ML22006A369

Enclosure 4: CR3MP Transport Package Safety Analysis Report, Revision 1

ML22006A369
Person / Time
Site:	07109393
Issue date:	01/31/2022
From:	Orano Federal Services
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML22006A364	List: ML22006A365 ML22006A366 ML22006A369 ML22006A370
References
EPID L-2021-NEW-0003, FS-21-0147
Download: ML22006A369 (111)

Text

NON-PROPRIETARY DOCKET 71-9393 CR3MP TRANSPORT PACKAGE Safety Analysis Report Revision 1 Orano Federal Services LLC January 2022

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 TABLE OF CONTENTS Table of Contents ............................................................................................................................ ii Glossary of Acronyms and Abbreviations ..................................................................................... vi List of Figures .............................................................................................................................. viii List of Tables ...................................................................................................................................x 1.0 General Information........................................................................................................... 1.1-1 1.1 Introduction and Background ..................................................................................... 1.1-1 1.2 Package Description ................................................................................................... 1.2-1 1.2.1 General CR3MP Description ........................................................................... 1.2-1 1.2.2 Contents ........................................................................................................... 1.2-3 1.3 Appendices ................................................................................................................. 1.3-1 1.3.1 References........................................................................................................ 1.3-2 1.3.2 Packaging General Arrangement Drawings .................................................... 1.3-3 2.0 Structural Evaluation ......................................................................................................... 2.1-1 2.1 Structural Design ........................................................................................................ 2.1-1 2.1.1 Discussion ........................................................................................................ 2.1-1 2.1.2 Design Criteria ................................................................................................. 2.1-1 2.1.3 Weights and Centers of Gravity ...................................................................... 2.1-3 2.1.4 Identification of Codes and Standards for Package Design............................. 2.1-3 2.2 Materials ..................................................................................................................... 2.2-1 2.2.1 Material Properties and Specifications ............................................................ 2.2-1 2.2.2 Chemical, Galvanic, or Other Reactions ......................................................... 2.2-1 2.2.3 Effects of Radiation on Materials .................................................................... 2.2-2 2.3 Fabrication and Examination ...................................................................................... 2.3-1 2.3.1 Fabrication ....................................................................................................... 2.3-1 2.3.2 Examination ..................................................................................................... 2.3-2 2.4 General Standards for All Packages ........................................................................... 2.4-1 2.4.1 Minimum Package Size ................................................................................... 2.4-1 2.4.2 Tamper-Indicating Feature .............................................................................. 2.4-1 2.4.3 Positive Closure ............................................................................................... 2.4-1 2.4.4 Materials .......................................................................................................... 2.4-1 2.4.5 Valves .............................................................................................................. 2.4-1 2.4.6 Package Design and NCT Conditions ............................................................. 2.4-1 2.4.7 External Temperatures ..................................................................................... 2.4-2 2.4.8 Venting ............................................................................................................ 2.4-2 2.5 Lifting and Tie-down Standards for All Packages ..................................................... 2.5-1 ii

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.5.1 Lifting Devices ................................................................................................ 2.5-1 2.5.2 Tie-down Devices ............................................................................................ 2.5-1 2.6 Normal Conditions of Transport ................................................................................ 2.6-1 2.6.1 Heat .................................................................................................................. 2.6-1 2.6.2 Cold.................................................................................................................. 2.6-3 2.6.3 Reduced External Pressure .............................................................................. 2.6-3 2.6.4 Increased External Pressure ............................................................................. 2.6-3 2.6.5 Vibration .......................................................................................................... 2.6-4 2.6.6 Water Spray ..................................................................................................... 2.6-4 2.6.7 Free Drop ......................................................................................................... 2.6-4 2.6.8 Corner Drop ..................................................................................................... 2.6-5 2.6.9 Compression .................................................................................................... 2.6-5 2.6.10 Penetration ....................................................................................................... 2.6-5 2.7 Hypothetical Accident Conditions ............................................................................. 2.7-1 2.7.1 Free Drop ......................................................................................................... 2.7-1 2.7.2 Crush ................................................................................................................ 2.7-3 2.7.3 Puncture ........................................................................................................... 2.7-3 2.7.4 Thermal ............................................................................................................ 2.7-5 2.7.5 Immersion - Fissile.......................................................................................... 2.7-6 2.7.6 Immersion - All Packages ............................................................................... 2.7-6 2.7.7 Deep Water Immersion Test ............................................................................ 2.7-6 2.7.8 Summary of Damage ....................................................................................... 2.7-6 2.8 Accident Conditions for Air Transport of Plutonium................................................. 2.8-1 2.9 Accident Conditions for Fissile Material Packages for Air Transport ....................... 2.9-1 2.10 Special Form ............................................................................................................. 2.10-1 2.11 Fuel Rods .................................................................................................................. 2.11-1 2.12 Appendices ............................................................................................................... 2.12-1 2.12.1 References...................................................................................................... 2.12-2 2.12.2 Free Drop Evaluation ..................................................................................... 2.12-4 3.0 ......................................................................................................................................... 2.12-1 3.0 Thermal Evaluation ........................................................................................................... 3.1-1 3.1 Description of Thermal Design .................................................................................. 3.1-1 3.1.1 Design Features ............................................................................................... 3.1-1 3.1.2 Contents Decay Heat ...................................................................................... 3.1-1 3.1.3 Summary Tables of Temperatures ................................................................... 3.1-1 3.1.4 Summary Tables of Maximum Pressures ........................................................ 3.1-2 3.2 Material Properties and Component Specifications ................................................... 3.2-1 3.2.1 Material Properties........................................................................................... 3.2-1 3.2.2 Component Specifications ............................................................................... 3.2-7 iii

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.3 Thermal Evaluation under Normal Conditions of Transport ..................................... 3.3-1 3.3.1 Heat and Cold .................................................................................................. 3.3-3 3.3.2 Maximum Normal Operating Pressure ............................................................ 3.3-3 3.4 Thermal Evaluation under Hypothetical Accident Conditions .................................. 3.4-1 3.4.1 Initial Conditions ............................................................................................. 3.4-1 3.4.2 Fire Test Conditions ........................................................................................ 3.4-1 3.4.3 Maximum Temperatures and Pressure ............................................................ 3.4-3 3.4.4 Maximum Thermal Stresses ............................................................................ 3.4-4 3.4.5 Accident Conditions for Fissile Material Packages for Air Transport ............ 3.4-4 3.5 Appendices ................................................................................................................. 3.5-1 3.5.1 References........................................................................................................ 3.5-2 3.5.2 Evaluation of Pressure in the CR3MP ............................................................. 3.5-3 3.5.3 Natural Convection Heat Transfer ................................................................... 3.5-9 4.0 Containment ....................................................................................................................... 4.1-1 4.1 Description of the Containment System ..................................................................... 4.1-1 4.1.1 Containment Boundary .................................................................................... 4.1-1 4.1.2 Containment Penetrations, Closures, and Seals ............................................... 4.1-1 4.1.3 Welds ............................................................................................................... 4.1-1 4.2 Containment under Normal Conditions of Transport ................................................. 4.2-1 4.2.1 Hydrogen Concentration in the Package ......................................................... 4.2-1 4.3 Containment under Hypothetical Accident Conditions .............................................. 4.3-1 4.4 Leakage Rate Tests for Type B Packages .................................................................. 4.4-1 4.5 Appendix .................................................................................................................... 4.5-1 4.5.1 References........................................................................................................ 4.5-1 5.0 Shielding Evaluation .......................................................................................................... 5.1-1 5.1 Description of Shielding Design ................................................................................ 5.1-1 5.1.1 Design Features ............................................................................................... 5.1-1 5.1.2 Summary of Maximum Radiation Levels........................................................ 5.1-2 5.2 Source Specification ................................................................................................... 5.2-1 5.2.1 Gamma Source................................................................................................. 5.2-2 5.2.2 Neutron Source ................................................................................................ 5.2-3 5.3 Shielding Model ......................................................................................................... 5.3-1 5.3.1 Configuration of Source and Shielding ........................................................... 5.3-1 5.3.2 Material Properties........................................................................................... 5.3-4 5.4 Shielding Evaluation .................................................................................................. 5.4-1 5.4.1 Methods ........................................................................................................... 5.4-1 5.4.2 Flux-to-Dose Rate Conversion ........................................................................ 5.4-2 5.4.3 External Radiation Levels................................................................................ 5.4-3 5.4.4 Radiolytic Gas Generation ............................................................................... 5.4-3 iv

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.5 Appendices ................................................................................................................. 5.5-1 5.5.1 References........................................................................................................ 5.5-2 5.5.2 Input Data ........................................................................................................ 5.5-3 5.5.3 G-value Calculation ......................................................................................... 5.5-8 6.0 Criticality Evaluation ......................................................................................................... 6.1-1 6.1 References .................................................................................................................. 6.1-1 7.0 Package Operations ........................................................................................................... 7.1-1 7.1 Procedures for Loading the Package .......................................................................... 7.1-1 7.1.1 Preparation for Loading ................................................................................... 7.1-1 7.1.2 Loading of Contents ........................................................................................ 7.1-1 7.1.3 Preparation of the CR3MP for Transport ........................................................ 7.1-2 7.2 Package Unloading ..................................................................................................... 7.2-1 7.2.1 Receipt of Package from Carrier ..................................................................... 7.2-1 7.2.2 Removal of Contents ....................................................................................... 7.2-1 7.3 Preparation of Empty Package for Transport ............................................................. 7.3-1 7.4 Other Operations ........................................................................................................ 7.4-1 7.5 Appendix .................................................................................................................... 7.5-1 7.5.1 References........................................................................................................ 7.5-1 8.0 Acceptance Tests and Maintenance Program .................................................................... 8.1-1 8.1 Acceptance Tests ........................................................................................................ 8.1-1 8.1.1 Visual Inspection and Measurements .............................................................. 8.1-1 8.1.2 Weld Examinations .......................................................................................... 8.1-1 8.1.3 Structural and Pressure Tests ........................................................................... 8.1-2 8.1.4 Leakage Tests .................................................................................................. 8.1-2 8.1.5 Component and Material Tests ........................................................................ 8.1-2 8.1.6 Shielding Tests................................................................................................. 8.1-3 8.1.7 Thermal Tests .................................................................................................. 8.1-4 8.1.8 Miscellaneous Tests ......................................................................................... 8.1-4 8.2 Maintenance Program ................................................................................................. 8.2-1 8.2.1 Structural and Pressure Tests ........................................................................... 8.2-1 8.2.2 Leakage Tests .................................................................................................. 8.2-1 8.2.3 Component and Material Tests ........................................................................ 8.2-1 8.2.4 Thermal Tests .................................................................................................. 8.2-1 8.2.5 Miscellaneous Tests ......................................................................................... 8.2-1 8.3 Appendix .................................................................................................................... 8.3-1 8.3.1 References........................................................................................................ 8.3-1 v

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 GLOSSARY OF ACRONYMS AND ABBREVIATIONS This list of acronyms and abbreviations is consistent across all chapters and appendices in this Safety Analysis Report.

Acronym Description ACI American Concrete Institute ANSI American National Standards Institute ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials AWS American Welding Society BPVC ASME Boiler and Pressure Vessel Code BWR Boiling Water Reactor CAD Computer Aided Drafting/Design CFR Code of Federal Regulations CG Center of Gravity Ci Curie CJP Complete Joint Penetration CR3 Crystal River Reactor Unit #3 CR3MP CR3 Middle Package CSI Criticality Safety Index DOT Department of Transportation DWS Diamond Wire Saw FEA Finite Element Analysis GTCC Greater Than Class C HAC Hypothetical Accident Conditions HDCC High Density Cellular Concrete HHT Heavy Haul Trailer ISFSI Independent Spent Fuel Storage Installation ksi thousand pounds per square inch lb pounds LDCC Low Density Cellular Concrete LST Lowest Service Temperature LSTC Livermore Software Technology Corporation M&TE Measuring and Test Equipment MCNP Monte Carlo N-Particle MNOP Maximum Normal Operating Pressure MS Margin of Safety MT Magnetic Particle Examination NAA Neutron Activation Analysis NCT Normal Conditions of Transport NDE Non Destructive Examination NDT Nil Ductility Transition NRC Nuclear Regulatory Commission vi

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Acronym Description OEM Original Equipment Manufacturer OFS Orano Federal Services pcf pounds per cubic foot psi pounds per square inch psia pounds per square inch absolute psig pounds per square inch gauge PT Liquid Penetrant Examination QA Quality Assurance RCS Reactor Coolant System RPV Reactor Pressure Vessel RT Radiographic Examination RVI Reactor Pressure Vessel Internals SAR Safety Analysis Report SPA Special Package Authorization SPMT Self-Propelled Modular Transporter UT Ultrasonic Examination VT Visual Examination VTK Visualization Toolkit WCS Waste Control Specialists vii

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 LIST OF FIGURES Figure 1.1 CR3MP Cross-Section ...................................................................................... 1.1-3 Figure 2.1 CR3MP Cross Section ...................................................................................... 2.1-4 Figure 2.7 HAC Side Wall Puncture Configuration ........................................................... 2.7-7 Figure 2.12.2 LS-DYNA Model ................................................................................... 2.12-14 Figure 2.12.2 ASTM A516 Gr 70 Plastic Stress-Strain Curve ....................................... 2.12-15 Figure 2.12.2 NCT End Drop Plastic Strains ................................................................. 2.12-16 Figure 2.12.2 Maximum NCT End Drop Plastic Strain ................................................. 2.12-16 Figure 2.12.2 NCT End Drop Impact Force Curve ........................................................ 2.12-17 Figure 2.12.2 NCT End Drop Force Curve - After Initial Spike ................................... 2.12-17 Figure 2.12.2 NCT End Drop Force Curve - Low Pass Filtered ................................... 2.12-18 Figure 2.12.2 NCT Side Drop Plastic Strains................................................................. 2.12-19 Figure 2.12.2 Maximum NCT Side Drop Plastic Strain................................................. 2.12-19 Figure 2.12.2 NCT Side Drop Impact Force Curve ..................................................... 2.12-20 Figure 2.12.2 NCT Corner Drop Top Closure Weld Erosion ...................................... 2.12-21 Figure 2.12.2 NCT Corner Drop Effective Strains ....................................................... 2.12-21 Figure 2.12.2 Maximum NCT Corner Drop Effective Strain....................................... 2.12-22 Figure 2.12.2 NCT Corner Drop Effective Strain Range Limited ............................... 2.12-22 Figure 2.12.2 NCT Corner Drop Impact Force Curve ................................................. 2.12-23 Figure 2.12.2 NCT Corner Drop Initial Impact ............................................................ 2.12-23 Figure 2.12.2 HAC End Drop Plastic Strains ............................................................... 2.12-24 Figure 2.12.2 Close-up View of HAC End Drop Plastic Strains ................................. 2.12-25 Figure 2.12.2 HAC End Drop Impact Force Curve ...................................................... 2.12-25 Figure 2.12.2 HAC End Drop Impact Force Curve - After Initial Spike..................... 2.12-26 Figure 2.12.2 HAC End Drop Impact Force Curve - Low Pass Filtered ..................... 2.12-26 Figure 2.12.2 HAC Side Drop Top Closure Weld Erosion .......................................... 2.12-28 Figure 2.12.2 HAC Side Drop Bottom Closure Weld Erosion .................................... 2.12-28 Figure 2.12.2 HAC Side Drop Bottom Closure Weld Gap Measurement ................... 2.12-29 Figure 2.12.2 Maximum HAC Side Drop Top Closure Base Metal Strain .................. 2.12-29 Figure 2.12.2 HAC Side Drop Impact Force Curve ..................................................... 2.12-30 Figure 2.12.2 HAC Side Drop Package Velocity ......................................................... 2.12-30 Figure 2.12.2 HAC Corner Drop Top Closure Weld Erosion ...................................... 2.12-32 Figure 2.12.2 HAC Corner Drop Top Closure Weld Gap Measurement ..................... 2.12-32 Figure 2.12.2 HAC Corner Drop Base Metal Strains ................................................... 2.12-33 Figure 2.12.2 Maximum HAC Corner Drop Base Metal Strain ................................... 2.12-33 Figure 2.12.2 HAC Corner Drop Impact Force Curves ............................................... 2.12-34 Figure 2.12.2 HAC Corner Drop Package Velocity ..................................................... 2.12-34 Figure 2.12.2 HAC Corner Grout Exit Path ................................................................. 2.12-35 Figure 3.2 Grout Thermal Conductivity versus Oven-Dry Density ................................... 3.2-4 Figure 3.3 CR3MP Thermal Model Materials and Mesh ................................................... 3.3-2 Figure 3.3 CR3MP NCT Maximum Temperature Distribution ......................................... 3.3-3 Figure 3.4 CR3MP Thermal Model with HAC Crack........................................................ 3.4-2 Figure 3.4 CR3MP HAC Maximum Temperatures During Fire Transient ........................ 3.4-3 Figure 3.4 CR3MP HAC Post-Fire Steady-State Temperatures ........................................ 3.4-4 viii

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Figure 3.5 Rayleigh Numbers for CR3MP Surfaces ........................................................ 3.5-10 Figure 3.5 Convection Heat Transfer Coefficients for CR3MP Surfaces ........................ 3.5-10 Figure 5.1 CR3 RPV/RVI (Decommissioning Configuration, Middle Segment) .............. 5.1-1 Figure 5.2 Co-60 Spatial Distribution (Bq/g) ..................................................................... 5.2-3 Figure 5.3 CR3MP NCT Model (XZ and YZ Planes)........................................................ 5.3-2 Figure 5.3 CR3MP NCT Model (XY Plane, Lower and Upper Sections) ......................... 5.3-3 Figure 5.3 CR3MP HAC Model (YZ and XY Planes) ....................................................... 5.3-3 Figure 5.4 CR3MP Radiolysis Model ................................................................................ 5.4-6 Figure 5.4 CR3MP Radiolysis Flux Distribution (particles/cm2-s).................................... 5.4-7 ix

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 LIST OF TABLES Table 1.2 CR3MP Contents Radionuclide Activity Levels ................................................ 1.2-6 Table 2.1 Packaging Allowable Stress Limits .................................................................... 2.1-3 Table 2.1 CR3MP Component Weights ............................................................................. 2.1-4 Table 2.2 Mechanical Properties of ASTM/ASME A516/SA516 Grade 70 Steel ............. 2.2-3 Table 2.12.2 A Performance Record of LS-DYNA in the Nuclear Industry ................. 2.12-7 Table 2.12.2 Parts Listing ............................................................................................... 2.12-13 Table 2.12.2 Package Model Mass Verification............................................................. 2.12-13 Table 2.12.2 ASTM A516 Gr 70 Stress-Strain Curve Parameters ................................. 2.12-14 Table 2.12.2 Weld Opening Characteristics ................................................................... 2.12-35 Table 2.12.2 NCT Results .............................................................................................. 2.12-36 Table 2.12.2 HAC Results .............................................................................................. 2.12-37 Table 3.1 Summary of CR3MP NCT Temperatures .......................................................... 3.1-2 Table 3.1 Summary of CR3MP HAC Temperatures .......................................................... 3.1-2 Table 3.2 Carbon Steel Material Properties........................................................................ 3.2-2 Table 3.2 Stainless Steel Material Properties ..................................................................... 3.2-3 Table 3.2 Grout Material Properties ................................................................................... 3.2-4 Table 3.2 Air Material Properties ....................................................................................... 3.2-5 Table 3.3 Key CR3MP Thermal Model Dimensions ......................................................... 3.3-2 Table 3.3 CR3MP NCT Temperatures ............................................................................... 3.3-3 Table 3.4 CR3MP HAC Temperatures............................................................................... 3.4-3 Table 3.5 Moles of Water Vapor Released under NCT ..................................................... 3.5-6 Table 3.5 Moles of Water Vapor Released under HAC - Fire Peak .................................. 3.5-7 Table 3.5 Moles of Water Vapor Released under HAC - Post-Fire Steady State ............. 3.5-7 Table 3.5 Summary of Maximum Pressures for the CR3MP ............................................. 3.5-7 Table 3.5 Numerical Example for Temperature Range 101 - 125 °C ............................... 3.5-8 Table 5.1 Summary of Maximum NCT Dose Rates (mrem/hr) ......................................... 5.1-2 Table 5.1 Summary of Maximum HAC Dose Rates (mrem/hr)......................................... 5.1-2 Table 5.2 Co-60 Discrete Gamma Spectrum ...................................................................... 5.2-2 Table 5.3 Key CR3MP Dimensions ................................................................................... 5.3-1 Table 5.3 Carbon Steel Composition.................................................................................. 5.3-4 Table 5.3 Portland Concrete (Grout) Composition ............................................................ 5.3-4 Table 5.4 Photon Flux-to-Dose Rate Conversion Factors .................................................. 5.4-2 Table 5.4 Tally Maximum Dose Rates (mrem/hr) ............................................................. 5.4-3 Table 5.4 Evaluated Radiolysis Parameters ....................................................................... 5.4-8 Table 5.5 Isoplast 1440 Species Summary ......................................................................... 5.5-9 Table 5.5 CMX Species Summary ................................................................................... 5.5-10 Table 5.5 G-value Determination Summary..................................................................... 5.5-12 Table 5.5 Temperature-Corrected Results Summary ....................................................... 5.5-12 x

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.0 GENERAL INFORMATION This section presents a general introduction and description of the Crystal River Reactor Unit #3 (CR3) Middle Package (CR3MP). The CR3MP is used to safely and compliantly transport the segmented middle section of the decommissioned CR3 Reactor Pressure Vessel (RPV) and RPV Internals (RVI). This Safety Analysis Report (SAR) supports a license application seeking authorization of the CR3MP as a Type B(U)-96 shipping package in accordance with the provisions of Title 10, Part 71 of the Code of Federal Regulations (CFR) [1]. This SAR follows the general format and content provided in the Nuclear Regulatory Commission (NRC)

Regulatory Guide 7.9 [2].

The major components comprising the package are discussed in Section 1.2, Package Description, and illustrated in Figure 1.1-1. Detailed packaging SAR drawings are presented in Appendix 1.3.2, Packaging General Arrangement Drawings.

1.1 Introduction and Background The CR3MP has been developed by Orano Federal Services (OFS) to transport the segmented middle section of the decommissioned CR3 RPV and RVI. The middle section is the core portion of the RPV, extending approximately over the active fuel assembly region and containing a high amount of activated metal. The top and bottom RPV sections are planned for shipment in Department of Transportation (DOT) packages. The middle section segment of the consolidated RPV and RVI components will be transported in the CR3MP Type B package described herein.

As such, the CR3MP is a one-time, single use, expendable package. The CR3MP will be shipped via exclusive use from CR3 to the licensed low-level waste disposal facility of Waste Control Specialists (WCS) near Andrews, Texas.

In terms of the packaging configuration, an isometric cross section of the CR3MP is shown in Figure 1.1-1. The CR3MP consists of a 3-in. thick steel body assembly shell, 6-in. thick top and bottom covers, a closure joint weld, and other welds necessary for fabrication of the large material cross-sections. In addition, a layer of Low Density Cellular Concrete (LDCC) grout fills the annulus between the RPV shell exterior and the CR3MP shell. The overall height of the package is 178.1-in. tall while the overall diameter is 200.3-in. The package is designed to be transported by ground or water with its cylindrical axis vertical. The overall package gross weight is a maximum of 860,000 lb.

As defined by 10 CFR 61.55 [3] for Class B and Class C radiological waste materials, the CR3MP authorized contents will contain both waste classes. None of the source contents contain fissile content, therefore the payload is fissile exempt per the provisions of §71.15(b) [1].

Since the RPV and RVI contents transported in the CR3MP are fissile-exempt, the Criticality Safety Index (CSI) described in 10 CFR 71.59 does not apply.

The CR3MP does provide shielding from gamma radiation via the thick steel covers and thick steel walls of the shell. The containment boundary is provided by the shell walls and covers and the circumferential weld joint between the cover and shell wall. The containment boundary will be described in greater detail in Section 1.2.1.1, Containment Vessel.

1.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 OFS is seeking a Special Package Authorization (SPA) in accordance with 10 CFR 71.41(d) for the one-time shipment of the CR3MP. There is one equivalency determination sought, as follows:

Due to material property limits discussed in Section 2.1.2.1.1, Brittle Fracture, a Lowest Service Temperature (LST) of 0°F is established. Therefore, OFS is requesting a condition for the LST to be greater than or equal to 0°F during the entirety of the transport. As outlined in NRC Regulatory Guide 7.12 [8], an equivalent level of safety for the 10 CFR 71.71 and 10 CFR 71.73 Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) initial test conditions is offered for brittle fracture criteria of the bounding 6-in. thick CR3MP top and bottom covers at the LST identified. Of note, a buffer zone ranging from 0-5°F is included for operational convenience in Section 7.1.3, Preparation of the CR3MP for Transport.

For the LST low ambient temperature, the primarily impacted test conditions (i.e., the NCT and HAC structural drop tests) use the more conservative properties of steel at the high temperature condition of 150°F (see Appendix 2.12.2, Free Drop Evaluation). In addition, as recommended by NUREG/CR-3826 [9], in order to preclude a brittle fracture failure initiation mode under any NCT or HAC, a supporting analysis in Section 2.1.2.1.1, Brittle Fracture, has been performed showing that the material conforms to the toughness requirements of NUREG/CR-6491 [10] at the LST.

1.1-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Figure 1.1 CR3MP Cross-Section 1.1-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.2 Package Description This section presents a basic description of the CR3MP components and construction. In the following, drawing references are to the general arrangement drawings provided in Appendix 1.3.2, Packaging General Arrangement Drawings.

1.2.1 General CR3MP Description In terms of the packaging configuration, as shown in Appendix 1.3.2, Packaging General Arrangement Drawings, the packaging is a right circular cylinder steel shell made of 3-in. thick steel and two 6-in. thick covers, one top and one bottom. Each top and bottom cover is groove welded to the shell wall along the circumference. [

] The package cross section is shown in Figure 1.1-1. The overall nominal height of the package is 178.1-in. tall, while the overall diameter is 200.3-in.

The RPV payload centrally rests on the inside of the bottom cover. [

] The nominal 3-in. gap between the top surface of the RPV and the bottom surface of the top cover is unfilled (i.e., nominal air gap). However, the radial 3-in. nominal annular gap between the shell inner wall and the RPV outer diameter is filled with LDCC, or informally identified simply as grout.

As shown in Figure 1.1-1, RVI components are rigidly constrained as one body within the RPV by up to three layers of grout, of which two layers may be a High Density Cellular Concrete (HDCC) grout and one layer is the LDCC. Regardless of the thickness of the HDCC, all cavities within the RPV will be filled with grout. The higher density layer is up to 9-in. thick on the top and up to 9-in. thick on the bottom. The HDCC is nominally 135 pounds per cubic foot (pcf) while the LDCC grout is nominally 45 pcf.

The maximum gross weight of the CR3MP is 860,000 pounds, while the authorized contents weight of the RPV with RVI is conservatively set to 645,000 pounds maximum. A summary of overall component weights is provided in Table 2.1-2.

The CR3MP complies with the requirements of 10 CFR Part 71 [1]. The remaining paragraphs in this section provide reference to the sections of this SAR that are used to specifically address compliance with the requirements of Subparts E and F of 10 CFR Part 71.

The shell and top and bottom covers provide adequate structural load bearing capacity in order to comply with resultant effects on the package from the 10 CFR 71.71 NCT and 10 CFR 71.73 HAC. Structural performance of the package is covered in greater detail in Chapter 2.0, Structural Evaluation. The materials of construction of the package are carbon steel plate and cementitious grout. A complete evaluation of the materials and their acceptance criteria under both NCT and HAC conditions is covered in Section 2.2, Materials.

1.2-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 The dissipation of heat from the CR3MP is entirely passive and is adequate to comply with the requirements of 10 CFR Part 71 and no coolants are required. A more detailed description of the package thermal design is given in Chapter 3.0, Thermal Evaluation.

Containment of the radioactive waste in the package is provided by the main cylindrical shell, top and bottom covers, and weld joints of the CR3MP. A brief description of the package bodys containment boundary and performance is included in Section 1.2.1.1, Containment Vessel and the containment capabilities of the CR3MP after both the NCT and HAC tests are evaluated in Chapter 4.0, Containment and are shown to be adequate.

Biological shielding of gamma radiation is provided by the steel located in walls of both the shell body and top and bottom covers. In addition, the RPV steel shell primarily provides radial shielding on the sidewalls of the package. No other components whose primary purpose is shielding are included in the CR3MP. Gamma shielding is described and evaluated in Chapter 5.0, Shielding Evaluation and are shown to be adequate.

As stated in Chapter 6.0, Criticality Evaluation, the CR3MP transports fissile exempt material.

Therefore, no moderation or neutron absorption is necessary to control criticality.

In addition, a detailed discussion of the materials acceptance tests and weld examinations, along with a description of the maintenance program is covered in Chapter 8.0, Acceptance Tests and Maintenance Program.

The CR3MP is of conventional design and is not complex to operate. Operational features are depicted on the drawing provided in Appendix 1.3.2, Packaging General Arrangement Drawings. The package is oriented with the cylindrical axis of the package in a vertical orientation during transport. A complete description of the operating controls and procedures for the CR3MP is covered in Chapter 7.0, Package Operations. The operational procedures, acceptance tests and maintenance program adequately comply with 10 CFR Part 71 requirements. Finally, the CR3MP will be fabricated and assembled in accordance with an NRC approved Part 71 Quality Assurance (QA) program.

1.2.1.1 Containment Vessel The CR3MPs containment feature is the containers steel body itself consisting of the shell, both top and bottom covers and the circumferential closure joint welds for each of the covers. Due to material construction and availability considerations, the shell along with both the top and bottom covers are constructed of multiple plate sections joined with Complete Joint Penetration (CJP) welds.

1.2-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 The shell is constructed from one or more longitudinal CJP welds and one circumferential CJP weld, as necessary. Each of the top and bottom covers are constructed with up to three flat segments joined with CJP welds. Since they are located at the containment boundary, these additional welds are also part of the containment boundary. As detailed in Chapter 4.0, Containment, the CR3MP demonstrates containment compliance with 10 CFR 71 under the NCT conditions of 10 CFR 71.51(a)(1) and with HAC conditions of 10 CFR 71.51(a)(2) [1].

The packaging containment boundary is of welded construction, using American Society for Testing and Materials (ASTM) A516, Grade 70 [4] or American Society of Mechanical Engineers (ASME) SA-516, Grade 70 [5] carbon steel plate. The CR3MP packaging consists of a 3-in. thick cylindrical shell body with a nominal inner diameter of 194.3-in. and two flat heads (i.e., covers), one top and one bottom, both 6-in. thick. Each of the covers is nominally 193.8-in.

(Outside Diameter) OD.

The plate section CJP welds for the top and bottom covers and the shell longitudinal weld seams are full penetration welds classified as Category A welds per Subparagraph ND-3352.1 of the ASME Boiler and Pressure Vessel Code (BPVC) [6]. The shell circumferential weld (if required) is classified as a Category B weld in accordance with Subparagraph ND-3352.2.

In accordance with Subparagraph ND-3352.3, the closure corner joint welds for the shell to top/bottom cover interface are considered as Category C weld joints [6]. These welds are also CJP welds following the likeness of Figure ND-4243-1(j) in the BPVC.

1.2.1.2 Grout The annulus between the RPV shell and the interior body surface of the CR3MP is filled with a layer of cementitious LDCC grout. The grout fills the [ ] layer within the annulus. The grout is a low-density grout which has a nominal density of 45 pcf, with a minimum compressive strength of 100 psi at a 7 day cure time. The grout used in the CR3MP principally consists of dry cement and water, but has small percentages of other admixtures, which may include the following: CMX Foam Concentrate, Isoplast 1440, Isoxel 4400 and Fly Ash.

1.2.2 Contents 1.2.2.1 Reactor Vessel and Reactor Vessel Internals 1.2-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.2.2.2 Grout within the RPV The voids in the RPV will be filled with grout to prevent any shifting of the contents during transport. [

] The RVI components are rigidly constrained as one body within the RPV by up to three different density layers of grout, of which two layers may be HDCC and one layer is LDCC. The HDCC is nominally 135 pcf while the LDCC grout is nominally 45 pcf.

As shown in Figure 1.1-1, the possible regions of HDCC grout are:

For the upper grout, a maximum thickness of 9-in. below the upper RPV segmentation location For the lower grout, a maximum thickness of 9-in. above the lower RPV segmentation location If these upper and lower regions of RPV grout are not filled with HDCC, then they will be filled with LDCC. The remaining middle region receives the LDCC grout. The grout used in the RPV principally consists of dry cement and water, but has small percentages of other admixtures, which may include the following: CMX Foam Concentrate, Isoplast 1440, Isoxel 4400 and Fly Ash. The physical properties of the grout are detailed in Section 2.2, Materials.

1.2.2.3 Radioactive Contents Description As required by 10 CFR 71.33(b), to be authorized for transport and consistent with the above description of the RPV, RVI and grout, this section describes in greater detail the radioactive material, including radionuclides, their quantities, and as needed, mass. This is covered in greater detail in Chapter 5.0, Shielding Evaluation.

The radioactive contents are of normal form. Table 1.2-1 lists the package radionuclide activity levels. The total payload activity due to neutron activation as of June 30, 2021 is [

] input for all the components. Of note, GTCC waste is not part of the RVI authorized contents.

1.2-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Page 1.2-5 withheld pursuant to 10 CFR 2.390 1.2-5

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Summarizing, the total bounding activation activity is set to [ ]. A concentration for both fixed and loose surface contamination is conservatively determined to be an average concentration of [ ]. The bounding A2 quantity is 3,000 A2. The decay heat for the thermal analysis is set conservatively at 500 watts. For radiolytic gas generation, the decay heat, based on a shipment date of March 31, 2023 is 358.1 watts.

Table 1.2 CR3MP Contents Radionuclide Activity Levels 1.2-6

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.3 Appendices Appendix 1.3.1 ..................................................................................................... References Appendix 1.3.2 ..................................................Packaging General Arrangement Drawings 1.3-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.3.1 References

1. Title 10 - Energy, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

2. U.S. Nuclear Regulatory Commission, Regulatory Guide 7.9, Revision 2, Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material, March 2005, NRC Accession Number ML050540321.

3. Title 10 - Energy, Code of Federal Regulations, Part 61 (10 CFR 61), Licensing Requirements for Land Disposal of Radioactive Waste, 01-01-20 Edition.

4. ASTM A516 - 2017, Standard Specification for Pressure Vessel Plates, Carbon Steel, for Moderate- and Lower-Temperature Service, ASTM International, November 2017.

5. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Materials, Part A, Ferrous Material Specifications (SA-451 to End), SA516/SA-516M, Specification for Pressure Vessel Plates, Carbon Steel, for Moderate- and Lower-Temperature Service, 2017 Edition.

6. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, Division 1 - Subsection ND, Class 3 Components, 2017 Edition.

7. Title 49 - Transportation, Code of Federal Regulations, Subtitle B - Other Regulations Relating to Transportation (Continued) (Parts 100 - 1699); Chapter I - Pipeline and Hazardous Materials Safety Administration, Department of Transportation (Parts 100 - 199),

Subchapter C - Hazardous Materials Regulations, 10-01-2019 Edition.

8. U.S. Nuclear Regulatory Commission, Regulatory Guide 7.12, Revision 0, Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m),

June 1991, NRC Accession Number ML003739424.

9. U.S. Nuclear Regulatory Commission, NUREG/CR-3826, UCRL-53538, Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Greater Than Four Inches Thick, July 1984, NRC Accession Number ML20093N045.

10. U.S. Nuclear Regulatory Commission, NUREG/CR-6491, UCRL-ID-124583, Recommendations for Protecting Against Failure by Brittle Fracture, August 1996, NRC Accession Number ML20117F196.

11. U.S. Nuclear Regulatory Commission, Final Waste Classification and Waste Form Technical Position Papers, May 1983, NRC Accession Number ML103420507.

1.3-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.3.2 Packaging General Arrangement Drawings The packaging general arrangement SAR drawing is as follows (see attached):

3024427, CR3MP Assembly SAR Drawing, 2 sheets 1.3-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.3-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 1.3-5

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.0 STRUCTURAL EVALUATION This section presents evaluations demonstrating that the CR3MP meets all applicable structural criteria of 10 CFR 71 [1], or else provides equivalent safety per the provisions of 10 CFR 71.41(d). The CR3MP is evaluated by analysis. Demonstration techniques comply with the methodology presented in NRC Regulatory Guides 7.6 [2] and 7.8 [3]

2.1 Structural Design 2.1.1 Discussion As shown in the SAR drawing in Appendix 1.3.2, Packaging General Arrangement Drawings, the CR3MP is a thick-walled steel shell that encloses the middle portion of the CR3 RPV. The CR3MP and the RPV payload are described in detail in Sections 1.2.1, General CR3MP Description, and 1.2.2, Contents, respectively.

The CR3MP packaging consists of a cylindrical 3-in. thick steel shell, and 6-in. thick top and bottom cover plates. These components and their welds make up the containment boundary.

The material of construction of the packaging base metal is ASTM A516 Grade 70 [4] or optionally ASME SA516 Grade 70 [5]. The cylindrical shell and each cover may have multiple full penetration welds connecting constituent plates. The cover plates are attached to the shell with full penetration closure welds. The top cover plate closure weld is a field weld, performed after placement of the payload into the packaging. The package is fully welded closed and has no closures, seals, or vent ports. The package is 200.3-in. in diameter and 178.1-in. tall, and has a maximum bounding weight of 860,000 pounds. A cross section of the package and payload is depicted in Figure 2.1-1.

The payload consists of the middle portion of the CR3 RPV. In addition, RVI components, immobilized in grout, are included in the RPV cavity. The RPV payload will rest on the bottom of the package, leaving an approximately three inch thick annulus around the sides and an approximately three inch thick space over the top of the payload. The annulus is filled with low density grout, leaving a nominal air space of 3 inches at the top of the payload.

The CR3MP design does not include any impact limiters or any other features that are specifically designed to absorb free drop energy. The package is designed to be resistant to fracture at the LST and provides containment of radioactive material under NCT and HAC.

The package will be transported in exclusive use by barge and by road between the CR3 site and the WCS disposal site.

2.1.2 Design Criteria The acceptance criteria for analytic assessments are in accordance with NRC Regulatory Guide 7.6. These design criteria meet the following safety requirements of 10 CFR 71.51:

For NCT, there shall be no loss or dispersal of radioactive contents, as demonstrated to a sensitivity of 10-6 A2 per hour, no significant increase in external radiation levels, and no substantial reduction in the effectiveness of the packaging.

2.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 For HAC, there shall be no escape of krypton-85 exceeding 10 A2 in 1 week, no escape of other radioactive material exceeding a total amount of one A2 in one week, and no external radiation dose rate exceeding one rem per hour at 40 inches from the external surface of the package.

The CR3MP contains a bounding value of [ ] of activity. [

] Accordingly, the CR3MP design will follow the guidance of Subsection ND. A summary of allowable stresses used for the containment (outer cylindrical shell and top and bottom closure plates) is presented in Table 2.1-1. The allowable stresses shown in the table are consistent with NRC Regulatory Guide 7.6.

For the NCT free drop event and the HAC free drop and puncture events, the containment shell materials are allowed to deform plastically. Material properties for non-linear analyses are developed in Appendix 2.12.2, Free Drop Evaluation.

The packaging has no lifting provisions available for use in the transport configuration. Thus, 10 CFR 71.45(a) does not apply to the CR3MP. In addition, since the CR3MP is not attached to the conveyance using any structural part of the package, tiedown structural criteria are not required.

2.1.2.1 Miscellaneous Structural Failure Modes 2.1.2.1.1 Brittle Fracture All structural materials of the CR3MP are made from ASTM/ASME A516/SA516, Grade 70 alloy steel [4] [5]. This is a fine grain steel designed for low temperature service. The recommendations of NRC NUREG/CR-6491 [11] for a Category II package are used to establish the LST of the base material, equivalent to the minimum transportation ambient temperature, for transport of the CR3MP.

Entering Figure 1 of NUREG/CR-6491 [11] with a thickness of six inches (equal to the maximum thickness of material in the package), and following that down to the = 0.6 curve, the resulting value of KID/yd is 1.9 in1/2. The room temperature yield strength of ASTM A516, Grade 70 is 38 ksi. Following down to the ordinate from ys = 38 ksi yields an A-value of 19 °F.

(Conservatively, a value of 20 °F will be used.) The SAR drawing states that the Nil Ductility Transition (NDT) temperature of the material in the CR3MP shall be no higher than -20 °F, as determined by the drop weight test of ASTM E208 [8]. The LST of the CR3MP is therefore:

LST = TNDT + A = 20 + 20 = 0 Per the recommendation of NRC NUREG/CR-3019, Table 2 [12], the criteria for the welding material for a Category II package shall meet the requirements of ASME BPVC Subarticle ND-2400 [7].

2.1-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 The CR3MP will not commence transport, or will be stopped if in overland transport, if the ambient temperature falls below 0 °F. This will prevent a brittle fracture failure mode under NCT or HAC.

2.1.2.1.2 Fatigue Assessment Fatigue failure of the CR3MP is not of concern. The package is designed for a single use to transport the payload from CR3 in Florida to WCS, the disposal site in Texas. The design of the package is very simple, having only an outer shell and two end cover plates, welded in place.

There are no repetitively used components such as bolts, and no repetitive loading. Fatigue associated with normal vibration over the road is addressed in Section 2.6.5, Vibration.

2.1.2.1.3 Buckling Assessment The CR3MP, when loaded and closed for transport, is a very robust and stout mass, which is not subject to buckling instability. The principal part of the payload is a cylindrical cross-section of RPV steel, [ .] thick and running almost the full length of the package. The interior of the RPV is filled with grout, and the annulus between the RPV and the package is also filled with grout. The packaging body shell and covers are also made of very thick steel. As such, for the conditions specified by 10 CFR 71, buckling behavior is not of concern.

2.1.3 Weights and Centers of Gravity The maximum gross weight of the CR3MP is 860,000 lb. The CR3MP weights are summarized in Table 2.1-2. The Center of Gravity (CG) of the CR3MP is located essentially at the package geometric center.

2.1.4 Identification of Codes and Standards for Package Design As discussed in Section 2.1.2, Design Criteria, the CR3MP is classified as a Category II package, and per the guidance of NUREG/CR-3854, the appropriate design criteria for the containment isSection III, Division 1, Subsection ND of the ASME BPVC. Consequently, the design of the containment boundary is based on the methodology of NRC Regulatory Guide 7.6, and load cases are applied and combined according to NRC Regulatory Guide 7.8.

Table 2.1 Packaging Allowable Stress Limits Stress Category NCT HAC General Primary Membrane Stress Intensity Lesser of: 2.4Sm Sm 0.7Su Primary Membrane + Bending Stress Intensity Lesser of: 3.6Sm 1.5Sm Su Range of Primary + Secondary Stress Intensity 3.0Sm N/A Pure Shear Stress 0.6Sm 0.42Su 2.1-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Table 2.1 CR3MP Component Weights Figure 2.1 CR3MP Cross Section 2.1-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.2 Materials The CR3MP consists of ASTM/ASME A516/SA516 Grade 70 steel shell and covers, with the shell nominally 3-in. thick and the covers nominally 6-in. thick. The void space within the RPV segment surrounding the RVI and the annulus between the RPV and the package wall is filled with grout. The package as assembled for transport is depicted in Figure 2.1-1. There are no bolts or other structural components used in the CR3MP and no seals as well. Nonstructural elements of the CR3MP include the following plain carbon steel components: top cover backing bar, top cover set screw plugs, and remnants of empty packaging lift lugs on the inside of the shell.

2.2.1 Material Properties and Specifications Table 2.2-1 presents the material properties for the ASTM/ASME A516/SA516 Grade 70 material. Of note, for purposes of this SAR, the material properties of ASTM A516, Grade 70 are considered identical to those of ASME SA516, Grade 70. As necessary and as noted in Table 2.2-1, material data is interpolated or extrapolated from the tabulated dataset. The density of steel used is 0.280 lb/in3.

The interior of the RPV is filled with grout, filling the void space and immobilizing the RVI components within. A LDCC grout having a density range of 30 - 60 pcf is used. As an option, HDCC grout (130 - 140 pcf) with a thickness of up to 9 inches at the top and at the bottom of the RPV may fill that portion of the interior volume. Outside of the RPV, in the nominal [ ]

wide annulus between the RPV and the interior of the package, LDCC is used. The nominal 3-in. wide space above the RPV and below the top cover is filled with air.

The LDCC and HDCC consist of Portland cement per ASTM C150 [13]. The LDCC is mixed with foaming agents per ASTM C869 [14], and follows the guidance of American Concrete Institute (ACI) 523.1R [15]. The thermal expansion coefficient for the grout material is similar to that of steel (i.e., ranging between approximately 5 - 7 x 10-6 in/in/°F) per [15] and ACI 523.3R-14 [16]. In the free drop evaluations under NCT and HAC, a crush strength of 100 psi is conservatively assumed for both densities of grout material.

Material properties for non-linear analyses are developed in Appendix 2.12.2, Free Drop Evaluation.

2.2.2 Chemical, Galvanic, or Other Reactions The CR3MP steel and concrete materials of construction will not have significant chemical, galvanic or other reactions, neither internally or externally. The integral contact between carbon steel and concrete is a common practice in structures designed to last many years (e.g.,

reinforcement rods in concrete structures). The outside (top and sides) of the package is painted.

The marine leg of the transport from the CR3 site to the WCS disposal site will be of relatively brief duration, and the package is designed for a single trip. No deleterious corrosion is expected from the brief sea voyage. Therefore, the CR3MP will not be compromised by any chemical, galvanic, or other reactions.

2.2-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.2.3 Effects of Radiation on Materials The radiation associated with the RPV and its RVI contents is essentially all gamma radiation, and will have no effect on the material properties of the containment boundary steel or on the integrity of the grout material. Some radiolysis of the moisture hydrated in the grout may occur, releasing hydrogen and oxygen gas. The accumulation of hydrogen within the package air space is further discussed in Section 4.2, Containment under Normal Conditions of Transport.

Properties related to the interaction of the grout and absorbed radiation and thus hydrogen and total gas production rates of the grout is discussed in greater detail in Section 5.4.4, Radiolytic Gas Generation.

2.2-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Table 2.2 Mechanical Properties of ASTM/ASME A516/SA516 Grade 70 Steel Yield Ultimate Design Stress Elastic Thermal Expansion Material Strength, Sy Strength, Su Intensity, Sm Modulus, E Coefficient, Specification6 Temperature (F) (psi)1 (psi)2 (psi)3 (x106 psi)4 (x10-6 /ºF)5

-100 38,000 70,000 23,300 30.3 5.8

-40 38,000 70,000 23,300 30.0 6.0

-20 38,000 70,000 23,300 29.9 6.1 ASTM A516 70 38,000 70,000 23,300 29.4 6.4 Grade 70 100 38,000 70,000 23,300 29.3 6.5 or 150 35,700 70,000 23,300 29.0 6.6 ASME SA516 200 34,800 70,000 23,200 28.8 6.7 Grade 70 300 33,600 70,000 22,400 28.3 6.9 400 32,500 70,000 21,600 27.9 7.1 500 31,000 70,000 20,600 27.3 7.3 600 29,100 70,000 19,400 26.5 7.4 700 27,200 70,000 18,100 25.5 7.6 Notes:

1

- ASME BPVC,Section II, Part D, Table Y-1. Value at -100 ºF - 70 ºF conservatively assumed using the value at 100 ºF.

2

- ASME BPVC,Section II, Part D, Table U. Value at -100 ºF - 70 ºF extrapolated using the values at 100 ºF and 150 ºF.

3

- ASME BPVC,Section II, Part D, Table 2A. Value at -100 ºF - 70 ºF extrapolated using the values at 100 ºF and 150 ºF.

4

- ASME BPVC,Section II, Part D, Table TM-1, Carbon Steels with C 0.30%. Values for -40 ºF and -20 ºF interpolated from 70 ºF and -100 ºF. Values at 100 ºF and 150 °F interpolated using the values at 70 ºF and 200 ºF.

5

- ASME BPVC,Section II, Part D, Table TE-1, Material Group 1, Mean Coefficient. Values for -100 ºF, -40 ºF and -20 ºF extrapolated from 70 ºF and 100 ºF.

6

- All ASME BPVC references from [17].

2.2-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.3 Fabrication and Examination 2.3.1 Fabrication The containment boundary material (cylindrical shell, Item No. 1 on SAR drawing, and top and bottom covers, Item No. 2) must meet the ASTM specifications delineated on the SAR drawing shown in Appendix 1.3.2, Packaging General Arrangement Drawings. Containment boundary material requirements are as follows:

Material shall meet a maximum NDT temperature of -20 °F using the drop weight test method per ASTM E208 [8].

Material carbon content shall not exceed 0.30%.

Weld metal tensile strength shall not be greater than 10% above the specified maximum tensile strength of the base metal.

Category A and B cover and shell welds (i.e., those welds joining separate sections of the shell or covers, as required) shall be full penetration joints.

Closure joint welds between the top and bottom covers and the outer shell are CJP Category C welds meeting the requirements of ASME BPVC,Section III, Subparagraph ND-4243.1, Figure ND-4243-1(j) [7].

Welding requirements are as follows:

All welding procedures and welding personnel must be qualified in accordance with Section IX of the ASME BPVC [19].

Weld Coupons of Each Heat of weld filler metal shall be Charpy V-Notch tested in accordance with ASME BPVC,Section III, Division 1, Subsection ND, Subarticle ND-2400 and Table ND-2331(A)-2 [7]. The lowest service temperature shall be 0°F.

Weld filler material and welding procedure qualifications shall be in accordance with ASME BPVC,Section III, Division 1, Subsection ND, Paragraph ND-4335 [7].

Weld procedure qualifications shall be performed using base metal having a carbon content and carbon equivalency greater than or equal to that of the actual containment component materials.

The LDCC shall have an as-cast density between 30 - 60 pcf and the HDCC shall have an as-cast density of 130 - 140 pcf. The HDCC and LDCC grout will be formulated and placed using a written procedure that uses guidance from ACI 523.1R [15].

2.3-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.3.2 Examination All welds are subject to visual examination (VT) per ASME BPVC,Section III, Division 1, Subsection ND, Paragraph ND-4123 with acceptance criteria of Paragraph ND-4424 [7]. The Category A and B cover and shell welds shall be radiograph (RT) inspected and liquid penetrant (PT) or magnetic particle (MT) inspected on the inner and outer finished surfaces in accordance with ASME BPVC, Subsection ND, Subarticle ND-5300 [7]. In lieu of the RT requirement of Subsubarticle ND-5230, and in accordance with Paragraph ND-5279, the Category C CJP closure joints (both top and bottom covers) shall receive a full volumetric inspection of the final weld joint via Ultrasonic Examination (UT). The Category C weld joining the bottom cover and the shell shall be UT inspected on the finished weld and either PT or MT inspected on the inside fillet weld and on the outer finished surface in accordance with ASME BPVC, Subsection ND, Subarticle ND-5300. The Category C weld joining the top cover and the shell shall be UT inspected on the finished weld and either PT or MT inspected on the root pass and on the outer finished surface in accordance with ASME BPVC, Subsection ND, Subarticle ND-5300.

Both LDCC and HDCC shall have a minimum compressive strength of 100 psi at 7 days, when tested using guidance from ASTM C495 [21].

2.3-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.4 General Standards for All Packages This section defines the 10 CFR 71.43 compliance standards required to be met by the CR3MP.

The CR3MP meets all requirements delineated in this section.

2.4.1 Minimum Package Size In accordance with 10 CFR 71.43(a), the overall dimensions of the CR3MP must be greater than 4 inches. The minimum dimension of the CR3MP is approximately 178 inches. Thus, the 4-in.

minimum requirement of 71.43(a) is satisfied.

2.4.2 Tamper-Indicating Feature In accordance with 10 CFR 71.43(b), as configured for transport, the CR3MP is sealed and would not be readily breakable by unauthorized persons. The CR3MP is welded closed using a minimum 3.75-in. thick weld. Entry into the package cannot occur without destructively breaching this weld. Thus, the requirement of 71.43(b) is satisfied.

2.4.3 Positive Closure In accordance with 10 CFR 71.43(c), the package body and covers are the containment boundary and are joined at the interface seams by large full penetration welded joints. As such, the package cannot be opened unintentionally or by a pressure rise within the package. Thus, the requirements of 71.43(c) are satisfied.

2.4.4 Materials The CR3MP meets the requirements of 10 CFR 71.43(d) as discussed in Section 2.2, Materials.

2.4.5 Valves In accordance with 10 CFR 71.43(e), there are no valves, receptacles, testing, venting or sampling ports used in the CR3MP containment boundary. Therefore, no such component needs protection and the requirements of 71.43(e) are satisfied.

2.4.6 Package Design and NCT Conditions In accordance with 10 CFR 71.43(f), the CR3MP is designed to comply with NCT while preventing loss or dispersal of radioactive contents, not significantly increasing the external surface radiation level and not substantially reducing the effectiveness of the packaging. This is shown in Chapter 2.0, Structural Evaluation, Chapter 3.0, Thermal Evaluation, and Chapter 5.0, Shielding Evaluation, for the structural, thermal, and shielding requirements, respectively.

Therefore, the requirements of 71.43(f) are satisfied for the CR3MP.

2.4-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.4.7 External Temperatures In accordance with 10 CFR 71.43(g), the CR3MP is designed such that while exposed to a temperature of 100°F in the shade, that no accessible surface of the package will exceed 185°F when shipped as an exclusive use shipment. Since the CR3MP is a single-use package, there will only be a one-time, exclusive use shipment of the CR3MP. As shown in Table 3.1-1 from Section 3.1.3, Summary Tables of Temperatures, the maximum accessible surface temperature with no insolation is bounded by 85 °C, or 185 °F. This satisfies the limit of 71.43(g) for exclusive use shipments.

2.4.8 Venting In accordance with 10 CFR 71.43(h), there is no pressure relief (i.e., venting) system features in the CR3MP, therefore no continuous venting is intended to occur. Thus, the requirements of 71.43(h) are satisfied.

2.4-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.5 Lifting and Tie-down Standards for All Packages 2.5.1 Lifting Devices The CR3MP does not include any devices that are a structural part of the package that are present in the transport configuration. In addition, as indicated in Section 7.1.2, Loading of Contents, the threaded holes for lifting the top cover will be plugged in order to prevent any inadvertent lifting. Thus, 10 CFR 71.45(a) does not apply.

2.5.2 Tie-down Devices As covered in Chapter 7.0, Package Operations during transport, the CR3MP [ ]

and is held down by means of passive, indirect tiedowns (e.g., tiedown frame) which rest on top of the package. [

] In addition, as indicated in Section 7.1.2, Loading of Contents, the threaded holes for lifting the top cover will be plugged in order to render those holes inoperable for tiedown of the package during transport.

Therefore, the CR3MP has no integral tie-down devices which are a structural part of the package. As a result, per 10 CFR 71.45(b)(1), the evaluation of tie-down devices is not required.

2.5-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.6 Normal Conditions of Transport As specified in 10 CFR 71.71 [1], the CR3MP meets the performance criteria specified in Subpart E of 10 CFR 71. This is demonstrated in the following subsections where each NCT condition is addressed and shown to meet the applicable design criteria. Load combinations used in this section are consistent with NRC Regulatory Guide 7.8 [3].

2.6.1 Heat The NCT heat condition, as defined in 10 CFR 71.71(c)(1), is evaluated in Chapter 3.0, Thermal Evaluation. The bounding temperatures and pressures for use in structural analyses are summarized in the following subsections. Material properties and stress limits are taken from the design criteria shown in Table 2.1-1.

2.6.1.1 Summary of Pressures and Temperatures The CR3MP containment components are bounded by a temperature of 50 °C or 122 °F in the 100 ºF ambient NCT condition, as presented in Table 3.1-1 of Chapter 3.0, Thermal Evaluation.

Conservatively, a temperature of 150 °F will be used for NCT structural evaluations.

The initial pressure in the package at the time of welding shut the top cover is at Standard Temperature and Pressure (STP) conditions, (i.e., 14.7 psia). Pressure is generated in the package due to the release of moisture from the RPV internal grout as a result of decay heat. As determined in Section 3.3.2, Maximum Normal Operating Pressure, the MNOP is set at a value of 5 psig. The design pressure of the CR3MP is set at 25 psig.

2.6.1.2 Differential Thermal Expansion As shown in Section 2.2, Materials, grout has a thermal expansion coefficient which is similar to that of carbon steel. The volume of grout that is significantly warmer than the steel packaging containment shell is limited to a small region at the central interior of the RPV. The expansion of this region will be absorbed by the cooler material outside of it, and will not increase the stress of the packaging shell by expansion. The outer grout material near the shell body has essentially the same temperature and thermal expansion coefficient as the shell. Thus, differential thermal expansion is not of concern.

2.6.1.3 Stress Calculations 2.6.1.3.1 Stresses Due to Pressure Loading The containment boundary will be evaluated for the internal pressure condition by combining the MNOP with the reduced external pressure condition of 3.5 psia per 10 CFR 71.71(c)(3). MNOP is 5 psig or 19.7 psia. For an external pressure of 3.5 psia, the differential pressure to be used in the following calculations is 19.7 - 3.5 = 16.2 psi. However, a conservative value of 26.2 psi will be used. This pressure is governing compared to the differential pressure formed using the internal design pressure of 25 psig.

2.6-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Given that the CR3MP is a simple cylindrical shell with flat ends, the membrane stress in the cylindrical walls is:

= = 848 Where:

q = 26.2 psi r = 97.15 inches, radius of closure, equal to half the Inside Diameter (ID) (or 194.3/2) t = 3 inches, thickness of shell wall The top and bottom covers are identical 6.0-in. thick plates. As shown in the SAR drawing, each cover tapers to a thickness of 3.75 inches for a radial distance of 5.75 inches at the outer edge.

From Table 24, Case 10b of Roark [22], the bending stress at the center of the closure plate, assuming fixed edge support at the junction to the shell is:

2 (1 + )

6 6[ ]

16

= = = 3,349 2 2 Where:

= 0.3, Poissons ratio t = 6 inches, thickness of the cover plates From Table 24, Case 10b of [22], the stress at the outside edge of the cover (the weld), assuming a fixed edge, is:

2 6 6[ ]

8

= = = 13,188 2 2 Where:

t = 3.75 inches, thickness of the cover plate welds.

2.6.1.3.2 Comparison with Allowable Stresses From Table 2.1-1, at the bounding temperature of 150 ºF, the value of Sm for the package material is 23,300 psi.

The stress in the side wall, a, is a membrane stress, Pm. From Table 2.1-1, the limit on membrane stress is Sm. The MS is:

23,300 1 = 1 = +

848 The bending stress in the closure plates is calculated above to be b = 3,349 psi, and is classified as membrane plus bending, or Pm + Pb. From Table 2.1-1, the limit on Pm + Pb is 1.5Sm, or 1.5 x 23,300 = 34,950 psi. The MS is:

34,950 2 = 1 = +9.4 3,349 2.6-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 The bending stress in the closure plate welds is calculated above to be c = 13,188 psi and is again classified as membrane plus bending, where the stress limit is 34,950 psi. The MS is:

34,950 1 = 1 = +1.65 13,188 Thus, the NCT warm condition is of no concern.

2.6.2 Cold For the cold condition of 10 CFR 71.71(c)(2), a -40 ºF steady state ambient temperature is used per NRC Regulatory Guide 7.8, with zero insolation and zero decay heat. This results in a uniform temperature of -40 ºF throughout the package. Since the steel containment shell and the grout have a similar coefficient of thermal expansion and the temperature of the materials is essentially the same, thus, no interference load will occur. Brittle fracture of the containment boundary is also of no concern because the CR3MP will be transported at a temperature above the LST, which has been set at 0 °F, as discussed in Section 2.1.2.1.1, Brittle Fracture.

2.6.3 Reduced External Pressure The effect of reduced external pressure of 3.5 psia, per 10 CFR 71.71(c)(3), has been considered in the NCT structural analysis presented in Section 2.6.1, Heat. Based on the MNOP of 5 psig, the reduced external pressure condition would cause a pressure differential of 16.2 psi.

However, conservatively using a pressure value of 26.2 psi, a bounding pressure stress was calculated. Given this pressure load, the worst case bending stress in the closure plate welds show a positive margin. Therefore, the reduced external pressure case of 71.71(c)(3) is of no concern.

2.6.4 Increased External Pressure The effect of an increased external pressure of 20 psia, per 10 CFR 71.71(c)(4), is acceptable for the CR3MP. Consistent with NRC Regulatory Guide 7.8, this loading corresponds to a minimum ambient temperature of -20 ºF, with no insolation, no decay heat, and minimum internal pressure.

With the CR3MP closed under ambient conditions, the internal pressure at a temperature of -20 ºF is:

(20 + 460)

= = 12.2 (70 + 460)

Where pamb is 14.7 psia. Therefore, the differential gas pressure from outside the shell side is pds = (20 - 12.2) = 7.8 psi. Since the package is filled with grout which has crush strength much greater than this pressure, the external pressure can be resisted by the grout alone without assistance from the steel shell. The top cover is not supported by grout. However, it has been evaluated for the much greater differential pressure of 26.2 psi in Section 2.6.1.3.1, Stresses Due to Pressure Loading. Thus, the increased external pressure load case of 71.71(c)(4) is of no concern.

2.6-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.6.5 Vibration Per 10 CFR 71.71(c)(5), the vibration normally incident to transport will not have a deleterious effect on the CR3MP packaging or its contents. The massive components of the package have natural frequencies which are unlikely to receive any consequential amount of energy from transport vibration. The package is also filled with grout material which serves as a damping component. In addition, the overall number of loading cycles the CR3MP experiences is minor over a single use shipment. Therefore, fatigue of the CR3MP due to transportation vibration would not adversely affect compliance with the 10 CFR 71.51(a)(1) NCT requirements.

2.6.6 Water Spray The material of construction (steel) used in the CR3MP is not affected by the water spray test identified in 10 CFR 71.71(c)(6).

2.6.7 Free Drop 10 CFR 71.71(c)(7) specifies a free drop from a height of one foot for a package weight more than 33,100 lb. The governing orientations of flat end, side, and CG over corner are evaluated for the NCT free drop event. Details of the free drop analysis are provided in Appendix 2.12.2, Free Drop Evaluation. The results are summarized below.

The evaluation was performed using LS-DYNA software. Because the key structural parameter is the strain in the containment boundary material, and deformation and strain is maximized at warm temperatures, all drop simulations use the warm NCT temperature of 150 °F. Nonlinear material behavior was included through use of a piecewise linear stress-strain curve which was developed using the method outlined in Annex 3-D of ASME BPVC Section VIII, Division 2

[20]. The structural response of the CR3MP to the one foot free drop impact was evaluated using a limiting triaxial strain criteria, developed using the method of Paragraph 5.3.3 of [20].

The resulting limiting strain is 22% as discussed in Appendix Section 2.12.2.2.2, Acceptance Criteria. The elements representing the weld between the side shell and the top and bottom covers were set to erode (i.e., be removed from the model analysis) when the effective plastic strain reached 22% in an element. In this way, not only the plastic response, but the potential failure of the containment welds could be identified. A design pressure of 25 psi is applied to the internal surfaces of the package. The impact surface was unyielding.

2.6.7.1 NCT End Drop The package end drop case was modeled with the top end facing down, since in that orientation, there is a 3-inch air gap between the RPV top surface and the top cover. Filtered at 1,000 Hz, as shown in Table 2.12.2-6, the maximum impact of the package is 94 g. The maximum strain is 3.3%. Plots of strain and time histories of impact are provided in Appendix Section 2.12.2.5, NCT End Drop.

2.6-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.6.7.2 NCT Side Drop The package side drop case was modeled with the shell cylindrical axis parallel to the ground, causing the radial edge of the shell to horizontally impact the drop pad. As shown in Table 2.12.2-6, the maximum impact is 21 g. The maximum strain is 10.2%, which as shown in Figure 2.12.2-9, occurs in two localized regions at the inside and the outside of the closure plate weld. Plots of strain and time histories of impact are provided in Appendix Section 2.12.2.6, NCT Side Drop.

2.6.7.3 NCT CG over Corner Drop The package CG over corner drop case was modeled with the top end of the package down and the shell cylindrical axis inclined at an angle of 47.8° from the horizontal surface of the drop pad.

As shown in Table 2.12.2-6, the maximum impact is 8.1 g. As shown in Figure 2.12.2-11, approximately 1/4 of the closure weld elements at the outside edge of the weld in a region close to the impact point exceed the strain limit of 22%. The distorted shape plot in Figure 2.12.2-13 indicates that the forces on the weld are primarily compressive, since the gap formed by the removal of the higher-strain weld elements has closed. The effective plastic strain in the remaining 3/4 of the weld is below the strain limit, and the weld retains its integrity as a barrier to the release of radioactivity. Plots of strain and time histories of impact are provided in Appendix Section 2.12.2.7, NCT Corner Drop.

In summary, when subjected to a 1 ft free drop onto an unyielding surface, the containment boundary of the CR3MP remains intact.

2.6.8 Corner Drop The CR3MP is not required to be evaluated for the 10 CFR 71.71(c)(8) corner drop condition, since it applies only to fiberboard, wood or fissile material packages of varying configurations.

The material of construction of the CR3MP is steel and it is not a fissile package, therefore the CR3MP does not need to be evaluated for the NCT corner drop.

2.6.9 Compression 10 CFR 71.71(c)(9) specifies that for packages weighing up to 11,000 lb, a 24-hour compressive load be applied with the load being the larger load of either 5 times the package weight or the equivalent of 2 psi projected over the package area. The CR3MP weight exceeds the 11,000 lb limit, and therefore does not need to be evaluated for compression.

2.6.10 Penetration In accordance with 10 CFR 71.71 (c)(10), the impact of a 1.25-in. diameter, hemispherical ended, 13-lb steel bar dropped vertically from a height of 40 inches would not have any deleterious effect on the safety features of the CR3MP. Dropping vertically, the bar would impact the 6-in. thick top closure plate or the 3.75-in. thick closure weld. The bar would possess an impact energy of only 520 in-lb and could not damage the package in any way. Therefore, consequential damage from the steel bar penetration test is of no concern.

2.6-5

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.7 Hypothetical Accident Conditions When subjected to the HAC as specified in 10 CFR 71.73, the CR3MP meets the performance requirements specified in Subpart E of 10 CFR 71. This is demonstrated in the following subsections, where each accident condition is addressed and the package shown to meet the applicable design criteria. The method of demonstration is by analysis. The loads specified in 10 CFR 71.73 are applied sequentially, per Regulatory Guide 7.8. Resulting stresses are maintained below the limits established by Regulatory Guide 7.6 or other limits on strain as established in the analysis sections herein. A summary of cumulative damage is provided in Section 2.7.8, Summary of Damage. The primary acceptance criteria for all HAC events is a release of no more than one A2 of activity in one week, as established in Section 2.1.2, Design Criteria.

2.7.1 Free Drop Subpart F of 10 CFR 71 requires that a 30 ft free drop be considered. The free drop is to occur onto a flat, essentially unyielding, horizontal surface, and the CR3MP is to strike the surface in an orientation for which maximum damage is reasonably expected. Three representative worst-case orientations are chosen: on the end, the side, and CG over corner. Because the package diameter and height do not differ significantly (diameter of 200.3-in. and height of 178.1-in.),

secondary impacts such as slapdown are not considered. In order to include the damage which would occur from a prior NCT one-foot free drop, the drop height for all HAC drops is 31 ft.

The evaluation was performed using LS-DYNA software. A design pressure of 25 psi is applied to the internal surfaces of the package. The impact surface was unyielding. Details of the free drop analysis are provided in Appendix 2.12.2, Free Drop Evaluation.

2.7.1.1 Material Properties Used in Free Drop Analysis Because the key structural parameter is the strain in the containment boundary material, and deformation and strain is maximized at warm temperatures, all drop simulations use the warm NCT temperature of 150 °F. Nonlinear material behavior was included through use of a piecewise linear stress-strain curve which was developed using the method outlined in Annex 3-D of ASME BPVC Section VIII, Division 2 [20]. Detailed development of the stress-strain curve is provided in Appendix Section 2.12.2.4, Model, and the resulting curve in Figure 2.12.2-2. The structural response to the HAC free drop impact was evaluated using a limiting triaxial strain criteria, developed using the method of Paragraph 5.3.3 of [20]. The resulting limiting strain is 22% as discussed in Appendix Section 2.12.2.2.2, Acceptance Criteria. The elements representing the weld between the side shell and the end cover plates were set to erode (i.e., be removed from the model analysis automatically by the software) when the effective plastic strain reached 22% in an element. In this way, not only the plastic response, but the potential failure of the containment welds could be identified.

2.7-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.7.1.2 HAC End Drop The package end drop case was modeled with the top end facing down, since in that orientation, there is a 3-inch air gap between the RPV top surface and the top cover. Filtered at 1,000 Hz, as shown in Table 2.12.2-7, the maximum impact of the package is 384 g. The maximum strain is 9.7%. Plots of strain and time histories of impact are provided in Appendix Section 2.12.2.8, HAC End Drop.

2.7.1.3 HAC Side Drop The package side drop case was modeled with the shell cylindrical axis parallel to the ground, causing the radial edge of the shell to horizontally impact the drop pad. As shown in Table 2.12.2-7, the maximum impact is 81 g. At the center of the impact zone, the strain across the full width of the closure weld at both ends of the package exceeds the 22% strain limit. As shown in Figure 2.12.2-22 and Figure 2.12.2-23, a number of elements were consequently removed from the model. The failed area represents an opening which may allow some of the contents of the package to escape. Both the HAC side drop and the HAC CG over corner drop experience a degree of weld failure. To determine the bounding case, relevant data from Table 2.12.2-5 will be collected from each free drop analysis as follows:

HAC Side Drop The aggregate length of failed weld, including both ends and full symmetry, is 117 inches.

The maximum opening of the joint as measured from the model is 0.29 inches.

The time between initial impact and secondary impact is 0.65 seconds.

Plots of strain and time histories of impact are provided in Appendix 2.12.2.9, HAC Side Drop.

2.7.1.4 HAC CG over Corner Drop The package CG over corner drop case was modeled with the top end of the package down and the shell cylindrical axis inclined at an angle of 47.8° from the horizontal surface of the drop pad.

As shown in Table 2.12.2-7, the maximum impact is 45 g. At the center of the impact zone, the strain across the full width of the closure weld exceeds the 22% strain limit. As shown in Figure 2.12.2-28, a number of elements were consequently removed from the model. The failed area represents an opening for some of the contents of the package to escape. Relevant data collected from Table 2.12.2-5 for the CG over corner drop case include:

HAC CG over Corner Drop The total length of failed weld, including full symmetry, is 146 inches.

The maximum opening of the joint as measured from the model is 0.87 inches.

The time between initial rebound and secondary impact is 0.68 seconds.

Plots of strain and time histories of impact are provided in Appendix Section 2.12.2.10, HAC Corner Drop. By comparison with the side drop, the CG over corner drop case is bounding, and the parameters of this case are used in the calculation described in Section 4.3, Containment under Hypothetical Accident Conditions.

2.7-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.7.2 Crush The 10 CFR 71.73(c)(2) crush test is required only when the package has a mass under 1,100 lb.

Since the weight of the CR3MP exceeds 1,100 lb, the crush test specified in 71.73(c)(2) does not apply.

2.7.3 Puncture The CR3MP is evaluated for puncture resistance under HAC as defined in 10 CFR 71.73(c)(3).

The puncture event is defined as a free drop from a height of 40 inches onto a vertical, cylindrical mild steel bar, 6 inches in diameter, in an orientation and in a location for which maximum damage is expected. Puncture performance of the CR3MP is evaluated on two surfaces: puncture on the flat ends, and puncture on the cylindrical side shell.

2.7.3.1 Puncture on the Ends The puncture resistance of the end covers of the CR3MP, both of which have the same material and thickness, is evaluated using Nelms Equation [23]. From Table 2.2-1, for the NCT warm case bounding temperature of 150 ºF, the ultimate strength of the package steel material (Su) is 70,000 psi. The bounding weight of the CR3MP (W) is 860,000 lb. The required thickness (t) to resist puncture then becomes:

0.71

=( ) = 5.94 The thickness of the closure plate is 6.0 inches. The MS on the package closure plate thickness is:

6.00

= 1 = +0.01 5.94 Of note, this calculation conservatively neglects the load limit of a mild steel puncture bar.

Assuming a bar made of ASTM A36 material, with properties as provided in Appendix Section 2.12.2.1.2, Materials, having a yield strength at room temperature of 36 ksi, and a tensile strength of 58 ksi, the flow stress of the puncture bar is the average of yield and tensile strengths, or 47 ksi. Since the bar has a 6-in. OD and has an area of 28.3 in2, the maximum load that could be sustained by the bar is based on the flow stress of the bar material and is equal to 28.3 x 47,000 = 1.33 x 106 lb. The minimum load to shear a 6-in. diameter hole through a 6-in.

thick cover plate (F), conservatively assuming a shear length of only 50% of the thickness, or 3 inches, is:

= 6 x x 3 x 0.6 x 70,000 = 2.38 x 106 In this equation, the ultimate shear strength of the plate is considered to be 0.6 times the tensile strength of 70 ksi for the ASTM A516 Grade 70 steel [4]. Thus, the maximum load which can be sustained by the mild steel puncture bar, 1.33 x 106 lb, is only about 56% of the load needed to fully shear through the 6-in. closure plate of 2.38 x 106 lb, implying that the bar would fail in compression before the plate sheared through. Therefore, the MS is considerably larger than

+0.01, and puncture of the CR3MP top and bottom cover plates is of no concern.

2.7-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.7.3.2 Puncture on the Package Body Shell From the foregoing, it is evident that the 3-in. thick body shell may experience perforation from the puncture bar, both from the perspective of Nelms equation and from the fact that the maximum puncture bar load of 1.33 x 106 lb is greater than the load to fully shear a 3-in. thick section of ASTM A516 Grade 70 steel (again assuming 50% shear, or 1.5 inches), equal to half of 2.38 x 106 lb, or 1.19 x 106 lb. Thus, it may be reasonably assumed that a puncture drop on the cylindrical side shell could result in the configuration shown in Figure 2.7-1. Conservatively, intervening grout material between the shell and the RPV will be neglected.

The consequences of a puncture impact on the side shell of the CR3MP will be inconsequential due to the resistance to puncture from the thick RPV wall, which is located just behind the packaging shell. The RPV wall (t) is [ ] thick with an OD of [ .] Table 30, Case 7a of Roark [22] provides a formula for the deflection under a concentrated load on a circular shell. [

] The deflection under the load (d)

(i.e., the local radial deformation of the RPV shell) due to the puncture bar load then becomes:

3/2 3/4

= 6.5 ( ) ( ) = 0.70 Where:

P = 1.33 x 106 lb, the maximum sustainable load of the puncture bar E = 29.0 x 106 psi, the modulus of elasticity for carbon steel (taken from Table 2.2-1 at 150 °F) t=[ ] the RPV wall thickness R and L are defined above.

Thus, the distance (G) shown in Figure 2.7-1 is 0.70 inches. This is a very conservative value since it neglects any inward deformation of the package shell that will occur due to puncture bar loading and any thickness of grout compressed between the side shell and the RPV. The same formula as used above could be applied to the package shell, resulting in a significant local dent in the package shell that would reduce the magnitude of G and possibly allow the package shell to be supported by the RPV and prevent complete perforation of the shell. However, the actual deformation of the package shell prior to its perforation is difficult to evaluate due to the resistance of the grout, and this effect is conservatively neglected, as depicted in Figure 2.7-1.

The upper-bound width of the opening into the package, (G), is just under 3/4-in., and very little grout could escape through such an opening. In addition, the grout in the side annulus is poured in place after the placement of the grouted RPV, and therefore is not contaminated.

Consequently, no activity from within the package would be released in such a puncture event.

If the puncture bar were applied to the free drop damage resulting from the CG over corner impact evaluated in Section 2.7.1.4, HAC CG over Corner Drop, it could penetrate the damaged area where contaminated grout may be present. However, as calculated in Section 4.3, Containment under Hypothetical Accident Conditions, the open area due to the weld damage is conservatively bounded by 150 in2, and the added opening due to the puncture event would be unlikely to significantly exceed the area of the puncture bar itself, equal to 28.2 in2.

2.7-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 As a result, the potential additional opening due to puncture is small relative to the free drop damage opening. In addition, while the release of contaminated grout in the free drop event is conservatively calculated using the full free drop impact velocity of the package combined with a rebound time period, the puncture event has a much lower impact velocity and essentially no rebound. Consequently, any further release of contaminated grout from the puncture event on the worst case free drop damage is considered negligible. Therefore, puncture of the CR3MP is of no concern.

2.7.4 Thermal The CR3MP is designed to withstand the HAC 30 minute fire specified in 10 CFR 71.73(c)(4).

The thermal evaluation is presented in Section 3.4, Thermal Evaluation under Hypothetical Accident Conditions.

2.7.4.1 Summary of Pressures and Temperatures As shown in Table 3.5-4, the maximum internal pressure of the CR3MP as a result of the HAC fire event is bounded by a value of 18.1 psig. From Section 3.4.3, Maximum Temperatures and Pressure, the maximum temperature of the weld between the end covers and the body shell as a result of the HAC fire event is 493 °C or 920 °F.

2.7.4.2 Differential Thermal Expansion As shown in Section 2.2, Materials, grout has a thermal expansion coefficient which is similar to that of carbon steel. In the HAC fire event, the shell is hotter than the grout. The maximum temperature of the packaging from Table 3.4-1 is 579 °C (1074 °F) and from Figure 3.4-2, the maximum temperature of the annulus grout (excluding the small region of grout that could be exposed to the fire due to a free drop weld fracture) is 334 °C (633 °F). Thus, differential thermal expansion is of no concern.

2.7.4.3 Stress Calculations Pressure stress in the CR3MP was calculated in Section 2.6.1.3.1, Stresses Due to Pressure Loading. The governing stress was found to be located at the outside edge of the package cover, assuming a fixed edge condition. For an internal pressure of 5 psig (MNOP) and an external pressure of 3.5 psia, a differential pressure of 16.2 psi was formed. Using a conservative pressure of 26.2 psi, the maximum stress (c) was calculated to be 13,188 psi. Since the maximum internal pressure stated in Section 2.7.4.1, Summary of Pressures and Temperatures is lower than 26.2 psi, it is conservative to use the same stress, c-HAC = 13,188 psi for the HAC fire case.

From Table 2.1-1, for a primary membrane plus bending stress under HAC, the allowable stress is the lesser of 3.6Sm or Su. At the peak weld temperature of 920 °F provided in Section 2.7.4.1, Summary of Pressures and Temperatures, the yield stress of ASTM A516 material (Sy) is 23,700 psi by interpolation from ASME BPVC,Section II, Part D, Table Y-1 [17]. Sm is 2/3 of this value, or Sm = 15,800 psi. Thus, 3.6Sm = 56,880 psi. Again at 920 °F, Su = 49,740 psi by interpolation from ASME BPVC,Section II, Part D, Table U [17]. Thus, the lesser value of 49,740 psi is governing.

2.7-5

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 The MS then becomes:

49,740 1 = 1 = +2.77 13,188 Of note, this result is conservative because it assumes that the peak temperature of the containment occurs at the same time as the peak internal pressure, whereas these two peaks will not coincide. Thus, pressure stress is of no concern for the HAC fire event.

2.7.5 Immersion - Fissile An immersion test for fissile material packages is required by 10 CFR 71.73(c)(5). Since the CR3MP does not transport fissile materials, this requirement does not apply.

2.7.6 Immersion - All Packages An immersion test for all packages is required by 10 CFR 71.73(c)(6), in which a separate, undamaged specimen must be subjected to an equivalent pressure of 21.7 psig. Since the CR3MP is filled with grout which has a crush strength which is much greater than this pressure, the external pressure can be resisted by the grout alone without assistance from the steel shell.

Thus, the immersion load case of 71.73(c)(6) is of no concern.

2.7.7 Deep Water Immersion Test For Type B packages containing an activity of more than 105 A2, 10 CFR 71.61 requires that an undamaged containment system withstand an external water pressure of 290 psi for a period of not less than one hour without collapse, buckling, or inleakage of water. As stated in Section 1.2.2.3, Radioactive Contents Description, the bounding activity in the CR3MP is 3,000 A2.

Therefore, this requirement does not apply.

2.7.8 Summary of Damage The CR3MP is analytically subjected to the applicable sequence of HAC events from 10 CFR 71, which include free drop, puncture, and thermal. Free drop of the package is considered using three representative worst-case orientations: end, side, and CG over corner.

Computer simulation using LS-DYNA software indicates that openings into the containment boundary can occur in the side drop and CG over corner drop orientations. A conservative estimate of the size of the openings is recorded, and the containment evaluation documented in Section 4.3, Containment under Hypothetical Accident Conditions shows that the containment criterion of Section 2.1.2, Design Criteria, is met.

Puncture is evaluated using Nelms equation and shows no penetration of the top or bottom covers. Penetration of the package shell is possible. However, a manual analysis of the effect of puncture bar loading on the RPV wall shows that the RPV wall deformation will be minimal and the contaminated grout inside the RPV will not be disturbed. Thus penetration of the side shell of the package will expose only uncontaminated grout, and due to the small size of the opening, very little will be lost. Puncture of the damaged package post-CG over corner free drop is also considered, and it is concluded that such a puncture will have an inconsequential influence on the activity release calculations of Section 4.3, Containment under Hypothetical Accident Conditions.

2.7-6

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Consideration is also given to the effect of internal pressure due to the generation of water vapor from the grout in the fire event. The review assumes that no breach of the containment boundary has occurred before the regulatory fire event occurs. The resulting maximum stress is shown to be below allowable limits.

The evaluations of HAC in Section 2.7, Hypothetical Accident Conditions, along with the containment evaluation shown in Section 4.3, Containment under Hypothetical Accident Conditions, shows that the design criteria of Section 2.1.2, Design Criteria, have been met by the CR3MP.

Figure 2.7 HAC Side Wall Puncture Configuration 2.7-7

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.8 Accident Conditions for Air Transport of Plutonium This section does not apply, since plutonium is not transported in the CR3MP.

2.8-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.9 Accident Conditions for Fissile Material Packages for Air Transport This section does not apply, since fissile material is not transported in the CR3MP.

2.9-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.10 Special Form This section does not apply, since special form materials are not authorized contents of the CR3MP.

2.10-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.11 Fuel Rods This section does not apply, since fuel rods are not authorized contents of the CR3MP.

2.11-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.12 Appendices Appendix 2.12.1 ................................................................................................... References Appendix 2.12.2 .................................................................................. Free Drop Evaluation 2.12-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 2.12.1 References

1. Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

2. U. S. Nuclear Regulatory Commission, Regulatory Guide 7.6, Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels, Revision 1, March 1978.

3. U. S. Nuclear Regulatory Commission, Regulatory Guide 7.8, Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material, Revision 1, March 1989.

4. ASTM A516 - 2017, Standard Specification for Pressure Vessel Plates, Carbon Steel, for Moderate- and Lower-Temperature Service, ASTM International, November 2017.

5. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Materials, Part A, Ferrous Material Specifications (SA-451 to End), SA516/SA-516M, Specification for Pressure Vessel Plates, Carbon Steel, for Moderate- and Lower-Temperature Service, 2017 Edition.

6. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, Division 1 - Subsection NB, Class 1 Components, 2017 Edition.

7. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, Division 1 - Subsection ND, Class 3 Components, 2017 Edition.

8. ASTM E208 - 2020, Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels, ASTM International, July 2020.

9. U. S. Nuclear Regulatory Commission, Regulatory Guide 7.11, Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m), June 1991, NRC Accession Number ML003739413.

10. L. E. Fischer, W. Lai, Fabrication Criteria for Shipping Containers, NUREG/CR-3854, UCRL-53544, U.S. Nuclear Regulatory Commission, March 1985.

11. M. W. Schwartz, L. E. Fischer, Recommendations for Protecting Against Failure by Brittle Fracture/Category II and III Ferritic Steel Shipping Containers with Wall Thickness Greater than Four Inches, NUREG/CR-6491, UCRL-ID-124583, U.S. Nuclear Regulatory Commission, August 1996.

12. R. E. Monroe, H. H. Woo, and R. G. Sears, Recommended Welding Criteria for Use in the Fabrication of Shipping Containers for Radioactive Materials, NUREG/CR-3019, UCRL-53044, U.S. Nuclear Regulatory Commission, March 1984.

13. ASTM C150/C150M - 2020, Standard Specification for Portland Cement, ASTM International, April 2020.

14. ASTM C869/C869M - 2016, Standard Specification for Foaming Agents Used in Making Preformed Foam for Cellular Concrete, ASTM International, August 2016.

15. ACI 523.1R - 2006, Guide for Cast-in-Place Low-Density Cellular Concrete, American Concrete Institute, August 2006.

2.12-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022

16. ACI 523.3R - 2014, Guide for Cellular Concretes above 50 lb/ft3 (800 kg/m3), American Concrete Institute, April 2014.

17. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Materials, Part D, Properties, 2017 Edition.

18. ASTM A36 - 2019, Standard Specification for Carbon Structural Steel, ASTM International, July 2019.

19. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section IX, Qualification Standard for Welding and Brazing Procedures, Welders, Brazers, and Welding and Brazing Operators, Latest Edition.

20. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section VIII, Rules for Construction of Pressure Vessels, Division 2, Alternate Rules, 2017 Edition.

21. ASTM C495/C495M - 2019, Standard Test Method for Compressive Strength of Lightweight Insulating Concrete, ASTM International, December 2019.

22. Roark's Formulas for Stress and Strain, Sixth Edition, McGraw-Hill, New York, 1989.

23. A. Nelms, Structural Analysis of Shipping Casks, Effect of Jacket Physical Properties and Curvature on Puncture Resistance, ORNL-TM-1312, Vol. 3, Oak Ridge National Laboratory, 1968.

24. Title 10, Code of Federal Regulations, Part 72 (10 CFR 72), Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste, 01-01-20 Edition.

25. Livermore Software Technology Corporation, LS-DYNA Keyword Users Manual/Volume II/Material Models, Version R7.0, February 2013.

26. Livermore Software Technology Corporation (LSTC), LS-DYNA Keyword Users Manual, Volume III, Multi-Physics Solvers, Version R7.0, February 2013.

27. Livermore Software Technology Corporation (LSTC), LS-DYNA Theory Manual, Revision 5061, March 2014.

2.12-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Pages 2.12-4 through 2.12-37 withheld pursuant to 10 CFR 2.390 2.12-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.0 THERMAL EVALUATION The following analysis demonstrates that the CR3MP complies with the thermal requirements of 10 CFR 71 [1] for exclusive use transport of the unique, one-time payload.

3.1 Description of Thermal Design 3.1.1 Design Features The CR3MP is a thick-walled steel shell constructed of ASTM A516 Grade 70 carbon steel. The package internal cavity has a 194.3-inch inner diameter and a 166.13-inch height. Both the top and bottom covers are 6-in. thick, while the shell wall is 3-in. thick. The exterior top and side package surfaces are painted white.

The CR3MP payload is comprised of the sectioned RPV along with the RVI components.

Within the RPV shell, the RVI components are surrounded by cellular concrete fill material (i.e., grout). The activated RVI components are constructed of carbon steel and stainless steel, with the majority of decay heat coming from Co-60. The RVI components are rigidly constrained as one body within the RPV by up to three different layers of grout, of which two layers may be a higher density mix (i.e., HDCC) and one layer is of lower density (i.e., LDCC).

If used, the HDCC (130 to 140 pcf) layers of grout may extend 9 inches above the bottom cut line and 9 inches below the top cut line. Where the HDCC is not used, all remaining volume within the RPV will be filled by LDCC (30 to 60 pcf) grout.

The RPV payload is approximately [ ] smaller in diameter than the packaging internal cavity.

Therefore, this radial annulus formed between the RPV outer shell and the CR3MP inner shell wall will be filled with the aforementioned LDCC grout, while the upper 3-in. gap above the RPV payload and bottom of the top cover is nominally free of grout.

3.1.2 Contents Decay Heat Based on a NAA of the RVI components within the payload, the maximum decay heat of the CR3MP payload is calculated in Section 5.2, Source Specification, as 358.1 watts. However, a bounding value of 500 watts is set to characterize the payload decay heat. All decay heat is conservatively modeled as a volumetric heat source within the payload steel.

3.1.3 Summary Tables of Temperatures The CR3MP is shipped vertically-oriented under exclusive use requirements. For exclusive use under NCT and HAC, the following load conditions are analyzed:

- NCT Hot with Insolation: Per 10 CFR 71.71(c)(1) [1], the package is evaluated with an ambient air temperature of 38 °C (100 °F), maximum decay heat, and maximum insolation to determine maximum component temperatures during NCT.

- NCT Hot without Insolation: Per 10 CFR 71.43(g) [1], the package is evaluated with an ambient air temperature of 38 °C (100 °F), maximum decay heat, and in shade to verify no accessible surface of the package exceeds 85 °C (185 °F).

3.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022

- NCT Cold: Per 10 CFR 71.71(c)(2) [1], the package is evaluated with an ambient air temperature of -40 °C (-40 °F), minimum decay heat, and in shade to determine minimum component temperatures during NCT.

- HAC Fire Transient: Per 10 CFR 71.73(c)(4) [1], the package is evaluated engulfed in flame (or equivalent condition) for a period of 30 minutes to determine maximum component temperatures during HAC. The fire load must simulate an average flame temperature of at least 800 °C (1475 °F) with an average flame emissivity coefficient of 0.9. The package surface absorptivity coefficient should be based on expected package conditions, but may not be less than 0.8. The most limiting NCT conditions (NCT Hot) are maintained before and after the fire event.

Temperatures for the CR3MP are computed using ANSYS 19.2 (Mechanical via Workbench).

CR3MP component temperatures resulting from the worst-case conditions specified by 10 CFR 71 are summarized in Table 3.1-1 and Table 3.1-2. All temperatures are below applicable limits. Note, grout bulk temperature (rather than peak) is limited based on pressure calculations and thus no explicit maximum temperature limit is applied.

Table 3.1 Summary of CR3MP NCT Temperatures Maximum Maximum Minimum Minimum Component Temperature (°C) Limit (°C) Temperature (°C) Limit (°C)

Package 50 371 -40 < -40 Payload Steel 160 371 -40 < -40 Grout 159 - -40 < -40 Package Surface (in shade) 40 85 - -

Table 3.1 Summary of CR3MP HAC Temperatures Maximum Maximum Component Temperature (°C) Limit (°C)

Package 579 1495 Payload Steel 279 1400 Grout 799 -

3.1.4 Summary Tables of Maximum Pressures MNOP, NCT pressure, and HAC pressure are evaluated in Appendix 3.5.2, Evaluation of Pressure in the CR3MP.

3.1-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.2 Material Properties and Component Specifications 3.2.1 Material Properties The material properties for package carbon steel and payload stainless steel are taken from Tables TCD and PRD in [2]. The payload is a mixture of carbon steel and stainless steel, but is modeled solely as stainless steel. Stainless steel has lower thermal conductivity than carbon steel, and thus its use in payload modeling results in conservatively high temperatures. The density of carbon steel is set to 7750 kg/m3, while the density of stainless steel is set to 8030 kg/m3. Specific heat, Cp, is calculated from the thermal conductivity, thermal diffusivity, and density values (k, , and respectively) in [2] using the following relation:

=

The material properties for carbon steel and stainless steel are shown in Table 3.2-1 and Table 3.2-2, respectively.

The exterior top and side surfaces of the package will be painted with white paint. Per Table 4.2 of [3], the solar absorptivity of white paint ranges from 0.18 to 0.34 while the emissivity ranges from 0.88 to 0.92. To maximize heat flow into the package and minimize heat flow out, the solar absorptivity and emissivity values are assumed to be 0.34 and 0.88 respectively for NCT. For HAC, the solar absorptivity and emissivity values rise to 0.8 and 0.9 as required by [1].

The package inner surfaces will not be painted. The emissivity of rough steel is assumed to be 0.95 [9], while the emissivity of concrete can be assumed to be 0.90 [15]. For radiation across the internal air gap, the package inner surface is modeled with an emissivity of 0.95 while the payload surface is modeled with an emissivity of 0.90.

HDCC is conservatively not modeled as there is no minimum requirement for HDCC thickness at either the top or bottom of the payload. The LDCC has a minimum as-cast density of 30 pcf (481 kg/m3). Limited data for thermal conductivity and specific heat of grout is available in [4]

and [5]. For thermal conductivity, values are reported as a function of oven-dry density rather than as-cast density. Equation 6.1.2.3b in [5] provides a means to estimate oven-dry density, D, from as-cast density, f:

kg

= [ 122]

m3 Based on Figure 3.4 in [4], thermal conductivity as a function of oven-dry density follows exponential behavior. Thus, the thermal conductivity of the LDCC is calculated from an exponential curve fitted to the available data points. This curve fitting is shown in Figure 3.2-1.

Minimum grout densities are utilized resulting in conservatively low thermal conductivities. The resulting material properties for grout are shown in Table 3.2-3. The specific heat of grout is set to 980 J/kgK per [5]1. All modeling uses as-cast density rather than oven-dry density.

1 The specific heat of 0.98 J/kgK stated in [5] is incorrect and does not match the corresponding value stated in U.S.

customary units (0.23 BTU/lb°F). A literature review (see Table 1 in [6]) confirms this correction.

3.2-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Grout thermal properties are not adjusted to account for changes in temperature and thus are modeled as singular values. Per Table 2 and Figure 85 in [7], lightweight concretes with densities and thermal conductivities similar to the CR3MP grout have relatively constant thermal conductivities across a wide range of temperatures (0 °C to 1000 °C). Figures 94 through 97 in

[7] show concrete specific heat increases with increases in temperature. Since higher specific heat values oppose increases in temperature, it is conservative to not account for this behavior.

The thermal properties of air are used directly within ANSYS as well as for calculation of convective heat transfer coefficients. Air properties are taken from Table A.6 in [8] and are shown in Table 3.2-4.

Table 3.2 Carbon Steel Material Properties Temperature Thermal Conductivity Specific Heat

(°C) (W/mK) (J/kgK) 20 60.4 431 50 59.8 453 75 58.9 467 100 58.0 480 125 57.0 490 150 55.9 500 175 54.7 508 200 53.6 516 225 52.5 525 250 51.4 534 275 50.3 543 300 49.2 553 325 48.1 564 350 47.0 575 375 45.9 586 400 44.9 600 425 43.8 614 450 42.7 628 475 41.6 644 500 40.5 660 525 39.3 675 550 38.2 694 575 37.0 712 600 35.8 732 625 34.7 755 650 33.5 780 675 32.3 816 700 31.2 877 725 30.1 1011 750 29.1 1552 3.2-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Table 3.2 Stainless Steel Material Properties Temperature Thermal Conductivity Specific Heat

(°C) (W/mK) (J/kgK) 20 14.8 473 50 15.3 484 75 15.8 493 100 16.2 499 125 16.6 507 150 17.0 511 175 17.5 520 200 17.9 526 225 18.3 530 250 18.6 532 275 19.0 537 300 19.4 542 325 19.8 546 350 20.1 548 375 20.5 551 400 20.8 552 425 21.2 557 450 21.5 558 475 21.9 562 500 22.2 563 525 22.6 566 550 22.9 568 575 23.3 571 600 23.6 573 625 24.0 576 650 24.3 578 675 24.7 580 700 25.0 582 725 25.4 586 750 25.7 587 3.2-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Figure 3.2 Grout Thermal Conductivity versus Oven-Dry Density Table 3.2 Grout Material Properties Cast Density Oven-Dry Density Thermal Conductivity Specific Heat (kg/m3) (kg/m3) (W/mK) (J/kgK) 481 359 0.11 980 3.2-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Table 3.2 Air Material Properties Temperature Density Specific Heat Kinematic Viscosity

(°C) (kg/m3) (J/kgK) (m2/s)

-73 1.769 1007 7.537E-06

-23 1.413 1006 1.135E-05

-13 1.359 1006 1.218E-05

-3 1.308 1006 1.304E-05 7 1.261 1006 1.392E-05 17 1.218 1006 1.482E-05 27 1.177 1006 1.575E-05 37 1.139 1007 1.670E-05 47 1.103 1007 1.766E-05 57 1.070 1008 1.865E-05 67 1.038 1009 1.966E-05 77 1.009 1009 2.069E-05 127 0.882 1014 2.613E-05 177 0.784 1021 3.204E-05 227 0.706 1030 3.839E-05 277 0.642 1040 4.515E-05 327 0.588 1051 5.232E-05 377 0.543 1063 5.987E-05 427 0.504 1075 6.780E-05 477 0.471 1087 7.608E-05 527 0.441 1099 8.472E-05 577 0.415 1110 9.371E-05 627 0.392 1121 1.030E-04 677 0.372 1131 1.127E-04 727 0.353 1141 1.227E-04 827 0.321 1159 1.436E-04 3.2-5

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Table 3.2 Air Material Properties (continued)

Temperature Thermal Conductivity Thermal Diffusivity Prandtl

(°C) (W/mK) (m2/s) Number

-73 0.0185 1.04E-05 0.726

-23 0.0226 1.59E-05 0.715

-13 0.0233 1.71E-05 0.713

-3 0.0241 1.83E-05 0.711 7 0.0249 1.96E-05 0.710 17 0.0256 2.09E-05 0.708 27 0.0264 2.23E-05 0.707 37 0.0271 2.37E-05 0.706 47 0.0279 2.51E-05 0.705 57 0.0286 2.65E-05 0.704 67 0.0293 2.80E-05 0.703 77 0.0300 2.95E-05 0.702 127 0.0335 3.74E-05 0.699 177 0.0368 4.59E-05 0.698 227 0.0399 5.50E-05 0.698 277 0.0430 6.45E-05 0.700 327 0.0460 7.44E-05 0.703 377 0.0489 8.48E-05 0.706 427 0.0518 9.55E-05 0.710 477 0.0545 1.07E-04 0.714 527 0.0572 1.18E-04 0.717 577 0.0599 1.30E-04 0.721 627 0.0625 1.42E-04 0.724 677 0.0651 1.55E-04 0.727 727 0.0677 1.68E-04 0.730 827 0.0727 1.96E-04 0.734 3.2-6

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.2.2 Component Specifications For NCT, the maximum allowable temperature for the carbon steel package is based on the maximum temperature limits in Table 2A of [2] (SA 516 Gr. 70, applicability limit for Part III).

The maximum allowable temperature for NCT is 371 °C (700 °F). For HAC, the maximum allowable temperature for the carbon steel package is based on the melting temperature of carbon steel. Per Table 4 of [9], carbon steel begins melting at 1495 °C (2723 °F).

For steel within the payload, credit is taken for components remaining in the loading configuration throughout transport. Thus, similar to the package steel, the NCT maximum allowable temperature is based on Table 2A of [2] (SA-240 Gr. 304 for stainless steel) and the HAC maximum allowable temperature is based on the melting temperature in Table 4 of [9].

Since both carbon steel and stainless steel exist in the payload, the lower of the two limits is applied for both NCT and HAC. The maximum allowable temperatures for the payload steel are 371 °C (700°F) and 1400 °C (2552 °F) for NCT and HAC, respectively.

No explicit temperature limits, for either NCT or HAC, are applied to either density of grout.

The primary concern for high grout temperatures is the bulk release of water vapor generating internal pressure within the CR3MP. Thus, acceptance of the NCT and HAC grout temperatures is based on pressure calculations.

The minimum allowable temperature for all CR3MP components is below -40 °C (-40 °F). Steel components will not be negatively affected as the strength characteristics improve as component temperatures decrease [10]. Cellular concrete has excellent resistance to freezing and thawing due to its high cement content and extended internal void structure, with strength even improving after freezing and thawing [5]. Thus, the payload grout will not be compromised by reduced temperatures.

3.2-7

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.3 Thermal Evaluation under Normal Conditions of Transport Temperatures for the CR3MP are computed using ANSYS 19.2 (Mechanical via Workbench).

Two steady-state thermal runs are performed to evaluate the maximum NCT temperatures with and without solar insolation. No thermal run is performed to evaluate minimum temperatures.

The package is simulated using a 2D, axisymmetric (i.e., cylindrical symmetry) model. The LDCC is modeled as multiple individual regions. While LDCC is used throughout the model, two regions corresponding to the maximum HDCC volumes are identified in the model. These regions are used to support the conservative pressure calculations in Appendix 3.5.2, Evaluation of Pressure in the CR3MP. The payload steel is split into two regions: the RPV shell wall and a centrally-located slug containing the remaining volume of payload steel. Modeling the RVI as a centrally-located slug and not extending the steel to the bottom and top of the RPV was a conservative simplifying assumption. The grout is more insulating than steel (i.e., lower conductivity); therefore, the payload peak temperature is maximized internally. Except for the air gap at the top of the payload, regions are modeled with shared nodes and thus there is no additional thermal resistance to heat transfer between materials. Due to the large size of the package and grouted payload, gaps are expected to be small and have an insignificant effect on heat transfer relative to the bulk materials. The air gap does not use shared nodes to allow modeling of radiation heat transfer across the gap.

All decay heat is conservatively concentrated in the payload steel slug since the RPV contains only a small fraction of the total decay heat. Insolation is modeled on the top and side surfaces, as the CR3MP will be shipped in a vertical orientation. Since the CR3MP is thermally massive, component temperatures will be effectively decoupled from diurnal changes in insolation loading. Thus, steady-state modeling with constant insolation loads, equal to the 10 CFR 71.71(c) [1] 12-hour total insolation loads averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, can be used to evaluate maximum component temperatures under NCT. The modeled insolation loads, qmodel, are calculated as a function of the regulation-specified 12-hour total insolation loads, qspecified, and the solar absorptivity, a:

=

24 For NCT, the insolation loads for the top (flat surface transported horizontally) and side (curved surface) surfaces are 131.72 W/m2 and 65.86 W/m2, respectively.

Radiation and convection to 38 °C ambient is modeled at the top and side surfaces, while the bottom surface is modeled with no heat transfer mechanisms (i.e., perfectly insulated).

Calculation of convective heat transfer coefficients for use in ANSYS is discussed in Appendix 3.5.3, Natural Convection Heat Transfer.

The mesh is defined to have quadrilateral elements of ~0.05 m side lengths. The resulting mesh has 14,512 nodes and 4,677 elements. A mesh refinement study has been performed to confirm that the mesh is sufficiently detailed and results to do not change significantly with increases in the number of nodes and elements.

The thermal model is shown in Figure 3.3-1. Model dimensions are shown in Table 3.3-1.

Modeling is done with nominal dimensions as tolerances are very small relative to their corresponding dimensions.

3.3-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Figure 3.3 CR3MP Thermal Model Materials and Mesh Table 3.3 Key CR3MP Thermal Model Dimensions 3.3-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.3.1 Heat and Cold NCT maximum temperatures are summarized in Table 3.3-2. The maximum distribution throughout the package is shown in Figure 3.3-2. All components are below their allowable temperature limits.

No modeling of minimum temperatures is performed. For the minimum temperature condition (no decay heat and -40 °C ambient air), as shown in Table 3.1-1, all components will eventually reach -40 °C steady-state. Per Section 3.2.2, Component Specifications, this temperature is acceptable for all components.

3.3.2 Maximum Normal Operating Pressure A MNOP of 5 psig is calculated in Appendix 3.5.2, Evaluation of Pressure in the CR3MP.

Table 3.3 CR3MP NCT Temperatures Maximum Allowable Component Temperature (°C) Temperature (°C)

Packaging 50 371 Payload Steel 160 371 Grout 159 -

Packaging Surface (in shade) 40 85 Figure 3.3 CR3MP NCT Maximum Temperature Distribution 3.3-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.4 Thermal Evaluation under Hypothetical Accident Conditions The NCT thermal model described in Section 3.3, Thermal Evaluation under Normal Conditions of Transport is reused for the HAC analysis. Geometry and general model design are unchanged. Specific parameters are adjusted as discussed below to model the HAC fire event.

3.4.1 Initial Conditions The initial conditions assumed for the package prior to the HAC fire transient are as follows:

- Package temperatures are initialized based on NCT maximum temperature conditions.

These maximums are calculated at steady-state with 38 °C ambient air and insolation loads based on undamaged package surfaces.

- For pre- and post-fire steady-state analysis, package orientation is vertical as this orientation results in lower heat removal to ambient and higher insolation loads. For the fire event, package orientation is horizontal so all sides are exposed to the fire and heat flow into the package is maximized.

- The surface absorptivity of all external surfaces is increased to 0.8 in order to account for possible oxidation and/or soot accumulation.

3.4.2 Fire Test Conditions The HAC fire transient is evaluated as follows:

- At initiation of the fire (t = 0), any heat removal due to convection to ambient as well as insolation loads are suspended. The ambient air temperature is increased to 800 °C, resulting in a heat flux into the package. A surface emissivity of 0.9 conservatively bounds the 10 CFR 71 [1] fire conditions.

- As part of the HAC, it is assumed a crack may form at the lower corner of the package.

As such, the fire radiation condition is also applied to an exposed 3-in. segment of internal grout at the lower corner to simulate direct exposure to the fire. This crack is shown in Figure 3.4-1.

- At termination of the fire (t = 30 minutes), the ambient air temperature is reduced to 38 °C. For the post fire transient analysis, convective heat removal is not restored.

Increased insolation loads (due to increased post-fire solar absorptivity) are applied. The insolation loads for the top and side surfaces are 309.93 W/m2 and 154.96 W/m2, respectively.

- To allow for any transient temperature responses to subside, the transient is evaluated for a period of 1 day.

- A post-fire steady-state model (t ) is evaluated using the post-fire conditions described above to determine the steady-state maximum temperatures. Convective heat removal is applied for this portion of the analysis.

3.4-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 The 10 CFR 71 [1] prescribed fire condition results in the following heat flux, qfire:

4 4

= ( ) ( )

Where:

-  : surface absorptivity

-  : Stefan-Boltzmann constant

-  : fire emissivity

- ,  : fire and surface temperatures (absolute)

Per [11], the fire heat flux resulting from the convection (rather than radiation) can be up to 20%

of the total. Thus, the prescribed fire heat flux can be reduced to the following:

4 1

= (0.8)((0.9) 4 ) ( )

1 0.2 4

= (0.9 4 )

For simplicity, the fire is conservatively modeled using a radiation condition with the CR3MP surface emissivity, surface, set to 0.9.

4 4

= ( 4 ) = 0.9( 4 )

Figure 3.4 CR3MP Thermal Model with HAC Crack 3.4-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.4.3 Maximum Temperatures and Pressure HAC maximum temperatures are summarized in Table 3.4-1. The maximum temperatures achieved throughout the CR3MP (for each node at any time step) are shown in Figure 3.4-2, while the post-fire steady-state temperature distribution is shown in Figure 3.4-3. Fire transient maximums are achieved at or shortly after termination of the fire (30 minutes t 60 minutes).

All components are below their temperature limits.

The maximum temperature of the weld region connecting the end closure plate to the side shell, not including the region of the opening crack, is 493 °C.

Maximum pressure is calculated in Appendix 3.5.2, Evaluation of Pressure in the CR3MP. This calculation conservatively assumes that the damage to the containment boundary discussed in Section 3.4.2, Fire Test Conditions, has not prevented the retention of pressure.

Table 3.4 CR3MP HAC Temperatures Fire Transient Post-Fire Steady-State Allowable Component Maximum Temperature (°C) Maximum Temperature (°C) Temperature (°C)

Packaging 579 63 1495 Payload Steel 279 169 1400 Grout 799 169 -

Figure 3.4 CR3MP HAC Maximum Temperatures During Fire Transient 3.4-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Figure 3.4 CR3MP HAC Post-Fire Steady-State Temperatures 3.4.4 Maximum Thermal Stresses The maximum thermal stresses are addressed in Section 2.7.4, Thermal.

3.4.5 Accident Conditions for Fissile Material Packages for Air Transport This section is not applicable as the CR3MP does not contain fissile material and will not be transported by air.

3.4-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.5 Appendices Appendix 3.5.1 ..................................................................................................... References Appendix 3.5.2 ..Evaluation of Pressure in the CR3MP Appendix 3.5.3 Natural Convection Heat Transfer 3.5-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 3.5.1 References

1. Title 10 - Energy, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

2. American Society of Mechanical Engineers Standard Boiler and Pressure Vessel Code,Section II, Materials Part D: Properties (Metric), 2017 Edition.

3. NASA/TP-2005-212762, Spacecraft Thermal Control Coatings References, NASA/Goddard Space Flight Center, December 2005.

4. American Concrete Institute Report, ACI 523.1R-06, Guide for Cast-in-Place Low-Density Cellular Concrete, American Concrete Institute, August 2006.

5. American Concrete Institute Report, ACI 523.3R-14, Guide for Cellular Concretes above 50 lb/ft3 (800 kg/m3), American Concrete Institute, April 2014.

6. Roberz, F., R.C.G.M Loonen, P. Hoes, and J.L.M. Hensen, Ultra-lightweight concrete:

Energy and comfort performance evaluation in relation to buildings with low and high thermal mass, Energy and Buildings Volume 138, March 2017.

7. NUREG/CR-6900, The Effect of Elevated Temperature on Concrete Materials and Structures - A Literature Review, March 2006, NRC Accession Number ML060970563.

8. Lienhard IV, John H. and Lienhard V, John H., A Heat Transfer Textbook, 5th edition, Phlogiston Press, 2020.

9. Valencia, Juan J. and Quested, Peter N., ASM Handbook, Volume 15: Casting, Thermophysical Properties, ASM Handbook Committee, p468-481, 2008.

10. McClintock, R. Michael and Hugh P. Gibbons, Mechanical Properties of Structural Material at Low Temperatures: A Compilation from the Literature, U.S. Department of Commerce, National Bureau of Standards Monograph 13, June 1960.

11. ASTM E2230 - 2013, Standard Practice for Thermal Qualification of Type B Packages for Radioactive Material, ASTM International, April 2013.

12. Wang, Jin Doctoral Thesis, Modeling of Concrete Dehydration and Multhiphase Transfer in Nuclear Containment Concrete Wall During Loss of Cooling Accident, Génie civil nucléaire

- Université Paul Sabatier - Toulouse III, 2016. Available at: https://tel.archives-ouvertes.fr/tel-01578096, Retrieved July 20, 2021.

13. U.S. Department of Energy, West Valley Demonstration Project, SARWVMP-01, Revision 1, Safety Analysis Report for the West Valley Melter Package, Chapter 3, USNRC Docket Number 71-9797, April 2015, NRC Accession Number ML15126A341.

14. ASTM C150 - 2020, Standard Specification for Portland Cement, ASTM International, April 2020.

15. American Concrete Institute Report, ACI/TMS 122R-14, Guide to Thermal Properties of Concrete and Masonry Systems, December 2014.

3.5-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Pages 3.5-3 through 3.5-10 withheld pursuant to 10 CFR 2.390 3.5-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 4.0 CONTAINMENT 4.1 Description of the Containment System 4.1.1 Containment Boundary The CR3MP provides a single level of containment for the payload defined in Section 1.2.2, Contents. A leak-tight containment boundary is obtained by means of thick, volumetrically inspected closure welds. The containment boundary of the CR3MP consists of the bottom closure plate cover, the cylindrical shell, and the top closure plate cover. All containment boundary components are made from ASTM A516/ASME SA516, Grade70 carbon steel. A full description of the packaging is given in Chapter 1.0, General Information.

4.1.2 Containment Penetrations, Closures, and Seals There are no valves, ports, bolted closures, or seals in the containment boundary. The package is permanently welded closed after placement of the payload and annular packaging grout.

4.1.3 Welds The weld material meets the requirements of ASME BPVC, Subsection ND, Subarticle ND-2400

[1]. All welds used in the containment boundary are full penetration and volumetrically inspected to ensure structural and containment integrity. The weld inspections that are performed are discussed in Section 2.3.2, Examination.

4.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 4.2 Containment under Normal Conditions of Transport The containment criterion for NCT is stated in Section 2.1.2, Design Criteria, and is based on 10 CFR 71.51(a)(1) [2] which states that there is to be no loss or dispersal of radioactive contents exceeding 10-6 A2 per hour. The results of the NCT structural and thermal evaluations presented in Sections 2.6, Normal Conditions of Transport, and 3.3, Thermal Evaluation under Normal Conditions of Transport, respectively, demonstrate that there is no release of radioactive materials under any of the NCT tests described in 10 CFR 71.71. While some damage occurs to the closure weld in the NCT one foot, CG over corner free drop, the weld remains intact, thus maintaining containment (see section 2.6.7.3, NCT CG over Corner Drop).

4.2.1 Hydrogen Concentration in the Package 4.2-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 4.3 Containment under Hypothetical Accident Conditions The containment criterion for HAC is stated in Section 2.1.2, Design Criteria, and is based on 10 CFR 71.51(a)(2) [2]: there shall be no escape of krypton-85 exceeding 10 A2 in one week, and no escape of other radioactive contents exceeding one A2 in one week. Under HAC, the immersion and thermal evaluations performed in Sections 2.7, Hypothetical Accident Conditions, and 3.4, Thermal Evaluation under Hypothetical Accident Conditions, respectively, show no release of radioactive material. Under the HAC free drop and puncture events, some release of radioactive material may occur, however, as demonstrated in this section, the containment criterion of 10 CFR 71.51 is met by the CR3MP. The following evaluation provides a conservative estimate of the maximum amount of radioactivity that could be released under HAC by the free drop and puncture events.

Regarding the puncture test condition, Section 2.7.3.2, Puncture on the Package Body Shell, contains a discussion of the effect of the HAC puncture event on potential release of contamination. As concluded from that discussion, no significant release of contaminated grout is to be expected from the puncture event.

4.3-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Page 4.3-2 withheld pursuant to 10 CFR 2.390 4.3-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 As a result of this conservative evaluation, the containment criterion for HAC is met.

4.3-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 4.4 Leakage Rate Tests for Type B Packages The CR3MP is closed using a thick, 3.75-inch weld which is volumetrically inspected. This weld and its Non Destructive Examination (NDE) (see Section 4.1.3, Welds) complete the leak-tight boundary of the package. No leakage rate tests are performed.

4.4-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 4.5 Appendix 4.5.1 References

1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, Division 1 - Subsection ND, Class 3 Components, 2017 Edition.

2. Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

3. U.S. Nuclear Regulatory Commission, NUREG-2216, Standard Review Plan for Spent Fuel Transportation, August 2020, NRC Accession Number ML20234A651.

4.5-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.0 SHIELDING EVALUATION The following analysis demonstrates that the CR3MP complies with the dose rate requirements of 10 CFR 71 [1] for exclusive use transport of the unique, one-time payload.

5.1 Description of Shielding Design 5.1.1 Design Features The CR3MP is a relatively thick-walled, sealed cylinder constructed of ASTM A516 Grade 70 carbon steel. The package internal cavity has a 194.3-in. nominal diameter and a 166.13-in.

nominal height. The top and bottom axial package walls are 6-in. thick, while the side package wall is 3-in. thick.

The CR3MP payload is comprised of activated RPV and RVI surrounded by cellular concrete fill material (i.e. grout). [

]

The CR3MP payload is slightly smaller than the package internal cavity. All free volume outside the RPV will be filled with an additional volume of LDCC grout. There will be a 3-in.

nominal air gap between the payload and the package lid.

Figure 5.1 CR3 RPV/RVI (Decommissioning Configuration, Middle Segment) 5.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.1.2 Summary of Maximum Radiation Levels The package is shipped vertically-oriented under exclusive use requirements. The requirements for exclusive use under NCT and HAC, per 10 CFR 71.47(b) and 10 CFR 71.51(a)(2) [1],

respectively, are summarized and applied as follows:

Limits for NCT

- 200 mrem/hr on the external surface of the package

- 200 mrem/hr at the projected outer surfaces of the transport vehicle

- 10 mrem/hr at any point 2 meters from the projected side surfaces of the transport vehicle (Note: per 10 CFR 71.47(b)(3) excludes the top and underside of the vehicle in Table 5.1-1)

- 2 mrem/hr in any normally occupied space Limits for HAC

- 1000 mrem/hr at any point 1 meter from the outer surface of the package The external surfaces of the package are conservatively used as the projected outer surfaces of the transport vehicle. Any normally occupied space is assumed to be at least 25 feet from the centerline of the package.

Summaries of the maximum dose rates are shown in Table 5.1-1 and Table 5.1-2 for NCT and HAC, respectively. Based on these results, it can be concluded that the CR3MP complies with the external radiation requirements of 10 CFR 71 for exclusive use transport.

Table 5.1 Summary of Maximum NCT Dose Rates (mrem/hr) 2 Meters from Occupied Package Surface Package Surface Location Radiation 25 ft from Top Side Bottom Top Side Bottom Package center Total (Gamma Only) 9.46 4.46 2.08 - 1.33 - 0.38 10 CFR 71.47 (b) Limit 200 200 200 10 10 10 2 Table 5.1 Summary of Maximum HAC Dose Rates (mrem/hr) 1 Meter from Radiation Package Surface Top Side Bottom Total (Gamma Only) 2.73 2.62 1.48 10 CFR 71.51 (a)(2) Limit 1000 1000 1000 5.1-2

PROPRIETARY Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.2 Source Specification The geometry and source distribution of the payload is based on RPV/RVI models and mapped

[Trade activation data calculated by the CR3 Original Equipment Manufacturer (OEM). [

Secret]

]

[Trade Secret]

Based on the NAA, the activation source term is estimated to be 35,600 Ci total with 19,300 Ci Co-60. These values are based on a date of June 30th, 2021. The payload source is predominantly Co-60 (54%), Ni-63 (28%), and Fe-55 (17%), with trace amounts of other isotopes. Only gamma sources are present among the isotopes (no neutron sources). Ni-63 and Fe-55 are relatively weak radiation sources relative to Co-60, and thus key parameters such as total decay heat, total gamma energy release rate, and total A2 quantity are dominated by Co-60 (contributes ~99% of total for each).

The CR3MP activation source term is modeled as solely Co-60. The total activation activity is set to a bounding value of 30,000 Ci. A similarly bounding value of 3,000 A2 is set for the A2 quantity. These values are significantly higher ( 55% increases) than the values calculated by the NAA and are intended to bound any uncertainties. The relative spatial distribution calculated by the NAA is used for distributing the activation source. The spatial distribution of the Co-60 source term as calculated in the NAA is shown in Figure 5.2-1.

The surface contamination of CR3 components is estimated to be [ ] based on

[Trade empirical samples. The total contamination source strength is 24.8 Ci. The surface contamination is composed primarily of Co-60 (58%), Ni-63 (30%), Cs-137 (5%), and Secret]

Fe-55 (5%). Like the activation source term, the contamination source term is conservatively modeled as only Co-60.

[

]

Unlike the shielding source term and A2 value, the payload decay heat is calculated based on a [Trade payload of 19,300 Ci Co-60 with additional decay to the earliest ship date of March 31st, 2023. Secret]

To account for the uncertainty in OEM flux calculations, the decay heat is increased by a [ ]

factor. Additionally, to account for decay heat from isotopes other than Co-60 as well as contamination, the decay heat is further increased by [

]

5.2-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.2.1 Gamma Source The Co-60 gamma spectrum is shown in Table 5.2-1. The Co-60 gamma spectrum is taken from ORIGEN discrete gamma data included within SCALE 6.2.4 [2]. ORIGEN decay data is based on ENDF/B-VII.1 evaluations. [

]

Table 5.2 Co-60 Discrete Gamma Spectrum Gamma Energy (MeV) Probability of Gamma per Isotope Decay 7.5100E-04 1.6946E-06 8.5234E-04 8.0550E-07 8.7689E-04 1.3826E-08 8.8364E-04 5.6638E-07 7.4178E-03 3.1894E-05 7.4358E-03 6.2286E-05 8.2223E-03 3.9005E-06 8.2246E-03 7.6481E-06 8.2879E-03 3.3435E-09 8.2881E-03 4.8594E-09 3.4714E-01 7.5000E-05 8.2610E-01 7.6000E-05 1.1732E+00 9.9850E-01 1.3325E+00 9.9983E-01 2.1586E+00 1.2000E-05 2.5057E+00 2.0000E-08 5.2-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Figure 5.2 Co-60 Spatial Distribution (Bq/g) 5.2.2 Neutron Source No neutron sources are utilized.

5.2-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.3 Shielding Model 5.3.1 Configuration of Source and Shielding All relevant design features of the CR3MP are modeled in Monte Carlo N-Particle (MCNP)

Version 6.2 [3]. The key dimensions of the modeled CR3MP are summarized in Table 5.3-1.

The RPV and RVI components are modeled algorithmically, based on OEM 3D models, using hexahedron voxels. The remaining volume in the payload is conservatively filled with LDCC based on planned fill dimensions. As a result, the payload dimensions are inexact but otherwise reasonably representative of the source and material distributions.

The MCNP model is shown in Figure 5.3-1, Figure 5.3-2, and Figure 5.3-3. For all figures the color scheme is as follows: payload steel in purple, package steel in blue, LDCC in green, and void in white.

Table 5.3 Key CR3MP Dimensions 5.3-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Pages 5.3-2 through 5.3-3 withheld pursuant to 10 CFR 2.390 5.3-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.3.2 Material Properties The CR3MP is constructed of carbon steel, while the payload consists of carbon steel and stainless steel RVI components surrounded by grout.

Carbon steel is modeled per [5] (material 294, Steel, Carbon) and shown in Table 5.3-2. The payload steel is conservatively modeled as solely carbon steel. The package carbon steel uses a reference density of 7.82 g/cm3, while the payload carbon steel uses a reduced density of 6.92 g/cm3 to offset the increase in component volume due to the conversion to voxels. This reduced density, payload steel, is a function of the payload component masses, mi, and the component voxel volumes,  :

=

The payload grout is modeled as Portland concrete per [5] (material 98, Concrete, Portland).

All grout is conservatively modeled as LDCC for evaluation of dose rates. The grout density is the set to minimum as-cast density of 0.48 g/cm3 (30 pcf). The grout composition is shown in Table 5.3-3.

Table 5.3 Carbon Steel Composition Weight Element ZAID Fraction C 6000 0.005000 Fe 26000 0.995000 Table 5.3 Portland Concrete (Grout) Composition Weight Element ZAID Fraction H 1000 0.010000 C 6000 0.001000 O 8000 0.529107 Na 11000 0.016000 Mg 12000 0.002000 Al 13000 0.033872 Si 14000 0.337021 K 19000 0.013000 Ca 20000 0.044000 Fe 26000 0.014000 5.3-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.4 Shielding Evaluation 5.4.1 Methods 5.4.1.1 Conversion of OEM Models to MCNP 5.4.1.2 MCNP Shielding Model Dose rates from the CR3MP are computed using MCNP6.2 [3] using default cross-sections (ENDF/B-VI.8 for photons [7]). All modeling is done in three dimensions. A quarter-symmetry package shielding model is utilized. The packaging and payload are symmetric across the x- and y- axes (radial axes), and thus a quarter-symmetry model utilizing reflective x- and y- axes is acceptable. The CR3MP payload is modeled as reduced density carbon steel and LDCC, while the packaging is modeled as standard density carbon steel. A 3-in. air gap exists between the top of the payload and the package lid, which is modeled as void. Any volume outside the CR3MP is also modeled as void.

5.4-1

PROPRIETARY Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Separate runs are performed to model the activation and contamination sources. [

[Trade Secret]

] Each source is composed of individual voxel probabilities describing the portion of the total source strength located within the associated voxel. Source particle starting position is sampled uniformly within associated voxel volumes.

For NCT, the payload and packaging are modeled without damage. For HAC, the welds may fail in limited areas and allow for some release of grout. The damage to the CR3MP is insignificant with respect to shielding and thus no CR3MP damage is modeled. The loss of grout may be significant and is conservatively modeled by removing all grout outside the RPV outer radius, bounding the grout loss during HAC.

Dose rates are computed using segmented mesh tallies. Mesh tallies compute fluxes in thin, non-physical volumes [ ] before converting to dose rates using the flux- [Trade to-dose rate conversion factors in Section 5.4.2, Flux-to-Dose Rate Conversion. Tallies are Secret]

subdivided to capture variations in dose rates and properly identify localized maximums.

5.4.2 Flux-to-Dose Rate Conversion American National Standards Institute ANSI/ANS-6.1.1-1977 photon flux-to-dose rate conversion factors [8] are used in this analysis. The reference conversion factors have been multiplied by a factor of 1,000 to generate dose rates in units of mrem/hr rather than rem/hr. The conversion factors are provided in Table 5.4-1.

Table 5.4 Photon Flux-to-Dose Rate Conversion Factors Energy, E DF(E) Energy, E DF(E)

(MeV) (mrem/hr)/(/cm2-s) (MeV) (mrem/hr)/(/cm2-s) 0.01 3.96E-03 1.40 2.51E-03 0.03 5.82E-04 1.80 2.99E-03 0.05 2.90E-04 2.20 3.42E-03 0.07 2.58E-04 2.60 3.82E-03 0.10 2.83E-04 2.80 4.01E-03 0.15 3.79E-04 3.25 4.41E-03 0.20 5.01E-04 3.75 4.83E-03 0.25 6.31E-04 4.25 5.23E-03 0.30 7.59E-04 4.75 5.60E-03 0.35 8.78E-04 5.00 5.80E-03 0.40 9.85E-04 5.25 6.01E-03 0.45 1.08E-03 5.75 6.37E-03 0.50 1.17E-03 6.25 6.74E-03 0.55 1.27E-03 6.75 7.11E-03 0.60 1.36E-03 7.50 7.66E-03 0.65 1.44E-03 9.00 8.77E-03 0.70 1.52E-03 11.00 1.03E-02 0.80 1.68E-03 13.00 1.18E-02 1.00 1.98E-03 15.00 1.33E-02 5.4-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.4.3 External Radiation Levels For NCT, CR3MP surface dose rates are calculated using three tallies at the top, bottom, and side surfaces while 2 meter dose rates are calculated using a single tally located 2 meters from the side surface. The occupied location dose rate is calculated with a side tally located 25 feet from the CR3MP centerline. For HAC, 1 meter dose rates are calculated using three tallies located 1 meter from the top, bottom, and side surfaces.

The maximum dose rates for each location along with associated relative errors are shown in Table 5.4-2. Relative errors for all maximum dose rates are less than or equal to 10% (with one exception at 14%), satisfying guidance in [3].

Table 5.4 Tally Maximum Dose Rates (mrem/hr)

Activation Contamination Total Location Result Error Result Error Result Error NCT, Package Surface, Side 4.45 1% 0.00 4% 4.46 1%

NCT, Package Surface, Top 8.97 1% 0.49 1% 9.46 1%

NCT, Package Surface, Bottom 1.36 14% 0.72 3% 2.08 9%

NCT, Package 2 meter, Side 1.32 1% 0.00 5% 1.33 1%

NCT, Occupied Location 0.38 1% 0.00 3% 0.38 1%

HAC, Package 1 meter, Side 2.61 1% 0.00 3% 2.62 1%

HAC, Package 1 meter, Top 2.21 1% 0.52 1% 2.73 1%

HAC, Package 1 meter, Bottom 0.94 7% 0.54 2% 1.48 5%

Note: Total dose rates may not be equal to the exact sum of activation and contamination dose rates due to rounding.

5.4.4 Radiolytic Gas Generation The generation of gases due to radiolysis in the payload grout may result in an increase in package pressure. Additionally, generation of hydrogen gas specifically may result in a combustible internal gas mixture. To support the evaluation of CR3MP pressure and gas mixture, the maximum quantities of total gas and hydrogen gas that may be generated due to radiolysis are calculated. Similarly, to support the evaluation of gas flammability, the maximum quantity of hydrogen generated due to radiolysis is also calculated.

5.4-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Pages 5.4-4 through 5.4-8 withheld pursuant to 10 CFR 2.390 5.4-4

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.5 Appendices Appendix 5.5.1 ..................................................................................................... References Appendix 5.5.2 ......................................................................................................Input Data Appendix 5.5.3 ...................................................................................... G-value Calculation 5.5-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 5.5.1 References

1. Title 10, "Energy", Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

2. W. A. Wieselquist, R. A. Lefebvre, and M. A. Jessee, Eds., SCALE Code System, ORNL/TM-2005/39, Version 6.2.4, Oak Ridge National Laboratory , Oak Ridge, Tennessee, April 2020.

3. LA-UR-17-29981, MCNP User's Manual: Code Version 6.2, Los Alamos National Laboratory, October 2017.

4. LA-UR-03-1987, MCNP - A General Monte Carlo N-Particle Transport Code, Version 5, Volume 1: Overview and Theory, Los Alamos National Laboratory, April 2003.

5. PNNL-15870, Compendium of Material Composition Data for Radiation Transport Modeling, Pacific Northwest National Laboratory, Revision 1, March 2011.

6. Schroeder, Will; Martin, Ken; Lorensen, Bill (2006), The Visualization Toolkit (4th ed.),

Kitware, ISBN 978-1-930934-19-1 (see vtk.org for additional information).

7. LA-UR-17-20709, Listing of Available ACE Data Tables, Los Alamos National Laboratory, October 2017.

8. ANSI/ANS-6.1.1-1977, American National Standard Neutron and Gamma-Ray Flux-to-Dose-Rate Factors, March 1977.

9. Lawrence Livermore National Laboratory, Hydrogen Generation in TRU Waste Transportation Packages, NUREG/CR-6673, UCRL-ID-13852, U.S. Nuclear Regulatory Commission, May 2000, NRC Accession Number ML003723404.

10. EPRI NP-5977, Radwaste Radiolytic Gas Generation Literature Review, Electric Power Research Institute, September 1988

11. BNL-NUREG-50957, Properties of Radioactive Wastes and Waste Containers, Brookhaven National Laboratory, August 1979

12. NIST Standard Reference Database 8, XCOM: Photon Cross Sections Database, National Institute of Standards and Technology, DOI: 10.18434/T48G6X

13. NIST Standard Reference Database 124, Stopping-Power & Range Tables for Electrons, Protons, and Helium Ions, National Institute of Standards and Technology, DOI: 10.18434/T4NC7P

14. S. Kim, J. Chen, T. Cheng, et al., PubChem in 2021: new data content and improved web interfaces, Nucleic Acids Research Volume 49 Issue D1, DOI:10.1093/nar/gkaa971

15. Taylor, S. and G. Halsted., Guide to Lightweight Cellular Concrete for Geotechnical Applications, Portland Cement Association, Washington, DC, and National Concrete Pavement Technology Center at Iowa State University, Ames, IA, January 2021.

5.5-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 Proprietary Information on Pages 5.5-3 through 5.5-12 withheld pursuant to 10 CFR 2.390 5.5-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022

6.0 CRITICALITY EVALUATION

As shown in Table 1.2-1, the CR3MP contains less than 2g of fissile material. Thus, per the provisions of 10 CFR 71.15(a) [1], the CR3MP is exempt from classification as a fissile material package. Therefore, a criticality evaluation is not required.

6.1 References

1. Title 10 - Energy, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

6.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.0 PACKAGE OPERATIONS In accordance with NRC Regulatory Guide 7.9, this chapter describes the operating procedures to be used for loading and transport of the CR3MP in order to ensure safe operations in compliance with the regulations and the package evaluation in this SAR. The CR3MP is a 10 CFR Part 71, exclusive use Type B package used for a onetime shipment and disposal of a portion of the CR3 RPV at a licensed low level radioactive waste disposal facility. Since the package is permanently sealed and will be buried with its contents, the Preparation of Empty Package for Transport as defined in Regulatory Guide 7.9 does not apply. For the same reason, package opening instructions as stated in 10 CFR 71.89 are not applicable. In addition, operational controls and precautions as described in 10 CFR 71.35(c) for fissile material packages does not apply since the package is fissile exempt.

All the required operations discussed in this chapter will be performed in accordance with written procedures approved under the licensees QA Program.

7.1 Procedures for Loading the Package This section delineates the procedures for loading the payload into the CR3MP. The CR3MP is loaded and closed in accordance with detailed written procedures, the contents are authorized in the package approval, and the package is in unimpaired physical condition. [

] The steps provided in the below subsections may be performed out-of-order such that the most appropriate sequence is achieved.

7.1.1 Preparation for Loading 7.1.2 Loading of Contents Visual inspections of packaging components delineated in the following steps may be performed at any time during the loading sequence. [

]

7.1-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.1.3 Preparation of the CR3MP for Transport The following conditions are required to prepare for and complete the CR3MP transport:

Complete all necessary shipping papers in accordance with Subpart C of 49 CFR 172

[3]. The CR3MP shall comply with applicable DOT requirements, including for marking, labeling and placarding of the package and conveyance. In this regard, the CR3MP shall follow the requirements of 10 CFR §71.85(c) [1] and Subpart D of 49 CFR 172 [3]. Package labeling shall be in accordance with Subpart E of 49 CFR 172. Package placarding shall be in accordance with Subpart F of 49 CFR 172.

If there is a credible scenario for the ambient temperature to reach 0°F, then provide a continuous ambient temperature monitoring sensor as part of the transport. If at any point during the transport, the ambient temperature reaches a range between 0°F and 5°F, the transport shall be halted until the ambient temperature sensor measures a value above this temperature requirement.

The CR3MP contamination limits shall not exceed the limits set forth in Table 9 of 49 CFR 173.443 [2].

The following basic steps are performed to transport the package:

1. Perform a radiation survey of all accessible surfaces of the CR3MP. For transport requirements, and as specified in 49 CFR §173.441 [2], the dose rate must be less than 200 mrem/hr on the surface and less than 10 mrem/hr at a distance of 2 meters from the surface.

7.1-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.1-3

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.2 Package Unloading This section delineates the procedures for unloading the [

]

7.2.1 Receipt of Package from Carrier

5. The CR3MP is disposed of in accordance with disposal site requirements.

7.2.2 Removal of Contents This subsection is not applicable. The package with contents will be disposed of as a one-time use package and the CR3MP will not be opened at the disposal site.

7.2-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.3 Preparation of Empty Package for Transport This subsection is not applicable since no transport of the empty package occurs.

7.3-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.4 Other Operations There are no other special operational control provisions necessary for operation of the CR3MP.

7.4-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 7.5 Appendix 7.5.1 References

1. Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

2. Title 49, Code of Federal Regulations, Part 173 (49 CFR 173), Shippers-General Requirements for Shipments and Packagings, 10-01-20 Edition

3. Title 49, Code of Federal Regulations, Part 172 (49 CFR 172), Hazardous Materials Tables and Hazardous Communications Regulations, 10-01-20 Edition.

7.5-1

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM This section describes the acceptance tests and the maintenance program that shall be used on the CR3MP to ensure compliance with its design requirements, and the requirements of Subpart G of 10 CFR 71 [1].

8.1 Acceptance Tests Per the requirements of 10 CFR §71.85, this section discusses the inspections and tests to be performed prior to first use of the CR3MP for transportation activities. Acceptance criteria for all inspections and tests are found either on the drawings in Appendix 1.3.2, Packaging General Arrangement Drawings, or in the sections that follow. All the tests and inspections on the CR3MP described in this chapter are conducted and documented in accordance with written procedures approved under an NRC approved QA program.

8.1.1 Visual Inspection and Measurements The CR3MP packaging is visually inspected and measured to ensure that all of the requirements delineated on the SAR drawing in Appendix 1.3.2, Packaging General Arrangement Drawings are satisfied. [

]

8.1.2 Weld Examinations The locations, types, and sizes of all welds are identified and recorded to ensure compliance with the SAR drawing in Appendix 1.3.2, Packaging General Arrangement Drawings. All welds are Visually Examined (VT) in accordance with the SAR drawing.

All containment boundary welds are in accordance with Subarticle ND-5300 of the ASME BPVC [2]. The Category A and B cover and shell welds are specified to have a full RT examination along with MT or PT examinations on both the inner and outer surfaces. In lieu of the RT requirement of Subsubarticle ND-5230, and in accordance with Paragraph ND-5279, NDE of the Category C closure joints (both top and bottom covers) includes a full volumetric UT of the final weld joint. In addition, either a MT or PT examination is also performed on the Category C closure joint welds on both the inner/outer finished surfaces of the bottom cover and root/final pass of the top cover outer finished surface.

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Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 8.1.3 Structural and Pressure Tests 8.1.3.1 Lifting Device Load Testing 8.1.3.2 Containment Boundary Pressure Testing 10 CFR 71.85(b) stipulates testing the containment system at an internal pressure at least 50 percent higher than the MNOP, if the MNOP exceeds 5 psi. As stated in Section 3.3.2, Maximum Normal Operating Pressure, the MNOP is 5 psi. Therefore the containment system does not require a pressure test.

8.1.4 Leakage Tests The containment boundary consists of a welded cylindrical steel shell plus top and bottom plates welded to the shell. The welds which are used to fabricate the shell and the top and bottom covers along with the closure joint welds between the shell and covers undergo examinations as stated in Sections 8.1.1, Visual Inspection and Measurements and 8.1.2, Weld Examinations in order to ensure that the welds are sound and continuous. [

] As concluded in Section 4.2, Containment under Normal Conditions of Transport, the package integrity under NCT provides assurance that the radioactive materials will remain contained in the package and that there is no release of radioactive materials under any of the NCT tests described in 10 CFR 71.71. The discussion in Section 4.3, Containment under Hypothetical Accident Conditions, shows that in the event of a partial loss of containment under HAC, the released radioactivity levels are within the limits of 10 CFR 71. As a result, leakage rate tests are not applicable to the CR3MP.

8.1.5 Component and Material Tests 8.1.5.1 Steel Shell, Covers and Welds The containment shell and top and bottom covers consist of a welded steel enclosure used for the transportation and disposal of the RPV. Plate material is to be provided with certified mechanical and chemical test reports in compliance with the SAR drawing in Appendix 1.3.2, Packaging General Arrangement Drawings. In addition, material tests of the base metal and weld filler metal are completed in compliance with the SAR drawing. 8.1-2

Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 8.1.5.2 Low Density Cellular Concrete Both the LDCC within the RPV and that between the CR3MP interior shell and the outside of the RPV shall have both density and compressive strength confirmed. A minimum of two sample cylinders are to be molded for each LDCC placement using ASTM C495 [3] for guidance. The wet cast density is measured and recorded using guidance from ASTM C567 [4]

at the point of placement. The mix is adjusted as required in order to obtain the specified cast density of 30-60 pcf. The minimum compressive strength of the LDCC is to be 100 psi at 7 days when tested in accordance with ASTM C495 [3]. Prior to aeration, the LDCC slurry density is measured and recorded in order to obtain a minimum slurry density of 105 pcf.

8.1.5.3 High Density Cellular Concrete The HDCC within the RPV, if used, shall have both the density and compressive strength confirmed. A minimum of two sample cylinders are to be molded for each HDCC placement using ASTM C495 [3] for guidance. The wet cast density is measured and recorded using guidance from ASTM C567 [4] at the point of placement. The mix is adjusted as required in order to obtain the specified cast density of 130-140 pcf. The minimum compressive strength of the HDCC is to be 100 psi at 7 days when tested in accordance with ASTM C495 [3].

8.1.6 Shielding Tests As discussed below, shielding tests prior to final acceptance for shipment are not required for the CR3MP. CR3MP fabrication is performed in accordance with the OFS QA Program, which provides assurance that the as-built package is constructed in compliance with the design requirements described in this SAR. The controlled processes for loading the package described in Section 7.1, Procedures for Loading the Package, the weld examinations described in Sections 8.1.1, Visual Inspection and Measurements and 8.1.2, Weld Examinations, and the pre-shipment dose rate surveys discussed in Section 7.1.3, Preparation of the CR3MP for Transport, confirm the adequacy of the shielding as required by the package design.

Moreover, Chapter 5.0, Shielding Evaluation, provides calculated dose rates that are based upon a bounding estimate of the contents and the package built to the certified design using certified materials. Notably, the calculated dose rates are bounded by the regulatory limits defined in 10 CFR 71.47 [1].

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Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 8.1.7 Thermal Tests Tests to demonstrate the heat transfer capability of the CR3MP are not required because the thermal evaluations presented in Chapter 3.0, Thermal Evaluation, are based on conservative heat transfer properties and methodologies. In addition, the CR3MP design does not incorporate active heat transfer features nor are passive heat transfer mechanisms particularly sensitive to normal variations in the materials of construction or fabrication methods. As such, the CR3MP is capable of withstanding temperatures within its design envelope, therefore thermal testing is not applicable. See Chapter 3.0, Thermal Evaluation for further discussions.

8.1.8 Miscellaneous Tests No additional tests are necessary to be performed prior to use of the CR3MP.

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Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 8.2 Maintenance Program No maintenance program is applicable to the CR3MP since the CR3MP is a single-shipment package used for transportation and disposal of the CR3 RPV and RVI.

8.2.1 Structural and Pressure Tests Not applicable. A maintenance program and associated tests are not required for this package.

8.2.2 Leakage Tests Not applicable. A maintenance program and associated tests are not required for this package.

8.2.3 Component and Material Tests Not applicable. A maintenance program and associated tests are not required for this package.

8.2.4 Thermal Tests Not applicable. A maintenance program and associated tests are not required for this package.

8.2.5 Miscellaneous Tests Not applicable. A maintenance program and associated tests are not required for this package.

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Docket No. 71-9393 CR3MP Safety Analysis Report Rev. 1, January 2022 8.3 Appendix 8.3.1 References

1. Title 10 - Energy, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-20 Edition.

2. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, Division 1 - Subsection ND, Class 3 Components, 2017 Edition.

3. ASTM C495/C495M - 12, Standard Test Method for Compressive Strength of Lightweight Insulating Concrete, American Society for Testing and Materials (ASTM), 2012.

4. ASTM C567 - 19, Standard Test Method for Determining Density of Structural Lightweight Concrete, American Society for Testing and Materials (ASTM), 2019.

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