ML17129A321

TSD-13-006, Rev. 0 - RB Units 1 and 2 End State Concrete and Liner Initial Characterization Source Terms and Distributions

ML17129A321
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Site:	Zion  File:ZionSolutions icon.png
Issue date:	12/06/2014
From:	Farr H ZionSolutions
To:	Office of Nuclear Reactor Regulation
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ZionSolutions Technical Support Document TSD 13-006 Reactor Building Units 1 & 2 End State Concrete and Liner Initial Characterization Source Terms and Distributions Revision 0 Originator: (Signature on file) Date: 12/06/14 Harvey Farr Reviewer: (Signature on file) Date: 12/05/14 Wade Adams Approval: (Signature on file) Date: 12/17/14 Robert F. Yetter

TSD 13-006 Revision 0 Page 2 of 200 Summary of Changes in this Revision:

• Rev. 0 -Initial issuance.

TSD 13-006 Revision 0 Page 3 of 200 Table of Contents

1.

Introduction.................................................................................................................................... 7

2.

Background.................................................................................................................................... 7 2.1.

Pressurized Water Reactor Containment End Sates and Concrete Characterization.......... 7 2.2.

Zion Reactor Building (Containment) End State............................................................... 12 2.3.

Reactor Building Source Terms and Characterization...................................................... 16 2.4.

Zion Core Collection and Handling Method..................................................................... 17 2.5.

Sample Core Processing and Analysis.............................................................................. 19

3.

Calculations and Evaluations - Interior Concrete Remaining In End State................................ 19 3.1.

Summary of Unit 1 and 2 On-Site Gamma Spectroscopy Results for 568 Foot Floor Cores........................................................................................................................ 19 3.2.

Unit 1 568 Foot Radionuclide Profile from On-Site Gamma Spectroscopy Results........ 21 3.3.

Unit 2 568 Foot Radionuclide Profile from On-Site Gamma Spectroscopy Results........ 24 3.4.

Evaluation of 568 Eberline Off-Site Laboratory Results................................................. 26 3.5.

Evaluation of 568 Scaling Factors and Source Terms..................................................... 34 3.6.

Unit 1 and 2 On-Site Gamma Spectroscopy Results for 541.5 Foot Incore Area............. 42 3.7.

Unit 1 Average Concentrations and Source Terms for 541.5 Foot Incore Area............... 50 3.8.

Unit 2 Average Concentrations and Source Terms for 541.5 Foot Incore Area............... 76 3.9.

Summary of Unit 1 and 2 Source Terms from In-House Gamma Spectroscopy Results................................................................................................................................ 96 3.10. Evaluation of Unit 1 and 2 Incore Area Eberline Off-Site Laboratory Results................. 97 3.11. Summary of Reactor Building Results and Calculated End State Source Terms with Interior Concrete Remaining........................................................................................... 108

4.

Calculations and Evaluations - Interior Concrete Removed In End State................................ 110 4.1.

Unit 1 Source Terms........................................................................................................ 110

5.

Conclusions................................................................................................................................ 112

6.

References.................................................................................................................................. 112

7.

Attachments............................................................................................................................... 114 7.1.

Attachment A - Unit 1 and 2 568 Elevation Core Locations......................................... 115 7.2.

Attachment B - U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results................................................................................................................. 117 7.3.

Attachment C - U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results................................................................................................................. 142 7.4.

Attachment D - U1 & 2 568 Elevation First Half Inch Eberline Results........................ 169 7.5.

Attachment E - Decay Corrected U1 & 2 568 Elevation First Half Inch Eberline Results............................................................................................................... 173 7.6.

Attachment F - Key Radionuclide Ratios Decay Corrected U1 & 2 568 Elevation Eberline Results............................................................................................................... 177 7.7.

Attachment G - U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results.............................................................................................................................. 181 7.8.

Attachment H - U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results.............................................................................................................................. 189 7.9.

Attachment I - U1 & 2 541.5 Foot Elevation First Half Inch Eberline Results.............. 198 7.10. Attachment J - Radionuclide Emissions and Yields........................................................ 199

TSD 13-006 Revision 0 Page 4 of 200 Table of Figures Figure 1 - Maine Yankee Incore Area Configuration............................................................................. 10 Figure 2 - Connecticut Yankee Incore Area Configuration.................................................................... 11 Figure 3 - Reactor Building End State with Potential Contaminated Concrete Inside Liner................. 12 Figure 4 - Zion Unit 1 and 2 Incore Area Side View............................................................................. 13 Figure 5 - Incore Area Concrete Included In Source Term Calculations............................................... 14 Figure 6 - Core Sample Puck Labeling................................................................................................... 19 Figure 7 - Example of Decay Corrected On-Site Gamma Spectroscopy Core Results in Attachment B..................................................................................................................... 20 Figure 8 - Unit 1 568' Total Activity Profile With Depth....................................................................... 23 Figure 9-Unit 2 568' Total Activity Profile Ci With Depth................................................................... 26 Figure 10 - Units 1 and 2 Incore Area Wall Profiles.............................................................................. 43 Figure 11 - Units 1 and 2 Co-60 Under Vessel Center Floor 14 Inch Cores......................................... 43 Figure 12 - Units 1 and 2 Co-60 Under Vessel Side Floor 6 Inch Cores............................................... 44 Figure 13 - Units 1 and 2 Co-60s-137 Under Vessel Wall 6 Inch Cores............................................... 44 Figure 14 - Units 1 and 2 Cs-137 Under Vessel Center Floor 14 Inch Core.......................................... 45 Figure 15 - Units 1 and 2 Cs-137 Under Vessel Side Floor 6 Inch Core............................................... 45 Figure 16 - Units 1 and 2 Cs-137 Under Vessel Wall 6 Inch Core........................................................ 46 Figure 17 - Units 1 and 2 Cs-134 Under Vessel Center Floor 14 Inch Core.......................................... 46 Figure 18 - Units 1 and 2 Cs-134 Under Vessel Side Floor 6 Inch Core............................................... 47 Figure 19 - Units 1 and 2 Cs-134 Under Vessel Wall 6 Inch Core........................................................ 47 Figure 20 - Units 1 and 2 Eu-152 Under Vessel Center Floor 14 Inch Core......................................... 48 Figure 21 - Units 1 and 2 Eu-152 Under Vessel Side Floor 6 Inch Core............................................... 48 Figure 22 - Units 1 and 2 Eu-152 Under Vessel Wall 6 Inch Core........................................................ 49 Figure 23 - Units 1 and 2 Eu-154 Under Vessel Center Floor 14 Inch Core......................................... 49 Figure 24 - Units 1 and 2 Eu-154 Under Vessel Side Floor 6 Inch Core............................................... 50 Figure 25 - Units 1 and 2 Eu-154 Under Vessel Wall 6 Inch Core........................................................ 50 Figure 26 - Unit 1 Incore Floor Average Co-60 Concentrations............................................................ 51 Figure 27 - Unit 1 Incore Floor Average Co-60 Concentrations First Puck Data Eliminated............... 52 Figure 28 - U1 Co-60 Incore Wall Profile Actual versus Worst Case................................................... 55 Figure 29 - Unit 1 Incore Floor Average Cs-137 Concentrations First Puck Data Eliminated.............. 57 Figure 30 - Unit 1 Incore Center Floor Average Cs-137 Concentrations First Puck Data Included...... 57 Figure 31 - U1 Cs-137 Incore Wall Profile Actual versus Worst Case.................................................. 59 Figure 32 - Unit 1 Incore Center Floor Average Cs-134 Concentrations............................................... 61 Figure 33 -Unit 1 Incore Center Floor Average Cs-134 Concentrations First Puck Data Included....... 61 Figure 34 - U1 Cs-134 Incore Wall Profile Actual versus Worst Case.................................................. 64 Figure 35 - U1 Eu-152 Data with Moving Average Trend Line Estimated Concentrations.................. 66 Figure 36 - U1 Eu-152 Data from 2.75 Inches with Moving Average Trend Line................................ 66 Figure 37 - U1 Eu-152 Incore Wall Profile Actual versus Worst Case.................................................. 68 Figure 38 - U1 Eu-154 Data with Moving Average Trend Line Estimated Concentrations.................. 70 Figure 39 - U1 Eu-154 Incore Wall Profile Actual versus Worst Case.................................................. 72 Figure 40 - Unit 2 Incore Floor Average Co-60 Concentrations............................................................ 76 Figure 41 - U2 Co-60 Incore Wall Profile Actual versus Worst Case................................................... 78 Figure 42 - Unit 2 Incore Floor Average Cs-137 Concentrations.......................................................... 80 Figure 43 - Unit 2 Incore Floor Average Cs-137 Concentrations At Greater Than 1 Inch.................... 80 Figure 44 - U2 Cs-137 Incore Wall Profile Actual versus Worst Case.................................................. 82 Figure 45 - Unit 2 Incore Floor Average Cs-134 Concentrations.......................................................... 84

TSD 13-006 Revision 0 Page 5 of 200 Figure 46 - U2 Cs-134 Incore Wall Profile Actual versus Worst Case................................................. 86 Figure 47 - Unit 2 Incore Floor Average Eu-152 Concentrations.......................................................... 87 Figure 48 - U2 Eu-152 Incore Wall Profile Actual versus Worst Case................................................. 89 Figure 49 - Unit 2 Incore Floor Average Eu-154 Concentrations.......................................................... 91 Figure 50 - Unit 1 & 2 Incore Wall Eu-154 Concentrations.................................................................. 92 Figure 51 - U2 Eu-154 Incore Wall Profile Actual versus Worst Case................................................. 93 List of Tables Table 1 - Power Reactors Decommissioned Through License Termination............................................ 7 Table 2-Summary of 568 Foot and Incore Under Vessel Area Concrete Calculations......................... 13 Table 3 - Reactor Building End State Surface Areas and Volumes....................................................... 14 Table 4 - Estimated Surface Area and Volume of Containment Steel Liner.......................................... 15 Table 5 - Reactor Building Concrete Core Survey Units and Samples................................................. 17 Table 6 - Unit 1 568' Co-60 Profile........................................................................................................ 21 Table 7 - Unit 1 568' Cs-137 Profile....................................................................................................... 21 Table 8 - Unit 1 568' Cs-134 Profile....................................................................................................... 22 Table 9 - July 1993 Zion UFSAR Table 3.8-8 Containment Concrete Mixes....................................... 22 Table 10 - Summary of Unit 1 568 Foot On-Site Gamma Spectroscopy Radionuclide Profiles and Fractions............................................................................................................................... 23 Table 11 - Unit 2 568' Co-60 Profile...................................................................................................... 24 Table 12 - Unit 2 568' Cs-137 Profile..................................................................................................... 24 Table 13 - Unit 2 568' Cs-134 Profile..................................................................................................... 25 Table 14 - Summary of Unit 2 568 Foot On-Site Gamma Spectroscopy Radionuclide Profiles and Fractions............................................................................................................................... 25 Table 15 - Ba-137m 32 - 37 keV Photon Energy/Intensity Data from NRC Radiological Toolbox.... 27 Table 16 - Sandia Report Table F1. Hazard category 3 threshold for one gram of spent fuel UO2....... 32 Table 17 - Comparison of Calculated Am-243 Concentrations to Decay Corrected Unit 2 Results..... 33 Table 18 - Comparison of In-House and Eberline Co-60 and Cs-137 Results for Unit 1 568' Samples.............................................................................................................. 34 Table 19 - Comparison of In-House and Eberline Co-60 and Cs-137 Results for Unit 2 568' Samples.............................................................................................................. 34 Table 20 - Summary of Key Radionuclide Ratios for U1 568 EL Cores............................................... 35 Table 21 - Summary of Key Radionuclide Ratios for U2 568 EL Cores............................................... 36 Table 22 - Summary of Unit 1 568 EL Eberline Results........................................................................ 38 Table 23 - Summary of Unit 2 568 EL Eberline Results........................................................................ 39 Table 24 - Summary of Estimated 568 EL Source Terms from Table 10 and Table 14....................... 40 Table 25 - Estimated Unit 1 and 2 568 EL Source Terms Based Upon Hard-To-Detect Scaling Factors...................................................................................................................... 41 Table 26 - Unit 1 Incore Floor Co-60 Profile......................................................................................... 52 Table 27 - Unit 1 Incore Wall Co-60 Profile Using Wall Core.............................................................. 54 Table 28-Connecticut Yankee Ratios Between Upper and Lower Incore Walls Based on Maximum and Average Concentrations............................................................................... 54 Table 29 - Unit 1 Incore Wall Co-60 Profile Using Floor Concentrations............................................ 55 Table 30 - Unit 1 Incore Floor Cs-137 Profile....................................................................................... 58 Table 31 - Unit 1 Incore Wall Cs-137 Profile Using Wall Core............................................................ 59 Table 32 - Unit 1 Incore Wall Cs-137 Profile Using Floor Concentrations........................................... 60 Table 33 - Unit 1 Incore Floor Cs-134 Profile....................................................................................... 62

TSD 13-006 Revision 0 Page 6 of 200 Table 34 - Unit 1 Incore Wall Cs-134 Profile Using Wall Core............................................................ 63 Table 35 - Unit 1 Incore Wall Cs-134 Profile Using Floor Concentrations........................................... 64 Table 36 - Unit 1 Incore Floor Eu-152 Profile....................................................................................... 67 Table 37 - Unit 1 Incore Wall Eu-152 Profile Using Wall Core............................................................ 68 Table 38 - Unit 1 Incore Wall Eu-152 Profile Using Floor Concentrations........................................... 69 Table 39 - Unit 1 Incore Floor Eu-154 Profile....................................................................................... 70 Table 40 - Unit 1 Incore Wall Eu-154 Profile Using Wall Core............................................................ 71 Table 41 - Unit 1 Incore Wall Eu-154 Profile Using Floor Concentrations........................................... 72 Table 42 - Summary of Calculated Unit 1 Incore Under Vessel Floor Source Terms........................... 73 Table 43 - Summary of Calculated Unit 1 Incore Under Vessel Wall Source Terms............................ 74 Table 44 - Unit 2 Incore Floor Co-60 Profile......................................................................................... 77 Table 45 - Unit 2 Incore Wall Co-60 Profile Using Wall Core.............................................................. 78 Table 46 - Unit 2 Incore Wall Co-60 Profile Using Floor Concentrations............................................ 79 Table 47 - Unit 2 Incore Floor Cs-137 Profile....................................................................................... 81 Table 48 - Unit 2 Incore Wall Cs-137 Profile Using Wall Core............................................................ 82 Table 49 - Unit 2 Incore Wall Cs-137 Profile Using Floor Concentrations........................................... 83 Table 50 - Unit 2 Incore Floor Cs-134 Profile....................................................................................... 84 Table 51 - Unit 2 Incore Wall Cs-134 Profile Using Wall Core............................................................ 85 Table 52 - Unit 2 Incore Wall Cs-134 Profile Using Floor Concentrations........................................... 86 Table 53 - Unit 2 Incore Floor Eu-152 Profile....................................................................................... 88 Table 54 - Unit 2 Incore Wall Eu-152 Profile Using Wall Core............................................................ 89 Table 55 - Unit 2 Incore Wall Eu-152 Profile Using Floor Concentrations........................................... 90 Table 56 - Unit 2 Incore Floor Eu-154 Profile....................................................................................... 91 Table 57 - Unit 2 Incore Wall Eu-154 Profile Using Wall Core............................................................ 93 Table 58 - Unit 2 Incore Wall Eu-154 Profile Using Floor Concentrations........................................... 94 Table 59 - Summary of Calculated Unit 2 Incore Under Vessel Floor Source Terms........................... 95 Table 60 - Summary of Calculated Unit 2 Incore Under Vessel Wall Source Terms............................ 96 Table 61 - Summary of Unit 1 and 2 Reactor Building Gamma Emitter Source Terms........................ 97 Table 62 - Unit 1 and 2 Reactor Source Term Fractions........................................................................ 97 Table 63 - Comparison of In-House and Eberline Gamma Spectroscopy Results for Unit 1 541.5' Samples......................................................................................................... 100 Table 64 - Comparison of In-House and Eberline Gamma Spectroscopy Results for Unit 2 541.5' Samples......................................................................................................... 101 Table 65 - Summary of Key Radionuclide Ratios for U1 541.5 EL Cores.......................................... 101 Table 66 - Summary of Key Radionuclide Ratios for U2 541.5 EL Cores.......................................... 103 Table 67 - Summary of Unit 1 541.5 EL Eberline Results................................................................... 105 Table 68 - Summary of Unit 2 541.5 EL Eberline Results................................................................... 106 Table 69 - Estimated Unit 1 and 2 In-Core Source Terms................................................................... 107 Table 70 - Unit 1 and 2 January 1, 2013 Scaled Radionuclide Inventories s....................................... 108 Table 71 - Unit 1 and 2 July 1, 2018 Scaled Radionuclide Inventories............................................... 109 Table 72 - Liner Surface Areas and Removable Contamination Source Terms Equivalent to 1000 dpm/100 cm2....................................................................................................................... 110 Table 73 - Summary of Bounding Liner Removable Surface Contamination Terms January 1, 2013................................................................................................................... 110 Table 74 - Summary of Liner Removable Surface Contamination Terms Decayed to July 1 2018.......................................................................................................................... 111

TSD 13-006 Revision 0 Page 7 of 200

1.

Introduction 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. [1] This technical support document (TSD) provides bounding estimates for the embedded concrete source terms in the Unit 1 and 2 Reactor Buildings below the 588 foot elevation. The source term estimates are based upon concrete cores collected from the 568 elevation concrete floor inside the liner and from the 541 6 Incore Under Vessel Area floor and wall. Cores were collected in Units 1 and 2 at locations exhibiting high contact dose rates and are therefore biased high.

The TSD also provides bounding estimates of the residual contamination on the containment liner in the event that all of the interior concrete is removed. 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 to guide remediation and final status survey (FSS) planning.

2.

Background

2.1.

Pressurized Water Reactor Containment End Sates and Concrete Characterization Prior to reviewing the sampling methodology and analysis results for the end state concrete at the Zion Station Restoration Project (ZSRP) Unit 1 and 2 it is important to understand the containment designs, end state configurations, and fate and transport modeling applied at other decommissioned reactors. As seen in Table 1, there are only 17 power reactors in the world whose licenses have been terminated, of these, 15 have been in the United Sates. [2], [3]

Table 1 - Power Reactors Decommissioned Through License Termination Country Plant Type MW Gross Ops Start Year/Month Shutdown Year/Month License Termination Year USA BONUS BWR 18 1965-9 1968-6 1970 USA HALLAM terphenyl 84 1963-11 1964-9 1971 USA ELK RIVER BWR 24 1964-7 1968-2 1974 USA SHIPPINGPORT PWR 68 1958-5 1982-10 1989 USA SHOREHAM BWR 849 NA 1989-5 1995 USA FORT ST. VRAIN HTGR 342 1979-7 1989-8 1996 JAPAN JPDR BWR 13 1965-3 1976-3 2002 SWITZERLAND LUCENS HWGCR 6

NA 1969-1 2004 USA SAXTON PWR 3

1967-3 1972-5 2005 USA YANKEE NPS PWR 180 1961-7 1991-10 2005 USA MAINE YANKEE PWR 900 1972-12 1997-8 2005 USA TROJAN PWR 1155 1976-5 1992-11 2005 USA BIG ROCK POINT BWR 71 1963-3 1997-8 2007 USA HADDAM NECK PWR 603 1968-1 1996-12 2007 USA SAN ONOFRE-1 PWR 456 1968-1 1992-11 2008 USA CVTR PHWR 19 NA 1967-1 2009 USA RANCHO SECO-1 PWR 917 1975-4 1989-6 2009 Total 17

TSD 13-006 Revision 0 Page 8 of 200 Pressurized Water Reactors (PWR), with similar reactor building designs, that have decommissioned to license termination include Maine Yankee (2005), Trojan (2005), Haddam Neck/Connecticut Yankee (2007), San Onofre 1, (2008) and Rancho Seco (2009). The Yankee Rowe containment design was an early spherical PWR containment design, with no subsurface structures and is not analogous to ZSRP Units 1 and 2. Rancho Seco, Trojan and San Onofre 1 used industrial scenario Derived Concentration Guideline Levels (DCGLs) to terminate their licenses with the containment buildings remaining largely intact at the time of license termination. The industrial scenario assumes a building occupancy after the license is terminated and has entirely different DCGLs and source term fate and transport modeling than the basement fill end state planned for Zion. Industrial scenario DCGLs are driven by direct dose rates and by inhalation from source term in the walls of the intact structure. The end state fate and transport and DCGLs are derived using RESRAD-BUILD for the industrial scenario.

Maine Yankee and Haddam Neck (e.g. Connecticut Yankee) demolished the containment building interiors and removed the structures to below ground level using a basement fill model similar to the end state plan for the Zion Unit 1 & 2 Reactor Buildings. The Maine Yankee and Connecticut Yankee decommissioning used DCGLs based upon a Resident Farmer scenario with fate and transport modeling and DCGLs determined using RESRAD, and spreadsheet calculations of source term release and transport in groundwater. For subsurface source terms in excavations and buried substructures the resultant doses are driven by the groundwater pathway with drinking water and meat ingestion doses from the Resident Farmer well dominating the future occupant doses post license termination.

All of the above PWRs characterized containment concrete using concrete cores for the purpose of planning remediation and demonstrating compliance with license termination criteria. This is the most commonly used concrete characterization method and is described in EPRI 1015502 [4] and NUREG/CR-5849 [5]

Since the Unit 1 and 2 bioshields will be removed and are not part of the end state, the activated concrete source term is limited to the Incore Area under the vessel. The under vessel in-core area designs of the above facilities are markedly different than Zion Unit 1 and 2. Another significant difference was the presence of neutron shield tanks in lieu of a bioshield at Maine Yankee and Connecticut Yankee. The reflective properties of the 2 inch thick steel plate on the inner face of the neutron shield tanks contributed to neutron streaming into the Incore area at Maine and CY.

Therefore concrete activation of the containment liners and in concrete beyond the containment liners were additional considerations at CY and MY. The end state configurations and source terms required more extensive remediation to meet the 10 CFR 20 Subpart E 25 mrem/year license termination dose limit and the EPA groundwater target of 15 picocuries per liter (pCi/L) alpha and less than 4 millirem per year (mrem/yr) for beta and photon emitters. [6], [7], [8]

Trojan Trojan chose to use the NRC Industrial Scenario Screening DCGLs for structures and to decontaminate all concrete structures Containment, Fuel and Auxiliary Buildings that were left intact. [9] Sample and survey results indicated the Containment Building interior structural concrete would need to be removed to assure compliance with dose objectives based upon future occupants of the structures. Samples taken at a number of structural joints, cracks in concrete and in-bed interfaces indicated the contamination might exceed release criteria. An estimate of the Containment Building concrete volume requiring removal to meet the screening

TSD 13-006 Revision 0 Page 9 of 200 DCGL was made through analyses of samples and direct surveys. Only Trojans containment structure and the approximately 1/4-in. thick steel liner remained following demolition activities and license termination. [10] Therefore, their end state is not analogous to the basement fill scenario planned for ZSRP.

At Trojan, samples of containment concrete were collected by core boring at four locations.

The bores were collected from the reactor shield wall, reactor vessel missile shield, secondary shield wall, and containment dome. The samples consisted of 3 inch diameter bores. The bores were segmented and counted on-site for radioactivity using gamma spectroscopy. The cores were used to validate the neutron activation analysis, to determine penetrating depth of activation products in concrete structures (other than the primary reactor vessel shield), and to estimate the area extent and levels of fixed surface contamination. [10] The Containment Building Bioshield Area 3 inch diameter concrete core bore was taken from the reactor vessel shield wall at approximately the 50 ft elevation (corresponding to near centerline of the reactor vessel). The core was segmented and analyzed for gamma ray emitters. Predominant radionuclides identified were Co-60, Eu-152, Eu-154, Eu,-155 and Cs-134. Radioactivity was detected to a depth of approximately 50 inches (total shield thickness is 102 inches). Close agreement was noted between the calculated neutron activation results and the measured activation values. The comparison was good for Eu-152 in the first 3 inch segment. The calculated Eu-152 activity value was 0.29 picocuries per gram (pCi/g) while the measured value was 0.25 pCi/g. The agreement was not as good for segments farther from the inner wall, although the calculated values were conservative. [10]

Maine Yankee At Maine Yankee (MY) concrete activity was due to penetration of surface contamination as well as activation of concrete constituents in areas exposed to neutron flux. (Activated concrete comprised approximately 5% of the concrete in containment.) Surface contamination penetration was primarily limited to the top 0.1 centimeters (cm). Activation generally followed expected activation curves, peaking at 1 to 2 inches into the concrete, and dropping off at greater depths. Slight anomalies in concrete activation were noted in the vicinity of embedded rebar. Positive indications of activation were seen as deep as 24 inches in some concrete samples that were exposed to high neutron fluence. [1] Concrete cores were removed and analyzed in order to estimate the radioactivity levels and nuclide distributions of shielding materials. The predominant radionuclides present in structural (activated) concrete were H-3, Fe-55, Eu-152, C-14, and Co-60 (comprising approximately 98 percent of the activity in activated concrete). [1]

TSD 13-006 Revision 0 Page 10 of 200 Figure 1 - Maine Yankee Incore Area Configuration The major variation with activated concrete was a decrease in total activity with depth in the material as shown by two deep core profile samples. [1] There was also a local effect on nuclide activity and ratio in the area immediately surrounding rebar contained within the concrete. As seen in Figure 1, there was no concrete on the walls inside the liner in the MY Incore Area and the Incore floor was only one foot thick. Consequently there was activation of the containment liner and in the concrete outside the liner.

Two highly activated concrete samples were analyzed for hard-to-detect (HTD) radionuclides.

One portion of activated concrete included embedded rebar. The rebar sample was also analyzed for HTDs. The HTD nuclides showed the same level of consistency as the gamma emitters when compared to published values (NUREG/CR-3474). [1] A core from the in-core instrumentation (ICI) sump was extended to a depth of 22 inches in order to improve the activated concrete profile. The depth profile was used to plan remediation activities for the ICI sump area. The projected post remediation activity remaining in the ICI sump area was used in the license termination dose calculations. [1] Two floor trench concrete samples were taken and submitted for HTD analysis to confirm and/or rule out some nuclide outliers reported by off-site laboratory from a trench sample processed by another laboratory. [1]

The nuclide profile determined for contaminated concrete was assumed to apply to all concrete surfaces. The sample results were averaged over the entire population and the individual samples compared for consistency. As might be expected, the data were somewhat varied depending on the concrete location, spill history, decontamination history, surface coating and age.

The nuclide fraction for contaminated material was established using each of the positively identified nuclides. The non-detected nuclides were assumed not to be present in the mixture.

In order to ensure that the elimination of non-detected nuclides at their MDC levels would not significantly affect the results, a sensitivity analysis based on dose was performed. Dose rates were determined for each individual core, for the core average values and for the average of the fractions using all nuclides in the suite at their actual value or their reported MDA, then the analysis was repeated using only the detected nuclides. [1] It is important to note that activation outside the containment liner was an important consideration driving the removal of the contaminated concrete floors at MY in order to meet the license termination dose objectives.

TSD 13-006 Revision 0 Page 11 of 200 Connecticut Yankee Concrete cores were taken in four of the five areas of the site at Connecticut Yankee (CY) where subsurface concrete was being considered for leaving in place post site closure. [11]

Core sampling also included many subsurface structures that are normally not impacted but had the potential for sorbed source term due to extensive soil and groundwater contamination. [12]

The samples were all analyzed for gamma radionuclides and tritium; and selected samples were analyzed for transuranic radionuclides, strontium-90, and other hard-to-detect radionuclides.

Due to the significant sorption of radionuclides from the soil and groundwater contamination, CY decided to remove much of the concrete, but still planned to leave concrete below 4 foot under grade in the cable vault, the containment liner, the containment in-core sump, and the containment sump suction line piping. [11] The Auxiliary Building subsurface concrete was completely removed to bedrock. A large excavation was required to remediate soil contamination and activity in bedrock fractures below the Aux Building RHR Sump; remediation required bedrock blasting to remove the source term in order to meet the license termination dose criterion.

The final Containment end state at Connecticut Yankee had interior walls and floors demolished and removed. The Containment liner was removed with the exception of the Incore Sump, which was filled with grout to the basement floor elevation. The dose contribution from the sorbed contamination in the Containment foundation pop-corn concrete was a significant factor that drove the end state configuration at CY. There was very little margin for additional source term in subsurface structures. In addition, the difficulty of physically removing activated concrete beyond the Incore area liner and significant potential for groundwater intrusion during such remediation were significant factors driving the MY and CY containment end state configurations.

As seen in Figure 2, there was no concrete interior to the liner on the Incore area walls and the Incore Area floor under the vessel was only one foot thick. This resulted in neutron activation beyond the liner at CY.

Figure 2 - Connecticut Yankee Incore Area Configuration The remaining interior surfaces inside the Containment shell were decontaminated. Following decontamination, the Containment basement was filled with soil to the grade of the exterior open land. [13] The radionuclides that were identified as volumetric contaminants in concrete

TSD 13-006 Revision 0 Page 12 of 200 at CY were H-3, Fe-55. Co-60, Sr-90, Cs-137 and Eu-152. Preliminary core data at CY found H-3, Co-60, and Eu-152 in the walls and floors of certain basements with Fe-55, Sr-90 and Cs-137 found in less significant quantities. [14]

2.2.

Zion Reactor Building (Containment) End State In accordance with Section 8.5 Removal of Improvements; Site Restoration of the Asset Sale Agreement, [15] the Reactor Building end states will consist of the walls and floors below 588 foot elevation remaining. Initially it was planned that only the steel liner, 568 foot elevation concrete floor, and the Incore Tunnel Area concrete walls and floor would remain in the end state. The final end state configuration is currently being planned. The final end state may include the annulus wall and other ancillary walls. The source term in these ancillary walls is anticipated to be minimal in comparison to the 568 foot elevation floors. It may also include removal of all interior concrete due to non-radiological contaminants. The basements will be backfilled with clean fill upon completion of FSSs. This TSD estimates residual radioactivity under either scenario.

The Reactor Building end state estimated concrete surface areas and volumes (without the annulus wall and other ancillary walls) are provided in TSD 13-005 [16]. The liner volumes and surface area, if the interior concrete is removed, are also provided in the TSD. This calculation assumes the concrete inside the containment liner remains at the time of license termination as shown in Figure 3. The worst case bounding source term based upon removable contamination on the liner is also estimated in the event that all interior concrete is removed.

Figure 3 - Reactor Building End State with Potential Contaminated Concrete Inside Liner The TSD 13-005 [16] calculations included surface areas and void spaces for sumps, the Incore tunnel walls, etc. The calculated surface areas and volumes of concrete for the 568 elevation floor and the under vessel Incore area floor and walls are summarized in Table 2. The end state calculations do not include the annulus wall and other ancillary walls that may be part of the final end state configuration but would have minimal contribution to the overall source term.

The calculation does not include the reduced volume or increased surface area that may result from any removals of embedded piping that may be part of the final end state configuration.

TSD 13-006 Revision 0 Page 13 of 200 Table 2-Summary of 568 Foot and Incore Under Vessel Area Concrete Calculations Section Length in Width or Radius in Thickness in Surface Area ft2 Volume ft3 Surface Area cm2 568' EL Floor Sump Corrected N/A 840 36 15714.2 44546.1 1.46E+07 Incore Area Under Vessel Floor N/A 102.5 30 229.2 573.0 2.13E+05 Incore Area Under Vessel Wall 348 102.5 23.5 1442.9 3149.7 1.34E+06 Incore Area Sump Area Floor 87 90 30 70.4 127.9 6.54E+04 Incore Area Fan Shaped Floor 185.5 126 30 157.1 392.7 1.46E+05 Totals feet 17613.8 48789.4 1.64E+07 Totals meters 1636.4 1381.6 4.63E+05 TSD 13-005. [16] included calculation of surface areas and volumes of the walls, sloped floors and ceilings of the Incore Access Tunnel as seen in Figure 4.

Figure 4 - Zion Unit 1 and 2 Incore Area Side View As seen in Figure 5 only the shaded concrete walls and floor areas were included in the embedded contamination source term calculations. Any source term embedded in the sloped tunnel floor, walls or ceiling is bounded by the selection of 568 foot core locations at locations with elevated readings or that had physical evidence of leaks and spills.

TSD 13-006 Revision 0 Page 14 of 200 Figure 5 - Incore Area Concrete Included In Source Term Calculations The surface areas and volumes from TSD 13-005 [16] are provided in Table 3. The total surface area in the Reactor Building end state is 27,640 square feet or 2,568 square meters.

Although located outside the containment liner, the Tendon Tunnels and their sumps also have exhibited trace levels of radioactivity from removable contamination tracked in over the years.

Prior to reviewing and considering the Reactor Building core data it is important to recognize that the Incore design at Zion varies markedly from the other PWRs discussed above. There is a 23.5 inch thick interior concrete wall inside the Incore area liner walls and the Incore area floor is 30 inches thick as opposed to other facilities that had no interior concrete in the Incore area and significantly less interior concrete on the floors (e.g., 12 inch floors at MY and CY and a 5 inch floor at Rancho Seco).

Table 3 - Reactor Building End State Surface Areas and Volumes Section Length in Width or Radius in Thickness in Total Surface Area ft2 Total Volume ft3 Containment 588' to 568' Containment Liner 588' to 568' (L) Not Concrete Related 240 840 N/A 8796.46 N/A 568' EL Floor (K) Sump Corrected N/A 840 36 15714.20 44546.07 Under Vessel Incore Area 568' to 541'6" Under Vessel Wall (J) 348 102.5 23.5 1442.94 3149.68 Under Vessel Floor (I)

N/A 102.5 30 229.21 573.03 Incore Area Access Tunnel Sloped Tunnel Floor (A) 320 90 15 199.93 249.91

TSD 13-006 Revision 0 Page 15 of 200 Section Length in Width or Radius in Thickness in Total Surface Area ft2 Total Volume ft3 Sloped Tunnel Ceiling (B) 168 90 15 105.00 131.25 Sloped Tunnel Walls (C) 319.9 94 15 417.62 688.64 Tunnel Ceiling (D) 196 90 15 122.50 153.13 Sump Area Floor (E) 87 90 30 70.38 127.94 Sump Area Walls (F) 87 123 15 148.63 253.75 Fan Shaped Floor(G) 179.5 126 30 157.06 392.66 Fan Shaped Walls (H) 157.04 123 15 268.27 458.02 Reactor Building Interior Totals feet 27672.19 50724.06 Reactor Building Interior Totals meters 2570.83 1436.35 Reactor Building Interior Concrete Only meters 18875.73 1436.35 Tendon Tunnel Tendon Access Gallery Floor (M)

N/A 798 24 1943.86 3887.72 Tendon Access Gallery Inner Wall (N) 90 798 24 1566.87 8058.19 Tendon Access Gallery Outer Wall (O) 90 852 24 1672.90 8595.40 Totals feet 5183.63 20541.30 Totals meters 481.57 581.66 The surface areas and volumes of steel liner below the 588 elevation were also calculated in TSD 13-005 [16] in the event that all of the interior concrete is removed and only the 1/4 inch liner remains. This assumes all of the liner including sumps and Incore area ceilings, walls and floors remains intact.

Table 4 - Estimated Surface Area and Volume of Containment Steel Liner Section Length in Width or Radius in Thickness in Surface Area ft2 Vol ft3 Num of Items Total Surface Area ft2 Total Liner Volume ft3 Sloped Tunnel Floor (A) 346 120 0.25 288 6

1 288 6

Sloped Tunnel Ceiling (B) 168 120 0.25 140 3

1 140 3

Sloped Tunnel Walls (C) 346 183 0.25 440 9

2 880 18 Tunnel Ceiling (D) 124 120 0.25 103 2

1 103 2

Sump Area Floor (E) 87 120 0.25 73 2

1 73 2

Sump Area Walls (F) 87 168 0.25 102 8

2 203 17 Fan Shaped Floor(G) 138 183 0.25 175 4

1 175 4

Fan Shaped Walls (H) 276 124 0.25 238 5

2 475 10 Under Vessel Floor (I)

N/A 126 0.25 346 7

1 346 7

Under Vessel Wall (J) 312 126 0.25 1526 32 1

1526 32 565' EL Floor (K) Sump Corrected N/A 840 0.25 15361.2 320 1

15361 320 Containment Liner Wall 565' to 588' 276 840 0.25 10116 211 1

10116 211 Totals feet 29,687.6 631.4 Totals meters 2,758.1 17.9

TSD 13-006 Revision 0 Page 16 of 200 2.3.

Reactor Building Source Terms and Characterization Radionuclide profiles and source terms are determined by concrete core sampling in order to determine radionuclide concentrations at depth in end state concrete. [15] There are several components of the overall radioactive source term that may remain in reactor building end state concrete.

Radionuclides absorbed from contaminated water (e.g., spills and leaks)

Activation radionuclides from neutron flux in areas adjacent to the active core.

Radionuclides absorbed from diffusion of gaseous radionuclides or parent nuclides Removable surface contamination from spills, leaks and airborne radioactivity.

The embedded source terms from neutron activation and diffusion of gases into the end state materials (e.g., paint, concrete, and steel) ceased when the units were permanently shut down in September of 1997. Other source terms such as those associated airborne radioactivity and spills have the potential to be changed by decontamination and decommissioning (D&D) activities during removal of systems, structures and components (SSCs). Removable surface contamination levels are more easily controlled and bounded by establishing Final Status Survey (FSS) limits on allowable removable contamination levels, such as 1,000 disintegrations per minute per one hundred square centimeters (dpm/100 cm2) beta gamma activity. Contamination deposited in an area during commodity removal and demolition can be deposited in concrete cracks or sorbed by concrete from standing water. Thus end state surface contamination and embedded contamination associated with these deposition modes have the potential to change between initial characterization and the final post remediation end state once D&D activities are completed in the buildings. Whereas gaseous deposition (e.g., H-3, C-14, etc.) and neutron activation source term contributions have ceased and will only change due to decay. Since production of radionuclides ceased when the facility shut down in 1997, radionuclides such as Cr-51, Fe-55, Co-58, Cs-134, Mn-54, Ag-110m, Ce-144, etc. which have half-lives of a few years or less, also have a limited inventory relative to the end state.

Embedded source terms from diffusion of gases such as C-14 and H-3 are deposited during plant operation. Due to the weak beta emissions and low production and diffusion rates, these source terms tend to be minor in terms of end state dose consequences in comparison to neutron activation source terms and sorbed source terms from spills. Activation source terms from neutron flux are also anticipated to be minor in comparison to source terms deposited from leaks and spills since the bioshield which surrounds the active core region will be removed to the 568 foot floor. Activation source terms are dominated Eu-152, Eu-154, Co-60, and Cs-134 which build up over time from neutron activation reactions with trace amounts of stable Europium, Cobalt, and Cesium on concrete. Production of Co-60 is dominated by activation of rebar in the concrete. Other activation constituents such as H-3 and C-14 from activation of water in the concrete can have significant concentrations, but generally have insignificant dose consequences due to the weak beta emissions.

The most highly activated end state concrete will be the 568 foot floor concrete surrounding the reactor since it is closest to the active core region. The concrete inside the liner in the under vessel Incore area will also be activated. Other facilities, such as Rancho Seco, Maine Yankee and Connecticut Yankee exhibited significant neutron activation of concrete outside the liner.

However, these facilities either had no concrete or minimal concrete inside the liner in the Incore area to moderate and absorb neutrons. As mentioned above, Zion Units 1 and 2 have

TSD 13-006 Revision 0 Page 17 of 200 interior concrete walls 23.5 inches thick in the under vessel Incore area and 30 inch thick concrete floors inside the liner. Thus unlike CY and MY, the potential for activation outside the liner is minimal. As noted above the sorbed activity from spills and leaks typically comprises the bulk of the embedded concrete source term in other PWRs and is predominantly deposited in the upper most layer of the profile.

2.4.

Zion Core Collection and Handling Method A series of core samples were collected at the 568 elevation in Units 1 and 2 as shown in Attachment A. The cores were obtained using characterization survey packages prepared and approved in accordance ZS-RP-107-001-001 [17]. A survey package was prepared for each of the Unit 1 and 2 568 foot elevation survey units as defined in the ComEd Zion Station Historical Site Assessment [18]. Since the bioshield is to be removed as waste and will not remain in the end state configuration, only one core was obtained for Survey Unit 1101. No bioshield core was obtained in Unit 2 survey unit 2101. The survey units, characterization package identification, and description are provided in Table 5. A total of 39 cores were collected (20 in Unit 1, 19 in Unit 2).

Table 5 - Reactor Building Concrete Core Survey Units and Samples Surv Unit Characterization Survey Package Identification Survey Unit Description Number of Cores In-House Gamma Spec Off-Site Analysis Unit 1 1101 B101101C-U1 CTMT Bioshield Vessel Bioshield U1 CTMT 1

1 0

1102 B101102C-U1 CTMT A Loop IMB 568 Inside Missile Barrier - A Loop 568 Ft U1 CTMT 2

2 1

1103 B101103C-U1 CTMT B Loop IMB 568 Inside Missile Barrier - B Loop 568 Ft U1 CTMT 2

2 1

1104 B101104C-U1 CTMT C Loop IMB 568 Inside Missile Barrier - C Loop 568 Ft U1 CTMT 2

2 1

1105 B101105C-U1 CTMT D Loop IMB 568 Inside Missile Barrier - D Loop 568 Ft U1 CTMT 2

2 2

1106 B101106C-U1 CTMT A Loop OMB 568 Outside Missile Barrier - A Loop 568 Ft U1 CTMT 2

2 1

1107 B101107C-U1 CTMT B Loop OMB 568 Outside Missile Barrier - B Loop 568 Ft U1 CTMT 2

2 1

1108 B101108C-U1 CTMT C Loop OMB 568 Outside Missile Barrier - C Loop 568 Ft U1 CTMT 2

2 1

1109 B101109C-U1 CTMT D Loop OMB 568 Outside Missile Barrier - D Loop 568 Ft U1 CTMT 2

2 1

1110 B101110C-U1 CTMT Undervessel 539 Incore Area 543 Ft Elevation U1 CTMT 3

3 2

Unit 2 2102 B102102C-U2 CTMT A Loop IMB 568 Inside Missile Barrier - A Loop 568 Ft U2 CTMT 2

2 1

2103 B102103C-U2 CTMT B Loop IMB 568 Inside Missile Barrier - B Loop 568 Ft U2 CTMT 2

2 2

2104 B102104C-U2 CTMT C Loop IMB 568 Inside Missile Barrier - C Loop 568 Ft U2 CTMT 2

2 0

2105 B102105C-U2 CTMT D Loop Inside Missile Barrier - D Loop 568 Ft 2

2 2

TSD 13-006 Revision 0 Page 18 of 200 Surv Unit Characterization Survey Package Identification Survey Unit Description Number of Cores In-House Gamma Spec Off-Site Analysis IMB 568 U2 CTMT 2106 B102106C-U2 CTMT A Loop OMB 568 Outside Missile Barrier - A Loop 568 Ft U2 CTMT 2

2 2

2107 B102107C-U2 CTMT B Loop OMB 568 Outside Missile Barrier - B Loop 568 Ft U2 CTMT 2

2 1

2108 B102108C-U2 CTMT C Loop OMB 568 Outside Missile Barrier - C Loop 568 Ft U2 CTMT 2

2 0

2109 B102109C-U2 CTMT D Loop OMB 568 Outside Missile Barrier - D Loop 568 Ft U2 CTMT 2

2 0

2110 B102110C-U2 CTMT Undervessel 539 Incore Area 543 Ft Elevation U2 CTMT 3

3 2

Total Cores 38 38 21 Note: The bioshield core is not included in the totals and the data is not provided or discussed since it was from the outside of the bioshield inward and only deep enough to start detecting activation. It is therefore of limited value since the interior of the bioshield was not characterized and it is being removed and will not be part of the end state.

A Bioshield core in Unit 1 was obtained to verify that neutrons were attenuated prior to traversing the bioshield and therefore there was no potential for activation in areas outside the bioshield from the 588 to the 568. A 6 foot core was obtained from the outer surface of the Unit 1 bioshield inward at the core center line. The core centerline was approximately 3 feet above the 568 foot floor.

Core locations for the 568 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 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.

Unless refusal was encountered due to piping or rebar, the cores were obtained using a 3 inch bit at depths of 6 inches for the 568 foot samples. The Reactor Building 568 foot concrete floors are 3 feet thick. Six inch cores were obtained in order to ensure there was no risk of puncturing the 1/4 steel liner creating a path for groundwater in-leakage. The Unit 1 and Unit 2 568 cores ranged from 1 to 6 inches in depth.

The six 541.5 foot elevation Incore area cores were obtained from three pre-selected locations based upon previous scans in the under vessel area of each unit. The Incore area cores were obtained to assess the neutron activation radionuclide profiles as well as fixed surface and/or embedded contamination from spills. The Incore area walls inside the 1/4 steel liner are 23.5 inches thick. The floor inside the liners is 30 inches thick. Core depths were selected to prevent damage of the liner. A 6 inch core sample was collected from the floor and the wall of each unit. In addition an 18 inch core sample was collected from the 541.5 foot floor of each unit to assess the activation radionuclide profile at depth.

TSD 13-006 Revision 0 Page 19 of 200 Figure 6 - Core Sample Puck Labeling Upon extraction the top of each core 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 Chain of Custody form.

2.5.

Sample Core Processing and Analysis Prior to processing, cores were wiped down and smear surveyed to ensure that 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 21 out of the 38 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 and Evaluations - Interior Concrete Remaining In End State 3.1.

Summary of Unit 1 and 2 On-Site Gamma Spectroscopy Results for 568 Foot Floor Cores The on-site gamma spectroscopy results for the sectioned cores from the 568 foot elevations are provided in Attachment B for Unit 1 and Attachment C for Unit 2. With one exception, Co-60, Cs-137 and Cs-134 were identified by gamma spectroscopy in each of the core samples. Core B102105-CJFCCV-001 positively identified Eu-154 in the first half inch. 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

TSD 13-006 Revision 0 Page 20 of 200 in the results when the nuclide was not positively identified. The MDA values used are noted in bold italics.

Figure 7 is an example of the data table for each core contained in Attachments B and C. 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 taken is also provided in the summary of the data in Attachments B and C.

As seen in Figure 7 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.

Figure 7 - Example of Decay Corrected On-Site Gamma Spectroscopy Core Results in Attachment B Each Unit 1 and 2 core has a table similar to Figure 7 provided in Attachment B or C. This represents the initial characterization concentrations present in the U1 and U2 568 ft floors on January 1, 2013.

6/12/12 1/1/13 0.131527 0.336479 0.023105 Core Section Depth wt (gms)

Date Time Date Time Count time Decay Days Co-60 pCi/gm Cs-134 pCi/gm Cs-137 pCi/gm Total pCi/gm 0

8/27/12 0738 8/23/12 14:52 300 131 96.9 30.8 3.46E+04 3.47E+04 0.5 8/27/12 0739 8/23/12 14:53 300 131 65.9 23.1 2.38E+04 2.39E+04 0.5 7/25/12 1127 7/18/12 13:37 1000 167 1.58 0.13 2.26 3.97E+00 1

7/25/12 1146 7/18/12 13:37 1000 167 1.43 0.13 2.12 3.68E+00 1

7/25/12 1205 7/18/12 13:37 1000 167 0.39 0.07 1.36 1.83E+00 1.5 7/25/12 1243 7/18/12 13:37 1000 167 0.47 0.13 1.23 1.82E+00 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/gm Cs-134 Puck Avg pCi/gm Cs-137 Puck Avg pCi/gm 92.4 27.3 3.43E+04 62.9 20.5 2.36E+04 1.5 0.1 2.24E+00 1.3 0.1 2.10E+00 0.4 0.1 1.35E+00 0.4 0.1 1.22E+00 U1 CTMT 568 IMB Loop A B101102-CJFCCV-001 Gamma Spec Report Gamma Spec Report Sample Taken On Puck 1 137 Puck 3 Decay Const y-1 Core Collection Date Decay To Date 2.2 0.4 150 141 Puck 2 Puck 3 Puck 1 Puck 2 0.1 1.3 77.6 23.9 2.90E+04 1.4 0.1

TSD 13-006 Revision 0 Page 21 of 200 3.2.

Unit 1 568 Foot Radionuclide Profile from On-Site Gamma Spectroscopy Results 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. As seen in Table 6 through Table 8 the majority of the Unit 1 source term for each nuclide (Co-60, Cs-137 and Cs-134) is in the first half-inch of the 568 foot concrete. The maximum, minimum and average concentration results at each depth were calculated and are provided in Column 2 of each table.

Table 6 - Unit 1 568' Co-60 Profile U1 568 Co-60 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Co-60 pCi/g Min.

Co-60 pCi/g Avg.

Co-60 pCi/g Co-60 Ci Co-60 dpm/100 cm2 Source Term Distribution 0.25 16 33374.2 7.5 2656.7 0.118 1.80E+06 57%

0.75 16 14732.3 0.1 927.8 0.041 6.29E+05 20%

1.25 11 6446.0 0.2 594.6 0.027 4.03E+05 13%

1.75 9

2558.2 0.4 292.7 0.013 1.98E+05 6%

2.25 8

509.3 0.3 74.5 0.003 5.05E+04 2%

2.75 8

231.3 0.2 36.6 0.002 2.48E+04 1%

3.25 8

119.9 0.7 21.6 0.001 1.46E+04 0.5%

3.75 6

20.2 0.7 9.1 0.000 6.19E+03 0.2%

4.25 4

19.4 4.0 12.0 0.001 8.11E+03 0.3%

4.75 3

64.2 5.4 29.0 0.001 1.96E+04 1%

Total 0.208 3.16E+06 1.00 Table 7 - Unit 1 568' Cs-137 Profile U1 568 Cs-137 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-137 pCi/g Min.

Cs-137 pCi/g Avg.

Cs-137 pCi/g Cs-137 Ci Cs-137 dpm/100 cm2 Source Term Distribution 0.25 16 449698.0 57.7 103029.8 4.5936 6.99E+07 68%

0.75 16 123952.0 0.2 10779.8 0.4806 7.31E+06 7%

1.25 11 108086.2 1.3 12445.3 0.5549 8.44E+06 8%

1.75 9

40987.8 1.6 6767.2 0.3017 4.59E+06 4%

2.25 8

19676.1 0.3 3274.6 0.1460 2.22E+06 2%

2.75 8

14422.5 0.3 3403.0 0.1517 2.31E+06 2%

3.25 8

19230.1 4.5 3394.6 0.1513 2.30E+06 2%

3.75 6

20222.6 6.0 4435.9 0.1978 3.01E+06 3%

4.25 4

13630.4 12.7 3998.3 0.1783 2.71E+06 3%

4.75 3

2638.1 10.4 905.0 0.0404 6.14E+05 1%

Total 6.796 1.03E+08 1.00

TSD 13-006 Revision 0 Page 22 of 200 Table 8 - Unit 1 568' Cs-134 Profile U1 568 Cs-134 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-134 pCi/g Min.

Cs-134 pCi/g Avg.

Cs-134 pCi/g Cs-134 Ci Cs-134 dpm/100 cm2 Source Term Distribution 0.25 16 103.2 0.3 28.9 0.0013 1.96E+04 64%

0.75 16 67.2 0.1 5.9 0.0003 3.98E+03 13%

1.25 11 42.4 0.1 6.2 0.0003 4.18E+03 14%

1.75 9

3.1 0.1 0.9 4.01E-05 6.09E+02 2%

2.25 8

2.0 0.1 0.7 2.91E-05 4.43E+02 1%

2.75 8

2.1 0.1 0.6 2.53E-05 3.84E+02 1%

3.25 8

1.7 0.1 0.5 2.07E-05 3.15E+02 1%

3.75 6

1.2 0.1 0.4 1.84E-05 2.80E+02 1%

4.25 4

1.3 0.2 0.6 2.49E-05 3.79E+02 1%

4.75 3

0.5 0.1 0.4 1.75E-05 2.66E+02 1%

Total 0.002 3.04E+04 1.00 The estimated source term in Curies (Ci) for each nuclide was calculated based on the 568 foot elevation surface area of 15,714.20 square feet from Table 2. [16] A 1/2 inch thick depth of this surface area has a volume of 1.854E+07 cubic centimeters. Table 3.8-8 of the Zion Updated Final Safety Analysis Report (UFSAR) [19] provides the weights of materials per cubic yard for 5500 pounds per square inch (psi) concrete and 5000 psi concrete used in the containments at ZSRP. These material tallies are used to calculate the densities as shown in Table 9.

Table 9 - July 1993 Zion UFSAR Table 3.8-8 Containment Concrete Mixes Material 5500 psi Pounds per Cubic Yard 5000 psi Pounds per Cubic Yard Cement 565 520 Fly Ash 110 110 Sand 1310 1270 Course Aggregate 3/4" No. 4 1820 1860 Water 248 255 Darex 0.31 0.30 Total Pounds per Cubic Yard 4053.3 4015.3 Totals Grams per Cubic Yard 1.84E+06 1.82E+06 Densities g/cc 2.40 2.38 Using a density for concrete of 2.40 grams per cubic centimeter (g/cc) yields a mass of 4.459E+7 grams for each 1/2 inch layer of the 568 floor and sump walls. When multiplied times the average concentration this provides a bounding estimate of the source term in each layer.

Since the 568 foot surface area includes the walls and floors of the sumps, which are normally steel lined, this is also a conservative assumption. As such the estimated source terms are worst case and bounding when used for remediation planning or estimates of the dose consequences associated with the end state conceptual site model.

TSD 13-006 Revision 0 Page 23 of 200 Table 10 compares the estimated source terms for each nuclide at depth and the fractional contribution of each nuclide. The Unit 1 floor source term is dominated by Cs-137 which accounts for over 97% of the total source term and exceeds 90 percent of the source term at all depths. In relative terms the Co-60 and Cs-134 source terms are not significant.

Table 10 - Summary of Unit 1 568 Foot On-Site Gamma Spectroscopy Radionuclide Profiles and Fractions Avg Depth in Co-60 Ci Cs-137 Ci Cs-134 Ci Total Ci Co-60 Fraction Cs-137 Fraction Cs-134 Fraction Total Activity Profile 0.25 0.118 4.594 0.0013 4.7 3%

97%

0.03%

67%

0.75 0.041 0.481 0.00026 0.5 8%

92%

0.05%

7%

1.25 0.027 0.555 0.00028 0.6 5%

95%

0.05%

8%

1.75 0.013 0.302 0.00004 0.3 4%

96%

0.01%

4%

2.25 0.003 0.146 0.00003 0.1 2%

98%

0.02%

2%

2.75 0.002 0.152 0.00003 0.2 1%

99%

0.02%

2%

3.25 0.001 0.151 0.00002 0.2 1%

99%

0.01%

2%

3.75 0.000 0.198 0.00002 0.2 0.2%

100%

0.01%

3%

4.25 0.001 0.178 0.00002 0.2 0.3%

100%

0.01%

3%

4.75 0.001 0.040 0.00002 0.0 3.1%

97%

0.04%

1%

Totals 0.208 6.796 0.002 7.006 3.0%

97.0%

0.03%

100%

The data also shows that 67% of the source term is contained in the first half inch of the floor.

As seen in Figure 8 the concentration is relatively uniform after the first half inch.

Figure 8 - Unit 1 568' Total Activity Profile With Depth 0%

10%

20%

30%

40%

50%

60%

70%

80%

0 1

2 3

4 5

% Activity Depth Inches Unit 1 568' Total Activity Profile Fraction Total Activity Profile

TSD 13-006 Revision 0 Page 24 of 200 3.3.

Unit 2 568 Foot Radionuclide Profile from On-Site Gamma Spectroscopy Results 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. As seen in Table 11 through Table 13 the majority of the Unit 2 source term for each nuclide (Co-60, Cs-137 and Cs-134) is in the first half-inch of the 568 foot concrete. The number of results that each depth profiles maximum, minimum and average concentrations are based on is shown in Column 2 of each table.

The estimated source term in Curies for each nuclide was calculated by using the 568 foot elevation surface area of 15,714.20 square feet from Table 2. [16] A 1/2 inch thick depth of this surface area has a volume of 1.854E+7 cubic centimeters (cc). Using a density for concrete of 2.40 g/cc yields a mass of 4.459E+7 grams for each 1/2 inch layer of the floor.

Table 11 - Unit 2 568' Co-60 Profile U2 568 Co-60 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Co-60 pCi/g Min.

Co-60 pCi/g Avg.

Co-60 pCi/g Co-60 Ci Source Term Distribution 0.25 16 85059.3 10.4 5562.0 0.248 97%

0.75 16 207.7 0.2 19.5 0.001 0.3%

1.25 16 253.8 0.1 18.7 0.001 0.3%

1.75 13 104.0 0.1 11.8 0.001 0.2%

2.25 11 273.5 0.1 32.2 0.001 0.6%

2.75 10 622.8 0.1 67.5 0.003 1.2%

3.25 9

10.1 0.1 2.2 0.0001 0.04%

3.75 9

6.5 0.1 1.5 0.0001 0.03%

4.25 6

4.7 0.1 1.7 0.0001 0.03%

4.75 4

4.1 0.1 1.2 0.0001 0.02%

5.25 4

2.6 0.1 0.7 0.00003 0.01%

5.75 2

3.5 0.4 1.9 0.0001 0.03%

Total 0.255 1.00 Table 12 - Unit 2 568' Cs-137 Profile U2 568 Cs-137 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-137 pCi/g Min.

Cs-137 pCi/g Avg.

Cs-137 pCi/g Cs-137 Ci Source Term Distribution 0.25 16 107434.4 189.5 13492.3 0.6016 83%

0.75 16 20031.0 0.1 1355.0 0.0604 8%

1.25 16 12098.9 0.1 776.2 0.0346 5%

1.75 13 5492.2 0.1 427.2 0.0190 3%

2.25 11 1405.7 0.1 131.5 0.0059 1%

2.75 10 420.7 0.1 45.8 0.0020 0.282%

3.25 9

40.9 0.1 5.8 0.0003 0.036%

3.75 9

34.4 0.1 4.4 0.0002 0.027%

4.25 6

17.3 0.1 3.3 0.0001 0.020%

TSD 13-006 Revision 0 Page 25 of 200 U2 568 Cs-137 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-137 pCi/g Min.

Cs-137 pCi/g Avg.

Cs-137 pCi/g Cs-137 Ci Source Term Distribution 4.75 4

0.8 0.1 0.3 0.00002 0.002%

5.25 4

0.4 0.1 0.2 0.00001 0.001%

5.75 2

0.4 0.1 0.2 0.00001 0.002%

Total 0.724 1.00 Table 13 - Unit 2 568' Cs-134 Profile U2 568 Cs-134 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-134 pCi/g Min.

Cs-134 pCi/g Avg.

Cs-134 pCi/g Cs-134 Ci Source Term Distribution 0.25 16 197.3 0.3 20.3 9.03E-04 85%

0.75 16 27.3 0.1 1.9 8.43E-05 8%

1.25 16 2.8 0.1 0.3 1.38E-05 1%

1.75 13 1.2 0.1 0.2 1.03E-05 1%

2.25 11 0.8 0.1 0.2 1.05E-05 1%

2.75 10 0.7 0.1 0.2 1.07E-05 1%

3.25 9

0.2 0.1 0.1 6.18E-06 1%

3.75 9

0.5 0.1 0.2 8.12E-06 1%

4.25 6

0.2 0.1 0.1 5.54E-06 1%

4.75 4

0.1 0.1 0.1 5.45E-06 1%

5.25 4

0.1 0.1 0.1 4.19E-06 0.4%

5.75 2

0.1 0.1 0.1 5.56E-06 1%

Total 1.07E-03 100%

As seen in the tables above and Table 14 the overall source term in Unit 2 is much lower than Unit 1 with 0.980 Ci total in Unit 2 as opposed to 7.00 Ci for Unit 1. Co-60 also has a higher abundance relative to Cs-137 in Unit 2.

Table 14 - Summary of Unit 2 568 Foot On-Site Gamma Spectroscopy Radionuclide Profiles and Fractions Avg Depth in Co-60 Ci Cs-137 Ci Cs-134 Ci Total Ci Co-60 Fraction Cs-137 Fraction Cs-134 Fraction Total Activity Profile 0.25 0.248 0.602 0.001 0.8504 29%

71%

0.1%

86.8%

0.75 0.001 0.060 0.00008 0.0614 1%

98%

0.1%

6.3%

1.25 0.001 0.035 0.00001 0.0355 2%

98%

0.0%

3.6%

1.75 0.001 0.019 0.00001 0.0196 3%

97%

0.1%

2.0%

2.25 0.001 0.006 0.00001 0.0073 20%

80%

0.1%

0.7%

2.75 0.003 0.002 0.00001 0.0051 59%

40%

0.2%

0.5%

3.25 0.00010 0.00026 0.00001 0.0004 27%

71%

2%

0.04%

TSD 13-006 Revision 0 Page 26 of 200 Avg Depth in Co-60 Ci Cs-137 Ci Cs-134 Ci Total Ci Co-60 Fraction Cs-137 Fraction Cs-134 Fraction Total Activity Profile 3.75 0.00007 0.00020 0.00001 0.0003 25%

72%

3%

0.03%

4.25 0.00007 0.00015 0.00001 0.0002 33%

65%

2%

0.02%

4.75 0.00005 0.00002 0.00001 0.0001 72%

21%

7%

0.01%

5.25 0.00003 0.00001 0.00000 0.0000 71%

20%

9%

0.00%

5.75 0.00009 0.00001 0.00001 0.0001 84%

11%

5%

0.01%

Totals 0.255 0.724 0.001 0.980 26.0%

73.9%

0.11%

100%

Similar to Unit 1, Figure 9 shows that the majority of the source term is within the first 1/2 inch of the surface, after which it drops off rapidly and is relatively uniform in the remainder of the concrete.

Figure 9-Unit 2 568' Total Activity Profile Ci With Depth 3.4.

Evaluation of 568 Eberline Off-Site Laboratory Results The first 1/2 inch pucks from 17 cores (9 from Unit 1 and 8 from Unit 2) were sent to Eberline Laboratory for gamma spectroscopy and HTD analyses for radionuclides such as tritium, 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 Unit 1 results were reported in Eberline report 12-02088 and 13-02003. The Unit 2 results were reported in Eberline report 13-0384 and 13-04110. The Eberline reports contained results for duplicate samples, spikes and blanks and 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 for licensed radioactive material to use. Naturally occurring radioactive materials (NORM) were not included in the results evaluated.

1. Where results for duplicate (DUP) and duplicate original (DO) are both <MDA, the lower MDA was used.

0.0%

10.0%

20.0%

30.0%

40.0%

50.0%

60.0%

70.0%

80.0%

90.0%

100.0%

0 1

2 3

4 5

Depth in Inches U2 568' Total Activity Profile Fraction Total Activity Profile

TSD 13-006 Revision 0 Page 27 of 200

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 Am-241 59.5 keV peak.

The results extracted from the reports based upon the above criteria are provided in Attachment D. Using this criteria there were no positive results in the Unit 1 or Unit 2 568 foot elevation concrete core samples for Mn-54, Fe-55, Ni-59, Nb-94, Sb-125, Ba-133, Eu-152, Eu-154, Ho-166m, or Np-237.

The bold red results in Attachment D 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 15.

Table 15 - Ba-137m 32 - 37 keV Photon Energy/Intensity Data from NRC Radiological Toolbox Radiation Intensity Energy (MeV)

Energy (keV)

X-Ray 2.160%

0.031819 31.8 X-Ray 3.977%

0.032206 32.2 The case narratives and reported results were reviewed in detail to determine valid positively identified results that should be incorporated into the source term calculations.

Ag-108m and I-129 The Eberline report 12-12088 Case Narrative, for the Unit 1 cores states, Due to the presence of significantly positive Cesium-137 activity in most samples, most required gamma emitting radionuclides are not resolvable. In other instances in the case of the source term for this site, some radionuclides as required would be completely decayed; therefore, should be qualified as appropriate. As a result of these conditions results for several radionuclides are qualified as non-detect, "U". This includes all results for Actinium-228, Silver-108m, Barium-133, Cesium-134, Europium-152, Europium-154, Europium-155, Holmium-166m, Iodine-129, Potassium-40, Manganese-54, Niobium-94, Lead-210, Lead-212, Lead-214, Radium-226, Antimony-125, Thorium-234, Thallium-208 and Uranium-235.

The other Eberline report that includes the Unit 1 568 foot elevation cores 13-02003, does not contain this language in the narrative. However, all the Ag-108m results are less than the MDA.

One I-129 result is greater than the MDA but is reported as undetected U for core B101106-CJFCCV-002. The Case Narrative states, Promethium-145 for sample fractions -03 and -07 (Client IDs: B101106CJFCCV002 DUP and B101110CJFCCV001) and all Cobalt-60, Cesium-I37 and Potassium-40 results are biased high due to interfering 36 keV x-ray from Barium 137m.

TSD 13-006 Revision 0 Page 28 of 200 I-129 emits a 0.039 MeV Gamma at 7.51%, and 0.029 MeV X-Ray at 56.9%. Thus the 15.9 pCi/g result for I-129 for core B101106-CJFCCV-002 is also a False Positive and designated as undetected in the report. Based on this, the Unit 1 568 foot cores did not identify Ag-108m or I-129 and they are removed from the radionuclide inventory for scaling in the hard to detect source terms.

The Unit 2 568 foot results for core B1-02102-CJFCCV001 indicate a positive result of 68.5 pCi/g for Ag-108m in Eberline report 13-03084. This result is marked as undetected U in the reported results. The Case Narrative of the report states, Samples demonstrated acceptable results for all gamma-emitting radionuclides as reported. Due to the positive Cesium-l37 activity in these samples, some results demonstrated slightly high method detection limits.

Promethium-145 results for all samples are biased high due to the interfering 36 keV x-ray from Barium-137m. Therefore, all Promethium-145 results are qualified as "Estimated High" (JH). Europium-152 and Europium-154 results for sample fraction -08 (Client ID: B1-02110-CJFCCV001) are biased high due to the interfering 36 keV x-ray from Barium-137m and are therefore qualified as "Estimated High" (JH). The Case Narrative of report 13-04110 states, Samples demonstrated acceptable results for all gamma-emitting radionuclides as reported.

In many instances, gamma emitting radionuclides as reported are biased positive as a result of Compton or summation effects from significantly positive Cobalt-60 and Cesium-137 activity in these samples. All results are that are affected by this condition are qualified as estimated high, JH. The reported I-129 results in 13-04110 are justified high JH in the report. Based on this I-129 is not included in the Unit 2 568 foot elevation source term estimates.

Pm-145 Pm-145 emits a 0.072 MeV gamma ray with a 2% yield. In addition to the Pm-145 results (B101106CJFCCV002 DUP and B101110CJFCCV001) that are reported as biased high in the 13-02003 case narrative, the Pm-145 result for core B101109CJFCCV001 is designated as undetected U in the reported results. B101107-CJFCCV-002 reported a Pm-145 positive result of 1.74 without the undetected U designation. However, given the low energy and minimal yield in the Compton edge region of the spectrum, this result is also considered to be a False Positive although it is not designated as such in the Case Narrative or in the reported results. Based on this, there are no reported positive results for Pm-145 in the Unit 1 568 foot cores.

As noted above in the Ag-108m and I-129 discussion, Eberline reports 13-03084 and 13-04110 Case Narratives contain similar language. All reported Pm-145 results in reports 13-03084 and 13-04110 are justified high (JH). Based on this there are no reported positive results for Pm-145 in the Unit 2 568 foot cores.

Pm-147 All of the Pm-147 results reported in Eberline reports 12-12088 and 13-02003 were Justified High in the reported results. The Case Narrative for 12-2008 states Samples were prepared by leaching a representative aliquot of each solid sample in HNO3. Leachates were taken to near dryness. Sample residues were dissolved in deionized water. The pH of each sample was adjusted as appropriate. Samples were then extracted using a PPO/POPOP/HDEHP in toluene scintillation extractant. Organic phase of each extraction was transferred to scintillation vials.

Promethium-147 was determined by liquid scintillation counting. Samples demonstrated problematic results for all Promethium-147 analyses. The presence of gamma and beta emitting interferences within the extractant was evident within all liquid scintillation spectra.

TSD 13-006 Revision 0 Page 29 of 200 The Case Narrative for 13-02003 states, Samples demonstrated acceptable results for all Promethium-147 analyses. Sample results may be biased positive by the presence of low levels of Cesium-137; therefore, Promethium-147 results are qualified as estimated high (JH).

There were no positive identifications of Pm-147 in Eberline report 13-03084 for the Unit 2 568 foot cores. The Eberline report 13-04110 Case Narrative states, Samples demonstrated acceptable results for all Promethium-147 analyses. Due to the positive nature of these samples with Cobalt-60 and Cesium-l37 activity, Promethium-147 results are most likely biased positive. Due to this condition, all Promethium-147 results are qualified as estimated high, JH. Based on this there are no reported positive results for Pm-147 in the Unit 1 or 2 568 foot cores.

Tc-99 For Tc-99, representative aliquots of samples were prepared by oxidative reactions with Nitric acid and Hydrogen Peroxide. After complete oxidization, Technetium was selectively extracted by the use of EIChroM stabilized resins. Special cleanup chemistry was conducted for complete removal of interferences associated with Uranium. Processed resins were then transferred to liquid scintillation vials, scintillation cocktail was added and sample was counted by beta liquid scintillation. The Eberline Case Narrative for 12-02088 states, Sample fractions -04 and -06 (Client IDs: 01102-CJFCCV-002 and 01104-CJFCCV-001) demonstrated interferences from Cesium-137. The extractions were counted by gamma spectroscopy in an attempt to determine Cesium-137 activity present. In both attempts Cesium-137 activity as determined by gamma spectroscopy was much higher than the Technetium-99 result. This is most likely due to the LSC cocktail response or efficiency for Cesium-137 versus Technetium-99. In this case it is apparent, based on LSC spectral evaluations and gamma spectroscopy, results are biased positive and sample fractions -04 and -06 (Client IDs: 01102-CJFCCV-002 and 01104-CJFCCV-001) should be qualified as JH. Core B101106-CJFCCV-002 in the 13-02003 Eberline report also contains a positive identification of Tc-99 at 0.296 pCi/g. The 13-02003 Case Narrative states, Samples demonstrated acceptable results for all Technetium-99 analyses. However, the reported result has an undetected U designation for this core. This leaves positively identified results for cores B101103-CJFCCV-002 at 1.22 pCi/g, B101105-CJFCCV-002 at 0.935 pCi/g in the 12-2008 report. Due to the fact that Tc-99 is highly mobile in groundwater, these two Tc-99 results will be rolled up into the overall Unit 1 568 foot source term calculations and evaluated relative to their end state dose significance.

The Case Narrative for Eberline report 13-03084 states, Samples demonstrated acceptable results for all Technetium-99 analyses. Sample fraction -05 (Client ID: B1-02103-CJFCCV001) demonstrated a potential positive bias which may be due to Cesium-137 interferences. Due to this condition, this result is qualified as "Estimated High" (JH). All other results are "Non-Detect" equivalent and are qualified as (U). The Case Narrative of report 13-04110 states, Samples demonstrated acceptable results for all Technetium-99 analyses. The reported results contained four Tc-99 positive identifications that were not designated justified high JH or undetected U. Due to the fact that Tc-99 is highly mobile in groundwater, these four Tc-99 results will be rolled up into the overall Unit 2 568 foot source term calculations and evaluated relative to their end state dose significance.

Nickel 63 Eberline Case Narratives 12-02088 and 13-02003 state, Samples demonstrated acceptable results for all Nickel-63 analyses. The ratios of the decay corrected (January 1, 2013) Ni-63 to

TSD 13-006 Revision 0 Page 30 of 200 Co-60 results range from to 0.018 to 225 on the decay corrected cores. The decay corrected (January 1, 2013) Unit 1 reactor vessel and internals ratios range from 0.125.to 1.2 [20], [21]

The Case Narrative for Eberline Unit 2 reports 13-03084 and 13-04110 state that sample results may be biased high due to interferences from Cobalt-60 and Cesium-137 and are therefore qualified as justified high (JH).

Therefore the high Ni-63 results are bolded red as suspect results that could be from carryover of trace levels of Cs-137 in the precipitated samples analyzed by liquid scintillation. However, due to the differences in the 100 year half-life of Ni-63 and the 5 year half-life of Co-60, they could also be due depositions that occurred early in plant operations where the Co-60 decay has resulted in a large Ni-63 to Co-60 ratios in some core samples. Therefore the Ni-63 results are retained and used for the roll-up of the estimated Unit 1 568 elevation source term.

Eu-155 There was a positive Eu-155 result for core 01103-CJFCCV-002 in Eberline report 12-12088.

This result is designated as undetected U in the reported results. As noted above in the Ag-108m and I-129 discussion, Eu-155 is among the results considered as undetected due to interference from high Cs-137 levels in the sample. It would also be expected to be present with Eu-152, Eu-154 since it is principally a concrete neutron activation product. Therefore this result is considered a False Positive.

Pu-238, Pu-239/240 The Unit 1 568 foot elevation cores had positive results for Pu-238 and Pu-239/240. The Case Narrative of Eberline report 12-02088 states that with the exception of sample fraction -07 (Client ID: 01105-CJFCCV-001), all samples demonstrated near detection limit equivalent results for Plutonium-238 and Plutonium-239/240 activity. The results for 01105-CJFCCV-001 are not justified high in the reported results and are considered valid positive results. The Case Narrative for Eberline report 13-02003 states, 2nd Analytical Attempt Sample fraction -04 (Client ID: B101106CJFCCV002) was reanalyzed due to a low chemical recovery. Sample demonstrated acceptable results for all Plutonium analyses. Special cleanup chemistry was conducted to remove Thorium-228 from the extraction. Plutonium-239/240 results may still be slightly biased positive due to very minor interferences from Thorium-228. Due to this condition, Plutonium-239/240 results are qualified as estimated high (JH). The reported concentration was 0.0525 pCi/g which is in the range of other positive Pu-239/240 results, so it was retained as a valid result as well.

There were no positive identifications of Pu-238 or Pu-239/240 in the Unit 2 13-03084 Eberline report. The Unit 2 13-04110 Case Narrative states, results for fraction -05 (Client ID: B102105-CJFCCV-001) may be biased positive due to interferences from Thorium-228. Therefore, results are qualified as estimated high, JH. These results are in the range of the Pu-239/240 results for core B102103-CJFCCV-002 and are therefore treated as valid.

Pu-241 The Case Narrative for 12-12088 states, Samples demonstrated acceptable results for all Plutonium-241 analyses. Some LSC spectra are indicative of Alpha emitting radionuclides being present in the final extractions. In this case this does not appear to have had any effect on any result except maybe sample fraction -07 (Client ID: 01105-CJFCCV-001) which was also positive with Plutonium-238 and Plutonium-239/240. We are qualifying this result as estimated high (JH); it is difficult to determine if the result is an artifact of the positive

TSD 13-006 Revision 0 Page 31 of 200 Plutonium-238 and Plutonium-239/240 or is related to Plutonium-241 results. Based on this the 12.4 pCi/g result for B101105-CJFCCV-001 is considered a False Positive and removed from the data set.

In addition, cores B101106-CJFCCV-002, B101107-CJFCCV-002, and B101109-CJFCCV-001 were re-analyzed to achieve lower MDAs. The re-analysis results are provided in Eberline report 13-04025. These lower MDA values replace the previous Pu-241 MDAs for these cores.

Based on this there were no positive identifications of Pu-241 in the Unit 1 568 foot cores.

Similarly there were no positive identifications of Pu-241 in the Unit 2 568 foot elevation core results. Pu-241 is not included in the Unit 1 or 2 568 foot elevation concrete estimated source terms.

Am-241 The concern over Th-228 carry over expressed above resulted in the B101106CJFCCV002 Am-241 results being designated as justified high (JH) in the 13-02003 results. However, the 0.167 pCi/g result is in the range of the other positive Am-241 results, so it was retained as a valid concentration. All positive results for Am-241 from Unit 1 568 foot cores were retained as valid results even if they were reported as estimated high JH or undetected U.

For Unit 2 568 foot elevation core results, all 13-04110 Am-241 concentrations were less than MDA with the exception of two cores. B1-02103-CJFCCV-002 had a 0.127 pCi/g concentration above the 2 sigma and MDA values. However, the result is designated as undetected U by the laboratory in Eberline report. B1-02105-CJFCCV-001 had a reported concentration of 6.28 pCi/g that was not mentioned in the Case Narrative or noted as being justified high (JH) in the reported results. Positive Am-241 results were identified in Eberline report 13-03084. The Case Narrative states, Sample fractions -04 and -05 (Client IDs: B1-02102-CJFCCV001 and B1-02103-CJFCCV001) may be slightly biased positive due to interferences from Thorium-228 and Radium-224. Due to this condition, results for these two samples are qualified as "Estimated High" (JH). All positive results for Am-241 from Unit 2 568 foot cores were retained as valid results even if they were reported as estimated high JH or undetected U.

Am-243 The Case Narrative for Eberline Report 13-03084 states, Samples demonstrated acceptable results for all Americium-243 analyses. In some instances results are only slightly higher than method detection limits. All sample results are non-detect and are therefore all qualified as "Non-Detect" (U). Due to the slightly positive nature of these samples with Cesium-137 activity, slightly smaller aliquots were used which resulted in slightly high method detection limits. Chemical recovery was acceptable for all samples. Thus the positive Am-243 results for Unit 2 568 foot cores B102102-CJFCCV-001 and B102103-CJFCCV-001 are designated as undetected U in the report. The results for core B1-02105-CJFCCV-001 in the Eberline report 13-04110 indicate a positive Am-243 result of 0.381 pCi/g that is not designated as undetected U in the reported results.

A ZionSolutions email dated June 20, 2013, which was included in the 13-04110 the Eberline report, requested Eberline to look at he Am-243 results again, the email states, I suspect this is tracer or Th-228 interference. To date Am-243 has not been qualified in any of the previous samples that Eberline has examined (in some cases this was confirmed by reanalysis of samples that were initially reported as positive). An email dated June 21, 2013 is included in the 13-04110 report. This email is in response to a request to re-analyze the transuranics reported in

TSD 13-006 Revision 0 Page 32 of 200 Eberline reports 13-04120 and 13-04110. The email states the following, We reanalyzed your sample number B1-02105-CJFCCV for Americium-243 to try and obtain results that are

<MDA and to ascertain it there is Am-241 in this sample. This was done as per your first email; however serves the purpose for your additional request below. We also analyzed a large aliquot again in an attempt to provide you with a low MDA that you also want. First off, there is positive Am-241 and Cm-244 in this sample. There is no doubt about it, it is the cause of the analytical issues with Am-243. There is nothing more we can do because of this condition. Any radiochemistry laboratory will have the same issue with this sample. Additionally, the presence of Americium-243 is possible, difficult to determine with all of the Americum-241 present. Due to the use of large aliquots to obtain your requested MDA's the Americium-241 present is causing some spectral trailing into the Americium-243 region of interest. This may be causing the slightly positive result for Americium-243; however with Curium-244 being present, this could be a strong indicator that Americium-243 is real. Therefore unless you want to try to do something else such as reduce the aliquot significantly, which will raise the MDA, improvement of the Americium-243 result is not possible.

The 13-04110 Case Narrative states, 2nd Analytical Attempt Sample fraction -05 (Client ID: B 1-021 05-CJFCCV) was reanalyzed due to a potential positive bias. Reanalysis results demonstrated statistically equivalent results. However, Americium-243 results may be slightly bias positive. Due to the presence of Americium-241 and the need to analyze a larger aliquot for method detection limit demonstration, alpha spectra demonstrated some trailing of Americium-241 into the Americium-243 region of interest. As a result of this condition, Americium-243 results are qualified as "Estimated High" (JH).

Sandia Report - SAND2004-2757 Table F1 [22] provides the calculated Ci/g of transuranics for one gram of UO2 in spent PWR Fuel. The table is presented in Table 16. The Am-243/Am-241 and Am-243/Cm-244 scaling factors based on the data in the table are calculated in the bottom two rows of the table.

Table 16 - Sandia Report Table F1. Hazard category 3 threshold for one gram of spent fuel UO2 Nuclides Hazard Category 3 Threshold (Ci)

H. B. Robinson 72 GWd/MTU Surry Average Power 38.6 GWd/MTU Surry Real Power 38.6 GWd/MTU Activity (Ci/g)

HC3 (fraction/g)

Activity (Ci/g)

HC3 (fraction/g)

Activity (Ci/g)

HC3 (fraction/g)

Pu-242 6.20E-01 6.09E-06 9.83E-06 2.61E-06 4.21E-06 2.58E-06 4.16E-06 Pu-243 1.14E+05 3.18E-11 2.79E-16 5.81E-13 5.10E-18 5.46E-13 4.79E-18 Am-241 5.20E-01 2.57E-03 4.93E-03 3.01E-03 5.79E-03 3.03E-03 5.82E-03 Am-242m 5.20E-01 3.89E-05 7.48E-05 6.52E-06 1.25E-05 1.14E-05 2.20E-05 Am-242 8.20E+03 3.87E-05 4.72E-09 6.49E-06 7.91E-10 1.14E-05 1.39E-09 Am-243 5.20E-01 1.33E-04 2.55E-04 3.20E-05 6.15E-05 3.10E-05 5.97E-05 Am-245 3.40E+05 3.44E-14 1.01E-19 ND ND ND ND Cm-241 1.90E+03 3.18E-32 1.67E-35 ND ND ND ND Cm-242 3.20E+01 3.32E-05 1.04E-06 5.37E-06 1.68E-07 9.41E-06 2.94E-07 Cm-243 8.20E-01 3.15E-04 3.84E-04 1.25E-05 1.52E-05 2.48E-05 3.02E-05 Cm-244 1.04E+00 3.30E-02 3.17E-02 1.94E-03 1.86E-03 1.86E-03 1.78E-03 Cm-245 5.20E-01 6.10E-06 1.17E-05 3.42E-07 6.57E-07 3.25E-07 6.25E-07 Cm-246 5.20E-01 4.08E-06 7.85E-06 1.04E-07 2.00E-07 9.83E-08 1.89E-07 Cm-247 6.20E-01 3.18E-11 5.12E-11 ND ND ND ND

TSD 13-006 Revision 0 Page 33 of 200 Nuclides Hazard Category 3 Threshold (Ci)

H. B. Robinson 72 GWd/MTU Surry Average Power 38.6 GWd/MTU Surry Real Power 38.6 GWd/MTU Activity (Ci/g)

HC3 (fraction/g)

Activity (Ci/g)

HC3 (fraction/g)

Activity (Ci/g)

HC3 (fraction/g)

Cm-248 1.04E-01 2.36E-10 2.27E-09 ND ND ND ND Bk-249 2.00E+01 2.37E-09 1.19E-10 4.86E-16 2.43E-17 4.43E-16 2.22E-17 Bk-250 4.20E+03 7.29E-14 1.73E-17 ND ND ND ND Cf-249 5.20E-01 4.41E-09 8.48E-09 ND ND ND ND Cf-250 1.04E+00 1.61E-08 1.55E-08 ND ND ND ND Cf-251 5.20E-01 1.87E-10 3.60E-10 ND ND ND ND Cf-252 3.20E+00 1.25E-08 3.91E-09 ND ND ND ND Es-254 1.04E+01 7.28E-14 7.00E-15 ND ND ND ND Totals 5.13E-01 7.30E-02 2.15E-01 1.91E-02 2.09E-01 1.97E-02 Am-243/Am-241 5.17E-02 1.06E-02 1.02E-02 Am-243/Cm-244 4.03E-03 1.65E-02 1.67E-02 Using the bolded scaling factors from Table 16 and the decay corrected Unit 2 568 foot core Am-241 and Cm-244 results allows the estimated Am-243 concentrations to be calculated as shown in the last two rows of Table 17 and the Attachment E Unit 2 568 foot decay corrected data.

Table 17 - Comparison of Calculated Am-243 Concentrations to Decay Corrected Unit 2 Results Sample ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline WO 13-03084 13-03084 13-04110 13-04110 13-03084 13-04110 13-03084 13-04110 Eberline Sample Date 3/20/2013 3/20/2013 2/25/2013 2/28/2013 3/20/2013 3/5/2013 3/20/2013 2/25/2013 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years

-0.215

-0.215

-0.152

-0.160

-0.215

-0.174

-0.215

-0.152 Nuclide Decay Const yr-1 Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Pu-241 4.81E-02 3.38E+00 4.01E+00 2.79E+00 6.17E+00 4.65E+00 3.45E+00 4.20E+00 3.09E+00 Am-241 1.60E-03 2.49E-01 1.24E-01 1.27E-01 6.28E+00 5.08E-02 4.55E-02 4.48E-02 4.25E-02 Am-243 9.39E-05 4.86E-02 3.28E-02 3.92E-02 3.80E-01 3.58E-02 7.19E-02 5.63E-02 3.94E-02 Cm-243 2.43E-02 4.52E-02 2.27E-02 2.78E-02 5.93E-01 1.75E-02 1.99E-02 2.30E-02 1.83E-02 Cm-244 3.83E-02 4.52E-02 2.27E-02 2.78E-02 5.93E-01 1.75E-02 1.99E-02 2.30E-02 1.83E-02 Est Am-243 Using SF 1.29E-02 6.42E-03 6.58E-03 3.25E-01 2.63E-03 2.35E-03 2.32E-03 2.20E-03 Est Cm-244 Using SF 7.56E-04 3.80E-04 4.65E-04 9.92E-03 2.92E-04 3.33E-04 3.84E-04 3.07E-04 Note: Bold Italic are MDA values As noted in the bolded results in the last two rows of Table 17, the scaling factors from Table 16 lead to calculated concentrations that approach the reported results. Based on these results, Am-243 will be included in the Unit 2 568 foot source term estimates.

Based upon the above evaluation of the Eberline results for the 568 foot elevation cores. The following radionuclides exhibited positive results H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-134, Cs-137, Pu-238, Pu-239, Pu-240, Am-241, Am-243, Cm-243, Cm-244.

TSD 13-006 Revision 0 Page 34 of 200 The following radionuclides were designated as False Positives or had no positive results. Ag-108m, I-129, Pm-145, Pm-147, Eu-155, and Pu-241.

3.5.

Evaluation of 568 Scaling Factors and Source Terms The results in Attachment E were decay corrected to January 1, 2013 for comparison to the decay corrected in-house gamma spectroscopy results. As seen in Table 18 and Table 19, 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 Cs-137 concentrations reported were 48.5% lower than the In-House gamma spectroscopy results for Unit 1 (Table 18). The Eberline results were higher than the In-House gamma spectroscopy results for both Co-60 and Cs-137 in Unit 2 (Table 19). This is probably due to the actual peak concentration depths within the concrete pucks.

Table 18 - Comparison of In-House and Eberline Co-60 and Cs-137 Results for Unit 1 568' Samples Sample ID Eberline Lab Report In-House Co-60 pCi/g Eberline Co-60 pCi/g Eberline

/In-House In-House Cs-137 pCi/g Eberline Cs-137 pCi/g Eberline

/In-House B101102-CJFCCV-002 12-12088 1.49E+02 8.05E+01 54%

3.44E+05 1.45E+05 42%

B101103-CJFCCV-002 12-12088 7.16E+03 7.04E+03 98%

8.51E+04 9.42E+04 111%

B101104-CJFCCV-001 12-12088 1.08E+02 8.63E+01 80%

4.50E+05 1.21E+05 27%

B101105-CJFCCV-001 12-12088 3.34E+04 3.33E+04 100%

2.31E+03 2.71E+03 117%

B101105-CJFCCV-002 12-12088 8.52E+02 9.70E+02 114%

2.73E+04 4.26E+04 156%

B101106-CJFCCV-002 13-02003 1.95E+01 4.40E+01 226%

5.77E+01 1.38E+02 239%

B101107-CJFCCV-002 13-02003 1.39E+01 1.51E+01 109%

1.69E+02 1.60E+02 95%

B101108-CJFCCV-002 12-12088 5.61E+01 8.61E+01 153%

5.12E+04 5.90E+04 115%

B101109-CJFCCV-001 13-02003 7.48E+00 8.59E+00 115%

1.38E+02 1.43E+02 104%

Totals 4.17E+04 4.16E+04 99.7%

9.60E+05 4.66E+05 48.5%

Table 19 - Comparison of In-House and Eberline Co-60 and Cs-137 Results for Unit 2 568' Samples Sample ID Eberline Lab Report In-House Co-60 pCi/g Eberline Co-60 pCi/g Eberline/

In-House In-House Cs-137 pCi/g Eberline Cs-137 pCi/g Eberlin e/In-House B102102-CJFCCV-001 13-03084 7.11E+02 9.96E+02 140%

1.07E+05 2.14E+05 199%

B102103-CJFCCV-001 13-03084 5.00E+02 6.91E+02 138%

3.92E+04 5.58E+04 142%

B102103-CJFCCV-002 13-04110 1.52E+02 2.59E+02 171%

4.83E+03 8.45E+03 175%

B102105-CJFCCV-001 13-04110 9.16E+02 1.09E+03 119%

2.19E+03 2.49E+03 114%

B102105-CJFCCV-002 13-03084 8.67E+01 1.83E+02 212%

9.15E+03 2.09E+04 229%

B102106-CJFCCV-001 13-04110 4.45E+01 8.01E+01 180%

5.77E+02 1.13E+03 195%

B102106-CJFCCV-002 13-03084 2.38E+01 4.35E+01 183%

1.31E+04 2.66E+04 204%

B102107-CJFCCV-001 13-04110 5.62E+01 7.57E+01 135%

3.12E+03 4.51E+03 145%

Totals 2.49E+03 3.42E+03 137%

1.80E+05 3.34E+05 186%

The LABSOCS in-house gamma spectroscopy model assumes a uniform distribution within the puck. Actual peak concentrations probably vary with depth across the puck placing the bulk of

TSD 13-006 Revision 0 Page 35 of 200 the source term at different proximities to the detector, yielding slightly different actual efficiencies for the top and bottom gamma spectroscopy results as opposed to powdered, more uniformly distributed results. Since the overall concentrations are biased high by the core location selection process, these variations are not significant relative to the calculated source terms.

Key radionuclide ratios were calculated for each core as shown in Attachment F. The detectable gross beta included results for nuclides with a beta average > 40 keV and reported above the MDA. The emissions, energies, and yields used for this evaluation are provided in Attachment J. The Sr-90 contribution to the gross beta was multiplied by 2 to account for the Y-90 beta. The transuranic alpha emitters above MDA were used to calculate the gross alpha activity. The gross alpha to gross beta key radionuclide ratios of the samples were also calculated. As seen in Table 20 and Table 21 the range of key radionuclide ratios varied by several orders of magnitude across the Unit 1 and 2 568 foot elevation cores.

Table 20 - Summary of Key Radionuclide Ratios for U1 568 EL Cores Key Ratio Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio All Results Positive Results Gross Beta > 0.4 keV 1.78E+05 1.57E+02 6.23E+04 1.78E+05 1.57E+02 6.23E+04 Gross Alpha 6.77E+01 3.26E-01 8.27E+00 6.77E+01 3.78E-01 1.05E+01 Gross Beta/Gross Alpha 2.11E+05 3.78E+02 6.29E+04 2.11E+05 3.78E+02 6.29E+04 Am-241 Ratios Pu-238/Am-241 Ratio 1.73E+00 6.17E-02 7.37E-01 1.17E+00 6.17E-02 5.30E-01 Pu-239/Am-241 Ratio 9.33E-01 2.23E-02 2.92E-01 9.33E-01 2.23E-02 2.57E-01 Pu-240/Am-241 Ratio 9.33E-01 2.23E-02 2.92E-01 9.33E-01 2.23E-02 2.57E-01 Pu-241/Am-241 Ratio 9.21E+01 2.40E-01 2.07E+01 ND ND ND Am-243/Am-241 Ratio 7.53E-01 1.03E-02 3.01E-01 9.76E-02 1.03E-02 5.40E-02 Cm-243/Am-241 Ratio 6.00E-01 9.77E-02 2.30E-01 2.65E-01 9.77E-02 1.51E-01 Cm-244/Am-241 Ratio 6.00E-01 9.76E-02 2.30E-01 2.65E-01 9.76E-02 1.50E-01 Am-241/Gross Alpha 7.61E-01 1.84E-01 4.52E-01 7.61E-01 1.84E-01 4.52E-01 Cs-137 Ratios H-3/Cs-137 5.92E-01 1.31E-04 1.45E-01 5.92E-01 1.31E-04 1.45E-01 C-14/Cs-137 1.10E-02 1.72E-05 3.89E-03 1.10E-02 3.62E-05 4.37E-03 Co-60/Cs-137 1.23E+01 5.55E-04 1.43E+00 1.23E+01 7.10E-04 1.61E+00 Ni-63/Cs-137 1.04E+00 2.68E-04 1.75E-01 1.04E+00 2.68E-04 1.75E-01 Sr-90/Cs-137 5.36E-03 8.06E-05 1.91E-03 5.36E-03 8.06E-05 1.91E-03 Tc-99/Cs-137 2.15E-03 1.29E-05 7.18E-04 2.19E-05 1.29E-05 1.74E-05 Sb-125/Cs-137 1.41E-02 2.11E-04 4.84E-03 ND ND ND Eu-152/Cs-137 4.58E-02 3.29E-04 8.74E-03 ND ND ND Eu-154/Cs-137 1.89E-02 2.97E-04 4.06E-03 ND ND ND Eu-155/Cs-137 6.20E-03 2.49E-04 2.31E-03 2.49E-04 2.49E-04 2.49E-04 Np-237/Cs-137 2.26E-04 5.96E-07 6.91E-05 ND ND ND Pu-238/Cs-137 1.17E-03 8.61E-07 3.19E-04 1.17E-03 2.50E-06 6.07E-04

TSD 13-006 Revision 0 Page 36 of 200 Key Ratio Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio All Results Positive Results Pu-239/Cs-137 5.13E-04 3.39E-07 1.48E-04 5.13E-04 4.60E-07 2.26E-04 Pu-240/Cs-137 5.13E-04 3.39E-07 1.48E-04 5.13E-04 4.60E-07 2.26E-04 Pu-241/Cs-137 4.56E-03 5.61E-05 1.71E-03 4.56E-03 4.56E-03 4.56E-03 Am-241/Cs-137 1.90E-02 1.72E-06 2.35E-03 1.90E-02 2.47E-06 2.97E-03 Am-243/Cs-137 2.80E-04 4.98E-08 1.07E-04 1.97E-04 1.44E-06 9.90E-05 Cm-243/Cs-137 1.86E-03 2.99E-07 2.64E-04 1.86E-03 2.99E-07 3.72E-04 Cm-244/Cs-137 1.85E-03 2.99E-07 2.63E-04 1.85E-03 2.99E-07 3.72E-04 Gross Alpha/Cs-137 2.50E-02 5.81E-06 4.39E-03 2.50E-02 5.81E-06 4.39E-03 Co-60 Ratios H-3/Co-60 6.31E+00 8.10E-04 1.47E+00 6.31E+00 8.10E-04 1.62E+00 C-14/Co-60 1.27E-01 5.15E-04 4.80E-02 1.27E-01 5.15E-04 5.01E-02 Fe-55/Co-60 7.12E+00 1.37E-03 1.13E+00 ND ND ND Ni-59/Co-60 8.50E-01 9.04E-04 2.87E-01 ND ND ND Ni-63/Co-60 2.25E+02 1.18E-02 3.34E+01 7.29E+01 1.18E-02 9.50E+00 Sr-90/Co-60 5.36E-03 8.06E-05 1.91E-03 5.36E-03 8.06E-05 2.11E-03 Nb-94/Co-60 1.06E+00 7.68E-04 2.04E-01 ND ND ND Tc-99/Co-60 4.02E-01 2.80E-05 8.34E-02 9.65E-04 1.73E-04 5.69E-04 Ag-108m/Co-60 2.97E+00 6.16E-04 4.26E-01 2.97E+00 2.97E+00 2.97E+00 Pu-238/Co-60 1.09E-02 3.34E-05 2.91E-03 6.83E-03 3.34E-05 2.62E-03 Pu-239/Co-60 5.43E-03 7.89E-06 1.27E-03 5.43E-03 7.89E-06 1.34E-03 Pu-240/Co-60 5.43E-03 7.89E-06 1.27E-03 5.43E-03 7.89E-06 1.34E-03 Pu-241/Co-60 1.08E-01 3.72E-04 4.63E-02 ND ND ND Am-241/Co-60 6.29E-03 1.97E-04 3.16E-03 5.82E-03 1.97E-04 2.76E-03 Am-243/Co-60 3.45E-03 1.60E-05 1.04E-03 1.93E-05 1.60E-05 1.76E-05 Cm-243/Co-60 3.77E-03 2.37E-05 8.39E-04 7.37E-04 2.37E-05 2.46E-04 Cm-244/Co-60 3.78E-03 2.36E-05 8.40E-04 7.36E-04 2.36E-05 2.46E-04 Gross Alpha/Co-60 3.15E-02 3.27E-04 9.42E-03 3.15E-02 3.27E-04 9.24E-03 Table 21 - Summary of Key Radionuclide Ratios for U2 568 EL Cores Key Ratio Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio All Results Positive Results Gross Beta > 0.4 keV 2.15E+05 1.21E+03 4.22E+04 2.15E+05 1.21E+03 4.22E+04 Gross Alpha 8.17E+00 2.02E-01 2.25E+00 8.17E+00 2.02E-01 2.25E+00 Gross Beta/Gross Alpha 8.17E+00 2.02E-01 2.25E+00 8.17E+00 2.02E-01 2.25E+00 Am-241 Ratios Pu-238/Am-241 Ratio 9.88E-01 2.62E-02 5.15E-01 2.62E-02 2.62E-02 2.62E-02 Pu-239/Am-241 Ratio 4.50E-01 1.23E-02 2.49E-01 1.87E-01 1.23E-02 9.95E-02

TSD 13-006 Revision 0 Page 37 of 200 Key Ratio Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio All Results Positive Results Pu-240/Am-241 Ratio 4.50E-01 1.23E-02 2.49E-01 1.87E-01 1.23E-02 9.95E-02 Pu-241/Am-241 Ratio 9.38E+01 9.82E-01 5.04E+01 ND ND ND Am-243/Am-241 Ratio 1.58E+00 6.04E-02 6.62E-01 2.64E-01 6.04E-02 1.73E-01 Cm-243/Am-241 Ratio 5.13E-01 9.44E-02 3.00E-01 2.19E-01 9.44E-02 1.69E-01 Cm-244/Am-241 Ratio 5.13E-01 9.44E-02 3.00E-01 2.19E-01 9.44E-02 1.69E-01 Am-241/Gross Alpha 7.69E-01 5.52E-01 6.44E-01 7.69E-01 5.52E-01 6.44E-01 Cs-137 Ratios H-3/Cs-137 9.95E-03 5.94E-04 3.71E-03 9.95E-03 5.94E-04 3.71E-03 C-14/Cs-137 2.42E-03 1.31E-05 6.74E-04 2.42E-03 1.31E-05 6.74E-04 Co-60/Cs-137 4.37E-01 1.63E-03 7.29E-02 4.37E-01 1.63E-03 7.29E-02 Ni-63/Cs-137 1.95E+00 4.02E-03 2.64E-01 1.95E+00 4.02E-03 2.64E-01 Sr-90/Cs-137 7.05E-03 2.26E-05 1.03E-03 7.05E-03 2.26E-05 1.03E-03 Tc-99/Cs-137 2.62E-04 1.33E-06 7.91E-05 2.62E-04 6.21E-05 1.41E-04 Sb-125/Cs-137 1.19E-02 1.12E-03 3.77E-03 ND ND ND Eu-152/Cs-137 6.01E-03 1.86E-04 1.94E-03 6.01E-03 6.01E-03 6.01E-03 Eu-154/Cs-137 3.96E-03 1.26E-04 1.18E-03 3.96E-03 3.96E-03 3.96E-03 Eu-155/Cs-137 2.06E-03 3.72E-04 1.04E-03 ND ND ND Np-237/Cs-137 3.41E-05 1.28E-07 7.49E-06 ND ND ND Pu-238/Cs-137 6.60E-05 1.94E-07 1.34E-05 6.60E-05 6.60E-05 6.60E-05 Pu-239/Cs-137 3.09E-05 1.03E-07 6.45E-06 3.09E-05 2.81E-06 1.69E-05 Pu-240/Cs-137 3.09E-05 1.03E-07 6.45E-06 3.09E-05 2.81E-06 1.69E-05 Pu-241/Cs-137 3.07E-03 1.58E-05 8.79E-04 ND ND ND Am-241/Cs-137 2.52E-03 1.16E-06 3.24E-04 2.52E-03 1.16E-06 6.35E-04 Am-243/Cs-137 1.52E-04 2.27E-07 2.93E-05 1.52E-04 2.27E-07 5.11E-05 Cm-243/Cs-137 2.38E-04 2.11E-07 3.32E-05 2.38E-04 2.11E-07 6.05E-05 Cm-244/Cs-137 2.38E-04 2.11E-07 3.32E-05 2.38E-04 2.11E-07 6.05E-05 Gross Alpha/Cs-137 3.28E-03 1.81E-06 8.28E-04 3.28E-03 1.81E-06 8.28E-04 Co-60 Ratios H-3/Co-60 1.19E+00 8.44E-03 3.52E-01 1.19E+00 8.44E-03 3.52E-01 C-14/Co-60 5.86E-02 2.81E-03 2.20E-02 5.86E-02 2.81E-03 2.20E-02 Fe-55/Co-60 5.78E-01 5.07E-03 1.46E-01 ND ND ND N-59/C0-60 1.63E-01 7.71E-03 5.39E-02 ND ND ND Ni-63/Co-60 4.46E+00 1.25E-01 2.37E+00 4.46E+00 1.25E-01 2.37E+00 Sr-90/Co-60 8.71E-02 2.03E-03 1.91E-02 8.71E-02 2.03E-03 1.91E-02 Tc-99/Co-60 9.11E-03 2.87E-04 3.05E-03 3.70E-03 3.65E-04 2.60E-03 Nb-94/Co-60 1.62E-01 3.22E-03 4.26E-02 ND ND ND Ag-108m/Co-60 2.24E-01 2.69E-03 4.98E-02 ND ND ND Pu-238/Co-60 1.02E-03 4.16E-05 3.08E-04 1.51E-04 1.51E-04 1.51E-04

TSD 13-006 Revision 0 Page 38 of 200 Key Ratio Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio All Results Positive Results Pu-239/Co-60 4.64E-04 2.21E-05 1.44E-04 9.15E-05 7.07E-05 8.11E-05 Pu-240/Co-60 4.64E-04 2.21E-05 1.44E-04 9.15E-05 7.07E-05 8.11E-05 Pu-241/Co-60 9.67E-02 3.39E-03 2.90E-02 ND ND ND Am-241/Co-60 5.77E-03 1.80E-04 1.14E-03 5.77E-03 1.80E-04 1.67E-03 Am-243/Co-60 1.30E-03 4.74E-05 4.38E-04 3.49E-04 4.74E-05 1.48E-04 Cm-243/Co-60 5.45E-04 3.29E-05 2.31E-04 5.45E-04 3.29E-05 1.83E-04 Cm-244/Co-60 5.45E-04 3.29E-05 2.31E-04 5.45E-04 3.29E-05 1.83E-04 Gross Alpha/Co-60 7.51E-03 2.93E-04 2.27E-03 7.51E-03 2.93E-04 2.27E-03 The Eberline offsite results from Attachment E decay corrected to 1/1/2013 are summarized in Table 22 for Unit 1 and Table 23 for Unit 2. The average concentrations in pCi/g are used to estimate the source term of each nuclide in the first half inch of the 568 foot elevation based on the decay corrected Eberline results. The estimated source term in Curies for each nuclide was calculated by using the 568 foot elevation surface area of 15,701.76 square feet from Table 2.

[16] A 1/2 inch thick depth of this surface area has a volume of 1.853E+7 cubic centimeters.

Using a density for concrete of 2.40 g/cc yields a mass of 4.455E+7 grams for the 1/2 inch layer of the floor. This mass, multiplied by the average concentration of the cores, equals the estimated 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 22 and Table 23.

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 from the positive results.

Table 22 - Summary of Unit 1 568 EL Eberline Results Nuclide Max All Results pCi/g Min All Results pCi/g Avg All Results pCi/g First Half Inch Source Term Floor All Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Max Positive Results pCi/g Min Positive Results pCi/g Avg Positive Results pCi/g First Half Inch Source Term Floor Positive Ci Percent of Total Source Term H-3 1.19E+02 1.90E+01 5.45E+01 2.4E-03 0.1%

Cs-137 1.05E-03 1.19E+02 1.90E+01 5.45E+01 2.4E-03 0.1%

C-14 2.46E+01 1.09E+00 5.68E+00 2.5E-04 0.01%

Cs-137 1.10E-04 2.46E+01 1.09E+00 6.07E+00 2.7E-04 0.01%

Fe-55 5.73E+02 2.03E+00 1.09E+02 4.8E-03 0.2%

Co-60 2.35E-02 ND ND ND ND Ni-59 3.33E+01 6.52E+00 2.30E+01 1.0E-03 0.04%

Co-60 4.99E-03 ND ND ND ND Co-60 3.33E+04 8.59E+00 4.62E+03 2.1E-01 7.7%

Co-60 1.00E+00 3.33E+04 8.59E+00 5.19E+03 2.3E-01 8.6%

Ni-63 1.81E+04 5.48E+00 3.28E+03 1.5E-01 5.5%

Co-60 7.10E-01 1.81E+04 5.48E+00 3.28E+03 1.5E-01 5.4%

Sr-90 1.63E+02 3.97E-01 2.77E+01 1.2E-03 0.05%

Cs-137 5.36E-04 1.63E+02 3.97E-01 2.77E+01 1.2E-03 0.05%

Nb-94 8.56E+01 2.37E-01 2.18E+01 9.7E-04 0.04%

Co-60 4.72E-03 ND ND ND ND Tc-99 3.46E+01 2.60E-01 6.91E+00 3.1E-04 0.01%

Cs-137 1.34E-04 1.22E+00 9.35E-01 1.08E+00 4.8E-05 0.002%

Ag-108m 2.39E+02 2.09E-01 3.96E+01 1.8E-03 0.1%

Co-60 8.56E-03 ND ND ND ND Sb-125 1.89E+02 3.02E-02 5.66E+01 2.5E-03 0.1%

Cs-137 1.09E-03 ND ND ND ND

TSD 13-006 Revision 0 Page 39 of 200 Nuclide Max All Results pCi/g Min All Results pCi/g Avg All Results pCi/g First Half Inch Source Term Floor All Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Max Positive Results pCi/g Min Positive Results pCi/g Avg Positive Results pCi/g First Half Inch Source Term Floor Positive Ci Percent of Total Source Term Cs-134 5.36E+01 3.40E-01 1.88E+01 8.4E-04 0.03%

Cs-134 1.00E+00 3.85E+01 9.28E+00 2.12E+01 9.4E-04 0.04%

Cs-137 1.45E+05 1.38E+02 5.17E+04 2.3E+00 85.9%

Cs-137 1.00E+00 1.45E+05 1.38E+02 5.17E+04 2.3E+00 85.7%

Eu-152 4.51E+02 8.59E-01 1.05E+02 4.7E-03 0.2%

Cs-137 2.03E-03 ND ND ND ND Eu-154 2.25E+02 5.29E-01 5.27E+01 2.3E-03 0.1%

Cs-137 1.02E-03 ND ND ND ND Eu-155 5.34E+01 6.18E-01 1.85E+01 8.2E-04 0.03%

Cs-137 3.57E-04 2.35E+01 2.35E+01 2.35E+01 1.0E-03 0.0389%

Np-237 1.01E-01 2.40E-02 6.94E-02 3.1E-06 0.0%

Cs-137 1.34E-06 ND ND ND ND Pu-238 3.18E+00 5.40E-02 4.88E-01 2.2E-05 0.001%

Cs-137 9.43E-06 3.18E+00 1.03E-01 9.56E-01 4.3E-05 0.002%

Pu-239 1.15E+00 2.62E-02 1.71E-01 7.6E-06 0.0003%

Cs-137 3.30E-06 1.15E+00 2.62E-02 2.74E-01 1.2E-05 0.0005%

Pu-240 1.15E+00 2.62E-02 1.71E-01 7.6E-06 0.0003%

Cs-137 3.30E-06 1.15E+00 2.62E-02 2.74E-01 1.2E-05 0.0005%

Pu-241 1.24E+01 4.55E-01 6.08E+00 2.7E-04 0.01%

Cs-137 1.18E-04 1.24E+01 1.24E+01 1.24E+01 5.5E-04 0.0205%

Am-241 5.15E+01 5.40E-02 6.04E+00 2.7E-04 0.01%

Cs-137 1.17E-04 5.15E+01 8.79E-02 7.74E+00 3.5E-04 0.01%

Am-243 5.33E-01 6.05E-03 1.15E-01 5.1E-06 0.0002%

Cs-137 2.21E-06 5.33E-01 1.36E-01 3.34E-01 1.5E-05 0.001%

Cm-243 5.03E+00 2.03E-02 6.10E-01 2.7E-05 0.001%

Cs-137 1.18E-05 5.03E+00 4.34E-02 1.08E+00 4.8E-05 0.002%

Cm-244 5.03E+00 2.03E-02 6.09E-01 2.7E-05 0.001%

Cs-137 1.18E-05 5.03E+00 4.34E-02 1.07E+00 4.8E-05 0.002%

Total 2.7E+00 100%

Total 2.7E+00 100%

Table 23 - Summary of Unit 2 568 EL Eberline Results Nuclide Max All Results pCi/g Min All Results pCi/g Avg All Results pCi/g First Half Inch Source Term Floor All Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Max Positive Results pCi/g Min Positive Results pCi/g Avg Positive Results pCi/g First Half Inch Source Term Floor Positive Ci Percent of Total Source Term H-3 2.06E+02 5.57E+00 6.17E+01 2.8E-03 0.14%

Cs-137 1.48E-03 2.06E+02 5.57E+00 6.17E+01 2.8E-03 0.14%

C-14 5.80E+00 1.17E+00 3.08E+00 1.4E-04 0.01%

Cs-137 7.37E-05 5.80E+00 1.17E+00 3.08E+00 1.4E-04 0.01%

Fe-55 1.41E+02 3.17E+00 3.54E+01 1.6E-03 0.08%

Co-60 8.28E-02 ND ND ND ND Ni-59 9.68E+00 6.75E+00 7.42E+00 3.3E-04 0.02%

Co-60 1.74E-02 ND ND ND ND Co-60 1.09E+03 4.35E+01 4.27E+02 1.9E-02 0.97%

Co-60 1.00E+00 1.09E+03 4.35E+01 4.27E+02 1.9E-02 0.98%

Ni-63 4.85E+03 9.98E+00 1.40E+03 6.3E-02 3.20%

Co-60 3.29E+00 4.85E+03 9.98E+00 1.40E+03 6.3E-02 3.2%

Sr-90 1.76E+01 4.17E-01 4.05E+00 1.8E-04 0.01%

Cs-137 9.70E-05 1.76E+01 8.33E-01 4.57E+00 2.0E-04 0.01%

Nb-94 1.92E+01 1.06E+00 9.16E+00 4.1E-04 0.02%

Co-60 2.15E-02 ND ND ND ND Tc-99 2.22E+00 2.54E-01 6.02E-01 2.7E-05 0.00%

Cs-137 1.44E-05 6.85E-01 2.80E-01 4.14E-01 1.8E-05 0.001%

Ag-108m 6.85E+01 8.09E-01 1.44E+01 6.4E-04 0.03%

Co-60 3.36E-02 ND ND ND ND Sb-125 2.39E+02 2.93E+00 7.31E+01 3.3E-03 0.17%

Cs-137 1.75E-03 ND ND ND ND Cs-134 6.09E+01 1.26E+00 1.64E+01 7.3E-04 0.04%

Cs-134 1.00E+00 6.09E+01 1.26E+00 1.65E+01 7.4E-04 0.04%

Cs-137 2.14E+05 1.13E+03 4.17E+04 1.9E+00 95.16%

Cs-137 1.00E+00 2.14E+05 1.13E+03 4.17E+04 1.9E+00 95.6%

TSD 13-006 Revision 0 Page 40 of 200 Nuclide Max All Results pCi/g Min All Results pCi/g Avg All Results pCi/g First Half Inch Source Term Floor All Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Max Positive Results pCi/g Min Positive Results pCi/g Avg Positive Results pCi/g First Half Inch Source Term Floor Positive Ci Percent of Total Source Term Eu-152 5.08E+01 3.28E+00 2.26E+01 1.0E-03 0.05%

Cs-137 5.42E-04 5.08E+01 5.08E+01 5.08E+01 2.3E-03 0.12%

Eu-154 3.35E+01 1.43E+00 1.56E+01 6.9E-04 0.04%

Cs-137 3.73E-04 3.35E+01 3.35E+01 3.35E+01 1.5E-03 0.08%

Eu-155 7.97E+01 2.32E+00 2.20E+01 9.8E-04 0.05%

Cs-137 5.27E-04 ND ND ND ND Np-237 3.84E-02 2.74E-02 3.12E-02 1.4E-06 0.0001%

Cs-137 7.49E-07 ND ND ND ND Pu-238 1.64E-01 2.59E-02 5.35E-02 2.4E-06 0.0001%

Cs-137 1.28E-06 1.64E-01 1.64E-01 1.64E-01 7.3E-06 0.0004%

Pu-239 7.70E-02 1.28E-02 2.72E-02 1.2E-06 0.0001%

Cs-137 6.51E-07 7.70E-02 2.37E-02 5.04E-02 2.2E-06 0.0001%

Pu-240 7.70E-02 1.28E-02 2.72E-02 1.2E-06 0.0001%

Cs-137 6.51E-07 7.70E-02 2.37E-02 5.04E-02 2.2E-06 0.0001%

Pu-241 6.17E+00 2.79E+00 3.97E+00 1.8E-04 0.01%

Cs-137 9.51E-05 ND ND ND ND Am-241 6.28E+00 4.25E-02 8.71E-01 3.9E-05 0.002%

Cs-137 2.09E-05 6.28E+00 1.24E-01 1.70E+00 7.6E-05 0.004%

Am-243 3.80E-01 3.28E-02 8.79E-02 3.9E-06 0.0002%

Cs-137 2.11E-06 3.80E-01 3.28E-02 1.54E-01 6.8E-06 0.0004%

Cm-243 5.93E-01 1.75E-02 9.59E-02 4.3E-06 0.0002%

Cs-137 2.30E-06 5.93E-01 2.27E-02 1.72E-01 7.7E-06 0.0004%

Cm-244 5.93E-01 1.75E-02 9.59E-02 4.3E-06 0.000%

Cs-137 2.30E-06 5.93E-01 2.27E-02 1.72E-01 7.7E-06 0.0004%

Total 2.0E+00 100.0%

Total 1.9E+00 100.2%

Comparison of the calculated source terms in the first half-inch of concrete in Table 22 for Unit 1 and Table 23 for Unit 2 show that the radionuclides eliminated as False Positives such as Ag-108m and I-129 were not significant contributors to the source term in the samples sent to Eberline for analysis. The purple shaded columns show data based on all results. The calculated source terms based upon the average concentrations of all the results show that even with the false positives included, these nuclides would comprise less than 15 to 20 percent of the total source term.

It is important to note that the Eberline results are for a subset of the Unit 1 and 2 cores that were 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 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 568 foot elevation. The overall source terms for these nuclides over all cores, at all depths, are provided in Table 10 and Table 14. These source terms are conservative since they included MDA values as well as positively identified results from in-house gamma spectroscopy reports. The Table 10 and Table 14 Unit 1 and 2 estimated total activities are summarized in Table 24.

Table 24 - Summary of Estimated 568 EL Source Terms from Table 10 and Table 14 Nuclide U1 Ci U2 Ci Co-60 2.08E-01 2.55E-01 Cs-137 6.80E+00 7.24E-01 Cs-134 1.99E-03 1.07E-03

TSD 13-006 Revision 0 Page 41 of 200 Total 7.006 0.980 Scaling factors were used to estimate the HTD source terms based upon the estimated Co-60, Cs-134, and Cs-137 source terms in Table 24. The scaling nuclides, scaling factors, and estimated source terms for Unit 1 and 2 568 foot concrete are provided in Table 25. The scaling factors were based upon the estimated source terms in the first half-inch based upon the average concentration of each nuclide in the Eberline report.

Table 25 - Estimated Unit 1 and 2 568 EL Source Terms Based Upon Hard-To-Detect Scaling Factors Unit 1 568 Foot Unit 2 568 Foot Nuclide Scaling Nuclide Scaling Factor Total 568' Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Total 568' Ci Percent of Total Source Term H-3 Cs-137 1.05E-03 7.15E-03 0.1%

Cs-137 1.48E-03 1.07E-03 0.1%

C-14 Cs-137 1.10E-04 7.46E-04 0.01%

Cs-137 7.37E-05 5.34E-05 0.0%

Fe-55 Co-60 2.35E-02 4.88E-03 0.07%

Co-60 8.28E-02 2.11E-02 1.1%

Ni-59 Co-60 4.99E-03 1.03E-03 0.01%

Co-60 1.74E-02 4.43E-03 0.2%

Co-60 Co-60 1.00E+00 2.08E-01 2.88%

Co-60 1.00E+00 2.55E-01 13.7%

Ni-63 Co-60 7.10E-01 1.47E-01 2.04%

Co-60 3.29E+00 8.38E-01 45.0%

Sr-90 Cs-137 5.36E-04 3.64E-03 0.05%

Cs-137 9.70E-05 7.02E-05 0.0%

Nb-94 Co-60 4.72E-03 9.79E-04 0.01%

Co-60 2.15E-02 5.47E-03 0.3%

Tc-99 Cs-137 1.34E-04 9.08E-04 0.01%

Cs-137 1.44E-05 1.04E-05 0.0%

Ag-108m Co-60 8.56E-03 1.78E-03 0.02%

Co-60 3.36E-02 8.57E-03 0.5%

Sb-125 Cs-137 1.09E-03 7.43E-03 0.10%

Cs-137 1.75E-03 1.27E-03 0.1%

Cs-134 Cs-134 1.00E+00 2.00E-03 0.03%

Cs-134 1.00E+00 1.07E-03 0.1%

Cs-137 Cs-137 1.00E+00 6.80E+00 94.30%

Cs-137 1.00E+00 7.24E-01 38.9%

Eu-152 Cs-137 2.03E-03 1.38E-02 0.19%

Cs-137 5.42E-04 3.92E-04 0.0%

Eu-154 Cs-137 1.02E-03 6.92E-03 0.10%

Cs-137 3.73E-04 2.70E-04 0.0%

Eu-155 Cs-137 3.57E-04 2.42E-03 0.03%

Cs-137 5.27E-04 3.82E-04 0.0%

Np-237 Cs-137 1.34E-06 9.11E-06 0.00%

Cs-137 7.49E-07 5.42E-07 0.0%

Pu-238 Cs-137 9.43E-06 6.41E-05 0.00%

Cs-137 1.28E-06 9.29E-07 0.0%

Pu-239 Cs-137 3.30E-06 2.24E-05 0.00%

Cs-137 6.51E-07 4.71E-07 0.0%

Pu-240 Cs-137 3.30E-06 2.24E-05 0.00%

Cs-137 6.51E-07 4.71E-07 0.0%

Pu-241 Cs-137 1.18E-04 7.99E-04 0.01%

Cs-137 9.51E-05 6.89E-05 0.0%

Am-241 Cs-137 1.17E-04 7.94E-04 0.01%

Cs-137 2.09E-05 1.51E-05 0.0%

Am-243 Cs-137 2.21E-06 1.50E-05 0.00%

Cs-137 2.11E-06 1.53E-06 0.0%

Cm-243 Cs-137 1.18E-05 8.01E-05 0.00%

Cs-137 2.30E-06 1.66E-06 0.0%

Cm-244 Cs-137 1.18E-05 8.00E-05 0.00%

Cs-137 2.30E-06 1.66E-06 0.0%

Total 7.21 100%

Total 1.86 100%

Note: Bold Italic are MDA values When the HTD nuclides are scaled into the mix, the Unit 1 total activity increased from 7.00 Ci to 7.20 Ci. This is principally due to the Ni-63 which added an additional 0.147 Ci to the estimated source term. Since many of the Ni-63 results were justified high (JH) but were

TSD 13-006 Revision 0 Page 42 of 200 retained as valid as described in Section 3.4, this is a conservative estimate of the Ni-63 source term.

The inclusion of the HTD nuclides for Unit 2 increased the total estimated 568 foot elevation source term from 0.98 Ci to 1.85 Ci. The higher ratio of Co-60 to Cs-137 in Unit 2 resulted in a larger increase in the relative Ni-63 source term. Ni-63 added 0.837 Ci to the overall source term. The Unit 2 Ni-63 results also included justified high (JH) results that were retained as valid as described in Section 3.4. The Unit 2 568 foot elevation source term remains well bounded by the Unit 1 source term.

3.6.

Unit 1 and 2 On-Site Gamma Spectroscopy Results for 541.5 Foot Incore Area Three cores were obtained from the Incore Under Vessel Area in each Zion Station Unit (e.g.,

two from the floor and one from the wall). The on-site gamma spectroscopy results for the sectioned cores from the In-Core Under Vessel Areas are provided in Attachment G for Unit 1 and Attachment H for Unit 2. The on-site gamma spectroscopy results identified Co-60, Cs-134, Cs-137, Eu-152 and Eu-154. The core from the floor directly under the reactor vessel was 15.5 inches in length. This core also positively detected Cs-134 to a depth of 4.5 inches in Unit

2. The other floor and the wall cores in each unit were 6 inches in length. As in Section 2.4 the core locations were 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 for Co-60, Cs-134 and Cs-137 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-134, Cs-137, Eu-152 and Eu-154 were included in the results when the nuclide was not positively identified. The MDA values used are noted in bold italics.

Figure 7 is an example of the data table for each core contained in Attachments G and H. 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 taken is also provided in the summary of the data in Attachments G and H.

As seen in Figure 7, there are two gamma spectroscopy results (top and bottom) for most of the sectioned pucks. The decay corrected average of the top and bottom results are shown in the lower table for each core on Attachments G and H. 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 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 one side counted was used as the average concentration. The Incore Area center floor 14 inch core from Unit 1 was fractured and discontinuous from 4.5 to 9.5 inches, the other floor and wall cores were less than 6 inches in length. Thus the profile at depth is incomplete for Unit 1. The Co-60 results for the three cores (floor center, floor side, and wall) in both units are shown Figure 11, Figure 12, and Figure 13.

TSD 13-006 Revision 0 Page 43 of 200 Figure 10 - Units 1 and 2 Incore Area Wall Profiles The elevated 267 pCi/g reading from the Unit 1 floor side core in Figure 12 was excluded from the graph to better show the overall activation pattern. Locations in the vicinity of rebar showed elevated Co-60 concentrations.

Figure 11 - Units 1 and 2 Co-60 Under Vessel Center Floor 14 Inch Cores 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Co-60 pCi/g U2 Co-60 pCi/g 0.00 5.00 10.00 15.00 20.00 25.00 30.00 0

2 4

6 8

10 12 14 16 pCi/g Depth Inches Under Vessel Floor Center 14 Inch Core U1 Co-60 pCi/g U2 Co-60 pCi/g

TSD 13-006 Revision 0 Page 44 of 200 Figure 12 - Units 1 and 2 Co-60 Under Vessel Side Floor 6 Inch Cores Figure 13 - Units 1 and 2 Co-60s-137 Under Vessel Wall 6 Inch Cores 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 0

1 2

3 4

5 pCi/g Depth Inches Under Vessel Floor Side 6 Inch Core U1 Co-60 pCi/g U2 Co-60 pCi/g 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Cs-137 pCi/g U2 Cs-137 pCi/g

TSD 13-006 Revision 0 Page 45 of 200 Figure 14 - Units 1 and 2 Cs-137 Under Vessel Center Floor 14 Inch Core As seen in Figure 14, Cs-137 concentration did not evidence a progressively downward trend with depth for the 14 inch center floor core, even with the Unit 2 0.25 inch 577 pCi/g result excluded from the data set. The high results in the first inch are probably due to absorption of Cs-137 from water leaked onto the floor at some point during plant operation.The Unit 1 side floor 6 inch core had an average Cs-137concentration of 1971 pCi/g and Unit 2 had an average of 13 pCi/g in the first half inch puck. When the 0.25 inch results are excluded, Unit 1 and Unit 2 concentrations look similar at depth as seen in Figure 15.

Figure 15 - Units 1 and 2 Cs-137 Under Vessel Side Floor 6 Inch Core 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 0

2 4

6 8

10 12 14 16 pCi/g Depth Inches Under Vessel Floor Center 14 Inch Core U1 Cs-137 pCi/g U2 Cs-137 pCi/g 0.00 0.20 0.40 0.60 0.80 1.00 1.20 0

1 2

3 4

5 pCi/g Depth Inches Under Vessel Floor Side 6 Inch Core U1 Cs-137 pCi/g U2 Cs-137 pCi/g

TSD 13-006 Revision 0 Page 46 of 200 The first half inch sections of the wall sections averaged 28.6 and 40.6 pCi/g in Unit 1 and 2 respectively. The Cs-137 profile with the first half inch puck removed from the data set is shown in Figure 16.

Figure 16 - Units 1 and 2 Cs-137 Under Vessel Wall 6 Inch Core There are three potential modes of deposition of Cs-137 in under vessel concrete. Absorption from contaminated water, diffusion of the gaseous parents (I-137 and Xe-137) into concrete, and neutron activation. Of these, activation is the least significant in the first half inch of concrete.

The principle gamma emitting concrete activation products are Cs-134, Eu-152 and Eu-154. As seen in the Figures 13 through 21 below the under vessel Incore area profiles show diminishing activation at depth. As is the case with Co-60, concentrations are generally lower in Unit 1 than in Unit 2 for Cs-134, Eu-152 and Eu-154.

Figure 17 - Units 1 and 2 Cs-134 Under Vessel Center Floor 14 Inch Core 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Cs-137 pCi/g U2 Cs-137 pCi/g 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0

5 10 15 pCi/g Depth Inches Under Vessel Floor Center 14 Inch Core U1 Cs-134 pCi/g U2 Cs-134 pCi/g

TSD 13-006 Revision 0 Page 47 of 200 Figure 18 - Units 1 and 2 Cs-134 Under Vessel Side Floor 6 Inch Core Figure 19 - Units 1 and 2 Cs-134 Under Vessel Wall 6 Inch Core 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 0

1 2

3 4

5 pCi/g Depth Inches Under Vessel Floor Side 6 Inch Core U1 Cs-134 pCi/g U2 Cs-134 pCi/g 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Cs-134 pCi/g U2 Cs-134 pCi/g

TSD 13-006 Revision 0 Page 48 of 200 Figure 20 - Units 1 and 2 Eu-152 Under Vessel Center Floor 14 Inch Core Figure 21 - Units 1 and 2 Eu-152 Under Vessel Side Floor 6 Inch Core 0.00 20.00 40.00 60.00 80.00 100.00 120.00 140.00 160.00 180.00 200.00 0

5 10 15 pCi/g Depth Inches Under Vessel Floor Center 14 Inch Core U1 Eu-152 pCi/g U2 Eu-152 pCi/g 0.00 20.00 40.00 60.00 80.00 100.00 120.00 140.00 160.00 0

1 2

3 4

5 pCi/g Depth Inches Under Vessel Floor Side 6 Inch Core U1 Eu-152 pCi/g U2 Eu-152 pCi/g

TSD 13-006 Revision 0 Page 49 of 200 Figure 22 - Units 1 and 2 Eu-152 Under Vessel Wall 6 Inch Core Figure 23 - Units 1 and 2 Eu-154 Under Vessel Center Floor 14 Inch Core 0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 80.00 90.00 100.00 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Eu-152 pCi/g U2 Eu-152 pCi/g 0.00 2.00 4.00 6.00 8.00 10.00 12.00 0

5 10 15 pCi/g Depth Inches Under Vessel Floor Center 14 Inch Core U1 Eu-154 pCi/g U2 Eu-154 pCi/g

TSD 13-006 Revision 0 Page 50 of 200 Figure 24 - Units 1 and 2 Eu-154 Under Vessel Side Floor 6 Inch Core Figure 25 - Units 1 and 2 Eu-154 Under Vessel Wall 6 Inch Core 3.7.

Unit 1 Average Concentrations and Source Terms for 541.5 Foot Incore Area 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. As seen in Attachment G, and Table 42, the majority of the Unit 1 under vessel floor source term is in the first half-inch of the concrete.

The source term is more evenly distributed in the Unit 2 floor as seen in Table 59 and in the Unit 1 and 2 walls as seen in Table 43 and Table 64. The number of results that each depth profiles maximum, minimum and average concentrations were calculated from are shown in Column 2 of each table.

The estimated floor area source term in Curies for each nuclide was calculated by using the 541.5 foot elevation surface area of 229.21 square feet from Table 2. [16] A 1/2 inch thick depth of this surface area has a volume of 2.70E+5 cubic centimeters. Using a density for concrete of 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 0

1 2

3 4

5 pCi/g Depth Inches Under Vessel Floor Side 6 Inch Core U1 Eu-154 pCi/g U2 Eu-154 pCi/g 0.00 1.00 2.00 3.00 4.00 5.00 6.00 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Eu-154 pCi/g U2 Eu-154 pCi/g

TSD 13-006 Revision 0 Page 51 of 200 2.40 g/cc yields a mass of 6.50E+5 grams for each 1/2 inch floor layer. When multiplied times the average concentration this provides a bounding estimate of the source term in each layer of the under vessel Incore area floor. Since the concentrations at depth are based on the core from the center of the floor, the estimated source terms are worst case and bounding when used for remediation planning or estimates of the dose consequences associated with the end state conceptual site model.

Because there are no concentration results from the 5 inch to 9.5 inch section of the Unit 1 core from the center of the floor, it was necessary to estimate the concentrations using the Unit 2 profile, which was from a complete core. This was done by using the ratio of the Unit 2 core data point and the next depth data point times the Unit 1 values (e.g., 4.75 inch pCi/g/5.25 inch pCi/g X U2 4.75 inch pCi/g, etc.). This drops the curve progressively at the rate observed for those depths in Unit 2. Figure 26 shows the U1 floor Co-60 profile when the result for the first half inch puck is included.

Figure 26 - Unit 1 Incore Floor Average Co-60 Concentrations Figure 27 shows the Unit 1 Co-60 profile containing the estimated values when the first half inch result is eliminated.

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0 0

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 pCi/g Depth Inches U1 Incore Co-60 Avg Concentration Floor Avg.

Co-60 pCi/g

TSD 13-006 Revision 0 Page 52 of 200 Figure 27 - Unit 1 Incore Floor Average Co-60 Concentrations First Puck Data Eliminated It can be seen that the Co-60 sample results approach zero at 14 to 16 inches of depth. Thus although maximum core length was only 14 inches and the floor is 30 inches thick it is unlikely that there is significant source term beyond the core depth. As seen in Table 26 the shallow depth pucks encompass the majority of the Co-60 source term.

Table 26 shows the maximum, minimum and average Co-60 concentration profile and the estimated source term in Curies using 6.50E+05 grams per half inch floor depth.

Table 26 - Unit 1 Incore Floor Co-60 Profile U1 542 ft Floor Co-60 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Co-60 pCi/g Min.

Co-60 pCi/g Avg.

Co-60 pCi/g Source Term Floor Co-60 Ci Source Term Distribution Floor 0.25 2.0 267.4 24.2 145.8 9.5E-05 49%

0.75 2.0 14.2 13.7 14.0 9.1E-06 5%

1.25 2.0 14.7 12.3 13.5 8.8E-06 5%

1.75 2.0 11.8 11.5 11.6 7.6E-06 4%

2.25 2.0 11.7 11.4 11.6 7.5E-06 4%

2.75 2.0 14.1 11.6 12.9 8.4E-06 4%

3.25 2.0 12.9 10.6 11.7 7.6E-06 4%

3.75 2.0 12.1 6.1 9.1 5.9E-06 3%

4.25 2.0 12.1 6.0 9.0 5.9E-06 3%

4.75 1.0 10.2 10.2 10.2 6.6E-06 3.4%

5.25 NR NR NR 6.5 4.2E-06 2.2%

5.75 NR NR NR 4.8 3.1E-06 1.6%

0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 0

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 pCi/g Depth Inches U1 Incore Co-60 Avg Concentration Floor Avg.

Co-60 pCi/g

TSD 13-006 Revision 0 Page 53 of 200 U1 542 ft Floor Co-60 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Co-60 pCi/g Min.

Co-60 pCi/g Avg.

Co-60 pCi/g Source Term Floor Co-60 Ci Source Term Distribution Floor 6.25 NR NR NR 3.9 2.5E-06 1.3%

6.75 NR NR NR 5.0 3.2E-06 1.7%

7.25 NR NR NR 3.4 2.2E-06 1.1%

7.75 NR NR NR 2.2 1.4E-06 0.7%

8.25 NR NR NR 2.1 1.3E-06 0.7%

8.75 NR NR NR 2.0 1.3E-06 0.7%

9.25 NR NR NR 1.2 7.8E-07 0.4%

9.75 1.0 2.8 2.8 2.8 1.8E-06 0.9%

10.25 1.0 2.4 2.4 2.4 1.5E-06 0.8%

10.75 1.0 1.8 1.8 1.8 1.2E-06 0.6%

11.25 1.0 2.0 2.0 2.0 1.3E-06 0.7%

11.75 1.0 2.9 2.9 2.9 1.9E-06 1.0%

12.25 1.0 2.0 2.0 2.0 1.3E-06 0.7%

12.75 1.0 1.2 1.2 1.2 8.1E-07 0.4%

13.25 1.0 1.6 1.6 1.6 1.0E-06 0.5%

13.75 1.0 1.2 1.2 1.2 7.8E-07 0.4%

Total 1.9E-04 100%

Note: Highlighted results are calculated using ratio of Unit 2 core results.

As noted above, a six inch core was obtained from the wall in each Incore Access Area. This area has an inner radius of 102.5 inches and is 348 inches high (e.g., 539 to 568). This 348 inch height is from the 539 foot liner to the 568 floor. Thus this includes a portion of the 568 foot floor which adds conservatism to the overall source term estimate since it was included in the 568 foot floor source term estimates. The Incore Area has interior concrete walls under the vessel bioshield that are 23.5 inches thick. The concrete mass used to estimate the wall source term corresponding to each puck concentration was calculated using the equation for the volume of a cylinder. The concrete mass in each 1/2 inch section corresponding to a puck increases for each 1/2 inch depth since the inner (ri) and outer (ro) radius is increasing with depth. The mass of concrete calculated at each puck depth using Equation 1 was multiplied times the average concentration to calculate the source term for each radionuclide.

Equation 1 - Concrete Mass for Incore Area Wall Puck Depth

[(

) (

)]

As seen in Figure 13, the wall Co-60 concentrations are lower than the floor and the wall profile only extends to 3.25 inches. Because the Co-60 concentration does not approach zero at this depth, use of this data along with Equation 1 masses leads to the source term estimate (Column 3) in Table 27.

TSD 13-006 Revision 0 Page 54 of 200 Table 27 - Unit 1 Incore Wall Co-60 Profile Using Wall Core U1 542 ft Wall Co-60 Summary Decayed To 1/1/13 Depth Wall Co-60 pCi/g Source Term Wall Co-60 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 10.2 5.68E-05 67%

102.5 103 2.311E+06 5.557E+06 0.75 6.2 4.03E-06 5%

103 103.5 2.322E+06 5.584E+06 1.25 8.2 5.31E-06 6%

103.5 104 2.333E+06 5.611E+06 1.75 8.6 5.56E-06 7%

104 104.5 2.345E+06 5.638E+06 2.25 8.1 5.30E-06 6%

104.5 105 2.356E+06 5.665E+06 2.75 6.4 4.14E-06 5%

105 105.5 2.367E+06 5.692E+06 3.25 5.5 3.59E-06 4%

105.5 106 2.378E+06 5.719E+06 Total 8.47E-05 1.00 The wall core is from the lower wall and may not be indicative of the concentrations in the upper wall closer to the vessel where neutron flux may have been higher during operation.

At Connecticut Yankee [14] it was expected that the side walls of the sump would have different activation levels than the floor level. For this reason, the In-core sump was represented by three regions. A circular top region which is 11.5 ft high having a radius of 8 ft and thickness of 2 ft. The bottom region had an identical geometry. The floor was represented as a circular disk with a 10 ft radius and 2 ft thickness. Analysis was performed for the exterior wall, mat, the in-core sump beneath the reactor in the containment building, and for the walls and floor of the Spent Fuel Pool. Contaminant levels in the upper-half walls of the Incore sump (below the ledge that supported the Neutron Shield Tank) were expected to be much higher than in the lower half walls due to the greater neutron flux experienced in this region.

Therefore, the cylindrical wall portion of the in-core sump was divided into two regions for the analysis.

At Maine Yankee, activated concrete extended past the containment liner [23]. During operations, a small neutron flux from the reactor activated the carbon steel liner and the concrete outside the liner.

At CY, upper wall concentrations were higher than lower wall concentrations. [24] The CY data indicated that average concentrations were two to three times higher in the upper portion of the Incore Area wall. Assuming the volumes are equal between the upper and lower walls, this indicates the overall (e.g. average including upper and lower) Zion in-core wall concentrations can be calculated by adjusting the lower wall concentrations by the values in the last row of Table 28.

Table 28-Connecticut Yankee Ratios Between Upper and Lower Incore Walls Based on Maximum and Average Concentrations Ratios Co-60 Eu-152 Eu-154 Upper to Lower Wall Max Ratio 3.11 3.43 3.65 Upper to Lower Wall Avg Ratio 2.10 2.38 2.47 Overall Lower Wall Adj Factor 1.05 1.19 1.23

TSD 13-006 Revision 0 Page 55 of 200 The Zion Incore floor concentrations with depth can be used in order to provide a conservative estimate of the Co-60 source term in the Incore wall as shown in Table 29. As seen in Figure 28, using the floor minimum concentrations to a depth of 3.5 inches, and the average floor concentrations at depths greater than 3.5 inches, removes the bias of the high Co-60 concentrations in the initial floor pucks and provides a conservative basis for estimating the Co-60 source term in the Incore walls under vessel.

Figure 28 - U1 Co-60 Incore Wall Profile Actual versus Worst Case As seen in Table 29 this leads to a higher estimated source term for the Incore Area wall.

Table 29 - Unit 1 Incore Wall Co-60 Profile Using Floor Concentrations U1 542 ft Wall Co-60 Summary Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Co-60 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Co-60 Ci 0.25 24.2 102.5 103 2.311E+06 5.557E+06 1.3E-04 0.75 13.7 103 103.5 2.322E+06 5.584E+06 7.7E-05 1.25 12.3 103.5 104 2.333E+06 5.611E+06 6.9E-05 1.75 11.5 104 104.5 2.345E+06 5.638E+06 6.5E-05 2.25 11.4 104.5 105 2.356E+06 5.665E+06 6.4E-05 2.75 11.6 105 105.5 2.367E+06 5.692E+06 6.6E-05 3.25 10.6 105.5 106 2.378E+06 5.719E+06 6.1E-05 3.75 9.1 106 106.5 2.390E+06 5.746E+06 5.2E-05 4.25 9.0 106.5 107 2.401E+06 5.773E+06 5.2E-05 4.75 10.2 107 107.5 2.412E+06 5.800E+06 5.9E-05 5.25 6.5 107.5 108 2.423E+06 5.827E+06 3.8E-05 5.75 4.8 108 108.5 2.434E+06 5.854E+06 2.8E-05 6.25 3.9 108.5 109 2.446E+06 5.881E+06 2.3E-05 0.0 5.0 10.0 15.0 20.0 25.0 30.0 0

5 10 15 pCi/g Depth Inches U1 Incore Co-60 Concentration Wall Average Conc Wall Co-60 pCi/g Worst Case Wall Co-60 pCi/g

TSD 13-006 Revision 0 Page 56 of 200 U1 542 ft Wall Co-60 Summary Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Co-60 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Co-60 Ci 6.75 5.0 109 109.5 2.457E+06 5.908E+06 2.9E-05 7.25 3.4 109.5 110 2.468E+06 5.935E+06 2.0E-05 7.75 2.2 110 110.5 2.479E+06 5.962E+06 1.3E-05 8.25 2.1 110.5 111 2.491E+06 5.990E+06 1.2E-05 8.75 2.0 111 111.5 2.502E+06 6.017E+06 1.2E-05 9.25 1.2 111.5 112 2.513E+06 6.044E+06 7.2E-06 9.75 2.8 112 112.5 2.524E+06 6.071E+06 1.7E-05 10.25 2.4 112.5 113 2.536E+06 6.098E+06 1.5E-05 10.75 1.8 113 113.5 2.547E+06 6.125E+06 1.1E-05 11.25 2.0 113.5 114 2.558E+06 6.152E+06 1.2E-05 11.75 2.9 114 114.5 2.569E+06 6.179E+06 1.8E-05 12.25 2.0 114.5 115 2.581E+06 6.206E+06 1.3E-05 12.75 1.2 115 115.5 2.592E+06 6.233E+06 7.7E-06 13.25 1.6 115.5 116 2.603E+06 6.260E+06 1.0E-05 13.75 1.2 116 116.5 2.614E+06 6.287E+06 7.5E-06 Total 9.9E-04 There was no apparent trend line for the Unit 1 Incore floor Cs-137 results shown in Figure 29.

However, when the results of the first two pucks are eliminated and the ratio Unit 2 core data is used to estimate the concentrations of the missing pucks, the concentration peaks at 8 to 9 inches as seen in Figure 29.

TSD 13-006 Revision 0 Page 57 of 200 Figure 29 - Unit 1 Incore Floor Average Cs-137 Concentrations First Puck Data Eliminated Figure 30 - Unit 1 Incore Center Floor Average Cs-137 Concentrations First Puck Data Included 0.0 10.0 20.0 30.0 40.0 50.0 60.0 0

5 10 15 pCi/g Depth Inches U1 Incore Cs-137 Avg Concentration Floor Avg.

Cs-137 pCi/g 0.0 200.0 400.0 600.0 800.0 1000.0 1200.0 0

5 10 15 pCi/g Depth Inches U1 Incore Cs-137 Avg Concentration Floor Avg.

Cs-137 pCi/g

TSD 13-006 Revision 0 Page 58 of 200 The Cs-137 profile using the estimated values for the 5 inch to 9.5 inch sections are shown in Table 30.

Table 30 - Unit 1 Incore Floor Cs-137 Profile U1 542 ft Floor Cs-137 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-137 pCi/g Min.

Cs-137 pCi/g Avg.

Cs-137 pCi/g Source Term Floor Cs-137 Ci Source Term Distribution Floor 0.25 2.0 1970.9 40.9 1005.9 6.5E-04 68.4%

0.75 2.0 5.2 1.1 3.2 2.06E-06 0.2%

1.25 2.0 4.2 0.8 2.5 1.63E-06 0.2%

1.75 2.0 6.8 0.5 3.7 2.38E-06 0.2%

2.25 2.0 4.2 0.6 2.4 1.58E-06 0.2%

2.75 2.0 5.1 0.5 2.8 1.81E-06 0.2%

3.25 2.0 4.0 0.5 2.3 1.47E-06 0.2%

3.75 2.0 25.6 0.4 13.0 8.46E-06 0.9%

4.25 2.0 25.6 0.4 13.0 8.48E-06 0.9%

4.75 1.0 20.2 20.2 20.2 1.32E-05 1.4%

5.25 NR NR NR 36.9 2.40E-05 2.5%

5.75 NR NR NR 31.1 2.02E-05 2.1%

6.25 NR NR NR 47.1 3.07E-05 3.2%

6.75 NR NR NR 40.2 2.62E-05 2.7%

7.25 NR NR NR 48.7 3.17E-05 3.3%

7.75 NR NR NR 50.7 3.30E-05 3.4%

8.25 NR NR NR 56.3 3.66E-05 3.8%

8.75 NR NR NR 46.6 3.03E-05 3.2%

9.25 NR NR NR 34.9 2.27E-05 2.4%

9.75 1.0 0.7 0.7 0.7 4.81E-07 0.1%

10.25 1.0 0.7 0.7 0.7 4.64E-07 0.0%

10.75 1.0 0.8 0.8 0.8 4.98E-07 0.1%

11.25 1.0 1.3 1.3 1.3 8.40E-07 0.1%

11.75 1.0 1.6 1.6 1.6 1.03E-06 0.1%

12.25 1.0 1.2 1.2 1.2 7.49E-07 0.1%

12.75 1.0 1.1 1.1 1.1 7.10E-07 0.1%

13.25 1.0 1.2 1.2 1.2 7.49E-07 0.1%

13.75 1.0 1.3 1.3 1.3 8.60E-07 0.1%

Total 9.6E-04 100%

Note: Highlighted results are estimated based ratio of Unit 2 results.

As seen in Figure 16, the wall Cs-137 concentrations are lower than the floor and the wall profile only extends to 3.25 inches. Because the Cs-137 concentration does not approach zero at this depth, use of this data along with the Equation 1 calculated masses leads to the lower source term estimate shown in Table 31.

TSD 13-006 Revision 0 Page 59 of 200 Table 31 - Unit 1 Incore Wall Cs-137 Profile Using Wall Core U1 Incore Wall Cs-137 Using Wall Data Decayed To 1/1/13 Depth Wall Cs-137 pCi/g Source Term Wall Cs-137 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 28.5 1.59E-04 81%

102.5 103 2.311E+06 5.557E+06 0.75 1.2 6.74E-06 3%

103 103.5 2.322E+06 5.584E+06 1.25 1.2 6.77E-06 3%

103.5 104 2.333E+06 5.611E+06 1.75 0.8 4.76E-06 2%

104 104.5 2.345E+06 5.638E+06 2.25 1.0 5.75E-06 3%

104.5 105 2.356E+06 5.665E+06 2.75 1.1 6.11E-06 3%

105 105.5 2.367E+06 5.692E+06 3.25 1.4 7.95E-06 4%

105.5 106 2.378E+06 5.719E+06 Total 1.97E-04 100%

The floor concentrations can be used in order to provide a conservative estimate of the Cs-137 source term in the Incore wall as shown in Table 32. As seen Figure 31, in using the floor minimum concentration at 0.5 inches, and the average floor concentrations for the rest of the profile, removes the bias of the high Cs-137 concentrations in the initial floor surface puck and provides conservative basis for estimating the Cs-137 source term in the Incore walls under vessel.

Figure 31 - U1 Cs-137 Incore Wall Profile Actual versus Worst Case 0.0 10.0 20.0 30.0 40.0 50.0 60.0 0

5 10 15 pCi/g Depth Inches U1 Incore Cs-137 Concentration Wall Wall Cs-137 pCi/g Worst Case Wall Cs-137 pCi/g

TSD 13-006 Revision 0 Page 60 of 200 The floor concentrations with depth can be used in order to provide a conservative estimate of the Cs-137 in the wall as seen in Table 32.

Table 32 - Unit 1 Incore Wall Cs-137 Profile Using Floor Concentrations U1 Incore Wall Cs-137 Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Cs-137 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Cs-137 Ci 0.25 40.9 102.5 103 2.311E+06 5.557E+06 2.3E-04 0.75 3.2 103 103.5 2.322E+06 5.584E+06 1.8E-05 1.25 2.5 103.5 104 2.333E+06 5.611E+06 1.4E-05 1.75 3.7 104 104.5 2.345E+06 5.638E+06 2.1E-05 2.25 2.4 104.5 105 2.356E+06 5.665E+06 1.4E-05 2.75 2.8 105 105.5 2.367E+06 5.692E+06 1.6E-05 3.25 2.3 105.5 106 2.378E+06 5.719E+06 1.3E-05 3.75 13.0 106 106.5 2.390E+06 5.746E+06 7.5E-05 4.25 13.0 106.5 107 2.401E+06 5.773E+06 7.5E-05 4.75 20.2 107 107.5 2.412E+06 5.800E+06 1.2E-04 5.25 36.9 107.5 108 2.423E+06 5.827E+06 2.2E-04 5.75 31.1 108 108.5 2.434E+06 5.854E+06 1.8E-04 6.25 47.1 108.5 109 2.446E+06 5.881E+06 2.8E-04 6.75 40.2 109 109.5 2.457E+06 5.908E+06 2.4E-04 7.25 48.7 109.5 110 2.468E+06 5.935E+06 2.9E-04 7.75 50.7 110 110.5 2.479E+06 5.962E+06 3.0E-04 8.25 56.3 110.5 111 2.491E+06 5.990E+06 3.4E-04 8.75 46.6 111 111.5 2.502E+06 6.017E+06 2.8E-04 9.25 34.9 111.5 112 2.513E+06 6.044E+06 2.1E-04 9.75 0.7 112 112.5 2.524E+06 6.071E+06 4.5E-06 10.25 0.7 112.5 113 2.536E+06 6.098E+06 4.4E-06 10.75 0.8 113 113.5 2.547E+06 6.125E+06 4.7E-06 11.25 1.3 113.5 114 2.558E+06 6.152E+06 7.9E-06 11.75 1.6 114 114.5 2.569E+06 6.179E+06 9.8E-06 12.25 1.2 114.5 115 2.581E+06 6.206E+06 7.1E-06 12.75 1.1 115 115.5 2.592E+06 6.233E+06 6.8E-06 13.25 1.2 115.5 116 2.603E+06 6.260E+06 7.2E-06 13.75 1.3 116 116.5 2.614E+06 6.287E+06 8.3E-06 Total 3.0E-03 As seen in Figure 32, Cs-134 did display a downward trend when the Unit 2 data ratios were used to estimate the concentration for pucks from 5 inches to 9.5 inches.

TSD 13-006 Revision 0 Page 61 of 200 Figure 32 - Unit 1 Incore Center Floor Average Cs-134 Concentrations Figure 33 -Unit 1 Incore Center Floor Average Cs-134 Concentrations First Puck Data Included As seen Figure 32, Cs-134 concentrations does not approach zero until well past the 14 inch core length. The trend line equation in Figure 33 was used to calculate the concentration until the values turned negative at the 19 inch depth. The calculated concentrations and source terms out to 19 inches are provided in Table 33.

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 0

5 10 15 pCi/g Depth inches U1 Incore Cs-134 Avg Concentration Floor Avg.

Cs-134 pCi/g y = -0.0245x + 0.4629 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0

5 10 15 Ci/g Depth inches U1 Incore Cs-134 Avg Floor Concentration Trend Avg.

Cs-134 pCi/g Linear (Avg.

Cs-134 pCi/g)

TSD 13-006 Revision 0 Page 62 of 200 Table 33 - Unit 1 Incore Floor Cs-134 Profile U1 542 ft Floor Cs-134 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-134 pCi/g Min.

Cs-134 pCi/g Avg.

Cs-134 pCi/g Source Term Floor Cs-134 Ci Source Term Distribution Floor 0.25 2.0 1.2 0.4 0.8 5.36E-07 9.0%

0.75 2.0 0.4 0.4 0.4 2.61E-07 4.4%

1.25 2.0 0.5 0.5 0.5 3.22E-07 5.4%

1.75 2.0 0.4 0.4 0.4 2.67E-07 4.5%

2.25 2.0 0.4 0.4 0.4 2.84E-07 4.8%

2.75 2.0 0.4 0.4 0.4 2.85E-07 4.8%

3.25 2.0 0.4 0.4 0.4 2.44E-07 4.1%

3.75 2.0 0.3 0.2 0.3 1.70E-07 2.9%

4.25 2.0 0.3 0.2 0.2 1.55E-07 2.6%

4.75 1.0 0.4 0.4 0.4 2.77E-07 4.7%

5.25 NR NR NR 0.3 2.04E-07 3.4%

5.75 NR NR NR 0.4 2.60E-07 4.4%

6.25 NR NR NR 0.3 1.73E-07 2.9%

6.75 NR NR NR 0.4 2.56E-07 4.3%

7.25 NR NR NR 0.3 1.95E-07 3.3%

7.75 NR NR NR 0.3 1.96E-07 3.3%

8.25 NR NR NR 0.2 1.60E-07 2.7%

8.75 NR NR NR 0.3 1.69E-07 2.8%

9.25 NR NR NR 0.2 1.14E-07 1.9%

9.75 1.0 0.3 0.3 0.3 1.68E-07 2.8%

10.25 1.0 0.2 0.2 0.2 1.11E-07 1.9%

10.75 1.0 0.2 0.2 0.2 1.31E-07 2.2%

11.25 1.0 0.2 0.2 0.2 9.76E-08 1.6%

11.75 1.0 0.2 0.2 0.2 1.21E-07 2.0%

12.25 1.0 0.2 0.2 0.2 1.39E-07 2.4%

12.75 1.0 0.1 0.1 0.1 7.17E-08 1.2%

13.25 1.0 0.2 0.2 0.2 1.09E-07 1.8%

13.75 1.0 0.1 0.1 0.1 7.37E-08 1.2%

14.25 NR NR NR 0.1 7.40E-08 1.2%

14.75 NR NR NR 0.1 6.60E-08 1.1%

15.25 NR NR NR 0.1 5.81E-08 1.0%

15.75 NR NR NR 0.1 5.01E-08 0.8%

16.25 NR NR NR 0.1 4.21E-08 0.7%

16.75 NR NR NR 0.1 3.42E-08 0.6%

17.25 NR NR NR 0.04 2.62E-08 0.4%

17.75 NR NR NR 0.03 1.82E-08 0.3%

18.25 NR NR NR 0.02 1.03E-08 0.2%

TSD 13-006 Revision 0 Page 63 of 200 U1 542 ft Floor Cs-134 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-134 pCi/g Min.

Cs-134 pCi/g Avg.

Cs-134 pCi/g Source Term Floor Cs-134 Ci Source Term Distribution Floor 18.75 NR NR NR 0.004 2.29E-09 0.0%

Total 5.9E-06 100%

Note: Highlighted results are estimated based on Unit 2 average floor ratios and the trend line equation in Figure 33.

As seen in Figure 19, the wall Cs-134 concentrations are lower than the floor and the wall profile only extends to 3.25 inches. Using only the 3.25 inch core data along with Equation 1 calculated masses leads to the source term estimate in Table 34.

Table 34 - Unit 1 Incore Wall Cs-134 Profile Using Wall Core U1 542 ft Wall Cs-134 Summary Decayed To 1/1/13 Depth Wall Cs-134 pCi/g Source Term Wall Cs-134 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 0.4 2.04E-06 15%

102.5 103 2.311E+06 5.557E+06 0.75 0.3 1.82E-06 13%

103 103.5 2.322E+06 5.584E+06 1.25 0.4 2.12E-06 15%

103.5 104 2.333E+06 5.611E+06 1.75 0.4 2.05E-06 15%

104 104.5 2.345E+06 5.638E+06 2.25 0.4 2.05E-06 15%

104.5 105 2.356E+06 5.665E+06 2.75 0.4 2.19E-06 16%

105 105.5 2.367E+06 5.692E+06 3.25 0.3 1.77E-06 13%

105.5 106 2.378E+06 5.719E+06 Total 1.40E-05 100%

The floor concentrations can be used in order to provide a conservative estimate of the Cs-134 source term in the Incore wall as shown in Table 35. As seen in Figure 34, using the floor the average floor concentrations provides conservative basis for estimating the Cs-134 source term in the Incore walls under vessel.

TSD 13-006 Revision 0 Page 64 of 200 Figure 34 - U1 Cs-134 Incore Wall Profile Actual versus Worst Case The floor concentrations with depth can be used in order to provide a conservative estimate of the Cs-137 in the wall and result in a higher source term estimate as seen in Table 35.

Table 35 - Unit 1 Incore Wall Cs-134 Profile Using Floor Concentrations U1 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Cs-134 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Cs-134 Ci 0.25 0.8 102.5 103 2.311E+06 5.557E+06 4.6E-06 0.75 0.4 103 103.5 2.322E+06 5.584E+06 2.2E-06 1.25 0.5 103.5 104 2.333E+06 5.611E+06 2.8E-06 1.75 0.4 104 104.5 2.345E+06 5.638E+06 2.3E-06 2.25 0.4 104.5 105 2.356E+06 5.665E+06 2.5E-06 2.75 0.4 105 105.5 2.367E+06 5.692E+06 2.5E-06 3.25 0.4 105.5 106 2.378E+06 5.719E+06 2.1E-06 3.75 0.3 106 106.5 2.390E+06 5.746E+06 1.5E-06 4.25 0.2 106.5 107 2.401E+06 5.773E+06 1.4E-06 4.75 0.4 107 107.5 2.412E+06 5.800E+06 2.5E-06 5.25 0.3 107.5 108 2.423E+06 5.827E+06 1.8E-06 5.75 0.4 108 108.5 2.434E+06 5.854E+06 2.3E-06 6.25 0.3 108.5 109 2.446E+06 5.881E+06 1.6E-06 6.75 0.4 109 109.5 2.457E+06 5.908E+06 2.3E-06 7.25 0.3 109.5 110 2.468E+06 5.935E+06 1.8E-06 7.75 0.3 110 110.5 2.479E+06 5.962E+06 1.8E-06 8.25 0.2 110.5 111 2.491E+06 5.990E+06 1.5E-06 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 0

5 10 15 20 pCi/g Depth Inches U1 Incore Cs-134 Concentration Wall Wall Cs-134 pCi/g Worst Case Wall Cs-134 pCi/g

TSD 13-006 Revision 0 Page 65 of 200 U1 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Cs-134 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Cs-134 Ci 8.75 0.3 111 111.5 2.502E+06 6.017E+06 1.6E-06 9.25 0.2 111.5 112 2.513E+06 6.044E+06 1.1E-06 9.75 0.3 112 112.5 2.524E+06 6.071E+06 1.6E-06 10.25 0.2 112.5 113 2.536E+06 6.098E+06 1.0E-06 10.75 0.2 113 113.5 2.547E+06 6.125E+06 1.2E-06 11.25 0.2 113.5 114 2.558E+06 6.152E+06 9.2E-07 11.75 0.2 114 114.5 2.569E+06 6.179E+06 1.2E-06 12.25 0.2 114.5 115 2.581E+06 6.206E+06 1.3E-06 12.75 0.1 115 115.5 2.592E+06 6.233E+06 6.9E-07 13.25 0.2 115.5 116 2.603E+06 6.260E+06 1.0E-06 13.75 0.1 116 116.5 2.614E+06 6.287E+06 7.1E-07 14.25 0.1 116.5 117 2.626E+06 6.314E+06 7.2E-07 14.75 0.1 117 117.5 2.637E+06 6.341E+06 6.4E-07 15.25 0.1 117.5 118 2.648E+06 6.368E+06 5.7E-07 15.75 0.1 118 118.5 2.659E+06 6.395E+06 4.9E-07 16.25 0.1 118.5 119 2.671E+06 6.422E+06 4.2E-07 16.75 0.1 119 119.5 2.682E+06 6.449E+06 3.4E-07 17.25 0.04 119.5 120 2.693E+06 6.476E+06 2.6E-07 17.75 0.03 120 120.5 2.704E+06 6.503E+06 1.8E-07 18.25 0.02 120.5 121 2.716E+06 6.530E+06 1.0E-07 18.75 0.00 121 121.5 2.727E+06 6.557E+06 2.3E-08 Total 5.4E-05 The Unit 1 floor average concentrations for Eu-152 are shown in Figure 35. It can be seen that the concentrations trend downward at 2.75 inches depth.

TSD 13-006 Revision 0 Page 66 of 200 Figure 35 - U1 Eu-152 Data with Moving Average Trend Line Estimated Concentrations The concentrations between 5 inches and 9.5 inches were estimated by using a moving average trend as shown in Figure 36. Using the ratios of the Unit 2 core data as was done Co-60, Cs-137 and Cs-134 underestimated the concentrations in that region.

Figure 36 - U1 Eu-152 Data from 2.75 Inches with Moving Average Trend Line The concentration is trending toward zero at the 14 to 16 inch depth. The Unit 1 Incore Eu-152 profile is provided in Table 36. The 0 to 3.5 inch depth contains 61% of the wall Eu-152 source term.

0.0 20.0 40.0 60.0 80.0 100.0 120.0 0

5 10 15 pCi/g Depth inches U1 Incore Eu-152 Avg Concentration Floor Avg.

Eu-152 pCi/g 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 0

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 pCi/g Depth inches U1 Incore Eu-152 Avg Concentration Floor Avg.

Eu-152 pCi/g

TSD 13-006 Revision 0 Page 67 of 200 Table 36 - Unit 1 Incore Floor Eu-152 Profile U1 542 ft Floor Eu-152 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Eu-152 pCi/g Min.

Eu-152 pCi/g Avg.

Eu-152 pCi/g Source Term Floor Eu-152 Ci Source Term Distribution Floor 0.25 2.0 71.8 66.0 68.9 4.48E-05 6.9%

0.75 2.0 85.2 81.8 83.5 5.43E-05 8.3%

1.25 2.0 99.4 97.9 98.6 6.41E-05 9.9%

1.75 2.0 101.4 87.6 94.5 6.14E-05 9.4%

2.25 2.0 99.9 86.7 93.3 6.07E-05 9.3%

2.75 2.0 100.5 87.3 93.9 6.10E-05 9.4%

3.25 2.0 85.4 69.8 77.6 5.05E-05 7.8%

3.75 2.0 57.0 25.7 41.4 2.69E-05 4.1%

4.25 2.0 48.0 25.7 36.9 2.40E-05 3.7%

4.75 1.0 25.8 25.8 25.8 1.68E-05 2.6%

5.25 NR NR NR 25.1 1.63E-05 2.5%

5.75 NR NR NR 24.3 1.58E-05 2.4%

6.25 NR NR NR 23.6 1.53E-05 2.4%

6.75 NR NR NR 22.8 1.49E-05 2.3%

7.25 NR NR NR 22.1 1.44E-05 2.2%

7.75 NR NR NR 21.4 1.39E-05 2.1%

8.25 NR NR NR 20.7 1.35E-05 2.1%

8.75 NR NR NR 20.0 1.30E-05 2.0%

9.25 NR NR NR 19.3 1.25E-05 1.9%

9.75 1.0 19.4 19.4 19.4 1.26E-05 1.9%

10.25 1.0 14.0 14.0 14.0 9.13E-06 1.4%

10.75 1.0 11.8 11.8 11.8 7.70E-06 1.2%

11.25 1.0 8.8 8.8 8.8 5.70E-06 0.9%

11.75 1.0 9.3 9.3 9.3 6.07E-06 0.9%

12.25 1.0 10.1 10.1 10.1 6.59E-06 1.0%

12.75 1.0 4.8 4.8 4.8 3.14E-06 0.5%

13.25 1.0 5.5 5.5 5.5 3.58E-06 0.5%

13.75 1.0 3.1 3.1 3.1 1.99E-06 0.3%

Total 6.5E-04 1.000 Note: Highlighted results are estimated based on moving average like the trend line of Figure 36.

As seen in Figure 22, the wall Eu-152 concentrations are lower than the floor. Use of this data along with Equation 1 calculated masses leads to the source term estimate in Table 37.

TSD 13-006 Revision 0 Page 68 of 200 Table 37 - Unit 1 Incore Wall Eu-152 Profile Using Wall Core U1 542 ft Wall Eu-152 Summary Decayed To 1/1/13 Depth Wall Eu-152 pCi/g Source Term Wall Eu-152 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 56.7 3.15E-04 12%

102.5 103 2.311E+06 5.557E+06 0.75 50.8 2.84E-04 11%

103 103.5 2.322E+06 5.584E+06 1.25 81.3 4.56E-04 18%

103.5 104 2.333E+06 5.611E+06 1.75 79.5 4.48E-04 17%

104 104.5 2.345E+06 5.638E+06 2.25 70.5 3.99E-04 16%

104.5 105 2.356E+06 5.665E+06 2.75 62.0 3.53E-04 14%

105 105.5 2.367E+06 5.692E+06 3.25 54.0 3.09E-04 12%

105.5 106 2.378E+06 5.719E+06 Total 2.56E-03 100%

The floor concentrations can be used in order to provide a conservative estimate of the Eu-152 source term in the Incore wall as shown in Table 38. As seen in Figure 37using the floor the average floor concentrations times the Eu-152 adjustment factor in Table 28 provides conservative basis for estimating the Eu-152 source term in the Incore walls under vessel.

Figure 37 - U1 Eu-152 Incore Wall Profile Actual versus Worst Case The floor concentrations with depth can be used in order to provide a conservative estimate of the Eu-152 in the wall.

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 0

5 10 15 pCi/g Depth Inches U1 Incore Eu-152 Concentration Wall Wall Eu-152 pCi/g Worst Case Wall Eu-152 pCi/g

TSD 13-006 Revision 0 Page 69 of 200 Table 38 - Unit 1 Incore Wall Eu-152 Profile Using Floor Concentrations U1 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Eu-152 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Eu-152 Ci 0.25 81.9 102.5 103 2.311E+06 5.557E+06 4.6E-04 0.75 99.2 103 103.5 2.322E+06 5.584E+06 5.5E-04 1.25 117.2 103.5 104 2.333E+06 5.611E+06 6.6E-04 1.75 112.3 104 104.5 2.345E+06 5.638E+06 6.3E-04 2.25 110.9 104.5 105 2.356E+06 5.665E+06 6.3E-04 2.75 111.5 105 105.5 2.367E+06 5.692E+06 6.3E-04 3.25 92.2 105.5 106 2.378E+06 5.719E+06 5.3E-04 3.75 49.2 106 106.5 2.390E+06 5.746E+06 2.8E-04 4.25 43.8 106.5 107 2.401E+06 5.773E+06 2.5E-04 4.75 30.6 107 107.5 2.412E+06 5.800E+06 1.8E-04 5.25 29.8 107.5 108 2.423E+06 5.827E+06 1.7E-04 5.75 28.8 108 108.5 2.434E+06 5.854E+06 1.7E-04 6.25 28.0 108.5 109 2.446E+06 5.881E+06 1.6E-04 6.75 27.1 109 109.5 2.457E+06 5.908E+06 1.6E-04 7.25 26.3 109.5 110 2.468E+06 5.935E+06 1.6E-04 7.75 25.4 110 110.5 2.479E+06 5.962E+06 1.5E-04 8.25 24.6 110.5 111 2.491E+06 5.990E+06 1.5E-04 8.75 23.7 111 111.5 2.502E+06 6.017E+06 1.4E-04 9.25 22.9 111.5 112 2.513E+06 6.044E+06 1.4E-04 9.75 23.0 112 112.5 2.524E+06 6.071E+06 1.4E-04 10.25 16.7 112.5 113 2.536E+06 6.098E+06 1.0E-04 10.75 14.1 113 113.5 2.547E+06 6.125E+06 8.6E-05 11.25 10.4 113.5 114 2.558E+06 6.152E+06 6.4E-05 11.75 11.1 114 114.5 2.569E+06 6.179E+06 6.9E-05 12.25 12.0 114.5 115 2.581E+06 6.206E+06 7.5E-05 12.75 5.7 115 115.5 2.592E+06 6.233E+06 3.6E-05 13.25 6.5 115.5 116 2.603E+06 6.260E+06 4.1E-05 13.75 3.6 116 116.5 2.614E+06 6.287E+06 2.3E-05 Total 6.8E-03 The Eu-154 profile is similar to the Eu-152 profile and a moving average was used to estimate the concentration for the pucks between 5 and 9.5 inches. The Eu-154 graph is provided in Figure 38.

TSD 13-006 Revision 0 Page 70 of 200 Figure 38 - U1 Eu-154 Data with Moving Average Trend Line Estimated Concentrations The U1 Eu-154 Incore floor source term profile is provided in Table 39. The 0 - 3.5 profile contains 63.5% of the source term.

Table 39 - Unit 1 Incore Floor Eu-154 Profile U1 542 ft Floor Eu-154 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Eu-154 pCi/g Min.

Eu-154 pCi/g Avg.

Eu-154 pCi/g Source Term Floor Eu-154 Ci Source Term Distribution Floor 0.25 2.0 5.4 4.8 5.1 3.31E-06 9.7%

0.75 2.0 5.8 2.8 4.3 2.79E-06 8.2%

1.25 2.0 6.2 5.4 5.8 3.77E-06 11.0%

1.75 2.0 6.1 4.1 5.1 3.32E-06 9.7%

2.25 2.0 5.6 5.1 5.3 3.48E-06 10.2%

2.75 2.0 5.0 4.4 4.7 3.07E-06 9.0%

3.25 2.0 3.7 2.3 3.0 1.97E-06 5.8%

3.75 2.0 2.9 1.3 2.1 1.37E-06 4.0%

4.25 2.0 1.3 0.6 0.9 6.05E-07 1.8%

4.75 1.0 1.3 1.3 1.3 8.56E-07 2.5%

5.25 NR NR NR 1.3 8.23E-07 2.4%

5.75 NR NR NR 1.2 7.91E-07 2.3%

6.25 NR NR NR 1.2 7.58E-07 2.2%

6.75 NR NR NR 1.1 7.25E-07 2.1%

7.25 NR NR NR 1.1 6.93E-07 2.0%

7.75 NR NR NR 1.0 6.60E-07 1.9%

0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 0

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 pCi/g Depth inches U1 Incore Eu-154 Avg Concentration Floor Avg.

Eu-154 pCi/g

TSD 13-006 Revision 0 Page 71 of 200 U1 542 ft Floor Eu-154 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Eu-154 pCi/g Min.

Eu-154 pCi/g Avg.

Eu-154 pCi/g Source Term Floor Eu-154 Ci Source Term Distribution Floor 8.25 NR NR NR 1.0 6.27E-07 1.8%

8.75 NR NR NR 0.9 5.95E-07 1.7%

9.25 NR NR NR 0.9 5.62E-07 1.6%

9.75 1.0 0.9 0.9 0.9 5.62E-07 1.6%

10.25 1.0 0.7 0.7 0.7 4.87E-07 1.4%

10.75 1.0 0.7 0.7 0.7 4.64E-07 1.4%

11.25 1.0 0.5 0.5 0.5 3.31E-07 1.0%

11.75 1.0 0.5 0.5 0.5 3.08E-07 0.9%

12.25 1.0 0.7 0.7 0.7 4.57E-07 1.3%

12.75 1.0 0.4 0.4 0.4 2.52E-07 0.7%

13.25 1.0 0.5 0.5 0.5 3.33E-07 1.0%

13.75 1.0 0.3 0.3 0.3 2.17E-07 0.6%

Total 3.42E-05 100%

Note: Highlighted results are estimated based on moving average like the trend line of Figure 38 As seen in Figure 25, the wall Eu-154 concentrations are lower than the floor. Use of this data along with Equation 1 calculated the Table 40 masses leads to the source term estimate in Table

40.

Table 40 - Unit 1 Incore Wall Eu-154 Profile Using Wall Core U1 542 ft Wall Eu-154 Summary Decayed To 1/1/13 Depth Wall Eu-154 pCi/g Source Term Wall Eu-154 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 4.2 2.32E-05 16%

102.5 103 2.311E+06 5.557E+06 0.75 2.8 1.56E-05 11%

103 103.5 2.322E+06 5.584E+06 1.25 4.6 2.60E-05 18%

103.5 104 2.333E+06 5.611E+06 1.75 4.5 2.55E-05 18%

104 104.5 2.345E+06 5.638E+06 2.25 3.6 2.04E-05 14%

104.5 105 2.356E+06 5.665E+06 2.75 3.5 1.97E-05 14%

105 105.5 2.367E+06 5.692E+06 3.25 2.6 1.47E-05 10%

105.5 106 2.378E+06 5.719E+06 Total 1.45E-04 100%

The floor concentrations can be used in order to provide a conservative estimate of the Eu-154 source term in the Incore wall as shown in Table 41. As seen in Figure 39, using the floor the average floor concentrations times the Eu-154 adjustment factor in Table 28 provides conservative basis for estimating the Eu-154 source term in the Incore walls under vessel.

TSD 13-006 Revision 0 Page 72 of 200 Figure 39 - U1 Eu-154 Incore Wall Profile Actual versus Worst Case The floor concentrations with depth can be used in order to provide a conservative estimate of the Eu-154 in the wall as seen in Table 41.

Table 41 - Unit 1 Incore Wall Eu-154 Profile Using Floor Concentrations U1 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Eu-154 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Eu-154 Ci 0.25 6.3 102.5 103 2.311E+06 5.557E+06 3.5E-05 0.75 5.3 103 103.5 2.322E+06 5.584E+06 3.0E-05 1.25 7.1 103.5 104 2.333E+06 5.611E+06 4.0E-05 1.75 6.3 104 104.5 2.345E+06 5.638E+06 3.6E-05 2.25 6.6 104.5 105 2.356E+06 5.665E+06 3.7E-05 2.75 5.8 105 105.5 2.367E+06 5.692E+06 3.3E-05 3.25 3.7 105.5 106 2.378E+06 5.719E+06 2.1E-05 3.75 2.6 106 106.5 2.390E+06 5.746E+06 1.5E-05 4.25 1.1 106.5 107 2.401E+06 5.773E+06 6.6E-06 4.75 1.6 107 107.5 2.412E+06 5.800E+06 9.4E-06 5.25 1.6 107.5 108 2.423E+06 5.827E+06 9.1E-06 5.75 1.5 108 108.5 2.434E+06 5.854E+06 8.8E-06 6.25 1.4 108.5 109 2.446E+06 5.881E+06 8.5E-06 6.75 1.4 109 109.5 2.457E+06 5.908E+06 8.1E-06 7.25 1.3 109.5 110 2.468E+06 5.935E+06 7.8E-06 7.75 1.3 110 110.5 2.479E+06 5.962E+06 7.5E-06 8.25 1.2 110.5 111 2.491E+06 5.990E+06 7.1E-06 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 0

5 10 15 pCi/g Depth Inches U1 Incore Eu-154 Concentration Wall Wall Eu-154 pCi/g Worst Case Wall Eu-154 pCi/g

TSD 13-006 Revision 0 Page 73 of 200 U1 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Eu-154 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Eu-154 Ci 8.75 1.1 111 111.5 2.502E+06 6.017E+06 6.8E-06 9.25 1.1 111.5 112 2.513E+06 6.044E+06 6.4E-06 9.75 1.1 112 112.5 2.524E+06 6.071E+06 6.5E-06 10.25 0.9 112.5 113 2.536E+06 6.098E+06 5.6E-06 10.75 0.9 113 113.5 2.547E+06 6.125E+06 5.4E-06 11.25 0.6 113.5 114 2.558E+06 6.152E+06 3.9E-06 11.75 0.6 114 114.5 2.569E+06 6.179E+06 3.6E-06 12.25 0.9 114.5 115 2.581E+06 6.206E+06 5.4E-06 12.75 0.5 115 115.5 2.592E+06 6.233E+06 3.0E-06 13.25 0.6 115.5 116 2.603E+06 6.260E+06 4.0E-06 13.75 0.4 116 116.5 2.614E+06 6.287E+06 2.6E-06 Total 3.7E-04 The calculated Unit 1 541.5 foot elevation floor source terms and their profiles are summarized in Table 42. Since Cs-137 in the first half inch of the floor is a couple of orders of magnitude higher than the Cs-134, Eu-152 and Eu-154 the first half inch of the Unit 1 floor contains 62%

of the source term in the floor.

Table 42 - Summary of Calculated Unit 1 Incore Under Vessel Floor Source Terms Avg Depth in Source Term Floor Co-60 Ci Source Term Floor Cs-137 Ci Source Term Floor Cs-134 Ci Source Term Floor Eu-152 Ci Source Term Floor Eu-154 Ci Total Ci

% Total 0.25 9.5E-05 6.5E-04 5.4E-07 4.5E-05 3.3E-06 8.0E-04 43%

0.75 9.1E-06 2.1E-06 2.6E-07 5.4E-05 2.8E-06 6.8E-05 4%

1.25 8.8E-06 1.6E-06 3.2E-07 6.4E-05 3.8E-06 7.9E-05 4%

1.75 7.6E-06 2.4E-06 2.7E-07 6.1E-05 3.3E-06 7.5E-05 4%

2.25 7.5E-06 1.6E-06 2.8E-07 6.1E-05 3.5E-06 7.4E-05 4%

2.75 8.4E-06 1.8E-06 2.8E-07 6.1E-05 3.1E-06 7.5E-05 4%

3.25 7.6E-06 1.5E-06 2.4E-07 5.0E-05 2.0E-06 6.2E-05 3%

3.75 5.9E-06 8.5E-06 1.7E-07 2.7E-05 1.4E-06 4.3E-05 2%

4.25 5.9E-06 8.5E-06 1.6E-07 2.4E-05 6.0E-07 3.9E-05 2%

4.75 6.6E-06 1.3E-05 2.8E-07 1.7E-05 8.6E-07 3.8E-05 2%

5.25 4.2E-06 2.4E-05 2.0E-07 1.6E-05 8.2E-07 4.6E-05 2%

5.75 3.1E-06 2.0E-05 2.6E-07 1.6E-05 7.9E-07 4.0E-05 2%

6.25 2.5E-06 3.1E-05 1.7E-07 1.5E-05 7.6E-07 4.9E-05 3%

6.75 3.2E-06 2.6E-05 2.6E-07 1.5E-05 7.3E-07 4.5E-05 2%

7.25 2.2E-06 3.2E-05 1.9E-07 1.4E-05 6.9E-07 4.9E-05 3%

7.75 1.4E-06 3.3E-05 2.0E-07 1.4E-05 6.6E-07 4.9E-05 3%

TSD 13-006 Revision 0 Page 74 of 200 Avg Depth in Source Term Floor Co-60 Ci Source Term Floor Cs-137 Ci Source Term Floor Cs-134 Ci Source Term Floor Eu-152 Ci Source Term Floor Eu-154 Ci Total Ci

% Total 8.25 1.3E-06 3.7E-05 1.6E-07 1.3E-05 6.3E-07 5.2E-05 3%

8.75 1.3E-06 3.0E-05 1.7E-07 1.3E-05 5.9E-07 4.5E-05 2%

9.25 7.8E-07 2.3E-05 1.1E-07 1.3E-05 5.6E-07 3.7E-05 2%

9.75 1.8E-06 4.8E-07 1.7E-07 1.3E-05 5.6E-07 1.6E-05 0.8%

10.25 1.5E-06 4.6E-07 1.1E-07 9.1E-06 4.9E-07 1.2E-05 0.6%

10.75 1.2E-06 5.0E-07 1.3E-07 7.7E-06 4.6E-07 1.0E-05 0.5%

11.25 1.3E-06 8.4E-07 9.8E-08 5.7E-06 3.3E-07 8.2E-06 0.4%

11.75 1.9E-06 1.0E-06 1.2E-07 6.1E-06 3.1E-07 9.4E-06 0.5%

12.25 1.3E-06 7.5E-07 1.4E-07 6.6E-06 4.6E-07 9.3E-06 0.5%

12.75 8.1E-07 7.1E-07 7.2E-08 3.1E-06 2.5E-07 5.0E-06 0.3%

13.25 1.0E-06 7.5E-07 1.1E-07 3.6E-06 3.3E-07 5.8E-06 0.3%

13.75 7.8E-07 8.6E-07 7.4E-08 2.0E-06 2.2E-07 3.9E-06 0.2%

14.25 NR NR 7.4E-08 NR NR 7.4E-08 0.00%

14.75 NR NR 6.6E-08 NR NR 6.6E-08 0.00%

15.25 NR NR 5.8E-08 NR NR 5.8E-08 0.003%

15.75 NR NR 5.0E-08 NR NR 5.0E-08 0.003%

16.25 NR NR 4.2E-08 NR NR 4.2E-08 0.002%

16.75 NR NR 3.4E-08 NR NR 3.4E-08 0.002%

17.25 NR NR 2.6E-08 NR NR 2.6E-08 0.001%

17.75 NR NR 1.8E-08 NR NR 1.8E-08 0.001%

18.25 NR NR 1.0E-08 NR NR 1.0E-08 0.001%

18.75 NR NR 2.3E-09 NR NR 2.3E-09 0.000%

Total Ci 1.9E-04 9.6E-04 5.9E-06 6.5E-04 3.4E-05 1.84E-03 100%

% Total 11%

52%

0%

35%

2%

100%

Table 43 summarizes the calculated Incore wall gamma emitter source terms which are not dominated by the source terms at the shallow depths even though the wall graphs show the concentrations dropping with depth. This is because the mass of the 1/2 inch slice of the cylinder wall increases as the radius inner radius increases with depth.

Table 43 - Summary of Calculated Unit 1 Incore Under Vessel Wall Source Terms Avg Depth in Wall Source Term Using Floor Data Co-60 Ci Wall Source Term Using Floor Data Cs-137 Ci Wall Source Term Using Floor Data Cs-134 Ci Wall Source Term Using Floor Data Eu-152 Ci Wall Source Term Using Floor Data Eu-154 Ci Total Ci

% Total 0.25 1.3E-04 2.3E-04 4.6E-06 4.6E-04 3.5E-05 8.6E-04 8%

0.75 7.7E-05 1.8E-05 2.2E-06 5.5E-04 3.0E-05 6.8E-04 6%

1.25 6.9E-05 1.4E-05 2.8E-06 6.6E-04 4.0E-05 7.8E-04 7%

1.75 6.5E-05 2.1E-05 2.3E-06 6.3E-04 3.6E-05 7.6E-04 7%

TSD 13-006 Revision 0 Page 75 of 200 Avg Depth in Wall Source Term Using Floor Data Co-60 Ci Wall Source Term Using Floor Data Cs-137 Ci Wall Source Term Using Floor Data Cs-134 Ci Wall Source Term Using Floor Data Eu-152 Ci Wall Source Term Using Floor Data Eu-154 Ci Total Ci

% Total 2.25 6.4E-05 1.4E-05 2.5E-06 6.3E-04 3.7E-05 7.5E-04 7%

2.75 6.6E-05 1.6E-05 2.5E-06 6.3E-04 3.3E-05 7.5E-04 7%

3.25 6.1E-05 1.3E-05 2.1E-06 5.3E-04 2.1E-05 6.2E-04 6%

3.75 5.2E-05 7.5E-05 1.5E-06 2.8E-04 1.5E-05 4.3E-04 4%

4.25 5.2E-05 7.5E-05 1.4E-06 2.5E-04 6.6E-06 3.9E-04 3%

4.75 5.9E-05 1.2E-04 2.5E-06 1.8E-04 9.4E-06 3.7E-04 3%

5.25 3.8E-05 2.2E-04 1.8E-06 1.7E-04 9.1E-06 4.4E-04 4%

5.75 2.8E-05 1.8E-04 2.3E-06 1.7E-04 8.8E-06 3.9E-04 3%

6.25 2.3E-05 2.8E-04 1.6E-06 1.6E-04 8.5E-06 4.7E-04 4%

6.75 2.9E-05 2.4E-04 2.3E-06 1.6E-04 8.1E-06 4.4E-04 4%

7.25 2.0E-05 2.9E-04 1.8E-06 1.6E-04 7.8E-06 4.7E-04 4%

7.75 1.3E-05 3.0E-04 1.8E-06 1.5E-04 7.5E-06 4.8E-04 4%

8.25 1.2E-05 3.4E-04 1.5E-06 1.5E-04 7.1E-06 5.1E-04 4%

8.75 1.2E-05 2.8E-04 1.6E-06 1.4E-04 6.8E-06 4.4E-04 4%

9.25 7.2E-06 2.1E-04 1.1E-06 1.4E-04 6.4E-06 3.6E-04 3%

9.75 1.7E-05 4.5E-06 1.6E-06 1.4E-04 6.5E-06 1.7E-04 1.5%

10.25 1.5E-05 4.4E-06 1.0E-06 1.0E-04 5.6E-06 1.3E-04 1.1%

10.75 1.1E-05 4.7E-06 1.2E-06 8.6E-05 5.4E-06 1.1E-04 1.0%

11.25 1.2E-05 7.9E-06 9.2E-07 6.4E-05 3.9E-06 8.9E-05 0.8%

11.75 1.8E-05 9.8E-06 1.2E-06 6.9E-05 3.6E-06 1.0E-04 0.9%

12.25 1.3E-05 7.1E-06 1.3E-06 7.5E-05 5.4E-06 1.0E-04 0.9%

12.75 7.7E-06 6.8E-06 6.9E-07 3.6E-05 3.0E-06 5.4E-05 0.5%

13.25 1.0E-05 7.2E-06 1.0E-06 4.1E-05 4.0E-06 6.3E-05 0.6%

13.75 7.5E-06 8.3E-06 7.1E-07 2.3E-05 2.6E-06 4.2E-05 0.4%

14.25 NR NR 7.2E-07 NR NR 7.2E-07 0.01%

14.75 NR NR 6.4E-07 NR NR 6.4E-07 0.01%

15.25 NR NR 5.7E-07 NR NR 5.7E-07 0.01%

15.75 NR NR 4.9E-07 NR NR 4.9E-07 0.004%

16.25 NR NR 4.2E-07 NR NR 4.2E-07 0.004%

16.75 NR NR 3.4E-07 NR NR 3.4E-07 0.003%

17.25 NR NR 2.6E-07 NR NR 2.6E-07 0.002%

17.75 NR NR 1.8E-07 NR NR 1.8E-07 0.002%

18.25 NR NR 1.0E-07 NR NR 1.0E-07 0.001%

Total Ci 9.9E-04 3.0E-03 5.4E-05 6.8E-03 3.7E-04 1.1E-02 100%

% Total 9%

27%

0%

61%

3%

100%

TSD 13-006 Revision 0 Page 76 of 200 There are several things worth noting with regard to the activated concrete in the Unit 1 Incore Under Vessel Area. As seen in Table 42 and Table 59 the 541.5 foot floor source term is dominated by the Cs-137 in the first half inch. In Unit 1, the first half inch contains 43% of all the source term and Cs-137 is 52% of the overall source term. Also, the total activity of the gamma emitter source term is 1.84E-3 Ci. The wall source term is dominated by Eu-152 which accounts for 61% of the calculated source term. Due to the larger amount of concrete mass corresponding to each 1/2 inch puck section in the Incore wall, the estimated source term of the Incore wall exceeds that of the floor at 1.1E-2 Ci. Thus the Incore area total activity (floor and wall) of 0.012 Ci is insignificant in comparison to the 568 elevation estimated 7.00 Ci shown in Table 10. Finally the 541.5 foot elevation floor is 30 inches thick and rests on the Containment liner. As opposed to Maine Yankee, Connecticut Yankee, and Rancho Seco which had one foot thick or less concrete floors inside the liner. In addition, these facilities had no concrete on the interior wall of the Incore area. Thus there was no neutron attenuation prior to the liners on the walls and floor activation extended into and past the liner as well. As seen in the graphs for the Zion Unit 1 activation profiles, there is very little probability of any significant activation of the steel liner or the concrete outside the liner at Zion due to the shielding afforded by 231/2 inch thick Incore concrete walls and the 30 inch thick floor inside the liner.

3.8.

Unit 2 Average Concentrations and Source Terms for 541.5 Foot Incore Area The Unit 2 14 inch center core under the vessel remained intact and thus interpolation of the data is not required. The Co-60 concentrations with depth exhibit a downward trend as would be expected where neutron activation is the predominant source of the activity as seen in Figure

40.

Figure 40 - Unit 2 Incore Floor Average Co-60 Concentrations 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 0

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 pCi/g Depth Inches U2 Incore Co-60 Avg Concentration Floor Avg. Co-60 pCi/g

TSD 13-006 Revision 0 Page 77 of 200 The Unit 2 Co-60 source term profile of the Incore floor is shown in Table 44.

Table 44 - Unit 2 Incore Floor Co-60 Profile U2 542 ft Floor Co-60 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Co-60 pCi/g Min.

Co-60 pCi/g Avg.

Co-60 pCi/g Source Term Floor Co-60 Ci Source Term Distribution Floor 0.25 2.0 23.0 14.3 18.7 1.2E-05 7.8%

0.75 2.0 21.5 15.4 18.4 1.2E-05 7.7%

1.25 2.0 18.9 17.8 18.3 1.2E-05 7.7%

1.75 2.0 23.6 14.3 19.0 1.2E-05 7.9%

2.25 2.0 20.7 14.1 17.4 1.1E-05 7.3%

2.75 2.0 15.5 12.5 14.0 9.1E-06 5.9%

3.25 2.0 16.1 11.6 13.8 9.0E-06 5.8%

3.75 2.0 14.0 11.5 12.7 8.3E-06 5.3%

4.25 2.0 15.8 12.9 14.4 9.3E-06 6.0%

4.75 2.0 20.4 8.7 14.5 9.5E-06 6.1%

5.25 1.0 13.0 3.1 13.0 8.5E-06 5.4%

5.75 1.0 9.6 9.6 9.6 6.2E-06 4.0%

6.25 1.0 7.8 7.8 7.8 5.0E-06 3.2%

6.75 1.0 10.0 10.0 10.0 6.5E-06 4.2%

7.25 1.0 6.8 6.8 6.8 4.4E-06 2.8%

7.75 1.0 4.4 4.4 4.4 2.8E-06 1.8%

8.25 1.0 4.1 4.1 4.1 2.7E-06 1.7%

8.75 1.0 4.0 4.0 4.0 2.6E-06 1.7%

9.25 1.0 2.4 2.4 2.4 1.6E-06 1.0%

9.75 1.0 2.6 2.6 2.6 1.7E-06 1.1%

10.25 1.0 2.6 2.6 2.6 1.7E-06 1.1%

10.75 1.0 2.6 2.6 2.6 1.7E-06 1.1%

11.25 1.0 1.4 1.4 1.4 9.2E-07 0.6%

11.75 1.0 3.5 3.5 3.5 2.2E-06 1.4%

12.25 1.0 1.2 1.2 1.2 8.0E-07 0.5%

12.75 1.0 0.6 0.6 0.6 4.2E-07 0.3%

13.25 1.0 0.5 0.5 0.5 3.0E-07 0.2%

13.75 1.0 0.5 0.5 0.5 3.1E-07 0.2%

Total 1.6E-04 1.00 As seen in Figure 13, the wall Co-60 concentrations are lower than the floor and the wall profile only extends to 3.25 inches. Because the Co-60 concentration does not approach zero at this depth, use of this data along with Equation 1 masses leads to the source term estimate in Table 45.

TSD 13-006 Revision 0 Page 78 of 200 Table 45 - Unit 2 Incore Wall Co-60 Profile Using Wall Core U2 542 ft Wall Co-60 Summary Decayed To 1/1/13 Depth Wall Co-60 pCi/g Source Term Wall Co-60 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 13.3 7.40E-05 58%

102.5 103 2310801 5556856 0.75 16.6 1.08E-05 8%

103 103.5 2322046 5583897 1.25 12.9 8.41E-06 7%

103.5 104 2333291 5610937 1.75 10.2 6.66E-06 5%

104 104.5 2344536 5637978 2.25 7.6 4.92E-06 4%

104.5 105 2355781 5665019 2.75 10.3 6.70E-06 5%

105 105.5 2367025 5692059 3.25 9.7 6.33E-06 5%

105.5 106 2378270 5719100 3.75 4.6 2.98E-06 2%

106 106.5 2389515 5746141 4.25 4.9 3.22E-06 3%

106.5 107 2400760 5773181 4.75 3.8 2.46E-06 2%

107 107.5 2412004 5800222 5.25 3.1 2.01E-06 2%

107.5 108 2423249 5827263 Total 1.28E-04 100%

The floor concentrations with depth can be used in order to provide a conservative estimate of the Co-60 source term in the Incore wall as shown in Table 46. As seen in Figure 41, using the average floor concentrations provides conservative basis for estimating the Co-60 source term in the Incore walls under vessel.

Figure 41 - U2 Co-60 Incore Wall Profile Actual versus Worst Case 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 0

5 10 15 pCi/g Depth Inches U2 Incore Co-60 Concentration Wall Wall Co-60 pCi/g Worst Case Wall Co-60 pCi/g

TSD 13-006 Revision 0 Page 79 of 200 The wall Co-60 source term profile using the floor concentrations and the calculated concrete masses from Equation 1 are shown in Table 46.

Table 46 - Unit 2 Incore Wall Co-60 Profile Using Floor Concentrations U2 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Co-60 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Co-60 Ci 0.25 18.7 102.5 103 2.311E+06 5.557E+06 1.0E-04 0.75 18.4 103 103.5 2.322E+06 5.584E+06 1.0E-04 1.25 18.3 103.5 104 2.333E+06 5.611E+06 1.0E-04 1.75 19.0 104 104.5 2.345E+06 5.638E+06 1.1E-04 2.25 17.4 104.5 105 2.356E+06 5.665E+06 9.9E-05 2.75 14.0 105 105.5 2.367E+06 5.692E+06 8.0E-05 3.25 13.8 105.5 106 2.378E+06 5.719E+06 7.9E-05 3.75 12.7 106 106.5 2.390E+06 5.746E+06 7.3E-05 4.25 14.4 106.5 107 2.401E+06 5.773E+06 8.3E-05 4.75 14.5 107 107.5 2.412E+06 5.800E+06 8.4E-05 5.25 13.0 107.5 108 2.423E+06 5.827E+06 7.6E-05 5.75 9.6 108 108.5 2.434E+06 5.854E+06 5.6E-05 6.25 7.8 108.5 109 2.446E+06 5.881E+06 4.6E-05 6.75 10.0 109 109.5 2.457E+06 5.908E+06 5.9E-05 7.25 6.8 109.5 110 2.468E+06 5.935E+06 4.0E-05 7.75 4.4 110 110.5 2.479E+06 5.962E+06 2.6E-05 8.25 4.1 110.5 111 2.491E+06 5.990E+06 2.5E-05 8.75 4.0 111 111.5 2.502E+06 6.017E+06 2.4E-05 9.25 2.4 111.5 112 2.513E+06 6.044E+06 1.4E-05 9.75 2.6 112 112.5 2.524E+06 6.071E+06 1.6E-05 10.25 2.6 112.5 113 2.536E+06 6.098E+06 1.6E-05 10.75 2.6 113 113.5 2.547E+06 6.125E+06 1.6E-05 11.25 1.4 113.5 114 2.558E+06 6.152E+06 8.7E-06 11.75 3.5 114 114.5 2.569E+06 6.179E+06 2.1E-05 12.25 1.2 114.5 115 2.581E+06 6.206E+06 7.6E-06 12.75 0.6 115 115.5 2.592E+06 6.233E+06 4.0E-06 13.25 0.5 115.5 116 2.603E+06 6.260E+06 2.9E-06 13.75 0.5 116 116.5 2.614E+06 6.287E+06 2.9E-06 Total 1.4E-03 As seen in Figure 42, the Unit 2 Cs-137 concentrations are much higher in the first half inch than in the rest of the profile.

TSD 13-006 Revision 0 Page 80 of 200 Figure 42 - Unit 2 Incore Floor Average Cs-137 Concentrations The Unit 2 Incore Floor Cs-137 results shown in Figure 43 with the first two pucks data eliminated indicates that at depth concentrations peak at around the 8 to 9 inches. This is similar to the patter evidence by the discontinuous Unit 1 core as seen in Figure 14.

Figure 43 - Unit 2 Incore Floor Average Cs-137 Concentrations At Greater Than 1 Inch The Unit 2 Cs-137 source term profile of the Incore floor is shown in Table 47.

0.0 50.0 100.0 150.0 200.0 250.0 300.0 350.0 0

5 10 15 pCi/g Depth Inches U2 Incore Cs-137 Avg Concentration Floor Avg. Cs-137 pCi/g 0.0 0.5 1.0 1.5 2.0 2.5 0

5 10 15 pCi/g Depth Inches U2 Incore Cs-137 Avg Concentration Floor After 1 Inch Avg. Cs-137 pCi/g

TSD 13-006 Revision 0 Page 81 of 200 Table 47 - Unit 2 Incore Floor Cs-137 Profile U2 542 ft Floor Cs-137 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-137 pCi/g Min.

Cs-137 pCi/g Avg.

Cs-137 pCi/g Source Term Floor Cs-137 Ci Source Term Distribution Floor 0.25 2.0 577.0 13.0 295.0 1.9E-04 88.1%

0.75 2.0 25.0 0.3 12.7 8.24E-06 3.8%

1.25 2.0 0.6 0.4 0.5 3.18E-07 0.1%

1.75 2.0 0.7 0.5 0.6 3.97E-07 0.2%

2.25 2.0 0.6 0.5 0.6 3.80E-07 0.2%

2.75 2.0 0.5 0.4 0.4 2.87E-07 0.1%

3.25 2.0 0.7 0.6 0.7 4.23E-07 0.2%

3.75 2.0 0.7 0.6 0.7 4.39E-07 0.2%

4.25 2.0 1.0 0.4 0.7 4.55E-07 0.2%

4.75 2.0 1.1 0.5 0.8 4.97E-07 0.2%

5.25 1.0 1.4 1.4 1.4 9.06E-07 0.4%

5.75 1.0 1.2 1.2 1.2 7.63E-07 0.4%

6.25 1.0 1.8 1.8 1.8 1.16E-06 0.5%

6.75 1.0 1.5 1.5 1.5 9.88E-07 0.5%

7.25 1.0 1.8 1.8 1.8 1.20E-06 0.5%

7.75 1.0 1.9 1.9 1.9 1.25E-06 0.6%

8.25 1.0 2.1 2.1 2.1 1.38E-06 0.6%

8.75 1.0 1.8 1.8 1.8 1.14E-06 0.5%

9.25 1.0 1.3 1.3 1.3 8.57E-07 0.4%

9.75 1.0 1.0 1.0 1.0 6.68E-07 0.3%

10.25 1.0 0.8 0.8 0.8 5.24E-07 0.2%

10.75 1.0 1.0 1.0 1.0 6.35E-07 0.3%

11.25 1.0 1.0 1.0 1.0 6.32E-07 0.3%

11.75 1.0 0.6 0.6 0.6 3.88E-07 0.2%

12.25 1.0 0.9 0.9 0.9 6.16E-07 0.3%

12.75 1.0 0.7 0.7 0.7 4.40E-07 0.2%

13.25 1.0 0.8 0.8 0.8 5.43E-07 0.2%

13.75 1.0 0.7 0.7 0.7 4.81E-07 0.2%

Total 2.2E-04 100%

As seen in Figure 16, the wall Cs-137 concentrations are lower than the floor and the wall profile only extends to 3.25 inches. Because the Cs-137 concentration does not approach zero at this depth, use of this data along with Equation 1 calculated masses leads to the source term estimate in Table 48.

TSD 13-006 Revision 0 Page 82 of 200 Table 48 - Unit 2 Incore Wall Cs-137 Profile Using Wall Core U2 542 ft Wall Cs-137 Summary Decayed To 1/1/13 Depth Wall Cs-137 pCi/g Source Term Wall Cs-137 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 40.6 2.26E-04 88%

102.5 103 2310801 5556856 0.75 1.5 8.54E-06 3%

103 103.5 2322046 5583897 1.25 0.6 3.16E-06 1%

103.5 104 2333291 5610937 1.75 0.4 2.26E-06 1%

104 104.5 2344536 5637978 2.25 0.4 2.40E-06 1%

104.5 105 2355781 5665019 2.75 0.4 2.25E-06 1%

105 105.5 2367025 5692059 3.25 0.4 2.40E-06 1%

105.5 106 2378270 5719100 3.75 0.3 1.99E-06 1%

106 106.5 2389515 5746141 4.25 0.2 1.36E-06 1%

106.5 107 2400760 5773181 4.75 0.4 2.12E-06 1%

107 107.5 2412004 5800222 5.25 0.8 4.85E-06 2%

107.5 108 2423249 5827263 Total 2.57E-04 100%

The floor concentrations can be used in order to provide a conservative estimate of the Cs-137 source term in the Incore wall as shown in Table 49. As seen in Figure 44, using wall core data multiplied by 2 for 0.25 to 5.25 inches and then the average floor concentrations for the depths greater than 5.25 inches provides conservative basis for estimating the Cs-137 source term in the Incore walls under vessel.

Figure 44 - U2 Cs-137 Incore Wall Profile Actual versus Worst Case 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 0

5 10 15 pCi/g Depth Inches U2 Incore Cs-137 Concentration Wall Greater Than 1/2 Inch Wall Cs-137 pCi/g Worst Case Wall Cs-137 pCi/g

TSD 13-006 Revision 0 Page 83 of 200 Using the Figure 29, floor concentrations with depth provides a conservative estimate of the Cs-137 in the wall source term profile, as seen in Table 49.

Table 49 - Unit 2 Incore Wall Cs-137 Profile Using Floor Concentrations U2 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Cs-137 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Cs-137 Ci 0.25 81.2 102.5 103 2.311E+06 5.557E+06 4.5E-04 0.75 3.1 103 103.5 2.322E+06 5.584E+06 1.7E-05 1.25 1.1 103.5 104 2.333E+06 5.611E+06 6.3E-06 1.75 0.8 104 104.5 2.345E+06 5.638E+06 4.5E-06 2.25 0.8 104.5 105 2.356E+06 5.665E+06 4.8E-06 2.75 0.8 105 105.5 2.367E+06 5.692E+06 4.5E-06 3.25 0.8 105.5 106 2.378E+06 5.719E+06 4.8E-06 3.75 0.7 106 106.5 2.390E+06 5.746E+06 4.0E-06 4.25 0.5 106.5 107 2.401E+06 5.773E+06 2.7E-06 4.75 0.7 107 107.5 2.412E+06 5.800E+06 4.2E-06 5.25 1.7 107.5 108 2.423E+06 5.827E+06 9.7E-06 5.75 1.2 108 108.5 2.434E+06 5.854E+06 6.9E-06 6.25 1.8 108.5 109 2.446E+06 5.881E+06 1.0E-05 6.75 1.5 109 109.5 2.457E+06 5.908E+06 9.0E-06 7.25 1.8 109.5 110 2.468E+06 5.935E+06 1.1E-05 7.75 1.9 110 110.5 2.479E+06 5.962E+06 1.1E-05 8.25 2.1 110.5 111 2.491E+06 5.990E+06 1.3E-05 8.75 1.8 111 111.5 2.502E+06 6.017E+06 1.1E-05 9.25 1.3 111.5 112 2.513E+06 6.044E+06 8.0E-06 9.75 1.0 112 112.5 2.524E+06 6.071E+06 6.2E-06 10.25 0.8 112.5 113 2.536E+06 6.098E+06 4.9E-06 10.75 1.0 113 113.5 2.547E+06 6.125E+06 6.0E-06 11.25 1.0 113.5 114 2.558E+06 6.152E+06 6.0E-06 11.75 0.6 114 114.5 2.569E+06 6.179E+06 3.7E-06 12.25 0.9 114.5 115 2.581E+06 6.206E+06 5.9E-06 12.75 0.7 115 115.5 2.592E+06 6.233E+06 4.2E-06 13.25 0.8 115.5 116 2.603E+06 6.260E+06 5.2E-06 13.75 0.7 116 116.5 2.614E+06 6.287E+06 4.7E-06 Total 6.4E-04 The Unit 2 floor Cs-134 concentrations did display a continuous downward trend when the first puck average concentration was eliminated from the data set as seen in Figure 45.

TSD 13-006 Revision 0 Page 84 of 200 Figure 45 - Unit 2 Incore Floor Average Cs-134 Concentrations The additional source term at depths beyond 14 inches is negligible but can be estimated using trend line equation in Figure 45. The estimated Cs-134 source term profile in the Unit 2 floor is shown in Table 50.

Table 50 - Unit 2 Incore Floor Cs-134 Profile U2 542 ft Floor Cs-134 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-134 pCi/g Min.

Cs-134 pCi/g Avg.

Cs-134 pCi/g Source Term Floor Cs-134 Ci Source Term Distribution Floor 0.25 2.0 0.7 0.6 0.6 4.19E-07 6.3%

0.75 2.0 0.7 0.4 0.6 3.72E-07 5.6%

1.25 2.0 0.6 0.6 0.6 3.72E-07 5.6%

1.75 2.0 0.7 0.5 0.6 3.81E-07 5.8%

2.25 2.0 0.6 0.3 0.5 3.03E-07 4.6%

2.75 2.0 0.4 0.3 0.3 2.26E-07 3.4%

3.25 2.0 0.6 0.5 0.6 3.71E-07 5.6%

3.75 2.0 0.5 0.4 0.5 3.09E-07 4.7%

4.25 2.0 0.6 0.4 0.5 3.19E-07 4.8%

4.75 2.0 0.6 0.4 0.5 3.36E-07 5.1%

5.25 1.0 0.4 0.4 0.4 2.47E-07 3.7%

5.75 1.0 0.5 0.5 0.5 3.15E-07 4.8%

6.25 1.0 0.3 0.3 0.3 2.10E-07 3.2%

6.75 1.0 0.5 0.5 0.5 3.11E-07 4.7%

7.25 1.0 0.4 0.4 0.4 2.36E-07 3.6%

7.75 1.0 0.4 0.4 0.4 2.38E-07 3.6%

8.25 1.0 0.3 0.3 0.3 1.93E-07 2.9%

y = -0.036x + 0.6156 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0

5 10 15 pCi/g Depth inches U2 Incore Cs-134 Avg Concentration Floor Avg. Cs-134 pCi/g Linear (Avg. Cs-134 pCi/g)

TSD 13-006 Revision 0 Page 85 of 200 U2 542 ft Floor Cs-134 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Cs-134 pCi/g Min.

Cs-134 pCi/g Avg.

Cs-134 pCi/g Source Term Floor Cs-134 Ci Source Term Distribution Floor 8.75 1.0 0.3 0.3 0.3 2.04E-07 3.1%

9.25 1.0 0.2 0.2 0.2 1.38E-07 2.1%

9.75 1.0 0.3 0.3 0.3 1.65E-07 2.5%

10.25 1.0 0.2 0.2 0.2 1.47E-07 2.2%

10.75 1.0 0.3 0.3 0.3 2.14E-07 3.2%

11.25 1.0 0.2 0.2 0.2 1.06E-07 1.6%

11.75 1.0 0.2 0.2 0.2 1.39E-07 2.1%

12.25 1.0 0.1 0.1 0.1 8.08E-08 1.2%

12.75 1.0 0.2 0.2 0.2 1.20E-07 1.8%

13.25 1.0 0.1 0.1 0.1 8.55E-08 1.3%

13.75 1.0 0.1 0.1 0.1 6.71E-08 1.0%

Total 6.6E-06 100%

As seen in Figure 19, the wall Cs-134 concentrations are lower than the floor and the wall profile only extends to 3.25 inches. Because the Cs-134 concentration does not approach zero at this depth, use of this data along with Equation 1 calculated masses leads to the source term estimate in Table 51.

Table 51 - Unit 2 Incore Wall Cs-134 Profile Using Wall Core U2 542 ft Wall Cs-134 Summary Decayed To 1/1/13 Depth Wall Cs-134 pCi/g Source Term Wall Cs-134 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 0.4 2.02E-06 9%

102.5 103 2310801 5556856 0.75 0.5 2.64E-06 12%

103 103.5 2322046 5583897 1.25 0.4 2.51E-06 12%

103.5 104 2333291 5610937 1.75 0.4 2.02E-06 9%

104 104.5 2344536 5637978 2.25 0.3 1.89E-06 9%

104.5 105 2355781 5665019 2.75 0.3 1.99E-06 9%

105 105.5 2367025 5692059 3.25 0.4 2.42E-06 11%

105.5 106 2378270 5719100 3.75 0.3 1.45E-06 7%

106 106.5 2389515 5746141 4.25 0.2 1.36E-06 6%

106.5 107 2400760 5773181 4.75 0.3 1.92E-06 9%

107 107.5 2412004 5800222 5.25 0.2 1.19E-06 6%

107.5 108 2423249 5827263 Total 2.14E-05 100%

As seen in Figure 46, using the floor the average floor concentrations provides conservative basis for estimating the Cs-134 source term in the Incore walls under vessel.

TSD 13-006 Revision 0 Page 86 of 200 Figure 46 - U2 Cs-134 Incore Wall Profile Actual versus Worst Case The floor concentrations can be used in order to provide a conservative estimate of the Cs-134 source term in the Incore wall as shown in Table 49. The floor concentrations with depth can be used in order to provide a conservative estimate of the Cs-137 in the wall.

Table 52 - Unit 2 Incore Wall Cs-134 Profile Using Floor Concentrations U2 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Cs-134 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Cs-134 Ci 0.25 0.6 102.5 103 2.311E+06 5.557E+06 3.6E-06 0.75 0.6 103 103.5 2.322E+06 5.584E+06 3.2E-06 1.25 0.6 103.5 104 2.333E+06 5.611E+06 3.2E-06 1.75 0.6 104 104.5 2.345E+06 5.638E+06 3.3E-06 2.25 0.5 104.5 105 2.356E+06 5.665E+06 2.6E-06 2.75 0.3 105 105.5 2.367E+06 5.692E+06 2.0E-06 3.25 0.6 105.5 106 2.378E+06 5.719E+06 3.3E-06 3.75 0.5 106 106.5 2.390E+06 5.746E+06 2.7E-06 4.25 0.5 106.5 107 2.401E+06 5.773E+06 2.8E-06 4.75 0.5 107 107.5 2.412E+06 5.800E+06 3.0E-06 5.25 0.4 107.5 108 2.423E+06 5.827E+06 2.2E-06 5.75 0.5 108 108.5 2.434E+06 5.854E+06 2.8E-06 6.25 0.3 108.5 109 2.446E+06 5.881E+06 1.9E-06 6.75 0.5 109 109.5 2.457E+06 5.908E+06 2.8E-06 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0

5 10 15 pCi/g Depth Inches U2 Incore Cs-134 Concentration Wall Wall Cs-134 pCi/g Worst Case Wall Cs-134 pCi/g

TSD 13-006 Revision 0 Page 87 of 200 U2 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Cs-134 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Cs-134 Ci 7.25 0.4 109.5 110 2.468E+06 5.935E+06 2.2E-06 7.75 0.4 110 110.5 2.479E+06 5.962E+06 2.2E-06 8.25 0.3 110.5 111 2.491E+06 5.990E+06 1.8E-06 8.75 0.3 111 111.5 2.502E+06 6.017E+06 1.9E-06 9.25 0.2 111.5 112 2.513E+06 6.044E+06 1.3E-06 9.75 0.3 112 112.5 2.524E+06 6.071E+06 1.5E-06 10.25 0.2 112.5 113 2.536E+06 6.098E+06 1.4E-06 10.75 0.3 113 113.5 2.547E+06 6.125E+06 2.0E-06 11.25 0.2 113.5 114 2.558E+06 6.152E+06 1.0E-06 11.75 0.2 114 114.5 2.569E+06 6.179E+06 1.3E-06 12.25 0.1 114.5 115 2.581E+06 6.206E+06 7.7E-07 12.75 0.2 115 115.5 2.592E+06 6.233E+06 1.1E-06 13.25 0.1 115.5 116 2.603E+06 6.260E+06 8.2E-07 13.75 0.1 116 116.5 2.614E+06 6.287E+06 6.5E-07 Total 5.9E-05 The Unit 2 floor average concentrations for Eu-152 are shown in Figure 47. It can be seen that the concentrations trend downward consistently at 3 inches depth.

Figure 47 - Unit 2 Incore Floor Average Eu-152 Concentrations The U2 Eu-152 source term profile for the Incore 541.5 foot floor is shown in Table 53.

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0 180.0 0

5 10 15 pCi/g Depth inches U2 Incore Eu-152 Avg Concentration Floor Avg. Eu-152 pCi/g

TSD 13-006 Revision 0 Page 88 of 200 Table 53 - Unit 2 Incore Floor Eu-152 Profile U2 542 ft Floor Eu-152 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Eu-152 pCi/g Min.

Eu-152 pCi/g Avg.

Eu-152 pCi/g Source Term Floor Eu-152 Ci Source Term Distribution Floor 0.25 2.0 121.7 112.8 117.3 7.63E-05 5.9%

0.75 2.0 182.6 125.9 154.2 1.00E-04 7.8%

1.25 2.0 182.6 149.0 165.8 1.08E-04 8.3%

1.75 2.0 179.5 124.9 152.2 9.90E-05 7.7%

2.25 2.0 186.2 136.5 161.3 1.05E-04 8.1%

2.75 2.0 148.4 121.8 135.1 8.79E-05 6.8%

3.25 2.0 147.4 122.9 135.1 8.79E-05 6.8%

3.75 2.0 130.3 116.3 123.3 8.02E-05 6.2%

4.25 2.0 125.7 103.2 114.5 7.45E-05 5.8%

4.75 2.0 129.3 91.7 110.5 7.18E-05 5.6%

5.25 1.0 95.8 95.8 95.8 6.23E-05 4.8%

5.75 1.0 91.8 91.8 91.8 5.97E-05 4.6%

6.25 1.0 67.9 67.9 67.9 4.42E-05 3.4%

6.75 1.0 71.8 71.8 71.8 4.67E-05 3.6%

7.25 1.0 57.2 57.2 57.2 3.72E-05 2.9%

7.75 1.0 44.9 44.9 44.9 2.92E-05 2.3%

8.25 1.0 35.5 35.5 35.5 2.31E-05 1.8%

8.75 1.0 33.1 33.1 33.1 2.15E-05 1.7%

9.25 1.0 22.7 22.7 22.7 1.48E-05 1.1%

9.75 1.0 22.8 22.8 22.8 1.48E-05 1.1%

10.25 1.0 17.4 17.4 17.4 1.13E-05 0.9%

10.75 1.0 16.9 16.9 16.9 1.10E-05 0.9%

11.25 1.0 11.3 11.3 11.3 7.36E-06 0.6%

11.75 1.0 11.1 11.1 11.1 7.20E-06 0.6%

12.25 1.0 7.5 7.5 7.5 4.86E-06 0.4%

12.75 1.0 5.5 5.5 5.5 3.58E-06 0.3%

13.25 1.0 4.2 4.2 4.2 2.74E-06 0.2%

13.75 1.0 2.8 2.8 2.8 1.84E-06 0.1%

Total 1.3E-03 100%

As seen in Figure 22, the wall Eu-152 concentrations are lower than the floor. Use of this data along with Equation 1 calculated masses leads to the source term estimate in Table 54.

TSD 13-006 Revision 0 Page 89 of 200 Table 54 - Unit 2 Incore Wall Eu-152 Profile Using Wall Core U2 542 ft Wall Eu-152 Summary Decayed To 1/1/13 Depth Wall Eu-152 pCi/g Source Term Wall Eu-152 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 72.2 4.01E-04 10%

102.5 103 2310801 5556856 0.75 87.2 4.87E-04 12%

103 103.5 2322046 5583897 1.25 89.5 5.02E-04 13%

103.5 104 2333291 5610937 1.75 80.9 4.56E-04 12%

104 104.5 2344536 5637978 2.25 73.4 4.16E-04 11%

104.5 105 2355781 5665019 2.75 78.4 4.47E-04 11%

105 105.5 2367025 5692059 3.25 64.7 3.70E-04 9%

105.5 106 2378270 5719100 3.75 43.7 2.51E-04 6%

106 106.5 2389515 5746141 4.25 41.4 2.39E-04 6%

106.5 107 2400760 5773181 4.75 38.6 2.24E-04 6%

107 107.5 2412004 5800222 5.25 28.0 1.63E-04 4%

107.5 108 2423249 5827263 Total 3.96E-03 100%

As seen in Figure 48, using the average floor concentrations provides a conservative basis for estimating the Eu-152 source term in the Incore walls under vessel.

Figure 48 - U2 Eu-152 Incore Wall Profile Actual versus Worst Case The floor concentrations can be used in order to provide a conservative estimate of the Eu-152 source term in the Incore wall as shown in Table 55.

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0 180.0 0

5 10 15 pCi/g Depth Inches U2 Incore Cs-134 Concentration Wall Wall Eu-152 pCi/g Worst Case Wall Eu-152 pCi/g

TSD 13-006 Revision 0 Page 90 of 200 Table 55 - Unit 2 Incore Wall Eu-152 Profile Using Floor Concentrations U2 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Eu-152 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Eu-152 Ci 0.25 117.3 102.5 103 2.311E+06 5.557E+06 6.5E-04 0.75 154.2 103 103.5 2.322E+06 5.584E+06 8.6E-04 1.25 165.8 103.5 104 2.333E+06 5.611E+06 9.3E-04 1.75 152.2 104 104.5 2.345E+06 5.638E+06 8.6E-04 2.25 161.3 104.5 105 2.356E+06 5.665E+06 9.1E-04 2.75 135.1 105 105.5 2.367E+06 5.692E+06 7.7E-04 3.25 135.1 105.5 106 2.378E+06 5.719E+06 7.7E-04 3.75 123.3 106 106.5 2.390E+06 5.746E+06 7.1E-04 4.25 114.5 106.5 107 2.401E+06 5.773E+06 6.6E-04 4.75 110.5 107 107.5 2.412E+06 5.800E+06 6.4E-04 5.25 95.8 107.5 108 2.423E+06 5.827E+06 5.6E-04 5.75 91.8 108 108.5 2.434E+06 5.854E+06 5.4E-04 6.25 67.9 108.5 109 2.446E+06 5.881E+06 4.0E-04 6.75 71.8 109 109.5 2.457E+06 5.908E+06 4.2E-04 7.25 57.2 109.5 110 2.468E+06 5.935E+06 3.4E-04 7.75 44.9 110 110.5 2.479E+06 5.962E+06 2.7E-04 8.25 35.5 110.5 111 2.491E+06 5.990E+06 2.1E-04 8.75 33.1 111 111.5 2.502E+06 6.017E+06 2.0E-04 9.25 22.7 111.5 112 2.513E+06 6.044E+06 1.4E-04 9.75 22.8 112 112.5 2.524E+06 6.071E+06 1.4E-04 10.25 17.4 112.5 113 2.536E+06 6.098E+06 1.1E-04 10.75 16.9 113 113.5 2.547E+06 6.125E+06 1.0E-04 11.25 11.3 113.5 114 2.558E+06 6.152E+06 7.0E-05 11.75 11.1 114 114.5 2.569E+06 6.179E+06 6.8E-05 12.25 7.5 114.5 115 2.581E+06 6.206E+06 4.6E-05 12.75 5.5 115 115.5 2.592E+06 6.233E+06 3.4E-05 13.25 4.2 115.5 116 2.603E+06 6.260E+06 2.6E-05 13.75 2.8 116 116.5 2.614E+06 6.287E+06 1.8E-05 Total 1.1E-02 The graph of the Unit 2 541.5 foot floor Eu-154 concentrations is provided in Figure 49.

TSD 13-006 Revision 0 Page 91 of 200 Figure 49 - Unit 2 Incore Floor Average Eu-154 Concentrations The calculated Eu-154 activity profile in the Unit 2 Incore floor is provided in Table 56.

Table 56 - Unit 2 Incore Floor Eu-154 Profile U2 542 ft Floor Eu-154 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Eu-154 pCi/g Min.

Eu-154 pCi/g Avg.

Eu-154 pCi/g Source Term Floor Eu-154 Ci Source Term Distribution Floor 0.25 2.0 9.0 9.0 9.0 5.86E-06 7.9%

0.75 2.0 11.0 8.6 9.8 6.38E-06 8.6%

1.25 2.0 11.4 9.1 10.2 6.64E-06 9.0%

1.75 2.0 10.9 7.8 9.4 6.08E-06 8.2%

2.25 2.0 10.7 8.9 9.8 6.36E-06 8.6%

2.75 2.0 8.6 7.2 7.9 5.16E-06 7.0%

3.25 2.0 8.6 6.6 7.6 4.93E-06 6.7%

3.75 2.0 7.6 6.3 7.0 4.53E-06 6.1%

4.25 2.0 6.8 5.4 6.1 3.97E-06 5.4%

4.75 2.0 7.1 5.2 6.1 3.99E-06 5.4%

5.25 1.0 5.0 5.0 5.0 3.27E-06 4.4%

5.75 1.0 3.8 3.8 3.8 2.46E-06 3.3%

6.25 1.0 3.2 3.2 3.2 2.07E-06 2.8%

6.75 1.0 3.7 3.7 3.7 2.42E-06 3.3%

7.25 1.0 2.8 2.8 2.8 1.83E-06 2.5%

7.75 1.0 2.2 2.2 2.2 1.42E-06 1.9%

8.25 1.0 1.1 1.1 1.1 7.39E-07 1.0%

0.0 2.0 4.0 6.0 8.0 10.0 12.0 0

5 10 15 pCi/g Depth inches U2 Incore Eu-154 Avg Concentration Floor Avg. Eu-154 pCi/g

TSD 13-006 Revision 0 Page 92 of 200 U2 542 ft Floor Eu-154 Summary Decayed To 1/1/13 Avg Depth in Results Max.

Eu-154 pCi/g Min.

Eu-154 pCi/g Avg.

Eu-154 pCi/g Source Term Floor Eu-154 Ci Source Term Distribution Floor 8.75 1.0 1.6 1.6 1.6 1.07E-06 1.4%

9.25 1.0 1.0 1.0 1.0 6.30E-07 0.9%

9.75 1.0 1.0 1.0 1.0 6.20E-07 0.8%

10.25 1.0 1.3 1.3 1.3 8.13E-07 1.1%

10.75 1.0 0.9 0.9 0.9 5.60E-07 0.8%

11.25 1.0 0.6 0.6 0.6 4.21E-07 0.6%

11.75 1.0 0.7 0.7 0.7 4.57E-07 0.6%

12.25 1.0 0.4 0.4 0.4 2.83E-07 0.4%

12.75 1.0 0.5 0.5 0.5 3.24E-07 0.4%

13.25 1.0 0.5 0.5 0.5 3.32E-07 0.4%

13.75 1.0 0.3 0.3 0.3 1.90E-07 0.3%

Total 7.38E-05 100%

Figure 50 - Unit 1 & 2 Incore Wall Eu-154 Concentrations As seen in Figure 50, the wall Eu-154 wall concentrations are lower than the floor. Use of this data along with Equation 1 calculated masses leads to the source term estimate in Table 57.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 0

1 2

3 4

5 6

pCi/g Depth Inches Under Vessel Wall 6 Inch Core U1 Eu-154 pCi/g U2 Eu-154 pCi/g

TSD 13-006 Revision 0 Page 93 of 200 Table 57 - Unit 2 Incore Wall Eu-154 Profile Using Wall Core U2 542 ft Wall Eu-154 Summary Decayed To 1/1/13 Depth Wall Eu-154 pCi/g Source Term Wall Eu-154 Ci Source Term Distribution Wall ID inches OD inches Volume cm3 Mass g 0.25 5.0 2.78E-05 12%

102.5 103 2310801 5556856 0.75 5.2 2.89E-05 13%

103 103.5 2322046 5583897 1.25 5.6 3.13E-05 14%

103.5 104 2333291 5610937 1.75 4.5 2.54E-05 11%

104 104.5 2344536 5637978 2.25 4.2 2.39E-05 10%

104.5 105 2355781 5665019 2.75 4.6 2.63E-05 11%

105 105.5 2367025 5692059 3.25 3.2 1.81E-05 8%

105.5 106 2378270 5719100 3.75 2.4 1.36E-05 6%

106 106.5 2389515 5746141 4.25 2.2 1.29E-05 6%

106.5 107 2400760 5773181 4.75 2.2 1.26E-05 6%

107 107.5 2412004 5800222 5.25 1.4 7.92E-06 3%

107.5 108 2423249 5827263 Total 2.29E-04 1.00 As seen in Figure 51, using the average floor concentrations, without the Eu-154 CY based adjustment factor in Table 28, provides a conservative basis for estimating the Eu-154 source term in the Incore walls under vessel.

Figure 51 - U2 Eu-154 Incore Wall Profile Actual versus Worst Case The floor concentrations can be used in order to provide a conservative estimate of the Eu-154 source term in the Incore wall as shown in Table 58.

0.0 2.0 4.0 6.0 8.0 10.0 12.0 0

5 10 15 pCi/g Depth Inches U2 Incore Eu-154 Concentration Wall Wall Eu-154 pCi/g Worst Case Wall Eu-154 pCi/g

TSD 13-006 Revision 0 Page 94 of 200 Table 58 - Unit 2 Incore Wall Eu-154 Profile Using Floor Concentrations U2 Incore Wall Using Floor Data Decayed To 1/1/13 Avg Depth in Worst Case Wall Eu-154 pCi/g ID inches OD inches Volume cm3 Mass g Wall Source Term Using Floor Data Eu-154 Ci 0.25 9.0 102.5 103 2.311E+06 5.557E+06 5.0E-05 0.75 9.8 103 103.5 2.322E+06 5.584E+06 5.5E-05 1.25 10.2 103.5 104 2.333E+06 5.611E+06 5.7E-05 1.75 9.4 104 104.5 2.345E+06 5.638E+06 5.3E-05 2.25 9.8 104.5 105 2.356E+06 5.665E+06 5.5E-05 2.75 7.9 105 105.5 2.367E+06 5.692E+06 4.5E-05 3.25 7.6 105.5 106 2.378E+06 5.719E+06 4.3E-05 3.75 7.0 106 106.5 2.390E+06 5.746E+06 4.0E-05 4.25 6.1 106.5 107 2.401E+06 5.773E+06 3.5E-05 4.75 6.1 107 107.5 2.412E+06 5.800E+06 3.6E-05 5.25 5.0 107.5 108 2.423E+06 5.827E+06 2.9E-05 5.75 3.8 108 108.5 2.434E+06 5.854E+06 2.2E-05 6.25 3.2 108.5 109 2.446E+06 5.881E+06 1.9E-05 6.75 3.7 109 109.5 2.457E+06 5.908E+06 2.2E-05 7.25 2.8 109.5 110 2.468E+06 5.935E+06 1.7E-05 7.75 2.2 110 110.5 2.479E+06 5.962E+06 1.3E-05 8.25 1.1 110.5 111 2.491E+06 5.990E+06 6.8E-06 8.75 1.6 111 111.5 2.502E+06 6.017E+06 9.9E-06 9.25 1.0 111.5 112 2.513E+06 6.044E+06 5.9E-06 9.75 1.0 112 112.5 2.524E+06 6.071E+06 5.8E-06 10.25 1.3 112.5 113 2.536E+06 6.098E+06 7.6E-06 10.75 0.9 113 113.5 2.547E+06 6.125E+06 5.3E-06 11.25 0.6 113.5 114 2.558E+06 6.152E+06 4.0E-06 11.75 0.7 114 114.5 2.569E+06 6.179E+06 4.3E-06 12.25 0.4 114.5 115 2.581E+06 6.206E+06 2.7E-06 12.75 0.5 115 115.5 2.592E+06 6.233E+06 3.1E-06 13.25 0.5 115.5 116 2.603E+06 6.260E+06 3.2E-06 13.75 0.3 116 116.5 2.614E+06 6.287E+06 1.8E-06 Total 6.5E-04 The calculated Unit 2 Incore Area source terms and their profiles are summarized in Table 59.

It can be seen that the source term is not dominated by the first half inch concentrations as it is in Unit 1.

TSD 13-006 Revision 0 Page 95 of 200 Table 59 - Summary of Calculated Unit 2 Incore Under Vessel Floor Source Terms Avg Depth in Source Term Floor Co-60 Ci Source Term Floor Cs-137 Ci Source Term Floor Cs-134 Ci Source Term Floor Eu-152 Ci Source Term Floor Eu-154 Ci Total Ci

% Total 0.25 1.2E-05 1.9E-04 4.2E-07 7.6E-05 5.9E-06 2.9E-04 16%

0.75 1.2E-05 8.2E-06 3.7E-07 1.0E-04 6.4E-06 1.3E-04 7%

1.25 1.2E-05 3.2E-07 3.7E-07 1.1E-04 6.6E-06 1.3E-04 7%

1.75 1.2E-05 4.0E-07 3.8E-07 9.9E-05 6.1E-06 1.2E-04 7%

2.25 1.1E-05 3.8E-07 3.0E-07 1.0E-04 6.4E-06 1.2E-04 7%

2.75 9.1E-06 2.9E-07 2.3E-07 8.8E-05 5.2E-06 1.0E-04 6%

3.25 9.0E-06 4.2E-07 3.7E-07 8.8E-05 4.9E-06 1.0E-04 6%

3.75 8.3E-06 4.4E-07 3.1E-07 8.0E-05 4.5E-06 9.4E-05 5%

4.25 9.3E-06 4.5E-07 3.2E-07 7.4E-05 4.0E-06 8.9E-05 5%

4.75 9.5E-06 5.0E-07 3.4E-07 7.2E-05 4.0E-06 8.6E-05 5%

5.25 8.5E-06 9.1E-07 2.5E-07 6.2E-05 3.3E-06 7.5E-05 4%

5.75 6.2E-06 7.6E-07 3.1E-07 6.0E-05 2.5E-06 6.9E-05 4%

6.25 5.0E-06 1.2E-06 2.1E-07 4.4E-05 2.1E-06 5.3E-05 3%

6.75 6.5E-06 9.9E-07 3.1E-07 4.7E-05 2.4E-06 5.7E-05 3%

7.25 4.4E-06 1.2E-06 2.4E-07 3.7E-05 1.8E-06 4.5E-05 3%

7.75 2.8E-06 1.2E-06 2.4E-07 2.9E-05 1.4E-06 3.5E-05 2%

8.25 2.7E-06 1.4E-06 1.9E-07 2.3E-05 7.4E-07 2.8E-05 2%

8.75 2.6E-06 1.1E-06 2.0E-07 2.2E-05 1.1E-06 2.7E-05 2%

9.25 1.6E-06 8.6E-07 1.4E-07 1.5E-05 6.3E-07 1.8E-05 1%

9.75 1.7E-06 6.7E-07 1.7E-07 1.5E-05 6.2E-07 1.8E-05 1.0%

10.25 1.7E-06 5.2E-07 1.5E-07 1.1E-05 8.1E-07 1.4E-05 0.8%

10.75 1.7E-06 6.4E-07 2.1E-07 1.1E-05 5.6E-07 1.4E-05 0.8%

11.25 9.2E-07 6.3E-07 1.1E-07 7.4E-06 4.2E-07 9.4E-06 0.5%

11.75 2.2E-06 3.9E-07 1.4E-07 7.2E-06 4.6E-07 1.0E-05 0.6%

12.25 8.0E-07 6.2E-07 8.1E-08 4.9E-06 2.8E-07 6.6E-06 0.4%

12.75 4.2E-07 4.4E-07 1.2E-07 3.6E-06 3.2E-07 4.9E-06 0.3%

13.25 3.0E-07 5.4E-07 8.6E-08 2.7E-06 3.3E-07 4.0E-06 0.2%

13.75 3.1E-07 4.8E-07 6.7E-08 1.8E-06 1.9E-07 2.9E-06 0.2%

Total Ci 1.6E-04 2.2E-04 6.6E-06 1.3E-03 7.4E-05 1.7E-03 100%

% Total 8.9%

12.5%

0.4%

74.0%

4.2%

100%

Table 60 summarizes the Unit 2 calculated Incore wall gamma emitter source terms.

TSD 13-006 Revision 0 Page 96 of 200 Table 60 - Summary of Calculated Unit 2 Incore Under Vessel Wall Source Terms Avg Depth in Wall Source Term Using Floor Data Co-60 Ci Wall Source Term Using Floor Data Cs-137 Ci Wall Source Term Using Floor Data Cs-134 Ci Wall Source Term Using Floor Data Eu-152 Ci Wall Source Term Using Floor Data Eu-154 Ci Total Ci

% Total 0.25 1.0E-04 4.5E-04 3.6E-06 6.5E-04 5.0E-05 1.3E-03 9%

0.75 1.0E-04 1.7E-05 3.2E-06 8.6E-04 5.5E-05 1.0E-03 7%

1.25 1.0E-04 6.3E-06 3.2E-06 9.3E-04 5.7E-05 1.1E-03 8%

1.75 1.1E-04 4.5E-06 3.3E-06 8.6E-04 5.3E-05 1.0E-03 7%

2.25 9.9E-05 4.8E-06 2.6E-06 9.1E-04 5.5E-05 1.1E-03 8%

2.75 8.0E-05 4.5E-06 2.0E-06 7.7E-04 4.5E-05 9.0E-04 6%

3.25 7.9E-05 4.8E-06 3.3E-06 7.7E-04 4.3E-05 9.0E-04 6%

3.75 7.3E-05 4.0E-06 2.7E-06 7.1E-04 4.0E-05 8.3E-04 6%

4.25 8.3E-05 2.7E-06 2.8E-06 6.6E-04 3.5E-05 7.8E-04 6%

4.75 8.4E-05 4.2E-06 3.0E-06 6.4E-04 3.6E-05 7.7E-04 5%

5.25 7.6E-05 9.7E-06 2.2E-06 5.6E-04 2.9E-05 6.8E-04 5%

5.75 5.6E-05 6.9E-06 2.8E-06 5.4E-04 2.2E-05 6.3E-04 4%

6.25 4.6E-05 1.0E-05 1.9E-06 4.0E-04 1.9E-05 4.8E-04 3%

6.75 5.9E-05 9.0E-06 2.8E-06 4.2E-04 2.2E-05 5.2E-04 4%

7.25 4.0E-05 1.1E-05 2.2E-06 3.4E-04 1.7E-05 4.1E-04 3%

7.75 2.6E-05 1.1E-05 2.2E-06 2.7E-04 1.3E-05 3.2E-04 2%

8.25 2.5E-05 1.3E-05 1.8E-06 2.1E-04 6.8E-06 2.6E-04 2%

8.75 2.4E-05 1.1E-05 1.9E-06 2.0E-04 9.9E-06 2.5E-04 2%

9.25 1.4E-05 8.0E-06 1.3E-06 1.4E-04 5.9E-06 1.7E-04 1.2%

9.75 1.6E-05 6.2E-06 1.5E-06 1.4E-04 5.8E-06 1.7E-04 1.2%

10.25 1.6E-05 4.9E-06 1.4E-06 1.1E-04 7.6E-06 1.4E-04 1.0%

10.75 1.6E-05 6.0E-06 2.0E-06 1.0E-04 5.3E-06 1.3E-04 0.9%

11.25 8.7E-06 6.0E-06 1.0E-06 7.0E-05 4.0E-06 8.9E-05 0.6%

11.75 2.1E-05 3.7E-06 1.3E-06 6.8E-05 4.3E-06 9.9E-05 0.7%

12.25 7.6E-06 5.9E-06 7.7E-07 4.6E-05 2.7E-06 6.3E-05 0.4%

12.75 4.0E-06 4.2E-06 1.1E-06 3.4E-05 3.1E-06 4.7E-05 0.3%

13.25 2.9E-06 5.2E-06 8.2E-07 2.6E-05 3.2E-06 3.8E-05 0.3%

13.75 2.9E-06 4.7E-06 6.5E-07 1.8E-05 1.8E-06 2.8E-05 0.2%

Total Ci 1.4E-03 6.4E-04 5.9E-05 1.1E-02 6.5E-04 1.4E-02 100%

% Total 9.7%

4.5%

0.4%

80.8%

4.6%

100%

3.9.

Summary of Unit 1 and 2 Source Terms from In-House Gamma Spectroscopy Results The calculated embedded concrete gamma emitter source terms for the Unit 1 and Unit 2 Reactor Buildings are provided in Table 61. The Unit 1 6.750 Ci source term clearly bounds the 0.958 Ci source term of Unit 2. These source terms are based upon cores taken at areas exhibiting evidence of spills and leakage and with elevated dose rates, they are therefore biased high and bound any actual potential source terms present in the end state configuration.

TSD 13-006 Revision 0 Page 97 of 200 Table 61 - Summary of Unit 1 and 2 Reactor Building Gamma Emitter Source Terms Location Co-60 Ci Cs-137 Ci Cs-134 Ci Eu-152 Ci Eu-154 Ci Total U1 568' Floor 0.208 6.796 0.002 N/A N/A 7.006 U1 542' Floor 1.94E-04 9.57E-04 5.93E-06 6.51E-04 3.42E-05 0.002 U1 Incore Wall 9.93E-04 2.98E-03 5.35E-05 6.84E-03 3.73E-04 0.011 U1 Total 0.209 6.800 0.002 0.007 0.0004 7.019 U2 568' Floor 0.255 0.724 0.001 N/A N/A 0.980 U2 542' Floor 1.55E-04 2.18E-04 6.62E-06 1.29E-03 7.38E-05 0.002 U2 Incore Wall 1.38E-03 6.41E-04 5.94E-05 1.15E-02 6.52E-04 0.014 U2 Total 0.257 0.725 0.001 0.013 0.0007 0.996 As seen in Table 62 the 568 foot floor source term dominates the Unit 1 and 2 source terms with Cs-137 and to a lesser extent Co-60 comprising most of the source term, even with conservative assumptions applied to the Incore activation nuclides the 568 foot elevation floors account for over 99% of the gamma emitter source term in Unit 1 and over 98% of the gamma emitter source term in Unit 2. This indicates that control of leaks and spills throughout a facilities operation is the biggest factor in controlling end state source term for scenarios in which the bioshield is removed.

Table 62 - Unit 1 and 2 Reactor Source Term Fractions Location Co-60 Cs-137 Cs-134 Eu-152 Eu-154 Total U1 568' Floor 3.0%

96.8%

0.03%

N/A N/A 99.8%

U1 542' Floor 0.003%

0.014%

0.0001%

0.01%

0.0005%

0.03%

U1 Incore Wall 0.01%

0.04%

0.001%

0.10%

0.01%

0.16%

U1 Total 2.97%

96.88%

0.03%

0.11%

0.01%

100.00%

U2 568' Floor 25.6%

72.7%

0.11%

N/A N/A 98.4%

U2 542' Floor 0.02%

0.02%

0.001%

0.13%

0.01%

0.18%

U2 Incore Wall 0.14%

0.06%

0.01%

1.2%

0.07%

1.42%

U2 Total 25.8%

72.8%

0.1%

1.3%

0.1%

100.0%

In Unit 2 the first half inch of the Incore floor area only accounts for 16% of the overall source term and Cs-137 is only 12.5 % as opposed to Eu-152 which is 74% as seen in Table 59. This indicates the contamination is largely due to neutron activation in Unit 2 as opposed to leaks and spills in Unit 1.As in Unit 1, the Incore area wall contains bulk of the source term at 1.4E-02 Ci for gamma emitters as opposed to the floor which has 1.7E-03 Ci. As in Unit 1 the wall source term is dominated by the activation product Eu-152 which is 81% of the mix.

3.10. Evaluation of Unit 1 and 2 Incore Area Eberline Off-Site Laboratory Results The first 1/2 inch puck from 4 floor cores of the Incore floors were sent to Eberline Laboratory for gamma spectroscopy and hard to detect analyses for radionuclides such as tritium, C-14, Tc-99, I-129, Ni-59/63, Sr-90, and alpha emitters. The pucks were powdered at Eberline and used for gamma spectroscopy and isotopic extractions and analyses. The Unit 1 results were reported in Eberline reports 12-12088 and 13-02003. 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-214, Bi-214, etc. that are not licensed material. As stated in Section 3.4, the following criteria were used when deciding which reported values to use.

TSD 13-006 Revision 0 Page 98 of 200

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) were reported, half the reported value was used for each nuclide.

4. For Am-241, alpha spectroscopy results (EML Am-01 Modified) were used rather than the gamma spectroscopy results (LANL ER-130 Modified) because alpha spectroscopy is less subject to Compton edge interference from the wide array of natural and licensed radioactive material photon emitters in the concrete samples at the Am-241 59.5 keV photo-peak.

The relevant results excerpted from the reports based upon the above criteria are provided in Attachment I. There were no positive results in the Unit 1 and 2 Incore samples for Mn-54, Fe-55, Ni-59, Sb-125, Ba-133, Ho-166m, and Np-237. Therefore they are not included in Attachment I. As noted in Section 3.4, the case narratives reported issues with sample results potentially biased positive by the presence of high levels of Cesium-137 which carried over into pure beta emitter samples such as Ni-63 and interfered with gamma spectroscopy results.

Therefore, as described in in Section 3.4, Ag-108m, I-129, Pm-145, and Pm-147 results were considered False Positives and are not included in the final source terms. A detailed review of the reported results and Eberline Case Narratives was performed to determine the positively identified radionuclides and their concentrations.

Nb-94 The Case Narrative for Eberline report 12-12088 states, Due to the presence of significantly positive Cesium-137 activity in most samples, most required gamma emitting radionuclides are not resolvable. In other instances in the case of the source term for this site, some radionuclides as required would be completely decayed; therefore, should be qualified as appropriate. As a result of these conditions results for several radionuclides are qualified as non-detect, "U". This includes all results for Actinium-228, Silver-108m, Barium-133, Cesium-134, Europium-152, Europium-154, Europium-155, Holmium-166m, Iodine-129, Potassium-40, Manganese-54, Niobium-94, Lead-210, Lead-212, Lead-214, Radium-226, Antimony-125, Thorium-234, Thallium-208 and Uranium-235. In the case of Cesium-134 and Promethium-145, energy lines were identified; however, these are interference lines from other radionuclides and therefore results are non-detect. In the case of Canberra software derived results for Cesium-134 and Promethium-145, results are greater than the MDA; however, results are "not true positives" and therefore are qualified as "U". The Nb-94 result of core 01110-CJFCCV-002 is well below the reported MDA and 2 sigma values and is undetected U.

The 1.48 pCi/g result for Unit 1 core B101110CJFCCV001 is designated as undetected U in the Eberline results reported in 13-02003. This result met the above criteria as a positive identification. The Case Narrative is silent on the basis for the undetected designation. Nb-94 was also positively identified in Eberline reports 13-03084 and 13-04110 for the Unit 2 cores at 3.22 and 2.48 pCi/g. The 3.22 pCi/g result in report 13-03084 is also designated as undetected U in the results while the 2.48 pCi/g result in 13-04110 is reported as a positive result. The report 13-03084 Case Narrative is silent on the undetected designation as well. As seen in Attachment J, Nb-94 is identified by gamma spectroscopy based on a 100% emission of a 871

TSD 13-006 Revision 0 Page 99 of 200 keV gamma ray. Based on this it is considered a valid result and will be included in the Unit 1 Incore Area source term estimates.

Tc-99 There were no positive identifications of Tc-99 in the 541.5 foot cores.

Eu-152, Eu-154 and Eu-155 As noted above the Case Narrative of 12-12088 states that the results for these nuclides are qualified as non-detects U. However the 12-12088 results have only the Eu-154 and Eu-155 results qualified with a U. The Eu-154 result was above the MDA and 2 sigma values and is considered a positive identification. The Case Narrative for Eberline report 13-02003 states, Sample fraction -07 (Client ID: B101110CJFCCV001) Europium-I52 and Europium-I54 results are greater than the detection limits. The Eu-155 concentration in Eberline results reported in 13-02003 is designated U for core B101110CJFCCV001, but is above the MDA and 2 sigma value and is also considered a valid result that will be include in the Unit 1 source term evaluation.

The Case Narrative for Eberline reports 13-03084 states, Europium-152 and Europium-154 results for sample fraction -08 (Client ID: B102110-CJFCCV001) are biased high due to the interfering 36 keV x-ray from Barium-137m and are therefore qualified as "Estimated High" (JH). Eu-152 and Eu-155 results are designated as JH in the reported results. Eu-155 is reported as a positive result. As seen in Attachment J, Eu-155 is detected by gamma spectroscopy based on a 105 keV gamma ray with a 21% yield. The Case Narrative for 13-04110 states, In many instances, gamma emitting radionuclides as reported are bias positive as a result of Compton or summation effects from significantly positive Cobalt-60 and Cesium-I 3 7 activity in these samples. All results are that are affected by this condition are qualified as estimated high, JH. The Eu-152, 154, and 155 results are not reported as JH in 13-04110.

As seen in Attachment J, Eu-152 and Eu-154 are identified by gamma spectroscopy based on 1.408 MeV at 21% and 1.27 MeV at 36% emissions respectively. Therefore 36 keV X-rays would not interfere with detection and the results are considered valid.

Pu-238 One core B101110CJFCCV001 had positive Pu-238 results reported in Eberline report 13-02003.

Pu-239/240 One core 01110-CJFCCV-002 out of the four Unit 1 and 2 cores reported positive Pu-239/240 results in Eberline report 12-12088. Although the concentration 0.109 pCi/g was only slightly above the 0.106 pCi/g MDA, the result is not designated as undetected (U). This core also contained Cm-243/244 positively identified well above the MDA. It will therefore be considered a positive identification.

Pu-241 Cores B101110-CJFCCV-001 was re-analyzed to achieve lower MDAs. The re-analysis results are provided in Eberline report 13-04025. These lower MDA values replace the previous Pu-241 MDA for the core. Based on this there were no positive identifications of Pu-241 in the Unit 1 541.5 foot cores. Similarly there were no positive identifications of Pu-241 in the Unit 2

TSD 13-006 Revision 0 Page 100 of 200 568 foot elevation core results. Based on this, Pu-241 is not included in the Unit 1 or 2 568 foot elevation concrete estimated source terms.

Am-243 The Am-243 result for Unit 2 core B1-02110-CJFCCV001 is designated as undetected U in Eberline report 13-03084 even though it is slightly over 5.01E-2 pCi/g MDA. The Case Narrative states, Samples demonstrated acceptable results for all Americium-243 analyses. In some instances results are only slightly higher than method detection limits. All sample results are non-detect and are therefore all qualified as "Non-Detect" (U). There was no other positive result in the Unit 1 or 2 541.5 foot cores. Based on this the 13-03084 result is considered a False Positive and Am-243 will not be included in the Incore area source term.

The results in Attachment I also contain data decay corrected to January 1, 2013 for comparison to the decay corrected in-house gamma spectroscopy results. As seen in Table 63 and Table 64, the Co-60, Cs-137, Eu-152 and Eu-154 results for individual samples varied significantly relative to the average concentration from the puck top and bottom in-house gamma spectroscopy results. Overall, the Unit 1 the Eberline reported Co-60 and Cs-137 concentrations were 133% and 144% higher than the In-House gamma spectroscopy results (Table 63). Similarly the Eu-152 and Eu-154 Eberline results were 194% and 207% higher than the In-House gamma spectroscopy results. The Unit 2.Eberline results were higher than the In-House gamma spectroscopy results by 200% as seen in Table 64.

Table 63 - Comparison of In-House and Eberline Gamma Spectroscopy Results for Unit 1 541.5' Samples Sample ID Eberline Lab Report In-House Co-60 pCi/g Eberline Co-60 pCi/g Eberline/

In-House In-House Cs-137 pCi/g Eberline Cs-137 pCi/g Eberline/

In-House B101110-CJFCCV-001 13-02003 24.2 42.5 175%

4.09E+01 8.76E+01 214%

B101110-CJFCCV-002 12-12088 267.4 344.1 129%

1.97E+03 2.81E+03 143%

Totals 291.6 386.6 133%

2011.7 2902.3 144%

Sample ID Eberline Lab Report In-House Eu-152 pCi/g Eberline Eu-152 pCi/g Eberline/

In-House In-House Eu-154 pCi/g Eberline Eu-154 pCi/g Eberline/

In-House B101110-CJFCCV-001 13-02003 7.18E+01 1.61E+02 225%

5.38E+00 1.26E+01 234%

B101110-CJFCCV-002 12-12088 6.60E+01 1.06E+02 161%

4.79E+00 8.46E+00 177%

Totals 137.8 267.6 194%

10.2 21.0 207%

TSD 13-006 Revision 0 Page 101 of 200 Table 64 - Comparison of In-House and Eberline Gamma Spectroscopy Results for Unit 2 541.5' Samples Sample ID Eberline Lab Report In-House Co-60 pCi/g Eberline Co-60 pCi/g Eberline/

In-House In-House Cs-137 pCi/g Eberline Cs-137 pCi/g Eberline

/ -House B102110-CJFCCV-001 13-03084 2.30E+01 5.00E+01 217%

5.77E+02 1.05E+03 182%

B102110-CJFCCV-002 13-04110 1.43E+01 2.29E+01 160%

1.30E+01 1.56E+01 120%

Totals 3.73E+01 7.29E+01 195%

590.0 1063.5 180%

Sample ID Eberline Lab Report In-House Eu-152 pCi/g Eberline Eu-152 pCi/g Eberline/

In-House In-House Eu-154 pCi/g Eberline Eu-154 pCi/g Eberline

/ In-House B102110-CJFCCV-001 13-03084 1.22E+02 3.97E+02 326%

9.02E+00 2.58E+01 286%

B102110-CJFCCV-002 13-04110 1.13E+02 2.53E+02 225%

9.00E+00 2.17E+01 241%

Totals 234.5 650.5 277%

18.0 47.5 263%

The decay corrected data in Attachment I was used to calculate key radionuclide ratios as shown in Table 65 and Table 66. The detectable gross beta included results for nuclides with a beta average > 40 keV and reported above the MDA. The emissions, energies, and yields used for this evaluation are provided in Attachment J. Pm-147 was excluded from the calculated gross beta result due to the unreliability of gamma spectroscopy results (0.121 MeV, 0.002%

yield) for this nuclide when in the presence of other gamma emitting nuclides. The Sr-90 contribution to the gross beta activity was multiplied by 2 to account for the Y-90 beta. The Eu-152 activity was multiplied by 0.28 to correct for the beta yield per decay. The transuranic alpha emitters above MDA were used to calculate the Unit 1 gross alpha. There were no positively identified transuranics in the Unit 2 cores, so the MDAs were used to calculate an estimated upper gross alpha activity.

The gross alpha to gross beta key radionuclide ratios were calculated based on these results. In addition, scaling factors for hard to detect nuclides relative to Am-241, Cs-137, Co-60 and Eu-152 were calculated and compared. As seen in Table 65 and Table 66 the range of ratios varied by several orders of magnitude across the Unit 1 and Unit 2 541.5 elevation cores. The values that are based in part on a reported MDA are shown in bold italics.

Table 65 - Summary of Key Radionuclide Ratios for U1 541.5 EL Cores Core ID B101110-CJFCCV-001 B101110-CJFCCV-002 Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio Eberline Report 13-02003 12-12088 All Results Positive Results Gross beta to alpha Gross Beta > 0.4 keV 1.93E+02 3.20E+03 3.20E+03 1.93E+02 1.70E+03 3.20E+03 1.93E+0 2

1.70E+03 Gross Alpha 5.20E-02 4.83E-01 4.83E-01 5.20E-02 2.67E-01 4.83E-01 5.20E-02 2.67E-01 Gross Beta/Gross Alpha 3.71E+03 6.63E+03 6.63E+03 3.71E+03 5.17E+03 6.63E+03 3.71E+0 3

5.17E+03 Am-241 Ratios Pu-238/Am-241 Ratio 1.19E+00 5.53E-01 1.19E+00 5.53E-01 8.70E-01 ND ND ND Pu-239/Am-241 Ratio 5.14E-01 2.49E-01 5.14E-01 2.49E-01 3.81E-01 2.49E-01 2.49E-01 2.49E-01 Pu-240/Am-241 Ratio 5.14E-01 2.49E-01 5.14E-01 2.49E-01 3.81E-01 2.49E-01 2.49E-01 2.49E-01 Pu-241/Am-241 Ratio 9.61E+00 3.26E+01 3.26E+01 9.61E+00 2.11E+01 ND ND ND

TSD 13-006 Revision 0 Page 102 of 200 Core ID B101110-CJFCCV-001 B101110-CJFCCV-002 Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio Eberline Report 13-02003 12-12088 All Results Positive Results Am-243/Am-241 Ratio 6.94E-01 4.26E-01 6.94E-01 4.26E-01 5.60E-01 ND ND ND Cm-243/Am-241 Ratio 7.19E-01 3.54E-01 7.19E-01 3.54E-01 5.37E-01 3.54E-01 3.54E-01 3.54E-01 Cm-244/Am-241 Ratio 7.16E-01 3.52E-01 7.16E-01 3.52E-01 5.34E-01 3.52E-01 3.52E-01 3.52E-01 Am-241/Gross Alpha 84%

45%

84%

45%

65%

45%

45%

45%

Cs-137 Ratios H-3/Cs-137 1.49E+00 7.66E-02 1.49E+00 7.66E-02 7.81E-01 1.49E+00 7.66E-02 7.81E-01 C-14/Cs-137 1.13E-02 1.17E-03 1.13E-02 1.17E-03 6.23E-03 1.17E-03 1.17E-03 1.17E-03 Co-60/Cs-137 4.85E-01 1.22E-01 4.85E-01 1.22E-01 3.04E-01 4.85E-01 1.22E-01 3.04E-01 Ni-63/Cs-137 1.60E+00 1.06E-02 1.60E+00 1.06E-02 8.04E-01 1.60E+00 1.06E-02 8.04E-01 Sr-90/Cs-137 3.58E-03 2.12E-04 3.58E-03 2.12E-04 1.90E-03 2.12E-04 2.12E-04 2.12E-04 Tc-99/Cs-137 3.01E-03 4.71E-04 3.01E-03 4.71E-04 1.74E-03 ND ND ND Sb-125/Cs-137 2.04E-02 2.93E-03 2.04E-02 2.93E-03 1.17E-02 ND ND ND Eu-152/Cs-137 1.84E+00 3.78E-02 1.84E+00 3.78E-02 9.40E-01 3.78E-02 3.78E-02 3.78E-02 Eu-154/Cs-137 1.44E-01 3.00E-03 1.44E-01 3.00E-03 7.33E-02 3.00E-03 3.00E-03 3.00E-03 Eu-155/Cs-137 4.20E-02 1.19E-03 4.20E-02 1.19E-03 2.16E-02 4.20E-02 4.20E-02 4.20E-02 Np-237/Cs-137 3.13E-04 2.49E-05 3.13E-04 2.49E-05 1.69E-04 ND ND ND Pu-238/Cs-137 5.93E-04 4.31E-05 5.93E-04 4.31E-05 3.18E-04 ND ND ND Pu-239/Cs-137 2.57E-04 1.94E-05 2.57E-04 1.94E-05 1.38E-04 1.94E-05 1.94E-05 1.94E-05 Pu-240/Cs-137 2.57E-04 1.94E-05 2.57E-04 1.94E-05 1.38E-04 1.94E-05 1.94E-05 1.94E-05 Pu-241/Cs-137 4.80E-03 2.54E-03 4.80E-03 2.54E-03 3.67E-03 ND ND ND Am-241/Cs-137 5.00E-04 7.79E-05 5.00E-04 7.79E-05 2.89E-04 7.79E-05 7.79E-05 7.79E-05 Am-243/Cs-137 3.47E-04 3.32E-05 3.47E-04 3.32E-05 1.90E-04 ND ND ND Cm-243/Cs-137 3.59E-04 2.76E-05 3.59E-04 2.76E-05 1.93E-04 2.76E-05 2.76E-05 2.76E-05 Cm-244/Cs-137 3.58E-04 2.74E-05 3.58E-04 2.74E-05 1.93E-04 2.74E-05 2.74E-05 2.74E-05 Gross Alpha/Cs-137 5.93E-04 1.72E-04 5.93E-04 1.72E-04 3.82E-04 5.93E-04 1.72E-04 3.82E-04 Co-60 Ratios H-3/Co-60 3.06E+00 6.27E-01 3.06E+00 6.27E-01 1.84E+00 3.06E+00 6.27E-01 1.84E+00 C-14/Co-60 2.33E-02 9.58E-03 2.33E-02 9.58E-03 1.64E-02 9.58E-03 9.58E-03 9.58E-03 Fe-55/Co-60 1.91E-02 3.41E-01 3.41E-01 1.91E-02 1.80E-01 ND ND ND Ni-59/C0-60 2.32E+01 2.77E+01 2.77E+01 2.32E+01 2.55E+01 ND ND ND Ni-63/Co-60 3.29E+00 8.63E-02 3.29E+00 8.63E-02 1.69E+00 3.29E+00 8.63E-02 1.69E+00 Sr-90/Co-60 7.38E-03 1.73E-03 7.38E-03 1.73E-03 4.56E-03 1.73E-03 1.73E-03 1.73E-03 Nb-94/Co-60 3.47E-02 5.72E-03 3.47E-02 5.72E-03 2.02E-02 3.47E-02 5.72E-03 2.02E-02 Tc-99/Co-60 6.20E-03 3.85E-03 6.20E-03 3.85E-03 5.03E-03 ND ND ND Ag-108m/Co-60 3.43E-02 5.55E-03 3.43E-02 5.55E-03 1.99E-02 ND ND ND Pu-238/Co-60 1.22E-03 3.52E-04 1.22E-03 3.52E-04 7.87E-04 1.22E-03 1.22E-03 1.22E-03 Pu-239/Co-60 5.29E-04 1.58E-04 5.29E-04 1.58E-04 3.44E-04 1.58E-04 1.58E-04 1.58E-04 Pu-240/Co-60 5.29E-04 1.58E-04 5.29E-04 1.58E-04 3.44E-04 1.58E-04 1.58E-04 1.58E-04

TSD 13-006 Revision 0 Page 103 of 200 Core ID B101110-CJFCCV-001 B101110-CJFCCV-002 Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio Eberline Report 13-02003 12-12088 All Results Positive Results Pu-241/Co-60 9.90E-03 2.08E-02 2.08E-02 9.90E-03 1.53E-02 ND ND ND Am-241/Co-60 1.03E-03 6.37E-04 1.03E-03 6.37E-04 8.34E-04 6.37E-04 6.37E-04 6.37E-04 Am-243/Co-60 7.15E-04 2.71E-04 7.15E-04 2.71E-04 4.93E-04 ND ND ND Cm-243/Co-60 7.41E-04 2.26E-04 7.41E-04 2.26E-04 4.83E-04 2.26E-04 2.26E-04 2.26E-04 Cm-244/Co-60 7.37E-04 2.24E-04 7.37E-04 2.24E-04 4.81E-04 2.24E-04 2.24E-04 2.24E-04 Gross Alpha/Co-60 1.22E-03 1.40E-03 1.40E-03 1.22E-03 1.31E-03 1.40E-03 1.22E-03 1.31E-03 Eu-152 Ratios Eu-155/Eu-152 2.28E-02 3.15E-02 3.15E-02 2.28E-02 2.71E-02 3.15E-02 3.15E-02 3.15E-02 Note: Bold Italics are MDA values Table 66 - Summary of Key Radionuclide Ratios for U2 541.5 EL Cores Core ID B102110-CJFCCV-001 B102110-CJFCCV-002 Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio Eberline Report 13-03084 13-04110 All Results Positive Results Detectable Gross Beta > 0.4 keV 1.25E+03 1.42E+02 1.25E+03 1.42E+02 6.95E+02 1.25E+03 1.42E+02 6.95E+02 Non-Detectable Gross Alpha 2.10E-01 1.35E-01 2.10E-01 1.35E-01 1.73E-01 ND ND ND Gross Beta/Gross Alpha 5.93E+03 1.05E+03 5.93E+03 1.05E+03 3.49E+03 ND ND ND Am-241 Ratios Pu-238/Am-241 Ratio 6.48E-01 1.40E+00 1.40E+00 6.48E-01 1.02E+00 ND ND ND Pu-239/Am-241 Ratio 2.82E-01 6.09E-01 6.09E-01 2.82E-01 4.46E-01 ND ND ND Pu-240/Am-241 Ratio 2.82E-01 6.09E-01 6.09E-01 2.82E-01 4.46E-01 ND ND ND Pu-241/Am-241 Ratio 6.72E+01 1.39E+02 1.39E+02 6.72E+01 1.03E+02 ND ND ND Am-243/Am-241 Ratio 1.05E+00 1.86E+00 1.86E+00 1.05E+00 1.46E+00 ND ND ND Cm-243/Am-241 Ratio 5.05E-01 7.38E-01 7.38E-01 5.05E-01 6.21E-01 ND ND ND Cm-244/Am-241 Ratio 5.06E-01 7.39E-01 7.39E-01 5.06E-01 6.22E-01 ND ND ND Am-241/Gross Alpha 23%

14%

23%

14%

19%

ND ND ND Cs-137 Ratios H-3/Cs-137 2.30E-01 2.11E+00 2.11E+00 2.30E-01 1.17E+00 2.11E+00 2.30E-01 1.17E+00 C-14/Cs-137 9.27E-04 1.18E-01 1.18E-01 9.27E-04 5.95E-02 1.18E-01 1.18E-01 1.18E-01 Co-60/Cs-137 4.77E-02 1.47E+00 1.47E+00 4.77E-02 7.58E-01 1.47E+00 4.77E-02 7.58E-01 Ni-63/Cs-137 6.98E-02 3.03E+00 3.03E+00 6.98E-02 1.55E+00 3.03E+00 6.98E-02 1.55E+00 Sr-90/Cs-137 3.55E-04 2.15E-02 2.15E-02 3.55E-04 1.09E-02 2.15E-02 3.55E-04 1.09E-02 Tc-99/Cs-137 2.48E-04 1.60E-02 1.60E-02 2.48E-04 8.13E-03 ND ND ND Sb-125/Cs-137 5.71E-03 1.43E-01 1.43E-01 5.71E-03 7.45E-02 ND ND ND Eu-152/Cs-137 3.79E-01 1.62E+01 1.62E+01 3.79E-01 8.30E+00 1.62E+01 3.79E-01 8.30E+00 Eu-154/Cs-137 2.46E-02 1.39E+00 1.39E+00 2.46E-02 7.07E-01 1.39E+00 2.46E-02 7.07E-01 Eu-155/Cs-137 6.71E-03 3.83E-01 3.83E-01 6.71E-03 1.95E-01 3.83E-01 6.71E-03 1.95E-01 Np-237/Cs-137 4.28E-05 2.23E-03 2.23E-03 4.28E-05 1.14E-03 ND ND ND Pu-238/Cs-137 3.04E-05 1.74E-03 1.74E-03 3.04E-05 8.84E-04 ND ND ND

TSD 13-006 Revision 0 Page 104 of 200 Core ID B102110-CJFCCV-001 B102110-CJFCCV-002 Max Ratio Min Ratio Avg Ratio Max Ratio Min Ratio Avg Ratio Eberline Report 13-03084 13-04110 All Results Positive Results Pu-239/Cs-137 1.32E-05 7.56E-04 7.56E-04 1.32E-05 3.85E-04 ND ND ND Pu-240/Cs-137 1.32E-05 7.56E-04 7.56E-04 1.32E-05 3.85E-04 ND ND ND Pu-241/Cs-137 3.15E-03 1.73E-01 1.73E-01 3.15E-03 8.81E-02 ND ND ND Am-241/Cs-137 4.69E-05 1.24E-03 1.24E-03 4.69E-05 6.44E-04 ND ND ND Am-243/Cs-137 4.95E-05 2.31E-03 2.31E-03 4.95E-05 1.18E-03 4.95E-05 4.95E-05 4.95E-05 Cm-243/Cs-137 2.37E-05 9.16E-04 9.16E-04 2.37E-05 4.70E-04 ND ND ND Cm-244/Cs-137 2.37E-05 9.17E-04 9.17E-04 2.37E-05 4.70E-04 ND ND ND Gross Alpha/Cs-137 2.01E-04 8.64E-03 8.64E-03 2.01E-04 4.42E-03 ND ND ND Co-60 Ratios H-3/Co-60 4.83E+00 1.43E+00 4.83E+00 1.43E+00 3.13E+00 4.83E+00 1.43E+00 3.13E+00 C-14/Co-60 1.94E-02 8.04E-02 8.04E-02 1.94E-02 4.99E-02 8.04E-02 8.04E-02 8.04E-02 Fe-55/Co-60 8.94E-02 8.74E-02 8.94E-02 8.74E-02 8.84E-02 ND ND ND Ni-59/C0-60 1.39E-01 3.25E-01 3.25E-01 1.39E-01 2.32E-01 ND ND ND Ni-63/Co-60 1.46E+00 2.06E+00 2.06E+00 1.46E+00 1.76E+00 2.06E+00 1.46E+00 1.76E+00 Sr-90/Co-60 7.44E-03 1.46E-02 1.46E-02 7.44E-03 1.10E-02 1.46E-02 7.44E-03 1.10E-02 Nb-94/Co-60 6.44E-02 1.08E-01 1.08E-01 6.44E-02 8.62E-02 1.08E-01 6.44E-02 8.62E-02 Tc-99/Co-60 5.20E-03 1.09E-02 1.09E-02 5.20E-03 8.05E-03 ND ND ND Ag-108m/Co-60 8.34E-02 9.06E-02 9.06E-02 8.34E-02 8.70E-02 9.06E-02 8.34E-02 8.70E-02 Pu-238/Co-60 6.36E-04 1.18E-03 1.18E-03 6.36E-04 9.10E-04 ND ND ND Pu-239/Co-60 2.78E-04 5.15E-04 5.15E-04 2.78E-04 3.96E-04 ND ND ND Pu-240/Co-60 2.78E-04 5.15E-04 5.15E-04 2.78E-04 3.96E-04 ND ND ND Pu-241/Co-60 6.60E-02 1.18E-01 1.18E-01 6.60E-02 9.20E-02 ND ND ND Am-241/Co-60 9.83E-04 8.46E-04 9.83E-04 8.46E-04 9.14E-04 ND ND ND Am-243/Co-60 1.04E-03 1.57E-03 1.57E-03 1.04E-03 1.31E-03 1.04E-03 1.04E-03 1.04E-03 Cm-243/Co-60 4.96E-04 6.24E-04 6.24E-04 4.96E-04 5.60E-04 ND ND ND Cm-244/Co-60 4.97E-04 6.25E-04 6.25E-04 4.97E-04 5.61E-04 ND ND ND Gross Alpha/Co-60 4.20E-03 5.88E-03 5.88E-03 4.20E-03 5.04E-03 ND ND ND Eu-152 Ratios Eu-155/Eu-152 1.77E-02 2.36E-02 2.36E-02 1.77E-02 2.07E-02 2.36E-02 1.77E-02 2.07E-02 Note: Bold Italics are MDA values Due to the lower Cs-137 source term in the Unit 2 Incore area floor, the Cs-137 ratios are substantially different from the Unit 2 Cs-137 ratios. This indicates that the primary mechanisms for deposition of these radionuclides in the activated concrete is from activation or gaseous diffusion into the concrete.

The estimated source term in Curies for each nuclide was calculated by using the 541.5 foot elevation floor surface area of 229.21 square feet from Table 2. [16] A 1/2 inch thick depth of this surface area has a volume of 2.70E+05 cubic centimeters. Using a density for concrete of 2.40 g/cc yields a mass of 6.50E+05 grams for the 1/2 inch layer of the floor. This mass times the average concentration of the two cores equals the estimated source term for the nuclide. The

TSD 13-006 Revision 0 Page 105 of 200 calculated source terms in the first half inch of concrete based upon the Eberline average concentrations are shown in Table 67 and Table 68. 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 67 - Summary of Unit 1 541.5 EL Eberline Results Nuclide Max All Results pCi/g Min All Results pCi/g Avg All Results pCi/g First Half Inch Source Term Floor All Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Max Positive Results pCi/g Min Positive Results pCi/g Avg Positive Results pCi/g First Half Inch Source Term Floor Positive Ci Percent of Total Source Term H-3 2.16E+02 1.30E+02 1.73E+02 1.1E-04 7%

Cs-137 1.19E-01 2.16E+02 1.30E+02 1.73E+02 1.1E-04 8%

C-14 3.30E+00 9.89E-01 2.14E+00 1.4E-06 0.1%

Cs-137 1.48E-03 3.30E+00 3.30E+00 3.30E+00 2.1E-06 0.16%

Fe-55 1.01E+01 2.67E+00 6.40E+00 4.2E-06 0.3%

Co-60 3.31E-02 ND ND ND ND ND Ni-59 1.65E+01 7.28E+00 1.19E+01 7.7E-06 0.5%

Co-60 6.16E-02 ND ND ND ND ND Co-60 3.44E+02 4.25E+01 1.93E+02 1.3E-04 8%

Co-60 1.00E+00 3.44E+02 4.25E+01 1.93E+02 1.3E-04 9%

Ni-63 1.40E+02 2.97E+01 8.49E+01 5.5E-05 4%

Co-60 4.39E-01 1.40E+02 2.97E+01 8.49E+01 5.5E-05 4%

Sr-90 5.96E-01 3.14E-01 4.55E-01 3.0E-07 0.0%

Cs-137 3.13E-04 5.96E-01 5.96E-01 5.96E-01 3.9E-07 0.03%

Nb-94 1.97E+00 1.47E+00 1.72E+00 1.1E-06 0.1%

Co-60 8.91E-03 1.97E+00 1.47E+00 1.72E+00 1.1E-06 0.08%

Tc-99 1.33E+00 2.63E-01 7.95E-01 5.2E-07 0.0%

Cs-137 5.48E-04 ND ND ND ND ND Ag-108m 1.91E+00 1.46E+00 1.68E+00 1.1E-06 0.1%

Co-60 8.71E-03 ND ND ND ND ND Sb-125 8.23E+00 1.79E+00 5.01E+00 3.3E-06 0.2%

Cs-137 3.45E-03 ND ND ND ND ND Cs-134 1.44E+00 5.70E-01 1.00E+00 6.5E-07 0.0%

Cs-134 1.00E+00 ND ND ND ND ND Cs-137 2.81E+03 8.76E+01 1.45E+03 9.4E-04 62%

Cs-137 1.00E+00 2.81E+03 8.76E+01 1.45E+03 9.4E-04 71%

Eu-152 1.61E+02 1.06E+02 1.34E+02 8.7E-05 6%

Eu-152 1.00E+00 1.61E+02 1.06E+02 1.34E+02 8.7E-05 7%

Eu-154 1.26E+01 8.46E+00 1.05E+01 6.8E-06 0.449%

Eu-154 1.00E+00 1.26E+01 8.46E+00 1.05E+01 6.8E-06 0.51%

Eu-155 3.68E+00 3.34E+00 3.51E+00 2.3E-06 0.150%

Eu-152 2.63E-02 3.68E+00 3.68E+00 3.68E+00 2.4E-06 0.18%

Np-237 7.00E-02 2.74E-02 4.87E-02 3.2E-08 0.0%

Cs-137 3.36E-05 ND ND ND ND ND Pu-238 1.21E-01 5.20E-02 8.66E-02 5.6E-08 0.004%

Cs-137 5.97E-05 5.20E-02 5.20E-02 5.20E-02 3.4E-08 0.003%

Pu-239 5.45E-02 2.25E-02 3.85E-02 2.5E-08 0.002%

Cs-137 2.65E-05 5.45E-02 5.45E-02 5.45E-02 3.5E-08 0.003%

Pu-240 5.45E-02 2.25E-02 3.85E-02 2.5E-08 0.002%

Cs-137 2.65E-05 5.45E-02 5.45E-02 5.45E-02 3.5E-08 0.003%

Pu-241 7.16E+00 4.21E-01 3.79E+00 2.5E-06 0.162%

Cs-137 2.61E-03 ND ND ND ND ND Am-241 2.19E-01 4.38E-02 1.32E-01 8.6E-08 0.006%

Cs-137 9.06E-05 2.19E-01 2.19E-01 2.19E-01 1.4E-07 0.011%

Am-243 9.33E-02 3.04E-02 6.19E-02 4.0E-08 0.003%

Cs-137 4.26E-05 ND ND ND ND ND Cm-243 7.76E-02 3.15E-02 5.45E-02 3.5E-08 0.002%

Cs-137 3.76E-05 7.76E-02 7.76E-02 7.76E-02 5.0E-08 0.004%

Cm-244 7.72E-02 3.13E-02 5.43E-02 3.5E-08 0.002%

Cs-137 3.74E-05 7.72E-02 7.72E-02 7.72E-02 5.0E-08 0.004%

Total 1.5E-03 100%

Total 1.3E-03 100%

Note: Bold Italics are MDA values

TSD 13-006 Revision 0 Page 106 of 200 Table 68 - Summary of Unit 2 541.5 EL Eberline Results Nuclide Max All Results pCi/g Min All Results pCi/g Avg All Results pCi/g First Half Inch Source Term Floor All Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Max Positive Results pCi/g Min Positive Results pCi/g Avg Positive Results pCi/g First Half Inch Source Term Floor Positive Ci Percent of Total Source Term H-3 2.41E+02 3.29E+01 1.37E+02 8.9E-05 12%

Cs-137 2.58E-01 2.41E+02 3.29E+01 1.37E+02 8.9E-05 12%

C-14 1.84E+00 9.72E-01 1.41E+00 9.2E-07 0.1%

Cs-137 2.65E-03 1.84E+00 1.84E+00 1.84E+00 1.2E-06 0.2%

Fe-55 4.47E+00 2.01E+00 3.24E+00 2.1E-06 0.3%

Co-60 8.88E-02 ND ND ND ND ND Ni-59 7.46E+00 6.96E+00 7.21E+00 4.7E-06 1%

Co-60 1.98E-01 ND ND ND ND ND Co-60 5.00E+01 2.29E+01 3.65E+01 2.4E-05 3%

Co-60 1.00E+00 5.00E+01 2.29E+01 3.65E+01 2.4E-05 3%

Ni-63 7.31E+01 4.73E+01 6.02E+01 3.9E-05 5%

Co-60 1.65E+00 7.31E+01 4.73E+01 6.02E+01 3.9E-05 5%

Sr-90 3.72E-01 3.35E-01 3.54E-01 2.3E-07 0.03%

Cs-137 6.65E-04 3.72E-01 3.35E-01 3.54E-01 2.3E-07 0.03%

Nb-94 3.22E+00 2.48E+00 2.85E+00 1.9E-06 0.2%

Co-60 6.99E-03 3.22E+00 2.48E+00 2.85E+00 1.9E-06 0.3%

Tc-99 2.60E-01 2.50E-01 2.55E-01 1.7E-07 0.02%

Cs-137 4.79E-04 ND ND ND ND ND Ag-108m 4.17E+00 2.08E+00 3.12E+00 2.0E-06 0.3%

Co-60 8.57E-02 4.17E+00 2.08E+00 3.12E+00 2.0E-06 0.3%

Sb-125 5.99E+00 2.24E+00 4.11E+00 2.7E-06 0.4%

Cs-137 7.73E-03 ND ND ND ND ND Cs-134 1.30E+00 8.19E-01 1.06E+00 6.9E-07 0.1%

Cs-134 1.00E+00 1.30E+00 1.30E+00 1.30E+00 8.5E-07 0.1%

Cs-137 1.05E+03 1.56E+01 5.32E+02 3.5E-04 46%

Cs-137 1.00E+00 1.05E+03 1.56E+01 5.32E+02 3.5E-04 47%

Eu-152 3.97E+02 2.53E+02 3.25E+02 2.1E-04 28%

Eu-152 1.00E+00 3.97E+02 2.53E+02 3.25E+02 2.1E-04 29%

Eu-154 2.58E+01 2.17E+01 2.37E+01 1.5E-05 2%

Eu-154 1.00E+00 2.58E+01 2.17E+01 2.37E+01 1.5E-05 2%

Eu-155 7.03E+00 5.98E+00 6.51E+00 4.2E-06 1%

Eu-152 2.00E-02 7.03E+00 5.98E+00 6.51E+00 4.2E-06 1%

Np-237 4.49E-02 3.49E-02 3.99E-02 2.6E-08 0.003%

Cs-137 7.50E-05 ND ND ND ND ND Pu-238 3.18E-02 2.71E-02 2.95E-02 1.9E-08 0.003%

Cs-137 5.54E-05 ND ND ND ND ND Pu-239 1.39E-02 1.18E-02 1.28E-02 8.4E-09 0.001%

Cs-137 2.42E-05 ND ND ND ND ND Pu-240 1.39E-02 1.18E-02 1.28E-02 8.4E-09 0.001%

Cs-137 2.42E-05 ND ND ND ND ND Pu-241 3.30E+00 2.70E+00 3.00E+00 2.0E-06 0.26%

Cs-137 5.65E-03 ND ND ND ND ND Am-241 4.91E-02 1.94E-02 3.43E-02 2.2E-08 0.003%

Cs-137 6.44E-05 ND ND ND ND ND Am-243 5.18E-02 3.61E-02 4.40E-02 2.9E-08 0.004%

Cs-137 8.27E-05 5.18E-02 5.18E-02 5.18E-02 3.4E-08 0%

Cm-243 2.48E-02 1.43E-02 1.96E-02 1.3E-08 0.002%

Cs-137 3.68E-05 ND ND ND ND ND Cm-244 2.48E-02 1.43E-02 1.96E-02 1.3E-08 0.002%

Cs-137 3.68E-05 ND ND ND ND ND Total 7.5E-04 100%

Total 7.4E-04 100%

Note: Bold Italics are MDA values The above source terms were used to calculate the scaling factors which were used to estimate the hard-to-detect source terms based upon the estimated Co-60, Cs-137 and Eu-152 source terms from the In-House Gamma Spectroscopy results in Table 61. These estimated source terms are based upon the in-house gamma spectroscopy average concentration from all cores at the various depths. The Eberline gamma spectroscopy results are only from the first half inch pucks of the floor and do not include the walls or the other depths. The in-house gamma spectroscopy results provide a source term that is based upon the Co-60, Cs-137 and Eu-152

TSD 13-006 Revision 0 Page 107 of 200 depth profiles. The estimated total in-core area source terms including the hard-to-detect nuclides for Unit 1 and Unit 2 are provided in Table 69.

Table 69 - Estimated Unit 1 and 2 In-Core Source Terms Unit 1 541.5 Foot Unit 2 541.5 Foot Nuclide Scaling Nuclide Scaling Factor Total 541.5' Ci Percent of Total Source Term Scaling Nuclide Scaling Factor Total 541.5' Ci Percent of Total Source Term H-3 Cs-137 1.19E-01 4.69E-04 3.2%

Cs-137 2.58E-01 2.2E-04 1.1%

C-14 Cs-137 1.48E-03 5.82E-06 0.0%

Cs-137 2.65E-03 2.3E-06 0.0%

Fe-55 Co-60 3.31E-02 3.93E-05 0.3%

Co-60 8.88E-02 1.4E-04 0.7%

Ni-59 Co-60 6.16E-02 7.31E-05 0.5%

Co-60 1.98E-01 3.0E-04 1.5%

Co-60 Co-60 1.00E+00 1.19E-03 8.2%

Co-60 1.00E+00 1.5E-03 7.8%

Ni-63 Co-60 4.39E-01 5.21E-04 3.6%

Co-60 1.65E+00 2.5E-03 12.9%

Sr-90 Cs-137 3.13E-04 1.23E-06 0.0%

Cs-137 6.65E-04 5.7E-07 0.0%

Nb-94 Co-60 8.91E-03 1.06E-05 0.1%

Co-60 6.99E-03 1.1E-05 0.1%

Tc-99 Cs-137 5.48E-04 2.16E-06 0.0%

Cs-137 4.79E-04 4.1E-07 0.0%

Ag-108m Co-60 8.71E-03 1.03E-05 0.1%

Co-60 8.57E-02 1.3E-04 0.7%

Sb-125 Cs-137 3.45E-03 1.36E-05 0.1%

Cs-137 7.73E-03 6.6E-06 0.0%

Cs-134 Cs-134 1.00E+00 5.95E-05 0.4%

Cs-134 1.00E+00 6.6E-05 0.3%

Cs-137 Cs-137 1.00E+00 3.94E-03 27.3%

Cs-137 1.00E+00 8.6E-04 4.4%

Eu-152 Cs-137 1.00E+00 7.49E-03 51.9%

Eu-152 1.00E+00 1.3E-02 65.3%

Eu-154 Cs-137 1.00E+00 4.07E-04 2.8%

Eu-154 1.00E+00 7.3E-04 3.7%

Eu-155 Cs-137 2.63E-02 1.97E-04 1.4%

Eu-152 2.00E-02 2.6E-04 1.3%

Np-237 Cs-137 3.36E-05 1.32E-07 0.0%

Cs-137 7.50E-05 6.4E-08 0.0%

Pu-238 Cs-137 5.97E-05 2.35E-07 0.002%

Cs-137 5.54E-05 4.8E-08 2.44E-06 Pu-239 Cs-137 2.65E-05 1.05E-07 0.001%

Cs-137 2.42E-05 2.1E-08 1.06E-06 Pu-240 Cs-137 2.65E-05 1.05E-07 0.001%

Cs-137 2.42E-05 2.1E-08 1.06E-06 Pu-241 Cs-137 2.61E-03 1.03E-05 0.1%

Cs-137 5.65E-03 4.8E-06 0.0%

Am-241 Cs-137 9.06E-05 3.57E-07 0.002%

Cs-137 6.44E-05 5.5E-08 2.83E-06 Am-243 Cs-137 4.26E-05 1.68E-07 0.0%

Cs-137 8.27E-05 7.1E-08 0.0%

Cm-243 Cs-137 3.76E-05 1.48E-07 0.001%

Cs-137 3.68E-05 3.2E-08 1.62E-06 Cm-244 Cs-137 3.74E-05 1.47E-07 0.001%

Cs-137 3.68E-05 3.2E-08 1.62E-06 Total 0.014 100%

Total 0.020 100%

Note: Bold Italics are MDA values When the hard-to-detect nuclides are included in the mix, the Unit 1 total activity increased from 1.2E-2 Ci to 1.4E-2 Ci. This indicates that the source term in Unit 1 is dominated by the gamma emitting radionuclides such as Eu-152 and Cs-137 in particular. The inclusion of the hard-to-detect nuclides for Unit 2 increased the total estimated source term from1,6E-2 Ci to 2.0E-2 Ci.

TSD 13-006 Revision 0 Page 108 of 200 3.11. Summary of Reactor Building Results and Calculated End State Source Terms with Interior Concrete Remaining The scaled radionuclide inventories calculated for the Unit 1 and Unit 2 Reactor Building end states as of January 1, 2013 are provided in Table 70. These results are based upon the estimated gamma emitter source terms for (Co-60, Cs-134, Cs-137, Eu-152, Eu-154) from in-house analysis of the core pucks. These estimates are very conservative because core locations were biased toward areas that evidenced leaks and spills or exhibited high contact dose rates. In addition, the source term inventory included MDA values from the in-house gamma spectroscopy results.

The hard-to-detect nuclide source terms were estimated using scaling factors derived from positively identified off-site laboratory results. This is also very conservative since on the first half-inch puck from selected cores were sent for off-site laboratory analysis. Thus the estimated source term assumes the scaling factors for the first half-inch apply throughout the entire core profile. In addition, the positive results included some that were justified high for N-63 due to interference from other radionuclides.

Table 70 - Unit 1 and 2 January 1, 2013 Scaled Radionuclide Inventories s Nuclide Decay Const y-1 Unit 1 568 ft Ci Unit 1 Incore Area Ci Unit 1 Total Percent Inventory Unit 2 568 ft Ci Unit 2 Incore Area Ci Unit2 Total Percent Inventory H-3 5.63E-02 7.15E-03 4.69E-04 7.62E-03 0.11%

1.07E-03 2.2E-04 1.29E-03 0.07%

C-14 1.22E-04 7.46E-04 5.82E-06 7.52E-04 0.01%

5.34E-05 2.3E-06 5.57E-05 0.00%

Fe-55 2.53E-01 4.88E-03 3.93E-05 4.92E-03 0.07%

2.11E-02 1.4E-04 2.13E-02 1.13%

Ni-59 6.86E-06 1.03E-03 7.31E-05 1.11E-03 0.02%

4.43E-03 3.0E-04 4.73E-03 0.25%

Co-60 1.31E-01 2.08E-01 1.19E-03 2.09E-01 2.89%

2.55E-01 1.5E-03 2.57E-01 13.64%

Ni-63 6.92E-03 1.47E-01 5.21E-04 1.48E-01 2.05%

8.38E-01 2.5E-03 8.41E-01 44.69%

Sr-90 2.41E-02 3.64E-03 1.23E-06 3.64E-03 0.05%

7.02E-05 5.7E-07 7.08E-05 0.00%

Nb-94 3.41E-05 9.79E-04 1.06E-05 9.90E-04 0.01%

5.47E-03 1.1E-05 5.48E-03 0.29%

Tc-99 3.28E-06 9.08E-04 2.16E-06 9.10E-04 0.01%

1.04E-05 4.1E-07 1.09E-05 0.00%

Ag-108m 1.66E-03 1.78E-03 1.03E-05 1.79E-03 0.02%

8.57E-03 1.3E-04 8.70E-03 0.46%

Sb-125 2.51E-01 7.43E-03 1.36E-05 7.45E-03 0.10%

1.27E-03 6.6E-06 1.27E-03 0.07%

Cs-134 3.36E-01 2.00E-03 5.95E-05 2.06E-03 0.03%

1.07E-03 6.6E-05 1.13E-03 0.06%

Cs-137 2.30E-02 6.80E+00 3.94E-03 6.80E+00 94.17%

7.24E-01 8.6E-04 7.25E-01 38.54%

Eu-152 5.12E-02 1.38E-02 7.49E-03 2.13E-02 0.29%

3.92E-04 1.3E-02 1.31E-02 0.70%

Eu-154 7.88E-02 6.92E-03 4.07E-04 7.33E-03 0.10%

2.70E-04 7.3E-04 9.96E-04 0.05%

Eu-155 1.46E-01 2.42E-03 1.97E-04 2.62E-03 0.04%

3.82E-04 2.6E-04 6.37E-04 0.03%

Np-237 3.23E-07 9.11E-06 1.32E-07 9.24E-06 0.00%

5.42E-07 6.4E-08 6.07E-07 0.00%

Pu-238 7.90E-03 6.41E-05 2.35E-07 6.43E-05 0.001%

9.29E-07 4.8E-08 9.76E-07 0.00%

Pu-239 2.87E-05 2.24E-05 1.05E-07 2.25E-05 0.000%

4.71E-07 2.1E-08 4.92E-07 0.00%

Pu-240 1.06E-04 2.24E-05 1.05E-07 2.25E-05 0.000%

4.71E-07 2.1E-08 4.92E-07 0.00%

Pu-241 4.83E-02 7.99E-04 1.03E-05 8.10E-04 0.01%

6.89E-05 4.8E-06 7.37E-05 0.00%

Am-241 1.60E-03 7.94E-04 3.57E-07 7.94E-04 0.01%

1.51E-05 5.5E-08 1.52E-05 0.00%

Am-243 9.40E-05 1.50E-05 1.68E-07 1.52E-05 0.000%

1.53E-06 7.1E-08 1.60E-06 0.00%

Cm-243 2.43E-02 8.01E-05 1.48E-07 8.02E-05 0.001%

1.66E-06 3.2E-08 1.70E-06 0.00%

TSD 13-006 Revision 0 Page 109 of 200 Cm-244 3.83E-02 8.00E-05 1.47E-07 8.02E-05 0.001%

1.66E-06 3.2E-08 1.70E-06 0.00%

Totals 7.21E+00 1.44E-02 7.22E+00 100%

1.86E+00 1.95E-02 1.88E+00 100%

Note: Bold Italics are MDA values 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 71.

Table 71 - Unit 1 and 2 July 1, 2018 Scaled Radionuclide Inventories Nuclide Decay Const y-1 Unit 1 568 ft Ci Unit 1 Incore Area Ci Unit 1 Total Percent Inventor y

Unit 2 568 ft Ci Unit 2 Incore Area Ci Unit2 Total Percent Inventory H-3 5.63E-02 5.25E-03 3.44E-04 5.60E-03 0.09%

7.86E-04 1.6E-04 9.49E-04 0.06%

C-14 1.22E-04 7.45E-04 5.81E-06 7.51E-04 0.01%

5.34E-05 2.3E-06 5.56E-05 0.00%

Fe-55 2.53E-01 1.21E-03 9.76E-06 1.22E-03 0.02%

5.25E-03 3.4E-05 5.28E-03 0.33%

Ni-59 6.86E-06 1.03E-03 7.31E-05 1.11E-03 0.02%

4.43E-03 3.0E-04 4.73E-03 0.29%

Co-60 1.31E-01 1.01E-01 5.76E-04 1.01E-01 1.61%

1.24E-01 7.4E-04 1.25E-01 7.74%

Ni-63 6.92E-03 1.42E-01 5.02E-04 1.42E-01 2.27%

8.07E-01 2.4E-03 8.09E-01 50.28%

Sr-90 2.41E-02 3.19E-03 1.08E-06 3.19E-03 0.05%

6.15E-05 5.0E-07 6.20E-05 0.00%

Nb-94 3.41E-05 9.79E-04 1.06E-05 9.90E-04 0.02%

5.47E-03 1.1E-05 5.48E-03 0.34%

Tc-99 3.28E-06 9.08E-04 2.16E-06 9.10E-04 0.01%

1.04E-05 4.1E-07 1.09E-05 0.00%

Ag-108m 1.66E-03 1.76E-03 1.02E-05 1.77E-03 0.03%

8.49E-03 1.3E-04 8.62E-03 0.54%

Sb-125 2.51E-01 1.87E-03 3.42E-06 1.87E-03 0.03%

3.18E-04 1.7E-06 3.20E-04 0.02%

I-129 4.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00%

0.00E+00 0.0E+00 0.00E+00 0.00%

Cs-134 3.36E-01 3.16E-04 9.39E-06 3.25E-04 0.01%

1.69E-04 1.0E-05 1.79E-04 0.01%

Cs-137 2.30E-02 5.99E+00 3.47E-03 5.99E+00 95.46%

6.38E-01 7.6E-04 6.39E-01 39.70%

Pm-145 3.92E-02 0.00E+00 0.00E+00 0.00E+00 0.00%

0.00E+00 0.0E+00 0.00E+00 0.00%

Pm-147 2.64E-01 0.00E+00 0.00E+00 0.00E+00 0.00%

0.00E+00 0.0E+00 0.00E+00 0.00%

Eu-152 5.12E-02 1.04E-02 5.65E-03 1.61E-02 0.26%

2.96E-04 9.6E-03 9.92E-03 0.62%

Eu-154 7.88E-02 4.49E-03 2.64E-04 4.75E-03 0.08%

1.75E-04 4.7E-04 6.46E-04 0.04%

Eu-155 1.46E-01 1.09E-03 8.83E-05 1.18E-03 0.02%

1.72E-04 1.1E-04 2.86E-04 0.02%

Np-237 3.23E-07 9.11E-06 1.32E-07 9.24E-06 0.00%

5.42E-07 6.4E-08 6.07E-07 0.00%

Pu-238 7.90E-03 6.14E-05 2.25E-07 6.16E-05 0.001%

8.89E-07 4.6E-08 9.35E-07 0.00%

Pu-239 2.87E-05 2.24E-05 1.04E-07 2.25E-05 0.000%

4.71E-07 2.1E-08 4.92E-07 0.00%

Pu-240 1.06E-04 2.24E-05 1.04E-07 2.25E-05 0.000%

4.71E-07 2.1E-08 4.92E-07 0.00%

Pu-241 4.83E-02 6.13E-04 7.89E-06 6.21E-04 0.01%

5.28E-05 3.7E-06 5.65E-05 0.00%

Am-241 1.60E-03 7.87E-04 3.54E-07 7.87E-04 0.01%

1.50E-05 5.5E-08 1.50E-05 0.00%

Am-243 9.40E-05 1.50E-05 1.68E-07 1.52E-05 0.000%

1.53E-06 7.1E-08 1.60E-06 0.00%

Cm-243 2.43E-02 7.01E-05 1.30E-07 7.02E-05 0.001%

1.46E-06 2.8E-08 1.48E-06 0.00%

Cm-244 3.83E-02 6.48E-05 1.19E-07 6.49E-05 0.001%

1.35E-06 2.6E-08 1.37E-06 0.00%

Totals 6.27E+00 1.10E-02 6.28E+00 100%

1.59E+00 1.48E-02 1.61E+00 100%

Note: Bold Italics are MDA values

TSD 13-006 Revision 0 Page 110 of 200

4.

Calculations and Evaluations - Interior Concrete Removed In End State 4.1.

Unit 1 Source Terms The 565 foot source term consists of the floor area and the inner containment wall from the 588 to 565 elevation. These surface areas are calculated in TSD 13-005 [16] and summarized in Table 4. A maximum removable surface activity of 1000 dpm/100 cm2 with a 10% collection efficiency results in the following source terms in both Units Reactor Buildings.

Table 72 - Liner Surface Areas and Removable Contamination Source Terms Equivalent to 1000 dpm/100 cm2 Liner Surface Area ft2 100 cm2 U1 Detectable Beta SF U1 Ci U2 Detectable Beta SF U2 Ci 565 to 588 Wall 1.01E+04 9.40E+04 9.40E-01 4.50E-04 9.64E-01 4.39E-04 Sump Corrected Floor 1.54E+04 1.43E+05 9.40E-01 6.84E-04 2.94E-05 6.67E-04 Incore Liner Surface Areas 4.21E+03 3.91E+04 1.48E-01 1.19E-03 7.67E-01 2.30E-04 Totals 2.32E-03 1.34E-03 Multiplying each source terms removable contamination activity times the percentage of the mix in Table 25 for Unit 1 and 2 568 foot wall and floor and Table 71 for the Incore areas.

Table 73 - Summary of Bounding Liner Removable Surface Contamination Terms January 1, 2013 Nuclide Decay Const y-1 Unit 1 565 ft Ci Unit 1 Incore Area Ci Unit 1 Total Percent Inventory Unit 2 565 ft Ci Unit 2 Incore Area Ci Unit2 Total Percent Inventory H-3 5.63E-02 1.13E-06 3.86E-05 3.97E-05 1.71%

6.37E-07 2.6E-06 3.24E-06 0.24%

C-14 1.22E-04 1.17E-07 4.79E-07 5.96E-07 0.03%

3.17E-08 2.7E-08 5.85E-08 0.004%

Fe-55 2.53E-01 7.68E-07 3.23E-06 4.00E-06 0.17%

1.26E-05 1.6E-06 1.42E-05 1.060%

Ni-59 6.86E-06 1.63E-07 6.01E-06 6.18E-06 0.27%

2.63E-06 3.6E-06 6.19E-06 0.463%

Co-60 1.31E-01 3.27E-05 9.76E-05 1.30E-04 5.61%

1.52E-04 1.8E-05 1.70E-04 12.69%

Ni-63 6.92E-03 2.32E-05 4.29E-05 6.61E-05 2.84%

4.98E-04 3.0E-05 5.28E-04 39.51%

Sr-90 2.41E-02 5.73E-07 1.02E-07 6.75E-07 0.03%

4.17E-08 6.7E-09 4.85E-08 0.004%

Nb-94 3.41E-05 1.54E-07 8.70E-07 1.02E-06 0.0441%

3.25E-06 1.3E-07 3.38E-06 0.2528%

Tc-99 3.28E-06 1.43E-07 1.77E-07 3.20E-07 0.014%

6.20E-09 4.8E-09 1.10E-08 0.0008%

Ag-108m 1.66E-03 2.80E-07 8.50E-07 1.13E-06 0.049%

5.09E-06 1.5E-06 6.64E-06 0.4966%

Sb-125 2.51E-01 1.17E-06 1.12E-06 2.29E-06 0.099%

7.54E-07 7.8E-08 8.32E-07 0.0622%

Cs-134 3.36E-01 3.15E-07 4.89E-06 5.21E-06 0.22%

6.34E-07 7.8E-07 1.41E-06 0.11%

Cs-137 2.30E-02 1.07E-03 3.24E-04 1.39E-03 60.02%

4.30E-04 1.0E-05 4.41E-04 32.97%

Eu-152 5.12E-02 2.17E-06 6.16E-04 6.19E-04 26.63%

2.33E-07 1.5E-04 1.50E-04 11.24%

Eu-154 7.88E-02 1.09E-06 3.35E-05 3.46E-05 1.49%

1.61E-07 8.5E-06 8.69E-06 0.65%

Eu-155 1.46E-01 3.82E-07 1.62E-05 1.66E-05 0.713%

2.27E-07 3.0E-06 3.23E-06 0.241%

Np-237 3.23E-07 1.43E-09 1.09E-08 1.23E-08 0.001%

3.22E-10 7.6E-10 1.08E-09 0.000%

Pu-238 7.90E-03 1.01E-08 1.93E-08 2.94E-08 0.001%

5.52E-10 5.6E-10 1.11E-09 0.00008%

Pu-239 2.87E-05 3.53E-09 8.60E-09 1.21E-08 0.001%

2.80E-10 2.4E-10 5.24E-10 0.00004%

Pu-240 1.06E-04 3.53E-09 8.60E-09 1.21E-08 0.001%

2.80E-10 2.4E-10 5.24E-10 0.00004%

Pu-241 4.83E-02 1.26E-07 8.46E-07 9.72E-07 0.042%

4.09E-08 5.7E-08 9.79E-08 0.00733%

Am-241 1.60E-03 1.25E-07 2.94E-08 1.54E-07 0.01%

8.98E-09 6.5E-10 9.63E-09 0.00072%

Am-243 9.40E-05 2.37E-09 1.38E-08 1.62E-08 0.001%

9.07E-10 8.3E-10 1.74E-09 0.00013%

TSD 13-006 Revision 0 Page 111 of 200 Cm-243 2.43E-02 1.26E-08 1.22E-08 2.48E-08 0.001%

9.90E-10 3.7E-10 1.36E-09 0.00010%

Cm-244 3.83E-02 1.26E-08 1.21E-08 2.47E-08 0.001%

9.90E-10 3.7E-10 1.36E-09 0.00010%

Totals 1.13E-03 1.19E-03 2.32E-03 100%

1.11E-03 2.30E-04 1.34E-03 100%

Note: Bold Italics are MDA values The estimated source terms decay corrected to July 1, 2018 are provided in Table 74 - Summary of Liner Removable Surface Contamination Terms Decayed to July 1 2018 Nuclide Decay Const y-1 Unit 1 568 ft Ci Unit 1 Incore Area Ci Unit 1 Total Percent Inventory Unit 2 568 ft Ci Unit 2 Incore Area Ci Unit2 Total Percent Inventory H-3 5.63E-02 8.27E-07 2.83E-05 2.92E-05 1.54%

4.67E-07 1.9E-06 2.38E-06 0.21%

C-14 1.22E-04 1.17E-07 4.78E-07 5.96E-07 0.03%

3.17E-08 2.7E-08 5.84E-08 0.005%

Fe-55 2.53E-01 1.91E-07 8.03E-07 9.94E-07 0.05%

3.12E-06 4.0E-07 3.52E-06 0.314%

Ni-59 6.86E-06 1.63E-07 6.01E-06 6.18E-06 0.33%

2.63E-06 3.6E-06 6.19E-06 0.552%

Co-60 1.31E-01 1.59E-05 4.74E-05 6.32E-05 3.34%

7.36E-05 8.7E-06 8.23E-05 7.34%

Ni-63 6.92E-03 2.23E-05 4.13E-05 6.36E-05 3.36%

4.80E-04 2.9E-05 5.08E-04 45.30%

Sr-90 2.41E-02 5.02E-07 8.90E-08 5.91E-07 0.03%

3.66E-08 5.9E-09 4.24E-08 0.004%

Nb-94 3.41E-05 1.54E-07 8.70E-07 1.02E-06 0.0540%

3.25E-06 1.3E-07 3.38E-06 0.3011%

Tc-99 3.28E-06 1.43E-07 1.77E-07 3.20E-07 0.017%

6.20E-09 4.8E-09 1.10E-08 0.0010%

Ag-108m 1.66E-03 2.77E-07 8.42E-07 1.12E-06 0.059%

5.05E-06 1.5E-06 6.58E-06 0.5862%

Sb-125 2.51E-01 2.94E-07 2.81E-07 5.75E-07 0.030%

1.89E-07 2.0E-08 2.09E-07 0.0186%

Cs-134 3.36E-01 4.97E-08 7.72E-07 8.22E-07 0.04%

1.00E-07 1.2E-07 2.23E-07 0.02%

Cs-137 2.30E-02 9.43E-04 2.86E-04 1.23E-03 64.85%

3.79E-04 8.9E-06 3.88E-04 34.61%

Eu-152 5.12E-02 1.64E-06 4.65E-04 4.67E-04 24.64%

1.76E-07 1.1E-04 1.13E-04 10.10%

Eu-154 7.88E-02 7.06E-07 2.17E-05 2.24E-05 1.18%

1.04E-07 5.5E-06 5.64E-06 0.50%

Eu-155 1.46E-01 1.71E-07 7.27E-06 7.44E-06 0.393%

1.02E-07 1.3E-06 1.45E-06 0.129%

Np-237 3.23E-07 1.43E-09 1.09E-08 1.23E-08 0.001%

3.22E-10 7.6E-10 1.08E-09 0.000%

Pu-238 7.90E-03 9.66E-09 1.85E-08 2.82E-08 0.001%

5.29E-10 5.4E-10 1.06E-09 0.00009%

Pu-239 2.87E-05 3.53E-09 8.60E-09 1.21E-08 0.001%

2.80E-10 2.4E-10 5.24E-10 0.00005%

Pu-240 1.06E-04 3.53E-09 8.59E-09 1.21E-08 0.001%

2.80E-10 2.4E-10 5.24E-10 0.00005%

Pu-241 4.83E-02 9.65E-08 6.49E-07 7.45E-07 0.039%

3.14E-08 4.4E-08 7.51E-08 0.00669%

Am-241 1.60E-03 1.24E-07 2.91E-08 1.53E-07 0.01%

8.90E-09 6.4E-10 9.55E-09 0.00085%

Am-243 9.40E-05 2.37E-09 1.38E-08 1.62E-08 0.001%

9.07E-10 8.3E-10 1.74E-09 0.00016%

Cm-243 2.43E-02 1.10E-08 1.07E-08 2.17E-08 0.001%

8.66E-10 3.2E-10 1.19E-09 0.00011%

Cm-244 3.83E-02 1.02E-08 9.82E-09 2.00E-08 0.001%

8.02E-10 3.0E-10 1.10E-09 0.00010%

Totals 9.87E-04 9.08E-04 1.89E-03 100%

9.48E-04 1.74E-04 1.12E-03 100%

Note: Bold Italics are MDA values Any potential remaining source terms remaining after removal of all interior concrete will be minimal in comparison to the embedded concrete source terms.

TSD 13-006 Revision 0 Page 112 of 200

5.

Conclusions The methodology for characterization of embedded source term in Reactor Building end state concrete is consistent with the approaches and results used for the Trojan, San Onofre, Rancho Seco, Maine Yankee and Connecticut Yankee decommissionings. The Zion Unit 1 and 2 end states are comparable to the initial proposed end states for Maine Yankee and Connecticut Yankee. Unlike Maine Yankee and Connecticut Yankee, the Zion Incore area design precludes activation of the containment liner and exterior concrete. The activation profiles indicate that significant activation is limited to an 18 inch depth in the 23.5 inch thick Incore concrete wall and the 30 inch thick Incore concrete floor.

In addition, groundwater monitoring and soil characterization and scoping surveys to date indicate there is no significant soil and groundwater contamination present at Zion. Thus unlike Connecticut Yankee, there is no significant radionuclide sorption in concrete outside the containment liners that needs to be considered in the end state dose modeling and license termination criterion.

The source terms in both Units are driven by the embedded radionuclides in the first half inch of 3 foot thick 568 foot elevation concrete floors interior to the containment liner. The Incore area source terms are two orders of magnitude lower than the 568 foot concrete source terms.

The core location selection process and conservative assumptions used to estimate the source term profiles ensures that the estimated source terms are conservative and bounding of any potential end state source terms remaining after remediation and final characterization. Even assuming high levels of removable contamination and low smear collection efficiencies, potential source terms that will remain if all interior concrete is removed are minimal.

Since these source terms will be buried at a minimum of 20 feet, the resulting groundwater concentrations and associated exposure pathways will drive the potential doses to future site occupants.

6.

References

[1]

"Maine Yankee Atomic Power Company (MYAPC) License Termination Plan Revision 4 February 28, 2005".

[2]

"IAEA Power Reactor Information System web site.

http://www.iaea.org/programmes/a2".

[3]

"IAEA-RDS-2/32 Nuclear Power Reactors in the World, Reference Data Series No. 2, 2012 Edition, Vienna, 2012 http://www-pub.iaea.org/books/IAEABooks/8954/Nuclear-Power-Reactors-in-the-World-2012-Edition".

[4]

"EPRI 1015502, Concrete Characterization and Dose Modeling During Plant Decommissioning Detailed Experience 1993 - 2007, March 2008".

[5]

"NUREG/CR - 5849, Manual for Conducting Radiological Surveys in Support of License Termination, Draft Report for Comment, ML090640319".

[6]

"10 CFR 40 PART 141National Primary Drinking Water Regulations,"

http://www.ecfr.gov/cgi-bin/text-

TSD 13-006 Revision 0 Page 113 of 200 idx?c=ecfr&tpl=/ecfrbrowse/Title40/40cfr141_main_02.tpl.

[7]

"EPA National Primary Drinking Water Regulations, http://water.epa.gov/drink/contaminants/index.cfm#Radionuclides".

[8]

"Memorandum of Understanding Between the Environmental Protection Agency and the Nuclear Regulatory Commission Consultation and Finality On Decommissioning and Decontamination of Contaminated Sites, October 12, 2002,"

http://www.nrc.gov/reading-rm/doc-collections/news/2002/mou2fin.pdf.

[9]

"Two Approaches to Reactor Decommissioning 10 CFR 50 License Termination and License Amendment, B Watson et al Waste Management Conference, 2006".

[10]

"PGE-1061, Trojan Nuclear Plant Defueled Safety Analysis Report and License Termination Plan (PGE-1078), Revision 22, June 6, 2005".

[11]

"NRC Memorandum, Meeting with Connecticut Yankee Atomic Power Company to Update Decommissioning And License Termination Plan Status, Ted Smith, August 24, 2004 Ascension No. ML042370290".

[12]

"BYR 2005-094,Compliance with Beneficial Use Determination (BUD)

Subsurface Structures/Concrete Rubble BWPSW013, November 2, 2005".

[13]

"Final Report Phase VII Appendix A3 Survey Unit Release Record 9312-0001, Containment (Former Radiologically Controlled Area) May 2007 Ascension No.

ML071730449".

[14]

"BNL-73965-2005-IR, Estimates for Release of Radionuclides from Potentially Contaminated Concrete at the Haddam Neck Nuclear Plant, Terry Sullivan, September 2004".

[15]

"Zion Nuclear Power Station, Units 1 And 2 Asset Sale Agreement by and Among Exelon Generation Company, LLC as Seller, ZionSolutions, LLC as Buyer, EnergySolutions, LLC as Buyer's Parent and EnergySolutions, Inc. as Guarantor, December 11, 2007".

[16]

"TSD 13-005, Unit 1 &2 Reactor Building Estimated End State Concrete Volumes and Surface Areas".

[17]

"ZS-RP-107-001-001, Rev. 0 - Characterization Survey Package Development".

[18]

"ComEd Zion Station Historical Site Assessment, Version 1 - August, 1999".

[19]

"Zion Updated Final Safety Analysis Report (UFSAR) July 1993".

[20]

"9.1 Report 07-046D-RE-088, Zion Units 1 and 2 Activation Analysis and Component Characterization, January 2008, WMG Project 07-046D".

TSD 13-006 Revision 0 Page 114 of 200

[21]

"TSD 11-005, Estimated Reactor Vessel Segmentation Work Area Dose Rates".

[22]

"Sandia Report - SAND2004-2757, Calculation of the Radionuclides in PWR Spent Fuel Samples for SFR Experiment Planning, Robert E. Naegeli June 2004".

[23]

"BNL-71537-2003 Assessment of Release Rates for Radionuclides in Activated Concrete T.M. Sullivan August 21, 2003".

[24]

"CY-HP-0202, Rev. 0, "Calculation of Future Groundwater Dose Resulting From Residual Radioactivity in Concrete to Remain in Groundwater Saturated Zone Using the CY LTP Basement Fill Model, May 23, 2007 NRC Asc ML071870494".

7.

Attachments 7.1.

Attachment A - Unit 1 and 2 568 Elevation Core Locations 7.2.

Attachment B - U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results 7.3.

Attachment C - U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results 7.4.

Attachment D - U1 & 2 568 Elevation First Half Inch Eberline Results 7.5.

Attachment E - Decay Corrected U1 & 2 568 Elevation First Half Inch Eberline Results 7.6.

Attachment F - Key Radionuclide Ratios Decay Corrected U1 & 2 568 Elevation Eberline Results 7.7.

Attachment G - U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results 7.8.

Attachment H - U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results 7.9.

Attachment I - U1 & 2 541.5 Foot Elevation First Half Inch Eberline Results 7.10. Attachment J - Radionuclide Emissions and Yields

Attachment A Unit 1 and 2 568 Elevation Core Locations TSD 13-006 Revision 0 Page 115 of 200

Attachment A Unit 1 and 2 568 Elevation Core Locations TSD 13-006 Revision 0 Page 116 of 200

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 117 of 200 U1 CTMT 568 IMB Loop A Core Collection Date 6/12/12 B101102-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

137 8/27/12 0738 8/23/12 14:52 300 131 96.9 30.8 3.46E+04 3.47E+04 0.5 8/27/12 0739 8/23/12 14:53 300 131 65.9 23.1 2.38E+04 2.39E+04 Puck 2 0.5 150 7/25/12 1127 7/18/12 13:37 1000 167 1.58 0.13 2.26 3.97E+00 1

7/25/12 1146 7/18/12 13:37 1000 167 1.43 0.13 2.12 3.68E+00 Puck 3 1

141 7/25/12 1205 7/18/12 13:37 1000 167 0.39 0.07 1.36 1.83E+00 1.5 7/25/12 1243 7/18/12 13:37 1000 167 0.47 0.13 1.23 1.82E+00 B101102-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 92.4 27.3 3.43E+04 77.6 23.9 2.90E+04 62.9 20.5 2.36E+04 Puck 2 1.5 0.1 2.24E+00 1.4 0.1 2.2 1.3 0.1 2.10E+00 Puck 3 0.4 0.1 1.35E+00 0.4 0.1 1.3 0.4 0.1 1.22E+00

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 118 of 200 U1 CTMT 568 IMB Loop A Core Collection Date 6/12/12 B101102-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

139 8/23/12 1416 8/23/12 14:10 300 131 191.0 56.4 4.04E+05 4.04E+05 0.5 8/23/12 1422 8/23/12 14:11 300 131 122.0 44.8 2.89E+05 2.89E+05 Puck 2 0.5 127 7/24/12 1149 7/18/12 13:25 1000 167 10.6 1.17 1.16E+04 1.16E+04 1

7/24/12 1208 7/18/12 13:25 1000 167 10.8 1.04 9.03E+03 9.04E+03 Puck 3 1

144 7/24/12 1436 7/18/12 13:25 1000 167 12.0 0.4 1.63E+03 1.64E+03 1.5 7/24/12 1455 7/18/12 13:25 1000 167 12.1 0.3 1.30E+03 1.31E+03 Puck 4 1.5 137 7/25/12 630 7/18/12 13:26 1000 167 22.9 0.4 384.0 4.07E+02 2

7/25/12 649 7/18/12 13:26 1000 167 30.2 0.4 358.0 3.89E+02 Puck 5 2

134 7/25/12 708 7/18/12 13:27 1000 167 40.5 0.4 101.0 1.42E+02 2.5 7/25/12 725 7/18/12 13:27 1000 167 35.8 0.4 76.8 1.13E+02 Puck 6 2.5 129 7/25/12 745 7/18/12 13:27 1000 167 11.4 0.2 31.6 4.32E+01 3

7/25/12 803 7/18/12 13:27 1000 167 10.8 0.2 26.9 3.79E+01 Puck 7 3

206 7/25/12 822 7/18/12 13:28 1000 167 7.2 0.2 24.5 3.19E+01 3.5 7/25/12 841 7/18/12 13:28 1000 167 6.6 0.2 18.9 2.57E+01 Puck 8 3.5 131 7/25/12 902 7/18/12 13:29 1000 167 4.0 0.2 9.6 1.38E+01 4

7/25/12 949 7/18/12 13:29 1000 167 3.9 0.1 9.5 1.35E+01 Puck 9 4

116 7/25/12 1008 7/18/12 13:29 1000 167 4.2 0.2 15.3 1.97E+01 4.5 7/25/12 1026 7/18/12 13:30 1000 167 4.3 0.2 12.4 1.68E+01 Puck 10 4.5 167 7/25/12 1045 7/18/12 13:30 1000 167 5.2 0.1 9.8 1.52E+01 5

7/25/12 1103 7/18/12 13:30 1000 167 6.3 0.2 11.2 1.76E+01

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 119 of 200 B101102-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 182.2 50.0 4.01E+05 149.3 44.8 3.44E+05 116.4 39.7 2.87E+05 Puck 2 10.0 1.0 1.15E+04 10.1 0.9 1.02E+04 10.2 0.9 8.94E+03 Puck 3 11.3 0.3 1.61E+03 11.3 0.3 1.45E+03 11.4 0.3 1.29E+03 Puck 4 21.6 0.3 3.80E+02 25.0 0.4 3.67E+02 28.4 0.4 3.54E+02 Puck 5 38.1 0.4 9.99E+01 35.9 0.3 8.80E+01 33.7 0.3 7.60E+01 Puck 6 10.7 0.2 3.13E+01 10.5 0.2 2.89E+01 10.2 0.2 2.66E+01 Puck 7 6.8 0.1 2.42E+01 6.5 0.1 2.15E+01 6.2 0.1 1.87E+01 Puck 8 3.8 0.1 9.50E+00 3.7 0.1 9.44E+00 3.7 0.1 9.39E+00 Puck 9 4.0 0.2 1.51E+01 4.0 0.2 1.37E+01 4.0 0.1 1.23E+01 Puck 10 4.9 0.1 9.73E+00 5.4 0.1 1.04E+01 5.9 0.1 1.11E+01 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 120 of 200 U1 CTMT 568 IMB Loop B Core Collection Date 6/11/12 B101103-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

139 8/27/12 733 8/23/12 14:24 300 131 218.0 38 3.05E+05 3.05E+05 0.5 8/27/12 734 8/23/12 14:24 300 131 168.0 36.3 2.50E+05 2.50E+05 Puck 2 0.5 161 7/19/12 622 7/19/12 6:02 1000 166 6.1 1.3 2.62E+04 2.62E+04 1

7/19/12 641 7/19/12 6:06 1000 166 6.5 1.4 2.53E+04 2.53E+04 Puck 3 1

126 7/19/12 724 7/19/12 6:32 1000 166 9.6 1.3 1.96E+04 1.96E+04 1.5 7/19/12 743 7/19/12 6:32 1000 166 8.7 1.4 1.88E+04 1.88E+04 Puck 4 1.5 118 7/19/12 802 7/19/12 7:45 1000 166 10.2 1.0 1.27E+04 1.27E+04 2

7/19/12 821 7/19/12 7:45 1000 166 10.4 1.0 1.27E+04 1.27E+04 Puck 5 2

319 Fragmented Sample Not Analyzed 2.5 Puck 6 2.5 124 7/19/12 925 7/18/12 12:52 1000 167 14.8 0.6 9.28E+03 9.30E+03 3

7/19/12 944 7/18/12 12:53 1000 167 15.2 0.8 8.20E+03 8.22E+03 Puck 7 3

139 7/19/12 1014 7/18/12 12:53 1000 167 19.4 0.8 5.39E+03 5.41E+03 3.5 7/19/12 1033 7/18/12 12:53 1000 167 19.6 0.6 5.34E+03 5.36E+03 Puck 8 3.4 121 7/19/12 1055 7/18/12 12:53 1000 167 21.4 0.6 4.69E+03 4.71E+03 4

7/19/12 1119 7/18/12 12:54 1000 167 21.5 0.6 4.89E+03 4.91E+03

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 121 of 200 B101103-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 207.9 33.7 3.02E+05 184.1 32.9 2.75E+05 160.3 32.2 2.48E+05 Puck 2 5.7 1.1 2.59E+04 5.9 1.2 2.55E+04 6.1 1.2 2.50E+04 Puck 3 9.0 1.1 1.94E+04 8.6 1.1 1.90E+04 8.2 1.2 1.86E+04 Puck 4 9.6 0.9 1.26E+04 9.7 0.9 1.26E+04 9.8 0.8 1.26E+04 Puck 5 Fragmented Sample Not Analyzed Puck 6 13.9 0.5 9.18E+03 14.1 0.6 8.65E+03 14.3 0.7 8.11E+03 Puck 7 18.3 0.6 5.33E+03 18.4 0.6 5.31E+03 18.5 0.5 5.28E+03 Puck 8 20.2 0.5 4.64E+03 20.2 0.5 4.74E+03 20.2 0.5 4.84E+03 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 122 of 200 U1 CTMT 568 IMB Loop B Core Collection Date 6/11/12 B101103-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

128 8/27/12 740 8/23/12 15:06 300

-73 7970.0 80.9 9.86E+04 1.07E+05 0.5 8/27/12 741 8/23/12 15:06 300

-73 5980.0 74.0 7.08E+04 7.69E+04 Puck 2 0.5 129 7/10/12 722 7/10/12 7:06 1000

-29 36.4 0.5 323.0 3.60E+02 1

7/10/12 704 7/9/12 12:04 1000

-28 33.8 NR 247.0 2.81E+02 Puck 3 1

153 7/10/12 742 7/9/12 12:04 1000

-28 15.8 0.3 31.5 4.76E+01 1.5 7/10/12 800 7/9/12 12:04 1000

-28 13.0 0.2 37.0 5.02E+01 Puck 4 1.5 481 7/10/12 822 7/9/12 12:08 1000

-28 1.95 0.06 5.5 7.49E+00 2

7/10/12 841 7/9/12 12:08 1000

-28 2.7 0.1 7.1 9.87E+00 Puck 5 2

126 7/10/12 859 7/9/12 12:09 1000

-28 13.2 0.3 132.0 1.46E+02 2.5 7/10/12 916 7/9/12 12:09 1000

-28 12.2 0.3 143.0 1.55E+02 Puck 6 2.5 133 7/10/12 934 7/9/12 12:09 1000

-28 7.9 0.2 12.2 2.03E+01 3

7/10/12 952 7/9/12 12:10 1000

-28 7.5 0.2 13.2 2.09E+01 Puck 7 3

144 7/10/12 1218 7/9/12 12:10 1000

-28 5.0 0.2 10.2 1.54E+01 3.5 7/11/12 724 7/11/12 6:42 1000

-30 4.9 0.2 9.9 1.50E+01 Puck 8 3.5 139.77 10/17/12 819 10/17/12 8:19 1000

-128 5.5 0.2 9.5 1.53E+01 4

10/17/12 838 10/17/12 8:19 1000

-128 6.2 0.2 8.4 1.47E+01 Puck 9 4

137.19 10/17/12 917 10/17/12 9:16 1000

-128 17.1 0.3 11.8 2.92E+01 4.5 10/17/12 937 10/17/12 9:17 1000

-128 18.5 0.3 13.4 3.22E+01 xs 4.5 117.25 10/17/12 1001 10/17/12 10:01 1000

-128 61.3 0.4 66.0 1.28E+02 Note: NR = Not Reported

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 123 of 200 B101103-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 8182.4 86.5 99056.7 7160.9 82.8 85092.3 6139.4 79.2 71127.9 Puck 2 36.8 0.5 323.6 35.5 0.5 285.5 34.1 NR 247.4 Puck 3 16.0 0.3 31.6 14.5 0.3 34.3 13.1 0.3 37.1 Puck 4 2.0 0.1 5.5 2.4 0.1 6.3 2.8 0.1 7.1 Puck 5 13.3 0.3 132.2 12.8 0.3 137.7 12.3 0.3 143.3 Puck 6 7.9 0.2 12.2 7.8 0.2 12.7 7.6 0.2 13.2 Puck 7 5.1 0.2 10.2 5.0 0.2 10.1 4.9 0.2 9.9 Puck 8 5.8 0.2 9.6 6.1 0.2 9.0 6.4 0.2 8.4 Puck 9 17.9 0.3 11.9 18.6 0.3 12.7 19.4 0.3 13.5 xs 64.2 0.5 66.5 64.2 0.5 66.5 Note: NR = Not Reported Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 124 of 200 U1 CTMT 568 IMB Loop C Core Collection Date 6/12/12 B101104-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

155 8/21/12 1443 8/21/12 14:34 300 133 125.0 54.3 4.93E+05 4.93E+05 0.5 8/21/12 1450 8/21/12 14:41 300 133 101.0 56.1 4.14E+05 4.14E+05 Puck 2 0.5 149 8/21/12 1456 8/21/12 14:41 300 133 29.1 21.2 1.26E+05 1.26E+05 1

8/21/12 1502 8/21/12 14:42 300 133 27.8 26.2 1.24E+05 1.24E+05 Puck 3 1

147 8/21/12 1508 8/21/12 14:42 300 133 25.6 22.9 1.11E+05 1.11E+05 1.5 8/21/12 1513 8/21/12 14:42 300 133 31.9 25.5 1.07E+05 1.07E+05 Puck 4 1.5 149 8/15/12 1115 8/15/12 10:58 1000 139 5.6 3.8 4.26E+04 4.26E+04 2

8/15/12 1053 8/15/12 9:52 1000 139 7.2 3.1 4.01E+04 4.01E+04 Puck 5 2

146 8/15/12 1136 8/15/12 11;19 1000 139 4.0 2.4 2.16E+04 2.16E+04 2.5 8/15/12 1200 8/15/12 11:20 1000 139 5.3 2.2 1.81E+04 1.81E+04 Puck 6 2.5 150 8/15/12 1222 8/15/12 12:05 1000 139 4.4 2.3 1.43E+04 1.43E+04 3

8/15/12 1241 8/15/12 12:06 1000 139 4.7 2.6 1.48E+04 1.48E+04 Puck 7 3

151 8/15/12 1523 8/15/12 15:05 1000 139 4.9 2.5 1.92E+04 1.92E+04 3.5 8/15/12 1543 8/15/12 15:06 1000 139 5.3 1.4 1.96E+04 1.96E+04 Puck 8 3.5 144 8/16/12 0732 8/16/12 7:14 1000 138 9.3 1.2 1.98E+04 1.98E+04 4

8/16/12 0752 8/16/12 7:14 1000 138 9.4 1.5 2.10E+04 2.10E+04 Puck 9 4

140 8/16/12 0812 8/16/12 7:54 1000 138 6.4 1.9 1.45E+04 1.45E+04 4.5 8/16/12 0835 8/16/12 7:55 1000 138 5.8 1.1 1.30E+04 1.30E+04

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 125 of 200 B101104-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 119.2 48.0 4.89E+05 107.7 48.8 4.50E+05 96.3 49.6 4.11E+05 Puck 2 27.7 18.8 1.25E+05 27.1 21.0 1.24E+05 26.5 23.2 1.23E+05 Puck 3 24.4 20.3 1.10E+05 27.4 21.4 1.08E+05 30.4 22.6 1.06E+05 Puck 4 5.3 3.4 4.22E+04 6.1 3.1 4.10E+04 6.9 2.8 3.97E+04 Puck 5 3.8 2.1 2.14E+04 4.4 2.0 1.97E+04 5.0 2.0 1.79E+04 Puck 6 4.2 2.0 1.42E+04 4.3 2.1 1.44E+04 4.5 2.3 1.47E+04 Puck 7 4.6 2.2 1.90E+04 4.9 1.7 1.92E+04 5.1 1.2 1.94E+04 Puck 8 8.9 1.1 1.96E+04 8.9 1.2 2.02E+04 9.0 1.3 2.08E+04 Puck 9 6.1 1.7 1.44E+04 5.8 1.3 1.36E+04 5.5 1.0 1.29E+04 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 126 of 200 U1 CTMT 568 IMB Loop C B101104-CJFCCV-002 Core Collection Date 6/12/12 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

136 8/23/12 1445 8/23/12 14:39 300 131 463.0 58.6 4.40E+05 4.41E+05 0.5 8/23/12 1451 8/23/12 14:39 300 131 342.0 49.7 3.08E+05 3.08E+05 Puck 2 0.5 130 7/10/12 1314 7/9/12 12:11 1000 176 11.2 0.4 1.92E+03 1.93E+03 1

7/9/12 1332 7/9/12 13:34 1000 176 11.9 0.5 1.78E+03 1.79E+03 Puck 3 1

138 7/10/12 1351 7/9/12 13:34 1000 176 8.1 0.3 532.0 5.40E+02 1.5 7/10/12 1409 7/9/12 13:34 1000 176 7.6 0.3 428.0 4.36E+02 Puck 4 1.5 126 7/10/12 1431 7/9/12 13:34 1000 176 5.1 0.2 126.0 1.31E+02 2

7/10/12 1449 7/9/12 13:35 1000 176 5.8 0.2 115.0 1.21E+02 Puck 5 2

128 7/10/12 1512 7/9/12 13:35 1000 176 8.1 0.3 66.6 7.49E+01 2.5 7/10/12 1532 7/9/12 13:35 1000 176 8.8 0.3 99.3 1.08E+02 Puck 6 2.5 130 7/11/12 705 7/11/12 6:42 1000 174 6.3 0.2 13.0 1.95E+01 3

7/11/12 0648 7/9/12 13:36 1000 176 6.3 0.2 11.1 1.76E+01 Puck 7 3

127 7/11/12 748 7/9/12 13:36 1000 176 3.4 0.2 10.9 1.44E+01 3.5 7/11/12 808 7/9/12 13:37 1000 176 2.5 0.2 10.3 1.30E+01 Puck 8 3.5 139 7/11/12 0830 7/9/12 13:37 1000 176 0.7 0.1 6.0 6.78E+00 4

7/11/12 0847 7/9/12 13:37 1000 176 0.7 0.1 6.2 7.06E+00

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 127 of 200 B101104-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 441.7 51.9 4.36E+05 383.9 48.0 3.71E+05 326.2 44.0 3.05E+05 Puck 2 10.5 0.3 1898.7 10.8 0.4 1.83E+03 11.2 0.4 1760.3 Puck 3 7.6 0.3 526.1 7.4 0.3 4.75E+02 7.1 0.3 423.3 Puck 4 4.8 0.2 124.6 5.1 0.2 1.19E+02 5.4 0.1 113.7 Puck 5 7.6 0.2 65.9 7.9 0.2 8.20E+01 8.3 0.2 98.2 Puck 6 5.9 0.2 12.9 5.9 0.2 1.19E+01 5.9 0.2 11.0 Puck 7 3.2 0.1 10.8 2.8 0.1 1.05E+01 2.4 0.1 10.2 Puck 8 0.7 0.1 5.9 0.7 0.1 6.03E+00 0.6 0.1 6.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 128 of 200 U1 CTMT 568 IMB Loop D Core Collection Date 6/11/12 B101105-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

133 8/22/12 1440 8/22/12 14:11 300 132 3.66E+04 116.0 2560.0 3.93E+04 0.5 8/22/12 1427 8/22/12 14:11 300 132 3.34E+04 117.0 2100.0 3.56E+04 Puck 2 0.5 140 8/22/12 1449 8/22/12 14:13 300 132 1.59E+04 73.2 224.0 1.62E+04 1

8/22/12 1455 8/22/12 14:21 300 132 1.50E+04 78.5 152.0 1.52E+04 Puck 3 1

144 8/22/12 1502 8/22/12 14:21 300 132 7020.0 49.5 76.7 7.15E+03 1.5 8/22/12 1508 8/22/12 14:21 300 132 6500.0 46.3 75.5 6.62E+03 Puck 4 1.5 142 7/25/12 1314 7/25/12 12:52 1000 160 2840.0 2.5 27.2 2.87E+03 2

7/25/12 1336 7/25/12 12:52 1000 160 2580.0 2.4 23.8 2.61E+03 Puck 5 2

128 7/25/12 1357 7/25/12 12:52 1000 160 571.0 1.1 11.2 5.83E+02 2.5 7/25/12 1416 7/25/12 12:53 1000 160 508.0 1.2 9.6 5.19E+02 Puck 6 2.5 121 7/25/12 1436 7/25/12 12:54 1000 160 259.0 0.8 6.6 2.66E+02 3

7/25/12 1455 7/25/12 12:54 1000 160 231.0 0.8 5.8 2.38E+02 Puck 7 3

111 7/26/12 1438 7/25/12 12:54 1000 160 127.0 0.6 4.9 1.32E+02 3.5 7/26/12 1516 7/25/12 12:54 1000 160 127.0 0.6 4.2 1.32E+02

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 129 of 200 B101105-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 34899.8 102.7 2538.7 33374.2 103.2 2.31E+03 31848.5 103.6 2082.5 Puck 2 15161.4 64.8 222.1 14732.3 67.2 1.86E+02 14303.2 69.5 150.7 Puck 3 6693.9 43.8 76.1 6446.0 42.4 7.55E+01 6198.1 41.0 74.9 Puck 4 2680.9 2.1 26.9 2558.2 2.1 2.52E+01 2435.5 2.0 23.6 Puck 5 539.0 1.0 11.1 509.3 1.0 1.03E+01 479.5 1.0 9.5 Puck 6 244.5 0.7 6.5 231.3 0.7 6.13E+00 218.1 0.7 5.8 Puck 7 119.9 0.5 4.8 119.9 0.5 4.48E+00 119.9 0.5 4.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 130 of 200 U1 CTMT 568 IMB Loop D Core Collection Date 6/11/12 B101105-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

134 8/22/12 1434 8/22/12 14:12 300 132 1040.0 33.6 3.07E+04 3.18E+04 0.5 8/22/12 1440 8/22/12 14:12 300 132 747.0 39.3 2.43E+04 2.51E+04 Puck 2 0.5 137 7/31/12 0724 7/25/12 13:00 1000 160 16.9 3.4 1.00E+04 1.00E+04 1

7/31/12 0745 7/25/12 13:00 1000 160 17.0 1.0 9.89E+03 9.91E+03 Puck 3 1

139 7/31/12 0806 7/25/12 13:01 1000 160 24.2 2.1 7.16E+03 7.19E+03 1.5 7/31/12 0825 7/25/12 13:01 1000 160 25.2 1.5 7.24E+03 7.27E+03 Puck 4 1.5 137 8/1/12 1508 7/25/12 13:01 1000 160 27.9 1.2 6.47E+03 6.50E+03 2

8/1/12 1527 7/25/12 13:02 1000 160 28.7 1.7 6.79E+03 6.82E+03 Puck 5 2

136 8/2/12 1522 8/2/12 14:49 1000 152 26.0 1.2 5.92E+03 5.95E+03 2.5 8/2/12 1457 7/25/12 13:35 1000 160 24.6 1.3 5.61E+03 5.64E+03 Puck 6 2.5 137 8/8/12 0649 7/25/12 13:37 1000 160 20.0 0.5 4.15E+03 4.17E+03 3

8/8/12 0708 7/25/12 13:37 1000 160 19.9 0.6 4.12E+03 4.14E+03 Puck 7 3

140 8/8/12 0726 7/25/12 13:41 1000 160 15.9 0.4 2.69E+03 2.71E+03 3.5 8/8/12 0743 7/25/12 13:41 1000 160 14.7 0.5 2.42E+03 2.44E+03 Puck 8 3.5 139 8/8/12 0806 7/25/12 13:42 1000 160 15.0 0.4 1.53E+03 1.55E+03 4

8/8/12 0826 7/25/12 13:42 1000 160 17.1 0.4 1.76E+03 1.78E+03 Puck 9 4

139 8/8/12 0845 7/25/12 13:43 1000 160 20.3 0.6 2.34E+03 2.36E+03 4.5 8/8/12 0904 7/25/12 13:43 1000 160 20.8 0.4 2.38E+03 2.40E+03 Puck 10 4.5 136 8/15/12 0833 7/25/12 13:44 1000 160 18.3 0.5 2.57E+03 2.59E+03 5

8/15/12 0851 7/25/12 13:44 1000 160 18.3 0.8 2.76E+03 2.78E+03

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 131 of 200 B101105-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 991.7 29.8 30444.5 852.0 32.3 2.73E+04 712.3 34.8 24097.8 Puck 2 16.0 2.9 9899.2 16.0 1.9 9.84E+03 16.0 0.8 9790.3 Puck 3 22.8 1.8 7087.8 23.3 1.6 7.13E+03 23.8 1.3 7167.0 Puck 4 26.3 1.0 6404.8 26.7 1.3 6.56E+03 27.1 1.5 6721.6 Puck 5 24.6 1.0 5863.3 23.9 1.1 5.71E+03 23.2 1.1 5553.5 Puck 6 18.9 0.4 4108.2 18.8 0.5 4.09E+03 18.8 0.5 4078.5 Puck 7 15.0 0.3 2662.9 14.4 0.4 2.53E+03 13.9 0.4 2395.6 Puck 8 14.2 0.3 1514.6 15.2 0.3 1.63E+03 16.1 0.4 1742.3 Puck 9 19.2 0.5 2316.4 19.4 0.4 2.34E+03 19.6 0.3 2356.0 Puck 10 17.3 0.4 2544.1 17.3 0.5 2.64E+03 17.3 0.7 2732.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 132 of 200 U1 CTMT OMB A Loop Core Collection Date 7/18/12 B101106-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

135 8/16/12 0902 7/25/12 16:11 1000 160 18.4 0.5 1390.0 1.41E+03 0.5 8/16/12 0920 7/25/12 16:11 1000 160 9.8 0.4 652.0 6.62E+02 Puck 2 0.5 142 8/16/12 0939 7/25/12 16:12 1000 160 0.7 0.2 40.9 4.18E+01 1

8/16/12 0957 7/25/12 16:12 1000 160 0.7 0.1 44.2 4.50E+01 Puck 3 1

143 8/16/12 1014 7/25/12 16:13 1000 160 0.6 0.2 15.4 1.62E+01 1.5 8/16/12 1031 7/25/12 16:13 1000 160 0.7 0.1 13.6 1.44E+01 Puck 4 1.5 137.82 10/16/12 1005 10/16/12 9:47 1000 77 0.5 0.1 2.0 2.59E+00 2

10/16/12 1024 10/16/12 9:48 1000 77 0.4 0.1 1.1 1.63E+00 Puck 5 2

122.18 10/16/12 1042 10/16/12 10:25 1000 77 0.3 0.1 0.4 8.10E-01 2.5 10/16/12 1101 10/16/12 10:25 1000 77 0.2 0.1 0.3 5.89E-01 Puck 6 2.5 138.84 10/16/12 1121 10/16/12 11:03 1000 77 0.2 0.1 0.3 5.91E-01 3

10/16/12 1139 10/16/12 11:04 1000 77 0.1 0.1 0.3 4.87E-01 Puck 7 3

169.97 10/16/12 1157 10/16/12 11:41 1000 77 0.2 0.1 0.2 4.26E-01 Bottom Side Not Analyzed

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 133 of 200 B101106-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 17.4 0.4 1376.0 13.3 0.3 1.01E+03 9.2 0.3 645.4 Puck 2 0.7 0.1 40.5 0.7 0.1 4.21E+01 0.7 0.1 43.8 Puck 3 0.6 0.1 15.2 0.6 0.1 1.44E+01 0.7 0.1 13.5 Puck 4 0.5 0.1 2.0 0.4 0.1 1.55E+00 0.4 0.1 1.1 Puck 5 0.3 0.1 0.4 0.3 0.1 3.31E-01 0.2 0.1 0.3 Puck 6 0.2 0.1 0.3 0.2 0.1 2.76E-01 0.1 0.1 0.3 Puck 7 0.2 0.1 0.2 0.2 0.1 1.92E-01 Bottom Side Not Analyzed Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 134 of 200 U1 CTMT OMB A Loop Core Collection Date 7/18/12 B101106-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

133 8/16/12 1050 7/25/12 16:14 1000 160 26.6 0.4 80.3 1.07E+02 0.5 8/16/12 1107 7/25/12 16:14 1000 160 14.7 0.3 36.2 5.12E+01 Puck 2 0.5 125 8/16/12 1132 7/25/12 16:15 1000 160 2.1 0.1 0.5 2.72E+00 1

8/16/12 1310 7/25/12 16:15 1000 160 1.7 0.1 0.3 2.12E+00 B101106-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 25.1 0.3 79.5 19.5 0.3 57.7 13.9 0.3 35.8 Puck 2 2.0 0.1 0.5 1.8 0.1 0.4 1.6 0.1 0.3

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 135 of 200 U1 CTMT OMB B Loop Core Collection Date 7/18/12 B101107-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

122.0 8/16/12 1329 7/25/12 16:17 1000 160 20.4 0.4 368.0 388.8 0.5 8/16/12 1426 7/25/12 16:17 1000 160 9.7 0.3 156.0 166.0 Puck 2 0.5 135.0 8/16/12 1449 7/25/12 16:17 1000 160 0.2 0.1 0.2 0.5 1

8/16/12 1506 7/25/12 16:17 1000 160 0.2 0.1 0.2 0.5 B101107-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 19.3 0.3 364.3 14.2 0.3 259.4 9.1 0.3 154.4 Puck 2 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 136 of 200 U1 CTMT OMB B Loop Core Collection Date 7/18/12 B101107-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

127.0 8/20/12 0726 7/25/12 16:16 1000 160 19.2 0.4 241.0 2.61E+02 0.5 8/20/12 0746 7/25/12 16:16 1000 160 10.2 0.3 99.8 1.10E+02 Puck 2 0.5 128.0 8/20/12 1219 7/25/12 16:16 1000 160 0.3 0.1 0.9 1.18E+00 1

8/20/12 1236 7/25/12 16:16 1000 160 0.2 0.1 1.2 1.55E+00 B101107-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 18.1 0.4 238.6 13.9 0.3 168.7 9.6 0.2 98.8 Puck 2 0.2 0.1 0.8 0.2 0.1 1.0 0.2 0.1 1.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 137 of 200 Unit 1 OMB C Loop Core Collection Date 7/19/12 B101108-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

134.0 8/27/12 0731 8/27/12 07;09 1000 127 15.0 0.9 8700.0 8.70E+03 0.5 8/27/12 0749 8/27/12 7:10 1000 127 9.3 1.0 6540.0 6.55E+03 Puck 2 0.5 137.0 8/27/12 0812 8/27/12 7:06 1000 127 1.1 0.1 690.0 6.91E+02 1

8/27/12 0830 8/27/12 7:07 1000 127 1.0 0.2 597.0 5.98E+02 Puck 3 1

137.0 8/27/12 0928 8/27/12 7:07 1000 127 1.4 0.2 703.0 7.05E+02 1.5 8/27/12 0911 8/27/12 7:07 1000 127 1.3 0.2 577.0 5.79E+02 Puck 4 1.5 135.0 8/27/12 0947 8/27/12 7:08 1000 127 0.8 0.1 263.0 2.64E+02 2

8/27/12 1105 8/27/12 10:46 1000 127 0.7 0.2 276.0 2.77E+02 Puck 5 2

126.0 8/27/12 1026 8/27/12 7:08 1000 127 1.6 0.2 525.0 5.27E+02 2.5 8/27/12 1045 8/27/12 7:08 1000 127 1.7 0.2 471.0 4.73E+02

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 138 of 200 B101108-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 14.3 0.8 8630.3 11.6 0.8 7559.0 8.9 0.9 6487.6 Puck 2 1.1 0.1 684.5 1.0 0.2 638.3 1.0 0.2 592.2 Puck 3 1.3 0.2 697.4 1.3 0.2 634.9 1.3 0.2 572.4 Puck 4 0.7 0.1 260.9 0.7 0.1 267.3 0.7 0.1 273.8 Puck 5 1.5 0.2 520.8 1.6 0.2 494.0 1.7 0.2 467.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 139 of 200 U1 CTMT OMB C Loop Core Collection Date 7/18/12 B101108-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

137.0 8/21/12 1430 8/21/12 14:24 300 133 61.6 41.8 6.08E+04 6.09E+04 0.5 8/21/12 1436 8/21/12 14:26 300 133 56.1 41.8 4.25E+04 4.26E+04 Puck 2 0.5 132.0 8/20/12 1333 8/20/12 13:16 1000 134 0.9 0.1 3.8 4.72E+00 1

8/20/12 1351 8/20/12 13:16 1000 134 0.7 0.1 2.6 3.46E+00 Puck 3 1

119.0 8/20/12 1419 8/20/12 14:02 1000 134 0.2 0.2 1.3 1.69E+00 1.5 8/20/12 1439 8/20/12 14:02 1000 134 0.2 0.1 1.2 1.56E+00 B101108-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 58.7 37.0 6.03E+04 56.1 37.0 5.12E+04 53.5 37.0 4.21E+04 Puck 2 0.8 0.1 3.7 0.7 0.1 3.2 0.7 0.1 2.6 Puck 3 0.2 0.1 1.3 0.2 0.1 1.3 0.2 0.1 1.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 140 of 200 U1 CTMT OMB D Loop Core Collection Date 7/18/12 B101109-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

131.0 8/20/12 1540 8/20/12 15:23 1000 134 10.2 0.5 194.0 2.05E+02 0.5 8/20/12 1521 8/20/12 14:46 1000 134 5.5 0.3 83.4 8.92E+01 Puck 2 0.5 134.0 8/22/12 0729 8/21/12 6:57 1000 133 0.1 0.1 0.8 1.05E+00 1

8/22/12 0747 8/21/12 6:57 1000 133 0.1 0.1 1.2 1.46E+00 B101109-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 9.7 0.4 192.4 7.5 0.3 137.5 5.2 0.3 82.7 Puck 2 0.1 0.1 0.8 0.1 0.1 1.0 0.1 0.1 1.2 Note: Bold Italics are MDA values

Attachment B U1 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 141 of 200 U1 CTMT OMB D Loop Core Collection Date 7/17/12 B101109-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

143.0 8/23/12 1036 8/21/12 6:59 1000 133 118.0 9.1 7.32E+03 7.45E+03 0.5 8/23/12 1054 8/21/12 6:59 1000 133 53.5 4.0 2.72E+03 2.78E+03 Puck 2 0.5 124.0 8/23/12 1159 8/23/12 10:18 1000 131 1.0 0.1 2.9 4.07E+00 1

8/23/12 1227 8/23/12 10:18 1000 131 0.8 0.1 2.4 3.34E+00 B101109-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 112.5 8.1 7258.6 81.7 5.8 4977.9 51.0 3.5 2697.2 Puck 2 1.0 0.1 2.9 0.9 0.1 2.6 0.7 0.1 2.4 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 142 of 200 U2 CTMT 568 IMB Loop A Core Collection Date 1/31/13 B102102-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

108.71 3/6/13 1432 3/6/13 12:28 300

-64 756.0 53.6 1.10E+05 1.11E+05 0.5 3/6/13 1436 3/6/13 12:28 300

-64 633.0 58.2 1.04E+05 1.05E+05 Puck 2 0.5 109.5 3/6/13 1439 3/6/13 12:29 300

-64 196.0 26.9 2.04E+04 2.06E+04 1

3/6/13 1445 3/6/13 12;29 300

-64 210.0 24.6 1.95E+04 1.97E+04 Puck 3 1

99.79 3/6/13 1451 3/6/13 12:08 600

-64 255.0 2.3 1.23E+04 1.26E+04 1.5 3/6/13 1456 3/6/13 12:08 600

-64 241.0 3.0 1.18E+04 1.20E+04 Puck 4 1.5 110.47 3/6/13 1458 3/6/13 13:45 600

-64 108.0 1.2 5950.0 6.06E+03 2

3/6/13 1500 3/6/13 12:09 1000

-64 95.3 1.0 4990.0 5.09E+03 Puck 5 2

121.8 3/6/13 1501 3/6/13 12:09 300

-64 68.1 0.9 1450.0 1.52E+03 2.5 3/6/13 1502 3/6/13 12:09 600

-64 69.7 0.6 1350.0 1.42E+03 Puck 6 2.5 158.92 3/6/13 1504 3/6/13 12:10 600

-64 45.6 0.4 467.0 5.13E+02 3

3/6/13 1506 3/6/13 12:10 600

-64 39.0 0.4 371.0 4.10E+02

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 143 of 200 B102102-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 773.6 56.9 1.10E+05 710.7 59.3 1.07E+05 647.8 61.7 1.04E+05 Puck 2 200.6 28.5 2.05E+04 207.7 27.3 2.00E+04 214.9 26.1 1.96E+04 Puck 3 260.9 2.4 1.23E+04 253.8 2.8 1.21E+04 246.6 3.2 1.18E+04 Puck 4 110.5 1.3 5974.2 104.0 1.2 5.49E+03 97.5 1.1 5010.3 Puck 5 69.7 0.9 1455.9 70.5 0.8 1.41E+03 71.3 0.7 1355.5 Puck 6 46.7 0.5 468.9 43.3 0.5 4.21E+02 39.9 0.5 372.5 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 144 of 200 U2 CTMT 568 IMB Loop A Core Collection Date 2/4/13 B102102-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

111.53 2/28/13 743 2/28/13 7:37 300

-58 9.40E+04 1.90E+02 1.75E+03 9.59E+04 0.5 2/28/13 749 2/28/13 7:37 300

-58 7.26E+04 1.84E+02 1.29E+03 7.41E+04 Puck 2 0.5 115.65 3/4/13 1535 3/4/13 15:01 845

-62 26.1 0.2 0.4 2.68E+01 1

3/4/13 1031 3/4/13 7:58 3000

-62 24.4 0.2 0.4 2.49E+01 Puck 3 1

107.27 3/4/13 1021 3/4/13 7:58 1500

-62 23.0 0.2 0.5 2.37E+01 1.5 3/4/13 1041 3/4/13 7:58 1000

-62 21.4 0.2 0.5 2.21E+01 Puck 4 1.5 111.89 3/4/13 1059 3/4/13 7:58 1500

-62 30.0 0.3 0.7 3.10E+01 2

3/4/13 1142 3/4/13 7:59 1500

-62 31.0 0.3 1.5 3.27E+01 Puck 5 2

127.77 3/4/13 1102 3/4/13 7:59 1000

-62 238.0 0.6 1.3 2.40E+02 2.5 3/4/13 1143 3/4/13 7:59 1500

-62 297.0 0.5 0.7 2.98E+02 Puck 6 2.5 116.51 3/5/13 704 3/4/13 15:40 906

-62 597.0 1.0 1.3 5.99E+02 3

3/4/13 1701 3/4/13 15:02 5000

-62 621.0 0.4 1.1 6.23E+02 Puck 7 3

109.94 3/4/13 1204 3/4/13 8:00 1000

-62 10.7 0.1 0.3 1.11E+01 3.5 3/4/13 1224 3/4/13 8:00 1000

-62 9.0 0.2 0.2 9.34E+00 Puck 8 3.5 113.3 3/4/13 1310 3/4/13 8:01 2776

-62 6.3 0.1 0.2 6.53E+00 4

3/5/13 735 3/4/13 15:02 2806

-62 6.5 0.1 0.2 6.74E+00 Puck 9 4

96.18 3/4/13 1251 3/4/13 8:01 1388

-62 4.6 0.1 0.2 4.88E+00 4.5 3/4/13 1345 3/4/13 8:02 1125

-62 4.6 0.1 0.2 4.93E+00 Puck 10 4.5 105.36 3/4/13 1406 3/4/13 8:02 1000

-62 4.0 0.1 0.2 4.34E+00 5

3/4/13 1449 3/4/13 8:02 1000

-62 3.9 0.2 0.1 4.15E+00 Puck 11 5

107.99 3/4/13 1524 3/4/13 14:59 1446

-62 2.6 0.1 0.2 2.90E+00 5.5 3/4/13 1713 3/4/13 15:49 5000

-62 2.5 0.1 0.1 2.70E+00 Puck 12 5.5 106.39 3/4/13 1448 3/4/13 8:03 1000

-62 3.3 0.1 0.1 3.52E+00 6

3/4/13 1518 3/4/13 8:03 1500

-62 3.4 0.1 0.1 3.66E+00 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 145 of 200 B102102-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 9.60E+04 200.4 1756.4 8.51E+04 197.3 1525.6 7.41E+04 194.1 1294.7 Puck 2 26.7 0.2 0.4 25.8 0.2 0.4 25.0 0.2 0.4 Puck 3 23.5 0.2 0.5 22.7 0.2 0.5 21.9 0.2 0.5 Puck 4 30.7 0.3 0.7 31.2 0.3 1.1 31.7 0.3 1.5 Puck 5 243.4 0.6 1.3 273.5 0.6 1.0 303.7 0.5 0.7 Puck 6 610.5 1.1 1.3 622.8 0.7 1.2 635.0 0.4 1.1 Puck 7 10.9 0.2 0.3 10.1 0.2 0.2 9.2 0.2 0.2 Puck 8 6.4 0.1 0.2 6.5 0.1 0.2 6.6 0.1 0.2 Puck 9 4.7 0.1 0.2 4.7 0.1 0.2 4.7 0.1 0.2 Puck 10 4.1 0.1 0.2 4.1 0.1 0.1 4.0 0.2 0.1 Puck 11 2.6 0.1 0.2 2.6 0.1 0.1 2.6 0.1 0.1 Puck 12 3.4 0.1 0.1 3.5 0.1 0.1 3.5 0.1 0.1 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 146 of 200 U2 CTMT 568 IMB Loop B Core Collection Date 2/5/13 B102103-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

115.82 2/27/13 931 2/26/13 10:06 1000

-21 564.0 16.1 4.57E+04 4.63E+04 0.5 2/27/13 1225 2/26/13 12:07 1000

-21 429.0 5.0 3.26E+04 3.30E+04 Puck 2 0.5 115.2 2/26/13 1053 2/26/13 10:35 1000

-21 9.9 0.2 164.0 1.74E+02 1

2/26/13 1224 2/26/13 10:36 1000

-21 9.2 0.2 134.0 1.43E+02 Puck 3 1

113.72 2/26/13 1343 2/26/13 13:25 1000

-21 9.0 0.2 43.1 5.23E+01 1.5 2/26/13 1405 2/26/13 13:25 1000

-21 7.9 0.2 35.6 4.37E+01 Puck 4 1.5 118.91 2/26/13 1455 2/26/13 14:10 1000

-21 3.7 0.1 12.6 1.64E+01 2

2/26/13 1428 2/26/13 14:10 1000

-21 3.9 0.1 13.2 1.72E+01 Puck 5 2

110.88 2/27/13 707 2/27/13 6:49 1000

-22 3.9 0.2 22.0 2.61E+01 2.5 2/27/13 728 2/27/13 6:50 1000

-22 3.1 0.2 20.3 2.36E+01 Puck 6 2.5 120.24 2/27/13 752 2/27/13 7:35 1000

-22 1.5 0.1 11.2 1.29E+01 3

2/27/13 815 2/27/13 7:35 1000

-22 1.3 0.1 9.8 1.13E+01 Puck 7 3

116.82 2/27/13 759 2/27/13 7:41 1000

-22 0.4 0.1 5.1 5.58E+00 3.5 2/27/13 837 2/27/13 7:41 1000

-22 0.8 0.1 4.7 5.65E+00 Puck 8 3.5 119.54 2/27/13 909 2/27/13 8:51 1000

-22 0.3 0.1 1.3 1.68E+00 4

2/27/13 928 2/27/13 8:51 1000

-22 0.2 0.1 1.3 1.66E+00 Puck 9 4

110.29 2/27/13 957 2/27/13 9:39 1000

-22 0.2 0.1 0.4 5.97E-01 4.5 2/27/13 1113 2/27/13 10:39 1000

-22 0.1 0.1 0.4 6.21E-01 Puck 10 4.5 109.87 2/27/13 1000 2/27/13 9:42 1000

-22 0.1 0.1 0.3 4.99E-01 5

2/27/13 1038 2/27/13 9:43 1000

-22 0.1 0.1 0.2 3.96E-01 Puck 11 5

118.24 2/27/13 1100 2/27/13 10:42 1000

-22 0.1 0.1 0.2 3.84E-01 5.5 2/27/13 1217 2/27/13 10:42 1000

-22 0.1 0.1 0.3 4.99E-01

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 147 of 200 B102103-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 568.3 16.4 4.58E+04 500.3 10.7 39202.1 432.3 5.1 3.26E+04 Puck 2 10.0 0.2 164.2 9.6 0.2 149.2 9.3 0.2 134.2 Puck 3 9.0 0.2 43.2 8.5 0.2 39.4 7.9 0.2 35.6 Puck 4 3.7 0.1 12.6 3.8 0.1 12.9 3.9 0.1 13.2 Puck 5 4.0 0.2 22.0 3.5 0.2 21.2 3.1 0.2 20.3 Puck 6 1.6 0.1 11.2 1.4 0.1 10.5 1.3 0.1 9.9 Puck 7 0.4 0.1 5.1 0.6 0.1 4.9 0.8 0.1 4.7 Puck 8 0.3 0.1 1.3 0.3 0.1 1.3 0.2 0.1 1.3 Puck 9 0.2 0.1 0.4 0.1 0.1 0.4 0.1 0.1 0.4 Puck 10 0.1 0.1 0.3 0.1 0.1 0.2 0.1 0.1 0.2 Puck 11 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.1 0.3 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 148 of 200 U2 CTMT 568 IMB Loop B Core Collection Date 2/5/13 B102103-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

109.8 2/25/13 733 2/25/13 7:14 1000

-20 191.0 5.7 6.39E+03 6.59E+03 0.5 2/25/13 752 2/25/13 7:14 1000

-20 110.0 3.5 3.25E+03 3.36E+03 Puck 2 0.5 113.25 2/25/13 732 2/25/13 7:13 1000

-20 1.4 0.9 44.5 4.68E+01 1

2/25/13 751 2/25/13 7:13 1000

-20 1.4 0.2 41.0 4.25E+01 Puck 3 1

114.13 2/25/13 818 2/25/13 7:58 1000

-20 1.2 0.2 21.9 2.33E+01 1.5 2/25/13 837 2/25/13 7:59 1000

-20 1.2 0.2 19.1 2.05E+01 Puck 4 1.5 114.39 2/25/13 819 2/25/13 7:59 1000

-20 1.4 0.1 10.9 1.25E+01 2

2/25/13 838 2/25/13 8:00 1000

-20 1.4 0.1 10.8 1.23E+01 Puck 5 2

105.32 2/25/13 903 2/25/13 8:41 1000

-20 1.0 0.1 2.9 3.99E+00 2.5 2/25/13 1005 2/25/13 9:48 1000

-20 1.1 0.2 3.0 4.17E+00 Puck 6 2.5 99.35 2/25/13 926 2/25/13 9:07 1000

-20 0.5 0.2 2.6 3.26E+00 3

2/25/13 945 2/25/13 9:07 1000

-20 0.5 0.1 2.3 2.92E+00 Puck 7 3

98.16 2/25/13 947 2/25/13 9:30 1000

-20 0.2 0.1 0.7 9.78E-01 3.5 2/25/13 1006 2/25/13 9:30 1000

-20 0.2 0.1 0.7 9.62E-01 Puck 8 3.5 110.37 2/25/13 1030 2/25/13 10:10 1000

-20 0.1 0.1 0.3 4.81E-01 4

2/25/13 1049 2/25/13 10:11 1000

-20 0.1 0.1 0.3 5.33E-01

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 149 of 200 B102103-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 192.4 5.8 6398.1 151.6 4.6 4826.1 110.8 3.5 3254.1 Puck 2 1.4 0.9 44.6 1.4 0.5 42.8 1.4 0.2 41.1 Puck 3 1.2 0.2 21.9 1.2 0.2 20.5 1.2 0.2 19.1 Puck 4 1.4 0.1 10.9 1.4 0.1 10.9 1.4 0.1 10.8 Puck 5 1.0 0.1 2.9 1.0 0.1 2.9 1.1 0.2 3.0 Puck 6 0.5 0.2 2.6 0.5 0.2 2.4 0.5 0.1 2.3 Puck 7 0.2 0.1 0.7 0.2 0.1 0.7 0.2 0.1 0.7 Puck 8 0.1 0.1 0.3 0.1 0.1 0.3 0.1 0.1 0.3 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 150 of 200 U2 CTMT 568 IMB Loop C Core Collection Date 1/31/13 B102104-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

108.73 3/6/13 0821 3/6/13 8:13 300

-64 355.0 12.8 1.94E+04 1.98E+04 0.5 3/6/13 0827 3/6/13 8:13 300

-64 260.0 13.3 1.40E+04 1.43E+04 Puck 2 0.5 112.12 3/6/13 1112 3/6/13 10:51 1200

-64 0.4 0.1 211.0 211.5 1

3/6/13 1159 3/6/13 10:38 1200

-64 0.4 0.1 181.0 181.5 Puck 3 1

108.45 3/6/13 1052 3/6/13 10:35 1000

-64 0.4 0.2 31.9 32.5 1.5 3/6/13 0850 3/6/13 7:57 300

-64 0.6 0.3 22.7 23.5 Puck 4 1.5 112.48 3/6/13 0836 3/6/13 7:57 300

-64 0.7 0.3 8.4 9.4 2

3/6/13 0842 3/6/13 7:58 300

-64 0.9 0.4 6.6 7.9 Puck 5 2

113.98 3/6/13 1031 3/6/13 10:20 600

-64 0.3 0.2 5.2 5.6 2.5 3/6/13 1017 3/6/13 9:49 600

-64 0.4 0.2 5.7 6.3 Puck 6 2.5 108.17 3/6/13 0858 3/6/13 7:59 300

-64 0.5 0.2 6.6 7.3 3

3/6/13 0904 3/6/13 8:00 300

-64 0.5 0.3 6.4 7.2 Puck 7 3

113.41 3/6/13 0909 3/6/13 8:00 300

-64 0.5 0.2 4.8 5.6 3.5 3/6/13 0915 3/6/13 8:00 300

-64 0.5 0.1 4.2 4.8 Puck 8 3.5 104.26 3/6/13 0912 3/6/13 8:01 300

-64 0.4 0.2 3.3 3.9 4

3/6/13 0918 3/6/13 8:03 300

-64 0.5 0.2 2.5 3.2 Puck 9 4

107.14 3/6/13 0922 3/6/13 8:04 300

-64 0.5 0.1 1.5 2.1 4.5 3/6/13 0929 3/6/13 8:05 300

-64 0.4 0.1 1.8 2.3 Puck 10 4.5 105.6 3/6/13 0925 3/6/13 8:05 300

-64 0.3 0.1 0.7 1.1 5

3/6/13 0931 3/6/13 8:06 300

-64 0.4 0.1 0.9 1.4 Puck 11 5

110.56 3/6/13 1020 3/6/13 10:06 804

-64 0.2 0.1 0.4 0.7 5.5 3/6/13 1035 3/6/13 9:46 800

-64 0.2 0.1 0.3 0.6 Puck 12 5.5 133.96 3/6/13 938 3/6/13 8:07 300

-64 0.4 0.141 0.4 0.9 6

Bottom Irregular Geometry - Not Analyzed

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 151 of 200 B102104-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 363.3 13.6 1.95E+04 314.7 13.8 1.68E+04 266.1 14.1 1.41E+04 Puck 2 0.4 0.1 211.9 0.4 0.1 196.8 0.4 0.1 181.7 Puck 3 0.4 0.2 32.0 0.5 0.2 27.4 0.6 0.3 22.8 Puck 4 0.8 0.3 8.4 0.8 0.4 7.5 0.9 0.4 6.7 Puck 5 0.3 0.2 5.2 0.4 0.2 5.5 0.4 0.2 5.7 Puck 6 0.5 0.2 6.6 0.5 0.3 6.6 0.5 0.3 6.5 Puck 7 0.5 0.3 4.8 0.5 0.2 4.5 0.5 0.1 4.2 Puck 8 0.4 0.3 3.3 0.4 0.2 2.9 0.5 0.2 2.5 Puck 9 0.5 0.1 1.5 0.5 0.1 1.7 0.4 0.1 1.8 Puck 10 0.3 0.1 0.7 0.3 0.1 0.8 0.4 0.2 0.9 Puck 11 0.2 0.1 0.4 0.2 0.1 0.4 0.2 0.1 0.3 Puck 12 0.4 0.1 0.4 0.4 0.1 0.4 Bottom Irregular Geometry - Not Analyzed Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 152 of 200 U2 CTMT 568 IMB Loop C Core Collection Date 1/31/13 B102104-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

119.15 3/6/13 1433 3/6/13 14:22 300

-64 140.0 10.6 1.45E+04 1.47E+04 0.5 3/6/13 1521 3/6/13 15:12 500

-64 9.7 0.5 770.0 7.80E+02 Puck 2 0.5 128.66 3/6/13 1454 3/6/13 14:23 600

-64 4.3 0.3 45.4 5.00E+01 1

3/6/13 1505 3/6/13 14:23 600

-64 4.2 0.3 43.4 4.78E+01 Puck 3 1

126.73 3/6/13 1438 3/6/13 14:23 600

-64 1.1 0.1 4.4 5.57E+00 1.5 3/6/13 1452 3/6/13 14:24 600

-64 1.0 0.1 3.7 4.86E+00 B102104-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 143.3 11.2 1.46E+04 76.6 5.9 7666.0 9.9 0.5 773.1 Puck 2 4.4 0.4 45.6 4.3 0.3 44.6 4.2 0.3 43.6 Puck 3 1.1 0.1 4.4 1.1 0.1 4.1 1.0 0.1 3.8 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 153 of 200 U2 CTMT 568 IMB Loop D Core Collection Date 2/5/13 B102105-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0

105.5 2/28/13 0325 2/28/13 12:25 2500

-58 1110.0 2.3 2883.0 5.1 4.00E+03 0.5 2/28/13 1432 2/28/13 13:49 2500

-58 684.0 1.1 1480.0 2.7 2.17E+03 Puck 2 0.5 107.12 2/28/13 0821 2/28/13 8:03 1000

-58 26.4 0.2 3.1

< MDA 2.98E+01 1

2/28/13 0841 2/28/13 8:04 1000

-58 24.3 0.2 2.6

< MDA 2.72E+01 Puck 3 1

102.16 2/28/13 1055 2/28/13 10:31 1400

-58 0.6 0.1 0.1

< MDA 8.86E-01 1.5 2/28/13 1247 2/28/13 12:23 1400

-58 0.5 0.1 0.2

< MDA 8.33E-01 Puck 4 1.5 102.72 2/28/13 1418 2/28/13 13:54 1400

-58 0.6 0.1 0.1

< MDA 8.61E-01 2

2/28/13 1132 2/28/13 10:52 1000

-58 1.1 0.1 0.2

< MDA 1.50E+00 Puck 5 2

102.78 2/28/13 1311 2/28/13 12:53 1000

-58 1.2 0.1 0.3

< MDA 1.72E+00 2.5 2/28/13 1335 2/28/13 12:53 1000

-58 1.3 0.1 0.3

< MDA 1.66E+00 Puck 6 2.5 73.67 2/28/13 1523 2/28/13 15:04 1000

-58 1.4 0.2 1.0

< MDA 2.56E+00 3

2/28/13 1541 2/28/13 15:05 1000

-58 1.3 0.2 1.0

< MDA 2.55E+00 Puck 7 3

82.7 2/28/13 1527 2/28/13 15:08 1000

-58 1.0 0.1 0.5

< MDA 1.60E+00 3.5 2/28/13 1545 2/28/13 15:09 1000

-58 1.0 0.2 0.5

< MDA 1.67E+00 Puck 8 3.5 109.22 3/4/13 0710 2/28/13 15:25 1000

-58 1.0 0.1 0.4

< MDA 1.44E+00 4

3/4/13 0739 2/28/13 15:25 1000

-58 0.6 0.1 0.3

< MDA 9.88E-01 Puck 9 4

108.45 3/4/13 0807 3/4/13 7:42 1391

-62 0.2 0.1 0.1

< MDA 3.48E-01 4.5 3/4/13 0949 3/4/13 9:15 2000

-62 0.2 0.1 0.2

< MDA 3.93E-01

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 154 of 200 B102105-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Eu-154 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 1133.4 2.5 2893.6 5.2 915.9 1.8 2189.5 4.0 698.4 1.2 1485.4 2.8 Puck 2 27.0 0.2 3.1

< MDA 25.9 0.3 2.9 24.8 0.3 2.6

< MDA Puck 3 0.7 0.1 0.1

< MDA 0.6 0.1 0.2 0.5 0.1 0.2

< MDA Puck 4 0.7 0.1 0.1

< MDA 0.9 0.1 0.2 1.2 0.1 0.2

< MDA Puck 5 1.3 0.1 0.4

< MDA 1.3 0.1 0.3 1.3 0.1 0.3

< MDA Puck 6 1.5 0.2 1.0

< MDA 1.4 0.2 1.0 1.4 0.2 1.0

< MDA Puck 7 1.0 0.2 0.5

< MDA 1.0 0.2 0.5 1.0 0.2 0.5

< MDA Puck 8 1.0 0.1 0.4

< MDA 0.8 0.1 0.3 0.6 0.1 0.3

< MDA Puck 9 0.2 0.1 0.1

< MDA 0.2 0.1 0.1 0.2 0.1 0.2

< MDA Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 155 of 200 U2 CTMT 568 IMB Loop D Core Collection Date 2/5/13 B102105-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

111.2 3/7/13 0707 3/7/13 06:51 600

-65 111.0 5.8 12500.0 1.26E+04 0.5 3/7/13 1053 3/7/13 10:36 1000

-65 58.3 3.4 5720.0 5.78E+03 Puck 2 0.5 108.7 3/7/13 0706 3/7/13 6:52 600

-65 0.2 0.2 0.2 5.81E-01 1

3/7/13 1040 3/7/13 10:14 1500

-65 0.1 0.1 0.9 1.11E+00 Puck 3 1

113.7 3/7/13 0738 3/7/13 06:53 1000

-65 0.2 0.1 0.2 5.11E-01 1.5 3/7/13 0803 3/7/13 06:53 1000

-65 0.2 0.1 0.2 5.10E-01 Puck 4 1.5 107.9 3/7/13 0742 3/7/13 6:54 1000

-65 0.1 0.1 0.1 3.46E-01 2

3/7/13 0802 3/7/13 6:54 1000

-65 0.1 0.1 0.2 3.89E-01 Puck 5 2

111.8 3/7/13 0910 3/7/13 6:55 1000

-65 0.1 0.1 0.2 4.32E-01 2.5 3/7/13 0928 3/7/13 6:55 1000

-65 0.1 0.1 0.2 4.36E-01 Puck 6 2.5 119.2 3/7/13 0912 3/7/13 6:57 1000

-65 0.3 0.1 0.2 6.22E-01 3

3/7/13 0929 3/7/13 6:57 1000

-65 0.3 0.1 0.2 5.99E-01 Puck 7 3

115.3 3/7/13 0946 3/7/13 6:58 1000

-65 0.1 0.1 0.1 3.71E-01 3.5 3/7/13 1005 3/7/13 6:58 1000

-65 0.1 0.1 0.1 3.68E-01 Puck 8 3.5 123.3 3/7/13 0947 3/7/13 6:58 1000

-65 0.2 0.1 0.2 4.48E-01 4

3/7/13 1006 3/7/13 6:59 1000

-65 0.2 0.1 0.2 4.58E-01

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 156 of 200 B102105-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 113.6 6.2 1.26E+04 86.7 4.9 9147.6 59.7 3.6 5743.6 Puck 2 0.2 0.2 0.2 0.2 0.1 0.5 0.1 0.1 0.9 Puck 3 0.2 0.1 0.2 0.2 0.1 0.2 0.3 0.1 0.2 Puck 4 0.1 0.1 0.1 0.1 0.1 0.1 0.2 0.1 0.2 Puck 5 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.1 0.2 Puck 6 0.3 0.1 0.2 0.3 0.1 0.2 0.3 0.1 0.2 Puck 7 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Puck 8 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.2 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 157 of 200 U2 CTMT OMB A Loop Core Collection Date 2/11/13 B102106-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

106.3 3/5/13 0829 3/5/13 7:53 1000

-63 55.9 0.9 813.0 8.70E+02 0.5 3/5/13 0847 3/5/13 7:54 1000

-63 31.2 0.6 337.0 3.69E+02 Puck 2 0.5 115.3 3/5/13 0830 3/5/13 7:55 1000

-63 0.5 0.1 0.2 8.01E-01 1

3/5/13 0849 3/5/13 7:55 1000

-63 0.4 0.1 0.1 6.42E-01 Puck 3 1

114.4 3/5/13 1545 3/5/13 13:20 1434

-63 0.1 0.1 0.1 3.50E-01 1.5 3/5/13 0922 3/5/13 7:58 1000

-63 0.2 0.1 0.1 4.83E-01 Puck 4 1.5 119.9 3/5/13 1313 3/5/13 12:48 1400

-63 0.2 0.1 0.2 4.26E-01 2

3/5/13 1347 3/5/13 13:23 1400

-63 0.2 0.1 0.2 4.40E-01 Puck 5 2

118.1 3/5/13 1401 3/5/13 9:52 798

-63 0.1 0.1 0.1 4.02E-01 2.5 3/5/13 1006 3/5/13 8:00 1200

-63 0.2 0.1 0.2 4.96E-01 Puck 6 2.5 128.2 3/5/13 0949 3/5/13 8:01 1112

-63 0.1 0.1 0.1 3.06E-01 3

3/5/13 1010 3/5/13 8:01 1200

-63 0.1 0.1 0.1 2.87E-01 Puck 7 3

126.1 3/5/13 1029 3/5/13 8:02 1200

-63 0.2 0.1 0.2 4.63E-01 3.5 3/5/13 1052 3/5/13 8:02 1200

-63 0.2 0.1 0.2 4.98E-01 Puck 8 3.5 121.1 3/5/13 1033 3/5/13 8:03 1200

-63 0.1 0.9 0.1 1.19E+00 4

3/5/13 1055 3/5/13 8:03 1200

-63 0.1 0.1 0.1 2.61E-01 Puck 9 4

114.5 3/5/13 1113 3/5/13 8:05 1200

-63 0.2 0.1 0.2 4.65E-01 4.5 3/5/13 1224 3/5/13 8:05 1200

-63 0.2 0.1 0.2 4.80E-01 Puck 10 4.5 77.3 3/5/13 1414 3/5/13 13:50 1400

-63 0.3 0.1 0.2 6.34E-01 5

3/5/13 1223 3/5/13 8:06 1200

-63 0.2 0.1 0.1 4.10E-01 Puck 11

> 5 150.8 3/5/13 1245 3/5/13 8:07 1200

-63 0.1 0.1 0.1 2.38E-01 Bottom Irregular Geometry - Not Analyzed

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 158 of 200 B102106-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 57.2 0.9 816.2 44.5 0.8 577.3 31.9 0.6 338.3 Puck 2 0.5 0.1 0.2 0.5 0.1 0.1 0.4 0.1 0.1 Puck 3 0.2 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.1 Puck 4 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.2 Puck 5 0.2 0.1 0.1 0.2 0.1 0.2 0.2 0.1 0.2 Puck 6 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Puck 7 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.2 Puck 8 0.1 1.0 0.1 0.1 0.5 0.1 0.1 0.1 0.1 Puck 9 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.2 Puck 10 0.3 0.2 0.2 0.2 0.1 0.2 0.2 0.1 0.1 Puck 11 0.1 0.1 0.1 0.1 0.1 0.1 Bottom Irregular Geometry - Not Analyzed Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 159 of 200 U2 CTMT OMB A Loop Core Collection Date 2/11/13 B102106-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

117.4 3/5/13 1526 3/5/13 15:07 1000

-63 27.1 0.7 1.40E+04 1.40E+04 0.5 3/5/13 1507 3/5/13 14:21 1200

-63 19.4 0.6 1.20E+04 1.20E+04 Puck 2 0.5 119.0 3/5/13 1443 3/5/13 14:21 1200

-63 13.8 0.2 1240.0 1.25E+03 1

3/5/13 1505 3/5/13 14:21 1200

-63 24.0 0.3 1000.0 1.02E+03 Puck 3 1

123.6 3/5/13 1527 3/5/13 14:22 1200

-63 1.3 0.1 204.0 2.05E+02 1.5 3/5/13 1543 3/5/13 14:22 1000

-63 1.5 0.1 189.0 1.91E+02 B102106-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 27.7 0.8 1.41E+04 23.8 0.7 1.31E+04 19.8 0.6 1.20E+04 Puck 2 14.1 0.2 1245.0 19.3 0.2 1124.5 24.6 0.3 1004.0 Puck 3 1.3 0.1 204.8 1.4 0.1 197.3 1.5 0.1 189.8 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 160 of 200 U2 CTMT OMB B Loop Core Collection Date 2/6/13 B102107-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

110.2 2/25/13 0857 2/25/13 8:11 1000

-55 66.1 14.3 4020.0 4.10E+03 0.5 2/20/13 1409 2/20/13 13:27 1000

-50 44.1 8.9 2190.0 2.24E+03 Puck 2 0.5 113.3 2/20/13 1345 2/20/13 13:27 1000

-50 9.1 0.2 88.2 9.75E+01 1

2/20/13 1410 2/20/13 13:28 1000

-50 9.7 0.2 80.8 9.07E+01 Puck 3 1

121.4 2/20/13 1446 2/20/13 14:28 1000

-50 7.1 0.2 30.6 3.79E+01 1.5 2/20/13 1513 2/20/13 14:28 1000

-50 6.8 0.2 28.8 3.57E+01 Puck 4 1.5 109.2 2/20/13 1443 2/20/13 14:24 1000

-50 10.8 0.2 30.0 4.10E+01 2

2/20/13 1512 2/20/13 14:25 1000

-50 9.4 0.2 25.7 3.53E+01 Puck 5 2

122.7 2/21/13 0722 2/21/13 7:04 1000

-51 3.7 0.2 9.6 1.34E+01 2.5 2/21/13 0742 2/21/13 7:04 1000

-51 3.8 0.1 9.5 1.35E+01 Puck 6 2.5 134.5 2/21/13 0723 2/21/13 7:05 1000

-51 4.3 0.1 14.2 1.87E+01 3

2/21/13 0741 2/21/13 7:05 1000

-51 4.3 0.1 16.8 2.13E+01 Puck 7 3

126.9 2/21/13 0800 2/21/13 7:42 1000

-51 6.6 0.2 41.0 4.77E+01 3.5 2/21/13 0821 2/21/13 7:42 1000

-51 6.4 0.2 40.5 4.71E+01 Puck 8 3.5 143.5 2/21/13 0801 2/21/13 7:43 1000

-51 5.0 0.3 36.9 4.22E+01 4

2/21/13 0821 2/21/13 7:43 1000

-51 4.7 0.2 31.7 3.66E+01 Puck 9 4

132.5 2/21/13 0854 2/21/13 8:36 1000

-51 4.5 0.2 20.0 2.47E+01 4.5 2/21/13 0914 2/21/13 8:36 1000

-51 3.9 0.2 14.5 1.86E+01 Puck 10 4.5 159.2 2/21/13 0855 2/21/13 8:37 1000

-51 2.7 0.1 4.2 7.06E+00 5

Bottom Irregular Geometry - Not Analyzed

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 161 of 200 B102107-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 67.4 15.0 4034.0 56.2 12.2 3115.5 44.9 9.3 2196.9 Puck 2 9.3 0.3 88.5 9.6 0.2 84.8 9.9 0.2 81.1 Puck 3 7.3 0.2 30.7 7.1 0.2 29.8 6.9 0.2 28.9 Puck 4 11.0 0.2 30.1 10.3 0.2 27.9 9.5 0.2 25.8 Puck 5 3.8 0.2 9.6 3.8 0.2 9.6 3.9 0.1 9.6 Puck 6 4.4 0.1 14.2 4.4 0.1 15.6 4.4 0.1 16.9 Puck 7 6.7 0.2 41.1 6.6 0.2 40.9 6.5 0.2 40.6 Puck 8 5.1 0.3 37.0 5.0 0.2 34.4 4.8 0.2 31.8 Puck 9 4.6 0.2 20.1 4.3 0.2 17.3 4.0 0.2 14.5 Puck 10 2.8 0.1 4.2 2.8 0.1 4.2 Bottom Irregular Geometry - Not Analyzed Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 162 of 200 U2 CTMT OMB B Loop Core Collection Date 2/6/13 B102107-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

123.2 2/25/13 1029 2/25/13 10:12 1000

-55 35.7 10.3 2090.0 2.14E+03 0.5 2/25/13 1048 2/25/13 10:12 1000

-55 18.4 5.0 908.0 9.31E+02 Puck 2 0.5 107.6 2/25/13 1119 2/25/13 10:59 1000

-55 0.3 0.1 0.2 5.10E-01 1

2/25/13 1136 2/25/13 11:00 1000

-55 0.2 0.1 0.2 4.94E-01 Puck 3 1

111.2 2/25/13 1120 2/25/13 11:00 1000

-55 0.1 0.1 0.1 3.75E-01 1.5 2/25/13 1301 2/25/13 12:44 1000

-55 0.2 0.1 0.2 5.15E-01 B102107-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 36.4 10.8 2097.3 27.6 8.0 1504.2 18.8 5.3 911.2 Puck 2 0.3 0.1 0.2 0.3 0.1 0.2 0.2 0.1 0.2 Puck 3 0.2 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.2 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 163 of 200 Unit 2 OMB C Loop Core Collection Date 2/11/13 B102108-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

119.2 2/14/13 1306 2/14/13 10:55 1000

-44 13.0 0.3 255.0 2.55E+02 0.5 2/14/13 1308 2/14/13 10:55 1000

-44 7.5 0.2 123.0 1.31E+02 Puck 2 0.5 109.8 2/14/13 1312 2/14/13 10:53 1000

-44 0.2 0.1 0.2 4.90E-01 1

2/14/13 1314 2/14/13 10:54 1000

-44 0.1 0.1 0.1 4.09E-01 Puck 3 1

110.2 2/14/13 1258 2/14/13 12:38 1000

-44 0.1 0.1 0.1 3.86E-01 1.5 2/14/13 1317 2/14/13 12:39 1000

-44 0.0 0.1 0.2 3.39E-01 Puck 4 1.5 103.3 2/14/13 1259 2/14/13 12:36 1000

-44 0.1 0.1 0.1 3.02E-01 2

2/14/13 1318 2/14/13 12:37 1000

-44 0.1 0.1 0.1 3.11E-01 B102108-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 13.2 0.3 255.7 10.4 0.3 189.5 7.6 0.2 123.3 Puck 2 0.2 0.1 0.2 0.2 0.1 0.2 0.1 0.1 0.1 Puck 3 0.1 0.1 0.1 0.1 0.1 0.2 0.0 0.1 0.2 Puck 4 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 164 of 200 U2 CTMT OMB C Loop Core Collection Date 2/11/13 B102108-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

113.8 2/14/13 0940 2/14/13 9:20 1000

-44 18.9 0.5 397.0 4.16E+02 0.5 2/19/13 1514 2/19/13 14:56 1000

-49 10.5 0.3 184.0 1.95E+02 Puck 2 0.5 118.9 2/14/13 0941 2/14/13 9:21 1000

-44 0.2 0.1 0.1 3.40E-01 1

2/14/13 1000 2/14/13 9:22 1000

-44 0.2 0.1 0.2 4.88E-01 Puck 3 1

114.8 2/14/13 1023 2/14/13 10:02 1000

-44 0.2 0.1 0.2 4.65E-01 1.5 2/14/13 1041 2/14/13 10:03 1000

-44 0.2 0.1 0.1 5.07E-01 Puck 4 1.5 125.3 2/14/13 1024 2/14/13 10:05 1000

-44 0.1 0.1 0.1 2.54E-01 2

2/14/13 1042 2/14/13 10:05 1000

-44 0.1 0.1 0.1 2.93E-01 B102108-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 19.2 0.5 398.1 14.9 0.4 291.3 10.7 0.3 184.6 Puck 2 0.2 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.2 Puck 3 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.1 Puck 4 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 165 of 200 U2 CTMT OMB D Loop Core Collection Date 2/7/13 B102109-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

104.4 2/25/13 1345 2/25/13 13:26 1000

-55 1130.0 2.6 6070.0 7.20E+03 0.5 2/25/13 1402 2/25/13 13:26 1000

-55 682.0 2.2 3220.0 3.90E+03 Puck 2 0.5 117.0 2/25/13 1344 2/25/13 13:26 1000

-55 3.1 0.1 0.5 3.75E+00 1

2/25/13 1401 2/25/13 13:27 1000

-55 3.0 0.1 0.3 3.47E+00 Puck 3 1

108.1 2/25/13 1456 2/25/13 14:38 1000

-55 0.7 0.0 0.3 9.76E-01 1.5 2/25/13 1518 2/25/13 14:38 1000

-55 0.5 0.1 0.2 8.37E-01 Puck 4 1.5 115.3 2/26/13 0833 2/26/13 8:15 1000

-56 0.1 0.1 0.1 3.38E-01 2

2/27/13 0844 2/27/13 8:27 1000

-57 0.2 0.1 0.1 3.68E-01 Puck 5 2

116.1 2/26/13 0734 2/26/13 7:16 1000

-56 0.2 0.1 0.2 4.43E-01 2.5 2/26/13 1250 2/26/13 12:30 1000

-56 0.1 0.1 0.1 3.10E-01 Puck 6 2.5 120.2 2/26/13 1451 2/26/13 14:08 1000

-56 0.1 0.1 0.1 2.99E-01 3

2/26/13 0834 2/26/13 7:58 1000

-56 0.3 0.1 0.2 5.29E-01 Puck 7 3

114.7 2/26/13 1519 2/26/13 12:55 1000

-56 0.2 0.1 0.1 4.14E-01 3.5 2/26/13 0942 2/26/13 9:24 1000

-56 0.2 0.1 0.2 5.06E-01 Puck 8 3.5 126.7 2/26/13 0933 2/26/13 9:15 1000

-56 0.2 0.1 0.1 3.90E-01 4

2/26/13 0954 2/26/13 8:46 1000

-56 0.1 0.1 0.1 3.50E-01

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 166 of 200 B102109-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 1152.6 2.7 6091.2 924.1 2.5 4661.2 695.7 2.3 3231.2 Puck 2 3.2 0.1 0.5 3.1 0.1 0.4 3.1 0.2 0.3 Puck 3 0.7 0.0 0.3 0.6 0.1 0.3 0.5 0.1 0.2 Puck 4 0.1 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.1 Puck 5 0.2 0.1 0.2 0.2 0.1 0.1 0.1 0.1 0.1 Puck 6 0.1 0.1 0.1 0.2 0.1 0.1 0.3 0.1 0.2 Puck 7 0.2 0.1 0.1 0.2 0.1 0.2 0.2 0.1 0.2 Puck 8 0.2 0.1 0.1 0.2 0.1 0.1 0.2 0.1 0.1 Note: Bold Italics are MDA values

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 167 of 200 U2 CTMT OMB D Loop Core Collection Date 2/7/13 B102109-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Total pCi/g Puck 1 0

107.0 2/21/13 1124 2/21/13 11:07 1000

-51 86.2 0.6 4650.0 4.74E+03 0.5 2/21/13 1002 2/21/13 9:17 1000

-51 59.1 0.7 2780.0 2.84E+03 Puck 2 0.5 120.4 2/21/13 0941 2/21/13 9:23 1000

-51 2.8 0.1 1.0 3.88E+00 1

2/21/13 1003 2/21/13 9:23 1000

-51 2.9 0.1 0.7 3.73E+00 Puck 3 1

118.9 2/21/13 1034 2/21/13 10:15 1000

-51 0.9 0.1 0.2 1.25E+00 1.5 2/21/13 1052 2/21/13 10:15 1000

-51 0.8 0.1 0.2 1.10E+00 Puck 4 1.5 129.4 2/21/13 1253 2/21/13 12:36 1000

-51 0.2 0.1 0.2 5.16E-01 2

2/21/13 1051 2/21/13 12:36 1000

-51 0.2 0.1 0.2 5.99E-01 Puck 5 2

126.8 2/21/13 1123 2/21/13 11:05 1000

-51 0.0 0.1 0.2 3.56E-01 2.5 2/21/13 1146 2/21/13 11:06 1000

-51 0.1 0.1 0.2 4.27E-01

Attachment C U2 568 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 168 of 200 B102109-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Puck 1 87.8 0.7 4665.0 74.0 0.7 3727.0 60.2 0.8 2789.0 Puck 2 2.9 0.1 1.0 2.9 0.1 0.8 2.9 0.1 0.7 Puck 3 1.0 0.1 0.2 0.9 0.1 0.2 0.8 0.1 0.2 Puck 4 0.2 0.1 0.2 0.2 0.1 0.2 0.2 0.1 0.2 Puck 5 0.0 0.1 0.2 0.1 0.1 0.2 0.1 0.1 0.2 Note: Bold Italics are MDA values

Attachment D U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 169 of 200 Sample ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline WO 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Eberline Sample Date 12/10/2012 12/10/2012 12/10/2012 12/10/2012 12/10/2012 1/30/2013 1/30/2013 12/10/2012 1/30/2013 Nuclide Decay Const yr-1 Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g H-3 5.63E-02 1.91E+01 2.60E+01 3.75E+01 2.71E+01 1.19E+02 8.11E+01 5.05E+01 7.61E+01 5.40E+01 C-14 1.22E-04 2.50E+00 3.62E+00 4.40E+00 2.46E+01 2.71E+00 1.51E+00 1.12E+00 9.52E+00 1.09E+00 Fe-55 2.53E-01 5.82E+02 9.16E+01 1.79E+02 4.64E+01 4.05E+01 1.99E+00 2.12E+00 4.76E+01 2.00E+00 Ni-59 6.86E-06 3.26E+01 3.31E+01 2.65E+01 3.01E+01 3.07E+01 7.33E+00 6.52E+00 3.33E+01 7.30E+00 Co-60 1.31E-01 8.12E+01 7.09E+03 8.69E+01 3.35E+04 9.77E+02 4.36E+01 1.50E+01 8.67E+01 8.50E+00 Ni-63 6.92E-03 1.81E+04 2.26E+03 6.29E+03 2.81E+03 1.14E+01 3.02E+01 5.48E+00 2.39E+01 1.13E+01 Sr-90 2.41E-02 4.75E+01 7.60E+00 1.63E+02 1.45E+01 7.08E+00 3.97E-01 5.67E-01 8.46E+00 4.74E-01 Nb-94 3.41E-05 8.56E+01 1.56E+01 5.13E+01 2.56E+01 7.85E+00 6.01E-01 3.03E-01 9.30E+00 2.37E-01 Tc-99 3.28E-06 2.25E+01 1.22E+00 3.46E+01 9.31E-01 9.35E-01 2.96E-01 2.60E-01 1.13E+00 2.66E-01 Ag-108m 1.66E-03 2.39E+02 1.72E+01 5.72E+01 2.05E+01 9.25E+00 4.50E-01 2.35E-01 1.19E+01 2.09E-01 Sb-125 2.51E-01 1.92E+02 5.54E+01 1.23E+02 3.88E+01 4.78E+01 1.86E+00 1.65E+00 5.62E+01 2.96E-02 I-129 4.41E-08 3.19E+04 1.22E+04 5.26E+03 2.05E+02 7.48E+02 1.59E+01 5.07E-01 8.84E+02 8.06E-01 Cs-134 3.36E-01 5.47E+01 1.61E+01 3.68E+01 1.53E+01 9.47E+00 4.45E-01 3.31E-01 3.92E+01 3.54E-01 Cs-137 2.30E-02 1.45E+05 9.44E+04 1.22E+05 2.72E+03 4.27E+04 1.38E+02 1.60E+02 5.91E+04 1.43E+02 Pm-145 3.92E-02 1.49E+04 1.38E+04 3.49E+03 2.75E+02 5.26E+03 1.42E+01 1.74E+00 8.49E+03 2.02E+00 Pm-147 2.64E-01 7.04E+01 5.24E+01 4.06E+02 3.89E+02 1.47E+01 1.19E+00 5.12E-01 1.48E+01 5.16E-01 Eu-152 5.12E-02 4.52E+02 7.31E+01 2.52E+02 1.25E+02 2.29E+01 1.82E+00 8.56E-01 1.95E+01 1.06E+00 Eu-154 7.88E-02 2.26E+02 3.58E+01 1.29E+02 5.16E+01 1.48E+01 9.41E-01 5.26E-01 1.76E+01 5.44E-01 Eu-155 1.46E-01 5.39E+01 2.37E+01 3.54E+01 1.70E+01 1.68E+01 6.24E-01 6.11E-01 1.89E+01 6.41E-01 Np-237 3.23E-07 9.15E-02 9.56E-02 7.24E-02 9.82E-02 7.93E-02 2.40E-02 3.62E-02 1.01E-01 2.56E-02

Attachment D U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 170 of 200 Sample ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline WO 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Eberline Sample Date 12/10/2012 12/10/2012 12/10/2012 12/10/2012 12/10/2012 1/30/2013 1/30/2013 12/10/2012 1/30/2013 Nuclide Decay Const yr-1 Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Pu-238 7.90E-03 1.25E-01 2.35E-01 3.05E-01 3.18E+00 1.31E-01 5.39E-02 1.03E-01 1.65E-01 9.33E-02 Pu-239 2.87E-05 4.92E-02 5.55E-02 5.58E-02 1.15E+00 3.81E-02 2.62E-02 8.21E-02 5.26E-02 2.94E-02 Pu-240 1.06E-04 4.92E-02 5.55E-02 5.58E-02 1.15E+00 3.81E-02 2.62E-02 8.21E-02 5.26E-02 2.94E-02 Pu-241 4.83E-02 8.17E+00 7.08E+00 8.54E+00 1.24E+01 7.86E+00 5.60E-01 4.53E-01 9.36E+00 4.79E-01 Am-241 1.60E-03 3.58E-01 1.39E+00 4.25E-01 5.15E+01 2.68E-01 1.67E-01 8.80E-02 1.01E-01 5.40E-02 Am-243 9.40E-05 8.37E-02 1.36E-01 6.05E-03 5.33E-01 8.36E-02 3.80E-02 4.49E-02 7.63E-02 2.96E-02 Cm-243 2.43E-02 4.35E-02 1.67E-01 6.36E-02 5.04E+00 7.14E-02 2.17E-02 2.02E-02 3.63E-02 3.23E-02 Cm-244 3.83E-02 4.35E-02 1.67E-01 6.36E-02 5.04E+00 7.14E-02 2.17E-02 2.02E-02 3.63E-02 3.23E-02 Note: Bold Italics = MDA Value, Bold Red = Questionable or Suspect Results retained as valid results, Bold Blue = Questionable or Suspect Results eliminated as False Positives. Yellow Cells = Samples with high Cs-137 that had low Ni-63 values. Purple Cells = Pu-241 results replaced by 13-04025 reanalysis results. (See basis in Section 3.4)

Attachment D U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 171 of 200 Sample ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline WO 13-03084 13-03084 13-03084 13-04110 13-03084 13-04110 13-03084 13-04110 Eberline Sample Date 3/20/2013 3/20/2013 2/25/2013 2/28/2013 3/20/2013 3/5/2013 3/20/2013 2/25/2013 Nuclide Decay Const yr-1 Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g H-3 5.63E-02 1.27E+02 7.61E+01 5.57E+00 9.18E+00 2.06E+02 1.12E+01 5.19E+01 7.26E+00 C-14 1.22E-04 2.80E+00 5.80E+00 1.17E+00 3.94E+00 1.23E+00 2.72E+00 2.51E+00 4.44E+00 Fe-55 2.53E-01 1.41E+02 4.07E+01 4.07E+01 5.52E+00 2.14E+01 3.17E+00 2.51E+01 5.34E+00 Ni-59 6.86E-06 7.68E+00 7.19E+00 7.19E+00 9.68E+00 6.88E+00 6.95E+00 7.08E+00 6.75E+00 Co-60 1.31E-01 9.96E+02 6.91E+02 2.59E+02 1.09E+03 1.83E+02 8.01E+01 4.35E+01 7.57E+01 Ni-63 6.92E-03 4.35E+03 1.23E+03 2.72E+02 4.85E+03 1.08E+02 9.98E+00 1.07E+02 3.11E+02 Sr-90 2.41E-02 4.84E+00 1.41E+00 1.46E+00 1.76E+01 8.33E-01 4.17E-01 3.79E+00 2.08E+00 Nb-94 3.41E-05 1.92E+01 1.77E+01 1.77E+01 3.50E+00 5.97E+00 1.06E+00 7.04E+00 1.25E+00 Tc-99 3.28E-06 2.86E-01 2.22E+00 6.85E-01 3.97E-01 2.54E-01 2.95E-01 3.96E-01 2.80E-01 Ag-108m 1.66E-03 6.85E+01 2.29E+01 1.88E+00 2.93E+00 7.03E+00 8.09E-01 9.72E+00 1.08E+00 Sb-125 2.51E-01 2.39E+02 1.00E+02 1.00E+02 2.93E+00 5.56E+01 6.51E+00 6.41E+01 1.52E+01 I-129 4.41E-08 1.70E+04 4.14E+02 6.76E+01 1.02E+01 2.38E+02 1.11E+01 8.05E+02 4.31E+02 Cs-134 3.36E-01 6.09E+01 2.10E+01 8.27E+00 3.10E+00 8.75E+00 1.26E+00 1.12E+01 1.68E+01 Cs-137 2.30E-02 2.14E+05 5.58E+04 8.45E+03 2.49E+03 2.09E+04 1.13E+03 2.66E+04 4.51E+03 Pm-145 3.92E-02 1.23E+04 8.75E+02 1.08E+03 3.31E+01 2.62E+03 1.28E+02 1.12E+03 3.88E+02 Pm-147 2.64E-01 1.82E-01 1.93E-01 2.22E+00 8.95E+00 1.88E-01 6.22E-01 1.80E-01 3.77E+00 Eu-152 5.12E-02 3.98E+01 5.08E+01 5.08E+01 9.27E+00 1.22E+01 3.28E+00 1.11E+01 3.58E+00 Eu-154 7.88E-02 2.70E+01 3.35E+01 3.35E+01 5.45E+00 9.97E+00 1.43E+00 1.21E+01 1.75E+00 Eu-155 1.46E-01 7.97E+01 3.55E+01 6.12E+00 4.05E+00 2.00E+01 2.32E+00 2.39E+01 4.58E+00 Np-237 3.23E-07 2.74E-02 2.85E-02 2.85E-02 2.96E-02 3.68E-02 3.84E-02 2.90E-02 3.17E-02 Pu-238 7.90E-03 4.15E-02 3.99E-02 2.59E-02 1.64E-01 4.71E-02 2.85E-02 4.43E-02 3.67E-02 Pu-239 2.87E-05 2.20E-02 2.50E-02 2.37E-02 7.70E-02 2.24E-02 1.43E-02 2.02E-02 1.28E-02

Attachment D U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 172 of 200 Sample ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline WO 13-03084 13-03084 13-03084 13-04110 13-03084 13-04110 13-03084 13-04110 Eberline Sample Date 3/20/2013 3/20/2013 2/25/2013 2/28/2013 3/20/2013 3/5/2013 3/20/2013 2/25/2013 Nuclide Decay Const yr-1 Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Result pCi/g Pu-240 1.06E-04 2.20E-02 2.50E-02 2.37E-02 7.70E-02 2.24E-02 1.43E-02 2.02E-02 1.28E-02 Pu-241 4.83E-02 3.38E+00 4.01E+00 2.79E+00 6.17E+00 4.65E+00 3.45E+00 4.20E+00 3.09E+00 Am-241 1.60E-03 2.49E-01 1.24E-01 1.27E-01 6.28E+00 5.08E-02 4.55E-02 4.48E-02 4.25E-02 Am-243 9.40E-05 4.86E-02 3.28E-02 3.92E-02 3.80E-01 3.58E-02 7.19E-02 5.63E-02 3.94E-02 Cm-243 2.43E-02 4.52E-02 2.27E-02 2.78E-02 5.93E-01 1.75E-02 1.99E-02 2.30E-02 1.83E-02 Cm-244 3.83E-02 4.52E-02 2.27E-02 2.78E-02 5.93E-01 1.75E-02 1.99E-02 2.30E-02 1.83E-02 Note: Bold Italics are MDA values Note: Bold Italics = MDA Value, Bold Red = Questionable or Suspect Results retained as valid results, Bold Blue = Questionable or Suspect Results eliminated as False Positives. Yellow Cells = Samples with high Cs-137 that had low Ni-63 values. (See basis in Section 3.4)

Attachment E Decay Corrected U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 173 of 200 Sample ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline WO 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Eberline Sample Date 12/10/2012 12/10/2012 12/10/2012 12/10/2012 12/10/2012 1/30/2013 1/30/2013 12/10/2012 1/30/2013 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years 0.059 0.059 0.059 0.059 0.059

-0.081

-0.081 0.059

-0.081 Nuclide Decay Const yr-1 Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g H-3 5.63E-02 1.90E+01 2.59E+01 3.73E+01 2.70E+01 1.19E+02 8.15E+01 5.07E+01 7.58E+01 5.42E+01 C-14 1.22E-04 2.50E+00 3.62E+00 4.40E+00 2.46E+01 2.71E+00 1.51E+00 1.12E+00 9.52E+00 1.09E+00 Fe-55 2.53E-01 5.73E+02 9.02E+01 1.76E+02 4.57E+01 3.99E+01 2.03E+00 2.17E+00 4.69E+01 2.04E+00 Ni-59 6.86E-06 3.26E+01 3.31E+01 2.65E+01 3.01E+01 3.07E+01 7.33E+00 6.52E+00 3.33E+01 7.30E+00 Co-60 1.31E-01 8.05E+01 7.04E+03 8.63E+01 3.33E+04 9.70E+02 4.40E+01 1.51E+01 8.61E+01 8.59E+00 Ni-63 6.92E-03 1.81E+04 2.26E+03 6.29E+03 2.81E+03 1.14E+01 3.02E+01 5.48E+00 2.39E+01 1.13E+01 Sr-90 2.41E-02 4.74E+01 7.59E+00 1.63E+02 1.45E+01 7.07E+00 3.97E-01 5.68E-01 8.45E+00 4.75E-01 Nb-94 3.41E-05 8.56E+01 1.56E+01 5.13E+01 2.55E+01 7.85E+00 6.01E-01 3.03E-01 9.30E+00 2.37E-01 Tc-99 3.28E-06 2.25E+01 1.22E+00 3.46E+01 9.31E-01 9.35E-01 2.96E-01 2.60E-01 1.13E+00 2.66E-01 Ag-108m 1.66E-03 2.39E+02 1.72E+01 5.72E+01 2.05E+01 9.25E+00 4.50E-01 2.35E-01 1.19E+01 2.09E-01 Sb-125 2.51E-01 1.89E+02 5.46E+01 1.21E+02 3.82E+01 4.70E+01 1.90E+00 1.68E+00 5.54E+01 3.02E-02 I-129 4.41E-08 3.19E+04 1.22E+04 5.26E+03 2.05E+02 7.47E+02 1.59E+01 5.07E-01 8.83E+02 8.06E-01 Cs-134 3.36E-01 5.36E+01 1.58E+01 3.61E+01 1.50E+01 9.28E+00 4.57E-01 3.40E-01 3.85E+01 3.64E-01 Cs-137 2.30E-02 1.45E+05 9.42E+04 1.21E+05 2.71E+03 4.26E+04 1.38E+02 1.60E+02 5.90E+04 1.43E+02 Pm-145 3.92E-02 1.49E+04 1.38E+04 3.48E+03 2.75E+02 5.24E+03 1.43E+01 1.74E+00 8.47E+03 2.03E+00 Pm-147 2.64E-01 6.93E+01 5.15E+01 4.00E+02 3.83E+02 1.45E+01 1.21E+00 5.23E-01 1.45E+01 5.27E-01 Eu-152 5.12E-02 4.51E+02 7.28E+01 2.51E+02 1.24E+02 2.29E+01 1.82E+00 8.59E-01 1.94E+01 1.06E+00 Eu-154 7.88E-02 2.25E+02 3.56E+01 1.28E+02 5.13E+01 1.47E+01 9.47E-01 5.29E-01 1.75E+01 5.47E-01

Attachment E Decay Corrected U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 174 of 200 Sample ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline WO 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Eberline Sample Date 12/10/2012 12/10/2012 12/10/2012 12/10/2012 12/10/2012 1/30/2013 1/30/2013 12/10/2012 1/30/2013 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years 0.059 0.059 0.059 0.059 0.059

-0.081

-0.081 0.059

-0.081 Nuclide Decay Const yr-1 Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Eu-155 1.46E-01 5.34E+01 2.35E+01 3.51E+01 1.68E+01 1.66E+01 6.31E-01 6.18E-01 1.87E+01 6.48E-01 Np-237 3.23E-07 9.15E-02 9.56E-02 7.24E-02 9.82E-02 7.93E-02 2.40E-02 3.62E-02 1.01E-01 2.56E-02 Pu-238 7.90E-03 1.25E-01 2.35E-01 3.05E-01 3.18E+00 1.31E-01 5.40E-02 1.03E-01 1.64E-01 9.34E-02 Pu-239 2.87E-05 4.92E-02 5.55E-02 5.58E-02 1.15E+00 3.81E-02 2.62E-02 8.21E-02 5.26E-02 2.94E-02 Pu-240 1.06E-04 4.92E-02 5.55E-02 5.58E-02 1.15E+00 3.81E-02 2.62E-02 8.21E-02 5.26E-02 2.94E-02 Pu-241 4.83E-02 8.15E+00 7.06E+00 8.51E+00 1.24E+01 7.84E+00 5.62E-01 4.55E-01 9.33E+00 4.81E-01 Am-241 1.60E-03 3.58E-01 1.39E+00 4.26E-01 5.15E+01 2.69E-01 1.66E-01 8.79E-02 1.01E-01 5.40E-02 Am-243 9.40E-05 8.37E-02 1.36E-01 6.05E-03 5.33E-01 8.36E-02 3.80E-02 4.49E-02 7.63E-02 2.96E-02 Cm-243 2.43E-02 4.34E-02 1.67E-01 6.35E-02 5.03E+00 7.13E-02 2.18E-02 2.03E-02 3.62E-02 3.24E-02 Cm-244 3.83E-02 4.34E-02 1.66E-01 6.35E-02 5.03E+00 7.12E-02 2.18E-02 2.03E-02 3.62E-02 3.24E-02 Note: Bold Italics = MDA Value, Bold Red = Questionable or Suspect Results retained as valid results, Bold Blue = Questionable or Suspect Results eliminated as False Positives. Yellow Cells = Samples with high Cs-137 that had low Ni-63 values. Purple Cells = Pu-241 results replaced by 13-04025 reanalysis results. (See basis in Section 3.4)

Attachment E Decay Corrected U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 175 of 200 Sample ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline WO 13-03084 13-03084 13-03084 13-04110 13-03084 13-04110 13-03084 13-04110 Eberline Sample Date 3/20/2013 3/20/2013 2/25/2013 2/28/2013 3/20/2013 3/5/2013 3/20/2013 2/25/2013 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years

-0.215

-0.215

-0.152

-0.160

-0.215

-0.174

-0.215

-0.152 Nuclide Decay Const yr-1 Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g H-3 5.63E-02 1.27E+02 7.61E+01 5.57E+00 9.18E+00 2.06E+02 1.12E+01 5.19E+01 7.26E+00 C-14 1.22E-04 2.80E+00 5.80E+00 1.17E+00 3.94E+00 1.23E+00 2.72E+00 2.51E+00 4.44E+00 Fe-55 2.53E-01 1.41E+02 4.07E+01 4.07E+01 5.52E+00 2.14E+01 3.17E+00 2.51E+01 5.34E+00 Ni-59 6.86E-06 7.68E+00 7.19E+00 7.19E+00 9.68E+00 6.88E+00 6.95E+00 7.08E+00 6.75E+00 Co-60 1.31E-01 9.96E+02 6.91E+02 2.59E+02 1.09E+03 1.83E+02 8.01E+01 4.35E+01 7.57E+01 Ni-63 6.92E-03 4.35E+03 1.23E+03 2.72E+02 4.85E+03 1.08E+02 9.98E+00 1.07E+02 3.11E+02 Sr-90 2.41E-02 4.84E+00 1.41E+00 1.46E+00 1.76E+01 8.33E-01 4.17E-01 3.79E+00 2.08E+00 Nb-94 3.41E-05 1.92E+01 1.77E+01 1.77E+01 3.50E+00 5.97E+00 1.06E+00 7.04E+00 1.25E+00 Tc-99 3.28E-06 2.86E-01 2.22E+00 6.85E-01 3.97E-01 2.54E-01 2.95E-01 3.96E-01 2.80E-01 Ag-108m 1.66E-03 6.85E+01 2.29E+01 1.88E+00 2.93E+00 7.03E+00 8.09E-01 9.72E+00 1.08E+00 Sb-125 2.51E-01 2.39E+02 1.00E+02 1.00E+02 2.93E+00 5.56E+01 6.51E+00 6.41E+01 1.52E+01 I-129 4.41E-08 1.70E+04 4.14E+02 6.76E+01 1.02E+01 2.38E+02 1.11E+01 8.05E+02 4.31E+02 Cs-134 3.36E-01 6.09E+01 2.10E+01 8.27E+00 3.10E+00 8.75E+00 1.26E+00 1.12E+01 1.68E+01 Cs-137 2.30E-02 2.14E+05 5.58E+04 8.45E+03 2.49E+03 2.09E+04 1.13E+03 2.66E+04 4.51E+03 Pm-145 3.92E-02 1.23E+04 8.75E+02 1.08E+03 3.31E+01 2.62E+03 1.28E+02 1.12E+03 3.88E+02 Pm-147 2.64E-01 1.82E-01 1.93E-01 2.22E+00 8.95E+00 1.88E-01 6.22E-01 1.80E-01 3.77E+00 Eu-152 5.12E-02 3.98E+01 5.08E+01 5.08E+01 9.27E+00 1.22E+01 3.28E+00 1.11E+01 3.58E+00 Eu-154 7.88E-02 2.70E+01 3.35E+01 3.35E+01 5.45E+00 9.97E+00 1.43E+00 1.21E+01 1.75E+00

Attachment E Decay Corrected U1 & 2 568 Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 176 of 200 Sample ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline WO 13-03084 13-03084 13-03084 13-04110 13-03084 13-04110 13-03084 13-04110 Eberline Sample Date 3/20/2013 3/20/2013 2/25/2013 2/28/2013 3/20/2013 3/5/2013 3/20/2013 2/25/2013 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years

-0.215

-0.215

-0.152

-0.160

-0.215

-0.174

-0.215

-0.152 Nuclide Decay Const yr-1 Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Eu-155 1.46E-01 7.97E+01 3.55E+01 6.12E+00 4.05E+00 2.00E+01 2.32E+00 2.39E+01 4.58E+00 Np-237 3.23E-07 2.74E-02 2.85E-02 2.85E-02 2.96E-02 3.68E-02 3.84E-02 2.90E-02 3.17E-02 Pu-238 7.90E-03 4.15E-02 3.99E-02 2.59E-02 1.64E-01 4.71E-02 2.85E-02 4.43E-02 3.67E-02 Pu-239 2.87E-05 2.20E-02 2.50E-02 2.37E-02 7.70E-02 2.24E-02 1.43E-02 2.02E-02 1.28E-02 Pu-240 1.06E-04 2.20E-02 2.50E-02 2.37E-02 7.70E-02 2.24E-02 1.43E-02 2.02E-02 1.28E-02 Pu-241 4.83E-02 3.38E+00 4.01E+00 2.79E+00 6.17E+00 4.65E+00 3.45E+00 4.20E+00 3.09E+00 Am-241 1.60E-03 2.49E-01 1.24E-01 1.27E-01 6.28E+00 5.08E-02 4.55E-02 4.48E-02 4.25E-02 Am-243 9.40E-05 4.86E-02 3.28E-02 3.92E-02 3.80E-01 3.58E-02 7.19E-02 5.63E-02 3.94E-02 Cm-243 2.43E-02 4.52E-02 2.27E-02 2.78E-02 5.93E-01 1.75E-02 1.99E-02 2.30E-02 1.83E-02 Cm-244 3.83E-02 4.52E-02 2.27E-02 2.78E-02 5.93E-01 1.75E-02 1.99E-02 2.30E-02 1.83E-02 Est Am-243 Using SF 1.29E-02 6.42E-03 6.58E-03 3.25E-01 2.63E-03 2.35E-03 2.32E-03 2.20E-03 Est Cm-244 Using SF 7.56E-04 3.80E-04 4.65E-04 9.92E-03 2.92E-04 3.33E-04 3.84E-04 3.07E-04 Note: Bold Italics = MDA Value, Bold Red = Questionable or Suspect Results retained as valid results, Bold Blue = Questionable or Suspect Results eliminated as False Positives. Yellow Cells = Samples with high Cs-137 that had low Ni-63 values. (See basis in Section 3.4)

Attachment F Key Radionuclide Ratios Decay Corrected U1 & 2 568 Elevation Eberline Results TSD 13-006 Revision 0 Page 177 of 200 Unit 1 568 Foot Concrete Key Radionuclide Ratios Core ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline Report 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Gross beta to alpha Detectable Gross Beta > 0.4 keV 1.78E+05 1.14E+05 1.28E+05 3.68E+04 4.44E+04 2.04E+02 1.80E+02 6.01E+04 1.57E+02 Detectable Gross Alpha 8.44E-01 2.30E+00 1.05E+00 6.77E+01 7.81E-01 3.78E-01 4.77E-01 6.21E-01 3.26E-01 Gross Beta/Gross Alpha 2.11E+05 4.94E+04 1.22E+05 5.43E+02 5.68E+04 5.39E+02 3.78E+02 9.68E+04 4.81E+02 Am-241 Ratios Pu-238/Am-241 3.48E-01 1.69E-01 7.15E-01 6.17E-02 4.86E-01 3.24E-01 1.17E+00 1.62E+00 1.73E+00 Pu-239/Am-241 1.37E-01 4.00E-02 1.31E-01 2.23E-02 1.42E-01 1.58E-01 9.33E-01 5.19E-01 5.45E-01 Pu-240/Am-241 1.37E-01 4.00E-02 1.31E-01 2.23E-02 1.42E-01 1.58E-01 9.33E-01 5.19E-01 5.45E-01 Pu-241/Am-241 2.27E+01 5.08E+00 2.00E+01 2.40E-01 2.91E+01 3.38E+00 5.18E+00 9.21E+01 8.91E+00 Am-243/Am-241 2.34E-01 9.76E-02 1.42E-02 1.03E-02 3.11E-01 2.28E-01 5.10E-01 7.53E-01 5.48E-01 Cm-243/Am-241 1.21E-01 1.20E-01 1.49E-01 9.77E-02 2.65E-01 1.31E-01 2.31E-01 3.58E-01 6.00E-01 Cm-244/Am-241 1.21E-01 1.20E-01 1.49E-01 9.76E-02 2.65E-01 1.31E-01 2.31E-01 3.57E-01 6.00E-01 Am-241/Gross Alpha 42%

60%

41%

76%

34%

44%

18%

ND ND Cs-137 Ratios H-3/Cs-137 1.31E-04 2.75E-04 3.07E-04 9.94E-03 2.78E-03 5.92E-01 3.17E-01 1.28E-03 3.79E-01 C-14/Cs-137 1.72E-05 3.85E-05 3.62E-05 9.08E-03 6.35E-05 1.10E-02 6.97E-03 1.61E-04 7.66E-03 Co-60/Cs-137 5.55E-04 7.47E-02 7.10E-04 1.23E+01 2.27E-02 3.20E-01 9.44E-02 1.46E-03 6.01E-02 Ni-63/Cs-137 1.25E-01 2.40E-02 5.18E-02 1.04E+00 2.68E-04 2.19E-01 3.42E-02 4.05E-04 7.90E-02 Sr-90/Cs-137 3.27E-04 8.06E-05 1.34E-03 5.36E-03 1.66E-04 2.88E-03 3.55E-03 1.43E-04 3.32E-03 Tc-99/Cs-137 1.55E-04 1.29E-05 2.85E-04 3.43E-04 2.19E-05 2.15E-03 1.62E-03 1.91E-05 1.86E-03 Sb-125/Cs-137 1.31E-03 5.79E-04 9.96E-04 1.41E-02 1.10E-03 1.38E-02 1.05E-02 9.38E-04 2.11E-04 I-129/Cs-137 2.20E-01 1.30E-01 4.33E-02 7.56E-02 1.75E-02 1.15E-01 3.16E-03 1.50E-02 5.64E-03 Pm-145/Cs-137 1.03E-01 1.46E-01 2.87E-02 1.01E-01 1.23E-01 1.04E-01 1.09E-02 1.44E-01 1.42E-02 Pm-147/Cs-137 4.78E-04 5.47E-04 3.29E-03 1.41E-01 3.40E-04 8.82E-03 3.27E-03 2.46E-04 3.68E-03 Eu-152/Cs-137 3.10E-03 7.73E-04 2.07E-03 4.58E-02 5.36E-04 1.32E-02 5.37E-03 3.29E-04 7.43E-03 Eu-154/Cs-137 1.55E-03 3.78E-04 1.05E-03 1.89E-02 3.45E-04 6.87E-03 3.30E-03 2.97E-04 3.83E-03

Attachment F Key Radionuclide Ratios Decay Corrected U1 & 2 568 Elevation Eberline Results TSD 13-006 Revision 0 Page 178 of 200 Core ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline Report 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Eu-155/Cs-137 3.68E-04 2.49E-04 2.89E-04 6.20E-03 3.90E-04 4.58E-03 3.86E-03 3.17E-04 4.53E-03 Np-237/Cs-137 6.31E-07 1.01E-06 5.96E-07 3.62E-05 1.86E-06 1.74E-04 2.26E-04 1.72E-06 1.79E-04 Pu-238/Cs-137 8.61E-07 2.50E-06 2.51E-06 1.17E-03 3.07E-06 3.92E-04 6.45E-04 2.78E-06 6.53E-04 Pu-239/Cs-137 3.39E-07 5.89E-07 4.60E-07 4.24E-04 8.94E-07 1.91E-04 5.13E-04 8.91E-07 2.06E-04 Pu-240/Cs-137 3.39E-07 5.89E-07 4.60E-07 4.24E-04 8.94E-07 1.91E-04 5.13E-04 8.91E-07 2.06E-04 Pu-241/Cs-137 5.61E-05 7.49E-05 7.01E-05 4.56E-03 1.84E-04 4.08E-03 2.84E-03 1.58E-04 3.37E-03 Am-241/Cs-137 2.47E-06 1.47E-05 3.51E-06 1.90E-02 6.31E-06 1.21E-03 5.49E-04 1.72E-06 3.78E-04 Am-243/Cs-137 5.77E-07 1.44E-06 4.98E-08 1.97E-04 1.96E-06 2.76E-04 2.80E-04 1.29E-06 2.07E-04 Cm-243/Cs-137 2.99E-07 1.77E-06 5.23E-07 1.86E-03 1.67E-06 1.58E-04 1.27E-04 6.14E-07 2.27E-04 Cm-244/Cs-137 2.99E-07 1.77E-06 5.23E-07 1.85E-03 1.67E-06 1.58E-04 1.27E-04 6.13E-07 2.27E-04 Gross Alpha/Cs-137 5.81E-06 2.44E-05 8.63E-06 2.50E-02 1.83E-05 2.75E-03 2.98E-03 ND ND Co-60 Ratios H-3/Co-60 2.36E-01 3.68E-03 4.33E-01 8.10E-04 1.22E-01 1.85E+00 3.36E+00 8.81E-01 6.31E+00 C-14/Co-60 3.11E-02 5.15E-04 5.10E-02 7.40E-04 2.79E-03 3.43E-02 7.38E-02 1.11E-01 1.27E-01 Fe-55/Co-60 7.12E+00 1.28E-02 2.04E+00 1.37E-03 4.12E-02 4.62E-02 1.43E-01 5.45E-01 2.38E-01 Ni-59/C0-60 4.05E-01 4.70E-03 3.07E-01 9.04E-04 3.16E-02 1.67E-01 4.31E-01 3.87E-01 8.50E-01 Ni-63/Co-60 2.25E+02 3.21E-01 7.29E+01 8.45E-02 1.18E-02 6.87E-01 3.63E-01 2.78E-01 1.32E+00 Sr-90/Co-60 3.27E-04 8.06E-05 1.34E-03 5.36E-03 1.66E-04 2.88E-03 3.55E-03 1.43E-04 3.32E-03 Nb-94/Co-60 1.06E+00 2.21E-03 5.95E-01 7.68E-04 8.09E-03 1.37E-02 2.00E-02 1.08E-01 2.75E-02 Tc-99/Co-60 2.80E-01 1.73E-04 4.02E-01 2.80E-05 9.65E-04 6.72E-03 1.72E-02 1.31E-02 3.09E-02 Ag-108m/Co-60 2.97E+00 2.44E-03 6.63E-01 6.16E-04 9.54E-03 1.02E-02 1.55E-02 1.39E-01 2.43E-02 Pu-238/Co-60 1.55E-03 3.34E-05 3.53E-03 9.56E-05 1.35E-04 1.23E-03 6.83E-03 1.91E-03 1.09E-02 Pu-239/Co-60 6.11E-04 7.89E-06 6.47E-04 3.45E-05 3.93E-05 5.96E-04 5.43E-03 6.11E-04 3.43E-03 Pu-240/Co-60 6.11E-04 7.89E-06 6.47E-04 3.45E-05 3.93E-05 5.96E-04 5.43E-03 6.11E-04 3.43E-03 Pu-241/Co-60 1.01E-01 1.00E-03 9.87E-02 3.72E-04 8.08E-03 1.28E-02 3.01E-02 1.08E-01 5.60E-02 Am-241/Co-60 4.45E-03 1.97E-04 4.94E-03 1.55E-03 2.77E-04 3.78E-03 5.82E-03 1.18E-03 6.29E-03 Am-243/Co-60 1.04E-03 1.93E-05 7.01E-05 1.60E-05 8.63E-05 8.62E-04 2.97E-03 8.86E-04 3.45E-03

Attachment F Key Radionuclide Ratios Decay Corrected U1 & 2 568 Elevation Eberline Results TSD 13-006 Revision 0 Page 179 of 200 Core ID B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Eberline Report 12-12088 12-12088 12-12088 12-12088 12-12088 13-02003 13-02003 12-12088 13-02003 Cm-243/Co-60 5.39E-04 2.37E-05 7.37E-04 1.51E-04 7.35E-05 4.95E-04 1.34E-03 4.21E-04 3.77E-03 Cm-244/Co-60 5.39E-04 2.36E-05 7.36E-04 1.51E-04 7.35E-05 4.95E-04 1.34E-03 4.21E-04 3.78E-03 Gross Alpha/Co-60 1.05E-02 3.27E-04 1.21E-02 2.03E-03 8.06E-04 8.60E-03 3.15E-02 ND ND Note: Bold Italics are MDA values Unit 2 568 Foot Concrete Key Radionuclide Ratios Core ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline Report 13-03084 13-03084 13-04110 13-04110 13-03084 13-04110 13-03084 13-04110 Detectable Gross Beta > 0.4 keV 2.15E+05 5.65E+04 8.72E+03 3.62E+03 2.11E+04 1.21E+03 2.67E+04 4.61E+03 Detectable Gross Alpha 3.88E-01 2.02E-01 2.30E-01 8.17E+00 ND ND ND ND Gross Beta/Gross Alpha 5.54E+05 2.79E+05 3.79E+04 4.43E+02 ND ND ND ND Am-241 Ratios Pu-238/Am-241 Ratio 1.67E-01 3.21E-01 2.04E-01 2.62E-02 9.25E-01 6.28E-01 9.88E-01 8.64E-01 Pu-239/Am-241 Ratio 8.86E-02 2.01E-01 1.87E-01 1.23E-02 4.40E-01 3.14E-01 4.50E-01 3.00E-01 Pu-240/Am-241 Ratio 8.86E-02 2.01E-01 1.87E-01 1.23E-02 4.40E-01 3.14E-01 4.50E-01 3.00E-01 Pu-241/Am-241 Ratio 1.36E+01 3.23E+01 2.20E+01 9.82E-01 9.15E+01 7.60E+01 9.38E+01 7.28E+01 Am-243/Am-241 Ratio 1.96E-01 2.64E-01 3.08E-01 6.04E-02 7.05E-01 1.58E+00 1.26E+00 9.27E-01 Cm-243/Am-241 Ratio 1.82E-01 1.83E-01 2.19E-01 9.44E-02 3.44E-01 4.38E-01 5.13E-01 4.31E-01 Cm-244/Am-241 Ratio 1.82E-01 1.83E-01 2.19E-01 9.44E-02 3.44E-01 4.38E-01 5.13E-01 4.31E-01 Am-241/Gross Alpha 64%

61%

55%

77%

ND ND ND ND Cs-137 Ratios H-3/Cs-137 5.94E-04 1.36E-03 6.59E-04 3.69E-03 9.84E-03 9.95E-03 1.95E-03 1.61E-03 C-14/Cs-137 1.31E-05 1.04E-04 1.39E-04 1.58E-03 5.88E-05 2.42E-03 9.43E-05 9.84E-04 Co-60/Cs-137 4.66E-03 1.24E-02 3.07E-02 4.37E-01 8.77E-03 7.11E-02 1.63E-03 1.68E-02 Sr-90/Cs-137 2.26E-05 2.52E-05 1.73E-04 7.05E-03 3.98E-05 3.70E-04 1.42E-04 4.61E-04 Tc-99/Cs-137 1.33E-06 3.97E-05 8.10E-05 1.59E-04 1.22E-05 2.62E-04 1.49E-05 6.21E-05 Pu-238/Cs-137 1.94E-07 7.14E-07 3.07E-06 6.60E-05 2.25E-06 2.54E-05 1.66E-06 8.15E-06

Attachment F Key Radionuclide Ratios Decay Corrected U1 & 2 568 Elevation Eberline Results TSD 13-006 Revision 0 Page 180 of 200 Core ID B102102-CJFCCV-001 B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 B102107-CJFCCV-001 Eberline Report 13-03084 13-03084 13-04110 13-04110 13-03084 13-04110 13-03084 13-04110 Pu-239/Cs-137 1.03E-07 4.47E-07 2.81E-06 3.09E-05 1.07E-06 1.27E-05 7.58E-07 2.83E-06 Pu-240/Cs-137 1.03E-07 4.47E-07 2.81E-06 3.09E-05 1.07E-06 1.27E-05 7.58E-07 2.83E-06 Pu-241/Cs-137 1.58E-05 7.19E-05 3.31E-04 2.48E-03 2.23E-04 3.07E-03 1.58E-04 6.87E-04 Am-241/Cs-137 1.16E-06 2.22E-06 1.51E-05 2.52E-03 2.43E-06 4.04E-05 1.68E-06 9.43E-06 Am-243/Cs-137 2.27E-07 5.87E-07 4.64E-06 1.52E-04 1.71E-06 6.39E-05 2.12E-06 8.74E-06 Cm-243/Cs-137 2.11E-07 4.07E-07 3.29E-06 2.38E-04 8.36E-07 1.77E-05 8.64E-07 4.06E-06 Cm-244/Cs-137 2.11E-07 4.07E-07 3.29E-06 2.38E-04 8.36E-07 1.77E-05 8.64E-07 4.06E-06 Gross Alpha/Cs-137 1.81E-06 3.62E-06 2.73E-05 3.28E-03 ND ND ND ND Co-60 Ratios H-3/Co-60 1.27E-01 1.10E-01 2.15E-02 8.44E-03 1.12E+00 1.40E-01 1.19E+00 9.59E-02 C-14/Co-60 2.81E-03 8.39E-03 4.52E-03 3.62E-03 6.71E-03 3.40E-02 5.77E-02 5.86E-02 Ni-63/Co-60 4.36E+00 1.77E+00 1.05E+00 4.46E+00 5.88E-01 1.25E-01 2.46E+00 4.11E+00 Sr-90/Co-60 4.86E-03 2.03E-03 5.63E-03 1.61E-02 4.54E-03 5.20E-03 8.71E-02 2.75E-02 Tc-99/Co-60 2.87E-04 3.21E-03 2.64E-03 3.65E-04 1.39E-03 3.69E-03 9.11E-03 3.70E-03 Pu-238/Co-60 4.16E-05 5.77E-05 9.99E-05 1.51E-04 2.57E-04 3.56E-04 1.02E-03 4.85E-04 Pu-239/Co-60 2.21E-05 3.61E-05 9.15E-05 7.07E-05 1.22E-04 1.78E-04 4.64E-04 1.69E-04 Pu-240/Co-60 2.21E-05 3.61E-05 9.15E-05 7.07E-05 1.22E-04 1.78E-04 4.64E-04 1.69E-04 Pu-241/Co-60 3.39E-03 5.80E-03 1.08E-02 5.67E-03 2.54E-02 4.31E-02 9.67E-02 4.09E-02 Am-241/Co-60 2.50E-04 1.80E-04 4.90E-04 5.77E-03 2.77E-04 5.68E-04 1.03E-03 5.62E-04 Am-243/Co-60 4.88E-05 4.74E-05 1.51E-04 3.49E-04 1.95E-04 8.98E-04 1.30E-03 5.21E-04 Cm-243/Co-60 4.54E-05 3.29E-05 1.07E-04 5.45E-04 9.53E-05 2.49E-04 5.29E-04 2.42E-04 Cm-244/Co-60 4.54E-05 3.29E-05 1.07E-04 5.45E-04 9.53E-05 2.49E-04 5.29E-04 2.42E-04 Gross Alpha/Co-60 3.89E-04 2.93E-04 8.88E-04 7.51E-03 ND ND ND ND Note: Bold Italics are MDA values

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 181 of 200 U1 CTMT Under Vessel 541.5' Floor Core Collection Date 8/29/12 B101110-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0.0 141.71 9/10/12 0914 9/10/12 8:56 1000 113 27.9 0.5 52.7 69.7 5.2 1.56E+02 0.5 9/10/12 0933 9/10/12 8:56 1000 113 22.6 0.5 29.6 76.3 5.8 1.35E+02 Puck 2 0.5 138.23 9/10/12 0952 9/10/12 9:34 1000 113 14.8 0.5 5.3 81.7 4.8 1.07E+02 1.0 9/10/12 1018 9/10/12 9:34 1000 113 14.8 0.4 5.2 84.6 0.9 1.06E+02 Puck 3 1.0 129.85 9/10/12 1040 9/10/12 10:22 1000 113 12.3 0.7 4.8 94.9 6.4 1.19E+02 1.5 9/10/12 1057 9/10/12 10:22 1000 113 13.3 0.4 3.6 104.0 6.3 1.28E+02 Puck 4 1.5 126.4 9/12/12 1253 9/12/12 12:36 1000 111 12.1 0.4 6.8 91.2 4.6 1.15E+02 2.0 9/12/12 1310 9/12/12 12:36 1000 111 11.8 0.4 6.9 86.7 3.8 1.10E+02 Puck 5 2.0 128.74 9/12/12 1330 9/12/12 13:13 1000 111 12.1 0.5 4.5 85.3 5.2 1.08E+02 2.5 9/12/12 1349 9/12/12 13:13 1000 111 11.6 0.5 4.1 90.9 5.3 1.12E+02 Puck 6 2.5 119.5 9/12/12 1408 9/12/12 13:51 1000 111 12.3 0.5 5.3 91.1 4.9 1.14E+02 3.0 9/12/12 1425 9/12/12 13:51 1000 111 11.9 0.5 5.0 86.2 4.1 1.08E+02 Puck 7 3.0 138.3 3.5 9/12/12 1502 9/12/12 14:27 1000 111 13.4 0.4 4.0 70.9 3.8 9.25E+01 Puck 9 3.5 546.36 Fragmented Sample Analyzed As Single Piece 4.0 Puck 20 9.0 9.5 1/24/13 0800 1/24/13 7:43 1000

-23 12.0 0.2 25.6 25.6 1.3 6.47E+01 Puck 21 67.91 9.5 1/24/13 0734 1/24/13 7:16 1000

-23 10.1 0.4 20.2 25.7 1.3 5.77E+01 Puck 22 9.5 123.27 1/24/13 1514 1/23/13 14:39 1000

-22 2.7 0.2 0.9 19.6 0.9 2.42E+01 10.0 1/23/13 1456 1/23/13 14:39 1000

-22 2.7 0.3 0.7 19.3 0.9 2.39E+01

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 182 of 200 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 23 10.0 121.47 1/23/13 1419 1/23/13 13:43 1000

-22 2.2 0.2 0.6 13.4 0.7 1.71E+01 10.5 1/23/13 1402 1/23/13 13:43 1000

-22 2.4 0.2 0.7 14.0 0.7 1.80E+01 Puck 24 10.5 116.85 1/24/13 0713 1/24/13 06;39 1000

-23 2.1 0.2 1.0 11.8 0.7 1.59E+01 11.0 1/24/13 0656 1/24/13 6:39 1000

-23 1.8 0.2 0.8 11.8 0.7 1.53E+01 Puck 25 11.0 116.91 1/24/13 0637 1/24/13 5:43 1000

-23 1.8 0.2 1.2 9.8 0.7 1.36E+01 11.5 1/23/13 1518 1/23/13 15;00 1000

-22 2.0 0.1 1.3 8.7 0.5 1.26E+01 Puck 26 11.5 110.54 1/23/13 1457 1/23/13 14:22 1000

-22 3.3 0.2 2.0 10.5 0.6 1.65E+01 12.0 1/23/13 1440 1/23/13 14:22 1000

-22 2.9 0.2 1.6 9.3 0.5 1.44E+01 Puck 27 12.0 106.55 1/23/13 1418 1/23/13 13:42 1000

-22 1.9 0.2 1.3 10.2 0.7 1.43E+01 12.5 1/23/13 1401 1/23/13 13:42 1000

-22 2.0 0.2 1.2 10.1 0.7 1.42E+01 Puck 28 12.5 113.34 1/23/13 1334 1/23/13 12;49 1000

-22 1.4 0.1 1.1 4.7 0.5 7.84E+00 13.0 1/23/13 1354 1/23/13 12;49 1000

-22 1.2 0.1 1.1 4.8 0.4 7.63E+00 Puck 29 13.0 112.88 1/23/13 1437 1/23/13 14:01 1000

-22 1.6 0.2 1.1 6.3 0.5 9.69E+00 13.5 1/23/13 1352 1/23/13 12:47 1000

-22 1.6 0.2 1.2 5.5 0.5 8.90E+00 Puck 30 13.5 110.86 1/23/13 1351 1/23/13 11:11 1000

-22 1.2 0.1 1.1 3.2 0.4 5.94E+00 14.0 1/23/13 1348 1/23/13 11:12 1000

-22 1.2 0.1 1.3 3.1 0.3 6.00E+00 Puck 31 14.0 112.96 1/23/13 1349 1/23/13 11:13 1000

-22 0.7 0.1 0.8 2.9 0.4 4.96E+00 14.5 1/23/12 1346 1/23/13 11:12 1000

-22 0.8 0.1 1.0 3.2 0.4 5.55E+00 Puck 31 14.5 115.67 1/24/13 0740 1/24/13 7:04 1000

-23 0.8 0.1 0.8 1.7 0.2 3.55E+00 15.0 1/24/13 0721 1/24/13 7:04 1000

-23 0.7 0.1 0.8 1.9 0.3 3.86E+00 Puck 32 15.0 133.46 1/24/13 0658 1/24/13 6:22 1000

-23 0.7 0.1 0.7 1.6 0.3 3.45E+00 15.5 1/24/13 0640 1/24/13 6:22 1000

-23 0.8 0.7 1.7 3.25E+00

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 183 of 200 B101110-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 26.8 0.4 52.3 68.6 5.1 24.2 0.4 40.9 71.8 5.4 21.7 0.4 29.4 75.1 5.7 Puck 2 14.2 0.4 5.3 80.4 4.7 14.2 0.4 5.2 81.8 2.8 14.2 0.4 5.2 83.2 0.9 Puck 3 11.8 0.7 4.8 93.4 6.2 12.3 0.5 4.2 97.9 6.2 12.8 0.4 3.6 102.3 6.1 Puck 4 11.6 0.4 6.7 89.8 4.5 11.5 0.4 6.8 87.6 4.1 11.3 0.4 6.8 85.3 3.7 Puck 5 11.6 0.4 4.4 84.0 5.1 11.4 0.4 4.2 86.7 5.1 11.1 0.4 4.0 89.5 5.2 Puck 6 11.8 0.4 5.3 89.7 4.8 11.6 0.4 5.1 87.3 4.4 11.4 0.4 4.9 84.8 4.0 Puck 7 0.0 0.0 0.0 0.0 0.0 12.9 0.4 4.0 69.8 3.7 12.9 0.4 4.0 69.8 3.7 Puck 9 Fragmented Sample Analyzed As Single Piece 12.1 0.2 25.6 25.7 1.3 Puck 20 12.1 0.2 25.6 25.7 1.3 Puck 21 0.0 0.0 0.0 0.0 0.0 10.2 0.4 20.2 25.8 1.3 10.2 0.4 20.2 25.8 1.3 Puck 22 2.7 0.2 0.9 19.7 0.9 2.8 0.3 0.7 19.4 0.9 2.8 0.3 0.7 19.4 0.9 Puck 23 2.3 0.2 0.6 13.4 0.7 2.4 0.2 0.7 14.0 0.7 2.4 0.2 0.7 14.0 0.7 Puck 24 2.1 0.2 1.0 11.8 0.7 1.8 0.2 0.8 11.8 0.7

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 184 of 200 B101110-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g 1.8 0.2 0.8 11.8 0.7 Puck 25 1.8 0.2 1.2 9.9 0.7 2.0 0.2 1.3 8.8 0.5 2.0 0.2 1.3 8.8 0.5 Puck 26 3.3 0.2 2.0 10.5 0.6 2.9 0.2 1.6 9.3 0.5 2.9 0.2 1.6 9.3 0.5 Puck 27 1.9 0.2 1.3 10.2 0.7 2.0 0.2 1.2 10.1 0.7 2.0 0.2 1.2 10.1 0.7 Puck 28 1.4 0.1 1.1 4.8 0.5 1.2 0.1 1.1 4.8 0.4 1.2 0.1 1.1 4.8 0.4 Puck 29 1.6 0.2 1.1 6.3 0.5 1.6 0.2 1.2 5.5 0.5 1.6 0.2 1.2 5.5 0.5 Puck 30 1.2 0.1 1.1 3.2 0.4 1.2 0.1 1.3 3.1 0.3 1.2 0.1 1.3 3.1 0.3 Puck 31 0.7 0.1 0.8 2.9 0.4 0.8 0.2 1.0 3.2 0.4 0.8 0.2 1.0 3.2 0.4 Puck 31 0.8 0.1 0.8 1.7 0.2 0.7 0.1 0.8 1.9 0.3 0.7 0.1 0.8 1.9 0.3 Puck 32 0.7 0.1 0.7 1.6 0.3 0.9 0.0 0.7 1.7 0.0 0.9 0.0 0.7 1.7 0.0 Note: Bold Italics are MDA values

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 185 of 200 U1 CTMT Under Vessel 541.5' Floor Core Collection Date 8/29/12 B101110-CJFCCV-002 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0

123.68 9/10/12 0721 9/10/12 7:03 1000 113 348.0 1.5 2710.0 63.0 4.4 3.13E+03 0.5 9/10/12 0739 9/10/12 7:03 1000 113 209.0 1.2 1260.0 71.1 5.5 1.55E+03 Puck 2 0.5 130.97 9/10/12 0756 9/10/12 7:39 1000 113 14.7 0.4 1.6 85.3 5.3 1.07E+02 1

9/10/12 0813 9/10/12 7:39 1000 113 13.9 0.5 0.7 87.8 6.6 1.09E+02 Puck 3 1

129.04 9/10/12 0832 9/10/12 8:14 1000 113 15.2 0.5 1.0 101.0 5.7 1.23E+02 1.5 9/10/12 0854 9/10/12 8:15 1000 113 15.4 0.5 0.7 101.0 5.4 1.23E+02 Puck 4 1.5 134.68 9/17/12 1138 9/13/12 12:10 1000 110 11.9 0.5 0.4 100.0 6.2 1.19E+02 2

9/17/12 1142 9/13/12 12:10 1000 110 12.6 0.5 0.7 106.0 6.3 1.26E+02 Puck 5 2

134.11 9/17/12 1144 9/13/12 12:14 1000 110 11.8 0.5 0.624 102.0 6.0 1.21E+02 2.5 9/17/12 1225 9/13/12 12:15 1000 110 12.6 0.5 0.588 101.0 5.5 1.20E+02 Puck 6 2.5 136.44 9/17/12 1148 9/13/12 12:15 1000 110 15.7 0.5 0.4 108.0 5.4 1.30E+02 3

9/17/12 1150 9/13/12 12:15 1000 110 13.6 0.5 0.569 96.1 4.9 1.16E+02 Puck 7 3

137.32 9/17/12 1154 9/13/12 12:16 1000 110 11.2 0.4 0.545 87.5 0.4 1.00E+02 3.5 9/17/12 1155 9/13/12 12:16 1000 110 10.9 0.4 0.524 86.1 4.3 1.02E+02 Puck 8 3.5 150.45 9/17/12 1157 9/13/12 12:16 1000 110 6.3 0.4 0.41 58.7 2.7 6.84E+01 4

9/17/12 1159 9/13/12 12:16 1000 110 6.4 0.4 0.3 57.2 3.4 6.76E+01 Remain der 4

171.46 9/17/12 1200 9/13/12 12:17 1000 110 6.2 0.3 0.4 48.8 0.6 5.64E+01 Bottom Irregular Geometry - Not Analyzed

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 186 of 200 B101110-CJFCCV-002 Decay Corrected Results Core Section Co-60 Decay ed pCi/g Cs-134 Decaye d pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decaye d pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 334.1 1.3 2690.7 62.0 4.2 267.4 1.2 1970.9 66.0 4.8 200.7 1.1 1251.0 70.0 5.3 Puck 2 14.1 0.4 1.6 83.9 5.1 13.7 0.4 1.1 85.2 5.8 13.3 0.4 0.7 86.4 6.5 Puck 3 14.6 0.5 1.0 99.4 5.6 14.7 0.5 0.8 99.4 5.4 14.8 0.5 0.7 99.4 5.3 Puck 4 11.4 0.4 0.4 98.4 6.1 11.8 0.4 0.5 101.4 6.1 12.1 0.4 0.7 104.3 6.1 Puck 5 11.3 0.4 0.6 100.4 5.8 11.7 0.4 0.6 99.9 5.6 12.1 0.5 0.6 99.4 5.4 Puck 6 15.1 0.4 0.4 106.3 5.3 14.1 0.4 0.5 100.5 5.0 13.1 0.4 0.6 94.6 4.8 Puck 7 10.8 0.4 0.5 86.1 0.4 10.6 0.4 0.5 85.4 2.3 10.5 0.4 0.5 84.8 4.2 Puck 8 6.0 0.3 0.4 57.8 2.6 6.1 0.3 0.4 57.0 2.9 6.1 0.3 0.3 56.3 3.3 Remain der 6.0 0.3 0.4 48.0 0.6 6.0 0.3 0.4 48.0 0.6 Bottom Irregular Geometry - Not Analyzed Note: Bold Italics are MDA values

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 187 of 200 U1 CTMT Under Vessel 541.5' WALL Core Collection Date 8/29/12 B101110-CJWCCV-003 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.0231 0

0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0

130.24 9/10/12 1244 9/10/12 11:52 1000 113 11.2 0.4 37.2 56.0 4.2 1.09E+02 0.5 9/10/12 1242 9/10/12 11:52 1000 113 10.1 0.4 20.3 59.3 4.4 9.45E+01 Puck 2 0.5 134.58 9/10/12 1258 9/10/12 12:41 1000 113 6.4 0.3 1.4 52.4 2.7 6.31E+01 1

9/10/12 1317 9/10/12 12:41 1000 113 6.6 0.4 1.1 50.9 3.1 6.20E+01 Puck 3 1

137.12 9/17/12 1217 9/17/12 9:47 1000 106 8.6 0.4 1.3 79.5 4.6 9.44E+01 1.5 9/17/12 1204 9/17/12 9:58 1000 106 8.4 0.4 1.2 85.6 4.9 1.00E+02 Puck 4 1.5 149.39 9/17/12 1206 9/17/12 9:48 1000 106 9.2 0.4 0.8 82.8 4.3 9.75E+01 2

9/17/12 1208 9/17/12 9:48 1000 106 8.6 0.4 0.9 78.6 5.0 9.34E+01 Puck 5 2

138.36 9/17/12 1210 9/17/12 11:53 1000 106 8.7 0.4 1.1 73.1 3.1 8.63E+01 2.5 9/17/12 1236 9/17/12 9:49 1000 106 8.2 0.4 1.0 70.0 4.3 8.39E+01 Puck 6 2.5 121.65 9/17/12 1254 9/17/12 9:50 1000 106 6.7 0.4 0.9 63.4 3.9 7.53E+01 3

9/17/12 1312 9/17/12 9:50 1000 106 6.5 0.4 1.2 62.4 3.2 7.38E+01 Puck 7 3

149.02 9/17/12 1409 9/17/12 13:51 1000 106 6.0 0.3 1.8 55.3 2.9 6.62E+01 3.5 9/17/12 1349 9/17/12 9:50 1000 106 5.5 0.3 1.1 54.3 2.4 6.36E+01

Attachment G U1 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 188 of 200 B101110-CJWCCV-003 Decay Corrected Results Core Section Co-60 Decaye d pCi/g Cs-134 Decaye d pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decaye d pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 10.8 0.4 36.9 55.1 4.1 10.2 0.4 28.5 56.7 4.2 9.7 0.4 20.2 58.4 4.3 Puck 2 6.1 0.3 1.4 51.6 2.6 6.2 0.3 1.2 50.8 2.8 6.3 0.3 1.1 50.1 3.0 Puck 3 8.3 0.4 1.3 78.3 4.5 8.2 0.4 1.2 81.3 4.6 8.0 0.4 1.2 84.3 4.8 Puck 4 8.9 0.4 0.8 81.6 4.2 8.6 0.4 0.8 79.5 4.5 8.2 0.4 0.9 77.4 4.9 Puck 5 8.4 0.4 1.0 72.0 3.0 8.1 0.4 1.0 70.5 3.6 7.9 0.4 1.0 68.9 4.2 Puck 6 6.5 0.4 0.9 62.4 3.8 6.4 0.4 1.1 62.0 3.5 6.3 0.4 1.2 61.5 3.2 Puck 7 5.7 0.3 1.7 54.5 2.8 5.5 0.3 1.4 54.0 2.6 5.3 0.3 1.0 53.5 2.3 Note: Bold Italics are MDA values

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 189 of 200 U2 CTMT Under Vessel 541.5' Floor Core Collection Date 1/29/13 B102110-CJFCCV-001 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0

111.62 2/11/13 0749 2/11/13 7:32 1000

-41 23.5 0.5 674.0 114.0 8.5 8.20E+02 0.5 2/11/13 0817 2/11/13 7:34 1000

-41 21.9 0.8 477.0 128.0 9.4 6.37E+02 Puck 2 0.5 119.1 2/11/13 0844 2/11/13 8:18 1000

-41 21.9 0.7 27.8 180.0 11.3 2.42E+02 1

2/11/13 0904 2/11/13 8:19 1000

-41 20.5 0.7 22.1 183.0 10.5 2.37E+02 Puck 3 1

124.6 2/13/13 0757 2/13/13 7:40 1000

-43 18.2 0.7 0.4 190.0 10.9 2.20E+02 1.5 2/13/13 0820 2/13/13 8:02 1000

-43 16.8 0.5 0.4 173.0 11.6 2.02E+02 Puck 4 1.5 121.43 2/11/13 0923 2/11/13 8:21 1000

-41 22.7 0.7 0.6 181.0 11.2 2.16E+02 2

2/11/13 0943 2/11/13 8:22 1000

-41 23.9 0.7 0.8 176.0 10.4 2.12E+02 Puck 5 2

114.18 2/14/13 0904 2/14/13 8:46 1060

-44 20.0 0.5 0.5 178.0 9.9 2.09E+02 2.5 2/13/13 1905 2/13/13 14:03 18000

-43 20.7 0.2 0.5 192.0 11.3 2.25E+02 Puck 6 2.5 105.04 2/13/13 1907 2/13/13 14:05 18000

-43 15.7 0.1 0.5 149.0 8.8 1.74E+02 3

2/11/13 1018 2/11/13 8:24 1000

-41 14.8 0.4 0.5 146.0 8.3 1.70E+02 Puck 7 3

118.94 2/11/13 1002 2/11/13 8:25 1000

-41 15.9 0.6 0.8 149.0 7.9 1.74E+02 3.5 2/11/13 1019 2/11/13 8:25 1000

-41 15.8 0.6 0.7 144.0 9.1 1.70E+02 Puck 8 3.5 117.68 2/11/13 1036 2/11/13 8:26 1000

-41 14.3 0.4 0.7 132.0 7.6 1.55E+02 4

2/11/13 1057 2/11/13 8:26 1000

-41 13.3 0.4 0.7 127.0 7.5 1.49E+02 Puck 9 4

111.89 2/11/13 1037 2/11/13 10:09 1000

-41 12.8 0.6 1.0 127.0 6.1 1.48E+02 4.5 2/11/13 1058 2/11/13 10:09 1000

-41 12.6 0.6 1.0 123.0 7.4 1.45E+02 Puck 10 4.5 117.45 2/11/13 1203 2/11/13 10:09 1000

-41 19.8 0.6 1.3 127.0 7.2 1.56E+02 5

2/11/13 1222 2/11/13 10:10 1000

-41 20.4 0.6 0.8 130.0 6.9 1.59E+02 Puck 11 5

115.77 2/13/13 0839 2/13/13 8:22 1000

-43 12.8 0.4 1.4 96.7 5.0 1.16E+02 5.5 2/13/13 0857 2/13/13 8:22 1000

-43 12.8 0.4 1.4 93.7 5.0 1.13E+02

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 190 of 200 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 12 5.5 119.33 2/11/13 1240 2/11/13 10:11 1000

-41 9.3 0.5 1.3 92.5 4.8 1.08E+02 6

2/11/13 1259 2/11/13 10:11 1000

-41 9.6 0.5 1.0 90.1 2.7 1.04E+02 Puck 13 6

124.04 2/11/13 1241 2/11/13 10:11 1000

-41 8.1 0.3 2.0 68.8 3.4 8.26E+01 6.5 2/13/13 1043 2/13/13 10:26 1000

-43 7.2 0.3 1.6 66.2 2.9 7.82E+01 Puck 14 6.5 124.84 2/11/13 1316 2/11/13 10:12 1000

-41 9.2 0.5 1.4 71.2 3.4 8.57E+01 7

2/11/13 1334 2/11/13 10:12 1000

-41 10.4 0.5 1.6 71.6 4.0 8.80E+01 Puck 15 7

119.09 2/12/13 1056 2/12/13 10:38 1000

-42 7.8 0.4 1.9 62.5 2.9 7.55E+01 7.5 2/11/13 1335 2/11/13 10:13 1000

-41 5.6 0.3 1.7 51.2 2.7 6.14E+01 Puck 16 7.5 122.28 2/11/13 1352 2/11/13 10:15 1000

-41 4.3 0.4 2.1 46.0 1.8 5.46E+01 8

2/11/13 1422 2/11/13 10:16 1000

-41 4.3 0.3 1.7 43.3 2.5 5.22E+01 Puck 17 8

118.06 2/11/13 1353 2/11/13 13:07 1000

-41 4.1 0.2 2.1 33.8 1.7 4.20E+01 8.5 2/13/13 1042 2/13/13 10:25 1000

-43 4.0 0.4 2.2 36.7 0.5 4.38E+01 Puck 18 8.5 120.1 2/11/13 1442 2/11/13 13:08 1000

-41 4.0 0.3 1.7 35.1 1.8 4.30E+01 9

2/11/13 1500 2/11/13 13:08 1000

-41 3.9 0.3 1.8 30.7 1.4 3.81E+01 Puck 19 9

112.24 2/11/13 1443 2/11/13 13:09 1000

-41 2.4 0.2 1.4 23.2 1.0 2.82E+01 9.5 2/11/13 1501 2/11/13 13:09 1000

-41 2.3 0.2 1.2 21.9 0.9 2.66E+01 Puck 20 9.5 117.05 2/11/13 1521 2/11/13 13:09 1000

-41 2.7 0.2 1.2 21.8 0.7 2.65E+01 10 2/12/13 0654 2/11/13 13:10 1000

-41 2.5 0.3 0.9 23.5 1.2 2.84E+01 Puck 21 10 120.63 2/12/13 0655 2/11/13 15:23 1000

-41 2.4 0.2 0.9 16.7 1.6 2.18E+01 10.5 2/11/13 1528 2/11/13 13:11 1000

-41 2.6 0.3 0.7 17.9 0.9 2.24E+01 Puck 22 10.5 123.11 2/12/13 0713 2/11/13 13:11 1000

-41 2.7 0.4 1.0 18.0 0.9 2.29E+01 11 2/12/13 0734 2/11/13 13:12 1000

-41 2.5 0.3 1.0 15.7 0.8 2.03E+01 Puck 23 11 118.52 2/12/13 0847 2/12/13 8:29 1000

-42 1.5 0.2 1.1 11.8 0.7 1.52E+01 11.5 2/12/13 0733 2/12/13 7:16 1000

-42 1.3 0.2 0.9 10.7 0.6 1.36E+01 Puck 24 11.5 127.36 2/12/13 0751 2/11/13 13:13 1000

-41 3.5 0.2 0.7 11.3 0.7 1.64E+01 12 2/12/13 0824 2/11/13 13:14 1000

-41 3.3 0.2 0.5 10.7 0.7 1.54E+01

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 191 of 200 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 25 12 133.92 2/13/13 0928 2/13/13 9:10 1000

-43 1.2 0.1 0.9 7.4 0.4 1.01E+01 12.5 2/12/13 0823 2/11/13 13:15 1000

-41 1.2 0.1 1.0 7.4 0.4 1.01E+01 Puck 26 12.5 126.26 2/12/13 0917 2/12/13 7:37 1000

-42 0.5 0.2 0.7 5.9 0.5 7.74E+00 13 2/12/13 0936 2/12/13 7:37 1000

-42 0.8 0.2 0.6 5.1 0.5 7.16E+00 Puck 27 13 116.83 2/12/13 0849 2/12/13 7:37 1000

-42 0.4 0.1 0.8 3.9 0.4 5.59E+00 13.5 2/13/13 0926 2/12/13 9:08 1000

-42 0.5 0.2 0.8 4.5 0.7 6.61E+00 Puck 28 13.5 175.9 2/12/13 0928 2/12/13 7:38 1000

-42 0.5 0.1 0.7 2.8 0.3 4.40E+00 excess Bottom Irregular Geometry - Not Analyzed B102110-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 23.8 0.6 675.8 114.7 8.5 23.0 0.7 577.0 121.7 9.0 22.2 0.8 478.2 128.8 9.5 Puck 2 22.2 0.7 27.9 181.1 11.4 21.5 0.7 25.0 182.6 11.0 20.8 0.7 22.2 184.1 10.6 Puck 3 18.5 0.7 0.4 191.2 11.0 17.8 0.6 0.4 182.6 11.4 17.1 0.5 0.4 174.1 11.7 Puck 4 23.0 0.7 0.6 182.1 11.3 23.6 0.7 0.7 179.5 10.9 24.3 0.7 0.8 177.0 10.5 Puck 5 20.3 0.5 0.5 179.1 10.0 20.7 0.3 0.5 186.2 10.7 21.0 0.2 0.5 193.2 11.4 Puck 6 15.9 0.1 0.6 149.9 8.9 15.5 0.3 0.5 148.4 8.6 15.0 0.4 0.5 146.9 8.4 Puck 7 16.1 0.6 0.8 149.9 8.0 16.1 0.6 0.7 147.4 8.6

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 192 of 200 B102110-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g 16.0 0.6 0.7 144.8 9.2 Puck 8 14.5 0.4 0.7 132.8 7.7 14.0 0.4 0.7 130.3 7.6 13.5 0.4 0.7 127.7 7.5 Puck 9 13.0 0.6 1.0 127.7 6.2 12.9 0.6 1.0 125.7 6.8 12.8 0.6 1.0 123.7 7.4 Puck 10 20.1 0.6 1.3 127.7 7.3 20.4 0.6 1.1 129.3 7.1 20.7 0.6 0.8 130.8 6.9 Puck 11 13.0 0.4 1.4 97.3 5.0 13.0 0.4 1.4 95.8 5.0 13.0 0.4 1.4 94.3 5.0 Puck 12 9.4 0.5 1.3 93.0 4.9 9.6 0.5 1.2 91.8 3.8 9.7 0.5 1.0 90.6 2.7 Puck 13 8.2 0.3 2.0 69.2 3.4 7.8 0.3 1.8 67.9 3.2 7.3 0.3 1.6 66.6 2.9 Puck 14 9.4 0.5 1.4 71.6 3.5 10.0 0.5 1.5 71.8 3.7 10.6 0.5 1.6 72.0 4.0 Puck 15 7.9 0.4 1.9 62.9 2.9 6.8 0.4 1.8 57.2 2.8 5.6 0.3 1.7 51.5 2.7 Puck 16 4.4 0.4 2.1 46.3 1.8 4.4 0.4 1.9 44.9 2.2 4.4 0.4 1.7 43.6 2.5 Puck 17 4.2 0.2 2.1 34.0 1.7 4.1 0.3 2.1 35.5 1.1 4.1 0.4 2.2 36.9 0.5 Puck 18 4.1 0.3 1.7 35.3 1.9 4.0 0.3 1.8 33.1 1.6 4.0 0.3 1.8 30.9 1.4 Puck 19 2.4 0.2 1.4 23.3 1.0 2.4 0.2 1.3 22.7 1.0 2.4 0.2 1.2 22.0 0.9 Puck 20 2.7 0.2 1.2 21.9 0.7 2.6 0.3 1.0 22.8 1.0 2.6 0.3 0.9 23.6 1.2

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 193 of 200 B102110-CJFCCV-001 Decay Corrected Results Core Section Co-60 Decayed pCi/g Cs-134 Decayed pCi/g Cs-137 Decayed pCi/g Eu-152 Decayed pCi/g Eu-154 Decayed pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 21 2.5 0.2 0.9 16.8 1.6 2.6 0.2 0.8 17.4 1.3 2.7 0.3 0.7 18.0 0.9 Puck 22 2.7 0.4 1.0 18.1 0.9 2.6 0.3 1.0 16.9 0.9 2.5 0.3 1.0 15.8 0.8 Puck 23 1.5 0.2 1.1 11.9 0.7 1.4 0.2 1.0 11.3 0.6 1.4 0.2 0.9 10.8 0.6 Puck 24 3.5 0.2 0.7 11.4 0.7 3.5 0.2 0.6 11.1 0.7 3.4 0.2 0.5 10.8 0.7 Puck 25 1.2 0.1 0.9 7.5 0.5 1.2 0.1 0.9 7.5 0.4 1.2 0.1 1.0 7.5 0.4 Puck 26 0.5 0.2 0.7 5.9 0.5 0.6 0.2 0.7 5.5 0.5 0.8 0.2 0.6 5.1 0.5 Puck 27 0.4 0.1 0.8 3.9 0.4 0.5 0.1 0.8 4.2 0.5 0.5 0.2 0.8 4.5 0.7 Puck 28 0.5 0.1 0.7 2.8 0.3 0.5 0.1 0.7 2.8 0.3 Bottom Irregular Geometry - Not Analyzed Note: Bold Italics are MDA values

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 194 of 200 U2 CTMT Under Vessel 541.5' Wall Core Collection Date 1/30/13 B102110-CJWCCV-003 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0

120.17 2/14/13 1342 2/14/13 13:23 1000

-44 13.5 0.3 50.1 70.8 5.1 1.40E+02 0.5 2/14/13 1401 2/14/13 13:24 1000

-44 12.7 0.4 30.9 72.7 4.8 1.21E+02 Puck 2 0.5 118.82 2/14/13 1423 2/14/13 14:05 1000

-44 15.9 0.5 1.7 87.8 5.2 1.11E+02 1

2/14/13 1458 2/14/13 14:40 1000

-44 16.8 0.4 1.4 85.5 5.1 1.09E+02 Puck 3 1

122.62 2/21/13 1149 2/21/13 11:31 1000

-51 12.6 0.4 0.6 85.6 5.1 9.76E+01 1.5 2/21/13 1423 2/21/13 14:05 1000

-51 12.8 0.5 0.6 92.2 6.0 9.38E+01 Puck 4 1.5 113.71 2/14/13 1501 2/14/13 14:43 1000

-44 10.4 0.4 0.4 82.0 4.4 8.74E+01 2

2/14/13 1519 2/14/13 14:44 1000

-44 9.8 0.3 0.4 78.8 4.5 8.30E+01 Puck 5 2

109.22 2/19/13 0834 2/19/13 6:56 1000

-49 8.0 0.3 0.4 74.1 4.5 8.74E+01 2.5 2/19/13 0857 2/19/13 6:56 1000

-49 6.8 0.3 0.5 71.6 3.8 8.30E+01 Puck 6 2.5 130.95 2/19/13 1531 2/19/13 10:41 3000

-49 9.7 0.2 0.3 78.0 4.6 9.28E+01 3

2/19/13 0858 2/19/13 8:20 1000

-49 10.5 0.4 0.5 77.8 4.6 9.38E+01 Puck 7 3

120.48 2/19/13 0922 2/19/13 8:52 1000

-49 10.5 0.4 0.3 66.8 2.7 8.08E+01 3.5 2/19/13 0941 2/19/13 8:52 1000

-49 8.6 0.4 0.5 61.7 3.6 7.48E+01 Puck 8 3.5 138.16 2/19/13 0916 2/19/13 8:53 1000

-49 4.6 0.2 0.4 43.6 2.5 5.14E+01 4

2/19/13 1012 2/19/13 8:53 1000

-49 4.4 0.2 0.3 43.2 2.2 5.03E+01 Puck 9 4

129.1 2/19/13 1011 2/19/13 9:52 1000

-49 5.4 0.2 0.2 43.4 2.3 5.15E+01 4.5 2/19/13 1031 2/19/13 9:53 1000

-49 4.3 0.2 0.3 38.9 2.2 4.59E+01 Puck 10 4.5 117.28 2/19/13 1016 2/19/13 9:58 1000

-49 3.9 0.3 0.4 39.7 2.6 4.69E+01 5

2/19/13 1033 2/19/13 9:58 1000

-49 3.6 0.3 0.3 37.0 1.7 4.29E+01 Puck 11 5

142.27 2/19/13 1104 2/19/13 10:44 1000

-49 3.2 0.2 0.7 30.5 1.5 3.62E+01 XS 2/19/13 1125 2/19/13 10:46 1000

-49 2.8 0.2 0.9 25.1 1.2 3.02E+01

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 195 of 200 B102110-CJWCCV-003 Decay Corrected Results Core Section Co-60 Decaye d pCi/g Cs-134 Decaye d pCi/g Cs-137 Decayed pCi/g Eu-152 Decaye d pCi/g Eu-154 Decaye d pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 13.7 0.3 50.2 71.2 5.2 13.3 0.4 40.6 72.2 5.0 12.9 0.4 31.0 73.2 4.8 Puck 2 16.2 0.5 1.7 88.4 5.2 16.6 0.5 1.5 87.2 5.2 17.1 0.5 1.4 86.0 5.1 Puck 3 12.8 0.4 0.6 86.2 5.1 12.9 0.4 0.6 89.5 5.6 13.0 0.5 0.6 92.9 6.0 Puck 4 10.6 0.4 0.4 82.5 4.5 10.2 0.4 0.4 80.9 4.5 9.9 0.3 0.4 79.3 4.5 Puck 5 8.2 0.3 0.4 74.6 4.6 7.6 0.3 0.4 73.4 4.2 7.0 0.3 0.5 72.1 3.9 Puck 6 9.9 0.3 0.3 78.5 4.6 10.3 0.3 0.4 78.4 4.6 10.7 0.4 0.5 78.3 4.6 Puck 7 10.7 0.5 0.3 67.3 2.7 9.7 0.4 0.4 64.7 3.2 8.8 0.4 0.5 62.1 3.6 Puck 8 4.7 0.3 0.4 43.9 2.6 4.6 0.3 0.3 43.7 2.4 4.4 0.3 0.3 43.5 2.2 Puck 9 5.5 0.2 0.2 43.7 2.3 4.9 0.2 0.2 41.4 2.2 4.4 0.2 0.3 39.2 2.2 Puck 10 3.9 0.3 0.4 40.0 2.6 3.8 0.3 0.4 38.6 2.2 3.6 0.3 0.3 37.3 1.7 Puck 11 3.3 0.2 0.7 30.7 1.5 3.1 0.2 0.8 28.0 1.4 2.9 0.2 0.9 25.3 1.2 Note: Bold Italics are MDA values

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 196 of 200 U2 CTMT Under Vessel 541.5' Wall Core Collection Date 1/30/13 B102110-CJWCCV-003 Decay To Date 1/1/13 Gamma Spec Report Gamma Spec Report Sample Taken On Decay Const y-1 0.13153 0.33648 0.02310 0.05212 0.07877 Core Section Depth wt (gms)

Date Time Date Time Count time sec Decay Days Co-60 pCi/g Cs-134 pCi/g Cs-137 pCi/g Eu-152 pCi/g Eu-154 pCi/g Total pCi/g Puck 1 0

120.17 2/14/13 1342 2/14/13 13:23 1000

-44 13.5 0.3 50.1 70.8 5.1 1.40E+02 0.5 2/14/13 1401 2/14/13 13:24 1000

-44 12.7 0.4 30.9 72.7 4.8 1.21E+02 Puck 2 0.5 118.82 2/14/13 1423 2/14/13 14:05 1000

-44 15.9 0.5 1.7 87.8 5.2 1.11E+02 1

2/14/13 1458 2/14/13 14:40 1000

-44 16.8 0.4 1.4 85.5 5.1 1.09E+02 Puck 3 1

122.62 2/21/13 1149 2/21/13 11:31 1000

-51 12.6 0.4 0.6 85.6 5.1 9.76E+01 1.5 2/21/13 1423 2/21/13 14:05 1000

-51 12.8 0.5 0.6 92.2 6.0 9.38E+01 Puck 4 1.5 113.71 2/14/13 1501 2/14/13 14:43 1000

-44 10.4 0.4 0.4 82.0 4.4 8.74E+01 2

2/14/13 1519 2/14/13 14:44 1000

-44 9.8 0.3 0.4 78.8 4.5 8.30E+01 Puck 5 2

109.22 2/19/13 0834 2/19/13 6:56 1000

-49 8.0 0.3 0.4 74.1 4.5 8.74E+01 2.5 2/19/13 0857 2/19/13 6:56 1000

-49 6.8 0.3 0.5 71.6 3.8 8.30E+01 Puck 6 2.5 130.95 2/19/13 1531 2/19/13 10:41 3000

-49 9.7 0.2 0.3 78.0 4.6 9.28E+01 3

2/19/13 0858 2/19/13 8:20 1000

-49 10.5 0.4 0.5 77.8 4.6 9.38E+01 Puck 7 3

120.48 2/19/13 0922 2/19/13 8:52 1000

-49 10.5 0.4 0.3 66.8 2.7 8.08E+01 3.5 2/19/13 0941 2/19/13 8:52 1000

-49 8.6 0.4 0.5 61.7 3.6 7.48E+01 Puck 8 3.5 138.16 2/19/13 0916 2/19/13 8:53 1000

-49 4.6 0.2 0.4 43.6 2.5 5.14E+01 4

2/19/13 1012 2/19/13 8:53 1000

-49 4.4 0.2 0.3 43.2 2.2 5.03E+01 Puck 9 4

129.1 2/19/13 1011 2/19/13 9:52 1000

-49 5.4 0.2 0.2 43.4 2.3 5.15E+01 4.5 2/19/13 1031 2/19/13 9:53 1000

-49 4.3 0.2 0.3 38.9 2.2 4.59E+01 Puck 10 4.5 117.28 2/19/13 1016 2/19/13 9:58 1000

-49 3.9 0.3 0.4 39.7 2.6 4.69E+01 5

2/19/13 1033 2/19/13 9:58 1000

-49 3.6 0.3 0.3 37.0 1.7 4.29E+01 Puck 11 5

142.27 2/19/13 1104 2/19/13 10:44 1000

-49 3.2 0.2 0.7 30.5 1.5 3.62E+01 XS 2/19/13 1125 2/19/13 10:46 1000

-49 2.8 0.2 0.9 25.1 1.2 3.02E+01

Attachment H U2 5426 Elevation In-House Gamma Spectroscopy Core Sample Results TSD 13-006 Revision 0 Page 197 of 200 B102110-CJWCCV-003 Decay Corrected Results Core Section Co-60 Decaye d pCi/g Cs-134 Decaye d pCi/g Cs-137 Decayed pCi/g Eu-152 Decaye d

pCi/g Eu-154 Decaye d pCi/g Co-60 Puck Avg pCi/g Cs-134 Puck Avg pCi/g Cs-137 Puck Avg pCi/g Eu-152 Puck Avg pCi/g Eu-154 Puck Avg pCi/g Puck 1 13.7 0.3 50.2 71.2 5.2 13.3 0.4 40.6 72.2 5.0 12.9 0.4 31.0 73.2 4.8 Puck 2 16.2 0.5 1.7 88.4 5.2 16.6 0.5 1.5 87.2 5.2 17.1 0.5 1.4 86.0 5.1 Puck 3 12.8 0.4 0.6 86.2 5.1 12.9 0.4 0.6 89.5 5.6 13.0 0.5 0.6 92.9 6.0 Puck 4 10.6 0.4 0.4 82.5 4.5 10.2 0.4 0.4 80.9 4.5 9.9 0.3 0.4 79.3 4.5 Puck 5 8.2 0.3 0.4 74.6 4.6 7.6 0.3 0.4 73.4 4.2 7.0 0.3 0.5 72.1 3.9 Puck 6 9.9 0.3 0.3 78.5 4.6 10.3 0.3 0.4 78.4 4.6 10.7 0.4 0.5 78.3 4.6 Puck 7 10.7 0.5 0.3 67.3 2.7 9.7 0.4 0.4 64.7 3.2 8.8 0.4 0.5 62.1 3.6 Puck 8 4.7 0.3 0.4 43.9 2.6 4.6 0.3 0.3 43.7 2.4 4.4 0.3 0.3 43.5 2.2 Puck 9 5.5 0.2 0.2 43.7 2.3 4.9 0.2 0.2 41.4 2.2 4.4 0.2 0.3 39.2 2.2 Puck 10 3.9 0.3 0.4 40.0 2.6 3.8 0.3 0.4 38.6 2.2 3.6 0.3 0.3 37.3 1.7 Puck 11 3.3 0.2 0.7 30.7 1.5 3.1 0.2 0.8 28.0 1.4 2.9 0.2 0.9 25.3 1.2 Note: Bold Italics are MDA values

Attachment I U1 & 2 541.5 Foot Elevation First Half Inch Eberline Results TSD 13-006 Revision 0 Page 198 of 200 Unit 1 Unit 2 Sample ID B101110-CJFCCV-001 B101110-CJFCCV-002 B102110-CJFCCV-001 B102110-CJFCCV-002 Eberline WO 13-02003 12-12088 13-03084 13-04110 Eberline Sample Date 8/29/2012 8/29/2012 1/29/2013 1/30/2013 Decay To Date 1/1/2013 1/1/2013 1/1/2013 1/1/2013 Decay Years 0.342 0.342

-0.077

-0.079 Nuclide Decay Const yr-1 Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g Decay Corrected Result pCi/g H-3 5.63E-02 1.30E+02 2.16E+02 2.41E+02 3.29E+01 C-14 1.21E-04 9.89E-01 3.30E+00 9.72E-01 1.84E+00 Co-60 1.32E-01 4.25E+01 3.44E+02 5.00E+01 2.29E+01 Ni-63 7.22E-03 1.40E+02 2.97E+01 7.31E+01 4.73E+01 Sr-90 2.38E-02 3.14E-01 5.96E-01 3.72E-01 3.35E-01 Nb-94 3.41E-05 1.47E+00 1.97E+00 3.22E+00 2.48E+00 Tc-99 3.25E-06 2.63E-01 1.33E+00 2.60E-01 2.50E-01 Ag-108m 5.46E-03 1.45E+00 1.91E+00 4.17E+00 2.08E+00 I-129 4.41E-08 1.88E+00 3.87E+01 7.71E+00 4.47E+00 Cs-134 3.36E-01 5.69E-01 1.44E+00 1.30E+00 8.19E-01 Cs-137 2.31E-02 8.76E+01 2.81E+03 1.05E+03 1.56E+01 Pm-145 3.92E-02 1.61E+01 3.94E+02 4.78E+01 2.79E+01 Pm-147 2.64E-01 2.46E+01 3.60E+01 2.02E-01 3.99E+01 Eu-152 5.21E-02 1.61E+02 1.06E+02 3.97E+02 2.53E+02 Eu-154 7.88E-02 1.26E+01 8.46E+00 2.58E+01 2.17E+01 Eu-155 1.40E-01 3.69E+00 3.35E+00 7.02E+00 5.98E+00 Pu-238 7.90E-03 5.20E-02 1.21E-01 3.18E-02 2.71E-02 Pu-239 2.87E-05 2.25E-02 5.45E-02 1.39E-02 1.18E-02 Pu-240 1.06E-04 2.25E-02 5.45E-02 1.39E-02 1.18E-02 Pu-241 4.81E-02 4.21E-01 7.16E+00 3.30E+00 2.70E+00 Am-241 1.60E-03 4.38E-02 2.19E-01 4.91E-02 1.94E-02 Am-243 9.39E-05 3.04E-02 9.33E-02 5.18E-02 3.61E-02 Cm-243 2.43E-02 3.15E-02 7.76E-02 2.48E-02 1.43E-02 Cm-244 3.83E-02 3.13E-02 7.72E-02 2.48E-02 1.43E-02 Note: Bold Italics = MDA Value, Bold Red = Questionable or Suspect Results retained as valid results, Bold Blue = Questionable or Suspect Results eliminated as False Positives.

Purple Cells = Pu-241 results replaced by 13-04025 reanalysis results. (See basis in Section 3.10)

Attachment J Radionuclide Emissions and Yields TSD 13-006 Revision 0 Page 199 of 200 Nuclide T 1/2 (years)

Include in Gross Beta Beta Avg MeV Beta Yield %

Alpha Mev Alpha Yield Gamma ID MeV Gamma Yield Eberline Analysis Method Ag-108m 4.18E+02 0.723 90%

LANL ER-130 Modified Gamma Spec 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 C-14 5.70E+03 YES 0.0495 100%

EPA 520.0 Modified Liquid Scint Cm-242 4.46E-01 6.102 100%

Method EML Am-Ol Modified 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 Co-60 5.27E+00 YES 0.096 100%

1.17, 1.33 99.9%, 100%

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%

1.40801 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 Fe-55 2.74E+00 EML Method Fe-Ol-01 Modified Liquid Scint Fe-59 1.22E-01 YES 0.1174 100%

1.143 1%

Gamma Spec H-3 1.23E+01 5.86E-03 100%

LANL ER-210 Modified Liquid Scint I-129 1.57E+07 YES 0.0489 100%

0.039 Gamma, 0.029 X-Ray 7.51%, 56.9%

LANL ER-130 Modified Gamma Count Nb-94 2.03E+04 YES 0.166 100%

0.871 100%

LANL ER-130 Modified Gamma Spec Nb-95 9.58E-02 YES 0.04332 100%

0.766 100%

Gamma Spec Ni-59 1.01E+05 0.00607 24.000%

ASTM 3S00-Ni Modified Liquid Scint Ni-63 1.00E+02 0.017 100%

ASTM 3500-Ni Modified Liquid Scint Np-237 2.14E+06 4.796 100%

0.0865 13%

EIChroM Method ACW08 Modified Pm-145 1.77E+01 0.072 2%

LANL ER-130 Modified Gamma Spec Pm-147 2.62E+00 YES 0.062 100%

0.121 0%

EML Pm-01 Modified Liquid Scint Pr-144 3.29E-05 YES 1.207 100%

0.696 0%

Gamma Spec Pr-147 2.55E-05 YES 0.751 100%

0.641 19%

Gamma Spec Pu-238 8.77E+01 5.48 100%

EML Pu-02 Modified Alpha Spec

Attachment J Radionuclide Emissions and Yields TSD 13-006 Revision 0 Page 200 of 200 Nuclide T 1/2 (years)

Include in Gross Beta Beta Avg MeV Beta Yield %

Alpha Mev Alpha Yield Gamma ID MeV Gamma Yield Eberline Analysis Method 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-239/240 2.41E+04 5.148 100%

Pu-241 1.44E+01 0.00524 100%

4.9 0.000%

EML Pu-02 Modified Liquid Scint Pu-242 3.75E+05 4.9 100%

Alpha Spec Rh-106 9.44E-07 YES 1.412 100%

0.512 21%

Gamma Spec Ru-103 1.07E-01 YES 0.0722 100%

0.497 86%

Ru-106 1.02E+00 0.001 100%

Gamma Spec Rh-106 daughter Sb-124 1.65E-01 YES 0.3829 100%

1.69, 0.723 47.7%, 11%

Sb-125 2.76E+00 YES 0.0866 100%

0.428 30%

Gamma Spec Sr-90 2.88E+01 YES 0.1957 100%

EIChroM SRW01 Modified Gas Fl Prop Tc-99 2.11E+05 YES 0.1013 100%

EIChroM TCS01 Modified Liquid Scint Zr-95 1.75E-01 YES 0.1153 100%

0.724, 0.757 0.446, 0.550 NOTE: Data is from NRC Radiological Toolbox Software http://www.nrc.gov/about-nrc/regulatory/research/radiological-toolbox.html