ML17129A323

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TSD-14-013, Rev. 0 - Zion Auxiliary Building End Sate Estimated Concrete Volumes Surface Areas and Source Terms
ML17129A323
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Site: Zion  File:ZionSolutions icon.png
Issue date: 12/16/2014
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ZionSolutions
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Office of Nuclear Reactor Regulation
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ML17129A311 List: ... further results
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ZS-2016-0022
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ZionSolutions, LLC.

Technical Support Document TSD 14-013 Zion Auxiliary Building End State Estimated Concrete Volumes, Surface Areas, and Source Terms Revision 0 Originator: _(signature on file) Date: 12/16/14 Harvey Farr Reviewer: (signature on file) Date: 12/05/14 Wade Adams Approval: (signature on file) Date: 12/17/14 Donald E. (Nick) Williams

TSD 14-013 Revision 0 Summary of Changes in this Revision:

  • Rev. 0 -Initial issuance.

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TSD 14-013 Revision 0 Table of Contents

1. PURPOSE ...................................................................................................................................... 6
2. DISCUSSION ................................................................................................................................ 6 2.1. Zion Auxiliary Building End State ..................................................................................6 2.2. Zion Core Sample Collection and Handling Method ......................................................8 2.3. Core Sample Processing and Analysis ..........................................................................10
3. CALCULATIONS ....................................................................................................................... 10 3.1. Concrete Surface Areas and Volumes ...........................................................................10 3.2. Summary of Auxiliary Building Core Sample Gamma Spectroscopy Results .............15 3.3. Evaluation of 542 Eberline Off-Site Laboratory Results .............................................25 3.4. Evaluation of 542 Scaling Factors and Source Terms .................................................26 3.5. Evaluation of Potential Removable Contamination Source Terms on Walls Above 3 Feet .................................................................................................................34 3.6. Source Term Estimate Based Upon Contact Dose Rates ..............................................35
4. CONCLUSION ............................................................................................................................ 37
5. REFERENCES ............................................................................................................................ 37
6. ATTACHMENTS ........................................................................................................................ 38 6.1. Attachment 1 - Auxiliary Building Concrete Core Sample Locations ..........................39 6.2. Attachment 2 - 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results .....................................................................................................40 6.3. Attachment 3 - Eberline Off-Site Laboratory Results ...................................................74 6.4. Attachment 4 - Eberline Off-Site Laboratory Decay Corrected Results .......................75 6.5. Attachment 5 - Eberline Off-Site Laboratory Decay Corrected Results .......................76 6.6. Attachment 6 - Radionuclide Emissions and Yields .....................................................78 6.7. Attachment 7 - Contact Dose Rate MicroShield Reports..............................................79 6.8. Attachment 8 - Contact Dose Rate Survey Results .......................................................89 Page 3 of 92

TSD 14-013 Revision 0 List of Tables Table 1 - Auxiliary Building Concrete Core Survey Units and Samples ............................................ 8 Table 2 - Auxiliary Building Estimated Floor Surface Areas and Volumes ..................................... 10 Table 3 - Estimate Auxiliary Building Wall Surface Areas and Volumes ........................................ 12 Table 4 - Floor Co-60 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 ................................................................................................................... 16 Table 5 - Floor Cs-137 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 ................................................................................................................... 18 Table 6 - Floor Cs-134 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 ................................................................................................................... 19 Table 7 - Summary of Auxiliary Building Floor Source Term Depth Profile ................................... 20 Table 8 - Wall Co-60 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 ................................................................................................................... 22 Table 9 - Wall Cs-137 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 ................................................................................................................... 23 Table 10 - Wall Cs-134 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 ................................................................................................................ 24 Table 11 - Summary of Estimated Auxiliary Building Wall and Floor Source Terms .................... 25 Table 12 - Ba-137m 32 - 37 keV Photon Energy/Intensity Data from NRC Radiological Toolbox V3.0 .............................................................................................. 25 Table 13 - Comparison of In-House and Eberline Co-60 and Cs-137 Results for Auxiliary 542' Floor/Wall Samples .................................................................................................. 27 Table 14 - Summary of Key Radionuclide Ratios for 542' Floor and Wall ...................................... 27 Table 15 - Summary of Aux Building 542' Floor Eberline Results ................................................... 30 Table 16 - Summary of Aux Building 542' Walls Eberline Results .................................................. 31 Table 17 - Estimated Auxiliary Building EL 542' Floor & Wall Source Terms Based Upon Eberline Sample Result Scaling Factors ................................................................ 32 Table 18 - Auxiliary Building July 1, 2018 Scaled Radionuclide Inventories Based on Positive Results ................................................................................................................ 33 Table 19 - Wall Surface Area Remaining With Removable Contamination Only ........................... 35 Table 20 - Source Term for 2 Inch Thick Disc Source ...................................................................... 35 Table 21 - Striated Source Modeled Source Terms and Dose Rates ................................................. 36 Table 22 - Summary of Attachment 8 Contact Survey Data and Estimated Concentrations ........... 36 Table 23 - Estimated Cs-137 Source Terms Based On Contact Dose Rates ..................................... 37 Page 4 of 92

TSD 14-013 Revision 0 Table of Figures Figure 1 - Top View Zion Auxiliary Building End State from Drawing M-7 ..................................... 7 Figure 2 - East West Side View of Auxiliary Building from Drawing M-9........................................ 7 Figure 3 - North South Side View of Auxiliary Building from Drawing M-11 .................................. 8 Figure 4 - Core Sample Puck Labeling ................................................................................................ 9 Figure 5 - Auxiliary Building Surface Area and Volume Sections ................................................... 11 Figure 6 - 574 6 Pipe Penetration Area Interior Dimensions ......................................................... 12 Figure 7 - 542' Pipe Penetration Area (Section 6) ............................................................................. 14 Figure 8 - East Wall Volume Calculation .......................................................................................... 14 Figure 9 - Example of Decay Corrected On-Site Gamma Spectroscopy Core Results in Attachment 2 ..................................................................................................................... 16 Figure 10 - Auxiliary Building Activity Profile at Depth ................................................................. 21 Page 5 of 92

TSD 14-013 Revision 0

1. PURPOSE This technical support document (TSD) estimates the volume of concrete below the 588 foot elevation remaining on site upon license termination for the Zion Auxiliary Building. The TSD also estimates the volume and surface area of potentially radioactively contaminated concrete.

One of the purposes of Site Characterization is to establish the radionuclide profiles for the various contaminated media which provide dose to the critical group. This TSD provides bounding estimates for the embedded concrete source terms in the Auxiliary Building below the 588 foot elevation. The source term estimates are based upon concrete cores collected from the 542' elevation concrete floor and wall. Cores were collected at locations exhibiting high contact dose rates and are therefore biased high. The purpose of the calculations is to provide a conservative bounding estimate of the initial source terms to aid in evaluating the potential dose consequences and guide remediation and final status survey (FSS) planning.

2. DISCUSSION 2.1. Zion Auxiliary Building End State Item 8.5 under Article VIII of the Exelon and ZionSolutions Asset Sale Agreement (1) states, Tenant shall, at its expense, remove all improvements.... located at the Premises as of the Lease Commencement Date to a minimum of three feet (3') below the expected finished grade following site restoration or as otherwise required by Law, Permits or Environmental Permits and, except as otherwise required by applicable Law, Permits or Environmental Permits, back-fill such areas...

Thus concrete structures 3 feet below grade may remain on-site if allowed by applicable laws and permits and as authorized by the U.S. Nuclear Regulatory Commission (NRC) for license termination in accordance with 10 CFR 20.1402.

Zion Nuclear Power Station Units 1 and 2 Amended Post-Shutdown Decommissioning Activities Report (2) states that, After the systems and components are removed and processed as described above, the remaining contaminated concrete and structural steel components will be decontaminated and/or removed. Contaminated concrete will be packaged and shipped to a low-level waste disposal facility. Remaining concrete will be decontaminated to meet the License Termination Plan (LTP) requirements for release of the site from NRC regulatory control.

The Auxiliary Building will have all interior walls and floors below 588' elevation removed except for any interior walls required for structural integrity. The end state will consist of two small portions of the 574' 6" elevation and the 542' elevation of the building as seen in Figure 1, Figure 2, and Figure 3. The top and side views show the end state exterior walls and floor area dimensions that are used to estimate the concrete volumes and source terms.

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TSD 14-013 Revision 0 Figure 1 - Top View Zion Auxiliary Building End State from Drawing M-7 Figure 2 - East West Side View of Auxiliary Building from Drawing M-9 Page 7 of 92

TSD 14-013 Revision 0 Figure 3 - North South Side View of Auxiliary Building from Drawing M-11 This document calculates the surface area and volume of Auxiliary Building end state concrete using information in the above figures.

2.2. Zion Core Sample Collection and Handling Method A series of core samples were collected at the 542' elevation in Auxiliary Building as shown in Attachment 1. This is the most commonly used concrete characterization method and is described in EPRI 1015502 (3)and NUREG/CR-5849 (4) The cores were obtained using characterization survey packages prepared and approved in accordance ZS-RP-107-001-001 (5). A survey package was prepared for each of the Auxiliary Building survey units as defined in the ComEd Zion Station Historical Site Assessment (HSA) (6). The survey units, characterization package identification, and description are provided in Table 1. A total of 20 cores were collected (17 floor and 3 wall).

Table 1 - Auxiliary Building Concrete Core Survey Units and Samples In-Number House Survey Characterization Survey Package of Gamma Off-Site Unit Identification Survey Unit Description Cores Spec Analysis Unit 1 A RHR Pump Room 542 Ft 1 1 1 05101 B105101C-Aux 542 1A RHR Pmp Auxiliary Building Unit 1 B RHR Pump Room 542 Ft 05102 B105102C-Aux 542 1B RHR Pmp Auxiliary Building Unit 2A RHR Pump Room 542 Ft 1 1 1 05103 B105103C-Aux 542 2A RHR Pmp Auxiliary Building Unit 2B RHR Pump Room 542 Ft 1 1 1 05104 B105104C-Aux 542 2B RHR Pmp Auxiliary Building Unit 1 Pipe Chase 542 Ft Auxiliary 1 1 05105 B105105C-Aux 542 U1 Pipe Tunnel Building Unit 2 Pipe Chase 542 Ft Auxiliary 2 2 05106 B105106C-Aux 542 U2 Pipe Tunnel Building Hold Up Tanks 542 Ft Auxiliary 1 1 05107 B105107C-Aux 542 HUT Cubicles Building 05108 B105108C-Aux 542 Central Area Central Area 542 Ft Auxiliary Building 4 4 2 05109 B105109C-Aux 542 South Area South Area 542 Ft Auxiliary Building 1 1 05110 B105110C-Aux 542 North Area North Area 542 Ft Auxiliary Building 2 2 Page 8 of 92

TSD 14-013 Revision 0 In-Number House Survey Characterization Survey Package of Gamma Off-Site Unit Identification Survey Unit Description Cores Spec Analysis 05111 B105111C-Aux 542 East Area West Area 542 Ft Auxiliary Building 2 2 Gas Decay Tanks 542 Ft Auxiliary 05112 B105112C-Aux 542 Gas Decay Tks Building Unit 1 Equipment Drain Collection Tank 3 3 1 05113 B105113C-Aux 542 U1 EDCT Rm 542 Ft Auxiliary Building Unit 2 Equipment Drain Collection Tank 1 1 05114 B105114C-Aux 542 U2 EDCT Rm 542 Ft Auxiliary Building B105115C-Aux 542 HUT Recirc HUT Recirculation and BAE Feed 05115 BAE Feed Pumps 542 Ft Auxiliary Building Aux Building Equipment Drain Tank 05116 B105116C-Aux 542 EDT and Pumps 542 Ft Auxiliary Building Aux Building Sump A 542 Ft Auxiliary 05117 B105117C-Aux 542 A Sump Building Aux Building Sump B 542 Ft Auxiliary 05118 B105118C-Aux 542 B Sump Building Total Cores 20 20 6 Core locations for the 542 foot elevation floors were selected by assessing physical and radiological conditions of the concrete. Locations with visual cues of previous leaks were targeted. Other locations were determined based upon contact dose rates or count rates using 100 cm2 ZnS(Ag) scintillation probes or open window ion chamber readings. The locations are therefore biased sample locations where indications of elevated activity were observed. This judgmental sampling approach ensured there was sufficient source term in the cores to achieve the sensitivities required to determine the radionuclide distributions of gamma emitters as well as hard to detect (HTD) radionuclides. However, it biased the nuclide concentration results high, making the subsequent source term estimates based on the core data very conservative and bounding.

The cores were obtained using a 3 inch bit at depths of 6 inches unless refusal was encountered due to piping or rebar. The B105107C core in the HUT Cubicles was 14 inches long.

Upon extraction each core top was labeled 0" and the bottom was labeled with the appropriate depth. The side of each core was labeled with the sample ID. The cores were then transported to the core processing area maintaining continuous custody or using a Figure 4 - Core Sample Puck Labeling Chain of Custody form.

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TSD 14-013 Revision 0 2.3. Core Sample Processing and Analysis Prior to processing, cores were wiped down and smear surveyed to ensure any activity identified was not from cross contamination. The cores were then sectioned into 1/2 inch pucks. Pucks were weighed and then counted on both sides (top and bottom) on the Zion Station intrinsic germanium gamma spectroscopy unit using an approved LABSOCS geometry. The gamma spectroscopy reports include the puck mass in grams. Due to concrete cracks and crumbling a few sections of some cores could not be made into pucks. These sections were not consistent with the sample geometry and were not counted leaving gaps in the depth profile.

In addition, the core processing date, when the pucks were made, was used on the gamma spectroscopy reports as the sample date rather than a common date or the date the core was obtained in the building. Although only longer lived radionuclides were anticipated to be present, the in-house gamma spectroscopy results were back decayed to the sample collection date recorded in the field logs of the survey package in order to ensure continuity across sample results. The top half inch puck of 6 out of the 20 cores was sent for off-site laboratory analysis for gamma emitters and HTD nuclides. The puck was powdered, mixed and then aliquots were used for the various analyses at the off-site laboratory. This was to ensure the results were representative of the overall radionuclide concentration in the puck.

3. CALCULATIONS 3.1. Concrete Surface Areas and Volumes The end states and relevant dimensions for the Auxiliary Building are depicted in Figure 1, Figure 2, and Figure 3. The Auxiliary Building surface areas and volumes were calculated by breaking the Auxiliary Building up into six sections (Figure 5) and by considering the sump walls to be part of the 542' elevation floor area since there is a potential for contamination outside the stainless steel liner.

The estimated floor surface areas and volumes are provided in Table 2. The estimated surface areas and volumes of the wall are provided in Table 3. The estimate void space below the water table at 579' elevation is 1.004E+06 ft3 or 28,422.6 m3 as provided in Table 2.

Table 2 - Auxiliary Building Estimated Floor Surface Areas and Volumes Void Space Void Space Below Below Concrete Concrete Water Water Fig. Length Width Volume Volume Table Table Sections 5# ft ft ft2 cm2 ft3 cm3 Height ft Volume ft3 Pipe Penetration Areas 574'6" 1 26 11.5 507 4.71E+05 2.87E+03 8.14E+07 4.5 2281.5 Hold-Up Tank Cubicles 2 29 84 2436 2.26E+06 1.38E+04 3.91E+08 37.5 91350.0 West Aux Bld 3 13.5 119.0 1606.7 1.49E+06 9.10E+03 2.58E+08 37 59448.8 Center 4 49.5 84 4158 3.86E+06 2.36E+04 6.67E+08 37 153846.0 East 5 65 262.8 17084 1.59E+07 9.68E+04 2.74E+09 37 632114.2 North and South Pipe Penetration 6 35.75 27 1658.5 1.54E+06 9.40E+03 2.66E+08 37 61364.5 Boric Acid Area Sump 9 26 234 2.17E+05 1.33E+03 3.75E+07 9 2106.0 Page 10 of 92

TSD 14-013 Revision 0 Void Space Void Space Below Below Concrete Concrete Water Water Fig. Length Width Volume Volume Table Table Sections 5# ft ft ft2 cm2 ft3 cm3 Height ft Volume ft3 Walls Waste Gas Decay Area Sump Walls 6 34 204 1.90E+05 1.16E+03 3.27E+07 6 1224.0 Total 27888 2.59E+07 1.58E+05 4.48E+09 1.004E+06 Figure 5 - Auxiliary Building Surface Area and Volume Sections Page 11 of 92

TSD 14-013 Revision 0 Table 3 - Estimate Auxiliary Building Wall Surface Areas and Volumes Est Est Volume Volume Wall Fig. Inside Contam Contam Height Length Thickness Volume Sections 5# Height Length ft2 ft2 cm2 ft ft ft ft3 Pipe Penetration Areas 9.62E+

574'6" 1 13.5 71.7 968.4 215.2 2.00E+05 19.2 34.17 3 1 02 Hold-Up Tank Cubicles 2.19E+

West 2 46.5 84 3906 3906 3.63E+06 52.17 84 5 04 Hold-Up Tank Cubicles 1.06E+

North and South 2 46.5 58 2697 2697 2.51E+06 52.17 68 3 04 1.60E+

West Aux Bld 3 46 97.0 4462 291 2.70E+05 51.67 103 3 04 Center and North and 2.17E+

South Pipe Penetration 4, 6 46 137.2 6309.7 411.5 3.82E+05 51.67 140.2 3 04 1.68E+

East Aux North and South 5 46 254.8 11722 764.5 7.10E+05 51.67 270.8 3 05 East Aux East Wall TB 1.22E+

Common 5 46 262.8 12088 788.375 7.32E+05 51.67 262.8 5.0 12 05 3.62E+

Total 4.22E+04 9.07E+03 8.43E+06 Total 05 As seen in Figure 1 there is a portion of the Auxiliary Building on the 574 6 that does not have any rooms below them. These are a pipe Unit 1 and 2 pipe penetration area designated as 1 in Figure 5. The interior dimension used to calculate the floor and wall surface areas are shown in Figure 6.

Figure 6 - 574 6 Pipe Penetration Area Interior Dimensions The interior surface is 6 feet less than the 17 foot 6 inch dimension since the walls are 3 feet thick; similarly the interior wall is 26 feet long. The base of the right triangle formed at the northwest corner with containment is 11 feet 6 inches minus 8 feet or 3 feet 6 inches. The floor surface area is

( )

This equals 507 square feet for both the Unit 1 and Unit 2 penetrations areas. The volume of the floor is the surface area times the floor thickness of 5 feet 8 inches.

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TSD 14-013 Revision 0 The interior surface area height of the wall is 588 foot - 574.5 or 13.5 feet. The interior surface area is calculated as

( )

Since it is unlikely that the entire wall would have contamination sorbed at depth, it is assumed that embedded contamination of the walls is limited to the bottom 3 feet where they could have been in contact with standing water. The embedded contaminated area that will be applied to the wall core data is 215 square feet assuming a contaminated wall height of 3 feet. Any embedded source term above 3 feet would be negligible.

Since the volumes of the 17.5 foot wall and 26 foot wall are calculated as part of the 542 foot elevation walls, only the volume of the 8 foot long West wall section and the North wall section are calculated. The height of the wall for volume calculations is 13.5 feet plus the thickness of the floor 5 feet 8 inches. The 8 foot long West wall is 3 feet thick, the North wall which corresponds to the containment perimeter is one foot thick. The volumes are calculated as:

( ) ( )

As seen in Figure 2 the Hold-Up tank cubicle (Section 2) is at 541 ft 6, making the height of the wall to the 588 foot elevation 46.5 feet for the surface area calculation and 52.17 feet high for the volume calculation when the 5 foot 8 inch thick floor below it is included. The West wall is 5 feet thick and the north and south walls are 3 feet thick. Five feet on the West end of the North and South 29 foot long walls is added to the length for the volume calculations, making the total length 68 feet as seen in Table 3.

The West area of the Auxiliary Building (Section 3), has two 176 and one 136 wall on the north and south sections. The walls are three feet thick and the floor elevation is 542.

The Section 6 pipe penetration floor area consists of an 8 foot long west wall, an 329 north wall a 24 foot east wall and a 145 section of south wall as seen in Figure 7. As seen in Figure 1 the floor length is 359 with the east wall gone and 27 feet with the north wall removed.

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TSD 14-013 Revision 0 Figure 7 - 542' Pipe Penetration Area (Section 6)

The floor surface area is calculated as,

[( ) ]

The walls of Center and Pipe Penetration Areas (Sections 4 and 6) consist of the 139 north and south walls of the center section and the 11, 265 and 175 walls of the pipe penetrations areas, which equal a total length of 137.2 feet. The interior surface area height is 46 feet. The volume calculation height includes the 58 thick floor and is 51.67 feet.

The East section 5 wall, consist two west walls 62 5 long each and north and south walls 65 feet long tat are three feet thick. The 26291/2east wall consists of 5 foot thick and 12 foot thick sections as seen in Figure 1. Each taper from 5 feet to 12 feet is approximately 5.64 feet long. The 12 foot thick section between the tapers is approximately 145.3 feet long. The volume can be calculated as a 5 foot thick section 262.8 feet long and a 7 foot thick section that is 1454 plus 58 or 151 feet long and 7 feet thick as shown in Figure 8.

Figure 8 - East Wall Volume Calculation The east wall volume is

( ) ( )

As seen in Table 3, there is an estimated contaminated surface area for the walls in addition to the overall surface areas calculated above. The HUT walls are assumed to be contaminated for the Page 14 of 92

TSD 14-013 Revision 0 entire height from the 588 to the 5416: elevation. The remaining walls are estimated to be contaminated to only 3 feet above the 542 floor as evidenced by the bathtub ring visible in the 542 walls of the Auxiliary Building. Wall surfaces above three feet would not have been subjected to standing water and are therefore expected to have minimal embedded contamination above three feet. The contaminated surface areas are used to estimate the embedded contamination in the walls from the core data.

3.2. Summary of Auxiliary Building Core Sample Gamma Spectroscopy Results There were 17 concrete core samples from the floors and three cores from the walls obtained as described in Sections 2.2 and 2.3 seen in Attachment 1. The on-site gamma spectroscopy results for the sectioned cores from the 542 foot elevations are provided in Attachment 2. In most instances, except for one core, only Co-60 and Cs-134 were identified by gamma spectroscopy. Two cores had no positively identified Co-60 and only two cores has positively identified Cs-134. As noted above, the core locations are biased to those with the greatest potential for high concentrations based upon their physical location (e.g., locations with visual evidence of past leaks) and exhibiting high contact dose rates. This biases the overall concentrations high and provides a bounding source term that over estimates the overall concentrations. To add another layer of conservatism, reported minimum detectable activities (MDAs) for Co-60, Cs-137 and Cs-134 were included in the results when the nuclide was not positively identified. The MDA values used are noted in bold italics.

Figure 9 is an example of the data table for each core contained in Attachment 2. The results were also decay corrected to a common date of January 1, 2013. The gamma spectroscopy analysis used the date the core was sectioned into pucks as the sample taken on date. Thus the reported concentrations reflect the concentrations on that date. The actual sample date at which the core was collected is also provided in the summary of the data in Attachment 2.

As seen in Figure 9 there are two gamma spectroscopy results (top and bottom) for most of the sectioned pucks. The decay corrected top and bottom results are shown in the lower table. The concentration used for each 0.5 puck is the average of the top and bottom decay corrected results.

These averages are reported at the mid-point depth of each puck (e.g., 0.25, 0.75 inches, etc.).

Some Pucks were not counted because they were fractured in segments and thus did not fit the counting geometry. Similarly, there are some pucks for which only one side was counted due to a fracture. In those instances, the result for the side counted was used as the average concentration.

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TSD 14-013 Revision 0 Aux 542 North Area Core Collection Date 5/14/12 B105110-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13 0.34 0.02310 Core Count Decay Co-60 Cs-134 Cs-137 Section Depth wt (gms) Date Time Date Time time sec Days pCi/g pCi/g pCi/g Total pCi/g 0 7/11/12 917 7/9/12 13:40 1000 176 0.33 0.13 63.70 6.42E+01 Puck 1 129.0 0.5 7/11/12 936 7/9/12 13:41 1000 176 0.17 0.18 25.20 2.56E+01 0.5 10/24/12 1439 10/24/12 14:19 1000 69 0.03 0.10 0.19 3.26E-01 Puck 2 133.1 1 10/24/12 1456 10/24/12 14:19 1000 69 0.12 0.08 0.14 3.30E-01 1 10/24/12 1515 10/24/12 14:57 1000 69 0.03 0.11 0.15 2.95E-01 Puck 3 135.8 1.5 10/24/12 1532 10/24/12 14:57 1000 69 0.04 0.11 0.19 3.32E-01 B105110-CJFCCV-0022 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Core Decayed Decayed Decayed Puck Avg Puck Avg Puck Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.31 0.11 62.99 Puck 1 0.2 0.1 44.0 0.16 0.15 24.92 0.03 0.09 0.19 Puck 2 0.1 0.1 0.2 0.11 0.07 0.13 0.03 0.10 0.15 Puck 3 0.0 0.1 0.2 0.04 0.10 0.19 Figure 9 - Example of Decay Corrected On-Site Gamma Spectroscopy Core Results in Attachment 2 The maximum, minimum, and average concentration of the core at each puck centerline depth (e.g.,

0.25, 0.75, etc.) was calculated for each nuclide. At the Table 1 floor surface area of 2.59E+07 cm2, each 1/2 inch (i.e., 1.27 cm) layer equals 3.29E+07 cm3. Using a density of 2.40 g/cm3 for concrete (7) the 1/2 inch mass equals 7.90E+07 grams. The source term in each 1/2 inch increment is estimated by multiplying the average value across cores at that depth times the 7.90E+07 grams. As seen in Table 4 through Table 6, the majority of the Auxiliary Building floors source term for each nuclide (Co-60, Cs-137 and Cs-134) is in the first half-inch of the 568 foot concrete. Only cores with results reported at the depth being evaluated were used to determine the average concentration and source term. Since the MDA was used when gamma spectroscopy results did not positively identify the radionuclide concentrations at lower depths, Co-60 and Cs-134 results are over represented. This results in the percentage of source term in the first two inches being slightly under estimated and why the Cs-134 source term appears to be more evenly distributed than the Co-60 and Cs-137 where over 70% of the source term is in the top 2 inches of concrete.

Table 4 - Floor Co-60 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 Avg Max. Min. Avg. Source Depth Co-60 Co-60 Co-60 Term Puck Depth inches Results pCi/g pCi/g pCi/g Co-60 Ci Distribution Puck 1 0 - 0.5 0.25 17 404.1 0.2 41.9 3.31E-03 27.9%

Puck 2 0.5 - 1.0 0.75 17 355.3 0.1 24.7 1.95E-03 16.5%

Puck 3 1.0 - 1.5 1.25 13 256.6 0.0 23.9 1.89E-03 15.9%

Puck 4 1.5 - 2.0 1.75 12 162.8 0.1 15.8 1.25E-03 10.5%

Puck 5 2.0 - 2.5 2.25 12 171.2 0.1 15.8 1.25E-03 10.5%

Puck 6 2.5 - 3.0 2.75 12 98.3 0.1 10.8 8.56E-04 7.2%

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TSD 14-013 Revision 0 Avg Max. Min. Avg. Source Depth Co-60 Co-60 Co-60 Term Puck Depth inches Results pCi/g pCi/g pCi/g Co-60 Ci Distribution Puck 7 3.0 - 3.5 3.25 11 61.9 0.1 6.9 5.47E-04 4.6%

Puck 8 3.5 - 4.0 3.75 10 52.1 0.1 5.9 4.63E-04 3.9%

Puck 9 4.0 - 4.5 4.25 7 1.9 0.1 0.5 3.97E-05 0.33%

Puck 10 4.5 - 5.0 4.75 5 0.7 0.1 0.3 2.04E-05 0.17%

Puck 11 5.0 - 5.5 5.25 4 0.3 0.1 0.2 1.64E-05 0.14%

Puck 12 5.5 - 6.0 5.75 1 0.2 0.2 0.2 1.70E-05 0.14%

Puck 13 6.0 - 6.5 6.25 1 0.2 0.2 0.2 1.32E-05 0.11%

Puck 14 6.5 - 7.0 6.75 1 0.4 0.4 0.4 2.97E-05 0.25%

Puck 15 7.0 - 7.5 7.25 1 0.4 0.4 0.4 2.97E-05 0.25%

Puck 16 7.5 - 8.0 7.75 1 0.4 0.4 0.4 2.97E-05 0.25%

Puck 17 8.0 - 8.5 8.25 1 0.2 0.2 0.2 1.60E-05 0.13%

Puck 18 8.5 - 9.0 8.75 1 0.2 0.2 0.2 1.62E-05 0.14%

Puck 19 9.0 - 9.5 9.25 1 0.2 0.2 0.2 1.62E-05 0.14%

Puck 20 9.5 - 10.0 9.75 1 0.1 0.1 0.1 1.01E-05 0.08%

Puck 21 10.0 - 10.5 10.25 1 0.1 0.1 0.1 1.01E-05 0.08%

Puck 22 10.5 - 11.0 10.75 1 0.2 0.2 0.2 1.33E-05 0.11%

Puck 23 11.0 - 11.5 11.25 1 0.1 0.1 0.1 9.22E-06 0.08%

Puck 24 11.5 - 12.0 11.75 1 0.2 0.2 0.2 1.53E-05 0.13%

Puck 25 12.0 - 12.5 12.25 1 0.1 0.1 0.1 1.00E-05 0.08%

Puck 26 12.5 - 13.0 12.75 1 0.2 0.2 0.2 1.62E-05 0.14%

Puck 27 13.0 - 13.5 13.25 1 0.1 0.1 0.1 1.07E-05 0.09%

Puck 28 13.5 - 14.0 13.75 1 0.2 0.2 0.2 1.64E-05 0.14%

Total Ci and Top 2 inch % Total 0.012 71%

Page 17 of 92

TSD 14-013 Revision 0 Table 5 - Floor Cs-137 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 Avg Max. Min. Avg. Source Depth Cs-137 Cs-137 Cs-137 Cs-137 Term Puck Depth inches Results pCi/g pCi/g pCi/g Ci Distribution Puck 1 0 - 0.5 0.25 17 22926.4 7.1 3121.7 2.47E-01 41%

Puck 2 0.5 - 1.0 0.75 17 12882.2 0.1 1437.2 1.14E-01 19%

Puck 3 1.0 - 1.5 1.25 13 6161.9 0.2 836.9 6.61E-02 11%

Puck 4 1.5 - 2.0 1.75 12 2507.9 0.1 511.6 4.04E-02 7%

Puck 5 2.0 - 2.5 2.25 12 2153.0 0.2 413.1 3.26E-02 5%

Puck 6 2.5 - 3.0 2.75 12 1438.8 0.1 295.6 2.33E-02 4%

Puck 7 3.0 - 3.5 3.25 11 1203.9 0.2 223.4 1.76E-02 3%

Puck 8 3.5 - 4.0 3.75 10 1830.5 0.1 266.3 2.10E-02 4%

Puck 9 4.0 - 4.5 4.25 7 712.1 0.2 130.3 1.03E-02 2%

Puck 10 4.5 - 5.0 4.75 5 1624.9 0.1 325.2 2.57E-02 4.3%

Puck 11 5.0 - 5.5 5.25 4 0.9 0.3 0.5 3.67E-05 0.006%

Puck 12 5.5 - 6.0 5.75 1 0.6 0.6 0.6 4.91E-05 0.008%

Puck 13 6.0 - 6.5 6.25 1 1.4 1.4 1.4 1.10E-04 0.018%

Puck 14 6.5 - 7.0 6.75 1 2.8 2.8 2.8 2.18E-04 0.036%

Puck 15 7.0 - 7.5 7.25 1 2.8 2.8 2.8 2.18E-04 0.036%

Puck 16 7.5 - 8.0 7.75 1 2.8 2.8 2.8 2.18E-04 0.036%

Puck 17 8.0 - 8.5 8.25 1 1.5 1.5 1.5 1.15E-04 0.019%

Puck 18 8.5 - 9.0 8.75 1 1.8 1.8 1.8 1.43E-04 0.024%

Puck 19 9.0 - 9.5 9.25 1 1.8 1.8 1.8 1.43E-04 0.024%

Puck 20 9.5 - 10.0 9.75 1 0.6 0.6 0.6 4.43E-05 0.007%

Puck 21 10.0 - 10.5 10.25 1 0.6 0.6 0.6 4.43E-05 0.007%

Puck 22 10.5 - 11.0 10.75 1 0.4 0.4 0.4 3.43E-05 0.006%

Puck 23 11.0 - 11.5 11.25 1 0.5 0.5 0.5 4.10E-05 0.007%

Puck 24 11.5 - 12.0 11.75 1 0.6 0.6 0.6 5.09E-05 0.008%

Puck 25 12.0 - 12.5 12.25 1 0.7 0.7 0.7 5.20E-05 0.009%

Puck 26 12.5 - 13.0 12.75 1 0.6 0.6 0.6 4.56E-05 0.008%

Puck 27 13.0 - 13.5 13.25 1 0.8 0.8 0.8 6.14E-05 0.010%

Puck 28 13.5 - 14.0 13.75 1 0.7 0.7 0.7 5.89E-05 0.010%

Total Ci and Top 2 inch % Total 0.599 78%

Page 18 of 92

TSD 14-013 Revision 0 Table 6 - Floor Cs-134 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 Avg Max. Min. Avg. Source Depth Cs-134 Cs-134 Cs-134 Cs-134 Term Puck Depth inches Results pCi/g pCi/g pCi/g Ci Distribution Puck 1 0 - 0.5 0.25 17 2.3 0.1 0.6 4.51E-05 13%

Puck 2 0.5 - 1.0 0.75 17 1.2 0.1 0.3 2.13E-05 6%

Puck 3 1.0 - 1.5 1.25 13 0.9 0.1 0.3 2.29E-05 7%

Puck 4 1.5 - 2.0 1.75 12 0.8 0.1 0.2 1.97E-05 6%

Puck 5 2.0 - 2.5 2.25 12 0.8 0.1 0.2 1.84E-05 5%

Puck 6 2.5 - 3.0 2.75 12 0.6 0.1 0.2 1.53E-05 4%

Puck 7 3.0 - 3.5 3.25 11 0.5 0.1 0.2 1.29E-05 4%

Puck 8 3.5 - 4.0 3.75 10 0.4 0.1 0.1 1.16E-05 3%

Puck 9 4.0 - 4.5 4.25 7 0.2 0.1 0.1 8.43E-06 2%

Puck 10 4.5 - 5.0 4.75 5 0.2 0.1 0.1 7.36E-06 2%

Puck 11 5.0 - 5.5 5.25 4 0.9 0.1 0.3 2.36E-05 7%

Puck 12 5.5 - 6.0 5.75 1 0.1 0.1 0.1 6.85E-06 2.0%

Puck 13 6.0 - 6.5 6.25 1 0.1 0.1 0.1 5.71E-06 1.7%

Puck 14 6.5 - 7.0 6.75 1 0.1 0.1 0.1 1.00E-05 2.9%

Puck 15 7.0 - 7.5 7.25 1 0.1 0.1 0.1 1.00E-05 2.9%

Puck 16 7.5 - 8.0 7.75 1 0.1 0.1 0.1 1.00E-05 2.9%

Puck 17 8.0 - 8.5 8.25 1 0.1 0.1 0.1 9.10E-06 2.7%

Puck 18 8.5 - 9.0 8.75 1 0.1 0.1 0.1 5.08E-06 1.5%

Puck 19 9.0 - 9.5 9.25 1 0.1 0.1 0.1 5.08E-06 1.5%

Puck 20 9.5 - 10.0 9.75 1 0.1 0.1 0.1 7.30E-06 2.1%

Puck 21 10.0 - 10.5 10.25 1 0.1 0.1 0.1 7.30E-06 2.1%

Puck 22 10.5 - 11.0 10.75 1 0.1 0.1 0.1 1.10E-05 3.2%

Puck 23 11.0 - 11.5 11.25 1 0.1 0.1 0.1 7.22E-06 2.1%

Puck 24 11.5 - 12.0 11.75 1 0.1 0.1 0.1 8.97E-06 2.6%

Puck 25 12.0 - 12.5 12.25 1 0.1 0.1 0.1 6.57E-06 1.9%

Puck 26 12.5 - 13.0 12.75 1 0.1 0.1 0.1 1.02E-05 3.0%

Puck 27 13.0 - 13.5 13.25 1 0.1 0.1 0.1 6.30E-06 1.8%

Puck 28 13.5 - 14.0 13.75 1 0.1 0.1 0.1 7.75E-06 2.3%

Total Ci and Top 2 inch % Total 3.41E-04 32%

The floor source term distribution at depth based on the in-house gamma spectroscopy results is summarized for Co-60, Cs-137 and Cs-134 in Table 7 and Figure 10.

Page 19 of 92

TSD 14-013 Revision 0 Table 7 - Summary of Auxiliary Building Floor Source Term Depth Profile Total Avg Activity Puck Depth Depth in Co-60 Ci Cs-137 Ci Cs-134 Ci Total Ci Profile Puck 1 0 - 0.5 0.25 3.31E-03 2.47E-01 4.51E-05 2.50E-01 41%

Puck 2 0.5 - 1.0 0.75 1.95E-03 1.14E-01 2.13E-05 1.15E-01 19%

Puck 3 1.0 - 1.5 1.25 1.89E-03 6.61E-02 2.29E-05 6.80E-02 11%

Puck 4 1.5 - 2.0 1.75 1.25E-03 4.04E-02 1.97E-05 4.17E-02 7%

Puck 5 2.0 - 2.5 2.25 1.25E-03 3.26E-02 1.84E-05 3.39E-02 6%

Puck 6 2.5 - 3.0 2.75 8.56E-04 2.33E-02 1.53E-05 2.42E-02 4%

Puck 7 3.0 - 3.5 3.25 5.47E-04 1.76E-02 1.29E-05 1.82E-02 3%

Puck 8 3.5 - 4.0 3.75 4.63E-04 2.10E-02 1.16E-05 2.15E-02 4%

Puck 9 4.0 - 4.5 4.25 3.97E-05 1.03E-02 8.43E-06 1.03E-02 2%

Puck 10 4.5 - 5.0 4.75 2.04E-05 2.57E-02 7.36E-06 2.57E-02 4.22%

Puck 11 5.0 - 5.5 5.25 1.64E-05 3.67E-05 2.36E-05 7.67E-05 0.01%

Puck 12 5.5 - 6.0 5.75 1.70E-05 4.91E-05 6.85E-06 7.30E-05 0.01%

Puck 13 6.0 - 6.5 6.25 1.32E-05 1.10E-04 5.71E-06 1.29E-04 0.02%

Puck 14 6.5 - 7.0 6.75 2.97E-05 2.18E-04 1.00E-05 2.58E-04 0.04%

Puck 15 7.0 - 7.5 7.25 2.97E-05 2.18E-04 1.00E-05 2.58E-04 0.04%

Puck 16 7.5 - 8.0 7.75 2.97E-05 2.18E-04 1.00E-05 2.58E-04 0.04%

Puck 17 8.0 - 8.5 8.25 1.60E-05 1.15E-04 9.10E-06 1.40E-04 0.02%

Puck 18 8.5 - 9.0 8.75 1.62E-05 1.43E-04 5.08E-06 1.65E-04 0.03%

Puck 19 9.0 - 9.5 9.25 1.62E-05 1.43E-04 5.08E-06 1.65E-04 0.03%

Puck 20 9.5 - 10.0 9.75 1.01E-05 4.43E-05 7.30E-06 6.17E-05 0.01%

Puck 21 10.0 - 10.5 10.25 1.01E-05 4.43E-05 7.30E-06 6.17E-05 0.01%

Puck 22 10.5 - 11.0 10.75 1.33E-05 3.43E-05 1.10E-05 5.86E-05 0.01%

Puck 23 11.0 - 11.5 11.25 9.22E-06 4.10E-05 7.22E-06 5.75E-05 0.01%

Puck 24 11.5 - 12.0 11.75 1.53E-05 5.09E-05 8.97E-06 7.51E-05 0.01%

Puck 25 12.0 - 12.5 12.25 1.00E-05 5.20E-05 6.57E-06 6.86E-05 0.01%

Puck 26 12.5 - 13.0 12.75 1.62E-05 4.56E-05 1.02E-05 7.20E-05 0.01%

Puck 27 13.0 - 13.5 13.25 1.07E-05 6.14E-05 6.30E-06 7.84E-05 0.01%

Puck 28 13.5 - 14.0 13.75 1.64E-05 5.89E-05 7.75E-06 8.30E-05 0.01%

Totals 1.16E-02 5.97E-01 1.83E-04 6.09E-01 100%

Page 20 of 92

TSD 14-013 Revision 0 Aux Floor Activity at Depth 2.50E-01 2.00E-01 Total Ci Co-60, Cs-137, Cs-134 1.50E-01 Activity Ci 1.00E-01 5.00E-02 0.00E+00 0 5 10 15 20 25 30 Depth inches Figure 10 - Auxiliary Building Activity Profile at Depth Three cores from Auxiliary Building walls were also obtained. The results are included in the summaries. As noted above in Table 3 the embedded source term was assumed to be limited to within three feet of the floor for all the walls except those in the HUT cubicles walls which were assumed to be contaminated at the same concentration as the floor core B105107-CJFCCV-001. As seen in Table 3 the total contaminated wall surface area is 8.43E+06 cm2. At depths of 1/2 inch this is 1.07E+07 cm3 and at a density of 2.40 g/cm3 this is 2.57E+07 grams. This mass multiplied by the average picocuries per gram (pCi/g) at each depth is used to estimate the source term in the walls. Since this includes the HUT floor sample which goes to 14 inches deep, the source term in the walls is a very conservative estimate that is probably greater than the actual activity embedded in the walls.

Page 21 of 92

TSD 14-013 Revision 0 Table 8 - Wall Co-60 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 Avg Max. Min. Avg. Source Depth Co-60 Co-60 Co-60 Term Puck Depth inches Results pCi/g pCi/g pCi/g Co-60 Ci Distribution Puck 1 0 - 0.5 0.25 4.0 560.7 0.2 147.1 0.004 96%

Puck 2 0.5 - 1.0 0.75 3.0 0.6 0.2 0.4 1.07E-05 0.3%

Puck 3 1.0 - 1.5 1.25 1.0 0.2 0.2 0.2 6.33E-06 0.2%

Puck 4 1.5 - 2.0 1.75 1.0 0.2 0.2 0.2 6.36E-06 0.2%

Puck 5 2.0 - 2.5 2.25 1.0 0.2 0.2 0.2 5.97E-06 0.2%

Puck 6 2.5 - 3.0 2.75 1.0 0.2 0.2 0.2 6.27E-06 0.2%

Puck 7 3.0 - 3.5 3.25 1.0 0.3 0.3 0.3 6.84E-06 0.2%

Puck 8 3.5 - 4.0 3.75 1.0 0.2 0.2 0.2 5.47E-06 0.1%

Puck 9 4.0 - 4.5 4.25 1.0 0.1 0.1 0.1 3.40E-06 0.1%

Puck 10 4.5 - 5.0 4.75 1.0 0.2 0.2 0.2 4.95E-06 0.1%

Puck 11 5.0 - 5.5 5.25 1.0 0.1 0.1 0.1 3.33E-06 0.1%

Puck 12 5.5 - 6.0 5.75 1.0 0.2 0.2 0.2 5.52E-06 0.1%

Puck 13 6.0 - 6.5 6.25 1.0 0.2 0.2 0.2 4.30E-06 0.1%

Puck 14 6.5 - 7.0 6.75 1.0 0.4 0.4 0.4 9.65E-06 0.2%

Puck 15 7.0 - 7.5 7.25 1.0 0.4 0.4 0.4 9.65E-06 0.2%

Puck 16 7.5 - 8.0 7.75 1.0 0.4 0.4 0.4 9.65E-06 0.2%

Puck 17 8.0 - 8.5 8.25 1.0 0.2 0.2 0.2 5.20E-06 0.1%

Puck 18 8.5 - 9.0 8.75 1.0 0.2 0.2 0.2 5.28E-06 0.1%

Puck 19 9.0 - 9.5 9.25 1.0 0.2 0.2 0.2 5.28E-06 0.1%

Puck 20 9.5 - 10.0 9.75 1.0 0.1 0.1 0.1 3.28E-06 0.1%

Puck 21 10.0 - 10.5 10.25 1.0 0.1 0.1 0.1 3.28E-06 0.1%

Puck 22 10.5 - 11.0 10.75 1.0 0.2 0.2 0.2 4.33E-06 0.1%

Puck 23 11.0 - 11.5 11.25 1.0 0.1 0.1 0.1 3.00E-06 0.1%

Puck 24 11.5 - 12.0 11.75 1.0 0.2 0.2 0.2 4.96E-06 0.1%

Puck 25 12.0 - 12.5 12.25 1.0 0.1 0.1 0.1 3.27E-06 0.1%

Puck 26 12.5 - 13.0 12.75 1.0 0.2 0.2 0.2 5.26E-06 0.1%

Puck 27 13.0 - 13.5 13.25 1.0 0.1 0.1 0.1 3.49E-06 0.1%

Puck 28 13.5 - 14.0 13.75 1.0 0.2 0.2 0.2 5.32E-06 0.1%

Total Ci and Top 2 inch % Total 0.004 97%

Page 22 of 92

TSD 14-013 Revision 0 Table 9 - Wall Cs-137 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 Avg Max. Min. Avg. Source Depth Cs-137 Cs-137 Cs-137 Cs-137 Term Puck Depth inches Results pCi/g pCi/g pCi/g Ci Distribution Puck 1 0 - 0.5 0.25 4.0 13833.9 0.7 4266.0 0.1096 99%

Puck 2 0.5 - 1.0 0.75 3.0 1.5 0.7 1.0 2.52E-05 0.02%

Puck 3 1.0 - 1.5 1.25 1.0 1.0 1.0 1.0 2.69E-05 0.02%

Puck 4 1.5 - 2.0 1.75 1.0 1.1 1.1 1.1 2.91E-05 0.03%

Puck 5 2.0 - 2.5 2.25 1.0 1.5 1.5 1.5 3.76E-05 0.03%

Puck 6 2.5 - 3.0 2.75 1.0 1.1 1.1 1.1 2.80E-05 0.03%

Puck 7 3.0 - 3.5 3.25 1.0 0.9 0.9 0.9 2.19E-05 0.02%

Puck 8 3.5 - 4.0 3.75 1.0 0.7 0.7 0.7 1.77E-05 0.02%

Puck 9 4.0 - 4.5 4.25 1.0 0.7 0.7 0.7 1.87E-05 0.02%

Puck 10 4.5 - 5.0 4.75 1.0 0.5 0.5 0.5 1.25E-05 0.01%

Puck 11 5.0 - 5.5 5.25 1.0 0.9 0.9 0.9 2.24E-05 0.02%

Puck 12 5.5 - 6.0 5.75 1.0 0.6 0.6 0.6 1.60E-05 0.01%

Puck 13 6.0 - 6.5 6.25 1.0 1.4 1.4 1.4 3.58E-05 0.03%

Puck 14 6.5 - 7.0 6.75 1.0 2.8 2.8 2.8 7.11E-05 0.06%

Puck 15 7.0 - 7.5 7.25 1.0 2.8 2.8 2.8 7.11E-05 0.06%

Puck 16 7.5 - 8.0 7.75 1.0 2.8 2.8 2.8 7.11E-05 0.06%

Puck 17 8.0 - 8.5 8.25 1.0 1.5 1.5 1.5 3.75E-05 0.03%

Puck 18 8.5 - 9.0 8.75 1.0 1.8 1.8 1.8 4.66E-05 0.04%

Puck 19 9.0 - 9.5 9.25 1.0 1.8 1.8 1.8 4.66E-05 0.04%

Puck 20 9.5 - 10.0 9.75 1.0 0.6 0.6 0.6 1.44E-05 0.01%

Puck 21 10.0 - 10.5 10.25 1.0 0.6 0.6 0.6 1.44E-05 0.01%

Puck 22 10.5 - 11.0 10.75 1.0 0.4 0.4 0.4 1.12E-05 0.01%

Puck 23 11.0 - 11.5 11.25 1.0 0.5 0.5 0.5 1.33E-05 0.01%

Puck 24 11.5 - 12.0 11.75 1.0 0.6 0.6 0.6 1.66E-05 0.01%

Puck 25 12.0 - 12.5 12.25 1.0 0.7 0.7 0.7 1.69E-05 0.02%

Puck 26 12.5 - 13.0 12.75 1.0 0.6 0.6 0.6 1.48E-05 0.01%

Puck 27 13.0 - 13.5 13.25 1.0 0.8 0.8 0.8 2.00E-05 0.02%

Puck 28 13.5 - 14.0 13.75 1.0 0.7 0.7 0.7 1.92E-05 0.02%

Total Ci and Top 2 inch % Total 0.110 99%

Page 23 of 92

TSD 14-013 Revision 0 Table 10 - Wall Cs-134 In-House Gamma Spectroscopy Results Summary Decay Corrected to January 1, 2013 Avg Max. Min. Avg. Source Depth Cs-134 Cs-134 Cs-134 Term Puck Depth inches Results pCi/g pCi/g pCi/g Cs-134 Ci Distribution Puck 1 0 - 0.5 0.25 4.0 27.0 0.2 7.1 1.82E-04 72%

Puck 2 0.5 - 1.0 0.75 3.0 0.2 0.1 0.1 3.04E-06 1%

Puck 3 1.0 - 1.5 1.25 1.0 0.1 0.1 0.1 2.73E-06 1%

Puck 4 1.5 - 2.0 1.75 1.0 0.1 0.1 0.1 2.20E-06 1%

Puck 5 2.0 - 2.5 2.25 1.0 0.1 0.1 0.1 2.77E-06 1%

Puck 6 2.5 - 3.0 2.75 1.0 0.1 0.1 0.1 3.23E-06 1%

Puck 7 3.0 - 3.5 3.25 1.0 0.1 0.1 0.1 3.15E-06 1%

Puck 8 3.5 - 4.0 3.75 1.0 0.1 0.1 0.1 2.93E-06 1%

Puck 9 4.0 - 4.5 4.25 1.0 0.1 0.1 0.1 2.35E-06 1%

Puck 10 4.5 - 5.0 4.75 1.0 0.1 0.1 0.1 1.62E-06 1%

Puck 11 5.0 - 5.5 5.25 1.0 0.1 0.1 0.1 2.34E-06 1%

Puck 12 5.5 - 6.0 5.75 1.0 0.1 0.1 0.1 2.23E-06 1%

Puck 13 6.0 - 6.5 6.25 1.0 0.1 0.1 0.1 1.86E-06 1%

Puck 14 6.5 - 7.0 6.75 1.0 0.1 0.1 0.1 3.26E-06 1%

Puck 15 7.0 - 7.5 7.25 1.0 0.1 0.1 0.1 3.26E-06 1%

Puck 16 7.5 - 8.0 7.75 1.0 0.1 0.1 0.1 3.26E-06 1%

Puck 17 8.0 - 8.5 8.25 1.0 0.1 0.1 0.1 2.96E-06 1%

Puck 18 8.5 - 9.0 8.75 1.0 0.1 0.1 0.1 1.65E-06 1%

Puck 19 9.0 - 9.5 9.25 1.0 0.1 0.1 0.1 1.65E-06 1%

Puck 20 9.5 - 10.0 9.75 1.0 0.1 0.1 0.1 2.37E-06 1%

Puck 21 10.0 - 10.5 10.25 1.0 0.1 0.1 0.1 2.37E-06 1%

Puck 22 10.5 - 11.0 10.75 1.0 0.1 0.1 0.1 3.58E-06 1%

Puck 23 11.0 - 11.5 11.25 1.0 0.1 0.1 0.1 2.35E-06 1%

Puck 24 11.5 - 12.0 11.75 1.0 0.1 0.1 0.1 2.92E-06 1%

Puck 25 12.0 - 12.5 12.25 1.0 0.1 0.1 0.1 2.14E-06 1%

Puck 26 12.5 - 13.0 12.75 1.0 0.1 0.1 0.1 3.33E-06 1%

Puck 27 13.0 - 13.5 13.25 1.0 0.1 0.1 0.1 2.05E-06 1%

Puck 28 13.5 - 14.0 13.75 1.0 0.1 0.1 0.1 2.52E-06 1%

Total Ci and Top 2 inch % Total 2.52E-04 75%

As seen in the above tables the overall embedded source term is dominated by the activity in the first several inches of the floor. The total embedded Co-60, Cs-137, Cs-134 source term of the wall and floors estimated based upon the concrete core data is summarized in Table 11.

Page 24 of 92

TSD 14-013 Revision 0 Table 11 - Summary of Estimated Auxiliary Building Wall and Floor Source Terms Location Co-60 Ci Cs-137 Ci Cs-134 Ci Total Floor 1.19E-02 5.99E-01 3.41E-04 6.11E-01 Wall 3.93E-03 1.10E-01 2.52E-04 1.15E-01 Total 1.58E-02 7.09E-01 5.93E-04 7.26E-01

% Mix 2.2% 97.7% 0.1% 100%

3.3. Evaluation of 542 Eberline Off-Site Laboratory Results The first 1/2 inch puck from five cores were sent to Eberline Laboratory for gamma spectroscopy and HTD analyses for radionuclides such as H-3, C-14, Tc-99, I-129, Ni-59/63, Sr-90, and alpha emitters. The pucks were powdered and used for extractions and analyses. The results were reported in Eberline report 12-09081. The Eberline reports contained results for duplicate samples, spikes and blanks and contained results for naturally occurring radionuclides such as K-40, Ra-226, Pb-212, Pb-214, Bi-214, Tl-208, Ac-228, Th-234, U-238, etc. that are not licensed material. The following criteria were used when deciding which reported values to use.

1. Where results for duplicate (DUP) and duplicate original (DO) are both <MDA, the lower MDA was used.
2. Where results for DUP and DO are both positive, the higher result was used.
3. Where results are for two radionuclides (e.g., Pu-239/240) half the reported value is used for each nuclide.
4. For Am-241 alpha spectroscopy results (EML Am-01 Modified) were used over gamma spectroscopy results (LANL ER-130 Modified) because alpha spectroscopy is less subject to compton edge interference from the wide array of licensed and radioactive material photon emitters in the samples at the 59.5 keV peak Am-241.

The results extracted from the reports based upon the above criteria are provided in Attachment 3.

Using this criteria there were no positive results in the concrete core samples for Mn-54, Fe-55, Ni-59, Nb-94, Sb-125, Ba-133, Eu-152, Eu-154, Eu-155, Np-237, Pu-241, Cm-242, Cm-243 or Cm-244.

The bold red and bold blue results in Attachment 3 are considered highly suspicious and potentially resulting from wet chemistry or gamma spectrum analysis interpretation errors such as Pm-145 and Pm-147 identifications which are based upon low energy and low yield (0.072 MeV 2% yield and 0.121 MeV 0.002% yield). Similarly, the I-129 results were attributed to the Cs-137 daughter Ba-137m which emits X-Rays in the 32 keV range, as shown in Table 12.

Table 12 - Ba-137m 32 - 37 keV Photon Energy/Intensity Data from NRC Radiological Toolbox V3.0 Energy Energy Radiation Intensity (MeV) (keV)

X-Ray 2% 0.031817 31.8 X-Ray 4% 0.032194 32.2 X-Ray 0.27% 0.037278 37.3 Page 25 of 92

TSD 14-013 Revision 0 Ag-108m and I-129 The Eberline report 12-09081 Case Narrative reports one Ag-108m result above the 1.06 pCi/g MDA at 1.66 pCi/g for B105103-CJFCCV-001. The final report has the No in the Identified column indicating it was not considered to be a valid result. All other results were less than MDA.

For conservatism the result was retained as valid in order to evaluate the significance of Ag-108m in potential dose consequences in the fate and transport models.

I-129 emits a 0.039 MeV Gamma at 7.51%, and 0.029 MeV X-Ray at 56.9% which results in False Positives for samples with high Cs-137 levels. Despite all the results for the six core analyze offsite having results exceeding the MDA, all were labeled as not identified in the final report. The report states, lodine-129 results were greater than the detection limit; however, lodine-129 is being reported from gamma spectroscopy "non-identified" radionuclides report in most instance and therefore is qualified as "nondetect" (U). Where determined to be positive, lodine-129 results are directly related to Cesium-137, K shell X-Ray emissions. As a result of this condition, lodine-129 is not positive in any samples and therefore, all results are qualified as "U" irrespective of the result versus the method detection limit. Therefore I-129 is not considered to have been positively identified.

Pm-145 Pm-145 emits a 0.072 MeV gamma ray with a 2% yield. The case narrative states, Regarding the case of positive Promethium-145 results for all samples, it is apparent that all results are "false positives", due to the presence ofa 36 KeV, K-Shell X-Ray from Barium-137. These samples do not contain Promethium-145. All results for Promethium-145 should be qualified as appropriate. We have qualified all Promethium-145 results within the electronic data file provided as "R" (rejected) as 8 result of this circumstance. Therefore Pm-145 is not considered to have been positively identified.

Pm-147 Pm-147 levels were determined by liquid scintillation. The case narrative states, Spectral evaluations of sample fractions -03 and -06 (Client IDs: BI-05I03-CJFCCV-00I and BI-05106-CJFCCV-001) may be somewhat indicative ofCobalt-60 interference. As a result of this condition, results for these two samples may need to be qualified as estimated high (JH). Despite two of the positive results being from Co-60 interference, all Pm-147 results were retained as valid in order to evaluate the significance of Pm-147 dose contribution in end state fate and transport modeling.

3.4. Evaluation of 542 Scaling Factors and Source Terms The results in Attachment 3 were decay corrected to January 1, 2013 for comparison to the decay corrected in-house gamma spectroscopy results as provided in Attachment 4. As seen in Table 13 Co-60 and Cs-137 results for individual samples varied significantly relative to the average concentration based upon the puck top and bottom in-house gamma spectroscopy results. Overall the Eberline reported Co-60 and Cs-137 concentrations for the powdered samples were approximately half the In-House gamma spectroscopy results.

Page 26 of 92

TSD 14-013 Revision 0 Table 13 - Comparison of In-House and Eberline Co-60 and Cs-137 Results for Auxiliary 542' Floor/Wall Samples Eberline In-House Eberline  % In-House Eberline  %

Lab Co-60 Co-60 Eberline/In- Cs-137 Cs-137 Eberline/

Sample ID Report pCi/g pCi/g House pCi/g pCi/g In-House B105101-CJFCCV-001 12-09081 4.96E+01 2.57E+01 52% 3.20E+03 1.34E+03 42%

B105103-CJFCCV-001 12-09081 4.04E+02 2.19E+02 54% 2.29E+04 1.32E+04 58%

B105105-CJFCCV-001 12-09081 5.30E+00 3.08E+00 58% 9.60E+03 5.26E+03 55%

B105106-CJFCCV-002 12-09081 1.31E+01 9.69E+00 74% 2.14E+03 1.67E+03 78%

B105108-CJFCCV-003 12-09081 2.18E+01 1.76E+01 81% 1.21E+03 1.04E+03 85%

B105113-CJWCCV-003 12-09081 5.61E+02 1.95E+02 35% 1.38E+04 4.19E+03 30%

Totals 1.05E+03 4.71E+02 44.6% 5.29E+04 2.67E+04 50.5%

Key radionuclide ratios were calculated based upon Eberline reported concentrations for each core as shown in Attachment 5. The detectable gross beta included results for nuclides with a beta average > 40 keV. The emissions, energies, and yields used for this evaluation are provided in Attachment 6. The Sr-90 contribution to the gross beta was multiplied by 2 to account for the Y-90 beta. The Eu-152 MDAs were corrected for a 28% yield. The transuranic alpha emitters were also calculated and the gross alpha to gross beta key radionuclide ratios were compared with and without MDAs. As seen in Table 14, the range of key radionuclide ratios varied by several orders of magnitude across the542 elevation cores.

Table 14 - Summary of Key Radionuclide Ratios for 542' Floor and Wall 542 EL Floor Wall B105113-Max Min Avg Max Min Avg CJWCCV Key Ratio Ratio Ratio Ratio Ratio Ratio Ratio -003 Single All Results Positive Results Core Gross beta to alpha 5.38E+0 1.35E+0 1.07E+0 5.38E+0 Detected Gross Beta > 0.4 keV 1.35E+04 1.07E+03 3 4 3 3 4.38E+03 Detected Gross Alpha 9.53E-01 2.39E-02 2.25E-01 9.53E-01 2.39E-02 2.25E-01 3.18E-02 4.56E+0 8.80E+0 1.41E+0 4.56E+0 Detected Gross Beta/Gross Alpha 8.80E+04 1.41E+04 4 4 4 4 1.38E+05 Am-241 Ratios 1.50E+0 1.50E+0 1.50E+0 Pu-238/Am-241 Ratio 1.50E+00 3.13E-01 7.03E-01 0 0 0 4.39E-01 Pu-239/Am-241 Ratio 5.98E-01 1.28E-01 2.64E-01 5.98E-01 5.98E-01 5.98E-01 2.13E-01 Pu-240/Am-241 Ratio 5.98E-01 1.28E-01 2.64E-01 5.98E-01 5.98E-01 5.98E-01 2.13E-01 4.66E+0 Pu-241/Am-241 Ratio 8.53E+01 1.06E+01 1 ND ND ND 5.36E+01 Am-243/Am-241 Ratio 1.43E+00 4.76E-01 9.94E-01 4.76E-01 4.76E-01 4.76E-01 1.00E+00 Cm-243/Am-241 Ratio 7.10E-01 9.57E-02 4.71E-01 ND ND ND 6.73E-01 Cm-244/Am-241 Ratio 7.07E-01 9.54E-02 4.69E-01 ND ND ND 6.71E-01 Am-241/Gross Alpha 1.62E-05 4.79E-07 3.96E-06 1.62E-05 1.62E-05 1.62E-05 9.96E-01 Cs-137 Ratios Page 27 of 92

TSD 14-013 Revision 0 542 EL Floor Wall B105113-Max Min Avg Max Min Avg CJWCCV Key Ratio Ratio Ratio Ratio Ratio Ratio Ratio -003 Single All Results Positive Results Core H-3/Cs-137 1.75E-02 1.25E-03 6.87E-03 1.75E-02 1.25E-03 6.87E-03 1.11E-03 C-14/Cs-137 1.69E-03 1.90E-04 8.57E-04 1.69E-03 3.69E-04 1.02E-03 7.43E-04 Co-60/Cs-137 1.92E-02 5.86E-04 1.18E-02 1.92E-02 5.86E-04 1.18E-02 4.69E-02 Ni-63/Cs-137 2.56E-01 5.49E-02 1.12E-01 2.56E-01 5.49E-02 1.12E-01 3.94E-01 Sr-90/Cs-137 1.48E-03 2.41E-04 5.47E-04 1.48E-03 2.41E-04 6.05E-04 2.10E-03 Tc-99/Cs-137 1.08E-03 7.27E-05 4.88E-04 1.08E-03 7.27E-05 4.88E-04 1.40E-04 Sb-125/Cs-137 1.78E-03 5.49E-04 1.21E-03 ND ND ND 1.02E-03 Eu-152/Cs-137 6.73E-04 1.92E-04 3.79E-04 ND ND ND 4.26E-04 Eu-154/Cs-137 3.02E-04 1.02E-04 2.23E-04 ND ND ND 2.47E-04 Eu-155/Cs-137 4.48E-04 1.28E-04 3.13E-04 ND ND ND 2.42E-04 Np-237/Cs-137 1.85E-05 1.61E-06 1.05E-05 ND ND ND 7.68E-06 Pu-238/Cs-137 2.59E-05 2.51E-06 1.43E-05 2.59E-05 1.71E-05 2.03E-05 3.34E-06 Pu-239/Cs-137 1.04E-05 1.03E-06 5.22E-06 1.04E-05 1.04E-05 1.04E-05 1.62E-06 Pu-240/Cs-137 1.04E-05 1.03E-06 5.22E-06 1.04E-05 1.04E-05 1.04E-05 1.62E-06 Pu-241/Cs-137 1.64E-03 1.84E-04 9.61E-04 ND ND ND 4.08E-04 Am-241/Cs-137 4.13E-05 8.01E-06 2.11E-05 1.73E-05 1.73E-05 1.73E-05 7.60E-06 Am-243/Cs-137 3.24E-05 8.23E-06 1.91E-05 3.24E-05 8.23E-06 1.84E-05 7.64E-06 Cm-243/Cs-137 1.92E-05 1.66E-06 1.01E-05 ND ND ND 5.12E-06 Cm-244/Cs-137 1.92E-05 1.65E-06 1.01E-05 ND ND ND 5.10E-06 Gross Alpha/Cs-137 7.21E-05 1.14E-05 3.45E-05 7.21E-05 1.14E-05 3.45E-05 7.64E-06 Co-60 Ratios 1.22E+0 3.01E+0 1.22E+0 H-3/Co-60 3.01E+00 7.54E-02 0 0 7.54E-02 0 2.37E-02 C-14/Co-60 3.24E-01 2.23E-02 1.31E-01 1.53E-01 2.23E-02 8.27E-02 1.58E-02 1.51E+0 Fe-55/Co-60 5.45E+00 1.34E-01 0 ND ND ND 8.25E-02 1.87E+0 N-59/C0-60 5.87E+00 9.47E-02 0 ND ND ND 8.95E-02 2.60E+0 9.44E+0 4.87E+0 2.60E+0 Ni-63/Co-60 9.44E+01 4.87E+00 1 1 0 1 8.40E+00 Sr-90/Co-60 4.91E-01 1.85E-02 1.31E-01 4.91E-01 2.47E-02 1.59E-01 4.48E-02 Tc-99/Co-60 2.18E-01 4.39E-03 7.57E-02 2.18E-01 4.39E-03 7.57E-02 3.36E-03 Nb-94/Co-60 2.01E-01 3.73E-03 5.05E-02 1.71E-02 1.71E-02 1.71E-02 2.97E-03 Ag-108m/Co-60 2.62E-01 7.58E-03 6.27E-02 7.58E-03 7.58E-03 7.58E-03 3.02E-02 Pu-238/Co-60 4.28E-03 9.28E-04 1.84E-03 1.56E-03 9.28E-04 1.17E-03 7.11E-05 Pu-239/Co-60 1.75E-03 2.20E-04 7.37E-04 6.24E-04 6.24E-04 6.24E-04 3.45E-05 Pu-240/Co-60 1.75E-03 2.20E-04 7.37E-04 6.24E-04 6.24E-04 6.24E-04 3.45E-05 Page 28 of 92

TSD 14-013 Revision 0 542 EL Floor Wall B105113-Max Min Avg Max Min Avg CJWCCV Key Ratio Ratio Ratio Ratio Ratio Ratio Ratio -003 Single All Results Positive Results Core Pu-241/Co-60 5.74E-01 1.11E-02 1.97E-01 ND ND ND 8.69E-03 Am-241/Co-60 1.37E-02 1.04E-03 4.23E-03 1.04E-03 1.04E-03 1.04E-03 1.62E-04 Am-243/Co-60 1.95E-02 4.96E-04 5.36E-03 1.95E-02 4.96E-04 6.42E-03 1.63E-04 Cm-243/Co-60 6.06E-03 9.99E-05 2.01E-03 ND ND ND 1.09E-04 Cm-244/Co-60 6.04E-03 9.95E-05 2.00E-03 ND ND ND 1.09E-04 Gross Alpha/Co-60 1.95E-02 9.28E-04 6.93E-03 1.95E-02 2.92E-03 8.93E-03 1.63E-04 Note: Bold Italic Values are MDAs The Eberline offsite results from Attachment 5 decay corrected to 1/1/2013 are summarized in Table 15. The average concentrations in pCi/g are used to estimate the source term of each nuclide in the first half inch of the 543 foot elevation based on the decay corrected Eberline results. The estimated source term in Curies for each nuclide was calculated by using the 542 foot elevation surface area of 27,888 square feet from Table 2. A 1/2 inch thick depth of this surface area has a volume of 3.29E+7 cm3. Using a density for concrete of 2.40 g/cm3 yields a mass of 7.90E+7 grams for the 1/2 inch layer of the floor. This mass times the average concentration of the cores equals the estimate source term for the nuclide. The calculated source terms in the first half inch of concrete based upon the Eberline average concentrations are shown in Table 15. The calculated source terms for all results including False Positives and MDAs are shown as well as the source terms based upon the positive results. Scaling factors were calculated based on the ratio of the calculated source terms of all results including MDAs.

Page 29 of 92

TSD 14-013 Revision 0 Table 15 - Summary of Aux Building 542' Floor Eberline Results First First Half Half Inch Inch Percent Source Source of Max Min Avg Term Percent Max All Min All Avg All Term Total Positive Positive Positive Floor of Total Results Results Results Floor Source Results Results Results Positive Source Nuclide pCi/g pCi/g pCi/g All Ci Term pCi/g pCi/g pCi/g Ci Term H-3 2.92E+01 5.52E+00 1.40E+01 1.1E-03 0.3% 2.92E+01 5.52E+00 1.40E+01 1.1E-03 0.3%

C-14 4.88E+00 9.98E-01 2.16E+00 1.7E-04 0.04% 4.88E+00 1.19E+00 2.46E+00 1.9E-04 0.05%

Fe-55 2.94E+01 7.60E+00 1.51E+01 1.2E-03 0.3% ND ND ND ND ND Ni-59 2.08E+01 1.59E+01 1.78E+01 1.4E-03 0.3% ND ND ND ND ND Co-60 2.19E+02 3.08E+00 5.50E+01 4.3E-03 1.0% 2.19E+02 3.08E+00 5.50E+01 4.3E-03 1.0%

Ni-63 3.38E+03 8.57E+01 7.99E+02 6.3E-02 14.7% 3.38E+03 8.57E+01 7.99E+02 6.3E-02 14.9%

Sr-90 5.40E+00 3.27E-01 1.93E+00 1.5E-04 0.04% 5.40E+00 4.02E-01 2.33E+00 1.8E-04 0.04%

Nb-94 8.17E-01 2.13E-01 4.35E-01 3.4E-05 0.01% 3.02E-01 3.02E-01 3.02E-01 2.4E-05 0.01%

Tc-99 1.45E+00 4.73E-01 8.92E-01 7.0E-05 0.02% 1.45E+00 4.73E-01 8.92E-01 7.0E-05 0.02%

Ag-108m 1.66E+00 1.82E-01 6.21E-01 4.9E-05 0.01% 1.66E+00 1.66E+00 1.66E+00 1.3E-04 0.03%

Sb-125 7.25E+00 1.85E+00 3.52E+00 2.8E-04 0.1% ND ND ND ND ND Cs-134 1.34E+00 2.64E-01 7.10E-01 5.6E-05 0.0% 7.37E-01 4.30E-01 5.84E-01 4.6E-05 0.01%

Cs-137 1.32E+04 1.04E+03 4.50E+03 3.6E-01 83.1% 1.32E+04 1.04E+03 4.50E+03 3.6E-01 83.7%

Eu-152 2.54E+00 5.81E-01 1.11E+00 8.7E-05 0.02% ND ND ND ND ND Eu-154 1.35E+00 3.14E-01 7.12E-01 5.6E-05 0.01% ND ND ND ND ND Eu-155 1.69E+00 4.64E-01 8.85E-01 7.0E-05 0.02% ND ND ND ND ND Np-237 2.39E-02 1.92E-02 2.12E-02 1.7E-06 0.00% ND ND ND ND ND Pu-238 3.42E-01 1.32E-02 8.21E-02 6.5E-06 0.00% 3.42E-01 1.77E-02 1.28E-01 1.0E-05 0.002%

Pu-239 1.37E-01 5.41E-03 3.23E-02 2.5E-06 0.00% 1.37E-01 1.37E-01 1.37E-01 1.1E-05 0.003%

Pu-240 1.37E-01 5.41E-03 3.23E-02 2.5E-06 0.00% 1.37E-01 1.37E-01 1.37E-01 1.1E-05 0.003%

Pu-241 2.43E+00 1.68E+00 1.98E+00 1.6E-04 0.04% ND ND ND ND ND Am-241 2.29E-01 2.72E-02 7.42E-02 5.9E-06 0.00% 2.29E-01 2.29E-01 2.29E-01 1.8E-05 0.004%

Am-243 1.09E-01 2.89E-02 5.35E-02 4.2E-06 0.00% 1.09E-01 3.36E-02 5.97E-02 4.7E-06 0.001%

Cm-243 2.19E-02 1.87E-02 1.99E-02 1.6E-06 0.00% ND ND ND ND ND Cm-244 2.18E-02 1.86E-02 1.98E-02 1.6E-06 0.00% ND ND ND ND ND Total 4.3E-01 100% Total 4.2E-01 100%

Note: Bold Italic Values are MDAs As noted above in Table 3 the embedded source term was assumed to be limited to within three feet of the floor for all the walls except those in the HUT cubicles walls which were assumed to be contaminated at the same concentration as the floor core B105107-CJFCCV-001. As seen in Table 3 the surface area of the HUT walls and the three feet above the floor is 8.43E+06 cm2. At depths of 1/2 inch this is 1.07E+07 cm3 and at a density of 2.40 g/cm3 this is 2.57E+07 grams. This mass times the average concentration of the cores equals the estimate source term for the nuclide. The calculated source terms in the first half inch of concrete based upon the Eberline average Page 30 of 92

TSD 14-013 Revision 0 concentrations are shown in Table 16. The calculated source terms for all results including False Positives and MDAs are shown as well as the source terms based upon the positive results. Scaling factors were calculated based on the ratio of the calculated source terms of the positive results.

Table 16 - Summary of Aux Building 542' Walls Eberline Results First First Half Half Inch Inch Source Source Percent Max Min Avg Term Percent Max All Min All Avg All Term of Total Positive Positive Positive Floor of Total Results Results Results Floor All Source Results Results Results Positive Source Nuclide pCi/g pCi/g pCi/g Ci Term pCi/g pCi/g pCi/g Ci Term H-3 4.64E+00 4.64E+00 4.64E+00 1.19E-04 0.1% 4.64E+00 4.64E+00 4.64E+00 1.19E-04 0.1%

C-14 3.09E+00 3.09E+00 3.09E+00 7.95E-05 0.1% 3.09E+00 3.09E+00 3.09E+00 7.95E-05 0.1%

Fe-55 1.61E+01 1.61E+01 1.61E+01 4.15E-04 0.3% ND ND ND ND ND Ni-59 1.75E+01 1.75E+01 1.75E+01 4.50E-04 0.3% ND ND ND ND ND Co-60 1.95E+02 1.95E+02 1.95E+02 5.02E-03 3.2% 1.95E+02 1.95E+02 1.95E+02 5.02E-03 3.2%

Ni-63 1.64E+03 1.64E+03 1.64E+03 4.22E-02 27.1% 1.64E+03 1.64E+03 1.64E+03 4.22E-02 27.3%

Sr-90 8.76E+00 8.76E+00 8.76E+00 2.25E-04 0.1% 8.76E+00 8.76E+00 8.76E+00 2.25E-04 0.1%

Nb-94 6.57E-01 6.57E-01 6.57E-01 1.69E-05 0.01% ND ND ND ND ND Tc-99 5.81E-01 5.81E-01 5.81E-01 1.49E-05 0.01% 5.81E-01 5.81E-01 5.81E-01 1.49E-05 0.01%

Ag-108m 5.95E-01 5.95E-01 5.95E-01 1.53E-05 0.01% ND ND ND ND ND Sb-125 4.25E+00 4.25E+00 4.25E+00 1.09E-04 0.1% ND ND ND ND ND Cs-134 4.51E-01 4.51E-01 4.51E-01 1.16E-05 0.0% 4.51E-01 4.51E-01 4.51E-01 1.16E-05 0.01%

Cs-137 4.16E+03 4.16E+03 4.16E+03 1.07E-01 68.7% 4.16E+03 4.16E+03 4.16E+03 1.07E-01 69.2%

Eu-152 1.78E+00 1.78E+00 1.78E+00 4.56E-05 0.029% ND ND ND ND ND Eu-154 1.03E+00 1.03E+00 1.03E+00 2.64E-05 0.017% ND ND ND ND ND Eu-155 1.01E+00 1.01E+00 1.01E+00 2.59E-05 0.017% ND ND ND ND ND Np-237 3.20E-02 3.20E-02 3.20E-02 8.22E-07 0.001% ND ND ND ND ND Pu-238 1.39E-02 1.39E-02 1.39E-02 3.57E-07 0.000% ND ND ND ND ND Pu-239 6.75E-03 6.75E-03 6.75E-03 1.73E-07 0.000% ND ND ND ND ND Pu-240 6.75E-03 6.75E-03 6.75E-03 1.73E-07 0.000% ND ND ND ND ND Pu-241 1.70E+00 1.70E+00 1.70E+00 4.36E-05 0.028% ND ND ND ND ND Am-241 3.17E-02 3.17E-02 3.17E-02 8.14E-07 0.001% ND ND ND ND ND Am-243 3.18E-02 3.18E-02 3.18E-02 8.17E-07 0.001% 3.18E-02 3.18E-02 3.18E-02 8.17E-07 0.001%

Cm-243 2.13E-02 2.13E-02 2.13E-02 5.48E-07 0.000% ND ND ND ND ND Cm-244 2.12E-02 2.12E-02 2.12E-02 5.46E-07 0.000% ND ND ND ND ND Total 1.6E-01 100% Total 1.55E-01 100%

Note: Bold Italic Values are MDAs It is important to note that these Eberline results are for a subset of the 542 foot floor cores analyzed in-house (e.g., not all cores had first half-inch sent to Eberline) and that they are representative of the source term in the first half inch of those cores only. Thus the calculated source terms and Page 31 of 92

TSD 14-013 Revision 0 gamma emitting (e.g., Co-60, Cs-134, Cs-137) ratios are not representative of the overall gamma emitting nuclide profiles over the entire depth of the core or the overall average over all cores from the 542 foot elevation. The overall source terms are provided in Table 11.

The scaling factors based on the 1st half inch source terms for all results in Table 15 and Table 16 were used to estimate the hard-to-detect source terms based upon the estimated Co-60, Cs-134, and Cs-137 source terms in Table 11. The scaling nuclides, scaling factors, and estimated source terms for 542 foot concrete are provided in Table 17.

Table 17 - Estimated Auxiliary Building EL 542' Floor & Wall Source Terms Based Upon Eberline Sample Result Scaling Factors Floor Wall Overall Total Percent Total Percent Percent of Total Contam of Total of Total Scaling Scaling Total Source Scaling Scaling Wall Source Source Nuclide Nuclide Factor 542' Ci Term Nuclide Factor 542' Ci Term Total Ci Term H-3 Cs-137 3.12E-03 1.87E-03 0.23% Cs-137 1.1E-03 1.22E-04 0.08% 1.99E-03 0.21%

C-14 Cs-137 4.81E-04 2.88E-04 0.04% Cs-137 7.4E-04 8.16E-05 0.06% 3.69E-04 0.04%

3.25E-Fe-55 Co-60 2.74E-01 03 0.41% Co-60 8.3E-02 3.13E-04 0.21% 3.56E-03 0.38%

3.83E-Ni-59 Co-60 3.23E-01 03 0.48% Co-60 9.0E-02 3.39E-04 0.23% 4.17E-03 0.44%

Co-60 Co-60 1.00E+00 1.19E-02 1.49% Co-60 1.0E+00 3.79E-03 2.58% 1.57E-02 1.66%

Ni-63 Co-60 1.45E+01 1.72E-01 21.70% Co-60 8.4E+00 3.19E-02 21.66% 2.04E-01 21.69%

Sr-90 Cs-137 4.28E-04 2.56E-04 0.03% Cs-137 2.1E-03 2.31E-04 0.16% 4.87E-04 0.05%

9.38E-Nb-94 Co-60 7.90E-03 05 0.01% Co-60 3.4E-03 1.27E-05 0.01% 1.07E-04 0.01%

Tc-99 Cs-137 1.98E-04 1.19E-04 0.01% Cs-137 1.4E-04 1.53E-05 0.01% 1.34E-04 0.01%

1.34E-Ag-108m Co-60 1.13E-02 04 0.02% Co-60 3.0E-03 1.15E-05 0.01% 1.45E-04 0.02%

4.68E-Sb-125 Cs-137 7.81E-04 04 0.06% Cs-137 1.0E-03 1.12E-04 0.08% 5.80E-04 0.06%

Cs-134 Cs-134 1.00E+00 3.41E-04 0.04% Cs-134 1.0E+00 2.06E-04 0.14% 5.47E-04 0.06%

Cs-137 Cs-137 1.00E+00 5.99E-01 75.38% Cs-137 1.0E+00 1.10E-01 74.68% 7.09E-01 75.27%

1.47E-Eu-152 Cs-137 2.45E-04 04 0.02% Cs-137 4.3E-04 4.68E-05 0.03% 1.94E-04 0.02%

9.46E-Eu-154 Cs-137 1.58E-04 05 0.01% Cs-137 2.5E-04 2.71E-05 0.02% 1.22E-04 0.01%

1.18E-Eu-155 Cs-137 1.96E-04 04 0.01% Cs-137 2.4E-04 2.66E-05 0.02% 1.44E-04 0.02%

2.81E-Np-237 Cs-137 4.70E-06 06 0.00% Cs-137 7.7E-06 8.43E-07 0.00% 3.66E-06 0.00%

1.09E-Pu-238 Cs-137 1.82E-05 05 0.00% Cs-137 3.3E-06 3.66E-07 0.00% 1.13E-05 0.00%

4.29E-Pu-239 Cs-137 7.16E-06 06 0.00% Cs-137 1.6E-06 1.78E-07 0.00% 4.47E-06 0.00%

4.29E-Pu-240 Cs-137 7.16E-06 06 0.00% Cs-137 1.6E-06 1.78E-07 0.00% 4.47E-06 0.00%

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TSD 14-013 Revision 0 2.63E-Pu-241 Cs-137 4.40E-04 04 0.03% Cs-137 4.1E-04 4.48E-05 0.03% 3.08E-04 0.03%

9.87E-Am-241 Cs-137 1.65E-05 06 0.00% Cs-137 7.6E-06 8.35E-07 0.00% 1.07E-05 0.00%

Am-243 Cs-137 1.19E-05 7.12E-06 0.00% Cs-137 7.6E-06 8.39E-07 0.00% 7.96E-06 0.00%

2.64E-Cm-243 Cs-137 4.41E-06 06 0.00% Cs-137 5.1E-06 5.62E-07 0.00% 3.20E-06 0.00%

2.63E-Cm-244 Cs-137 4.39E-06 06 0.00% Cs-137 5.1E-06 5.60E-07 0.00% 3.19E-06 0.00%

Total All 7.94E-01 100% Total All 1.47E-01 100% 9.41E-01 100%

Total >MDA 7.86E-01 Total >MDA 1.46E-01 9.32E-01 Note: Bold Italic Values are MDAs When the HTD nuclides are included in the mix, the Auxiliary Building total activity increased from 0.726 Ci to 0.941 Ci. This is principally due to the Ni-63 which added an additional 0.204 Ci to the estimated source term.

Source terms used to demonstrate compliance with the 10 CFR 20 Subpart E and groundwater dose criterion will be those present at the time of License Termination. A conservative estimate of the earliest potential date for license termination, based upon the current schedule is July 1 of 2018. The estimated source terms decay corrected to July 1, 2018 are provided in Table 18.

Table 18 - Auxiliary Building July 1, 2018 Scaled Radionuclide Inventories Based on Positive Results Decay to Date 7/1/2018 Decay Years 5.50 Years Total Half- Decay Total Contam Floor Wall Overall Life Const 542' Wall 542' Overall Percent Percent Percent Nuclide years yr-1 Floor Ci Ci Total Ci Total Total Total H-3 1.23E+01 5.63E-02 1.37E-03 8.97E-05 1.46E-03 0.19% 0.07% 0.17%

C-14 5.73E+03 1.21E-04 2.88E-04 8.16E-05 3.69E-04 0.04% 0.06% 0.04%

Fe-55 2.70E+00 2.57E-01 7.92E-04 7.63E-05 8.68E-04 0.11% 0.06% 0.10%

Ni-59 7.50E+03 9.24E-05 3.83E-03 3.39E-04 4.17E-03 0.54% 0.26% 0.50%

Co-60 5.27E+00 1.32E-01 5.76E-03 1.84E-03 7.60E-03 0.82% 1.41% 0.91%

Ni-63 9.60E+01 7.22E-03 1.66E-01 3.06E-02 1.96E-01 23.45% 23.52% 23.46%

Sr-90 2.91E+01 2.38E-02 2.25E-04 2.03E-04 4.27E-04 0.03% 0.16% 0.05%

Nb-94 2.03E+04 3.41E-05 9.38E-05 1.27E-05 1.07E-04 0.01% 0.01% 0.01%

Tc-99 2.13E+05 3.25E-06 1.19E-04 1.53E-05 1.34E-04 0.02% 0.01% 0.02%

Ag-108m 4.10E+02 1.69E-03 1.33E-04 1.14E-05 1.44E-04 0.02% 0.01% 0.02%

Sb-125 2.77E+00 2.50E-01 1.18E-04 2.83E-05 1.46E-04 0.02% 0.02% 0.02%

Cs-134 2.06E+00 3.36E-01 5.36E-05 3.24E-05 8.60E-05 0.01% 0.02% 0.01%

Cs-137 3.00E+01 2.31E-02 5.27E-01 9.67E-02 6.24E-01 74.67% 74.30% 74.61%

Eu-152 1.33E+01 5.21E-02 1.10E-04 3.52E-05 1.46E-04 0.02% 0.03% 0.02%

Eu-154 8.80E+00 7.88E-02 6.13E-05 1.76E-05 7.89E-05 0.01% 0.01% 0.01%

Eu-155 4.96E+00 1.40E-01 5.46E-05 1.23E-05 6.69E-05 0.01% 0.01% 0.01%

Np-237 2.14E+06 3.24E-07 2.81E-06 8.43E-07 3.66E-06 0.00% 0.00% 0.00%

Pu-238 8.77E+01 7.90E-03 1.05E-05 3.51E-07 1.08E-05 0.001% 0.000% 0.001%

Page 33 of 92

TSD 14-013 Revision 0 Pu-239 2.41E+04 2.87E-05 4.29E-06 1.78E-07 4.47E-06 0.001% 0.000% 0.001%

Pu-240 6.54E+03 1.06E-04 4.29E-06 1.78E-07 4.47E-06 0.001% 0.000% 0.001%

Pu-241 1.44E+01 4.81E-02 2.02E-04 3.44E-05 2.36E-04 0.029% 0.026% 0.028%

Am-241 4.32E+02 1.60E-03 9.78E-06 8.28E-07 1.06E-05 0.001% 0.001% 0.001%

Am-243 7.38E+03 9.39E-05 7.11E-06 8.38E-07 7.95E-06 0.001% 0.001% 0.001%

Cm-243 2.85E+01 2.43E-02 2.31E-06 4.92E-07 2.80E-06 0.00% 0.00% 0.00%

Cm-244 1.81E+01 3.83E-02 2.13E-06 4.54E-07 2.58E-06 0.00% 0.00% 0.00%

Total All 7.06E-01 1.30E-01 8.36E-01 100% 100% 100%

% Reduction 11% 11% 11%

Total > MDA 6.95E-01 1.28E-01 8.22E-01

% Reduction 12% 13% 12%

Note: Bold Italic Values are MDAs Decay correction to July 1, 2018 reduces the overall source term by 11%. The decay corrected 0.836 Ci source term is 73% Cs-137 and 23% Ni-63. These two nuclides account for 95.6% of the end state source term. This is based upon core results obtained from areas with high contact dose rates or locations that exhibited evidence of leaks and spills. It is therefore very bounding and conservative.

3.5. Evaluation of Potential Removable Contamination Source Terms on Walls Above 3 Feet As noted in Section 3.2, all of the HUT walls were assumed to be contaminated at the same levels as the HUT floor cores, but only the bottom 3 feet of the remaining walls was assumed to be contaminated to the levels indicated by the one wall core from the Unit 1 AEDCT Room B105113-CJWCCV-003. There is a potential for the walls above 3 feet to be contaminated in spots where there were localized leaks and by surface contamination. The potential contribution of localized leaks will be limited by the 2 mrem/hr contact dose rate cut-off for open air demolition. The surface contamination will approximate the overall radionuclide distribution in Table 17.

The total wall surface areas and the amount used to estimate the embedded source term activities are provided in Table 3. As seen in Table 19, there is an additional 33,080 square feet of wall surface area above the 3 foot level that could have residual surface contamination.

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TSD 14-013 Revision 0 Table 19 - Wall Surface Area Remaining With Removable Contamination Only Est Fig. 5 Inside Contam Remainin 2

Sections # Height Length ft ft2 g ft2 Pipe Penetration Areas 574'6" 1 13.5 72 968 215 753 Hold-Up Tank Cubicles West 2 46.5 84 3906 3906 0 Hold-Up Tank Cubicles North and South 2 46.5 58 2697 2697 0 West Aux Bld 3 46 97 4462 291 4171 Center and North and South Pipe Penetration 4, 6 46 137 6310 412 5898 East Aux North and South 5 46 255 11722 765 10958 East Aux East Wall TB Common 5 46 263 12088 788 11300 4.22E+0 9.07E+0 Total 4 3 3.31E+04 There are 9.29 100 cm2 sections in one square foot meaning there are 3.07E+05 100 cm2 sections in the remaining wall surface area. If it is assumed the removable contamination is at the posting limit for a Contaminated Area (e.g., 1000 dpm/100 cm2), the source term on the remaining walls is 3.07E+08 dpm. At 2.22E+12 dpm/Ci, this equals a potential overall source term of 1.38E-04 Ci which is inconsequential relative to the estimated embedded source terms in Table 17. The potential radionuclide distribution can easily be calculated by multiplying the 1.38E-04 Ci by the Overall Percent Total value for each nuclide in Table 17, but at levels approaching one ten thousandth of the estimated embedded source term any dose contribution would be insignificant in comparison to the error associated with the source term estimates.

3.6. Source Term Estimate Based Upon Contact Dose Rates As noted in Table 7 the majority of the source term is located in the top 2 inches of the floor. A general model indicating dose rates that correspond to a 2 inch thick concrete disc source with a 3 foot diameter was constructed assuming 99% of the source term was Cs-137 and 1% was Co-60.

The concrete density used was 2.40 g/cm3. The MicroShield report is provided in Attachment 7.

The model indicates that an average 2 inch Cs-137 concentration of 1.97E+04 pCi/g results in a dose rate of 7.569 mrem/hr at one inch above the center of the source as seen in Attachment 7 and summarized in Table 20.

Table 20 - Source Term for 2 Inch Thick Disc Source Nuclide Ci Bq µCi/cm³ pCi/g Co-60 1.54E-05 5.69E+05 4.61E-04 1.92E+02 Cs-137 1.58E-03 5.84E+07 4.73E-02 1.97E+04 Contact @ 1" 7.569 mrem/hr This indicates that for a source where the concentration is uniform over the 2 inch thickness, 2,606 pCi/g of Cs-137 equals 1 mrem/hr.

As noted in Figure 10 the source term is not uniform over two inches and can be modeled as a striated source consisting of four 0.5 inch sections. A 36 inch diameter circle has 7.07 square foot (6566.9 cm2) surface area. Each half inch (1.27 cm) striation has a mass of 20,016 grams at a density of 2.40 g/cm3. The source term in each striation can be calculated based upon the average Co-60, Cs-134, and Cs-137 concentrations as shown Table 21.

Page 35 of 92

TSD 14-013 Revision 0 Table 21 - Striated Source Modeled Source Terms and Dose Rates Avg. Avg. Avg. MS One Co-60 Cs-137 Cs-134 Cs-134 inch Depth pCi/g pCi/g pCi/g Co-60 Ci Cs-137 Ci Ci mrem/hr 0 - 0.5 41.9 3121.7 0.6 8.39E-07 6.25E-05 1.14E-08 0.4857 0.5 - 1.0 24.7 1437.2 0.3 4.95E-07 2.88E-05 5.40E-09 0.1511 1.0 - 1.5 23.9 836.9 0.3 4.79E-07 1.68E-05 5.79E-09 0.06652 1.5 - 2.0 15.8 511.6 0.2 3.16E-07 1.02E-05 4.98E-09 0.03078 Avg 26.6 1476.9 0.345 1.18E-04 2.76E-08 9.47E-12 N/A Totals 2.13E-06 1.18E-04 2.76E-08 7.34E-01 The MicroShield reports corresponding to each of the four layers of the source are provided in . Thus a location containing the average concentrations of Co-60, Cs-134 and Cs-137 would be expected to read 0.734 mrem/hr at 1 inch. This results in a slightly lower 2,012 pCi/g Cs-137 per mrem/hr value because the source term is weighted toward surface and results in less self-attenuation.

In order to evaluate the overall source term of the Auxiliary Building floor, contact dose rates were obtained at 165 locations. The dose rates were obtained using a Ludlum 2350 with a Ludlum 44-10 2 inch by 2 inch NaI gamma detector. At locations that were too high for the Ludlum 44-10, contact dose rates were obtained with a Ludlum 14C probe. The results are provided in Attachment 8. The locations where dose rates are based on the Ludlum 14C readings are denoted in red. The Ludlum 2350 44-10 readings in cpm were converted to mrem/hr using the Ludlum count rate to dose conversion of 900 cpm/R/hr. Thus 900,000 cpm equals 1 mrem/hr. The Ludlum 2350 data converted to dose rates is provided in Attachment 8. Attachment 8 also contains a data set where dose rates are capped at the 2 mrem/hr contact dose rate open air demolition limit. The uniform 2,606 pCi/g of Cs-137per mrem/hr values and the striated source 2,012 pCi/g Cs-137 per mrem/hr value are used to calculate the concentrations corresponding to the un-remediated current dose rates and the open air demolition remediated dose rates. The estimated concentrations using the two models for the un-remediated and remediated dose rates are provide in Attachment 8 and summarized in Table 22.

Table 22 - Summary of Attachment 8 Contact Survey Data and Estimated Concentrations Uniform Source Model Striated Source Model Dose Rates Concentrations Concentrations Open Air Un- Remediated Un- Open Air Un- Demo Remediated 2 inch Remediated Demo Remediated 2 Remediated Stratified 2 Stratified Current Remediate inch Cs-137 2 inch Cs- inch Cs-137 Cs-137 mrem/hr d mrem/hr pCi/g 137 pCi/g pCi/g pCi/g Max 15.00 2.00 39096.25 5212.83 30176.86 4023.58 Min 0.004 0.004 11.08 11.08 8.55 8.55 Average 0.71 0.36 1840.08 947.58 1420.29 731.40 Based upon the contact dose rates, the average Cs-137 concentration in the first 2 inches of concrete floor is between 1420 (striated) and 1840 (uniform) pCi/g. As seen in Table 21, this is close to the overall average concentration of the first two inches from the in-house gamma spectroscopy core Page 36 of 92

TSD 14-013 Revision 0 data of 1477 pCi/g. As noted previously, a 1/2 inch layer of the Auxiliary Building floor equals 7.90E+07 grams. Thus a 2 inch layer equals 3.16E+08 grams. This mass multiplied by the calculated average concentrations in Table 22 equals the estimated source term in the first 2 inches based upon the contact dose rate survey results shown in Table 23.

Table 23 - Estimated Cs-137 Source Terms Based On Contact Dose Rates Overall MS Model Striated MS Model Un- Un-remediated Ci Remediated remediated Ci Remediated Percent Depth Cs-137 Ci Cs-137 Cs-137 Ci Cs-137 Total First 2 Inches 5.81E-01 2.99E-01 4.49E-01 2.31E-01 78%

Remaining 1.65E-01 8.49E-02 1.27E-01 6.55E-02 22%

Total 7.46E-01 3.84E-01 5.76E-01 2.97E-01 100%

As noted in Table 7, 78% of the Cs-137 source term is contained in the first 2 inches indicating and additional 22% of the source term would be in the remaining concrete below 2 inches. The remaining source term is 0.22/0.78 (e.g., 28%) of the 2 inch source term. This results in an overall estimated Cs-137 source term of 0.576 Ci using the striated source, which closely matches the 0.599 Ci source term based upon the core data in Table 11 for the Auxiliary Building floor. As seen in Table 23, remediating the floor to less than 2 mrem/hr would be expected to reduce the source term to half this value.

4. CONCLUSION The end state estimated embedded concrete source terms for the Auxiliary Building walls and floors are provided in Table 17 and Table 18. The end state source terms are dominated by Co-60, Cs-137 and Ni-63. Core data indicates that over 70% of the source term is in the first two inches of the floor and that the depth profile follows an exponential curve as seen in Figure 10. The embedded source term was estimated based upon in-house gamma spectroscopy Co-60, Cs-134 and Cs-137 results which were about 50% higher than off-site laboratory results and that included using the MDA concentrations for all pucks analyzed. The source term estimated from in-house gamma spectroscopy results were used to scale HTD radionuclides providing a conservative estimate of the overall radionuclide source terms. The embedded source term estimates were further biased high by the selection of core locations. They also do not reflect the anticipated post remediation source term and are therefore considered highly conservative and bounding.
5. REFERENCES
1. Zion Nuclear Power Station, Units 1 And 2 Asset Sale Agreement, December 11, 2007.
2. Zion Nuclear Power Station Units 1 and 2 Amended Post-Shutdown Decommissioning Activities Report March 17, 2008.
3. EPRI 1015502, Concrete Characterization and Dose Modeling During Plant Decommissioning Detailed Experience 1993 - 2007, March 2008.
4. NUREG/CR - 5849, Manual for Conducting Radiological Surveys in Support of License Termination, Draft Report for Comment, ML090640319.
5. ZS-RP-107-001-001, Characterization Survey Package Development.

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TSD 14-013 Revision 0

6. ComEd Zion Station Historical Site Assessment, Version 1 - August, 1999.
7. TSD 13-006 Reactor Building Units 1 and 2 End State Concrete and Liner Initial Characterization Source Terms and Distributions.
6. ATTACHMENTS 6.1. Attachment 1 - Auxiliary Building Concrete Core Sample Locations 6.2. Attachment 2 - 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results 6.3. Attachment 3 - Eberline Off-Site Laboratory Results 6.4. Attachment 4 - Eberline Off-Site Laboratory Decay Corrected Results 6.5. Attachment 5 - Eberline Off-Site Laboratory Decay Corrected Results 6.6. Attachment 6 - Radionuclide Emissions and Yields 6.7. Attachment 7 - Contact Dose Rate MicroShield Reports 6.8. Attachment 8 - Contact Dose Rate Survey Results Page 38 of 92

Attachment 1 TSD 14-013 Auxiliary Building Concrete Core Sample Locations Revision 0 Page 39 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 1A RHR Pump Core Collection Date 5/29/12 B105101-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 7/16/12 1246 7/10/12 10:39 1000 324 61.10 0.92 3.74E+03 3.80E+03 Puck 1 134 0.5 7/16/12 1305 7/10/12 12:39 1000 324 50.40 0.70 2.79E+03 2.84E+03 0.5 7/16/12 1409 7/10/12 12:39 1000 324 21.20 0.49 7.02E+02 7.24E+02 Puck 2 132 1 7/16/12 1427 7/10/12 12:39 1000 324 18.60 0.51 6.34E+02 6.53E+02 1 7/16/12 1446 7/10/12 12:40 1000 324 13.60 0.42 4.90E+02 5.04E+02 Puck 3 125 1.5 7/16/12 1505 7/10/12 12:40 1000 324 14.10 0.43 5.15E+02 5.30E+02 1.5 7/16/12 1527 7/10/12 12:40 1000 324 7.97 0.24 2.67E+02 2.75E+02 Puck 4 135 2 7/16/12 1546 7/10/12 12:41 1000 324 7.01 0.28 2.06E+02 2.13E+02 2 7/17/12 622 7/10/12 12:42 1000 324 7.24 0.28 1.39E+02 1.47E+02 Puck 5 127 2.5 7/17/12 640 7/10/12 12:42 1000 324 6.93 0.20 1.24E+02 1.31E+02 2.5 7/17/12 701 7/10/12 12:43 1000 324 21.70 0.35 1.21E+02 1.43E+02 Puck 6 131 3 7/17/12 720 7/10/12 12:43 1000 324 25.20 0.43 1.21E+02 1.47E+02 3 7/16/12 1328 7/10/12 12:44 1000 324 8.07 0.22 1.60E+01 2.43E+01 Puck 7 132.1 3.5 7/16/12 1350 7/10/12 13:03 1000 324 7.36 0.20 1.32E+01 2.08E+01 3.5 7/17/12 738 7/10/12 13:03 1000 324 3.77 0.15 5.15E+00 9.07E+00 Puck 8 129 4 7/17/12 756 7/10/12 13:04 1000 324 3.08 0.17 4.79E+00 8.04E+00 4 10/23/12 1331 10/23/12 13:13 1000 219 2.27 0.12 4.24E+00 6.63E+00 Puck 9 149.84 4.5 10/23/12 1350 10/23/12 13:14 1000 219 1.79 0.12 2.62E+00 4.53E+00 4.5 10/23/12 1413 10/23/12 15:56 1000 219 0.73 0.12 4.28E-01 1.27E+00 Puck 10 154.77 5 10/23/12 1440 10/23/12 15:56 1000 219 0.76 0.07 3.51E-01 1.18E+00 5 10/24/12 723 10/24/12 7:00 1400 218 0.35 0.08 4.52E-01 8.84E-01 Puck 11 161.75 5.5 10/24/12 743 10/24/12 7:00 1000 218 0.35 0.08 3.19E-01 7.54E-01 Page 40 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105101-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 54.37 0.68 3.66E+03 Puck 1 49.6 0.6 3.20E+03 44.85 0.52 2.73E+03 18.86 0.36 6.88E+02 Puck 2 17.7 0.4 6.54E+02 16.55 0.38 6.21E+02 12.10 0.31 4.80E+02 Puck 3 12.3 0.3 4.92E+02 12.55 0.32 5.05E+02 7.09 0.18 2.62E+02 Puck 4 6.7 0.2 2.32E+02 6.24 0.21 2.02E+02 6.44 0.21 1.36E+02 Puck 5 6.3 0.2 1.29E+02 6.17 0.15 1.21E+02 19.31 0.26 1.19E+02 Puck 6 20.9 0.3 1.19E+02 22.42 0.32 1.19E+02 7.18 0.16 1.57E+01 Puck 7 6.9 0.2 1.43E+01 6.55 0.15 1.29E+01 3.35 0.11 5.05E+00 Puck 8 3.0 0.1 4.87E+00 2.74 0.13 4.69E+00 2.10 0.10 4.18E+00 Puck 9 1.9 0.1 3.38E+00 1.65 0.10 2.58E+00 0.67 0.10 4.22E-01 Puck 10 0.7 0.1 3.84E-01 0.70 0.06 3.46E-01 0.32 0.07 4.46E-01 Puck 11 0.3 0.1 3.80E-01 0.33 0.07 3.15E-01 Page 41 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 2A RHR Pump Core Collection Date 5/29/12 B105103-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 7/11/12 1400 7/11/12 13:27 1000 323 456.00 3.12 2.51E+04 2.56E+04 Puck 1 132 0.5 7/11/12 1420 7/11/12 13:55 1000 323 452.00 3.00 2.17E+04 2.22E+04 0.5 7/11/12 1101 7/9/12 13:42 1000 325 410.00 1.59 1.37E+04 1.41E+04 Puck 2 131 1 7/11/12 1121 7/9/12 13:43 1000 325 389.00 1.53 1.26E+04 1.30E+04 1 7/11/12 1148 7/9/12 13:44 1000 325 294.00 1.31 6.72E+03 7.02E+03 Puck 3 131 1.5 7/11/12 1209 7/9/12 13:45 1000 325 283.00 1.25 5.86E+03 6.14E+03 1.5 7/11/12 1246 7/9/12 13:45 1000 325 178.00 0.98 2.68E+03 2.86E+03 Puck 4 132 2 7/11/12 1440 7/9/12 13:45 1000 325 188.00 1.07 2.44E+03 2.63E+03 2 7/11/12 1500 7/9/12 13:47 1000 325 199.00 1.13 2.05E+03 2.25E+03 Puck 5 117 2.5 7/11/12 1517 7/9/12 13:47 1000 325 186.00 1.08 2.08E+03 2.27E+03 2.5 7/16/12 846 7/9/12 13:48 1000 325 119.00 0.81 1.62E+03 1.74E+03 Puck 6 131 3 7/16/12 904 7/9/12 13:49 1000 325 102.00 0.78 1.13E+03 1.23E+03 3 7/16/12 924 7/9/12 13:49 1000 325 66.40 0.64 3.58E+02 4.25E+02 Puck 7 122 3.5 7/16/12 943 7/9/12 13:49 1000 325 72.80 0.64 3.83E+02 4.56E+02 3.5 7/16/12 1004 7/9/12 13:50 1000 325 61.50 0.54 2.40E+02 3.02E+02 Puck 8 127 4 7/16/12 1022 7/9/12 13:50 1000 325 55.70 0.53 2.12E+02 2.68E+02 Page 42 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105103-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 405.90 2.32 2.46E+04 Puck 1 404.1 2.3 22926.4 402.34 2.23 2.13E+04 364.69 1.18 1.34E+04 Puck 2 355.3 1.2 12882.2 346.01 1.13 1.23E+04 261.51 0.97 6.58E+03 Puck 3 256.6 0.9 6161.9 251.72 0.93 5.74E+03 158.33 0.72 2.63E+03 Puck 4 162.8 0.8 2507.9 167.22 0.79 2.39E+03 177.01 0.84 2.01E+03 Puck 5 171.2 0.8 2023.0 165.44 0.80 2.04E+03 105.85 0.60 1.59E+03 Puck 6 98.3 0.6 1347.0 90.73 0.58 1.11E+03 59.06 0.47 3.51E+02 Puck 7 61.9 0.5 363.0 64.75 0.47 3.75E+02 54.70 0.40 2.35E+02 Puck 8 52.1 0.4 221.4 49.54 0.39 2.08E+02 Page 43 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 2B RHR Core Collection Date 5/30/13 B105104-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 7/18/12 1004 7/18/12 9:46 1000 316 0.41 0.13 9.44E+00 9.98E+00 Puck 1 131.7 0.5 7/18/12 1030 7/18/12 9:46 1000 316 0.28 0.10 5.04E+00 5.42E+00 0.5 7/18/12 1047 7/18/12 9:46 1000 316 0.09 0.12 1.77E-01 3.84E-01 Puck 2 140.1 1 7/18/12 1109 7/18/12 9:47 1000 316 0.10 0.09 1.55E-01 3.37E-01 B105104-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.36 0.10 9.25E+00 Puck 1 0.3 0.1 7.1 0.25 0.08 4.94E+00 0.08 0.09 1.73E-01 Puck 2 0.1 0.1 0.2 0.09 0.06 1.52E-01 Page 44 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 U1 Pipe Tunnel Core Collection Date 5/30/12 B105105-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 6/20/12 1423 6/20/12 14:22 600 344 7.00 1.12 9830.0 9.84E+03 Puck 1 136 0.5 6/20/12 1440 6/20/12 14:40 600 344 4.99 1.04 9790.0 9.80E+03 0.5 6/20/12 1452 6/20/12 14:52 600 344 2.24 0.85 8810.0 8.81E+03 Puck 2 133 1 6/20/12 1503 6/21/12 13:17 600 343 1.69 0.78 6300.0 6.30E+03 1 6/20/12 1524 6/20/12 15:24 600 344 0.87 0.39 1660.0 1.66E+03 Puck 3 133 1.5 6/21/12 1341 6/21/12 13:31 600 343 1.02 0.39 1720.0 1.72E+03 1.5 6/21/12 1400 6/21/12 13:49 600 343 0.71 0.33 1820.0 1.82E+03 Puck 4 139 2 6/21/12 1425 6/21/12 14:15 600 343 0.61 0.39 2000.0 2.00E+03 2 6/21/12 1505 6/21/12 14:54 600 343 0.38 0.43 2270.0 2.27E+03 Puck 5 138 2.5 6/25/12 740 6/25/12 7:30 600 339 0.54 0.36 2130.0 2.13E+03 2.5 6/25/12 753 6/25/12 7:43 600 339 0.51 0.34 1520.0 1.52E+03 Puck 6 136 3 6/25/12 815 6/25/12 8:05 600 339 0.44 0.32 1420.0 1.42E+03 3 6/25/12 830 6/25/12 8:19 600 339 0.42 0.28 1130.0 1.13E+03 Puck 7 140 3.5 6/25/12 840 6/25/12 8:30 600 339 0.48 0.24 1330.0 1.33E+03 3.5 6/25/12 903 6/25/12 8:52 600 339 0.46 0.40 2000.0 2.00E+03 Puck 8 136 4 7/3/12 705 6/28/12 13:54 1000 336 0.34 0.19 1740.0 1.74E+03 4 6/25/12 927 6/25/12 9:16 600 339 0.31 0.21 715.0 7.16E+02 Puck 9 138 4.5 6/25/12 941 6/25/12 9:32 600 339 0.31 0.30 740.0 7.41E+02 4.5 7/3/12 733 6/28/12 13:36 1000 336 0.20 0.16 1670.0 1.67E+03 Puck 10 135 5 6/25/12 1048 6/25/12 10:38 600 339 0.33 0.28 1650.0 1.65E+03 Page 45 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105105-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 6.18 0.82 9618.3 Puck 1 5.3 0.8 9598.7 4.41 0.76 9579.1 1.98 0.62 8620.2 Puck 2 1.7 0.6 7392.5 1.49 0.57 6164.7 0.77 0.28 1624.2 Puck 3 0.8 0.3 1653.7 0.90 0.28 1683.1 0.63 0.24 1780.9 Puck 4 0.6 0.3 1869.0 0.54 0.28 1957.0 0.34 0.31 2221.2 Puck 5 0.4 0.3 2153.0 0.48 0.26 2084.8 0.45 0.25 1487.7 Puck 6 0.4 0.2 1438.8 0.39 0.24 1389.9 0.37 0.20 1106.0 Puck 7 0.4 0.2 1203.9 0.43 0.18 1301.8 0.41 0.29 1957.5 Puck 8 0.4 0.2 1830.5 0.30 0.14 1703.4 0.27 0.16 699.8 Puck 9 0.3 0.2 712.1 0.27 0.22 724.3 0.18 0.12 1634.9 Puck 10 0.2 0.2 1624.9 0.29 0.20 1615.0 Page 46 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 U2 Hot Pipe Chase Core Collection Date 5/29/12 B105106-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 7/9/12 1102 7/9/12 10:41 1000 176 3.86 0.23 2770.0 2.77E+03 Puck 1 136 0.5 7/9/12 1120 7/9/12 10:41 1000 176 3.11 0.22 2300.0 2.30E+03 0.5 7/9/12 1141 7/9/12 10:52 1000 176 2.26 0.24 2090.0 2.09E+03 Puck 2 112.12 1 7/9/12 1200 7/9/12 10:53 1000 176 2.12 0.24 2140.0 2.14E+03 1 7/9/12 1220 7/9/12 10:54 1000 176 1.54 0.22 2030.0 2.03E+03 Puck 3 108.45 1.5 7/9/12 1243 7/9/12 10:54 1000 176 1.43 0.21 2070.0 2.07E+03 1.5 7/9/12 1318 7/9/12 10:54 1000 176 1.88 0.17 1090.0 1.09E+03 Puck 4 112.48 2 7/9/12 1337 7/9/12 10:55 1000 176 2.19 0.21 1110.0 1.11E+03 2 7/9/12 1356 7/9/12 10:55 1000 176 0.83 0.14 419.0 4.20E+02 Puck 5 113.98 2.5 7/9/12 1414 7/9/12 10:56 1000 176 0.70 0.15 423.0 4.24E+02 2.5 7/9/12 1510 7/9/12 14:53 1000 176 1.54 0.19 554.0 5.56E+02 Puck 6 108.17 3 7/9/12 1451 7/9/12 10:56 1000 176 1.24 0.19 515.0 5.16E+02 3 7/9/12 1530 7/9/12 10:57 1000 176 1.62 0.17 805.0 8.07E+02 Puck 7 113.41 3.5 7/9/12 1548 7/9/12 10:57 1000 176 1.54 0.17 852.0 8.54E+02 3.5 7/10/12 607 7/9/12 10:58 1000 176 1.18 0.16 623.0 6.24E+02 Puck 8 104.26 4 7/10/12 628 7/10/12 10:58 1000 175 1.14 0.14 530.0 5.31E+02 4 10/17/12 1347 10/17/12 13:29 1000 76 0.70 0.10 198.0 1.99E+02 Puck 9 107.14 4.5 10/17/12 1404 10/17/12 13:29 1000 76 0.61 0.12 164.0 1.65E+02 Page 47 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105106-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 3.62 0.19 2739.3 Puck 1 3.3 0.2 2.51E+03 2.92 0.19 2274.5 2.12 0.20 2066.8 Puck 2 2.1 0.2 2091.6 1.99 0.20 2116.3 1.45 0.18 2007.5 Puck 3 1.4 0.2 2027.3 1.34 0.18 2047.1 1.76 0.14 1077.9 Puck 4 1.9 0.2 1087.8 2.06 0.18 1097.7 0.78 0.12 414.4 Puck 5 0.7 0.1 416.3 0.66 0.13 418.3 1.45 0.16 547.9 Puck 6 1.3 0.2 528.6 1.16 0.16 509.3 1.52 0.14 796.1 Puck 7 1.5 0.1 819.3 1.45 0.15 842.6 1.11 0.13 616.1 Puck 8 1.1 0.1 570.1 1.07 0.12 524.2 0.68 0.09 197.0 Puck 9 0.6 0.1 180.1 0.60 0.11 163.2 Page 48 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 U2 Hot Pipe Chase Core Collection Date 6/16/12 B105106-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 7/18/12 757 7/18/12 7:35 1000 167 17.50 2.28 3090.0 3.11E+03 Puck 1 126 0.5 7/18/12 815 7/18/12 7:35 1000 167 10.40 0.66 1240.0 1.25E+03 0.5 7/18/12 915 7/18/12 8:56 1000 167 0.31 0.09 0.4 7.99E-01 Puck 2 127.8 1 7/18/12 931 7/18/12 8:56 1000 167 0.23 0.11 0.5 7.99E-01 B105106-CJFCCV-002 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 16.48 1.95 3057.5 Puck 1 13.1 1.3 2142.2 9.79 0.56 1227.0 0.29 0.08 0.4 Puck 2 0.3 0.1 0.4 0.22 0.10 0.5 Page 49 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 HUT Core Collection Date 3/28/13 B105107-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 4/2/13 1345 4/2/13 8:00 1000 -91 11.80 0.35 117.0 1.29E+02 Puck 1 113.15 0.5 4/2/13 1440 4/2/13 8:00 1000 -91 7.88 0.26 61.0 6.91E+01 0.5 4/3/13 1520 4/2/13 14:58 1195 -91 0.73 0.07 1.5 2.32E+00 Puck 2 123.91 1 4/2/13 1443 4/2/13 14:03 1000 -91 0.43 0.10 1.4 1.90E+00 1 4/2/13 1000 4/2/13 14:43 1000 -91 0.26 0.12 0.9 1.30E+00 Puck 3 114.26 1.5 4/3/13 1537 4/3/13 15:16 1158.9 -92 0.22 0.08 1.2 1.46E+00 1.5 4/2/13 1508 4/2/13 14:50 1000 -91 0.25 0.12 1.1 1.43E+00 Puck 4 111.07 2 4/2/13 1528 4/2/13 14:50 1000 -91 0.23 0.04 1.2 1.45E+00 2 4/2/13 1527 4/2/13 15:05 1000 -91 0.23 0.07 1.4 1.66E+00 Puck 5 105.53 2.5 4/3/13 1545 4/3/13 15:25 1081.4 -92 0.23 0.13 1.6 1.90E+00 2.5 4/2/13 1551 4/2/13 15:05 1000 -91 0.20 0.10 1.2 1.50E+00 Puck 6 111.49 3 4/3/13 651 4/3/13 15:06 1000 -92 0.27 0.13 1.0 1.37E+00 3 4/3/13 1555 4/3/13 15:38 1000 -92 0.28 0.11 0.9 1.28E+00 Puck 7 118.67 3.5 4/4/13 721 4/4/13 7:03 1000 -93 0.23 0.11 0.8 1.15E+00 3.5 4/3/13 713 4/2/13 15:07 1000 -91 0.19 0.11 0.7 9.49E-01 Puck 8 126.57 4 4/3/13 735 4/2/13 15:08 1000 -91 0.22 0.11 0.7 1.04E+00 4 4/3/13 734 4/2/13 15:09 1000 -91 0.13 0.09 0.7 9.08E-01 Puck 9 119.03 4.5 4/3/13 752 4/2/13 15:09 1000 -91 0.13 0.08 0.8 9.68E-01 4.5 4/3/13 753 4/2/13 15:09 1000 -91 0.23 0.02 0.4 6.98E-01 Puck 10 128.49 5 4/3/13 1605 4/2/13 15:48 1000 -91 0.15 0.09 0.5 7.59E-01 5 4/3/13 816 4/2/13 7:57 1000 -91 0.15 0.10 0.9 1.17E+00 Puck 11 115.96 5.5 4/4/13 753 4/4/13 7:04 1600 -93 0.10 0.07 0.8 9.84E-01 Puck 12 5.5 117.9 4/3/13 846 4/2/13 8:07 1000 -91 0.17 0.12 0.5 8.38E-01 Page 50 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 HUT Core Collection Date 3/28/13 B105107-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 6 4/3/13 907 4/2/13 8:08 1000 -91 0.25 0.04 0.7 9.75E-01 6 4/3/13 906 4/2/13 8:10 1000 -91 0.16 0.07 1.2 1.40E+00 Puck 13 159.84 7.25 4/3/13 927 4/2/13 8:11 1000 -91 0.16 0.06 1.6 1.83E+00 7.25 4/3/13 928 4/2/13 8:16 1000 -91 0.39 0.11 2.9 3.40E+00 Puck 14 96 7.5 Discontinuous Section 7.5 Puck 15 0 8 4/3/13 948 4/2/13 8:17 1000 -91 0.33 0.13 2.6 3.06E+00 8 4/3/13 947 4/2/13 8:18 1000 -91 0.19 0.11 1.4 1.69E+00 Puck 16 104.27 8.5 4/3/13 1005 4/2/13 8:18 1000 -91 0.20 0.11 1.5 1.82E+00 8.5 4/3/13 1012 4/2/13 8:20 1000 -91 0.25 0.06 2.0 2.32E+00 Puck 17 197.58 9.5 4/3/13 1116 4/2/13 8:20 1000 -91 0.15 0.06 1.6 1.81E+00 10 4/3/13 1024 4/2/13 8:21 1000 -91 0.12 0.09 0.6 7.98E-01 Puck 18 119.91 10.5 4/3/13 1115 4/2/13 8:22 1000 -91 0.13 0.08 0.5 7.34E-01 10.5 4/3/13 1139 4/2/13 8:22 1000 -91 0.15 0.11 0.4 6.71E-01 Puck 19 117.57 11 4/3/13 1243 4/2/13 8:25 1000 -91 0.17 0.14 0.5 7.75E-01 11 4/3/13 1244 4/2/13 12:15 1000 -91 0.12 0.07 0.6 7.45E-01 Puck 20 120.33 11.5 4/3/13 1306 4/2/13 12:15 1000 -91 0.10 0.10 0.5 6.83E-01 11.5 4/3/13 1307 4/2/13 12:16 1000 -91 0.18 0.11 0.6 8.42E-01 Puck 21 112.12 12 4/3/13 1344 4/2/13 12:17 1000 -91 0.20 0.10 0.7 1.02E+00 12 4/3/13 1345 4/2/13 12:18 1000 -91 0.13 0.09 0.6 8.54E-01 Puck 22 120.45 12.5 4/3/13 1411 4/2/13 12:18 1000 -91 0.11 0.06 0.7 8.54E-01 12.5 4/3/13 1412 4/2/13 12:19 1000 -91 0.21 0.10 0.5 8.52E-01 Puck 23 115.79 13 4/3/13 1433 4/2/13 12:19 1000 -91 0.19 0.14 0.6 9.31E-01 Page 51 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 HUT Core Collection Date 3/28/13 B105107-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 13 4/3/13 1432 4/2/13 12:20 1000 -91 0.14 0.08 0.7 9.31E-01 Puck 24 113.86 13.5 4/3/13 1451 4/2/13 12:21 1000 -91 0.13 0.07 0.8 1.02E+00 13.5 4/3/13 1453 4/2/13 12:21 1000 -91 0.15 0.11 0.7 9.56E-01 Puck 25 111.5 14 4/3/13 1511 4/2/13 12:22 1000 -91 0.25 0.07 0.8 1.11E+00 B105107-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 12.19 0.38 117.7 Puck 1 10.2 0.3 89.5 8.14 0.28 61.4 0.75 0.07 1.5 Puck 2 0.6 0.1 1.5 0.45 0.11 1.4 0.26 0.13 0.9 Puck 3 0.2 0.1 1.0 0.23 0.08 1.2 0.26 0.13 1.1 Puck 4 0.2 0.1 1.1 0.23 0.04 1.2 0.23 0.08 1.4 Puck 5 0.2 0.1 1.5 0.23 0.14 1.6 0.20 0.11 1.2 Puck 6 0.2 0.1 1.1 0.28 0.14 1.0 Puck 7 0.29 0.12 0.9 0.3 0.1 0.9 Page 52 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105107-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.24 0.12 0.8 0.20 0.11 0.7 Puck 8 0.2 0.1 0.7 0.23 0.11 0.7 0.13 0.09 0.7 Puck 9 0.1 0.1 0.7 0.13 0.09 0.8 0.23 0.03 0.5 Puck 10 0.2 0.1 0.5 0.15 0.10 0.5 0.15 0.11 0.9 Puck 11 0.1 0.1 0.9 0.11 0.07 0.8 0.17 0.13 0.5 Puck 12 0.2 0.1 0.6 0.26 0.04 0.7 0.17 0.08 1.2 Puck 13 0.2 0.1 1.4 0.17 0.07 1.6 0.41 0.12 2.9 Puck 14 0.4 0.1 2.8 0.0 0.0 0.0 0.0 0.0 0.0 Puck 15 0.4 0.1 2.8 0.35 0.14 2.6 0.20 0.12 1.4 Puck 16 0.2 0.1 1.5 0.21 0.12 1.5 0.26 0.06 2.0 Puck 17 0.2 0.1 1.8 0.15 0.07 1.6 0.12 0.10 0.6 Puck 18 0.1 0.1 0.6 0.13 0.09 0.5 0.16 0.12 0.4 Puck 19 0.2 0.1 0.4 0.18 0.15 0.5 Page 53 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105107-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.13 0.08 0.6 Puck 20 0.1 0.1 0.5 0.11 0.10 0.5 0.18 0.12 0.6 Puck 21 0.2 0.1 0.6 0.20 0.11 0.7 0.14 0.10 0.6 Puck 22 0.1 0.1 0.7 0.12 0.07 0.7 0.21 0.11 0.5 Puck 23 0.2 0.1 0.6 0.20 0.15 0.6 0.14 0.08 0.7 Puck 24 0.1 0.1 0.8 0.13 0.08 0.8 0.16 0.12 0.7 Puck 25 0.2 0.1 0.7 0.26 0.08 0.8 Aux 542 Common Area Core Collection Date 5/22/12 B105108-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 7/18/12 1259 7/18/12 12:41 1000 167 0.43 0.14 1920.00 1.92E+03 Puck 1 83.0 0.5 7/18/12 1319 7/18/12 12:42 1000 167 0.39 0.25 1890.00 1.89E+03 0.5 7/18/12 1338 7/18/12 12:43 1000 167 0.25 0.19 629.00 6.29E+02 Puck 2 96.0 1 7/18/12 1356 7/18/12 12:43 1000 167 0.21 0.24 470.00 4.70E+02 Puck 3 1 101.0 7/18/12 1414 7/18/12 12:44 1000 167 0.12 0.22 146.00 1.46E+02 Page 54 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 Common Area Core Collection Date 5/22/12 B105108-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 1.5 7/18/12 1432 7/18/12 12:44 1000 167 0.22 0.14 144.00 1.44E+02 1.5 7/18/12 1451 7/18/12 12:45 1000 167 0.27 0.14 69.30 6.97E+01 Puck 4 103.0 2 7/18/12 1510 7/18/12 12:45 1000 167 0.12 0.18 56.80 5.71E+01 2 10/24/12 1144 10/24/12 11:27 1000 69 0.15 0.22 55.20 5.56E+01 Puck 5 100.2 2.5 10/24/12 1201 10/24/12 11:27 1000 69 0.17 0.17 57.10 5.74E+01 2.5 10/24/12 1219 10/24/12 12:01 1000 69 0.14 0.15 31.80 3.21E+01 Puck 6 132.6 3 10/24/12 1236 10/24/12 12:01 1000 69 0.13 0.11 28.50 2.87E+01 3 10/24/12 1254 10/24/12 12:31 1000 69 0.15 0.08 16.70 1.69E+01 Puck 7 150.6 3.5 10/24/12 1311 10/24/12 12:31 1000 69 0.15 0.10 17.20 1.75E+01 3.5 10/24/12 1330 10/24/12 13:13 1000 69 0.09 0.10 30.80 3.10E+01 Puck 8 147.9 4 10/24/12 1348 10/24/12 13:13 1000 69 0.12 0.11 34.20 3.44E+01 4 10/24/12 1405 10/24/12 13:47 1000 69 0.13 0.11 17.40 1.76E+01 Puck 9 151.5 4.5 10/24/12 1348 10/24/12 13:47 1000 69 0.18 0.11 13.10 1.34E+01 B105108-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.41 0.12 1899.81 Puck 1 0.4 0.2 1885.0 0.36 0.21 1870.13 0.24 0.17 622.39 Puck 2 0.2 0.2 543.7 0.19 0.21 465.06 Page 55 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105108-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.11 0.19 144.46 Puck 3 0.2 0.2 143.5 0.21 0.12 142.49 0.25 0.12 68.57 Puck 4 0.2 0.1 62.4 0.11 0.16 56.20 0.14 0.20 54.96 Puck 5 0.2 0.2 55.9 0.17 0.16 56.85 0.13 0.14 31.66 Puck 6 0.1 0.1 30.0 0.13 0.10 28.38 0.14 0.07 16.63 Puck 7 0.1 0.1 16.9 0.14 0.10 17.13 0.09 0.09 30.67 Puck 8 0.1 0.1 32.4 0.11 0.11 34.05 0.13 0.10 17.32 Puck 9 0.1 0.1 15.2 0.17 0.10 13.04 Page 56 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 Common Central Area Core Collection Date 5/15/12 B105108-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 6/20/12 1345 6/20/12 13:35 600 195 2.80 0.35 113.00 1.16E+02 Puck 1 130.0 0.5 6/20/12 1356 6/20/12 13:46 600 195 2.43 0.45 64.90 6.78E+01 0.5 6/20/12 1408 6/20/12 13:58 600 195 2.02 0.27 20.40 2.27E+01 Puck 2 124.0 1 6/20/12 1420 6/20/12 14:09 600 195 2.01 0.32 18.90 2.12E+01 1 7/16/12 1046 7/9/12 13:51 1000 176 1.56 0.18 8.43 1.02E+01 Puck 3 125.0 1.5 7/16/12 1104 7/9/12 13:51 1000 176 1.60 0.13 7.82 9.55E+00 1.5 7/16/12 1123 7/9/12 13:51 1000 176 1.60 0.18 14.90 1.67E+01 Puck 4 129.0 2 7/16/12 1221 7/9/12 13:52 1000 176 1.46 0.18 15.50 1.71E+01 2 10/17/12 1202 10/17/12 10:20 1000 76 1.50 0.17 21.20 2.29E+01 Puck 5 141.5 2.5 10/13/02 1206 10/17/13 10:21 1000 -289 1.54 0.17 19.90 2.16E+01 2.5 10/17/12 1209 10/17/12 11:23 1000 76 0.46 0.13 8.41 9.00E+00 Puck 6 146.2 3 10/17/12 1303 10/17/12 12:39 1400 76 0.58 0.08 7.18 7.84E+00 3 10/17/12 1218 10/17/12 12:01 1000 76 0.35 0.09 3.09 3.54E+00 Puck 7 157.6 3.5 10/17/12 1236 10/17/12 12:01 1000 76 0.48 0.11 2.47 3.06E+00 3.5 10/17/12 1325 10/17/12 13:08 1000 76 0.39 0.09 0.83 1.32E+00 Puck 8 121.1 4 Bottom Irregular Geometry - Not Analyzed Page 57 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105108-CJFCCV-002 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 2.61 0.29 111.61 Puck 1 2.4 0.3 87.9 2.27 0.37 64.10 1.88 0.23 20.15 Puck 2 1.9 0.2 19.4 1.87 0.26 18.67 1.46 0.15 8.34 Puck 3 1.5 0.1 8.0 1.50 0.11 7.73 1.50 0.15 14.73 Puck 4 1.4 0.2 15.0 1.37 0.15 15.33 1.46 0.16 21.10 Puck 5 1.6 0.2 20.7 1.71 0.23 20.27 0.44 0.12 8.37 Puck 6 0.5 0.1 7.8 0.56 0.08 7.15 0.34 0.09 3.08 Puck 7 0.4 0.1 2.8 0.47 0.10 2.46 0.38 0.09 0.83 0.4 0.1 0.8 Puck 8 Bottom Irregular Geometry - Not Analyzed Page 58 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 Common Central Area Core Collection Date 5/15/12 B105108-CJFCCV-003 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 7/17/12 818 7/10/12 13:18 1000 175 30.30 0.45 1670.00 1.70E+03 Puck 1 125.0 0.5 7/17/12 837 7/10/12 13:19 1000 175 16.20 0.32 787.00 8.04E+02 0.5 7/17/12 855 7/10/12 13:19 1000 175 0.33 0.09 5.06 5.48E+00 Puck 2 131.0 1 7/17/12 912 7/10/12 13:21 1000 175 0.41 0.13 3.67 4.21E+00 1 10/17/12 1432 10/17/12 14:15 1000 76 0.16 0.10 1.09 1.35E+00 Puck 3 143.2 1.5 10/17/12 1455 10/17/12 14:15 1000 76 0.21 0.03 0.85 1.08E+00 1.5 10/23/12 727 10/23/12 7:10 1000 70 0.27 0.16 0.51 9.38E-01 Puck 4 107.5 2 10/23/12 746 10/23/12 7:11 1000 70 0.16 0.14 0.29 5.87E-01 2 10/23/12 805 10/23/12 7:48 1000 70 0.15 0.10 0.12 3.59E-01 Puck 5 123.7 2.5 10/23/12 823 10/23/12 7:48 1000 70 0.04 0.14 0.19 3.64E-01 2.5 10/23/12 845 10/23/12 8:28 1000 70 0.12 0.09 0.13 3.44E-01 Puck 6 140.9 3 10/23/12 920 10/23/12 9:02 1000 70 0.13 0.10 0.16 3.94E-01 B105108-CJFCCV-003 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 28.45 0.38 1651.60 Puck 1 21.8 0.3 1.21E+03 15.21 0.28 778.33 0.31 0.08 5.00 Puck 2 0.3 0.1 4.3 0.38 0.11 3.63 Page 59 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105108-CJFCCV-003 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.15 0.10 1.08 Puck 3 0.2 0.1 1.0 0.20 0.03 0.84 0.27 0.15 0.51 Puck 4 0.2 0.1 0.4 0.16 0.13 0.29 0.14 0.09 0.12 Puck 5 0.1 0.1 0.2 0.04 0.13 0.19 0.12 0.09 0.13 Puck 6 0.1 0.1 0.1 0.13 0.09 0.16 Aux 542 Common Elevator Shaft Core Collection Date 3/6/13 B105108-CJFCCV-004 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 3/11/13 857 3/11/13 8:36 1000 -69 4.05 0.25 151.00 1.55E+02 Puck 1 109.5 0.5 3/11/13 916 3/11/13 8:36 1000 -69 2.34 0.20 71.90 7.44E+01 0.5 3/11/13 858 3/11/13 8:37 1000 -69 0.16 0.08 0.14 3.80E-01 Puck 2 129.9 1 3/11/13 917 3/11/13 8:38 1000 -69 0.13 0.07 0.11 3.00E-01 1 3/11/13 919 3/11/13 8:38 1000 -69 0.13 0.10 0.19 4.17E-01 Puck 3 103.9 1.5 3/11/13 937 3/11/13 8:39 1000 -69 0.15 0.16 0.15 4.57E-01 1.5 3/11/13 921 3/11/13 8:39 1000 -69 0.13 0.07 0.13 3.30E-01 Puck 4 117.9 2 3/11/13 939 3/11/13 8:39 1000 -69 0.11 0.11 0.11 3.25E-01 Page 60 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 Common Elevator Shaft Core Collection Date 3/6/13 B105108-CJFCCV-004 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 2 3/11/13 1005 3/11/13 9:56 1000 -69 0.15 0.12 0.19 4.65E-01 Puck 5 120.1 2.5 3/11/13 1023 3/11/13 9:57 1000 -69 0.11 0.11 0.15 3.74E-01 2.5 3/11/13 1025 3/11/13 9:58 1000 -69 0.10 0.10 0.11 3.14E-01 Puck 6 123.1 3 3/11/13 1006 3/11/13 9:57 1000 -69 0.08 0.10 0.11 2.91E-01 3 3/11/13 1042 3/11/13 9:58 1000 -69 0.14 0.13 0.20 4.66E-01 Puck 7 113.2 3.5 3/11/13 1102 3/11/13 9:59 1000 -69 0.18 0.13 0.13 4.29E-01 3.5 3/11/13 1043 3/11/13 10:01 1000 -69 0.07 0.09 0.13 2.86E-01 Puck 8 117.2 4 3/11/13 1101 3/11/13 10:01 1000 -69 0.10 0.08 0.12 3.05E-01 B105108-CJFCCV-004 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 4.15 0.26 151.66 Puck 1 3.3 0.2 111.9 2.40 0.21 72.21 0.16 0.09 0.14 Puck 2 0.1 0.1 0.1 0.13 0.07 0.11 0.13 0.11 0.19 Puck 3 0.1 0.1 0.2 0.15 0.17 0.15 0.13 0.08 0.13 Puck 4 0.1 0.1 0.1 0.11 0.12 0.11 Page 61 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105108-CJFCCV-004 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.15 0.13 0.19 Puck 5 0.1 0.1 0.2 0.12 0.12 0.15 0.11 0.10 0.11 Puck 6 0.1 0.1 0.1 0.08 0.11 0.11 0.14 0.14 0.20 Puck 7 0.2 0.1 0.2 0.18 0.14 0.13 0.07 0.10 0.13 Puck 8 0.1 0.1 0.1 0.10 0.09 0.12 Aux 542 South Area Core Collection Date 5/23/12 B105109-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Decay Days pCi/g pCi/g pCi/g pCi/g 0 7/17/12 932 7/10/12 13:22 1000 175 4.22 0.16 1430.00 1.43E+03 Puck 1 125.0 0.5 7/17/12 952 7/10/12 13:25 1000 175 2.21 0.19 638.00 6.40E+02 0.5 7/17/12 1314 7/10/12 13:25 1000 175 0.10 0.08 0.39 5.70E-01 Puck 2 126.0 1 7/17/12 1337 7/10/12 13:26 1000 175 0.16 0.13 0.26 5.47E-01 B105109-CJFCCV-001 Decay Corrected Results Page 62 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 3.96 0.14 1414.25 Puck 1 3.0 0.1 1022.6 2.07 0.16 630.97 0.09 0.07 0.38 Puck 2 0.1 0.1 0.3 0.15 0.11 0.26 Aux 542 North Area Core Collection Date 5/22/12 B105110-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 7/24/12 1322 7/18/12 13:28 1000 167 8.09 0.31 2110.00 2.11E+03 Puck 1 120.0 0.5 7/24/12 1340 7/18/12 13:38 1000 167 4.97 0.26 1050.00 1.06E+03 0.5 7/24/12 1358 7/18/12 13:38 1000 167 0.20 0.12 0.61 9.29E-01 Puck 2 137.0 1 7/24/12 1417 7/18/12 13:39 1000 167 0.26 0.06 0.50 8.20E-01 B105110-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 7.62 0.27 2087.81 Puck 1 6.1 0.2 1563.4 4.68 0.22 1038.96 0.19 0.10 0.61 Puck 2 0.2 0.1 0.5 0.25 0.05 0.49 Page 63 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 North Area Core Collection Date 5/14/12 B105110-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 7/11/12 917 7/9/12 13:40 1000 176 0.33 0.13 63.70 6.42E+01 Puck 1 129.0 0.5 7/11/12 936 7/9/12 13:41 1000 176 0.17 0.18 25.20 2.56E+01 0.5 10/24/12 1439 10/24/12 14:19 1000 69 0.03 0.10 0.19 3.26E-01 Puck 2 133.1 1 10/24/12 1456 10/24/12 14:19 1000 69 0.12 0.08 0.14 3.30E-01 1 10/24/12 1515 10/24/12 14:57 1000 69 0.03 0.11 0.15 2.95E-01 Puck 3 135.8 1.5 10/24/12 1532 10/24/12 14:57 1000 69 0.04 0.11 0.19 3.32E-01 B105110-CJFCCV-0022 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.31 0.11 62.99 Puck 1 0.2 0.1 44.0 0.16 0.15 24.92 0.03 0.09 0.19 Puck 2 0.1 0.1 0.2 0.11 0.07 0.13 0.03 0.10 0.15 Puck 3 0.03 0.1 0.2 0.04 0.10 0.19 Page 64 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 East Area Core Collection Date 5/22/12 B105111-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 6/25/12 959 6/25/12 9:49 600 190 2.06 0.56 1130.00 1.13E+03 Puck 1 120.0 0.5 6/25/12 1010 6/25/12 10:00 600 190 1.47 0.44 803.00 8.05E+02 0.5 6/28/12 956 6/28/12 9:37 600 187 0.86 0.16 343.00 3.44E+02 Puck 2 118.0 1 7/2/12 1434 6/28/12 13:37 1000 187 0.91 0.22 310.00 3.11E+02 1 7/2/12 1416 6/28/12 13:31 1000 187 0.62 0.20 127.00 1.28E+02 Puck 3 116.0 1.5 6/25/12 1201 6/25/12 11:51 600 190 0.46 0.71 120.00 1.21E+02 1.5 6/25/12 1215 6/25/12 12:05 600 190 1.58 0.45 259.00 2.61E+02 Puck 4 116.0 2 6/25/12 1226 6/25/12 12:16 600 190 1.37 0.34 268.00 2.70E+02 2 6/25/12 1237 6/25/12 12:26 600 190 0.53 0.26 96.60 9.74E+01 Puck 5 132.0 2.5 7/2/12 1505 6/28/12 13:35 1000 187 0.48 0.15 88.90 8.95E+01 2.5 7/3/12 630 6/28/12 13:34 1000 187 0.34 0.18 57.40 5.79E+01 Puck 6 114.0 3 6/25/12 1310 6/25/12 13:00 600 190 0.48 0.33 56.10 5.69E+01 3 7/9/12 740 7/9/12 6:44 600 176 0.44 0.18 27.40 2.80E+01 Puck 7 105.0 3.5 7/9/12 750 7/9/12 06;44 600 176 0.42 0.25 31.10 3.18E+01 B105111-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 1.92 0.47 1116.49 Puck 1 1.6 0.4 954.9 1.37 0.37 793.40 Page 65 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105111-CJFCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.80 0.14 338.96 Puck 2 0.8 0.2 322.7 0.85 0.18 306.35 0.58 0.17 125.51 Puck 3 0.5 0.4 122.0 0.43 0.59 118.57 1.48 0.37 255.90 Puck 4 1.4 0.3 260.3 1.28 0.28 264.80 0.49 0.21 95.45 Puck 5 0.5 0.2 91.6 0.45 0.13 87.85 0.32 0.15 56.72 Puck 6 0.4 0.2 56.1 0.45 0.28 55.43 0.41 0.15 27.10 Puck 7 0.4 0.2 28.9 0.40 0.21 30.76 Aux 542 U1 ABEDCT Core Collection Date 5/22/12 B105113-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 7/17/12 1358 7/10/12 13:27 1000 175 196.00 1.47 5690.00 5.89E+03 Puck 1 128.0 0.5 7/17/12 1422 7/10/12 13:27 1000 175 123.00 0.97 2640.00 2.76E+03 0.5 7/17/12 1439 7/10/12 13:27 1000 175 25.90 0.46 178.00 2.04E+02 Puck 2 125.0 1 7/17/12 1458 7/10/12 13:28 1000 175 26.70 0.43 156.00 1.83E+02 Page 66 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 U1 ABEDCT Core Collection Date 5/22/12 B105113-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 1 7/17/12 1517 7/10/12 13:28 1000 175 26.40 0.32 46.00 7.27E+01 Puck 3 129.0 1.5 7/17/12 1537 7/10/12 13:28 1000 175 23.40 0.31 34.70 5.84E+01 1.5 7/18/12 623 7/10/12 13:29 1000 175 9.15 0.21 9.09 1.85E+01 Puck 4 128.0 2 7/18/12 645 7/10/12 13:29 1000 175 7.76 0.22 7.12 1.51E+01 2 10/16/12 1223 10/16/12 12:06 1000 77 4.17 0.12 1.23 5.52E+00 Puck 5 155.4 2.5 10/16/12 1244 10/16/12 12:06 1000 77 4.08 0.12 0.95 5.15E+00 2.5 10/16/12 1303 10/16/12 12:46 1000 77 4.83 0.18 0.99 6.00E+00 Puck 6 129.3 3 10/16/12 1323 10/16/12 12:46 1000 77 4.89 0.16 1.02 6.07E+00 3 10/16/12 1345 10/16/12 13:28 1000 77 2.33 0.13 0.98 3.44E+00 Puck 7 126.9 3.5 10/16/12 1406 10/16/12 13:28 1000 77 1.46 0.09 0.86 2.41E+00 3.5 10/16/12 1430 10/16/12 14:12 1000 77 0.18 0.11 0.44 7.38E-01 Puck 8 130.8 4 10/16/12 1455 10/16/12 14:13 1000 77 0.14 0.11 0.30 5.51E-01 4 10/17/12 633 10/17/12 6:16 1000 76 0.26 0.03 0.21 5.05E-01 Puck 9 122.4 4.5 10/17/12 651 10/17/12 6:16 1000 76 0.28 0.14 0.21 6.41E-01 4.5 10/17/12 752 10/17/12 7:19 1000 76 0.10 0.11 0.14 3.50E-01 Puck 10 134.6 5 10/17/12 734 10/17/12 6:57 1000 76 0.09 0.10 0.15 3.39E-01 5 10/17/12 756 10/17/12 7:55 1000 76 0.26 0.11 0.29 6.47E-01 Puck 11 98.4 0 Bottom Irregular Geometry - Not Analyzed B105113-CJFCCV-001 Decay Corrected Results Page 67 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 184.02 1.25 5627.32 Puck 1 149.8 1.0 4119.1 115.48 0.82 2610.92 24.32 0.39 176.04 Puck 2 24.7 0.4 165.2 25.07 0.36 154.28 24.79 0.27 45.49 Puck 3 23.4 0.3 39.9 21.97 0.26 34.32 8.59 0.18 8.99 Puck 4 7.9 0.2 8.0 7.29 0.19 7.04 4.06 0.11 1.22 Puck 5 4.0 0.1 1.1 3.97 0.11 0.94 4.70 0.17 0.98 Puck 6 4.7 0.2 1.0 4.76 0.15 1.02 2.27 0.12 0.97 Puck 7 1.8 0.1 0.9 1.42 0.09 0.85 0.18 0.10 0.44 Puck 8 0.2 0.1 0.4 0.14 0.10 0.29 0.25 0.03 0.21 Puck 9 0.3 0.1 0.2 0.28 0.13 0.21 0.10 0.10 0.14 Puck 10 0.1 0.1 0.1 0.09 0.09 0.15 0.25 0.10 0.28 0.2 0.1 0.3 Puck 11 Bottom Irregular Geometry - Not Analyzed Page 68 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 U1 ABEDCT Core Collection Date 5/22/12 B105113-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 6/20/12 928 6/20/12 9:31 600 195 37.60 1.32 1790.00 1.83E+03 Puck 1 112.0 0.5 6/20/12 940 6/20/12 9:40 600 195 43.90 1.39 1440.00 1.49E+03 0.5 6/20/12 956 6/20/12 9:56 600 195 15.00 0.75 356.00 3.72E+02 Puck 2 117.0 1 6/21/12 1305 6/21/12 12:55 600 194 15.90 0.73 361.00 3.78E+02 1 6/20/12 1030 6/20/12 10:30 600 195 14.10 0.80 226.00 2.41E+02 Puck 3 119.0 1.5 6/20/12 1046 6/20/12 10:46 600 195 15.40 0.87 238.00 2.54E+02 1.5 6/20/12 1212 6/20/12 12:09 600 195 6.37 0.54 102.00 1.09E+02 Puck 4 116.0 2 6/20/12 1224 6/20/12 12:22 600 195 6.10 0.64 90.50 9.72E+01 2 6/21/12 1249 6/21/12 12:39 600 194 4.39 0.53 69.30 7.42E+01 Puck 5 118.0 2.5 6/20/12 1256 6/20/12 12:57 600 195 4.53 0.42 63.10 6.80E+01 2.5 10/24/12 808 10/24/12 7:50 1000 69 3.30 0.16 20.00 2.35E+01 Puck 6 153.8 3 10/24/12 826 10/24/12 7:51 1000 69 2.89 0.13 16.30 1.93E+01 3 10/24/12 853 10/24/12 8:35 1000 69 2.19 0.12 6.14 8.45E+00 Puck 7 141.9 3.5 10/24/12 911 10/24/12 8:36 1000 69 2.57 0.12 5.90 8.59E+00 3.5 10/24/12 933 10/24/12 9:16 1000 69 1.24 0.12 1.61 2.97E+00 Puck 8 139.9 4 10/24/12 954 10/24/12 9:16 1000 69 1.00 0.11 1.22 2.33E+00 4 10/24/12 1012 10/24/12 9:55 1000 69 0.22 0.09 0.17 4.79E-01 Puck 9 155.6 4.5 10/24/12 1029 10/24/12 9:55 1000 69 0.16 0.09 0.23 4.68E-01 4.5 10/24/12 1048 10/24/12 10:30 1000 69 0.07 0.08 0.11 2.58E-01 Puck 10 174.8 5 10/24/12 1106 10/24/12 10:30 1000 69 0.10 0.07 0.09 2.56E-01 5 10/24/12 1107 10/24/12 11:05 1000 69 0.13 1.00 0.32 1.46E+00 Puck 11 0.0 0 Bottom Irregular Geometry - Not Analyzed Page 69 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 B105113-CJFCCV-002 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 35.05 1.10 1768.04 Puck 1 38.0 1.1 1595.2 40.92 1.16 1422.33 13.98 0.63 351.63 Puck 2 14.4 0.6 354.1 14.83 0.61 356.59 13.14 0.67 223.23 Puck 3 13.7 0.7 229.2 14.36 0.73 235.08 5.94 0.45 100.75 Puck 4 5.8 0.5 95.1 5.69 0.53 89.39 4.09 0.44 68.45 Puck 5 4.2 0.4 65.4 4.22 0.35 62.33 3.22 0.15 19.91 Puck 6 3.0 0.1 18.1 2.82 0.12 16.23 2.14 0.11 6.11 Puck 7 2.3 0.1 6.0 2.51 0.11 5.87 1.21 0.11 1.60 Puck 8 1.1 0.1 1.4 0.98 0.11 1.21 0.22 0.08 0.17 Puck 9 0.2 0.1 0.2 0.15 0.08 0.23 0.07 0.07 0.11 Puck 10 0.1 0.1 0.1 0.10 0.06 0.09 0.13 0.94 0.32 0.1 0.9 0.3 Puck 11 Bottom Irregular Geometry - Not Analyzed Page 70 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Aux 542 East Wall Core Collection Date 5/30/12 B105111-CJWCCV-002 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 6/20/12 1311 6/20/12 11:59 600 195 0.19 0.18 0.95 1.13E+00 Puck 1 135.0 0.5 6/20/12 1323 6/20/12 13:24 600 195 0.29 0.22 0.43 9.28E-01 B105111-CJWCCV-002 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.18 0.15 0.94 Puck 1 0.2 0.2 0.7 0.27 0.18 0.42 Page 71 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 Unit 1 AEDCT Room Core Collection Date 5/23/12 B105113-CJWCCV-003 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 8/22/12 1402 8/22/12 14:01 300 132 671.00 31.00 16600.00 1.66E+04 Puck 1 136.0 0.5 8/22/12 1418 8/22/12 14:03 300 132 505.00 29.90 11300.00 1.18E+04 0.5 7/19/12 1413 7/19/12 13:55 1000 166 0.54 0.12 0.86 1.52E+00 Puck 2 134.0 1 7/19/12 1414 7/19/12 13:56 1000 166 0.36 0.11 0.78 1.25E+00 B105113-CJWCCV-003 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 639.83 27.45 16461.87 Puck 1 560.7 27.0 13833.9 481.54 26.47 11205.97 0.51 0.11 0.85 Puck 2 0.4 0.1 0.8 0.34 0.09 0.77 Page 72 of 92

Attachment 2 TSD 14-013 542 Auxiliary Building Cores In-House Gamma Spectroscopy Results Revision 0 AUX 542 U2 EDT Core Collection Date 6/4/12 B105114-CJWCCV-001 Decay To Date 1/1/13 Gamma Spec Gamma Spec Report Sample Report Taken On Decay Const y-1 0.13 0.34 0.02310 Count Core wt time Decay Co-60 Cs-134 Cs-137 Total Section Depth (gms) Date Time Date Time sec Days pCi/g pCi/g pCi/g pCi/g 0 7/9/12 1022 7/9/12 9:54 1000 176 24.60 1.38 4530.00 4.53E+03 Puck 1 136.0 0.5 7/9/12 946 7/9/12 9:28 1000 176 12.30 0.64 1820.00 1.83E+03 0.5 6/20/12 830 6/20/12 8:30 600 195 0.52 0.22 0.40 1.14E+00 Puck 2 128.0 1 6/20/12 854 6/20/12 8:41 1800 195 0.50 0.30 0.48 1.27E+00 B105114-CJWCCV-001 Decay Corrected Results Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Puck Puck Puck Core Decayed Decayed Decayed Avg Avg Avg Section pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 23.09 1.17 4479.81 Puck 1 17.3 0.9 3139.8 11.54 0.54 1799.84 0.48 0.18 0.40 Puck 2 0.5 0.2 0.4 0.46 0.25 0.47 Page 73 of 92

Attachment 3 TSD 14-013 Eberline Off-Site Laboratory Results Revision 0 Aux 542 Aux 542 AUX 542 AUX 542 Aux 542 U2 Hot Common Unit 1 1A RHR 2A RHR U1 Pipe Pipe Central AEDCT Sample ID Pump Pump Tunnel Chase Area Room Eberline WO 12-09081 12-09081 12-09081 12-09081 12-09081 12-09081 Eberline Sample Date 9/19/2012 9/19/2012 9/19/2012 9/19/2012 9/19/2012 9/19/2012 B105101- B105103- B105105- B105108- B105108- B105113-Decay CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJWCCV-Nuclide Const yr-1 001 001 001 003 003 003 H-3 5.63E-02 1.23E+01 1.68E+01 6.98E+00 2.96E+01 5.61E+00 4.71E+00 C-14 1.22E-04 2.27E+00 4.88E+00 9.98E-01 1.48E+00 1.19E+00 3.10E+00 Fe-55 2.53E-01 1.19E+01 3.16E+01 1.81E+01 1.12E+01 8.17E+00 1.73E+01 Ni-59 6.86E-06 1.59E+01 2.08E+01 1.81E+01 1.74E+01 1.67E+01 1.75E+01 Co-60 1.31E-01 2.67E+01 2.28E+02 3.20E+00 1.01E+01 1.83E+01 2.03E+02 Ni-63 6.92E-03 1.52E+02 3.38E+03 2.91E+02 9.18E+01 8.59E+01 1.65E+03 Sr-90 2.41E-02 2.00E+00 5.44E+00 1.52E+00 4.04E-01 3.29E-01 8.82E+00 Nb-94 3.41E-05 2.24E-01 8.17E-01 6.19E-01 2.13E-01 3.02E-01 6.57E-01 Tc-99 3.28E-06 1.45E+00 9.61E-01 6.70E-01 4.73E-01 9.09E-01 5.81E-01 Ag-108m 1.66E-03 2.06E-01 1.66E+00 8.06E-01 2.53E-01 1.82E-01 5.96E-01 Sb-125 2.51E-01 2.27E+00 7.79E+00 4.39E+00 2.46E+00 1.99E+00 4.57E+00 Cs-134 3.36E-01 4.73E-01 1.47E+00 8.63E-01 8.11E-01 2.90E-01 4.97E-01 Cs-137 2.30E-02 1.35E+03 1.33E+04 5.29E+03 1.68E+03 1.05E+03 4.19E+03 Eu-152 5.12E-02 5.89E-01 2.58E+00 1.05E+00 6.75E-01 7.10E-01 1.80E+00 Eu-154 7.88E-02 3.54E-01 1.38E+00 1.19E+00 3.95E-01 3.21E-01 1.05E+00 Eu-155 1.46E-01 5.76E-01 1.76E+00 1.16E+00 6.33E-01 4.84E-01 1.05E+00 Np-237 3.23E-07 2.04E-02 2.13E-02 2.39E-02 2.10E-02 1.92E-02 3.20E-02 Pu-238 7.90E-03 2.39E-02 3.43E-01 1.32E-02 1.37E-02 1.78E-02 1.39E-02 Pu-239 2.87E-05 5.66E-03 1.37E-01 5.41E-03 6.86E-03 6.66E-03 6.75E-03 Pu-240 1.06E-04 5.66E-03 1.37E-01 5.41E-03 6.86E-03 6.66E-03 6.75E-03 Pu-241 4.83E-02 1.70E+00 2.46E+00 1.79E+00 2.36E+00 1.73E+00 1.72E+00 Am-241 1.60E-03 3.03E-02 2.29E-01 4.22E-02 2.72E-02 4.29E-02 3.17E-02 Am-243 9.40E-05 2.89E-02 1.09E-01 6.01E-02 3.62E-02 3.36E-02 3.18E-02 Cm-243 2.43E-02 1.96E-02 2.20E-02 1.88E-02 1.95E-02 2.01E-02 2.15E-02 Cm-244 3.83E-02 1.96E-02 2.20E-02 1.88E-02 1.95E-02 2.01E-02 2.15E-02 Note: Bold Italics = MDA Value Page 74 of 92

Attachment 4 TSD 14-013 Eberline Off-Site Laboratory Decay Corrected Results Revision 0 B105101- B105103- B105105- B105106- B105108-CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV-Sample ID 001 001 001 002 003 Eberline WO 12-09081 12-09081 12-09081 12-09081 12-09081 Eberline Sample Date 9/19/2012 9/19/2012 9/19/2012 9/19/2012 9/19/2012 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years 0.285 0.285 0.285 0.285 0.285 Decay Decay Decay Decay Decay Corrected Corrected Corrected Corrected Corrected Decay Result Result Result Result Result Nuclide Const yr-1 pCi/g pCi/g pCi/g pCi/g pCi/g H-3 5.63E-02 1.21E+01 1.65E+01 6.87E+00 2.92E+01 5.52E+00 C-14 1.22E-04 2.27E+00 4.88E+00 9.98E-01 1.48E+00 1.19E+00 Fe-55 2.53E-01 1.11E+01 2.94E+01 1.68E+01 1.04E+01 7.60E+00 Ni-59 6.86E-06 1.59E+01 2.08E+01 1.81E+01 1.74E+01 1.67E+01 Co-60 1.31E-01 2.57E+01 2.19E+02 3.08E+00 9.69E+00 1.76E+01 Ni-63 6.92E-03 1.52E+02 3.38E+03 2.91E+02 9.16E+01 8.57E+01 Sr-90 2.41E-02 1.99E+00 5.40E+00 1.51E+00 4.02E-01 3.27E-01 Nb-94 3.41E-05 2.24E-01 8.17E-01 6.19E-01 2.13E-01 3.02E-01 Tc-99 3.28E-06 1.45E+00 9.61E-01 6.70E-01 4.73E-01 9.09E-01 Ag-108m 1.66E-03 2.06E-01 1.66E+00 8.06E-01 2.53E-01 1.82E-01 Sb-125 2.51E-01 2.11E+00 7.25E+00 4.09E+00 2.29E+00 1.85E+00 Cs-134 3.36E-01 4.30E-01 1.34E+00 7.84E-01 7.37E-01 2.64E-01 Cs-137 2.30E-02 1.34E+03 1.32E+04 5.26E+03 1.67E+03 1.04E+03 Eu-152 5.12E-02 5.81E-01 2.54E+00 1.04E+00 6.66E-01 6.99E-01 Eu-154 7.88E-02 3.46E-01 1.35E+00 1.16E+00 3.87E-01 3.14E-01 Eu-155 1.46E-01 5.52E-01 1.69E+00 1.11E+00 6.07E-01 4.64E-01 Np-237 3.23E-07 2.04E-02 2.13E-02 2.39E-02 2.10E-02 1.92E-02 Pu-238 7.90E-03 2.39E-02 3.42E-01 1.32E-02 1.37E-02 1.77E-02 Pu-239 2.87E-05 5.66E-03 1.37E-01 5.41E-03 6.86E-03 6.66E-03 Pu-240 1.06E-04 5.66E-03 1.37E-01 5.41E-03 6.86E-03 6.66E-03 Pu-241 4.83E-02 1.68E+00 2.43E+00 1.77E+00 2.32E+00 1.71E+00 Am-241 1.60E-03 3.03E-02 2.29E-01 4.21E-02 2.72E-02 4.29E-02 Am-243 9.40E-05 2.89E-02 1.09E-01 6.01E-02 3.62E-02 3.36E-02 Cm-243 2.43E-02 1.94E-02 2.19E-02 1.87E-02 1.93E-02 2.00E-02 Cm-244 3.83E-02 1.93E-02 2.18E-02 1.86E-02 1.93E-02 1.99E-02 Note: Bold Italics = MDA Value, Page 75 of 92

Attachment 5 TSD 14-013 Eberline Off-Site Laboratory Decay Corrected Results Revision 0 Floor Cores Wall Core B105101- B105103- B105105- B105106- B105108- B105113-CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJWCCV-Core ID 001 001 001 002 003 003 Eberline Report 12-09081 12-09081 12-09081 12-09081 12-09081 12-09081 Gross beta to alpha Detected Gross Beta > 0.4 keV 1.39E+03 1.35E+04 5.29E+03 1.69E+03 1.07E+03 4.38E+03 Detected Gross Alpha 2.39E-02 9.53E-01 6.01E-02 3.62E-02 5.13E-02 3.18E-02 Detected Gross Beta/Gross Alpha 5.82E+04 1.41E+04 8.80E+04 4.67E+04 2.08E+04 1.38E+05 Am-241 Ratios Pu-238/Am-241 7.87E-01 1.50E+00 3.13E-01 5.03E-01 4.13E-01 4.39E-01 Pu-239/Am-241 1.87E-01 5.98E-01 1.28E-01 2.52E-01 1.55E-01 2.13E-01 Pu-240/Am-241 1.87E-01 5.98E-01 1.28E-01 2.52E-01 1.55E-01 2.13E-01 Pu-241/Am-241 5.54E+01 1.06E+01 4.19E+01 8.53E+01 3.98E+01 5.36E+01 Am-243/Am-241 9.55E-01 4.76E-01 1.43E+00 1.33E+00 7.84E-01 1.00E+00 Cm-243/Am-241 6.41E-01 9.57E-02 4.43E-01 7.10E-01 4.65E-01 6.73E-01 Cm-244/Am-241 6.38E-01 9.54E-02 4.41E-01 7.07E-01 4.63E-01 6.71E-01 Am-241/Gross Alpha 5.21E-07 1.62E-05 4.79E-07 5.84E-07 2.07E-06 9.96E-01 Cs-137 Ratios H-3/Cs-137 9.02E-03 1.25E-03 1.31E-03 1.75E-02 5.32E-03 1.11E-03 C-14/Cs-137 1.69E-03 3.69E-04 1.90E-04 8.85E-04 1.15E-03 7.43E-04 Co-60/Cs-137 1.92E-02 1.66E-02 5.86E-04 5.80E-03 1.70E-02 4.69E-02 Ni-63/Cs-137 1.13E-01 2.56E-01 5.53E-02 5.49E-02 8.26E-02 3.94E-01 Sr-90/Cs-137 1.48E-03 4.09E-04 2.88E-04 2.41E-04 3.15E-04 2.10E-03 Tc-99/Cs-137 1.08E-03 7.27E-05 1.27E-04 2.83E-04 8.75E-04 1.40E-04 Sb-125/Cs-137 1.57E-03 5.49E-04 7.77E-04 1.37E-03 1.78E-03 1.02E-03 I-129/Cs-137 6.72E-03 3.66E-03 1.33E-03 2.52E-03 2.64E-03 1.24E-03 Pm-145/Cs-137 4.80E+01 4.22E+02 1.76E+02 1.14E+02 1.90E+02 4.57E-03 Pm-147/Cs-137 9.89E-03 1.61E-03 5.29E-03 2.94E-03 8.55E-03 1.60E-03 Eu-152/Cs-137 4.33E-04 1.93E-04 1.98E-04 3.99E-04 6.74E-04 4.26E-04 Eu-154/Cs-137 2.58E-04 1.02E-04 2.20E-04 2.32E-04 3.02E-04 2.47E-04 Eu-155/Cs-137 4.11E-04 1.28E-04 2.11E-04 3.63E-04 4.47E-04 2.42E-04 Np-237/Cs-137 1.52E-05 1.61E-06 4.55E-06 1.26E-05 1.85E-05 7.68E-06 Pu-238/Cs-137 1.78E-05 2.59E-05 2.51E-06 8.20E-06 1.71E-05 3.34E-06 Pu-239/Cs-137 4.22E-06 1.03E-05 1.03E-06 4.11E-06 6.41E-06 1.62E-06 Pu-240/Cs-137 4.22E-06 1.03E-05 1.03E-06 4.11E-06 6.41E-06 1.62E-06 Pu-241/Cs-137 1.25E-03 1.84E-04 3.36E-04 1.39E-03 1.64E-03 4.08E-04 Am-241/Cs-137 2.26E-05 1.73E-05 8.01E-06 1.63E-05 4.13E-05 7.60E-06 Am-243/Cs-137 2.16E-05 8.23E-06 1.14E-05 2.17E-05 3.24E-05 7.64E-06 Cm-243/Cs-137 1.45E-05 1.66E-06 3.55E-06 1.16E-05 1.92E-05 5.12E-06 Cm-244/Cs-137 1.44E-05 1.65E-06 3.54E-06 1.15E-05 1.92E-05 5.10E-06 Gross Alpha/Cs-137 1.78E-05 7.21E-05 1.14E-05 2.17E-05 4.95E-05 7.64E-06 Page 76 of 92

Attachment 5 TSD 14-013 Eberline Off-Site Laboratory Decay Corrected Results Revision 0 Floor Cores Wall Core B105101- B105103- B105105- B105106- B105108- B105113-CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJWCCV-Core ID 001 001 001 002 003 003 Eberline Report 12-09081 12-09081 12-09081 12-09081 12-09081 12-09081 Co-60 Ratios H-3/Co-60 4.71E-01 7.54E-02 2.23E+00 3.01E+00 3.14E-01 2.37E-02 C-14/Co-60 8.84E-02 2.23E-02 3.24E-01 1.53E-01 6.77E-02 1.58E-02 Fe-55/Co-60 4.32E-01 1.34E-01 5.46E+00 1.08E+00 4.32E-01 8.25E-02 N-59/C0-60 6.18E-01 9.47E-02 5.87E+00 1.79E+00 9.50E-01 8.95E-02 Ni-63/Co-60 5.89E+00 1.54E+01 9.44E+01 9.46E+00 4.87E+00 8.41E+00 Sr-90/Co-60 7.73E-02 2.47E-02 4.91E-01 4.15E-02 1.85E-02 4.48E-02 Tc-99/Co-60 5.63E-02 4.39E-03 2.18E-01 4.88E-02 5.16E-02 3.36E-03 Nb-94/Co-60 8.69E-03 3.73E-03 2.01E-01 2.20E-02 1.71E-02 2.97E-03 Ag-108m/Co-60 8.00E-03 7.58E-03 2.62E-01 2.61E-02 1.03E-02 3.05E-03 Pu-238/Co-60 9.28E-04 1.56E-03 4.28E-03 1.41E-03 1.01E-03 7.11E-05 Pu-239/Co-60 2.20E-04 6.24E-04 1.75E-03 7.08E-04 3.78E-04 3.45E-05 Pu-240/Co-60 2.20E-04 6.24E-04 1.75E-03 7.08E-04 3.78E-04 3.45E-05 Pu-241/Co-60 6.53E-02 1.11E-02 5.74E-01 2.40E-01 9.69E-02 8.68E-03 Am-241/Co-60 1.18E-03 1.04E-03 1.37E-02 2.81E-03 2.44E-03 1.62E-04 Am-243/Co-60 1.13E-03 4.96E-04 1.95E-02 3.73E-03 1.91E-03 1.63E-04 Cm-243/Co-60 7.55E-04 9.99E-05 6.06E-03 1.99E-03 1.13E-03 1.09E-04 Cm-244/Co-60 7.52E-04 9.95E-05 6.04E-03 1.99E-03 1.13E-03 1.09E-04 Gross Alpha/Co-60 9.28E-04 4.35E-03 1.95E-02 3.73E-03 2.92E-03 1.63E-04 Note: Bold Italic equals MDA value.

Page 77 of 92

Attachment 6 TSD 14-013 Radionuclide Emissions and Yields Revision 0 T 1/2 Gross Beta Avg Beta Alpha Alpha Nuclide (years) Beta MeV Yield % Mev Yield Gamma ID MeV Gamma Yield Analysis Method H-3 1.23E+01 5.86E-03 100% LANL ER-210 Modified Liquid Scint C-14 5.70E+03 YES 0.0495 100% EPA 520.0 Modified Liquid Scint Fe-55 2.74E+00 EML Method Fe-Ol- 01 Modified Liquid Scint Ni-59 1.01e+05 0.00607 24.000% ASTM 3500-Ni Modified Liquid Scint Co-60 5.27E+00 YES 0.096 100% 1.17, 1.33 99.9%, 100% LANL ER-130 Modified Gamma Spec Ni-63 1.00E+02 0.017 100% ASTM 3500-Ni Modified Liquid Scint Sr-90 2.88E+01 YES 0.1957 100% EIChroM SRW01 Modified Gas Fl Prop Y-90 7.31E-03 YES 0.9346 100% EIChroM SRW01 Modified Gas Fl Prop Nb-94 2.03E+04 YES 0.166 100% 0.871 100% LANL ER-130 Modified Gamma Spec Tc-99 2.11E+05 YES 0.1013 100% EIChroM TCS01 Modified Liquid Scint Ag-108m 4.18+02 0.723 90% LANL ER-130 Modified Gamma Spec Sb-125 2.76E+00 YES 0.0866 100% 0.428 30% LANL ER-130 Modified Gamma Spec Cs-134 2.06E+00 YES 0.157 100% 0.605 98% LANL ER-130 Modified Gamma Spec Cs-137 3.02E+01 YES 0.187 100% 0.662 90% LANL ER-130 Modified Gamma Spec Eu-152 1.35E+01 YES 0.2988 28% 1.408 21% LANL ER-130 Modified Gamma Spec Eu-154 8.80E+00 YES 0.226 100% 1.27 36% LANL ER-130 Modified Gamma Spec Eu-155 4.76E+00 YES 0.045 100% 0.105 21% LANL ER-130 Modified Gamma Spec Np-237 2.14E+06 4.796 100% 0.0865 13% EIChroM Method ACW08 Modified Pu-238 8.77E+01 5.48 100% EML Pu-02 Modified Alpha Spec Pu-239 2.41E+04 5.148 100% EML Pu-02 Modified Alpha Spec Pu-240 6.56E+03 5.156 100% EML Pu-02 Modified Alpha Spec Pu-241 1.44E+01 5.24E-03 100% 4.9 2.04E-07 EML Pu-02 Modified Liquid Scint Am-241 4.32E+02 5.479 100% 0.0595 36% EML Am-01 Modified Alpha Spec Am-243 7.37E+03 5.27 100% 0.0747 66% EML Am-01 Modified Alpha Spec Cm-243 2.85E+01 5.795 99.8% 0.278, 0.228 14%, 10.6% EML Am-01 Modified Alpha Spec Cm-244 1.81E+01 5.795 100% EML Am-01 Modified Alpha Spec NOTE: Data is from NRC Radiological Toolbox V3.0 Software http://www.nrc.gov/about-nrc/regulatory/research/radiological-toolbox.html Page 78 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 MicroShield 8.03 Radiation Safety and Control Services (8.03-0000)

Date By Checked Filename Run Date Run Time Duration Three Foot Dia Two Inch.msd July 18, 2014 10:04:47 AM 00:00:00 Project Info Case Title Aux Worst Description 0 - 2 in 36 Inch Diameter at Center 44-10 NaI Detector Geometry 8 - Cylinder Volume - End Shields Source Dimensions Height 5.08 cm (2.0 in)

Radius 45.72 cm (1 ft 6.0 in)

Dose Points A X Y Z

  1. 1 0.0 cm (0 in) 7.62 cm (3.0 in) 0.0 cm (0 in)

Shields Shield N Dimension Material Density Source 2035.752 in³ Concrete 2.4 Air Gap Air 0.00122 Source Input: Grouping Method - Actual Photon Energies Nuclide Ci Bq µCi/cm³ Bq/cm³ Ba-137m 1.4942e-003 5.5286e+007 4.4790e-002 1.6572e+003 Co-60 1.5390e-005 5.6943e+005 4.6133e-004 1.7069e+001 Cs-137 1.5795e-003 5.8442e+007 4.7347e-002 1.7518e+003 Buildup: The material reference is Source Integration Parameters Radial 20 Circumferential 10 Y Direction (axial) 10 Results Energy (MeV) Activity (Photons/sec) Fluence Rate Fluence Rate Exposure Rate Exposure Rate Page 79 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0045 5.739e+05 1.763e-03 1.813e-03 1.209e-03 1.243e-03 0.0318 1.145e+06 2.183e-01 2.643e-01 1.818e-03 2.201e-03 0.0322 2.112e+06 4.199e-01 5.115e-01 3.380e-03 4.117e-03 0.0364 7.685e+05 2.335e-01 3.054e-01 1.327e-03 1.735e-03 0.6616 4.975e+07 2.066e+03 3.747e+03 4.005e+00 7.264e+00 0.6938 9.289e+01 4.104e-03 7.346e-03 7.924e-06 1.418e-05 1.1732 5.694e+05 5.007e+01 7.826e+01 8.948e-02 1.398e-01 1.3325 5.694e+05 5.912e+01 8.962e+01 1.026e-01 1.555e-01 Totals 5.548e+07 2.176e+03 3.916e+03 4.204e+00 7.569e+00 MicroShield 8.03 Radiation Safety and Control Services (8.03-0000)

Date By Checked Filename Run Date Run Time Duration First Half Inch At Avg Conc.msd July 18, 2014 11:19:03 AM 00:00:00 Project Info Case Title Aux Average Description 0.0 - 0.5 in 36 Inch Diameter at Center 44-10 NaI Detector Geometry 8 - Cylinder Volume - End Shields Source Dimensions Height 1.27 cm (0.5 in)

Radius 45.72 cm (1 ft 6.0 in)

Dose Points A X Y Z

  1. 1 0.0 cm (0 in) 3.81 cm (1.5 in) 0.0 cm (0 in)

Shields Shield N Dimension Material Density Source 508.938 in³ Concrete 2.4 Air Gap Air 0.00122 Page 80 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 Source Input: Grouping Method - Actual Photon Energies Nuclide Ci Bq µCi/cm³ Bq/cm³ Ba-137m 5.9125e-005 2.1876e+006 7.0893e-003 2.6231e+002 Co-60 8.3900e-007 3.1043e+004 1.0060e-004 3.7222e+000 Cs-134 1.1400e-008 4.2180e+002 1.3669e-006 5.0576e-002 Cs-137 6.2500e-005 2.3125e+006 7.4940e-003 2.7728e+002 Buildup: The material reference is Source Integration Parameters Radial 20 Circumferential 10 Y Direction (axial) 10 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0045 2.271e+04 2.923e-04 2.995e-04 2.003e-04 2.053e-04 0.0045 3.769e-01 4.851e-09 4.971e-09 3.325e-09 3.407e-09 0.0318 4.529e+04 3.416e-02 4.124e-02 2.845e-04 3.435e-04 0.0318 9.043e-01 6.820e-07 8.234e-07 5.681e-09 6.859e-09 0.0322 1.668e+00 1.310e-06 1.591e-06 1.054e-08 1.280e-08 0.0322 8.356e+04 6.562e-02 7.968e-02 5.281e-04 6.413e-04 0.0364 3.041e+04 3.575e-02 4.624e-02 2.031e-04 2.627e-04 0.0364 6.071e-01 7.138e-07 9.232e-07 4.055e-09 5.245e-09 0.2769 1.493e-01 4.719e-06 7.874e-06 8.852e-09 1.477e-08 0.4753 6.158e+00 3.657e-04 5.406e-04 7.176e-07 1.061e-06 0.5632 3.535e+01 2.557e-03 3.646e-03 5.007e-06 7.139e-06 0.5693 6.508e+01 4.768e-03 6.783e-03 9.331e-06 1.327e-05 0.6047 4.117e+02 3.235e-02 4.543e-02 6.311e-05 8.864e-05 0.6616 1.968e+06 1.717e+02 2.369e+02 3.329e-01 4.592e-01 0.6938 5.064e+00 4.668e-04 6.381e-04 9.013e-07 1.232e-06 0.7958 3.602e+02 3.894e-02 5.195e-02 7.410e-05 9.887e-05 0.8019 3.682e+01 4.016e-03 5.351e-03 7.636e-06 1.017e-05 1.0386 4.218e+00 6.204e-04 7.930e-04 1.136e-06 1.452e-06 Page 81 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 1.1679 7.592e+00 1.279e-03 1.604e-03 2.287e-06 2.870e-06 1.1732 3.104e+04 5.255e+00 6.589e+00 9.391e-03 1.178e-02 1.3325 3.104e+04 6.083e+00 7.485e+00 1.055e-02 1.299e-02 1.3652 1.282e+01 2.583e-03 3.168e-03 4.455e-06 5.463e-06 Totals 2.213e+06 1.833e+02 2.512e+02 3.542e-01 4.857e-01 MicroShield 8.03 Radiation Safety and Control Services (8.03-0000)

Date By Checked Filename Run Date Run Time Duration Second Half Inch At Avg Conc.msd July 18, 2014 11:24:41 AM 00:00:00 Project Info Case Title Aux Average Description 0.5 - 1.0 in 36 Inch Diameter at Center 44-10 NaI Detector Geometry 8 - Cylinder Volume - End Shields Source Dimensions Height 1.27 cm (0.5 in)

Radius 45.72 cm (1 ft 6.0 in)

Dose Points A X Y Z

  1. 1 0.0 cm (0 in) 5.08 cm (2.0 in) 0.0 cm (0 in)

Shields Shield N Dimension Material Density Source 508.938 in³ Concrete 2.4 Shield 1 .5 in Concrete 2.4 Air Gap Air 0.00122 Source Input: Grouping Method - Actual Photon Energies Nuclide Ci Bq µCi/cm³ Bq/cm³ Ba-137m 2.7245e-005 1.0081e+006 3.2668e-003 1.2087e+002 Co-60 4.9500e-007 1.8315e+004 5.9353e-005 2.1960e+000 Cs-134 5.4000e-009 1.9980e+002 6.4748e-007 2.3957e-002 Page 82 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 Cs-137 2.8800e-005 1.0656e+006 3.4532e-003 1.2777e+002 Buildup: The material reference is Shield 1 Integration Parameters Radial 20 Circumferential 10 Y Direction (axial) 10 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0045 1.046e+04 1.110e-16 1.224e-16 7.608e-17 8.389e-17 0.0045 1.785e-01 1.894e-21 2.088e-21 1.298e-21 1.431e-21 0.0318 2.087e+04 1.763e-04 2.710e-04 1.468e-06 2.258e-06 0.0318 4.283e-01 3.617e-09 5.563e-09 3.013e-11 4.634e-11 0.0322 7.903e-01 7.732e-09 1.200e-08 6.222e-11 9.654e-11 0.0322 3.850e+04 3.767e-04 5.845e-04 3.032e-06 4.704e-06 0.0364 1.401e+04 5.185e-04 8.888e-04 2.946e-06 5.050e-06 0.0364 2.876e-01 1.064e-08 1.824e-08 6.046e-11 1.037e-10 0.2769 7.073e-02 8.489e-07 2.370e-06 1.592e-09 4.446e-09 0.4753 2.917e+00 7.432e-05 1.682e-04 1.458e-07 3.300e-07 0.5632 1.674e+01 5.395e-04 1.142e-03 1.056e-06 2.237e-06 0.5693 3.083e+01 1.008e-03 2.126e-03 1.973e-06 4.161e-06 0.6047 1.950e+02 6.932e-03 1.428e-02 1.352e-05 2.785e-05 0.6616 9.071e+05 3.650e+01 7.269e+01 7.077e-02 1.409e-01 0.6938 2.988e+00 1.284e-04 2.512e-04 2.478e-07 4.851e-07 0.7958 1.706e+02 8.854e-03 1.653e-02 1.685e-05 3.146e-05 0.8019 1.744e+01 9.147e-04 1.703e-03 1.739e-06 3.239e-06 1.0386 1.998e+00 1.493e-04 2.559e-04 2.734e-07 4.685e-07 1.1679 3.596e+00 3.153e-04 5.209e-04 5.639e-07 9.318e-07 1.1732 1.832e+04 1.615e+00 2.665e+00 2.887e-03 4.763e-03 1.3325 1.832e+04 1.919e+00 3.049e+00 3.329e-03 5.290e-03 1.3652 6.074e+00 6.575e-04 1.038e-03 1.134e-06 1.789e-06 Totals 1.028e+06 4.006e+01 7.844e+01 7.703e-02 1.511e-01 Page 83 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 MicroShield 8.03 Radiation Safety and Control Services (8.03-0000)

Date By Checked Filename Run Date Run Time Duration Third Half Inch At Avg Conc.msd July 18, 2014 11:28:26 AM 00:00:00 Project Info Case Title Aux Average Description 1.0 - 1.5 in 36 Inch Diameter at Center 44-10 NaI Detector Geometry 8 - Cylinder Volume - End Shields Source Dimensions Height 1.27 cm (0.5 in)

Radius 45.72 cm (1 ft 6.0 in)

Dose Points A X Y Z

  1. 1 0.0 cm (0 in) 6.35 cm (2.5 in) 0.0 cm (0 in)

Shields Shield N Dimension Material Density Source 508.938 in³ Concrete 2.4 Shield 1 1.0 in Concrete 2.4 Air Gap Air 0.00122 Source Input: Grouping Method - Actual Photon Energies Nuclide Ci Bq µCi/cm³ Bq/cm³ Ba-137m 1.5893e-005 5.8803e+005 1.9056e-003 7.0508e+001 Co-60 4.7900e-007 1.7723e+004 5.7434e-005 2.1251e+000 Cs-134 5.7900e-009 2.1423e+002 6.9424e-007 2.5687e-002 Cs-137 1.6800e-005 6.2160e+005 2.0144e-003 7.4532e+001 Buildup: The material reference is Shield 1 Integration Parameters Radial 20 Circumferential 10 Page 84 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 Y Direction (axial) 10 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0045 6.104e+03 6.873e-28 8.041e-28 4.711e-28 5.512e-28 0.0045 1.914e-01 2.155e-32 2.522e-32 1.477e-32 1.729e-32 0.0318 1.217e+04 3.086e-06 5.167e-06 2.570e-08 4.304e-08 0.0318 4.593e-01 1.164e-10 1.949e-10 9.696e-13 1.624e-12 0.0322 8.474e-01 2.725e-10 4.613e-10 2.193e-12 3.712e-12 0.0322 2.246e+04 7.223e-06 1.223e-05 5.813e-08 9.840e-08 0.0364 8.174e+03 2.173e-05 4.156e-05 1.234e-07 2.361e-07 0.0364 3.084e-01 8.197e-10 1.568e-09 4.657e-12 8.909e-12 0.2769 7.584e-02 4.684e-07 1.726e-06 8.787e-10 3.237e-09 0.4753 3.128e+00 4.456e-05 1.274e-04 8.743e-08 2.500e-07 0.5632 1.795e+01 3.316e-04 8.742e-04 6.493e-07 1.712e-06 0.5693 3.306e+01 6.208e-04 1.628e-03 1.215e-06 3.186e-06 0.6047 2.091e+02 4.305e-03 1.097e-02 8.399e-06 2.140e-05 0.6616 5.291e+05 1.250e+01 3.054e+01 2.423e-02 5.921e-02 0.6938 2.891e+00 7.339e-05 1.756e-04 1.417e-07 3.390e-07 0.7958 1.830e+02 5.720e-03 1.290e-02 1.089e-05 2.454e-05 0.8019 1.870e+01 5.915e-04 1.329e-03 1.125e-06 2.528e-06 1.0386 2.142e+00 1.001e-04 2.025e-04 1.832e-07 3.708e-07 1.1679 3.856e+00 2.147e-04 4.151e-04 3.841e-07 7.425e-07 1.1732 1.772e+04 9.936e-01 1.917e+00 1.776e-03 3.426e-03 1.3325 1.772e+04 1.200e+00 2.209e+00 2.083e-03 3.833e-03 1.3652 6.513e+00 4.572e-04 8.341e-04 7.884e-07 1.438e-06 Totals 6.140e+05 1.470e+01 3.470e+01 2.811e-02 6.652e-02 MicroShield 8.03 Radiation Safety and Control Services (8.03-0000)

Date By Checked Page 85 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 Filename Run Date Run Time Duration Fourth Half Inch At Avg Conc.msd July 18, 2014 11:32:40 AM 00:00:00 Project Info Case Title Aux Average Description 1.5 - 2.0 in 36 Inch Diameter at Center 44-10 NaI Detector Geometry 8 - Cylinder Volume - End Shields Source Dimensions Height 1.27 cm (0.5 in)

Radius 45.72 cm (1 ft 6.0 in)

Dose Points A X Y Z

  1. 1 0.0 cm (0 in) 7.62 cm (3.0 in) 0.0 cm (0 in)

Shields Shield N Dimension Material Density Source 508.938 in³ Concrete 2.4 Shield 1 1.5 in Concrete 2.4 Air Gap Air 0.00122 Source Input: Grouping Method - Actual Photon Energies Nuclide Ci Bq µCi/cm³ Bq/cm³ Ba-137m 9.6492e-006 3.5702e+005 1.1570e-003 4.2808e+001 Co-60 3.1600e-007 1.1692e+004 3.7890e-005 1.4019e+000 Cs-134 4.9800e-009 1.8426e+002 5.9712e-007 2.2094e-002 Cs-137 1.0200e-005 3.7740e+005 1.2230e-003 4.5252e+001 Buildup: The material reference is Shield 1 Integration Parameters Radial 20 Circumferential 10 Y Direction (axial) 10 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup Page 86 of 92

Attachment 7 TSD 14-013 Contact Dose Rate MicroShield Reports Revision 0 0.0045 3.706e+03 5.757e-39 2.316e-29 3.946e-39 1.588e-29 0.0045 1.647e-01 2.557e-43 1.029e-33 1.753e-43 7.053e-34 0.0318 7.391e+03 6.742e-08 1.202e-07 5.616e-10 1.001e-09 0.0318 3.950e-01 3.603e-12 6.421e-12 3.001e-14 5.349e-14 0.0322 7.288e-01 9.224e-12 1.663e-11 7.423e-14 1.339e-13 0.0322 1.364e+04 1.726e-07 3.112e-07 1.389e-09 2.505e-09 0.0364 4.963e+03 1.118e-06 2.306e-06 6.354e-09 1.310e-08 0.0364 2.652e-01 5.977e-11 1.233e-10 3.396e-13 7.004e-13 0.2769 6.523e-02 2.282e-07 1.048e-06 4.280e-10 1.966e-09 0.4753 2.690e+00 2.341e-05 8.075e-05 4.594e-08 1.584e-07 0.5632 1.544e+01 1.783e-04 5.598e-04 3.490e-07 1.096e-06 0.5693 2.843e+01 3.341e-04 1.043e-03 6.539e-07 2.042e-06 0.6047 1.798e+02 2.336e-03 7.055e-03 4.557e-06 1.376e-05 0.6616 3.212e+05 4.842e+00 1.394e+01 9.386e-03 2.702e-02 0.6938 1.907e+00 3.109e-05 8.730e-05 6.002e-08 1.685e-07 0.7958 1.574e+02 3.214e-03 8.420e-03 6.117e-06 1.603e-05 0.8019 1.609e+01 3.327e-04 8.683e-04 6.326e-07 1.651e-06 1.0386 1.843e+00 5.809e-05 1.341e-04 1.064e-07 2.455e-07 1.1679 3.317e+00 1.264e-04 2.765e-04 2.261e-07 4.947e-07 1.1732 1.169e+04 4.488e-01 9.800e-01 8.021e-04 1.751e-03 1.3325 1.169e+04 5.502e-01 1.137e+00 9.546e-04 1.973e-03 1.3652 5.602e+00 2.740e-04 5.604e-04 4.724e-07 9.664e-07 Totals 3.747e+05 5.847e+00 1.607e+01 1.116e-02 3.078e-02 Page 87 of 92

Attachment 8 TSD 14-013 Contact Dose Rate Survey Results Revision 0 Open Air Limit 2 Logged Current Open Air Current inch Reading Open Air 2 inch Limit 2 Stratified 2 Stratified Survey Surv 2350 Current Limit Cs-137 inch Cs-137 inch Cs-137 Cs-137 Unit ID pt (cpm) mrem/hr mrem/hr pCi/g pCi/g pCi/g pCi/g B1-05101 1 4.00 2.00 10425.67 5212.83 8047.16 4023.58 B1-05101 2 8.00 2.00 20851.33 5212.83 16094.33 4023.58 B1-05101 3 4.00 2.00 10425.67 5212.83 8047.16 4023.58 B1-05101 4 5.00 2.00 13032.08 5212.83 10058.95 4023.58 B1-05101 5 12.00 2.00 31277.00 5212.83 24141.49 4023.58 B1-05101 6 15.00 2.00 39096.25 5212.83 30176.86 4023.58 B1-05102 1 355792 0.40 0.40 1030.38 1030.38 795.31 795.31 B1-05102 2 471218 0.52 0.52 1364.66 1364.66 1053.32 1053.32 B1-05102 3 530605 0.59 0.59 1536.64 1536.64 1186.07 1186.07 B1-05102 4 486202 0.54 0.54 1408.05 1408.05 1086.82 1086.82 B1-05102 5 629256 0.70 0.70 1822.34 1822.34 1406.59 1406.59 B1-05102 6 537715 0.60 0.60 1557.23 1557.23 1201.97 1201.97 B1-05103 1 42827 0.05 0.05 124.03 124.03 95.73 95.73 B1-05103 2 59602 0.07 0.07 172.61 172.61 133.23 133.23 B1-05103 3 175980 0.20 0.20 509.64 509.64 393.37 393.37 B1-05103 4 491454 0.55 0.55 1423.26 1423.26 1098.56 1098.56 B1-05103 5 649403 0.72 0.72 1880.68 1880.68 1451.63 1451.63 B1-05103 6 1460593 1.62 1.62 4229.90 4229.90 3264.90 3264.90 B1-05103 7 603273 0.67 0.67 1747.09 1747.09 1348.51 1348.51 B1-05103 8 564653 0.63 0.63 1635.25 1635.25 1262.18 1262.18 B1-05103 9 460730 0.51 0.51 1334.28 1334.28 1029.88 1029.88 B1-05103 10 515535 0.57 0.57 1493.00 1493.00 1152.39 1152.39 B1-05104 1 398911 0.44 0.44 1155.25 1155.25 891.69 891.69 B1-05104 2 336101 0.37 0.37 973.35 973.35 751.29 751.29 B1-05104 3 468742 0.52 0.52 1357.49 1357.49 1047.79 1047.79 B1-05104 4 492410 0.55 0.55 1426.03 1426.03 1100.70 1100.70 B1-05104 5 698256 0.78 0.78 2022.16 2022.16 1560.83 1560.83 B1-05104 6 740105 0.82 0.82 2143.36 2143.36 1654.37 1654.37 B1-05105 1 4.00 2.00 10425.67 5212.83 8047.16 4023.58 B1-05105 2 6.00 2.00 15638.50 5212.83 12070.74 4023.58 B1-05105 3 3.50 2.00 9122.46 5212.83 7041.27 4023.58 B1-05105 4 4.50 2.00 11728.88 5212.83 9053.06 4023.58 B1-05105 5 6.50 2.00 16941.71 5212.83 13076.64 4023.58 B1-05105 6 6.00 2.00 15638.50 5212.83 12070.74 4023.58 B1-05105 7 4.00 2.00 10425.67 5212.83 8047.16 4023.58 Page 88 of 92

Attachment 8 TSD 14-013 Contact Dose Rate Survey Results Revision 0 Open Air Limit 2 Logged Current Open Air Current inch Reading Open Air 2 inch Limit 2 Stratified 2 Stratified Survey Surv 2350 Current Limit Cs-137 inch Cs-137 inch Cs-137 Cs-137 Unit ID pt (cpm) mrem/hr mrem/hr pCi/g pCi/g pCi/g pCi/g B1-05105 8 2.00 2.00 5212.83 5212.83 4023.58 4023.58 B1-05105 9 1.00 1.00 2606.42 2606.42 2011.79 2011.79 B1-05105 10 1.00 1.00 2606.42 2606.42 2011.79 2011.79 B1-05105 11 0.60 0.60 1563.85 1563.85 1207.07 1207.07 B1-05105 12 0.40 0.40 1042.57 1042.57 804.72 804.72 B1-05105 13 0.40 0.40 1042.57 1042.57 804.72 804.72 B1-05105 14 0.80 0.80 2085.13 2085.13 1609.43 1609.43 B1-05106 1 371529 0.41 0.41 1075.95 1075.95 830.49 830.49 B1-05106 2 443756 0.49 0.49 1285.13 1285.13 991.94 991.94 B1-05106 3 483389 0.54 0.54 1399.90 1399.90 1080.53 1080.53 B1-05106 4 393116 0.44 0.44 1138.47 1138.47 878.74 878.74 B1-05106 5 305603 0.34 0.34 885.03 885.03 683.12 683.12 B1-05106 6 377390 0.42 0.42 1092.93 1092.93 843.59 843.59 B1-05106 7 329964 0.37 0.37 955.58 955.58 737.58 737.58 B1-05106 8 268627 0.30 0.30 777.95 777.95 600.47 600.47 B1-05106 9 223152 0.25 0.25 646.25 646.25 498.82 498.82 B1-05106 10 178261 0.20 0.20 516.25 516.25 398.47 398.47 B1-05106 11 117804 0.13 0.13 341.16 341.16 263.33 263.33 B1-05106 12 115419 0.13 0.13 334.26 334.26 258.00 258.00 B1-05108 1 48111 0.05 0.05 139.33 139.33 107.54 107.54 B1-05108 2 389907 0.43 0.43 1129.18 1129.18 871.57 871.57 B1-05108 3 171960 0.19 0.19 498.00 498.00 384.39 384.39 B1-05108 4 15436 0.02 0.02 44.70 44.70 34.50 34.50 B1-05108 5 42250 0.05 0.05 122.36 122.36 94.44 94.44 B1-05108 6 17866 0.02 0.02 51.74 51.74 39.94 39.94 B1-05108 7 28539 0.03 0.03 82.65 82.65 63.79 63.79 B1-05108 8 23562 0.03 0.03 68.24 68.24 52.67 52.67 B1-05108 9 62437 0.07 0.07 180.82 180.82 139.57 139.57 B1-05108 10 23408 0.03 0.03 67.79 67.79 52.32 52.32 B1-05108 11 13406 0.01 0.01 38.82 38.82 29.97 29.97 B1-05108 12 7310 0.01 0.01 21.17 21.17 16.34 16.34 B1-05108 13 20863 0.02 0.02 60.42 60.42 46.64 46.64 B1-05108 14 15343 0.02 0.02 44.43 44.43 34.30 34.30 B1-05108 15 692270 0.77 0.77 2004.83 2004.83 1547.45 1547.45 B1-05108 16 11248 0.01 0.01 32.57 32.57 25.14 25.14 B1-05109 1 46818 0.05 0.05 135.59 135.59 104.65 104.65 B1-05109 2 53393 0.06 0.06 154.63 154.63 119.35 119.35 Page 89 of 92

Attachment 8 TSD 14-013 Contact Dose Rate Survey Results Revision 0 Open Air Limit 2 Logged Current Open Air Current inch Reading Open Air 2 inch Limit 2 Stratified 2 Stratified Survey Surv 2350 Current Limit Cs-137 inch Cs-137 inch Cs-137 Cs-137 Unit ID pt (cpm) mrem/hr mrem/hr pCi/g pCi/g pCi/g pCi/g B1-05109 3 38460 0.04 0.04 111.38 111.38 85.97 85.97 B1-05109 4 51068 0.06 0.06 147.89 147.89 114.15 114.15 B1-05109 5 12200 0.01 0.01 35.33 35.33 27.27 27.27 B1-05109 6 35046 0.04 0.04 101.49 101.49 78.34 78.34 B1-05109 7 14455 0.02 0.02 41.86 41.86 32.31 32.31 B1-05110 1 22243 0.02 0.02 64.42 64.42 49.72 49.72 B1-05110 2 18785 0.02 0.02 54.40 54.40 41.99 41.99 B1-05110 3 25273 0.03 0.03 73.19 73.19 56.49 56.49 B1-05110 4 29749 0.03 0.03 86.15 86.15 66.50 66.50 B1-05110 5 23632 0.03 0.03 68.44 68.44 52.83 52.83 B1-05110 6 27771 0.03 0.03 80.43 80.43 62.08 62.08 B1-05110 7 18191 0.02 0.02 52.68 52.68 40.66 40.66 B1-05110 8 13682 0.02 0.02 39.62 39.62 30.58 30.58 B1-05110 9 14381 0.02 0.02 41.65 41.65 32.15 32.15 B1-05110 10 16497 0.02 0.02 47.78 47.78 36.88 36.88 B1-05110 11 14644 0.02 0.02 42.41 42.41 32.73 32.73 B1-05110 12 18119 0.02 0.02 52.47 52.47 40.50 40.50 B1-05110 13 7296 0.01 0.01 21.13 21.13 16.31 16.31 B1-05110 14 7609 0.01 0.01 22.04 22.04 17.01 17.01 B1-05110 15 12747 0.01 0.01 36.92 36.92 28.49 28.49 B1-05110 16 16903 0.02 0.02 48.95 48.95 37.78 37.78 B1-05110 17 17890 0.02 0.02 51.81 51.81 39.99 39.99 B1-05110 18 19331 0.02 0.02 55.98 55.98 43.21 43.21 B1-05110 19 23234 0.03 0.03 67.29 67.29 51.94 51.94 B1-05110 20 23087 0.03 0.03 66.86 66.86 51.61 51.61 B1-05110 21 40965 0.05 0.05 118.64 118.64 91.57 91.57 B1-05110 22 38527 0.04 0.04 111.57 111.57 86.12 86.12 B1-05110 23 22382 0.02 0.02 64.82 64.82 50.03 50.03 B1-05110 24 24133 0.03 0.03 69.89 69.89 53.95 53.95 B1-05110 25 28624 0.03 0.03 82.90 82.90 63.98 63.98 B1-05110 26 58873 0.07 0.07 170.50 170.50 131.60 131.60 B1-05110 27 25739 0.03 0.03 74.54 74.54 57.53 57.53 B1-05110 28 16592 0.02 0.02 48.05 48.05 37.09 37.09 B1-05110 29 9988 0.01 0.01 28.93 28.93 22.33 22.33 B1-05110 30 5543 0.01 0.01 16.05 16.05 12.39 12.39 B1-05110 31 4884 0.01 0.01 14.14 14.14 10.92 10.92 B1-05110 32 4491 0.005 0.005 13.01 13.01 10.04 10.04 Page 90 of 92

Attachment 8 TSD 14-013 Contact Dose Rate Survey Results Revision 0 Open Air Limit 2 Logged Current Open Air Current inch Reading Open Air 2 inch Limit 2 Stratified 2 Stratified Survey Surv 2350 Current Limit Cs-137 inch Cs-137 inch Cs-137 Cs-137 Unit ID pt (cpm) mrem/hr mrem/hr pCi/g pCi/g pCi/g pCi/g B1-05110 33 4050 0.005 0.005 11.73 11.73 9.05 9.05 B1-05110 34 136002 0.15 0.15 393.86 393.86 304.01 304.01 B1-05110 35 202470 0.22 0.22 586.36 586.36 452.59 452.59 B1-05110 36 179498 0.20 0.20 519.83 519.83 401.24 401.24 B1-05110 37 49996 0.06 0.06 144.79 144.79 111.76 111.76 B1-05110 38 145118 0.16 0.16 420.26 420.26 324.39 324.39 B1-05110 39 215187 0.24 0.24 623.19 623.19 481.01 481.01 B1-05110 40 212368 0.24 0.24 615.02 615.02 474.71 474.71 B1-05110 41 191383 0.21 0.21 554.25 554.25 427.80 427.80 B1-05111 1 409668 0.46 0.46 1186.41 1186.41 915.74 915.74 B1-05111 2 101609 0.11 0.11 294.26 294.26 227.13 227.13 B1-05111 3 31531 0.04 0.04 91.31 91.31 70.48 70.48 B1-05111 4 473983 0.53 0.53 1372.66 1372.66 1059.51 1059.51 B1-05111 5 276549 0.31 0.31 800.89 800.89 618.18 618.18 B1-05111 6 17117 0.02 0.02 49.57 49.57 38.26 38.26 B1-05111 7 25242 0.03 0.03 73.10 73.10 56.42 56.42 B1-05111 8 48212 0.05 0.05 139.62 139.62 107.77 107.77 B1-05111 9 100272 0.11 0.11 290.39 290.39 224.14 224.14 B1-05111 10 155208 0.17 0.17 449.49 449.49 346.94 346.94 B1-05111 11 19169 0.02 0.02 55.51 55.51 42.85 42.85 B1-05111 12 40644 0.05 0.05 117.71 117.71 90.85 90.85 B1-05111 13 34972 0.04 0.04 101.28 101.28 78.17 78.17 B1-05111 14 114756 0.13 0.13 332.34 332.34 256.52 256.52 B1-05111 15 69655 0.08 0.08 201.72 201.72 155.70 155.70 B1-05111 16 30299 0.03 0.03 87.75 87.75 67.73 67.73 B1-05111 17 87221 0.10 0.10 252.59 252.59 194.97 194.97 B1-05111 18 74514 0.08 0.08 215.79 215.79 166.56 166.56 B1-05111 19 46873 0.05 0.05 135.75 135.75 104.78 104.78 B1-05111 20 72479 0.08 0.08 209.90 209.90 162.01 162.01 B1-05111 21 80554 0.09 0.09 233.29 233.29 180.06 180.06 B1-05111 22 79286 0.09 0.09 229.61 229.61 177.23 177.23 B1-05111 23 83800 0.09 0.09 242.69 242.69 187.32 187.32 B1-05111 24 204226 0.23 0.23 591.44 591.44 456.51 456.51 B1-05112 1 10015 0.01 0.01 29.00 29.00 22.39 22.39 B1-05112 2 4621 0.01 0.01 13.38 13.38 10.33 10.33 B1-05112 3 4959 0.01 0.01 14.36 14.36 11.08 11.08 B1-05112 4 3826 0.004 0.004 11.08 11.08 8.55 8.55 Page 91 of 92

Attachment 8 TSD 14-013 Contact Dose Rate Survey Results Revision 0 Open Air Limit 2 Logged Current Open Air Current inch Reading Open Air 2 inch Limit 2 Stratified 2 Stratified Survey Surv 2350 Current Limit Cs-137 inch Cs-137 inch Cs-137 Cs-137 Unit ID pt (cpm) mrem/hr mrem/hr pCi/g pCi/g pCi/g pCi/g B1-05112 5 4569 0.01 0.01 13.23 13.23 10.21 10.21 B1-05112 6 5668 0.01 0.01 16.41 16.41 12.67 12.67 B1-05112 7 5880 0.01 0.01 17.03 17.03 13.14 13.14 B1-05112 8 4112 0.005 0.005 11.91 11.91 9.19 9.19 B1-05113 1 581733 0.65 0.65 1684.71 1684.71 1300.36 1300.36 B1-05113 2 549564 0.61 0.61 1591.55 1591.55 1228.45 1228.45 B1-05113 3 440799 0.49 0.49 1276.56 1276.56 985.33 985.33 B1-05113 4 585995 0.65 0.65 1697.05 1697.05 1309.89 1309.89 B1-05113 5 836629 0.93 0.93 2422.89 2422.89 1870.14 1870.14 B1-05114 1 95231 0.11 0.11 275.79 275.79 212.87 212.87 B1-05114 2 99364 0.11 0.11 287.76 287.76 222.11 222.11 B1-05114 3 82252 0.09 0.09 238.20 238.20 183.86 183.86 B1-05114 4 70665 0.08 0.08 204.65 204.65 157.96 157.96 B1-05114 5 31838 0.04 0.04 92.20 92.20 71.17 71.17 B1-05114 6 23323 0.03 0.03 67.54 67.54 52.13 52.13 B1-05114 7 66540 0.07 0.07 192.70 192.70 148.74 148.74 B1-05114 8 97775 0.11 0.11 283.16 283.16 218.56 218.56 B1-05114 9 101839 0.11 0.11 294.93 294.93 227.64 227.64 B1-05114 10 22558 0.03 0.03 65.33 65.33 50.42 50.42 Ludlum 14C Dose Rates

"@epoxy recoat" 900 cpm/R/hr "original dupont coating" 900,000 cpm/mrem/hr Page 92 of 92

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