ML22252A038

0045-BSH-2020-001, Rev. 2 - Safety Analysis Report for the DN30-X Package

ML22252A038
Person / Time
Site:	07109388
Issue date:	09/09/2022
From:	Hennebach M Orano NCS GmbH
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML22252A036	List: ML22252A037 ML22252A038 ML22252A039
References
0045-SVK-2022-001, EPID L-2020-NEW-0003 0045-BSH-2020-001 Rev. 2
Download: ML22252A038 (172)

Text

Safety Analysis Report for the DN30-X Package 0045-BSH-2020-001 Rev. 2 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH Prepared Checked Released M. Hennebach Y. van Wijk F. Hilbert September 09, 2022 September 09, 2022 September 09, 2022 1 / 172

0045-BSH-2020-001 Rev. 2 Table of Contents List of Revisions 6 List of Abbreviations 7 List of Tables 8 List of Figures 10 Literature 12 PART 1 GENERAL INFORMATION 1.1 List and Status of Documents Pertaining to this SAR 15 1.2 Administrative Information 16 1.2.1 Name of Package.................................................................................................................... 16 1.2.2 Identification of Package Designer ......................................................................................... 16 1.2.3 Type of Package Design ......................................................................................................... 16 1.2.4 Shipping Name and UN Number ............................................................................................ 17 Geistiges Eigentum der Orano NCS GmbH 1.2.5 Criticality Safety Index ............................................................................................................ 17 1.2.6 Package Design Identification and Restrictions ...................................................................... 17 1.2.7 Modes of Transport for which the Package is Designed ........................................................ 17 1.2.8 Lowest Transport Temperature for which the Package is Designed ...................................... 17 Property of Orano NCS GmbH 1.2.9 Maximum Normal Operating Pressure ................................................................................... 18 1.2.10 Maximal Standardized Helium Leakage Rate ......................................................................... 18 1.2.11 Reference to Applicable Regulations and Standards ............................................................. 18 1.3 Specification of the Radioactive Contents 19 1.3.1 General Specification of UF6 grade HALEU 10 and HALEU 20 ............................................. 19 1.3.2 Permissible Contents for the DN30-X Package ...................................................................... 21 1.4 Specification of the Packaging 28 1.4.1 List of all Packaging Components and Complete Design Drawings....................................... 28 1.4.2 Description of the DN30-X Packaging .................................................................................... 33 1.4.3 Components of the Packaging Relevant for the Containment System................................... 44 1.4.4 Components of the Packaging Relevant for Shielding ........................................................... 44 1.4.5 Components of the Packaging Relevant for the Confinement System................................... 45 1.4.6 Components of the Packaging Relevant for Thermal Protection ............................................ 45 1.4.7 Components of the Packaging Relevant for Heat Dissipation ................................................ 45 1.4.8 Protection against Corrosion ................................................................................................... 45 1.4.9 Protection Against Contamination........................................................................................... 45 1.4.10 Shock Absorbing Components of the Packaging ................................................................... 46 1.4.11 Evaluation of the Impact of Aging Mechanisms ...................................................................... 46 1.4.12 Transport Concept .................................................................................................................. 47 2 / 172

0045-BSH-2020-001 Rev. 2 1.5 Package Performance Characteristics 48 1.5.1 Main Design Principles ........................................................................................................... 48 1.5.2 Performance Characteristics ................................................................................................... 48 1.5.3 Assumptions Used for the Safety Analysis ............................................................................. 49 1.6 Compliance with Regulatory Requirements 50 1.6.1 Compliance with 10 CFR Part 71............................................................................................ 50 1.6.2 Compliance with 49 CFR Part 173.......................................................................................... 59 1.7 Operation 68 1.7.1 Testing Requirements and Controls before first Use .............................................................. 68 1.7.2 Testing Requirements and Controls before each Transport ................................................... 68 1.7.3 Handling and Tie-down Requirements ................................................................................... 71 1.7.4 Loading Procedures for the 30B-X Cylinder and the DN30 PSP ............................................ 71 1.7.5 Supplementary Equipment and Operational Controls ............................................................ 72 1.7.6 Precautions and Measures because of the other Dangerous Properties of the Content ....... 72 1.8 Inspection 73 1.8.1 Annual Inspection Requirements for the DN30 PSP .............................................................. 73 Geistiges Eigentum der Orano NCS GmbH 1.8.2 5-year Inspection Requirements for the 30B-X Cylinder and the DN30 PSP ......................... 73 1.9 Management System 75 1.9.1 Design, SAR, Documentation and Records ............................................................................ 75 Property of Orano NCS GmbH 1.9.2 Manufacturing and Testing ..................................................................................................... 76 1.9.3 Operation ................................................................................................................................ 77 1.9.4 Maintenance and Repair ......................................................................................................... 78 1.9.5 Compliance of any Activity with the SAR ................................................................................ 78 1.9.6 Deviations ............................................................................................................................... 78 1.9.7 Safety Elements ...................................................................................................................... 78 1.10 Package Illustration 80 PART 2 TECHNICAL ANALYSES 2.1 Introduction 83 2.1.1 Guideline through Technical Analyses ................................................................................... 83 2.1.2 Common Provisions for all Technical Analyses ...................................................................... 88 2.2 Structural Analysis 94 2.2.1 Objective of Verification .......................................................................................................... 94 2.2.2 Basic Assumptions for the Calculations .................................................................................. 95 2.2.3 Normal Operating Conditions for the 30B-X Cylinder ............................................................. 99 2.2.4 Handling of the DN30-X Package ......................................................................................... 100 2.2.5 Ability of the DN30-X Package to Withstand RCT ................................................................ 101 2.2.6 Ability of the DN30-X Package to Withstand NCT ................................................................ 102 3 / 172

0045-BSH-2020-001 Rev. 2 2.2.7 Ability of the DN30-X Package to Withstand NCT and HAC ................................................ 104 2.3 Thermal Analysis 117 2.3.1 Objective of Verification ........................................................................................................ 117 2.3.2 Admissible Component Temperatures of the DN30-X Package .......................................... 118 2.3.3 Prototype Fire Tests .............................................................................................................. 121 2.3.4 Thermal Analysis of the DN30-X Package ........................................................................... 121 2.3.5 Proof for the DN30-X Package to Meet the Regulatory Requirements ................................ 132 2.4 Containment Design Analysis 134 2.4.1 Objective of verification ......................................................................................................... 134 2.4.2 Calculation Method and Assumptions .................................................................................. 135 2.4.3 Summary and Evaluation of Results ..................................................................................... 135 2.5 External Dose Rate Analysis 136 2.5.1 Objective of Verification ........................................................................................................ 136 2.5.2 Assumptions for the Calculations .......................................................................................... 137 2.5.3 Calculation Method, its Verification and Validation ............................................................... 138 2.5.4 Gamma and Neutron Source Terms ..................................................................................... 138 2.5.5 Model Specification ............................................................................................................... 138 Geistiges Eigentum der Orano NCS GmbH 2.5.6 Verification of Compliance with Dose Rate Limits ................................................................ 141 2.5.7 Summary and Evaluation of Results ..................................................................................... 143 2.6 Criticality Safety Analysis 144 Property of Orano NCS GmbH 2.6.1 Objective of Proof.................................................................................................................. 144 2.6.2 Assumptions for the Proof of Criticality Safety ...................................................................... 144 2.6.3 Calculation Method, Verification and Validation ................................................................... 146 2.6.4 Material Compositions .......................................................................................................... 147 2.6.5 Calculation Models ................................................................................................................ 148 2.6.6 Proof of Criticality Safety for the Single Package in Isolation ............................................... 152 2.6.7 Proof of Criticality Safety for the Infinite Array of Packages ................................................. 153 2.6.8 Summary and Evaluation of Results ..................................................................................... 154 Appendix 1.1 (List of Applicable Documents) 155 Appendix 1.4.1A (Drawings 30B-X Cylinder) 156 Appendix 1.4.1B (Drawings DN30 PSP) 157 Appendix 1.4.2 (Material Properties) 158 Appendix 1.7.1 (Handling Instruction) 159 Appendix 1.7.2 (Contamination and Dose Rate Measurements) 160 Appendix 1.7.3 (30B-X Cylinder Facility Operations) 161 Appendix 1.8.1 (Inspections of 30B-X Cylinders) 162 4 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.8.2 (Inspections of DN30 PSPs) 163 Appendix 1.9.1 (IMS) 164 Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) 165 Appendix 1.9.2B (Manufacturing Specification DN30 PSP) 166 Appendix 1.9.3 (Quality Assurance Program) 167 Appendix 2.2 (Structural Analysis) 168 Appendix 2.3 (Thermal Analysis) 169 Appendix 2.4 (Containment Analysis) 170 Appendix 2.5 (External Dose Rate Analysis) 171 Appendix 2.6 (Criticality Safety Analysis) 172 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 5 / 172

0045-BSH-2020-001 Rev. 2 List of Revisions Revision Date of revision Modifications 0 June 29, 2021 Original 1 October 7, 2021

• Amended the definition of the permissible content in section 1.3.

• Amended the material specification for the interior criticality control system in section 1.4.1.1.3.

• Reorganized the description of the 30B-X cylinder in section 1.4.2.1 and added section 1.4.2.1.4, covering additional provisions to ANSI N14.1.

• Amended section 1.7.4.1 by also discussing potential impacts on the filling, emptying, and washing operations of the 30B-X cylinder because of the presence of the interior criticality control system.

• Update of results of dose rate analysis in section 2.5 for permissible content weights of final cylinder designs.

2 September 09, 2022

• Addition of responses to the NRC requests for additional information (RAIs) dated June 10th 2022 Geistiges Eigentum der Orano NCS GmbH

• Complete revision to create a standalone and self-contained SAR without references to the SAR for the DN30 package. All necessary information from the DN30 SAR was transferred to this document and its appendices without change.

Property of Orano NCS GmbH 6 / 172

0045-BSH-2020-001 Rev. 2 List of Abbreviations BAM Bundesanstalt für Materialforschung und- prüfung (German Federal Institute for Material Research and Testing)

BPVC Boiler and Pressure Vessel Code CCR Criticality Control Rod CCS Criticality Control System CSI Criticality Safety Index HAC Hypothetical Accident Conditions HALEU High-Assay Low-Enriched Uranium IMS Integrated Management System MAWP Maximum Allowable Working Pressure MNOP Maximum Normal Operating Pressure MTSP Manufacturing and Test Sequence Plan NCT Normal Conditions of Transport ONCS Orano NCS GmbH PIR Polyisocyanurate PSP Protective Structural Packaging QA Quality Assurance RCT Routine Conditions of Transport SAR Safety Analysis Report TI Transport Index Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 7 / 172

0045-BSH-2020-001 Rev. 2 List of Tables Table 1-1 UF6 properties ................................................................................................... 20 Table 1-2 Isotopic limits of UF6 grade HALEU 10 and HALEU 20 ...................................... 21 Table 1-3 Activity limits for heels of UF6 grade HALEU 10 and HALEU 20 ........................ 21 Table 1-4 Permissible mass of UF6 for each package design ............................................ 21 Table 1-5 Mass of fissile material for each DN30-X package design ................................. 22 Table 1-6 Heat generation rate of UF6 ............................................................................... 23 Table 1-7 Calculation scenario of the radioactivity in 30B-X cylinders for contents complying with HALEU 10 and HALEU 20 for a continuous use without washing ............................................................................................................. 25 Table 1-8 Radioactivity in 30B-10 and 30B-20 cylinders for a 3-month filled/heeled cycle followed by a 10-year storage of filled cylinders ........................................ 26 Table 1-9 Material specification of the 30B-X cylinder ....................................................... 30 Table 1-10 Material specification of valve and plug of the 30B-X cylinder ............................ 30 Table 1-11 Material specification of interior CCS of the 30B-X cylinder ............................... 31 Table 1-12 Material specification of the DN30 PSP ............................................................. 32 Table 1-13 Main data of the 30B-X cylinder ......................................................................... 36 Table 1-14 Main data of the DN30 PSP ............................................................................... 38 Table 1-15 Safety elements ................................................................................................. 79 Geistiges Eigentum der Orano NCS GmbH Table 2-1 Provisions for the UF6 content of the DN30-X package used in the technical analyses ............................................................................................................ 89 Table 2-2 Provisions for the 30B-X cylinder used in the technical analyses ....................... 90 Property of Orano NCS GmbH Table 2-3 Provisions for the DN30 PSP used in the technical analyses ............................. 91 Table 2-4 Load assumptions for handling .......................................................................... 96 Table 2-5 Load assumptions for RCT ................................................................................ 96 Table 2-6 Load assumptions for NCT ................................................................................ 97 Table 2-7 Load assumptions for HAC ................................................................................ 98 Table 2-8 Corner drop onto the valve side from a height of 10.2 m - Measured distances at the impact zone after the drop test ............................................... 108 Table 2-9 Safety margins for the pressure build-up inside the 30B-X cylinder ................. 119 Table 2-10 Safety margins for the required wall thickness of the 30B-X cylinder ............... 119 Table 2-11 Admissible component temperatures of the DN30-X package ......................... 120 Table 2-12 Solar insolation ................................................................................................ 122 Table 2-13 Maximum temperatures for NCT at the DN30-X package for 12-hour insolation / no insolation cycles ........................................................................ 123 Table 2-14 Maximum temperatures for HAC at the DN30-X package loaded with an empty 30B-X cylinder....................................................................................... 125 Table 2-15 Maximum temperatures for HAC at the DN30-X package loaded with a full 30B-X cylinder ................................................................................................. 128 Table 2-16 Maximum temperatures calculated for HAC at the DN30-X package loaded with a partially filled 30B-X cylinder.................................................................. 130 Table 2-17 Overview for the sensitivity analyses ............................................................... 131 Table 2-18 Permissible standardized helium leakage rates under NCT ............................. 135 8 / 172

0045-BSH-2020-001 Rev. 2 Table 2-19 Maximal total dose rates under RCT at a distance of 1 m from the external surface of the package - DN30-X package loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20.................................................................................. 141 Table 2-20 Maximal total dose rates under RCT at the surface of the package -

DN30-X package loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 ............... 141 Table 2-21 Maximal total dose rates under RCT at the external surface of a vehicle loaded with DN30-X packages each loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 ....................................................................................................... 142 Table 2-22 Maximal total dose rates under RCT at a distance of 2 m from the external surface of a vehicle transporting four DN30-X packages each loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 .............................................................. 142 Table 2-23 CCR numbers, ring diameters and lengths for the 30B-10 and the 30B-20 ...... 149 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 9 / 172

0045-BSH-2020-001 Rev. 2 List of Figures Figure 1-1 CORROSIVE and POISON placard ................................................................... 24 Figure 1-2 Radioactivity in 30B-10 and 30B-20 cylinders in comparison to 30B cylinders for a 3-month filled/heeled cycle followed by a 10-year storage of filled/heeled cylinders ........................................................................................ 27 Figure 1-3 30B-X cylinder - Outside view ........................................................................... 33 Figure 1-4 30B-X cylinder - Interior criticality control system .............................................. 34 Figure 1-5 30B-X cylinder - Cross sectional view ............................................................... 35 Figure 1-6 Lifting of the DN30-X package by using the 4 lifting lugs ................................... 41 Figure 1-7 Lifting of the DN30-X package by using a forklift................................................ 42 Figure 1-8 Lifting of the empty DN30 PSP by using slings .................................................. 42 Figure 1-9 Lifting of the top half of the DN30-X packaging .................................................. 43 Figure 1-10 General tie-down method for the DN30-X package / DN30 PSP ........................ 44 Figure 1-11 Tie-down of the empty DN30 PSP using straps ................................................. 44 Figure 1-12 DN30-X Package Overview ............................................................................... 80 Figure 1-13 DN30 PSP bottom half....................................................................................... 81 Figure 1-14 30B-X cylinder - Outside view ........................................................................... 81 Figure 2-1 Corner drop onto the valve side from a height of 10.2 m - State with the maximal deformation of the DN30-X and DN30 package ................................. 107 Geistiges Eigentum der Orano NCS GmbH Figure 2-2 Measured distances for the corner drop onto the valve side ............................ 107 Figure 2-3 Flat drop onto the valve side under NCT - Comparison of equivalent plastic strain at the cylinder pressure envelope........................................................... 111 Property of Orano NCS GmbH Figure 2-4 Temperature development of an empty DN30-X package for NCT during 12-hours insolation / no insolation cycles ......................................................... 124 Figure 2-5 Temperatures at the DN30-X package for HAC with an empty 30B-X cylinder ............................................................................................................ 125 Figure 2-6 Temperature distribution for the empty DN30-X package for HAC at the time when the maximum temperature is reached for the valve (t = 10296 s or ~172 min) .................................................................................................... 126 Figure 2-7 Temperature distribution for the empty DN30-X package for HAC at the time when the maximum temperature difference between 30B-X pressure envelope and CCS is reached (t = 6096 s or ~102 min)................................... 126 Figure 2-8 Temperatures at the DN30-X package for HAC with a full 30B-X cylinder ....... 127 Figure 2-9 Temperature distribution for the full DN30-X package for HAC at the time when the maximum temperature is reached for the valve (t = 8489 s or

~141 min) ........................................................................................................ 128 Figure 2-10 Temperature distribution for the full DN30-X package for HAC at the time when the maximum temperature is reached for the UF6 (t = 8489 s or

~141 min) ........................................................................................................ 129 Figure 2-11 Temperatures calculated at the valve of the DN30-X package for HAC for different filling ratios (0, 50, and 100 %) ........................................................... 130 Figure 2-12 Cross section of the calculation model along the longitudinal axis ................... 139 Figure 2-13 Cross section of the calculation model perpendicular to the longitudinal axis .. 140 Figure 2-14 Calculation model of the 30B-X cylinder calculation model (without CCS) ....... 148 10 / 172

0045-BSH-2020-001 Rev. 2 Figure 2-15 Calculation models for the 30B-10 and 30B-20 cylinder................................... 149 Figure 2-16 Calculation model for the single package in isolation ....................................... 150 Figure 2-17 Calculation model for the infinite package array............................................... 151 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 11 / 172

0045-BSH-2020-001 Rev. 2 Literature

[10 CFR Part 71] Code of Federal Regulations Title 10 Part 71 Packaging and Transportation of Radioactive Material

[49 CFR Part 173] Code of Federal Regulations Title 49 Part 173 Shippers - General Requirements for Shipments and Packagings

[ANSI N14.1] Uranium Hexafluoride - Packaging for Transport, ANSI N14.1, 2019

[ANSI N14.5] Radioactive Materials - Leakage Tests on Packages for Shipment, ANSI N14.5, 2014

[ANSYS] ANSYS, Release 2021 R1, Help System, ANSYS, Inc

[ASME BPVC] ASME Boiler and Pressure Vessel Code, 2019 Edition

[ASTM A333] ASTM A333 / A333M-18, Standard Specification for Seamless and Welded Steel Pipe for Low-Temperature Service and Other Applications with Re-quired Notch Toughness, ASTM International, West Conshohocken, PA, 2018, www.astm.org

[ASTM A516] ASTM A516 / A516M-17, Standard Specification for Pressure Vessel Plates, Carbon Steel, for Moderate- and Lower-Temperature Service, ASTM International, West Conshohocken, PA, 2017, www.astm.org Geistiges Eigentum der Orano NCS GmbH

[ASTM C996] ASTM C996-20, Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U, ASTM International, West Conshohocken, PA, 2020, www.astm.org

[DIN EN 10028-3] Flat products made of steels for pressure purposes - Part 3: Weldable fine Property of Orano NCS GmbH grain steels, normalized, October 2017

[DIN EN 10088-2] Stainless steels - Part 2: Technical delivery conditions for sheet/plate and strip of corrosion resisting steels for general purposes, December 2014

[DIN EN 10088-3] Stainless steels - Part 3: Technical delivery conditions for semi-finished products, bars, rods, wire, sections and bright products of corrosion resist-ing steels for general purposes, December 2014

[DIN EN 10216-3] Seamless steel tubes for pressure purposes - Technical delivery condi-tions - Part 3: Alloy fine grain steel tubes, March 2014

[Harris Sn50] Technical Information Sheet 50/50 Tin Lead Solder - The Harris Products Group, 2017

[ISO 12807] Safe transport of radioactive materials - Leakage testing on packages, ISO 12807, September 2018

[ISO 7195] ISO 7195, Nuclear Energy - Packagings for the transport of uranium hex-afluoride (UF6 ), Third edition, November 2020

[MILIN 2016] Milin M. et al, Hydration of uranium residues contained in enriched UF6 cyl-inders, Proceedings PATRAM 2016, Kobe, September 2016

[NEA 2019] International Handbook of Evaluated Criticality Safety Benchmark Experi-ments, NEA, July 2019 Edition, NEA/NSC/DOC(95)03 12 / 172

0045-BSH-2020-001 Rev. 2

[NUREG 2216] Standard Review Plan for Transportation Packages for Spent Fuel and Ra-dioactive Material, U.S. NRC, Office of Nuclear Material Safety and Safe-guards, NUREG-2216, August 2020

[SCALE 2011] SCALE 6.1, Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory, 2011

[SCALE 2020] SCALE 6.2.4, SCALE Code System, ORNL/TM-2005/39, Version 6.2.4, Oak Ridge National Laboratory, 2020

[SSG-26 2012] Advisory Material for the IAEA Regulations for the Safe Transport of Radio-active Material (2012 Edition), Specific Safety Guide No. SSG-26, IAEA, Vienna, 2014

[SSR-6 2018] Regulations for the Safe Transport of Radioactive Material, 2018 Edition, SSR-6 Rev. 1, IAEA, Vienna, 2018

[USEC 651] The UF6 Manual - Good Handling Practices for Uranium Hexafluoride, Rev. 9, USEC, 2006 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 13 / 172

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH PART 1 GENERAL INFORMATION 14 / 172 0045-BSH-2020-001 Rev. 2

0045-BSH-2020-001 Rev. 2 1.1 List and Status of Documents Pertaining to this SAR The list of applicable documents and their status pertaining to this safety analysis report (SAR) is included in Appendix 1.1 (List of Applicable Documents).

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 15 / 172

0045-BSH-2020-001 Rev. 2 1.2 Administrative Information 1.2.1 Name of Package The package is designated DN30-X and consists of the DN30 protective structural packag-ing (PSP) and the 30B-X cylinder. The X in DN30-X and 30B-X is either replaced by 10 or by 235 20 to refer to a specific design for a maximal enrichment of 10 or 20 wt.-% U in uranium, respectively.

Since both the 30B-10 and the 30B-20 cylinder are transported in the same DN30 PSP that has been designed for the transport of standard 30B cylinders according to [ANSI N14.1], the follow-ing path is taken with respect to licensing of the DN30-X package:

• The designs of the 30B-10 and the 30B-20 cylinder shall be incorporated into a single pack-age approval for the DN30-X package.

• The package approval for the DN30-X package shall incorporate the allowable contents for each cylinder as specified in section 1.3.

• Already existing DN30 PSPs that have been manufactured for the transport of standard 30B cylinders according to [ANSI N14.1] are allowed to be used for the transport of 30B-10 and 30B-20 cylinders as well.

Geistiges Eigentum der Orano NCS GmbH 1.2.2 Identification of Package Designer The designer and license holder of the DN30-X package is:

Property of Orano NCS GmbH Orano NCS GmbH Margarete-von-Wrangell-Strae 7 D-63457 Hanau Germany The principal contact is:

Name: Mr. Franz Hilbert Tel: +49 6181 501-232 Fax: +49 6181 501-266 E-mail: franz.hilbert@orano-ncs.com In this report, Orano NCS GmbH is designated ONCS.

1.2.3 Type of Package Design The DN30-X package, loaded with the allowable content as described in section 1.3, fulfills the requirements of [10 CFR Part 71] and [49 CFR Part 173], as well as [SSR-6 2018] for a Type AF package for uranium hexafluoride (UF6 )

containing UF6 grade HALEU in less than or equal to A2 quantities:

235

• For the DN30-10, the maximal allowed enrichment is 10 wt.-% U in uranium.

235

• For the DN30-20, the maximal allowed enrichment is 20 wt.-% U in uranium.

16 / 172

0045-BSH-2020-001 Rev. 2 1.2.4 Shipping Name and UN Number For the DN30-X package containing fissile UF6, the proper shipping name and UN number Radioactive material, uranium hexafluoride, fissile, UN 2977 is used as prescribed in [49 CFR Part 173] §420(e).

1.2.5 Criticality Safety Index For the DN30-X package, the criticality safety index (CSI) is:

CSI = 0 1.2.6 Package Design Identification and Restrictions A unique serial number is assigned to each DN30 PSP valid for its entire operation time. This number is stamped on the nameplate that is used for the already licensed DN30 package under the entry Serial No. (cf. Appendix 1.4.1B (Drawings DN30 PSP), drawing 0023-ZFZ-1000-001).

The serial number has the following pattern:

XX-YYYY-ZZZZ Where:

Geistiges Eigentum der Orano NCS GmbH XX = designation of the fabricator (abbreviation assigned by ONCS)

YYYY = year of manufacturing Property of Orano NCS GmbH ZZZZ = sequential number The list of all serial numbers is managed and filed by ONCS. All users of the DN30-X packaging will be requested to update the status of the individual packaging after completion of the regular periodical inspections. Packagings with overdue periodical inspections (more than 1-year over-due) will be marked in that list as not in use.

Each individual DN30 PSP may be marked with an owner serial number different from the man-ufacturer serial number. This owner serial number may be marked on the nameplate under the entry Owners Serial No. or on an additional nameplate attached to the DN30 PSP. The owner serial number may change whenever required by the owner.

1.2.7 Modes of Transport for which the Package is Designed

• The DN30-X package is designed for transport by road, rail, sea, and inland waterways.

• Transport by air is not permitted.

• Hump shunting of wagons transporting the DN30-X packages is not allowed.

1.2.8 Lowest Transport Temperature for which the Package is Designed The lowest transport temperature allowed for the DN30-X package is -40 °C.

17 / 172

0045-BSH-2020-001 Rev. 2 1.2.9 Maximum Normal Operating Pressure The maximum normal operating pressure (MNOP) for the DN30-X package is defined as the pressure at the triple point of UF6 (see table 1-1):

MNOP = 152 kPa Note: the maximum allowable working pressure (MAWP) of the 30B-X cylinder is specified with regard to the requirements of [ANSI N14.1] as 1.38 MPa. This definition of the MAWP only applies to the use of the 30B-X cylinder in the enrichment and fuel fabrication process and not for its use as part of the DN30-X package.

1.2.10 Maximal Standardized Helium Leakage Rate With reference to [ANSI N14.1], the maximal standardized helium leakage rate of the 30B-X cyl-inder is specified as:

N(SLR) = 1 104 Pa m3 s 1.2.11 Reference to Applicable Regulations and Standards The safety proof of the DN30-X package is based on the following regulations and standards:

Geistiges Eigentum der Orano NCS GmbH

• [10 CFR Part 71] Code of Federal Regulations Title 10 Part 71, Packaging and Transpor-tation of Radioactive Material

• [49 CFR Part 173] Code of Federal Regulations Title 49 Part 173, Shippers - General Re-Property of Orano NCS GmbH quirements for Shipments and Packagings

• [ANSI N14.1] American National Standard, For Nuclear Materials - Uranium Hexafluoride

- Packagings for Transport, ANSI N14, 2019-12-05

• [ISO 7195] Nuclear Energy - Packagings for the transport of uranium hexafluoride (UF6 ),

Third edition, November 2020

• [SSR-6 2018] Regulations for the Safe Transport of Radioactive Material, 2018 Edition, SSR-6, Rev. 1, International Atomic Energy Agency (IAEA), Vienna, 2018 In the remainder of this SAR, reference is only made to [ANSI N14.1]. However, unless stated otherwise, references to [ANSI N14.1] always include [ISO 7195] as well.

18 / 172

0045-BSH-2020-001 Rev. 2 1.3 Specification of the Radioactive Contents The allowable content of the DN30-X packaging is uranium in the chemical composition UF6 with 235 maximal enrichments of 10 and 20 wt.-% U in uranium. In the context of this SAR, the allowable content is designated:

235

• HALEU 10 for an enrichment of 10 wt.-% U in uranium 235

• HALEU 20 for an enrichment of 20 wt.-% U in uranium A general specification of HALEU 10 and HALEU 20 defining the impurity and uranium isotope limits is provided in section 1.3.1. Based on this general specification, the permissible contents for the DN30-10 and DN30-20 package are specified in section 1.3.2.

1.3.1 General Specification of UF6 grade HALEU 10 and HALEU 20 This general specification of UF6 grade HALEU 10 and HALEU 20 covers nuclear grade UF6 that has been processed through an enrichment plant and that is intended for fuel fabrication. It cor-responds to a large extent to [ASTM C996] and the objective of this specification is to define the impurity and uranium isotope limits for HALEU 10 and HALEU 20 that can be transported in the DN30-10 and DN30-20 package, respectively.

Geistiges Eigentum der Orano NCS GmbH 1.3.1.1 Terminology In the following specification of the permissible contents of the DN30-X package, the definitions of terms defined in [ASTM C996], section 3 are used.

Property of Orano NCS GmbH 1.3.1.2 Origin of Material HALEU 10 and HALEU 20 shall be enriched from Commercial Natural UF6 . Neither Reprocessed nor Derived Enriched UF6 shall be used for HALEU 10 and HALEU 20.

1.3.1.3 Safety, Health Physics and Criticality Requirements The safety, health, and criticality requirements for HALEU 10 and HALEU 20 are identical to the requirements provided in [ASTM C996], section 4 for Enriched Commercial Grade UF6 with a 235 maximal enrichment of 5 wt.-% U in uranium:

(1) The UF6 concentration shall not be less than 99.5 g UF6 per 100 g of sample in order to limit the potential hydrogen content for nuclear criticality safety.

(2) The total absolute vapor pressure shall not exceed the following values:

• 380 kPa at 80 °C (55 psia at 176 °F), or

• 517 kPa at 93 °C (75 psia at 200 °F), or

• 862 kPa at 112 °C (125 psia at 235 °F)

Additionally, if a measurement is taken over solid UF6 , the vapor pressure shall not exceed the following values:

• 50 kPa at 20 °C (7 psia at 68 °F), or

• 69 kPa at 35 °C (10 psia at 95 °F) 19 / 172

0045-BSH-2020-001 Rev. 2 The purpose of the pressure check is to limit the hydrogen fluoride, air, or other volatile compo-nents that might cause overpressure when heating the 30B-10 or 30B-20 cylinder (see

[ASTM C996], section 4.2 for further details).

(3) The total hydrocarbon, chlorocarbon, and partially substituted halohydrocarbon content shall not exceed 0.01 mol % of the UF6 . The reason for the exclusion of these materials is to prevent a vigorous reaction with UF6 upon heating (see [ASTM C996], section 4.3 for further details).

(4) For HALEU 10 and HALEU 20 meeting the requirements of section 1.3.1.4, the gamma ac-tivity from fission products and the alpha activity from neptunium and plutonium are expected to be below the detection limits (see [ASTM C996], section 4.4 for further details).

1.3.1.4 Chemical, Physical and Isotopic Requirements Table 1-1 shows the most relevant properties of UF6 extracted from [USEC 651].

Table 1-1 UF6 properties Metric Imperial Property Value Unit Value Unit Density solid at 20 °C (68 °F) 5.09 g/cm³ 317.8 lb/ft³ Density liquid at 64.1 °C (147.3 °F) 3.65 g/cm³ 227.7 lb/ft³ Geistiges Eigentum der Orano NCS GmbH Density liquid at 121 °C (250 °F) 3.26 g/cm³ 203.3 lb/ft³ Sublimation point at 101 kPa (14.7 psia) 56.6 °C 133.8 °F Triple point at 152 kPa (22 psia) 64.1 °C 147.3 °F Property of Orano NCS GmbH Heat of sublimation at 64.1 °C (147.3 °F) 135 kJ/kg 58.2 BTU/lb Heat of fusion at 64.1 °C (147.3 °F) 56 kJ/kg 23.5 BTU/lb Heat of vaporization at 64.1 °C (147.3 °F) 81 kJ/kg 35.1 BTU/lb Critical pressure 4610 kPa 668.8 psia Critical temperature 230.2 °C 446.4 °F Specific heat, solid at 27 °C (81 °F) 477 J/(kg K) 0.114 BTU/(lb °F)

Specific heat, liquid at 72 °C (162 °F) 544 J/(kg K) 0.130 BTU/(lb °F)

The chemical, physical and isotopic requirements for HALEU 10 and HALEU 20 are based on

[ASTM C996], section 5.

(1) Both HALEU 10 and HALEU 20 must meet the specification criteria. Except for the isotopes given in table 1-2, but including artificially created radioactive species, limits are set so as to have no special impact on the use of this material in existing facilities (see [ASTM C996], section 5.1 for further details).

(2) The following impurities shall not exceed these values:

Boron: 4 µg/gU Silicon: 250 µg/gU (3) HALEU 10 and HALEU 20 shall comply with the limits given in table 1-2. For purposes of determining conformance with these limits, the observed values shall be rounded to the nearest significant digit indicated as described in [ASTM C996], section 5.5.

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0045-BSH-2020-001 Rev. 2 Table 1-2 Isotopic limits of UF6 grade HALEU 10 and HALEU 20 Maximal concentration in wt.-% in uranium Nuclide Enriched Commercial Grade1) HALEU 10 HALEU 20 232 1 108 3 108 7 108 U

234 5.5 102 1.2 101 2.6 101 U

235 U 5 10 20 236 2.5 102 5.0 102 1.0 101 U

238 U rest rest rest 99 1.0 106 1.0 106 1.0 106 Tc According to [ASTM C996], provided for information purposes only.

(4) Heels of HALEU 10 and HALEU 20 shall also comply with the limits given in table 1-2. Addi-tionally, the activity limits given in table 1-3 apply for heels of HALEU 10 and HALEU 20.

Table 1-3 Activity limits for heels of UF6 grade HALEU 10 and HALEU 20 Maximal activity in Bq Nuclide HALEU 10 HALEU 20 Geistiges Eigentum der Orano NCS GmbH 99 7 6.0 107 Tc1) 7.6 10 99 Calculated based on the maximal A2 value for Tc after a 5-year refilling cycle and 10 years of storage of a filled cylinder (see table 1-8).

Property of Orano NCS GmbH 1.3.2 Permissible Contents for the DN30-X Package 1.3.2.1 Permissible Mass of UF6 The permissible mass of UF6 and the maximum heel quantities for each package design are listed in table 1-4.

Table 1-4 Permissible mass of UF6 for each package design Package Enrichment limit Permissible mass of UF6 Maximum heel quantities design in wt.-% 235U in U in kg in kg DN30-10 10 1460 11.3 DN30-20 20 1271 11.3 Note: Todays cleaning processes for standard 30B cylinders achieve heel quantities below 2 kg on a regular basis, which leaves sufficient margins for the increased free surfaces of the 30B-10 and 30B-20 cylinder in comparison to the standard 30B cylinder. Calculating the ratios of the internal free surfaces of the 30B-X and the 30B cylinder given in table 1-13, heel quantities below 2 kg 20.01 m24.75 m2 = 8.5 kg and 2 kg 22.89 m24.75 m2 = 9.7 kg are expected for the 30B-10 and the 30B-20 cylinder, respectively. This allows for defining the same maximum heel quantities for the 30B-10 and 30B-20 cylinder as defined in [ANSI N14.1] for the standard 30B cylinder.

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0045-BSH-2020-001 Rev. 2 1.3.2.2 Non-Fissile and Fissile Material The uranium is classified as fissile material enriched from original uranium with natural isotopic 235 composition. The maximal enrichment in U for each package design is listed in table 1-4.

1.3.2.3 Mass of Fissile Material and Nuclides The mass of the fissile material for each package design is calculated from the permissible mass 235 of UF6 that is given in table 1-4 and the corresponding maximum enrichment in U according to the following equation:

235U fiss,X = UF6 ,X enrich,X (1)

(enrich,X 235U + (1 enrich,X ) 238U + 6 F )

235 238 In equation (1), 235U , 238U , and F are the atomic masses of U, U, and fluorine, respec-tively. The fissile masses calculated with equation (1) are listed in table 1-5.

Table 1-5 Mass of fissile material for each DN30-X package design Enrichment limit Mass of UF6 Fissile material Package design in kg in kg in wt.-% 235U in U DN30-10 10 1460 98 Geistiges Eigentum der Orano NCS GmbH DN30-20 20 1271 170 1.3.2.4 Special Form or Low Dispersible Radioactive Material Property of Orano NCS GmbH The radioactive content in the DN30-X package is neither in special form nor low dispersible.

1.3.2.5 Total Radioactivity The radioactive contents have a total radioactivity of less than or equal to 1 A2 . For filled cylinders, this is due to the unlimited A2 value of enriched uranium with natural isotopic composition U (en-riched to 20 % or less) according to [10 CFR Part 71] Appendix A. Furthermore, the analysis in section 1.3.2.11 shows that the DN30-X also complies with this limit when the 30B-X cylinders are regularly refilled without intermediate washing before loading.

1.3.2.6 Nature and Characteristics of the Radiation Emitted The radiation emitted by the content of the DN30-X package is mainly gamma radiation with a very small contribution from neutron radiation.

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0045-BSH-2020-001 Rev. 2 1.3.2.7 Limitation of the Heat Generation Rate of the Content The heat generation rate for an enrichment limit of 5 wt.-% 235U in uranium is based on a UF6 net weight of UF6 ,5 = 2277 kg. Using the isotopic composition given in table 1-2 and the permissible mass of UF6 UF6 ,X for the DN30-X as listed in table 1-4, the heat generation rates for maximum 235 enrichments of wt.-% U in uranium are calculated according to equation (2):

%,X UF6 ,X Gen,X = (2)

%,5 UF6 ,5 Gen,5 In equation (2), %,X refers to the content limit of each uranium isotope for an enrichment of wt.-% 235U in uranium. The corresponding content limit for an enrichment of 5 wt.-% is used as the reference. Table 1-6 shows the resulting heat generation rate of UF6 for maximum enrich-235 ments of 5, 10, and 20 wt.-% U in uranium.

For each enrichment limit, the most significant contribution is from 234U and the contribution to the thermal power from the traces of fission products and other actinides is negligible. For the thermal analysis in section 2.3, a heat generation rate of 3 W is assumed, safely covering the actual heat generation rate of the content of the DN30-X.

Table 1-6 Heat generation rate of UF6 Geistiges Eigentum der Orano NCS GmbH Heat generation rate in W Nuclide 235 235 235 5 wt.-% U in U1) 10 wt.-% U in U1) 20 wt.-% U in U1) 232 1.0 104 1.92 104 3.91 104 U

Property of Orano NCS GmbH 234 1.52 101 2.13 101 4.01 101 U

235 4.56 103 5.85 103 1.02 102 U

236 6.73 104 8.63 104 1.50 103 U

238 1.24 102 7.52 103 5.81 103 U

Total 1.70 101 2.27 101 4.19 101 The underlying isotopic limits are given in table 1-2.

1.3.2.8 Physical and Chemical State During transport, the UF6 contained in the DN30-X package is in solid form. UF6 reacts with most metals (nickel, Monel, copper, and aluminum) to create a fluoride of the metal and other uranium compounds. It heavily reacts with hydrocarbons so that the absence of hydrocarbons in empty 30B-X cylinders is essential before those are filled with UF6 .

UF6 does not react with nitrogen, oxygen, carbon dioxide or dry air. However, UF6 reacts strongly with water and water vapor in the air producing HF-H2 O fog. If inhaled, this fog is very harmful.

UF6 + 2H2 O UO2 F2 + 4HF The UF6 could contain some impurities that are due to chemical reactions. These impurities, like HF or UO2 F2 5.5 H2 O, are also considered in the criticality safety analysis (see section 2.6).

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0045-BSH-2020-001 Rev. 2 1.3.2.9 Other Dangerous Properties In accordance with 49 CFR Subpart F - Placarding, § 172.505 (b), UF6 is classified as corrosive and poisonous. Consequently, the CORROSIVE and POISON placard must be used alongside the RADIOACTIVE placard (see figure 1-1).

Figure 1-1 CORROSIVE and POISON placard 1.3.2.10 Permissible Conditions for Repeated Use 30B-X cylinders complying with their specification in section 1.4.1.1 and within their valid recerti-fication period as specified in section 1.8 may be refilled with content complying with the defini-tions in section 1.3.1 and 1.3.2. It is shown in section 1.3.2.11 that the DN30-X complies with the limit of 1 A2 for a Type AF package when the 30B-X cylinders are regularly refilled without inter-Geistiges Eigentum der Orano NCS GmbH mediate washing before loading.

1.3.2.11 Refilling of Cylinders Containing Heel Quantities Property of Orano NCS GmbH After emptying of 30B-X cylinders, heel quantities of UF6 might remain in the cylinder. In table 1-4, the heel quantities of UF6 are specified as maximal 11.3 kg for the 30B-10 and the 30B-20 cylin-der. With reference to [ANSI N14.1], a heel is defined as:

A heel is a residual amount of UF6 and/or nonvolatile reaction products of uranium According to [10 CFR Part 71] Appendix A or [SSR-6 2018] Table 2, the A2 values of natural ura-nium U(nat), enriched uranium with natural isotopic composition U(enriched to 20 % or less), and depleted uranium U(dep) are unlimited. Hence, all amounts of contents ranging from 0 kg up to the fill limits of the 30B-10 and 30B-20 cylinder specified in table 1-4 that comply with the content specifications in section 1.3 can be transported in the DN30-X package. However, subsequent refilling of 30B-X cylinders without washing before loading may lead to a build-up of decay products that contribute to the radioactivity relevant for the A2 value. This is investigated in the following.

Table 1-7 illustrates the calculation procedure, which is based on the covering inventories listed in table 1-4 assumed for the contents of the 30B-10 and 30B-20 cylinder.First, a new (or emptied and washed) 30B-X cylinder is filled with UF6 content. Then, several cycles follow in which the filled cylinder is transported to the destination, emptied, and transported back to the enrichment facility containing the maximum heel quantities of UF6 (see table 1-4).

During these cycles, decay products build up that contribute to the radioactivity relevant for the A2 value. For each cycle, it is conservatively assumed that all decay products resulting from the previous filling and emptying cycles remain in the heels. Furthermore, the mass of heels already present in the cylinder is conservatively not taken into account for subsequent fillings.

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0045-BSH-2020-001 Rev. 2 Hence, with each filling and emptying cycle, the content mass in the 30B-X cylinder is increased by the maximal permissible amount of heel quantities of 11.3 kg. Using the example of the 30B-10 cylinder, this means that after 3 cycles the calculation model actually represents a content mass of 1460 kg + 3 11.3 kg = 1493.9 kg (using the definition of cycles in table 1-7). The contribution of the decay products in each cycle is therefore based on the contribution of the decay products from all previous cycles as well as a new filling of the cylinder, assuming the maximal permissible content mass specified in table 1-4.

Table 1-7 Calculation scenario of the radioactivity in 30B-X cylinders for contents complying with HALEU 10 and HALEU 20 for a continuous use without washing Content mass in kg Cycle Time Cylinder condition 30B-10 30B-20 Initial 0 New or empty and washed 0 0 1 1 Filled and transported to destination 1460 1271 1 2 Emptied and returned to enrichment facility 11.3 11.3 2 3 Filled and transported to destination 1460 1271 2 4 Emptied and returned to enrichment facility 11.3 11.3 3 5 Filled and transported to destination 1460 1271 3 Emptied and returned to enrichment facility 11.3 11.3 Geistiges Eigentum der Orano NCS GmbH 6

2 1 Filled and transported to destination 1460 1271 (2) ( ) (Emptied and returned to enrichment facility) (11.3) (11.3)

Property of Orano NCS GmbH Final +1 After 5 years refilling is not permissible.1) 11.3 or 1460 11.3 or 1271 Before next use, the cylinder has to be washed and recertified. Transportation of filled or heeled cylinders to the destination is still possible.

After 5 years, the 30B-X cylinder has to be recertified (see section 1.8), which requires the cylin-der to be emptied and washed. However, it is still possible to store a filled or heeled cylinder for a certain time. A final transport to the destination for emptying and/or washing, and recertification is permitted. Since the A2 value is mainly driven by the accumulating decay products of 232U, the maximum value is reached within 10 years of storage time (at this point, secular equilibrium of 232 U and its decay products is reached). A penalizing 3-month filled/heeled cycle is investigated.

Table 1-8 lists the radioactivity of the contributing nuclides for the 3-month filled/heeled cycle in a 30B-10 and 30B-20 cylinder, including a 10-year storage time in filled condition after the 5-year cycle time. A graphical representation of table 1-8 is shown in figure 1-2. This figure also shows the radioactivity of heeled cylinders being stored for 10 years after the 5-year cycle time, and, for comparison purposes, the results for a standard 30B cylinder loaded with Enriched Commercial Grade UF6 as specified in [ASTM C996].

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0045-BSH-2020-001 Rev. 2 Table 1-8 Radioactivity in 30B-10 and 30B-20 cylinders for a 3-month filled/heeled cycle followed by a 10-year storage of filled cylinders Cylinder Radioactivity in A2 Cycle condition 228 Th 230 Th 231 Pa 234 Th 99 Tc Total 30B-10 cylinder 1 Filled 2.09 10 2 6.27 10 4 1.08 104 3.80 102 6.94 106 0.0597 1 Heeled 1.93 102 6.32 104 1.09 104 3.05 103 7.00 106 0.0231 2 Filled 3.85 10 2 1.26 10 3 2.17 10 4 3.82 10 2 1.39 10 5 0.0782 2 Heeled 3.54 102 1.26 103 2.18 104 3.06 103 1.40 105 0.0399 10 Filled 1.06 101 6.31 103 1.09 103 3.82 102 6.99 105 0.152 10 Heeled 9.74 10 2 6.32 10 3 1.09 10 3 3.06 10 3 7.00 10 5 0.108 Final1) Filled 2.20 101 3.39 102 5.75 103 4.09 102 7.69 105 0.301 30B-20 cylinder 1 Filled 4.25 102 1.18 103 1.88 104 3.31 102 6.04 106 0.077 1 Heeled 3.92 102 1.19 103 1.90 104 2.69 103 6.10 106 0.0433 2 Filled 7.83 10 2 2.37 10 3 3.78 10 4 3.33 10 2 1.21 10 5 0.1144 Geistiges Eigentum der Orano NCS GmbH 2 Heeled 7.19 102 2.39 103 3.79 104 2.70 103 1.22 105 0.0774 10 Filled 2.16 101 1.19 102 1.89 103 3.33 102 6.09 105 0.264 Property of Orano NCS GmbH 10 Heeled 1.98 10 1 1.19 10 2 1.90 10 3 2.70 10 3 6.10 10 5 0.215 Final1) Filled 4.47 101 6.39 102 1.00 102 3.56 102 6.70 105 0.557 After 10 years of storage The results show that the DN30-X complies by a large margin with the limit of 1 A2 for a Type AF package, even for the assumption that the 30B-X cylinders are regularly refilled with the contents specified in table 1-2 and without intermediate washing before loading. After a 10-year storage of filled cylinders, a maximal radioactivity of 0.3 A2 and 0.56 A2 is present in the 30B-10 and 30B-20 cylinder, respectively.

The calculation procedure above has been used for an additional investigation to determine to what degree the maximal radioactivity is affected by larger amounts of heels remaining in a cyl-inder. Assuming higher amounts of heels only affects the development of the radioactivity during the filling/emptying cycles and the storage of a filled cylinder. However, the maximal value that is reached at the end is not affected. This is due to the fact that the used calculation procedure assumes that all decay products resulting from all previous cycles completely remain in the heels.

The amount of resulting decay products is thereby determined through the maximum permissible content mass, but not by the permissible amount of heel quantities, which is why the actual mass of the heels is irrelevant in the used calculation model.

As an example, the corresponding bounding cases of a filled 30B-10 and 30B-20 cylinder that is continuously stored for 16 years are shown in figure 1-2 as well. The small differences in the maximal radioactivity at the end of the storage time in comparison to the calculations for the fill-ing/emptying cycles are due to the fact that the mass of heels remaining in the cylinders is not accounted for in subsequent filling cycles. As already explained above, the cylinders therefore 26 / 172

0045-BSH-2020-001 Rev. 2 effectively contain more and more UF6 after each filling cycle, which leads to a slightly higher maximal radioactivity at the end of the storage time in comparison to the calculations assuming a continuous storage.

The performed investigations in this section prove:

• The maximal radioactivity that is obtained for the most penalizing 3-month filled/heeled cy-cle and a 10-year storage of a filled 30B-10 or 30B-20 cylinder is affected by the isotopic limits specified in table 1-2 as well as the maximal permissible mass of UF6 specified in table 1-4.

• Increasing the amount of heels remaining in a 30B-10 or 30B-20 cylinder does not further increase the resulting maximal radioactivity.

Accordingly, compliance with the limit of 1 A2 for a Type AF package is proven without taking any credit for the maximal mass of heels contents specified in table 1-4.

0.60 0.55 0.50 0.45 Total radioactivity in A2 0.40 Geistiges Eigentum der Orano NCS GmbH 0.35 0.30 0.25 Property of Orano NCS GmbH 0.20 0.15 0.10 0.05 0.00 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 Time in years Standard 30B (End Filled) 30B-10 (End Filled) 30B-20 (End Filled)

Standard 30B (End Heels) 30B-10 (End Heels) 30B-20 (End Heels)

Standard 30B (Filled) 30B-10 (Filled) 30B-20 (Filled)

Figure 1-2 Radioactivity in 30B-10 and 30B-20 cylinders in comparison to 30B cylinders for a 3-month filled/heeled cycle followed by a 10-year storage of filled/heeled cylinders 27 / 172

0045-BSH-2020-001 Rev. 2 1.4 Specification of the Packaging 1.4.1 List of all Packaging Components and Complete Design Drawings The DN30-X is a partially new package design, consisting of the new 30B-X cylinder and the DN30 PSP that is already licensed for transport of standard 30B cylinders. The DN30 PSP pro-vides both the mechanical and thermal protection for the 30B-X cylinder including its radioactive content. The DN30-X packaging is designed to meet routine conditions of transport (RCT), normal conditions of transport (NCT), and hypothetical accident conditions (HAC) as required by

[10 CFR Part 71] and [49 CFR Part 173], or [SSR-6 2018].

The main packaging components are:

• The 30B-X cylinder consisting of:

- The cylinder shell with an ellipsoidal head on each end

- The valve and plug half coupling

- The cylinder valve and plug

- Two skirts being attached to each ellipsoidal head, where the skirt on the valve side has two horizontally aligned holes that are used to prevent the rotation of the cylinder inside the DN30 PSP Geistiges Eigentum der Orano NCS GmbH

- Two criticality control system (CCS) restraints, each consisting of a backing bar and a rotation preventing device, that maintain the position of the interior CCS within the 30B-X cylinder cavity Property of Orano NCS GmbH

- The interior CCS consisting of criticality control rods (CCRs) containing neutron poison material in the form of boron carbide (B4 C), and three lattice holders that keep each CCR in place. The separation of the lattice holders is maintained by 14 longitudinal stiffeners

• The DN30 PSP consisting of:

- The bottom half with two feet welded to the outer shell for tie-down during transport in-corporating four load attachment points to be used for handling the DN30-X package and two forklift pockets for handling the empty and loaded packaging

- The top half with two load attachment points for handling the top half

- The valve protecting device that is attached to the bottom half by means of hinges

- The plug protecting device that is welded to the interior shell of the bottom half

- The rotation preventing devices consisting of two pins welded to the flange of the bottom half

- The closure system consisting of six steel blocks welded to the top half and six steel blocks welded to the bottom half forming mortise-and-tenon style joints connected through steel pins

- Steel blocks welded to the top and bottom half for sealing the DN30-X packaging 28 / 172

0045-BSH-2020-001 Rev. 2 Since the DN30-X is only a partially new design, a new set of drawings is only required for the designs of the 30B-10 and the 30B-20 cylinder (see section 1.4.1.1). The specification and draw-ings of the DN30 PSP are provided in section 1.4.1.2 with the following revised and new drawings:

• Revised to include the 30B-X:

- Datasheet 0023-ZDB-1000-000 DN30 PSP

- Drawing 0023-ZFZ-1000-000 DN30 PSP

• New to include the 30B-X:

- Drawing 0023-ZFZ-1000-003 Additional package nameplate 1.4.1.1 30B-X Cylinder The DN30 PSP may be loaded with the 30B-10 or the 30B-20 cylinder that both are derived from a standard 30B cylinder as specified in [ANSI N14.1] adding an interior criticality control system (CCS). The CCS consists of criticality control rods (CCRs) containing neutron poison material in the form of boron carbide (B4 C), and lattice holders that keep each CCR in place.

The 30B-10 and the 30B-20 cylinders are defined in the following main drawings:

• 30B-10 Cylinder:

- Parts list 0045-STL-1000-000 30B-10 Cylinder Geistiges Eigentum der Orano NCS GmbH

- Drawing 0045-ZFZ-1000-000 30B-10 Cylinder

- Drawing 0045-ZFZ-1100-000 30B Cylinder modified

- Drawing 0045-ZFZ-1200-000 CCS Property of Orano NCS GmbH

• 0045-ZFZ-2000-000 30B-20 Cylinder

- Parts list 0045-STL-2000-000 30B-20 Cylinder

- Drawing 0045-ZFZ-2000-000 30B-20 Cylinder

- Drawing 0045-ZFZ-1100-000 30B Cylinder modified

- Drawing 0045-ZFZ-2200-000 CCS Appendix 1.4.1A (Drawings 30B-X Cylinder) contains proprietary drawings and parts lists of the individual parts of the 30B-10 and the 30B-20 cylinder, respectively. The following material spec-ifications for the 30B-X cylinder pressure envelope in section 1.4.1.1.1 as well as the valve and plug in section 1.4.1.1.2 are identical to the material specifications for a standard 30B cylinder and, thus, are adopted from [ANSI N14.1] as they stand. However, additional material specifica-tions are required in case of the CCS, which are given in section 1.4.1.1.3.

1.4.1.1.1 Pressure Envelope and Skirts The materials of the 30B-X cylinder are specified in table 1-9. They are identical to the material specifications of a standard 30B cylinder and, thus, are adopted from [ANSI N14.1] as they stand.

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0045-BSH-2020-001 Rev. 2 Table 1-9 Material specification of the 30B-X cylinder Item Material specification Cylinder Cylinder shell, heads, backing bars, and skirts shall conform to [ASTM A516],

steel, grade 65 or 70 and shall be normalized.

a) All steel shall be Charpy V-notch impact tested and shall meet the Charpy V-notch impact requirements as stated in ASTM A20.

b) Steel may be plate or coil form.

Couplings Modified half-coupling per [ANSI N14.1], Figure 14, Forged ASTM A105.

Note: ASTM A106 Grade C may be used in lieu of ASTM A105.

Nameplate Sheet, ASTM A240, UNS S30400 or S30403.

Valve protector Plate, weldable carbon steel with a minimum tensile strength of 45000 Psi and a (optional) maximum carbon content of 0.26 %, such as ASTM A36.

Seal loop(s) Rod, ASTM A36.

1.4.1.1.2 Valve and Plug The materials of the valve and the plug are specified in table 1-10. They are identical to the ma-terial specifications of a standard 30B cylinder and, thus, are adopted from [ANSI N14.1] as they stand.

Geistiges Eigentum der Orano NCS GmbH Table 1-10 Material specification of valve and plug of the 30B-X cylinder Item Material specification Body Forging, aluminum bronze (UNS C63600), conforming to [ANSI N14.1],

Property of Orano NCS GmbH section 7.1.2 and 7.1.4.

Stem Bar, cold drawn, nickel-copper alloy (UNS N04400) ASTM B164 and stress-relieved per [ANSI N14.1], section 7.1.5-2. Certification to include results of testing in accordance with ASTM E2375 over 100 % of stock material. Testing to be per Class AA with straight beam.

Packing nut Note: Packing nuts require stress-relieving after final machining. Surface hardness measurements of packing nuts after final stress-relieving may be made on the top of the nut.

a) Bar, aluminum bronze (UNS C61300) ASTM B150, stress-relieved per

[ANSI N14.1], section 7.1.5-3 or, b) Bar, nickel-copper alloy (UNS N04400) ASTM B164, stress-relieved per

[ANSI N14.1], section 7.1.5-2.

Port cap a) Bar, aluminum bronze (UNS C61300) ASTM B150, stress-relieved per

[ANSI N14.1], section 7.1.5-3 or, b) Bar, nickel-copper alloy (UNS N04400) ASTM B164, stress-relieved per

[ANSI N14.1], section 7.1.5-2, or c) Bar, aluminum bronze (UNS C63600), stress-relieved per [ANSI N14.1],

section 7.1.5-1.

Packing follower, a) Bar, aluminum bronze (UNS C61300) ASTM B150, stress-relieved per packing ring [ANSI N14.1], section 7.1.5-3 or, b) Bar, aluminum bronze (UNS C63600), stress-relieved per [ANSI N14.1],

section 7.1.5-1.

Packing, cap gasket PTFE Fluorinated lubricant Compatible for UF6 service.

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0045-BSH-2020-001 Rev. 2 Item Material specification Solder Tin-lead alloy, with a minimum tin content of 45 % such as alloy SN50 ASTM B32.

Solder flux Phosphoric acid or approved equivalent.

Hex head plug Bar, upset forged, extruded, or extruded and drawn, aluminum bronze (UNS C61300) ASTM B150.

Socket head plug Note: These plugs may be used in lieu of hex head plugs.

a) Bar, upset forged, extruded, or extruded and drawn, aluminum bronze (UNS C61300) ASTM B150 or b) Bar, upset forged, extruded, or extruded and drawn, aluminum bronze D (UNS C61400, with a tin content restricted to 0.2-0.5 %) ASTM B150 or c) Plate, chemical composition as specified in a) or b) and conforming to ASTM B171.

1.4.1.1.3 Criticality Control System The materials of the interior CCS of the 30B-X cylinder are specified in table 1-11. Except for the neutron poison material in the form of boron carbide (B4 C), the same materials as for the pres-sure-envelope of a standard 30B cylinder are used for the CCS. Consequently, the same stand-ards according to [ANSI N14.1] are applied for these parts.

Geistiges Eigentum der Orano NCS GmbH Table 1-11 Material specification of interior CCS of the 30B-X cylinder Item Applicable standards Lattice holders, a) The CCR lids, longitudinal stiffeners, and lattice holders shall Property of Orano NCS GmbH longitudinal stiffeners, conform to [ASTM A516], steel, grade 65 or 70 and shall be and CCR lids normalized.

b) All steel shall be Charpy V-notch impact tested per ASTM A20. The test temperature and acceptance criteria shall be as specified in ASTM A20, Table A1.15. Alternatively, the maximum test temperature is specified as -40 °C and the minimum average energy absorption for 3 full-size specimen shall be 27 J. None of the specimen shall have an energy absorption below 22 J.

c) Steel may be plate or coil form.

Note: Steel confirming to [DIN EN 10028-3] grade P355NL1 or P355NL2 may be used in lieu of [ASTM A516] grade 65 or 70. In this case, the minimum impact energy requirements of [DIN EN 10028-3] apply.

CCR pipes a) The CCR pipes shall conform to [ASTM A333] grade 9 b) All steel shall be Charpy V-notch impact tested. The impact test temperature and impact requirements shall be as specified in

[ASTM A333]. Alternatively, the impact test temperature is specified as -40 °C and the minimum average notched bar impact value of each set of 3 full-size specimen shall be 27 J. None of the specimen shall have a minimum average notched bar impact value below 22 J.

Note: Seamless steel pipes confirming to [DIN EN 10216-3]

grade P355NL1 or P355NL2 may be used in lieu of [ASTM A333]

grade 9. In this case, the minimum impact energy requirements of

[DIN EN 10216-3] apply.

Neutron poison material Boron carbide (B4 C) as specified in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) 31 / 172

0045-BSH-2020-001 Rev. 2 1.4.1.2 DN30 PSP The design of the DN30 PSP is defined in the following main drawings:

• 0023-ZFZ-1000-000 DN30 PSP

• 0023-ZFZ-1000-100 Closure device

• 0023-ZFZ-1100-000 Bottom half

• 0023-ZFZ-1200-000 Top half

• 0023-ZFZ-1140-000 Rotation Preventing Device

• 0023-ZFZ-1140-000 Valve Protecting Device

• 0023-STL-1000-000 Part list DN30 PSP Appendix 1.4.1B (Drawings DN30 PSP) contains proprietary drawings and parts lists of the indi-vidual parts of the DN30 PSP. The materials of these parts are specified in table 1-12.

Table 1-12 Material specification of the DN30 PSP Item Applicable EU standards Applicable US standards Inner / outer [DIN EN 10088-2], Grade 1.4301, ASME SA-240, Type 304 (UNS S30400) steel shells 1.4307, or 1.4541 or Type 321 (UNS S32100)

Geistiges Eigentum der Orano NCS GmbH Inner structure [DIN EN 10088-2], Grade 1.4301, ASME SA-240, Type 304 (UNS S30400) 1.4307, or 1.4541 or Type 321 (UNS S32100)

Feet [DIN EN 10088-2], Grade 1.4301, ASME SA-240, Type 304 (UNS S30400) 1.4307, or 1.4541 or Type 321 (UNS S32100)

Property of Orano NCS GmbH Lifting lugs (feet) [DIN EN 10088-2], Grade 1.4462 ASME SA-240, Type 2205 (UNS S31803)

Steel shells of [DIN EN 10088-2], Grade 1.4301, ASME SA-240, Type 304 (UNS S30400) valve protecting 1.4307, or 1.4541 or Type 321 (UNS S32100) device Rotation preventing [DIN EN 10088-2], Grade 1.4301, ASME SA-240, Type 304 (UNS S30400) device 1.4307, or 1.4541 or Type 321 (UNS S32100)

Plug protecting [DIN EN 10088-2], Grade 1.4301, ASME SA-240, Type 304 (UNS S30400) device 1.4307, or 1.4541 or Type 321 (UNS S32100)

Closure device [DIN EN 10088-3] / ASME SA-479 / ASME SA-240, Type 321

[DIN EN 10088-2], Grade 1.4541 (UNS S32100)

[DIN EN 10088-3] / ASME SA-479 / ASME SA-240,

[DIN EN 10088-2], Grade 1.4571 Type 316Ti (UNS S31635)

Body of pin [DIN EN 10088-3], Grade 1.4542 ASME SA-564, Type 630 (Alloy 17-4 PH, UNS S17400)

Head of pin [DIN EN 10088-3], Grade 1.4541 ASME SA-479, Type 321 (UNS S32100) or 1.4571 or Type 316Ti (UNS S31635)

Securing bolt Nitronic 50 ASME SA-193, Type XM-19 (UNS S20910)

Washers NL16-254SMO ASME SA-240M, Alloy 254 (UNS S31254)

([DIN EN 10088-2], Grade 1.4547)

Gaskets EPDM 32 / 172

0045-BSH-2020-001 Rev. 2 Item Applicable EU standards Applicable US standards Foam Polyisocyanurate (PIR) foam conforming to the specifications RTS 120 and RTS 320 (see Appendix 1.4.2 (Material Properties))

Intumescent material Intumescent material, e.g., conforming to the specifications Promaseal-PL (see Appendix 1.4.2 (Material Properties))

Thermal insulation Microporous material, e.g., conforming to the specifications MICROTHERM OVERSTITCHED 1000R HY or WDS Multiflex ST 2D50 HY (see Appendix 1.4.2 (Material Properties))

Thermal plugs Polyamide Pads Silicone 1.4.2 Description of the DN30-X Packaging The DN30 packaging consists of:

• The 30B-X cylinder

• The DN30 PSP Geistiges Eigentum der Orano NCS GmbH 1.4.2.1 30B-X Cylinder The 30B-X cylinder is identical to a standard 30B cylinder as specified in [ANSI N14.1], except that an interior criticality control system (CCS) is built into the 30B-X cylinder (see figure 1-3). In the following sections 1.4.2.1.1 to 1.4.2.1.3, a detailed description of 30B-X cylinder is provided.

Property of Orano NCS GmbH Furthermore, additional provisions to [ANSI N14.1] and their implications on the safety features of the 30B-X cylinder are discussed in section 1.4.2.1.4.

Figure 1-3 30B-X cylinder - Outside view 33 / 172

0045-BSH-2020-001 Rev. 2 1.4.2.1.1 Criticality Control System The CCS consists of criticality control rods (CCRs) filled with neutron poison material and lattice holders that retain the CCR positionings. Longitudinal stiffeners between the lattice holders help to keep the lattice holders separated from each other. The interior CCS of the 30B-X cylinder is shown in figure 1-4.

Geistiges Eigentum der Orano NCS GmbH Lattice Holder Longitudinal Stiffener B4C Property of Orano NCS GmbH Criticality Control Rod (CCR)

Complete Criticality Control System (CCS)

Figure 1-4 30B-X cylinder - Interior criticality control system The CCRs are seamless steel pipes that are filled with boron carbide (B4 C) as a neutron absorb-ing material for criticality control and that are sealed by a welded lid on each end. For the CCRs, 34 / 172

0045-BSH-2020-001 Rev. 2 standardized seamless pipes are used having an outer diameter of 60.3 mm and a wall thickness of 5.54 mm. Their proper placement, which is crucial for criticality control, is ensured by the three lattice holders. According to the specification in table 1-11, only materials that are already speci-fied in [ANSI N14.1] are used for the steel pipes and the lattice holders. Hence, compatibility is ensured between the interior CCS, the cylinder material and the UF6 contents.

The cross section through the 30B-X cylinder in figure 1-5 displays the CCS within the cylinder.

The length of the CCRs is fitted to the ellipsoidal heads of the 30B-X cylinder. Of special note are the CCRs that end directly in front of the valve and plug - these are shortened by 60 mm to avoid interference with filling and emptying of the cylinder. Shortening these CCRs also helps to ensure that there will be no impact of the CCS on the valve or plug, even under HAC.

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH Figure 1-5 30B-X cylinder - Cross sectional view 1.4.2.1.2 Pressure Envelope The pressure envelope of the 30B-X cylinder is identical to the standard 30B cylinder, except for CCS restraints welded to the straight portion of each cylinder head. These inhibit the longitudinal movement and axial rotation of the interior CCS within the 30B-X cylinder, but no fixed connection exists between the CCS and the pressure envelope of the 30B-X cylinder. The CCS restraints also serve as backing bars for the circumferential head welds of the 30B-X cylinder.

The specification of the outer dimensions, the materials as well as the valve and plug of the 30B-X cylinder are identical to the standard 30B cylinder. However, deviating from [ANSI N14.1], a min-imal wall thickness of 11 mm is specified for the 30B-X cylinder shell and heads.

1.4.2.1.3 Main Characteristics of the 30B-X Cylinder The main characteristics of the 30B-10 and the 30B-20 cylinder in comparison to the standard 30B cylinder are listed in table 1-13. Only the enrichment limit, nominal tare weight, maximum net weight, minimum volume and minimum ullage differ from a standard 30B cylinder.

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0045-BSH-2020-001 Rev. 2 Table 1-13 Main data of the 30B-X cylinder Value Item Unit Standard 30B 30B-10 30B-20 235 Enrichment limit U in U 5 10 20 wt.-%

Nominal diameter 762 762 762 mm Nominal length 2070 2070 2070 mm Nominal wall thickness 13 13 13 mm Minimum wall thickness 7.94 11 11 mm Nominal tare weight 635 1452 1641 kg Maximum net weight 2277 1460 1271 kg Maximum gross weight 2912 2912 2912 kg Minimum volume 0.736 0.544 0.493 m3 Nominal filling ratio at 20 °C 60.8 52.8 50.7  %

Minimum ullage at 121 °C 5 17.6 20.8  %

Nominal internal free surface 4.75 20.01 22.89 m2 Effective cross section of cavity At lattice holders (minimal) 0.426 0.205 0.171 m2 Geistiges Eigentum der Orano NCS GmbH At CCRs 0.426 0.328 0.298 m2 In the determination of the maximum net weight (permissible mass of UF6 ) listed in table 1-13, two limiting factors are considered. On the one hand, the nominal gross weight of the 30B-10 and Property of Orano NCS GmbH 30B-20 cylinder shall be identical to the standard 30B cylinder and, on the other hand, the mini-mum ullage of 5 % at 121 °C required by [ANSI N14.1] must be complied with. Beside the nominal gross weight, the outer dimensions, the wall thickness and, thus, also the volume of the inner cavity excluding the interior CCS are identical for all cylinder designs. Hence, comparing the den-sity of liquid UF6 at 121 °C and the average density of the interior CCS of the 30B-X cylinder suffices to determine the limiting case.

The lattice holders are entirely made of steel and, for the CCRs consisting of steel rods filled with boron carbide, an average density of about 4.2 g/cm³ is calculated. Consequently, the average density of the CCS is always higher than the density of liquid UF6 at 121 °C of 3.26 g/cm³ (see table 1-1). The limiting case in the determination of the maximum net weight is therefore the gross weight, leading to a minimum ullage for the 30B-10 and the 30B-20 cylinder at 121 °C that is significantly larger than the minimally required 5 % per [ANSI N14.1], respectively.

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0045-BSH-2020-001 Rev. 2 1.4.2.1.4 Additional provisions to ANSI N14.1 In this section, it is discussed how the safety aspects of the 30B-X cylinder, namely its contain-ment function (see section 1.4.2.3.1), continue to be maintained with the additional provisions to

[ANSI N14.1] that are required for the 30B-X cylinder. According to the description of the 30B-X cylinder in the previous sections, these additional provisions and their impact on the safety as-pects of the 30B-X cylinder are:

1. Addition of the interior CCS Under normal operating conditions for the 30B-X cylinder (see section 2.1.1.1.1), the presence of the CCS has no impact on the containment function of the 30B-X cylin-der. Due to the absence of a fixed connection between the CCS and the 30B-X cyl-inder pressure envelope, the deformation behavior under internal and external pres-sure loads is identical to the behavior of a standard 30B cylinder.

The interior CCS increases the nominal tare weight of the 30B-10 and 30B-20 cylin-der compared to a standard 30B cylinder. Since the maximum gross weight of the 30B-X and standard 30B cylinder are required to be identical (see table 1-13), han-dling of filled cylinders is not affected. Accordingly, the increased tare weight only needs to be considered with regard to the handling of empty 30B-X cylinders.

Another consequence of requiring identical maximum gross weights for the 30B-X and standard 30B cylinder is an increase in the minimum ullages at 121 °C for the Geistiges Eigentum der Orano NCS GmbH 30B-10 and 30B-20 cylinder (see table 1-13). Hence, the risk of a fatal pressure build-up caused by melted UF6 contents is significantly lower for the 30B-X cylinder than for the standard 30B cylinder (see section 2.3.2).

2. Incorporation of stronger backing bars in the design of the 30B-X cylinder that also serve Property of Orano NCS GmbH as a CCS restraint The incorporation of stronger backing bars has a positive impact on the resulting stresses at the junction of the cylinder shell and heads under normal operating con-ditions for the 30B-X cylinder.

This shows that all safety aspects of the standard 30B cylinder are at least maintained or even improved with the above-mentioned additional provisions to [ANSI N14.1] that apply to the 30B-X cylinder.

1.4.2.2 DN30 PSP The DN30 PSP consists of:

• The bottom half with integrated feet, load attachment points for handling the loaded pack-age, valve protecting device, plug protecting device, rotation preventing devices and bottom half of the closure devices

• The top half with integrated load attachment points for handling the top half and the top half of the closure devices The main data of the DN30 PSP are listed in table 1-14.

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0045-BSH-2020-001 Rev. 2 Table 1-14 Main data of the DN30 PSP Item Value Unit Nominal diameter 1216 mm Nominal height 1329 mm Nominal length 2437 mm Nominal tare weight 1100 kg Nominal gross weight 4012 kg Maximum gross weight 4100 kg 1.4.2.2.1 Bottom Half of the DN30 PSP The body of the bottom half is made of an inner and outer shell of stainless steel, both in the form of a tub that are connected at the top by a flange. The cavity between the inner and outer shell and flange is filled with the PIR foams RTS 120 and RTS 320. Between the inner shell and the RTS 120 foam, there is also a layer of 10 mm microporous material as thermal insulation. At the side the thickness of the inner shell is 2 mm and of the outer shell 3 mm. At the ends the thickness of the inner shell is 10 mm and of the outer shell 4 mm. All surfaces of the inner shell of the bottom half are covered with a layer of 2.6 mm intumescent material.

At the bottom side there are two feet of stainless-steel welded to the outer shell at each end of Geistiges Eigentum der Orano NCS GmbH the DN30 PSP. The feet have a base plate, made of two 10 mm thick stainless-steel plates welded on top of each other, which contains at each side two holes for tie-down to an adapted flatrack (the arrangement and size of these holes is compatible with existing PSP designs).

At the side of each of the feet there is an eyelet welded to the side plate of the foot. These eyelets Property of Orano NCS GmbH are designed to be used for lifting the loaded DN30-X package.

At the top side of the bottom half of the DN30 PSP, the lower halves of the mortise-and-tenon closure system are welded to the outer shell, three per side. Adjacent to one of these parts of the closure system, the sealing block is welded to the outer shell.

At the inside of the bottom half, the valve protecting device is attached to the flange by hinges at one end. The valve protecting device consists of a stainless-steel casing filled with PIR foam RTS 320 and a protecting housing that has its interior surfaces covered with intumescent material.

On the opposite end, there is the plug protecting device in the form of a pot that is welded to the inner shell and that has its interior surfaces covered with intumescent material.

At the inner sides of the flange there are two rotation preventing devices welded to the flange.

These devices consist of a pin, which is withdrawn into the flange during loading and inserted during transport into the two holes in the skirt of the 30B-X cylinder.

1.4.2.2.2 Top Half of the DN30 PSP The body of the top half is similar to the bottom half. It is made of an inner and outer shell of stainless-steel, both in the form of a tub that are connected at the bottom by a flange. The cavity between the inner and outer shell and flange is filled with the PIR foams RTS 120 and RTS 320.

Between the inner shell and the RTS 120 foam, there is also a layer of 10 mm microporous ma-terial as thermal insulation. At the side, the thickness of the inner shell is 2 mm and of the outer shell 3 mm. At the ends the thickness of the inner shell is 10 mm and of the outer shell 4 mm. All surfaces of the inner shell of the top half are covered with a layer of 2.6 mm intumescent material.

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0045-BSH-2020-001 Rev. 2 At the top, there are two eyelets welded to the outer shell, one on each side. These eyelets are designed to be used for lifting the top half only.

At the bottom side of the top half of the DN30 PSP, the upper halves of the mortise-and-tenon closure system are welded to the outer shell, three per side. Adjacent to one of these parts of the closure system, the sealing block is welded to the outer shell.

At the inside of the top half there is a recess to accommodate the valve protecting device.

In the flange of the top half, there is an elastomeric gasket to prevent water inleakage under RCT.

1.4.2.3 Design Safety Features of the DN30-X Packaging 1.4.2.3.1 Pressure Containment of the DN30-X Packaging The pressure containment consists of:

• The 30B-X cylinder including its valve and plug Note: the DN30 PSP is not designed as a pressure retaining component. Because of its design, a pressure difference between the ambient and the DN30 PSP can be excluded. For pressure release during the thermal test under HAC, the DN30 PSP is equipped with fusible plugs that release any pressure that may be induced by the decomposition of the foam parts.

Geistiges Eigentum der Orano NCS GmbH 1.4.2.3.2 Mechanical Protection System The mechanical protection system prevents excessive mechanical impacts on the 30B-X cylinder under RCT, NCT and HAC. It consists of:

Property of Orano NCS GmbH

• The stainless steel and foam structure of the bottom and top half of the DN30 PSP 1.4.2.3.3 Thermal Protection System The thermal protection system prevents excessive thermal loads on the 30B-X cylinder including its valve and plug under RCT, NCT and HAC. It consists of:

• The stainless steel / foam structure of the bottom and top half of the DN30 PSP (each fitted with nine thermal plugs/valves, screwed into the outer steel shells)

• The microporous thermal insulation layer between the RTS 120 foam and the inner steel shell

• The intumescent material at the inner surfaces of the DN30 PSP 1.4.2.3.4 Closure System The top and bottom half of the DN30 PSP are connected by the closure system consisting of 6 robust mortise-and-tenon like devices and the flange.

The two parts of each mortise-and-tenon system have four teeth each with a hole in its center.

When closed, the two halves are connected by a pin inserted into these holes. This pin is secured by a bolt. The design of the mortise-and-tenon system is such that neither the connecting pin nor the securing bolt are exposed to mechanical impacts but are protected by the massive body of the system. The system prevents excessive relative movements of top and bottom half in vertical direction under RCT, NCT and HAC.

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0045-BSH-2020-001 Rev. 2 The flange is shaped like an upside-down U. It prevents excessive relative movements of the top and bottom half in all horizontal directions under RCT, NCT and HAC. Furthermore, in flat drop orientations the flange will be deformed in such a way that the top and bottom half are clamped together.

1.4.2.3.5 Valve Protecting Device The valve protecting device consists of a stainless-steel housing filled with PIR foam. It is shaped like a U and encloses the valve of the 30B-X cylinder during transport. It is connected to the bottom half of the DN30 PSP through two hinges. In open condition, it is turned to horizontal position to allow loading and unloading of the cylinder. When the filled cylinder is loaded into the PSP, the device is turned by 90° to vertical orientation so that it is in contact with the cylinder head. The valve protecting device prevents contact of the valve with any part of the DN30 PSP or any other part the 30B-X cylinder except for its original point of contact (thread) under RCT, NCT and HAC.

A protecting housing is placed inside the U-shape of the valve protecting device. This housing is made of thin stainless-steel sheets and its inside is covered with intumescent material.

1.4.2.3.6 Plug Protecting Device The plug protecting device consists of a pot made of stainless steel welded to the inner shell of Geistiges Eigentum der Orano NCS GmbH the bottom half of the DN30 PSP. This device allows the plug of the 30B-X cylinder to move in axial direction without getting in contact with any part of the DN30 PSP under RCT, NCT and HAC. The inside of the pot is covered with intumescent material.

Property of Orano NCS GmbH 1.4.2.3.7 Rotation Preventing System The rotation preventing system consists of two rotation preventing devices installed at the sides of the inner flange of the bottom half of the DN30 PSP. The device consists of a stainless-steel pin accommodated in two sleeves, an internal sleeve in contact with the pin and an external sleeve that is welded to the flange. A lever is welded onto the steel pin to allow turning and lateral movements.

In open condition, the steel pin is withdrawn into the flange so that the cylinder can be loaded or unloaded. In this condition, the top half of the DN30 PSP cannot be put on the bottom half as the position of the lever prevents the correct placement of the top flange onto the bottom flange. The connection of top and bottom half is only possible when the rotation preventing system is properly engaged. This excludes the possibility of the pin being withdrawn while the packaging is closed.

1.4.2.3.8 Sealing System For sealing of the DN30-X package there are two sealing blocks welded to the top and bottom half adjacent to a closure device. These blocks allow the use of high security seals compliant with ISO 17712 / C-TPAT.

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0045-BSH-2020-001 Rev. 2 1.4.2.4 Handling Features of the DN30-X Packaging 1.4.2.4.1 Lifting of the DN30-X Package, DN30-X Packaging and Empty DN30 PSP The DN30-X package can be lifted by using:

• The 4 lifting lugs welded to the upper part of the feet

• A forklift

• Handling slings Handling of the DN30 PSP or empty DN30-X packaging is carried out in the same manner as for the DN30-X package.

1.4.2.4.1.1 Lifting by Using the 4 Lifting Lugs at the Feet For lifting the DN30-X package by using the 4 lifting lugs welded to the upper part of the feet, shackles must be used and fixed to the lifting lugs. It is preferable to use lifting slings made from Polyester or Nylon. The angle between the vertical axis of the lifting lugs and the slings/chains must not be greater than 30° (see figure 1-6).

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH Figure 1-6 Lifting of the DN30-X package by using the 4 lifting lugs 1.4.2.4.1.2 Lifting by Using a Forklift The loaded DN30-X package may be handled and lifted by using a forklift. For this purpose, two forklift pockets are welded to the bottom half of the DN30 PSP (see figure 1-7).

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0045-BSH-2020-001 Rev. 2 Figure 1-7 Lifting of the DN30-X package by using a forklift 1.4.2.4.1.3 Lifting by Using Slings (Empty DN30 PSP)

Geistiges Eigentum der Orano NCS GmbH Only the empty DN30 PSP may be handled by slings attached to the bottom half of the DN30 PSP as shown in figure 1-8.

Property of Orano NCS GmbH Figure 1-8 Lifting of the empty DN30 PSP by using slings 1.4.2.4.2 Lifting of the Top Half of the DN30 PSP When transported, the loaded DN30-X package or the empty DN30 PSP is usually mounted on dedicated flatracks. At the destination, only the top half of the DN30 PSP needs to be removed for loading or unloading the 30B-X cylinders into or from the DN30 PSPs.

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0045-BSH-2020-001 Rev. 2 For handling of the top half, there are two lifting lugs welded to each end of the outer shell of the DN30 PSP (see figure 1-9). These lifting lugs are designed for lifting the top half of the DN30 PSP only. During transport, they have to be rendered inoperable for lifting to prevent inadvertent use of these attachment points (e.g., for lifting the loaded package). Rendering the lifting lugs at the top half inoperable can be done by inserting bolts.

Geistiges Eigentum der Orano NCS GmbH Figure 1-9 Lifting of the top half of the DN30-X packaging Property of Orano NCS GmbH 1.4.2.5 Tie-Down Features of the DN30-X Packaging For tie-down, the DN30 PSP is equipped with two feet. The base plates of the feet consist of 2 x 10 mm thick stainless-steel sheets which incorporate two holes at each end. The dimension and position of these holes are compatible with other PSP designs currently in use. During transport, the DN30 PSP is bolted to a dedicated flatrack (see figure 1-10).

According to international practice, tie-down of the DN30-X package on flatracks by bolts is per-formed taking into account accelerations of 2 g in axial, 2 g in lateral and 2 g in vertical direction of travel. However, the tie-down features of the DN30-X package are designed to withstand an acceleration of 10 g in axial, 5 g in lateral and 1 g +/- 2 g in vertical direction of travel (see sec-tion 2.2.5). For application of such tie-down parameters, additional shocks or bumpers must be foreseen in the tie-down plan. However, this tie-down plan is not part of the application.

Only for the transport of DN30 PSP not loaded with a 30B-X cylinder and in case a dedicated flatrack cannot be made available, tie-down by using straps according to figure 1-11 is allowed.

In that case, a tie-down plan has to be drawn up based on a tie-down calculation.

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0045-BSH-2020-001 Rev. 2 Figure 1-10 General tie-down method for the DN30-X package / DN30 PSP Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH Figure 1-11 Tie-down of the empty DN30 PSP using straps 1.4.3 Components of the Packaging Relevant for the Containment System The containment system consists of:

• The 30B-X cylinder shell and heads together with the welding seams forming the pressure envelope

• The valve body and the stem including the threaded connection between the valve and the 30B-X cylinder body

• The plug including its threaded connection between the 30B-X cylinder body 1.4.4 Components of the Packaging Relevant for Shielding The DN30-X packaging has no components primarily intended for shielding. However, some level of shielding is provided by the 30B-X cylinder shell as well as the inner and outer shells of the DN30 PSP.

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0045-BSH-2020-001 Rev. 2 1.4.5 Components of the Packaging Relevant for the Confinement System The confinement system consists of:

• The components of the containment system (see section 1.4.3)

• The interior CCS of the 30B-X cylinder

• The inner and outer shells of the DN30 PSP 1.4.6 Components of the Packaging Relevant for Thermal Protection The following components of the DN30 PSP are relevant for thermal protection:

• The inner and outer shells

• The RTS 120 and RTS 320 foam

• The microporous thermal insulation layer between the inner shell and RTS 120 foam

• The intumescent material attached to the inside of the inner shell 1.4.7 Components of the Packaging Relevant for Heat Dissipation Because of the very low level of thermal power, there is no dedicated component for heat dissi-Geistiges Eigentum der Orano NCS GmbH pation.

1.4.8 Protection against Corrosion Property of Orano NCS GmbH All outer and interior surfaces of the DN30 PSP are made of austenitic stainless steel and, thus, are resistant to corrosion. There is no corrosion due to the interaction of the intumescent material or its glue, since the material is certified halogen-free (see Appendix 1.4.2 (Material Properties)).

Like standard 30B cylinders, the 30B-X cylinder is coated with high quality paint that prevents excessive corrosion on all outer surfaces. Corrosion at the interior surfaces of the 30B-X cylinder is negligible, which is proven by the long term and world-wide experience with standard 30B cyl-inders. Within the 5-year recertification period or when these cylinders are appropriately stored while loaded with UF6 or heels, there is no excessive corrosion, which could impair the safety functions of these cylinders. Since the same operation and maintenance procedures apply to the 30B-X cylinder, the corrosion behavior of standard 30B cylinders can be directly transferred to the 30B-X cylinder.

1.4.9 Protection Against Contamination All outer and interior surfaces of the DN30 PSP are made of austenitic stainless steel and, thus, are easy to decontaminate. Furthermore, the intumescent material is protected by an easy to decontaminate coating.

The 30B-X cylinder is coated with paint that can be easily decontaminated. In transport configu-ration, the surface of the 30B-X cylinder is not accessible from the outside.

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0045-BSH-2020-001 Rev. 2 1.4.10 Shock Absorbing Components of the Packaging The following components of the DN30 PSP are relevant for shock absorption:

• The inner and outer shells

• The RTS 120 and RTS 320 foam

• The valve protecting device 1.4.11 Evaluation of the Impact of Aging Mechanisms To take into account ageing mechanisms in the design of the DN30-X package, care has been taken to use materials with a long usage history.

1.4.11.1 DN30 PSP The DN30 PSP consists of an inner and outer shell of austenitic stainless steel enclosing a shock absorbing structure made of PIR foam and a thermal protection made of inorganic materials.

• There is no tensile stress during RCT (except during handling) in any of the steel parts of the DN30 PSP, hence for the austenitic stainless steel aging is not a topic. Fatigue analysis of all parts used during handling and tie-down is described in Appendix 2.2 (Structural Anal-ysis), section 4.3 and 5.1.

Geistiges Eigentum der Orano NCS GmbH

• Interaction of the austenitic stainless steel with the shock absorbing material and the ther-mal protection materials has been thoroughly investigated. It was concluded that due to the properties of the shock absorbing material (closed cell structure, free of acids and halogens)

Property of Orano NCS GmbH and of the thermal protection materials (inorganic materials, free of acids and halogens) no negative effects are to be considered.

• Aging of the shock absorbing material is taken into account by the testing of samples as described in section 1.9.2.4.

• The inorganic materials used as thermal protection do not show any deterioration of their thermal properties during long term use. Aging is for these materials not a topic.

1.4.11.2 30B-X cylinder The design of the 30B-X cylinder is based on the 30B cylinder as standardized in [ANSI N14.1],

which has been in world-wide use for decades. The 30B-X cylinder (including the CCS except for the B4 C filling of the CCRs) is made of the same materials as the 30B cylinder. Hence, it can be safely assumed that aging mechanisms will have no significant impact on the 30B-X cylinder.

Regarding the B4 C filling of the CCRs, the material is extremely heat resistant, and since it is in powder form, it is not vulnerable to mechanical pressure. There is no concern of long-term loss of efficacy from neutron absorption due to the low neutron fluxes that the material is exposed to.

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0045-BSH-2020-001 Rev. 2 1.4.12 Transport Concept Generally, the DN30-X package is transported on dedicated flatracks. A maximum of four DN30-X packages can be mounted onto a 20 flatrack using the holes in the feet and suitable bolts.

• The components of the DN30-X packaging relevant for lifting the package or packaging are described in section 1.4.2.4.

• The components of the DN30-X packaging relevant for tie-down are described in sec-tion 1.4.2.5.

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 47 / 172

0045-BSH-2020-001 Rev. 2 1.5 Package Performance Characteristics 1.5.1 Main Design Principles The DN30-X packaging consists of the DN30 PSP that accommodates the 30B-X cylinder. Both the DN30 PSP and the 30B-X cylinder are designed by ONCS, where the 30B-X cylinder is spe-cifically designed with regard to [ANSI N14.1], fulfilling the same requirements as a standard 30B cylinder.

The 30B-X cylinder is primarily designed to be used as a pressure vessel in enrichment and fuel manufacturing plants to accept UF6 from the enrichment process and to feed enriched UF6 into the process at the fuel manufacturers site. UF6 contents with enrichments up to 10 or 20 wt.-%

235 U in uranium are permissible for the 30B-10 or 30B-20 cylinder, respectively. The 30B-X cylin-der provides the containment and the main confinement function of the DN30-X package.

For public transportation, the 30B-X cylinder is protected by the DN30 PSP against mechanical and thermal impacts as defined in [10 CFR Part 71] and [49 CFR Part 173] or [SSR-6 2018], so that the containment and confinement function of the 30B-X cylinder are maintained under RCT, NCT and HAC.

1.5.2 Performance Characteristics Geistiges Eigentum der Orano NCS GmbH 1.5.2.1 Performance Characteristics under RCT Under RCT, the main performance characteristics are:

Property of Orano NCS GmbH

• Safe handling of the DN30-X package

• Safe tie-down of the DN30-X package

• Adequate design for accelerations and vibrations to be routinely expected

• Easy handling operations under the environmental conditions to be routinely expected

• Resistance against corrosion

• Long term usability by considering temperatures and ambient conditions to be routinely ex-pected 1.5.2.2 Performance Characteristics under NCT Under NCT, the main performance characteristics are:

• Protection of the 30B-X cylinder against the mechanical loads to be expected under NCT

• Limitation of deformations to fulfill the requirement regarding dose rate increase 1.5.2.3 Performance Characteristics under HAC Under HAC, the main performance characteristics are:

• Protection of the 30B-X cylinder against mechanical loads to be expected under HAC

• Protection of the 30B-X cylinder against the thermal loads to be expected under HAC 48 / 172

0045-BSH-2020-001 Rev. 2 1.5.3 Assumptions Used for the Safety Analysis 1.5.3.1 Containment Function The containment function is provided by the 30B-X cylinder and its installed valve and plug. It is assumed that the containment function is preserved if:

• Following the tests prescribed in [10 CFR Part 71] §59(a)(2) or [SSR-6 2018] para. 685(b),

there is no physical contact between the valve or plug and any other component of the packaging other than their original points of attachment.

• Following the test prescribed in [10 CFR Part 71] §73(c)(4) or [SSR-6 2018] para. 728, the valve and the plug remain leak-tight.

1.5.3.2 Dose Rates The shielding function is provided by the shell of the 30B-X cylinder and the inner and outer shells of the DN30 PSP. For RCT and NCT, the foam between the inner and outer shell of the DN30 PSP is credited as well.

For the proof that the increase of the dose rate after the mechanical tests simulating NCT does not exceed the limits specified in the regulations, the reduction of the wall thickness of the DN30 PSP due to deformation is considered.

Geistiges Eigentum der Orano NCS GmbH 1.5.3.3 Criticality Safety The following assumptions are made for the proof of criticality safety:

Property of Orano NCS GmbH

• There are no requirements on the content, neither on its arrangement within the 30B-X cyl-inder nor regarding the distribution of impurities.

• Based on section 1.5.3.1, the containment function of the 30B-X cylinder is maintained. The maximal amount of water ingress under HAC is less than 3 g (see section 2.6.2.4).

• When taking impacts from HAC into account, the steel shells of the DN30 PSP will maintain a total thickness of at least 10 cm in radial direction (around the mantle) and at least 8 cm in axial direction (on the valve/plug ends).

• The closure system has to ensure that the top and bottom half of the DN30 PSP remain connected during RCT, NCT and HAC.

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0045-BSH-2020-001 Rev. 2 1.6 Compliance with Regulatory Requirements 1.6.1 Compliance with 10 CFR Part 71 In this section, the compliance of the Type AF package design DN30-X with the regulatory requirements [10 CFR Part 71] for the packaging and transportation of radioactive material is shown. The order of the paragraphs in column 1 of the tables follows [10 CFR Part 71]. Whenever possible, reference to the corresponding paragraphs from the IAEA regulations [SSR-6 2018] is provided in column 2 because some of the supplemental documentation frequently refers to the IAEA regulations [SSR-6 2018].

1.6.1.1 10 CFR Part 71 - Subpart A to D - General Provisions, Exemptions and Application for Package Approval Geistiges Eigentum der Orano NCS GmbH 10 CFR §71 IAEA SSR-6 Remarks 235 4 (fissile) 222 There is only the fissile nuclide U present in the content (see section 1.3).

4 (Type A) 428 The DN30-X package complies with the DOT regulations in [49 CFR Part 173] (see section 1.6.2).

Property of Orano NCS GmbH 15 417 There are no exceptions by one of the provisions specified in this paragraph (see specification of contents in section 1.3).

The application for approval under [10 CFR Part 71] includes the following information:

(a) A package description in section 1.4 as required.

31 -

(b) A package evaluation in part 2 as required.

(c) A reference to a previously approved quality assurance program (see section 1.9).

33(a) - A detailed description of the DN30-X packaging is provided in section 1.4.

33(b) - A detailed description of the contents of the DN30-X package is provided in section 1.3.

A demonstration that the DN30-X package satisfies the standards specified in subparts E and F of [10 CFR Part 71] is given in 35(a) -

part 2 of this SAR.

35(b) - The criticality safety index for the DN30-X package is defined in section 1.2.4.

Special controls and precautions for the DN30-X regarding transport, loading, unloading, and handling are specified in section 1.7.

35(c) -

For the DN30-X, there are no special controls required in case of an accident or delay.

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0045-BSH-2020-001 Rev. 2 10 CFR §71 IAEA SSR-6 Remarks The management system of ONCS for the design, fabrication, assembly, testing, maintenance, repair, modification, and use of the DN30-X package is audited and certified by the German competent authority (see section 1.9). Appendix 1.9.3 (Quality Assurance 37 306 Program) shows compliance of this system with the requirements of [10 CFR Part 71] - Subpart H and contains the corresponding NRC approval.

The effects on the DN30-X package of the tests specified in 10 CFR §71.71 and the tests specified in 10 CFR §71.73 are evaluated by 41 701 (a) subjecting specimens to a specific test (see Appendix 2.2 (Structural Analysis) and Appendix 2.3 (Thermal Analysis)) and (b) analysis and calculations (see part 2 of this SAR).

1.6.1.2 10 CFR Part 71 - Subpart E - Package Approval Standards General standards for all packages Geistiges Eigentum der Orano NCS GmbH 10 CFR §71 IAEA SSR-6 Remarks 43(a) 636 The smallest overall dimension of the DN30-X package is not less than 10 cm (see section 1.4).

The outside of the DN30-X package incorporates a seal, that is not readily breakable and that, while intact, is evidence that the 43(b) 637 Property of Orano NCS GmbH package has not been opened by unauthorized persons (see section 1.4.2.3.8).

The containment system of the DN30-X package is defined in section 1.4.3. The containment system cannot be opened unintentionally as it is enclosed by the DN30 PSP, which in turn is securely closed by a positive fastening device during transport 43(c) 641 (see section 1.4.2.3.4).

The containment system cannot be opened by a pressure that may arise within the package, as it withstands a hydraulic strength test at a pressure of 2.76 MPa, which is much higher than the internal pressure under RCT and NCT (see section 2.2.3.3).

The design of the 30B cylinder is standardized in [ANSI N14.1]. This design is world-wide in use since decades. The 30B-X 43(d) 614 cylinder is made of the same kind of materials as the 30B cylinder. Hence, it can be assumed that there will be no significant chemical, galvanic, or other reaction among the packaging components and the package contents.

The 30B-X cylinder with its valve is enclosed by the DN30 PSP during transport and, thus, is also protected against unauthorized 43(e) 615, 646 operation.

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0045-BSH-2020-001 Rev. 2 General standards for all packages 10 CFR §71 IAEA SSR-6 Remarks The DN30-X package is designed, constructed, and prepared for shipment so that under the tests simulating NCT specified in 10 CFR §71.71 there is:

43(f) 648 (a) No loss or dispersal of the radioactive UF6 content (see section 2.4).

(b) No significant increase (not greater than 20 %) in external surface radiation levels (see section 2.5.6.4).

(c) No substantial reduction in the effectiveness of the packaging.

The DN30-X package is designed, constructed, and prepared for transport so that in still air at 38 °C and in the shade, no 43(g) (654) accessible surface of the package has a temperature exceeding 50 °C so that a nonexclusive use shipment is possible (see section 2.3).

43(h) - The DN30-X package does not incorporate a feature intended to allow continuous venting during transport.

Geistiges Eigentum der Orano NCS GmbH Lifting and tie-down standards for all packages 10 CFR §71 IAEA SSR-6 Remarks (a) The lifting attachments, that are a structural part of the DN30-X package, are designed with a minimum safety factor of 3 Property of Orano NCS GmbH against yielding when used to lift the package in the intended manner (see section 2.2.4.3).

(b) They are designed so that failure of any lifting device under excessive load does not impair the ability of the DN30-X package to 45(a) 608, 609 meet other requirements of [10 CFR Part 71].

(c) Any other structural part of the DN30-X package that could be used to lift the package is rendered inoperable for lifting the package during transport (see section 1.4.2.4.2).

Each tie-down device that is a structural part of the DN30-X package withstands the acceleration forces required by 45(b)(1) 613 10 CFR §71.45(b) without generating stresses in any material of the package in excess of its yield strength (see section 2.2.5.1).

45(b)(2) - There are no other structural parts of the DN30-X package that could be used for tie-down of the package.

Each tie-down device that is a structural part of the DN30-X package is designed so that failure of this device under excessive load 45(b)(3) 638 does not impair the ability of the package to meet other requirements of [10 CFR Part 71] (see section 2.2.5.1).

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0045-BSH-2020-001 Rev. 2 External radiation standards for all packages 10 CFR §71 IAEA SSR-6 Remarks For all permissible contents in section 1.3, the transport index (TI) of the DN30-X package is below 10 (see section 2.5.6.1).

47(a) 526, 527 Furthermore, the radiation level at the surface of each DN30-X package does not exceed 2 mSv/h under conditions normally incident to transportation (see section 2.5.6.2).

The DN30-X package does not exceed the radiation level limits specified in 10 CFR §71.47(a). Hence, the radiation level limits in 47(b) 528, 573 this paragraph do not apply to the DN30-X package.

General requirements for fissile material packages 10 CFR §71 IAEA SSR-6 Remarks The DN30-X package is designed and constructed in accordance with 10 CFR §71.41 through 71.47. As a Type AF package 55(a) 673 design, 10 CFR §71.51 does not apply.

Geistiges Eigentum der Orano NCS GmbH The DN30-X package is so designed and constructed and its contents so limited that even if water were to leak into the containment system, it remains subcritical. Under the following conditions, maximum reactivity of the fissile material is attained:

(1) The chemical form of UF6 is well known. For the isotopic compositions, maximal values of the fissile nuclide 235U are assumed.

Physical form, mass, concentration of impurities, moderation ratio or density and geometrical configuration are varied to Property of Orano NCS GmbH 676, 677, determine the maximum neutron multiplication factor. The variation calculations are documented in section 2.6.5 and Appendix 55(b) 679-682 2.2.5 (Criticality Safety Analysis).

(2) For the individual DN30-X package in isolation, it is assumed that water can leak into the containment system and optimal moderation is assumed (see section 2.6.2.2).

(3) The analysis for an individual package in isolation assumes a layer of 30 cm water surrounding the DN30-X package (see section 2.6.2.2).

55(c) - Does not apply to the DN30-X package.

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0045-BSH-2020-001 Rev. 2 General requirements for fissile material packages 10 CFR §71 IAEA SSR-6 Remarks The DN30-X package is so designed and constructed, and its contents so limited that after being subjected to the tests simulating NCT:

(1) The content is subcritical (see section 2.6.6).

(2) The geometric form of the package content is not substantially altered (see section 2.2.6).

55(d) 678 (3) In the evaluation of the undamaged package, optimal moderation is assumed (see section 2.6.2.2).

(4) There is no substantial reduction in the effectiveness of the DN30-X packaging (see section 2.2.6), including:

i. No more than 5 % reduction in the total effective volume of the packaging on which nuclear safety is assessed.

ii. No more than 5 % reduction in the effective spacing between the fissile content and outer surface of the packaging.

iii. No occurrence of an aperture in the outer surface of the packaging large enough to permit the entry of a 10 cm cube.

The DN30-X package is so designed and constructed, and its contents so limited that after being subjected to the tests simulating Geistiges Eigentum der Orano NCS GmbH HAC the package remains subcritical. For this determination, it is assumed in section 2.6 that:

(1) The fissile material is in the most reactive credible configuration consistent with the damaged condition of the package and the 676, 677, chemical and physical form of the content.

55(e) 679-682 (2) Water moderation occurs to the most reactive credible extent consistent with the damaged condition of the package and the chemical and physical form of the content.

Property of Orano NCS GmbH (3) There is full reflection by water on all sides, as close as is consistent with the damaged condition of the package.

55(f) 683 The DN30-X package shall not be transported by air.

235 55(g) 680(b) The exception for packages containing uranium hexafluoride with a maximum enrichment of 5 wt.-% U in cannot be credited for the DN30-X package.

Standards for arrays of fissile material packages 10 CFR §71 IAEA SSR-6 Remarks 59(a)(1) 684 The number N derived for the DN30-X package is infinite. The proof of subcriticality under NCT is provided in section 2.6.5.3.

59(a)(2) 685 The number N derived for the DN30-X package is infinite. The proof of subcriticality under HAC is provided in section 2.6.5.3.

59(b) 686 For the DN30-X package, the following applies: CSI = 0 (see section 1.2.4).

59(c) - For the DN30-X package, the CSI = 0 so that package may be shipped by a carrier in a nonexclusive use conveyance.

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0045-BSH-2020-001 Rev. 2 1.6.1.3 10 CFR Part 71 - Subpart F - Package, Special Form, and LSA-III Tests Normal Conditions of Transport 10 CFR §71 IAEA SSR-6 Remarks 71(a) 719 See remarks to 10 CFR §71.71(c)(7)-(10) below.

The time interval between the water spray test and the subsequent tests has no impact on the performance of the subsequent

- 720 tests (see remark to 10 CFR §71.71(c)(6)).

During the mechanical tests with DN30 PSP prototypes documented in Appendix 2.2 (Structural Analysis), the ambient temperature was about 20 °C and there was no internal pressure within the containment (the 30B cylinder) as this is the more 71(b) -

unfavorable condition. In the structural analysis of the DN30-X package, ambient temperatures between -40°C and +38°C including insolation are considered (see section 2.2).

The design of the DN30-X package considers ambient temperatures ranging from -40 °C to +38 °C including insolation (see 71(c)(1)-(2) -

section 2.2).

Geistiges Eigentum der Orano NCS GmbH The internal pressure in the 30B-X cylinder during transport is below atmospheric. As the 30B-X cylinder withstands the hydraulic strength test at a test pressure of 2.76 MPa, the containment is not affected by a reduction of ambient pressure to 25 kPa (see 71(c)(3)-(4) - section 2.2.6.5).

Furthermore, the 30B-X cylinder is designed for an external pressure of 172 kPa so that the containment is not affected by an Property of Orano NCS GmbH increased external pressure of 140 kPa absolute (see section 2.2.6.5).

The package is designed to withstand effects of any acceleration, vibration or vibration resonance that may arise under NCT (see 71(c)(5) -

section 2.2.5).

The DN30 PSP is a fully closed and welded structure of stainless steel. Any influence of the water spray test on the properties of 71(c)(6) 721 the DN30-X package can be excluded (see section 2.2.6.1).

The free drop test is analyzed in sections 2.2.6.2 and 2.2.7. It was also carried out with DN30 PSP prototypes as documented in 71(c)(7) 722, 717 Appendix 2.2 (Structural Analysis). The target for the experimental drop tests and the drop test analyses complies with the requirements of [SSG-26 2012] para. 717.2.

71(c)(8) - The corner drop from a height of 0.3 m is not applicable as the mass of the DN30-X package exceeds 100 kg.

The shape of the packaging effectively prevents stacking. Nevertheless, the DN30-X successfully passes the compression test as 71(c)(9) 723 demonstrated in section 2.2.6.3.

The DN30-X package is designed to withstand HAC. The puncture test specified in 10 CFR §71.73(c)(3) is much more severe than 71(c)(10) 724 the penetration test specified in this paragraph (see also section 2.2.6.4).

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0045-BSH-2020-001 Rev. 2 Hypothetical Accident Conditions 10 CFR §71 IAEA SSR-6 Remarks DN30 PSP prototypes used for testing were subject to the cumulative effects of twice the mechanical tests specified in 73(a) 726 10 CFR §71.71(c)(7), followed by twice the tests specified in 10 CFR §71.73(c)(1)-(3), and finally followed by the thermal test specified in 10 CFR §71.73(c)(4) (see Appendix 2.2 (Structural Analysis) and Appendix 2.3 (Thermal Analysis)).

During the mechanical tests with DN30 PSP prototypes the ambient temperature was about 20 °C and there was no internal pressure within the containment (the 30B cylinder) as this is the more unfavorable condition (see Appendix 2.2 (Structural 73(b) -

Analysis), appendix B). In the structural analysis of the DN30-X package in section 2.2, ambient temperatures between -40°C and

+38°C including insolation are considered.

The performance of the DN30-X package subject to the free drop test from a height of 9 m is analyzed in section 2.2.7. It is based on the analyses for the DN30 package in Appendix 2.2 (Structural Analysis), appendix A and B where several free drop tests with 73(c)(1) 727(a), 717 DN30 PSP prototypes from a height of 9 m onto a flat, essentially unyielding, and horizontal surface were performed, striking the surface in different orientations for which maximum damage is expected. The target for drop tests complied with the requirements Geistiges Eigentum der Orano NCS GmbH of [SSG-26 2012] para. 717.2.

73(c)(2) 727 (c) The dynamic crush test is not applicable as the mass of the DN30-X package exceeds 500 kg.

The performance of the DN30-X package subject to the puncture test is analyzed in section 2.2.7. It is based on the analyses for 73(c)(3) 727 (b) the DN30 package in Appendix 2.2 (Structural Analysis), appendix A and B. The requirements for the bar and the drop target were Property of Orano NCS GmbH fulfilled in these tests.

The analysis of the DN30-X package subject to the thermal test is based on thermal tests that were carried out using DN30 PSP prototypes that suffered the cumulative effects of twice the mechanical tests specified in 10 CFR §71.71(c)(7) followed by twice the 73(c)(4) 728 tests specified in 10 CFR §71.73(c)(1)-(3). The test results are documented in Appendix 2.3 (Thermal Analysis), appendix 1 and analyzed in section 2.3.

The immersion test for fissile material is not applicable to the DN30-X package as optimal moderation and full flooding is assumed 73(c)(5) 731-733 in the criticality safety analysis. Furthermore, the test conditions defined in 10 CFR §71.73(c)(6) are more demanding for the DN30-X package.

The water immersion test is analyzed in section 2.2.7.2. Inleakage of water during this test is taken into account in the criticality 73(c)(6) 729 safety analysis (see section 2.6 and Appendix 2.6 (Criticality Safety Analysis)). The test conditions before the water immersion test still comply with the test conditions required by 10 CFR §71.55.

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0045-BSH-2020-001 Rev. 2 1.6.1.4 10 CFR Part 71 - Subpart G - Operating Controls and Procedures 10 CFR §71 IAEA SSR-6 Remarks The chemical form of UF6 is well known. For the isotopic compositions, maximal values of the fissile nuclide 235U are assumed.

83 - Physical form, mass, concentration of impurities, moderation ratio or density, and geometrical configuration are varied to determine the maximum neutron multiplication factor.

The manufacturing specifications Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) and Appendix 1.9.2B (Manufacturing Specification DN30 PSP) as well as the testing requirements and controls before first use in section 1.7.1 ensure that there are no cracks, pinholes, uncontrolled voids, or other defects that could significantly reduce the effectiveness of the DN30-X packaging:

(a) The effectiveness of the containment is within the limits specified for the DN30-X package as the 30B-X cylinder is 85(a) 501(b)-(c) manufactured and tested before its first use to prove its compliance with [ANSI N14.1].

(b) The effectiveness of the confinement is within the limits specified for the DN30-X package as the applied measures ensure that the CCS of the 30B-X cylinder is present and in proper condition.

Geistiges Eigentum der Orano NCS GmbH (c) The effectiveness of the shielding, structural and thermal protection are within the limits specified for the package as the applied measures ensure that the 30B-X cylinder and the DN30 PSP are in proper condition.

The MNOP for the DN30-X package is defined in section 1.2.9 with 152 kPa. Consequently, the requirements of this paragraph are 85(b) 501(a) fulfilled, as a hydraulic strength test at a test pressure of 2.76 MPa is performed for the 30B-X cylinder, which is the containment Property of Orano NCS GmbH system of the DN30-X package (see section 2.2.3.3).

The DN30-X packaging is conspicuously and durably marked on the nameplate with its model number, serial number, gross weight, and the package identification number assigned by the NRC (see section 1.4).

85(c) 501, 533 Before the model number is applied to a DN30-X packaging, it is determined whether the packaging has been fabricated in accordance with the design approved by the Commission (see section 1.7.1).

The analyses in part 2 of this SAR prove that the DN30-X package is properly designed for the contents specified in section 1.3.

87(a) 502 Furthermore, administrative controls ensure that only the contents as specified in the certificate of package approval are loaded into the DN30 PSP (see section 1.7.2).

The testing requirements and controls before each transport in section 1.7.2 ensure that the DN30-X package is in unimpaired 87(b) -

physical condition except for superficial defects such as marks or dents.

The testing requirements and controls before each transport in section 1.7.2 ensure that the closure devices of the DN30-X 87(c) -

package (including any required gasket) are properly installed and secured and free of defects.

The testing requirements and controls before each transport in section 1.7.2 ensure that during transport the UF6 is in solid form.

87(d) - However, to make provisions for filling effects, the 30B-X cylinder is always filled to less than 60 % taking care of the significant expansion of UF6 during its solid to liquid phase change in case the UF6 is liquefied during filling or emptying.

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0045-BSH-2020-001 Rev. 2 10 CFR §71 IAEA SSR-6 Remarks 87(e) - Does not apply to the DN30-X package as no specific pressure relief devices are present in the package design.

The handling instructions defined in section 1.7.4 ensure that the DN30-X package is loaded and closed in accordance with written 87(f) 503(c) procedures.

The manufacturing specifications in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) and the testing requirements and controls before first use in section 1.7.1 ensure that the CCS of the 30B-X cylinder is present and in proper condition. The 87(g) 501(c) handling instructions defined in sections 1.7.3 and 1.7.4, the testing requirements and controls before each transport in section 1.7.2 and the prescribed inspections in section 1.8 ensure that the proper condition of the CCS is maintained throughout the life-time of a 30B-X cylinder.

87(h) 503(a) The handling instructions defined in sections 1.7.3 and 1.7.4 take into account the respective measures.

- 507 Other dangerous properties of UF6 are taken into account (see section 1.7.6).

Contamination checks defined in section 1.7.2 take the specified limits specified in DOT regulations in 49 CFR §173.443 into 87(i) 508 Geistiges Eigentum der Orano NCS GmbH account.

The external radiation levels around the DN30-X package and around the vehicle do not exceed the limits specified in 87(j) -

10 CFR §71.47 at any time during transportation (see section 1.6.1.2).

The accessible DN30-X package surface temperatures do not exceed the limits specified in 10 CFR §71.43(g) at any time during 87(k) 503(b)

Property of Orano NCS GmbH transportation (see section 1.6.1.2).

Special instructions needed to safely open the DN30-X package are documented in the handling instruction in Appendix 1.7.1 89 -

(Handling Instruction). The handling instruction will be made available to all users of the DN30-X package (see section 1.9.3).

1.6.1.5 10 CFR Part 71 - Subpart H - Quality Assurance 10 CFR §71 IAEA SSR-6 Remarks The management system of ONCS is audited and certified by the German competent authority (see section 1.9). Appendix 1.9.3 Subpart H 306 (Quality Assurance Program) shows compliance of this system with the requirements of this subpart and contains the (101 - 137) corresponding NRC approval.

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0045-BSH-2020-001 Rev. 2 1.6.2 Compliance with 49 CFR Part 173 In this section, the compliance of the Type AF package design DN30-X with the regulatory requirements [49 CFR Part 173] for the transport of radio-active material is shown. The order of the paragraphs in column 1 of the tables follows [49 CFR Part 173]. Whenever possible, reference to the corresponding paragraphs from the IAEA regulations [SSR-6 2018] is provided in column 2 because some of the supplemental documentation fre-quently refers to the IAEA regulations [SSR-6 2018].

1.6.2.1 Definitions and General Design Requirements General design requirements 49 CFR §173 IAEA SSR-6 Remarks 2(a) 507, 618 Other dangerous properties of UF6 are taken into account (see section 1.7.6).

235 403 (fissile) 222 Geistiges Eigentum der Orano NCS GmbH There is only the fissile nuclide U present in the content (see section 1.3).

410(a) 607 The DN30-X package can be easily handled and properly secured during transport (see sections 1.4.2.4 and 1.4.2.5).

(a) The lifting attachments, that are a structural part of the DN30-X package, are designed with a minimum safety factor of 3 against yielding when used to lift the package in the intended manner (see section 2.2.4.3).

Property of Orano NCS GmbH (b) They are designed so that failure of any lifting device under excessive load does not impair the ability of the DN30-X package 410(b) 608, 609 to meet other requirements of 49 CFR Subpart I.

(c) Any other structural part of the DN30-X package that could be used to lift the package is rendered inoperable for lifting the package during transport (see section 1.4.2.4.2).

The external surfaces of the DN30-X package, as far as practicable, are free from protruding features and consist of stainless 410(c) 610 steel. Therefore, they are easily decontaminated (see section 1.4.2).

410(d) 611 The outer layer of the package prevents the collection and retention of water (see section 1.4.2).

410(e) 612 There are no features added to the package at the time of transport that could reduce its safety (see section 1.4.2.5).

The DN30-X package is designed to withstand the effects of any acceleration, vibration or vibration resonance that may arise under RCT or NCT without any deterioration in the effectiveness of the closing devices on the various receptacles or in the 410(f) 613 integrity of the DN30-X package as a whole and without loosening or unintentionally releasing the nuts, bolts, or other securing devices even after repeated use (see section 2.2.5).

The DN30-X packaging consists mainly of the materials stainless steel and foam. Those are physically and chemically compatible 410(g) 614 with each other. Any part in contact with the radioactive UF6 content has been designed for this purpose (see section 1.4.2).

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0045-BSH-2020-001 Rev. 2 General design requirements 49 CFR §173 IAEA SSR-6 Remarks The valve and the plug of the 30B-X cylinder are protected by the DN30 PSP during transport and cannot be operated 410(h) 615 unauthorized (see section 1.4.2).

The DN30-X package is designed to comply with the requirements for fissile material packages. It takes into account ambient

- 616 temperatures and pressures that are likely to be encountered under RCT.

The radiation level at the surface of the DN30-X package does not exceed 2 mSv/h under conditions normally incident to

- 617 transportation (see section 2.5.6.2).

410(i) 619-621 The DN30-X package shall not be transported by air.

1.6.2.2 Additional Design Requirements for Type A Packages Geistiges Eigentum der Orano NCS GmbH Additional design requirements for Type A packages 49 CFR §173 IAEA SSR-6 Remarks The DN30-X package meets the general design requirements prescribed in 49 CFR §173.410 and is also designed to meet the 412 635 requirements prescribed in 49 CFR §173.412(a)-(l).

Property of Orano NCS GmbH The outside of the DN30-X package incorporates a seal, that is not readily breakable and that, while intact, is evidence that the 412(a) 637 package has not been opened by unauthorized persons (see section 1.4.2.3.8).

412(b) 636 The smallest overall dimension of the DN30-X package is not less than 10 cm (see section 1.4).

The design of the DN30-X packaging takes into account temperatures ranging from -40 °C to +70 °C (see section 1.4.1). Special 412(c) 639 attention is given to the potential degradation of the packaging materials within the temperature range.

The design and manufacturing techniques for the 30B-X cylinder are in accordance with ASME and ANSI standards.

- 640 The design and manufacturing techniques for the DN30 PSP are in accordance with ISO and EN standards.

The containment system of the DN30-X package is defined in section 1.4.3. The containment system cannot be opened unintentionally as it is enclosed in the DN30 PSP, which in turn is securely closed by a positive fastening device during transport 641, 642, (see section 1.4.2.3.4).

412(d) 643 The containment system cannot be opened by a pressure that may arise within the package, as it withstands a hydraulic strength test at a pressure of 2.76 MPa, which is much higher than the internal pressure under RCT and NCT (see section 2.2.3.3).

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0045-BSH-2020-001 Rev. 2 Additional design requirements for Type A packages 49 CFR §173 IAEA SSR-6 Remarks The design of the 30B cylinder is standardized in [ANSI N14.1]. This design is world-wide in use since decades. The 30B-X 412(e) 644 cylinder is made of the same kind of materials as the 30B cylinder. Hence, it can be assumed that there will be no significant radiolytic decomposition of materials or generation of gas by chemical reaction and radiolysis.

The pressure in the 30B-X cylinder during transport is below atmospheric pressure. As the 30B-X cylinder withstands a test 412(f) 645 pressure of 2.76 MPa, the containment is not affected by a reduction of ambient pressure to 60 kPa.

412(g) 646 The 30B-X cylinder with its valve is enclosed by the DN30 PSP during transport.

412(h) 647 The 30B-X cylinder is enclosed in the DN30 PSP, which is securely closed by a positive fastening device (see section 1.4.2).

Each tie-down device that is a structural part of the DN30-X package is designed so that failure of this device under excessive 412(i) 638 load does not impair the ability of the package to meet other requirements of 49 CFR Subpart I (see section 2.2.5.1).

When evaluated against the performance requirements of this section and the tests specified in 49 CFR §173.465, the DN30-X Geistiges Eigentum der Orano NCS GmbH packaging prevents:

412(j) 648 (1) Loss or dispersal of the radioactive UF6 contents (see section 2.4).

(2) A significant increase (more than 20 %) in the radiation levels recorded or calculated at the external surfaces for the condition before the test (see section 2.5.6.4).

Property of Orano NCS GmbH During transport the UF6 is in solid form. However, to make provisions for filling effects, the 30B-X cylinder is always filled to less 412(k)(1) 649 than 60 % taking care of the significant expansion of UF6 during its solid to liquid phase change in case the UF6 is liquefied during filling or emptying.

412(k)(2) 650 Not applicable to the DN30-X package as during transport the UF6 is in solid form.

412(l) 651 Not applicable to the DN30-X package as during transport the UF6 is in solid form.

1.6.2.3 Authorized Type A and Fissile Material Packages 49 CFR §173 IAEA SSR-6 Remarks The DN30-X is a Type AF packaging that meets the applicable standards for fissile materials in 10 CFR Part 71 and is used in 415 -

accordance with 49 CFR §173.471.

417 - The DN30-X is a Type AF packaging that meets the applicable standards for fissile material packages in 10 CFR Part 71.

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0045-BSH-2020-001 Rev. 2 1.6.2.4 Uranium Hexafluoride 49 CFR §173 IAEA SSR-6 Remarks The contents of the DN30-X package comply with the following requirements:

(a) The permissible mass of UF6 is specified for the 30B-X cylinder in section 1.3.2.1.

- 420 (b) The permissible mass of UF6 considers a minimal ullage of 5 % at the maximum temperature of the DN30-X package.

(c) When presented for transport, the UF6 is in solid form and the internal pressure is below atmospheric pressure.

In addition to the other applicable requirements of 49 CFR Subpart I, the following is considered for the DN30-X package with regard to its UF6 content:

(1) Before initial filling and during periodic inspection and test, the 30B-X cylinder is cleaned in following the requirements of

[ANSI N14.1] for standard 30B cylinders.

(2) The 30B-X cylinder is designed, fabricated, inspected, tested and marked with regard to the requirements for standard 30B cylinders in [ANSI N14.1]. A formal inclusion of the 30B-X cylinder in [ANSI N14.1] is in preparation.

Geistiges Eigentum der Orano NCS GmbH (3) The DN30-X package is designed so that it will:

(i) Withstand a hydraulic strength test at an internal pressure of 2.76 MPa without leakage (see section 2.2.3.3).

420, 631, 420(a) (ii) Withstand the test specified in 49 CFR §173.465(c) without loss or dispersal of the UF6 (see section 2.2.6).

632, 718 (iii) Withstand the test specified in 10 CFR §71.73(c)(4) without rupture of the containment system (see section 2.2.7).

Property of Orano NCS GmbH (4) The testing requirements and controls before each transport in section 1.7.2 ensure that during transport, the UF6 is in solid form.

(5) The volume of the solid UF6 content does not exceed 61 % of the certified volumetric capacity of the 30B-X cylinder at 20 °C to take care of the significant expansion of UF6 during its solid to liquid phase change in case the UF6 is liquefied during filling or emptying.

(6) The testing requirements and controls before each transport in section 1.7.2 ensure that during transport, the internal pressure in the 30B-X cylinder is below atmospheric pressure (less than 101.3 kPa at 20 °C).

- 633 The DN30-X package has no pressure relief valves.

- 634 Does not apply to the DN30-X package.

The inspections prescribed in section 1.8 ensure that the DN30-X package is periodically inspected, tested, marked and 420(b) -

otherwise conforms with the requirements of [ANSI N14.1].

420(c) - Each repair to a 30B-X cylinder is performed with regard to the requirements of [ANSI N14.1] (see section 1.9.4).

For the DN30-X package, the proper shipping name and UN number Radioactive material, uranium hexafluoride, fissile, 420(d)-(e) 401, 419 UN 2977 must be used (see section 1.2.4).

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0045-BSH-2020-001 Rev. 2 1.6.2.5 Activity Limits, Radiation Level and Thermal Limitations, Contamination Control and Transportation 49 CFR §173 IAEA SSR-6 Remarks 431(a) 429 The activity in a DN30-X package licensed as Type AF package is limited to 12 (see section 1.3.2.5).

433(d) 430 For mixtures of radionuclides, the respective formula is applied.

For all permissible contents in section 1.3, the transport index (TI) of the DN30-X package is below 10 (see section 2.5.6.1).

441 527, 617 Furthermore, the radiation level at the surface of each DN30-X package does not exceed 2 mSv/h under conditions normally incident to transportation (see section 2.5.6.2).

The DN30-X package is designed, constructed, and prepared for transport so that in still air at 38 °C and in the shade, no 442 (654), 679 accessible surface of the package has a temperature exceeding 50 °C so that a nonexclusive use shipment is possible (see section 2.3).

447 568 For the DN30-X package, the CSI = 0 in all cases and, thus, also for groups of DN30-X packages the sum of the CSIs is 0.

Geistiges Eigentum der Orano NCS GmbH

- 569 Not applicable to the DN30-X package as the CSI = 0 in all cases.

- 570 Not applicable as the material defined in section 1.3 does not meet any of the provisions in 49 CFR §173.453.

The DN30-X package is transported by road, rail or sea on dedicated flat racks. The tie-down features of the package are 448(a) 564 designed such that shifting of the package during normal transportation conditions is prevented.

Property of Orano NCS GmbH 448(b) 565 Not applicable to the DN30-X package.

448(c) 563 Not applicable to the DN30-X package.

448(d)-(g) - Not applicable to the DN30-X package.

The radiation level of a conveyance of several packages is below 2 mSv/h at any point of the external surface and below

- 566(b) 0.1 mSv/h at 2 m distance from the external surface (see section 2.5.6.3).

453 417 There are no exceptions by one of the provisions specified in this paragraph (see specification of contents in section 1.3).

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0045-BSH-2020-001 Rev. 2 49 CFR §173 IAEA SSR-6 Remarks (a) A CSI and a TI in accordance with 49 CFR §173.403 will be assigned to the DN30-X package.

(b) The DN30-X package satisfies the radiation level restrictions of 49 CFR §173.441(a).

(c) For the DN30-X package, the CSI = 0 so that package may be shipped by a carrier in a nonexclusive use conveyance.

(d) For the DN30-X package, the CSI = 0 in all cases and, thus, also for groups of DN30-X packages the sum of the CSIs is 0.

457 525-528 (e) See (c).

(f) See (b).

(g) See 49 CFR §173.447.

(h) See section 1.6.2.7.

459 - Not applicable to the DN30-X package.

1.6.2.6 Test Procedures Geistiges Eigentum der Orano NCS GmbH General test procedures 49 CFR §173 IAEA SSR-6 Remarks For the demonstration of compliance, the following methods are used:

Property of Orano NCS GmbH (1) Performance of tests with DN30 PSP prototypes (see Appendix 2.2 (Structural Analysis), appendix A and B, and Appendix 2.3 461 701 (Thermal Analysis), appendix 1).

(2) Analysis and calculations for the DN30-X package in part 2 of this SAR.

The DN30 PSP prototypes used for the tests were assessed before and after the tests according to written procedures (see

- 702 Appendix 2.2 (Structural Analysis), appendix B and Appendix 2.3 (Thermal Analysis), appendix 1).

The DN30 PSP prototypes used for the tests were inspected before each test according to a written procedure. The results of the inspection were documented. The inspection comprised at least:

(a) Divergence from the design (b) Defects in manufacture 462(a) 713 (c) Corrosion and deterioration (d) Distortion of features The inspection procedures are specified in Appendix 2.2 (Structural Analysis), appendix A and B, and Appendix 2.3 (Thermal Analysis), appendix 1.

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0045-BSH-2020-001 Rev. 2 General test procedures 49 CFR §173 IAEA SSR-6 Remarks The deviations from the specified design for the DN30 PSP were taken into account in the subsequent evaluation of the DN30-X 462(b) -

package.

462(c) 714 The containment system of the DN30-X package is defined in section 1.4.3.

The DN30 PSP prototypes used for the tests were marked with a serial No. and, therefore, could be easily referenced (see 462(d) 715 Appendix 2.2 (Structural Analysis), appendix A and B, and Appendix 2.3 (Thermal Analysis), appendix 1).

After each test or group of tests or sequence of the applicable tests, as appropriate:

(a) Faults and damage are identified and recorded (see Appendix 2.2 (Structural Analysis).

- 716 (b) It is determined whether the integrity of the containment system and shielding has been retained to the extent required (see Appendix 2.2 (Structural Analysis).

(c) It is determined whether the assumptions and conditions used in the criticality safety analysis for one or more packages are Geistiges Eigentum der Orano NCS GmbH valid (see Appendix 2.2 (Structural Analysis).

Type A packing tests and tests for demonstrating the ability of fissile materials packagings to withstand accident conditions in transportation Property of Orano NCS GmbH 49 CFR §173 IAEA SSR-6 Remarks 465(a) 719 See 49 CFR §173.465(b)-(e).

The DN30 PSP is a fully closed and welded structure of stainless steel. Any influence of the water spray test on the properties of 465(b) 720,721 the DN30-X package can be excluded (see section 2.2.6.1).

The free drop test is analyzed in sections 2.2.6.2 and 2.2.7. It was also carried out with DN30 PSP prototypes as documented in 465(c) 722 Appendix 2.2 (Structural Analysis), appendix B. The target for the experimental drop tests and the drop test analyses complies with the requirements of [SSG-26 2012] para. 717.2.

465(c)(2) - The impact from preceding 0.3 m corner drops is estimated to be negligible for the DN30-X package (see section 2.2.6.2).

465(c)(5) 717 The target for drop tests complies with the requirements of [SSG-26 2012] para. 718.2.

The shape of the packaging effectively prevents stacking. Nevertheless, the DN30-X successfully passes the compression test as 465(d) 723 demonstrated in section 2.2.6.3.

The DN30-X package is designed to withstand HAC. The puncture test (drop onto a bar) specified in 10 CFR §71.73(c)(3) is 465(e) 724 much more severe than the penetration test specified in this paragraph (see also section 2.2.6.4).

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0045-BSH-2020-001 Rev. 2 Type A packing tests and tests for demonstrating the ability of fissile materials packagings to withstand accident conditions in transportation 49 CFR §173 IAEA SSR-6 Remarks 466 725 Not applicable as during transport, the UF6 content is in solid form.

The DN30-X package meets the test requirements prescribed in 10 CFR Part 71 for the ability to withstand accident conditions in 467 726-733 transportation (see section 1.6.1.3).

Quality control for constructing of packaging and quality control requirements prior to each shipment 49 CFR §173 IAEA SSR-6 Remarks The manufacturing specifications in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) and Appendix 1.9.2B (Manufacturing Specification DN30 PSP) as well as the testing requirements and controls before first use in section 1.7.1 ensure that:

474 501, 501(b)

Geistiges Eigentum der Orano NCS GmbH (a) The DN30-X packaging meets the design and construction requirements as specified in 49 CFR Subpart I.

(b) The effectiveness of the shielding and containment are within the limits specified for the package. The DN30-X packaging has no dedicated component for heat dissipation because of the very low level of thermal power.

The administrative controls before shipment in section 1.7.2 ensure that only the contents as specified in the certificate of 475(a) 502 package approval are loaded into the DN30-X packaging.

Property of Orano NCS GmbH 475(b) - The DN30-X packaging is in unimpaired physical condition, except for superficial marks.

475(c) - Each closure device of the DN30-X packaging, including any required gasket, is properly installed, secured, and free of defects.

The manufacturing specification in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) and the testing requirements and controls before first use in section 1.7.1 ensure that the CCS of the 30B-X cylinder is present and in proper condition. The 475(d) 501(c) handling instructions defined in sections 1.7.3 and 1.7.4, the testing requirements and controls before each transport in section 1.7.2 and the prescribed inspections in section 1.8 ensure that the proper condition of the CCS is maintained throughout the life-time of a DN30-X package.

475(e) Each special instruction for filling, closing, and preparation of the packaging for shipment has been followed.

Each closure, valve, or other opening of the containment system through which the radioactive content might escape is properly 475(f) 503(c) closed and sealed.

475(g) - Not applicable to the DN30-X package.

475(h) - The internal pressure of the containment system will not exceed the design pressure during transportation.

475(i) - External radiation and contamination levels are within the allowable limits specified in 49 CFR Subpart I.

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0045-BSH-2020-001 Rev. 2 Quality control for constructing of packaging and quality control requirements prior to each shipment 49 CFR §173 IAEA SSR-6 Remarks 476 803 Not applicable to the DN30-X package.

1.6.2.7 Additional Requirements Relating to Transport by Vessel 49 CFR §176 IAEA SSR-6 Remarks The radiation level of a conveyance of several packages is below 2 mSv/h at any point of the external surface and below 704(a) 566 (b) 0.1 mSv/h at 2 m distance from the external surface (see section 2.5.6.3).

704(b) 575 The radiation level at the surface of each package is below 2 mSv/h (see section 2.5.6.3).

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 67 / 172

0045-BSH-2020-001 Rev. 2 1.7 Operation Operation of the DN30-X packaging is subdivided into four lifetime phases of the DN30-X pack-aging:

1. Testing and controls before its first use,

2. Regular usage and testing and controls before each transport,

3. Periodical inspection in defined intervals,

4. Repairs to return the DN30-X packaging to service.

All these phases are regulated in manufacturing specifications, handling and test instructions as specified below. At the time of application of these specifications and instructions, the user must make sure that valid revisions of these specifications and instructions are available.

Operation of the 30B-X cylinder in facilities, especially with regard to filling, emptying and washing, is described in Appendix 1.7.3 (30B-X Cylinder Facility Operations), along with the demonstration that these processes have no impact on the safe transport of the DN30-X package.

1.7.1 Testing Requirements and Controls before first Use Geistiges Eigentum der Orano NCS GmbH The testing requirements and controls before the first use of the packaging are specified in:

• The specification for the 30B-X cylinder in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder)

Property of Orano NCS GmbH

• The specification for the DN30 PSP in Appendix 1.9.2B (Manufacturing Specification DN30 PSP) 1.7.2 Testing Requirements and Controls before each Transport The testing requirements and controls before each transport are described in:

• Section 1.7.2.1 for the 30B-X cylinder

• Section 1.7.2.2 for the DN30 PSP

• For annual and 5-year inspection requirements as well as treatment of non-conformances and deviations see section 1.8.

1.7.2.1 Inspection of the 30B-X Cylinder Before filling the 30B-X cylinder, inspections in accordance with [ANSI N14.1] and at least as described in [USEC 651] (or in equivalent plant specific instructions) shall be carried out:

• The 30B-X cylinder shall be handled and filled in accordance with [ANSI N14.1] and at least as described in [USEC 651].

• The 30B-X cylinder has a valid maintenance certificate (valid date on the 30B-X cylinders nameplate).

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• 30B-X cylinders that have not been inspected and tested within the required 5-year period shall not be refilled until they are properly reinspected and retested. Prior to shipment, 30B-X cylinders that have not been recertified within the 5-year requirement shall be visually inspected for degradation of the cylinder wall. Any questionable conditions should be inves-tigated. Details on the visual inspection are provided in the test instruction in Appendix 1.8.1 (Inspections of 30B-X Cylinders).

• Any defective condition must be corrected before filling according to the requirements of

[ANSI N14.1]:

- The 30B-X cylinder shall be routinely examined as received and prior to sampling, with-drawal, filling, or shipping to ensure that it remains in a safe and usable condition.

- Leakage, cracks, excessive distortion, bent or broken valves or plugs, broken or torn skirts, or other conditions that may affect the safe use of the cylinder shall warrant ap-propriate precautions, including removing the cylinder from service until the defective condition is satisfactorily corrected.

- Questionable conditions should be referred to a qualified inspector for evaluation and for recommendations concerning use, repair, or condemnation of the cylinder in question.

- Conditions of the 30B-X cylinder that might indicate excessive damage of the CCS, such as severe outer damages of the cylinder shell or skirts, should be referred to a qualified inspector. Reuse of such cylinders is only allowed after internal inspection of such cylin-Geistiges Eigentum der Orano NCS GmbH ders and proof that the CCS is undamaged.

• Before filling, the cylinder is weighted to establish the net weight of the heels to ensure the fill limit will not be exceeded.

Property of Orano NCS GmbH

• To avoid overfilling, the 30B-X cylinder shall be weighted after being filled.

Before loading into the DN30 PSP, the inspection of the 30B-X cylinder should be carried out in accordance with [ANSI N14.1], and at least as described in [USEC 651] (or in equivalent plant specific instructions):

• The content of the 30B-X cylinder has to comply with the certificate of approval of the DN30-X package.

• Before shipping, the 30B-X cylinder shall be inspected for leak-tightness, damage, as well as other unacceptable conditions.

• UF6 shall be shipped only in solid form and when the vapor pressure within the 30B-X cyl-inder is below atmospheric.

• The safe state of the 30B-X cylinder shall be recorded by the UF6 supplier and the record shall be provided to the shipper.

Special care has to be taken to ensure that the filled cylinder fulfills the leak-tightness criteria of

[ANSI N14.1] and the following requirements:

• The leak tightness of the valve seat of a filled cylinder shall be verified by leakage rate testing of the pigtail before disconnection and after closing the cylinder valve seat.

• A standardized leakage rate larger than N = 1 104 Pa m3 s specified in section 1.2.10 shall not be permitted.

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• If air is used for a pressure drop test, the air supply should be clean, dry and free from oil.

If it is not, or if the quality of the air supply is uncertain, the test should be performed with nitrogen to ensure reliable results.

- The leakage test method shall comply to [ANSI N14.5] or [ISO 12807].

- The test shall be performed using a pressure gauge, accurate within 1 %, or less, of full scale.

- After the test pressure of 100 psig (690 kPa gauge) prescribed in [ANSI N14.1] has been applied, the pressure supply shall be removed. A drop in pressure within a test period of at least 15 minutes that is greater than the minimum detectable amount shall be cause for test failure.

- Corrective measures shall be taken to remedy the leak as prescribed by the facilitys operating procedures.

• Alternatively, a vacuum test may be performed on the cylinder by attaching a pigtail to the closed cylinder valve and drawing a vacuum for at least 15 minutes.

- The continued presence of UF6 in the pigtail is an indication that the valve is not fully closed or is defective.

- Corrective measures shall be taken to remedy the leak as prescribed by the facilitys operating procedures.

Geistiges Eigentum der Orano NCS GmbH Note: the cylinders outer surface shall be approximately at ambient temperature and its vapor pressure below atmospheric pressure.

Property of Orano NCS GmbH 1.7.2.2 Inspection of the DN30 PSP The DN30 PSP shall be inspected prior to loading according to the handling instruction in Appen-dix 1.7.1 (Handling Instruction). The inspection comprises:

• A visual inspection

• A functional test of all movable parts Following observations shall be cause for further investigation, replacement of parts, or rejection of the DN30 PSP as specified in detail in the test instruction in Appendix 1.8.2 (Inspections of DN30 PSPs):

• Structural changes of exterior or interior shells like excessive deformations, cracks, holes, etc.

• Excessive damage of flange areas

• Missing or damaged marking of the DN30 PSP

• Missing or damaged thermal plugs

• Missing or damaged gasket

• Damage of the mortise-and-tenon closure system

• Missing or damaged seals

• Damage of the valve protecting device as well as functional issues

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0045-BSH-2020-001 Rev. 2

• Excessive wear and tear of the intumescent material

• Damage to any welding seams like cracks, holes, excessive corrosion

• Excessive damage of handling devices

• Excessive damage of the silicon pads The test instruction in Appendix 1.8.2 (Inspections of DN30 PSPs) contains in detail the criteria and measures in case of deviations during the visual inspections and functional tests. Measures could comprise cleaning, replacement of parts, minor repairs (on site) and major repairs (to be carried out by the license holder or an authorized repair shop qualified for such repair).

1.7.3 Handling and Tie-down Requirements Handling of the DN30-X package, the DN30-X packaging and also its parts is described in section 1.4.2.4. For the handling operations, adequate means as described in the handling instruction in Appendix 1.7.1 (Handling Instruction) have to be used.

Tie-down of the DN30-X package and packaging is described in section 1.4.2.5. The procedures to be applied to ensure proper tie-down are specified in the handling instruction in Appendix 1.7.1 (Handling Instruction).

Geistiges Eigentum der Orano NCS GmbH 1.7.4 Loading Procedures for the 30B-X Cylinder and the DN30 PSP Before each use, the 30B-X cylinder and the DN30 PSP shall be inspected as described in sec-tion 1.7.2.1 and section 1.7.2.2, respectively.

Property of Orano NCS GmbH 1.7.4.1 Loading and unloading of UF6 content into the 30B-X Cylinder Filling with UF6, and emptying and washing of 30B-X cylinders is described in site-specific oper-ating handbooks that are not part of this SAR. General aspects of these processes are described in Appendix 1.7.3 (30B-X Cylinder Facility Operations), along with the demonstration that these processes have no impact on the safe transport of the DN30-X package.

Before transport, it must be assured that the 30B-X cylinder was given ample time for cooling down such that the UF6 is in solid form.

The testing and controls described in section 1.7.2 shall be performed and documented prior to loading a 30B-X cylinder into the DN30 PSP.

Any 30B-X cylinder filled with either UF6 or heels from UF6 shall comply with the transport regu-latory requirements for UF6.

1.7.4.2 Loading of the 30B-X Cylinder into the DN30 PSP Loading of a 30B-X cylinder into the DN30 PSP is identical to loading a standard 30B cylinder into the DN30 PSP. An overview of the safety related loading steps during loading of a 30B-X cyl-inder into the DN30 PSP is listed in the following:

1. The lever of the rotation preventing devices are in position open.

2. The valve protecting device and its housing are in position open.

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3. Lower the 30B-X cylinder in horizontal orientation with the valve in 12°oclock position into the bottom half of the DN30 PSP.

4. When the lower rim of the cylinder skirt has passed the valve protecting device, rotate the valve protecting device towards the cylinder head by about 90° until it gets in contact with the cylinder head. Then lower the cylinder until it rests on the inner shell of the bottom half of the DN30 PSP. Then push the housing in position closed.

5. Move the lever of the rotation preventing devices to position closed.

6. Lower the top half of the DN30 PSP onto the bottom half.

7. Insert the pins into the six mortise-and-tenon closure devices and fix the pins with the se-curing bolts.

8. Install the seals.

Details on each loading step are specified in the handling instruction in Appendix 1.7.1 (Handling Instruction).

1.7.4.3 Unloading of the 30B-X Cylinder from the DN30 PSP Unloading of a 30B-X cylinder from the DN30 PSP is identical to unloading a standard 30B cylin-der from the DN30 PSP. In order to prevent damage of any safety related feature during unload-ing, the following general steps are required:

Geistiges Eigentum der Orano NCS GmbH

1. Check and remove the seals.

2. Loosen the securing bolts and remove the pins of the six mortise-and-tenon closure de-vices.

Property of Orano NCS GmbH

3. Lift off the top half of the DN30 PSP.

4. Move the lever of the rotation preventing devices to position open.

5. Pull the housing from the valve protecting device in position open.

6. Lift the 30B-X cylinder and rotate the valve protecting device by about 90° until it rests on the flange of the bottom half.

7. Lift the 30B-X cylinder out of the bottom half of the DN30 PSP.

Details on each unloading step are given in the handling instruction in Appendix 1.7.1 (Handling Instruction).

1.7.5 Supplementary Equipment and Operational Controls No supplementary equipment except means for tie-down are used during transport of the DN30-X package in any transport mode.

1.7.6 Precautions and Measures because of the other Dangerous Properties of the Content No precautions and measures due to the other dangerous properties of the content are required except for the correct labeling according to the respective transport mode.

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0045-BSH-2020-001 Rev. 2 1.8 Inspection 1.8.1 Annual Inspection Requirements for the DN30 PSP The annual inspections of the DN30 PSP were already established in the safety analysis of the DN30 package and are described in the test instruction in Appendix 1.8.2 (Inspections of DN30 PSPs), in which the criteria for the checks and measures in case of non-conformances or deviations are specified as well.

In the case that non-conformances or deviations might affect the safety of the DN30-X packaging the user of the packaging has to inform the owner of the certificate of package approval in writing about the non-conformance or deviation. It is then the decision of the owner of the certificate of package approval to undertake suitable measures to return the packaging to service in full com-pliance with the SAR and the certificate of package approval.

1.8.2 5-year Inspection Requirements for the 30B-X Cylinder and the DN30 PSP The 5-year periodical inspections of the DN30-X packaging are subdivided into the periodical recertification of the 30B-X cylinder and the periodical inspection of the DN30 PSP.

The 5-year inspection of the 30B-X cylinder shall be performed conforming to the requirements of [ANSI N14.1] and at least as described in [USEC 651] (or in equivalent plant specific instruc-Geistiges Eigentum der Orano NCS GmbH tions). This inspection includes, but is not limited to, the following:

• 30B-X cylinders, except those already filled at the 5-year expiration date, are to be periodi-cally inspected and tested throughout their service life.

Property of Orano NCS GmbH

• 30B-X cylinders that have not been inspected and tested within the required 5-year period shall not be refilled until they are properly reinspected and retested. Prior to shipment, 30B-X cylinders that have not been recertified within the 5-year requirement shall be visually inspected for degradation of the cylinder wall. Any questionable conditions should be inves-tigated. Details on the visual inspection are provided in the test instruction in Appendix 1.8.1 (Inspections of 30B-X Cylinders).

• The 5-year periodic inspections and tests consist of the following:

- An internal and external examination of the 30B-X cylinder by a qualified inspector, in-cluding a visual inspection of the interior CCS as far as accessible.

- A hydraulic strength test as described in [ANSI N14.1].

- When a valve or plug change has occurred, a 100 psig pneumatic leak-test as described in [ANSI N14.1] is required.

• After a 30B-X cylinder is tested, its outer shell may be cleaned and repainted. At each 5-year periodic inspection, the cylinder shall have the tare weight re-established.

• A 30B-X cylinder shall be removed from service (for repair or replacement) when it is found to contain leaks, corrosion, cracks, bulges, dents, gouges, defective valves, damaged skirts, or other conditions that, in the opinion of a qualified inspector, render it unsafe or unservice-able in its existing condition.

• A 30B-X cylinder shall no longer be used in UF6 service when the shell thickness has de-creased below 11 mm.

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0045-BSH-2020-001 Rev. 2 The periodical inspections of the DN30 PSP were already established in the safety analysis of the DN30 package and are described in the test instruction in Appendix 1.8.2 (Inspections of DN30 PSPs), in which the criteria for the checks and measures in case of non-conformances or deviations are specified as well.

In case non-conformances or deviations might affect the safety of the DN30-X packaging, the user of the packaging has to inform the owner of the certificate of package approval in writing about the non-conformance or deviation. It is then the decision of the owner of the certificate of package approval to undertake suitable measures to return the packaging to service in full com-pliance with the SAR and the certificate of package approval.

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 74 / 172

0045-BSH-2020-001 Rev. 2 1.9 Management System The management system of company Orano NCS GmbH (ONCS) is laid down in the Integrated Management Handbook (see Appendix 1.9.1 (IMS)). The integrated management system (IMS) is certified according to:

• DIN EN ISO 9001

• DIN EN ISO 14001

• OSHAS 18001

• KTA 1401

• BAM GGR 011

• 10 CFR Part 71 - Subpart H The IMS covers the design and development, manufacturing and operation of packagings for packages requiring approval by the competent authorities for the transport of radioactive material.

Appendix 1.9.3 (Quality Assurance Program) provides a description of the ONCS quality assur-ance (QA) program that demonstrates compliance with the requirements of [10 CFR Part 71] -

Subpart H. It also includes the NRC approval of this program.

1.9.1 Design, SAR, Documentation and Records Geistiges Eigentum der Orano NCS GmbH 1.9.1.1 General ONCS is responsible for the design, development, safety analyses, manufacturer planning and Property of Orano NCS GmbH surveillance, inspection, and controls before first use of DN30 PSPs and 30B-X cylinders. ONCS is also responsible for the operation of DN30 PSPs and 30B-X cylinders including maintenance and periodical recertification.

All documents like drawings, calculations, specifications etc. are written, checked and released in accordance with the IMS of ONCS. The author and the examiner must be experienced in the respective field of technology whereas the person releasing the document must be authorized according to the organizational structure of ONCS. For each field of technology, the different roles of the employees of ONCS are described in the IMS.

Any design modifications including any revisions of specifications, drawings and instructions are carried out according to the processes laid down in the IMS and documented accordingly. In case there are documents from suppliers, ONCS will check these documents according to the process laid down in the IMS.

1.9.1.2 Design ONCS is responsible for the whole design process from establishing the requirements based on the applicable regulations and standards up to the completion of the drawings, safety analyses, and the manufacturing specification. All individual steps necessary for the design process are stipulated in the IMS of ONCS.

Design modifications required due to the progress in carrying out the safety analyses or resulting from the outcome of physical tests with specimens or prototypes are introduced into the design process in compliance with the respective process described in the IMS of ONCS.

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0045-BSH-2020-001 Rev. 2 1.9.1.3 Documents and Records Traceability of each document and record relevant during the design process is assured by the requirements of the IMS of ONCS with respect to a unique numbering and filing system. During the design process the documents listed in Appendix 1.1 (List of Applicable Documents) are pro-duced and filed.

For each document written and released by ONCS, the original workable document is stored together with the signed document as image. For documents and records of suppliers, only an image of the document might be made available and stored.

1.9.2 Manufacturing and Testing 1.9.2.1 Manufacturing of 30B-X Cylinders For the 30B-X cylinder, qualification and selection of the manufacturer as well as the requirements towards QA during material procurement, manufacturing, and final inspection before first use are specified in the manufacturing specification in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder). This specification details among others the following requirements:

• Qualification of manufacturer

• Scope of services and responsibilities of manufacturer Geistiges Eigentum der Orano NCS GmbH

• Responsibilities of ONCS

• Requirements for materials including certification

• Requirements concerning fabrication including welding Property of Orano NCS GmbH

• Requirements concerning final acceptance test

• Treatment of non-conformances

• Manufacturing test sequence plan (MTSP) 1.9.2.2 Manufacturing of Serial DN30 PSPs The manufacturing of serial DN30 PSPs has already been established for the DN30 package.

Therefore, qualification and selection of the manufacturer as well as the requirements towards QA during material procurement, manufacturing, and final inspection before first use are specified in the manufacturing specification in Appendix 1.9.2B (Manufacturing Specification DN30 PSP).

This specification details the same requirements as listed for the 30B-X cylinder in section 1.9.2.1 1.9.2.3 Testing of Samples and Prototypes Manufacturing and testing of samples and prototypes is managed comparably to the standards specified for the 30B-X cylinders and the serial DN30 PSPs.

Samples for mechanical and thermal testing of the foam used as shock absorbing material and thermal insulation in the DN30 PSP are manufactured, certified, and documented identically to the foam used in the DN30 PSP prototypes and serial DN30 PSPs.

Samples for thermal testing of the thermal intumescent material are manufactured, certified, and documented identically to the intumescent material used in the DN30 PSP prototypes and serial DN30 PSPs.

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0045-BSH-2020-001 Rev. 2 The tests to determine the properties of the foam and intumescent material are documented in the summary reports that are part of Appendix 1.4.2 (Material Properties). For these tests quali-fied institutes were involved:

• The Material Testing Institute, University of Stuttgart (MPA), for the mechanical tests with foam specimen.

• The institute for combustion and gas dynamics, University of Duisburg-Essen, for the anal-ysis of the chemical composition of the foam under different thermal conditions.

• Company Influtherm, an independent society specialized in thermal measurements and ser-vices, for the measurement of the thermal properties of the foam and the intumescent ma-terial.

• Company Thermoconcept, an independent society specialized in thermal measurements and services, for the measurement of the thermal conductivity of the expanded intumescent material.

• Company Mecanium, an independent society specialized in mechanical measurements and services, for the measurement of the expansion forces of the intumescent material.

• Experimental drop tests with DN30 PSP prototypes were carried out by the BAM. For pack-age approvals originating in Germany, BAM is one part of the German competent authorities and responsible for the structural, thermal, and containment analysis as well as QA.

Geistiges Eigentum der Orano NCS GmbH 1.9.2.4 Storage of Batch Samples During the manufacturing of the serial DN30 PSPs, several samples are taken from each batch of foam, intumescent material and thermal insulation and stored at DAHERs site for the lifetime Property of Orano NCS GmbH of the DN30 PSP (estimated between 30 and 50 years), for the following reasons:

• Monitoring and analyzing of the aging process of these materials, since most of them are not visible or easily accessible during the maintenance of the DN30 PSP.

• Being able to perform tests on the aged samples on request by any competent authority.

This is also mentioned in Appendix 1.4.2 (Material Properties).

1.9.3 Operation The quality management requirements for operation are specified in the handling instruction in Appendix 1.7.1 (Handling Instruction).

In case the DN30 PSP is leased to a customer for transports, the handling instruction is provided to this customer who has to confirm in writing that he will comply with the requirements stipulated there.

In case the DN30-X packaging is sold to a customer, the handling instruction and the test instruc-tion regulating regular and periodical inspections are provided to this customer who has to confirm in writing that he will comply with the requirements stipulated there.

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0045-BSH-2020-001 Rev. 2 1.9.4 Maintenance and Repair The quality management requirements for the recertification of 30B-X cylinders are described in the test instruction in Appendix 1.8.1 (Inspections of 30B-X Cylinders) and a description of the non-conformances and deviations for which repair is required is included in this test instruction as well. Since, the same non-conformances and deviations apply to the visual inspection of the 30B-X cylinder, this test instruction is also referenced in the handling instruction in Appendix 1.7.1 (Handling Instruction). In addition, the following applies to repairs other than replacement of parts:

• For repair of 30B-X cylinders other than replacement of parts, the specification in Appen-dix 1.9.2A (Manufacturing Specification 30B-X Cylinder) must be complied with.

The quality management requirements for periodical inspections of DN30 PSPs were already es-tablished in the safety analysis of the DN30 package and are described in Appendix 1.8.2 (In-spections of DN30 PSPs). This test instruction also contains the non-conformances and devia-tions for which repair of a DN30 PSP is required. In addition, the following applies to repairs other than replacement of parts:

• For repair of DN30 PSPs other than replacement of parts, the specification in Appen-dix 1.9.2B (Manufacturing Specification DN30 PSP) must be complied with.

In all cases in which repair of a 30B-X cylinder or a DN30 PSP is required, ONCS must be involved in the planning, authorization, and execution of the repair measures.

Geistiges Eigentum der Orano NCS GmbH 1.9.5 Compliance of any Activity with the SAR The specifications in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) and Appen-dix 1.9.2B (Manufacturing Specification DN30 PSP) ensure that during manufacturing and final Property of Orano NCS GmbH acceptance tests before first use, the requirements of this SAR towards the design of the 30B-X cylinder and the DN30 PSP are met. In detail the following requirements are considered:

• Specification of the material properties in material data sheets to comply with the properties used throughout this SAR

• Requirements for welders and welding to ensure the structural properties of the 30B-X cyl-inder and the DN30 PSP as defined in this SAR

• Specification of tests and documentation during manufacturing and before first use ensuring the design of the 30B-X cylinder and the DN30 PSP comply with the drawings The handling instruction in Appendix 1.7.1 (Handling Instruction) and test instruction in Appen-dix 1.8.1 (Inspections of 30B-X Cylinders) ensure that during operation, the 30B-X cylinder is kept compliant with this SAR. For the DN30 PSP, this is ensured by the application of the test instruc-tion in Appendix 1.8.2 (Inspections of DN30 PSPs).

1.9.6 Deviations Deviations concerning the safety elements listed in table 1-15 and the corrective actions imple-mented are to be reported to the competent authority.

1.9.7 Safety Elements The safety elements of the DN30-X package are summarized in table 1-15.

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0045-BSH-2020-001 Rev. 2 Table 1-15 Safety elements Element of the package Safety function Parameters Closure system Mechanical protection

• Welds

• Absence of structural defects

• Completeness Outer shell Mechanical protection

• Welds

• Absence of structural defects in the steel sheets Foam Mechanical protection

• Thickness

• Density Microporous material Thermal protection

• Thickness

• Thermal conductivity Intumescent material Thermal protection

• Thickness

• Completeness

• Thermal conductivity Inner shell Mechanical protection

• Welds

• Absence of structural defects in the steel sheets Geistiges Eigentum der Orano NCS GmbH Valve protecting device Mechanical protection

• Welds

• Absence of structural defects in the steel sheets

• No unacceptable deformation of the housing Property of Orano NCS GmbH

• Completeness Plug protecting device Mechanical protection

• Welds

• Absence of structural defects Rotation preventing devices Mechanical protection

• Welds

• Absence of structural defects of the bolts

• Completeness 30B-X cylinder Containment

• Welds

• Absence of structural defects

• Thickness Confinement

• Absence of structural defects

• Presence of neutron absorbing material 79 / 172

0045-BSH-2020-001 Rev. 2 1.10 Package Illustration Figure 1-12 to figure 1-14 show illustrations of the DN30-X package including the DN30 PSP and the 30B-X cylinder. More detailed illustrations of the 30B-X cylinder are presented in sec-tion 1.4.2.1. Appendix 1.4.1A (Drawings 30B-X Cylinder) and Appendix 1.4.1B (Drawings DN30 PSP) contain the set of drawings for the DN30 PSP and the 30B-X cylinder, respectively.

Lifting lugs Thermal plugs Sealing Alignment markings 30B-X cylinder Geistiges Eigentum der Orano NCS GmbH Bottom half Property of Orano NCS GmbH Forklift pockets Closure device Top half Valve protecting Intumescent material device Protecting rails Silicon pads Housing Lifting lugs Feet Figure 1-12 DN30-X Package Overview 80 / 172

0045-BSH-2020-001 Rev. 2 Plug protecting device Silicon pads Valve protecting device Protecting rails Housing Rotation preventing devices Figure 1-13 DN30 PSP bottom half Geistiges Eigentum der Orano NCS GmbH CCR Property of Orano NCS GmbH Valve Longitudinal Stiffener Lattice Holder CCS Restraint Figure 1-14 30B-X cylinder - Outside view 81 / 172

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH PART 2 TECHNICAL ANALYSES 82 / 172 0045-BSH-2020-001 Rev. 2

0045-BSH-2020-001 Rev. 2 2.1 Introduction This introductory section provides a general outline of the technical analyses presented in the following sections, especially regarding the use of results from tests performed with the DN30 package that uses the same DN30 PSP design. It also contains an overview of the provisions and central assumptions that each technical analysis is based upon.

Section 2.1.1 provides a general guideline through the entire technical analysis of the DN30-X package. This includes the description and justification of the analysis methods for each part of the technical analysis. For the structural and the thermal analysis, this also includes the reasons why the results from drop and fire tests carried out for the DN30 package can be transferred to the DN30-X package.

The guideline through the technical analysis is followed by the common provisions for all technical analyses in section 2.1.2. For each technical analysis, a summary of the package design forming the basis for the technical analyses and a description of the required content properties, funda-mental properties of the specification of the 30B-X cylinder and the DN30 PSP as well as the material characteristics are provided in section 2.1.2.1. With this at hand, the acceptance criteria and design assumptions for the 30B-X cylinder and the DN30-X package are defined in sec-tion 2.1.2.2.

Geistiges Eigentum der Orano NCS GmbH 2.1.1 Guideline through Technical Analyses 2.1.1.1 Structural Analysis Property of Orano NCS GmbH The structural analysis of the DN30-X package consists of two main parts:

1. The proof that the design requirements for normal operating conditions and recertification of the 30B-X cylinder are fulfilled (see section 2.1.1.1.1).

2. The proof that the requirements for Type AF packages for the transport of UF6 from

[10 CFR Part 71] and [49 CFR Part 173], resp. [SSR-6 2018] are fulfilled. This covers the structural analysis of the DN30-X for handling as well as under RCT, NCT, and HAC (see section 2.1.1.1.2.). Additional analyses regarding the the interaction between the 30B-X cylinder and the DN30 PSP are discussed in section 2.1.1.1.3.

The complete structural analysis of the DN30-X package is found in Appendix 2.2 (Structural Analysis) and summarized in section 2.2.

2.1.1.1.1 Structural Analysis of the 30B-X Cylinder for Normal Operating Conditions The structural analysis of the 30B-X cylinder for normal operating conditions in section 2.2.3 shows that the requirements towards design, fabrication, inspection, and testing stipulated for the 30B-X cylinder in Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) are fulfilled. The analysis for normal operating conditions comprises:

• The analysis of the 30B-X cylinder for an internal and external maximum allowable working pressure (MAWP) at the design temperature of 121 °C.

• The analysis of the 30B-X cylinder with regard to the minimum design metal temperature (MDMT) of -29 °C and the minimal transport temperature of -40 °C.

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• The analysis of the 30B-X cylinder for a hydraulic strength test at twice the MAWP.

These analyses are carried out by argumentation and, as required, by additional hand calcula-tions using well established formulas for stress and strain provided by the ASME boiler and pres-sure vessel code (BPVC) [ASME BPVC].

2.1.1.1.2 Structural Analysis of the DN30-X for Handling and under RCT The structural analysis of the DN30-X package for handling in section 2.2.4 and under RCT in section 2.2.5 comprises:

• Analysis of the lifting attachment points of the DN30 PSP

• Analysis of the features of the DN30 PSP used for tie-down

• Analysis of vibrations during transport

• Analysis of stresses caused by temperature influences These analyses are carried out using hand calculations and well-established formulas for stress and strain.

2.1.1.1.3 Structural Analysis of the DN30-X under NCT and HAC The structural analysis of the DN30-X under NCT in section 2.2.6 comprises the analysis of the Geistiges Eigentum der Orano NCS GmbH following:

• Water spray test

• Free drop test Property of Orano NCS GmbH

• Compression test

• Penetration test

• Reduced and increased external pressure As explained in section 2.2.6.2, the free drop test is analyzed in sequence with the drop tests under HAC. Compliance with the other requirements is demonstrated by argument or calculations.

The structural analysis of the DN30-X under NCT and HAC in section 2.2.7 comprises the analysis of the sequence of the following drop tests:

Test 1: 1.2 m free drop test Test 2: 9 m free drop test Test 3: Puncture test The calculation model for these analyses is validated via the simulation of results from the experimental drop test program for the DN30 package.

This validation is part of the structural analysis of the DN30 package under NCT and HAC (de-scribed in detail in appendix A of Appendix 2.2 (Structural Analysis)), carried out in three major steps:

1. Pre-analysis of the behavior of the DN30 package by using proven simulation tools and selection of benchmarks for real drop tests with prototypes.

2. Real testing of prototypes of the DN30 package by applying the selected benchmark test sequences.

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3. Refinement of the simulation model for the DN30 package based on the results of the tests and complete analysis of the behavior of the DN30 package under NCT and HAC for the operating temperature range of -40 °C to +60 °C.

The structural analysis of the DN30 package in conjunction with the experimental drop tests proved that the following major requirements of [10 CFR Part 71] or [SSR-6 2018] are fulfilled:

• The DN30 package withstands the free drop test from a height of 1.2 m under NCT without loss or dispersal of the UF6 content.

• The DN30 package withstands the free drop test from a height of 9 m and the puncture test under HAC without damage to the containment system.

The structural analysis of the DN30-X package under NCT and HAC assumes that the impact of the 30B-X cylinder on the DN30 PSP is comparable to the impact of the 30B cylinder on the DN30 PSP. This approach allows to use the results from prototype tests for the DN30 package and is admissible because of the following:

1. The 30B-X cylinder has the same gross weight as the standard 30B cylinder while also having the same outer dimensions, shell thicknesses and material specifications of the pressure envelope and the cylinder skirts (see Appendix 1.9.2A (Manufacturing Specifica-tion 30B-X Cylinder) and table 1-13).

2. The 30B-X and the standard 30B cylinder are equipped with the same valve and plug.

Geistiges Eigentum der Orano NCS GmbH

3. The 30B-X and the standard 30B cylinder are both transported in the same DN30 PSP.

With regard to the structural analysis, the only difference between the DN30 and the DN30-X package is the slightly different distribution of the content mass within the 30B-X cylinder, which is due to the addition of the interior CCS. Furthermore, the combination of the CCS and the UF6 Property of Orano NCS GmbH content might interact slightly differently with the cylinder shells than the UF6 content on its own.

However, when the UF6 is in solid form during transport, the CCS is essentially stuck in the con-tent. The possibilities of CCS to move around within the 30B-X cylinder are therefore very limited.

Consequently, the interaction of the content with the 30B cylinder and the interaction of the CCS stuck in the content with the 30B-X cylinder is comparable.

Based on this argumentation, the experimental drop tests performed for the DN30 package and the complete analysis of the behavior of the DN30 package under NCT and HAC for the operating temperature range of -40 °C to +60 °C are also covering for the DN30-X package. To complete the structural analysis of the DN30-X package under NCT and HAC, only a few additional anal-yses are required to account for the differences between the two packages. Consequently, the structural analysis of the DN30-X package under NCT and HAC consists of two fundamental parts:

1. The first part, described in detailed in section 2.1.1.1.3.1, demonstrates that the interaction between the 30B-X cylinder and the DN30 PSP is comparable to the interaction between the 30B cylinder and the DN30 PSP. These analyses prove that the initially made assump-tions are correct.

2. In the second part, described in detailed in section 2.1.1.1.3.2, analyses are performed that specifically consider the acceptance criteria established for the CCS of the 30B-X cylinder.

In the following, further details on each aspect of the structural analysis are given.

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0045-BSH-2020-001 Rev. 2 2.1.1.1.3.1 Comparison of Drop Test Analyses for the DN30-X and DN30 Package For the structural analysis under NCT and HAC, the interaction between the DN30 PSP and the 30B-X cylinder must be considered to show that the 30B-X cylinder withstands these tests in a similar condition as the standard 30B cylinder. This is shown in section 2.2.7.1.3 by comparing the simulation results of drop tests performed at room temperature for the DN30-X package to the corresponding results for the DN30 package. Specifically, the deformations at the outer shells of the DN30 PSP as well as the plastic deformations and decelerations at the cylinders are com-pared. The results of the analyses together with the experimental drop tests performed with DN30 PSP prototypes prove that the requirements of [10 CFR Part 71] or [SSR-6 2018] are also fulfilled for the DN30-X package.

Because of the fissile properties of the UF6 content, the structural analysis of the DN30-X must also demonstrate that the CCS retains its properties relevant to criticality control after the tests simulating NCT and HAC. This part of the structural analysis of the DN30-X represents the only major difference compared to the DN30 package. The criteria for the CCS of the 30B-X cylinder to ensure safe subcriticality after the tests simulating NCT and HAC are given in section 2.1.2.2.1.

2.1.1.1.3.2 Additional Analyses for the DN30-X Package The acceptance criteria for the CCS of the 30B-X cylinder that are established in section 2.1.2.2.1 require the investigation of additional drop test scenarios for the DN30-X package that were not Geistiges Eigentum der Orano NCS GmbH part of the structural analysis of the DN30 package. These are included in section 2.2.7.1.4. To complete the structural analysis of the DN30-X package, this part also contains a discussion of the remaining drop test scenarios that are not investigated in detail by analysis for the DN30-X package, but which were considered in the safety analysis of the DN30 package.

Property of Orano NCS GmbH 2.1.1.2 Thermal Analysis The thermal analysis of the DN30-X package is investigated for NCT and HAC with steady-state and transient calculations using FEM. The basis for benchmarking and validation of the used calculations models are two prototype fire tests that were carried out with DN30 PSP prototypes and empty 30B cylinders complying with [ANSI N14.1]. These two real world fire tests were ini-tially performed for the thermal analysis of the already licensed DN30 package, but the results are valid for the DN30-X package as well, as both packages share the same DN30 PSP and only parameters of the PSP are benchmarked.

Using empty cylinders minimizes the heat sink provided by the content and, thus, not only max-imizes the thermal load acting on the cylinder shells and the valve/plug during the thermal test under HAC but also in the subsequent cooling phase. The thermal analysis in conjunction with the prototype tests demonstrated that the requirements of [10 CFR Part 71] or [SSR-6 2018] with respect to the thermal behavior of the DN30-X package are fulfilled, especially regarding contain-ment and safety against rupture of the pressure envelope of the 30B-X cylinder.

The thermal analysis is described in detail in Appendix 2.3 (Thermal Analysis) and summarized in section 2.3.

2.1.1.2.1 Thermal Analysis for NCT The thermal analysis for NCT covers the conditions according to [10 CFR Part 71] §71.71(c)(1) or [SSR-6 2018] para. 657 for different filling ratios of the 30B-X cylinder for 12-hour solar insola-tion / 12-hour no insolation cycles.

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0045-BSH-2020-001 Rev. 2 2.1.1.2.2 Thermal Analysis for HAC The thermal analysis for HAC covers the conditions according to [10 CFR Part 71] §71.73(c)(4) or [SSR-6 2018] para. 728 for different filling ratios of the 30B-X cylinder.

• The thermal analysis considers a thermal test with an ambient temperature of 800 °C and an exposure time of 30 min, followed by a subsequent cooling phase at an ambient tem-perature of 38 °C and solar insulation.

• The thermal analysis is carried out for an empty 30B-X cylinder and for 30B-X cylinders with filling ratios of 50% and 100%.

• A possible pressure build-up by melting UF6 contents is investigated beforehand in the determination of the admissible temperatures for the DN30-X package.

• Additional sensitivity analyses are carried out to investigate the influence of certain pa-rameters like contact modelling, mesh size or time step size.

2.1.1.3 Containment Design Analysis The containment design analysis of the DN30-X package is described in detail in Appendix 2.4 (Containment Analysis) and summarized in section 2.4. It covers UF6 of grade HALEU 10 and HALEU 20 for all filling ratios ranging from 0 kg up to the specific fill limits of the 30B-10 and 30B-20 cylinder listed in table 1-4.

Geistiges Eigentum der Orano NCS GmbH Only RCT and NCT are considered, as the DN30-X is a Type AF package with no restriction on the radioactivity release under HAC due to the 1 A2 limit on the radioactivity of the contents.

2.1.1.4 External Dose Rate Analysis Property of Orano NCS GmbH The external dose rate analysis is documented in detail in Appendix 2.5 (External Dose Rate Analysis) and summarized in section 2.5. The analysis covers the DN30 package loaded with filled cylinders as well as cylinders containing heels under RCT and NCT. It is valid for UF6 con-tents of type HALEU 10 and HALEU 20 as specified in section 1.3 and considers the following assumptions:

• The internal CSS of the 30B-X cylinder is considered in the dose rates analysis.

• The analysis covers UF6 grade HALEU 10 and HALEU 20.

• For the 30B-X cylinder, the minimal wall thickness of 1.1 cm as specified in table 1-13 is applied.

2.1.1.4.1 External Dose Rate Analysis under RCT The external dose rate analysis of the DN30-X package under RCT consists of:

• The analysis of the external dose rates at the surface of the DN30-X package and at a distance of 2 m from the external surface of the DN30-X package.

• The analysis of the external dose rates at a distance of 1 m from the external surface of the DN30-X package to provide an estimate for the TI to be expected. Nevertheless, the TI will always be determined by measurement before each transport.

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• The analysis of the external dose rates at the surface of a standard vehicle routinely used for transportation of the DN30-X package and in a distance of 2 m from the external surface of the vehicle:

- Two possible transport configurations for the DN30-X package are considered.

- For the analysis of the external dose rates in 2 m distance from the vehicle, the influence of all transported DN30-X packages is taken into account.

2.1.1.4.2 External Dose Rate Analysis under NCT The external dose rate analysis under NCT consists of the comparison of the maximal dose rates for a non-damaged DN30-X package complying with the manufacturing drawings and for a dam-aged DN30-X package under NCT to prove that the increase in the maximal dose rates is not significant (not greater than 20 %).

2.1.1.5 Criticality Safety Analysis The criticality safety analysis for the DN30-X package takes into account the maximal enrichments of 10 wt.-% 235U for the DN30-10 and 20 wt.-% 235 U for the DN30-20. It is based on the following assumptions:

• For the single package in isolation, optimal water moderation of the UF6 content is assumed.

Geistiges Eigentum der Orano NCS GmbH

• For the array of packages, flooding with water is excluded because of the results of analyses and experimental drop tests described in the structural analysis in section 2.2.

• For all contents, the most reactive arrangement in the packaging is determined in all cases.

Property of Orano NCS GmbH All credible rearrangements of contents in the package are taken into account in the anal-yses. Based on the results of the structural and thermal analysis, release of contents from the package does not need to be assumed.

• Water around the package is considered in different layer thicknesses in the analysis of the array of packages.

• Temperature changes are taken into account by assuming a conservatively high density for UF6 and the theoretical maximal density of 1 g/cm³ for water. A decrease of water density caused by a temperature rise or freezing will lead to lower moderation that is less reactive.

2.1.2 Common Provisions for all Technical Analyses 2.1.2.1 Package Design Details of the DN30-X package design are described in section 1.3 for the content and in sec-tion 1.4 for the 30B-X cylinder and the DN30 PSP. In the following, the provisions for the content and the DN30-X packaging are given with respect to each part of the technical analysis. In addi-tion, an overview of the materials used in the structural and thermal analysis is included. The material properties for all other technical analysis are given in the corresponding sections of those analyses.

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0045-BSH-2020-001 Rev. 2 2.1.2.1.1 Content As defined in section 1.3, the content is UF6 for all technical analyses. However, referring to a specific analysis, only certain properties of the content may be relevant and, thus, are considered in the corresponding analysis. Further details on each of technical analysis are provided in ta-ble 2-1.

Table 2-1 Provisions for the UF6 content of the DN30-X package used in the technical analyses Technical analysis Provisions made for the DN30-X Structural

• The relevant physical property is the density.

• Potential deformations of the content and, thus, energy absorption by the content is neglected in the analysis.

Thermal

• The relevant physical properties are the density, thermal conductivity, and specific heat capacity.

• Scenarios under HAC are investigated for an empty, partially filled (50 %),

and a completely filled cylinder.

• For the partially filled and completely filled cylinder, an evenly distributed air/UF6 -mixture is considered, which completely fills the cylinder cavity.

Containment design

• The relevant physical property is the viscosity of gaseous UF6 . For the containment analysis, the content configuration has no impact on results.

• The radioactivity of the contents is conservatively assumed to be 1 A2.

Geistiges Eigentum der Orano NCS GmbH External dose rate

• The relevant physical properties are the density and the shielding properties of the UF6 contents.

• Conservatively, a 100 % filled 30B-X cylinder is considered, which exceeds the permissible mass of UF6 for the 30B-10 and 30B-20 cylinder listed in Property of Orano NCS GmbH table 1-4.

• For cylinders containing heels, a covering configuration with heels forming a puddle at the lower side of the 30B-X cylinder is investigated.

• The source terms are derived from the UF6 contents specified in section 1.3.

Criticality safety

• The relevant physical properties are the density, the purity (hydrogen impurities) and the 235U enrichment of the UF6 .

• Conservatively, a 100 % filled 30B-X cylinder is considered which exceeds the permissible mass of UF6 for the 30B-10 and 30B-20 cylinder listed in table 1-4.

• For the single package in isolation, optimal moderation of the UF6 contents with water is assumed.

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0045-BSH-2020-001 Rev. 2 2.1.2.1.2 30B-X Cylinder The design of the 30B-X cylinder is defined in the drawings in Appendix 1.4.1A (Drawings 30B-X Cylinder). A detailed description of the 30B-X cylinder is provided in sections 1.4.1.1 and 1.4.2.1.

Provisions made for each technical analysis with regard to the 30B-X cylinder are given in ta-ble 2-2.

Table 2-2 Provisions for the 30B-X cylinder used in the technical analyses Technical analysis Provisions made for the 30B-X cylinder Structural

• Nominal dimensions of the 30B-X cylinder are assumed.

• The influence of temperature on the mechanical behavior of the package is analyzed in variation calculations:

- The maximum package temperature is evaluated in the thermal analysis.

- The minimum temperature of -40 °C is required by the transport regulations.

Thermal

• Nominal dimensions of the 30B-X cylinder and standard physical properties of the materials of the 30B-X cylinder are assumed.

• The cylinder including the CCS is modeled in a simplified geometry for the 2D-environment.

Containment design

• The minimum free volume inside the 30B-X cylinder volume is assumed.

Geistiges Eigentum der Orano NCS GmbH External dose rate

• A simplified 30B-X cylinder without skirts and with flat ends is assumed.

• The minimum wall thickness of the 30B-X cylinder is assumed to be 1.1 cm.

Criticality safety

• The skirts and domed heads of the cylinder are represented in the calculation model, while valve, plug and nameplate are neglected.

Property of Orano NCS GmbH

• For the CCS, only the CCRs are taken into account, the lattice holders and all other structural parts of the CCS are conservatively neglected.

• The geometry of the cylinder and CCS are varied to assess the most reactive values within the range of the manufacturing tolerances and HAC deformations.

2.1.2.1.3 DN30 PSP The design of the DN30 PSP is defined in the drawings in Appendix 1.4.1B (Drawings DN30 PSP). A detailed description of the DN30 PSP is provided in sections 1.4.1.2 and 1.4.2.2.

Provisions made for each technical analysis with regard to the DN30 PSP are given in table 2-3.

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0045-BSH-2020-001 Rev. 2 Table 2-3 Provisions for the DN30 PSP used in the technical analyses Technical analysis Provisions Structural

• Nominal dimensions of the DN30 PSP are assumed.

• The influence of temperature on the mechanical behavior of the package is analyzed in variation calculations:

- The maximum package temperature is evaluated in the thermal analysis.

- The minimum temperature of -40 °C is required by the transport regulations.

Thermal

• Under NCT, nominal dimensions of the DN30 PSP and nominal physical properties of the materials of the DN30 PSP are assumed.

• Under HAC, nominal dimensions and deteriorated physical properties of the materials of the DN30 PSP are assumed. Damages from free drop tests from a height of 9 m and from drops on a bar from a height of 1 m are included by benchmarking the thermal model using two prototype fire tests with prototypes damaged by these drop tests. Furthermore, a self-sustaining pyrolysis of the foam as experienced in the thermal test under HAC is considered.

Containment design

• The DN30 PSP is not part of the containment system and, thus, is not considered in the containment design analysis.

External dose rate

• Nominal dimensions of the DN30 PSP and standard physical properties of the materials of the DN30 PSP are assumed.

Geistiges Eigentum der Orano NCS GmbH Criticality safety

• The foam material is neglected.

• The steel shells of the DN30 PSP are compacted around the 30B-X cylinder to a total thickness of 5 mm in radial direction and 14 mm in axial direction, thereby minimizing the distance between adjacent packages.

Property of Orano NCS GmbH 2.1.2.2 Acceptance Criteria and Design Assumptions 2.1.2.2.1 Structural Design The acceptance criteria and design assumptions for the structural design are:

• Lifting attachments that are a structural part of the DN30-X package are designed with a minimum safety factor of 3 against yielding when used to lift the package in the intended manner. Failure of any lifting device under excessive load does not impair the ability of the DN30-X package to meet other requirements of [10 CFR Part 71].

• Tie-down devices that are a structural part of the DN30-X package withstand, without gen-erating stress in any material of the package in excess of its yield strength, a static force applied to the center of gravity of the package having a vertical component of 2 times the weight of the package with its contents, a horizontal component along the direction in which the vehicle travels of 10 times the weight of the package with its contents, and a horizontal component in the transverse direction of 5 times the weight of the package with its contents.

Failure of the devices under excessive load does not impair the ability of the DN30-X pack-age to meet other requirements of [10 CFR Part 71].

• No failure of the DN30 PSP closure system.

• No physical contact between the valve of the 30B-X cylinder and any other component of the packaging other than its original point of attachment.

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• No physical contact between the plug of the 30B-X cylinder and any other component of the packaging other than its original point of attachment.

• No loss or dispersal of radioactive contents under NCT.

• No rupture of the 30B-X cylinder containment system under HAC.

• No failure of the 30B-X cylinder confinement system:

- The relative dislocation of the CCRs must remain below 5 mm.

- The increase in radial movability of the entire CCS out of the center of the 30B-X cylinder must remain below 3 mm.

- The increase in axial movability of the entire CCS out of the center of the 30B-X cylinder must remain below 7 mm.

- Failure of the lattice holders must not occur.

- Rupture of the CCRs must not occur.

The evaluation of these design criteria for the DN30-X package is possible without considering material damage or failure in the simulation model of the DN30-X package, even if local defor-mations of the DN30 PSP shells above the uniform elongation occur. However, the following must be considered in this case:

• The material models for the steel parts cover the inelastic range up to the uniform elonga-Geistiges Eigentum der Orano NCS GmbH tion. For plastic strains above the uniform elongation, the discrepancy compared to the real material behavior increases successively because of the negligence of a damage and fail-ure model. Thus, failure analysis of certain parts of the DN30 PSP is solely based on the experimental drop tests.

Property of Orano NCS GmbH

• Locations with plastic strains above the uniform elongation and close to or above the elon-gation at fracture are compared with the corresponding areas of the prototypes used for the experimental drop tests. If those locations match and failure occurred in the experimental drop tests, the exact value of the plastic strain is of no importance for the safety of the DN30-X package because the thermal test under HAC was passed with fractures in the inner and outer shells of the DN30 PSP.

• An analysis with previously introduced cracks in the inner shell of the DN30 PSP simulation model, exceeding the cracks observed after the drop tests, proves that safety relevant sim-ulation results are not sensitive to failure of the inner steel shells. The results of this sensi-tivity analysis are documented in Appendix 2.2 (Structural Analysis).

2.1.2.2.2 Thermal Design The acceptance criteria and design assumptions for the thermal design are:

• The temperatures at the 30B-X cylinder, including valve, plug and shell, should not exceed 131 °C during the thermal test simulating HAC for a package in the condition after the struc-tural tests simulating NCT and HAC (see section 2.3.2). The leakage rate after the thermal test should be less than 1.0 10-4 Pa

• m3s.

• Withstand, without rupture of the containment system (the 30B-X cylinder), the thermal test simulating HAC.

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0045-BSH-2020-001 Rev. 2 The thermal design considers different filling ratios from an empty cylinder up to a cylinder filled with the maximum admissible amount of UF6 .

2.1.2.2.3 Containment System Design The acceptance criteria and design assumptions for the containment system design are:

• Under NCT, the loss or dispersal of UF6 must be prevented.

• The containment is the 30B-X cylinder with its valve and plug.

• The DN30 PSP has no containment function.

2.1.2.2.4 External Dose Rate Assessment The acceptance criteria and design assumptions for the external dose rate assessment are:

• The external dose rate limits for RCT, NCT, and HAC as defined in [49 CFR Part 173] or

[SSR-6 2018] must not be exceeded.

• For the assessment of the dose rates, conservative assumptions with respect to the cylinder filling ratio and the shape of the 30B-X cylinder are used.

• For the assessment of the dose rate at the vehicle, two and four packages loaded side-by-side are considered, respectively.

Geistiges Eigentum der Orano NCS GmbH

• For the assessment of the dose rate increase after the tests simulating NCT, a covering value of 4 mm for the deformations of the DN30 PSP is taken into account to demonstrate compliance with the limit of 20 % dose rate increase compared to RCT dose rates.

Property of Orano NCS GmbH 2.1.2.2.5 Criticality Safety Assessment The acceptance criteria and design assumptions for the criticality safety assessment are:

• Criticality safety is ensured by the confinement system consisting of the 30B-X cylinder with the CCS and the steel shells of the DN30 PSP.

• For RCT, NCT and HAC the criticality safety criterion is keff + 3 + k 0.95. The system-atical deviations k are determined from a validation based on critical benchmark experi-ments applicable to the DN30-X.

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0045-BSH-2020-001 Rev. 2 2.2 Structural Analysis The structural analysis of the DN30-X package is described in detail in Appendix 2.2 (Structural Analysis). This section provides a summary of the main points and results.

The analysis of the DN30-X package under NCT and HAC is based on the experimental drop test program for the DN30 package, consisting of the 30B cylinder and the DN30 PSP, that is described in appendix B of Appendix 2.2 (Structural Analysis). This is possible for the following reasons:

• The 30B-X cylinder has the same gross weight as the standard 30B cylinder while also having the same outer dimensions, shell thicknesses and material specifications of the pres-sure envelope and the cylinder skirts (see Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder) and table 1-13).

• The 30B-X and the standard 30B cylinder are equipped with the same valve and plug.

• The 30B-X and the standard 30B cylinder are both transported in the same DN30 PSP.

Additional analyses are only required to account for the differences between the 30B and 30B-X cylinders, i.e. the interior CCS. The calculation model for these analyses is validated via the sim-ulation of results from the experimental drop test program for the DN30 package, described in detail in appendix A of Appendix 2.2 (Structural Analysis).

The acceptance criteria for the structural analysis are defined in section 2.2.1. A complete list of Geistiges Eigentum der Orano NCS GmbH the basic assumptions for the performed calculations is provided in section 2.2.2. This includes the load assumptions for normal operating conditions of the 30B-X cylinder, handling of the DN30-X package, RCT, NCT, and HAC as well as the material data used in these analyses. In sections 2.2.3 through 2.2.7, only the fundamental results are provided that are required to prove Property of Orano NCS GmbH compliance with the transport regulations. The corresponding detailed analyses are found in Ap-pendix 2.2 (Structural Analysis), section 3 through 7.

2.2.1 Objective of Verification The acceptance criteria for the structural analysis are:

• Lifting attachments that are a structural part of the DN30-X package are designed with a minimum safety factor of 3 against yielding when used to lift the package in the intended manner. Failure of any lifting device under excessive load does not impair the ability of the DN30-X package to meet other requirements of [10 CFR Part 71].

• Tie-down devices that are a structural part of the DN30-X package withstand, without gen-erating stress in any material of the package in excess of its yield strength, a static force applied to the center of gravity of the package having a vertical component of 2 times the weight of the package with its contents, a horizontal component along the direction in which the vehicle travels of 10 times the weight of the package with its contents, and a horizontal component in the transverse direction of 5 times the weight of the package with its contents.

Failure of the devices under excessive load does not impair the ability of the DN30-X pack-age to meet other requirements of [10 CFR Part 71].

• No failure of the DN30 PSP closure system.

• No physical contact between the valve of the 30B-X cylinder and any other component of the packaging other than its original point of attachment.

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• No physical contact between the plug of the 30B-X cylinder and any other component of the packaging other than its original point of attachment.

• No loss or dispersal of radioactive contents under NCT.

• No rupture of the 30B-X cylinder containment system under HAC.

• No failure of the 30B-X cylinder confinement system:

- The relative dislocation of the CCRs must remain below 5 mm.

- The increase in radial movability of the entire CCS out of the center of the 30B-X cylinder must remain below 3 mm.

- The increase in axial movability of the entire CCS out of the center of the 30B-X cylinder must remain below 7 mm.

- Failure of the lattice holders must not occur.

- Rupture of the CCRs must not occur.

2.2.2 Basic Assumptions for the Calculations Basic assumptions for the calculations are listed in the following. They include load assumptions for different load cases, the definition of calculation methods and material parameters of the ma-terials used for the proof.

Geistiges Eigentum der Orano NCS GmbH 2.2.2.1 Load Assumptions Individual load assumptions are made for normal operating conditions of the 30B-X cylinder as Property of Orano NCS GmbH well as for handling, RCT, NCT and HAC for the DN30-X package. They are discussed in detail in the following sections.

2.2.2.1.1 Normal Operating Conditions for the 30B-X Cylinder With reference to [ANSI N14.1], Table 1, the load assumptions for normal operating conditions of the 30B-X cylinder are adapted from the standard 30B cylinder:

• The 30B-X cylinder is designed for an internal maximum allowable working pressure (MAWP) of 1.38 MPa gauge at a temperature of 121 °C.

• The 30B-X cylinder is designed for an external MAWP of 172 kPa gauge.

• The 30B-X cylinder is designed for a minimum design metal temperature (MDMT) of -29 °C at 1.38 MPa gauge.

• The 30B-X cylinder is designed for a transport temperature of -40 °C.

• The 30B-X cylinder withstands the hydraulic strength test at a test pressure of 2.76 MPa gauge (twice the MAWP) without generating unacceptable stress.

2.2.2.1.2 Handling of the DN30-X Package Load assumptions for handling include:

• Temperatures at the package corresponding to an ambient temperature of 38 °C and solar insolation (see section 2.3) 95 / 172

0045-BSH-2020-001 Rev. 2

• Internal and external pressure

• Hoisting coefficients that are considered for handling operations Load assumptions as basis for calculations for handling the package are listed in table 2-4.

Table 2-4 Load assumptions for handling Load assumption Component Value Unit Temperature 30B-X cylinder 64 °C Lifting lugs at feet 70 °C Lifting lugs at top half 100 °C Feet 70 °C Internal / external pressure 30B-X cylinder 152 / 100 kPa Hoisting coefficient Lifting lugs 2 -

Load cycles for fatigue analysis Lifting lugs 150000 -

2.2.2.1.3 RCT for the DN30-X Package Load assumptions for RCT include:

Geistiges Eigentum der Orano NCS GmbH

• Temperatures at the package corresponding to an ambient temperature of 38 °C and solar insolation (see section 2.3)

• Maximum transport accelerations according to [10 CFR Part 71] §45(b)(1)

Property of Orano NCS GmbH

• Vibrations during transport Load assumptions as basis for calculations under RCT are listed in table 2-5.

Table 2-5 Load assumptions for RCT Load assumption Component Value Unit Temperature (ambient temperature of 38 °C and solar Outer shell, feet 70 °C insolation) 30B-X cylinder 64 °C Temperature (ambient temperature of -40 °C in the shade) Complete packaging -40 °C Accelerations Complete packaging axial 10.0 g lateral 5.0 g vertical -1.0 +/- 2.0 g Vibrations Complete packaging 0.3 g 96 / 172

0045-BSH-2020-001 Rev. 2 2.2.2.1.4 NCT for the DN30-X Package Load assumptions for NCT include:

• Temperatures at the package corresponding to an ambient temperature of 38 °C and solar insolation (see section 2.3)

• Tests for demonstrating the ability to withstand normal conditions of transport according to

[10 CFR Part 71] §71 and [49 CFR Part 173] §465 or [SSR-6 2018] para. 719

• Reduction of ambient pressure Load assumptions as basis for calculations under NCT are listed in table 2-6.

Table 2-6 Load assumptions for NCT Load assumption Individual test Component Value Temperature Drop test, DN30 PSP 60 °C stacking test, 30B-X cylinder 64 °C penetration test Tests according to Water spray Packaging [10 CFR Part 71] §71(c)(6) and

[10 CFR Part 71] §71(a) and surface [49 CFR Part 173] §465(b) or

[49 CFR Part 173] §465 or [SSR-6 2018] para. 721

[SSR-6 2018] para. 719 Free drop Complete [10 CFR Part 71] §71(c)(7) and Geistiges Eigentum der Orano NCS GmbH package [49 CFR Part 173] §465(c) or

[SSR-6 2018] para. 722 Free drop height 1.2 m Compression Complete [10 CFR Part 71] §71(c)(9) and Property of Orano NCS GmbH package [49 CFR Part 173] §465(d) or

[SSR-6 2018] para. 723 Penetration Packaging [10 CFR Part 71] §71(c)(10) and surface [49 CFR Part 173] §465(e) or

[SSR-6 2018] para. 724 Ambient pressure Reduced 30B-X cylinder [10 CFR Part 71] §71(c)(3) and

[49 CFR Part 173] §412(f) or

[SSR-6 2018] para. 645 25 kPa1)

Increased 30B-X cylinder [10 CFR Part 71] §71(c)(4) 140 kPa Only 60 kPa are required per [49 CFR Part 173] §412(f) or [SSR-6 2018] para. 645.

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0045-BSH-2020-001 Rev. 2 2.2.2.1.5 HAC for the DN30-X Package Load assumptions for hypothetical accident conditions of transport include:

• Temperatures at the package corresponding to an ambient temperature of 38 °C and solar insolation (see section 2.3)

• Tests for demonstrating the ability to withstand accident conditions of transport according to [10 CFR Part 71] §73(a) or [SSR-6 2018] para. 726

• Internal and external pressure Load assumptions for accident conditions of transport are listed in table 2-7.

Table 2-7 Load assumptions for HAC Load assumption Individual test Component Value Temperature Free drop and Packaging main 60 °C puncture body outer shell 30B-X cylinder 64 °C Tests according to Free drop Complete package [10 CFR Part 71] §73(c)(1) or

[10 CFR Part 71] §73 or [SSR-6 2018] para. 727(a)

[SSR-6 2018] para. 726 Free drop height 9 m Geistiges Eigentum der Orano NCS GmbH Puncture Complete package [10 CFR Part 71] §73(c)(3) or

[SSR-6 2018] para. 727 (b)

Free drop height 1 m Thermal Complete package [10 CFR Part 71] §73(c)(4) or

[SSR-6 2018] para. 728 Property of Orano NCS GmbH Immersion 30B-X cylinder [10 CFR Part 71] §73(c)(6) or

[SSR-6 2018] para. 729 150 kPa for 8 h Water pressure Immersion 30B-X cylinder [10 CFR Part 71] §73(c)(5) or (fissile material) [SSR-6 2018] para. 731 9 kPa for 8 h Increase of internal Thermal 30B-X cylinder [10 CFR Part 71] §73(c)(4) or pressure during the [SSR-6 2018] para. 728 thermal test 106 kPa (see section 2.2.7.3.1) 2.2.2.2 Material Data 2.2.2.2.1 Material Data 30B-X Cylinder The materials of the 30B-X cylinder are specified in section 1.4.1.1. A complete list of the corre-sponding material data is provided in Appendix 1.4.2 (Material Properties).

2.2.2.2.2 Material Data DN30 PSP The materials of the DN30 PSP are specified in section 1.4.1.2. The corresponding material data that is used in the structural analysis of the DN30-X package is provided in Appendix 1.4.2 (Ma-terial Properties).

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0045-BSH-2020-001 Rev. 2 2.2.3 Normal Operating Conditions for the 30B-X Cylinder This part of the structural analysis covers the normal operating conditions for the 30B-X cylinder as defined in section 2.2.2.1.1. For these analyses, the 30B-X cylinder is assumed to comply with its specification provided in section 1.4.1.1.

2.2.3.1 MDMT and Minimum Transport Temperature The analysis in Appendix 2.2 (Structural Analysis), section 3.1 shows that the requirements to-wards the MDMT of -29 °C at 1.38 MPa gauge and the minimum transport temperature of -40 °C are fulfilled for the 30B-X cylinder. Consequently, this also applies to the materials ductility and resistance to brittle failure at low temperatures.

2.2.3.2 MAWP The analyses in Appendix 2.2 (Structural Analysis), section 3.2 consider the whole design tem-perature range of -29 °C to 121 °C to prove the structural integrity of the 30B-X cylinder under the design conditions listed section 2.2.2.1.1. The following is shown with regard to a variation of material strength within this temperature range and thermally induced stresses:

1. The 30B-X cylinder and the standard 30B cylinder equally perform under the conditions of the hydraulic strength test at twice the MAWP.

2. The impact of a decrease in material strength of the 30B-X cylinder at the maximum design Geistiges Eigentum der Orano NCS GmbH temperature is always covered by the hydraulic strength test.

3. Thermally induced stresses are effectively prevented by the design of the 30B-X cylinder:

The entire CCS has no fixed connection to another component of the 30B-X cylinder.

Property of Orano NCS GmbH The longitudinal clearances between the lattice holders and the CCS restraints are sufficient to allow for a faster shrinking of the cylinder shells than the interior CCS.

The radial clearance between the lattice holders and the cylinder shell is sufficient to allow for a faster shrinking of the cylinder shells than the interior CCS.

The radial clearance between the CCRs and the lattice holders is sufficient to allow for a faster shrinking of the lattice holders than the CCRs.

The skirts of the 30B-X cylinder impose the same restrictions in the radial direction as for the standard 30B cylinder.

2.2.3.3 Hydraulic Strength Test The analyses in Appendix 2.2 (Structural Analysis), section 3.3 show that the 30B-X and the standard 30B cylinder equally perform under the conditions of the hydraulic strength test at twice the MAWP, and that the impact of the hydraulic strength test on the interior CCS of the 30B-X cylinder can be analyzed separately:

• The admissible external pressure for the CCRs is significantly higher than the test pressure of twice the MAWP.

• Failure of the CCRs under the test conditions of the hydraulic strength test can be excluded.

• This and the argumentation in section 2.2.3.2 prove that the 30B-X cylinder is well designed to operate over the same design temperature range as a standard 30B cylinder.

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0045-BSH-2020-001 Rev. 2 2.2.4 Handling of the DN30-X Package The DN30-X packaging is designed for the transport of UF6 . Specified contents are defined in section 1.3. Strains in the packaging result from the following loads:

• Internal and external pressure (see section 2.2.4.1)

• Assembling loads (see section 2.2.4.2)

• Handling loads (see section 2.2.4.3)

• Temperature gradients in the components (an analysis covering handling and RCT is pro-vided in section 2.2.5.2)

The corresponding load assumptions are listed in table 2-4.

2.2.4.1 Internal and External Pressure As shown in section 2.2.3.2, the 30B-X cylinder is designed for an external MAWP of 172 kPa and an internal MAWP of 1.38 MPa. Consequently, the requirements concerning the internal and external pressure for the 30B-X cylinder as well as for the DN30-X package are fulfilled. Further details are provided in Appendix 2.2 (Structural Analysis), section 4.1.

2.2.4.2 Assembling Geistiges Eigentum der Orano NCS GmbH During assembling, the components of the DN30-X packaging are inserted into each other without applying forces. Stresses in the components during assembling are negligible. For tightening the securing bolts of the closure system, tightening torques are defined in the handling instruction provided in Appendix 1.7.1 (Handling Instruction).

Property of Orano NCS GmbH 2.2.4.3 Handling Loads The following handling processes are carried out with the DN30-X package:

• Handling of the loaded and empty package by using the lifting lugs at the feet (see fig-ure 1-6)

• Handling of the loaded and empty package using a forklift (see figure 1-7)

• Handling of the empty package by using slings (see figure 1-8)

• Handling of the top half of the DN30 PSP by using the lifting lugs (see figure 1-9)

Based on the package weight, package dimensions, and material properties given in table 1-13 and table 1-14, the DN30-X package fulfills the following acceptance criteria defined in sec-tion 2.2.1 referring to [10 CFR Part 71] §45(a):

• All lifting attachments that are a structural part of the DN30-X package are designed with a minimum safety factor of 3 against yielding when used to lift the package in the intended manner.

• Failure of any lifting device under excessive load does not impair the ability of the DN30-X package to meet other requirements of [10 CFR Part 71].

The corresponding proofs are provided in Appendix 2.2 (Structural Analysis), section 4.3.

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0045-BSH-2020-001 Rev. 2 2.2.5 Ability of the DN30-X Package to Withstand RCT The DN30-X packaging is designed for the transport of UF6 . Specified contents are defined in section 1.3. Strains in the packaging result from the following loads under RCT:

• Maximum transport accelerations (see section 2.2.5.1)

• Vibrations during transport (see section 2.2.5.1 and 2.2.5.2)

• Temperature gradients in the components (see section 2.2.5.2)

The corresponding load assumptions are listed in table 2-5.

2.2.5.1 Tie-down The DN30-X package is transported by road, rail, or sea. For the transport, common flat racks or dedicated transport means are used (see figure 1-10). The tie-down features are designed such that relative movement between the vehicle and the DN30-X package is excluded. Thus, only the maximum acceleration values defined in table 2-5 affect the package during transport.

Based on the package weight, package dimensions, and material properties given in table 1-13 and table 1-14, the DN30-X package fulfills the following acceptance criteria defined in sec-tion 2.2.1 referring to [10 CFR Part 71] §45(b):

• All tie-down devices that are a structural part of the DN30-X package withstand, without Geistiges Eigentum der Orano NCS GmbH generating stress in any material of the package in excess of its yield strength, a static force applied to the center of gravity of the package having a vertical component of 2 times the weight of the package with its contents, a horizontal component along the direction in which the vehicle travels of 10 times the weight of the package with its contents, and a horizontal Property of Orano NCS GmbH component in the transverse direction of 5 times the weight of the package with its contents.

• Failure of the devices under excessive load does not impair the ability of the DN30-X pack-age to meet other requirements of [10 CFR Part 71].

The corresponding proofs are provided in Appendix 2.2 (Structural Analysis), section 5.1.

2.2.5.2 Impact of Vibrations During Transport on the Structural Integrity of the 30B-X Cylinder and its interior Criticality Control System Compliance with [10 CFR Part 71] §71(c)(5) requires the investigation of vibration normally inci-dent to transport. For the tie-down features of the DN30 PSP, this has been investigated in Ap-pendix 2.2 (Structural Analysis), section 5.1.2. What remains for the safety analysis of the DN30X package is the proof that the interior CCS of the 30B-X cylinder is also not affected by such vi-brations. The main concern here is the occurrence of resonances for the interior CCS that could lead to wear of the cylinder shell or fatigue failure of the CCRs.

Appendix 2.2 (Structural Analysis), section 5.2 contains an investigation of the possible impacts of vibration on the integrity of the 30B-X cylinder and possible interactions between the cylinder shell and the interior CCS. Furthermore, possible fatigue failure of the CCRs is investigated.

Therefore, a modal analysis is performed for the central CCR to calculate its natural frequencies.

Using the results of this modal analysis (the eigenmodes to each natural frequency), maximal stresses are determined at the central CCR, and it is shown that these stresses are insignificant with regard to the fatigue strength of the CCR material. Hence, the CCRs are not susceptible to fatigue failure and there is no impact of the structural analysis under RCT on the integrity of the interior CCS.

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0045-BSH-2020-001 Rev. 2 2.2.5.3 Analysis of Stresses Caused by Temperature Influences The analysis of stresses caused by temperature influences for the DN30-X package, provided in Appendix 2.2 (Structural Analysis), section 5.3, shows the following results:

• The possibly different expansions of the top and bottom half of the DN30 PSP, caused by temperature differences that are due to differing insolating conditions on the top and bottom half, are small. The gaps between the flanges of the top and bottom half allow for sufficient relative movement to compensate for different expansions.

• There is sufficient clearance between the DN30 PSP and the 30B-X cylinder to compensate differing thermal expansions of the DN30 PSP and the 30B-X cylinder.

• For the 30B-X cylinder itself, thermally induced stresses because of the expansion of the interior CCS or shrinking of the cylinder shell cannot occur under RCT and NCT.

2.2.6 Ability of the DN30-X Package to Withstand NCT 2.2.6.1 Water Spray Test The water spray test specified in [10 CFR Part 71] §71(c)(6) and [49 CFR Part 173] §465(b) or

[SSR-6 2018] para. 721 has no impact on either the loss or dispersal of the radioactive contents, or on the dose rate at any external surface of the DN30-X package with respect to the require-Geistiges Eigentum der Orano NCS GmbH ments in [10 CFR Part 71] §43(f) and [49 CFR Part 173] §412(j) or [SSR-6 2018] para. 648. Fur-ther details are provided in Appendix 2.2 (Structural Analysis), section 6.1.

2.2.6.2 Free Drop Test Property of Orano NCS GmbH The free drop test from a height of 1.2 m is analyzed in sequence with the tests simulating HAC (the 9 m free drop test and the puncture test). For better overview and comparison of the defor-mations after the 1.2 m free drop test and after the 9 m free drop test, the results of these se-quences are both discussed in section 2.2.7. As the DN30-X package is designed to withstand HAC, the proof that the DN30X package is also designed to withstand NCT is almost always a direct consequence. A more careful examination is only required for the proof of preventing loss or dispersal of the radioactive contents, which is further discussed in section 2.2.6.2.1.

As explained in Appendix 2.2 (Structural Analysis), section 6.2, preceding corner drops from a height of 0.3 m as required by [49 CFR Part 173] §465(c)(2) will not have any adverse effect on the DN30-X package.

In the following, the conditions for the proof of [10 CFR Part 71] §43(f) and [49 CFR Part 173]

§412(j) or [SSR-6 2018] para. 648 are established.

2.2.6.2.1 Conditions to Prevent Loss or Dispersal of the Radioactive Contents In section 2.2.7, it is shown that even after a 10.2 m free drop test, there is no physical contact between the valve or the plug and any other component of the DN30-X packaging other than its original point of attachment. Hence, structural damaging of the valve or the plug of the 30B-X cylinder during the 1.2 m free drop test can generally be excluded. Further analysis is only nec-essary for the flat drop onto the valve side because, after the combined 10.2 m drop test investi-gated in section 2.2.7.1.3.2, small plastic deformations are visible at the cylinder head at the valve half coupling. Accordingly, for the proof of compliance with [10 CFR Part 71] §43(f), a separate 102 / 172

0045-BSH-2020-001 Rev. 2 analysis of the 1.2 m free drop test under NCT for the flat drop onto the valve side is performed in section 2.2.7.1.4.1, which shows that the area of the valve half coupling is free of inelastic deformations. Further details are provided in Appendix 2.2 (Structural Analysis), section 6.2.1.

2.2.6.2.2 Conditions to Prevent the Increase of the Maximum External Radiation Level In section 4.1 of Appendix 2.5 (External Dose Rate Analysis), it is shown that the maximum dose rate at the surface of the DN30-X package is to be expected in radial direction in the center of the side of the package. In section 2.2.7, the deformations to be expected after the 1.2 m free drop tests are analyzed. For the 1.2 m free drop onto the top of the package described in sec-tion 2.2.7.1.4.3, a reduction of the distance between the inner and outer shell of the DN30 PSP of 4 mm was determined. Conservatively, a distance reduction of 6 mm is assumed for the dose rate analysis.

2.2.6.3 Compression Test The outer shape of the DN30 PSP effectively prevents stacking. However, according to

[10 CFR Part 71] §71(c)(9), a compression test must be performed for packages weighing up to 5000 kg. The corresponding analysis provided in Appendix 2.2 (Structural Analysis), section 6.3 shows that the DN30-X package fulfills the requirements of [10 CFR Part 71] §71(c)(9).

2.2.6.4 Penetration Test Geistiges Eigentum der Orano NCS GmbH According to [10 CFR Part 71] §71(c)(10), the impact of the hemispherical end of a vertical steel cylinder of 3.2 cm diameter and 6 kg mass, dropped from a height of 1 m onto the exposed sur-face of the DN30-X package has to be investigated that is expected to be most vulnerable to Property of Orano NCS GmbH puncture. As demonstrated in section 2.2.7, the DN30-X package is designed to withstand the puncture test under HAC, which is much more severe for the DN30-X package weighing about 4100 kg than the penetration test. Hence, the test as defined in [10 CFR Part 71] §71(c)(10) and

[49 CFR Part 173] §465(e) or [SSR-6 2018] para. 724 is covered by the test defined in

[10 CFR Part 71] §73(c)(3) or [SSR-6 2018] para. 727(b).

There is no impact of this test on the loss or dispersal of the radioactive contents with respect to the requirement stipulated in [10 CFR Part 71] §43(f) and [49 CFR Part 173] §412(j) or

[SSR-6 2018] para. 648(a).

In comparison to the free drop test from a height of 1.2 m, the impact of this test on the dose rate at any external surface of the DN30-X package is negligible with respect to the requirement in

[10 CFR Part 71] §43(f) and [49 CFR Part 173] §412(j), or [SSR-6 2018] para. 648(b).

2.2.6.5 Reduced and Increased External Pressure The 30B-X cylinder is designed for an external and internal MAWP of 172 kPa and 1.38 MPa, respectively. As defined in section 1.2.9, the MNOP of the DN30-X package during transport is 152 kPa. Hence, a reduction to 25 kPa or an increase to 140 kPa of the ambient pressure as specified in [10 CFR Part 71] §71(c)(3) and (4) will not affect the 30B-X cylinder (the containment system). This argumentation covers the reduction of the ambient pressure to 60 kPa as required by [49 CFR Part 173] §412(f) or [SSR-6 2018] para. 645.

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0045-BSH-2020-001 Rev. 2 2.2.7 Ability of the DN30-X Package to Withstand NCT and HAC Based on the argumentation in the beginning of section 2.2, the experimental drop tests and the drop tests analysis under NCT and HAC performed for the DN30 package (described in appen-dices A and B of Appendix 2.2 (Structural Analysis)) in the operating temperature range of -40 °C to +60 °C are also covering the DN30-X package. They are summarized in section 7.1 of Appen-dix 2.2 (Structural Analysis). To complete the structural analysis of the DN30-X package under NCT and HAC, only some additional analyses are required to account for the differences between the 30B and the 30B-X cylinder:

1. The first part in Appendix 2.2 (Structural Analysis), section 7.2.5 provides evidence that the interaction between the 30B-X cylinder and the DN30 PSP is comparable to the interaction between the 30B cylinder and the DN30 PSP. These analyses prove that the initially made assumptions are admissible.

2. In the second part in Appendix 2.2 (Structural Analysis), section 7.2.6, analyses are per-formed that specifically consider the acceptance criteria established for the interior CCS of the 30B-X cylinder in section 2.2.7.1.4 and, therefore, also account for the differences be-tween the DN30-X and the already licensed DN30 package.

Both the comparison between the two packages and the specific analyses for the DN30-X pack-age consider a 30B-X cylinder design with 35 CCRs arranged in a 1 x 6 x 12 x 16 pattern, which deviates from the actual designs of the 30B-10 and 30B-20 cylinder having 33 and 43 CCRs, Geistiges Eigentum der Orano NCS GmbH respectively. The impact of these deviations on the results of the structural analysis of the DN30-X package under NCT and HAC is discussed in in Appendix 2.2 (Structural Analysis), section 7.5.

The following sequential application of tests is considered in the analyses:

1. The free drop test under NCT as defined in [10 CFR Part 71] §71(c)(7) and Property of Orano NCS GmbH

[49 CFR Part 173] §465(c) or [SSR-6 2018] para. 722 (drop height 1.2 m)

2. The free drop test under HAC as defined in [10 CFR Part 71] §73(c)(1) or

[SSR-6 2018] para. 727(a) (drop height 9 m)

3. The puncture test under HAC as defined in [10 CFR Part 71] §73(c)(3) or

[SSR-6 2018] para. 727(b) (drop height 1 m)

Apart from the two fundamental parts of the structural analysis of the DN30-X under NCT and HAC, the water immersion test for packages containing fissile material is discussed in sec-tion 2.2.7.2. Finally, the influence of the thermal test under HAC on the structural integrity of the DN30-X package is evaluated in section 2.2.7.3.

2.2.7.1 Drop Test Analyses for the DN30-X Package under NCT and HAC As pointed out in the beginning of section 2.2.7, this part of the structural analysis of the DN30-X package provides evidence that the interaction between the 30B-X cylinder and the DN30 PSP is comparable to the interaction between the standard 30B cylinder and the DN30 PSP. This proves that the initially made assumptions are admissible, and that the drop test analyses as well as the experimental drop tests performed for the DN30 package are also covering for the DN30-X pack-age. The comparison of the drop test analyses for the DN30-X and the DN30 package is de-scribed in section 2.2.7.1.3.

With this at hand, additional analyses are described in section 2.2.7.1.4 that specifically consider the acceptance criteria in section 2.2.1 that have been established for the interior CCS of the 30B-X cylinder and, therefore, also account for the minor differences between the DN30-X and 104 / 172

0045-BSH-2020-001 Rev. 2 the DN30 package. Furthermore, this part contains a discussion of the remaining drop test sce-narios that were considered in the safety analysis of the DN30.

The analyses of the drop tests under NCT and HAC are valid for all filling ratios from 30B-X cyl-inders with heels up to 30B-X cylinders filled with the maximum amount of UF6 as defined in table 1-4. Further details on the investigated analysis sequences and orientations are provided in section 2.2.7.1.1. A brief introduction to the software being used to perform the simulations is provided in Appendix 2.2 (Structural Analysis), section 7.2.2.

The entire modelling procedure is described in Appendix 2.2 (Structural Analysis), section 7.2.3.

Since the same simulation model is used for the DN30 PSP that has already been developed for the structural analysis of drop tests for the DN30 package, the modelling description focuses on the specific design for the 30B-X cylinder. Apart from the deviations between the FEM and the CAD models of the cylinders, the chosen element types, applied initial and boundary conditions as well as contact definitions and material models are described. Finally, a comprehensive de-scription of the content modelling is provided.

2.2.7.1.1 Analysis Sequences and Orientations In Appendix 2.2 (Structural Analysis), section 7.2, detailed analyses are carried out for three drop test orientations of the DN30-X package:

1. Inclined onto the valve side so that the line between center of gravity and point of impact is Geistiges Eigentum der Orano NCS GmbH perpendicular to the target surface

2. Flat onto the valve side

3. Flat onto the feet Property of Orano NCS GmbH The first two drop test orientations are investigated in Appendix 2.2 (Structural Analysis), sec-tion 7.2.5 and are used to provide evidence that the interaction between the 30B-X cylinder and the DN30 PSP is comparable to the interaction between the standard 30B cylinder and the DN30 PSP. The drop test flat onto the feet has not been investigated for the DN30 package, but this orientation is specifically relevant with regard to the acceptance criteria for the CCS inside the 30B-X cylinder defined in section 2.2.1. The flat drop test onto the feet is investigated in Ap-pendix 2.2 (Structural Analysis), section 7.2.6.2.

The following drop test orientations, which have also been investigated for the DN30 package, are considered in the structural analysis of the DN30-X package as well:

• Flat onto the plug side

• Flat onto the closure system

• Flat onto the top side

• Inclined onto the plug side so that the line between center of gravity and point of impact is perpendicular to the target surface

• Inclined onto the closure system so that the line between center of gravity and point of impact is perpendicular to the target surface

• Inclined onto the feet (slap-down)

• Inclined onto the top side (slap-down)

The detailed discussion for each of the above drop test orientation is also provided in Appen-dix 2.2 (Structural Analysis), section 7.2.6.2.

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0045-BSH-2020-001 Rev. 2 2.2.7.1.2 FEM Model The FEM model of the DN30-X package is described in detail in Appendix 2.2 (Structural Analy-sis), section 7.2.3. Generally, it is identical to that of the DN30 package, except for the model of the standard 30B cylinder and its content being replaced by the model of the 30B-X cylinder.

Consequently, the same deviations and simplifications apply to the modelling of the DN30 PSP.

As mentioned in the beginning of section 2.2.7, the model of the 30B-X cylinder used in the struc-tural analysis of the DN30-X package considers 35 CCRs arranged in a 1 x 6 x 12 x 16 pattern.

This number of CCRs lies between the actual designs of the 30B-10 and the 30B-20 cylinder having 33 and 43 CCRs. However, the way the content of the 30B-X cylinder is modelled always ensures that the maximal allowable gross weight of a standard 30B cylinder of 2912 kg is achieved for the 30B-X cylinder as well. Consequently, the differences in the number of CCRs in comparison to the actual 30B-10 or 30B-20 cylinder designs has no relevant impact on the simu-lation results. This aspect of the structural analysis of the DN30-X package is discussed in more detail in Appendix 2.2 (Structural Analysis), section 7.5.

The geometry of the 30B-X cylinder FEM model is discretized with shell and solid elements. Solid elements are used for the valve, plug and their half couplings as well as the CCS restraints, the lattice holders and the neutron absorbing material within the CCRs. The cylinder shells, skirts, and the pipes of the CCRs are modeled using shell elements.

For solid elements, the default solid element formulation is used in nearly all cases. This is an eight-node solid hexahedron element with one-point integration and constant stress within each Geistiges Eigentum der Orano NCS GmbH element. The valve is discretized using the standard tetrahedral element formulation with one-point-integration. Since the valve is solely modelled to detect a contact, it is represented as a rigid body in the FEM model. In this case, the element formulation has no impact on the simulation Property of Orano NCS GmbH results, but using tetrahedral elements simplifies the meshing of the complex geometry of the valve body.

Without exception, the default shell element formulation is used for thin parts. It is an extremely effective 4-node element that uses one-point integration and can describe small deformations with large rotations.

The UF6 content is simulated by increasing the nodal mass of each mesh node of the outer CCR surfaces. This approach is described in detail in Appendix 2.2 (Structural Analysis), sec-tion 7.2.3.7, also discussing its conservatism with regard to the acceptance criteria for proving the integrity of the pressure-containment and the integrity of the CCS of the 30B-X cylinder that are established in section 2.2.1.

2.2.7.1.3 Comparison of Drop Test Analyses for the DN30-X and DN30 Package 2.2.7.1.3.1 Corner Drop onto the Valve Side - Drop Test Sequence 1 The structural analysis of the DN30 package showed that the corner drop onto the valve side, part of drop test sequence 1 for the DN30 package, is one of the most critical drop test orientations regarding the magnitude of deformations of the DN30 PSP in the valve area. As the valve is the most vulnerable part of the containment system, this drop test orientation is used in the compari-son analysis between the DN30-X and DN30 package.

A detailed presentation of the simulation results a provided in Appendix 2.2 (Structural Analysis),

section 7.2.5.1. Here, only a short summary is given, covering the fundamental results with regard to the acceptance criteria defined in section 2.2.1.

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0045-BSH-2020-001 Rev. 2 2.2.7.1.3.1.1 Deformations 2.2.7.1.3.1.1.1 DN30 PSP and Cylinder Pressure Envelope The state of maximal deformation for the DN30-X to the DN30 package during the corner drop test onto the valve side is compared in figure 2-1. For both packages, the compression of the foam in the valve area and the deformations of the inner and outer DN30 PSP shell are nearly identical. As for the DN30, no physical contact at the valve is detected for the DN30-X other than its initial point of attachment.

DN30-X DN30 Figure 2-1 Corner drop onto the valve side from a height of 10.2 m - State with the maximal de-formation of the DN30-X and DN30 package Geistiges Eigentum der Orano NCS GmbH At the end of the simulation, the deformations of the DN30 PSP are determined using two measurement locations at the impact zone (see figure 2-2). Table 2-8 lists the resulting values and provides a comparison to the corresponding results for the DN30 package.

Property of Orano NCS GmbH Figure 2-2 Measured distances for the corner drop onto the valve side The obtained results for the measured distances in table 2-8 correspond well to the very similar deformations visible in figure 2-1. The changes in 1x and 2x are increased by about 5 %, while the changes in 1y and 2y are slightly smaller. However, the extent of the impacted area meas-ured by the Euclidian norm 1 is nearly identical for both packages, proving that the deformations are comparable.

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0045-BSH-2020-001 Rev. 2 Table 2-8 Corner drop onto the valve side from a height of 10.2 m - Measured distances at the impact zone after the drop test Measurement point Parameter Deformation in mm Change in %

DN30-X DN30 Largest Fold 1x 175 167 5.0 1y 392 396 -0.9 430 429 0 1 = 1x 2 + 1y 2 Weld between head 2x 163 156 4.8 and outer shell 2y 368 372 -0.8 In case of the cylinder pressure envelope, the determined maximal plastic deformation slightly increases from 1.1 % for the standard 30B to 4.0 % for the 30B-X cylinder. Despite those differ-ences that solely refer to the content modelling, 4.0 % maximal plastic strain is significantly below the elongation at fracture of the cylinder shell material so that rupture of the containment system can safely be excluded.

2.2.7.1.3.1.1.2 Criticality Control System of the 30B-X Cylinder Geistiges Eigentum der Orano NCS GmbH Noticeable plastic strains at the CCS occur only in the lower half of the lattice holder on the valve side and near the connection between the lattice holders and the longitudinal stiffeners. The max-imal plastic strain in these areas reach 2.1 % and 1.6 %, respectively, which is acceptable for the lattice holders and the longitudinal stiffeners. Safety relevant is only the relative dislocation be-Property of Orano NCS GmbH tween the CCRs, which can be expected to be very small as the pipe clamps of the lattice holders hardly experience any plastic deformations.

2.2.7.1.3.1.2 Summary The DN30-X package design ensures that after the corner drop test onto the valve side simulating HAC, all acceptance criteria as defined in section 2.2.1 are met:

• There is no failure of the DN30 PSP closure system.

• There is no physical contact between the valve of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no physical contact between the plug of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no loss or dispersal of radioactive contents under NCT.

• There is no rupture of the 30B-X cylinder containment system under HAC.

• There is no failure of the 30B-X cylinder confinement system.

2.2.7.1.3.2 Flat Drop onto the Valve Side - Drop Test Sequence 3 With the corner drop onto the valve side, as described in section 2.2.7.1.3.1, maximal defor-mations are reached in the valve area. In contrast to that, maximal acceleration and, therefore, maximal forces at the valve are expected for the flat drop onto the valve side. This drop test orientation was part of drop test sequence 3 in the safety analysis of the DN30 package.

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0045-BSH-2020-001 Rev. 2 As the valve is the most vulnerable part of the containment system, the flat drop onto the valve side is used in the comparison analysis between the DN30-X and DN30 package. Furthermore, this drop test orientation puts the highest demands on the lattice holders and the CCS restraints of the 30B-X cylinder and, therefore, provides additional information on the structural integrity of the interior CCS of the 30B-X cylinder. Accordingly, the results of this drop test analysis are also used as input for the following analyses:

• Static structural analysis of the fillet weld between the CCS restraint and the 30B-X cylinder shell (see Appendix 2.2 (Structural Analysis), section 7.2.7)

• Static structural analysis of the step welds between the CCRs and the lattice holders (see Appendix 2.2 (Structural Analysis), section 7.2.8) 2.2.7.1.3.2.1 Deformations 2.2.7.1.3.2.1.1 DN30 PSP and Cylinder Pressure Envelope For both packages, the compression of the foam in the valve area and the deformations of the inner and outer DN30 PSP shell are nearly identical. As for the DN30 package, no physical con-tact at the valve is detected for the DN30-X other than its initial point of attachment.

The flat drop test onto the valve side also provides a good estimate of the closest axial approach of two neighboring DN30-X packages. Therefore, the permanent axial reduction in the wall thick-Geistiges Eigentum der Orano NCS GmbH ness of the DN30 PSP is evaluated in the valve area, which is required as input for the criticality safety analysis in section 2.6. Including the corresponding sheet thicknesses, a minimal perma-nent wall thickness of the DN30 PSP of 103 mm is obtained.

With regard to the cylinder pressure envelope, rupture of the containment system can safely be Property of Orano NCS GmbH excluded because the maximal plastic strain only increases from 1.8 % for the standard 30B to 4.0 % for the 30B-X cylinder. Such an increase was to be expected because the content is only implicitly incorporated in the FEM model of the DN30-X. However, there is still a very large margin to the elongation at fracture of the cylinder shell material.

2.2.7.1.3.2.1.2 Criticality Control System of the 30B-X Cylinder Noticeable plastic strains occur only at the most outer spokes of the lattice holders and near the connection between the lattice holders and the longitudinal stiffeners. The maximal plastic strain in these areas reach 2.6 % and 2.1 %, respectively, which is acceptable for the lattice holders and the longitudinal stiffeners.

Regarding the acceptance criteria for the CCS defined in section 2.2.1, the relative dislocations between the CCRs and also the movement of the entire CCS relative to the 30B-X cylinder shell are evaluated. Considering the plastic deformations at the lattice holders are limited to their outer-most spokes, there are no permanent relative dislocations between the CCRs.

For the flat drop onto the valve side, there are only negligible deformations that would increase the radial movability of the entire CCS within the 30B-X cylinder. With regard to the axial mova-bility of the entire CCS within the 30B-X cylinder, a detailed analysis provided in Appendix 2.2 (Structural Analysis), section 7.2.5.2.2.2 shows an increase of approximately 2 mm.

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0045-BSH-2020-001 Rev. 2 2.2.7.1.3.2.2 Summary The DN30-X package design ensures that after the flat drop test onto the valve side simulating HAC, all acceptance criteria as defined in section 2.2.1 are met:

• There is no failure of the DN30 PSP closure system.

• There is no physical contact between the valve of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no physical contact between the plug of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no loss or dispersal of radioactive contents under NCT (see additional analyses of the flat drop onto the valve side under NCT in section 2.2.7.1.4.1).

• There is no rupture of the 30B-X cylinder containment system under HAC.

• There is no failure of the 30B-X cylinder confinement system.

2.2.7.1.4 Additional Drop Test Analyses for the DN30-X Package As mentioned in the beginning of section 2.2.7.1, this part of the drop test analyses for the DN30X package under NCT and HAC contains additional analyses that specifically consider the ac-ceptance criteria in section 2.2.1 that have been established for the interior CCS of the 30B-X Geistiges Eigentum der Orano NCS GmbH cylinder and, therefore, also account for the minor differences between the DN30-X and the DN30 package. Furthermore, Appendix 2.2 (Structural Analysis), section 7.2.6 contains detailed discus-sions of the remaining drop test scenarios that were considered in the safety analysis of the DN30 package. Here, only those drop test scenarios are mentioned that are directly relevant for proving Property of Orano NCS GmbH compliance with the transport regulations or that are relevant to other safety analyses of the DN30-X package. Appendix 2.2 (Structural Analysis), section 7.2.6 also contains several sensi-tivity and comparison analyses for the DN30-X package.

2.2.7.1.4.1 Flat Drop onto the Valve Side - Drop Test Sequence 3 - Normal Conditions of Transport The results of the combined 10.2 m flat drop onto the valve side in section 2.2.7.1.3.2 revealed small plastic deformations close to the valve half coupling, probably largely because of the very conservative modelling approach for the UF6 contents. For the proof of compliance with

[10 CFR Part 71] §43(f) regarding the containment function of the 30B-X cylinder under NCT, in-elastic deformations of the containment have to be safely excluded near closure devices like the valve and the plug. Therefore, the safety analysis of the DN30X package is supplemented by a separate analysis of the flat drop onto the valve side under NCT, considering a free drop height of 1.2 m.

2.2.7.1.4.1.1 Deformations 2.2.7.1.4.1.1.1 DN30 PSP and Cylinder Pressure Envelope No physical contact at the valve occurs for the DN30-X other than at its initial point of attachment.

The maximum plastic strain at the inner shell of the DN30 PSP reaches 24 % in the simulation of the 1.2 m free drop test with the DN30 package. In case of the DN30-X package, 26.2 % are reached showing that the amount of deformation is comparable.

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0045-BSH-2020-001 Rev. 2 In case of the cylinder pressure envelope, the region where the maximal plastic strain occurs has changed for the 30B-X cylinder in comparison to the standard 30B cylinder. This behavior was to be expected because the content is only implicitly incorporated in the FEM model of the DN30-X.

As can be seen in figure 2-3, this leads to some deformations at the 30B-X cylinder head on the valve side that result from a stronger interaction between the valve protecting device of the DN30 PSP and the cylinder head. Nevertheless, the maximal plastic strains at the cylinder pres-sure envelope are identical for both cylinders and remain below the elastic limit (0.2 % proof stress).

Furthermore, the areas with very small plastic deformations occur far away from the valve and the plug half coupling so that the areas near closure devices of the containment system remain free of inelastic deformations. Based on this observation, there is no risk of loss or dispersal of the radioactive contents of the 30B-X cylinder.

DN30-X Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH DN30 Figure 2-3 Flat drop onto the valve side under NCT - Comparison of equivalent plastic strain at the cylinder pressure envelope 111 / 172

0045-BSH-2020-001 Rev. 2 2.2.7.1.4.1.1.2 Criticality Control System of the 30B-X Cylinder For the flat drop onto the valve side, covering deformations of the interior CCS of the 30B-X cylinder are obtained for the combined 10.2 m drop test investigated in section 2.2.7.1.3.2.1.2.

Since the requirements with regard to the parts of the CCS are identical under NCT and HAC, no additional evaluations are required for these parts.

2.2.7.1.4.1.2 Summary The DN30-X package design ensures that after the flat drop test onto the valve side simulating NCT, all acceptance criteria as defined in section 2.2.1 are met:

• There is no failure of the DN30 PSP closure system.

• There is no physical contact between the valve of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no physical contact between the plug of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There are no inelastic deformations of the 30B-X cylinder in the proximity of the valve and plug half coupling

• No loss or dispersal of radioactive contents of the 30B-X cylinder.

Geistiges Eigentum der Orano NCS GmbH

• There is no failure of the 30B-X cylinder confinement system.

2.2.7.1.4.2 Flat Drop onto the Feet - Drop Test Sequence 9 Property of Orano NCS GmbH With the corner drop and the flat drop onto the valve side as described in section 2.2.7.1.3.1 and 2.2.7.1.3.2, two drop test orientations have been investigated for the DN30-X that have also been used to validate the DN30 package FEM model against experimental drop test results. These two drop test scenarios put high stress on the DN30 PSP, but in case of the flat drop onto the valve side, the interior CCS of the 30B-X cylinder also experiences high loads, especially the lattice holders and the CCS restraints. In contrast to this, the investigation of the flat drop onto the feet aims at generating maximal decelerations at the CCRs perpendicular to their axis resulting in maximal bending stresses and, thus, the highest risk of kinking of the CCRs.

2.2.7.1.4.2.1 Deformations 2.2.7.1.4.2.1.1 DN30 PSP and Cylinder Pressure Envelope The feet of the DN30 PSP undergo severe buckling and are pushed into the outer shell of the DN30 PSP. The largest equivalent plastic strain in the outer shell is 29 % and occurs in the area where the feet are pushed into the outer shell. Because of the very high plastic deformations at the feet, cracks are to be expected. Nevertheless, the occurring plastic deformations of the inner steel parts remain below 10 %. Furthermore, the rotation preventing, valve and plug protecting device are nearly undamaged after the flat drop test onto the feet and no contact at the valve is detected, except for its initial point of attachment.

The flat drop test onto the feet is used to determine the permanent radial reduction in the wall thickness of the DN30 PSP, which is required as input for the criticality safety analysis in sec-tion 2.6. Including the sheet thicknesses of the inner and outer shell, a minimal permanent wall thickness of the DN30 PSP of 134 mm is obtained.

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0045-BSH-2020-001 Rev. 2 In case of the cylinder pressure envelope, the maximal equivalent plastic strain of 2.4 % is reached at the bottom of the cylinder, where the three lattice holders impact the cylinder shell.

This value is significantly below the elongation at fracture of the cylinder shell material so that rupture of the containment system can safely be excluded.

2.2.7.1.4.2.1.2 Criticality Control System of the 30B-X Cylinder Noticeable plastic deformations of the CCS only occur at the lower half of the lattice holders.

However, with maximally 3.9 % plastic strains, the relative dislocations between the CCRs is still small as most of the pipe clamps of the lattice holders hardly experience any plastic deformations.

Regarding the acceptance criteria for the CCS defined in section 2.2.1, the relative dislocations between the CCRs and also the movement of the entire CCS relative to the 30B-X cylinder shell are evaluated. A detailed evaluation of the relative dislocations between the inner and middle CCR as well as the middle and outer CCR is provided in Appendix 2.2 (Structural Analysis), sec-tion 7.2.6.1.2.2. This evaluation leads to a maximal permanent relative dislocation between the inner and middle ring of -0.31 mm. Applying the same procedure to the middle and outer ring results in a maximal permanent relative dislocation of -0.75 mm.

For the flat drop onto the feet, there are only negligible deformations that would increase the axial movability of the entire CCS within the 30B-X cylinder. The radial movability of the entire CCS within the cylinder is evaluated by measuring the radial gap between the central lattice holder and the cylinder shell as the maximal plastic deformations of the lattice holders and the cylinder shell Geistiges Eigentum der Orano NCS GmbH occur in this area. The detailed evaluation provided in Appendix 2.2 (Structural Analysis), sec-tion 7.2.6.1.2.2 shows an increase of the radial movability of the entire CCS within the cylinder of 2.1 mm.

Property of Orano NCS GmbH 2.2.7.1.4.2.2 Summary The DN30-X package design ensures that after the flat drop test onto the feet simulating HAC, all acceptance criteria as defined in section 2.2.1 are met:

• There is no failure of the DN30 PSP closure system.

• There is no physical contact between the valve of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no physical contact between the plug of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no rupture of the 30B-X cylinder containment system.

• There is no failure of the 30B-X cylinder confinement system.

2.2.7.1.4.3 Flat Drop onto the Top Half - Drop Test Sequence 8 The drop test sequence flat onto the top of the DN30 PSP was performed in the safety analysis of the DN30 package because of its relevance with regard to the determination of the increase in the maximal dose rate after the tests simulating NCT. Furthermore, the simulation provided infor-mation about the extent of the reduction of the thickness of the DN30 PSP for the thermal analy-sis. The detailed discussion in Appendix 2.2 (Structural Analysis), section 7.2.6.6 proves that the design of DN30-X package ensures that after the tests simulating HAC:

• There is no failure of the DN30 PSP closure system.

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• There is no physical contact between the valve of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no physical contact between the plug of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment.

• There is no rupture of the 30B-X cylinder containment system.

• There is no failure of the 30B-X cylinder confinement system.

• The extent of the reduction of the wall thickness of the DN30 PSP after NCT amounts to maximally 4 mm and, thus, is such that the increase of the dose rate does not exceed the limit specified in section 2.5.1.

• The extent of the reduction of the thickness of the DN30 PSP after HAC is such that the thermal protection properties of the DN30 PSP are still sufficient to limit the temperature increase in the thermal tests to the limits specified in section 2.3.1.

2.2.7.2 Water Immersion Test for all Packages The containment (the 30B-X cylinder) is designed to comply with requirements from [ANSI N14.1]

for an external MAWP of 172 kPa. The water immersion test for all packages defined in

[10 CFR Part 71] §73(c)(6) or [SSR-6 2018] para. 729 requires the immersion of the specimen under a head of water of at least 15 m for a period of not less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. This is equal to an Geistiges Eigentum der Orano NCS GmbH external gauge pressure of 150 kPa, which is below the external MAWP. Hence, the DN30-X package is designed to withstand the water immersion test.

2.2.7.3 Influence of the Thermal Test under HAC on the Structural Integrity of the Property of Orano NCS GmbH DN30-X Package 2.2.7.3.1 Internal Pressure The pressure build-up during the thermal test is investigated in the thermal analysis in section 2.3.2. The calculations prove that the maximum pressure in the 30B-X cylinder during the thermal test caused by elevated temperatures and by melted UF6 contents remains below the admissible pressure. Thus, an influence of the thermal test on the containment system of the DN30-X pack-age can be excluded.

2.2.7.3.2 Pressure Development because of Expansion of Intumescent Material In case of a fire accident, the expansion of the intumescent material is triggered when its expan-sion temperature is reached. This may cause the development of a pressure that is acting on the 30B-X cylinder. The analysis for the 30B-X cylinder in Appendix 2.2 (Structural Analysis), sec-tion 7.4.2, provesthat neither the 30B-X cylinder shells nor the valve or the plug will be damaged by the expansion of the intumescent material.

2.2.7.3.3 Thermally Induced Stresses The analysis of thermally induced stresses at the DN30 PSP during the thermal test under HAC for the DN30-X package is provided in Appendix 2.2 (Structural Analysis), section 7.4.3, and shows that no stresses occur in the DN30 PSP shells during or after the thermal test.

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0045-BSH-2020-001 Rev. 2 Additional considerations are required for the interior CCS of the 30B-X cylinder to investigate potential stresses due to temperature gradients. As pointed out in Appendix 2.2 (Structural Anal-ysis), section 7.4.3, this has already been discussed for normal operating conditions of the 30B-X cylinder. Using these results, and considering that the thermal analysis of the DN30-X package under HAC in section 2.3.4.4.1 proves that the maximum temperature during the thermal test under HAC remains below the maximal design temperature of the 30B-X cylinder of 121 °C in all cases, it follows that no thermally induced stresses in the CCS occur during the HAC thermal test.

2.2.7.4 Conclusion The analysis of the drop test sequences and the experimental drop tests for the DN30 package provided in Appendix 2.2 (Structural Analysis) in conjunction with the comparing analyses be-tween the DN30-X and the DN30 package in section 2.2.7.1.3 show compliance with the ac-ceptance criteria defined in section 2.2.1:

• There is no failure of the DN30 PSP closure system in any drop test sequence.

• There is no physical contact between the valve of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment in any drop test sequence.

• There is no physical contact between the plug of the 30B-X cylinder and any other compo-nent of the packaging other than its original point of attachment in any drop test sequence.

• There is no rupture of the 30B-X cylinder containment system in any drop test sequence.

Geistiges Eigentum der Orano NCS GmbH The additional analyses in section 2.2.7.1.4 performed specifically with regard to the acceptance criteria for the interior CCS of the 30B-X cylinder prove that the deformations of the 30B-X cylinder and its interior CCS are such that there is no failure of the confinement system of the DN30-X Property of Orano NCS GmbH package:

• The relative dislocation of the criticality control rods (CCRs) remains below 5 mm.

• The increase in radial movability of the entire CCS out of the center of the 30B-X cylinder remains below 3 mm.

• The increase in axial movability of the entire CCS out of the center of the 30B-X cylinder remains below 7 mm.

• There is no failure of the lattice holders.

• There is no rupture of the CCRs.

Furthermore, the following results from the analysis of the experimental drop tests provided in appendix A of Appendix 2.2 (Structural Analysis) can be applied wholly to the DN30-X package (see section 2.1.1.1):

• The leakage rate after each drop test sequence is less than 1.0 106 Pa

• m3 s.

• The valve protecting device of the DN30 PSP fulfills its function after each drop test se-quence.

• The rotation preventing device of the DN30 PSP fulfills its function after each drop test se-quence.

• The plug protecting device of the DN30 PSP fulfills its function after each drop test se-quence.

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• The intumescent material as well as the housing are still present and undamaged after each of the drop test sequences.

• The deformations of the DN30-X package at +60 °C have to be very similar to the defor-mations of the DN30 package at 60 °C.

• The deformations of the DN30-X package at -40 °C have to be very similar to the defor-mations of the DN30 package at -40 °C.

• Neither at -40 °C nor at +60 °C a physical contact between the valve of the 30B-X cylinder and any other component of the packaging other than its original point of attachment is detected.

• Neither at -40 °C nor at +60 °C a physical contact between the plug of the 30B-X cylinder and any other component of the packaging other than its original point of attachment is detected.

• The valve protecting device of the DN30 PSP fulfills its function after each drop test se-quence in the whole temperature range.

• The rotation preventing device of the DN30 PSP fulfills its function after each drop test se-quence in the whole temperature range.

• The plug protecting device of the DN30 PSP fulfills its function after each drop test se-quence in the whole temperature range.

Geistiges Eigentum der Orano NCS GmbH Consequently, the DN30 PSP provides the required mechanical protection of the 30B-X cylinder for the temperature range of -40 °C to +60 °C under RCT, NCT, and HAC.

Property of Orano NCS GmbH 116 / 172

0045-BSH-2020-001 Rev. 2 2.3 Thermal Analysis The thermal analysis for the DN30-X package, consisting of the DN30 PSP and the 30B-X cylin-der, is summarized in this section and evaluated in detail in Appendix 2.3 (Thermal Analysis). The thermal analysis is based a benchmarked and validated FEM model. Benchmarking and valida-tion was done using the results of two prototype fire tests carried out with DN30 prototypes. This is valid, because:

• The standard 30B and 30B-X cylinders are transported in identical overpacks, the DN30 PSP.

• Only parameters of the DN30 PSP are benchmarked.

• The assumed thermal load of 3 W for the UF6 content is by far covering for all admissible enrichment levels for the DN30-X package (see section 1.3.2.7).

The thermal analysis is detailed in the following structure: after listing the object of verification for the thermal analysis, at first the admissible component temperatures are evaluated and justified, followed by the analysis of the two prototype fire tests. The main part is the thermal analysis of the DN30-X package using transient-thermal FEM calculations. After presenting the calculation model and the boundary conditions, the benchmark calculations are described that demonstrate the validity of the assumptions by recalculating the two prototype fire tests. The following sections are then the thermal analysis of the DN30-X package for NCT, for ACT, and a comprehensive sensitivity analysis. The conclusion is given in the form of a summary demonstrating the proof for Geistiges Eigentum der Orano NCS GmbH the DN30-X package to meet the regulatory requirements.

2.3.1 Objective of Verification Property of Orano NCS GmbH 2.3.1.1 Verification for all Types of Packages It is verified that the design of the DN30-X package considers ambient temperatures and pres-sures that are likely to be encountered under NCT. Even though such a requirement is neither stipulated in [10 CFR Part 71] nor in [49 CFR Part 173], it is required for [SSR-6 2018] para. 616.

2.3.1.2 Verification for Packages Containing Uranium Hexafluoride It is verified that the DN30-X package withstands the thermal test specified in

[10 CFR Part 71] §73(c)(4) or [SSR-6 2018] para. 728 without rupture of the containment system.

2.3.1.3 Verification for Packages Containing Fissile Material The consequences of the thermal test specified in [10 CFR Part 71] §73(c)(4) or

[SSR-6 2018] para. 728 on the DN30-X package subjected to the mechanical tests specified in

[10 CFR Part 71] §73(a), §73(c)(1), §73(c)(3) and §73(c)(6) or [SSR-6 2018] paras. 726, 727(a),

727(b) and 729 are analyzed to verify the requirements of [10 CFR Part 71] §55(d), §55(e) and

§59(a)(2) or [SSR-6 2018] para. 682 and 685.

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0045-BSH-2020-001 Rev. 2 2.3.2 Admissible Component Temperatures of the DN30-X Package The containment system of the DN30-X package consists of the 30B-X cylinder shells with in-stalled valve and plug. The admissible temperature for these components is defined as 131 °C (267.8 °F).

This admissible temperature is lower than the admissible temperatures of the components of the 30B-X pressure envelope with installed valve and plug:

• 30B-X pressure envelope: the maximum temperature for the cylinder shells defined in

[ASME BPVC] for SA516 steel grade 55/60 is 371.11 °C or 700 °F.

• valve/plug body (aluminum bronze UNS C63600): the melting point is 1030 °C, the hot working temperature is 760 - 875 °C.

• valve/plug stem (nickel copper alloy UNS N04400): the melting point is 1300 - 1350 °C, the hot-working temperature is 648 - 1176 °C.

• valve/plug solder (tin-lead alloy): the solidus temperature of a tin lead solder compliant with ASTM B32 alloy grade Sn 50 is 183 °C, the liquidus temperature is 216 °C (cf. [Har-ris Sn50])

The limiting factor in the determination of this admissible temperature; apart from the solder of valve and plug, is the pressure build-up caused by melted UF6 contents for temperatures above the triple point of UF6 (64 °C/147.3 °F). This is investigated in the following, taking into account Geistiges Eigentum der Orano NCS GmbH the increased minimum ullage of the 30B-10 and 30B-20 cylinder in comparison to the standard 30B cylinder. Furthermore, the following conservative assumptions are used:

• The admissible temperature of 131 °C is assumed to be the average temperature of all UF6 Property of Orano NCS GmbH contents in the 30B-X cylinder. Calculations in section 2.3.4.6.2 show that only the outmost region of the UF6 in contact with the 30B-X cylinder shell will reach the maximum tempera-ture while the core of the UF6 is well below that temperature.

• For the calculation of the pressure build-up, the pressure in the empty 30B-X cylinder is conservatively assumed to be 5 psi instead of 3 psi (compare [USEC 651], sections 5.3.5 and 8.3).

• The calculations for the pressure build-up are performed with the maximum net weight and minimum volume of the 30B-X cylinder listed in Table 1-13.

• Any beneficial effects on the stability of the 30B-X pressure envelope by the structure of the CCS, lattice holders, and/or stiffeners are conservatively neglected.

• The admissible pressure under HAC is based on the hydraulic test pressure of twice the maximum allowable working pressure MAWP as specified in [ANSI N14.1] for standard 30B cylinders, which is applicable for the 30B-X cylinder as well. To consider the elevated tem-perature of 131 °C/267.8 °F, which is above the design limit of 121 °C/250 °F according to the [ASME BPVC], this test pressure is modified. The admissible pressure is reduced using the linear interpolated yield strength of [ASTM A516] Grade 55 for 267.8 °F:

,267.8 ° 26.82

= 2 = 2 200 = 397.36

,250 ° 27.0 118 / 172

0045-BSH-2020-001 Rev. 2 Therefore, the admissible pressure under HAC is set to 2.74 MPa/397.36 psig for the 30B-X cylinder including its valve and plug.

A calculation of the pressure build-up for filling ratios of 50 % and 100 % for the admissible tem-perature of 131 °C/267.8 °F (see Appendix 2.3 (Thermal Analysis), chapter 3 for details) results in the safety margins listed in table 2-9.

As these safeties are calculated with the testing pressure specified in [ANSI N14.1] for a standard 30B cylinder, this safety also includes an additional safety margin because the testing pressure only utilizes a maximum of 95 % of the yield strength for primary stresses (cf. [ASME BPVC]).

The requirements for the pressure envelope of the 30B-X cylinder are at least equal to those of regular 30B cylinders according to [ANSI N14.1].

Table 2-9 Safety margins for the pressure build-up inside the 30B-X cylinder Safety margin Filling Ratio in %

30B-10 cylinder 30B-20 cylinder 50 2.93 2.94 100 2.37 2.48 Because of the large minimum ullage of the 30B-10 and 30B-20 cylinder of 17.6 % and 20.8 %,

Geistiges Eigentum der Orano NCS GmbH respectively, the maximum pressure at a temperature of 267.8 °F/131 °C of 1.16 MPa is even below the MAWP (1.38 MPa/200 psig) of the 30B-X cylinder.

Additional calculations for the safety margin for the 30B-X cylinder according to ASME Code Sec-tion VIII - Division 1 for the maximum internal pressure of 1.16 MPa are listed in Appendix 2.3 Property of Orano NCS GmbH (Thermal Analysis), chapter 3. The calculated safety factors according to [ASME BPVC] are sum-marized in Table 2-10.

Table 2-10 Safety margins for the required wall thickness of the 30B-X cylinder Paragraph/ Required wall Safety Formula Appendix thickness treq factor I App. 1-1 (1) = 2.71 mm 4.05

+ 0.4 II UG-27 (1) = 2.73 mm 4.02 Cylinder 0.6 III App. 1-2 (1) = (1 ( )) 2.79 mm 3.94 IV App. 1-2 (1) = ( ( ) 1) 2.73 mm 4.03 I App. 1-4 (1) = 2.78 mm 3.95 Dished 2 + ( 0.1) heads II App. 1-4 (1) = 2.72 mm 4.04 2 0.2 119 / 172

0045-BSH-2020-001 Rev. 2 A possible pressure build-up caused by melted UF6 contents is therefore generally unproblematic, because the increased ullage compared to a standard 30B cylinder leads to relatively large safety margins.

The admissible temperature for the 30B-X cylinder is therefore set to 131 °C/267.8 °F. This ad-missible temperature is below the allowable temperatures defined in standards or the hot-working temperatures and liquidus temperatures/melting points of the materials being part of the pres-sure-containment of the 30B-X cylinder.

The additional components of a 30B-X cylinder compared to a standard 30B cylinder are the components of the CCS: the lattice holders, the criticality control rods (CCRs), and the neutron absorbing material. The material specifications for the lattice holders and the CCRs are in com-pliance with a standard 30B cylinder according to [ANSI N14.1] and, therefore, exceed the ad-missible temperature as well. With 2763 °C/ 5005 °F, the melting point of the neutron absorbing material in the form of B4 C is far above the admissible temperature.

Furthermore, there is no danger of rupture because of a possible pressure build-up caused by melted UF6 contents for temperatures above the triple point. The admissible component temper-atures for the DN30 PSP are derived from Appendix 1.4.2 (Material Properties). The admissible temperatures are summarized in table 2-11 below.

Table 2-11 Admissible component temperatures of the DN30-X package Geistiges Eigentum der Orano NCS GmbH Admissible temperature [°C]

Component Material NCT HAC DN30 PSP Property of Orano NCS GmbH Outer shell Type 304/1.4301 70 / 1001) 9006)

Inner shell Type 304/1.4301 601) 9006)

Foam PIR foam 602) -

Thermal insulation Microporous material (see table 1-12) 602) 1000 Intumescent material Intumescent material (see table 1-12) 1503) 600 30B-X cylinder Shells Pressure vessel steel Lattice Holder/CCRs Pressure vessel steel 644) 1315)

Neutron absorber Boron carbide Valve / plug Body Aluminum bronze Stem Nickel copper alloy 644) 1315)

Solder Tin lead alloy

1) Calculation temperature for the handling, for the outer shell: 70 °C in general and 100 °C for the lifting lugs at the top half.

2) Identical to the temperature of the shells.

3) Temperature where the expansion of the intumescent material begins.

4) Triple point temperature of UF .

6

5) Covering maximum temperature for the components of the 30B-X cylinder (see calculations above).

6) The hot forming of material Type 304/1.4301 is carried out at temperatures of 950 to 1200 °C. At 900 °C a sufficient strength remains and, thus, a deformation by own weight is not expected. The strength of the outer shell is neither relevant for the containment system nor for shielding and criticality safety.

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0045-BSH-2020-001 Rev. 2 2.3.3 Prototype Fire Tests To support the thermal analyses that is mainly conducted using FEM analyses, prototype fire tests of the DN30 package were carried out for benchmarking and validation of the thermal properties and of the heat transfer mechanisms of the DN30 PSP. Because the DN30 PSP used for the DN30 package is identical to the DN30 PSP used for the DN30-X package, these results are applicable for the DN30-X as well.

The performance and results of the prototype fire tests are described in detail in Appendix 2.3 (Thermal Analysis), chapter 4.

2.3.4 Thermal Analysis of the DN30-X Package The thermal analysis of the DN30-X package is based on transient-thermal calculations with benchmarked and validated FEM models. The prototype fire tests listed in section 2.3.3 were used for benchmarking and validation. The benchmark calculations are detailed in Appendix 2.3 (Thermal Analysis), section 5.4.

After a description of the calculation model and its material properties and heat transfer mecha-nisms, this benchmarked and validated calculation model is then used to investigate the behavior of the DN30-X package for NCT and HAC and to show compliance with the requirements defined in section 2.3.1. Sensitivity analyses for different parameters like contact definitions, mesh size, and time-step size are included as well.

Geistiges Eigentum der Orano NCS GmbH 2.3.4.1 Software The thermal analysis is carried out with [ANSYS] Workbench 2022 R2, which is a software envi-Property of Orano NCS GmbH ronment for performing linear and non-linear structural, thermal, and electromagnetic analyses using the finite element method (FEM). The capabilities of ANSYS Workbench encompass ge-ometry creation and optimization, meshing, preparing the finite element model, solving and post-processing of results. For thermal problems, ANSYS Workbench can solve steady-state as well as transient problems using two- or three-dimensional models.

2.3.4.2 Calculation Model For the thermal analysis of the DN30-X package, an axisymmetric two-dimensional model is used.

The models of the DN30 PSP and of the 30B-X cylinder are simplified for the 2D environment.

For example, the steel flange between top half and bottom half is not modelled but accounted for in the thermal properties of the foam used in the analysis; the valve and plug end of the 30B-X cylinder are modeled with straight heads instead of curved heads. All assumptions and a detailed description are listed in Appendix 2.3 (Thermal Analysis), section 5.3.

2.3.4.3 Material Properties The material properties are listed in Appendix 2.3 (Thermal Analysis), section 5.3.4, for three different conditions: for NCT conditions before the fire, HAC conditions during the fire, and HAC conditions after the fire during cooling down. For the foam parts, the material conditions of the HAC fire phase are used for the first 30 min of the HAC cool-down phase as well to account for the complete duration of the foam pyrolysis as observed during the prototype fire tests.

The material properties are mainly derived from Appendix 1.4.2 (Material Properties).

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0045-BSH-2020-001 Rev. 2 2.3.4.4 Boundary Conditions and Heat Exchange 2.3.4.4.1 Initial Temperatures The initial temperatures for the steady-state and transient calculations for NCT are uniformly 38 °C.

The initial temperatures for the transient calculations for HAC are:

• For the HAC fire phase: uniformly 63 °C, a conservative temperature calculated for NCT boundary conditions (see section 2.3.4.5).

• For the HAC cooling down phase: the temperature distribution at the end of the fire phase.

2.3.4.4.2 Thermal Contacts The thermal contacts for components in physical contact are modelled using standard bonded contacts with an augmented Lagrange formulation. The thermal conductance of these contacts is calculated by the program automatically based on the material properties.

2.3.4.4.3 Heat Generation Heat generation in form of the thermal power of the UF6 is considered for filled or partly filled packaged as well as the heat generation caused by the pyrolysis of the foam. Further details are Geistiges Eigentum der Orano NCS GmbH listed in Appendix 2.3 (Thermal Analysis), section 5.3.7.

2.3.4.4.4 Solar Insolation The solar insolation data are specified in Table 2-12. They comply with [10 CFR Part 71]

Property of Orano NCS GmbH

§71.71(c)(1) and [SSR-6 2018] para. 657. For the calculation for NCT and for the initial tempera-tures for HAC, several 12-hour insolation / no insolation cycles were investigated.

Table 2-12 Solar insolation Surface Orientation NCT HAC Fire Phase HAC Cooling Down Total insolation for a 12-hour period [W/m²]

Vertical surfaces 200 - 200 (valve and plug end)

Horizontal surfaces 400 - 400 (cylindrical surfaces) 2.3.4.4.5 Heat Transfer Heat transfer to the ambient is considered using radiation and convection. For NCT and the cool-ing phase of HAC, the ambient temperature is 38 °C/100 °F according to [10 CFR Part 71]

§71.71(c)(1) and §71.73(b) or [SSR-6 2018] para. 656. For the fire phase of HAC, the temperature is set to 800 °C/1475 °F according to [10 CFR Part 71] §71.73(c)(4) or [SSR-6 2018] para. 728.

Further details are listed in Appendix 2.3 (Thermal Analysis), section 5.3.9.

Heat transfer in gaps is considered using radiation, conduction, and convection. Further details are listed in Appendix 2.3 (Thermal Analysis), section 5.3.10.

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0045-BSH-2020-001 Rev. 2 2.3.4.5 Thermal Analysis of the DN30-X package for NCT The conditions for the thermal analysis of the DN30-X package for NCT were determined accord-ing to [10 CFR Part 71] §71.71(c)(1) or [SSR-6 2018] para. 657. The DN30-X package with dif-ferent filling ratios is subject to 12-hour insolation / 12-hour no insolation cycles. The cyclic inso-lation model is run for 20 days to reach conditions of steady periodic behavior.

The maximum temperature of 52 °C for a partially or completely filled 30B-X cylinder and its com-ponents is well below the NCT limit of 64 °C defined in Table 2-11. Hence, it can be assumed that the UF6 remains solid under NCT conditions. The maximum temperature of the outer shell of 63 °C is below the admissible temperature of 70 °C as well.

The maximum temperature of 63 °C complies with the initial conditions used for pre-heating of the prototype for the prototype fire test. The maximum temperatures for a DN30 package with an empty 30B cylinder are listed as well, as this combination was used for the prototype fire tests (see section 2.3.3). In general, the maximum temperatures at the 30B-X cylinder are nearly the same regardless of filling ratio because of the relative high heat sink of the internal CCS.

Table 2-13 Maximum temperatures for NCT at the DN30-X package for 12-hour insolation / no insolation cycles Position / Component Maximum temperature [°C]

Geistiges Eigentum der Orano NCS GmbH DN30-X DN30-X DN30-X DN30 package package with a package with package with a with an empty partially filled an empty 30B-X full (100 %)

30B cylinder (50 %) 30B-X cylinder 30B-X cylinder Property of Orano NCS GmbH cylinder Valve 53 52 52 52 Plug 53 52 51 52 Cylinder mantle 53 52 52 52 CCS - 51 51 51 Cylinder volume (Air/UF6) 53 52 52 52 Inner shell DN30 PSP 57 56 56 56 Outer shell DN30 PSP 63 63 63 63 Average of complete 56 54 54 54 package The temperature development of an empty 30B-X package for NCT during 12-hours insolation /

no insolation cycles is shown in Figure 2-4 for the maximum temperatures of the 30B-X pressure envelope (encompasses valve, plug, and mantle), the volume of the 30B-X cylinder (air filling),

the inner shell of the DN30 PSP, and the outer shell of the DN30 PSP.

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0045-BSH-2020-001 Rev. 2 65 60 55 Temperature [°C]

50 45 40 30B-X Pressure Envelope Cylinder Volume 35 DN30 PSP Inner Shell DN30 PSP Outer Shell 30 0 120 240 360 480 Geistiges Eigentum der Orano NCS GmbH Time [h]

Figure 2-4 Temperature development of an empty DN30-X package for NCT during 12-hours in-Property of Orano NCS GmbH solation / no insolation cycles The maximum temperature difference between the 30B-X pressure envelope and interior compo-nents like the CCRs and the lattice holder is evaluated for the calculation of thermal stresses (see Appendix 2.2 (Structural Analysis)). The maximum temperature difference for NCT is 3.9 °C for an empty 30B-X cylinder and 3.4 °C for a completely filled 30B-X cylinder (100 %).

2.3.4.6 Thermal Analysis of the DN30-X package for HAC For the calculations of the DN30-X package for HAC, the ambient temperatures according to

[10 CFR Part 71] §71.73(c)(4) or [SSR-6 2018] para. 728 of 800 °C for the fire phase and 38 °C for the cooling down phase are used.

The end time of the calculation is set to 25220 s or 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after the start of the fire and therefore includes 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of cooling-down. This end time is chosen so that the temperatures of all com-ponents have already reached their maximum and are decreasing.

2.3.4.6.1 Empty 30B-X Cylinder Figure 2-5 shows an overview of the temperatures at the DN30-X package loaded with an empty 30B-X cylinder. The maximum temperatures are listed in Table 2-14 for relevant components of the DN30-X package. The following can be observed:

• The maximum temperatures for the components of the pressure envelope are for the valve 118 °C, for the plug 114 °C, and for the mantle 118 °C. These temperatures are below the admissible temperature of 131 °C.

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• The maximum temperatures for the CCS and the cylinder volume are below the admissible temperature of 131 °C as well with 94 °C and 118 °C.

• The maximum temperatures for the inner and the outer shell are below the admissible tem-perature of 900 °C with 187°C and 785 °C.

• The maximum temperature difference between the 30B-X pressure envelope and interior components like the CCRs and the lattice holder is 15 °C. For an analysis of the thermal stresses, see Appendix 2.2 (Structural Analysis).

800 30B-X Valve 700 30B-X Plug 30B-X Mantle 600 DN30-X Inner Shell DN30-X Outer Shell 500 Temperature [°C]

400 Geistiges Eigentum der Orano NCS GmbH 300 200 Property of Orano NCS GmbH 100 0

0 3600 7200 10800 14400 18000 21600 25200 Time [s]

Figure 2-5 Temperatures at the DN30-X package for HAC with an empty 30B-X cylinder Table 2-14 Maximum temperatures for HAC at the DN30-X package loaded with an empty 30B-X cylinder Position / Component Temperature [°C] Time [s]

Valve 118 10296 Plug 114 7896 Cylinder mantle 118 9096 CCS 94 14496 Cylinder volume (Air/UF6) 118 10296 Inner shell DN30 PSP 187 3620 Outer shell DN30 PSP 785 1810 125 / 172

0045-BSH-2020-001 Rev. 2 Figure 2-6 shows the calculated temperature distribution at the time when the maximum temper-ature is reached for the valve of the 30B-X cylinder.

Temperature [°C]

150 131 112 93 74 141 122 103 84 65 Figure 2-6 Temperature distribution for the empty DN30-X package for HAC at the time when the maximum temperature is reached for the valve (t = 10296 s or ~172 min)

The temperature distribution for the DN30-X package for the time when the maximum tempera-ture difference of 15 °C is calculated between the 30B-X pressure envelope and interior compo-nents like the CCRs and the lattice holders is shown in Figure 2-7. Only the temperatures of the Geistiges Eigentum der Orano NCS GmbH components inside the 30B-X cylinder are shown in order to better present the temperature dis-tribution of these components.

Property of Orano NCS GmbH Temperature [°C]

115 103 91 78 66 109 97 84 72 60 Figure 2-7 Temperature distribution for the empty DN30-X package for HAC at the time when the maximum temperature difference between 30B-X pressure envelope and CCS is reached (t = 6096 s or ~102 min)

Further details are listed in Appendix 2.3 (Thermal Analysis), section 5.6.1.

2.3.4.6.2 Filled 30B-X Cylinder This calculation is similar to the calculation for an empty cylinder in the section before, but with a full 30B-X cylinder (filling ratio 100 %) instead. The UF6 is distributed homogeneously in the cavity of the 30B-X cylinder. The material properties are listed in Appendix 2.3 (Thermal Analysis). All other parameters are identical to the parameters used for the analysis of the DN30-X package 126 / 172

0045-BSH-2020-001 Rev. 2 loaded with an empty 30B-X cylinder documented in section 2.3.4.6.1. The different thermal con-ductance of the contacts UF6 to the 30B-X cylinder pressure envelope or the CCS compared to air are calculated automatically by the calculation program based on the material properties.

Figure 2-8 shows an overview of the temperatures at the DN30-X package loaded with a filled 30B-X cylinder.

800 30B-X Valve 700 30B-X Plug 30B-X Mantle 600 DN30-X Inner Shell DN30-X Outer Shell 500 Temperature [°C]

400 300 200 Geistiges Eigentum der Orano NCS GmbH 100 Property of Orano NCS GmbH 0

0 3600 7200 10800 14400 18000 21600 25200 Time [s]

Figure 2-8 Temperatures at the DN30-X package for HAC with a full 30B-X cylinder The temperatures at relevant positions of the completely filled DN30-X package calculated for the HAC fire test in comparison to the calculation for the empty DN30-X package are listed in Table 2-15. The following can be observed:

• The temperatures at the surface of the DN30 PSP for the completely filled DN30-X package are similar to the temperatures calculated for an empty DN30-X package.

• The temperatures at the 30B-X cylinder are 8 - 10 °C lower for the full cylinder compared to the temperatures calculated for an empty cylinder and the maximum is reached after a shorter time. The additional thermal power of the UF6 is not even remotely high enough to elevate the temperatures above the ones for an empty cylinder because of the increased heat sink of the UF6 compared to air.

• The maximum temperatures for the components of the pressure envelope are for the valve 110 °C, for the plug 106 °C, and for the mantle 110 °C. These temperatures are below the admissible temperature of 131 °C.

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• The maximum temperature difference between the 30B-X pressure envelope and interior components like the CCRs and the lattice holder is 12 °C. For an analysis of the thermal stresses, see Appendix 2.2 (Structural Analysis).

Table 2-15 Maximum temperatures for HAC at the DN30-X package loaded with a full 30B-X cyl-inder Position / Component DN30-X package loaded with a full DN30-X package loaded with an 30B-X cylinder empty 30B-X cylinder Temperature Time Temperature Time

[°C] [s] [°C] [s]

Valve 110 8489 118 10296 Plug 106 7289 114 7896 Cylinder mantle 110 8489 118 9096 CCS 86 12089 94 14496 Cylinder volume (Air/UF6) 109 8489 118 10296 Inner shell DN30 PSP 187 3620 187 3620 Outer shell DN30 PSP 785 1810 785 1810 Geistiges Eigentum der Orano NCS GmbH Figure 2-9 shows the temperature distribution at the time of the maximum valve temperature.

Property of Orano NCS GmbH Temperature [°C]

180 153 127 100 73 167 140 113 87 60 Figure 2-9 Temperature distribution for the full DN30-X package for HAC at the time when the maximum temperature is reached for the valve (t = 8489 s or ~141 min)

To better present the temperature distribution of the 30B-X cylinder and the UF6 contents, Figure 2-10 shows temperatures for these components only, with a correspondingly smaller temperature scale. The point in time is the same as for Figure 2-9, since this also results in maximal tempera-tures for the 30B-X cylinder and its contents. Only the outer regions of the UF6 reach this maxi-mum temperature while the core of the UF6 is still well below that temperature.

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0045-BSH-2020-001 Rev. 2 Temperature [°C]

110 99 88 77 66 104 93 82 71 60 Figure 2-10 Temperature distribution for the full DN30-X package for HAC at the time when the maximum temperature is reached for the UF6 (t = 8489 s or ~141 min)

Further details are listed in Appendix 2.3 (Thermal Analysis), section 5.6.2.

2.3.4.6.3 Partially Filled 30B-X Cylinder After the empty and completely filled 30B-X cylinder, a partially filled 30B-X cylinder (filling ratio 50 %) is investigated as well. The UF6 is distributed homogeneously in the cavity of the 30B-X Geistiges Eigentum der Orano NCS GmbH cylinder. Conservatively, the maximum thermal power for the UF6 is used for the partially filled 30B-X cylinder, too.

The temperatures at the valve of the 30B-X cylinder are shown in Figure 2-11 for HAC for different Property of Orano NCS GmbH filling ratios. The temperatures at relevant positions of the partially filled DN30-X package calcu-lated for the HAC fire test in comparison to the calculation for the empty and completely filled DN30-X package are listed in Table 2-16. The following can be observed:

• The temperatures at the surface of the DN30 PSP for the partially filled DN30-X package are similar to the temperatures calculated for an empty or filled DN30-X package.

• As expected, the temperatures for a partially filled 30B-X cylinder are between the empty and the completely filled 30B-X cylinder, but closer to the completely filled cylinder.

• The temperatures at the 30B-X cylinder are 5 - 7 °C lower for the partially filled cylinder compared to the temperatures calculated for an empty cylinder and the maximum is reached after a shorter time.

• The maximum temperatures for the components of the pressure envelope are for the valve 111 °C, for the plug 108 °C, and for the mantle 112 °C. These temperatures are below the admissible temperature of 131 °C.

• The maximum temperature difference between the 30B-X pressure envelope and interior components like the CCRs and the lattice holder is 13 °C. For an analysis of the thermal stresses, see Appendix 2.2 (Structural Analysis).

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0045-BSH-2020-001 Rev. 2 120 110 100 Temperature [°C]

90 80 30B-X Valve (empty) 70 30B-X Valve (50 % filling) 30B-X Valve (full) 60 0 3600 7200 10800 14400 18000 21600 25200 Time [s]

Figure 2-11 Temperatures calculated at the valve of the DN30-X package for HAC for different fill-Geistiges Eigentum der Orano NCS GmbH ing ratios (0, 50, and 100 %)

Table 2-16 Maximum temperatures calculated for HAC at the DN30-X package loaded with a par-tially filled 30B-X cylinder Property of Orano NCS GmbH Position / Component Partially filled (50 %) Empty Filled (100 %)

30B-X cylinder 30B-X cylinder 30B-X cylinder Maximum Temperature [°C]

Valve 111 118 110 Plug 108 114 106 Cylinder mantle 112 118 110 CCS 89 94 86 Cylinder volume (Air/UF6) 111 118 109 Inner shell DN30 PSP 187 187 187 Outer shell DN30 PSP 785 785 785 2.3.4.6.4 Sensitivity Analysis In addition to the calculations for different filling ratios of the 30B-X cylinder, sensitivity analyses are performed to investigate the influence of certain material properties or modelling approaches.

These calculations are performed with an empty DN30X package for conservative results, as the temperatures calculated for an empty DN30-X package were higher than for a completely or par-tially filled DN30-X package due to the lower heat sink. The full account of the conducted sensi-tivity analyses is listed in Appendix 2.3 (Thermal Analysis), section 5.7; a general overview is 130 / 172

0045-BSH-2020-001 Rev. 2 provided in Table 2-17, where the change in the maximum calculated temperature is listed com-pared to the base model with an empty 30B-X cylinder.

Table 2-17 Overview for the sensitivity analyses Resulting change in maximum Changed parameters for temperature compared to base the sensitivity analysis model At the valve At the plug Direct contact 30B-X cylinder shell - CCS -24 °C -20 °C Direct contact 30B-X cylinder shell - DN30 PSP +2 °C +2 °C Mesh size +20 % < 1 °C < 1 °C Mesh size -20 % < 1 °C < 1 °C Time step size +20 % < 1 °C < 1 °C Time step size -20 % < 1 °C < 1 °C Extrapolation material properties foam +10 % +3 °C +3 °C Extrapolation material properties foam -10 % -2 °C -3 °C Material properties foam without extrapolation -12 °C -13 °C Geistiges Eigentum der Orano NCS GmbH Parameters for foam pyrolysis +10 % +1 °C +1 °C Parameters for foam pyrolysis -10 % -1 °C -1 °C Thickness reduction of microporous insulation to 9.5 mm +1 °C +1 °C Property of Orano NCS GmbH Thickness reduction of microporous insulation to 8.5 mm +2 °C +3 °C Thickness reduction of microporous insulation to 7.0 mm +4 °C +6 °C Thickness reduction of microporous insulation to 5.0 mm +6 °C +13 °C Loss of microporous insulation equal to 1 x ADropBar < 1 °C +4 °C Loss of microporous insulation equal to 2 x ADropBar +1 °C +5 °C Loss of microporous insulation equal to 4 x ADropBar +1 °C +8 °C Loss of microporous insulation and foam equal to 1 x ADropBar +4 °C +5 °C Loss of microporous insulation and foam equal to 2 x ADropBar +7 °C +10 °C The following can be observed:

• A direct contact between the shell of the 30B-X cylinder and the CCS leads to greatly re-duced maximum temperatures because the impact of the CCS acting as a large heat sink is greatly improved by the contact.

• The conservative modelling of the direct contact between the 30B-X cylinder shell and the DN30 PSP only leads to a small increase in maximum temperatures.

• Rather large variations for mesh size, time step size, foam material properties, and foam pyrolysis properties lead to only small changes in the maximum temperatures. Using no extrapolation for the foam parameters leads to a rather large reduction in the maximum temperatures.

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0045-BSH-2020-001 Rev. 2

• A reduction in the thickness of the microporous insulation layer from nominal to minimal (9.5 mm) leads to only very small changes in the maximum temperature. Even very con-servative thickness reductions for HAC do not cause an increase above the admissible temperatures.

• The analyses for losses of microporous insulation and/or foam shows that even very con-servative scenarios do not cause an increase of the maximum temperatures above the ad-missible temperatures.

More details are listed in Appendix 2.3 (Thermal Analysis), section 5.7.

2.3.5 Proof for the DN30-X Package to Meet the Regulatory Requirements 2.3.5.1 Ambient Temperatures and Pressures For the analysis, an ambient temperature of 38 °C is considered (see section 2.3.4.5). Pressures that are likely to be encountered under RCT and NCT have no effect on the results of the thermal analysis. Consequently, the requirements of [10 CFR Part 71] §71(c)(1)-(4) or [SSR-6 2018]

para. 616 are met.

2.3.5.2 Component Temperatures of the DN30-X Package Geistiges Eigentum der Orano NCS GmbH In the thermal analysis for the DN30-X package for NCT in section 2.3.4.5, the maximal compo-nent temperatures are 63 °C for the DN30 PSP and 52 °C for the 30B-X cylinder and its contents.

Therefore, the maximal component temperatures of the DN30-X packaging during NCT are lower than the admissible values specified in Table 2-11.

Property of Orano NCS GmbH In the thermal analysis of the DN30-X package for HAC in section 2.3.4.6, the maximal component temperatures of the DN30 PSP are close to, but still below, the admissible temperatures defined in Table 2-11. Tests with a prototype of the DN30 package showed that these temperatures do not affect the function of the inner and outer shells of the DN30 PSP with respect to shielding and criticality safety.

The maximum temperature calculated for the 30B-X cylinder shell is below the admissible tem-perature defined in Table 2-11. The temperatures of the valve and plug thread are below the admissible temperature defined in Table 2-11 as well. The maximum temperatures calculated for the components of the 30B-X cylinder are even below the design limit specified in [ANSI N14.1]

of 121 °C/250 °F for regular 30B cylinders. The requirements for the pressure envelope of the 30B-X cylinder are at least equal to those of regular 30B cylinders according to [ANSI N14.1].

With regards to thermal stresses of the 30B-X cylinder, the maximum temperature difference be-tween the pressure envelope of the 30B-X cylinder and interior components like the CCS is less than 4 °C for NCT and maximal 15 °C for HAC. No significant thermal stresses occur for such low temperature differences (see Appendix 2.2 (Structural Analysis)).

2.3.5.3 Rupture of the Containment System Regarding a rupture of the containment system, an empty and a full cylinder define the two bound-ing cases. For an empty cylinder, the temperatures during the thermal test under HAC are max-imized as the 30B-X cylinder provides the lowest possible heat sink. For a full cylinder, the tem-peratures are generally lower, but the significant volume expansion of the UF6 content during its solid-to-liquid phase change potentially causes a pressure build-up with increasing temperatures.

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0045-BSH-2020-001 Rev. 2 The maximum temperatures reached during the thermal test under HAC required for the evalua-tions in this section are taken from the thermal analysis of the DN30-X package in 2.3.4.6.

For an empty 30B-X cylinder, a maximum temperature of 118 °C is reached at its components and its cavity during the thermal test under HAC. For a 100 % filled 30B-X cylinder, the maximum temperature reached during the thermal test under HAC are even lower with a maximum of 110 °C. These calculated temperatures are at least 10 °C below the admissible temperature for the containment system of the DN30-X of 131 °C listed in Table 2-11. The maximum tempera-tures do not exceed the design limit of 121 °C (250 °F) as specified in [ANSI N14.1] for regular 30B cylinders. The requirements for the pressure envelope of the 30B-X cylinder are at least equal to those of regular 30B cylinders according to [ANSI N14.1].

Additionally, the safety ratios calculated for a pressure build-up caused by melted UF6 contents include an additional safety factor of at least 2 (see Table 2-9). As proven by the above evaluation, all admissible temperatures are met for the containment system of the DN30-X packaging. In the determination of these admissible temperatures, a possible pressure build-up in the 30B-X cylin-der due to melted UF6 contents was considered. As the admissible internal pressure, the hydro-static test pressure of 2.76 MPa (400 psig) specified in [ANSI N14.1] was assumed, since the requirements for the pressure envelope of the 30B-X cylinder are at least equal to those of regular 30B cylinders according to [ANSI N14.1]. Furthermore, it was shown in section 2.3.2 that the wall thickness of the cylinder shell and of the cylinder heads are above the required wall thicknesses calculated according to [ASME BPVC].

Geistiges Eigentum der Orano NCS GmbH Therefore, all requirements of [49 CFR Part 173] §420(a)(3) or [SSR-6 2018] para. 632(c) are met.

2.3.5.4 Influence of the Thermal Test on the Criticality Safety Analysis Property of Orano NCS GmbH The thermal analysis for the DN30-X package in section 2.3.4.6 proves that the stainless-steel shells of the DN30 PSP as well as the carbon steel shell of the 30B-X cylinder are not affected by the thermal test in such a way that their thickness and density is reduced. The criticality safety is ensured when taking into account these results. In the criticality safety analysis in Appendix 2.6 (Criticality Safety Analysis), a complete loss of the foam is considered.

The requirements of [10 CFR Part 71]§55(d), §55(e) and §59(a)(2) or [SSR-6 2018] para. 682 and 685 with respect to the thermal test under HAC are met.

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0045-BSH-2020-001 Rev. 2 2.4 Containment Design Analysis The containment design analysis of the DN30-X package is described in detail in Appendix 2.4 (Containment Analysis). This section provides a summary of the main points and results. The analysis covers UF6 of grade HALEU 10 and HALEU 20 for all filling ratios ranging from 0 kg up to the specific fill limits of the 30B-10 and 30B-20 cylinder listed in table 1-4.

As applicable to a Type AF package, RCT and NCT are considered, as there is no restriction on the radioactivity release under HAC, which is due to the limit of 1 A2 for the radioactive content of Type A packages.

2.4.1 Objective of verification It is verified that the DN30-X package complies with the requirements under NCT according to

[10 CFR Part 71] §43(f) and [49 CFR Part 173] §412(j) or [SSR-6 2018] para. 648(a) when sub-mitted to the tests under NCT according to [10 CFR Part 71] §71(c)(7) and §71(c)(9) and

[49 CFR Part 173] §465(c) and §465(d) or [SSR-6 2018] para. 722 and 723:

Prevent loss or dispersal of the radioactive content It is specified in the Advisory Material for the IAEA Regulations for the Transport of Radioactive Material [SSG-26 2012] para. 648.2, that a maximum allowable leakage rate for NCT has never Geistiges Eigentum der Orano NCS GmbH been defined quantitatively. In [SSG-26 2012] para. 648.3 it is specified that the intention of

[SSR-6 2018] para. 648(a) is to ensure that under NCT the radioactive contents of the package cannot escape in quantities that may create a radiological hazard.

In this analysis, as a covering criterion the same maximum allowable leakage rate under NCT as Property of Orano NCS GmbH for Type B packages (as per [10 CFR Part 71] §71.51 or [SSR-6 2018] para. 659(a) is applied to Type A packages. Hence, the maximum permissible activity release rate under NCT is:

2 N 106 h

For Type AF packages, there is no restriction on the activity release under HAC due to the limit of 1 A2 for the whole content.

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0045-BSH-2020-001 Rev. 2 2.4.2 Calculation Method and Assumptions The containment design analysis for the DN30-X package is carried out per [ISO 12807] (or the equivalent standard [ANSI N14.5]) in the following steps:

1. Determination of radioactive contents,

2. Determination of total releasable activity, T

3. Determination of maximum permissible activity release rate,

4. Determination of activity release rate due to permeation,

5. Determination of maximum permissible activity release rate due to leakage, =

6. Determination of activity per unit volume,

7. Determination of maximum permissible leakage rate, =

8. Determination of maximum permissible equivalent capillary leak diameter,

9. Determination of the permissible standardized leakage rate, SLR These steps and their results are performed for packages with filled 30B-X cylinders and cylinders with heels contents. They are described in detail in Appendix 2.4 (Containment Analysis). A cen-tral point of the containment design analysis is the following conservatively covering assumption about the radioactive contents of the DN30-X package:

Geistiges Eigentum der Orano NCS GmbH As proven by the analysis in section 1.3.2.11, the radioactive contents will remain below 1 A2 even for the pessimistic case of multiple refillings of 30B-X cylinders without intermediate wash-ing. Nevertheless, the containment analysis assumes a radioactive content of 1 A2 for both filled cylinders and cylinders containing heels and therefore covers all real package contents.

Property of Orano NCS GmbH 2.4.3 Summary and Evaluation of Results The permissible standardized helium leakage rates for the 30B-10 and 30B-20 cylinder under NCT resulting from the containment design analysis for a covering radioactive content of 1 A2 are listed in table 2-18. For comparison, the results for the standard 30B cylinder are listed as well.

Table 2-18 Permissible standardized helium leakage rates under NCT Value Item Condition 30B cylinder 30B-10 cylinder 30B-20 cylinder Required standardized helium Filled 1.35 10 1 0.83 10 1 0.71 101 leakage rate in Pa

• m3 s Heels 4.93 104 3.09 104 2.66 104 These results show that the objective of verification defined in section 2.4.1 is met for all permitted package contents. The calculated permissible standardized helium leakage rates are less de-manding than the maximal standardized helium leakage of 10-4 Pa*m³/s that is specified for the 30B-X cylinder in section 1.2.10. For filled cylinders, the calculated results are higher by several orders of magnitude, and for cylinders with heels, they are higher by a factor of at least 2.6.

It should be noted that actual standardized helium leakage rates even after HAC tests, meas-ured after the regulatory tests performed with the DN30 package, were well below 10-6 Pa*m³/s (cf. appendix B of Appendix 2.2 (Structural Analysis)).

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0045-BSH-2020-001 Rev. 2 2.5 External Dose Rate Analysis The external dose rate analysis covers the DN30 package loaded with filled cylinders as well as cylinders containing heels under RCT and NCT. The analysis is valid for UF6 contents of type HALEU 10 and HALEU 20 as specified in section 1.3.

This section provides a summary of the main points and results of the external dose rate analysis, which is documented in detail in Appendix 2.5 (External Dose Rate Analysis).

2.5.1 Objective of Verification 2.5.1.1 Verification for all Types of Packages For DN30-X packages loaded with 30B-X cylinders that are either filled with UF6 complying with the compositions in table 1-2 or that contain heel quantities of UF6 complying with the composition in table 1-3, it has to be verified that the limit value for RCT specified in [10 CFR Part 71] §47(a) and [49 CFR Part 173] §441(a) or [SSR-6 2018] para. 526 is not exceeded:

TI 10 A transport index TI 10 is equivalent to:

Geistiges Eigentum der Orano NCS GmbH mSv at a distance of 1 m from the external surface of the package DL 0.1 h

It has to be verified that the limit value for RCT specified in [10 CFR Part 71] §47(a) and Property of Orano NCS GmbH

[49 CFR Part 173] §441(a) or [SSR-6 2018] para. 527 is not exceeded:

mSv at the surface of the package DL 2 h

It has to be verified that the limit values for RCT specified in [10 CFR Part 71] §47(b) or

[SSR-6 2018] para. 566(b) are not exceeded:

mSv at any point on the external surface of the vehicle DL 2 h

at any point 2 m from the vertical planes represented by the outer lateral mSv surfaces of the vehicle, or, if the load is transported in an open vehicle, at DL 0.1 h any point 2 m from the vertical planes projected from the outer edges of the vehicle Whenever calculations are performed for the vehicle, it is assumed that the external surface of the package coincides with the external surface of the vehicle. The package might be oriented with its longitudinal axis parallel or perpendicular to the longitudinal axis of the vehicle. In case of parallel orientation, two adjacent packages positioned face-to-face along their symmetry axis are considered. In case of perpendicular orientation four adjacent packages positioned side-by-side are considered.

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0045-BSH-2020-001 Rev. 2 2.5.1.2 Verification for Type AF Packages It has to be verified that, the package complies with the requirements according to

[10 CFR Part 71] §43(f) and [49 CFR Part 173] §412(j) or [SSR-6 2018] para. 648(b), when sub-mitted to the tests under NCT according to [10 CFR Part 71] §71(a)(6)-(10) and

[49 CFR Part 173] §465(a)-(e) or [SSR-6 2018] para. 719-724:

DL 20 % (no significant increase in external surface radiation)

DL is the increase in the maximal radiation level at any external surface of the package.

2.5.2 Assumptions for the Calculations The calculations of dose rates at the DN30-X package and at the vehicle are based on the as-sumptions listed in sections 2.5.2.1 to 2.5.2.3.

2.5.2.1 Assumptions Valid for all Calculations The following assumptions are valid for all calculations carried out throughout this chapter:

• The treated contents comply with the content description in section 1.3.

• The same maximal outer dimensions are used for the calculation model of the 30B-X cylin-Geistiges Eigentum der Orano NCS GmbH der as are defined for the standard 30B cylinder in [ANSI N14.1]. Conservatively, a minimal wall thickness of 1.1 cm is assumed (see table 1-13).

• Axial and radial dimensions of the 30B-X cylinder are identical under RCT and NCT.

Property of Orano NCS GmbH

• The skirts of the 30B-X cylinder are neglected in the considered calculation models and all 30B-X cylinders are assumed to have flat heads.

• The DN30 PSP is taken into account in the calculations.

• The CCS is considered by modelling 37 CCRs, which is an approximation for the 30B-10 and for the 30B-20 cylinder.

2.5.2.2 Assumptions for Routine Conditions of Transport A conservative density of 0.1 g/cm3 is assumed for the polyisocyanurate rigid foam (PIR foam).

In reality, the PIR foam used in the manufacturing of the DN30 PSP has a higher density than 0.1 g/cm3.

2.5.2.3 Assumptions for Normal Conditions of Transport The following assumptions are made with regard to the tests under NCT that are prescribed in

[10 CFR Part 71] §71(a)(6)-(10) and [49 CFR Part 173] §465(a)-(e) or [SSR-6 2018] para. 719-724:

• Neither the shape of the UF6 inside the 30B-X cylinder nor the dimensions of the 30B-X cyl-inder are affected by the tests.

• A covering maximal deformation of the DN30 PSP of 20 mm is taken into account.

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0045-BSH-2020-001 Rev. 2 2.5.3 Calculation Method, its Verification and Validation The calculation of dose rates at the DN30-X package is carried out by means of the program system SCALE 6.2.3/6.2.4 [SCALE 2020]. The gamma and neutron source terms are determined by means of the depletion analysis sequence ORIGEN in the v7-27n-19g energy-group structure.

The dose rates are calculated by means of the analysis sequence MAVRIC.

2.5.4 Gamma and Neutron Source Terms The gamma und neutron source terms used in the external dose rate analysis are determined by considering contributions from the isotopes present in the UF6 based on Table 1-2, and the con-tributions from the build-up of their daughter nuclides.

A period of up to 10 years for the build-up of daughter nuclides is used to obtain the maximal source intensities, covering all possible time periods of cylinder storage.

For the analysis of heels contents, it is conservatively assumed that 100% of the amount of all non-uranium nuclides built up from the UF6 content of the filled cylinder will remain in the heels.

As shown by the analysis, the external dose rates from neutrons are very low compared to the contribution from gamma dose rates, and can be accounted for in a covering way by multiplying the gamma dose rates by a factor of 1.05.

Geistiges Eigentum der Orano NCS GmbH 2.5.5 Model Specification 2.5.5.1 Geometrical Model for the DN30-X Packaging Property of Orano NCS GmbH 2.5.5.1.1 30B-X Cylinder The calculation model of the 30B-X cylinder is based on the dimensions of the standard 30B cyl-inder as specified in [ANSI N14.1]. Throughout the external dose rate analysis of the DN30-X package, the following conservative assumptions are made for the calculation model:

• The 30B-X cylinder is simplified to a cylinder with flat heads.

• The modeled 30B-X cylinder is compliant with the maximal dimensions specified for the standard 30B cylinder in [ANSI N14.1].

• The modeled 30B-X cylinder considers the minimal wall thickness of 1.1 cm as specified in table 1-13.

• The skirts, valve, plug and nameplate of the 30B-X cylinder are neglected.

• The CCS is modelled by 37 CCRs having a diameter of 6.03 cm and a wall thickness of 0.315 cm. The CCRs are arranged in a hexagonal pitch of 5 cm.

• A density of 1.2 g/cm2 is assumed for the B4 C content of the CCRs.

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0045-BSH-2020-001 Rev. 2 2.5.5.1.2 DN30 PSP The calculation model for the DN30 PSP is simplified significantly for the dose rate analysis of the DN30-X package. For this reason, neither the feet nor the six closure devices are modeled, even though they are made up of stainless steel and contribute to the attenuation of gamma radiation.

Based on the condition of transport to be modeled, two calculation models of DN30 PSPs are considered throughout the external dose rate analysis of the DN30-X package:

• RCT: In this case, the DN30 PSP is composed of two cylindrical shells of stainless steel with the full thickness of the PIR foam in between.

• NCT: Similar to the calculation model for RCT, but a reduction of the thickness of the PIR foam by 20 mm is assumed so that the outer diameter of the DN30 PSP is also reduced by 20 cm. The density of the PIR foam is conservatively kept unchanged.

2.5.5.2 Geometrical Models for the Content 2.5.5.2.1 Filled Cylinder under RCT and NCT The calculation model used for the filled 30B-X cylinder under RCT and NCT is a cylinder filled with UF6 having no ullage. The source is homogeneously distributed within the UF6 .

Figure 2-12 and figure 2-13 show the calculation model. The UF6 is shown in red, B4 C in blue, carbon steel in green, stainless steel in magenta and foam in yellow.

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH Figure 2-12 Cross section of the calculation model along the longitudinal axis 139 / 172

0045-BSH-2020-001 Rev. 2 Figure 2-13 Cross section of the calculation model perpendicular to the longitudinal axis Geistiges Eigentum der Orano NCS GmbH 2.5.5.2.2 Cylinder Containing Heel Quantities under RCT and NCT For 30B-X cylinder containing heel quantities, three different models are investigated:

• The radiation source is a thin layer of UF6 attached to the inner side of the cylinder wall.

Property of Orano NCS GmbH

• The radiation source is a pool of UF6 in form of a puddle at the bottom of the cylinder.

• The radiation source is a thin layer of UF6 attached to the inner side of one of the cylinder heads.

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0045-BSH-2020-001 Rev. 2 2.5.6 Verification of Compliance with Dose Rate Limits 2.5.6.1 Verification of the Dose Rates according to 10 CFR §71.47(a) and 49 CFR §173.441(a) or SSR-6 para. 526 The maximal total dose rates at a distance of 1 m from the surface of the DN30-X package loaded with a 30B-X cylinder filled with UF6 or containing heel quantities of UF6 complying with table 1-2 and table 1-3, respectively, are listed in table 2-19.

For the DN30-X package loaded with a filled 30B-X cylinder, the transport index is TI = 0.8.

Hence, the transport of the DN30-X package loaded with a 30B-X cylinder containing UF6 com-plying with the composition in table 1-2 may be carried out under non-exclusive use.

For the DN30-X package loaded with a 30B-X cylinder containing heel quantities, the transport index is TI = 5.6. Hence, the transport of the DN30-X package loaded with a 30B-X cylinder con-taining heel quantities of UF6 complying with the composition in table 1-3 may be carried out under non-exclusive use.

Table 2-19 Maximal total dose rates under RCT at a distance of 1 m from the external surface of the package - DN30-X package loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 UF6 composition Total dose rate in µSv/h Geistiges Eigentum der Orano NCS GmbH HALEU 10 5 HALEU 20 8 Heels of HALEU 10 45 Property of Orano NCS GmbH Heels of HALEU 20 56 Limit value (for non-exclusive use) 100 2.5.6.2 Verification of the Dose Rates according to 10 CFR §71.47(a) and 49 CFR §173.441(a) or SSR-6 para. 527 The maximal total dose rates at the surface of the DN30-X package loaded with a 30B-X cylinder filled with UF6 or containing heel quantities of UF6 complying with table 1-2 and table 1-3, respec-tively, are listed in table 2-20. The calculated dose rates are below the limit value and, thus, the objective of verification is met.

Table 2-20 Maximal total dose rates under RCT at the surface of the package - DN30-X package loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 UF6 composition Total dose rate in µSv/h HALEU 10 21 HALEU 20 34 Heels of HALEU 10 374 Heels of HALEU 20 476 Limit value (for non-exclusive use) 2000 141 / 172

0045-BSH-2020-001 Rev. 2 2.5.6.3 Verification of the Dose Rates according to 10 CFR §71.47(b) or SSR-6 para. 566(b)

Maximal total dose rates at the external surface of the vehicle (equivalent to the dose rate at the external package surface) loaded with DN30-X packages each loaded with a 30B-X cylinder filled with UF6 or containing heel quantities of UF6 are listed in table 2-21. The dose rates are below the limit of 2000 µSv/h and, thus, the objective of verification is met.

Table 2-21 Maximal total dose rates under RCT at the external surface of a vehicle loaded with DN30-X packages each loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 UF6 composition Total dose rate in µSv/h HALEU 10 21 HALEU 20 34 Heels of HALEU 10 374 Heels of HALEU 20 476 Limit value 2000 Maximal total dose rates at a distance of 2 m from the external surface of a vehicle transporting four DN30-X packages each loaded with a 30B-X cylinder filled with UF6 or containing heel quan-Geistiges Eigentum der Orano NCS GmbH tities of UF6 are given in table 2-22. The dose rates are below the limit of 100 µSv/h and, thus, the objective of verification is met.

Property of Orano NCS GmbH Table 2-22 Maximal total dose rates under RCT at a distance of 2 m from the external surface of a vehicle transporting four DN30-X packages each loaded with a 30B-X cylinder filled with HALEU 10 or HALEU 20 or containing heel quantities of HALEU 10 or HALEU 20 UF6 composition Total dose rate in µSv/h HALEU 10 3 HALEU 20 5 Heels of HALEU 10 23 Heels of HALEU 20 29 Limit value 100 2.5.6.4 Verification according to 10 CFR §71.43(f) and 49 CFR §173.412(j) or SSR-6 para. 648(b)

Even under very pessimistic assumptions, assuming significantly higher deformations of the DN30 PSP than determined in the structural analysis under NCT in section 2.2, an increase of maximally 11.4 % was determined for the dose rate at the surface of the DN30-X package, which is far below the admissible limit of 20 %.

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0045-BSH-2020-001 Rev. 2 2.5.7 Summary and Evaluation of Results The dose rate analysis shows that the dose rate limits as listed in section 2.5.1 and prescribed in

[10 CFR Part 71] and [49 CFR Part 173] or [SSR-6 2018] are met for the contents specified in table 1-2 and table 1-3.

The calculated dose rates at the DN30-X package containing filled 30B-X cylinders or 30B-X cyl-inders containing heel quantities are in all cases less than the dose rates limits. The assessment also covers multiple refilling of 30B-X cylinders containing heel quantities with new product.

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 143 / 172

0045-BSH-2020-001 Rev. 2 2.6 Criticality Safety Analysis The criticality safety analysis for the DN30-X package, documented in full in Appendix 2.6 (Criti-cality Safety Analysis), covers RCT, NCT and HAC, taking into account the maximal enrichment of 10 wt.-% 235U for the DN30-10 and 20 wt.-% 235U for the DN30-20. It is valid for all filling ratios from UF6 heels up to the maximum amount of UF6 defined in section 1.3.2.1, and covers UF6 containing up to 0.5 wt.-% volatile impurities (HF) and additional hydrogenated uranium residues from accumulated during the time period between recertifications.

Due to maximal UF6 enrichments above 5 wt.-% 235U, the analysis has to take into account opti-mal moderation of the UF6 for the single package. The exclusion of water inleakage allowed in

[10 CFR Part 71] §55(g) or [SSR-6 2018], para. 680 (b)(i), is only applicable for packages with UF6 enriched to a maximum of 5 wt.-% 235U and cannot be credited for higher enrichments.

The drop tests for the mechanical analysis demonstrate that any damage to the cylinder valve and plug can be excluded even under HAC, so that water ingress can be excluded for the package arrays under NCT and HAC.

2.6.1 Objective of Proof Criticality safety is proven according to the requirements for fissile material packages in

[10 CFR Part 71] §55 or [SSR-6 2018], para. 673. For RCT, NCT and HAC the following criticality safety criterion is applied:

Geistiges Eigentum der Orano NCS GmbH keff + 3 + k 0.95 For the proof, systematical deviations k of the calculation method are taken into account to de-termine an Upper Subcritical Limit (USL) that has to be complied with by the calculation result for Property of Orano NCS GmbH keff + 3. The safety criterion thus becomes:

keff + 3 USL = 0.95 - k Systematical deviations are determined via comparison with suitable benchmark experiments.

This validation analysis, summarized in section 2.6.3.2, results in the following USL values:

USL = 0.9419 for the DN30-X single package in isolation USL = 0.9263 for the DN30-X HAC array of packages It is shown that the DN30-X package fulfills the criticality safety criterion, taking into account all manufacturing tolerances, credible and hypothetical conditions of the arrangement of the UF6 and inleaked water in the 30B-X cylinder, as well as all deformations of the package and especially the CCS due to RCT, NCT and HAC.

2.6.2 Assumptions for the Proof of Criticality Safety The proof of criticality safety for the DN30-X package is based on the assumptions detailed in sections 2.6.2.1 through 2.6.2.4.

2.6.2.1 Assumptions Valid for all Calculations The following assumptions are valid for all calculations:

• The admissible number is N = infinite (CSI = 0).

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0045-BSH-2020-001 Rev. 2 235

• The content is enriched UF6 with an enrichment of 10 wt.-% U in uranium for the DN30-10, and 20 wt.-% 235U in uranium for the DN30-20.

• The density of UF6 is conservatively assumed at a theoretical density of 5.5 g/cm3 (see section 2.6.4.1).

• Axial and radial dimensions of the 30B cylinder are identical under RCT, NCT and HAC.

• For the representation of the 30B cylinder in the calculation model, the skirts and the shape of the cylinder heads are taken into account.

• The valve and plug as well as the name plate are neglected in all calculation models.

• Water might penetrate arbitrarily into the foam of the PSP.

2.6.2.2 Assumptions for the single package under RCT, NCT and HAC The proof for the single package under RCT, NCT and HAC is carried out under the assumption of optimal moderation of the contents with water and a full water reflector:

• The DN30 PSP is conservatively neglected

• The 30B-X cylinder is surrounded by a 30 cm water reflector.

• Optimal moderation of the UF6 contents with water is assumed.

• All deformations of the package and especially the CCS due to HAC are considered.

• Additional calculations are performed for the pessimistic assumption that the UF6 contents form a heterogeneous lattice with water or transform into the uranium compound UO2 F2.

Geistiges Eigentum der Orano NCS GmbH 2.6.2.3 Assumptions for 5 x N Packages under NCT The proof for 5 x N = infinite number of packages under NCT is covered by the proof for an infinite Property of Orano NCS GmbH number of packages under HAC according to section 2.6.2.4.

2.6.2.4 Assumptions for 2 x N Packages under HAC The proof is carried out for 2 x N = infinite number of packages under HAC. The proof is based on the conditions of the packages after the tests required to demonstrate their ability to withstand HAC. Ingress of large water volumes into the cavity of the 30B-X cylinder is not assumed as the mechanical analysis shows that the integrity of the cylinder is not compromised under HAC.

• The UF6 contains the maximum of 0.5 wt.-% volatile impurities (HF), as well as 11.3 kg of hydrogenated uranium residues (HUR) concentrated in a sphere.

• Moderation from water ingress due to the immersion under a head of 15 m water for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is negligible compared to the hydrogen in HF and HUR (see section 6.5.1 of Appendix 2.6).

• The 30B-X cylinder is completely filled with UF6. The HUR sphere can be placed anywhere within the cylinder cavity.

• The total thickness of the DN30 PSP around the 30B-X cylinder is reduced to 10 cm in radial direction (around the mantle) and 8 cm in axial direction (on the valve/plug ends), conser-vatively covering all deformations due to HAC impacts.

• Additional calculations are performed for the hypothetical assumption that the PSP is com-pletely compacted around the cylinder, taking only the steel of the shells into account.

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0045-BSH-2020-001 Rev. 2 2.6.3 Calculation Method, Verification and Validation All criticality safety calculations in this document are performed by means of the sequence CSAS6 of the criticality safety code KENO VI from version 6.1.2 of the SCALE package [SCALE 2011].

All calculations use the multi-group cross section library v7-238 based on ENDB/B-VII data.

2.6.3.1 Verification The verification consists of the installation and functional verification of the SCALE 6.1.2 program system. The functional verification is carried out by the editor of the program system on the basis of the appropriate verification plan. For the individual user, the verification of the program system SCALE 6.1.2 consists of the installation verification on the basis of case studies delivered by the editor. The case studies were calculated successfully and compared with the likewise delivered reference output files. There were no differences in the output files which exceeded the range of admissible deviations mentioned in the installation guide accompanying the code package. Thus, successful installation verification is given.

2.6.3.2 Validation The calculation method (code and cross-section data) used to establish criticality safety must be validated against measured data (e.g., criticality benchmark experiments) that could be applicable to the package design characteristics. The validation process provides a basis for the reliability of Geistiges Eigentum der Orano NCS GmbH the calculation method and should justify that the calculated keff, plus bias and uncertainties (if necessary) for the actual package conditions will ensure the compliance with the criticality safety criterion.

Property of Orano NCS GmbH The ICSBEP (International Criticality Safety Benchmark Evaluation Project) [NEA 2019] contains a large number of evaluated criticality safety benchmark experiments which can be used for vali-dation purposes. Applicable benchmarks should be selected based on their similarity to the ap-plication case. The validation analysis to determine applicability of benchmarks and to determine the calculation bias from the selected set of applicable benchmarks is described in detail in section 5.2 of Appendix 2.6. The most important points and results are summarized below.

For the single DN30-X package with optimal moderation and under covering assumptions (see section 2.6.6) applicable benchmarks are selected via a sensitivity analysis using the TSUNAMI module of the SCALE 6.1.2 package [SCALE 2011]. TSUNAMI provides a quantitative measure of the degree of similarity between an experiment and an application by comparing the sensitivity of keff to changes in the underlying cross-section data. The degree of similarity is expressed in the correlation coefficient ck. Applicable benchmarks must have a correlation coefficient of ck 0.80.

Investigation of several benchmark series resulted in a total of 76 applicable benchmarks for the DN30-X. The determination of the calculational bias from these benchmarks, taking into ac-count the bias uncertainty, results in an USL for the DN30-X single package of 0.9419.

For the HAC array without water in-leakage and accordingly low moderation of the UF6 contents, applicability of benchmark experiments is determined via sensitivity studies with the USLSTATS method. The selected benchmark experiments mostly have neutron spectra in the intermediate to fast region. Only benchmark cases with energy of average lethargy causing fission (EALF) between 10 eV to 100000 eV are used for the USLSTATS analysis, to provide a reasonable sim-ilarity with the EALF values for the application cases (402 eV for the DN30-10 and 1929 eV for the DN30-20). Based on a total of 31 applicable benchmarks, an EALF fit with USLSTATS is used to derive an USL for the DN30-X HAC array of 0.9263.

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0045-BSH-2020-001 Rev. 2 2.6.4 Material Compositions 2.6.4.1 UF6 For the UF6 , a maximal density of 5.5 g/cm³ is assumed. This conservative assumption is derived from a linear extrapolation of tabulated UF6 density values to -40 °C and covers the density of 5.1 g/cm³ at room temperature by a large margin.

2.6.4.1.1 UF6 impurities In the proof for the single package, optimal moderation of the UF6 with water is assumed. Accord-ingly, the assumption of pure UF6 is covering and neither HF impurities nor hydrogenated uranium residues (HUR) need to be taken into account in the calculations.

In the proof for arrays of packages, the maximal amount of 0.5 wt.-% volatile impurities is taken into account. These are assumed as HF, using the standard material hfacid in SCALE. The 5.5 g/cm³ density of UF6 is used for the mixture of UF6 and HF.

In addition to these volatile impurities, the moderation from hydrogenated uranium residues is taken into account with conservative assumptions based on [MILIN 2016]: The enveloping com-position of HUR is UO2 F2 -2H2 O-2HF, and the mass of HUR is assumed to be equivalent to the maximal allowable heels mass of 11.3 kg. In the calculations, this compound is replaced by UO2 F2 -3H2 O with the same H/U ratio and a density of 4.317 g/cm³.

Geistiges Eigentum der Orano NCS GmbH 2.6.4.2 Carbon steel (30B-X cylinder and CCS)

For the carbon steel of the 30B-X cylinder and the CCS, the standard material carbonsteel of Property of Orano NCS GmbH the SCALE library with a density of 7.8212 g/cm3 is used.

2.6.4.3 Boron carbide (B4C)

The neutron absorber B4 C in the CCRs is taken into account with a density of 1.2 g/cm³. This is equivalent to 88.9% of the specified B4 C density of 1.35 g/cm³, and thus slightly below the maxi-mal 90% credit applied to solid homogeneous boron-based neutron absorbers (see section 7.4.7.2 of [NUREG 2216]).

2.6.4.4 Stainless steel (DN30 PSP)

For calculations where the stainless steel walls of the DN30 PSP are taken into account, the standard material ss304 of SCALE library with a density of 7.94 g/cm3 is used.

2.6.4.5 Water For the water used as a reflector and moderator in the proof for the single package, and as inter-stitial moderation in the proof for package arrays, a covering density of 1.0 g/cm³ is taken into account in the calculations.

2.6.4.6 UO2F2 For the single package, a comparison calculation is performed for the pessimistic assumption that UF6 mixed with water will completely transform into the compound UO2 F2. For this compound, the maximal theoretical density of 6.37 g/cm³ is taken into account.

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0045-BSH-2020-001 Rev. 2 2.6.5 Calculation Models Since the outer cylinder shell is identical for the DN30-10 and DN30-20, and the CCS only differs in the number and distribution of CCRs, the criticality calculation models for both versions of the DN30-X are mostly identical and will be presented here together.

Section 2.6.5.1 presents the calculation model of the 30B-X cylinder itself, including the CCS. The calculation model for the single package in isolation, taking into account unlimited water modera-tion of the UF6 content, is described in section 2.6.5.2. The calculation model for the infinite array of packages under HAC, where moderation is provided only by the HF and HUR impurities in the UF6 , is described in section 2.6.5.3.

2.6.5.1 30B-X cylinder For the outer parts (walls and skirts) of the 30B-X cylinder, the domed heads are modeled in an ellipsoidal shape. Both skirts are modeled straight and without any bends at their ends. The outer diameter is 76.8 cm, and the outer length is 207.5 cm over the skirts and 193.5 cm over the ends of the domed heads. Using maximal values for the diameter and the length is conservative, since it maximizes the amount of UF6 in general and, more importantly, in regions not directly adjacent to the CCRs.

Valve, plug, and nameplate of the cylinder are completely neglected. The domed head at the plug end is modeled in such a way that its outer surface is in line with the end of the skirt, i.e., moved Geistiges Eigentum der Orano NCS GmbH 1.3 cm outwards. This is conservative since it allows for smaller distances between the fissile contents in adjacent packages.

The wall thickness is assumed at its nominal value of 13 mm. An overview of the dimensions of the walls and skirts of the 30B-X cylinder in the calculation model is shown in Figure 2-14.

Property of Orano NCS GmbH 140 2075 13

Ø 768 Figure 2-14 Calculation model of the 30B-X cylinder calculation model (without CCS) 148 / 172

0045-BSH-2020-001 Rev. 2 For the CCS, the CCRs are modelled with their nominal dimensions (outer Ø 60.3 mm, wall thick-ness 5.5 mm, lengths see table 2-23) and positions. Manufacturing tolerances and CCS defor-mations under HAC are evaluated with variational calculations. The lattice holders and all other structural parts of the CCS are conservatively neglected.

The criticality calculation models for the 30B-10 and the 30B-20 are shown in Figure 2-15. The cross section along the cylinder axis shows the shortened CCRs in front of the valve and the plug.

Table 2-23 CCR numbers, ring diameters and lengths for the 30B-10 and the 30B-20 number of CCRs CCR ring ring radius CCR length 30B-10 30B-20 central CCR 0 cm 185 cm 1 1 1st ring 10 cm 183 cm 6 7 2nd ring 19 cm 178 cm 10 12 2nd ring1) 19 cm 172 cm 2 2 3rd ring 28 cm 170 cm 14 21 shortened CCRs in front of the valve / plug 30B-10 (33 CCRs) 30B-20 (43 CCRs)

Geistiges Eigentum der Orano NCS GmbH 1st ring 1st ring 6 CCRs 7 CCRs Property of Orano NCS GmbH 2nd ring 2nd ring 12 CCRs 14 CCRs 3rd ring 3rd ring 14 CCRs 21 CCRs cut along axis valve end 30B-10 cut along axis plug end shortened CCR (valve) shortened CCR (plug) steel UF6/water B4C filling Figure 2-15 Calculation models for the 30B-10 and 30B-20 cylinder 149 / 172

0045-BSH-2020-001 Rev. 2 2.6.5.2 Single package in isolation For the single package with unlimited water moderation of the UF6 content, the 30B-X cylinder is assumed to be completely filled with a mixture of UF6 and water. The point of optimal moderation is determined through variation of the water/UF6 ratio. The UF6 fill limit is not taken into account, so that there is an overestimation of the fissile content for low amounts of water moderator.

On the outside, the 30B cylinder is surrounded by 30 cm of water reflector on all sides. The basic calculation model for the single package in isolation is shown in Figure 2-16.

Additional calculations are performed with a simplified representation of the DN30 PSP to show that the assumption of a bare 30B-X cylinder is the covering case. In this simplified representation, only the steel walls of the PSP are taken into account and assumed to be compacted around the cylinder, with a total thickness of 5 mm in radial direction and 14 mm in axial direction. The foam insulation as well as the distance between inner and outer shell is completely neglected.

Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH steel (30B-X)

UF6/water B4C filling water reflector Figure 2-16 Calculation model for the single package in isolation 150 / 172

0045-BSH-2020-001 Rev. 2 2.6.5.3 Infinite array of packages For the array of packages under HAC, an infinite three-dimensional array is achieved by enclosing the DN30-X package in a hexagonal prism with mirror reflection on all surfaces. External water moderation is investigated by adding water layers with varying thickness between packages.

The total thickness of the DN30 PSP around the 30B-X cylinder is assumed to be reduced to 10 cm in radial direction (around the mantle) and 8 cm in axial direction (on the valve/plug ends),

conservatively covering all deformations due to HAC impacts. The foam material is neglected.

Moderation of the UF6 is provided by the maximum of 0.5 wt.-% volatile impurities (HF), and the additional assumption of 11.3 kg HUR. Since the valve and plug retain their function under HAC, the ingressing water due to the immersion under a head of 15 m water for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> only amounts to < 3 g and can be neglected.

The covering assumption for the distribution of these impurities in UF6 cylinders is given in

[MILIN 2016]: the HF is dispersed evenly within the UF6 , but the HUR is assumed to be concen-trated in a sphere. To maximize the reactivity, the well-moderated HUR spheres in adjacent pack-ages are brought closely together by placing them at the wall of the domed plug head (where the shorter skirt makes for a small distance to the next cylinder). Furthermore, the sphere is placed close to the CCR that is shortened at the plug end. The covering calculation model for a cylinder within the infinite package array is shown in Figure 2-17.

Additional calculations are performed for the assumption that the PSP is completely compacted Geistiges Eigentum der Orano NCS GmbH around the 30B-X cylinder, taking only the steel material of the inner and outer shell into account.

It should be noted that even with these pessimistic assumptions regarding UF6 impurities and the deformations of the DN30 PSP, the keff result for the infinite array is below the result for the opti-mally moderated single package.

Property of Orano NCS GmbH outer PSP shell steel (30B-X)

UF6 inner PSP shell B4C filling steel (PSP) shortened CCR HUR material (plug) detail of HUR sphere (UF6 neglected)

Figure 2-17 Calculation model for the infinite package array 151 / 172

0045-BSH-2020-001 Rev. 2 2.6.6 Proof of Criticality Safety for the Single Package in Isolation Safe subcriticality for the single package under all conditions of transport is proven according to

[10 CFR Part 71] §55 or [SSR-6 2018], para. 682.

The covering calculation models for the DN30-10 and the DN30-20 take into account optimal moderation of the UF6 contents with water, manufacturing tolerances and the deformations of the package under HAC. The most penalizing assumptions for these parameters are derived via var-iation calculations described in detail in chapter 7 of Appendix 2.6.

As described in section 2.6.1, the safety criterion is expressed as keff + 3 USL, and the USL value for the DN30-X single package in isolation is USL = 0.9419.

The results for the covering calculation model are:

keff + 3 = 0.8981 for the DN30-10 keff + 3 = 0.9060 for the DN30-20 For the covering calculation model, the criticality safety criterion is met with a large margin to the limit of safe subcriticality.

Geistiges Eigentum der Orano NCS GmbH Comparison calculations with the hypothetical assumption of heterogeneous UF6/water mixtures with the optimal size of the UF6 particles give maximal results of:

keff + 3 = 0.9108 for the DN30-10 Property of Orano NCS GmbH keff + 3 = 0.9122 for the DN30-20 Comparison calculations with the pessimistic assumption that the UF6 contents will completely transform into the compound UO2 F2 give maximal results of:

keff + 3 = 0.9321 for the DN30-10 keff + 3 = 0.9341 for the DN30-20 The results from these comparison calculations demonstrate that the criticality safety criterion is met even when taking into account additional pessimistic assumptions about the UF6 contents.

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0045-BSH-2020-001 Rev. 2 2.6.7 Proof of Criticality Safety for the Infinite Array of Packages The criticality safety proof for the array of packages under HAC according to [10 CFR Part 71]

§59(a)(2) or [SSR-6 2018], para. 685 is carried out for an infinite number of packages in an infinite quadratic and hexagonal lattice with axial infinite stacking.

Since calculation assumptions under HAC are more restrictive than assumptions for NCT, the proof for the package array under NCT according to [10 CFR Part 71] §59(a)(1) or [SSR-6 2018],

para. 684 is covered by the proof for the array of packages under HAC.

As described in section 2.6.1, the safety criterion is expressed as keff + 3 USL, and the USL value for the HAC array of packages is USL = 0.9263.

In addition to the most penalizing assumptions regarding manufacturing tolerances and the de-formations of the package under HAC, the covering calculation model for the package array takes into account internal moderation from UF6 impurities: 0.5 wt.-% volatile impurities (HF), and the additional assumption of 11.3 kg HUR. The HF is dispersed evenly within the UF6 , while the well-moderated HUR impurities are assumed to be concentrated in a sphere.

Optimum interspersed hydrogenous moderation is achieved with a water layer on the 30B-X cyl-inder with maximal water density. The optimal thickness of this water layer is derived from varia-tion calculations presented in chapter 8 of Appendix 2.6.

With these covering assumptions, the maximal results for the array of packages are:

Geistiges Eigentum der Orano NCS GmbH keff + 3 = 0.7130 for the DN30-10 keff + 3 = 0.8707 for the DN30-20 For the covering calculation model, the criticality safety criterion is met with a large margin to the Property of Orano NCS GmbH limit of safe subcriticality. Especially for the DN30-10, the results are lower than for the single package in isolation.

Comparison calculations with the additional extremely pessimistic assumption of the DN30 PSP being completely compacted around the 30B-X cylinder give maximal results of:

keff + 3 = 0.7654 for the DN30-10 keff + 3 = 0.9039 for the DN30-20 The results from these comparison calculations demonstrate that the criticality safety criterion is met even when taking into account additional extremely pessimistic assumptions about the de-formations of the DN30-X package under HAC.

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0045-BSH-2020-001 Rev. 2 2.6.8 Summary and Evaluation of Results The criticality safety for the DN30-10 package loaded with UF6 with a maximal enrichment of 235 10 wt.-% U in uranium and the DN30-20 package loaded with UF6 with a maximal enrichment 235 of 20 wt.-% U in uranium is proven in accordance with the requirements of [10 CFR Part 71]

§55 and §59 or [SSR-6 2018], para. 673 under all credible considerations, including pessimistic or hypothetical assumptions about the packaging and the UF6 contents:

1. Flooding with water is taken into account for the single package in isolation under all con-ditions of transport. There is no credit taken from [10 CFR Part 71] §55(g) or [SSR-6 2018]

para. 680(b)(i).

2. For the content the most reactive arrangement in the packaging is determined. Any credible rearrangement of contents and the inleaked water in the package is taken into account in the analyses.

3. Based on results of analyses and drop tests described in the mechanical analysis, no re-lease of contents from the package needs to be assumed.

4. Water around the package is considered in the analysis of an array of packages with vari-ation of the water layer thickness at maximal water density.

5. Temperature changes are taken into account by assuming a conservatively high density for UF6 and a theoretical maximal water density of 1 g/cm3.

6. For the 30B-X cylinder, the most penalizing assumptions about manufacturing tolerances and deformations under HAC are taken into account in the analysis.

Geistiges Eigentum der Orano NCS GmbH

7. The DN30 PSP is completely neglected in the criticality analysis for the single package and assumed to be compacted to a thickness of 10 cm in radial direction (around the mantle) and 8 cm in axial direction (on the valve/plug ends), conservatively covering all defor-mations due to HAC impacts.

Property of Orano NCS GmbH

8. The neutron absorber B4 C in the CCRs is taken into account with 88.9 % of its specified density. This is slightly below the maximal 90 % credit applicable to solid homogeneous boron-based neutron absorbers (see section 7.4.7.2 of [NUREG 2216]).

The analysis, described in detail in Appendix 2.6, covers the following arrangements:

• Single package under all conditions of transport

• Arrangement of an infinite number of packages under NCT

• Arrangement of an infinite number of packages under HAC.

The results of the analysis demonstrate that the criticality safety criterion is met with a large safety margin for the covering calculation models for the single package and the infinite array of pack-ages.

For the single package in isolation, the analysis is extended by comparison calculations with pes-simistic assumptions about the UF6 contents, i.e., heterogeneous UF6 /water mixtures and trans-formation into the denser compound UO2 F2.

For the infinite array of packages under HAC, the analysis is extended by comparison calculations for the hypothetical assumption of a completely compacted DN30 PSP. The results of these com-parison calculations demonstrate safe subcriticality even with these additional pessimistic as-sumptions.

For both the DN30-10 and the DN30-20 package, the calculated keff -values are in all cases lower than the value defined as objective of proof in section 2.6.1. The criticality safety requirements for the transport of a package for fissile material according to

[10 CFR Part 71] §55 and §59 or [SSR-6 2018], para. 673 are fulfilled.

154 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.1 (List of Applicable Documents)

Applicable Documents List 0045-LST-2021-001 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 155 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.4.1A (Drawings 30B-X Cylinder)

1) 30B-10 Cylinder, Parts List 0045-STL-1000-000

2) 30B-20 Cylinder, Parts List 0045-STL-2000-000 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 156 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.4.1B (Drawings DN30 PSP)

Parts List 0023-STL-1000-000 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 157 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.4.2 (Material Properties)

Material Properties of the Components of the DN30-X Packaging, 0045-BSH-2020-001-Appendix-1.4.2 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 158 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.7.1 (Handling Instruction)

Use and handling of the DN30-X package, Handling Instruction 0045-HA-2021-001 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 159 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.7.2 (Contamination and Dose Rate Measurements)

Contamination and dose rate measurement at the DN30-X package, Test Instruction 0045-PA-2021-002 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 160 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.7.3 (30B-X Cylinder Facility Operations)

Facility operations with the 30B-X Cylinder, 0045-BSH-2020-001-Appendix-1.7.3, Rev. 0 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 161 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.8.1 (Inspections of 30B-X Cylinders)

Periodic Inspections of the 30B-X Cylinder, Test Instruction 0045-PA-2021-001 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 162 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.8.2 (Inspections of DN30 PSPs)

Periodic Inspections of the DN30 PSP, Test Instruction 0023-PA-2015-015 Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 163 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.9.1 (IMS)

1) Quality Management Handbook of company Orano NCS GmbH, 2022

2) DIN EN ISO 9001

3) Confirmation on quality assurance according to nuclear standard KTA 1401

4) Confirmation of the Qualification for the development, manufacturing and operation of packagings of packages requiring approval for the transport of radioactive material Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 164 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.9.2A (Manufacturing Specification 30B-X Cylinder)

Specification 30B-X cylinder, Specification 0045-SPZ-2021-001 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 165 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.9.2B (Manufacturing Specification DN30 PSP)

Specification DN30 PSP, Specification 0023-SPZ-2016-001 Manufacturing Test Sequence Plan 0023-BPP-2016-001 Material Test Sheet 0023-WPB-2016-001 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 166 / 172

0045-BSH-2020-001 Rev. 2 Appendix 1.9.3 (Quality Assurance Program)

1) U.S. NRC Quality Assurance Program Approval #0951, Rev. 1, July 6, 2018

2) Quality Assurance Program 0023-QAP-2017-001 Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 167 / 172

0045-BSH-2020-001 Rev. 2 Appendix 2.2 (Structural Analysis)

Structural Analysis of the DN30-X Package Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 168 / 172

0045-BSH-2020-001 Rev. 2 Appendix 2.3 (Thermal Analysis)

Thermal Analysis of the DN30-X Package Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 169 / 172

0045-BSH-2020-001 Rev. 2 Appendix 2.4 (Containment Analysis)

Containment Analysis of the DN30-X Package Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 170 / 172

0045-BSH-2020-001 Rev. 2 Appendix 2.5 (External Dose Rate Analysis)

External Dose Rate Analysis of the DN30-X Package Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 171 / 172

0045-BSH-2020-001 Rev. 2 Appendix 2.6 (Criticality Safety Analysis) 235 Criticality Analysis for the DN30-X Package with 10 wt.-% or 20 wt.-% U enrichment Proprietary Information Not to be published Geistiges Eigentum der Orano NCS GmbH Property of Orano NCS GmbH 172 / 172