ML22010A067

Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0001 Determination of the Safe Fuel Mass Limit for Decommissioning TMl-2

ML22010A067
Person / Time
Site:	Three Mile Island
Issue date:	01/05/2022
From:	EnergySolutions
To:	Office of Nuclear Reactor Regulation
References
TMI2-DPL-N-00-0001, Rev 1, TMl2-RA-COR-2022-0001 TMI2-EN-RPT-0001, Rev 1
Download: ML22010A067 (60)

Text

Attachment 2 to TMl2-RA-COR-2022-0001

Supplemental Information to License Amendment Request

Three Mile Island Nuclear Station, Unit 2

NRC Possession Only License No. DPR-73

Revision to TMl2-EN-RPT-0001 "Determination of the Safe Fuel Mass Limit for Decommissioning TMl-2" ENERGYSOLUTIONS Package Rev.: Rev 1 ~ Calculation Doc. No.: TMI2-EN-RPT-0001

Title:

Determination of the Safe Fuel Mass Limit for Decommissioning TMI-2 Design Plan No.: TMI2-DPL-N-00-0001 DP Rev.: 1 Signatures (printed name, signature, date)

Preparer Megan Pritchard

Approval Guy Rhoden

Record of Verification Item Verified Acceptable N/A - Explain a) Design Verification by Independent Checking Method b) Computer Software approved per CG-EN-PR-204 c) Calculation Package complete and per CG-EN-PR-203 Signature (printed name, signature, date)

Verifier Derrick Faunce

Record of Revisions Rev. Affected Affected Description (Print or Type)

Pages. Media Preparer Verifier

0 Initial Issue Megan Derrick - - Pritchard Faunce

- Updates to the description of the validation and USL Megan Derrick 1 §2, §3, §6 determination. - Pritchard Faunce

- Updates to the proposed operational description and upset conditions.

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Table of Contents

1. Introduction............................................................................................................................. 5 1.1. Purpose and Objectives.................................................................................................... 5 1.2. Background...................................................................................................................... 5

1.2.1. Safe Fuel Mass Limit................................................................................................ 5

1.2.2. Status ofTMI-2.......................................................................................................... 5 1.3. Scope................................................................................................................................ 7

2. Methodology........................................................................................................................... 7 2.1. General............................................................................................................................. 7 2.2. Computational.................................................................................................................. 7

2.2.1. Computer Codes........................................................................................................ 7

2.2.2. USL Determination................................................................................................... 7

3. Process Description............................................................................................................... 11 3.1. Operational Description.................................................................................................. 11 3.2. Normal Conditions......................................................................................................... 15

4. Inputs..................................................................................................................................... 17 4.1. Design Inputs.................................................................................................................. 18 4.2. Sampling and Impurities................................................................................................ 18

4.2.1. Reference Data for Lower Vessel Head.................................................................. 18

4.2.2. Reference Data for Core Debris Bed...................................................................... 19

4.2.3. Reference Data for Steam Generator Tube Sheet................................................... 19 4.3. Fuel Debris Composition............................................................................................... 19 4.4. Reference Data Summary............................................................................................... 20

5. Calculations........................................................................................................................... 21 5.1. Model Geometry Description......................................................................................... 21 5.2. Model Assumptions........................................................................................................ 24 5.3. Material Descriptions..................................................................................................... 24

5. 3.1. Fissile Material........................................................................................................ 24

5.3.2. Impurities................................................................................................................ 26 5.4. Results............................................................................................................................ 27*

5.4.1. Optimum Conditions............................................................................................... 27

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5.4.2. Impurity Content..................................................................................................... 28

5.4.3. Reflector Material Sensitivity................................................................................. 30

5.4.4. Summary ofResults................................. -............................................................... 31

6. Upset Conditions................................................................................................................... 31

7. Conclusions........................................................................................................................... 33

8. References............................................................................................................................. 34

9. Appendix A-Fuel Debris Composition.............................................................................. 37

10. Appendix B - Sample MCNP6 Computer Input.................................................................. 41

11. Appendix C - Sample ORIG EN Computer Input................................................................. 44

12. Appendix D - Electronic Files.............................................................................................. 44 12.1. Computer Runs............................................................................................................... 44 12.2. Other Electronic Files..................................................................................................... 59

List of Figures Figure 3-1. Volume Reduction Stations within RV Area............................................................ 12 Figure 3-2. Volume Reduction Stations and Work Zone............................................................ 13 Figure 3-3. Fissile Bearing Material Flow within the Working Area.......................................... 14 Figure 5-1. Cross Section of Fuel Region Lattice........................................................................ 22 Figure 5-2. Cross Section of Spherical Full Core Model.................................. :.......................... 23 Figure 5-3. Variation in Reproduction Factor as a Function of Fuel-to-Water Volume Ratio and Boron Content............................................................................................................................... 28 Figure 5-4. Variation in Reproduction Factor for Each Impurity Concentration as a Function of Impurity Boron Content................................................................................................................ 30 Figure 9-1. Energy Dependent Cross Section for Nuclides that Increased in the Decayed Composition.................................................................................................................................. 39 Figure 9-2. Energy Dependent Cross Section for Nuclides that Increased in the Decayed Composition.................................................................................................................................. 40 List of Tables Table 1-1. Remaining Fuel Mass Estimates (Ref. [2], Table 1).................................................... 6 Table 2-1. Properties of the MCNP6 Benchmark Models........................................................... 10 Table 3-1. Canister Estimates :from High Level Cutting and Packaging Plan............................. 17 Table 4-1. Burned Fuel Composition (Ref. [16])........................................................................ 20 Table 5-1. Parameters and Ranges Examined.............................................................................. 24 Table 5-2. Impurity Content of Core Debris ('Mix 3')................................................................ 26

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Table 5-3. Overall Boron Concentration in Fuel Debris.............................................................. 27 Table 5-4. Sensitivity of Reproduction Factor to Concrete Reflector......................................... 31 Table 9-1 - Fuel Composition as Calculated in 1988 (Ref. [3])................................................... 37 Table 9-2 - Fuel Composition as Calculated for 2022................................................................. 37

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1. INTRODUCTION

1.1. Purpose and Objectives

The purpose of this calculation and report is to identify a new safe fuel mass limit (SFML) for Three Mile Island (TMI)-2 decommissioning based on realistic but bounding assumptions about the material within the reactor vessel and outside the reactor vessel. It is intended that a single SFML can be utilized for all work in TMI-2 decommissioning and bound all credible operational upsets. This is accomplished through examination and application of material sampling results (i.e., impurities concentration), application of conservative assumptions where conditions are unknown or have associated uncertainty (i.e., fuel geometry, reflector), and taking credit for known phenom'ena (i.e., radioactive decay, burn-up). The sensitivity of each parameter to overall system reactivity is analyzed such that a balance between known and less ce1iain parameters can be achieved. Documentation and supporting information for the inputs utilized to derive the SFML is outlined in TMI2-EN-RPT-0003, TMI-2 Safe Fuel Mass Limit Computational Input Consensus (Ref. [1]).

1.2. Background

1.2.1. Safe Fuel Mass Limit

The SFML is a limit developed through criticality safety analyses as to the amount of fuel containing debris that may be safely handled at one time. It is intended that this limit bound all remaining fuel-containing debris in the TMI-2 reactor that is subject to decommissioning operations.

Previous defueling operations were performed using SFMLs developed based solely on credible upper bounds for input parameters as opposed to sample data or realistic conditions. However, defueling operations included potential removal of relatively intact fuel rods and fuel debris that varied extensively in its composition. This revision to the SFML is performed with more realistic and less conservative inputs than those used in previous analyses. The primary reasoning behind this approach is that the fuel debris is largely confined to an area with available characterization data, and intact fuel rods are no longer present. These inputs, while less conservative than those used in the original SFML determination, are still considered to be reasonably and sufficiently conservative for their use herein.

1.2.2. Status of TMI-2

The TMI-2 reactor has been undergoing various stages of defueling and clean-up since the accident in 1979. The primary defueling occun-ed in the late 1980s. The operations removed all fuel to the extent reasonably achievable and ultimately reduced the possibility of an inadvertent criticality under static or accident conditions. Approximately 99% of the original core inventory was removed during these operations with an estimate for residual U02 of 1097 kg ( ~ 1.2% of initial TMI-2 inventory). The remaining fuel is in the form of finely divided, small particle-size sediment material; re-solidified material either tightly adherent to components or in areas inaccessible to defueling; and adherent films on surfaces contained within piping, tanks, and

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other components. The 1097 kg includes fuel debris inside and outside the reactor vessel (RV) with the bulk of the mass residing in the lower head of the RV.

The remaining fuel mass estimates in each major area are provided in Table 1-1. During defueling, the majority of the mate1ial in the debris bed of the core was removed. Approximately 12% of the remaining material is estimated to be in the coolant system with some scattered throughout the plant (e.g., steam generators, hot legs, coolant pumps). Evaluation of the ex vessel residual fuel has demonstrated that no discrete (neutronically de-coupled) location has in excess of 127 kg U02, and the total estimate outside of the RV is 170 kg U02.

Table 1-1. Remaining Fuel Mass Estimates (Ref. [2], Table 1)

Area Estimated Mass Uncertainty (kg U02) (kg U02)

Plenum 2.1 +/- 1.9 Letdown Coolers 3.7 +/- 2.0

Pressurizer 0.3 +/- 0.2

Reactor Vessel Head 1.3 +/- 0.9

Reactor Building Basement 1.3 +/- 0.7

'A' and 'B' Once Through 62.3 +/- 9.7 Steam Generator (OTSG)

Auxiliary and Fuel Handling 11.5 +/- 5.8 Buildings Reactor Building 64.0 +/- 26.9 Miscellaneous Components

Reactor Coolant System (RCS) 25.8 +/- 11.1

Reactor Vessel 925 +/- 370

Total 1097 +/- 371

Detailed summaries as to how each of these estimates were developed can be found in TMI2-EN-RPT-0003, TMJ2 Safe Fuel Mass Limit Computational Input Consensus (Ref. [1], §2). Some of the residual quantities included in the estimates are reported as the minimum detectable level, indicating that the measurement technique did not detect a statistically significant number of events (counts) related to fissile nuclides. Physical measurements are subject to imprecisions which is an additional contributor to uncertainty. There are also uncertainties associated with counting statistics. The estimate for residual U02 is intended to be an upper bound, but carries an uncertainty in the RV of+/- 3 70 kg U02 (Ref. [ 4 ]). Including the uncertainty in the estimated mass for the RV results in a total for this area of ~1295 kg U02.

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1.3. Scope

The existing SFML is the fissile material mass limit for handling within the reactor vessel. The revised SFML derived herein applies to all decommissioning operations including removal from the RV, movement to the reactor cavity or other area intended for segmentation and movement to loading of the transpo11able storage container (TSC). Once fissile material (in actuality, these are components with damaged core material) is loaded into the TSC, it it outside the scope of the applicable SFML.

2. METHODOLOGY

2.1. General

The SFML is revised through evaluation of planned decommissioning operations and associated operational upsets, remaining fuel estimates, and the associated computation of a bounding mass limit that may be applied to those operations. Inputs to the supporting calculation are suppmted through review of robust historic sampling data and the conservative application of those results.

2.2. Computational

The approach to developing a new SFML encompasses two computational efforts: first, calculation of the source term (i.e., expected fuel composition) in 2022; and second, the criticality calculations for limiting reactor core fuel arrangements. Analytical software is qualified according to EnergySolutions Quality Assurance Program.

2.2.1. Computer Codes

Derivation of the expected source term is performed using the SCALE 6.2.4 ORIGEN depletion code to decay the previously calculated burned fuel. ORIGEN uses the continuous energy ENDF/B-VII decay data in the decay calculation (SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, Ref. [6]).

The criticality results in this report are calculated using Monte Carlo methods in the Monte Carlo n-Particle (MCNP) Version 6.2 code (Ref. [7]) with continuous energy ENDF/B-VIII.0 cross section data (Ref. [8]). MCNP is a general-purpose Monte Carlo particle transport code that can be used for neutron transport. MCNP treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first-and second-degree surfaces and fourth-degree elliptical tori. The code can be used to perform nuclear criticality safety analyses (keffeigenvalue calculations). The calculation of the neutron multiplication factor is performed by solving the neutron transport equation as an eigenvalue problem through the employment of Monte Carlo techniques.

2.2.2. USL Determination

Computer codes used to determine the effective neutron multiplication factor, keJJ, are to be properly verified and validated in accordance with ANSI/ANS-8.24 (Ref. [9]). The methodology

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used in the validation is taken from NUREG/CR-4604 (Ref [10]) and NUREG/CR-6698 (Ref

[11]).

Calculations are performed to validate MCNP v6.2 nuclear analysis code for neutron multiplication factor calculations performed in support ofraising the SFML for TMI-2 decommissioning. The validation report TMI-EN-RPT-0002, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDFIB-VIII.O Cross Section Library (Ref [12]) detennines the calculational margin (MoC) and margin of subcriticality (MoS), in order to establish the Upper Subcritical Limit (USL) for the area of applicability (AOA). The validation is applicable to heterogeneous spherical and annular configurations of low enriched UO2 and water.

The bias detennination report identifies applicable experiments to determine the bias and bias uncertainty for the geometric configuration, enrichment, fissile material distribution, impurity content, and potential soluble poison concentration included in the modeling. The bias and bias uncertainty is then used in combination with an estimate of the margin of subcriticality (MoS) to determine a USL such that for the specific application, calculated reactivity values, kcazc, and their associated Monte Carlo uncertainty CJ satisfy the relation

kcalc + 2cr < USL

This ensures that a system is safely subcritical, in this case at a 95% confidence level. The USL is established by subtracting quantified estimates of the code bias, bias uncertainty, and additional margin from unity.

USL = 1-MoC-MoA-MoS

Where,

MoC is the calculational margin and includes the bias and bias uncertainty in addition to any uncertainties related to the trending;

MoA is the Margin of Applicability, where is an allowance for any uncertainties related to extension of the AOA;

MoS is the Margin of Subcriticality, which is an administrative allowance beyond the MoC to ensure subcriticality.

The ANSI/ANS-8.24-2017 standard (Ref [9]) defines the following terms, which are incorporated in the USL determination defined above.

Bias The systematic difference between calculated results and experimental data. Note by convention the bias is determined as the calculated value minus the experimental value. Hence, a negative bias indicates that the code underpredicts the experimental result.

Bias Uncertainty The uncertainty that accounts for the combined effects of uncertainties in the experimental benchmarks, the calculational models of the benchmarks, and the calculational method.

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Calculational Margin An allowance for Bias and Bias Uncertainty plus considerations of uncertainties related to interpolation, extrapolation, and trending (MoC)

Margin of Subcriticality An allowance beyond the calculational margin to ensure subcriticality (MoS)

Validation Applicability A domain, which could be beyond the bounds of the benchmark applicability, within which the margins derived from validation of the calculational method have been applied.

Method

The bias determination is perfo1med in direct support of the SFML work and consists of two parts. The first involves the determination of the MCNP v6.2 computer code bias and bias uncertainty. The second part examines the AOA of the validation benchmark cases. The benchmarks represent a selection of uranium based critical experiments that are determined to be representative of the configurations modeled as paii of this report. The benchmai*k data is examined for potential trends to determine the proper bias determination method. The selection of benchmark cases and calculated bias are reported in TMI-EN-RPT-0002, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDFIB-VIII.O Cross Section Library (Ref. [12]).

The AOA consists of the range or values of various parameters important to the reactivity of the benchmark models. These define the range or values for a system parameter or parameters over which the validation and bias presented above are considered valid without modification. The parameter ranges of the validation models are compared to the models of the system being evaluated. If the system parameter falls within the AOA, no additional margin is necessary beyond the MoS for determining the USL. If one or more of the system parameters are found to fal outside of the AOA, additional margin may be added on the USL to extend the applicability of the validation.

Analysis and Result

The bias determination report validates the use ofMCNP Version 6.2 and ENDF/B-VIII.0 library for use in performing the calculations that estimate ke.trvalues for determination of the SFML. There is no notable trend within the data that needs to be compensated for in the determination of the bias, which is calculated as 0.9798. The AOA of the validation is provided in Table 2-1 and is generally sufficient to cover the range of parameters in the SFML calculation.

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Table 2-1. Properties of the MCNP6 Benchmark Models Property Validated AOA Fissile Materials U (2 - 10 wt.% 235U) in the form of compounds (Uo2, UF4) and solution (UO2F2)

Basic Geometry of the Array of fuel rods, array of rectangular parallelepipeds, UO2 in cubes in a Fissile Material cubic array, finely divided particles in cubes, cylinders, spheres, slabs Moderator Materials Water, Paraffin, Polyethylene Reflector Materials None, Water, Acrylic, Steel, Plexiglas, Paraffin, Polyethylene, Concrete Other Significant Al alloys, steel, borated steel, Bora], boroflex, Ag-In-Cd, Cu, Cu with Cd, absorbers, poisons, or Cd, Zircaloy-4, rubber structural materials Soluble Boron: 0 - 96 ppm present Specific Cross Sections 1001.00c 19039.00c 28058.00c 48106.00c h-poly.40t and S( a,P) used 5010.00c 19040.00c 28060.00c 48108.00c h-h2o.40t 501 l.00c 19041.00c 28061.00c 48110.00c (MCNP6 identifiers) 6012.00c 20040.00c 28062.00c 48111.00c 6013.00c 20042.00c 28064.00c 48112.00c 7014.00c 20044.00c 29063.00c 48113.00c 8016.00c 20046.00c 29065.00c 48114.00c 8017.00c 20048.00c 30064.00c 48116.00c 9019.00c 22046.00c 30066.00c 49113.00c 11023.00c 22047.00c 30067.00c 49115.00c 12024.00c 22048.00c 30068.00c 50112.00c 12025.00c 22049.00c 30070.00c 50114.00c 12026.00c 22050.00c 40090.00c 50115.00c 13027.00c 24050.00c 40091.00c 50116.00c 14028.00c 24052.00c 40092.00c 50117.00c 14029.00c 24053.00c 40094.00c 50118.00c 14030.00c 24054.00c 40096.00c 50119.00c 15031.00c 25055.00c 42092.00c 50120.00c 16032.00c 26054.00c 42094.00c 50122.00c 16033.00c 26056.00c 42095.00c 50124.00c 16034.00c 26057.00c 42096.00c 92234.00c 16036.00c 26058.00c 42097.00c 92235.00c 17035.00c 27059.00c 42098.00c 92236.00c 17037.00c 42100.00c 92238.00c 47107.00c 47109.00c Average Energy of Range (MeV): 2.43E-02 - 2.88E-01 Neutrons Causing Fission (AENCF) Average (MeV): l.40E-0l

A single USL is developed for the SFML application for TMI-2 decommissioning. The USL is derived based on the calculated bias using the limiting identified geometric configuration (sphere), fissile material type (low enriched 235 UO2), soluble poison concentrations (0- 96 ppm),

and distribution (heterogeneous) for the pertinent models.

The additional MoS applied to ensure the calculational results are adequately subcritical typically ranges from 0.02 (at a minimum) to 0.05, and depends on factors such as the systems to be

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modeled, the reliability of the calculational method, and knowledge of physical and chemical aspects of the systems to be modeled. There are a large number of experimental benchmarks used in the validation (125 cases covering nine benchmarks), which provides a large set of cases for the statistical evaluation of the bias and bias uncertainty. The additional MoS applied is 0.0298 for an overall USL of 0.95. This MoS is justified through the application of conservative input parameters and bounding configurations to the computational models.

A USL of 0.95 is utilized in the criticality safety analysis and provides adequate margin in supporting the SFML.

3. PROCESS DESCRIPTION

3.1. Operational Description

There are four main areas of core debris in TMI-2. The Reactor Pressure Vessel (also called RV),

the Reactor Coolant System (not including the RV), the Reactor Building (not including the RV and Reactor Coolant System), and the Auxiliary/Fuel Handing Building. Table 1-1 provides estimates for these areas, broken down into some smaller areas/systems. Each of the four general areas is handled separately during decommissioning.

The canal above the RV is used to process (i.e., size reduce) and decontaminate large components. The canal is located at the 347 ft elevation, is approximately 25 ft wide, 77 ft long, 20 ft deep in the shallow end and 34 ft deep in the deep end. The RV cavity is located in the approximate center of the canal. A maximum of two volume reduction stations (VRS) are installed at opposite ends of the canal with the working Waste Zone in the central region. The Waste Zone is sized such that it can hold four waste basket liners (WBL). A graphical depiction of the VRS locations within the canal is provided in Figure 3-1 and a potential layout of the Waste Zone is shown in Figure 3-2.

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Drawing shows :

VRS 1 & 2

Working Bridge 1&2 -

Working and Handling space

Fig ur e 3-1. Vo lum e Reduction Station s within R V Area

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VRS2 p

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Ci

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"( z

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lY 0

_J 0 ll.

Was te contain

. o os:-* ---..:. "'.::.-=:**-

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Figure 3-2. Volume Reduction Stations an d Work Zone

Core components removed from their in-situ location are moved to a YRS for size reduction, then transferred to the Work Zone for loading into a WBL. Finally, the liners are transferred to be loaded into a TSC. This flow is shown in Figure 3-3.

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FBM FBM

VRS Opera ing Zone VRS Operating Zone

Figure 3-3. Fissile Bearing Material Flow within the Working Area

Prior to the removal of any RV components, the RV and reactor cavity are flooded with water.

The types of components to be removed from the RV include core barrel remnants, the thermal shield, and the lower core support plate remnants. After removal of the main components, instrument nozzles and penetrations are cut and moved to the working area (reactor cavity) for loading into the transportation containers. All remaining debris material in the RV following removal of the main components and cut pieces is vacuumed or cleaned up by other mechanical means (e.g., scoops,jaw-type tools).

These components are associated with adhered and non-adhered (i.e., loose) debris material. The three types of debris material (also called damaged core material) associated with the TMI-2 core debris are:

• Type-I Core Debris - Loose debris consisting of finely-divided, small particle size material ;

• Type-2 Core Debris - Surface films consisting of thin films of debris material of varying depth on systems, structures, and components, and;

• Type-3 Core Debris - Re-solidified material and fuel assembly artifacts (average density of7.1 g/cm 3)

Components with tightly adhered debris material are cut up to fit into open design liner (WBL)/canisters (TSCs) that are compa tible with the ex isting Dry Cask Storage System. Loose debris material chips, and fine granu l ar material are scooped or vacuumed and captured in filter cans that are loaded into TSCs that are also compatible with the existing Dry Cask Storage System. The weight limit for the TSC is 55,000 lbs and they are expected to be loaded to approximately 95% efficiency for a waste weight of 52,2 50 lb s. Once the debris material is

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loaded into the TSCs, the remaining packaging process is identical to a conventional spent nuclear fuel assembly dry storage campaign.

As the components and associated debris are removed, they are moved to the YRS for segmentation and then the Work Zone for loading into a WBL/TSC. Fourteen (14) TSCs are anticipated to be used during the entire operation and multiple are available to receive segmented debris at any one time, which are loaded based on packaging efficiency and/or debris type.

Following segmentation, any recovered Type-I and Type-3 materials from that area during cleanup are loaded into a separate TSC intended for fines and chips collection.

Following cleaning of the RV, the Type-1 and Type-3 debris material in the Once Through Steam Generators is cleaned out and moved to the dry area of the reactor cavity for loading into the TSCs. Lastly, there is also the Auxiliary/Fuel Handing Building with an estimated 11.5 kg of debris material. This material is also moved to the reactor cavity and loaded into the WBL/TSCs.

Only one TSC is removed at a time by placing it into the Dry Storage Canister located inside the Transfer Shield. Once all TSCs are loaded and removed from the reactor cavity, the RV is drained of the remaining water. Loaded TSCs inserted into the Dry Storage Canister are moved from the loading location to a handling facility. Here, the Dry Storage Canister lid is welded on, the Canister is vacuumed dried and backfilled with inert cover gas.

3.2. Normal Conditions

Under anticipated normal conditions, all the ofremaining core debris (i.e., fissile material) consists of the three types listed above in the general locations listed in Table 1-1. The total amount of expected fissile material for the entire decommissioning is estimated to be about 1097 kg of irradiated and subsequently decayed UO2 (i.e., spent fuel) with, on average, 16 wt.%

impurities in the fuel debris. Boron is expected to be in the impurities at an average concentration of 0.11 wt.% of the fuel debris. Borosilicate glass is expected to be present in the lower head of the RV.

The four main areas (RV, RCS, Reactor Building, Auxiliary/Fuel Handling Building) are distinctly different and physically separated within the reactor building. Each area ( e.g., RV) has specific reactor components ( e.g., lower grid assembly [LGA]) or areas made up of components

( e.g., the plenum) with an estimated mass. These estimates can be used to visualize a high level packaging plan with some degree of certainty. Some components do not have estimates for the mass or volume so the Canister estimates in the high level packaging plan have relatively high uncertainty.

The segmentation and loading ofTSCs occurs in the reactor cavity (canal) where material is transported to after it is removed from its current location. For the majority of component segmentation, it will occur under water in a flooded reactor cavity. Some segmentation (like the OTSG components) may not occur under water and may be on a concrete platform. Additionally, some components may be set on concrete at some time during the operations. For this reason, the reactivity addition from a tight fitting concrete reflector is examined.

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Material and component removal from each area is treated as a separate operation, meaning that debris from two areas is not removed at the same time; however, a partially filled TSC from one area may remain for loading from the next facility area ifthere is remaining void space.

Estimates for the number of TSCs for each area based on estimated weight and packing efficiency are provided in Table 3-1.

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Table 3-1. Canister Estimates from High Level Cutting and Packaging Plan

Component/ Area Estimated TSCs Note

LGA, Core Support Assuming payload packing Assembly (CSA) 3.95 (4) efficiency of 95%. LGA and CSA are majority _of Plenu!n. ____________

Remaining plenum 2.07 (3) Remainder of 3rd canister may be filled with excess LGA and CSA.

Flow Distributor and 1 In the "A" D-ring ICI Guide Tubes *------* --------*

OTSG 3

_ Cl_!ip collection 2 ~proximately 6,000 lbs

Auxiliary and Fuel 1 Handling Building __

Total 14

The design inputs, and specifically reference information, provided in Section 4 and detailed in TMI2-EN-RPT-0003, Safe Fuel Mass Limit Computational Input Consensus (Ref [1]) serves as the basis to develop inputs to the computational models to develop the SFML. The values for input parameters include varied uncertainties: those that are well understood/accepted, those that have some uncertainty, and those that have larger uncertainties. The parameters include. 235 U enrichment, impurity content, fuel debris composition, UO2 density, etc. For several input parameters, the selected value is credibly bounding.

Development of the SFML includes optimization of parameters for maximum moderation, reflection and interaction conditions in a bounding geometry (sphere). Using a sphere as the material geometry for SFML minimizes the surface area to volume ratio and does not require taking credit for the distribution of the fuel debris.

4. INPUTS

Over the years since samples were retrieved at TMI-2 and analyzed at various laboratories, substantial effort has been put into using those results to inform operational decontamination and decommissioning (D&D) decisions, validate accident computer codes, estimate fission product release, and understand the nature of the TMI-2 accident. The majority of that work was used for duefueling operations, which occurred in the late 1980s. For the purposes of deriving a SFML for intended D&D operations, the sample results biased toward the bulk of the remaining material are used to develop compuatational input parameters.

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The input parameters for consensus include core debris composition (i.e., impurities concentration), fuel enrichment, fuel density, fuel bum-up and resulting composition, fuel pellet geometry, and modeling geometry, including moderation and reflection conditions. Discussion of each of these parameters is provided in TMI2-EN-RPT-0003 (Ref. [1]). Those that rely on historic references (primarily impurities content from sampling and debris composition) are summarized here.

4.1. Design Inputs

Inputs to the design of the SFML come from a combination of historical documents, reactor operation history, previous decommissioning operations, and planned future decommissioning operations. Planned future decommissioning operations, which support the criticality not credible argument for application of the SFML, are laid out in Section 3. The pertinent design input information that feeds into the calculation is further discussed in this section. Inputs that are adjusted as part of the parametric study associated with this calculation (i.e., geometry, emichment) are in Section 5.

A graded approach is used to apply the design input information to the development of the SFML, which depends on the strength of the basis of that information. For example, known natural phenomena, such as radioactive decay, are applied more assertively than a parameter with less assurance ( e.g., exact impurity content) which is applied more judiciously.

4.2. Sampling and Impurities

Samples were retrieved from multiple locations including the lower head region, the core debris bed, and the B-loop steam generator tube sheet, which are summarized here. Note that for each sample retrieved, it was processed into particles which were then analyzed individually. One sample can have multiple particles of varying sizes and elemental makeup.

4.2.1. Reference Data for Lower Vessel Head

In 1985, prior to defueling, 16 particles of debris from the lower reactor vessel (i.e., lower head) were obtained through the annulus. Although the analyses were performed prior to defueling, most of the remaining material is in the same region as the analyzed samples. The samples were intended to be both representative of the region "typical material" and a material that "looked different." The data indicate that the composition of the debris is similar to what would be expected if the principal components of the original core were mixed, melted, and a fraction subsequently relocated to the lower plenum of the reactor. The general appearance of the lower plenum debris and the microstructure of the samples indicate that they were once molten. The particles of pure U02 have changes in porosity that indicate it may have been near the melting point (GEND-INF-084, Examination of the Debris from the Lower Head of the TMI-2 Reactor Ref. [13]).

Boron was found in measurable concentrations ranging from 0.066 wt.% to 0.36 wt.% on average per debris sample. Gadolinium poison was not readily identifiable in the lower head debris but was more prevalent in the core debris bed. The structural material element with the

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highest concentrations in the lower head was iron, ranging from 1. 8 to 3. 7 wt.% average per debris sample.

For additional summary information on the sample analyses, refer to TMI2-EN-RPT-0003 (Ref.

[ 1 ]), and for the original analytical information refer to GEND-INF-0084, Examination of Debris from the Lower Head of the TMI-2 Reactor (Ref. [13]).

4.2.2. Reference Data for Core Debris Bed

A substantial amount of core debris bed was removed during defueling in the late 1980s. Prior to the defueling, a sampling of core debris from the center and radius was performed in 1983-1984, removing material from three depths: surface of the rubble bed, 3 inches deep into the bed, and 22 inches deep into the bed. A summary of the results is provided below. For reference, the as built TMI-2 active core region contained about 94.5 wt.% UO2 + Zr-4 and approximately 2.3 wt.% stainless steel + Inconel. The U/Zr ratio for the active core region was about 3.6.

• The average, normalized, U content was 82.6 wt.%, Zr content was 13.9 wt.%, Fe content was 2. 7 wt.%, and Ni content was 0.9 wt.%. The U/Zr ratio was higher than as-built

( ~5.9) and the Ni, Cr, and Fe was about 1.3 wt.% higher than as-built.

• The,degree of mixing and relocation suggests that molten core materials mixed vigorously to produce the degree of homogeneity observed.

• Original as-built uraniuim enrichment for specific fuel assemblies had no correlation to sample results, indicating significant physical relocation of the fuel.

4.2.3. Reference Data for Steam Generator Tube Sheet

Examination of loose core debris from the B-loop steam generator upper tube sheet was part of a fission product inventory evaluation and also provided insight into the deposition of core material outside the reactor vessel. The sample appeared similar to the sample below the surface of the core debris bed, and some of the particles in the lower plenum.

The sample particles were reaction products consisting primarily of U and Zr oxides. Fe, Ni, and Cr were trace elements within the matrix. Two of the 12 particles indicated control rod origen (i.e., Ag, In, and Cd).

4.3. Fuel Debris Composition

References [13], [14], and [15] analytically estimate the peak and sustained temperatures in the core in order to better estimate fission product release and fuel composition. It is estimated that about 20% of the core material in the debris bed experienced temperatures up to fuel melting.

The lower plenum material could have attained temperatures of at least 2810 K.

The only historical report that provides the explicit burned composition of the fuel (UO2 component of the debris) is the 1989 Criticality Safety Evaluation for Increasing the SFML (Ref.

[16]), which is provided as an attachment to the Defueling Completion Report (Ref. [3]). This composition accounts for bumup effects in all three fuel batches but no melted and comingled cladding or structural material (i.e., impurities) as described above. Comparisons of the

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calculated fission product composition with the analytical data indicated, at that time, that the calculational results were appropriate (Ref. [13]).

In each batch, the effects of uranium depletion, fissionable plutonium generation, and rare earth fission product production are considered. The base fuel composition input previously used is provided in Table 4-1. However, because this composition was derived 30-plus years ago, as part of this calculation, it is computationally decayed to the year 2022. The new composition is discussed in Section 6.3.1 as an input to this calculation.

Table 4-1. Burned Fuel Composition (Ref. [16])

Number Density Isotope (atoms/barn-cm) mu 5.21E-4 mu 2.25E-2 160 4.60E-2 239pu 4.0lE-5 240Pu 2.00E-6 24lpU 2.49E-7 149Sm l.0lE-7

151 Sm l.79E-7 1s1Eu 8.20E-9 1s3Eu l.32E-7 1s4Eu 4.51E-9 issEu 6.12E-9

4.4. Reference Data Summary

For the purposes of calculating a final SFML, general conclusions can be drawn from the abundance of analytical sample information, particularly that available for the lower head of the reactor vessel.

• The previously derived fuel composition was adequate as a reference composition for bum-up of the original TMI-2 fuel. This composition serves as a starting point to decay each isotope to the year 2022 in order to develop a current fuel composition.

• Impurities, whether from cladding, structural material, or control rods, exist throughout the TMI-2 core. Control rod material was not as commonly found in remaining core debris as structural material.

• The U/Zr compositions in the core are indicative of mixing of all core constituents.

• Boron is evenly distributed throughout sample particles at the same concentration as in the reactor coolant, although it is not known if the elemental boron originated in the coolant or poison rods.

• Gadolinium is distributed among the debris bed material at similar concentrations to the original burnable poison rod loading, indicating vast mixing. Gadolinium was not readily

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identified in the lower head or steam generator tube sheet as it was heavily concentrated in the core crusts.

• Most of the control rod material accumulated in the core debris bed or elsewhere, not in the lower head region.

• Temperatures during the accident reached levels to initiate and propagate core melting, peaking at greater than 2800 K. There are few examples of pure U02, indicating isolated temperatures greater than 3100 K.

• Mixing of different assemblies' emichment has occurred, and little or none of the 2.96 wt.% 235 U/U is contained in the lower head region. The average emichment of the 34 samples collected in the lower head is 2.23 wt.% 235 U/U.

• Core debris density ranges from about 6 g/cm3 to less than 9 g/cm3.

5. CALCULATIONS

5.1. Model Geometry Description

A single criticality model was developed using bounding and anticipated configurations of the remaining spent fuel. A spherical configuration of all remaining spent fuel was filled with a lattice of fuel and moderator. When impurities are included, they are modeled as part of each fuel region. A hexagonal lattice was selected because of the ability to closely pack the fuel elements.

Each spherical fuel element is surrounded by water on all sides. The size of the fuel element and spacing between each fuel element (i.e., the H/U ratio) is modified for each base arrangement in order to optimize reactivity in each study. The optimum configuration of fuel and moderator (i.e.,

H/U ratio) is dependent on multiple parameters and can change with the addition of absorbers to either the fuel or moderator. This adjustment has no physical basis. It is merely a means to maximize the fuel/water intereaction and is bounding of any credible configuration of the material. The base arrangements optimized for fmiher analysis are:

• Sphere with lattice of fuel debris with impurities; pure water moderator and reflector;

• Sphere with lattice of fuel debris; poisoned water moderator and pure water reflector;

• Sphere with lattice of fuel debris with impurities; poisoned water moderator and pure water reflector.

For comparison, a sphere with lattice of fuel debris (no impurities) and pure water as a reflector (no poison) and moderator is also included.

The spherical model assumes all modeled fuel and moderator is in a spherical configuration, surrounded by a close-fitting essentially infinite water reflector. The moderator to fuel ratio is optimized in each base case to achieve the highest reactivity prior to further perturbations on model parameters (e.g., fuel mass). This optimization is done by altering the pitch of the lattice for each unit cell. A graphical depiction of the cross-sectional unit cell lattice is provided in Figure 5-1. The blue area represents the fuel pellet and the red represents the moderator. The hexagonal region surrounding each cell is not a physical attribute but only a computational cell place-holder.

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Figure 5-1. Cross Section of Fuel Region Lattice A graphical depiction of the cross section of the spherica l model is provided in Figure 5-2. The interior shaded region is the fuel region lattice and the surrounding red is the effecti v ely infinite reflector.

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Figure 5-2. Cross Section of Spherical Full Core Model For each optimized configuration, the total uranium mass, percentage of impurities, and concentration of boron in the water were varied. Sensitivity to a lowered U0 2 density and concrete reflector were also examined on the most limiting configurations. The effect of a lowered U0 2 dens ity was within the margin of error and had little effect of k eff* In all examined cases, the higher U0 2 density was bounding. A concrete reflector is slightly more reactive than the equivalent thickness water reflector. This sensiti v ity is discussed as an upset condtion in Section 5.4.6.

The range of parameters studied for the spherical configuration are provided in Table 5-1.

Parameters such as fuel pellet radius, unit cell separation, and U0 2 density were used as part of scoping calculations to identify an optimum configuration. Once that optimum configuration was identified, uranium mass, impurity weight fraction, boron concentration, and reflector material were adju sted for the reported results. Note that 30 cm of reflection is effectively infinite.

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Table 5-1. Parameters and Ranges Examined

Parameter Range

Uranium Mass 925 kg - 1750 kg Reflector Thickness 30 cm Reflector Material Water, Concrete Impurity Weight Fraction 5% - 16.21 %

Boron Impurity Percentage 10% - 100%

Iron Percentage 90%

UO2 Density 10.55 - 10.97 g/cm3 Fuel Pellet Radius 0.2 cm - 0.6 cm Unit Cell Separation 0.2 cm - 0.4 cm

5.2. Model Assumptions

Because the distribution of the fuel within the RV is unknown, the SFML is derived through bounding assumptions intended to cover any credible upset conditions. The geometric configuration of the fuel is bounding in the heterogeneous spherical model. Because this is low enriched fuel, it is more reactive in a heterogeneous configuration than as a homogeneous model.

This was also demonstrated in scoping calculations (NSTS-ES-01 Ref [17]). A heterogeneous annular model was studied previously and shown to be less reactive than the heterogeneous spherical model (NSTS-ES-01 Ref. [17]). The fuel pellet is spherical, the moderation is optimized, and the fuel region is spherical. This represents a worst-case configuration for the fissile material. Additionally:

• The fuel pellet volume is assumed to be close to that of a standard sized fuel pellet; although a sphere and in a hexagonal lattice;

• Impurities are added as a uniform, homogeneous mix within the fuel sphere;

• The fuel is represented as TMI-2 average fuel (i.e., a homogeneous mixture of the three fuel batches), as discussed in Section 6.3.1;

• An effectively infinite reflector is assumed;

• No credit is taken for existing structural or solid poison materials ( e.g., borosilicate glass);

• Only limited credit is taken for the presence of fission product poisons.

5.3. Material Descriptions

5.3.1. Fissile Material

The fissile material is represented as a homogeneous medium assumed as TMI-2 average fuel.

The homogeneous medium is a mixture of the three known fuel batches and this is considered conservative because defueling data indicates that most of the batch 3 fuel (at least ~65%), with the highest initial enrichment of 2.96 wt.% has been removed from the RV. Consequently, any

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remaining fuel is expected to consist primarily of batch 1 and 2 fuel with 1. 98 wt.% and 2. 64 wt.% enrichment, respectively.

• The composition of the U02 component 1 is derived by staiiing with the composition supplied in the Defueling Completion Rep01i SFML calculation attachment (Ref. [3], Table 5-8). This composition accounts for burnup effects in all three fuel batches through application of a conservative approach to burnup credit. In each batch, the effects of uranium depletion, fissionable plutonium generation, and rare earth fission product production are considered. The gaseous fission products were assumed to be released at the time of the accident and the soluble ones were assumed to have leached out of the fuel matrix. Of the remaining non-soluble fission products, some become volatile under extremely high fuel temperatures and the formation of a zircaloy-fuel eutectic and, thus, were assumed not to remain within the fuel matrix. Of the non soluble fission products, only the rare earths were considered to be stable under TMI-2 accident conditions. The validity of the presence of rare earth elements, which serve as significant neutron poisons, is discussed extensively in Appendix B of Reference [18] (Reactor Coolant System Criticality Report).

The unburned fuel enrichments for the three batches were 1.98 wt.% (56 assemblies), 2.96 wt.%

(60 assemblies) and 2.64 wt.% (61 assemblies) 235 U/U. As a homogeneous mixture, the unburned overall enrichment was 2.54 wt.% (Ref. [3]). The TMI-2 fuel experienced the equivalent of approximately 94 effective full-power days ofburnup at the time of the accident (Ref. [18]). The actual exposure history for each fuel batch, using existing plant data, was applied to calculate burnup effects. The exposures and core operating history were applied to the ORIGEN-S model to calculate isotopic inventory at the time of the accident. The incorporation of the bumup effects for each fuel batch was used to produce a net 235 U enrichment of 2.24% for a homogeneous mixture of the three batches (Ref. [19]). This is in good agreement with samples retrieved from the bottom head with an average enrichment of2.23 wt.% 235 U/U (Ref. [20]).

The starting fuel composition is decayed using ORI GEN to the year 2022. Those nuclides that do not have available nuclear data in the ENDF-BNIII library are not included. Almost all of the neglected nuclides have decayed weight fractions less than 10-15. Attachment B lists the starting fuel composition (Table 9-1) and the decayed composition (Table 9-2) used in the simulations.

The neglected components are highlighted.

Nuclides that decreased in the decayed composition are 151 Sm, 241 Pu, 151 Eu, 154Eu, and 155 Eu. The largest decrease is in 154Eu and 155 Eu. An energy dependent cross section plot for these nuclides can be found in Figure 9-1 in Attachment B. The decrease (decay) in these two europium isotopes has resulted in an increased reactivity. Nuclides that increased in the decayed composition, originally from zero, to be above 1x10-7 are 241 Am, 234 U, and 155 Gd; however, they are still pretty low in abundance ( ~ 1 x 1 o-6). A cross section comparison for these nuclides can be found in Figure 9-2 in Attachment B. Based on the abundance of these nuclides and their cross section data, it is expected and confirmed through scoping that the decayed fuel composition is

1. The bumup and decay of U02 includes various isotopes other than uranium and oxygen. The table of impurities considers this component as 'fuel composition'.

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slightly more reactive than the original bum-up composition. This would present a more conservative fuel composition for the SFML calculation.

Full theoretical density (10.97 g/cm3), as well as a reduced density (10.55 g/cm3) based on bum up history (Ref. [21]), and an as-built density of92.5% of the theoretical density (10.14 g/cm3)

(Ref. [14]) are all used in the scoping calculations; however, the effect on reactivity is minimal.

The relative density as a function of burn-up is expressed as:

!!_ = 0.963 - 1

• 10- 4 * (burnup/12 Pth

5.3.2. Impurities

All samples of TMI-2 debris accumulations collected have shown that debris contains impurities, whether those be from structural material, control rods, burnable poison rods, coolant poison, or cladding. In many cases, impurities from each category were present in the sample. These are considered long-term impurities of the debris, not surface contaminants. A summary of previous analyses is in Section 4 with additional details in Reference [1]. Substantial fuel, control rod, and structural material mixing to create some degree of homogeneity was shown to have occurred during the TMI-2 accident. Additional justification of this from supporting documentation is also provided in Reference [1].

Core debris in the lower head region of the RV is most representative of what remains in the RV at the present time. For this reason, the impurity concentration is derived from the sampling results for the lower head of the RV. A composition representing the RV lower head was initially derived as 'Mix 3' in the Defueling Completion Report (Ref. [3], Table 5-11). In this mix, the fuel composition (UO2+fission products) makes up 83.79 wt.% of the core debris while the remainder (16.21 wt.%) is impurities. The debris composition with impurities is listed in Table 5-2. Homogenization of the impurity content of the RV lower head in the modeled fuel mixture represents a significant conservatism over what would be derived assuming a homogeneous mixture of the initial core composition, where the UO2 component is 65.8 wt.% of the TMI-2 core mass (Ref. [22]).

Table 5-2. Impurity Content of Core Debris ('Mix 3')

Component Weight Percent (%)

Fuel Composition 83.79 Zr 12.70 Fe 2.44 B 0.11 Cd 0.00 Cr 0.75 Mo 0.15 Mn 0.06

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The impurity composition within the core debris is varied in the analysis from 0% to 16.21 wt.%.

In addition, iron content is fixed at 90% of the relative impurity mixture and boron content is varied independently since the greatest reactivity worth comes from these constituents. This allows the SFML result to not rely on full credit from boron or iron impurities. Calculation of the modeled weight fraction of boron is performed using the following relationship, where Bmu/1 is the element's (e.g., boron's) multiplier. The same is done for iron where Bmu/1 is replaced with 0.9.

Bm deled = ----- ---- lt lmpwf BMix3 *B 0. core debris Imp wf mu

The overall fuel debris boron concentration for each multiplier is shown in Table 5-3 for all impurity fractions used. The values shown are weight percent of boron in total fuel debris.

Table 5-3. Overall Boron Concentration in Fuel Debris

B,,,,,11 Impurity Fraction (wt.%)

5 10 15 16.21 0 0 0 0 0 0.2 0.0068 0.014 0.020 0.022 0.3 0.010 0.020 0.031 0.033 0.5 0.017 0.034 0.051 0.055 0.8 0.027 0.054 0.082 0.088 1 0.034 0.068 0.10 0.11

5.4. Results

Note that calculation results in this section are generally in the form of total uranium, not total U02.

5.4.1. Optimum Conditions

An optimum moderation search is performed by adjusting the fuel pellet diameter and lattice pitch (i.e., H/U ratio). Once the most reactive arrangement is identified, that pellet size, pitch and fuel density can be used to examine variations on the total fuel mass, total impurity content, boron concentration, and reflector material.

The fuel pellet radius is varied from 0.2 cm to 0.6 cm, and the pellet separation from 0.1 cm to 0.4 cm in an effort to identify the optimum conditions for maximum reactivity. The fuel volume fraction for randomly packed whole fuel pellets is around 0.63, and a volume fraction of 0.74 corresponds to the maximum that can be achieved for spheres in contact in a hexagonal lattice. A pellet radius of 0.6 cm with a separation of 0.1 cm results in a fuel volume fraction of

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approximately 0.63 4, slightly higher than that for randomly packed spherical pellets. A pellet radius of 0.6 cm with a separation of 0.4 cm results in a fuel volume fraction of 0.34. As the pellet size and separation distance (i.e., unit cell pitch) are var ied, the optimum moderation can be found. Since the fuel i s low enriched, moderation is necessary to achieve criticality. A higher fuel vo lum e fraction (i.e., les s moderator present) in eac h mod e le d unit ce ll re sult s in a redu ce d reactivity. For this reaso n, the pellet radius and pitch are not varied b eyo nd these spec ified va lues. It is recognized th at fuel pellet sizes larger than 1.2 cm may ex is t due to fuel melting.

How ever, sample data h ave shown, and temperature-d ependent ph enom ena indicate that particle s of pur e UO2 are highly unlikel y.

Th e optimum UO2 d ensity for all cases is 10.9 7 g /cm 3.

A gra phi c depiction of the change in kefffor va r y in g fuel /mod erator ratios at 1200 kg U is pro v ided in Figure 5-3. The maximum keff for the system with minimal impurities occurs around

~ 1.5. Ther e are multiple fuel radius and pitch va lues that can produce the same ratio ( e.g., 0.4 cm radius; 0.2 cm pitch and 0.6 cm radius; 0.3 cm pitch both have a ratio of 2) with slightly different keff-

1.4

1.2

1

0.8

.::.!. li

0.6

0.4

0.2

0 0 1 2 3 4 5 6 7 Fuel Radius/Pitch Ratio

Figure 5-3. Variation in Reproduction Fact or as a Function of Fuel - to-Water Vol u me Ratio an d Boron Content

5.4.2. Impurity Content

The weig ht fraction of the 'Mix 3' impurity applied homogeneously to the fu el composition ha s a significant effect on the neutron multiplication factor. Although the impurity mix has multiple

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constituents, in reality made up from the melting and mixing of structural components and control rods, the boron has the highest neutron absorption cross section for the energy region of interest and therefore the greatest reactivity worth.

To show the effec t of overa11 impurity concentration in the fuel debris on keff, the uranium mas s is fixed at 1200 kg. The boron concentration is adjusted by a multipl er on th e value provided in

' Mix 3 ' ( i.e., 30% is a 70% reduction). Figure 5-4 displays the negati ve reacti v ity worth with each small addition of boron. For 15 and 16.21 wt.% impurity content, 20% of the boron impurity i s wort h appro x imately -15.07% ~k/k. In other words, -0.75% ~k/k on average for each 1 % addition of boron in the fuel mix. The positi ve and negati ve reactivity worth is reported in comparison to th e keff With no boron impurity rather than from unity since deviation from a purely critical state is not part of this study. As the boron impurity increases, it's negative re ac ti v ity worth decrea ses with each addition. Thi s is apparent by looking at the slope of the curve near the 100 % multiplier. Over the entire range of boron multipliers, the average worth is -

0.48 % ~k/k for each 1 % addition. For 5 wt.% impurity content, 20% of the boron impmity is worth approximately -5.52% ~k/k. In this case, there is an added 0.27 % ~k/k of negative reactivity on average for each 1 % addition of boron in the fuel mix. For 10 wt.% impurity content, 20 % of the boron impurity is w orth -11.4 % ~k/k, or -0.57 % ~k/k for each 1 % addition.

As expected, as the impurity weight percent increases, boron ha s a mor e significant impact on keff-

The reactivity worth of boron in the impurities is similar for the range of uranium loadings examined (925 kg - 1750 kg U) but has a s lightly higher worth at lower fissile loadings. Note that in all these results, only 90 % of the iron is credited.

For a 1200 kg U fuel loading, if 15 wt.% or more of the total impurity content is credited, at lea st 28% of the boron also has to be credited in order to stay below the USL. If 10 wt.% of the impurities is credited, at least 47 % of the boron content must be credited to stay below the USL.

With a boron mu ltiplier of 1 (100%), the boron is 0.11 wt.% of the fuel debris (see Table 5-2 and Table 5 -3). With a boron mu ltiplier of 0.47, the boron concentration is 0.0517 wt.% of the fuel debris. Using an impurity content of 10 wt.% and boron multiplier of 0.47, the overall boron impurity in the fuel debris required to stay below the USL is a minimum of 0.0319 wt.%.

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_._ 5% Impuri ties _._ 10% Impurities _._ 15% Impurities _._ 16.21% Impurities

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Impurity Boron Fraction Multiplier

Figure 5-4. Variation in Reproduction Factor for Each Impurity Concentration as a Function of Impurity Bor o n Content

5.4.3. Reflector Material Sensitivity

The tight fitting (i.e., effectively infinite) water reflector is used in the reported results in this section. The water is replaced with concrete to test the sensitivity of this parameter since concrete is present in the TMI-2 facility and it is possible that decommissioning operations will expose components to it. It is not considered credible that a tight fitting concrete reflector could be realized during decommissioning operations.

Comparison of the neutron multiplication factor for a uranium loading ranging from 925 kg to 1500 kg for 10 wt.% impurities and 50% boron impurity multiplier at optimum moderation for both a water and concrete reflector is provided in Table 5-4. The tight fitting concrete reflector provides approximately +0.0065 ~k/k at 1200 kg uranium loading.

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Table 5-4. Sensitivity of Reproduction Factor to Concrete Reflector

Reflector Umass keff+ 20' (kg)

925 0.9235

Water 1125 0.9334 1200 0.9365

1500 0.9465 925 0.9313

Concrete 1125 0.9401 1200 0.9427

1500 0.9519

5.4.4. Summary of Results

These results indicate that the entire remaining amount of uranium in the TMI-2 facility with some margin can be safely handled for decommissioning operations by taking credit for some impurity content. This analysis optimized moderation, fuel density, pellet size, and fuel configuration while taking partial credit, yet still applying conservative assumptions for fuel bum-up, fission products and decay, enrichment, impurity weight fraction and boron and iron content in the fuel debris. It is feasible to apply a SFML of 1200 kg U (1361 kg UO2) with a keff

+ 2a < 0.95 through taking credit for 10 wt.% of the impurities, 50% of the sampled boron content of those impurities, and 90% of the iron content of 'Mix 3' (keJJ+ 2a = 0.9365). This equates to 0.034 wt.% of boron in the fuel debris and 1.51 wt.% of iron. Only 31 % of the reported boron content and 62% of the reported iron content of the fuel debris (for the lower head RV sample results) is credited in a 1200 kg U SFML. With an estimated remaining core debris inventory of 1097 kg UO2, of which 90+% is in the RV, this SFML bounds all operations and credible upsets, including concrete reflection, and allows some margin for inventory and impurity uncertainty.

6. UPSET CONDITIONS

There are upset conditions associated with both the expected inventory of total uranium and its associated characteristics, and the decommissioning operations. Some upsets on the input parameters would require gross errors in historical information in addition to the absence of understood phenomena (i.e., nuclear fuel bum-up). Supporting information is provided both in this document and in reference documents on the assertion that anticipated phenomena has occurred and lead to the current conditions. One example of this is evidence of vast mixing of core components during the accident, which leads to impurity content in the fuel debris.

Upset conditions associated with decommissioning operations may include mishandling of components with fissile material to increase moderation, reflection conditions, or interaction conditions. This could potentially occur through removal and accumulation of fissile-bearing components from multiple areas into a single location. Given the size and complexity of the reactor components, and the effort required to remove and move each component, it is at least unlikely that a "pile" of reactor components can develop. Even if such a pile were to develop, the

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fissile material is at least partially adhered to structural members such that it's accumulation into a favorable geometry, either under water or not under water is not credible. Water (or gravity) serves to disperse and move any loose uranium thereby aiding in prevention of an ideal formation.

Components removed from their in-situ location are transferred to one of the YRS locations, which is located on the opposite end of the canal from the other YRS. It is not credible that components in one YRS can interact with components in the other YRS given the vast separation distance. Following segmentation, the pieces are moved to the Waste Zone for loading into the WBL and transfer to the TSC. It is possible that pieces that do not fit in the WBL may be placed aside. It is not credible that the segments placed aside could assemble into an ideal configuration with no structural components present. However, even if this were to occur, it would require gross errors in impurity content to erode the safety margin provided by these inherent characteristics of the fuel debris.

Development of the SFML includes optimization of parameters for maximum moderation, reflection and interaction conditions in a bounding geometry. Although the RV canal is flooded with water and a water reflector is considered as the material for all reported calculations, a tight fitting concrete reflector is also examined (see Section 5.4.3) and shown to only slightly increase the reactivity. The slight increase in reactivity offered by a tight fitting concrete reflector bounds any added reactivity from concrete walls or slab during decommissioning operations. There is sufficient margin between the base case reproduction factor and the USL to allow tight-fitting, effectively infinite concrete reflection, which is not considered a credible condition.

The derived SFML bounds the entire expected fissile mass inventory throughout all physically separated areas within the reactor building. The largest uncertainty is associated with the RV at+/-

370 kg UO2. The uncertainties on the fuel debris total mass associated with other areas are considered small, as these areas are better characterized (Ref. [ 4 ]). fucluding the maximum uncertainty, the total fuel debris for the RV could be ~1468 kg UO2. It is not logistically possible for the entire mass of the RV, which is deposited in a large area, to be removed at one time. Nor is it possible for the entire mass associated with the RV to be placed into a single TSC. The nature of segmentation operations separate and reduce the amount of fissile material in a single area and subsequently any TSC. There is estimated to be approximately 170 kg UO2 outside of the RV. It would require an unreasonable uncertainty associated with the other remaining areas to approach the estimated mass for the RV, and this is not considered credible. It is estimated that approximately 14 TSCs are necessary to pack the reactor components and internals when they are packed efficiently. There is no credible upset that could lead to a fuel debris mass of greater than 1468 kg UO2 in a single location, nevermind an idealized configuration.

There are uncertainties associated with the impurity content of 'Mix 3' as detailed in TMI2-EN RPT-0003 (Ref. [1]) as they apply to the fuel debris for the entire facility. The impurities are reduced by approximately 38% from the specification in the Mix 3. The boron content is further reduced by 50% ( ~ 31 % of the original B concentration remains) and the iron content by 10%

(~56% of the original Fe concentration remains). These conservative reductions provide sufficient margin to encompass uncertainties and heterogeneous flucutuations in the remaining fuel debris material. In comparison to the other mixes, the boron concentration is approximately

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 32 of 59 ENERGYSOLUTIONS ~

half that of Mix 4 (Ref. [3], Table 5-11) which is also de1ived from the sampling in the lower head of the RV. Additionally, the average boron concentration distribution for the OTSG samples was 0.109 wt.% (Ref. [1], Table 3-4), of which the value used in this calculation (0.034 wt.%) is approximately one third of that.

The above discussion demonstrates that it is not credible to expect all of the remaining fuel material to be collocated and for the resulting mass to exceed the determined 1200 kg U (1361 U02) SFML. It is further not considered credible that the segmentation operations would result in the fuel material being placed in an optimal physical arrangement that maximizes reactivity. A conservative approach to adequately represent the inherent characteristics of the remaining fuel debris is taken with respect to the development of an SFML for the remaining decommissioning activities. This, coupled with conservatively estimated masses and planned decommissioning operations provides significant and adequate margin of safety to ensure that a criticality is not credible.

7. CONCLUSIONS

The identified SFML to bound all planned TMI-2 decommissioning operations (i.e., normal conditions) and credible operational upsets is 1200 kg uranium or 1361 kg U02. This limit credits several key factors:

• 10 wt.% of the impurities identified in 'Mix 3' from the Defueling Completion Report, which is considered representative of the debris that remains in the RV;

• Boron and iron are further reduced by 50% and 10%, respectively, in the 10 wt.%

impurity fraction identified in 'Mix 3'; and

• Actual exposure histories applied to the average enrichment for all three batches of original TMI-2 fuel (bum-up credit).

And applies multiple conservatisms:

• A decayed fuel composition to the year 2022 which reduces key fission product poisons beyond the value used in the existing SFML calculation;

• Neglecting the removal of ~65% of the highest enrichment fuel assembly;

• Optimum moderation (fuel pellet to pitch ratio);

• Effectively infinite reflection;

• Optimum spherical core geometry; and

• Theoretical fuel density above the as-built specification for TMI-2.

The derived SFML bounds the entire expected fissile mass inventory throughout all physically separated areas within the reactor building. The bounding fissile mass used to produce the SFML is assembled in idealized conditions that cannot credibly exist during decommissioning operations. Even if the expected remaining fissile mass throughout the building (1097 kg U02),

including hold up in all piping and cubicles were to be brought together, a criticality is not feasible. There are no credible operational upsets to realize the ideal configuration but even in the event that the upset occurs, it would require fissile mass in excess of that analyzed, which is

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 33 of 59 ENERGYSOLUTIONS ~

greater than what is anticipated, in addition to a greatly reduced impurity concentration to present a criticality hazard.

8. REFERENCES

[l] M. Pritchard, "TMI2-EN-RPT-0003 Rev. 0, TMI-2 Safe Fuel Mass Limit Computational Input Consensus," Nucler Safety & Technology Services, 2020.

[2] E. Schrult, "Letter C312-93-2004, TMI-2 Post-Defueling Survey Report for the Reactor Vessel," GPU Nuclear Corporation, Middleton, PA, February 1, 1993.

[3] GPU Nuclear Corporation, "TMI Nuclear Station Unit 2 Defueling Completion Report Rev. 4," 1989.

[ 4] E. Schrult, "TMI-2 Post-Defueling Survey Report for the Reactor Vessel," GPU Nuclear, Middleton, PA, 1993.

[5] EnergySolutions, "CG-EN-PR-204 Rev. 1, Control and Use of Acquired Analytical Software," 2016.

[6] Oak Ridge National Laboratory, "ORNL/TM-2005/39, SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, Version 6.2.4,"

Available from Radiation Safety Information Computational Center, Oak Ridge, TN, 2020.

[7] LA-UR-17-29981, MCNP Users Manual - Code Version 6.2, 2017.

[8] M. Chadwick, "ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data," Nuclear Data Sheets, vol. 112, 2011.

[9] "ANSI/ANS-8.24-2017, Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations," American Nuclear Society, La Grange Park, IL, 2017.

[10] W. M. Bowen and C. Bennett, "NUREG/CR-4604, Statistical Methods for Nuclear Material Management," Pacific Northwest Laboratory, Prepared for U.S. Nuclear Regulatory Commission, Richland, WA, 1988.

[11] J. Dean and J. R.W. Tayloe, "NUREG/CR-6698, Guide for Validation ofNuclear Criticality Safety Calculational Methodology," Science Application International Corporation, Prepared for U.S. Nuclear Regulatory Commission, Oak Ridge, TN, 2000.

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 34 of 59 ENERGYSOLUf/ONS ~

[12] D. Faunce, "TMI2-EN-RPT-0002, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library," EnergySolutions, 2020.

[13] C. S. Olsen, D. W. Akers and R. K. McCardell, GEND-INF-084, Examination of the Debris from the Lower Head of the TMI-2 Reactor, Idaho Falls, Idaho: EG&G Idaho, Inc.,

1988.

[14] G. 0. Hayner, "GEND-INF-060 Vol. 2, TMI-2 H8A Core Debris Sample Examination Final Report," Prepared for EG&G Idaho, Inc and the U.S. DOE Three Mile Island Operations Office, Lynchburg, Virginia, 1985.

[15] D. W. Akers, E. R. Carlson, B. A. Cook, S. A. Ploger and J. 0. Carlson, "GEND-INF-075, TMI-2 Core Debris Grab Samples - Examination and Analysis Part l," EG&G Idaho, Inc.,

Idaho Falls, Idaho, 1986.

[16] GPU Nuclear Corporation, "4710-3220-89-1 Rev. 2, Criticality Safety Evaluation for Increasing the TMI-2 Safe Fuel Mass Limit," Submitted to Nuclear Regulatory Commission as Appendix B to the Defueling Completion Report Rev. 4, 1989.

[17] M. Pritchard, "NSTS-ES-01 Rev. 0, Safe Fuel Mass Limit Criticality Safety Analysis for TMI-2 Decommissioning," Nuclear Safety & Technology Services, 2020.

[18] "GPU Nuclear letter 4410-84-L-0199, Reactor Coolant System Criticality Report,"

November 8, 1984.

[19] Letter, C. V Parks, Oak Ridge National Laboratory, to D.S. Williams, GPU Nuclear Corporation, November 6, 1987.

[20] GPU Nuclear Corporation, 15737-2-N09-005 Rev. 2, Criticality Safety Evaluation for Increasing the TMI-2 Safe Fuel Mass Limit, 1989.

[21] M. Marchetti, D. Laux and L. Fongaro, "Physical and Mechanical Characterization of Irradiated Uranium Dioxide with a Broad Burnup Range and Different Dopants Using Acoustic Microscopy," Journal of Nuclear Materials, vol. 494, pp. 322-329, 2017.

[22] C. S. Olsen, D. W. Akers and R. K. Mccardell, "GEND-INF-084, Examination of the Debris from the Lower Head of the TMI-2 Reactor," EG&G Idaho, Prepared for the U.S.

Department of Energy Idaho Operations Office, Idaho Falls, Idaho, January 1988.

[23] E. Clayton, "PNNL-19176 Rev. 6, Anomalies of Nuclear Criticality," Pacific Northwest Laboratory, Richland, Washington, 2010.

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 35 of 59 ENERGYSOLUTIONS ~

[24] GPU Nuclear Corporation, "4410-88-L-0162/0356P, TMI-2 Post-Defueling Survey Report for The Upper Plenum Assembly," Middletown, PA, September 30, 1988.

[25] GPU Nuclear Corporation, "4410-89-L-0097/0356P, TMI-2 Post-Defueling Survey Report for the Pressurizer, Reactor Building Basement, and Letdown Cooler Room," three reports packaged together, Middletown, PA, September 22, 1989.

[26] GPU Nuclear Corporation, "4410-90-L-0019/0356P, Post-Defueling Survey Report for the Reactor Vessel Head Assembly," Middletown, PA, March 14, 1990.

[27] C. Distenfeld, "C312-91-2064 Rev. 1, TMI-2 Post-Defueling Survey Report for the 'A' and

'B' Once-Through Steam Generators," GPU Nuclear Corporation, Middletown, PA, August 20, 1991.

[28] F. Deininger, "Letter C3 l 2-91-2045, TMI-2 Post-Defueling Survey Report for the Auxiliary & Fuel Handling Buildings," GPU Nuclear Corporation, Middletown, PA, June 7, 1991.

[29] F. Deininger, "C312-91-2052, TMI-2 Post-Defueling Survey Report for Reactor Building Miscellaneous Components," GPU Nuclear Corporation, Middletown, PA, June 18, 1991.

[30] P. Deininger, "Letter C312-91-2055, TMI-2 Post-Defueling Survey Report for the Reactor Coolant System," GPU Nuclear Corporation, Middletown, PA, July 3, 1991.

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 36 of 59 ENERGYSOLUTIONS ~

9. APPENDIX A - FUEL DEBRIS COMPOSITION Table 9 Fuel Composition as Calculated in 1988 (Ref. [31)

Nuclide ZAID Number Den sity (atoms/barn-cm) 23su 92235 5.21E-4 23su 92238 2.25E-2 160 8016 4.60E-2 239 pu 94239 4.0lE-5 240pu 94240 2.00 E - 6 241 Pu 94241 2.49E-7 14 9Sm 62149 l.0lE-7 1s1sm 62151 l.79E-7 1s1 Eu 63151 8.20E-9 153 Eu 63153 l.32E-7 1s4 Eu 63154 4.51 E - 9 1ss Eu 63155 6.12E-9

Table 9-2 - Fuel Composition as Calculated for 2022

Nuclide ZAID Number Density (atoms/barn-cm) 4He 2004 5.160E-08 201Tl 81207 l.785E-21 209Tl 81209 1.25 lE-29 206pb 82206 3.238E-22 201pb 82207 l.618E-15 20spb 82208 7.470E-25 209Pb 82209 5.044E-26 21opb 82210 l.586E-21 211 pb 82211 l.355E-20 rn pb 82212 1.50 IE-28 214Pb 822 14 l.715E-26 209Bi 83209 6.484E -22 2l0Bi 83210 9.8 06E-25 2l)Bi 83211 8.030E-22 2l2Bi 83212 l.424E-29 2l3Bi 83213 l. 178E-26 2l4Bi 83214 l.274E-26 210p 0 84210 2.512E-23 211po 84211 8.906E-27 21sp 0 84215 l.l 14E-26 218po 84218 l.983E-27 2l9Rn 86219 2.476E-23 222 Rn 86222 3.524E-24

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 37 of 59 ENERGYSOLUTIONS ~

22 1Fr 87221 1.266£ -27 22 3Fr 8 7223 I. 137£ - 22 223Ra 88223 6. 176£ - 18 22 4R a 88224 1.239£ -27 22s R a 88 225 5.545 £ -24 226R a 88 226 5.3 8 6 £ -19 22 sR a 88 2 28 8. 6 51 £ -25 22s Ac 89225 3.721 £ -24 221Ac 89227 4.287£-15 22sA c 8 922 8 1.056£-2 8 221Th 90227 9.954£ -1 8 22sTh 90228 2.356 £- 25 229Th 90229 9.976 £ -1 9 23 °'fh 90230 5.350£ -1 5 23 1Th 90231 2. 155£ -1 5 232Th 90232 3.402£ - 15 23 4Th 90234 3. 323£-13 23l pa 91231 1.69 3£-11

233 P a 91233 2.232£-16 23 4Pa 91234 6.159£-18 mu 92233 2.580£ -14 234 u 92234 1. 149£-10 rn u 92235 5.2 10£-04 236U 92236 6.961E -09 mu 92237 1.59 4 £ -1 5 238u 92238 2.2 5 0£ -02 23 7Np 93237 6.478£ -09 239pu 94239 4.006£-05 24opu 94240 1.993£-06 241 pu 94241 5.023£-0 8 241Am 95241 1.923£ -07 t4 9Sm 62149 l.0 l 0E-07 1s1sm 62151 1.388£ -07 1s1E u 63 15 1 4.838£ -08 1s3 Eu 63153 1.320 £ -07 1s 4sm 62154 7.550£- 13 is4Eu 63 154 3.1 56£ - 10 l5 4Gd 64 154 4. 194 £ -09 iss Eu 63155 4.972 £ -1 1 l55 Gd 64155 6.070£-09 160 80 16 4.600£ -02

~ Hi11:hli11:hted rows are nuclides excluded from the simulations!

C alcu l ation Package No. TMI2-EN -RPT-000 1, R evi sion Re v 1 P age 38 of 59 E NERGYSOLUTIONS ~

1E6

1E5

1E4

• 1E3

lE2 8

-j lEl * ~

u lEO ~

lE-1

lE-2

lE -3

lE-4

lE -5 lE-3 lE -2 lE~ lEO lEl 1E2 lE S lE4 lE5 lE6 lE 7 lEB In cident Neutron Energy (eV)

- Pu -24l(n. g ) ENO FB -8. 0 - sm -15l(n,g ) ENDFB-8.0 Eu-1 5 l( n. g) END FB -8. 0 - Eu-1 54(n. g) ENDFB-8. 0 Eu -l 55 ( n, g ) END FB -8. 0

Figure 9-1. Energy Dependent Cross Section for Nuclides that Increased in the Decayed Composition

Calcu lation Package No. TMI2-EN-RPT-0001, R evision Rev 1 Page 39 of 59 ENERGY~ SOWTIONS

a

lE5,..*

lE4

1E3

lE2 **

8.6 j lEl

Ill g lEO

lE*l

lE*2

lE - 3

lE-4

1E *5 lE-4 lE-3 lE-2 lE*l lEO lEl lE2 lE3 1E4 lE6 1E 7 1E8 Incident Neutron Energy (eV)

!- Am-241Cn.g) ENDFB-8.0 - Gd-lSS(n0gJ ENDFB-a.o - U-234(n.g) ENDFB-a.o j The coordinates a t the cursor pos ition-Figure 9-2. Energy Dependent Cross Section for Nuclides that Increased in the Decayed Composition

Calc ulation P ac k age N o. T MI2 -EN-RPT-0001, Re v ision R ev 1 P age 40 of 59

~

ENERGYSOLUTJONS

10. APPENDIX B - SAMPLE MCNP6 COMPUTER INPUT T MI-spher eV 8W _ noBmod _ 0.4 _ 1200 _ 0. 1_ 0.3.in

TMI-2 - sphere model water reflector with all impurities, no po i son water c Separation 0.4 cm c No Soluble poison is in moderating water c Refined fuel composition from VS - from 'origen deca y comp' file c Simple sphere model with fuel plus impurities c Iron content fixed at 10 % reduced from reference c Parameters c U mass ( kg) = 1200 c Impurities wt frac: 0. 1 c Fuel wt frac:0.9 c Impurities Boron multiplier 0.3 c Iron mu l tiplier= 0.9 c Fuel Densit y = 10.97 c Borated moderating water, no boron in reflector water c Boron in water by weight 0 c Water Boron multiplier= 0 c pitch = 1.6 c HexVolume = 3.5472 c Fuel Vo l = 0.90478 c U Concentration = 2.2161 c Hexagonal prism unit cell c UO2 fuel, enrichment=2.24%

C C

c -------------------CELL CARDS------------ - - - ---------------------------

c FUEL UNIT CELL 10 100 -10.97 -4 u=2 imp:n=l $ fuel inside pellet 20 400 -0.998207 4 u=2 imp:n=l $ water around fuel pellet c LATTICE as UNIVERSE 1 FILLED WITH UNIVERSE 2 SO 0 -3 lat=2 fill=2 u=l imp:n=l $ hexagonal lattice c SQUARE LATTICE AS UNIVERSE 3 FILLED WITH UNIVERSE 1 60 0 -5 u=3 lat=l fill=l imp:n=l 70 0 -1 fill=3 imp:n=l $ space filled by Universe 3 (lattice) c WATER REFLECTOR 80 400 -0.998207 -2 1 imp:n=l $ water outside core c NEVERLAND 500 0 2 imp : n=0

c --------- - ---- - ----SURFACE CARDS---------------------------------------

C rph x y z of bottom of prism, height, Op 0, v ector to 2nd facet, vector to 3rd facet C

C CORE AND REFLECTOR 1 sph 0 0 0 50.563 $ whole core sphere for lattice 2 sph 0 0 0 80.563 $ water reflector sphere C FUEL PELLET 3 rhp 0 0 -10 0 0 20 0 0.8 0 $ hexagonal prism cell, p=2 4 sph 0 0 0 0.60 $ fuel sphere, r=0.50 5 rpp -500 500 -500 500 -0.80 0.80 $ divider for unit cells

c --------------------DATA CARDS------------------------------------------

c -------------------KCODE SOURCE-----------------------------------------

kcode 10000 1.0 50 1050 $ 10000 particles per cycle, 1050 cycles, skip 50 cycles sdef pos= 0 0 0 C

c ------------------MA TERIALS---------------------------------------- - ----

c c ------------UO2 fuel; Density=l0.97 g /cc 2.24% enr; ORNL Report-- - ---------

ml00 2004.00c -2.986e-08 $ He-4 c 81207.00c -5.342e-20 $ Tl-207 c 81209.00c -3.779e-28 $ Tl-209 82206.00c -9.643e-21 $ Pb-206 82207.00c -4.843e-14 $ Pb-207 82208.00c -2.246e-23 $ Pb-208

Ca l cul ati on P ackage N o. TMI 2-EN-RPT - 0001, R evisio n R ev 1 P age 41 o f59

~

ENERGYSOLUTIONS

C 82209.00c -l.524e-24 $ Pb-209 C 82210.00c -4.814e-20 $ Pb-210 C 82211. 00c -4. 132e-19 $ Pb-211 C 82212.00c -4.60le-27 $ Pb-212 C 82214. ooc -5.307e-25 $ Pb-214 83209. 00c -1. 959e-20 $ Bi-209 C 83210.00c -2.977e-23 $ Bi-210 C 83211. 00c -2.450e-20 $ Bi-211 C 83212.00c -4.363e-28 $ Bi-212 C 83213.00c -3.628e-25 $ Bi-213 C 83214.00c -3.942e-25 $ Bi-214 C 84210.00c -7.627e-22 $ Po-210 C 84211.00c -2. 716e-25 $ Po-211 C 84215.00c -3.462e-25 $ Po-215 C 84218.00c -6.25le-26 $ Po-218 C 86219.00c -7.842e-22 $ Rn-219 C 86222. 00c -l.13le-22 $ Rn-222 C 87221. ooc -4.046e-26 $ Fr-221 C 87223.00c -3.666e-21 $ Fr-223 88223.00c -l.99le-16 $ Ra-223 88224.00c -4.014e-26 $ Ra-224 88226.00c -l.760e-17 $ Ra-226 88225. 00c -1. 803e-22 $ Ra-225 C 88228.00c -2.852e-23 $ Ra-228 89225. 00c -1. 2lle-22 $ Ac-225 89227.00c -l.407e-13 $ Ac-227 C 89228.00c -3.480e-27 $ Ac-228 90227.00c -3.267e-16 $ Th-227 90228.00c -7.769e-24 $ Th-228 90229.00c -3. 304e-17 $ Th-229 90230.00c -1. 780e-13 $ Th-230 9023 1.00c -7. 200e-14 $ Th-231 90232.00c -l.142e-13 $ Th-232 90234. 00c -l.125e-ll $ Th-234 9 1 23 1. 00c -5.654e-10 $ Pa-231 91233.00c -7.519e-15 $ Pa-233 C 91234.00c -2.084e-16 $ Pa-234 92233.00c -8.695e-13 $ U-233 92234.00c -3.887e-09 $ U-234 92235.00c -1. 77le-02 $ U-235 92236.00c -2.376e-07 $ U-236 9223 7. 00c -5.462e-14 $ U-237 92238.00c -7.744e-01 $ U-238 93237.00c -2.220e-07 $ Np-237 8016.00c -1. 064e-0l $ 0-16 94239.00c -1. 385e-03 $ Pu-239 94240.00c -6.917e-0S $ Pu-240 94241.00c -1. 75le-06 $ Pu-241 95241. 00c -6.702e-06 $ Am-241 62149.00c -2.175e-06 $ Sm-149 62151.00c -3.029e-06 $ Sm-151 62154.00c -1. 680e-ll $ Sm-154 63151. ooc -1. 056e-06 $ Eu-151 63153.00c -2.918e-06 $ Eu-153 64154.00c -7.023e-09 $ Eu-154 63155.00c -1. 114e-09 $ Eu-155 64154.00c -9.333e-08 $ Gd-154 64155.00c -l.360e-07 $ Gd-155 40090.00c -3.973e-02 $ Zr-90 40091.00c -8.760e-03 $ Zr-91 40092.00c -1. 353e-02 $ Zr-92 40094.00c -1. 402e-02 $ Zr-94 40096.00c -2.307e-03 $ Zr-96 26054.00c -7.6Sle-04 $ Fe-54 26056.00c -l.24Se-02 $ Fe-56 26057.00c -2.927e-04 $ Fe-57 26058.00c -3.963e-05 $ Fe-58 5010.00c -3.75le-05 $ B-10 5011. 00c -l.66le-04 $ B-11 24050.00c -1. 93le-04 $ Cr-SO

Calculation P ac ka ge No. TMI2-EN-RPT-0001, Re v is ion Re v 1 Page 42 of 59

=-

ENERGYSOLUTIONS

24052.00c -3.872e-03 $ Cr-52 24053.00c -4.476e-04 $ Cr-53 24054.00c -l.135e-04 $ Cr-54 42092.00c -l.309e-04 $ Mo-92 42094.00c -8. 359e-os $ Mo-94 42095.00c -l.455e-04 $ Mo-95 42096. ooc -l.543e-04 $ Mo-96 42097.00c -8.933e-os $ Mo-97 42098.00c -2.284e-04 $ Mo-98 42100.00c -9.32le-05 $ Mo-100 25055.00c -3.70le-04 $ Mn-55 C

C ------------MODERATING WATER; Density 0.998207 ; PNNL-15870 -------------

rn200 5010.00c -0.000e+0 0 $ B-10 5011.00c -0.000e+00 $ B-11 1001.ooc -l.119e-01 $ H-1 8016.00c -8.88 le-01 $ 0-16 MT200 h-h2o.40t $ S(a,b) for light water C

C ------------CONCRETE; Density 2.3; PNNL-15870 ------------------- -----

rn300 1001.00c l. 68018E-01 1002.00c l.9 32 4 3E-05 8016.00c 5. 62969E-01 8017.00c 2.14009E-04 11023.00c 2.1 365 1E- 02 13027. 00c 2. 13429E-02 14028.00c l.87425E- 0 1 14029.00c 9.52136E-03 14030. 00c 6.28389E-03 20040.00c l.80258E-02 20042.00c l.20307E-04 20043.00c 2.51028E-05 20044.00c 3.87884E-04 20046. 00c 7.43786E-07 20048.00c 3.47720 E -05 26054.00c 2.48181E-04 26056.00c 3.89591E-03 26057.00c 8.99736E-05 26058. 00c l.19738E-05 MT300 h-h2o.40t fe - 56.40t $ S(a,b) f or light water, iron C

c --------------REFLECTOR WATER; Density =0.998207; PNNL-15870 -----------

rn400 1001.0 0c 0.66733 8016.00c 0.33267 MT400 h-h2 o. 40t $ S(a,b) for light water print

Calc ul ation P ackage No. TMI2-EN-RPT - 0001, R ev is io n R ev 1 P age 43 of 59 ENERGYSOLUTIONS ~

11. APPENDIX C - SAMPLE ORI GEN COMPUTER INPUT I TMIFuelDecay.inp

' TMI De ca ye d So ur ce Input

= orige n

case{

title="TMI Decayed Source" lib{

f ile="e n d7dec" %- OR I GEN Decay library

}

mat{

un i ts = mo l es iso= [

U 235 = B. 6 51 5 E- 0 4 U 238 = 3.7363 E -02 016 = 7.6386 E -02 Pu239=6. 6589 E -05 Pu2 4 0 = 3.32 11E -06 Pu241= 4.13 4 8 E -07 Sm l49= 1.6772 E -07 Sml51= 2.97 24E-0 7 Eul51=1. 3 61 7 E-0 8 Eu l 53=2.19 1 9 E -07 Eul54 = 7.4892 E- 09 Eul55= 1.0 1 63 E -08 l

}

t ime{

unit s = Y EAR S s t a rt = 1 989 t = [1990 1 99 1 1 993 1 997 200 5 20 1 3 2 0 1 9 202 1 2 0 2 2]

}

print{

n uc{ tota l =yes uni ts=[MOLE S ] }

c u to ff_s tep = 5 r e l c u t o ff= no cu t o ffs [ ALL =l.O E -30 l

}

save = y e s

}

e nd

12. APPENDIX D - ELECTRONIC FILES

12.1. Computer Runs

The files listed below do not include t he files associated with the scoping calculation to determine optimum moderation. A list of those files is included with the electroruc archive.

Filename File Date Computer Code Version Computer TMl-sphereV8W 1200 onlyimp 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W 1200 onlyimp 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 1125 0.05 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 1125 0.05 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 1125 0.05 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 1125 0.05 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 1125 0.05 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 1125 0.05 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 44 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBmod 0.4 1125 0.05 0.8. in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W n oBmod 0.4 1125 0.05 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.05 1.in 12/8 /2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.05 1.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W n oBmod 0.4 1125 0.1 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1 0.2.ino 12/8/20 20 MCNP 6.2.0 NS TS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1 0.5.ino 12/8 / 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBm od 0.4 1125 0.1 0.8. in 12/8/ 2020 MCNP 6.2.0 NSTS-LS 0l TM l-sphereV8W noBmod 0.4 1125 0.1 0.8. ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV 8W noBmod 0.4 1125 0.1 1.in 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1 1.ino 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.15 0.2.in 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV8W noBmod 0.4 1125 0. 15 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV 8W noBmod 0. 4 1125 0.15 0. 3.in 12/8/2020 MCNP 6.2.0 NSTS-L S0l TMl-sph e reV8W noBmod 0.4 1125 0. 15 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.15 0.5.in 12/8 / 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.15 0.5.ino 12/8 /2 020 MCNP 6.2.0 NSTS - LS0l TMl-sphereV8W noBmod 0.4 1125 0.15 0.8.in 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-s phereV8W n o Bm od 0.4 11 25 0. 15 0.8.ino 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV 8W n o Bm od 0.4 1125 0.15 1.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sph ereV8W noBmod 0.4 1125 0.15 1.ino 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W n o Bmod 0.4 1125 0.1 621 0.2.in 12/8/202 0 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV8W n o Bmod 0.4 1125 0.1621 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1621 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-s phereV8W n o Bmod 0.4 1125 0.1621 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0.1621 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS 0l TMl-sphereV8 W n o Bm od 0.4 1125 0.1621 0.5. ino 12/ 8/ 202 0 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1125 0. 1621 0.8.in 12/8/ 2020 MCNP 6.2.0 NSTS-LS 0 l TMl-sphereV8W noBmod 0.4 1125 0.1621 0.8.ino 12/8 / 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV 8W noBmod 0.4 1125 0.1 621 1.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sph e reV8W noBmod 0.4 1125 0.1 621 1.ino 12/8/2 020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.05 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.05 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.0 5 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.05 0.3. ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.05 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.05 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV8W noBmod 0.4 1200 0.05 0.8.in 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBmod 0.4 1200 0.05 0.8. ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV8W noBmod 0.4 1200 0.05 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.05 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.2.ino 12/ 8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.5.in 12/8/ 2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 0.8.ino 12/8/2020 MCNP 6.2.0 N5TS-LS01 TM l-sphereV8W noBmod 0.4 1200 0.1 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBmod 0.4 1200 0.15 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TM l-sphereV8W noBmod 0.4 1200 0.15 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.15 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.15 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0. 15 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0. 15 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.15 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-s phereV8W noBmod 0.4 1200 0. 15 0.8.in o 12/8 / 2020 MCNP 6.2.0 NSTS-LS0l

Calculation Packa ge No. TMI2-EN-RPT-0001, Re visio n Rev I Page 45 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBmod 0.4 1200 0.15 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.15 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1621 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV8W noBmod 0.4 1200 0.1621 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBmod 0.4 1200 0.1621 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1621 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1621 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 621 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 621 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1621 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1 621 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1200 0.1621 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.05 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 15 00 0.05 0.2.ino 12/8/2020 MCNP 6.2.0 NS TS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.05 0.3.in 12/8/20 20 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBm od 0.4 1500 0.05 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.05 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV8W noBmod 0.4 1500 0.05 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.05 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.05 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBmod 0.4 1500 0.05 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.05 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV 8W noBmod 0.4 1500 0.1 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sp hereV 8W noBmod 0.4 1500 0.1 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBmod 0.4 1500 0.15 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.15 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-s phereV8W noBmod 0.4 1500 0.1621 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.5.in 12/8/2020 MCNP 6.2.0 NS TS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphe reV8W noBmod 0.4 1500 0.1621 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 1500 0.1621 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-s phereV8W noBmod 0.4 925 0.05 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 l.in 12/8/2020 MCNP 6.2.0 NSTS-LS0l TMl-sphereV8W noBmod 0.4 925 0.05 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LS0l

Calcu lation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 46 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBmod 0.4 925 0.1 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.8.in 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 l.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.3. ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBm od 0.4 925 0.1 5 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 0.8.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 l.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.15 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.2.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.2.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.3.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.3.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBmod 0.4 925 0.1621 0.5.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.5.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.8.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 0.8.ino 12/8 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 l.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBmod 0.4 925 0.1621 l.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.05.ino 12/8/20 20 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W on lyimp 1125 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.1621.ino 12/8 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1125 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1500 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1500 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W on lyimp 1500 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1500 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W on lyimp 1500 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W only imp 1500 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1500 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1500 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 a.OS.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W on lyimp 1750 0.15.in o 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 1750 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 925 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV8W onlyimp 925 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 925 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W on lyimp 925 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W on lyimp 925 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 925 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W onlyimp 925 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W only imp 925 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Re v 1 Page 47 of 59 ENERGYSOLUTIONS ~

TMl-sphereVBC noBmod 1125 0.05 0.2.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.05 0.2.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.05 0.3.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.05 0.3.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.05 0.5.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.05 0.5.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.05 0.8.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.05 0.8.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.05 l.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.05 1.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 0.2.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.1 0.2.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 0.3.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 0.3.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 0.5.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 0.5.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 0.8.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.1 0.8.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.1 l.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphe reVBC noBmod 1125 0.1 l.ino 12/ 10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1 l.inr 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.1 l.ins 12/10/2020 MCNP 6.2.0 N5T5-L5 01 TMl-sphereV8C noBmod 1125 0.15 0.2.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.2.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.2.inr 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.2.ins 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.3.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.3.ino 12/10/ 2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBm od 1125 0.15 0.3.inr 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC n oBmod 1125 0. 15 0.3.ins 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.5.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.15 0.5.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphe reVBC noBmod 1125 0.15 0.5.inr 12/10/2020 MCNP 6.2.0 N5T5-L501 TM l-sphereVBC noBmod 1125 0.15 0.5.ins 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.8.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.15 0.8.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1621 0.2.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sp hereVBC noBmod 1125 0.1621 0.2.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1125 0.1621 0.5.in 12/ 10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1621 0.5.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1621 l.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1125 0.1621 l.ino 12/ 10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.05 0.3.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.05 0.3.ino 12/10/2020 MCNP 6.2.0 N5 T5-L501 TMl-sphereVBC noBmod 1200 0.05 0.8.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.05 0.8.ino 12/10/2020 MCNP 6.2.0 N5 T5-L501 TMl-sphereVBC noBmod 1200 0.1 0.2.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.1 0.2.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV 8C noBmod 1200 0.1 0.5.in 12/ 10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.1 0.5.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.1 l.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV BC noBmod 1200 0.1 l.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.15 0.3.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.15 0.3.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.15 0.8.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1200 0.15 0.8.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.15 l.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.15 l.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.1621 0.2.in 12/10 /2020 MCNP 6.2.0 N5T5-L501 TMl-s phereVBC noBmod 1200 0.1621 0.2.ino 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereVBC noBmod 1200 0.1621 0.3.in 12/10/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8C noBmod 1200 0.1621 0.3.ino 12/10/2020 MCNP 6.2.0 N5T5-L501

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 48 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8C noBmod 1200 0.1621 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1200 0.1621 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1200 0.1621 0.8.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1200 0.1621 0.8.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1200 0.1621 1.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1200 0.1621 1.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBmod 1500 0.05 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.05 0.2.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBmod 1500 0.05 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBmod 1500 0.05 0.3.ino 12/10/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBmod 1500 0.05 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBmod 1500 0.05 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBmod 1500 0.05 0.8.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBm od 1500 0.05 0.8.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.05 l.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8C noBmod 1500 0.05 l.ino 12/10 / 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBm od 1500 0.1 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8C noBm o d 1500 0.1 0. 2.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1S00 0.1 0.3.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 0.5.ino 12/1 0/ 2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV 8C noBm od 1500 0.1 0.8.in 12/10 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 0.8. in o 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 0.8.inr 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 0.8.ins 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 l.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 l.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 l.inr 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1 l.ins 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.2.ino 12/10 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.2.inr 12/10/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8C noBmod 1500 0.15 0.2.ins 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8C noBmod 1500 0.15 0.3.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.8.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 0.8.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBm o d 1500 0.15 l.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.15 l.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.2.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.3. ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.8. in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 0.8. ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 l.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 1500 0.1621 l.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.2.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.3. ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBm o d 925 0.05 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.8. in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 0.8.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 l.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.05 1.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 49 of 59 ENERGYSOLVTIONS ~

TMl-sphereV8C noBmod 925 0.1 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 0.2. in o 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 0.3.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 0.5.ino 12/10/2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV 8 C noBmod 925 0.1 0. 8.in 12/ 10/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 0.8.ino 12/10 / 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 l.in 12/ 10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 l.ino 12/ 10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.15 0.2.in 12/ 10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.15 0.2.ino 12/10 / 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.15 0.3.in 12/ 10/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 92 5 0.15 0.3.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8C noBmod 92 5 0.15 0.5.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1 5 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.15 0.8. in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.15 0.8.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.15 l.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBm od 925 0.15 l.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBm od 925 0.1621 0.2.in 12/10/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphereV8C noBmod 925 0.16 21 0.2.ino 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBmod 925 0.1621 0.3.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0. 162 1 0.3.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0. 1621 0.5.in 12/10/2020 MC NP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1621 0.5.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C n oBmod 925 0.1621 0.8.in 12/ 10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1621 0.8.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBmod 92 5 0.1621 l.in 12/10/2020 MCNP 6. 2. 0 NSTS-LSOl TMl-sphereV8C noBmod 925 0.1621 l.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 10 0. in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 100.ino 12/8/2020 MC NP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W n oBimp 1125 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 1125 0.05 50.in o 12/8/2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n o Bimp 1125 0.05 75.in o 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 1125 0. 1 100. in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8 W noBimp 1125 0. 1 100.ino 12/8/2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 25.in 12/8/2020 MCNP 6. 2.0 NSTS - LSOl TMl-sp hereV8W noBimp 1125 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS - LSOl TMl-sphereV8W noBimp 1125 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS - LS Ol TMl-sp hereV 8W noBimp 1125 0.1 50.ino 12/8/2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 5 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 100.ino 12/8/ 20 20 MCNP 6. 2.0 NSTS-LSOl TMl-sp hereV8W noBimp 1125 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphereV8W noBimp 1125 0. 15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphe reV8W n oB imp 1125 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8 W noBimp 11 25 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NS TS - LS Ol TMl-sphereV8W noBimp 1125 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV 8W noBimp 1125 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 11 25 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 75.in o 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Pa cka ge No. TMI2-EN -RPT - 0001, R ev i sion R ev 1 Page 50 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBimp 1200 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.05 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.05 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.05 SO.in 12/8/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8W noBimp 1200 0.05 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphereV8W noBimp 1200 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8W noBimp 1200 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1 SO.in 12/8/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8W noBimp 1200 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8W noBirnp 1200 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8W noBimp 1200 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 1200 0.1621 75.in 12/8/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8W noBimp 1200 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 1200 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1200 0.1 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphereV8W noBimp 1500 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n oBimp 1500 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8W noBimp 1500 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8W noBimp 1500 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 1500 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBimp 1500 0.15 50.ino 12/8/2020 MCNP 6.2.0 NST S-LSOl TMl-sphereV 8W noBimp 1500 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n oBimp 1500 0. 15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Packa ge No. TMI2-EN-RPT-0001, Re v ision Re v I Page51 of59

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ENERGYSOLUTIONS

TMl-sphereV8W noBimp 1500 0.1 75.in 12/8/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8W noBimp 1500 0.1 75.ino 12/8/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8W noBimp 1750 0.05 100.in 12/8/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8W noBimp 1750 0.05 100.ino 12/8/2020 MCNP 6.2.0 N5T5-L501 TMl-sphereV8W noBimp 1750 0.05 25.in 12/8/2020 MCNP 6.2.0 N5TS-L501 TMl-sphereV8W noBimp 1750 0.05 25.ino 12/8/2020 MCNP 6.2.0 N5TS-LS01 TMl-sphereV8W n oB imp 1750 0.05 SO.in 12/ 8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 50.ino 12/8/2020 MCNP 6.2.0 NST5-LS01 TMl-sphereV8W noBimp 1750 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV 8W noBimp 1750 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n oBimp 1750 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n o Bimp 1750 0.15 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBimp 1750 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LS Ol TMl-sphereV8W noBimp 1750 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8W noBimp 925 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noB imp 925 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8W noBimp 925 0.05 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBimp 925 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBimp 925 0.1 25. ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 92S 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.162 1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 52 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBimp 925 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LS Ol TMl-sphereV8W noBnoB 1750 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBnoB 925 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 25.ino 12/8 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV8W noBimp 1125 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1125 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 53 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W ncBimp 1125 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.15 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.15 75.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1621 100.in 12/8/2020 MCNP 6.2.0 NST S-LSOl TMl-sphereV8W ncBimp 1125 0.1621 100.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1621 25.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1621 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W ncBimp 1125 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1621 75.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1125 0.1 75.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.05 100.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV 8W ncBimp 1200 0.05 25. in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.05 25.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W ncBimp 1200 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W ncBimp 1200 0.05 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n c Bimp 1200 0.05 75.in 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8W ncBimp 1200 0.05 75.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8W ncBimp 1200 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV8W ncBimp 1200 0.1 100.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp he reV8W n c Bimp 1200 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1 25.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1 SO.inc 12/8/2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV8W n cBimp 1200 0.15 100.in 12/8/ 2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8W n cBimp 1200 0.15 100.inc 12/8/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphe reV8W ncBimp 1200 0.15 25.in 12/8 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n cBimp 1200 0.15 25.inc 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV 8W ncBimp 1200 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphereV8W ncBimp 1200 0.15 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W n cBimp 1200 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.15 75.in c 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1621 100.inc 12/8 / 2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV8W ncBimp 1200 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8 W ncBimp 1200 0.1621 25.inc 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1621 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSO l TMl-sphereV8W ncBimp 1200 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n cB imp 1200 0.1621 75.inc 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1200 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W ncBimp 1200 0.1 75.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8W ncBimp 1500 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.05 100.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W ncBimp 1500 0.05 25. in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.05 25.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.05 SO.inc 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W ncBimp 1500 0.05 75.inc 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.1 100.in c 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.1 25.inc 12/8/2020 MCNP 6.2.0 NSTS - LSOl TMl-sphereV8W ncBimp 1500 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS - LSOl TMl-sphereV8W ncBimp 1500 0.1 SO.inc 12/8/2020 MCNP 6.2.0 NSTS - LSOl TMl-sphe reV8W ncBimp 1500 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W ncBimp 1500 0.15 100.inc 12/8 /2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Re v 1 Page 54 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBimp 1500 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 50.ino 12/8 /2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1 621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1500 0.1 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 1750 0.1 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBimp 925 0.05 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBimp 925 0.05 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.05 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBimp 925 0.1 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 55 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8W noBimp 925 0.15 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 50.ino 12/8/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8W noBimp 925 0.15 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.15 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 100.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 621 100.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 25.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 25.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 SO.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 50.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1621 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 75.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBimp 925 0.1 75.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBnoB 1125 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.15.ino 12/8/2020 MCNP 6.2.0 NSTS-LS Ol TMl-sphereV8W noBnoB 1125 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1125 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBnoB 11 25 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.15.in o 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1200 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.05.ino 12/8 /20 20 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.15.in 12/8/2020 MCNP 6.2.0 NSTS-LS Ol TMl-sphereV8W noBnoB 1500 0.15.ino 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-s phereV8W noBnoB 1500 0.1.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1500 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.05.ino 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1 5.in 12/8 /202 0 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.15.ino 12/8 / 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W n oB noB 1750 0.1621.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1.in 12/8/ 2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 1750 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.05.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBnoB 925 0.05.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.15. in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sp hereV8W noBnoB 925 0.15.ino 12/8/2020 MCNP 6. 2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.1621.in 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8W noBnoB 925 0.1621.in o 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8W noBnoB 925 0.1.in 12/ 8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8W noBnoB 925 0.1.ino 12/8/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBimp 1125 0.05 100.in 12/ 10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.05 100.ino 12/ 10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.05 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.05 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 56 of 59 ENERGYSOLUTIONS ~

TMl-sphereV8C noBimp 1125 0.05 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.05 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.05 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.05 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C n oBimp 1125 0.15 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.15 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.15 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.15 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8C noBimp 1125 0.15 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8C noBimp 1125 0.15 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C n o Bimp 1125 0.15 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.15 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1621 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1621 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8 C noBimp 1125 0.1621 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C n o Bimp 1125 0.1621 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1621 SO.in 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1125 0.1621 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1621 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1621 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1125 0.1 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.05 75.in o 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.15 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.15 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.15 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.15 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV 8C noBimp 1200 0.15 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8C noBimp 1200 0.15 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TM l-sphereV8C noBimp 1200 0.15 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.15 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1621 75. ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1200 0.1 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.05 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.05 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl

Calculation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 57 of 59

~

ENE RGYSOLUTIONS

TMl-sphereV8C noBimp 1500 0.05 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.05 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.05 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.05 50.ino 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1500 0.05 75.in 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1500 0.05 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphe reV8C noBimp 1500 0.1 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.15 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.15 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.15 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.15 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 5 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.15 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.15 75.in 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1500 0.15 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1621 75.ino 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1500 0.1 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1500 0.1 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 100.in 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1750 0.05 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.05 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 100.in 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1750 0.1 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.15 75.ino 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1750 0.1621 100.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1621 100.ino 12/10/2020 MCNP 6.2.0 NS TS-LSOl TMl-sphereV8C noBimp 1750 0.1621 25.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1621 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1621 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1621 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1621 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1621 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 75.in 12/10/2020 MCNP 6.2.0 NSTS-LSOl TMl-sphereV8C noBimp 1750 0.1 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LSOl

Calcu l ation Package No. TMI2-EN-RPT-0001, Revision Rev 1 Page 58 of 59 ENERGYSOLlJTIONS ~

TMl-sphereV8C n oBimp 925 0.05 100.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.05 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.05 25.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sp hereV8C noBimp 925 0.05 25.ino 12/10/2020 MCNP 6.2.0 NS TS-LS01 TMl-sphereV8C noBimp 925 0.05 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sp hereV8C noBimp 925 0.05 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.05 75.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.05 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 100.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 25.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 SO.in 12/10/2020 MCNP 6.2.0 NS TS-LS01 TMl-sphereV8C noBimp 925 0.1 50.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 100.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 25.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 50.ino 12/10/2020 MCNP 6.2. 0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.15 75.in 12/10/2020 MCNP 6.2.0 NS TS-LS01 TMl-sphereV8C noBimp 925 0.15 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1621 100.in 12/10/2020 MCNP 6.2.0 NS TS-LS01 TMl-sphe reV8C noBimp 925 0.1621 100.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1621 25.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1621 25.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1621 SO.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1621 50.ino 12/10/2020 MCNP 6.2.0 NS TS-LS01 TMl-sphereV8C noBimp 925 0.1621 75.in 12/10/2020 MCNP 6.2.0 NS TS-LS0 1 TMl-sphereV8C noBimp 925 0.1621 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 75.in 12/10/2020 MCNP 6.2.0 NSTS-LS01 TMl-sphereV8C noBimp 925 0.1 75.ino 12/10/2020 MCNP 6.2.0 NSTS-LS01 LAPTOP*

TMIFuelDecay.inp 12/10/2020 ORIG EN/SCALE 6.2.4 MEGANP TMIFuelDecay.out 12/10/2020 ORIG EN/SCALE 6.2.4 21888-L

12.2. Other Electronic Fi l es

Filename File Date Description Final SFML 12/16/2020 Repository of all fina l MCNP ketTresults, tables, and plots.

Results.xlsb Material comp and 12/16/2020 ORIGEN output for material composition; MCNP ketT results for scoping.xis optimum moderation determination.

Calculation Package No. TMI2-EN-RPT-0001, R evision R ev 1 Page 59 of 59