Port #21: Nal Gross Gamma vs Depth 8000 (Due to High Background on-BPF) 7500 7000

'E 6500 E

E

• 6000 to U) a 5500 z

5000 4500 4000 I ' ' , I I I I I I I -

0 1 2 3 4 5 6 .7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 08-31-2006

FNR Storage Port #22: Nal Gross Gamma vs Depth 8000 7500 7000

. 6500

'0

(*6000

L.

'5500 5000 4500 4000 0 1 2 3" 4 5 6 7 8' 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 08-31-2006

FNR Storage Port #23: Nal Gross Gamma vs Depth 8000 Pt. #1 = 43,985 cpm (Due to High Background on BPF) 7500 7000

' 6500.

U E

E 6000 0

• 5500 I ,

z 5000 4500 4000

,2 3 4 2 5 0 1 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 08-31-2006

FNR Storage Port #24: Nal Gross Gamma vs Depth

'8000 7500 7000:

C. 6500 U.

E E

6000 I-

-* 5500 z

5000, 4500 4000

0. 1 2 3 4 5 6. 7 8 9 10 11 12. 13 14 Depth Into Port (ft)

Surveyed: 08-31-2006

FNR Storage, Port #25: Nal Gross Gamma vs Depth 8000-7500 7000 6500 6000

• ~5500,,

5000 4500 4000"1 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #26: Nal Gross Gamma vs Depth 8000 7500 7000 6500

.E

'E 6000 5500 Z

5000 4500 4000 0 1 2 3 4 5 6 7 8 ,9 10 11 12 13 14 Depth Into ,Port (ft)

Surveyed: 05-17-2007

FNRStorage Port #27: Nal Gross Gamma vs Depth 8000

(

7500 7000 65t00 Al 6000 5500 5000 4500 4000 I I I>~. I I I I I I 0 1 2 4 5 6 7 81 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #28: Nal Gross Gamma vs Depth 8000 I

,J 7500-7000 E

0. 6500 0

E 6000 0

0 0

z 5500 5000 4500 4000 I. I I I I I I I 0 1 2 .3 4- 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #29: Nal Gross Gamma vs Depth 8000 7500 7000 6500 E

6000 70 0

5500 z

5000 4500 4000 0 2 3 4 5 6 7 8 9 10 1.1 12 13 14 Depth Into Port (ft)

-Surveyed: 05-17-2007

FNR Storage Port #30: Nal Gross Gamma vs Depth 8000 7500 7000 6500

'E E

6000 7ra Z,

5500 5000 4500 4000 0 1 2 3 4. 5 6 7 8 9 1O 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #31: Nal Gross Gamma vs Depth 8000 7500 7000 a.6500 C) 6000

• -* 5500 5000 4500 4000 I.. I I* I 'I I* I I I 0 1 2 3 4 5 6 7 8 9 10- 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #32: Nal Gross Gamma vs Depth 8000 7500 7000 E

EL- .6500

E 6000 (A

05500 z

5000 4500 4000 1 2 3 4 5 6 7 8 9 10 11 12 13 14

.-Depth Into Port (ft)

Surveyed- 05-17-2007

FNR Storage Port #33: Nal Gross Gamma vs Depth 8000.

7500 7000 Ui. 6500:

(E E

0 6000 7g 5500 5000--

4500 4000 .2 1i I <

0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #34:1 Nal Gross Gamma vs Depth

'8000 7500 7000-

,E' 0L 6500 E

E

,( 6000.

0 2' 5500 5000-4500 4000 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #35: Nal Gross Gamma vs Depth

.7500 7000" 6500-Uf 0.

c 6000 E

E 2 5500 0,

CD z

5000 4500-4000 0 1 2 3 4 '5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17;-2007

FNR Storage Port #36: Nal Gross Gamma vs Depth

.8000.

7500 7000 E

cL6500 -.

.E

-E 6000 0

z, 5500 5000 4500, 400I I " . I I 0 1 2 3 4 5 6: 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #37: Nal Gross Gamma vs Depth 8000 7500 7000 CL 6500

E

• E 6000 0 5500 5000.

4500 4000 F.

0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-18-2007

FNR Storage Port #38: Nal Gross Gamma vs Depth 8000-7500 7000-600 E

E O6000

-a 5500 z

5000 4500 4000..

0 1 2 3- 4 5 6 7 8 9 10 11 12 13. 14

,Depth Into Port (ft)

Surveyed: 05-17-2007

FNR Storage Port #39: Nal Gross Gamma vs Depth 800 0 750 0-700 0*

a. 650 o

E)

E 550(

500 0'

450 500(

0' i¸ & I I t 0 1 2 3 4 5, 6 7 8 9 10 11 12 13 14 Depth Into Port (ft),

Surveyed: 05-18-2007

FNR Storage Port-#40: NalGross Gamma vs Depth 8000 7600 7000-C. 6500 E

E -

6000 U

" 5500

.z 5000 ----

4500 -

4000 0 1 2 a 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (if)

Surveyed: 05-18-2007

FNR Storage Port #41: Nal Gross Gamma vs Depth 9000 8500 8000 7500 0.

oS 7000 E

E 2 6500 0

o 6000 5500-5000 4500 4000I I I 0 1 2. 3 4 5 6 7 8 9 10. 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-18-2007

FNR Storage Port #42: Nal Gross Gammavs Depth 9000 -

8500 8000 7500 Ea.

.. 7000 E

Eý 6500

., 6000 z

5500U 5000-4500 4000 I I I I I t 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-18-2007

FNR Storage Port #43: Nal Gross Gamma vs Depth 7500 .

7000

,6500 C.

U w 6000 E

E 10 5500-5000 4500 4000' 0 1 2 .3 4 5' 6 7 8 9 10 11 12 13 14 Depth Into Port (fit)

Surveyed: 05-21-2007

FNR Storage Port#44: Nal Gross Gamma vs Depth 9000 8500 8000 7500 7000 E

E 6500 6000 I-5500 5000

'4500 4000

0. 1 2 3 4 5 6 7 8 9 10 11 12, '13 14 Depth Into. Port (ft)

Surveyed: 05-21-2007

FNR Storage Port #45:- Nal Gross Gamma vs Depth 8000 7500 7000 6500-6000 7r 5500 z

'5000 4500 4000- "'

0 1. 2 3 4 5 6 7 8 9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-21-2007

FNR Storage Port #46: Nal Gross Gamma vs Depth 9000

'8500 8000 7500 E

. 7000 E

E 6500 0 6000 z

5500 5000 4500.

4000 0 1 .2 3 4 5 6 7 8 -9 10 11 12 13 14 Depth Into Port (ft)

Surveyed: 05-21-2007

FNR Storage Port #47: Nal Gross Gamma vs Depth

'9000-8500-8000, 7500 E.

2. 7000; Cu E

W65001 0

6000 z

5500 5000'-

450W 4000I 0 1 2 3 4 5 :6 7 8 9 10 11 12 '13 .14 Depth Into Port (ft)

Surveyed: 05-21-2007

FNR Storage Port #48: Nal Gross Gamma vs Depth 10000-9500 9000 8500 8000 2

C.

m 7500 E

E 2

0 7000 (A

-6500 z 6000 5500 5000

'4500 4000 0 2 4 6 8 10, 12 14 Depth Into Port (ft)

Surveyed: 05-21-2007

FNRStorage Port-#49: Nal Gross Gamma vs Depth 9000 8500-8000 7500 C.

, 7000 E

6500:

6009 5500 5000 4500 4000 0 2 4 6 8 10 12 14 Depth Into Port (ft)

Surveyed: 05-21-2007

FNR Storage. Port #50: Nal Gross Gamma vs Depth 9000.

8500 8000 7500 E

C.

o 7000 E

E

• m 6500 (I) 0 o 6000 z

5500 5000 4500 4000 0 2 4 6 8 10 12 14 Depth Into Port (ft)

Surveyed: 05-21-2007

APPENDIX B UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

G A m MA E C TR U M A N A L Yf S Filename: C:\Soil\2008-11-06-01\2008-11-06-01N_100000_2008Novl0.CNF Report Generated On 12/17/2008 6:07:55 PM Sample Title Soil Background - Storage Port Fill Sample Description 500 ml nalgene Sample identification UM-2008-!!-06-01 sample Type soil Sample Geometry 500 ml Nalgene Peak Locate Threshold 3.00 Peak Locate Range (in channels) 1 - 8192 Peak Area Range (in channels) 5 - 8192 Identification Energy Tolerance 1.000 key Sample Size 1.000E+003 g Sample Taken On 9/1/2008 11:45:00 PM Acquisition Started 11/10/2008 9:07:01 AM Live Time 100000.0 seconds Real Time 100100.3 seconds Dead Time 0.10%

Energy Calibration Used Done On  : 12/17/2008-

Nuclide MDA Report 12/17/2008 '6:97:47 PM Page 1 N U C L I D E M D A R E P OR T Detector Name: HPGE Sample Geometry: 500 ml Nalgene Sample

Title:

Soil Background - Storage Port Fill Nuclide Library Used  :"

C\GENIE2K\CAMFILES\LIbraries\Soil_DCGL-Nuclide Energy Yield Line MDA Nuclide MDA Activity Name / (keY) (%) (uCi/g ) (uCi/g (uCi/g

+ Pb x-ray 72.80 61.00 1.7312E-008 1.73E-008 -6.8954E-009 75.00* 100.00 1.8854E-008 4.993OE-008

84. 90* 36.00 2.1462E-008 1.8456E-008 87.60* 10.00 9.0358E-008 -2.1696E-007 BE-7 477.59 10.42 2.8147E-007 2. 81E-007 2.8645E-008

+ K-40 1460.75* 10.67 2.0949E-007 2.09E-007 8. 9679E-006 MN-54 834.83 99. 98 1..7669E-008 1.77E-008 -4.,3999E-009 CO-60 1173.,24 99.90 2.0256E-008 1.76E-00'8 8.3258E-009 1332.50 99. 98 1.7643E-008 .1.5454E-008 ZN-65 511. 00 2.83 7.5535E-007 5.71E-008 -7.9533E-008 1115.55 50.70 5.7140E-008 -4.0718E-009 NB-94x 702.62 97.90 1.4098E-008 1.41E-008 3.1511E-009 871.09 99.90 i.4750E-00:8 5.3043E-009 AG-108m 79.13 6.60 1.6780E-007 1.30E-008 1. 6613E-008 433.94 90.50 1.3046E-008 8.7054E-009 614.28 89.80 2.5348E-008 2 .2054E-010 722.94 90.80 1. 6153E-008 4. 0493E-009

+ CD-109 88.03* 3.61 2.7407E-007 2.74E-007 6. 5808E-007 AG-110m 446.81 3 .75 3.A6686E-007 I..64E-008 1. 5427E-007 620.36 2.81 5. 4534E-007 -1. 188'2E-007 657.76 94.60 I.6445E-008 6. 0295E-010 677.62 10.35 1.4631E-007 -6. 8294E-008 687.02 6 . 44 2.49,55E-007 4. 0062E-008 706.68 16.44 I. 0337E-007 8. 7489E-008 744.28 4.73 3.6893E-007 1. 4310E-007 763..94 2,2.29 8.8737E-008 I. 8806E-008 818. 03 7.34 2.3929E-007 6. 7159E-009 884.68 72.70 2.4825E-008 -2. 5776E-010 937.49 34.36 5.7360E-008 -8. 6489t-009 1384.30 24.28 8.1767E-008 4. 3171E-008 1475.79 3.99 3. 64'1E-007 1. 1523E-007 1505.0'4 13.04 1.3429E-007 -8. 3139E-008 1562.30 1.03 1.4606E-006 4. 8391E-007 SB-125 176.33 6.79 1.5043E-007 4. 02E-008 -7. 9700E-008 380.43 1.52 7.5359E-007 3. 8838E-008 4'27.89 29.40 4.0236E-008 -1. 7034E-008 463.38 10.45 1.,2215E-007 1. 62480E-007 600.56 17.78 7.,5604E-008 6. 5278E-008 606.64 5.02 5.0997E-007 -5 .8991 E-008 635.90 11.32 1ý. 1386.E-001- 2.8665E-010 671.41 1.80 7.,5226E-007 -1.732923E -007 BA-133 53 .16 2z.20 3.7734E-007 *2.73E-008 1. 7622E-007

Nutlide MDA Report 12/17/2008 6:!r47 PM Page 2 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g (uCi/g (uci/g )

BA- 133 79.62 2 .62 4.2479E-007 2.73E-'008 -1. 9400E-009 81.00 34.10 2.7340E-008 -1. 1400E-008 160.61 0 .64 1.4401E-006 7. 0942E-007 223.23 0.45 2.2985E-006 7. 5210E-007 276.40 7.16 1.4778E-007 3. 9165E-008 3.02.85 18 .33 5.7083E-008 3. 8433E-010 356.02 62. 05 2.8064E-008 -2. 7673E-008 383.85 8 .94 1.2801E-007 6.5646E-008 CS-134 475.35 1.46 8.5311E-007 2i.90E-008 -2. 8470E-007 563 .23 8.38 1..5525E-007 -7.4280E-011 569. 32 15.43 8.5974E-008 8.6071E-009 604.70 97.60 2..0763.E-008 -3. 0739E-009 795.84 85.40 1. 9032E-008 2. 3069E-008 801.93 8.73 1.7546E-007 -7. 2547E-008 1038 .57 1. 00 1.8112E-006 -4. 1042E-007 1167.94 1.80 1.1535E-006 1. 0394E-006 1365.15 3 . 04 4.9918E-007 3. 8692E-007 CS-137 661.66 85.21 1.6079E-008 1.61E-008 7 .4697E-009 EU-152x 121.78 28.40 2.8786E-008 2.88E-008 1 0174E-009 244.70 7.49 i. 5999E-007 2ý.0757E-009 344 .28 26.60 4.1085E-008 -6.0935E-009 411.11 2.23 5.2242E-007 -1.2062E-007 443.98 2.78 4.1100E-007 -1.3841E-007 778.90 12.96 1.1246E-007 -8. 9233E-009 867.39 4.15 3.6246E-007 5. 2208E-008 964.13 14.34 1.3505E-007 -3. 9789E-008 1085,91 9.92 1. 7523E-007 -9. 4027E-009 1089. 70 1.'71 1.0295E-006 3. 0797E-0,07 1112 .12 13. 55 1.3612E-007 1. 8966E-008 1212. 95: 1.40 1.5750E-006 -7. 2865E-007 1299 12 1. 63 0.0407E-006 1. 3197E-007 1408 .01 20.87 7.8480E-008 1. 0402E-007 EU-154 123 . 07 40,40 2.0536E-008 2.05E-008 1. 1116E-009 188.25 0.23 4.9960E-006 -9. 2005E-007 247.93 ,6.'83 1. 4678E-007 -9. 6790E"009 4D01.30 0.19 6.0017E-006 -9. I079E-007 444.39 0.55 2..0762E-006 -1. 0161E-006 478.26 0.21 5.17388E-006 9. 3377E-007 557.56 0.25 4.7266E-006 -2. 3068E-006 582. 00 0.89 I. 9537E-006 1i0025E-005 591.76 4.91 2.4453E-007 -2.3015E-007 625.22 0.32 3.9055E-006 -1.6843E-006 676.59 0.14 9.2642E-006 -4.9429E-006 692.42 1.78 7.6497E-007 -5.9129E-008 715 .76 0.117 7.7322E-006 -5 2589E-006 722.30 2.0. 00 7.0082E-008 -2. 3892E-008 756.86 4.50 3.2676E-007 -7. 5369E-009 815.55 0.50 2.8984E-006 -1. 7062E-006 845'.39 0 458 2 .5718E-006 ý1.4378E-006 850.64 0.23 6.3928E-006 -2. 7820E-006 873; 20 12.09 1. 2349E-.007 2. 7098E-008

Nuclide'MDA Report 12/17/2008 6:,-:47 PM Page 3 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (uCi/g/ ) (uCi/g (uCi/g EU-154 892.73 0.50 3. 0741E-006 2. 05E-008 -1.2778E-0Q7 904.05 0.85 1. 81OE-006 1.5800E-007 996.30 10.34 1.5704E-007 -1.1905,E-008 1004.76 17. 90 9. 7292E-008 1.2028E-007

-3. 5137E-006 112'8.40 0.29 6. 3588E-006 1140.90 8. 5255E-006 -6. 8257E-007 1241.60 0.13 1. 9085E-005 -9. 0839E-006 1246.60 0.80 2. 5117E-006 -3. 5308E-006

-6. 9981E-008 1274.51 34.40 5. 2824E-008 1494.08 0'71 1. 8543E-006 -7. 9253E-007 1596.45 1.80 7. 7621E-007 -7. 5055E-008

+ TL-208B 7T2.8 2.02 5 .2279E-007 1. 79E-008 -2. 0823E-007 74.97* 3.41 5 5290E-007 1.4642E-006 84.90* 1.51 5. 1168E-007 4.4002E-007 277.3,6* .6.31 1. 2898E-007 7.9916E-008 510.77* 22.60 1. 1666E-007 1.3365E-007 583. 19* 84.50 1. 8279E-008 7.9848E-008 763.13 1.81 8. 7109E-007 -5.9783E-008 860. 56* 12.42 1.5089E-007 1.,1443E-007 2614.53* 99.16 1.7922E-008 9.1687E-008

+ Pb-2io 46.52* 4.05 2.3910E-007 2. 39E-007 3.:8653E-007

+ PB-212B 74,. 81* 10.50 1.7956E-007 4. 76E-008 4.7552E-007 77.111* 17.60 1.0722E-007 4.5689E-007

87. 30* :7. 90 1.1438E-007 2.7463E-007 238.63* 4,3.60 4.7555E-008 2.6027E-007 300.09* 3.34 3.1207E-007 1.3451E-0.07 BI-214B 609. 31* 44.80 4.8603E-008 4. 86E-008 3.8037E-007

+

665 45* 1.29 9.2101E-007 6. 6909E-007 768.36* 4.80 4.0987E-007 4.5556E-007 806. 17* 1.12 1.559ý5E-006 8.4699E-007 9 34. Q6* 3 03 7.4092E-007 1.6421E-007 11i20 29* 14,.80 1.9382E-007 4. 3643Ef-007 1155.19 1.64 1-2132E-006 1.3175E-006 1238.11* .5.886 4.2833E-007 5. 5968E-007 12'80.96 1.44 1.3007E-006 1. 7046E-006 1377?67* 3.,92 4.2373E-007 3. 7318E-007 1401.50* 1.55 9.1760E-007 4. 8399E-007 14.0,7.98* 2.80 5.,3286E-007 3. 7594E-007 1509.23* 2.12 7.7084E-007 5. 5296E-007 16.61.28 .i.14, 1.b0383E-006 -3. 6302E-007 1729. 59* 2.88 6.1080E-007 3.8151E-007 1764 49* 15. 3'6 1. 4213E-007 3.7158E-007 1847 .42* 2 .04 9.1315E-007 8.0059E-007 2118.55 1. 14 1.1561E-006 -2,1082E-007 2204. 21* 4 .86 2.8591E-007 7.3993E-007 2447.86* 1.,2947E-006 4.2322E-007

+ PB-214B 53.23* 1. 1'1 7. 0559E-007 4. 57E-008 3.5720E-007

74. 81* 5.90 3.1956E-007 8.4626E-007 77.11* 9.90 1; 9061E-007 8.1226E-007 87.30* 4.41 2.048 9E-007 4.;9197E-007 24.1.98* 7.50 2.,8262E-007 4.,6078E-0Q7

Nuclide MDA Report 12/17/2008 6:q4:47 PM Page 4 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (kev) (%) (uCi/g ) (uCi/g (uCi/g

+ PB-214B 295.21* 18.50 7.9660E-008 4. 57E-008 4.0375E-007 35.1.92* 35.80 4.5726E-008 3. 9887E-007

+ RA -226 186.10* 3'.50 3.6333E-007 3.63E-007 6. 8903E-007

+ AC-228B 12.95 15.10 1.6557E-006 7.09E-008 -1. 1996E-005 16.15 20.00 4 .4331E-007 -2. 6600E-006 19.11 4.60' 9. 2538E-007 -1. 5923E-006

.89.96* 3.40 3. 9161E-007 3.18590E-007 93.35* 5.60 2. 5957E-007 4,. 6363E-007

.99.55* 1 30 5 .4002E-007 4. 6691E-007 105.36 2.00 4. 0651E-007 4.7495E-008 129. 03* 2. 90 2. 6337E-007 1.4655E-O07 209.39* 4.10 2. 1806E-007 2. 7152E-007 270.26* 3.80 3 .4606E-007 2.4428E-007 328.07* 3 .50 2. 7746E-007 2. 2795E-007 33.8.42* 12. 40 8. 4379E-008 2. 9111E-007:

409.62* 2.20 6. 2330E-007 2. 0545E-007 463.10* 4.60 2.'6564E-007 3.5236E-007 5622. 65 1.01 1.2141E-006 -2. 1701E-007 755.28 1.32 i.1028E-006 9. 0669E-008 772.28 1. 09 1.5442E-006 6. 3911E-0o8 794. 79* 4 .60 -2.8188E-007 2.2660E-007 83;5.60 1.71 8.9855E-007 -1 .12797E-007 911.16* 29.00 7.0879E-008 2. 2971E-007 964.64* 5.80 2.4653E-007 1. 9612E-007 968.97* 17.40 8.4908E-008 2. 6778E-007 1.06 5. 6817E-006 9.3381E-005 1459..19 1496.00 1.05 1.2553E-006 4.6106E-067 3.60 4.3444E-007 -7. 8049E-008 1588.23 1630.47 1.95, 6.5277E-007 4 . 6825E-007 PA-234B 63.00 3.20 2.8589E-007 3. 50E-008 -8.4035E- 008-94.67 14,.30 6, 6056E-008 -1. 1601E-008 98.44 23.00 3.4991E-'008 3. 4064E-009 99.7.0 4. 80 1.683 9E-007 3. 4916E-008 111.00 100.80 7.673 OE-008 3. 6766E-008 125.40 1.00 84.4102E-007 -4.4674E-007 131.20 20.0.0 4 .3648E-008 5. 8143E-009 152.70 61.70 1.. 3965E-007 -3 .4 542E- 008 186.00 2.00 5,.8159E-007 2. 3512E-006 2.00.90 1.00 1.02i2E-006 1. 5893E-007 202.90 1.20 8.5387E-007 8.1785E-008 226.40 5.90 1. 7491E-007 -1, 0841E-007 227.20 5.50 1. 8848E-007 -8. - 1392E-0D08 248,.90 2'. 80 3.5761E-007 -6. 9412E- 008 272.10 1.00 1.1039E-006 -3. 5589E-007 293.70 3.90 3.6928E-007 -1. 2072E-007 369.80 2.19-0 3;8494E-007 1.9626E-007 372.40 1.30 8.,4695E-007 -1. 2731E-007 458.8,0 1.50 7.9411E-007 -2. 9967E-008 506.80 1.60 1. 0030E-006 -2.6117E-007 513 .70 -1.30 1.3535E-006 5. 0962E-008 5,65. 90 1.40 9.0435E-067 5. 770 9E'- 0017

Nuclide MDA Report 12/17/2008 6: 5:47 PM Page 5 Nuclide Energy Yield Line MDA Nuclide MDA .Activity (uCi/g )

Name (keV) (i) (uCi/g ) (uCi/g PA-234B 568 .70 3.30 3. 8179E-007 3 .50E-008 -2.5676E-008 569.50 10.00 1. 2613E-007 1. 2628E-008 574.00 2.00 6. 2872E-007 -2. 1914E-007

1. 3361E-006 664.80 1.30 1. 0724E-006 666.70 1.60 8. 6195E-007 3. 0313E-007 669. 90 1.40 9. 4827E-007 -1. 6473E-007 692.70 1.50 9.0478E-007 -4. 1787E-008 699.00 4.60 2. 9748E-007 -2. 1391E-007 706 .10 3.10 4. 5650E-007 5 .3844E-007 733.00 9.00 1. 6937E-007 2.1644E-009 738.00 1.00 1. 4768E-006 -2.6685E-007 742.81 2.40 6. 0690E-007 9.7801E-008 755. 60 1.40 1. 0416E-006 -6.7296E-009 780. 70 1.10 1. 3520E-006 -4.6143E-008 786.27 1.40 1. 0551E-006 -8.3617E-007 793 .60 1.50 1. 0392E-006 1.5215E-006 796.30 3.80 4 0829E-007 6.5897E-007 805.80 3.30 4 .4124E-007 2. 9526E-007 819. 60 2.60 5. 6820E-007 4..5623E-008 826.30 4.00 3. 8135E-007 3. 2153E-007 831 .60 5.50 2. 7817E-007 1.3670E-007 876.40 4.00 3. 6869E-007 -4 .33722E-008 880.50 4.00 3. 6424E-007 -3.0321E-007 880.51 9.00 1. 6188E-007 -1.3476E-007 883.24 15.00 9. 9918E-008 3.3205E7008 899.00 4.10 3 .7150E-007 -5. 0801E-009 925.00. 2.90 5. 2849E-007 7. 475.ý3E-008 926.00 ii. Q0 1-.3835E-007 -3.0267E-008 927.10 11.00 1.3780E-007 -9.0792E-008 946.00 .12.00 1.3229E-007 7.5176E-008 9'4 9. 00 :8.00 1. 9753E-007 1.6926E-007 978.80 1.40 1. 0857E-006 -1.3248E-007 2 .4922E-007 980.50 2 .00 7.6961E,-007 980.50 3. o0 5. 1307E-007 1. 6615E-007 984..00 1.90 8.2918E-007 6. 9079E-008 1353. .30 1.70 8.8483E-007 -2..4300E-007 1394,.10 3.00 4.5838E-007 2.5716E-008 1452. 70 1.00 1.8093E-006 -2.5344E-007 1668.50 1.20 9.4669E-007 -7.4170E-007 1694.60 1.20 1.0156E-006 -4ý 8341E-007

+ TH-234 63.29" 4.50 1.7585E-006 1. 76E-006 9.6449E-007 92.38 2.60 2.8420E-006 1. 5332E:-005 92.80* 2.60 4.1278E-006 7.3727E-006

+ UU-235 72.70 0 .11 9.4758E-006 2.21E-008 -3.7742E-006

89. 95* 2 .80 4.6931E-007 4.6246E-007 93.35* 4.50 3.1880E-007 5.6941E.007 94 . 00 0.40 2.3388E-006 -3.4545E-007 105.000 2 .10 3.8144E-007 7.7268.E-008 109.16 1.50 5.3782E-007 -3 .4139E-007 140.76 0.22 4. 1492E-.006 -7.6042E-007 143.76* 10.90 8 ,9113E-00o8 3.5441E-008

Nuclide MDA Report 12/17/2008 6:r':47 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keY) (%) (uCi/g ) (uCi/g (uCi/g

+ U-235 163.33 5.00 1.8444E-007 2. 21E-008 6.4852E-009 182.61 0.40 2. 6956E-006 -4.0257E-006 185.71* 57.50 2. 2114E-008 4.1937E-008 194.94 0.59 1. 6992E-006 3.3220E-008 202.11 1.00 1. 0055E-006 -5.,1415E-007 205.31 5.00 2 0423E-007 -1.1028E-008 279.50 0.27 3. 7867E7006 3.;2493E-006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

• = MDA value not calculated

@ = Half-life too short to be able to perform the decay correction

APPENDIX C- I UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

G A M MA S E C T R UM A N A L Y S Filename: C:\Soil\2008-12-18-01\2008-12-18-O1N 10000.0_2009Jan2.CNF Report Generated On 1/5/2009 3:47:54 PM Sample Title Soil Immediately in Vicinity of Storage Sample Description 500 ml Nalgene Sample Identification 2008-12-18-01N Sample Type Soil 2.0 g/cc Sample Geometry 500 ml Nalgene Peak Locate Threshold 3.00 Peak Locate Range (in channels) 8 - 8192 Peak Area Range (in channels) 8 - 8192 Identification Energy Tolerance 1.000 keY Sample Size  : 1.000E+003 g Sample Taken On :012/18/2008 11:55:00 AM Acquisition Started'  : 1/2/2009 10:37:40 PM Live Time 100000.0 seconds Real Time 100007.8 seconds Dead Time 0.01 %

Energy Calibration Used Done On  : 12/18/20Q08 Efficiency Calibration Used Done On 12/17/2008 Efficiency ID

Nuclide. MDA Report 1/5/2009 3:":51 PM Page 1 N U C L I D E M D A R E P 0 R T

• * ** * ** *** ** * *** ** ** * * ** ****** * ** *** ** * *** *~*** ** * * *** ** ** * ** ** ** ** ** * ** *****

Detector Name: HPGE Sample Geometry: 50Q ml Nalgene Sample

Title:

Soil Immediately in vicinity of Storage Nuclide Library Used: C:\GENIE2K\CAMFILES\Llbraries\SoilDCGL_

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uci/g

+ Pb x-ray 72.80 61.00 2. 279,OE-008 1. 99E-008 -7.3552,E-009

75. 00* 100.00 1.9939E-008 6.2027E-008 84 . 90* 36 .00 9.9714E-008 7.8783E-008 87.60* 10.00 3.5953E-007 4, 7002E-007 BE-7 477,59 10.42 1.9989E-007 2. OOE-007 9.2997E-008

+ K-40 1460.75* 10.67 2.1220E-007 2. 12E-007 1. 1019E-005

+ MN- 54 834.83* 99. 98 2.2026E-008 2.20E-008 l.5932E-008

+ CO-60 1173.24* 99.'.90 4.0304E-008 2. 61E-008 4. 6182E-007 1332.50* 99.98 2.6145E-008 4.4833E-007 ZN- 65 511.00 2.83 8.2718E-007 8..26E-008 4.6003E-006

,1155.55 50.70 8.2641E-008 6. 7304E-007 NB-94x 702.62 97 .90 2. 0800E-008 2. 08E-008 1. 3779E-008 871.09 99. 90 2. 8204E-008 1. 4854E-008 AG-108m 79.13 6. 60 2. 1680E-007 1. 77E-008 -3. 3509E-007 433.94 90. 50 1. 7691E-008 -1.0709E-008 614.28 89.80 2. 8847E-008 -2.9331E-008 722.94 90.80 2. 5222E-008 1.1850E-008

+ CD-109 88 .03* 3 .61 1 0163E-006 1.02E-006 1.3286E-006 AG-llm 446.8'1 3 .75 5.1169E-007 2. 15E-008 -1.0785E-007 620.36 2 .81 7. 0796E-007 -3,5764E-007 657.76 94.60 2. 1492E-008 -2 .0575E-008 677.62 10.*35 2.0031E-007 -i.2930E-007 687.02 6.44 3.3201E-007 1.1237E-007 706. 68 16.44 1.2912E-007 -3.6883E-008 744 .28 4.73 4.8487E-007 1 3,469E-007 763.94 22.29 1.1253E'007 -6.3800E-008 818.03 7.34 3.2259E-007 -2.2128513.E-008 884.68 72.70 3 .4213E-008 7.6985E-009 937.49 34.36 7 .4316E-'08 -7.5817E-009 1384..30 24.28 7. 4132E-008 -4.2231E-008 1475.79 3.99 3 .4329E-007 -l. 9457E-007 1505.O 4 13 .04

1. 1881E-007 -1.5693E-008 1562.30 1.03 1. 2901E-006 -6.2532E-007, SB-125 176.33 6.79 2. 1164E-007 5.53E-008 -3. 4249E-008 380.43 1 .52 1.0219E-006 -7 0704E-007 427.89 29.40 5.5274E-008 -1.8866E-008 463.38 10.45 1.6231E-007 5.8298E-008 600.56 17.78 1.1099E-007 4.1788E-010 606.764 5 .02 5.7244E-007 -2.3331E-008 635.90 1. 3.2. 1. 6916-E P007 3.2!18E-008 67,1..41 1.80 1. 1021E-006 -1. 09,18E-006 BA 133 53.16 2; 20 4. 9756E:-007 3. 15E-008 l. 0735E-007

Nuclide. MDA Report 1/5/2009 3:10:51 PM Page 2 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g .(VuCi/g BA-133 79.62 2.62 5.4466E-007 3. 19E-008 -8.4640E-007 81.00 34.10 3.8162E-008 -1.6450E-007 160.61 0 .'64 2.1384E-006 2.8297E-006 223-.23 0.45 3.3399E-006 1.1284E-006 276.40 7 .16 2.0579E-007 5.2598E-008 302.85 18 .33 8.0133E-008 -1. 6931E-008 356.02 62 .05 3.11866E-008 -1.0333E-007 383.85 8 .94 1.7541E-007 -4.4408E-009

+ CS-134 475.35 1.46 1.1640E-006 I 59E-008 2.7777E-008 563.23* 8.38 1.5977E-007 5.5290E-008 569.32 15 .43 1.2439E-007 -3.5171E-008 604. 70* 97.60 1.5930E-008 1.9392E-0081 7-95.84* 85.40 2.0223E-008 2. 7770E-008 801.93 ,--8.73 2.5819E-007 -2.2145E-007 1038.57 1.00 2.3764E-006 -2.9657E-006 1167.94 1.80 2,3336E-006 4;2343E-007 1365.15 3.04 5.3262E-007 2.1101E-007 CS-137 661. 66 85.21 2.3295E-008 2.33E-008 6. 7507E-009

+ EU-152x 121.78* 2,8.40 6.3672E-008 6. 37E-008 1.,9663E-006 244.70* 7.49 4.6185E"007 1.9143E-006 344 . 28* 26.60 7.0919E-008 1.8879E-006, 411. 11* 2 23 7.18608E-007 2.1749E-006 443 .98* 2.78 7.1092E-007 2.12104E-006 778. 90* 12.96 1.7189E-007 2.0531E-006 867.39* 4.15 6.1539E-007 1.8145E.-006 964. 13* 14.34 2. 9108E-007 2.0566E-006 1085.,91* 9.92. 4.6298E-007 2.0919E-006 1089.70*. 1.71 2.7021E-006 2.6391E-006 11-12.12* 13 .55 2.4919E-007 2.b0369E-006 1212.95* 1.40 1.7558E-006 2.2261E-006 1299.12. 1 .63 1. 1766E-006 1.9564E-006 14'08..01* 20.87 9.5893E-008 2.0823E-006 EU-154 12.3.07 40.40 5.3508E-008 5.,35E-008 - 4. 5774E-009 188.25 0.23 6.,7518E-006 -3.6636E-006 247.93 6.83 2.6435E-007 1.4184E-006 401.30 '0 19 8..332!E-006 3.1884E-006 444.39 0.55 3.3662E-006 1.1169E-005 478..26 0 .21 8. 1163E-006 5.2896E-006 557.5.6 0.25 7.2431E-006 -5. 1831E-006 582.000 0.89 2.6094E-006 9.6606E-006 591.76 4 .91 3.8831E-007 -2.7262E-007 625.22 0. 32 5.9727E-006 -2.9648E-008 676.59 0.14 1 .4582E-005 -2.2096E-006 692.42 1.78 1.1787E-006 -5.1231E-008 715.76 0.17 1.2112E-005 2.16098E-006 722.30 20.00 1.1154E-007 4.5687E-008 7.56.86 4.50 5ý!1234E-007 2.6612E-007.

815.55 .0.50. 4.564 OE-006 3.6749E-007 845.39 0.58 4. 0517E- 006 2.2147E-006 850.64 0. 23 .9.9898E-006 -5. 8306E-006 873'.20 12,.09 ,2.12458E-007 -2. 9083E-008

Nuclide. MDA Report 1/5/2009 3:"1:51 PM Page 3 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g (uCi/g (uCi/g EU-154 '892.73 0.50 .4.8349E-006 5. 35E-008 1.8677E-006 904.05 0.85 2.8602E-006 -4.8653E-007 996.30 10 .34 2.3656E-007 2.5683E-008 1004.76 17.90 1.4756E-007 2.3828E-007 1128.40 0.29 8.5146E-006 -9.5004E-006 1140.90 0.22 1.1294E-005 -7.9772E-006 1241.60 0 .13 2.0896E-005 -1. 4188E-005 1'246.60 0.80 2.9608E-006 -1. 9684E-006 1274.51 34.40 7.,0414E-0:8 1. 3229E-007 1494.'08 0.71 1.9605E-006 -3. 3617E-007 1596.45 1.80 8.8063E-007 -4. 5685E-008

+ TL-208B 72.80 2 .02 6.8822E-007 2. 61E-008 -2 2211E-007 74..97* 3.41 5.8472E-007 1. 8190E-006 84 .90* 1.51 2.3773E-006 1. 8783E-006 277.36* 6.31 1.6686E-007 7. 3518E-008 510. 77* 22 .60 1.3009E-007 9. 1441E-008 5.83.19* 84 .50 2. 6114E-008 9. 9847E-008 763.13 1.81 1.3183E-006 -8 .4216E-007 860.56* 12.42 1.4468E-007 1 3066E-007 2614-.53 99.16 2. 8487E-008 1. 2778E-007

+ Pb-210 46.52* 4.,05 3.8975E-007 3. 90E-007 1. 4607E-006

+ PB-212B 74. 81' 10.50 1.8989E-007 7. 93E-008 5. 9073E-007

77. 11* 17.60 1.1208E-007 5. 2798E-007 87.30* 7.90 4.5511E-007 5. 9496E-007 238.63* 4.3.60 7.9280E-008 3.48i5E-007 300,. 9* 3.34 4.0858E-007 4.0355E-00,7

+ BI-214B 60.9.3,1* 44,..80 4.,6571E-008 4. 66E-008 55.4 444E-007 665.45 1.29 1. 5492E-006 8.1125E-007 768.36* 4,80 3.8640E-007 6.2775E-007 806.17 1.12 2.00246E-006 6. 5388E-007 934.06* 3,03 8.5674E-007 5.0205E-007 1120.29* 14.80 1.9604E-007 5. 6662E-007 1155.19* 1.64 I-.2889E-0,06 1. 3812E-006 1238.11* 5.86 3.8957E-007 7. 3543E-007 1.280 '96 1.44 I.,6059E- 006 1. 1556E-006 1377,.67* 3 .92 4. 0913E-O07 7. 3397E,-00:7 1401.50* 1.55 1. 0Q90E- 006 5. 2258E-"007 1407. 98* 2.80 7.1529E-007 1. 5532Eý005 1509.23* 2 .12 8.4472E-007 1. 0995E-006 1661.28* 1. 14 1.2716E-006 6.1785E-007 1729.59* 2.88 3.5610E-007 6.0672E-007 1764 .49* 15.36 9.8206E-008 5.9582E-007 1847.42* 2. 04 6.,6568E-007 5. 6918E-007 2118.155 1.2111E-006 -9.1058E-009 2204.21* 4.8,6 4.7675E-007 ,6.7652E-007 2447. 86* .1.50 5.315!E-007 5.2608E-007 PB-214B 53'. 23* 1 . 11 7. 3,322E-007 5. 09E-008 5.4642E-007

74. 81*. 5.90 3.3795E,-007 1.0513E-006 77.. 11 , 9.90 1. 9-926E-b07 9. 3863E-007

87. 30* 4 .41 8.,1527E-007 1.,0658E-006 241.98* 7.50

4. 5906E-007 7. 3976E-00.7

Nuclide-MDA Report 1/5/20o9 3:-:51 PM Page 4 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keY) (%) (uCi/g ) (uCi/g (uCi/g

+ PB-214B 295.21* 18.50 8. 8721E-008 5.09E-008 6.4590E-007 351.92* 35.80 5. 0880E-008 5. 8294E-007

+ RA-226 186. 10* 3.50 4. 6241E-007 4.62E-007 9. 7896E-007

+ AC-228B 12 .95 15 .10 1 0284E-006 9.,54E-008 -9. 3529E-009 16 .15 2:0. 00 4. 1228E-007 7. 2653E-008 19.11 4.60 1. 0510E-006 -3. 8324E-007 89 .96* 3.40 1. 0702E-006 7. 7066E-007 93.35* 5.60 6. 5366E-007 4. 2049E-007 99.55 1.30 9. 7011E-007 6..8496E-007 105.36 2.00 6. 2 999E-007 6.9668E-008 129 03* 2 .90 3. 6627E-007 2.18412E-007 209.39* 4.10 2. 8160E-007 2.0020E-007 270.26* 3.80 4.8039E-007 6. 3653E-007 328. 07* 3.50 4.6898E-007 4.9838E-007 338.42* 12.40 1.2720E-007 2.2411E-007 409.62 2.20 8.1479E-007 2.1817E-006 463. 0b 4.60 2.7360E-007 3.9123E-007 562. 65* 1.01 1.3107E-006 4. 5359Er007 755.28 1.32 1.7386E-006 9.1203E-007 772.28 1.09 2.2972E-006 -1. 9324E-007 794.79* 4.60 3.7124E-007 5. 0978E-007 835. 60* 1.71 1.2464E-006 9. 0152E-007 911 .16* 29.00 9. 5369E-008 3.36440E-007 964 .64* 5.80 7.,2023E-007 5. 0887E-006 968. 97* 17.40 2'.4479E-007 4. 0219E-007 1459 19 1.06 6.2056E-006 1.1293E-004 1496.00 1.05 1.3325E-006 6.5624E-007 15-88.23 '3.60 4.6012E-007 3.2593E-007 16.30.47 1.95 6.6862E-007 -4. 289oE-007 PA-234B 63.00 33.20 3.6937E-007 5. 48E-008 8.1753E-007 94.67 14.30 9.4719E-008 -6. 7474E-008 98.44 23.00 5.4760E-008 -1. 8959E-008 4.80 2. 6241E-007 1. 5368E-007 99.70 111.00 10.80 1.,1953E-007 3 .4364E-008

'I .00 1. 5861E-006 -i. 8845E-006 131.20 20.00 6.0649E-008 -1. 0088E-008

• 152.70 6.70 2.0276E-007 2. 6111E-007 186.00 2.00 7.8496E-007 2.8385E-006 200.90 1.00 1.4599E-006 -8.8002,E-007 202.90 1.20 1.2187E-006ý -7. 0006E-00.7 226. 40 5.90 2.5304E-007 2.9514E-008 227.20 5.50 2.'6979E-007 --1 4786E-007 248.90 2.80 5.8582E-007 -2. 4409E-006 272. 10 1.00 1,4953E-006 -8. 5579E-007 293.70 3.9.0 4..5665E-007 -2. 2556E-007 369.80 2.90 5.,5821E-007 6. 8400E-007 372.40 1.30 1.2208E-006 -5. 9671E-007 458.80 1.50 :1.1212E-006 -1. 5552E-006

-9. 2358E- 008 506.80 1.60 1.,3293E-006 513. 7:0 1.30 1.7102E-006 -1. 0790E-006

1. 3769E-006 565.90 1-.40 2.9473E,-007

Nuclide. MDA Report 1/5/2009 3:-':51 PM Page 5 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uci/g ) (uCi/g (uCi/g PA-234B 568.70 3.30 5.8083E-00,7 5.48E-008 -2.0564E-007 569.50 10.00 1.8583E-007 -5.3675E-008 574.00 2.00 9.5072E-007 -1.8218E-007 664.80 1.30 1.5363E-006 6. 3837E-007 666.70 1.60 1.2578E-006 7. 7283E-007 669.90 1.40 1.4171E-006 -6. 3550E-007 692.70 1.50 1.3933E-006 1. 2949E-007 699.0.0 4.60 4.4232E-007 -6. 6417E-008 706.10 3.10 6.5587E-007 -2. 3926E-007 73.3.00 9.00 2.5459E-007 1. 2239E-007 738.00 1.00 2.1906E-006 -6 .3777E-007 742.81 2.40 9.1527E-007 -1. 8839E-007 755_6.0 1.40 1.6382E-006 4. 1169E-007 780..70 1.10 2.9876E-006 2. 2651E-005 786.27 1.40 1.6805E-006 -5. 5459E-006 793.60 1.50 1.5487E-006 2. 6658E-006 796.30 3.80 6.0802E-007 3. 9786E-007 805.80 3.30 6.8495E-007 1.4754E-007 819.60 2.60 8.6663E7007 -3 1580E-007 826.30 4.00 5.7048E-007 2. 9071E-007 831.60 5.50 4.2067E--007 7 .3590E-008 876.40 4.00 6.1878E-007 1. 5853E-007 880.50 4.00 5.9431E-007 -1. 8105E-007 880.51 9.00 2.6414E-007 -8. 469E-008 883.24 15.00 1.5919E-007 9. 3824E-008 899.00 4.10 5.8677E-007 -*1.8587E-007 925.00 2.90 8.3614E-007 2. 6960E-007 926.00 11.00 2.1969E-007 -5.9510E-008 927.1.0 11.00 2.1890E-007 6.8320E-009 946.00 i2.00 1.9941E-007 1.3339E-007 949.0Q 8.00 2.9850E-007 -9.1904E-008 978.80 1.40 1.6283E-'006 -1.1024E-007

-2 .4057E-007 980.50 2.00 1.1374E-006 980.50 3.00 7.5825E-007 -1.6038E-007 984.0.0 1.90 1.1918E-006 -7.6146E-007 1 [353.30 1.70 9.5839E-007 -5.1743E-007

1394.10 3.00 5.1917E-007 -2.5184E-008 452.70 1.00 2.3612E-006 -1.5479E-006 1 668.50 1.20 1.0105E-006 3.'1367E-007 694.60 1.20 9.6053E-007 -2. 6350E-007

+ TH-234 63.29* 4.50 4.5348E-007 4. 53E-007 5.4959E-007 92.38 2.60 8.4581E-007 2. 8175E&-006 92.80* 2.60 2.2256E-006 1.4317E-006

+ U-235 72.70 0.11 1.2603E-005 2.81E-008 -4.0673E-006 89.95* 2.80 1.2957E-006 9.3307E-007 93.35* 4.50 8.1106E-007 5.2175E-007 94.00 0.40 3.3771E-006 -1.7096E-006 105.00 2.10 5.9784E-007 1.6501E-007 109.16 1.50 8.4920E-007 -7.0172E-007 140.76 0221 5.8894E0'06 -2.5483E4006 143.76*" 10.90 1.1233E-007 2.4408E-008

Nuclide-MDA Report 1/5/2009 3:F,:51 r PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keY) (%) (-uCi/g (uCi/g (uci/g )

+ U-235 163 .33 5.00 2. 7595E-007 2.81E-008 3.0782E-007 182.61 0.40 3. 7883E-006 -3.1668E-006 185 .71" 57.50 2. 8146E-008 5.9587E-008 194 .94 0.59 2 .4691E-006 1.3618E-006 202.11 1.00 1 .4597E-006 -6.4174E-607 205.31 5.00 2. 9598E-007 -1.5979E-007 279.50 0.27 5. 4954E-006 1.13447E-006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

• = MDA value not calculated

@ = Half-life too short to be able to perform the decay correction

APPENDIX C 4-.91 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

G A M.M A ST-ECTRUM ANA LY/2 _ S

• • • • • • • • • • • • • • • • • • • • • • • • • • Fe

.************************,*** *********e****

Filename: C:\Soil\2008-11-20-0l\2008-l1-,20-01N'l00000_2008Novemnber28.cN Report Generated On 12/17/2008 8:02:02 PM Sample Title 2008-11-20-01-Nalgene Sample Description 500 ml Nalgene Sample Identification 208"11-20-01 Sample Type 500 ml Nalgene Sample Geometry 500 ml Nalgene Peak Locate Threshold 3.00 Peak Locate Range (in channels) 1 - 8192 Peak Area Range (in channels) 14 - 8192 Identification Energy Tolerance 1.000 key Sample Size 1.000E+003 g Sample Taken On 9/19/2008 8:45:00 AM Acquisition Started 11/28/2008 9:26:59 AM Live Time 100000.0 seconds Real Time .100005.3 seconds Dead Time 0.01 %

Energy Calibration Used Done On  : 12/17/2008 Efficiency Calibration Used Done On  : 12/17/2008 Efficiency ID

.Nuclide MDA Report 12/18/2008 10:2-:22 AM Page 1 NUCLIDE MDA REPORT Detector Name: HPGE Sample Geometry; 500 ml Nalgene Sample

Title:

2008-11-20-01-Nalgene Nuclide Library Used: C:\GENIE2K\CAMFILES\LIbraries\SoilDCGL Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keY) (%) (uCi/g ) (uCi/g (uci/g

+ Pb x-ray 72.80 61.00 1. 9507E-008 1. 95E-008 -1.1788E-008 75 00* 100 00 2. 5030E-008 5.8326E-008 84 . 90* 36.00 2. 1262E-008 4.2712E-008

87. 60* 10 .00 9 6304E-008 2.8112E-007 BE-7 477.59 10.42- 2. 9187E-007 2. 92E-007 -5.3608E-008

+ K-40 1460. 75* 10 .67 2. 1724E-007 2. 17E-007 1.0665E-005 MN-54 834 .83 99 .98 1. 9611E-008 1.96E-008

+ CO-60 1173.24* 99.90 2. 7008E-008 2. 05E-008 1.9877E-008 1332.50* '99. 98 2.0547E-008 2.4214E-008 ZN-65 511.00 2 .83 8.0625E-007 6.39E-008 5.,0777E-006 1115.55 50.70 6.3872E-008 2. 4557E-001.

NB-94x 702.62 97.90 1.5116E-008 1. 51E-008 5.1081E-009 871.09 99. 90 1.6684E-008 1.3197E-008 AG-108m 79. 13 6.60 1.8470E-007 1. 39E-008 3.2637E-007 433.94 90.50 1.3925E-008 8.7007E-009 614.28 89.80 2.7449E-008 -1.5479E-008 722. '94 90.8.0 1.7939E-008 3.8441E-009

2. 9235E-007

+ CD-109 88. 03* 3.61 2.92E-007 8,5340E-007 AG-iI0m 446.81 3'.75 3.9862E-007 1. 79E-008 1. 1423E-007 620.36 2. 81 6.0346E-007 -3.2289E-008 657.76 94.60 1.787,8E-008 -2.0951E-009 677.62 10.35 1.68417E-007 -6.2273E-008 68,7.02 6.44 2..6959E-007 -3..02OIE-008 70'6.68 16 .44 1.0788E-007 5.4925E-008 744.,28 4.773 3.97619E-007 2.'0204E-007

.763.94 22.29 9.8240E-008 -8. 1510E-008 818.03 7.34 2.6493E-007 1. 0330E-007 884.68 72.70 2.6939E-008 8.0247E-009 937.49 34 .36 6.3323E-008 2'.2241E-008 1384.30 24.28 9.1513E-008 -2.1218E-008 1475.79 3.99 3.743!E-007 -2.4713E7007 1505.04 13.04 1.4862E-007 5.4234E-009 1562.30 1 .03 1.5068E-006 i.2057E-006 SB-125 176.3.3 6. 79 1.6836E-007 4 .44E-008 -3.6817E-008 380.43 1 .52 8.3286E-007 6.4043E-009 427.89 29.40 4.4422E-008 -8.8267E-009 463.38 10.45 1.3023E-007 1.3505E-007 600.56 17.78 8.2433E-008 1.4410E-008 606.64 5 .02 5.5368E-007 -l.3854E-007 635.90 11.32 1.2411E7007 -6.6792E-008 671.41 1.80 8,.3897E-007 1.'.433E-007 BA-133 -53 16 2.ý,20 4. 1784E-00 7 3. 02E-008 4. 655,1E-007

Nuclide MDA Report 12/18/2008 10:2r:22 AM Page 2

,Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (kev) (uCi/g ) (uCi/g (uCi/g BA-133 79.62 2.62 4.6780E-007 3.02E-008 1.1162E-006 81.00 34.10 3.0161E-008 -4.2266E-007 160.61 0.64 1.6256E-006 2.8150E-007 223.23 0.45 2.5148E-006 -1.9541E-006 276.40 7.16 1.6088E-007 -2. 6087E-008 302.85 18.33 6,.3475E-008 -1.3120E-008 356.02 6.2.05 3. 0221E-008 -2.1460E-008 383.85 8.94 1 .3845E-007 -3.6701E-008 CS-134 475.35, 1.46 8. 8912E-007 2. 11E-008 1.4056E-007 563.23 8.38 1. 7097E-007 -8.6160E-008 569.32 15.43 9.3636E-008 -7.371!E-009 604.70 97.60 2. 2582E-008 -7.9836E-009 85.40 2. I078E-008 1.7273E-008 795.84 801.93 8.73 1. 9847E-007 -1.1229E-007

• 1038.57 1.00 1. 9187E-006 -1.0387E-00'6 1167. 94 1.80 1.3183E-006 3.3212E-007 1365.15 3.04 5.5730E-007 5.1356E-008 CS-137 66.1.66 85.21 1. 6851E-008 1.69E-008 -8.8619E-009

+ EU-152x 121.178* 28.40 3. 7810E-008 3. 78E-008 1.1047E-007 244. 70* 7.49 1. 1806E-007 4,.9216E-008 344.28* 26.60 4.2745E-008 9.19522E-,008 411.11 2. 23 5.8722E-007 3..2492E-007 I

443.98 2.78 4.4942E-007 6;5840E-008 778. 90* 12 .96 1.0771E-007 1.0168E-007 867.39 4 .15 4. 0912E-007 -1;00,85E-007 964. 13* 14 .34 2. 0822E-007 2.5714E-007 1085.91 9 .92 2. 0233E-007 19.2358E -008 1089.70 1.71 1. 1737E-006 2..9125E-007 1112.12* 13 .55 2. 1184E-007 1..2403E-007 1212.95 1.40 1. 6550E-006 4.,2269E-0,07 1299.'12 1.63 1.,1314E-006 2.6851E-007 1,408'. 01* 20. 87 6. 5551E-008 1.9388E-007 EU -154 123. 07 40.40 2.5252E7008 2. 53E-008 -1 .4260E-009ý 188.25 0 .23 5.5681E-006 -1.5640E-:005 247.93 6 .83 1.6584E-007 5, 0769E-008 401.30 0.19 6.6345E-006 2.3022E-006 444.39 0.55 2.2664 1E-006 1.56-47E-007 478 .26 0b.21 5.'9116E-006 -5.7596E-007 557.56 0.25 5.3097E-006 -3. 0550E-006

.582%.0o 0.89 2.2019E-006

• 1.3428E-005 591.76 4.91 2.8125E-007 -i.0302E-007 625.22 *.32 4.3906E-006 -4.5490E-006 676.59 0.14 1.0620E-005 -7. 7876E-006 692.42 1.78 8.3313E-007 4.6020E-008 715.76 0 ! 17 8.7511E-006 4.0263E-006 722.30 20.00 7.8827E-008 2. 5177E-008 756.86 4.50 3.5812E-007 2.9098E-009 815. 55 0.50 3.1869E-006 -3.3612E-007 845.39 0.58 2.8545E-006 -3.793OE-007 850.64 0.23 6. 9718E-006 -9. 2890E-006 8 73.20 12.,09 -1.3957E"007 1. 6585E-008

NUclide MDAReport 12/18/2008 10:2-:22 AM 'Page 3 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g (uCi/g (uCi/g EU-154 892.73 0.50 3.2917E-006 2. 53E-008 -9.0941E-007 904.05 0-.85 2. 0472E-006 5.2964E-007 9-96.30 10.34 1.7569E-007- -3.8026E-008 1004.76 17.90 1. 0729E-007 -1. 3880E-008 1128.40 0.29 6. 9146E-006 -1.8266E-006 1140.90 0.22 9.2528E-006 -1.7067E-006 1241.60 0.13 2 .0273E-005 4.,0159E-005 1246.60 0.80 2 .7411E-006 -2.2812E-006 1274.51 34.40 5. 8399E-008 1.0686E-008 1494.08 0.71 1. 9753E-006 -6.5782E-007 1596.45 1.80 8.4962E-007 -2.8908E-007

+ TL-208B 72.80 21,02 5. 8907E-007 1. 99E-008 -3.5598E-007 74.97* 3.41 7. 3401E-007 1. 7104E-00'6

84. 90* S1.51 5.0692E-007 1.0183E-006 277.36* 6.31 1.6163E-007 2.0963E-007 510.77* 22.60 1. 2084E-0.07 1.4063E-007 583.19* 84.50 2. 0727E-008 1.2109E-007 763.13 1.81 9. 7589E-007 -8.3550E-007 860.56* 12.42 1. 3708E-007 1. 5753E-007 2614.53* 99.16 1. 9892E-008 1.0345E-007

+ Pb-210 46.52* 4 .05 3. 0358E-007 3.04E-007 6.3411E-007

+ PB-212B 74.81* 10.50 2.3838E-007 4.62E-008 5.5548E-007 77.11* 17.60 1. 4218E"007 5-.-3836E-007 87.30* 7.90 1.2190E-007 3.5585E-007 238.63* 43 .60 4. 6:238E-008 3.3362E-007 3.00.09* 3 .34 2. 8958E-007 ,3.8694E-007

+ BI-214B 609.31* 44. 80 4. 2857E-008 4 .29E-008 5..9788E-007 665.45* 1.29 9.8018E-007 6.9112E-007 768.36* 4.80 3.1441E-007 5 .8983E-007 1.12 -1. 7565E-007 806.17 1.4330E-006 934.06* 3.03 5.8323E-007 7.,9035E-007 14 .80 1.5241E-007 6.6197E-007 1120 !29*

1155.19* 1 . 64 1. 1806ER-006 8. 1112E-007 1238.11* 5.86 3.'6751E-007 7.0365E-007 1280. 96* 1.44 1.6815E-006 8 0497E-007 1377. 67* 3.92 7.8218E-007 1. 0423E-006 1401.50 1.55 1.1505E-006 -7. 3310E-007 1407.98* 2'.80 4.9029E-0007 1 ,4501E-006 1509. 23* 2.12 1.0308E-006 1. 6538E-007 1661.28* 1.14 1. 2923E-'006 1-.133iE-006 1729.59.* 2.88 3.7642E-007 7. 2990E-007 1764.49* 15.36, 1.2965E-007 6. 8308E-007 1847. 42* 2 .04 4.8305E-007 1. 3387E-006 2118. 55* 1. 14 1..3079E-006 4. 8343E-007 2204 .21* 4. 86 3,.2401E-007 9. 9062E-007 2447. 86* 1.50 7.2595E-007 1. 4171E-006

+ PB-214B 53 .23* 1 11 6.9333E-007 4. 47E-008 6. 0276E-007 74.81* 5.90 4.2423E-007 9. 8857E-007 77.11* 9 .90 2.5276E-007 9. 6708E-007 87 .30 2. 1838E-007 6.3746E-007 241.98* 7.5,0 '2.6946E-007 7.3934 E -007

Nuclide MDA Report 12/18/2008 10:2r:22 AM Page 4 I

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uCi/g

+ PB-214B 295.21* 1.8.50 7.7561E-008 4. 47E-008 6.1113E-007 351.92* 35.80 4.4676E-008 6.0289E-007

+ RA-226 186.10* 3.50 3.6694E-007 3. 67E-007 1.2533E-006

+ AC-228B 12.95* 15.10 8.*0507E-007 7.67E-008 4.3442E-007 16.15 20.00 3.4020E-007 -6.2293E-008 4.60 1. 3943E-007 19.11 8. 6488E-'00G7 89.96* 3.40 1.9819E-007 5.1562E-007 93.35* 5.60 2.1872E-007 4.6177E-007 99.55* 1. 30 6.,5781E-007 3.9880E-007 105.36* 2.00 3.1788E-007 2.0236E-007 129.03* 22. 90 3.2153E-007 2. 9308E-007 209.39* 4.10 2.37310E-007 4.2225E-007 270.26* 3,.80 3.2268E-007 5. 7734E-007 328.07* 3.50 3.0666E-007 2. 7969E-007 338.42* 12.40 1.0797E-007 2. 8263E-007 409.62* 2.20 5.1529E-007 2. 6377E-007 463.10* 4.60 2.6449E-007 4.1318E-007 562.65 1.01 1.3577E-006 1..3747E-007 755.28* 1. 32 1.*3977E-006 7.0994E-007 772.28 1.09 1.6902E-006 -1.5779E-007 794.79* 4 .60 3.1624E-007 3.4805E-007 835.60 1.71 9.9980E-007 1.0275E-006 911.16* 29.00 7. 6685E-008 3,.2727E-007 964.64* 5.8.0 5. 1660E-007 6.37,96E-007 968.97* 17.40 1. 8138E-007 3.4843ýE-007 1459.19 1.06 6. 1602E-006 1I0870E-004 1496.00 1.05 1. 3443E-006 -5.2200E-007 1588.23* 3.60 3.01418E-007 4.0019E-007 1630.47* 1.95 6.5202E-007 1.3895E-007 PA-234B 63.00 3.20 3ý.1476E-007 3. 99E-008 -1.3943E-007 94.67 14.30 7.2975E-008 -9w.3142E-009 98.44 -23.00 3.9881E-008 2.1110E-008 99q.70 4.80 1. 9088E-007 1.9327E-007 111.00 10.80 8.5952E-008 2.9189E-008 125.40 1.00 9.6376E-007 $.57600E-007 131. 2 20.00 4.8884E-008 -1.8954E-008 152.70 6.70 1.58.19E-007 2.8734E-008 186.00 2.00 6.4333E-007' 2..8236E-006 200.90 1.010 i. 1440E-006 -5. 0799E-007 202. 90 1.20 9.54,28E-007 5.8837E-008 226.40 5.90 1.19453E-007 -2.2644E-O08 227 .20 5.50 2.0971E-007 6 4071E-008 248.90 2.80 4.0017E-007 1.6924E-007 272 10 1.00 1. 2014E-006 -1.8479E-007 293.70 3.90 3.9988E-007 4.7164E-008.

369. 80 2.90 4. 0940E-0Q7 -6.1541E-008 372.40 1.30 9.2200E-007 2.4178E-007 458.80 1.50 8.4807E-007 -1.8687E-007 506 .80 1.60 1.0870E-006 6.4392E-008 513..70 1.4540E-006 -1.2781E-007 565. 90 1.40 9.-8645E-007 2.1464E-007

Nuclide MDA Report 12/18/2008 10:21*22 AM Page 5 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (uCi/g ) (uCi/.g (uCi/g PA-234B 568.70 3.30 4.1447E-007 3. 99E-008 -3.0886E-007 569.50 j0.00 1.3731E-007 -1."0809E-008 574.00 2.00 6.8905E-007 -41.1730E-007 664.80 1.30 1.1409E-006 6.2704E-007 666.70 1.60 9 .2665E-007 1. 2331E-007 669.90 1.40 1.0651E-006 1. 3819E-007 692.70 1..50 9.8682E-007 1. 0637E-007 699.00 4.60 3.2873E-007 1. 7670E-007 706.10 4.7590E-007 2. 0801E-007 733..00 9.00 1.8609E-007 -1. 7127E-007 7'38.00 1.00 1,.5698E-006 4. 5560E-007 742.81 2.40 6.5164E-007 -1. 2292E-007 755.60 1.40 1.1407E-006 -8. 5827E-008 780.70 1 .10 1.5705E-006 1. 1282E-006 786.27 1.40 1.2091E-006 9. 3691E-007 7,93.60 1.50 1.1518E-006 8.5026E-007 796.3.0 3 .80 4 .4993E-007 2.6752E-007 805.80 3. 30 4.8573E-007 -1..3166E-007 819.60 12. 60 6.2647E-007 1.4057E-0,08 826.30 4.00 4.0474E-007 2. 1854E-008 831.60 5.50 3.0061E-007 3. 2026E-009 876.40 4.00o 4.1302E-007 2. 6478E-009

-4.00 880.50 4.0555E-007 -9. 4975E-008 9,.00 880 .51 1.8025E-007 -4. 2211E-008 15.00 883.24 1. 0787E-0O7 5. 2396E-008 41.10 899.00 2.90 4.2108E-007 2. 6449E-007 925..00 5. 8504E-007 -2. 4454E-008

11. 00 926.00 11.00 1.5346E-007 -4. 0452E-008 927.10 1.5337E-007 -4. 0489E-008 112. 00 946.00 1.4576E-007 -1. 9021E-008 82.00 949i00 2.2334E-007 5. 1564E-008 1.40 978.80 1.2359E-006: 2. 5749E-007 980.50 2.'00 8.6001E-007 -1. 0936E-007 980.50 3. 00 5 .7334E-007 -7.2908E-008 984.00 1.90 9. 0444E-007 -1. 8261E-007 1353.30 -1.70 9.4914E-007 3. 5773E7007 1394,10 3.00 5.0216E-007 -6.7873E-007 1452.70 1. 00 1. 8495E-006 -1.8362E-007 1668 .50 1.20 1. 0676E-006 2.1472E-007 1694.60 1. 20 1.0206E-006 -2.4406E-007

+ TH-234 63. 29* 4 .1_50 1.8596E-006 1. 86E-006 1.9361E-006 92.38 2..60 3,.,1727E-006 1.5315E-005 92 80* 2. 60 3 .5422E-006 7.4782E-006

+ U-.235 72 .70 0 .11 1.0676E-005 2. 23E-008 -6.4515E-006

89. 95* 2.80 2. 3748E-007 6..1785E-007 93 35* 4..5.0 2.6860E-007 5.6706E-007 94 .00* 2.7204E-006 9.7656E-007 105.00 2..10 4..2494E-007 -.1.7311E-007 109.16 1..-50 6.0659E-007 -1.1882,E-008 140.76 0.2:2 4. 6037E-006 -10. 799E-006 143. 76* 10'. 90 8. 8770E-008 2.5756E-008

Nuclide MDA Report 12/18/2008 10:29:22 AM Page 6 i

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keY) (%) (uCi/g ) (uCi/g (uCi/g

+ U-235 163 .33 5.00 2.0827E-007 2.23E-008 1.1497E-007 182 .61 0.40 2.9829E-006 -1.8655E-006 185 .71* 57.50 2.2334E-008 7.6280E-008 194 .94 0.59 1.9023E-006 4.9723E-007 202 .11 1100 1. 1279E-006 -6.2595E-007 205.31 5.00 2.2681E-007 -1.4373E-007 279.50 0,.27 4.1731E-006 5.8468E-007

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

• = MDA value not calculated

@ = Half-life too short to be able to perform the decay correction

APPENDIX C-3 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

G A MMA S C T R U M A N A L Y IS Filename: HPGE Report Generated On  :.12/18/2008 9:37:24 AM Sample Title :2008-li-20-02N_2008Dec16 Sample Description 500 ml Nalgene Sample Identification. 2008-iI-20-02 Sample Type 500 ml Nalgene Sample Geometry 500 ml Nalgene Peak Locate Threshold 3.00 Peak Locate Range (in channels) S 8- 8192 Peak Area Range (in channels) 8.- 8192 Identification Energy Tolerance 1.009 keV Sample Size  : lOOOE+003 g Sample Taken On 9/19/2008 9:45:00 AM Acquisition Started 12/16/2008 7:47:05 PM Live Time 100000.0.seconds Real Time 100005.5 seconds Dead Time 0.Z01 %

Nuclide MDA Report 12/18/2008 9:4.0:37 AM Page 1 NUCL IDE M DA REPORT Detector Name: HPGE Sample Geometry: 500 ml Nalgene Sample

Title:

2008-11-20-02N 2008Dec16 Nuclide Library Used; C:\GENIE2K\CAMFILES\LIbraries\Soil_DCGL_

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uci/g )

+ Pb x-ray 72.80 61.00 1.9771E-008 1.70E-008 -8.6747E-009

75. 0o* 100.00 1.7035E-008 5.9513E-008

84. 90* *36. 00 7. 6710E-008 3.7817E-008

87. 60* 10.00 2.7870E-007 3. 08.98E-007 477.59 10.42 3.8459E-007 3. 85E"007 6.1627E-008 BE-7 1. 0819E-005

+ K-40 1460.75* 10.67 2.0511E-007 2.05E-007

+ MN-54 834..83* 99.98 i. 3015E-008 1.30E-008 1,.3105E-008

+ cO-6o 1173.24* 99. 90 2. 5642E-008 2.34E-008 -2.5243E-008 1332.50* 99.98 2. 3358E-008 3.8339E-008 ZN1-65 511.00 2.83 8. 5220E-007 6.76E-008 5.'2298E-006 1115..55 50.70 6. 7579E-008 4.7919E-008 NB-94x 702.62 97.90 1. 5128E-008 1. 51E-008 -5.2-693E-009 871.09 99. 90 1. 7004E-008 2.0479E-008 AG-108m 79.13 6.60 1. 8821E"007 1.41E-008 -2.1692E-007 433.94 90.50 1.4120E-008 -3.2291E-009 614.28 89.80 2.7175E-008 -31.4055E-009 722.94 90.80 1.8051E-008 5. 5084E-011

+ CD-109 ý88.03* 3 .61 8.6664E-007 8.67E-007 9. 6082E-007 AG-i-Om 446.81 3.75 4.2884E-007 1.94E-008 2. 4598E-007 620.36 :2. 81 6.1394E-007 -3 2693E-007 657.76 94.60 1.'9351E-008 -6. 3456E-009 677.62 10.35 1.7154E-007 1. 5469E-008 687.02 6 .44 2. 8142E-007 -2. 5619E-008 706.68 16.44 1. 1544E-007 5.1336E-008 744.28 4 . 73 4.3196E-007 3.2756E-007 763.94 22.29. 1.,0525E-007 -6. 7215E-008 8,18.03 7,.34 2-.8249E-007 -7.4947E-008 884.68 72.70 2.9505E-008 3.4660E-008 937.49 6.8598E-008 6.5659E-008 1384.30 24. 28 9.5936E-008 -1.3727E-008 1475.79 3 .99 4. 1688E-007 -1.. 1341E-007 1505. 04 13 Q40 1.5747E-007 -3.8006E-009 1.03 1.5491E-006 -4. 7912E-008 1562.30 SB-125 176.33 6.79 1.7348E-007 4.47E-008 -4.1221E-008 380.43 1 .52 8.6771E-007 4.5805E-007 427.89 *29. 40 4.4716E-008 -1.3415E-008 463.38 10.45 1.3349E-007 7.2608E-008 600.56 17.78 8.2960E-008 1.,8588E-008 606.64 5.02 5.6297E-Q07 -,3.1577E-008 635. 90 11.32 1.2756E-007 -6..6065E-008

ý671.41 80 4704E-007 --8:,.4606E-007 BA-133 53,16 2.20 4. 18521E-007 3.06E-008 7. 5555E-009:

Nuclide 'MDA Report 12/18/2008 9-41:37 AM Page 2 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (uCi/g (uCi/g (uCi/g )

BA-133 79.62 2.62 4. 7747E-007 3.06E-008 -8.0979E-007 81.00 34.10 3. 1095E-008 -6.2254E-008 1601.61 0.164 1. 6661E-006 4.0547E-007 223.23 0.45 2. 6022E-006 -5 .3629E-008 276.40 7.16 1. 6340E-007 6. 7523E-008 302.85 18.33 6.4449E-008 -2. 65ilE-008 356.02 62.05 3. 0553E-008 -3. 2892E-009 383 85 8.94 1 .4087E-007 -7. 9324E-008 CS-134 475.3.5 1.46 9. 3177E-007 2.14E-008 -5..0733E-007 563 .23 8.38 1. 7768E-007 1.0518E-007 569 .32 15.43 9. 7569E-008 5.3462E-008 604.70 97.60 2. 3175E-008 -1.6525E-009 795.84 85.40 2. 1356E-008 2.0855E-008 801.93 8.73 2. 0733E-007 -2. 6268E-008 1038.57 1.00 2. 0034E-006 1.4765E-007 1167 .94 1.80 1. 3827E-006 4.2514E-007 1365.15 3.04 51 3616E-007 7.3781E-008 CS-137 661 .66 85.21 1.7767E-008 1.78E-008 1.4619E-008 EU-152X 121 .78* 28.40 4. 6101E-008 4.08E-008 1.4464E-007 244.70* 7.49 1.0767E-007 8.,3944E-008 344.28* 26. 60 4.0780E-008 1.2562E-007 4-11.11* 2.23 5.2569E7007 2.5166E-007 443 .98 2.78 4.5722E-007 -2.5908E-007 778.90* 12 .96 9.8501E-008. 1.3014E-007 867.39 4 .15 4.0891E-007 8.19574E-008 964. 13,* 14 .34 2. 3266E-007 2. 9.035E-007 1085.91* 9.92 1. 4649E-007 1.8209E-007 1089.70 1 .71 1. 1904E-006 8.3829E-007 1112.12* 13 .55 1. 2694E-007 1.3322E-007 1212. 95 1.40 1. 79SE-006 -4. 2966E-007 1299.12 1. 63 1. 1335E-Q06 '3%.2769E-007 1408.01* 20. 87 7. 7087E- 008 2. 5664E-007 EU-154 123.07 40.40 2. 6289E-008 2.63E-008 -8. 4530E-009 188.25 0 .23 5. 6072E-006 -2. 2803E-006 247.93 6,83 1. 678!E-007 -3. 5039E-0'08 401.30 0. 19 6. 7091E-006 9. 8740E-007 444.39 0o 55 2. 3206E7b006 1.6490E-006 478.26 0.21 6. 1364E-006 2. 3715E-006 557.56 0.25 5 3843E-006 -5. 9162E-006 582.00 0.89 2. 2155E-006 1.2670E-005 591.76 4 .91 2.8105E-007 -1.7564E-007 625.22 0.32 4.3548'E-006 8,2460E-00-1 676.59 0 .14 1.0440E-005 -9.4933E-008 692.42 1.78 8. 4264E-007 5.2719E-007 715.76 0.17 8.7491E-006 -3.9570E-006 722.30 20.00 7.9877E-008 -1.5282E-009 756.86 4.50 3..5858E-007 -2.1530E-007 815. 55 0.50 3. 3010E-006 -7.1129E-0;07 845.3-9 0. 58 2. 8982E-006 -26 2735E-006 850.64 0.23 7..2629E-006 -1. 9087E-006 873. 20 12.09 1. 40 97E-007 -9.2267E-0O10

NuclideMDA Report 12/18/2008 9:4-:37

( AM Page 3 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (key) (%I (uCi/g ) (uCi/g (uCi/g EU-154 892.73 0.50 3.4459E-006 2.63E-008 -9.0880E-007 904. 05 0.85 2. 1205E-006 -5 .4565E-007 996.30 10.34 1.7581E-007 9.2446E-008 1004.76 17.90 1.0626E-007 9 .7160E-00'9 1128.40 0.29 6.9690E-006 2 .4773E-006 11.40.90 0.122 9. 3566E-006 -5. 50'2E- 006 1241.60 0..13 2. 0231E-005 -7 44913E-006 1246.60 0.80 2. 7278E-006 -1. 0292E-006 1274.51 34.40 5. 6790E-008 -4. 8507E-008 14.94.08 0.71 1.9773E-006 -4. 5929E-007 159,6.45 1.80 8. 3011E-007 -7,.'6348E-007

+ TL-208B 72.80 2 . 02 5. 9703E-007 1. 94E-008 -2.6196E-007 74.97* 3.41 4. 9956E-007 1.,7453E-006

84. 90* 1. 51 1. 8288E-006 9.0161E-007 277.36 6.31 1. 8668E-007 8.6203E-008 510.77* 22.60 1. 2357E-007 2. 0574E-007 583.19* 84 .50 2. 2918E-008 1 .0971E-007 763.13 1.81 1. 0010E-006 -8. 0631E-007 860.56* 12. 42- 1. 4830E-007 1. 1172E-007 2614.53* 99 .16 1. 9417E-008 1. b53OE-o07

+ Pb 210 46.52* 4 .05 3. 1938E-O07 3.19E-007 5 .6445E-007

+ PB-212B 74.81* 10 .50 1. 6224E-007 4. 68E-008 5. 6679E-007

77. 11* 17 .60 9. 6064E-008 5 .4901E-007 87.30* 7.90 3. 5278E-007 3.9112E-007 238.63* 43.60 4. 6835E-008 3.5217E-007 300. 09* 3 .34 2. 5827E-007 4.3141E-007

+ BI-214B 60,9.31* 44 .80 4. 8205E-008 4. 82E-008 6.0001E-007 665.45 1.29 1. 1884E'006 9.1470E-007 768.36* 4 .80 4.4949E-007 4.8782E-007 806.17* 1. 1:2 1.2558E-006 7.6897E-007 934.06* 3.03 5.4109E-007 6.6708E-007 1120.29* 14.80 2.3865E-'007 6.9791E-007 1155.19 1. 64 1.3133E-006 -6.4333E-007 1238,.11* 5.86 4.4230E-007 5.7377E-007 1280.96 1.44' 1.4246E-006 7.5732E-007 1377. 67* 3.992 4. 5776E-007 7.7039E-007 1401.50* 1.55 8. 3668E-007 8.7994E-007 1407. 98* 2.80 5. 7710E-007 1.9213E-006 1509 23* 2.12 1. 0154E-006 1.2189E-006 1661.28 1.14 1. 1431E-006 2. 9841E-008 1729. 59* 2.88' -6.1631E-007 9.5715E-007 1764 49* 15.36 1. 7542E-007 6.8580E"007 1847.42* 2.04 5. 7644E-00.7 9.2342E-007 2118. 55 1,. 14 1. 1962E-006 7.0.094E-007 2204. 21* 4.86 2. 7413E-007 6. 8161E-007 2447.86 1.50 9.2179E-007 2.9824E-007

+ PB-214B 53.23*' 1 . 11 7. 8030E-007 5. OOE-008 5. 1161E-007 74 81* 5.90 2. 8873E-007 1.0087E-006 77...11* 9.190 1. 7078E-007 9.7603E-007 4.41 6.3,197E-007 7.,0065E-007 241 98* 7.5Q 2.7650E:-007 7. 5057E-0'01

Nuclide MDA Report 12/18/2008 9:4.::37 AM Page 4 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV)

(I) (uCi/g ) (uCi/g (uCi/g

+ PB-214B 295.21* 18.50 8.2709E-008 5. OE-008 6.2956E-007 351. 92* 35.80 5.0034E-008 6.4621E-007

+ RA- 226 186. 10* 3.50 4.2818E-007 4.28E-007 8.3083E-007

+ AC-228B 12 .95 15.10 1.0109E-006 6. 09E-008 -2.10875E-006 16 .15 20.00 3.7554E-007 3.9494E-008 19 .11 4.60 9.0977E-007 -2.0883E-007

89. 96* 3.40 8.0925E-007 5.2632E-007 93.35* 5.60 5.0886E-007 3.'8076E-007 99.55 1.30 7.1038E-007 -1.6147E-007 105.36* 2. 00' 4.4940E-007 2.6570E-007 129. 03* 2.90 2.9300E-007 3.30412E-007 209.39* 4.10 2.4257E-007 4.2862E-007 270.'26* 3.80 3.4880E-007 6.3227E-007 328..07* 3.50 3.7750E-007 5.3944E-007 338.42* 12.40 1,2303E-007 3.6875E-007 409.62* 2.20 5.4166E-007 4.,9087E-007 463. 10* 4.60 3.3399E-007 5.3332E-007 562. 65* 1.01 1.0648E-006 2.8323E-007 755.28 1.32 1.2170E-006 5..2264E-007 772.28 1. 09 1.7317E-006 -8.5947E-007 794.79* 4.60 4.8564E-007 4.1544E-007 835.60* 1.71 6.3503E-007 6.3941E-007 911.16* 29.00 6.0947E-008 3-.2663E-007 964 . 64* 5.80 5..7777E-007 7.2103E-007 9688.9.7* 17.40 1. 9729E-007 3.6263E-007 1459.19 1.06 6. 2360E-006 1. 1114E- 004 1496.00 1.05 1. 3450E-006 3.8894E-009 1588 .23* 3.60 3 .1427E-007 3.-1969E-007 1630.47 1.95 6. 6328E-007 -6..5222E-007

3. 1930E-007 4.03E-008 8 .2375E-007 PA -234 B 63o00 3.20 94.67 14.30 7 .4421E-008 -5;9071E-008 98.44 23 . 00 4 .0335E-008 -3.3875E-008 99.70 4.80 1 9264E--007 -2. 0025E-008 111.010 10.80 8.7144E-008 1. 3006E-008 125,.,40 i.oo 9i 9209E-007 - 1 .'1251E-006 131.20 20.00 4.9283E-008 3. 1355E-009 6.70 1.6122E-007 9. 9171E-008 152.7T 186.00 2.00 6.5039E-007 3. 0795E-006 200.90 1.0O 1.1711E-006 -5. 7985E-007 202,90 1.20 9.7608E-007 4:.. 31E-007 226-. 40 5.90 1.9900E-007 -3. 8803E-008 227..20 5.50 2.1435E-007 -2. 0708E-008 248.90 2.80 4.0345E-007 - 1.9161E-007 272.10 1i00 1.2216E-006 -2. 4644E-007 293.70 3.90 4.1064E-007 -3. 6712E-008 369.80 2. 90 4 .24i8E-007 6. 6356E-008

-2. 2619E-007 3ý72.40 1.30 9.4794E-007 458.80 1.50 8.,9522E-007 1. 1678E-007 506.80 1.60 1.0811E-006 -2.5258E-008 513.70 1.30 1.4649E-'006 -9.4003E-008 565.90 1.40 1.0159E-006 2.9432E-007

Nuclide&MDA Report 12/18/2008 9:dQ:37 AM Page 5 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uCi/g )

PA-234B 568 .70 3 30 4.2519E-007 4. 03E-008 2.0013E-007 569.50 10 .00 1.4117E-007 7. 7352E-008 574.00 2. 00 7.0874E=007 -7.7288E-009 664 .80 1.30 1 1788E-006 9.3773E-007 666.70 1.60 9. 6063E-007 1.O111E-006 669. 90, 1.40 1. 0680E-006 2.,0256E-007 692.70 1.50 1. 0047E-006 8.5147E-007 699.00 4 .60 3 .3092E-007 2.0942E-008 706.10 3 .10 4. 8836E-007 2.0943E-007 733. 00 9.00 1. 9137E-007 -1.0508E-007 738.00 1. 00 1.6096E-006 -6.(8019E-007 742.81 2.40 6.7675E-007 1.0238E-007 755.60 1.40 1.1497E-006 5.0565E-007 780.70 1 .10 1.6728E-006 1.5689E-006 786.27 1.40 1. 2676E-006 9. 1301E-007 793.60 1.50 1.1498E-006 -3. 5347E-007 796.30 3.80 4 .4995E-007 3. 1342E-007 805.80 3.30 5. 1877E-007 3. 5842E-007 819.60 2.60 6. 3198E-007 -1. 9968E-007 826.30 4 .00 4. 0872E-007 -1 5979E-007 831.60 5 .50 3. 0206E-007 -5. 2989E-00:8 876.40 4.00 4. 2382E-007 -1. 3958E-007 880.50 4 .00 4 .2285E-007 6.0178E-008 880.51 9.00 1 8793E-007 2.6746E-008 883 .24 15.00 1. 1120E-007 -8.6320E-008 899.00 4.10 4. 3127E-007 8.,'7464E-008

2. 90 5. 9652E-007 -3.8424E-008 925.00 926.00 11. 00 1.5680E-007 -4 .1726E-008 927.10 11.00 1.5482E-007 -1.1219E-007 946.00 12.00 1 4904E-007 -2.9778E-008 94-9.00 8.00 2.2381E-007 -7.4685E-008 978.80 1.40 1.. 2364E- 006 6.9376E-007 98O.50 2.00 8.7779E;-007 7.7073E-007 980.50 3.00 5.8519E-007 5.1382E-007 984 .00 1.90 9.1474E-007 -7..1859E-007 1353.30 1.70 9.3560E-007 -1.6114E-007 1394 .10 3.00 4.:9737E-007 -4.4321E-007 1452.70 1. 00 2.0321E-006 -4.9964E-007 1668 .50 .1.20 1. 0436E-006 -1.7203E-009 1694 .60 1.20 1.0459E-006 1.0262E-007

+ TH-234 63.29* 4.50 3.0689E-006 3. 07E-006 3.0594E-006

92. 38 2.60 5.4557E-006 2.7366E-005 92.80* 2.60 i. 3936E-b005 1.0428E-005

+ U-235 72.70 0.11 1. 0782E-005 2.61E-008 -4.7310E-006

89. 95* 2.80 9. 6631E-007 6.2847E-007 93 35* 4.50 6.2271E-007 4.6594E-007 94.00 0.40 2. 6213E-006 -1.3384E-006 105.00* 2.10 4 .2087E-007 2.4884E-007 109.16 1.50 6.1658E-007 I. 8173E-008 140. 76 ,22 4.. 6861,E-006 -4. 9986E-007Q 143.76 10.90 9. 5719E-008 2.1991E-008

Nuclide'MDA Report 12/18/2008 9:"s:37 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g (uCi/g (uCi/g

+ U-235 163.33 5.00 2. 1145E-007 2.61E-008 1.7451E-007 182.61 0.40 3 .0207E-006 -1.4635E-006 185-.71* 57.50 2 .6060E-008 5.0567E-008 194.94 0.59 1. 9468E-006 2.0713E-006 202.11 1.00 1. 1528E-006 -6.5152E-008 205.31 5.00 2 .3340E-007 -6.6598E-008 279.50 0.27 4.2900E-006 6.4679E-007

+ = Nuclide identified during the nuclide identification

• - Energy line found in the spectrum I

= MDA value not calculated

@= Half-life too short to be able to perform the decay correction

APPENDIX D -dI UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

UNIVERSITY OF MICHIGAN Concrete Material STANDARD LEVEL IV.

REPORT OF ANALYSIS WORK ORDER #10-02134-OR April-19,2010 EBERLINE ANALYTICAL/OAK RIDGE LABORATORY OAK RIDGE, TN

PrIntw- .412010 3:54 PM .4of 5 Report to., OUR Order Dulak Eberline Ebelin A nalytical Anlytcal MarkL. Driscoll HaSOG:,

s+: l10402134 1 Un kiv of M I , *,Occu a -to0nalS-afet & -E~nvHe a-ll Pui-dow r.ir ...... 50O 0-266 ...... .. .. . . --

Final Report of Analysis 1239 "KepAkeDr"ve_ A scw..... ENVIRONMENTAL . - -

Ann Arbor, MI 48109 Samp/e Maff:t SO Lab sample client S-O Reempt Analyasi Batch R I Repout 10 Type ID DatDte 1 Deft IID Analyk me"_ R _ _ _ _ _ _ Units

__~uMD 10-02134-01 LCS KNOWN 0224/1000.00 2 32482010 =1101 10-02134 Cabon-14 EPA 520.0 Modred 1.45E+03 4.05*601 -

• pCt/g 10-02134-01 LCS SPIKE 0=..4A.0 W.00 224010 ..... 3/182010. 10-02134 Cardor14 EPA 520.0 Moiled, 1.44E+03 1.42E+01 1"44E41 5.66w+00 pC0g 10.02134-02 MPL I BLANK 02W24/1000:00 2424W2010 3/1812010 10-02134 Cub W-14 EPA 520.0Moaid I 4.03E+00 3.30E+00 3 3.0E+00 &51E+00 pC0g i0-02i34-03]UP+ UM-200 01 02/25109 00:00i 2r241010 J3/1010 10.02134 Carbon-14 EPA 520.OModled I 4.10E-01 6.04E-01 6.64E-01 1.12E400 p0Mg 10-02134-04 D0 tUM-2006-02-26.01 02126/00 00:00 212412010 3M61820 10.02134 IZCmo-14EPA 520.0Maied M 0.00E+00 5.93E-01 5.9SE-01 1.02.+.0 pCvg.

10-02134-051 TRG UM-20..03-04-01 030068(000:00 212412010 3/1010 10.02134 Carrbn-14 EPA 5200 Mdiled I 0.006-+00W .4-01 6.40E-01 1.10+0 pCg 10-02134-06 TRG LBU-0 6 I 06/2910000:00 2124=00 ..MW1812010 10-02134 CarIbon-4 EPA 520.0 Modred I 3.97E01 6436.01 6.343E-0 1.096+00+- pCvg 10.02134-07 TRG UM-20*W9.MI0-.01 06122. 00:00 1241*10I 318101 10-02134 Carbon-14 EPA 520.0 Modrad *1.67E+0 6.9E-01 &90-01 1.14E+00 P0M 10021342242010 10023,-0U209 TR 1210*4000:0*v .... 3/12010

+ ....... 1002134

............. C on-14 1 EPA 520.0 M ~Ied 3.56E0 7.01E17.010.01

- -- *1 1.08E+00 pC0g 10-02134-0M ITRG IJM-2009-06.19-01 ,3/1 - 010000 I 0 0 10-02134 Carbon-14 EPA 520.0 MIleNd I 5.31E+00 7.52E.01 7526-01 1.12E+0 10-02134-10 TRG UM-2010.01-21/29/1000:00 I 2 Carbon-14 -EPA 5.0 Mored I 0.00E+0 6.25E-01 625E-01 I 1.07E+00 p0.g

!0.02134-01 - LOS KN N -KNON 024100:0 I V241240MO1 3*401'0 1002134 Ch+orke-M6 4500-C-BModred I 3.91E402 8,60600 :E+. pCl/

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APPENDIX D -

UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

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PrfnteL i/2010 3:54 PM 4 of 5 ftod To: Worw OrDefoa:

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10-02134-06 TRG UM-20094&612-01 06/4/90:0 2/421 M/1201010-0234 wpim 5 LAM. ER-ISO Maled i 7.692-01 4.04E-01 4.04E-01 0 142-01 Ci 10-02134-6 TRG UM-2000-12-01 061240900:00 21242010 3/4/2010 10-021341 Eumpkm-1w54 LAWl.ER-3S Miodled 2272-01 2 2.67- ..- 2. 6-01 3*5E;-M pCV9 104"214 G LW-200906-2-01 2142010 3410 10 10-02134 1_Eaupeam-55 LANLER-13O M e .052-01 1-014 - 1.59W-01 I 2.45E411 PCV9 10-02134-06 TWG UMA-200940612MO 06/2mB0000- - 224/2OI0 34210W -4 10 013 Mega-4 LM RIOMie .7-2 1020 .04E411 1 1.9"20 C/

CU-Coundng Uncert@eny7CSU-CoblIed StuWard Uncmtay (2-*4pm);MDA-.Inhne Detected AcdvWtyLCS34abrh Contol Sample; MSL,,,mnk DUP-Ouplrk~t; TRGNormW SPmle; DO.Dup.cafte O*Igin E B E R LI sEVICE-s N E EBERLINE ANALYTICAL CORPORATION 601 SCARORo ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621

PrInt6, . i 912010 3:54 PM i's of 5 Repor To. WObf 0m,VeDef{W Eberline Analytical Mark L Driscoll SDG;i 10-02134 Univ

, of MI, Occupatlonal Safey&_Env eal *Puth-s ..... 5000002634 Final Report of Analysis 1i i Kopke Drive .A..n.y.s.is Ann Arbor, M146109 c . ..... ENVIRONMENTAL SIwfe Mafx:i SO Lab Sampe COW SaMple Recep Anidyale Bath M.I C Report to Type mD Dab Daft Dub 10 0100 ringtCucu Urdua 103400 UM.04-90 IR - -- 00 1 22 32T 0 131512010

- -4

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5FERVCES 601l SCARSOROANALYTICAL EBERLINE CORPORATION ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/4.83-4621

APPENDIX E UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

Cutting of Storage Port Bleed-off Lines Survey No.: NA DATE:. 10-Dec-08 LOCATION: o/S, West of.FNR above Storage Ports TIME: 15,30 Smear Information dpm Frisking ProbeModel # 44-142 Serial,# 240718 E. 38 Es 0.25 Frisking Probe Efficiency 0.095 I Min BKG: If 3-5 2.r 55 Avg. BKG:T Lc Gross CPM: [T-7 Lc Net CPM: m LD Gross CPM: LD.Net CPM: m Note: Removed Storage Port Bleed-off Lines using abandsaw; Bleed-off lines were 1" in diameter. Pipes were Large Area Wiped internally at each end after cut. (4) Lines were cut in total, starting with the north most pipe. All Large Area Wipes were <Lc.

Pipe ends were then taped. All (4) now loose pipes were then placed in the FNR radioactive material area inside the FNR.

During cutting activities, a cardboard tray was used to collect any pipe shavings from

-utting the pipes with the bandsaw. Shavings were disposed of as radioactive materials and placed in-a radioactive materials slurry/piping drum. Frisk and wipes done.for the

.ardboard tray were all <Lc. Large Area Wipe of the bandsaw was <Lc.

instrument Serial Number Cal Due Date Efficiency Backgroind (CPM) MDA (DPM)

L-2221'144-142 2185791240714 8-Mar-09 0095 344 '773 d 3 p=0.:5 t(sec) 2 2087

[Frisker Detector`HV =. 1150 Vdc (240714) 'Thresfiold Voltage = .350, mVdc Detec6or cable-type/length = 5916ft Print/Signature of Surveyor:. i12,~,%w./L ( 2 9,L4 r~i~L2?Zx Date:

C Comments:

/7 Review By- Ef Date ý tzLe z L2 61 ý-,-

APPENDIX F UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18,2012

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port# 1 TIME: 16:25 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 E,_ 50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: If 32° Avg. BKG:*

Lc Gross CPM:- ] Lc Net CPM:r Tl ]

LD Gross CPM:- Ln Net CPM:.rM_1 Static Count CPM CPM DPM No. (Gross) (Net) _______

1 Static 1 37 7 <MOA 2 Static 2 38 8 <MOA 3 ___________ _______ ________ ________

4 __________ ______ _______ _______

5 ___________ _______ ________ ________

6 ___________ _______ _______ _______

7 ___________ _______ ________ ________

8 ___________ _______ ________ ________

9 ___________ _______ ________ ________

I0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1I____________ _______ ________ _________

ý2 __________ ______ _______ ______

[3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 ___________ ______ _______ _______

.5 ___________ _______ ________ ________

6 ___________ _______ _______ _______

'7 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

9 L I 20

• NOTE: All .counts are 1 minute static counts of the O/S portion end of each port. No Decon Necessary.

Smear taken was <MDA. Port end is freereleased up to plane of Wall.

Instrument Serial Number I Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221/44-1 218597 / 249243 9-Dec709 0.502 30 188 Id'1.38 p=0.5 t (sec) 3 377 Tenelec Series 5 2161 28-Jul 09 *=1741 a=17.25 1= .33 a=U00 IP-23.00 a=5.23 Frisker Detector, HV-= 700 Vdc (249243) Threshold Voltage = 50 mVdc [Detector cable type/length - 59/6 ft.

Print/Signature of Surveyor: _,JL)"u !l 51t I,kjl-A

,(U C/ ,,V -

Date: 4)-*Z .7 Comments:

d* m P ....

Review By:. iV

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 2 TIME: 16:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR24I 9243 Ei 50.5 0.25 Frisking Probe Efficiency 0.12625-"

I MIn BKG: I 28 Avg. BKG:;"sm Lc Gross CPMr- Lc Net CPM: "

LD Gross CPM:r L, Not CPM:W Static Count CPM 1 CPM DPM J No. (Gross) (Net) I I 1 Static 1 24 0 [ <MDA 2

.9 .9 9.

j

.1 .5 1.

4 4 4 9.

5

.9 .9 9.

7 4 4 I* 4-4 4 9. 4.-

8 9 ___________ _______ ________ ________

• 10 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

11 ____________ _______ ________ ________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14 _ _ _ _ _ _

15 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

17 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

191_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

20k i ________ _______ _______ _______

• NOTE: All counts are 1 minute static counts of the O/S portion end of each port. No Decon Necessary.

Smear taken was.<MDA. Port enid is free released up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CpM) MDA (DPM)

L-22Z1 /44-1 1218597./249243 9-Dec-09 0.502 33 1,96 d1 p=05

=38 t (sec) 3 '395 Tenelec Series 5 2161 28-Jul-09 l. 17,41 a= 17.25 P = 1.33a =b000 A= 23.00 a 5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc LDetector cable typelength = 59/6 ft.

PrntlSignatureof Surveyor: Te 4~.{ ')i~vj~~ .Date:

Comments:

A I

'fJAI::f or I Review By -. 4* .Y A/ .Date: 2/ A /, k Lv' " 7

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port #3 TIME: 15:45 Smear Information dpm Frisking Probe Model U 441 Serioal # PR24 9243 El .50.5 E, 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1I 31 3 29 Avg. BKG:*

Lc Gross CPM:* Lc Net CPM:1 " 2-LD Gross CPM:r L, Net CPM  : NIA

• NOTE: All counts are 1 minute static counts of the O/S portion end of each port. NoDecon Necessary.

Smeartaken was <MDA. Port endis free released up to plane of wall.

Instrument Serial Number Cal.'Due Date Efficiency IBackground (CPM) MDA (DPM)

L-2221 144-1. 218597 / 249243 9-Dec-09 0.502 33 196 d =138 p=0.5 t (sec) 3 TenelecSeries5 2161 28-Jul-09 17.41 a= 17.25 P= 1.33 o:=0.00 P=23.00 a5123 Frisker Detector HV= 700 Vdc (249243) [Threshold Voltage = 50 mVdc Detector cable type/length = 59/6 ft.

Print/Signature of Surveyor: Jef7 k ý,z Date:0t- 0 Comments:

A/I AA Review BV.L" ,/Lf' Daie: aA 4.

V/- -W

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port #4 TIME: 15:r15 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243

!50.

50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1. ~ ~

Avg. BKG:

Lc Gross CPM:r-M- Lc Net CPM'2 LD Gross CPM: ] Lo Net CPM:  :

Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 51 19 <MDA 2 Static 2 50 18 <MDA 3NOEAl onsre!int ttcout ft ipoto nofecpotN eo eesr 4 Smear tken was<MDA. Port nd _sfree released 5 nr SrlNb "_aLD Dckr _ CA 67221/44__2159 294 _9Dc0..523 9 9 _--o._ _,,_0, _ _ _ _ _

81n0 l _c 5 Series 2161 ... . 28,Ju1:09 _= . =7_= 3 = 0 .= 0 .5 91 ...... _ _. _ ._. . . . .

10 ris2 erDetectorHV = ___V __2_2 _ Thr_____olag = _ d D c al p e ' , 96 15______ _______

16 _ _ _ _ _ _ _ _ _ _____

20 _________ _____

• NOTE: All counts are I minuite'static counts of the 0/S portion end of each port.-No Decon Necessary.

Smear taken was <MDA. Port end is free, released upp too pplanee o~fwall.

'Instrument Serial Number- Cal. Due Dote I Efficiency Background (CPM) MDA (DPM)

L-2221/1-4;4-1 218597/1249243: 97Dec-09. 0.502 1 21111 311 93 IZI 1IIIII 4Tenelec Series 5 2161 28-Jul-09 10 17.41 a =17125.0=13 a 6.00 0 23.00 a,.= 513 Prisker Detector HI 7600Vdc. (249243) IThreshold 'Voltage = 50 mVdc jDetector cable type/length ý: 519/16, ft.

Print/Signatur.e of Survyor: ,) Date: O9-.~A -6)2 Comments:

hi,..

Review'By: .* {

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 5 TIME: 15:00 Smear Information dpm Frlsklng Probe Model # 44A-1 Serial # PR249243 50E5

%50 0.25 Frisking Probe Efficiency 012625 I Min BKG: 1.j[j Avg. BKG:r Lc Gross CPM:mr Lc Net CPM:

LD Gross CPM:* LD Net CP M:_:_'VA_

Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 41 13 <MDA 2 Static 2 42 14 <MDA 3 __OTE: AI_ countsare __minute static c tfeS rnd h r] e Nca 4-Smear tken was <MDA. PrnifeeadoaewU 5 Intumn"...SrilN __ffcecy mbrLua ]B ck rud__M28.. M A(PM__

6 L_2221 14-1 2185974 2424. _9Dc-90,0 7

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _

16______

17 19 ______ ______

15 ___-_____s___=0.5_____ _t__se___ _____3___

,NOT .E: AllIcounts are I minute sta Itic counts of the 0/S portion end of each port. No Decon Necessary!

Smear taken was <MIDA. Port-end is free released up to plane Ofwall.

Instriumenrt Serial Number ICal.Due Daite, Efficiency Blackground,(CýPMY) MDA (DPM)

I L-2221 / 44-1 1218597 /1249243. 9-Dec.09 1 0.502 I~II~ 111183 111 2811 TenelecSeries5

-0. 2161 28-Jul-09 138c Ip=:17.41 =17.25 t

01=133 30 a=O0.0 1P=23.00

'366 a=5:23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc IDetector cable type/lehgth = 59,/6 ft.

Print/Signatureof Surveyor: Date: ,0?

Comments:

/711!)  ! Date: ~/2 .2 ~

?/~

Review By: By: - LF __ r IF A Date;

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 6 TIME: 14:30 Smear Information dpm Frisking Probe Model #' 44-1 Serial # PR249243 E, 50.5 Es 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1 3. 31 Avg. BKC:-- -

Lc Gross CPM:r Le Net CPM['

Le Gross CPM:* L0 Net CPM:r)'*

Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 25 0 <MDA 2 Static 3_____

2 39 9 sMDA 4

b ___________________ _______

6 ___________ ______ _______

7 ____________ _______ ________

8 __________ _______ _______

9 __________ ______ _______ _______

10______ _______

11 ____________ _______ ________ ________

12______ _______

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i5 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

16 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _

17 _________ _____ ______

18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

As

• NOTE:, All counts are I minute static counts post-decon of the O/S portion end of each port. Up to 90 cpm gross pre-decon.

Smear taken~post-decon.was <MDA. Port end is-free released up,;to lane of wall.

Instrument I Serial Number ] Cal.Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1 218597 / 249243 9-Dec-09 0.502 30 j189 d-1 38 p-05 t (sec) 3 379 ]

'TenelecSefies5 2161 j 28-Jul-09 lp 17.41 a=17.25 P=1.33 a=0.O0 1 23.00 a=5.23 pFriker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc Detector cable type/length- 59/ 6 ft.

Pr~int/Signature of Stirveyor:_ jecif' Date: ,.-c' 1 -O

/ /*1 /

Comments:

0,_; F A Review By'L,ý fA-t/1 Date: -2/A 3 ,

'5- - r -

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 7 TIME: 14:15 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 E 550.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1. 1 291 3.I 381 Avg. BKG:r Lc Gross CPM:rn Lc Net tPM:r z7 I LD Gross CPM:* Lo Net CPM:, j Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 28 0 <MDA 2 static 2 31 0 <MDA 3 NTAcut a1i _t _utfth O o o rny 4Sma__aenws MA Poted sfe rlae uptoplanofail 10 _____

14 ____________

1- p

• NOTE, All counts are I mirn6te tatic coun~tsobf the 0/S portion end of each port No Decon Necessary.

Swear taken was <MDA. Port end is free released up to plane ofwafl

'Instrument Serial Number ICal. Duie'Date Efficiency Background (CPM) MDA (DPM)

L-22211 144-1 218597/294 9DEec09 050219 d 38 p=025 t,(aec) 3 403 Tenelec Series 5 2161 28-Jul-09 [=17.41 = 17.25 1P=1.33 a-0.00 0 23.00 a=5.23 Lrisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc Detector cable type/length = 59 /6 ft.

Print/Signature of Surveyor:ý Ck,'y'1 I

e.k f/ V 2

-V

' Date:  ?

Comments:

zQ I Ja ReieW By: /43t(q*  %=*. =- Date: A/A .711 4

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 8 TIME: 13:50 Smear Information dpm Frisking Probe Model # 44-1 SerlaI # PR24, 9243 El 50.5 0.25 Frisking Probe Efficiency 0.12625 1 Min BKG: 1. 30 3. j I Avg. BKG:r Lc Gross CPM:[-52 Le Net CPM;  :

LD Gross CPM: rV L0 Net CPM:[/*

Static Count CPM CPM DPIM No. (Gross) (Net)

I Static 1 31 0 <MDA 2 Static 2 .'5 20 <MDA 4

T5ne__c __res5 216 _ 28-_u_-09 =.a=2_13 00 =. .

106 DeeoHV 70 .244) heodV1e 5 vc eeocbetpent= 9 6f 13_________

-15______

d'=1.38 1___=_.5___t_(s__c____3-_387

• NOTE: All counts are I minute~static counts post-.decon of the 0/S portion end o ,feach port. Up to 75, cpM gross pre-decon.

Smdear tak~en post-decon was <MDA. 'Port endis free released up to p lane. of wall.

Instrument Serial Number Cal. Due Date Efficiency 'Background (CPM) MDA (DPM)

L-2221 / 44-1 21859,7/'249243 9-Dec.09 0.502 3 9 d't 36 p=. (s8) 387 Tenclec: Series 5 j 216 1 28 Jul 09 1317.41 a= 17.25 IP=.3 30 5.23 Frisker Detector H1V =700 Vdc (249243) Threshold Volag S Vdc Detiector cable type/lngth = ý59 / 6 ft.

Print/Signature of Surveyor: c~/ /l,/~,9s } l Date: -;,-

Comments:

IA .4 A Review By: Date Date: 4*6L-glI 2-t-I

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port #9 TIME: 13:30 Smear Information .dpm Frisking Probe Model # 44-1 Serial # PR249243 El5- 50.5 E, 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: I.r 6 261 Avg. BKG:E Lc Gross CPM:F Lc Net CPM' LD Gross CPM:F Lo Net CPM:[ N/A I Static Count CPM CPRM DPM No. (Gross) (Not)

I static 1 43 16 <MDA 2 Static 2 -46 19 <MDA 3 ____________ _______

4 ______ _______ _______

5 ___________ _______________

6 ___________ _______ ________ ________

7 ___________ _______

8 ___________ _______ ________ ________

9 ___________ _______

10 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

11 ____________ _______ ________

12 __________ ______ ______ ______

13 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

14 ______ ______ ______

15 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

187 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _ _ ______

198 _ _ _ _ _ _ _ _ _ ______ ______ ______

2019 ________ ______

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Up'to 65 cpm gross pre-decon.

Smear taken post~decon was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1 218597/249243 9-Dec-09 0.502 27 179 d'=1.38 p=0.5 t (se), 3 357 Tehelec SeriesS, 2161 28-Jul-09 01_-_17.41 a 17725 P- 1.33 ' = 0.0O =23.00

_ a= 5.23 Frisker Detector HV= 700 Vdc (2i49243) Threshold:Voltage = 50 mVdc IDetectore-ble=..ype/ength = 59/-6:ft.

Print/Signature of Surveyor: ..f('-jeer,,Sj J.4,_i l Date: /W- _r., -Q?

Comments:

Review ByA . Date:, .2 /ý4 De,.. 3k A,

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port# 10 TIME: 13:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR241)243

£, 50.5 0.25 Frisking Probe Efficiency 0.12625 I MIn BKG: I.E 30 Avg. BKG:m Lc Gross CPM:r L Net CPMrM:f--

LD Gross CPM:r ID Net CPM::

Static Count CPM CPM DPM No. (Gross) (Net) 1 Static I 38 10 <MDA 2 Static 2 47 19 <MDA 3Static 3 40 12 <M[DA 4

.4 4 C C-5 4 9 9-6 I.

7 C-

.4 4 C 8

1111 10 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _

11 ____________ _______ ________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

13 _ _ _ _ _ _ _ _ _____ _ _ _ _ _ _ _ _ _ _ _ _

14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

15__ _ _ _ __ _ _ _ _ _

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

17 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

201 1__________ 1______ 1_______ 1_____

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Refer to initial port survey report for pre-decon contamination results. Smear taken post-decon was <MDA. Port end is free released up to plane of walL Instrument Serial Number C Due 0l Date Efficiency Background (CPM) MDA (DPM)

L-2221 / 44-1 2185971249243 9-Dec-09 0.502 1 28 [183 M d-1.38 p=0.5 t (sec) 3 366 TenelecSeries5 2161 28-Jul-09 j1= 17.41 a=17.25 [13=1,33 on0.aO 0 /=23.00 a=5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage - 50 mVdc IDetector cable type/length - 59 / 6 ft.

Print/Signature of Surveyor: e*Jf7 Vi/1  !, - /L*.. 4  :. Date: _ J_ -6)

Comments:

21/1/

Review ByDt:z(,AA,,/ 16V .

Date:

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port #11 TIME: 11:30 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 E, '50.5 0.25 Frisking Probe Efficiency 0.12625 \

I Min BKG: 1.r 331 3 Avg. BKG: l Lc Gross CPM:" Lc Net CPM:*

Le Gross CPM:r-W-1 LD Net CPM :l.r- "I Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 33 "3 <MDA 2 Static 2 46 16 <MDA 4

5NOTE:_A___counts a_1muestcnsoheO proee_ ot__enesy 11 _p=0.___sec_3___7 1228-Ju109_. ___=174___=1.25_ _1_33_-_0.00 .. _=23.0__=5.2 13'__ etorHV __00V ____2 _ T oo "5 d tr y/ h 91 14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

15 _

7 _ _ _ _ _ _ _ _

222l ./______4-1 _

218597 2492

_.3 9.D ___09

_30 0.502 -' 189

• NOTE: All counts are.1 minute static couints of the 0/S portion end of ,each port. No Decon Necessary.

Smuiar taken was <MDA. Port end is free released up to plane of wall.

Instrument ISerial Number COl. Due Date .Efficiency. Background (CPM). MDA (DPM)

L-2221 / 44-1 J21.81597/249243 1 9-D&ec09 1 0.502 318 Tenelec SeriesS5 2161 '28-Jul-09 joý 17.41 a= 17.25 1:3 a =0.00P 23.00 5.23 Frisker Detector HV =700 Wec (249243) IThresholdVoltage = 50 mVdc IDetector cable type/length = .59 / 6 ft.

Print/Signature of Surveyor: JOf(y#4A~4A ~- Date: o?-,J-, -o0

.Comments:

Review Bi 1e4L A,4k L,- Date: .? *?/,, A-

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 12 TIME: 10:45 Smear Information dpmn Frisking ProbeModel# 44-1 Serial# PR249243 E, 50.5 E, 0.25 Frisking Probe Efficiency 0.12625 I~301 1Min BKG: lr Avg. BKG:[ j Lc Gross CPM:F"J* Le Net CPM:*

Lo Gross CPM:- Lo Net CPM:I Static Counit iCPM CPM DPMV No. (Gross) (Net) _______

1 Static 1 .42 9 <MDA 2 Statiic 2 30 0 <MDA 3 Static 3 28 0 <MDA 4 _ _ _ _ _ _ _ _ _ _ _ _

7 ___________ _______ _ _ _ _ _ _ _

612 _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _______

13 ___________ _______ _______ _______

14_______ ________

10 _ _ _ _ _ _ _ _ _ _____9 _ _ _ __ _ _ _ _ _ _ _ _ _

20 ____________ ________ _________ _________

• NOTE: All counts are i minute static counts postrdecon of the O/S portion end of each port, Up to 68 cpm gross pre-decon.

Smear taken post-aecon was <MDA. -. ort ena is tree released up to ,lane of wall.

Instrument Serial Number Cil. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1 218597/249243 9-Dec-09 0.502 33 197

'=.m p=O0.5 *(s~ec) 3 399 Tenelec Series 5 -2161 ,l28-Jul09 10 1741 a =17.25 1 =1.33 ao~oo P 23.00 a.=5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage 50 mVdc Detector cable type/length = 59 /6 t.

Print/Signature of Surveyor: Tef .Date:yI" - C)

Comments:

XZ7. 1 nh /

Review By: < 4A z . -Dae 1)Ae:a

/3/&

Storage Port Exterior Survey Report Survey NO.: NA DATE:- 9-Jan-09 LOCATION: Port#n3 TIME: 10ý00 Smear Information dpm Frisking Probe Model s 44-1 Serial # PR249243 E50.5 50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1 401 3. 32 Avg. BKG: =*l Lc Gross CPM:m Lc Net CPM:*

LD Gross CPM:" L0 NOt CPM: IA j Static Count CPM CPM DIPM No. (Gross) (Net) _______

1 Static 1 54 16<MDA 2 Static 2, 45 7 i5MDA 3 ___________ _______ ________ ________

4 _______ _______

5 _ _ _ _ _ _ _ _ _ _ _ _

6 _ _ _ _ _ _ _ _ _ _ _

7 ___________ _______ ________ ________

8 ___________ _______ ________ ________

9 10 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

12 _____________ __________________

123 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _ _ ______

'134 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _ _ _____

145 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _ _ ______

15 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _ _ ______

167 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

181_ _ _ _ _ _ _ _ _ ______ ______ ______

191_ _ _ _ _ _ _ _ _ ______ _______ _______

Ii ____________________ I_____________ I ______________ 1 ______________ .1

• NOTE: All counts are I minute static counts post-decon of the.O/S portion end of each port. Refer to initial poirt survey report for pre-decon contamination results. Smear taken post-decon was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number Cal, Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 I44ýl 1 218ý597 / 249243 9-De~c-09 0.502 38 208 W d'=1.38 p=0.5 t(sec) ý3 Q42 TenelecSeries-5 2161 28-Jul-09 1*7410a 1.7.25 R- 1.33 a=0.oo 1 = 23.00 a=5.23 Frisker Detector HV = 700 Vdc.(249243) Threshold Voltage = 50 nmVdc IDetector cable type/length = 59 6 ft.

Print/Signature of Surveyor: Z__.Tr'-f b"5J-Ž/. .J Date'j-- F Comments:

At .. ~ A Review By:~j. LA

Storage Port Exterior Survey Report Survey NO.: NA DATE: ,9-Jan-09 LOCATION: Port # 14 TIME: 9:45 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 50.

50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG; 1r r 5 Avg. BKG:*

Lc Gross CPM:* Lc Net CPM  :

LD Gross CPM: ) LD Net CPM:[ N/A 1 Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 38 8 <MDA 2 Static 2 33 3 <MDA 3 ____________ _______ ________ ________

41__________ ______ _______ _______

5

4. 4. 3

4. 4. ., I-7 & & 4 .3-8

.3 4. 4. .3 .6 ~

I. * *4-10 I. 4. .3 4 -

11 I I. 4. .3 12 I~ V *I -

13

& 4. 4 4-14

4. 4. .3 .3-15 I* V - '1 16 I. 4. 4 4-17

3. 4. .3 .3-18 U ~V .3-12 I I. 4 4-20

• NOTE: All counts are I minute static counts of the O/S portion end of each port. No Decon Necessary.

Smear taken was <MDA. Port end is,freerreleased up to plane of wall.

Instrument Serial-Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221/44-.1 218597 / 249243, 9-Dec-09 0.502 30 188 d'=1.38 p=0.5 t (sec) 3 377 Teneec Series 5 2161 28-Jul-09 P = 17:41 a =17,25 = 1.33; a 0.00 =200 a 5.23 Frisker Detector HV 700 Vdc (-249243) Threshold Voltage= 50 mVdc Detectorcable iype/length = 59/6 ft.

Print/Signature of Surveyor: TP

._ ' ,.7y Date:oý - -0'49 Comments:

A7Ii~ I I i Review By: /_d* A'. &* Date J.

V

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port# 15 TIME: 9:25 Smear Information dpm, Frisking Probe.Model# 44-1 Serial# PR249243 50.

50.5 Es 0.25 Frisking.Probe Efficiency 0.12625 I Min BKG: 1.

Avg. BKG:r Lc Gross CPM: Lc Net CPM:r t I LD Gross CPM:F LD Not CPM;:

Static Count CPM CPM DPM No. (Gross) (Net) _

1 Static 1 .23 0 <MDA 2 Static 2 18 0 <MDA 3 Static 3 39 7 <MDA 5

• NOTE:6All counts are1 mnut stti counts ofhe O/ proe oea ptNDcnesy 6me7r taken was <MDA. Poted sfe rlae _p O lae owll Instr8ment__ SerialNumber _al._DeDate E_ iey agon(MA(M L-9221 -/_4-_1 218597 / _924 9-Dec:09 0.502 32 193 10_________ ______

16 _______________

1d'-___.3e__p=0.5

• NOTE: All counts are i~minute static counts of the 0/S portion end of each port. No Decon Necessary.

___t___sc____3__389 Smear taken was <MDA. Port end is free released up to plane of wall._________

Cal. Due Date j instrument, L-22211/44w)

Serial Number 21859.7/ 24,9243 9-Decpý-09 f Efficiency 0.502, B~ackground (CPM) 32 MDA '(DPM) 193 I1ii d'-1 38 p"0.5 tl(iec)y 3 389 Tenelec Series 5 2161 28-Jul-09 j13=_17.41 a 17.25 P= 1.33 , a = 0.00 P =-23.00, 0:='5.23 Frisker Detector HV = 700 Vdc(249243) Threshold Voltage = 50 mVdc [Detector cable type/length = 59/6 ft.

Print/Signature of Surveyor:. T " 1 (.. Pate 6-jq. 1' - OP Comments:

Al , 1 1 2 Review By:e Date: 06 Z-

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port # 16 TIME: 9:00 Smear Information dpm Frisking Probe Model# 44-1 Serial # PR249243 El 50:5 0.25 Frsking Probe Efficiency 0.12625 IMin BKG: 139 3 31 Avg. BKG:*

Lc Gross CPM:m Lc Net CPMUK LD Gross CPM:r Lo Net CPM:r NA I Static Count CPM CPM DPM Sttc1No. (Gross) (Net) 2 Static 2 32 0 <MDA 3 _ _ _ _ _ _ _ _ _ _ _

4 __________ ______

6 ______ _______

7 ___________ _______ ________ ________

78 ____________ _______

89_______ _________ ________

910 __________ _______ _______

101 _ _ _ _ _ _ _ _ _____

14 ______ _ _ _ _ _ _

15 _ _ _ _ _ _ _ _ _ _____ ______

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

17 _________

18 _ _ _ _ _ _ _ _ _ _____ ______

• NOTE: All counts are 1 minute static counts of the o/Sportion end of each Port. No Decon Necessary.

Smear taken was <MDA. Port end is free*released up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency [Background (CPM) MDA (DPM)

L-222 1144-1 218597 49243 9-Dec-09 0.502 37 208 iTenelecSeries5 1d138 2161 28-Jul-09 rl7 141a=1725 p-OS5 :t(se)

-1.33' o 300 422 23.00a=523 risker Detector HV = 700 Vdc,(249243) IThreshold Voltage = 50 mVdc [Detector cable type/length = 5996 ft.

Print/Signature of Surveyor: -,12c"~(*,~b ,s~ .dh Date: ý ,',fO Comments; Review By/e4VA Date:

Storage Port Exterior Survey Report Survey NO.: NA DATE: 9-Jan-09 LOCATION: Port# 17 TIME: 8:45 Smear Information dpm Frisking Pr6be Mcdel # 44-1 Serial # PR249243 50.

50.5 E, 0.25 Frisking Probe Efficiency 0,12625 1 Min BKG: 1 3. 3 Avg. BKG:*

Lc Gross CPM: m Lc Net CPM:.

L0)Gross CPM:~ L Net CPM:N Static Count CPM CPM DPM No. (Gross) (Net) _______

1 static 1 37 2 <MDA 2 ttc2 50 15 <MDA 3 Static 3 41 6 4 MDA 4 _ _ _

5 ___________ ______ _______

6 ___________ ______ _______

7 ___________ _______ _______

9 _ _ _ _ _ _ _ _ _ _

9 ______ _______

1 1

14 15 ___________ _______ ________ ________

6 ___________ ______ _______ _______

71__________________ ___________ ____________

8L S

9* 9* .9 I-

1. .9

• NOTE: All counts are 1 minute static counts of the P/S portion end of each port. No Decon Necessary.

Smear taken was <MDA. Port end is free released.up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1I 218597 1249243 9-Dec-09 0.502 35 201 138 p=0;5 t (sec) 3 407 Tenelc Series5 2161 28-Jul-09 1P=17.41 = 1-725 121.33 a=0.00 13=23.00 ao=,:523 Frisker Detector HV =. 700 Vdc (249243), Threshold Voltage.= 50 mVdc, Detector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: 2~-u ~ ~ i.A. bate:09-;Xic7ýJd~

Comments:

,,jA, /1 ReviewBy: .-. at, Date: -;ý, 2.4 a-

Storage Port Exterior Survey Report Survey NO.: NA DATE; 9-Jan-09 LOCATION: Port # 18 TIME: 8:25 Smear Information dpm Frisking Probe Model# 44w1 Berlal # PR249243 50.5 5 . 0.25 Frisking Probe Efficiency 0.12625 I Mini BKG: 1~ 514 3.r 361 Avg. BKG:rr7 Lc Gross CPM:r-"d-l, Lc Net CP M:-r--

LD Gross CPM:[-- L,, Net CPM:r-X-Staltic Count CPM CPm DPMV No. (Gross) (Net) _______

1 static 1 38 1 -MDA 2 Static 2 50 13 <MDA 4 ___________ _______ _______

412__ _ _ _ _

13 __________ _______ _______

614 _________ _______ _______ _______

15 ____________________________

10 _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

17 ___________ _______ _______

128 _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

19 _ _ _ _ _ _ _ _ _ ______ _______ _______

120 _ _ _ __ _ _ _ ______

• NOTE: All countsare 1 minute static counts of the O/S portion end of each po-t. No Decon Necessary.

Smear taken was <MDA. Port end is free released up to plane ofWa H.

Instrument Serial Number Cal. DueDate Efficiency Background (CPM) MDA (DPM)

L-2221 /441 218597 4 249243 79-Dec-09 0.502 37 208 I d'138 p-=0.5 (sec) 3 422 Tenelec Series 5 2161 28-Jul-09 1__17.41 a = 17.25 1 = 1.33 6=-0.00 lp z2300 6=,5:23 Fnsker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc Detector cable type/length = 59/ 6ft.

Print/Signature of Surveyor: 2I."-1.*3,-.I- A . A .J .2l .Date: - ol Comments:

A I,. j (/ 0 2l Review By:ai".4' A L/- Ijate:,2/

Storage Port Exterior Survey Report Survey NO.; NA DATE: 9-Jan-09 LOCATION: Port # 19 TIME: 8:10 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 50.5 5i 0.25 Frisking Probe Efficiency 0.12625 I Min BKG, 1.-1 1~ 381J 3. 25 Avg. BKG:r Lc Gross CPM:j Lc'Net CPM:

Lo Gross CPM:r LD Net CPM:r Static Count CPM CPM DPM No. (Gross) (Not) 1 Static 1 32 0 <MDA 2 Static 2 35 2 <MDA 93_ _ _ __Seres_ _ _ _ 28_u-0 7 7 ===.

105 i_____Dete __or __ ___0_d _____ Thrshld____g 50 d ete eg_9 f 16 17 _________ _____ ______ _____

18 _ _ _ _ _ _ _ _ __ _ _ _ _

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

8 ___d_=1.38____p=0__5__t__(__ee)______39__

14 ee~re526

-13 2Jl9 ~

18~-~

14 7.5P .~ o J 2 O~

15 krDtco V 70Vc(423) TrsodVlae= 5 ~c IDtetrcbetp/egh= 5/ t Print/Signature of Surveyor:, 4 . Date 02-- 1,q-g0 Comments:

.1-I I Review By: */ ff/4 - Date;t t W,

Storage Port Exterior Survey Report Survey NO,: NA DATE: 8-Jan-09 LOCATION: Port # 20 TIME: 14:15 Smear Information dpm Frisking Probe Moclel # 44-1 Serial.# PR249243 C.i. 50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1.

.Avg. BKG:-r-'s Lc Gross CPM:r""m Lc Net CPM:*

LD Gross CPM:* LD Net CPM:r-WX-1 Static count CPM CPM DPM No., (Gross) (Net) _______

I static 1 39 5 -cMDA 2 Static2 35 1 <MDA 3 Static 3 32 18 <MDA 4 _______ _______

5 ___________ _______ _______ _______

6 __________ ______ _______ _______

7 __________ ______ _______ _______

8 __________ ______ _______ _______

9 ___________ _______ ________ ________

10 _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _

12 ___________ _______ ________ ________

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

134 _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

14 _ _ _ _ _ _ _ _ _ _ _ _ _ __ ______ ______

15 _ _ _ _ _ _ _ _ _ _ _ _ _ __ ______ ______

167 - ________ ______ ______ ______

178 _________ ______ ______ ______

___IL_

20 d &

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Up to 60 cprn gross pre-decon.

Smear taken post-decon was <MDA. Port end is. free released up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

Lw2221 / 44-1I 218597 / 249243 91Dec-09, 0.502 34 198 d=138 p=0.5 t (deq) 3 401 Tenel6c Series 5 2161 287Jul-09 [1 17.41 a =17.25 P - 1.33 o=o0.00 P.= 210Q a = 5.23 Frisker Detector HV 700 Vdc (249243) LThreshold Voltage = 50 mVdc IDetector cable type/length = 59/6 ft.

Print/Signature of Surveyor: ,,, /xl sko , , Date: 6v- 11 Comments:

.4 1 x4 'A- ý e Date"-_ _____

Review By: W, - ,AA 7

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port # 2.1 TIME: 14:00 Smear information dpm Frisking Probe Model # 44-1 Seriat # PR249243 El. 50.5 E, 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1~-26 1 4 Avg. BKG:i"0 Lc Gross CPM:  ? Lc'Net cPM:

L, Gross CpM:-MA* LD Not CPM:r-X-Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 37 7 <MDA 2 Static2 33 3 <MDA 3 Static 3 24 0 <MDA 5

6 7.

i1 i 12 13, 14 15

-16 17 20

• NOTE: All counts are'l minute static coun~ts' of the O/S portion end of each port. NO Decon Necessary.

Smear taken was <MDA. Port end is frete released up to plane of wall.

Instrument. Serial Number Cal. Due Date Efficiency Background (CPMj MDA (DPM)

L-2221 /44-1 218597 / 249243 9-Dec-09. 0.502 -.. Z30 Zf Z189 d'138 p=0.5 t (sac) 3 .381 Tenelec Series 5 2161 28-Jul-09 IP 17.41 a = 17.25 P3= 133 0.00 23.00 a= 5.23 Friskeir Detector HV-- 700 Vde (249243) Threshold Voltage.-- 50 mVdc Detectorcabuletypellength = 59/6 ft.

PrinSignature ofSurveyor: . /" ... Date: &  ;~- oi 11 Comments:

,/I ' A Review By: L44*.A. At Daie!

a

Storage Port Exterior Survey Report Survey NO.: NA DATE: ,8-Jan-09 LOCATION: Port#22 ,, TIME: 13:35 Smear Information dpim Frisking Probe Model # 44-1 Seriai # PR24, 9243 I M50.5. ,E 0.25 Frisking Probe Efficiency 0.12625 1Min BKG: i' -,-,2, Avg. BKG:9 Lc Gross CPM: m Lc Net CPM:J L, Gross CPM:I-7-l LD Net CPM:N

-Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 36 !7MDA 2 Static 2, 26 0 <MDA i2l isi r-!114- 1__________

2185971:24924 0.______

502' 186___

4rn/intr

________________ _____i_&_Date:

• NOTE: All counts are I minute static~counts ot~theO/S portion end of each port. No Dicon NeceSSaryi

....Smnearltaken was <MDA. Port end~is~free released up to pilanie'tofWalL.,

I ..rumen , ISeia aNumber ! CA).Due Date Effi,,ciency !Backgroidfd,(CP rM)'!MDA'(DPM )

IFri~ker Detector HV= 700 Vdc,(20;24ý3), Threshold. Voltage.= :50 inVdCL i1)0etbe-t~able type/engthIh 59/L6 ft.

Comments:

'11141/4 Rev-eW By:44 (-- Dat~e

Storage. Port Exterior Survey Report Survey NOý: NA DATE: 8-Janý09 LOCATION: Port # 23 TIME: 13:10, SmearInformation dpm Frisking Probe Model # 44-1 Serial # PR249243 E 5,,

50.b Ei, 0.25 Frisking Probe Efficieny b0.12625 i MM 8KG

1.r-32 Avg. BKG:*

Lc Gross CPM:m--I Lc Net CPM:[

LD Gross CPM:W Lo Net CPM:

• NOTEi All ciunts are I minute static counts of the O/S portion endofeach port. No Decon Necessary.

Smear taken was <MDA. Port end is :free released up to plane ofiwall.

Irnstrument Serial Numblr. Cal Due Date Efficiency Background,(CPM), MDAr(DiPM)l L-2221!/44r1 218597 /249243 9-Dec-,09, 0.502 "f 37 .208 d-1.38 p"0:5 J t(sec) 3.

3 .422 Teneolec Series 5 2161 [ 28-7Ju-09 p 17.41 a- 1725 a= 0.00 P 23.00 a =,5.3

• risker Detector HV = 700 VdC (249243) 'Threshold Voltage. 50 mVdc Detector cable ype/length = 3976 ft.

Print/Signature of Surveyor: ~L

- 1ý. , ' L.,

Date: 6 -&-O Comments:

- I jif *lt:,

• Reýview By *Date::*..-.'a- Date-

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port# 24 TIME: 13:00.

Smear Information dpm Frisking Probe Model # 44-1 Serial # PR24I9243 50.5

5. E, 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1.~ ~

Avg. BKG:r Lc Gross CPM:r Lc Net CPM:*

Lo Gross CPM:- Lo Net CPM:I '

Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 .36 0 <MDA 2 Static 2 22 0 <MDA 3 _______ _______

4 __________ ______ _______ _______

5 ___________ _______ ________ ________

6 __________ ______ _______

12 143 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

14 _________ ______ ______ ______

165 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

176 _________ ______ ______ ______

1871 _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

Th9 .5 I

.1 20

• NOTE: All counts arei minute static counts of the O/S portion end of each port. No Decon Necessary.

Smear taken was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number Cal Due Date Efficiency Background (CpM) MDA'(DPM)

L-222l144-I 218597/249243 9=Dec.09 _ 0.502 17 206 d 138 p=0.5 t,(sec) '3 419 Tenelec Series 5 2161 28 Jul-09 B 17.41 a 17:25 3 = 1.33 o =-0.00o, 3 =23.00 ' = 5:23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage 50 mVdc Detector c abie type/length.= 59/6 ft.

Print/Si gnatur o~f Surveyor:,-y' U/ e C4~ Date:. 6L z.-- oP

.1 (ýj V Comments:

~A iii Review By: 64444/_/. 1 Date: Z2-J..

'ooý

Storage Port Exterior Survey Report Survey No.: NA DATE: 8-Jan-09 LOCATION: Port.# 25 TIME:, 12:45-'

Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 t,. 50.5 ES 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: i.  ! EI- 3. 25 Avg. BKG: -

Lc Gross CpMrr Lc Net CPM:I Lo Gross UPM:I J LD Net CPM:I =-I Static Count CPM CPM DPM No. .(Gross) (Net) 1 Static 1 30 19 kMDA 2 Static 2ý 43- 12 <MDA 3

4 5

10 it 12 14 201

• NOTE: All counts are.1 minute static counts of the O/S portion end of each port. No Decon Neces .sary, Smear taken was <MDA. :Port end is free released up to plahe 0f~ali, linst'rum ,ent SerialI Number Col. Due'Date Efficiency. Background (CPM) MDA (DPM) 1-2221 /44-1 218597 Z2419243 9-Dec-09 0.502 '31 191 d'138 =05, t (sec) 3, 385 ITehelec Series 5 .2161 2J10 317A.41 a=17.25 10=1.33 a =0.00 I*23.00 a =.5.23 lFri~sker Detector.HV = 700 VdC (249243) IThresbold Voltage = 50 mnVdc jDetector cable type/length - 59 / 6 ft, Print/Signature of Sur veyor: ~~r*Ale'$'9~v /~~\ Date',nf ,ý&_70 Comments:

A A i

,Review BY: Ce:4.14.

- L~4' A -A ,  ::z Dateý .21A -9/Z 3-

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port # 26 TIME: 11:00 Smear Information dpm Frisking Probe Model # 44-1 Seilal # PR249243 E,. 50.5 E, 0.25 Frisking Probe Efficiency '0.1 2625 I Min BKG: 1.

Avg. BKG:m---

Lc Gross CPMl:"- I LC Net CPM:I Lo Gross CPM:r"x LD Net CPM :N static Count CPM CPM DPM No.. (Gross) (Net) ______ -

I Static-1 is .17 <MDA 2 Static 2 33 15  !<MDA 3 ___________ _______ ________ ________

4 __ _ _ _ __ _ _ _ _ _

5 __________ ______ _______

6 _ _ _ _ _ _ _ _ _ _ _ _

7 ___________ _______ ________

8 __________ ______ _______ _______

9 __________ ______ _______ _______

10 _ _ _ _ _ _ _ _ _____ ______

u1_____________ _________________ _________

123 _________ ______ ______ ______

134 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

145 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

156 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

167 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

• NOTE~i All counts are 1 minute static counts of the 0/S portion end of each port. No Decon Necessary.

Smear taken was <MDA. Port end is free released up to plane of wall.

.nstrument Serial Number Cal. Due Date Efficiency Bacroun L-2221 144-1 218597 / 249243 9-Dec-09 0.502 38 -20R d138 p=0.5 t (sec) 3 426 Tenelec Series 5 2161 .28-Jul-09 1A 17.41 a 17.25 P =1.33 a 0.00; P, 23.00 a = 523 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 -mVdc Detector cable type/length = 59/6 ft.

Print/Signature of Surveyor: 7J 'r .4 3& Date: -01 Comments:

4 1i o .

Review By: c-.4..A_ _ _ -, - Date

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port# 27 TIME: 10:25 Smear Information dpm Frisking ProbeModel # 44-1 Serial # PR24' 9243 E, 50.5 E 0,25 Frisking Probe Efficiency 0:12625 I Min BKG: 1.3. 42 Avg. BKG:

Lc Gross CPM:j 5 Lc Net CPM:W LD Gross CPM  :" LD Net CPM: '

Static Count CPM CPM DPM No. (Gross) (Net) _______

1 Static 1 29 0 <MDA 2

3 _ _ _ _ _ _ _ _ _ _ _ _

4 __________ ______ _______ _______

5 6 __________ _______ _______

7 __________ ______________

10 ___________ _______ _______ _______

812 __________ _______

13_______ ________ _______

104 ________ _____

15 ______________________ _________ _________

12.6 _ _ _ _ _ _ _ _ ______ _ _ _ __ _ _ _ _ _ _ _ _

137 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

• NOTE- AlI'counts are 1 minute static counts of the 0/S portion end of each port.. No Decon Necessary.

Smear taken was <MDA. Port.end is free, released up.to plane of wall.

Instrumenit Serial Number Cal. DueDate Efficiency Background (CPM) MDA.(DPM)

L,2221 /44-I 2.185971.249243 9-Dec-09 0.502 36I 205i d'=l"38 p=0.5 t,(sec) 3 417 Tenelec Series 5 2161 28-Jul-09 10 =,17.41 a = 17;25 1 = 1.33 ,00 = 23.00 a 5.23

[Frisker Detector lIV = 700 Vdc (249243) Threshold Voltage = 50 mVdc 1Detector cable typWIlength = 59 /6 ft.

Print/Signature of Surveyor: J6t(A* t L/"i. i. . Date:

Comments:

"7 /---~ or - F, Review By: Date: -.*A/. ,/i'2..

-V

Storage Port Exterior SurC'ey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port# 28 TIME: 10:00 Smear Information dpm Frisking Probe Model # 44-1 'Serial # PR249243 5o.

50.5 is 025 Frisking Probe Efficiency 0.12625

.1 Min B0KG 1.

Avg. BKG:r Lc Gross CPM:r Lc Net CPM:I LD Gross CPM:" LD.Net CPM:I Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 40 10 <MDA 2 Static 2 33 3. <MDA 3 Static 3 31 1 WMDA

'4 I-

4. 6. .1 4* 6. 9 I* I" 9 7 I 4-8.6 6. I 9 4-g I I 9

& I 4. .6-I. I 4. 4-12 9* I 9 13 6. I 4. .4-14 I I 6. 4-15 p i 9-Ib I I 17 18 19 20 ___ __ __ __

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Up to 60.cpm gross pre-decon.

Smear taken post-decon was <MDA. Port end is free released up to plane of Wall.

Instrument Serial Number Cal. Due.Date Efficiency Background (CPM) MDA (DPM)

L-2221/44-1 218597 / 249243 9-Dec-09 0A502 l 30 188

-'=d138 p=0.5 t (sac) 377 TenelecSeries5 2161 28Ju-09 13=.17.41 a =17.25 0=1.33 o=0.'0 .=23.00 o=5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc Detector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: . -sr.( r I9.AA ,..Q,. ilk,

• t pate: X - .,,ý _

I

• V q -

Cqmments:

A D¸ Ai

3 Ai M 1 Review By: CZL:.,t

. .A_-'-- att::gý Date: 3/ .

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port#29 TIME: .9:45 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 Eji 50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: i 351 Avg. BKG:r"-T1 Lc Cross CPM:* Lc Net CPM: ]

LD Gross CPM:F LD Net CPM: A Static Count CPM CPM OPM No, (Gross) (Net) ________

1 static 1 44

• 8 -CMDA 2 Static 2 .40 4 .CmbA

ý3Static 3 25' 0 '<MDA 4 _ _ _ _ _ _ _ _ _ _ _ _ _ _

5 ___________ _______ ________ ________

6 ___________ ______ _______ _______

7 ___________ _______________

8 ___________ ______

9 ___________ ______ _______ _______

10 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

11 _____________ ________ _________

12 __ _ _ _ _ _ _ _ __ _ _ _ _ _ _______

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14 __ _ _ _ _ _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

15 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

16. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

& I. .1 I-19

-. I 9. '9 ~* -

20

• NOTE: All counts are 1 minute static counts of the O/S portion end of each port. No Decon Necessary.

Smeartaken was <MDA. Port end is free released upto plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA.(DPM)

L-2221 /44,1 ý218597/249243 9-Dec09 0.502 .36 'i.....i205 d=138 p=0.5 t (sec) 3 417 Tenelec Series5 2161 28-Jul:09 P 7A14a= 17:25  !,133 ao):oo P=23.10 a=5.23

[Frisker Detector HVY= 700 Vdc (249243) Threshold Voltage 50 mVdc Detector,cable type/lengih = 59 6 ft.

Print/Signature of Surveyor: '-ecu iwti/C i ._L*a 4 Date:

[(.1 ("-"

Comments:

A A A Review B L..-A if -

Date: , a

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port # 30 TIME: 9:20 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 LrSO._5 50 5 E 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1 361 28 Avg. BKG:*

Lc Gross CPM:T Lc Net CPM:*

LD Gross CPM:- Lo Net CPM:j*

Static Count CPM CPM DPMV No. (CGross) (Net) _______

1 static 1 -43 9 'MDA

ý2 _ _ _ _ _ _ _ _ _ _

3 ___________ _______ _______

4 ___________ _______ _______ _______

5 ____________ _______ ________ ________

6 __________ ______ _______ _______

7 ____________ _______ ________ ________

8 ___________ _______ _______ _______

.9 __________ ______ _ _ _ _ _ _ _ _ _ _ _

10 __ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

11 ____________ _______ ________

12 ______ ______

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

14 _________ _____ ______

15 __________ ______ ______ ______

16 _________ _____ ______

17 _________ _____ ______

18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

2.0[ - 7I ~ i_______I_____ _

• NOTE: All counts are 1 minutestatic counts of the O/S portion end of each port. No Decon Necessary.

Smear taken was <MDA. 'Port end is free released up to plane of will.

Instrument I Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1 218597,1249243 9-Dec-09 0_502 34 199 di138 p=0.5 t (sec) 3 403 Tenelec Series 5 2161 28-Jul-09: p.- 17.41 a = 17.25 0,= 1.33 a = 0.00 [=-2300.a =.5:23 IFrisker Detector HV.= 700 Vdc (249243) Threshold Voltage 50 mVdc Detector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: Date: Olf-5,-0 Comments:

A & Ax F A

Review By: 4t-!I7*. AX - Date: .2/* jA( -a.

a

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port # 31 TIME: 9:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 IEi 50.5 0;25 Frisking Probe Efficiency 0.12625, I Min BKG: .E 7-2613. r - 38 Avg. BKG:r Lc Gross CPM: m--I Lc Nel CPM:*

LD Gross CPM:FVAI LD Net CPM:[

Static Count CPM CPM DPM No. (Gross) (Net) 1 Statici1 38. 4 -cMVDA 2 Static 2 40 .6 <MDA 7

10 _________ ______

12 _______

14 _________

15 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

167 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ ______

17A _________ ______ ______

18 _____ _______ ______

20

• NOTE: All counts arel minute static counts post-decon of the 01S portion end of each port. Up to 80ecpm gross pre-decon.,

Smear taken post4decon was <MDA. Port end is free released up to ]lane of wall.

Instrument Serial Number Cal. Due Date 'Efficiency Background (CPM) MDA (DPM)

L-2221 / 44-I 218597 / 249243 9-Deck09 0.502 34 200 I d1=38 p0.5 t (sec) 3 405 Tenelec Series 5 2161 28-Jul-09 p 17.41 a = 17.25 P=1.33 ao 0.O0 0='23.00 a=.5.23 Frisker Deteclor.l-V= 700 Vdc (249243) [Threshold Voltage.= 50. mVdc Detector cable type/length = 59 / 6 ft.

Print/Signature of Sur.veyor: . -- 3!v LN A1,1144 Al Date: R-T.10 IC/

I Comments:

1^ A A-Review By: .,t7kAY L-, A Date: J/ ,

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8LJan-09 LOCATION: Port # 32 TIME: 8:45 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243

.50.5 s 0.25 Frisking'Probe Efficiency '0.12625 1 MinoKG: 1 - j-j 3 31 1 Avg. BKG:'

Lc Gross CPM: Lc Net CPM: /

LD Gross CPM:r-WA-j LD Net CPM:r*F"I S tatic Count CPMr CPM DPM No. (Gross) (Net) _______

1 Static 1 47 16 <MDA 2 Static 2 49 18 -ýMDA 3 Static 3 44 13 <MDA 4 Static 4 47 16 <MDA 5 ___________ ______ _______ _______

6 __________ ______ _______ _______

7 ___________ _______ ________ ________

8 ___________ _______ ________ ________

9 _______ ________ ________

10 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1i ____________ _______ ________ ________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _____

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____

14 _ _ _ _ _ _ _ _ __ _ _ _ _

15 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _____

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

'7 __________ ______ ______ _____

9S _________ _____ ______ ______

19l I_________ I______ I______ I_____

• NOTE: All counts are 1 minute static counts post-decon of the oMs portion end of each port. Up to 61 cpm gross pre-decon.

Smear taken post-decon' was <MDA. Port end'is free released up to plane of wall.

Instrument I Serial Number Cal.'DueDate Efficiency Background.(CPM) MDA (DPM)

L2221 144,l '218597 /249243 97Dec-09 T19.1 0'502 31 I =138 p=.0.5 t (sec) 3 Tenelec Series 5' 2161 28-Jul-09 1 =17.41 a= 17.25 0 = 1.33 ao,=,0.00 lp= 23.00 a= 5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc IDetector cable type/length = 59 /6 ft.

Print/Signature of Surveyor: 2 'L Ag"

,,v6 L /A*ti(, 4A Date: -QfL-z- OP j / . . I Review By&ei& Date:

te X S W

Storage Port Exterior Survey Report Survey NO.: NA DATE: 8-Jan-09 LOCATION: Port # 33 " TIME: 8:25 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 El5. 50.5 Es 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: r ----33 Avg. BKG:*

Lc Gross CPM:m Lc Net CPM:2 LD Gross CPM:r Lo Not CPM:N Stati~c Count CPM CPM DPM No. (Gross) (Not) _______

1 Static 1 30 15 <MDA 2 Static 2 39 4 <MDA

.5 ______ ________

6 ___________ ______ _______

10 _ _ _ _ _ _ _ __

14 15 _________

'16 _ _ _ _ _ _ _ _ _ _ _ _ _ _

'19-20 _________

• NOTE: All counts are I minute static counts post-decon of the O/S, portion end of each port. Up to 63 cpm gross pre-decom Smear taken postwdecon was <MDA. Port end is free released Up to plane ofwall.

[ Instrument Serial Number Cal. Due'Date Efficiency Backgrouid(C-PM) MDA(DPM)

L-2221/44-1 218597/249243 9-Dec.09 0.502 35 201 0:138 p=0.5 t (sk) ' 3 . 407" '

lenielec Series 5 2161 28-Jul-09 =174.1 a =17T25 1 .=133 a = 0.00 = 23.00 d.-5,23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc Detector cabletypellength 59 /!6ft.

Print/Signature of Surveyor: Z rrvy *,. .,i/ * . Date: Q P--" h ý-4 Comments:

A, Al . A J Review By"."4-,frA,(.,, Date: .21A.?l

Storage Port Exterior Survey Report Survey NO.: NA DATE: Z8-Jan-09 LOCATION: Port # 34 TIME: 8:1.0 Smear Information dpm Frisking Probe Model # 44-1 Seral# 'PR2419243 El, 50.5 s 0.25 Frislng Probe Efficiency 0,12625, I Min 1 [ -KG: 61 r 2,1 Avg. BKG:r-I2' Lc Gross CPM: m 'Lc Net CPM:*

L, Gross CPM MA Lo Net CPM:r Static Count CPM CPM DPM No., (Gross) (Net) 1 Static i 44 165 <MDA 2 Static 2. 30 1 WMDA 3 Static 3 36 7 <MDA 4 Static 4 27 0 <MDA

.5 _

6i_ ___

7 NOTE: All counts areI intestti os - oh pod a rp mo e 8 Smear tken pt nwM Pt ifred a 9 Insrumen__Serial N__mbe a.uD e fi y B k n( ) (D 10 L-2221_/____ 2___97_4924 __ e_____0_2__

11Tene__c Series 5 d_=t_38 P=O.5 t (see 3_374 1209 =1 1_ . !3O__0 5 13 ri r ttrH = 0 c(_93_rhlVlg_ 0 d D et aet /ng f 14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

15 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

• NOTE: All counts are 1 minupte static counts post-decon of the 0/S portion end of each port. Up to 58 cpm gross pre-deco.06 Sme'ar taken post-decon was.ý<MDA._Portend is free released up to, Ilane of *all.

F Instrument" Serial Number. j Cal. Due Date 1 Efficiency Background (CPM) MDYAj(DIPM).

L-2221/144-1 j19/2943 qDec.-09 9 00 I ~ I Z 24 d' 170-0 . '2 T~epelec SerieSL5 2161 28'Jul-09L 1741 17.25--3 P 0- a 52 Frisker Detector H4V =700 Vdc (249243) IThreshold Voltage 50§ m~dc iDetector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: 2Tirlý '!"-" /u,- Date: tk.c 4t "

Comments:

A t *

- Dae / D/

Review Reie lYi~%

py-'r-ýZ-1-ýAj I---- * ,

Q W4..2ýAA 'I// -e

Storage Port Exterior Survey Report Survey NO.: NA DATE: 7-Jan-09 LOCATION: Port # 35 TIME: 11:30 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 E. 50.5 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1.32 Avg. BKG:r j Lc Gross CPM: m Lc Net CPM:;

Lo Gross CPM:r-'/-- Lo Net CPM:[*v"I Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 48 15 <MDA 2 Static 2 S43 12 <MDA 3 Static 3 34 1 <MDA 4 Static 4 32 0 <MDA 96 elcSeis _16__-u-0__=1. ____1.5__= .3 00 1 2.0 52 107ker Deteto_"

8i___________________

129 ________

HV = d 9h l a 0D t l e h /

130 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

141_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

12 _________ ______ ______

163 _________ ______ ______ ______

14 _________ ______ _______ ______

185 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ d'__=__1__38_p=0__5_t_ (sec)__3_397

• N'I:All counts ar1 minute static conspost-decon of the, 0/S poirtion end of each port. Refer to~initilpr uvyrpr for pre-decon, contamination results. Smear taken post-deconj Was <MDA. Port end is free released up to plane of'wall.

Instrument Serial Number Cal. Due Date j Efficiency IBackground (CPM) MDA (DPMV)

L-22211/44-1 218597 /249243 9-Dec.-09 0.502 '33. 197 2

Tenelec Series 5 1 2161]

28-JuJ-09 I 18p=0.5 JP 17.41 a 17.25 0 = 1.33 t(sec) a ~o 3 I

ý0 397 j P= 23.00 a = 5.23

!Frisker Detector HV = 700 Wde (249243) IThreshold Voltage = 50 MVdc IDetector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: cy Date: A 7- JTaq-op

/ U C-Comments:

A i I AAq I Review By:  !:Zj_. A,_,Dare:&...---- .- bate: '.) 14

Storage Port Exterior Survey Report Survey NO.: NA DATE: 7-Jan-09 LOCATION: Port # 36 TIME: 11:15 Smear Information dpm Frisking ProbeModel # 44-1 Seril # PR249243 Ei 50.5 E, .0.25 Frisking Probe Effclency 0:12625 1 Min BKG: 1 33 Avg. BKG:I-mI-l Lc Gross CPM:"-m-] Lc Net CPM:rF" l LD Gross CPM:T-7/7- Lo Net CPM:*

Static Count CPM CPM DPM No. (Gross) (Net)

Static 1 50 18 <M DA 2 Static 2 37 .5 <MDA 3 Static 3 331 MDA 4 _______ _______

8 ___________ _______ ________ ________

10_ _ _ _ _ _

11 ___________ _______ _________ ________

13 14 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

156 _______

17 _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

17 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

18 ____________ V________

219 1_________ 1_____1__

• NOTE: All counts are I minute static counts post-deconof the O/S portion end of each port.

Smear taken was <MDA. No Decon Necessary. Port end is free released up to plane of wall..

Instrument ISerial Number Cal. Due Date Efficienicy Background (CPM), MDA(DPM)

L-2221-/44-1 28597/249243 9-Dec-09 0.502 3Z. 195 d138 p=0.5 t,(sec) 3 393 Tenelec Series 5 2161 28-Jul109 3 17.41 a = 17.25 3 = 133 6 = 0.00 0 = 23.00 a = 5.23 Frisker Detector HV = 700 Vde (249243) ThresholdVoltage S0 mVdc ' Detector cable type/length = 59 / 6 ft.

Pri'nt/Signature. of Surveyor: /

0 *"rýk-e/ l .", .4 Date: A 7 -T4t

'Comments:

~jj -a i

- f J1 -V- # - -

Review By* ,LA'A...-------- Date: a &. -qA 2---

Storage Port Exterior Survey Report Survey NO.:ý NA DATE: 7-Jan-09 LOC, ATION: Port# 37 TIME: 11:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR24!9243 El 50.5 CI 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1 31 29 Avg. BKG:*

Lc Gross CPM:*IT .Le Net CPM::

LD Gross CPM:? Lo Net CPM.,

Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 39 6 <MDA 2 Static 2 44 11 <MDA 3 Static 3 37 4 <MDA 4 Static 4 26. 0 <MDA T8nelec Se__es_5___6 28-Ju_09 .71=7 =._0_= 0 .

5r 5ra 79 I ___e__)__3 d'=1.38_______p=0.5_______

2

.NOTE: All counts are I minute'static counts post-decon of the 0/S portion end of each port.

Instruimint L-2221 144-1 Serial Number 218597 /249243 Cal. Due Date 9-Dec-09

}

Smnear taken was <MDA. No Decon Necessary. Port end is free rel,,eased up to Olaine of WWIl.

Efficiency 0,502

[Background (CPM) I 33 MDA (D.PN)

-197 1d'=1.38 p=0.5 t isec 3. 397 ITenelec Series 5 1 2161 28-Jul 09 lp= 17:41 a= 17ý25 P = 1.33 a 000 lP=.23:00 a =5.23 lFrisker Detector HV =700 Vdc (249243) IThreshiold Voltage = 50 mVdc DetIector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: _"* (' .__p iiit._. Date: 6.'7-\ ,,P.7-O?

'/ V Comments:

A 0 -0 .6 if

ýe -

-F .

1 A

Review By: 'Da'te::.Z.4 // ,I

Storage Port Exterior Survey Report Survey NO.: NA DATE: 7-Jan-09 LOCATION: Port # 38 TIME: 10:50 Smear Information dpm Frisking Probe Model# 44-1 Serial # .PR24.9243 E, 50.5 Es 0.25 Frisking-Probe Efficiency 0,12625

'Min BKG: 1.E 34 3. 2 Avg. BKG:r Lc Gross CPM:-j Lc Net CPM:*

LD Gross CPM:I-"Z7* Lo Net CPM:I j Static Count CPM CPM DPM No. (Gross) (Net) 1 Statici 510 19 <MDA 2 Static 2 39 8 <MDA 3 ___________________

4.__________ ______ _______ _______

5 ___________ _______ ________ ________

6 __________ ______ _______ _______

7 _________

8 ___________ _______ ________ ________

9 ___________ _______ ________ ________

10 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

• 11 ____________ ________ ________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

15 __ _ _ _ _ _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

16 __ _ _ _ _ _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

17 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

.5 4. 4.-

20

• NOTE: All counts are I minute static counts post-decon of theO/S portion end of each port. Refer to initial port survey report for pre-decon contamination results. Smear taken post-decon was <MDA. Portend is free, released up to pianeof wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM). MDA (DPM)

L-2221 144-1 218597 /249243 9-Dec-09 0.502 31 , 191 d'138 p=0.5 t (sec) 3 385 Tenelec Series 5 2161 28-Jul,09 13 = 17.41 a = 17.25 0 = 1.33 a= 0.00 P=23.00 a=5.23 Frisker Detector HV= 700 Vde (249243) Threshold Voltage - 50 mVdc Detector cable type/length = 59/6 ft; Prini/Signatu.re of Surveyor: l*Ct' *J1*.,I-./9 */Jz 1 . Date: 6--X -09 Comments:

,t 'a 14 Review Date:.

Date: LZIa,)

22Ak/,2.. h 2-I

Storage Port Exterior Survey Report Survey NO.: NA DATE: 7-Jan-09 LOCATION: Port # 39 TIME: 10:30 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 50i

.50.5 0:25 Frisking Probe Efficiency 0.12625 I Min BXG: 1.~

Avg. BKG:-

Lc Gross CPM:F-4-l Lc Net CPM:*

LD Gross CPM: z LD Net CPM:r Static Count CPM CPM DPM No. (Gross) (Net) '

Static 1 43 15 ,<MDA 2 Static 2 36 8 <MDA 3 Static 3 .33 5 kMDA 4 ______ _______

b5 ___________ ________ ________

6 ______ _______ _______

7 _______ ________

8 _______ ________ ________

9 ___________________

10 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

11 _____________________ _________ _________

12 __________ ______ ______ ______

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

15 _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _

1.6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _

17 __________ ______ ______

18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

20 __________ ______ _______ _______

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Refer'to initial port survey report for pre-decon contaminiation results.Smear taken post<deCOn.Was <MDA. Port -endJs free released up to plane of wall.

Instrumen+t I Serial Number )Cal. Due Date Efficiency' Background (CPM) MDA (DPM)

L-2221 1441 12185971249243 9-Dec-09 0.502 28 184 d =1.38 p=0a5 t (sec) 3 368 TeneleoSeries 1 2161 28-Jul-09 17.41 a = 17.25 1.33 a =0 - 23;00 o.=5.23 Frisker'Detector HV = 700 Vdc (249243) Threshold Voltage - So mVdc Detector cable type/length = .59 /6 ft.

Print/Signature of Surveyor:. 'ZkayT V 7LjI'M Date: 2L iaP Comments:

A .. h /

~i z Review By: 4=," ,4Z= Date:. 1. a.jh--

Storage Port Exterior Survey Report Survey NO.: NA DATE: 7-Jan-09 LOCATION: Port # 40 TIME: 10:15 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243

£E 50.5 0.25 Frisking Probe Efficiency 0.12625

,341 1Min BKG: lE Avg. BKG:r Lc Gross CPM:g Lc Net CPM:"

LD Gross CPM:[ LD Net CPM:[

'i Static Count CPM CIPM DPM No. (Gross) (Net) _______

1 statici1 43 11 .CMDA 2 Static2 39 *7 <MDA 3 static 3 33 1 <MDA 4 Static 4 :37 5 MDA 5 ___________ _______

67 __________ ______ _______ _______

78 ___________ _______

89______

910 __________ _______ _______

14 _ _ _ _ _ _ _ _

15 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

17 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

1.8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

201 __ _ _ _ __ _ _ 1 __ _ _ _ _1 __ _ _ 1__ _ _ __ _ 1

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port.

Smear taken Was <MDA. No Decon Necessary. Port end is free released up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1 218597/249243 9-Dec-09 0.502 '32 193 d=138 p-0.5 t:(sec) 3 389' Tenelec Series 5 2161 28-Jul 09 P 17.41 = 17.25 P=1.33 a = 0.00 P=23.00 a =5.23.

Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc jDetector-cable type/length = 59/ 6 ft.

Print/Signature of Surveyor: -* -,e/fl' U

U, 4.J)Ký Date: A1J~-0c9 Comments:

Review By: " Ddte:

Dt): ?L4-!h2 .

Storage Port Exterior Survey Report Survey NO.: NA DATE: 7-Jan-09 LOCATION: Port #41 TIME: 10:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 50.5 5 . 'E. 0.25 Frisking Probe Efficiency 0.12625 I 1 25-1 Avg. BKG:m Lc Gross CPM: Lc Net CPMI Lo Gross CPM:I"=VX-l LD Not CPM:INA Static Count CPM CPM DPM No. (Gross) (Net) _______

1 Statici1 37 10 <MDA 2 Static 2 3/ 4 <MDA 3 Static 3 33 6 <MDA 4 Static 4 36 9 <MDA 5 __________ ______ _______ _______

10 _____ ______

11 _______ ________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

15 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

1 16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 17 __________ ______ _______ _______

1181 _____

1________ ____________

201 _ _ _ _ _ 1__ _ _ 1 __ _ _ _ _I 1___ _ _ _ _ 1

• NOTE: All counts are I minute static counts post-decon of the O/S portion end of each port. Up to 77 cpm gross pre-decon.

Smear taken post-decon was <MDA. Port end is free-released up to plane ofwall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /44-1 18597 /249243 9-Dec-09 0.502 27 179 d=138 p=0.5 t (sec) 3 2157 Tenelec Series 5 1 2161 . 28-Jul-09 3=1741 a = 17.25' 1.33 o=0.00 Pr=23.00 a = 5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 mVdc Detector cable type/length = 59 /.6.ft.

Print/Signature of Surveyor: Je fA . ,,i- /C.,..* Ji*Zt Date: c57-ýJ*. 1 -O' I /(./ U--

Comments:

.4 I

1. I

.i - A ReviiewBy6S*  ? - Date- ;V-13A X-

Storage Port Exterior Survey Report Sur4ey NO.: NA DATE: 6-Jan-09 LOCATION' Port.# 42 TIME: 15:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 IE 50.5 , 0.25 Frisking Probe Efficiency 0.12625 1Min BKG: 1J[*- -'"* " 3.-

Avg. BKG: "

Lc Gross CPM 55-" Lc Net C PM:

LD Gross.CPM:-r-A-I Lo Net CPM: -

Static Count CPM CPM DPM No. (Gross) (Ne2t) 1( NoStatic 36 2 <MDA 2Static 2 42 8 <MDA 3 Static 3 31 0 <MDA 4

4II 5 A I &

6

.5 .5 I.

7 4 4 4.

.1 4 4 I I

.5 .5 I. 4.-

10

• 4 4.

• 11 12______ __ _ _ _ _ _ _ _ _ _ _ _

13 _________ _____ ______

14 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

15 _____ ______

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______

17 _ _ __ _ _ _ 1__ _ _ _ 1__ _ _ _ _ 1__ _ _ _ _ 1__

18 _____ ______ ______

19 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

20

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Up to 77 cpm gross pre-decon.

Smear taken post-decon was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number I a!. Due Date Efficiency Background (CPM) VIDA (DPM)

L-222n]te44-1 r21l8m597

/l249 43 9-Dec09 0.502 (CM34 M D199 d'-d138 p=0.5 t (sec) 3 403 Tenelec Series 5 2161 28-Jul-09 3__17.41 o= 17.25 03.=1.33 a.= 0.00 13= 23:00 a =:5.23 Frisker Detector HV = 700 Vdc (249243) Threshold'Voltage 50 mVdc Detector cable type/length = 59 /6 ft.

Print/Signature of.Surveyor: . / .. , Date: 0& -- '*[%hO0

/L 'v (

Comments:

. . I I Review By'- #.#(

'A Adj*. ze Date: Z11-74

Storage Port Exterior Survey Report Survey NO": NA DATE: 6-Jan-09 LOCATION: Port # 43 TIME: 14:45 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 E0, 50.5 0.25 Frisking Probe Efficiency. 0.12625 I Min BKG: 1.r--2!

Avg* BKG:-

Lc Gross CPMr-W- Lc Net cPM:il Ln Gross CPM:F Lo Net CPM:l Static Count PMA CP -M DPM No. (Gross) (Net) _______

1 Static 1 3811 -cMDA 2 Static 2 44 17 <MDA 3._ _ _ __ _ _ _ _ _

4 5 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

6 ___________ ______ _______ _______

7 ___________ _______ _______ _______

8 ___________ _______ _______ _______

10 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _ _

10 _____________________ _________ _________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ ______

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______

14 _________ _____ ______

15 __________ ______ ______ ______

16 11__

17 _ _ _ _ _ _ _ _ _ _ _ _ _1_ _ _ _ _ _

19

.9 .9 9

.5 .5 &

• NOTE: All counts are 1 minute static counts of the 0/S portion end of each port. No decon necessary.

Smear taken was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number; CaL Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 / 44-1 2185971/ 249243 9-Dec-09 0.502 27 .181 d'138 p=0. 5 t(sec) 3 361 Tenelec Series 5 2161 28-Jul-09 3 17.41 a= 17.25 5,= 1.33 a =O.O0 23.00 a 5.23 Frisker Detector HV = 700 Vdc (249243) Threshold Voltage = 50 imVdc Detector cable type/length = 59 / 6ft.

PrintlSignature of Surveyor: ~~c~~/~~L-k' Date:;-Db-7-1 0 Comments:

Ah ,,

Review By: Date: ,,2/(/,L..

Storage Port Exterior Survey Report Survey NO.: NA DATE: 6-Jan-09 LOCATION: Port# 44 TIME: 14:25 Smear Ilformiation dpm Frisking Probe.Model # 44-1 Serial #4 PR249243 E, 50.5 0.25 Frisking Probe EfficIency 0.12625 I Min BKG:

I ~36 AVg. BKG: r-f-"

Lc Gross CPM: Lc Nie'CPM.

LD Gross CPM:* Lo Net CPM: "

Static. Count CPM CPM DPM No.. (Gross) (Net) I_....

1 Static 1 34 5 4MDA 2 Static 2 38 9 <MDA 3 Static 3 ý34 5 'MDA 4

'12 13

• 'NOTE, All counts are Iminute static counts post-decon of the O/S portion end of each. port; Up to 74 cpm gross, pre-d-econ.

.Smear taken pst-decon~was <ýMDA. Port, end'is free~released up to plane of walL, instrumi't Serial Number Cal.'Due Date Effici~ncy Background (CPM) MDA (DPM)

L*22'/,4*1 2159 /249243 9.-Dec-09 0.5022918 d'=5 1.36' p=0_5 t (sec) .3 "370_

ITe-nelec Seriecs:5 21-61. 2 -Jul-09 3=17.41 a = 17ý25 = 133 1 a =.0;66 P =23.00 o.=5.23 Frisker De.tector HV= 700 Vdc (240243) T

]hreshold Voltage ... 50 mjVde IDetector Cable type/length =f 59 /6 ftý 1

PrintlSignature of Surveyor: f0

'i -./

' . "(,Aec4Al Date: to

• (/ I Comments:

.4 1 ,.47 I Review By:c Eiate:l Date=----'

Storage Port Exterior Survey Report Survey NO.: NA DATE: 23-Dec-08 LOCQATION: Port# 45 TIME: 14:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 El ý50.5 IS 0.25 Frisking Probe Efficiency 0.12625 I MIn BKG:

Avg. BKG:*

Lc Gross CPM:r Lc Net CPM  : "

LD Gross CPM:F"J LD Net CPM: X Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 48 10 <MDA 2 Static 2 46 8 <MDA 3

4Nom tt foeea u bor5re-eo _n _a _rn orre 12 13 _____

15 _________

• NO0TE: All counts are 1 minute static counts post-d~econ of the 0/S portion end of-each port. Refer to initial port survey report 18 =__.38__p=0___5__t_(se_

________24 for pre-decon contamination results. Smear taken: ost-d econ was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number ICal. Due' Date-j Efficiency Background (CPM) MDA (DPM)

L72221 1444I 218597 /249243. 9-Dec-,09 0.502 38 '208 d18 Pý_0.5 t (aec) 3 Q42 TenelecSeries 5 2161 28-Jul*09 3= 17;41 a = 17.25 lP= ý1.33 a - 0ao. 13= 23.00 a = 5'23 Frisker Ditector. HV = 700 Vdc (249243) Threshold Voltage = 5 mVdc Detector cable type/length = 59/ 6 ft.

Print/Signature of Surveyor:, k.f ,-.. \ Date: .- _-' -

I~ (

U'I Comments:

-4 A i Review By.:. A Date: a 4".411L -t

Storage Port Exterior Survey Report Survey NO.: NA DATE: 23-Dec-08 LOCATION: Port# 46 TIME: 13:45 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243

• l 50.5 0.25 Frisking Probe Efficiency 0.1ý2625 Min BKG: 1.- 31 42 40 Avg. BKG:r 39 Lc Gross CPM:m Lc Net CPM:-

LD Gross CPM:* Lo Net CPM:[

Static Count CPM CPM DPM No. '(Gross) (Net) 1 Static 1 33 0 <MDA 2 Static 2 29 0 ýcMDA 3 static 3 35 0 <MDA 4 Static4. 49 10 <MDA

5. __

6 ___________ _______ ________ ________

7 ___________ _______ ________

8 ___________ _______ ________ ________

910 __________ _______ _________ ________

101 _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

12 ____________ ________ ________ ________

123 _________ ______ ______ ______

14 _ _ _ _ _ _ _ _ _ _ _ _ _ __ ______ ______

14 _ _ _ _ _ _ _ _ _ _ _ _ _ __ ______ ______

16 _____ ______ ______

167 _ _ _ _ _ _ _ _ _____ _ _ _ _ _ _ _ _ _ _ _ _

.5 .5 6. 6.-

19

.5 .9 6. 9 -

20

• NOTE: All counts are I minute static counts posi-decon of the O/S portion end of each port., Refer to initial port survey report.

for, pre-decon contamination results.,Smear taken post-decon was <MDA. Port endisfree released up to plahe of wall, 1lnstrument Serial Number Cal. Due Date Efficiency 1Background (CPM) MDA (DPM)

L-2221/-44-1 218597 / 249243 9*Dec,09 0.502 39 d-1.38 p=0.5 t (sec) 3 430 TenelecSeries,5 2161 '8-JuI09 P 17.41 a;=17.25 0:= 1.33 =.o0  :=23.00 a=,5.23 Frisker Detector HVB= 700 Vdc (249243) Threshold Voltage 50 mVdc Detector cable type/length = 59/6 ft.

Print/Signature of Surveyor: J'c i./ Date: 9--

Comments:

A I , I Review By: *244.4 ,t Date:

D 24; J.,ILz

/

Storage Port Exterior Survey Report Survey NO.: NA DATE: 6-Jan-09 LOCATION: Port # 47 TIME: 14:00 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR2419243 El 50;5 E, 0.25 Frisking Probe Efficiency 0.12625 1lMinBKG: 29 Avg. BKG:-

Lc Gross CPM:--"9 Lc Net CPM: "

LD Gross CPM:T-9/7 Lo Net CPM:r"NA-Static Count CPM CPM DPM No., (Gross) (Net) 1 Static 1 44 i6 <MDA 2 Static 2 34 6 <MDA 3 Static 3 37 9 <MDA 4 Static 4 41 13 <MDA 7

10 12 ___________ ________ ________

0 913_ _ __ _ _ _ _ _ _

104_ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

11 _____________ __________________

126 _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _ _

17 _ _ _ _ _ _ _ _ _ _ _

,8

• 6 I 0 0-9

-FW - W t-

.1 6

• NOTE: All counts are 1 minute static counts post-decon of the O/S portion end of each port. Up to 100 cpm gross pre-decon.

Smear taken post-decon was <-MDA. Port end is free released up to plane of waN.

Instrument Serial Number Cal. Due.Date Efficiency Background (CPM) MDA (DPM)

L-2221 / 441 21L8597/249243 !9-Dec-09 0.502 28 182 d1.38 p-0.5 t(sec) 3364 Tenelec Series 5 2161 28-Jul 09 1 17.41 a= 17.25 P= 1.33 a 0.00 I = 23.00 a ='5.23 Frisker Detector HV = 700 Vdc:(249243) IThreshold Voltage = 50 mVdc [Detector cable type/length = 59 / 6 ft.

Print/Signature of Surveyor: Je ty9, uk 0, , l Date: 1)6 -2t -

-( ~/c/ (~J Comments:

,I A'ý I Review By:!nq!A Al- Date: ZIaR/,'

Storage Port Exterior Survey Report

-Survey NO.: hA DATE: 6-Jan-09 LOCATION: Port# 48 TIME: 13:45 Smear Information dpm Frlsklng Probe Model # 44-1 Serial # PR2419243 El 50.5 E, 0.25 Frisking Probe Efficiency 0.12625 I Min BKG: 1. r71 29 3.1-Avg. BKG:F Lc Gross CPM:F= Lc Net CPM: =

LD Gross CPM:I-= Lo Net CPM: l Static Count CMCPM DPMV No. (Gross)(e) __ _____

1 Static 1 39 6 <MDA 2 Static 2 48 15 <MDA 3 ___________ _______

4 __________

5 ______ _______

6 __________ ______ _______

7 ___________

8 ______

9 ___________ ______ _______

10 _________

11 ________

12 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

13 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14 _ _ _ _ _ _ _ _ _ _____

15 _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _

16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

17. _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _

18 _ _ _ _ _ _ _ _ _ _____

291_ _ _ _ _ _ _ _ _ __ _ _ _ _ I__ _ _ _ _ _ __ _ _ _ _ _

2

• NOTE: All counts are I minute static counts post-decon of the O/S portion end of each port. Refer to initial port survey report for pre-decon contamination results. Smear taken post-decon was <MDA. Portend'is free released up to plane of wall.

Instrument Serial Number Cal. Due Date Efficiency Background (CPM) MDA (DPM)

• ' L-2221:14,4-1 218597 /249243 9-Dec-09 0.502, 33 '196

] 2d=138 p=0.5 t(sec) 3 395 Tenelec Series 5 j 2161 28-Jul09 13 17.41 a = 17.25 P = 1.33 a= 0.00 3 23.00 a = 5.23 LFnisker Detector HV = 700 Vdc (249243) iThreshold.Voltage = 50 mVdc Detector cable type/length = 59 /6 ft.

Print/Signature of Surveyor: cJ ViJr 1" 4A* Date:>Z.

Comments:

J A iA Review By:C4-"_? A L- Date;

Storage Port Exterior Survey Report Survey NO.: NA DATE: 6-Jan-09 LOCATION: Port # 49 TIME: 13:25 Smear Information dpm Frisking Probe Model # 44-1 Serial # PR249243 50.5,.

5i 0.25 Friskinig Probe Efficiency 0.12625 I Min BKG: 3. 291 Avg. BKG:r" j Lc Gross CPM:F Lc Net CPM: I L1 Gross CPM:* LD Net CPM:I N/J Static Count CPM CPM DPM No. (Gross) (Net) 1 Static 1 41 12 <cMDA 2 Static 2 46 17 <MDA 3

4 5

6 7

8 . .

9 10 11 12 13 14 15 16

'17 "191111 20FIIII

,*NOTE: All counts'are Iminute static countsvpost-decon of the O/S portion end of each port; Refer to initial port survey report for pre-decon contamination results. Smear taken post-decon Was <MDA. *Port end is free released up to plane of wall, Instrument Serial Number Col. Due Date Efficiency Background (CPM) MDA (DPM)

L-2221 /.41 2185971/249243 "9-Dec,09 0.502 29 186 d'138 p=0.:5 t,(saec) 3 372

ýTenelec ýseries 5 2161 2.8-Jul-09 [1= 17.41 a- 1-7.25 [ft= 1.33 a =0.00 1=323400 ýo = 5M2 V~risker Oeteetor'HV = 00 Vdc (249243) IfThr eshold Voltage = 50 mVdc IDetector cable type/ .length = 59/16 ft.

Print/Signature of Surveyor: Terry 0*';1. / "d ... $ Date:  %*. ,;n5, --0" Comments:

1 - . A I Review By: .6(i / k " Date:"

Storage Port Exterior Survey Report Survey NO.: NA DATE: 23-Dec-08 LOCATION: Port # 50 TIME: 13:30 Smear Information d pm Frisking Probe Model # 44-1 Serial # PR249243 El 50:5 Es 0.25 FriskingProbe Efficiency 0.12625 1MinBKG: 1 a 3.l 42 Avg. BKG:-

Lc Gross CPM:[ Lc Net CPM:I Lo Gross CPM:l"NIA LI Net CPM:I N/A Static Count CPM CPM DPMI t No. (Gross) (Net) 1 Static 1 45 9 <MDA I

2 Static 2 50 14 <MDA 3 Static 3 393 <MDA 4 _ _ _ _ __ _ _

5 ___________ _______

6 __________ ______ _______ _______

7 ___________ _______ ________ ________

8 ___________ ______ _______ _______

.9 __ _ _ _ _ ___ _ _ _

10 _ _ _ _ _ _ _ _ _____ ______

11 _____________ ________ _________ _________

12 _________ _____________

17 _________

lb181 _ __ _ _ _ _____________

191_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

201 ______ _______ _______

1_________

• NOTE: All counts are I minute static counts post-decoh of the O/S portion end of each port. Refer to initiai port survey report for pre-decon contamination results. Smear takeh post-decon Was <MDA. Port end is free released up to plane of wall.

Instrument Serial Number Cal. Due Date lEfficiency Background (CPM) MDA.(DPM)

L-2221 / 4421 218597 / 249243 9-Dec-09 0.502 36 205 p05 j-d0138 t (sec) 3 417 Tenelec Series 5 2161 28-Jul-09 13_ 17.41 d = 17.25 P = 1.33 a0:00 P. 23.00 6= 5.23 1Frisker Detector HV- 700 Vdc (249243) Threshold Voltage = 50 mVdc [Detectorucable type/length = 59 / 6 ft.

Print/SignatureofSurveyor: 'JL7v S'tid*r /(§ /j4* 3" Date:

/ C/ V ComnfnentS:

J I Review By: OUA , ----- Date- 2/2j? // a.

Sample Report Batch ID: Smears - 200901121728 Count Date: 1/12/2009 5:28:10PM Group: B Count Minutes: 3.00 Device: S5-XLB Count Mode: Simultaneous Batch Key: 233 Operating Volts: 1440 Selected Swipe/Smear Efficiency (%)

Alpha: 17.25 +/- 0.12 Beta: 17.41 +/- .0.05 Sample ID Sample Type Alpha Uric Alpha MDA Beta Unc Beta MDA (dpm). Ldpm) (drIM)2 (dprn)

Unloaded Swipe LCS 7.73 3.86 5.23 -1.91 5.07 23:00 Tc-99 Ebedine Standard LCS 27.05 7.23 5.23 1455.8.19 172.37 23.00 th-230 Eberline Standard LCS 13851.28 189.21 5.23 2812.46 74.04 23.00 20090112173951-B1 Unknown 0.00 0.00 5.23 -1.91 .5.07 23.00 20090112174311-B2 Unknown 0.00 0.00 5.23 3.83 6.05 23.00 20090112174621-B3 Unknown 0.00 0.00 5.23 0.00 5.42 23.00 20090112174941-84 Unknown 0.00 0.00 5.23 1.91 5.74 23.00 20090112175301-85 Unknown 1.93 1.93 5.23 -1.91 5.07 23.00 20090112175611-B6 Unknown 0.00 0.00 5.213 0.00 5.42 23.00 200901112175931-B7 Unknown 1.93 1.93 5.23 1.91 5.74 23.00 20090112180251-B8 Unknown 3.86 2.73 5.23 5.74 6.35 23.00 20090112180611-89 Unknown 1.93 1.93 5.23 7.66 6.63 23.00 20090112180921-B10 Unknown 0.00 0.00 5.23 3.83 .6.05 23.00 20090112181241-Bll Unknown 3.86 2.73 5.23 0.00 5.42 23.00 20090112181601-B12 Unknown 0.00 0.00 5.23 -1.91 5.07 23.00 20090112181911-813 Unknown 0.00 0.00 5.23 -5.74 4.28. 23.00 20090112182231-814 Unknown 0.00 0.00 5.23 -5.74 4.28 23.00 20090112182551-B15 Unknown 0.00 0.00 5.23 5174 6.35 23.00 20090112182911-B16 Unknown 0.00 0.00 5.23 5.74 6.35 23.00 20090112183221-B17 Unknown 0.00 0.00 5.23 -3.83 4.69 23.00 20090112183541-$18 Unknown 0.00 0.00 5.23 0.00 5.42 23.00 20090112183901-B19 Unknown 0.00 0.00 5.23 7.66 6.63 23.00 200901121842117820 Unknown 0.00 0.00 5.23 -3.83 4.69 23.00 20090112184531-821 Unknown 0.00 0.00 5.23 -1.91 5.07 23.00 20090112184851-B22 Unknown 0.00 0.00 5.23 1.91 5.74 23.00 20090112185211-B23 Unknown 0.00 0.00 5.23 9.57 6.90 23.00 20090112185521-B24 Unknown 0.00 0.00 5.23 1.1.49 7.16 23.00 20090112185841-125 Unknown 0.00 0.00 5.23 15.32 7.66 23.00 Unloaded Swipe Background Alpha (cpm): 0.00 Beta (cpm): 1.33 Unloaded Sw!pe LCS 1:93 .1.93 5:23 1.91. 5.74 23.00 Reviewed by: .1,L ,2f) " l .

/m nPage of 1i Print Daie 1/13/2009 CA\Pr'gram Files\Tennelec SystemnsVEclipse~sample report.rpt Print Time 7:2 :O0AM

Background Report Batch ID: Smears -20090112"1728 Count Date: 1/12/2009 5:28:10PM Group: B Count Minutes: 3.00 Device: S5-XLB Count Mode: Simultaneous Batch Key: 233 Operating Volts: 1440 Selected Swipe/Smear Background (cpm)

Alpha Rate: 0.00 + 0.00 Beta Rate: 133 +/- 0.67 Sample ID Alpha Unc Beta Unc Guard 20090112172810-B141 1.33 0.67 1.00 0.58 217.67 20090112173311-B149 4.67 1.25 2,536.00 29:07 205.67 2009011217363i-B150 2,389.67 28.22 491.00 12.79 213.33 20090112173951-B1 0.00 0.00 1.;00 0.58 197.00 20090112174311-B2 0.00 0100 2.00 0.82 222.67 20090112174621-B3 0.00 0.00 1.33 0.67 213;67 20090112174941-84 0.00 0.00 0o75 1.67 210.67 20090112175301-15 0.33 0.33 1.00 0.58 217.33 20090112175611-86 0.00 0.00 1.33 0.67 213.00 20090112175931-B7 0.33 1.67 0.75 213.67

.0.33 20090112180251-B8 0 67 0.47 2.33 0.88 216.33 20090112180611-B9 0.33 0.33 2.67 0.94 206.00 20090112180921-B10 0.00 0.00 2.00 0.82 217.00 200901!2181241-B11 0.67 0.47 1.33 0.67 200.00 20090112181601-B12 0.00 0.00 1I.00 0.58 209.67 20090112181911-B13 0.00 0.00 0.33 0.33 226.33 20090112182231-114 0.00 0.00 0.33 0.33 209.67 20090112182551-815 0.00 0.00 2.33 0.88 218.67 20090112182911 816 0.00 0.00 2.33 0.88 229.33 20090112183221-817 0.00 0.00 0.67 0.47 197.33 20090112183541-B18 0.00 0.00 1.33 0.67 221.00 20090112183901-B19 0.00 0.00 2.67 0.94 207.33 20090112184211-820 0.00 0.00 0.67 0.47 218.00 20090112184531-B21 0.00 0.00 1.00 0.58 214.67 20090112184851ýB22 0.00 0.00 1.67 0.75 194.00 20090112185211-B23 0.00 0.00 3.00 1.00 209.00 20090112185521-B24 0.00 0.60 3.33 1.05 210.67 20090112185841-B25 0.00 0.00 4.00  !,15 219.00.

20090112190201-B143 0.00 0.00 1.33 0.67 202.67 2009011219051-8147 0.33 0.33 1.67 0.75 216.00 Guard Avg Rate: 21,2.24 Reviewed by ~-~---

Page 1 of 1. Priiht Date 1113/2009 C:\Program Files\Tennelec Systems\Eclipse\background report.rpt :Print Timeh 7:20:52AM

Plocedure: Preselected Report Reporting Units W IsActive Preselected Group &Device: Background Subtraction Court Mode FNone []None Disable ( Enable SAlpha ( Apha then Beta Sample Court Do*ay r Previous Stored ro Method Blan*

• Sirimaneow 0.1 mute8 (0 to 9.999 minutes)

Discmir*oa Selecion Spilove, Conection Alphadeta ROI:

ITc-99 3.5%0.8% , Court Repetitions r* Disable (- Enable Beta Lower. Beta Upper: Apha Lower: Sample: 7 - 11-99)

Sarmple Activ Io. - 1W.3 I7*5

- Diable , Enable Batck [ (1-10)

Ak6a Cal Standard: jAn-241 47 mm FiJ Beta Cal Standard ITc-99 47 mm Filt Weak Sa-ple Reject 6eometry Selection (o- Disable C"Enable Cout" Time: F3 frinute: Genetry. S,*,/Sme j,-

Io coszib Initial Tea Time: F Beta Po courts Min Court Rate:

SaveA:

ro P t

)-Sl)

F6 r I 5b

/ -ta-07

APPENDIX G UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

Radiological Survey Report DATE LnfO LOCATI ON.Survey NOp TIME:'00 Smear Information iJA _______Survey Map Beta/ Alpha Gamma (

3,--

6 7

10 J4 15 16

.W _ _

17 10 iLegend: * =Contact;#!,# = Contact Reading / General Area: # General. A. ( = Smrnear location; A -AirSample.

Note: Readlings in mi-em/hr unless~noted otherwise.

lnstrument Serial Number' Cal. Due Date Efficiency Background (CPM) MDA.(DPM) 4,\ o0 to1,7i,3 zs., 1AAl . .. " ..

Frisker Detector HV = Vdc IThreshold Voltage = mVdc IN-Detector cable length ii

-ft.

Print/Sig-nature of Surveyor:j&,,..j./- waJj2Iufez Date: ___

Comments: iŽ i A4 1 y Review t r e.At 4 Date:' *-

Equivalent to HP-1O1, Re.v.5, Attach~ment, 1 Retention: LPa-io

APPENDIX H UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

G A MM A S , E C T R U M A N A L Y S S Yilename: C: \GENIE2K\CAMFILES\Det 264\StoragePortExcavation\UM-2009 Report Generated On  : 2/16/2012 5:13:27 PM Sample Title UM-2009-04-24-01 Sample Description Concrete ground from north cut f Sample Identification 2009-04-24-01 Sample Type concrete Sample Geometry 500 ml Nalgene Peak Locate Threshold 3.00 Peak Locate Range (in channels) 39 - 8192 Peak Area Range (in channels) 47 - 8192 Identification Energy Tolerance 0.750 FWHM Sample Size  : 6.OOOE+002 g Sample Taken On  : 2/24/2009 3:00:00 PM hcquisition Started  : 2/7/2012 4:05:55 PM Live Time 50000.0 seconds Real Time 50005.0 seconds Dead Time 0.01 %

Energy Calibration Used Done On 2/16/2012 Efficiency Calibration Used Done On' 2/5/2012 Efficiency ID 500ml 2.0 g/cc 0" 4A 773 e-)- f6-'

1:00tL,

>Juclide MDA Report I 2/16/2012 5: .13PM Page 1

• • • • • N UC L IDE M DA R E P ORT

• Detector Name: HPGE Sample Geometry: 500 ml Nalgene Sample

Title:

UM-2009-04-24-01 Nuclide Library Used: C:\GENIE2K\CAMFILES\Libraries\SoilDCGL_

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uCi/g BE-7 477.60 10.52 3. 0238E-001 3. 02E-001 2.8237E-002

+ K-40 1460.83* 10.67 3.2978E-007 3:. 30E-007 7 .4985E-006 MN-54 834.85 99.98 3.7205E-007 3. 72E-007 1.0129E-007

+ CO-60 1173 ,24* 99.97 5.8372E-008 5.84E-008 4.3962E-009 995.99 5. 9717E-008 5. 6344E-008 1332. 50*

ZN- 65 1115.55. 50.660 2.2101E-006 2.21E-006 -'l."088E-007 NB-94x 702.62 97.90 3.0977E-008 3'.10E-008 -1. 7010E-008 871.09 99.90 3.3103E-008 2.8596E-008 AG-108m 21.10 59.10 2. 9021E-007 2. 90E-008 -4.2206E-008 231. 80 9.60 1.1000E-006 3. 7623E-008 79.13 8.76 3.0715E-007 -1. 2767E-007 433.94 90.50 2.9036E-008 I.1123E-008 614.28 89.87 5.8451E-008 -8. 9361E-009 722.91 90.80 3.8 '072E-008 -5.5848E-009 CD-109 22 .10 85.20 8.2472E-007 8.25E-007 -3.6121E-007 25.02 16.81 2.6144E-006 -7.5823E-007 88.03 3.61 3 .1183E-006 2.8567E-007 AG- 10m 446.81 3.:72 1. 2919E-005 61.13E-007 5.8616 -006 2.79 1,9121IE-005 -1. 4550E-005 620.36 657.76 94.00 6.1270E-007 2. 0481E-007 677.62 10.28 5.5135E-006 -2.,1508E-006 687.02 6. 39 9.,3357E-006 6.0910E-006 706. 68 16,.33 3.7046E-006 2.9949E-006 744.28 4.70 .,2706E-005 6. 6709E-006 763.94 22.14 3.1887E-006 -2.27.00E-006 818.03 7.34 8.5823E-006 2. 4817E-006 884.68 72.70 8.796.8E-007 1.0407E-007 937.49 34.36 2.1135E-006 1.6964E-006 1384.30 24ý.28 2. 8403E-006 -2.8642E-0,07 T475.79 3~.99 1'.4517E-005 -1.3200 E-006 1505.04 13.04 5.2799E-006 -4. 02655E-007 1562.30 1.03 5.7636E-005 2-3703E'-,005 SB- 12 5 176.33 6.79 6.3825E-007 1.86E-007 -2.0701E-007 380.43 1. 52 3.3788E-006 -2.3257E-006 427.89 29; 40 1.8592E-007 -8.1883E-oo08 463.38 10 .45 5.4579E- 007 7.4082E-007 600.56 17 .78 3.4983E-007 1.2418E-008 606.64 5.02 2.4829E-006 -7.2793E-008 635.90 11.32 5.0898E-0'0.7 -3.8281E-009 671.41 1.80 3.2759E-006 -3.0495E-006 BA-133 53..16 !2.20 1.1860E-006 7. 88E-008 6 1883E-007 79.62 2. 62 1.,2292E-0 06 -5 1558E-Q007

guclide MDA Report 2/16/2012 5,:' 13 PM Page 2 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) M%) (uCi/g ) (uCi/g (uCi/g BA-133 81.00 34.10 7.8831E-008 7. 88E-008 -3.9516E-008 160.61 0.'64 3.7204E-006 -8.9237E-008 223.23 0.45 6.0509E-006 1.0282E-006 276.40 7.16 3.8953E-007 1. 5544E-007 I 302.85 18.33 1.6075E-007 1.3201E-007 356.02 62.005 7.9624E-008 -1.2952E-008 383 . 85 8.94 3.3550E-007 -2.7235E-007 CS-134 475.35 1.46 4.4711E-006 1. 05E"007 2.5662E-006 563.23 8.38 8.9872E-007 1.4368E-0Q7 569.32 15.43 4.7562E-007 5.6590E-008 604.70 97.60 1.4184E7007 -1. 8281E-008 795.84 85.40 1.0511E-007 6.5436E-008 801.93 8.73 9.7931E-007 4.3651E-007 10388.57 1.00 "9.2355E-006 -1.4515E-006 1167.94 1.80 642161E-006 -1. 7210E-906 1365.15 3.04 2.8191E-606 6.4870E-'007 CS-137 661.66 85.2.1 3.8032E-008 3. 80E-0o8 1. 99.34E-008 CE-139 165.85 79.89 2.6052E-008 2. 61E-008 -3. 2693E-010

+ EU-152x 121.78* 28.40 7.2633E-008 7. 26E- 008 8. 5815E-008 244.70* 7.49 3.0332E-007 5. 1063E-008 344.28* 26.60 8.2604E-008 8.2042E-008 411.11 2.23 1..3423E-006 3. 7311E-007 443.98 2.78 9..9661E-007 -2.2806E-007 778.90 12.96 2.7508E-007 -8.2245E-009 867.39 4 .15 9.3557E-007 1.0848E-007 964.13 14.34 3.6014E-007 5.9676E-008 1085.91 9.92 4.3500E-007 1.4024E-007 1089.70 1.71 2..5341E-0'06 3 .724.5E-007 1112.12 131.55 3,.2576E-007 -1.9859E-009 21i2 .95 .1.40 3,3727E-006 1 .6737E-006

'1299.12 1.63 2.5226E-006 9 . *149E-008 1408.01* 20.87 1.1873E-007 2. 4679E-007 EU-154 123.07 40.40 5.8266E-008 5. 83E-008 5. 8094E-008 1-88.25 0.23 1.4017E-005 -5.0999E-0o06 247.93 6.83 4. 1.19E-007 2.7898E-008 401.30 0.19 1.6072E-005 -9.9571E-006 444.39 0.55 5.4894E-006 -2.0581E-00.6 478.26 0..21 1. 4817E-005 -2,0735E-006 557.56 0.25 1. 3557E-005 4. 0431E-006 582.00 0.89 5.41581E-006 1.6515E-005 5911.76 4.491 6.93ý97E-007 -3.1158E-007 625.22 0.32 1.0818E-005 3. 8836E-007 676.5.9 0.14 2.6160E-005 -1. 5677E-005 692.42 1.78 2.0895E-006 -1 1498E-006 715.76 0.17 2.2879E-005 1. 0072E-005 722.30 20.00 2.1599E-007 -2. 0578E-009 756.86 4.50 8.61766E-007 -6. 7063E-008 815.55 0.50 7..9101E-006 -3 .3062E-006 845.39 0.58 6.6414E-006 -1. 9085E-007 850.64 0.23 1. 7313E-005 1.3369E-005 873 .20 12.0.9 3.4367E-007 1.3553E-007

quclide MDA Report 2/16/2012 5: "13 PM Page 3 Nuclide Energy) Yield Line MDA Nuclide MDA Activity Name (key) (%) c(uCi/g ) (uci/g 1 (uCi/g EU-154 89.2- 73 0.50 8.4607E-006 5. 83E-008 2. 9'852E-0,06 904,.'05 0.85 4.9222E-006 -3.8-438E9-00.6 996.30 10.34 4.3746E-007 -1. 993E- 007 1004.76 17.90 2.5585E-007

4. 1773E-008 1128.40 0.29 1.5780E-005 -8.1276E-006 1140.90 0.22 2.0837E-005 -8..,9336E-00.'6 1241.60 0.13 4.8046E-005 -7.9671E-006 1246.60 ,0.80 5.9038E-006 -4.7195E-006 12,74.51 34.40 1. 2941E-007 -7.3095E-008 1494.,08 0.71 5.7687E-006. 4.4402E-007 1596.45 i 80 2 .3964E-006 -4.1291E-007

+ TL-208B 72.80 2.02 1.5742E-006 5. 5.OE-008 8. 0762E-008

74. 97* 3.41 1.2160E-006 3.4242E-006 84.90 277.36 1 .51 1.8101E-006 1 .0951E-006 6.31 4,4674E-007 2. 8983E-007.

510.77" 22.60 3 , 0421E-0017 3.9585E-007 58.3.19* 84. 50 5.5003E-008 1.4500E00,7 763.13 1.81 2.3043E-Q06 -2.135:3E-006 8601. 56'* 12.42 4.0579E-007 1.6762E-007 261,4.53 99.16 8.3734E"008 2.3516E-007

+ Pb-210 4 6. 52,* 4 . 05 7. 6428E-007 7. 64E-007 1.2997E-006

+

PB-2,12B 74.81* 10. 50 3. 491E-qo7 1. 54E-007 1, 1121E-006 77.11* 1,7.6.0 12 . 60 2.3351E-007 1 .0611E-&006

5. 9477E-007 87.30* 7.90 2.9*624E-007

-238.63* 43.660 1.5368E-007 4.:9668E-007 300.09

• 3.34 6.3681E-007 5.1091E-007

+ BI-214B 609 .31* 44.80 1*.1250E-007 1. 12E-007 I.1332E-006 1.,29 66.5..45 2. 843)6E 00.6 1,.8892E-006 768..36* 4.8.0 7. 6886E-007 7 .2145E-007 806:. 17 1.12 3..5813E-006 4..3837E-006 934.06* 3.03 1.4667E-006 7 .:5853E-007 112 0. 29*

2 14. 80G 4.277-5E-007 1..0248E-006 1155.-19 1.64 2 .9536E-006 1. 5538E-006 1.52:87E-00.6 1238. 11*t 5.86 8. 0533E,007 128.0..96* 3. 92 1.44, 3.0451E-006 3 ."1718E-006 1377.67* 3.9,2 .2..0322E-006 1.3195E-006 140.1. 50* 1.55 2.66183E-006 1.24,98E-006 1407.98* 2.80 ,9.3357E-007 1.9406E-006 1509ý. 23 2.1.2 2 . 104'6E006 1.1105E-006 1661.2,8 1.1 3 650ý0E-bb06' -9. 82o0E-00o8 1729.59* 2 .88 1. 7145E-006 9,7237E:-007 1764.49* 15.36 2. 9063E-007 1.2331E-006 1847.42* 2.04 1.0027E-006 I1.7854E-006 2118.55*, 1.14 1.4220E-006 2 .98'66E-00,6 4.86 2204.21 1. 0202E-006 1 .2169E-006 2447.:86 1.50 2.9615.E-006 2i.89 41E-006

+ PB-214B 53.23* 2.3899E-0Q06 1.31E-007 61.1958E-'007 74.81* 5.910 7-.0280E-007 1. 9791E-006 77 . 11* 9.90 4.1513E-007 1.8864E -006 87.30* 4.41 5.3069E-007 1.0655E-006 2 41.98 7.50 8. 7664E-007 '1.5907E'-006

\Iuclide MDA Report 2/16/2012 5:Ro -13 PM Page 4 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uCi/g

+ PB-214B 295.21* 18.50 2. 0020E-007 1. 31E-007 1.2695E-006 351.92* 35.80 1.3081E-007 1.1792E-006

+ RA-226 186. 10* 3.50 7. 1912E-007 7. 19E-007 1.6436E-006

+ AC-228B 12.95 15.10 2. 0842E-007 1. 96E-0,07 0.OOOOE+000 16.15 20.00 2. 5069E-006 7 6400E-006 19.11 4.60 7. 0440E-0,06 3.4197E-005 89.96* 3.40 1. 1582E-006 6.2816E-007 93.35* 5.60 7.6131E-007 1. 0898E-006 99.55 1.30 1. 6663E-006 -1. 8988E-007 105.36 2.00 1. 0916E-006 -5. 6032E-007 129.03* 2.90 5. 9468E-007 5. 3074E-007 209 .39* 4.10 6. 9177E-007 5. 6981E-007 270.26* 3.80 9. 7025E-007 1. 7062E-006 328. 07* 3.50 9.0526E-007 7.9729E-007 338.42* 12.40 2. 5904E-007 5.8412E-007 409.62 2.20 1. 4270E-006 2.3282E-007 463.10* 4.60 \7.3494E-007 8. 7265E-007 562.65 i.Ol 3.3,551E-006 -1. 2755E-006 755.28 1.32 2. 8325E-006 6.5265E-008 772.28 1.09 3.99 58E- 006 -1.2434E-006 7-94 79* 4.660 9 .0227 E-007 1. 4130E-006 835.60 1 .71 2. 43 6-E- 006 1.0529E-006 911. 16* 29.00 1.,9637E-007 4.44613E-007 91.5092E- 007 964.64 5.80 3,0068E-007 968 97* 17.40 3. 0238E-007 3.7422E-007 1459.19 1.06 1.2,019E-005 9.4817E-005 1496 .00 1.05 3. 7125E-006 -2.3071E-006 1588.23 3. 60 1.2495E-006 8.5727E-007 1630.47 1.95 1. 8751E-006 2..8073E-007 PA-.234B 63 .00 3.20 8. 703o6E-o07 9. 45E-O08 1.1614E-006 94.67 14.30 1. 8379E-007 -6.6375E-008 98.44 23.00 9. 4517E-008 1.7385E-008 99.70 4.80 4..5318E-007 1.4763E-007 11.00 10.80 2..0783E-007 -1.4722E-008 125 .40 2.00

-2 .260lE-0o6 -5;3145E-007, 131.20 20.00 1. 1753E-007 5.1874E-008 152.70 6.70 3.5868E-007 i.1431E-007 186.00 2.00 1.5,645E-006 4.7542E-006 200.90 1.00 2..663,9E-006 -3.0975E-008 202.90 1.20 2.2191E-006 -3.1264E-007 226.40 5.90 4. 6867E-007 6. 1141E-008 227.220 5.50 5. 0196E-007 -2.4374E-007 248.90 2.80 9. 5020E-007 -7.,9629E-008 272.10 1.00 3.,0663E-0.06 -4.:2847E-007 293.70 3.90 1. 0713E-006 1.7151E-009 369.80 2.90 9.-9836E-007 -4.6059E-007 372.40 1.30 21.2495E-006 -2.7169E-007

1. 7249E-067 458.80 i.50 2. 0759E-006 506.80 1.60 3 . 0191E-0:06 -2.044,8E-00'6 513.70 1.30 3.9086E-006 -2.1919E-007 565.90 '1.40 2.4542E-0Q06 1.2850E-006

\Tuclide MDA Report 2/16/2012" 5:,: ,13 PM Page 5 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (kev) (%M (uCi/g ) (uCi/g (uCi/g PA-234B 568.70 3.30 1.0152E-006 9. 45E-008 2. 8251E-007 569.50 10.00 3.3214E-007 6. 1554E-008 574.00 2.00 1.6077E-006 -1.2991E-006 664.80 1.30 2.8518E-006 1 .7045E-006 666.70 1; 60 2.2316E-006 -7.2171E-007 669.90 1.40 2. 5222E-006 1. 666E-oo6 692.70 1.5.0 2..4138E-006 -1. 6946E-007 699.00 4.60 8.1634E-007, 4. 0541E-007 706.10 3. 10 1.1946E-006 3 .1546E-007 733.00 9.00 4.2152E-007 1.3331E-007 738.00 1.00 3.5663E-006 3. 1910E-008 742 .81 2.140 1'.5084E-006 -4. 0973E-007 755.60 1.40 2 .6643E-006 3.2781E-007 780.70 1 .10 3.6 079E-006 1. 6533E-006 786.27 1.40 2.7699E-006 -7.4167E-007 793.60 1.50 2.7595E-006 3.7125E-006 796.30 3.80 1.0711E-006 6.2056E-008 805.80 3.30 1 2055E-006 1.1891E-006 819.60 2.60 1.5065E-006 -1.3913E-007 826.30 4.00 9.8258E-007 2.1059E-007 831.60 5.50 7.3214E-007 -1. 6540E-007 876.40 4.00 9.6031E-007 -5.7628E-007 880.50 4.00 9.4959E-007 -3.6541E-008 880.51 9.00 4.2204E-007 -1.6241E-008 883.24 15.00 2.5255E-007 -3.6833E-008 899.00 4.10 1.0078E-006 2.6378E-007 925.00 2.90 1.4239E-006 6.0873E-007 926.00 11.00 3.7798E-007 9. 0370E-008 927.10 11.00 3.7718E-007 -4.6172E-007 946.00 1'2. 00 3.4466E-007 -4.9891E-008 949.00 8..00 5.23 87E-007 -4. 0844E-008 978.80 1.40 2.9640E-006 5. 8799E-007 980.50 2.00 2.0775E-006 4.2875E-007 980.50 3 . 00 1.3850E-006 2.8583E-007 984.00 1.90 2.2035E-006 -7. 0030E-007 1353.30 1 3.0 70 2.1771E-006 --7 542E-007 1394.10 1.2357E-006 -5. 5449E-007 1452.70 1.00 4.6547E-'006 -5.0377E-006 1668.50 1.20 2.:9992E-006 5..2892E-007 1694. 60 1.20 2.6785E-006 1.5344E-006 TH-234 63 .29 4.50 1,.4863E+007 1. 49E+007 2.073'5E+007 92.38 2.60 2.5777E+007 1. 1490E+008 92.80 2.60 2.5596E+007 1. 0897E+008 U-235 0o.11!

+ 72.70 2..3570E-005 4.37.E-008 1.2092E-006 89 .95* 2 .8,0 1..1461E-006 6.2164E-007 93.35* 4.50 7.7212E-007 1.1053E-006 94.00 0.40 5.4278E-006 -5.4716E-007 105.00 2.10 8.4662E-007 -2.4922E-007 109.16 1.50 1.2132E-006 -1. 4208E-007 140.76 0.22 8.6649E-006 -6.3840E-007 143 .76* 1o.90 2.3775E-007 1.6431E-007

/

Yluclide MDA Report 2/16/2012 5:( '13 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%). (uCi/g ) (uCi/g (uCi/g

+ U-235 163.33 5.00 4. 1311E-007 4.37E-008 7.1838E-008 182.61 0.40 6. 0901E-006 1.5608E-007 185.71* 57.50 4. 3717E-008 9.9919E-008 194.94 0.59 3 .6157E-006 -6.0892E-007 202.11 1 .00 2. 1629E-006 -4.7616E.-007 205.31* 5.00 4. 7894E-007 1.7975E-007 279.50 0.27 8.4534E-006 -2.4896E7006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = MDA value not calculated

@ = Half-life too short to be able to perform the decay correction

APPENDIX I UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

G A MMA S E C T R U M A N A L Y I S Filename: C:\GENIE2K\CAMFILES\Det 264\StoragePortExcavation\UM-2009 Report Generated On  : 2/16/2012 4:18:35 PM Sample Title UM-2009-03-25-02 Sample Description Soil sample from behind West sup Sample Identification 2009-03-25-02 Sample Type soil Sample Geometry 500 ml Nalgene Peak Locate Threshold 3.00 Peak Locate Range (in channels) 39 - 8192 Peak Area Range (in channels) 47 - 8192 Identification Energy Tolerance 0.750 FWHM Sample Size  : 1.000E+003 g Sample Taken On  : 3/25/2009 3:00:00 PM kcquisition Started  : 2/8/2012 7:31:14 PM Live Time 50000.0 seconds Real Time 50005.3 seconds Dead Time 0.01 %

Energy Calibration Used Done On 2/8/2012 Efficiency Calibration Used Done On 2/5/2012 Efficiency ID 500ml 2.0 g/cc C-If --/SL- ,ýOA5-,l c/k 49'04-I

,,juclideMDA Report 2/16/2012 4: '17 27 PM Page I N U C L I.D E M D A R E P 0 R T Detector Name: HPGE Sample Geometry: 500 ml Nalgene Sample

Title:

UM-2009-03-25-02 Nuclide Library Used: C:\GENIE2K\CAMFILES\Libraries\SoilDCGL_

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g ) (uCi/g (uCi/g BE-7 477.60 10.52 1.6456E-001 i.65E-001 1. 0882E-001

+ K-40 1460. 83* 10.67 3.1760E-007 3.18E-007 1. 0858E-005 MN-54 834.85 99.98 2.4037E-007 2. 40E-007 1. 6465E-008 CO-60 1173 .24 99.97 4.4321E-008 3. 70E-008 3. 1633E-008 1332. 50 99.99 3.6979E-008 1. 8919E-008 ZN-65 1115.55 50.610 1.4069E-006 1.41E-006 5. 2555E-007 NB-94x 702. 62 97.90 2 2608E-008 2. 26E-008 -i.0627E-008 871. 09 99.90 2. 3648E-008 1. 8787E-008 AG-108m 21 .10 59.10 1.9731E-007 1. 96E-008 3. 4438E-009 23'.80 9.60 7. 7467E-007 -4. 7816E-007 79-.13 8.76 2. 1390E-007 -3.5145E-008 433.94 90.50 1. 9616E-008 7. 2955E-009 614.28 89.87 3. 6118E-008 -5.4458E-009 722.91 90.80 2.6608E-008 CD-109 22.10 85.20 5.4719E-007 5. 47E-007 -1. 4555E-007 25.02 16.81 1.7679E-006 -4. 7782E-007 88.03 3.61 2.1691E-006 2. 0459E-006 AG- 11 Om 446.81 3.72 8.5387E-006 3. 82E-0007 -6. 4813E-007 620.36 .2.79 1.2880E-005 -1. 1860 E-005 657.76 94.00 3.8215E-007 677. 62 10.28 3,.6133E-006 -3. 3784E-007 687.02 6.39 6.2502E-006 2. 8184E-007 706. 68 16.33 2.4534E-006 4. 2788E-007 744.28 4.70 8, 4115E-006 3. 3779E-006 763 .94 22 .14 2. 0195E-006 -9. 1750E-007 818.03 7.i34 5..2690E-006 -1. 755.3E-006 884 .68 72.70 5.8,287E-007 ý5. 0385E-008 937.49 3,4.36 1.3261E-006 -2. 8503E-007 138.4.30 24.2'8 1.8113E-006 -1,. 0060E-006 1475.79 3.99 8.2:625E-006 1. 0959E-006 1505.04 13.04 3.0801E-006 3. 09-56E-007 1562.30 1. 03 2.9368E-005 1. 5026E-005 SB-125 176. 3:3 6.79 4.5856E-007 1. 23E-007 -2. 2914E-008 380.43 1.52 2..3359E-006 1.,3939E-006 427.89 29.40 1.2257E-007 3. 1802E"008 463.38 10.45 3. 7626E-007 5.0984E-007 600.56 17.78 2. 3678E-007 1. 3155E-007 606.64 5.502 1. 5158E-006 1. 0431E-005 635.90 11.32 3 .6155E-007 3.3139E-007 671.41 1.80 2.2683E-006 2.4419E-007 BA-133 53.16 2.20 8. 9274E-007 5. 36E-008 2.6670E-007 79;62 2.62 8. 5:178E-007- "1.4123E-007

,ýuclide MbA Report i A2/16/2012 4:7 27 PM *Page 2 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (uCi/g A,) (uCi/g ) (uCi/g

(%)

BA-133 81.00 34.10 5.7807E-0'08 5.36E-( )08 -I. 0824E-,008 160.61 0.64 2.8696E-006 4. 2189E-006 223.23 0.45 4.3390E-006 -3.3091E-006 276.40 7.16 2.7894E-007 8. 5359E-009 302.85 18.33 1.1607E-007 1. 1813E-008 356.02 62.05 5..3555E-008 -1.6372E-007 383.85 8.94 2. 2898E-007 -2.0086E-007

+ CS-134 475.35 1.46 3.3991E-006 5.23E-C108 -3.9913E-007 563.23 8.38 6.0952E-007 -7. 2275E-008 569.32 15.43 3.3739E-007 1. 6637E-007 604-.70* 97.60 5.5194E-008 1i.4989E-008 795. 84* 85.40 5.2280E-0'08 4,4372E-008 801.93 8.73 7.0044E-0.07 -5. 4224E-007 1038 .57 1.00 6.7490E-006 -7.,9711E-007 1167.94 1.80 4.2469E-006 -2. 6214E-006 1365. 15* 3 .04 1.4234E-006 3. 1159E-007 CS-137 661. 66 85.21 2.5861E-008 2 . 59E-( )08 -1.3351E-008 CE-139 165.85 79.89 1.8967E-008 1.90E-( )08 3.7266E-009

+ EU-152x 121 .78* 28.40 5.2888E-008 5.29E-( )08 5.2165E-008 244.70 7.49 2.8808E-007 -1.,9642E-007 344.28* 26.60 5.7823E-008 4. 0024E-008 411.11 2.23 9.6437E-007 5.,5213E-007 443.98 2.78 7. 2525E-007 -1. 6170E-007 778. 90 12.96 2. 0089E-007 5. 8606E- 000 867 .39 4.15 6. 4664E-007 -7. 0299E-008 964. 13* 14.34 3 .2956E-007 i.9433E-007 1085 .91 9.92 3. 1585E-007 -1. 5211E-007 1089 .70 1.71 1. 8703E-006 -9.44,96E-008 1112 .12 13 .55 2.4456E-007 . 27:94E-008 1212 . 95 1;40 21.7002E-006 1. 39'33 E-006 1299.12 1.63 1. 9402E-006 I.0649E-b006 1,408.. 01* 20.87 9. 5'03,5E-008 1. 659oE-oo7 EU-154 123.07 40.40 4.4047E-008 4.40E-( )08 4,.0526E-008 188;.25 0.23 9.7103E-006 -2.0107E-006 247. 93 6.83 2.9200E-007 -4. 8052E-007 401.30 0.19 1.1. 678E-005 -2 6578E-006 444.39 0.5,5 3.9730-0.06 6:.517 OE-006 4178.-26 0.21 1.1576E-005 557.56 0.25 9.3724E-006 -6. 524,1E-006 582.,00 0.89 3.9237E-0'06 1.552 1E-005 591. 76 4.91 4. 8753E-007 -3. 0548E"007 625!22 0.32 7. 7846E-006 -5. 2081E-008 676.59 0.14 1 .8846E-005 1 4567 E-.0 05 692.42 1.78 1.5915E-006 8.4011E-007 715.76 0.17 1.5699E-005 3. 3660E-006 722.30 20.00 1. 4674E-007 -1.0853E-007 756.86 4.50 6. 0252E-007 -1.1843E-008 815.55 0.50 5.3237E-006 1.30 15E-006 845.39 0.58 4. 9127E-006 1.1991E-006 850.64 0.23 1. 2719E-005 6. 1022E-006 873.20 12.09 2. 4410E-007 -8.9822E-008

,Juclide MDA Report 2/16/2012 4:2

. I 27 I PM Page 3 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keY) (%,) (uCi/g ) (uCi/g (uCi/g EU-154 892 .73 0.50 51.9369E-006 4.40E-008 -3..9812E-006 904 .05 0.85 3.6303E-006 7.5720E-007 996.30 10.34 3.1409E-007 -5.2863E-008 1004.76 17.90 1.8011E-007 1.1868E-007 1128.40 0.29 1.2238E-005 2. 5642E-006 1140.90 0.22 1.6436E-005 -6. 5126E-006 1241 .60.

0.13 3. 6399E-005 -1 0478E-005 1246.60 0.80 5. 0657E-006 -5. 5569E-006 1274.51 34.40 1. 0241E-007 -1. 8171E-008 1494.08 0.71 3 .4519E-006 -5. 1743E-007 1596.45 1.80 1. 6311E-006 -5. 4889E-007

+ TL-208B 72 80 2.02 1. 1090E-006 2. 87E-008 -1. 6946E-007 74;97* 3.41 8. 6269E-007 1. 9967E-006 84.90 1 ,51 i..2944E-006 1. 7831E7006 277.36 6.31 3.1700E-007 2. 8927E-008 510. 77* 22.60 1.6905E-007 2.4420E-007 583.19* .84.50 3.3663E-008 1.3488E-007 763.13 1. 81 1.5876E-006 -8.4405E-007 860.56* 12.42 2. 1580E-007 3.5145E-007 2614. 53* 99.16 2.88733E-008 1.3636E-007

+ Pb-210 46. 52* 4.05 5.5777E-007 5. 58E-007 9.9170E-007

+ PB-212B 10.50 2.8017E-007 74.81* 7. 92E-008 6.4845E-007

77. 11* 17.-60 1.6617E-007 6.6986E-007 87.30* 7 .'9,0 1.9957E-007 4.1504E-007 238 .63* 43.60 7.9198E-Q08

5. 9844E-007 4.1724E-007 300 .09* 3.34 3.9201E-007

+ BI-214B 609 .31* 44.80 7.1392E-008 7.14E-008 6.7005E-007 665.45* 1.29 2.4325E-006 8.3065E-007 768. 36*

4.80 5.9,498E-007 6.7654E-007 806. 17* 1.12 2 .3089E-006 1.7023E-006 934. 06* 3 ý03 9.9556E-007 9.,9021E-007 1120. 29* 14.80 3,2186E-007 7.,7439E-007 1155.19 1.64 2..2033E-006 -1.9795E-006 1238.11* 5.86 7.003OE-007 1.0434E-006 1280.96 1.44 2.3370E-006 -3.,8142E-007 1377.67 3.92 7. 6579E-007 -2.7056E-007 1401.50 1.55 1 1. 9213E-006 -3.1845E-007 1407.98* 2.80 7.,4626E-007 1;3027E-006 1509.23* 2.12 1. 1704E-006 8. 6018E-Q07 1661.28* 1 . 14 2.2138E-006 -*8.2237E-008 1729. 59* 2- 88 7.8428E-007 1.1796E-006 1764 49* 15.36 2.5293E-007 6. 2268E-007 1847.42* .2.04 1.1:579E-006 1. 1I47E-006 2118. 55* 1.14 1.7I55E-006 1.2161E-006 2204 21* 4.86 4'. 3,741E-007 1.2394E-006 2447.86 1.,50 1.6636E-006 9.5891E-007

+ PB-214B 53 .23* i1.11 1.47 91E-006 6.88E-008 7.4841E-007

74. 81* 5.90 4.9861E-007 1.1540E-006 77.11

• 9.90 2.9541E-007 1ý1909E-006 87.30* 4.41 3. 5750E-007 7.'4349E7007 241. 98* 7.50 4.3887E-007 9. 9044E-007

s7uclideMDA Report ( 2/16/2012 4:'7 27 PM Page 4 Nuclide Energy Yield Line MDA Nuclide MDA ActiVity Name (keV) (%) (uCi/g ) (UCi/g (uCi/g

+ PB-214B 295.21* 18.50 1.4388E-007 6. 88E-008 7.0992E-007 351.92* 35.80 6.8828E-008 6.9362E-007

+ RA-226 18.6.10* 3.50 5.8424E-007 5. 84E-007 1.1772E-006

+ AC-228B 12.95 15.10 1.2439E-007 1. 24E-007 0.O000E+00 16.15 20.00 1 .6790E-006 5.,9664E-006 191.11 4.60 4. 7754E-006 2.8416E-005 89.96* 3.40 4. 7443E-007 2.8156E-007 93 35* 5.60 3 .1238E-007 4.1891E-007 99.55 1.30 1. 2654E-006 6.1971E-008 105.36 2.00 8. 0505E-007 -6.4090E-007 129. 03* 2.90 5. 1759E-007 1.9787E-007 209.39* 4.10 3.8404E-007 3.4966E-007 270.26* 3.80 4. 4207E-007 4.2689E-007 328. 07* 3,5Q 5. 0172E-007 2.9218E-007 338. 42* 12.40 2. 0369E-007 3.5388E-007, 409 .62 2.20 1. 0431E-006 4.9016E-007 463 .10* 4.60 4. 3969E-007 4*.9870E-007 562 .65 1.01 2. 3373E-006 -4.8701E-008 755.28 1.32 1. 9926E-006 3.4770E-007 772.28 1.09 2. 7787E-006 -1.6951E-006 794 79* 4.60 4. 5063E-007 3.8247E-007 835.60 1.71 i. 6.578E-006 -1. 5997E-007 911. 16* 29.00 1. 2384E-007 3.'6938E-007 964. 64* 5.80 8.5840E-007 5.0618E-007 968 97* 17.40 2 .9849E-007 4.1.13 6E-007 1459.19 1.06 1. 0954E-005 1.3648E-004 1496.00 1.05 2. 3240E-0.06 .6 956.E-007 1588.23* 3.60 7.3820 E-007 7.4033E-007 1630.47 1.95 1. 2707E-006 -1.2856E-009 PA-234B 63.00 3.20 6.5526E-007 7.21E-008 7.5600E-007 94.67 14.30 1.3:077E-007 1.9657E-007 98.44 231. 00 7.2108E-008 -5.6487E-008 99.70 14.80 3.412164E.-007 -8.151!5E- b008 Iii.00 10.80 1.5421E-007 9. 76i1E-008 125.40 1.00 1.6968E-006 -1.1982Eý-007 131.20 20.00 8.6539E-008 7.4436E-008, 152.70 6.70 2. 6419E-007 2.7261E-007 186 .00 2.00 l. 0999E-006 4.A4341E-006 200.90 1.00 2.0015E-006 2.

91E-00.7 202.90 1.20 1.6.733E-006 -3. 8141E-007 226.40 5.90 3.4537E-007 1. 9175E-007 227.20 5.50 3. 7070E-007 1.9853E-007 248.90 2.80 6. 8903E-007 -3.8690E-007 272.10, 1. 00 2 ;00459E-006 1. 0987E-006 293.70 3 ;90 7. 1766E-007 3.16555E-006 1.,2002E-007 369.80 2.90 7. 1962E-007 372.40 1.30 1 .5727E-0.06 -7.0560E-007 458.80 1.50 1. 4812E-006 1.33,44E-007 506.80 1.60 1. 8958E-006 -5.5923E-007 513.70 1.30 2. 5046E-006 -2.2409E-007 565.90 1.40 1. 7269E-006 1.6773E-007

guclide MDA Report 2/16/2012 4:-, 27 PM Page 5

(

Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (keV) (%) (uCi/g (uCi/g (uCi/g PA-234B 568.70 3.30 7.3234E-007 7 .21E-008 5.6866E-008 569.50 10.00 2.4177E-007 1.1922E-007

.574 . 00 2.00 1.1876E-006 -1. 8042E-006 664.80 1.30 1.9532E-006 -5.1278E-007 666.70 1.60 1.5728E-006 1i.0091E-006 669.90 1.40 1 .7662E-006 -5.,0851E-008 692.70 1.50 1.8270E-006 .5.7135E-007 6999.00 4.60 5. 9248E-007 2.5955E-007 706.10 3 .10 8. 6171E-007 1.8698E-007 733.00 9 .00 3 .0143E-007 1.4113E-007 738.00 1.00 2. 5147E-006 -2.3615E-006 742.81 2.40 1.0934E-006 3. 0386E-007 755.60 1.40 1 8812E-006 2.8458E-007 780.70 1.10 2. 5166E-006 5.7929E-007 786.27 1.40 1.9096E-006 -2.3880E-006 793.60 1.50 1.9166E-006 1.1106E-006 796.30 3.80 7. 8208E-007 1..2383E-006 805.80 3.30 8. 2971E-007 -8.2459E-008 819.60 2.60 9. 9808E-007 9.:8931E-008 826.30 4.00 6.4387E-007 -8.'0917E-008 831;.60 5.50 4. 9043E-007 -1. 6702E-007 87-6.40 4.00 7. 2922E-007 3.3 6447E-007 880.50 4 .00 7.2378E-007 1.5370E-007 880.51 9 .00 3. 2168E-007 6.8312E-008 883.24 .15 .00 1. 9090E-007 9.7110E-008 899.00 4.10 7.4940E-007 6.8371E-007 925.00 2.90 1. 0194E-006 2. 4656E-007 926..00 11.00 2 .6327E-007 -1.5809E-008

,927.10 1.00 2 .7007E-007 7.'3471E-008 946. 00 12 .00 2. 5450E-007 2.4164E"007 949.0.0 8. 00 3 .7757E-007 4. 5851E-007 978.80 1.40 2 2.2406E-006 1.0624E-006 980.50 2.00 1. 5673E-006 9.7550E-007 980.50 3 .00 1.0448E-006 6.5033E-007 984.00 1.90 1..6338E-006 4.5651E-008 1353.30 1.70 1.5263E-006 -1.4107E-006 1394.10 3.00 8.4235E-007 -1.1945E-006 1452.70 1.00 3. 1833E-006 -1.10275E-005 1668 .50 1.20 1. 7071E-006 2. 5018E-007.

1694.60 1.20 1.7845E-006 8.7312E-008 TH-234 63.29 4. 50 5.0533E+006 5. 05E+006 4.9321E+006 92.38 2.60 8.2775E+006 3.4568E+007 92.80 2.60 8.2194E+006 3.1949E+007

+ U-235 72.70 0.11 1.6693E-005 3. 55E-008 -2..5506E-006 89.95* 2.80 4ý.7200E-007 2. 8012E-007 93.35* 4.50 3 . 1850E-007 4.2711E-007 94.00 0.40 3,.8695E-006 2.3803E-D006 105.00 2.10 6.2862E-007, -2.952E-'007, 109.16 1 ,5-0 8. 9941E-007 -6.7060E-008 140.76 0.022 6.4154E-006 4. 1898E -O 07 143.76* 10.90 1.3725E-007 -4.6871E-008

Sluclide MDA Report { 2/16/2012 4:7 27 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Name (key) (%) (uCi/g (uCi/g (uCi/g

+ U-235 163.33 5.00 3 .0016E-007 3.55E-008 -1.0624E-007 182.61 0.40 4. 2747E-006 7.2673E-008 185.71* 57.50 3 .5518E-008 7.1566E-008 194.94 0.59 2. 7465E-006 1.3752E-006 202.11 1.00 1. 6475E-006 -6.0269E-007 205.31 5.00 3 .3227E-007 -7.3465E-008 279.50 0.27 6. 0267E-006 1.6219E-006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

>= MDA value not calculated

@= Half-life too short to be able to perform the decay correction

APPENDIX J UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

University of Michigan Phoenix. Memorial Lab STANDARD LEVEL IV`.

REPORT OF ANALYSIS WORK ORDER #09-02104-0R March 3, 2009 EBERLINE ANALYTICAL OAK RIDGE LABORATORY OAK RIDGE, TN

~3M- 2OO~~b~O(o -Ok

TABLE OF CONTENTS SECTION DESCRIPTION PAGE I Chain Of Custody 004 II Sample Acknowledgement 008 III Case Narrative 011 IV Analytical Results Summary 014 V Analytical Standard 017 VI Quality Control Sample Results Summary 020 VII Laboratory Technician's Notes 025 VIII Analytical Data (Iron-55) 031 IX Analytical Data (Gamma Spectroscopy) 146 Last page 286 i/j..

(

EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD B E R L N E 0AK RIDG.E, TENNESSEE.37830 ERVIC:ES PHONE (865) 481-0683 FAX (865) 483-4621 EBS-OR-28435 March 3, 2009 Chris Becker University of Michigan Phoenix Memorial Lab 2301 Bonisteel Blvd.

Ann Arbor, MI 48109 CASE NARRATIVE Work Order # 09-02104-OR SAMPLE RECEIPT This work order contains four soil samples received 2/23/2009. These samples were analyzed for Iron-55 and by Gamma Spectroscopy.

CLENT ID LAB ID CLIENT ID LAB ID UM-2008-12-17-01 09-021 04-o4 UM-2009-02-06-03 09-02104-06 UM-2009-02-06-02 09-02.104-05 UM-2009-02-06-04 09-021 04-07 ANALYTICAL METHODS Iroýn- 5 5 was performed using EML Method E-Fe-01-O1 modified. Gamma Spectroscopy was performed using Method LANL ER-130 Modified.

ANALYTICAL RESULTS Conrbined Standard Uncertainto is reported at 2-sigma value.

IRON-55 A representative aliquot from each sample was placed into a Petri ge6metry container. Samples were,then counted on a planar low energy phton spectroscopy (LEPS) detector.

Samples demonstrated nonrdetect equivalent results for Iron-55 activity. Results for the Iron-55 method blank demonstrated ron-detect equivalent activity. Results for the Iron-55 replicate demonstrated a high relative percent difference;, however, normalized difference is within acceptable limits.for the analytical technique. ReSults for the Americium-241 Anid Cobalt-57 laboratory control sample demonstrated an acceptable percent recovery.

GAM4lMA SPECTROSCOPY Samples for Gamma Spectoscopy analysis were prepared by transferring a known mass/aliquot of each prepared and homogenized sample to a standard geometry container. Samples were counted on High Purity Germanium (HPGe) gamma ray detectors.

Paged I of 2

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ANALYTICAL RESULTS CONTINUED GAMMA SPECTROSCOPY continued Samples demonstrated non-detect equivalent results for Cerium-139, Cobalt-60, Cesium-134, Europium-152, Europium-154 and Manganese-54 activity. Results for the method blank demonstrated non-detect equivalent activity for all gamma-emitting radionuclides as reported. Results for the Cobalt-60, Cesium-134 and Europium-154 replicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Cobalt-60 and Cesium-137 laboratory control sample demonstrated an acceptable percent recovery.

CERTIFICATION OF ACCURACY I certify that this data report is in compliance with the terms and conditions of the Purchase Order, both technically and for completeness, for other than the conditions detailed above. Release of the data contained in this hard copy data package has been authorized by the cognizant project manager or his/her designee to be accurate as verified by the following signature.

Ma Laboratory Manake Date: 3/3/2009 Page. 2 of 2

Printed: 31312009 12:52 PM Page I of 2 R6porf To. Wor* OrderDetafl'.

Eberline Chrs Becker SDG:1 09-02104 An alytical Phoenix'Memoril Lab

'2301 Bonisteel Blvd.

PurchaseOrder, Analysis Category-f

_5000002634 ENVIRONMENTAL Final Report of Analysis An, Arbor, MI 48109.. " . ---

Sample Matrix:- SO Lab, Sample Client Sample Receipt I Analysis Batch Analyte Method Result CU CSU MDA Report ID Type ID Date Date 1 Date [ ID Unita 09-0210401 LCS jKNOWN 02124/0900:00 2/23200 2/24/2009 9-004 Ameum-241 EML Fe01-01 Modifed 3.73E+03 1.16E+02 p*plg 09-02104-01 LCS 1' KNOWN 0224109 00:00 2/23/2009 2124/2009 09-02104 Cobalt-57 EML Fe-.Ol-O Modified 1.16E+03 3.31E.+01 I pcig 09-02104-01 LCS , SPIKE 02124M0900:00 2 2 /109 22412009 09-02104 Americltmi-241 EML Fe-Ol-0t Modiftd 3.62E+03 4.35E402 4.36E0 4.I.0t PCtIg 09-02104-01 LCS I 0SPIKE 1 0400:00 2123r2009 2/24/2009 09-02104 'Cobalt-57 EML Fe-O"--

L Modified 1.33E+03 1.35E+02 1.35E*02 4.80E+00" pCi/g 09,02104-02 MBL jBLANK 02/24/09 00:00 2/23120091 2/24/2009 09-02104 Iron-fiS EML F"1 Modified 4.29E+00 8.18E+0T 8.18E400 9.13E-,00 ?CI/g-09".2104-03, 0U.11 UM-2008-12-1701 01/09/09.0:00 j 21232009 2124200.9 09-02104 lron-55 EML Fe-01-O1 Modified -7.20E-01 2.54E+00 j 2.64E+00-- *8E+00 UpC.g-og-0210D4-04 DO 008-12-.17-01 01/09/09 00:00 2 / 2 3 /2 0 0 9D 2/24/2009 09-021._ Iron-55 EML Fe-Ol-01 Modified -5.291-01 2.43E*00 243E+00 389E+00 PC 09-2104.05'T09-02-06-02

_02/11 /09 00:00 2t23/o0 2124/2009 09-02104 Irov-55o EML Fe-01 Modifled -1.46E+00 324E+00 3.87E000 p, 09-02104-06 I TR UL20N9-02K0"3 02/17/09W00:00 =223/2009 2/24/2009 09-02104 lron-55 EML FeR-1-01 Modified -3.85E-01 2.07tE42 2.07E-00 36:6E+00.

09-02104 Eroi-5 EML Fe-30 Modified -2.E-0 2 5E00 2.55E+00 I pCig 1*

4.1Ei LS KNWN 02124/09 00:00 2/231200 1"-2*412009 09-02104 Cob*anI-0 LANL ER-130 Modified 1.23E-02. 23.3E+00 , . pC1,.

09-02104-02 09-02104-01 L"U S KNOWN 02/041090000 ,2/23/2009 2 0 09-'02104 Cesiurn-137 LANL ER-130 Modified 7.64E-01 2.2215-00 pCl/g 09-02104-01 LCS SPIKE 02/241090)0:00 L2 23/209224/2009 09014 CobaIl-60 LALE-3 iid 1.305+02 6.04E+00 D.0E400 5.22E-01 1 'pC~g 09-02104-01 DL,_ P*IKE 02/24/09 00:00 I 21231200I 2/24/2009 09-02104 Cesaum-137 LANL ER-130 Modified e ".e+b 3-O 5. 2 4.71 E-01 p-1g 019-02104-02 -MDJL BLANK 02/124/0900:00' 2/23/2009- 2124/2009 0 L9-0 ed21, um-139 LANL ER-130 Modified -5.06E-03 1.76E-02. 1.76E-02 3.06E-02 p "

M.0902104-02 MB LANK 02/24/09,00:00 M~312009 V241242009. 09-ý02104 Cobalt-SOý LANL ER-130Modified -3.98E-03 I 36E0 .3-2 89-2t pCVg 0"-2104-02 MBL BLA.NK 02124/09)00:00 2/2312009 1 21241209 I09-02104 +Cesium-134 LANL ER-I 30 Modified 1.92E-02 3.02E-02 3.02E-02 560E-,02 C/

09-02104-02 MBL BLANK 02/24109 00:00 212/2009o 2124/2009 09-214 Europfuni-152 LANL ER-130 Modifiedý -4.75E-02 1.70E-01 1.70E-01 3.46E-01 pCVg OU9-2104-02 MBL I LAK02/409 00-00 2/23/2009 21412009 09-02104 Europium-154 LANL.ER-130,Modiffied -1.11E-02 8.11)Eo02 &.19E-02 I.88E-0l p01/9 09-02104-02 MDL BAK02/24/09 00:00 2/23/2009 12124/2009 09-02104 Manganese.54 LANL ER-130 Modified 1.42E 2.83E-02 I 2.83E-02 5.88E-02 p01g.

0"-2104-03 DUP UM-2008-12-17-01 061/09/000:00 212312009 21420 M14I CerftmA-39 LANLER-130Modiried -1.48E-02 2.BiE-02 2.8 1E-02 4.66E-02 p01/9 09-02104-03 DUP UM-2008-12-17-01 01/09/000:00 2/23/009 21241209 09-02104 Cobalt-SO LNL ER-130 Modifed 2.56E-02 3.I11E-02 1.11E-02 5.97E-02 p09/9 09-021040 DUP UM-2009-12-17-01 J 09-0214-03 DUP -

01/09/09 00;.00, 109900:00 Dim=0-1-10 2/23/2009 2/3/09 212/2009 2124/2009 09-02,104 09-02104 Ceslurn-I34 Europlum-152 LANL ER-1 30 Modified LANL ER-13 Modifie 1.33E-03

-8.92F-02 j2.08E-01 2.30E-02 2.30E-02 20E0 3.83E-02 1EQ P01/9 0/

09-210-03 DUP I.UM-2008-!2;17-01 0 /090900.00 2/2329 2/24/2009 09-02104 s uolm14 LANL ER-1 30 Modified 1.65E42 7.3-2 7.33E-0 1.36-01 I p~tig 09-02104,03 J U M2008-12-1 7-01 01/09109 0000 21320j14200-20IMangatiese-54 ,LANL ER-130 Modified j 2.06E-02 .1-2 27 -2j5250 C/

CU=Countlng Uncertalnty;CSU=Comblned Standard Uncertainty (2-sigma);MDA-Mirilmal Detected Actlvity;LCS=Labomtory Control Sample; MBL=Blank; DUP-Duplicate; TRGNormal Sample; DO-Duplicate Orig!qal B E RL-1 N E EBERLINE ANALYTICAL CORPORATION SERV'ICES 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 8651483-4621

• 1 P

Printed: 313/2009 12:52 PM Page 2 Of 2 Report To: Work OrderDetails:

Chris Becker SDG:J 09-02104 Analytical Phoenix Memorial Lab 2301 Bonisteel Blvd.

A aseO5000002634 Analysis Category: ENVIRONMENTAL Final Report of Analysis Ann Arbor, MI 48109 Sample Mebx:, SO Lab Sample Client Sample TReceipt, Analyasi Batch y Mthod / Re Cu S MD Rport ID Type ID Date Date I Date j ID I

• _ C. S - D-Units 09-02104-04 00 I UM-2008-12-17-01 01/09/09 00:00 223200 2/24/2009 09-02104 Cerium-139 LANL.ER-iS Modified 1.30E-02 2.78E-02 -0p 09-02104-04 DO UM-2008-i2-17-01 01/0910900:00 2*2 320 0 2/242009 09-021041 Cobalt-60 LANL ER-130 Modified 1:60E-03 2.77E-02 2.77E-02 5.04E-02 P.C9o 09-02104--04 DO-' UM-2008:12-17-01 01/09/0900:00 2/23/2009 2/24/2009 09-02104 Ceslum-134: LANL ER-130"Modified 5.21E-03 2;57E-02 2.-572-E2I 4.30E-02 pCi/g 09"02104-04 00 UMM.2008-12-17-01 01109/0900:00 2/23/2009 2/24/2009I 09-02104 Europium-152 LANLER-130Modified 219E-01 2:23E 2,23E0-01 3.17E-01 pC1/g 09-02104-04 DO-4 UM-2008-t2-17-0O 01/09/09,00:00 2)23/2009 2/24/2009 09-02104 EuMapeum-154 LANL ER-130 Modified 2.122-02 8.37E-02 8.37E-0 I pCI/

09-02104-04 0O9-02104-05 00 TRG 1 L/M-2012-17-0l UM-2009-02-06-02 01/09/09 00:00 02/11/0900.00 2123/2009 2/ 2 2

/2/2009' 9

09-2104 9014 Cru-3 ne-4 LANLER-130Modlfied, 2.14&-02 2.82E-02

.82.-0 .I Z 2.2- C...

09-02104-DS 09-02104-05 TRG I T211M0:0 UM-2009-02-06-02 02111/0900:00 2/23/2009 2/24/2009 2/24/2009 09-02104T 0-021-4 Cenum-139 -

Coblm-1O.

LANL ERA130 Modified LANL.ER-130IModified

-1.60E-02 7.64E 2.34E-02 3.1.E-02 2.34E-02 31GE-02 3.87E-02 6.51i-02 pCI.

pCI/

09-02104-05 TRG UM-2009.02-06-O2 02/11/090000 t 223/2009 2/24/2009 09-02104 Cesuim-134 LANL ER-130 Modified J .9E-02 3503E-02 3,03'E-02 -5.38E -pC1/a oa-o~iot-os O i -0?os-2 02/11/=00:0002123/2009 2/24/2009* 09-02104 Europlum-152 LANL ER-130 Modife .8120 .9-1 1120 3.58E-0l pCI/a O9-02104-05 TRG UM-2009-02-05-02 02/11/0900:00 I.2/23/2009 2/24/2009 09-02104t Europium-154: LANLER-130 Modified -7.99E-02 -- iOBE-0l 1.08E-01 1-*77E-01 1-pqi/g 09-02104-05 TRG UM-2009-02-06-02 02/11/0900:00 12123r2009 2/24/2009 09-02104.1 Manganese-54 LANLER-130 Modified, -2.30E-04 2.-0E.02- I 2"90E-02 5.36E-*02 pCI/

09-02104-06 TRG UM-2009-02-0-3 217/0900:00 2 4/ 09 0-02104 Cerium-139 LANL ER-130 Modified 1.25E-02 4.03E-02 4.03E-02 7.04E-02 p019 09-02104-06 TRG UM-2009-02-06-03 02117/090000 2/23/2009 V2/24/2009 09-02104 Cobalt-60 .LANL ER-130 Modified 7T07E-02 ,8.29E-02 8.29E-02 1.58E&01 pCl/g 09-02104-06 TRG UM-2009-02-06-03 02/17/0900:00 12/23/2009 2/24/2009.. 09-02104 Cesium-134 LANLER-1304Mofied 1.87F-02 6.21E-02 6.212-U j I.G2E-0-. i pCI/g 09-02104-08 TRG UM-2009-02-06-03 02/1710900:00 I 2/23/2009 2/24/2009 09-02104. Europium-152 ANL ER-130 Modified 9.04E-01 filE-01 5.11E-01 1.000+00 pCI/g 09-02104:06 TRG UM-2009-02-06-03 02/17109 00:0 2/23/2009 l 2/24)2009 09-02104 Europium-154 LANL ER-130 Modified -4.91E-02 1.61E-01 1.61-01 I 2.99E-O1 pC1/9 09-02104-0 TR lM200.-02-03--. 02/17/09 00 2 2 124_ 9 09-02104 Mang-anese-54 LANL ERA130 Modified 2.02E-02 -. 08o-02 o-T*T .i8i0-*-i -p0 09-02104;07 TRG . UM-2009-02-06-04 02/13/09.00:00 2/23/2009 2/24/2009 09-02104 Cedum-139 LAWL ER-130 Modified -1.17E-02 4.08E-02 4.08E'02 1 6.93E-02 pC/g.

09-02104-07 TRG I UM-2009-02-06-04 02/13/0900:00 2/23/2009 1 2/24/2009 09-02104 Cobalt-60 LANL ER-30 Modified -4.82E-02 8.182-02 .1 8.18E-02.

1 1.32E-01 pci/g.

09-02104-07 .TRG I UM-2009-02-0W-04 02/13/0900:00 2/23/2009 2/24/0*9 09-02104 Ceslum-134' LANL ER-130 Modified 7.58E-03 5.90E-02 5;90E-02 9.392-02 pCi/g T

09-2.0.0 "'To-C UM-2009 W0-4* 021309- 0:00 21231200. 2.24/2009 09-02104 I Europlum-152 LANL ER-130 Modified 3.87E-01 3.45E-01 3.45E-01 7"89E-01 pCI/a 09-02104-07 __G.I UM-2009.02-08-04 02/13/0900:00 I 2/23/2009 2 09-02104 1 Eurmplum-154 LANLER-130Modifled -6:13E03 11E1 1.81-p 09-02104-07 TRG[ UM-2009.02-06-04 02-13/0900:-0 2123/2009

- 0 2/2409 09-02104 j Manganese-54 ,LANL ER-130 Modified 5.79E-03 6.36E-2. 6.36E 02-- 1.13E-01 pCi/g, CU.Counting Uncertainty;C61UCombined Standard Uncertainty (2-ulgma);MDA.,MInimal Detected Actlvlty;LCS=Laboratory Control'Sample; MBL=Blank; DUP=oupllcate; TRGaNormal Sample; DOODupicate Original

=E.B ERLI N E EBERLINE ANALYTICAL CORPORATION S ERVIC.ES 601 SCARBORO ROAD OAK RIDGE, TN 57830 865/481-0683 FAX 865/485-4621

.Eberline Services Preliminary Data Report & Analytical Calculations Printed: 2/25/2009 10:05 AM Oak.Ridge Laboratory Page 1 of 1 Work Order: 09-02104-Fe055-1 Lab Sam *e Client ACdivlty J LSC LCS LCS RPD Sample Sample Counting

1. rcln Nuclide , 0ce tl~lao Identification nt Unitsow Results Error Estlnate MDA %R Knwndentilafitediqot Flag Flag Aliquot Ddentified Dlefin Iata

,01 AM-241 LCS LCS 'pci/g 3.GZE+03 4.35E*02 4.91E+00 3.73E*03 97.12 OK 02124/09 00:00 1.00E400 02124109 12:46 YES 01 CO-57 tCS LcS pcUg 1.33E+03 1.35E+02 4.80E+00 1.18E+03 112.24- OK 02/24109 00:00 t.00E400 02/24/09-12:48 YES 02 FE-55 "MBL BLANK .pclg 4.29E+00 S.ISE+00 9.13E+00 02/24/09 00:00 1.00E+00 021/24109 13:22 NO 03 FE455 DiJP UM-2008-12-17-01 pCi 9 -7.20E-01 2.54E+00 3.,86E+00 OK 01/09/09 00:00 2.97E+01 02124/09 14:22 NO 04 FE:55 00 UM-2008-1247101 pCI/g -5.29E-01 2.43E+00 3.89E+00 1 0109/09 00;00 2.97E401 02124/09 15M24 NO 05 FE.55 TRG UM-2009-02-06.02 ;pCI/g -1.46E+00 3.24E+00 3.87E+00 02/11109 00:00 3.05E+01 02/24109 18:30 NO 06 FE-55 - TRG UM.2009.0206.3 pciug -3.86E-01 2.07E+00 3.37E+00 02117/09 00:00 3.6IE401 02124/09 17:30 NO 07 FE;55 -TRO UM-2009-02-06-04 pCug -4.72E-01 2.55E+00 4.16E+00 02/13109 00:00 2.86E+01 02124/09 18:33 NO l;.,

Eberline Services; Preliminary Data Report & Analytical Calculations Printed: 2/25/2009 1:31 PM Oak Ridge Laboratory Page 1 of 1 Work Order: 09-02104-Gamma-1 rSample Clent Activty i fCS LmC I LCL R Sample L _a____Nu__d Defi Idtitlcatlon Units Known %R Fag Flag onat Aliquot Dale/rrin identified 01 CO-60 LCS LCS, pCI/g -1.30E+021 6.04E+00 5,22E-01 1.23+02 105.11 OK 02/24/09'00:00 1.00E+00 02124/09 14:5 YES 01 CS;137 LCS LCS pCIllg 6.16E+01 5.30E+00 4.71E-01 7.64E+01 108.89 OK 02/24/09 00:00 1.006+00 02/24109 14:56 YES 02 CE.139 MBL BLANK pCIIlg 5.06E-03 .176E-02 3,0E-02 02/24109 00:00 1.00E+00 02/24/09 14:37 NO 02 CO-60 MBL BLANK " pCl/g 43.98E-03 3.63E-02 6.692-02 02/24/09 00:00 1.002+00 02124109 14:37 NO ,.

02 CS-134 MBL. BLANK pCi/g 1.92E-02 3.02E-02 5.60E-02 '02124/09 00:00 1.0015+00 02124/0* 4:317 NO 02 EU-152 MSL BLANK PCU g -4.75E0.2 1.70E-01 3.45E-01 02/24/09 00:00 1.00E+00 02/24[09 14:37 NO 02 EU-154 MBL BLANK pCi/1 4-1A1E.02 8.19E-02 1.68E-01 02/24M09 00:00 1.00E+00 02124/09 14:37 NO 02 MN-S4 MBL BLANK p)CINg 1.42E-02 2.83E,-02 5.88E-02 .02124/09 00:00 1.0011+00 02/2416i 14:37 NO 03 CE-139 OUP UM.2008-12-17-01 pCI/g -1.48E-02 2.81E-02 4.60E-02 01/09109 00:00 7.17E+02 02/24/0912.'20 NO 03 CO-6o DUP UM-2008-!1217t01 pCI/g 2.56E-02 3.11E-02 5.97E-02 INV 01/09/09 00:00 7.17E+02 02/24109 15:28 NO 03 CS-134 DUP UM-2008-12-17-01 pCl/ 133E-03 2;30E-02 3.83E-02 INV 01/09/09 00:00 7.17E+02 02/24/09 15:28 03' EU-152 DUP UM-2008412-17-0t1 ýpcg -4.2202 '2.08E-01 3.14E-01 01/09109 00:00 7.17E+02 02/24109 15:25 NO 03! EU-154 DUP UM-2008-12117-0t pCI/g 1.65E-02 7.33E-02 11.36&01 OK 01/09/09 00:00 7.17E+02 02/24/09 15:28 NO 03 MN-S4 DUP UM-2008-12-17.-0I pCI0g 2.062.02, 2.712E42 5.222-02 01109109 00:00 7.17E+02 02)24/09 15:28 NO 04 CE-139 DO .UM-2008-.121i7-01 .pClg 1.30E-02 2.78E-02 4.83E202 01109109 00:00 7.17E+02 02/24/09 16:33 NO 04 CO-60 DO UM-2008-12-1741 pCI/g 1.60E-03 2.77E-02 5.04E-02 01109109 00:00 7.17E+02 02/24/09 16:33 NO 04 CS-134 DO UM-2008-12-17-01 pCI/g 5.21E03 2.57E-02 4.30E202 01109109 00:00 7.17E+02 02f24/09 16:33 NO 04 EU-152 DO UM;2008-12-17-01 PClg 2.19E41 2.23E-01 3.17E01 01109/09 00:00 7.17+E02 02124/09 16:33 NO 04 EU-154 DO UM-200$-i2-17-01. pCIlg 2.12E-02 8.37E-02 1.5,E01 01/09/09 00"00 7.172+02 02124/09 16:33 NO 04 MN-54 DO UM-2008-12-17-01 pCI/g 2.14E-02 2.82E-02 4.82E-02 01/09109 00:00 7.17E+02 02/24/09 16:33 YES 05 CE-139 TRG UM-2009-02-06-02 pCI1/ -1.60E-02 2.34E!02 3.-7E-21 02/11109 00:00 8.73E+02 02/24/09 18:27 NO 05 CO-Go TRG UM-200942-06-02 PCI/U 7.04E-02 3.19E-02 6.51E-02 02111/09 00:00 6.73E+02 02/24/09 15:27 YES 05 CS-134 TRO UM-2009-02-6.02 pC4/g 1.79E-02 3.03E-02 .5.9E.022 02/11/09 00:00 0.73E+02 02124/0918:27 NO-05 EU-152 TRG UM.20°942"06$'2 PCI/U 5.1OE-01 m1.12-01 3.583-01 02111109 00;00 6.73E+02 02/24109 15:27 YES

.05. EU-154 TRG UM-20094206,-02 pCI/g -7.99E-02 1'081-01 1.77E-01 02/11/09 00:00 6.7312+02 02/24/09 15:27 NO

,05 MN-54 TRG UM-2009-02-06-02 PCI/g 2.302E-04 2.90E-02 5.36E-02 02/11/09 00:00 6.732+02 02124/09 15:27 N ,-.

06 CE-139 TRG UM-2009-02-08-03 PCIl/g 1.25E42 4.03E-02 7t.04E-02 02117109 09:00 6.82F+02 02/24109 15:383 .

-06* CO040 TRG UM-2009-02-06-03 pCI/ 7.07E-02 8.29E-02 1.58E-01 02117109 00:00 6.82E+02 02/24/09 15:38 NO 06 CS-1ý4 TRG UM-2009424543 pCI/U 1.872-02 6.21E42 1.00E-01 02J17/09 00:00 .6.521+02 02124/09 15:30 . NO EU-152 TRO UM-2009-02-06-03 p.cio 0.04E-01 E;01 1.00E+00 02117/09 00:00 6.82E+02 02/24/09 15:31 NO 06- PCI/U 9.04241 5.1121 .0+0 06 EU-154 TRG; UM2009-02-0603 pCig -4.91E-02 1.61E-01 2 9912-1 02/17/09 00:00 6.82E+02 02/24/09 18:38 NO 0D6 MN-54o TRG' UM-?009.02-06-03 PCI/g 2.02E-02 ',6.0E-02 1.11E-01 02/17109 00:00 6.82E202 02/24/09 18:38 NO 07 CE-i39 TRGr U'-200942-06404 pC*I/ .1,17E-02 4;0.E-02 8.93E-02 02/13/09'00:00 6.61E+02 02124*09 16:39 NO 07 CO-60 TRG " UM-2009-02-06-.04 pCI/g -4.62E-02 8.16E02 1.322-01 0213109 00:00 6.SIE+02 02/24/09 16:39 'NO

'07, CS-134 TRG UM-2009-02-06-04 pCIWg 7.58-E03 5.90E-02. .39E;02 2/13/09 00:00 6.61E+02 02/24/09 16:39 NO 07 EU-152 TRO UM-20094..06.04-4 pC'19 3.72E41 3.46E201 7.19.41 .. 0/1/0100:00 ,6.04÷E+02 .01/V4/S00 16,i NO 07 I-EU-164 *TRG UM-2009402-08. 04 4-pCvg

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• 1 02/24/09 18:59 NO MN-54 TRG *04 pCv/g 5.79E;01 0,36E-02 1;1E-011 0OV13109 00:00 6,6112+02 02124109 1WW;0r NO 07 07 MNM54 THG0 2- 4 .920 .64 11210/3/90:0 6.1+2 0/4/91:9 N

APPENDIX K UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FINAL DISPOSITION OF THE STORAGE PORTS DATED: FEBRUARY 24, 2012 SUBMITTED: SEPTEMBER 18, 2012

N OA NE1z I S OAK RIDGE INSrTITUTE FKW SO0 AND EDUCATION June 1. 2009 Mr. Jeremy Tapp U.S. Nuclear Regulatory Commission Region III 2443 Warmnville Road lile, IL 60532-4351 ORISE CONTRACT NO. DE-ACO5-06OR23100

SUBJECT:

LETTER REPORT FOR ANALYTICAL RESULTS FOR TWO SOIL SAMPLES AND ONE CONCRETE SAMPLE FROM THE FORD REACTOR AT THE UNIVERSITY OF MICHIGAN, ANN ARBOR, MICHIGAN

[0000O02/20090021 (RFTA NO.09-001)

DCN: 1790-LR-01-0

Dear Mr. Tapp:

Thc Oak Ridge Institute for Science and Education (ORISE) received two soil samples and one concretc sample on March 26, 009. The samples were associated writh the Ford Reactor at the University of Michigan in Ann Arbor, Michigan. "l'he samples were analyzed by gamma spectroscopy for cobalt-60 with a requested detection limit of 0.4 pCi/g and for europium- 152 with a requested detection limit of 1.0 pCi/g. Tron-55(Fc-55) analysis was also requested with a detection limit of 1,000 pCi/g. The sample identifications are presented in Table I. the data for gamma spectroscopy are presented in Table 2, and the Fc-55 data are presented in Table 3. The pertinent procedure references are included with the respective data tables.

This letter report was delayed due to analytical problems associated with the Fe-55 analysis. We apologize for the delay, but we believe this was necessary to achieve more defensible analytical results.

ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.

My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.

Sincerely, Dale Condra, Manager lAboratory RDC:W\PI:bf Enclosures c T. Carter, NRC/FSME/DVMIP 7 J18 E'. Abelquist, ORLSIE T. Patterson, NRC/I"SII-ErT'-FN 8D42 T. Vitkus. ORISE W. Snell, NRC Region III File 1790 Disuibutioa approval and concurgrece: l 2'aNi%

Tcchnical Rcvkmw "LV Quiality Rcvkw I;-L Voice:- 865.241.3242 IFax. 865.241.3248 E-mail: Dale.Condra04 oratu.org

'),1k Rljý Ic J N ý'i71","ý1 I

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA FORD REACTOR UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN ORISE NRC Region I Cl Collection Sample ID Sample ID Time 1790S0001 UOM-09-1-01 3/25/2009 11:12 AM 1790S0002 UOM-09-1-02 3/25/2009 11"27 AM 1790M0001 UOM-09-1-03 3/25/2009 12:15 PM Ford RmcWo/Unemm" of Michiganm9-RO- 17W0LR-01-0

TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN SOIL AND CONCRETE SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 16 FORD REACTOR UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN Radionuclide Concentrations, TPUs, and ORISE NRC Region 111 MDs(pig Sample ID Sample ID Co-60 Eu-152 1790S0001 UOM-09-1-01 0.03 +/- 0 .0 3 b 0.03 0.02 +/- 0.01 0.03 1790S0002 UOM-0-9--02 0.01 +/- 0.02 , 0.03 0.06 _+ 0.02 , 0.04 1790M0001 UOM-09-1-03 0.04 +/- 0.03 , 0.05 0.08 +/- 0.03 , 0.06

,The MDCs are after the comma.

bUncertainties represent ihe 95% confidence level, based on total propagated uncertainties.

Ford Reactor/University of Michgan 179l0-MorV

TABLE 3 CONCENTRATIONS OF IRON-55 IN SOIL AND CONCRETE SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP16, REVISION 1; CP4, REVISION 3 FORD REACTOR UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN ORISE I4RC Region III Fe-55 Concentrations, Sample ID Sample ID TPUs, and MDCs*

Sample ID _ _SapeID (pCi/g wet weight) 1790S0001 UOM-09-1-01 0.3 + 1 .4 b , 2.4 1790S0002 UOM-09-1-02 0.7 + 1.4 , 2.4 1790M0001 UOM-09-1-03 0.7 + 1.3 2.3

'The MDCs are after the comma.

bUncertainties represent the 95% confidence level, based on total propagated uncertainties.

Ford Reactoi/University of Michigan  !*9*LR:0t-0