ML23066A250
| ML23066A250 | |
| Person / Time | |
|---|---|
| Site: | 07109400 |
| Issue date: | 02/28/2023 |
| From: | NAC International |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML23066A248 | List: |
| References | |
| ED20230023 | |
| Download: ML23066A250 (1) | |
Text
February 2023 Revision 23A PALADIN Package (PAckage for LArge DImensional coNtents)
SAFETY ANALYSIS REPORT BPMI Initial Application NON-PROPRIETARY VERSION Docket No. 71-9400 Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com to ED20230023 Page 1 of 2 Enclosure 1 Supporting Calculations PALADIN Package SAR, Revision 23A Initial Application February 2023 to ED20230023 Page 2 of 2 Contents
50059-2001 R1
50059-2005 R1
50059-2006 R1
50059-2020 R1
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to ED20230023 Page 1 of 1 Enclosure 2 LOEP and SAR Pages PALADIN Package SAR, Revision 23A Initial Application February 2023
February 2023 Revision 23A PALADIN Package (PAckage for LArge DImensional coNtents)
SAFETY ANALYSIS REPORT NON-PROPRIETARY VERSION Docket No. 71-9400 Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Peachtree Corners, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Effective Pages Chapter 1 Chapter 5 Page 1-i thru 1-ii ............... Revision 23A Page 5-i thru 5-iii .............. Revision 23A Page 1-1 ............................ Revision 23A Page 5-1 ............................ Revision 23A Page 1.1-1 thru 1.1-2......... Revision 23A Page 5.1-1 thru 5.1-2......... Revision 23A Page 1.2-1 thru 1.2-10....... Revision 23A Page 5.2-1 thru 5.2-2......... Revision 23A Page 1.3-1 thru 1.3-3......... Revision 23A Page 5.3-1 thru 5.3-5......... Revision 23A Page 5.4-1 thru 5.4-8......... Revision 23A 6 drawings (see Section 1.3) Page 5.5-1 ......................... Revision 23A Chapter 2 Chapter 6 Page 2-i thru 2-iv .............. Revision 23A Page 6-i ............................. Revision 23A Page 2-1 ............................ Revision 23A Page 6-1 ............................ Revision 23A Page 2.1-1 thru 2.1-18....... Revision 23A Page 2.2-1 thru 2.2-7......... Revision 23A Chapter 7 Page 2.3-1 thru 2.3-4......... Revision 23A Page 7-i ............................. Revision 23A Page 2.4-1 thru 2.4-2......... Revision 23A Page 7-1 ............................ Revision 23A Page 2.5-1 thru 2.5-4......... Revision 23A Page 7.1-1 thru 7.1-6......... Revision 23A Page 2.6-1 thru 2.6-17....... Revision 23A Page 7.2-1 thru 7.2-2......... Revision 23A Page 2.7-1 thru 2.7-33....... Revision 23A Page 7.3-1 thru 7.3-3......... Revision 23A Page 2.8-1 ......................... Revision 23A Page 7.4-1 ......................... Revision 23A Page 2.9-1 ......................... Revision 23A Page 7.5-1 ......................... Revision 23A Page 2.10-1 ....................... Revision 23A Page 2.11-1 ....................... Revision 23A Chapter 8 Page 2.12-1 thru 2.12-3..... Revision 23A Page 8-i thru 8-ii ............... Revision 23A Page 8-1 ............................ Revision 23A Chapter 3 Page 8.1-1 thru 8.1-3......... Revision 23A Page 3-i thru 3-iii .............. Revision 23A Page 8.2-1 thru 8.2-7......... Revision 23A Page 3-1 ............................ Revision 23A Page 8.3-1 ......................... Revision 21A Page 3.1-1 thru 3.1-5......... Revision 23A Page 3.2-1 thru 3.2-3......... Revision 23A Page 3.3-1 thru 3.3-7......... Revision 23A Page 3.4-1 thru 3.4-10....... Revision 23A Page 3.5-1 ......................... Revision 23A Chapter 4 Page 4-i thru 4-ii ............... Revision 23A Page 4-1 ............................ Revision 23A Page 4.1-1 thru 4.1-3......... Revision 23A Page 4.2-1 ......................... Revision 23A Page 4.3-1 ......................... Revision 23A Page 4.4-1 ......................... Revision 23A Page 4.5-1 ......................... Revision 23A Page 1 of 1
This page intentionally left blank PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 1 General Information Table of Contents 1 GENERAL INFORMATION .......................................................................................... 1-2 1.1 Introduction ................................................................................................................... 1.1-1 1.2 Package Description...................................................................................................... 1.2-1 1.2.1 Packaging .......................................................................................................... 1.2-1 1.2.2 Radioactive Contents ........................................................................................ 1.2-
1.2.3 Special Requirements for Plutonium ................................................................ 1.2-
1.2.4 Operational Features ......................................................................................... 1.2-
1.3 Appendix ....................................................................................................................... 1.3-1 1.3.1 References ......................................................................................................... 1.3-1 1.3.2 Glossary of Terms and Acronyms .................................................................... 1.3-2 1.3.3 Packaging General Arrangement Drawings...................................................... 1.3-3 NAC International 1-i
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Figures Figure 1-1 PALADIN Packaging.............................................................................................. 1.1-2
Figure 1-2 PALADIN Package Transport Configuration Concept........................................... 1.2-
Figure 1-3 PALADIN Impact Limiter System & Internal Support Components ..................... 1.2-
Figure 1-4 PALADIN Packaging Containment System ......................................................... 1.2-
NAC International 1-ii
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1 GENERAL INFORMATION This chapter of the Safety Analysis Report (SAR) presents a general introduction to, and description of the PAckage for LArge DImensional coNtents (PALADIN) transport package. A schematic of the packaging is shown in Figure 1-1. Descriptions of the packaging (including the packaging features), contents, and operational features, are presented in Section 1.2. A glossary of the general terminology and acronyms used throughout this SAR is presented in Appendix 1.3.2. The packaging General Arrangement Drawings are included in Appendix 1.3.3.
As demonstrated by this SAR, the PALADIN package satisfies the regulatory requirements of the United States Nuclear Regulatory Commission (NRC) regulations, namely Title 10, Part 71 of the Code of Federal Regulations (10 CFR 71).
NAC International 1-1
This page intentionally left blank.
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.1 Introduction The PALADIN transport system is designed as a Type B(U)F per 10 CFR 71.4 [1.8] and Category III container per Regulatory Guide 7.11 [1.7]. In more detail, Type B(U)F packaging refers to fissile material packaging together with its fissile material contents that requires unilateral approval of international shipments. Whereas a Category III container specifies that contents have less than 30,000 Ci as well as 30 A2 and A1 quantities of both special and normal form radioactive material. However, for the purpose of this SAR, the packages currently authorized radioactive contents consist of an irradiated Reactor Vessel, containing residual water and absorbent materials with limited quantities of Transuranic (TRU) and fissile waste, such that they do not exceed Type A quantities. The package is designed to be transported by rail, sea, and highway via railcar, barge, and heavy-haul vehicle, respectively, under exclusive-use controls. The Maximum Normal Operating Pressure (MNOP) of the package is with a vessel design pressure of used for structural evaluation and fabrication testing.
The packaging, described in greater detail in Section 1.2.1, consists of two (2) main components; a Containment Vessel (CV) and an Impact Limiter System (ILS), as shown in Figure 1-1. The CV is a stainless-steel vessel with a bolted closure designed to the leak-tight containment criterion in accordance with ANSI N14.5-2014 [1.1]. Additionally, the CV provides shielding, structural, and thermal protection to the contents. The ILS consists of both permanently installed and removable components designed to reduce the direct impact loading and protect the package containment boundary from the effects of the Normal Conditions of Transport (NCT) free drops and Hypothetical Accident Conditions (HAC) free drops.
This SAR demonstrates the packaging meets the applicable requirements of 10 CFR 71 [1.8].
The basis for qualification is the safety analysis contained herein.
NAC International 1.1-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 1-1 PALADIN Packaging NAC International 1.1-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.2 Package Description 1.2.1 Packaging The PALADIN Type B packaging consists of the CV equipped with the ILS. A view of the assembled packaging is shown in Figure 1-1. In accordance with 10 CFR 71.43(d), the package is made of materials and construction that assure that there will be no significant chemical, galvanic, or other reaction among the packaging components, among package contents, or between the packaging components and the package contents, including possible reaction resulting from inleakage of water, to the maximum credible extent, taking into account the behavior of materials under irradiation.
The CV is the packaging containment system. It is a stainless steel cylindrical vessel comprised of a body weldment, bolted lid, bolted port cover, and O-ring seals. The CV has a maximum outer diameter (OD) of (top end) and an overall length of The CV cavity is with a stepped diameter that transitions from inner diameter (ID) at the top end to inner diameter at the bottom end.
The CV body weldment is comprised of upper and lower shells, a transition ring, a bottom plate, and a upper flange, all of which perform a containment function. Non-containment features of the CV body weldment include a shear ring welded to the OD of the lower shell (used for tie-down); two (2) diametrically opposed trunnion pockets welded to the OD of lower shell (used for down/up-ending and tie-down); standoffs welded to the ID of the lower shell (center the contents in the cavity and provide support under lateral loading); an outer impact band wrapped around the OD of the upper shell and retained with welded retaining bands (provides protection to the upper shell under lateral loading); a mounting ring welded to the OD of the lower shell just below the transition ring (used to attach transition impact limiter sectors); an inner impact band welded to the ID of the upper shell (provides internal support and protection to the upper shell under lateral loading).
The CV lid is and is secured to the CV bodys upper flange by because their use allows for a pre-
-3 3 shipment leakage test to a test sensitivity of 1x10 ref-cm /sec versus the full leaktight test to leakage rate of 1x10-7 ref-cm3/sec. A test sensitivity of 1x10-3 ref cm3/sec allows the use of a pressure rise/fall test that can be performed with air in the package cavity versus helium mass NAC International 1.2-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A spectrometer type equipment required for the leaktight test (note that package cavity during operations will be air, not helium, filled).
Additionally, the CV includes internal features to provide protection of the containment boundary from the contents in critical areas during NCT and HAC drops. The standoffs welded to the ID of the lower shell, reinforce the lower shell and provide support under lateral loading. Similarly, the inner impact band provides support and protection to the CV bodys upper shell in the region where the reactor vessels head/shell flange impacts the inside of the CV under lateral loading conditions. Bolted reinforcement plates at the top and bottom of the CV cavity are also included to protect the containment boundary from the contents. A bottom reinforcement plate is bolted into a machined recess in the CV bodys bottom plate and reinforcement ring is bolted into a machined recess in the bottom side of the CV lid. These reinforcement plates provide protection to the containment boundary in specific areas of contact with the contents by distributing otherwise high localized bearing loads present due to design features of the contents (e.g. the reactor vessels hemispherical head/bottom and closure studs/nuts).
The following sections discuss the overall dimensions and weight of the package, the containment, shielding, criticality control, structural, and heat transfer features of the packaging, as well as the packaging marking and coolants.
NAC International 1.2-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.2.1.1 Overall Dimensions The PALADIN packagingin its shipping configurationhas an outer diameter of and an overall length of which are both greater than the minimum package dimension of 10 cm required by 10 CFR 71.43(a).
1.2.1.2 Package Weight The gross weight of the package, including the maximum CV content and ILS, is approximately pounds. A more detailed breakdown of the package weight, including major individual packaging subassemblies and contents, is provided in Table 2.1-5.
1.2.1.3 Maximum Normal Operating Pressure (MNOP)
The Maximum Normal Operating Pressure (MNOP), as defined in 10 CFR 71.4, of the package is Note, the design pressure of the CV is as discussed in Chapter 2.
1.2.1.4 Structural Features The structural features of the packaging are summarized in this section. A more detailed discussion of the packaging structural features is provided in Chapter 2.
Lifting and Tie-Down Devices The CV is equipped with a shear ring, two (2) diametrically opposed trunnion pockets, and threaded lifting attachment points in the center of the lid. The lifting attachment points in the lid facilitate the bolted attachment of a lift adapter plate for lifting and handling of the package. The trunnion pockets serve as pivot points for down/up-ending the CV onto the intermodal skid. Once the CV is down-ended onto the intermodal transportation skid and secured for transport, the trunnion pockets and shear ring function as tie-down devices as shown in Figure 1-2.
Energy-Absorbing Features NAC International 1.2-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Internal Supports or Positioning Features As previously discussed, the standoffs welded to the ID of the lower shell aid in positioning of the contents and reinforce the lower shell and provide support under lateral loading (side drops). The inner impact band provides support and protection to the CV bodys upper shell in the region where the reactor vessels head/shell flange contacts the inside of the CV under lateral loading conditions. Bolted reinforcement plates at the top and bottom of the CV cavity are also included to protect the containment boundary from the contents in areas of contact with the contents. These features are shown in Figures 1-1 and 1-3.
Containment Vessel (CV)
The CV is the packaging containment system that consists of a stainless-steel cylindrical vessel with a body weldment (including a shear ring, impact bands, and retaining bands), bolted lid, and two (2) diametrically opposed trunnion pockets. The CV has an outer diameter of (top end), an overall length of The lower region of the CV cavity is equipped with standoffs that center the contents in the cavity and support the contents under lateral loading (e.g., side drop load).
Packaging Closure Devices The packaging closure devices include the bolted CV lid, the lids inner seal, the bolted port cover, and the port covers inner seal to ensure a leak tight containment of radioactive material.
The primary safety function of the CV lid, port cover, and their inner seals is containment.
NAC International 1.2-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 1-2 PALADIN Package Transport Configuration Concept NAC International 1.2-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 1-3 PALADIN Impact Limiter System & Internal Support Components NAC International 1.2-6
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.2.1.5 Secondary Packaging Components Not applicable.
1.2.1.6 Tamper-Indicating Features The PALADIN packaging has security seals and safety wire that are attached to the upper impact limiter bolts, as shown on the general arrangement drawing, 50059-L001 in Appendix 1.3.3, to meet the requirement for tamper-indicating features as specified in 10 CFR 71.43(b). See Section 2.4.2 for more details.
1.2.1.7 Packaging Markings The packaging marking is included on a nameplate that is permanently affixed to the exposed exterior surface of the CV body, as shown on general arrangement drawing 50059-L002 in Appendix 1.3.3. At a minimum, the nameplate includes the package model number, serial number, gross weight, trefoil symbol, and package type.
1.2.1.8 Codes and Standards The codes and standards used for the packaging design, material specifications, fabrication, welding, and inspection are described throughout the SAR and summarized in this section. As detailed in Section 2.1.4, the package is designed, fabricated, tested, and maintained in accordance with codes and standards that are appropriate for transportation packages with special form and normal form radioactive material less than 30 A2 and less than 30,000 Ci.
Accordingly, the codes and standards used are based on Regulatory Guide 7.6 [1.2],
NUREG/CR-3854 [1.3], and Regulatory Guide 7.11 [1.7].
The package containment system is designed in accordance with the applicable requirements of the ASME Code,Section III, Division 1, Subsection NB [1.4]. The non-containment structural components of the packaging are designed in accordance with the applicable allowable stress design criteria for plate- and shell-type Class 2 supports from the ASME Code,Section III, Division 1, Subsection NF [1.5]. Further discussion of the codes and standards used for the structural design of the packaging is provided in Section 2.1.4. Discussion of the codes and standards used for the fabrication, welding, and examination of the packaging is provided in Section 2.3.
1.2.1.9 Heat Transfer Features This package does not rely upon any active cooling systems. Furthermore, the contents of the CV do not contain enough thermal loading for there to be a need for any specialized heat transfer NAC International 1.2-7
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A features. The primary driver for system temperatures under NCT is ambient temperature and solar energy. The packages significant thermal mass and negligible thermal loading from the contents is sufficient to ensure system temperatures remain within acceptable limits during the HAC fire. A more detailed discussion of the packagings thermal design and performance is provided in Chapter 3.
1.2.1.10 Containment Features The packaging has a simple, robust containment system design. Containment of radioactive material for the packaging is provided by the CV. Other than the CVs bolted lid and port cover, there are no penetrations to the containment system, and no valves or pressure relief devices of any kind. The packaging does not rely on any filter or mechanical cooling system to meet containment requirements, nor does it include vents or valves that allow for continuous venting.
Additionally, in accordance with the requirement of 10 CFR 71.43I, the package includes a containment system securely closed by a positive fastening device that cannot be opened unintentionally or by a pressure that may arise within the package.
The CV is comprised of a body weldment and bolted closure lid. The containment boundary is comprised of a solid stainless steel CV body weldment including the upper flange, upper shell, transition ring, lower shell, and bottom plate; a solid stainless steel CV lid (bolted to the CV bodys upper flange); the CV lids inner O-ring seal; a solid stainless steel CV port cover (bolted to a port recess in the CV Lid); and the port covers inner O-ring seal. A sketch of the CV is included in Figure 1-4, with the pressure-retaining boundary outlined in red. Furthermore, the CV containment boundary is designed, fabricated, examined, tested, and inspected in accordance with the applicable requirements of the ANSI N14.5 [1.1] and ASME Code with exceptions discussed in Chapter 2 and 4, as appropriate. A detailed description of the containment system is provided in Section 4.1.
1.2.1.11 Neutron and Gamma Shielding Features Shielding features are described in more detail in Chapter 5 of this SAR. The PALADIN package is designed for exclusive-use controls and meets the shielding requirement of 10 CFR 71.
Neutron shielding is not necessary for the specified radioactive contents as there is no significant neutron source.
1.2.1.12 Criticality Control Features Criticality control features are not employed in the CV because the specified radioactive contents comply with the fissile material exemption requirements of 10 CFR 71.15.
NAC International 1.2-8
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.2.2 Radioactive Contents PALADIN transportation system is intended to transport a used reactor vessel (i.e., non-fuel),
where the TRU and fissile wastes do not exceed Type A quantities. The PALADIN packages will be transported to a waste disposal facility. Additionally, 99+% of the source activity is from Co-60, F-55, and Ni-63 where 99.9% of the gamma source (MeV/sec) occurs in the energy bins associated with Co-60 decay. The radioactive content is modeled as of Co-60 for shielding, with a total heat load of 1.2.2.1 Waste The acceptable radioactive contents is an irradiated reactor vessel (in the form of neutron activated metals with solid metal oxides). In addition to the reactor vessel, some residual water and absorbent material are present. As previously stated, the quantities of TRU waste and fissile material do not exceed Type A quantities. PALADIN is limited to transporting one reactor vessel at a time.
1.2.2.2 Irradiated Fuel Waste Not applicable.
1.2.3 Special Requirements for Plutonium Not applicable.
1.2.4 Operational Features The packaging has no special or complex operational features. Chapter 7 describes the features and steps associated with operating the package.
NAC International 1.2-9
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 1-4 PALADIN Packaging Containment System NAC International 1.2-10
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.3 Appendix 1.3.1 References
[1.1] ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014.
[1.2] Regulatory Guide 7.6, Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels, Revision 1, March 1978.
[1.3] Fischer, L. E., and Lai, W., Fabrication Criteria for Shipping Containers, NUREG/CR-3854, UCRL-53544, U.S. Nuclear Regulatory Commission, March 1985.
[1.4] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NB, Class 1 Components, 2010 Edition with 2011 Addenda.
[1.5] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NF, Supports, 2010 Edition with 2011 Addenda.
[1.6] NUREG/CR-5502, Engineering Drawings for 10 CFR Part 71 Package Approvals, U.S.
Nuclear Regulatory Commission, May 1998.
[1.7] Regulatory Guide 7.11, Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels With a Maximum Wall Thickness of 4 Inches (0.1 m),
Revision 0, June 1991.
[1.8] 10 CFR 71, Code of Federal Regulations Title 10, Part 71-Packaging and Transportation of Radioactive Material, U.S. Nuclear Regulatory Commission, 2019.
NAC International 1.3-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.3.2 Glossary of Terms and Acronyms AAR Association of American Railroads ALARA As Low As Reasonably Achievable ANSI American National Standards Institute ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials B&PVC Boiler and Pressure Vessel Code CFR Code of Federal Regulations CV Containment Vessel DOT United States Department of Transportation HAC Hypothetical Accident Conditions IAEA International Atomic Energy Agency ID Inner Diameter ILS Impact Limiter System MNOP Maximum Normal Operating Pressure NCT Normal Conditions of Transport NRC United States Nuclear Regulatory Commission OD Outer Diameter PALADIN PAckage for LArge DImensional coNtents Package The packaging with its radioactive contents (payload), as presented for transportation. Within this report, the package is denoted as the PALADIN package.
Packaging The assembly of components necessary to ensure compliance with packaging requirements (i.e., the package minus its contents). Within this report, the Packaging is denoted as the PALADIN packaging, or simply as the packaging.
pcf pounds per cubic foot SAR Safety Analysis Report TRU Transuranic waste NAC International 1.3-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 1.3.3 Packaging General Arrangement Drawings The following drawings show the general arrangement and design features of the PALADIN packaging in accordance with NUREG/CR-5502 [1.6]. The drawings refer to material specifications, welding requirements, inspection and test requirements, and dimensions as necessary to support the safety analyses.
Drawing No. Title Rev.
50059-L001 CV SHIPPING CONFIGURATION, PALADIN 01P 50059-L002 CONTAINMENT VESSEL (CV) ASSEMBLY, PALADIN 01P 50059-L003 BODY WELDMENT, CV, PALADIN 01P 50059-L004 LID ASSEMBLY, CV, PALADIN 01P 50059-L005 UPPER IMPACT LIMITER, CV, PALADIN 01P 50059-L006 LOWER IMPACT LIMITER, CV, PALADIN 01P NAC International 1.3-3
THIS PAGE INTENTIONALLY LEFT BLANK 0NP INITIAL ISSUE DRAWING TYPE NEXT ASSEMBLY ALL DIMENSIONS ARE IN INCHES.
DIMENSIONING AND TOLERANCING SHALL BE PER ASME GROUP NAME DATE Y14.5M-94.
ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.
MACHINED SURFACES TO BE OR BETTER CV SHIPPING CONFIGURATION, PALADIN 0NP N. T. S. N/A 1 1 1/18/2023
0NP INITIAL ISSUE DRAWING TYPE NEXT ASSEMBLY ALL DIMENSIONS ARE IN INCHES.
DIMENSIONING AND TOLERANCING SHALL BE PER ASME GROUP NAME DATE Y14.5M-94.
ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.
MACHINED SURFACES TO BE OR BETTER CONTAINMENT VESSEL (CV)
ASSEMBLY, PALADIN 0NP N. T. S. N/A 1 1 1/18/2023
0NP INITIAL ISSUE DRAWING TYPE NEXT ASSEMBLY ALL DIMENSIONS ARE IN INCHES.
DIMENSIONING AND TOLERANCING SHALL BE PER ASME GROUP NAME DATE Y14.5M-94.
ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.
MACHINED SURFACES TO BE OR BETTER BODY WELDMENT, CV, PALADIN 0NP N. T. S. N/A 1 1 1/18/2023
0NP INITIAL ISSUE DRAWING TYPE NEXT ASSEMBLY ALL DIMENSIONS ARE IN INCHES.
DIMENSIONING AND TOLERANCING SHALL BE PER ASME GROUP NAME DATE Y14.5M-94.
ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.
MACHINED SURFACES TO BE OR BETTER LID ASSEMBLY, CV, PALADIN 0NP N. T. S. N/A 1 1 1/18/2023
0NP INITIAL ISSUE DRAWING TYPE NEXT ASSEMBLY ALL DIMENSIONS ARE IN INCHES.
DIMENSIONING AND TOLERANCING SHALL BE PER ASME GROUP NAME DATE Y14.5M-94.
ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.
MACHINED SURFACES TO BE OR BETTER UPPER IMPACT LIMITER, CV, PALADIN 0NP N. T. S. N/A 1 1 1/18/2023
0NP INITIAL ISSUE DRAWING TYPE NEXT ASSEMBLY ALL DIMENSIONS ARE IN INCHES.
DIMENSIONING AND TOLERANCING SHALL BE PER ASME GROUP NAME DATE Y14.5M-94.
ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.
MACHINED SURFACES TO BE OR BETTER LOWER IMPACT LIMITER, CV, PALADIN 0NP N. T. S. N/A 1 1 1/18/2023
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 2 Structural Evaluation Table of Contents 2 STRUCTURAL EVALUATION .................................................................................... 2-1 2.1 Description of Structural Design .................................................................................. 2.1-1 2.1.1 Discussion ......................................................................................................... 2.1-1 2.1.2 Design Criteria .................................................................................................. 2.1-2 2.1.3 Weights and Centers of Gravity...................................................................... 2.1-10 2.1.4 Identification of Codes and Standards for Packaging ..................................... 2.1-10 2.2 Materials ....................................................................................................................... 2.2-1 2.2.1 Material Properties and Specifications ............................................................. 2.2-1 2.2.2 Chemical, Galvanic or Other Reactions............................................................ 2.2-1 2.2.3 Effects of Radiation on Materials ..................................................................... 2.2-2 2.3 Fabrication and Examination ........................................................................................ 2.3-1 2.3.1 Fabrication ........................................................................................................ 2.3-1 2.3.2 Examination ...................................................................................................... 2.3-2 2.4 General Requirements for All Packages ....................................................................... 2.4-1 2.4.1 Minimum Package Size .................................................................................... 2.4-1 2.4.2 Tamper-Indicating Feature................................................................................ 2.4-1 2.4.3 Positive Closure ................................................................................................ 2.4-1 2.5 Lifting and Tie-Down Standards for All Packages ....................................................... 2.5-1 2.5.1 Lifting Devices.................................................................................................. 2.5-1 2.5.2 Tie-Down Devices ............................................................................................ 2.5-2 2.6 Normal Conditions of Transport ................................................................................... 2.6-1 2.6.1 Heat ................................................................................................................... 2.6-1 2.6.2 Cold ................................................................................................................... 2.6-2 2.6.3 Reduced External Pressure ............................................................................... 2.6-3 2.6.4 Increased External Pressure .............................................................................. 2.6-8 2.6.5 Vibration ........................................................................................................... 2.6-8 2.6.6 Water Spray ...................................................................................................... 2.6-9 2.6.7 Free Drop .......................................................................................................... 2.6-9 2.6.8 Corner Drop .................................................................................................... 2.6-17 2.6.9 Compression ................................................................................................... 2.6-17 2.6.10 Penetration ...................................................................................................... 2.6-17 2.7 Hypothetical Accident Conditions ................................................................................ 2.7-1 2.7.1 Free Drop .......................................................................................................... 2.7-1 2.7.2 Crush ............................................................................................................... 2.7-20 2.7.3 Puncture .......................................................................................................... 2.7-20 2.7.4 Thermal ........................................................................................................... 2.7-27 2.7.5 Immersion - Fissile Material .......................................................................... 2.7-31 2.7.6 Immersion - All Packages .............................................................................. 2.7-31 NAC International 2-i
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table of Contents (continued) 2.7.7 Deep-Water Immersion Test (for Type B Packages Containing more than 105 A2) ..................................................................................................... 2.7-31 2.8 Accident Conditions for Air Transport of Plutonium ................................................... 2.8-1 2.9 Accident Conditions for Fissile Material Packages for Air Transport ......................... 2.9-1 2.10 Special Form ............................................................................................................... 2.10-1 2.11 Fuel Rods .................................................................................................................... 2.11-1 2.12 Appendix .................................................................................................................... 2.12-1 2.12.1 References ....................................................................................................... 2.12-1 NAC International 2-ii
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Figures Figure 2.6-1 Axisymmetric Finite Element Model for the Containment Vessel (CV) ......... 2.6-6 Figure 2.6-2 Section Locations for Stress Evaluation of the CV .......................................... 2.6-7 Figure 2.6-3 Finite Element Model for 1-Foot Side Drop Evaluation ................................ 2.6-14 Figure 2.6-4 Finite Element Model for 1-Ft Side Drop - Isometric View .......................... 2.6-15 Figure 2.6-5 Finite Element Model for 1-Ft Side Drop - Impact Limiters ......................... 2.6-16 Figure 2.7-1 Finite Element Model for HAC Free Drop Evaluations ................................... 2.7-5 Figure 2.7-2 Finite Element Model for HAC Free Drops - Isometric View ......................... 2.7-6 Figure 2.7-3 Finite Element Model for HAC Free Drops - Impact Limiters ........................ 2.7-7 Figure 2.7-4 HAC End Drop Cases ..................................................................................... 2.7-10 Figure 2.7-5 HAC Side Drop Case ...................................................................................... 2.7-13 Figure 2.7-6 HAC Corner Drop Cases ................................................................................ 2.7-16 Figure 2.7-7 HAC Side Impact Puncture ............................................................................. 2.7-25 Figure 2.7-8 HAC End Impact Punctures ............................................................................ 2.7-26 NAC International 2-iii
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Tables Table 2.1-1 Load Combinations for Normal Conditions of Transport............................... 2.1-14 Table 2.1-2 Load Combinations for Hypothetical Accident Conditions............................ 2.1-15 Table 2.1-3 Containment System Allowable Stress Design Criteria ................................. 2.1-16 Table 2.1-4 Non-Containment Component Allowable Stress Design Criteria .................. 2.1-16 Table 2.1-5 Package Weight and Center of Gravity Summary .......................................... 2.1-17 Table 2.1-6 Alternatives to ASME Code Requirements .................................................... 2.1-18 Table 2.2-1 Packaging Structural Material Specifications ................................................... 2.2-4 Table 2.2-2 Mechanical Properties of Type 304 and Type F304 Stainless Steels ............... 2.2-5 Table 2.2-3 Mechanical Properties of ............................... 2.2-5 Table 2.2-4 Mechanical Properties of SA193, Steel Bolting................................................................................................ 2.2-5 Table 2.2-5 Mechanical Properties of the Limiter Material .......................................................................................... 2.2-6 Table 2.2-6 Mechanical Properties of A276, Type 304 Stainless Steel ............................... 2.2-7 Table 2.2-7 Mechanical Properties of Stainless Steel ............................................................................................. 2.2-7 Table 2.6-1 CV Stress Summary for Reduced External Pressure ........................................ 2.6-5 Table 2.6-2 CV Stress Summary for 1-Ft Side Drop ......................................................... 2.6-13 Table 2.7-1 CV Strain Summary for HAC End Drops......................................................... 2.7-9 Table 2.7-2 CV Strain Summary for HAC Side Drop ....................................................... 2.7-12 Table 2.7-3 CV Strain Summary for HAC Corner Drops .................................................. 2.7-15 Table 2.7-4 Lid Closure Bolt Evaluation Summary for HAC End Drops and Corner Drops ......................................................................................................... 2.7-19 Table 2.7-5 Lid Closure Bolt Evaluation Summary for HAC Side Drop .......................... 2.7-19 Table 2.7-6 CV Strain Summary for Side Puncture Impact ............................................... 2.7-22 Table 2.7-7 Lid Closure Bolt Evaluation Summary for Side Puncture Impact .................. 2.7-22 Table 2.7-8 CV Strain Summary for End Puncture Impact ............................................... 2.7-23 Table 2.7-9 Lid Closure Bolt Evaluation Summary for End Puncture Impact .................. 2.7-24 Table 2.7-10 CV Stress Summary for HAC Pressure (Fire Accident) ................................. 2.7-30 Table 2.7-11 CV Stress Summary for Deep Water Immersion ............................................ 2.7-33 NAC International 2-iv
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2 STRUCTURAL EVALUATION The structural evaluation of the PALADIN packaging demonstrates compliance with the applicable performance requirements of 10 CFR 71. Compliance with the applicable general requirements of 10 CFR 71.43(a), (b), and (c) is demonstrated in Section 2.4. Compliance with the lifting and tie-down standards of 10 CFR 71.45(a) and (b) is demonstrated in Section 2.5.
The structural evaluation for NCT tests (10 CFR 71.71) and HAC tests (10 CFR 71.73) presented in Sections 2.6 and 2.7, respectively, demonstrates the packaging satisfies the applicable structural design criteria, as described in Section 2.1.2.
The results of the structural evaluation demonstrate that the packaging will experience no loss or dispersal of radioactive contents, no significant increase in external surface radiation levels, and no substantial reduction in the effectiveness of the packaging under NCT tests. Therefore, the packaging satisfies the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(1). The structural evaluation also shows the cumulative packaging damage resulting from the HAC test sequence does not result in escape of other radioactive material exceeding a total amount of A2 in one week, nor does it result in an external radiation dose rate that exceeds 10 mSv/h (1000 mrem/h) at 1 m from the external surface of the packaging. Thus, the packaging satisfies the requirements of 10 CFR 71.51(a)(2).
The structural evaluation of the packaging is performed by analysis using computational modeling software (CMS) and classical closed form solutions (hand calculations). The analytic techniques used for the structural evaluation comply with guidance provided in Regulatory Guide 7.9 [2.1], as supplemented by NUREG-2216 [2.2]. The ANSYS and LS-DYNA computer programs are used for the structural evaluation of the packaging. These computer programs are well-benchmarked and widely used for structural analyses of transportation packages for radioactive materials. The computer models used for the structural evaluation are described in the following sections.
NAC International 2-1
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.1 Description of Structural Design 2.1.1 Discussion The packaging consists of two (2) main components; a Containment Vessel (CV) and an Impact Limiter System (ILS), as shown in Figure 1-1. The CV is a stainless-steel vessel with a bolted closure designed to the leak-tight containment criterion. Additionally, the CV provides shielding, structural, and thermal protection of the contents. The ILS consists of both permanently installed and removable components designed to reduce the direct impact loading, reinforce, and protect the package containment boundary from the effects of the Normal Conditions of Transport (NCT) free drops and Hypothetical Accident Conditions (HAC) free drops. Additional description of the CV and ILS are contained in the following sections.
2.1.1.1 Containment Vessel (CV)
The CV is the packaging containment system. It is a stainless steel cylindrical vessel comprised of a body weldment, bolted lid, bolted port cover, and O-ring seals. The CV has a maximum outer diameter of top end) and an overall length of The CV cavity is with a stepped diameter that transitions from inner diameter at the top end to inner diameter at the bottom end.
The CV body weldment, shown in general arrangement drawing 50059-L003 in Appendix 1.3.3, forms the majority of the containment boundary of the CV. It is comprised of upper and lower shells, a transition ring, a bottom plate, and a upper flange, together forming a cylindrical, stepped diameter, vessel with an open end. These containment components are fabricated from solid Type 304 stainless steel joined with Complete Joint Penetration (CJP) circumferential and longitudinal (e.g. rolled shell and forged segment seams) welds.
The CV body weldment also contains non-containment features that provide support, reinforcement, and positioning functions; facilitate lifting and tie-down; and allow for the attachment of ILS components. These features include a Type 304 stainless steel shear ring welded to the OD of the lower shell (used for tie-down); two (2) diametrically opposed 17-4PH stainless steel trunnion pockets welded to the OD of lower shell (used for down/up-ending and tie-down); Type 304 stainless steel standoffs welded to the ID of the lower shell (center the contents in the cavity and provide support under lateral loading); an aluminum or aluminum alloy outer impact band wrapped around the OD of the upper shell and retained with welded Type 304 stainless steel retaining bands (part of the ILS, provides protection to the upper shell under lateral loading); a Type 304 stainless steel mounting ring welded to the OD of the NAC International 2.1-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A lower shell just below the transition ring (used to attach transition impact limiter sectors); a Type 304 stainless steel inner impact band welded to the ID of the upper shell (provides internal support and protection to the upper shell under lateral loading).
The CV lid is secured to the open end of the CV body weldment by closure bolts as shown in general arrangement drawing 50059-L002 in Appendix 1.3.3. Note, the lid bolts are a hex head design based on SA-574, Grade 4340 socket-head cap screws, with equivalent mechanical property requirements as specified in the previously indicated general arrangement drawing. The CV lid, as shown in general arrangement drawing 50059-L004 in Appendix 1.3.3, is solid Type 304 stainless steel and includes a port used to access the CV cavity after lid installation. The port is sealed for transport using a bolted Type 304 stainless steel port cover which is secured to the lid using CV lid also has threaded holes in the center for the attachment of a lift adapter plate used for lifting and handling of the package and threaded holes for attachment and alignment of the upper impact limiter sectors.
The CV lid and port cover include O-ring containment seals installed in machined grooves in the mating/sealing surface of each component. Outer O-ring seals (non-containment) and a test port is provided in the CV lid and port cover to facilitate leak testing of the respective inner (containment) O-ring seals.
Additionally, the CV includes internal features to provide protection and reinforcement to the containment boundary from the contents in critical areas during NCT and HAC drops. A 17-4 PH stainless steel bottom reinforcement plate is bolted into a machined recess in the CV bodys bottom plate and a 17-4 PH stainless steel reinforcement ring is bolted into a machined recess in the bottom side of the CV lid. These reinforcement plates provide protection to the containment boundary in specific areas of contact with the contents by distributing otherwise high localized bearing loads present due to design features of the contents (e.g., the reactor vessels hemispherical head/bottom and closure studs/nuts). Similarly, the previously described standoffs welded to the ID of the lower shell and the inner impact band reinforce the respective containment boundary regions and provide support under lateral loading. Specifically, the inner impact band provides support and protection to the CV bodys upper shell in the region where the reactor vessels head/shell flange contacts the inside of the CV under lateral loading conditions.
NAC International 2.1-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A In general, threaded holes in the CV (lid and body) including the lid bolt holes in the upper flange, port cover bolt holes, reinforcement plate/ring bolt holes, impact limiter mounting holes, and package lift attachment holes utilize stainless steel threaded inserts to improve the wear resistance and serviceability of the threaded connection points.
2.1.1.2 Impact Limiter System (ILS)
NAC International 2.1-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.1.2 Design Criteria The design criteria used for the structural design of the packaging is selected in accordance with the codes and standards identified in Section 2.1.4. Structural analyses of the packaging are performed for the applicable NCT tests (i.e., 10 CFR 71.71) and HAC tests (i.e., 10 CFR 71.73).
The combination of initial conditions used for the structural evaluation of each NCT and HAC test are discussed in Section 2.1.2.1. As discussed in Section 2.1.2.2, the allowable stress design criteria is used for the NCT. are used for the HAC evaluation. Other structural failure modes, such as buckling, fatigue, and brittle fracture, are evaluated using the design criteria discussed in Sections 2.1.2.3 through 2.1.2.5.
2.1.2.1 Load Combinations The load combinations used for the structural evaluation of the packaging are developed in accordance with Regulatory Guide 7.8 [2.3]. The load combinations are based on Table 2.1-1 of Regulatory Guide 7.8, with additional load combinations for intermediate initial conditions that could possibly create a more limiting case for the packaging design. The NCT and HAC load combinations are summarized in Table 2.1-1 and Table 2.1-2, respectively.
2.1.2.2 Allowable Stresses and Strains In accordance with Regulatory Guide 7.6 [2.4], the pressure-retaining components of the containment vessel (CV). For the NCT, the CV is designed in accordance with the requirements of Section III, Subsection NB of the ASME Code [2.5]. The containment system stress intensity limits for NCT are developed in accordance with Figures NB-3221-1 and NB-3222-1 and summarized in Table 2.1-3. For the HAC, the containment vessel strain limits are developed in accordance with (See more detailed discussion in Section 2.7.1). For the HAC, the CV lid closure bolts are evaluated using the allowable stress defined in Appendix F of ASME Code,Section III, Division 1 [2.8]. The NCT and HAC allowable stress design criteria for the packaging non-containment components are based on ASME Section III, Subsection NF [2.28] as summarized in Table 2.1-4. Factors of Safety (FS) are calculated and reported in Sections 2.6 and 2.7 for NCT and HAC, respectively. Factors of Safety greater than 10 are reported as Large.
NAC International 2.1-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.1.2.3 Buckling The CV assembly is evaluated for buckling to ensure geometric stability of the containment boundary is maintained for all NCT and HAC load combinations. Loading conditions that generate the largest compressive stresses in the CV are of particular concern for buckling failure modes. These load conditions include cases in which increased external pressure is applied to the CV (e.g. immersion) and the free drops.
Therefore, it can be concluded that the CV has adequate resistance to buckling failure modes for all NCT and HAC loads.
2.1.2.4 Fatigue 2.1.2.4.1 Structural Components Other Than Bolts NAC International 2.1-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.1-6
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.1-7
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.1-8
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.1.2.4.2 Closure Bolting NAC International 2.1-9
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.1-10
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.1.2.5 Brittle Fracture NAC International 2.1-11
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.1-12
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.1.3 Weights and Centers of Gravity The weight and center of gravity of the package, including each of the major individual packaging subassemblies and contents, are summarized in Table 2.1-5.
2.1.4 Identification of Codes and Standards for Packaging The package is designed, fabricated, tested, and maintained in accordance with codes and standards that are appropriate for transportation packages with Category I container contents.
The codes and standards are selected based on guidance provided in Regulatory Guide 7.6 [2.4]
and NUREG/CR-3854 [2.15].
For NCT, the package containment vessel is designed in accordance with the applicable requirements of the ASME Code,Section III, Division 1, Subsection NB [2.5]. For HAC, the containment vessel is evaluated to use the strain limits developed in accordance with The design criteria for the packaging is discussed in Section 2.1.2. The load combinations used in the packaging structural evaluation are developed in accordance with Regulatory Guide 7.8 [2.3], as discussed in Section 2.1.2.1. The buckling evaluation of the packaging cylindrical shells is discussed in Section 2.1.2.3. Fracture toughness of the packaging components is evaluated in accordance with the requirements of Regulatory Guide 7.11 [2.23] and NUREG/CR-1815 [2.24] for Category I containers.
The packaging containment vessel is fabricated in accordance with the applicable requirements of Subsection NB of Section III, Division 1, of the ASME Code [2.5].
Specific alternatives to the ASME Code requirements are presented and justified in Table 2.1-6.
These alternatives are justified based on other requirements for the design and analysis of the packaging as well as based upon standard industry practice for fabrication of transport packagings.
NAC International 2.1-13
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.1-1 Load Combinations for Normal Conditions of Transport Initial Conditions(1)
Ambient Insolation(3) Decay Internal Fabri-NCT Test Temperature(2) Heat Pressure(4) cation Condition 100°F -40°F Max. Zero Max. Zero Max. Min. Stress(5)
Hot Environment X X X X X (100°F ambient)
Cold Environment X X X X X
(-40°F ambient)
Reduced External X X X X X Pressure Increased External X X X X X Pressure X X X X X Vibration X X X X X X X X X X Free Drop X X X X X Notes:
- 1. Initial packaging temperature distribution considered to be at steady state.
- 2. Lower bound ambient temperature of -40qC conservatively used.
- 3. Maximum insolation in accordance with 10 CFR 71.71(c)(1).
- 4. Internal pressure is consistent with the other initial conditions being considered. Minimum internal pressure is taken as atmospheric pressure (0 psig).
- 5. Stresses due to assembly of the major components of the packaging, including stresses due to bolt preload.
NAC International 2.1-14
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.1-2 Load Combinations for Hypothetical Accident Conditions HAC Test Initial Conditions(1)
Condition Ambient Insolation(3) Decay Heat Internal Fabri-Temperature(2) Pressure(4) cation 100°F -40°C Max. Zero Max. Zero Max. Min. Stress(5)
X X X X X Free Drop X X X X X X X X X X Puncture X X X X X Thermal X X X X(6) X Notes:
- 1. Initial packaging temperature distributions are at steady state.
- 2. Lower bound ambient temperature of -40qC conservatively used.
- 3. Maximum insolation in accordance with 10 CFR 71.71(c)(1).
- 4. Internal pressure is consistent with the other initial conditions being considered. Minimum internal pressure is taken as atmospheric pressure.
- 5. Stresses due to assembly of the major components of the packaging, including stresses due to bolt preload.
- 6. Maximum internal pressure for the HAC thermal condition includes increased pressure due to increased fill gas temperatures during the fire transient.
NAC International 2.1-15
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.1-3 Containment System Allowable Stress Design Criteria Table 2.1-4 Non-Containment Component Allowable Stress Design Criteria NAC International 2.1-16
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.1-5 Package Weight and Center of Gravity Summary Center of Gravity(1)
Package Component or Assembly Weight (lbs) (in)
CV Shipping Configuration (Empty)
Containment Vessel (CV) Assembly Body Weldment Lid Assembly Upper Impact Limiter Lower Impact Limiter Center Impact Limiter Contents CV Shipping Configuration (w/ Contents)
Note:
- 1. C.G. is measured from the bottom of the Lower Impact Limiter along the centerline of the package.
- 2. Upper Impact Limiter weight includes Upper Impact Limiter sectors, approximately each.
NAC International 2.1-17
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.1-6 Alternatives to ASME Code Requirements NAC International 2.1-18
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.2 Materials 2.2.1 Material Properties and Specifications The specifications for the packaging materials of construction are summarized in Table 2.2-1.
The mechanical properties of the packaging materials that are used in the structural evaluation are described in this section.
The packaging components are fabricated from stainless steel and alloy steel bolting material.
Type 304 austenitic stainless steels in the form of plates (SA-240) are used to fabricate the structural components of the containment vessel (CV), except that the CV upper flange and 2.2.2 Chemical, Galvanic or Other Reactions The packagings materials of construction, consisting of stainless steel, alloy bolting steel, and including lubricants and cleaning agents used in the operation of the packaging, will not cause significant chemical, galvanic, or other reactions in the operating environment. The packaging materials have been used in other radioactive material (RAM) packaging for transport of similar contents without incident. As discussed in Section 2.2.2.1, all phases of operations, including loading, unloading, handling and transportation, are considered for the environments that may be encountered under NCT or HAC. Based on the evaluation of reactions among contents (Section 2.2.2.2), reactions between the contents and the packaging (Section 2.2.2.3), and reactions among packaging (Section 2.2.2.4), no potential chemical, galvanic, or other reactions that could adversely affect the overall integrity of the packaging or the structural integrity and retrievability of the contents have been identified. This ensures the packaging integrity will not be compromised by any chemical, galvanic, or other reaction. Therefore, the requirements of 10 CFR 71.43(d) are met.
NAC International 2.2-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.2.2.1 Operating Environment The packaging is loaded and handled in a dry environment. The outer surface of the package may be exposed to air, rain/snow/ice, or a marine atmosphere including salt spray. Except for the CV closure bolts and O-rings, all exposed surfaces of the packaging are stainless steel. The CV closure bolts 2.2.2.2 Reactions Among Contents The content of the packaging is a single used reactor vessel that has been prepared for disposal.
Thus, no reactions are expected.
2.2.2.3 Reactions Between Contents and Packaging The containment vessel is constructed of Type 304 austenitic stainless steel, with high corrosion resistance in the operating environments of the packaging. The content is a used reactor vessel that is also stainless steel. Therefore, no significant chemical, galvanic, or other reactions are expected between the packaging and the contents in the transportation environment.
2.2.2.4 Reactions Among Packaging The packaging is operated in a dry environment. Therefore, no chemical, galvanic, or other material of the CV contains no corrosives to adversely affect the packaging. This material is organic in nature and has not had any chemical, galvanic, or other reactions with stainless steel.
2.2.3 Effects of Radiation on Materials The packaging is designed and constructed using materials that have a long, proven history of use in transportation packaging withstand damaging effects from radiation. The materials of construction, are unaffected by the radiation levels in this package.
NAC International 2.2-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.2-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.2-1 Packaging Structural Material Specifications NAC International 2.2-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.2-2 Mechanical Properties of Type 304 and Type F304 Stainless Steels Table 2.2-3 Mechanical Properties of NAC International 2.2-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.2-4 Mechanical Properties of Steel Bolting Table 2.2-5 Mechanical Properties of NAC International 2.2-6
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.2-6 Mechanical Properties of A276, Type 304 Stainless Steel Table 2.2-7 Mechanical Properties of Stainless Steel NAC International 2.2-7
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.3 Fabrication and Examination Fabrication, examination, and testing are performed in accordance with the applicable design criteria listed in Section 2.1.2, the codes and standards identified in Section 2.1.4, and the license drawings contained in Appendix 1.3.3. Detailed descriptions of these activities are provided in the following sections, as well as in Chapter 8.
2.3.1 Fabrication Fabrication of the packaging is performed under NACs 10 CFR 71, Subpart H quality assurance program, NRC approval number 0018. The packaging containment system is fabricated in accordance with the applicable requirements of ASME Subsection NB [2.5]. A graded quality approach consistent with the provisions of the NRC Regulatory Guide 7.10 [2.31] and the NRC-approved NAC International QA Program and implementing procedures is used. Unless otherwise specified, fabrication is performed to specifications of the same code or standard used for design.
To the extent practical, components that form the packaging containment system are fabricated from materials permitted by ASME Subsection NB [2.5] and included in ASME Section II, Part D [2.13]. All other non-containment structural components of the packaging may be fabricated from ASTM materials that are equivalent to ASME materials, as permitted by NUREG/CR-3854
[2.15]. The quality category of the weld material is required be equal to or greater than the higher quality category of the components being joined. A Certified Material Test Report (CMTR) is provided for all steel materials, including weld filler metals, used to fabricate the packaging containment system. Code stamping is not required, the packaging is marked in accordance with the requirements of 10 CFR 71, as discussed in Table 2.1-6.
Consumables, such as threaded inserts and are procured from commercial suppliers and commercially dedicated in accordance with the requirements of the NAC QA program, commensurate with their safety functions.
Category A and B materials, components, and assemblies used for the fabrication of the packaging, including the weld filler metal, are labeled to maintain control and traceability of materials throughout the fabrication process. Marking of materials, components, and assemblies is done using methods that do not result in harmful contamination or sharp discontinuities or infringe upon the minimum required material thickness.
NAC International 2.3-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Operations associated with the fabrication and assembly of the packaging are included in written shop instructions, e.g., fabrication travelers and/or procedures. Welding is performed in accordance with a written welding procedure specification (WPS) that is qualified in accordance with the applicable requirements of the ASME Code. Personnel performing welding are qualified to use the welding procedure, and their qualifications are documented in accordance with the applicable requirements of Section IX of the ASME Code [2.21].
The general processes used to fabricate each finished CV assembly of the packaging are described as follows. The CV assembly consists of a body weldment, a bolted closure lid, and a bolted port cover. The CV body weldment is constructed from a stainless-steel cylindrical upper shell, transition ring, cylindrical lower shell, bottom plate, and bolting flange. The bolting flange and transition ring may either be fabricated from a solid forging or fabricated from plate. The use of a backing bars made from similar material is permitted for the longitudinal seam welds, if it is removed for the finished assembly. The CV shell is aligned with the bottom plate and bolt flange and attached using complete joint penetration circumferential seam welds.
The CV lid is fabricated from a solid piece of stainless steel plate that is machined to form the closure bolt holes, vent port, and test port. The CV lid bolts are custom flanged hex head bolts.
Critical features of the CV body, such as the top face of the bolting flange (which is the mating O-ring seal surface for the lid) and the lid bolt holes in the upper flange may be machined to the final dimensions shown on the general arrangement drawings in Appendix 1.3.3 after completing the CV body welds.
2.3.2 Examination Examination and testing of the packaging is performed under NACs NRC approved QA program. The components and assemblies of the packaging are inspected to assure that the packaging satisfies the dimensional requirements shown on the general arrangement drawings in Appendix 1.3.3 and are examined using non-destructive techniques to assure quality of workmanship. In addition, materials, components, and assemblies are tested to assure that they have the required critical characteristics and that they satisfy the acceptance criteria for all required functional tests. All operations associated with the examination and testing of the packaging are performed by personnel that are trained and qualified, or approved, in accordance with the requirements of the NAC QA program and the requirements of the applicable codes and standards using calibrated measuring and test equipment (M&TE). Witness and hold points are included in the written shop instructions for activities that require QA inspection or oversight.
NAC International 2.3-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Copies of all written shop instructions, personnel training and qualification records, and M&TE calibration records are maintained with the final records package.
The processes used for the examination and testing of the packaging are described as follows:
Material Tests The steel materials used to fabricate the components and assemblies of the packaging containment system are furnished with CMTRs that assure that the materials possess the critical characteristics that are required to perform their safety functions. In accordance with additional base and welded material testing will be performed to determine Fabrication Tests and Examinations The dimensions of the components and assemblies of the packaging are measured with calibrated M&TE to assure compliance with the dimensional requirements shown on the general arrangement drawings in Appendix 1.3.3. In addition, the weights of the finished packaging components are measured to assure that they meet the weight requirements.
Welded joints receive a workmanship visual examination and/or liquid penetrant (PT) non-destructive examination (NDE) to assure that they do not include visible surface defects, such as lack of fusion, linear or crack like indications, or porosity. In addition, the full-penetration welds that form the containment boundary of the CV body weldment are examined using either radiography (RT) or ultrasonic testing (UT) methods to assure that they do not include any indications of weld flaws. Examinations of welded joints are performed in accordance with the applicable requirements of Section V of the ASME Code [2.7],
Subsection NB of the ASME Code for the CV assembly containment components. Areas of surface defect removal and completed weld repairs require thickness checks, using either a mechanical or UT device, by qualified personnel to verify compliance with the minimum thickness requirements. Written reports of each weld examination are prepared and maintained with the final records package.
The components of the finished containment systems, i.e., the CV body weldment, CV lid and closure bolts, CV port cover and closure bolts, and CV lid and port cover containment O-ring seals are leak-tested in accordance with ANSI N14.5 to demonstrate leak-tight containment, in accordance with the requirements of Section 8.1.4. The CV is also hydrostatically tested to an internal pressure of 150% of the design pressure in accordance with the requirements of NAC International 2.3-3
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NB-6220 to verify the structural integrity of the containment system, as described in Section 8.1.3.2.
Functional Tests Functional tests are performed to assure proper fit up of the packaging components.
NAC International 2.3-4
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.4 General Requirements for All Packages 2.4.1 Minimum Package Size In accordance with the requirement of 10 CFR 71.43(a), the smallest overall dimension of a package may not be less than 10 cm. The smallest overall dimension of the PALADIN package is much larger than 10 cm. Therefore, the package meets the minimum package size requirement of 10 CFR 71.43(a).
2.4.2 Tamper-Indicating Feature In accordance with the requirement of 10 CFR 71.43(b), the outside of a package must incorporate a feature, such as a seal, that is not readily breakable and that, while intact, would be evidence that the package has not been opened by unauthorized persons. Wire cable tamper-indicating seals or similar devices are attached to the upper impact limiter attachments after the impact limiter is secured to the Containment Vessel (CV) such that the upper impact limiter cannot be removed without damaging the tamper-indicating seals or the packaging. The location of the seal and its materials of construction minimize the potential for accidental damage during transport. Thus, the package satisfies the tamper indicating feature requirements of 10 CFR 71.43(b). The tamper indicating seal is not required to be installed for empty shipments.
2.4.3 Positive Closure In accordance with the requirement of 10 CFR 71.43(c), the package must include a containment system securely closed by a positive fastening device that cannot be opened unintentionally or by a pressure than may arise within the package. The Containment Vessel is enclosed on the top end by the upper impact limiter, which includes safety wire and tamper indicating seals, as discussed in Section 2.4.2. The safety wire and tamper indicating seals prevent the impact limiter from being unintentionally removed from the package. Furthermore, the Containment Vessel (CV) includes a closure lid that is secured by closure bolts. Since tools are required to remove these closure bolts, the package containment system cannot be unintentionally opened. The containment system does not include any covers, valves, or other access that could be inadvertently opened.
The package containment system is evaluated for internal pressure loads that arise during NCT and HAC in Section 2.6 and Section 2.7, respectively. The evaluations demonstrate that the CV closure bolts satisfy the applicable allowable stress or strain design criteria and that the NAC International 2.4-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A containment seals remain intact under NCT and HAC. Hence, the package containment system satisfies the positive closure requirements of 10 CFR 71.43(c).
NAC International 2.4-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.5 Lifting and Tie-Down Standards for All Packages 2.5.1 Lifting Devices In accordance with the requirements of 10 CFR 71.45(a), the lifting attachments that are structural parts of the package are designed with a minimum factor of safety of three against yield when used to lift the package in the intended manner. The lifting attachments are also designed so that failure of any lifting device under excessive load would not impair the ability of the package to meet the other requirements of 10 CFR 71 Subpart E.
The lifting attachments of the PALADIN package are designed in accordance with the requirements of ANSI N14.6 [2.12] for special lifting devices for critical lifts. Because the package lifting attachments do not include dual-load paths, the lifting attachments are designed to lift the package without generating a combined shear stress or maximum tensile stress at any point in the lifting attachment more than Sy/6 or Su/10 (Sy and Su are the material yield strength and ultimate strength, respectively). The ANSI N14.6 design limits for lifting devices are lower than the criteria of 10 CFR 71.45(a) and, therefore, compliance with ANSI N14.6 also demonstrates compliance with 10 CFR 71.45(a).
NAC International 2.5-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.5.2 Tie-Down Devices In accordance with the requirements of 10 CFR 71.45(b), the package tie-down devices are designed to withstand a static force applied to the package center gravity with a 2g vertical load NAC International 2.5-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A component, a 5g lateral load component, and a 10g longitudinal (i.e., horizontal component along the direction in which the vehicle travels) load component, without generating stress in any material of the package more than its yield strength.
The results demonstrate that the tie-down attachments satisfy the tie-down attachment requirements of 10 CFR 71.45(b)(1); the stresses do not exceed the yield strength of the packaging materials.
In addition, an evaluation of the shear ring weld and the trunnion pocket welds is performed to show that under excessive loading, these components (outside the CV shell) would fail and not impair the ability of the package to meet the other requirements of 10CFR71 Subpart E. The NAC International 2.5-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.5-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.6 Normal Conditions of Transport This section presents the structural evaluation of the package that demonstrates compliance with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(1) when subjected to the NCT tests specified in 10 CFR 71.71. In accordance with 10 CFR 71.71(a), the package is required to be evaluated for each NCT test individually based on the most unfavorable initial conditions, including an ambient temperature between -20°F and 100°F and an internal pressure between zero and the MNOP. The package is conservatively evaluated for NCT considering a lower bound initial ambient temperature of -40°F. The structural evaluation shows that there would be no loss or dispersal of radioactive contents, no significant increase in external surface radiation levels, and no substantial reduction in the effectiveness of the packaging.
2.6.1 Heat In accordance with 10 CFR 71.71(c)(1), the package is subjected to an ambient temperature of 100°F (38°C) in still air and insolation. The load combination corresponding to Heat condition for the NCT is shown in Table 2.1-1. Per Table 2.1-1, NCT heat consists of a 100qF (38qC) ambient temperature combined with maximum decay heat, maximum insolation, maximum internal pressure and fabrication stresses.
The maximum temperatures of the packaging components for NCT thermal conditions are summarized in Table 3.1-2. The maximum temperature of the CV is A maximum normal condition design pressure of is considered in the evaluation in this Section. The calculated MNOP as discussed in Section 3.3.3 is significantly lower than this design pressure.
Differential thermal expansion of the packaging components is evaluated considering possible interference resulting from a reduction in gap sizes. Since the CV and cargo are both made of stainless steel and there is negligible decay heat in the cargo, temperatures for CV and cargo are similar. Therefore, both the radial and longitudinal differential thermal expansions between the CV and the cargo are insignificant. The cargo will expand freely withing the CV cavity under NCT heat. Thermal stress in the CV for the NCT heat condition is negligible since there is no decay heat in the cargo and the CV is only subjected to solar insolation which results in insignificant thermal gradients in the CV components.
The only significant fabrication stresses in the package are those resulting from closure bolt preload. Maximum bolt preloads are applied to the CV closure bolts to produce the maximum bolt stresses. Minimum bolt preload has no significant effect on the integrity of the CV lid NAC International 2.6-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A attachments and sealing of the pressure boundaries. Based on the bolt preload (T) the maximum and minimum preload are calculated to be respectively, based on the following equation in Machinerys Handbook [2.22].
T = Fpreload u D b u k where:
Fpreload = Preload bolt force from torque Db = Diameter of lid bolt k = Torque coefficient Based on the seal compression force data, a bounding seal O-ring compression force is per linear inch. Using the bounding (outer) O-ring diameter of both lid O-rings (inner O-ring has a diameter of the total seal load required is conservatively calculated to be per bolt, which is significantly less than the minimum bolt preload of The structural evaluation for the NCT heat condition is bounded by the evaluation for the NCT Reduced External Pressure condition, which is evaluated in Section 2.6.3. Reduced External Pressure condition is the same as the Heat condition with a slightly higher internal pressure load of Therefore, no further analysis is required for the Heat condition. The results of the reduced external pressure structural evaluation demonstrate the packaging satisfies the applicable NCT allowable stress design criteria and does not experience and permanent deformation.
Therefore, the effectiveness of the packaging is not reduced by NCT heat. Furthermore, since the evaluation shows that the containment seal is maintained, there would be no loss or dispersal of radioactive contents. NCT heat does not cause any significant increase in external surface radiation levels. Therefore, the package complies with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(1) when subjected to the NCT heat test.
2.6.2 Cold The package is designed to withstand the effects of a steady state ambient temperature of -40qF in still air and shade in accordance with 10 CFR 71.71(c)(2). Per Table 2.1-1, the NCT cold environment is evaluated in combination with zero insolation, zero decay heat, and zero internal pressure. Therefore, the NCT cold environment results in a uniform temperature of -40qF throughout the package. There is no thermal stress in the CV. The structural evaluation for the NCT cold condition is bounded by the evaluation for the NCT Reduced External Pressure condition, which is evaluated in Section 2.6.3. The package thus complies with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(1) when subjected to NCT cold conditions.
NAC International 2.6-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.6.3 Reduced External Pressure In accordance with 10 CFR 71.71(c)(3) the package is designed to withstand the effects of a reduced external pressure of 3.5 psi absolute. Per Table 2.1-1, reduced external pressure loading is considered in combination with the maximum normal design pressure NCT heat, and fabrication stresses.
Under NCT heat conditions, MNOP does not exceed gauge. Therefore, the greatest pressure difference between the inside and outside of the containment vessel is The only significant fabrication stresses in the package are those resulting from closure bolt preload.
As discussed in Section 2.6.1, the maximum bolt preload is calculated to be NAC International 2.6-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A The results of the NCT reduced external pressure structural evaluation demonstrate that the package containment system satisfies the applicable NCT allowable stress design criteria.
Reduced external pressure loading does not cause any permanent deformation of the package, substantially reduce the effectiveness of the packaging, result in any loss or dispersal of radioactive contents, or cause any significant increase in external surface radiation levels.
Therefore, the package complies with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(1) when subjected to the NCT reduced external pressure test specified in 10 CFR 71.71(c)(3).
NAC International 2.6-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.6-1 CV Stress Summary for Reduced External Pressure NAC International 2.6-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.6-1 Axisymmetric Finite Element Model for the Containment Vessel (CV)
NAC International 2.6-6
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.6-2 Section Locations for Stress Evaluation of the CV NAC International 2.6-7
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.6.4 Increased External Pressure In accordance with 10 CFR 71.71(c)(4), the package is designed to withstand the effects of an increased external pressure of 20 psi absolute. Using the same 2-D axisymmetric finite element model for the evaluation of Reduced External Pressure (Section 2.6.3), the factors of safety are calculated to be Large for both the primary membrane (Pm) stress and primary membrane plus bending (Pm+Pb) stress. The effect of increased external pressure on the pressure-retaining components of the packaging is considered insignificant.
2.6.5 Vibration In accordance with 10 CFR 71.71(c)(5), the package is subjected to vibration normally incident to transport. The package is transported in a horizontal orientation and secured to a shipping skid that restrains the longitudinal movement of the package by the shear ring and rotation trunnion pockets located near the lower end of the CV. The weld stress and the bearing stress of the shear ring and rotation trunnion pockets are evaluated for a bounding vibration acceleration of 5g in the longitudinal direction of the transport skid. The bending stress of the CV body is evaluated for a bounding vibration acceleration of 3g for both the lateral directions. Note that these g-loads are bounding compared with the g-loads shown in Figure 2-11 and Figure 5-189 in the Data Analysis of ENSA/DOE Rail Cask Tests, Spent Fuel and Waste Disposition, SAND2018-13258R [2.15].
The maximum weight of the package in the transport configuration is The shear ring and the pair of rotation trunnion pockets are designed to resist the full 5g longitudinal load
( s). The shear ring weld stress is calculated to be . The corresponding equivalent stress is The allowable stress for shear is 0.6Sm. For Type 304 stainless steel, Sm (Design stress intensity) is 23.3 ksi at 125°F. The factor of safety (FS) is computed to be 1.02. The rotation trunnion pocket weld stress is calculated to be The corresponding equivalent stress is Using the same allowable stress for the Type 304 stainless steel base material, the factor of safety (FS) for the rotation trunnion pocket weld is computed to be 1.02. The bearing stress in the shear ring and rotation trunnion pockets for the 5g longitudinal load is bounded by the 10g tie-down load evaluations discussed in Section 2.5.2, which used the same allowable bearing stress, Sy.
The CV body is evaluated for bending stress for 3g load ) for lateral directions. The evaluation conservatively considers a simply supported beam with a concentrated load at mid-span. The moment of inertial of the CV body is The NAC International 2.6-8
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A bending stress is computed to be Using the allowable bending stress of 1.5Sm, the factor of safety is Large.
Therefore, it is concluded that the packaging satisfies the applicable NCT allowable stress design criteria for NCT vibration. NCT vibration loading does not cause any permanent deformation of the package, nor does it substantially reduce the effectiveness of the packaging. Finally, the configuration of the package under NCT vibration loading is bounded by that considered in the shielding evaluation. Therefore, NCT vibration loading does not cause any significant increase in external surface radiation levels. The package thus complies with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(1) when subjected to the NCT vibration test specified in 10 CFR 71.71(c)(5).
2.6.6 Water Spray In accordance with the requirements of 10 CFR 71.71(c)(6), the package must be subjected to a water spray that simulates exposure to rainfall of approximately 2 in/h (5 cm/h) for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Quenching effects due to the water spray test will not significantly affect the package. The package contents have insignificant heat generation and as such component temperatures under NCT are limited, as discussed in Section 3.3. Furthermore, the substantial thermal mass of the packaging is large enough to significantly slow the thermal response to sudden external temperature or environmental changes. Therefore, the water spray test condition is not significant to the structural design of the packaging, is not analyzed, and has no impact on the systems response to the subsequent free drop conditions.
2.6.7 Free Drop In accordance with 10 CFR 71.71(c)(7), the package, which weighs more than 15,000 kg (33,100 pounds), is subjected to a free drop from 0.3 m (1 foot) onto a flat, essentially unyielding, horizontal surface, striking in a position for which maximum damage is expected.
In this Section, the PALADIN package is evaluated for 1-foot side drop only, as there is no plausible mechanism for the 1-foot end drop or 1-foot corner drop to occur during normal conditions of transport due to the configuration and size of the packaging.
The load combinations for the NCT free drop are defined in Table 2.1-1. The governing loading combination is the side drop load combined with NCT heat, maximum normal design pressure and fabrication stresses (bolt preload).
NAC International 2.6-9
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Containment Vessel Evaluation The following six components form the containment boundary of the CV assembly.
- 1. Bottom Plate
- 2. Lower Shell
- 3. Transition Ring
- 4. Upper Shell
- 5. Upper Flange
- 6. Lid NAC International 2.6-10
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A The stress acceptance criteria for the evaluation of CV are based on ASME Boiler and Pressure Vessel Code, Subsection NB-3200 [2.5]. The regions for the stress evaluation are classified into the two following categories.
- 1. For regions that have inelastic deformation, they are considered as local discontinuity, the inelastic deformations are limited to 5% strain per NB-3228.4.
- 2. For regions that is not closer in the meridional direction of more than 1.0 ( NB-3213.10) from the inelastic region, where R is the radius of mid-thickness of a shell, and t is the thickness of the shell, the primary membrane (Pm) stress intensity is limited to 1.0 Sm, the primary membrane plus bending (Pm+Pb) stress intensity is limited to 1.5 Sm (See Figure NB-3221-1, Sm is the design stress intensity).
The CV stresses for these components are calculated using the 3-D half-symmetry finite element model. A summary of the CV stress evaluation for side drop condition is presented in Table 2.6-
- 2. The minimum factor of safety in the CV is 1.04 for primary membrane (Pm) stress intensity and 1.4 for primary membrane plus bending (Pm+Pb) stress intensity. Therefore, the CV satisfies the applicable allowable design criteria for the NCT side drop.
Lid Closure Bolts Side Drop Evaluation NAC International 2.6-11
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.6-12
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.6-2 CV Stress Summary for 1-Ft Side Drop NAC International 2.6-13
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.6-3 Finite Element Model for 1-Foot Side Drop Evaluation NAC International 2.6-14
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.6-4 Finite Element Model for 1-Ft Side Drop - Isometric View NAC International 2.6-15
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.6-5 Finite Element Model for 1-Ft Side Drop - Impact Limiters NAC International 2.6-16
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.6.8 Corner Drop In accordance with 10 CFR 71.71(c)(8), fiberboard, wood, or fissile material rectangular packages not exceeding 110 pounds (50 kg) and fiberboard, wood, or fissile material cylindrical packages not exceeding 220 pounds (100 kg) must be subjected to a free drop onto each corner of the package in succession, or in the case of a cylindrical package onto each quarter of each rim, from a height of 1 foot (0.3 m) onto a flat, essentially unyielding, horizontal surface. The package is not a fiberboard, wood, or fissile material package and it weighs more than 220 pounds (100 kg). Therefore, the corner drop test requirements of 10 CFR 71.71(c)(8) are not applicable to the package.
2.6.9 Compression In accordance with 10 CFR 71.71(c)(9), packages must be subjected to a compressive (e.g.,
stacking) load, applied uniformly to the top and bottom of the package in a position in which the package would normally be transported. The compressive load is equal to the greater of the equivalent of 5 times the weight of the package, and 2 psi (13 kPa) multiplied by the vertically projected area of the package. The compression test requirements of 10 CFR 71.71(c)(9) do not apply because the package weighs more than 11,000 pounds (5,000 kg).
2.6.10 Penetration In accordance with 10 CFR 71.71(c)(10), the package must be subjected to an impact of the hemispherical end of a vertical steel cylinder of 1.25 inch (3.2 cm) diameter and weighing 13 pounds (6 kg), dropped from a height of 40 inches (1 m) onto the exposed surface of the package that is expected to me most vulnerable to puncture. Per Regulatory Guide 7.8 [2.3], the penetration test is not structurally limiting for large packages without unprotected valves. The package is large and does not have any vulnerable locations on the package surface. Thus, the package need not be evaluated for NCT penetration.
NAC International 2.6-17
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7 Hypothetical Accident Conditions The package meets the standards specified in 10 CFR 71.51(a)(2) when subjected to the HAC tests specified in 10 CFR 71.73. In accordance with Regulatory Guide 7.6 [2.4], design by analysis is used for the structural evaluation of the package. The structural evaluation for HAC is based on sequential application of the HAC tests specified in 10 CFR 71.73(c) to determine the cumulative effect on the package, in accordance with 10 CFR 71.73(a). As discussed in Section 2.6, no significant package damage results from the NCT tests of 10 CFR 71.71. Thus, the evaluation of the package for the HAC test sequence is performed starting with an undamaged specimen. The package is evaluated for the most unfavorable initial conditions specified in 10 CFR 71.73(b). The HAC load combinations considered in the structural evaluation are developed in accordance with Regulatory Guide 7.8 [2.3] and summarized in Section 2.1.2.1. The results of the structural evaluation show that the package satisfies the applicable criteria in the ASME Code when subjected to the HAC tests of 10 CFR 71.73.
2.7.1 Free Drop NAC International 2.7-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.7-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.7-3
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A deformation of the packaging, except for the impact limiters, nor does it substantially reduce the effectiveness of the packaging. The evaluation shows that, under HAC free drop loading the containment seal is maintained and there is no loss or dispersal of radioactive contents. The damage to the impact limiters resulting from HAC free drop loading is considered in the HAC shielding evaluation, which demonstrates that the external dose rate limit requirements of 10 CFR 71.51(a)(2) are satisfied. Therefore, the package complies with the requirements of 10 CFR 71.51(a)(2) when subjected to the HAC free drop test of 10 CFR 71.73(c)(1).
NAC International 2.7-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-1 Finite Element Model for HAC Free Drop Evaluations NAC International 2.7-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-2 Finite Element Model for HAC Free Drops - Isometric View NAC International 2.7-6
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-3 Finite Element Model for HAC Free Drops - Impact Limiters NAC International 2.7-7
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.1.1 End Drop The package is evaluated for a 30-foot (9 m) HAC end drop, occurring on either the bottom or top end of the package, considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.3]. The structural evaluation of the package for the HAC end drop test is presented in this Section.
The dynamic analysis of the package for the HAC end drop orientation is performed using the three-dimensional half-symmetry finite element model as described in Section 2.7.1. As shown in Figure 2.7-4, the analyses are performed for two end drop cases: Bottom End Drop and Top End Drop.
A summary of the evaluation results for the CV for end drop conditions is presented in Table 2.7-1. The minimum factor of safety is 1.1, which occurs at the bottom plate for bottom end drop condition. The lid closure bolt evaluation for end drops is presented in Section 2.7.1.4 and shows that bolt tension following the drop condition is sufficient to maintain seal compression.
NAC International 2.7-8
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-1 CV Strain Summary for HAC End Drops NAC International 2.7-9
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-4 HAC End Drop Cases NAC International 2.7-10
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.1.2 Side Drop The package is evaluated for a 30-foot (9 m) HAC side drop considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.3].
The dynamic analysis of the package for the HAC side drop orientation is performed using the three-dimensional half-symmetry finite element model as described in Section 2.7.1. The drop orientation of the model is shown in Figure 2.7-5.
As noted in Section 2.7.1, A summary of the evaluation results for the CV for side drop conditions is presented in Table 2.7-2. The minimum factor of safety is 1.7, which occurs at the lid region. The lid closure bolt evaluation for the side drop is presented in Section 2.7.1.4 and shows that bolt tension following the drop condition is sufficient to maintain seal compression.
NAC International 2.7-11
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-2 CV Strain Summary for HAC Side Drop NAC International 2.7-12
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-5 HAC Side Drop Case NAC International 2.7-13
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.1.3 Corner Drop The package is evaluated for a 30-foot (9 m) HAC corner drop, occurring on either the bottom or top corner of the package, considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.3]. The structural evaluation of the package for the HAC corner drop test is presented in this Section.
The dynamic analysis of the package for the HAC end drop orientation is performed using the three-dimensional half-symmetry finite element model as described in Section 2.7.1. As shown in Figure 2.7-6, the analyses are performed for two corner drop cases: Top Corner Drop and Bottom Corner Drop.
As noted in Section 2.7.1, A summary of the evaluation results for the CV for corner drop conditions is presented in Table 2.7-3. The minimum factor of safety is 1.3, which occurs at the lower shell for the bottom corner drop condition. The lid closure bolt evaluation for the corner drops is presented in Section 2.7.1.4 and shows that bolt tension following the drop condition is sufficient to maintain seal compression.
and 8.2% for NAC International 2.7-14
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-3 CV Strain Summary for HAC Corner Drops NAC International 2.7-15
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-6 HAC Corner Drop Cases NAC International 2.7-16
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.1.4 Lid Closure Bolt Evaluation for Free Drops NAC International 2.7-17
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.7-18
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-4 Lid Closure Bolt Evaluation Summary for HAC End Drops and Corner Drops Table 2.7-5 Lid Closure Bolt Evaluation Summary for HAC Side Drop NAC International 2.7-19
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.2 Crush The crush test of 10 CFR 71.73(c)(2) is required only when the specimen has a mass not greater than 1,100 pounds, an overall density not greater than 62.4 lb/ft3 based on external dimensions, and radioactive contents greater than 1,000 A2 not as a special form radioactive material. The package weighs more than 1,100 pounds. Therefore, the crush test is not required.
2.7.3 Puncture In accordance with 10 CFR 71.73(c)(3), the package is evaluated for a 1 m (40-inch) free drop in a position for which maximum damage is expected, onto the upper end of a solid, vertical, cylindrical, mild steel bar, mounted on an essentially unyielding horizontal surface. The bar must be 6 inches in diameter, with the top horizontal and its edge rounded to a radius of not more than 0.25 inches, and a length as to cause maximum damage to the package, but not less than 8 inches long. The puncture drop test is performed in sequence following the HAC free drop test in accordance with 10 CFR 71.73(a). Therefore, the package damage resulting from the HAC free drop is considered in the HAC puncture drop evaluation.
HAC puncture impact analyses are performed for both side and end impacts, as discussed in Sections 2.7.3.1 and 2.7.3.2, respectively. The results show that HAC puncture test does not result in any significant damage to the packaging.
2.7.3.1 HAC Side Puncture Impact The dynamic analysis of the package for the HAC side puncture is performed using the three-dimensional half-symmetry finite element model as described in Section 2.7.1. As shown in Figure 2.7-5, a puncture pin (located at top portion of the CV) and a rigid plane are included in the model. An impact velocity of 175.8 in/sec is applied to the model to simulate the 40-inch free drop.
As noted in Section 2.7.1, are used for the containment vessel.
A summary of the evaluation results for the CV for the side puncture impact is presented in Table 2.7-6. The minimum factor of safety is 1.7, which occurs at the lid region.
The lid closure bolts are evaluated using the same methods as described in Section 2.7.1.4. The evaluation results of the lid closure bolts for side puncture are summarized in Table 2.7-7.
NAC International 2.7-20
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.3.2 HAC End Puncture Impact The dynamic analysis of the package for the HAC end puncture is performed using the three-dimensional half-symmetry finite element model as described in Section 2.7.1. As shown in Figure 2.7-8, a puncture pin with a rigid plane is added to the model and three (3) end puncture cases are considered: Bottom End Puncture - Pin Center, Bottom End Puncture - Pin Offset and Top End Puncture - Pin Center. An impact velocity of 175.8 in/sec is applied to the model to simulate the 40-inch free drop.
As noted in Section 2.7.1, A summary of the evaluation results for the CV for end drop conditions is presented in Table 2.7-8. The minimum factor of safety is 1.06, which occurs at the transition ring for bottom end puncture.
The lid closure bolts are evaluated using the same methods as described in Section 2.7.1.4. The evaluation results of the lid closure bolts for end punctures are summarized in Table 2.7-9.
NAC International 2.7-21
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-6 CV Strain Summary for Side Puncture Impact Table 2.7-7 Lid Closure Bolt Evaluation Summary for Side Puncture Impact NAC International 2.7-22
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-8 CV Strain Summary for End Puncture Impact NAC International 2.7-23
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-9 Lid Closure Bolt Evaluation Summary for End Puncture Impact NAC International 2.7-24
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-7 HAC Side Impact Puncture NAC International 2.7-25
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 2.7-8 HAC End Impact Punctures NAC International 2.7-26
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.4 Thermal In accordance with 10 CFR 71.73(c)(4), the package is designed to withstand the 30-minute fire with the flame temperature of 1,475°F (800°C). This section presents the structural evaluation of the package for the HAC thermal loading.
A transient thermal analysis for the fire condition is performed in Chapter 3. The thermal analysis results shows that the outer surface of the CV reaches a peak temperature of and the peak average temperature of the air inside the CV is during the HAC fire transient.
As shown in Section 3.4.2.2, the maximum internal pressure developed in the CV during the HAC thermal test is A conservative HAC design pressure of 100 psig is used for the structural evaluation of the packaging.
The stresses in the packaging resulting from temperature loading are classified as secondary and need not be evaluated for HAC in accordance with the ASME Code. Therefore, the only significant primary stresses in the packaging resulting from the HAC fire are due to increased internal pressure loading resulting from elevated temperature of the cavity contents and fill gas during the fire transient. For the HAC thermal test, a maximum internal pressure of 100 psig is evaluated in combination with preload.
A detailed stress analysis of the packaging for HAC pressure loading is performed using linear-elastic finite element analysis methods. The 2-D axisymmetric finite element model described in Section 2.6.1 is used to determine the stresses in the CV for the fire accident. A bounding accident internal pressure load of 100 psig is applied to the CV cavity surfaces. An upper-bound preload of is applied to each of the CV closure bolts. The stress results of the analysis are summarized in Table 2.7-10.
The maximum stress intensities in the CV are evaluated using the accident condition allowable stress design criteria of Subsection NB of the ASME B&PV Code. The accident condition allowable stress intensities used for this evaluation are conservatively based on a temperature of
. The allowable stresses are 2.4Sm (23.5 ksi) and 3.6Sm (35.3 ksi) for Pm and Pm+Pb stresses, respectively. As shown in Table 2.7-10, the minimum factor of safety for the deep-water immersion test is 12.0 for the primary membrane (Pm) stress intensity and 6.6 for the primary membrane plus bending (Pm+Pb) stress intensity.
Lid Bolts Evaluation NAC International 2.7-27
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A NAC International 2.7-28
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A criteria. Thus, containment will be maintained under HAC thermal loading, and there will be no loss or dispersal of radioactive contents. The damage to the impact limiters resulting from HAC free drop loading is considered in the HAC shielding evaluation in Chapter 5, which demonstrates that the external dose rate limit requirements of 10 CFR 71.51(a)(2) are satisfied.
Therefore, the package complies with the requirements of 10 CFR 71.51(a)(2) when subjected to the HAC thermal test of 10 CFR 71.73(c)(4).
NAC International 2.7-29
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-10 CV Stress Summary for HAC Pressure (Fire Accident)
NAC International 2.7-30
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.7.5 Immersion - Fissile Material The content of the PALADIN package is non-fissile material and, therefore, the requirement in 10 CFR 71.73(c)(5) for package containing fissile material is not applicable.
2.7.6 Immersion - All Packages In accordance with 10 CFR 71.73(c)(6), an undamaged package is subjected to a water pressure equivalent to immersion under a head of water of at least 50 feet (15 m), or an equivalent external pressure load of 21.7 psi (150 kPa) gauge. A 21.7 psi (150 kPa) gauge external pressure load has negligible effects on the packaging and is bounded by the 290 psi (2 MPa) external pressure load evaluated in Section 2.7.7. Therefore, no further evaluation is required for this test.
2.7.7 Deep-Water Immersion Test (for Type B Packages Containing more than 105 A2)
In accordance with 10 CFR 71.61, a Type B package containing more than 105 A2 must be designed so that its undamaged containment system can withstand an external water pressure of 290 psi (2 MPa) for a period of not less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> without collapse, buckling, or inleakage of water. Although the PALADIN package does not contain more than 105 A2, this section conservatively provides the analysis of the CV that demonstrates compliance with the deep-water immersion test requirements of 10 CFR 71.61.
The 2-D axisymmetric finite element model described in Section 2.6.1 is used to determine the stresses in the CV for deep-water immersion. The only loadings applied for this condition are a conservative external pressure load of 300 psi and the closure bolt preload. The external pressure loading is applied to all external surfaces of CV. An upper-bound preload of is applied to each of the CV closure bolts. The stress results of the analysis are summarized in Table 2.7-11.
The maximum stress intensities in the CV are evaluated using the accident condition allowable stress design criteria of Subsection NB of the ASME B&PV Code. The accident condition allowable stress intensities used for this evaluation are conservatively based on a temperature of 125qF. The allowable stresses are 0.7Su (52.5 ksi) and 1.0Su (75.0 ksi) for Pm and Pm+Pb stresses, respectively. As shown in Table 2.7-11, the minimum factor of safety for the deep-water immersion test is 8.9 for the membrane stress intensity (Pm) and 4.8 for the membrane plus bending stress intensity (Pm+Pb). Therefore, the CV meets the allowable stress design criteria for the deep-water immersion test of 10 CFR 71.61.
NAC International 2.7-31
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Additionally, an eigenvalue buckling analysis of the Containment Vessel (CV) is performed using the ANSYS finite element model used for deep-water immersion stress evaluation, described above. The results indicate a safety factor of 248 against buckling. Therefore, it is concluded that the CV will not buckle under the deep-water immersion condition.
NAC International 2.7-32
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 2.7-11 CV Stress Summary for Deep Water Immersion NAC International 2.7-33
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.8 Accident Conditions for Air Transport of Plutonium This section is not applicable to the PALADIN package because it is not designed for air transport of plutonium and will not be used for that purpose.
NAC International 2.8-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.9 Accident Conditions for Fissile Material Packages for Air Transport This section is not applicable to the PALADIN package because it is not designed for air transport of fissile material and will not be used for that purpose.
NAC International 2.9-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.10 Special Form This section is not applicable to the PALADIN package because the intended contents to be transported does not satisfy the 10 CFR 71.4 definition of special form radioactive material.
NAC International 2.10-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.11 Fuel Rods This section is not applicable to the PALADIN package because it is not designed for the transport of fuel rods and will not be used for that purpose.
NAC International 2.11-1
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 2.12 Appendix 2.12.1 References
[2.1] Regulatory Guide 7.9, Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material, Revision 2, March 2005.
[2.2] NUREG-2216, Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Materials- Final Report, U.S. Nuclear Regulatory Commission, Spent Fuel Project Office, August 2020.
[2.3] Regulatory Guide 7.8, Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material, Revision 1, U.S. Nuclear Regulatory Commission, Office of Standards Development, March 1989.
[2.4] Regulatory Guide 7.6, Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels, Revision 1, March 1978.
[2.5] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NB, Class 1 Components, 2013 Edition.
[2.7] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section V, Nondestructive Examination, Current Edition.
[2.8] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits, 2013 Edition.
[2.9] Young, W.C., Roarks Formulas for Stress and Strain, 4th Edition, 1965, McGraw-Hill Book Company, New York
[2.10] Formulas for Stress and Strain, 7th Edition, Warren C. Young and Richard Budynas, McGraw-Hill Book Company, New York, 2002
[2.11] Control of Heavy Loads at Nuclear Power Plants, NUREG-0612, U. S. Nuclear Regulatory Commission, Washington, DC, 1980.
[2.12] ANSI N14.6, Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More, American National Standards Institute, Inc., New York, 1993.
[2.13] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Part D, Materials, 2013 Edition.
NAC International 2.12-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
[2.14] Data Analysis of ENSA/DOE Rail Cask Tests, Spent Fuel and Waste Disposition, SAND2018-13258R, Prepared for US Department of Energy, Spent Fuel and Waste Science and Technology by Sandia National Laboratories, November 19, 2018.
[2.15] Fischer, L. E., and Lai, W., Fabrication Criteria for Shipping Containers, NUREG/CR-3854, UCRL-53544, U.S. Nuclear Regulatory Commission, March 1985.
[2.16] Plasticity: Theory and Application, Alexander Mandelson, 1970, The McMillan Company
[2.17] ASM Handbook, Properties and Selection: Nonferrous Alloys and Special-Purpose Material, Volume 2, 1992, ASM International.
[2.18] Regulations for the Safe Transport of Radioactive Material, IAEA Specific Safety Requirements No. SSR-6, International Atomic Energy Agency, 2012.
[2.19] Blodgett, Omer W, Design of Welded Structures, The James F. Lincoln Arc Welding Foundation, Cleveland, Ohio, 1966.
[2.20] Stress Analysis of Closure Bolts for Shipping Casks, NUREG / CR-6007, U.S. Nuclear Regulatory Commission, April 1992.
[2.21] ASME Boiler & Pressure Vessel Code,Section IX, Welding and Brazing Qualifications, American Society of Mechanical Engineers, New York, Latest Edition.
[2.22] Oberg, et. al., Machinerys Handbook, 29th Edition, Industrial Press, Inc., New York, 2012.
[2.23] Regulatory Guide 7.11, Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m),
Revision 0, June 1991.
[2.24] Holman, W. R., and Langland, R. T., Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick, NUREG/CR-1815, UCRL-53013, U.S. Nuclear Regulatory Commission, August 1981.
[2.25] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1, Appendix I, Design Stress Intensity Values, Allowable Stresses, Material Properties, and Design Fatigue Curves, 2013 Edition.
[2.26] ASTM A-276-10, Standard Specification for Stainless Steel Bars and Shapes.
[2.27] Boyer, Howard E., Metals Handbook Desk Edition, American Society for Metals, Metals Park, Ohio, 1985.
[2.28] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NF, Supports, 2013 Edition.
[2.29] Bergman, V. L., Ammerman, D. J., An Analysis of Parameters Affecting Slapdown of Transportation Packages, Sandia Report SAND90-2187, Sandia National Laboratory, Albuquerque, NM, June 1991.
NAC International 2.12-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
[2.30] ARMCO 17-4 PH Stainless Steel Product Data Bulletin, AK Steel, West Chester Township, OH, 2018
[2.31] Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material, Revision 2, March 2005.
[2.33] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Part A, Ferrous Material Specifications, 2013 Edition.
NAC International 2.12-3
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 3 Thermal Evaluation Table of Contents 3 THERMAL EVALUATION ........................................................................................... 3-1 3.1 Description of Thermal Design ..................................................................................... 3.1-1 3.1.1 Design Features ................................................................................................. 3.1-1 3.1.2 Content Decay Heat .......................................................................................... 3.1-1 3.1.3 Summary Tables of Temperatures .................................................................... 3.1-1 3.1.4 Summary Table of Maximum Pressures ........................................................... 3.1-3 3.2 Material Properties and Component Specifications ...................................................... 3.2-1 3.2.1 Material Properties ............................................................................................ 3.2-1 3.2.2 Component Specifications ................................................................................ 3.2-1 3.3 Thermal Evaluation Under Normal Conditions of Transport ....................................... 3.3-1 3.3.1 Thermal Model Description .............................................................................. 3.3-1 3.3.2 Heat and Cold ................................................................................................... 3.3-6 3.3.3 Maximum Normal Operating Pressure ............................................................. 3.3-7 3.4 Thermal Evaluation Under Fire Accident Conditions .................................................. 3.4-1 3.4.1 Fire Test Conditions.......................................................................................... 3.4-1 3.4.2 Maximum HAC Temperatures and Pressure .................................................... 3.4-2 3.4.3 Maximum Thermal Stresses ........................................................................... 3.4-10 3.4.4 Accident Conditions for Fissile Material Packages for Air Transport ........... 3.4-10 3.5 Appendix ....................................................................................................................... 3.5-1 3.5.1 References ......................................................................................................... 3.5-1 NAC International 3-i
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Figures Figure 3.2-1 Seal Life at Temperature................................................................................... 3.2-3
Figure 3.3-1 Three-Dimensional Half Symmetry Finite Element Model.............................. 3.3-5
Figure 3.4-1 Maximum Temperature of External and Internal Surface of CV - HAC Fire .............................................................................................................. 3.4-6
Figure 3.4-2 Average Air Temperature Inside CV - HAC Fire ............................................ 3.4-7
Figure 3.4-3 Average Content Temperature Inside RV - HAC Fire ..................................... 3.4-8 Figure 3.4-4 Maximum Lid and Port Cover Seal Temperature - HAC Fire ......................... 3.4-9 NAC International 3-ii
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Tables Table 3.1-1 Temperature Limits of Packaging Components ......................................... 3.1-4
Table 3.1-2 Summary of Packaging Temperatures for NCT ......................................... 3.1-5
Table 3.1-3 Summary of Packaging Temperatures for HAC ......................................... 3.1-5 Table 3.1-4 Summary of Maximum CV Pressure for NCT and HAC ........................... 3.1-5
Table 3.2-1 Thermal Properties of Type 304 Stainless Steel ......................................... 3.2-2
Table 3.2-2 Thermal Properties of Carbon Steel ............................................................ 3.2-2
Table 3.3-1 Insolation Data ............................................................................................ 3.3-4 Table 3.3-2 Steady State NCT Temperatures ................................................................. 3.3-6 Table 3.4-1 Summary of HAC Boundary Conditions .................................................... 3.4-4 Table 3.4-2 Maximum Temperature of Components During HAC Fire ........................ 3.4-4
NAC International 3-iii
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3 THERMAL EVALUATION This section summarizes the thermal evaluation of the PALADIN transport package for the Normal Conditions of Transport (NCT) and Hypothetical Accident Condition (HAC) prescribed by 10 CFR 71 in Sections 3.3 and 3.4. The results of the thermal evaluations demonstrate that the packaging will remain within the applicable thermal limits, demonstrating the packages structural, containment, and shielding integrity is not negatively affected by the NCT and HAC thermal conditions.
NAC International 3-1
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.1 Description of Thermal Design The PALADIN packaging, shown in Figure 1-1, consists of a Containment Vessel (CV) with bolted closure and an Impact Limiter System (ILS). Narrative descriptions of these components are provided in Section 3.1.1.
3.1.1 Design Features Containment, shielding, and thermal protection of the radioactive contents is provided by the packagings Containment Vessel (CV). The CV is comprised of a body weldment, bolted closure lid, bolted port cover, and the associated lid and port cover fluorocarbon containment O-ring seals. The CV body is a solid Type 304 stainless steel weldment consisting of a cylindrical shell, a bottom plate, and a bolt flange. The body weldment has an outer diameter of at the top section, a diameter of at the bottom section and a total height of The lid is stainless steel plate and is secured to the body weldment by alloy steel bolts.
3.1.2 Content Decay Heat The PALADIN package is designed to transport one irradiated Reactor Vessel (RV) within the PALADIN CV. The stainless steel RV contains absorbent material (with absorbed residual water) and limited quantities of TRU and fissile waste. The heat generation of the RV is as discussed in Section 1.2.2. This is insignificant compared to other heat energy sources considered during NCT and HAC such as solar insolance and fire. As such, heat generation from the contents is not included in the thermal analyses.
3.1.3 Summary Tables of Temperatures Thermal design criteria are specified for the packaging components that are significant to the shielding and containment design. All operating temperature limits are based on the NAC International 3.1-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A performance requirements of the individual packaging components. These operating temperature limits of the package components that are significant to the shielding and containment design are outlined in Table 3.1-1, including the temperature requirements for maximum temperature on the package accessible surfaces that are specified in 10CFR71.43(g).
Normal Conditions of Transport Per the requirements of 10 CFR 71.71(c)(1), the CV package with RV is evaluated for NCT, as presented in Section 3.3. Specifically, steady state thermal analyses are performed simulating exposure of the package to a 100°F ambient temperature with insolation as specified in Table 3.3-1. The results of the analyses are presented in Section 3.3.2. The temperatures of key components are summarized and compared with their allowable temperatures in Table 3.1-2.
As presented in Table 3.1-2, the package components remain below their allowable temperatures for NCT. Therefore, when exposed to NCT, the structural, containment, and shielding performance of the package will not be adversely affected by the temperatures experienced under these conditions.
In accordance with 10 CFR 71.43(g) the maximum temperature on the accessible surface of the package in still air at 100qF and in the shade is limited to 185°F for exclusive use. As shown in Table 3.3-2, the maximum temperature of the accessible surface of the CV, when exposed to an ambient temperature of 100°F in still air and solar, is 122°F, which meets the requirement of 185°F temperature limit for exclusive use.
Hypothetical Accident Conditions Per the requirements of 10 CFR 71.73(c)(4), the package is evaluated for the HAC thermal test (i.e., HAC fire), as presented in Section 3.4. The results of the analyses are presented in Section 3.4.2. The temperatures of several key components of the CV are summarized and compared to their allowable temperatures in Table 3.1-3. The ILS is not credited for a containment, shielding, or thermal function during the HAC fire; therefore, it is not included in the summary.
As presented in Table 3.1-3, the package components remain below their allowable service temperatures for HAC, except the lid seal and port cover seal. However, the lid seal and port cover seal maintain margins of 29% and 81%, respectively, when evaluated against short-term temperature exposure limits as discussed in Section 3.4.2.1. Therefore, when exposed to HAC, the structural, containment, and shielding performance of the package will not be adversely affected by the temperatures experienced under these conditions.
NAC International 3.1-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.1.4 Summary Table of Maximum Pressures The summary of maximum internal pressures in the CV for NCT and HAC, calculated as described in Sections 3.3. and 3.4.2.2, respectively, is provided in Table 3.1-4. The maximum calculated internal pressure loads under NCT and HAC are 2.4 psig and 13.6 psig, respectively.
NAC International 3.1-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 3.1 Temperature Limits of Packaging Components NAC International 3.1-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 3.1 Summary of Packaging Temperatures for NCT Table 3.1 Summary of Packaging Temperatures for HAC Table 3.1 Summary of Maximum CV Pressure for NCT and HAC NAC International 3.1-5
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.2 Material Properties and Component Specifications 3.2.1 Material Properties The CV is fabricated primarily from Type 304 stainless steel, and aluminum or aluminum alloy for the impact limiter system (ILS) components. The ILS is not modeled for thermal analysis.
The RV is conservatively modeled as carbon steel, as it has higher emissivity and thermal conductivity which maximizes heat transfer into the RV and its contents via radiation and conduction during the fire accident condition and cooldown period afterwards. Table 3.2-1 and Table 3.2-2 provide the thermal properties for stainless steel and carbon steel that are used for the CV and RV, respectively. The contents of RV and backfill air between RV and CV are not modeled. Hence, the properties of these materials are not used.
3.2.2 Component Specifications The package components that are significant to the containment and shielding design are primarily stainless steel. The temperature limits of these components are summarized in Table 3.1-1. Otherwise, component maximum temperature limits are defined as the melting temperature of the material of construction. The minimum temperature limit for all components is -40°F.
NAC International 3.2-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 3.2 Thermal Properties of Type 304 Stainless Steel Table 3.2 Thermal Properties of Carbon Steel NAC International 3.2-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 3.2-1 Seal Life at Temperature NAC International 3.2-3
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.3 Thermal Evaluation Under Normal Conditions of Transport This section describes the thermal evaluation of the package under normal conditions of transport (NCT). The evaluation is conducted using analytical methods in accordance with 10 CFR 71 and Regulatory Guide 7.8 for the applicable NCT thermal loads. The results are compared with the allowable limits of temperature and pressure for the package components.
3.3.1 Thermal Model Description The containment vessel and reactor vessel are modeled using finite element code ANSYS v16.2
[3.4] to simulate thermal performance during NCT.
The three-dimensional (3D) half-symmetry model of the containment vessel and the reactor vessel is generated as shown in Figure 3.3-1. Details such as lid bolts, O-ring seal, outer impact band, standoffs, mounting rings, etc., that do not significantly affect the thermal performance of the containment vessel are not explicitly modeled. The temperature of the components that are not modeled explicitly are derived from the model at the location of the required components.
The CV body weldment and the inner impact band are modeled as stainless steel whereas the RV is modeled as carbon steel. The RV is conservatively modeled as carbon steel because it has higher emissivity and conductivity compared to stainless steel. Higher emissivity and conductivity results in conservatively higher temperatures for the RV and its contents. The backfill air between CV and RV is not modeled as the conductivity and density of air is insignificant to effectively transfer heat across the walls of CV and RV. Hence, the only mode of heat transfer between CV and RV is via radiation. The contents inside the RV are also not modeled as they are not significant to the thermal analysis. The total heat generation of the contents in the RV is which is negligible compared to solar insolation on the outer surfaces of the CV. Hence, only thermal load on the system during NCT is solar insolation and the heat transfer out of the CV is via natural convection.
The finite element model of the CV and RV is generated with the ANSYS Parametric Design Language (APDL) using a combination of SOLID70, SHELL57 and SURF152 element types.
Each of the element types used to model the package and the modes of heat transfer modeled by these elements are discussed in the following paragraphs.
The SOLID70 is a 3D, 8-node, single degree-of-freedom (DOF) thermal solid element and is used to model heat flow through the solid regions of the package via conduction heat transfer.
These elements are used to model solid components of CV and RV.
NAC International 3.3-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A The SURF152 3D thermal surface effect elements are overlaid onto area faces of the SOLID70 elements and are used to apply solar heat flux on the outer surfaces of the CV.
The SHELL57 3D thermal shell elements are overlaid onto area faces of the SOLID70 elements of the inner surfaces of CV and outer surface of RV. These elements are used to generate radiation matrix to apply radiation heat transfer between the two surfaces.
Application of Solar Insolance via Surface Heat Flux Solar insolance is applied on SURF152 elements that are laid on the outer surface of CV. The heat flux applied on CV cylindrical surface is based on 1475 Btu/ft2 per day for curved surfaces as per 10CFR71.71. For top and bottom surfaces, 737.5 Btu/ft2 is applied as per 10CFR71.71 for flat surfaces not transported horizontally.
Natural Convection During NCT, heat is rejected from the model via natural convection and thermal radiation boundary conditions. To simplify the application of boundary conditions, a single convection boundary condition is applied to each external surface of the package that has a convection coefficient (h) combining natural convection (hc) and thermal radiation (hr) based on the emissivity of that surface. This combined temperature-dependent convection coefficient (hc + hr) is defined for all external surfaces and stored in an ANSYS material property definition. The calculation of the radiation component (hr) of the total heat transfer coefficient is discussed below in the Thermal Radiation section.
The natural convection coefficient is calculated using the following equation [3.5]:
0.00132 'T/
- where,
' = temperature difference between CV surface and ambient (Ts - Tf)
Thermal Radiation As previously discussed, the convection boundary conditions applied to the model are a combination of both natural convection and thermal radiation coefficients. The thermal radiation coefficient (hr) is calculated by linearizing the radiation. Assuming a view factor of 1.0 with the NAC International 3.3-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A surroundings, the heat transfer rate by thermal radiation, Qrad, from a surface can be described as follows:
Q A T T
- where, H = emissivity, V = Stefan-Boltzmann constant (1.19 E -11 Btu/h-in²-°R),
A = surface area, Ts = surface temperature (°R), and Tf = temperature of surroundings (°R).
Due to the temperatures being raised to the 4th power in the previous equation, the heat transfer rate is nonlinear. Instead, treating the thermal radiation as a convection boundary condition and substituting hr (radiation coefficient) for hc (convection coefficient) yields the following linear equation [3.3]
Q hr AT T Setting the two equations for Qrad equal to each other yields the following equation:
hr AT T A T T Solving for the thermal radiation coefficient (hr) yields [3.3]:
hr T T T T NAC International 3.3-3
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 3.3 Insolation Data Total insolation for a 12-hour period Form and location of surface (g cal/cm²)
Flat surfaces transported horizontally; Base None Other surface 800 Flat surfaces not transported horizontally 200 Curved surfaces 400 NAC International 3.3-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 3.3 Three-Dimensional Half Symmetry Finite Element Model NAC International 3.3-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.3.2 Heat and Cold Per the requirements of 10 CFR 71.71(c)(1), the CV package with RV and its contents is evaluated for NCT heat and cold. For steady state NCT cold, the package is considered to be at a uniform temperature of -40°F throughout. No additional thermal analyses are required for NCT cold. For NCT heat, steady state thermal finite element analyses are performed, simulating exposure of the CV package to 100°F ambient temperature with insolation as specified in Table 3.3-1. The results of the analyses are presented as follows.
The maximum temperature of the CV during steady state NCT heat is The volumetric average temperature of the CV is and the average temperature of the air inside the CV is The maximum temperatures remain below the allowable temperatures for NCT for all package components.
Table 3.3-2 Steady State NCT Temperatures Components Temperature (°F)
Maximum CV temperature Average CV temperature Average CV air temperature NAC International 3.3-6
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.3.3 Maximum Normal Operating Pressure The Maximum Normal Operating Pressure (MNOP) as defined in 10 CFR 71.4 is the maximum gauge pressure that would develop in the containment system in a period of 1 year under the heat condition specified in 10 CFR 71.71(c)(1), in the absence of venting, external cooling by an ancillary system, or operational controls during transport. The MNOP is calculated by treating the air inside the CV as an ideal gas. The only significant pressure inside the CV results from the gas temperature changes after containment sealing. While residual water in an absorbent is retained within the RV inside the containment boundary, under normal conditions the temperature of the containment boundary and all package contents is well below the boiling point of water at 1 atm, producing no steam pressure, and no significant gas generation originating from the RV radionuclide decay energy deposition.
The average air temperature under steady state NCT heat conditions is Assuming a conservative initial backfill of atmospheric air the maximum air pressure inside the CV under steady state NCT is as calculated below.
- where, P1 = initial gas pressure in the CV, T1 = initial backfill gas temperature in the CV, T2 = steady state NCT average gas temperature in the CV, Due to the insignificant heat generation of the RV, which also has an initial backfill of atmospheric air, this pressure is also considered to be the maximum air pressure within the RV for steady state NCT.
NAC International 3.3-7
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.4 Thermal Evaluation Under Fire Accident Conditions The thermal performance of the package for the HAC fire prescribed in 10 CFR 71.73(c)(4) is assessed by performing transient heat transfer analyses using the same finite element model used for steady state NCT thermal analysis, described in Section 3.3.1. The transient thermal analysis is performed to simulate the fire accident condition for 30 minutes. After the 30-minute fire accident condition is complete, a transient analysis for a 24-hour cooldown period is conducted.
During the fire accident condition, the solar insolance on the outer surfaces of the CV is removed and the ambient temperature is set to 1475°F. The heat transfer coefficient and the emissivity of the CV surface are also modified. Additional details of the initial and boundary conditions used during the fire condition are discussed below. After the fire accident condition, the boundary conditions are changed back to NCT for 24-hours of cooldown.
3.4.1 Fire Test Conditions 3.4.1.1 Initial Conditions The maximum temperature of the steady state thermal condition of NCT heat is conservatively used as the initial temperature for the fire accident condition. Cumulative physical damage to the CV following the HAC free drop and puncture tests is limited to localized regions of permanent deformation that is considered insignificant to the thermal performance of the package in the HAC fire. As with the NCT analysis, the aluminum ILS components are not included in the model and are not credited for any function during HAC fire.
3.4.1.2 Boundary Conditions The following boundary conditions are applied to the model to simulate transient fire analysis and cooldown after fire. The boundary conditions applied are tabulated in Table 3.4-1.
30-minute fire (transient analysis):
x Convection heat transfer from the 1475°F environment to the CV external surfaces [3.6].
Conservatively, 50% higher convection heat transfer coefficient is applied.
1.5 0.012229166 'T/
x Thermal radiation exchange between the fire (1475°F) and the CV surfaces with emissivity of 0.9 for all surfaces.
hr T T T T NAC International 3.4-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A x Solar heat flux is not applied.
24-hour post-fire cool-down (transient analysis):
x Natural convection from the package external surfaces to the 100°F environment as discussed in Section 3.3.1 x Thermal radiation (emissivity of 0.36 for all CV external surfaces) to the 100°F environment as discussed in Section 3.3.1 x Solar heat flux as discussed in Section 3.3.1 Application of Boundary Conditions As discussed in Section 3.3.1, the convection coefficient (h) combining natural convection (hc) and thermal radiation (hr) is applied on the outer surface nodes of the CV. The ambient temperature during fire is 1475 °F with surface emissivity set to 0.9. During fire accident condition, the surface heat loads applied for solar insolance are removed.
After 30 minutes of the fire accident simulation is complete, the solar heat flux is reapplied on the outer surface elements of CV as a surface heat load. The ambient temperature is changed to 100 °F with surface emissivity of 0.36 and convection heat transfer coefficient for NCT is applied as discussed in Section 3.3.1.
3.4.2 Maximum HAC Temperatures and Pressure 3.4.2.1 Maximum HAC Temperature Results Per the requirements of 10 CFR 71.73(c)(4), the CV package with RV contents is evaluated for the hypothetical accident condition of fire. The results of the HAC thermal analysis are presented in this section for the key components of the CV and RV.
The maximum temperatures of the CV package exposed to fire accident are summarized in Table 3.4-2. Of particular interest for fire accident is the maximum temperatures of the CV O-rings seals for the lid and port cover, average bolt temperatures of the lid and port cover, peak temperatures of the CV outer and inner surfaces, and average CV temperature. Additionally, the average air temperature inside the containment vessel and average temperature of contents inside the RV are also tabulated to facilitate calculation of pressure inside the CV.
During the fire accident condition, the maximum temperature occurs on the outer surface of the CV. The maximum temperature of the inner and outer surfaces of the CV are evaluated at nodal locations on the respective surfaces. The average CV temperature is calculated as volumetric NAC International 3.4-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A average of all elements of the CV. The average CV air temperature is calculated as the volumetric average of inner surface elements of the CV as the air between the CV and RV is not explicitly modeled. This is conservative as the CV surface temperature is higher than the RV surface temperature during fire and cooldown, and will result in a higher average air temperature.
The average RV contents temperature is calculated as the volumetric average of inner surface elements of the RV. The bolts for both the CV lid and port cover are not explicitly modeled.
The average temperatures of the lid bolt and port cover bolt are calculated as the average of the points generated along the bolt length during post processing at the location of bolt.
The temperature time-histories of these components are also plotted for duration of the 30 minutes fire and subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of cooldown in Figures 3.4-1 to 3.4-4.
The remaining life of the lid and port-cover seals during and after the fire are calculated based on the temperature of each seal and the time duration at the particular temperature. The seal life at different temperatures as established by the seal manufacturer is shown in Figure 3.2-1.
Hence, the lid seal maintains 29%
margin and the port cover seal maintains 81% margin to the short-term temperature exposure limits.
NAC International 3.4-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 3.4 Summary of HAC Fire Boundary Conditions Solar Heat Convection coefficient Emissivity for Environment Flux (Btu/hr-in2-°F) Radiation Conditions Temperature, Boundary Boundary
°F Condition Condition NCT 100 Yes (pre-fire)
HAC 1475 No (fire)a HAC 100 Yes (post-fire)
Notes:
a The NCT maximum temperature is used as the initial temperatures for the HAC simulation b
As prescribed by 10 CFR 71.73(c)(4)
Table 3.4 Maximum Temperature of Components During HAC Fire Temperature Component
(°F)
Maximum CV outer surface temperature Maximum average CV temperature Maximum CV inner surface temperature Maximum RV temperature Maximum average CV air temperature Maximum average RV content temperature Maximum lid seal temperature Maximum port cover seal temperature Maximum average lid bolt temperature Maximum average port cover bolt temperature Notes:
(1)
- Maximum inner surface temperature of CV is conservatively used.
(2)
- Average temperature along the length of bolt is used.
NAC International 3.4-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.4.2.2 Maximum HAC Pressure Results The maximum pressure inside the CV during the fire accident condition and cooldown are determined using the same methodology as in Section 3.3.3, treating the air inside the CV as an ideal gas. The increase in average air temperature inside the CV results in additional pressure.
The steady state maximum air pressure is calculated as in Section 3.3.3. Conservatively applying an initial gas pressure of the maximum pressure during the fire accident is psig as calculated below.
- where, P1 = initial gas pressure in the CV, bounds MNOP)
T1 = initial gas temperature in the CV, 100°F (310.9K) (bounds NCT temperature of T2 = maximum average gas temperature in the CV, The average RV content temperature reaches a peak of approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after the start of the fire condition. This is above the boiling point of water in atmospheric conditions and could result in some of the residual water (contained within an absorbent) turning to vapor.
However, based on the properties of saturated steam, at the saturated pressure is only NAC International 3.4-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 3.4-1 Maximum Temperature of External and Internal Surface of CV - HAC Fire NAC International 3.4-6
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 3.4-2 Average Air Temperature inside CV - HAC Fire NAC International 3.4-7
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 3.4-3 Average Content Temperature inside RV - HAC Fire NAC International 3.4-8
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 3.4-4 Maximum Lid and Port Cover Seal Temperature - HAC Fire NAC International 3.4-9
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.4.3 Maximum Thermal Stresses Thermal Stresses of the package are addressed in Section 2.7.1.
3.4.4 Accident Conditions for Fissile Material Packages for Air Transport Not applicable.
NAC International 3.4-10
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 3.5 Appendix 3.5.1 References
[3.1] Parker, "O-Ring Handbook," ORD 5700, 2007.
[3.2] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Part D, Materials, 2013 Edition.
[3.3] F. P. Incropera and D. P. DeWitt, in Fundamentals of Heat and Mass Transfer, Fifth ed.,
New York, John Wiley & Sons, Inc., 2002.
[3.4] ANSYS Inc., "ANSYS, Release 16.2," Canonsburg, PA.
[3.5] Avallone, E.A, Baumesiter III, T., Standard Handbook for Mechanical Engineers, Ninth Edition, McGraw-Hill Book Company
[3.6] S.D. Wix, Proceedings Volume 2, The 11th International Conference on the Packaging and Transportation of Radioactive Materials (PATRAM95), pp 672-678, Convective Effects in a Regulatory and Proposed Fire Model, December, 1995.
[3.7] Rohsenw, W.M. and Hartnett, J.P., Handbook of Heat Transfer, McGraw-Hill
[3.8] Parker Hannifin Corporation, "Technical Bulletin No. ORD 5746, "VM835-75 for Aerospace Applications"," Lexington, KY, 2006.
NAC International 3.5-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 4 Containment Table of Contents 4 CONTAINMENT ............................................................................................................ 4-1 4.1 Description of the Containment System ....................................................................... 4.1-1 4.2 Containment Under Normal Conditions of Transport .................................................. 4.2-1 4.2.1 NCT Pressurization of the Containment Vessel ............................................... 4.2-1 4.2.2 NCT Containment Criterion ............................................................................. 4.2-1 4.2.3 Compliance with NCT Containment Criterion ................................................. 4.2-1 4.3 Containment Under Hypothetical Accident Conditions ............................................... 4.3-1 4.3.1 HAC Pressurization of the Containment Vessel ............................................... 4.3-1 4.3.2 HAC Containment Criterion ............................................................................. 4.3-1 4.3.3 Compliance with HAC Containment Criterion................................................. 4.3-1 4.4 Leakage Rate Tests for Type B Packages ..................................................................... 4.4-1 4.4.1 Fabrication Leakage Rate Test.......................................................................... 4.4-1 4.4.2 Maintenance Leakage Rate Test ....................................................................... 4.4-1 4.4.3 Periodic Leakage Rate Test .............................................................................. 4.4-1 4.4.4 Pre-shipment Leakage Rate Test ...................................................................... 4.4-1 4.5 Appendix ....................................................................................................................... 4.5-1 4.5.1 References ......................................................................................................... 4.5-1 NAC International i
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Figures Figure 4.1-1 Packaging Containment System ....................................................................... 4.1-3 NAC International ii
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 4 CONTAINMENT In accordance with the requirements of 10 CFR 71.43(f), the package is designed, constructed, and prepared for shipment to assure no loss or dispersal of radioactive contents as demonstrated to a sensitivity of 10-6 A2 per hour in accordance with 10 CFR 71.51(a)(1), no significant increase in external surface radiation levels (i.e., more than 20% of the maximum radiation level at any surface of the package), and no substantial reduction on the effectiveness of the packaging under the NCT tests specified in 10 CFR 71.71. In addition, the package is designed, constructed, and prepared for shipment to assure no escape of Krypton-85 exceeding 10 A2 in 1 week, no escape of radioactive material exceeding a total amount A2 in 1 week, and no external radiation dose rate exceeding 10 mSv/h (1 rem/h) at 1 m (40 in) from the external surface of the package under the HAC tests specified in 10 CFR 71.73, in accordance with the requirements of 10 CFR 71.51(a).
This chapter describes the packagings containment system design and how it meets the containment requirements under NCT and HAC tests and defines the criteria for leak rate testing during package fabrication, use, maintenance, and repair.
NAC International
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 4.1 Description of the Containment System The packaging has a simple, robust containment system design. Containment of radioactive material for the packaging is provided by the cask containment vessel (CV). The welds within the containment boundary are the full-penetration welds connecting the CV lower shell to the bottom plate, lower shell to the transition ring, transition ring to the upper shell, upper shell to the upper flange and longitudinal seam weld of the lower shell. Additionally, there is option to fabricate the upper flange and transition ring from multiple segments and then be welded together, also full-penetrating welds. Other than the CV lid closure and port cover closure, there are no penetrations to the containment system, and no valves or pressure relief devices of any kind. In accordance with the requirements of 10 CFR 71.51(c), the packaging does not rely on any filter or mechanical cooling system to meet containment requirements, nor does the containment system include any vents or valves that allow for continuous venting.
The CV is comprised of a body weldment, bolted closure lid, bolted port cover, and the associated lid and port cover containment O-ring seals. A sketch of the CV is included in Figure 4.1-1, with the pressure-retaining boundary. The top view is simplified to only show the components significant to the containment system, removing details such as test ports, lifting locations, and alignment pins.
The CV body is a solid Type 304 stainless steel weldment consisting of a cylindrical shell, a bottom plate, and a bolt flange. The CV upper and lower cylindrical shells are rolled from plate and formed into a cylinder by a full-penetration longitudinal seam weld.
The transition ring is a forging. The bottom plate and bolt flange are connected to the cylindrical shell by full-penetration circumferential welds. The bolt flange includes threaded bolt holes to accommodate the CV lid bolts. The portion inboard of the bolt holes forms the sealing surface for the CV lid closure O-ring seals.
The CV lid is a solid austenitic stainless steel (Type 304) plate with a stepped-edge design preventing any significant shear loading of the CV closure bolts. The CV lid has machined bolt holes, two (2) concentric O-ring grooves, O-ring test port, and a port that is used for WKHPDLQWHQDQFHDQGSHULRGLFOHDNDJHUDWHWHVWLQJ. The CV lid is secured to the
&9body by (ASME SA574 Gr. 4340) socket head cap screws (i.e., lid bolts).
The CV port cover, which fits flush into the port opening of the CV lid, is also a solid austenitic stainless steel (Type 304) plate, with machined bolt holes, two (2) concentric O-ring grooves, and two (2) O-ring test ports. The CV port cover fits over a quick-connect fitting attached to the CV port, filling most of the void space to maximize shielding efficiency. No credit is taken for NAC International 4.1-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A containment provided by the CV port quick-connect fitting. The CV port cover is attached to the CV lid by socket head cap screws (i.e., port cover bolts).
Both the CV lid and port cover O-ring grooves include a shallow undercut between the inner and outer grooves to prevent metal-to-metal contact and reduce the dwell time required for leakage rate testing. The CV lid and port cover O-ring grooves are both fitted with The inner O-rings form the leak-tight containment seal for the lid and the outer O-rings are used to facilitate leakage rate testing of the assembled closure.
The CV is designed, fabricated, examined, tested, and inspected in accordance with the applicable requirements of Subsection NB of the ASME Code [4.1] with certain exceptions discussed in Chapter 2. The containment system materials of construction are evaluated in Section 2.2.1 and selected to avoid chemical, galvanic, or other reactions, discussed in Section 2.2.2. The materials of construction are compatible with each other and the chemical form of the payload.
NAC International 4.1-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 4.1-1 Packaging Containment System NAC International 4.1-3
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 4.2 Containment Under Normal Conditions of Transport 4.2.1 NCT Pressurization of the Containment Vessel The package maximum normal operating pressure (MNOP) was calculated to be gauge, with structural evaluation and fabrication testing being based on an MNOP of . Section 3.3.2 further discusses the NCT pressurization.
4.2.2 NCT Containment Criterion The package is designed to a leaktight containment criterion per ANSI N14.5 [4.3]. Therefore, the containment criterion is 1x10-7 ref cm3/sec.
4.2.3 Compliance with NCT Containment Criterion Compliance with the NCT containment criterion is demonstrated by analysis. The structural evaluation in Section 2.6 shows there would be no loss or dispersal of radioactive contents, and that the containment boundary, seal region, and closure bolts do not undergo any inelastic deformation when subjected to the conditions of 10 CFR 71.71. The thermal evaluation in Section 3.3.1 shows the seals, bolts and containment system materials of construction do not exceed their temperature limits when subjected to the conditions of 10 CFR 71.71.
NAC International 4.2-1
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 4.3 Containment Under Hypothetical Accident Conditions 4.3.1 HAC Pressurization of the Containment Vessel The containment evaluation for HAC is conservatively based on a maximum pressure of 100 psig. Calculated HAC maximum package pressure is gauge as determined in Section 3.4.3.2.
4.3.2 HAC Containment Criterion The packaging is designed to a leaktight containment criterion per ANSI N14.5 [4.3].
Therefore, the containment criterion is 1x10-7 ref cm3/sec.
4.3.3 Compliance with HAC Containment Criterion Compliance with the HAC containment criterion is demonstrated by analysis. The structural evaluation in Section 2.7 shows there would be no loss or dispersal of radioactive contents, and that the containment boundary, seal region, and closure bolts do not undergo any inelastic deformation when subjected to the conditions of 10 CFR 71.73. The thermal evaluation in Section 3.4.3 shows the seals, bolts and containment system materials of construction do not exceed their temperature limits when subjected to the conditions 10 CFR 71.73.
NAC International 4.3-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 4.4 Leakage Rate Tests for Type B Packages 4.4.1 Fabrication Leakage Rate Test The CV assembly is tested during fabrication, prior to first use, to demonstrate the leakage rate of the containment system, as fabricated, does not exceed 1x10-7 ref cm3/sec. The maximum allowable sensitivity for the fabrication leakage rate test is half of the required 1x10-7 ref cm3/sec test criterion (i.e., 5x10-8 ref-cm3/sec). The fabrication leakage rate test requirements are further described in Section 8.1.4.
4.4.2 Maintenance Leakage Rate Test The CV assembly is tested after maintenance of the CV assembly to confirm the leakage rate of the containment system after maintenance, repair, or replacement of components does not exceed 1x10-7 ref cm3/sec. The maximum allowable sensitivity for the maintenance leakage rate test is half of the required 1x10-7 ref cm3/sec test criterion (i.e., 5x10-8 ref-cm3/sec). The maintenance leakage rate testing and the replacement or repair activities requiring a maintenance leak rate test are further described in Section 8.2.2.1.
4.4.3 Periodic Leakage Rate Test The CV assembly is tested within 12 months prior to each shipment to confirm the leakage rate of the containment system does not exceed 1x10-7 ref cm3/sec. The maximum allowable sensitivity for the maintenance leakage rate test is half of the required 1x10-7 ref cm3/sec test criterion (i.e., 5x10-8 ref-cm3/sec). The periodic leakage rate test requirements are further described in Section 8.2.2.1.
4.4.4 Pre-shipment Leakage Rate Test Each packaging is tested prior to shipment to confirm the containment system is properly assembled for shipment. The pre-shipment leakage rate test is performed using the gas pressure drop or rise method in ANSI N14.5, Sections A.5.1 or A.5.2, following the steps outlined in Section 7.1.3. The acceptance criterion for the pre-shipment leak test is no detected leakage when tested to a sensitivity of at least 1x10-3 ref-cm3/sec. The pre-shipment leakage rate test requirements are further described in Section 8.2.2.2.
NAC International 4.4-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 4.5 Appendix 4.5.1 References
[4.1] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NB, Class 1 Components, 2010 Edition with 2011 Addenda.
[4.2] Parker Hannifin Corporation, Parker O-Ring Handbook, ORD 5700/USA, 2007.
[4.3] ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014.
NAC International 4.5-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 5 Shielding Evaluation Table of Contents 5 SHIELDING EVALUATION ......................................................................................... 5-1
5.1 Description of Shielding Design ................................................................................... 5.1-1
5.1.1 Shielding Design Features ................................................................................ 5.1-1
5.1.2 Summary of Maximum Radiation Levels ......................................................... 5.1-1
5.2 Source Specification ..................................................................................................... 5.2-1
5.2.1 Gamma Source .................................................................................................. 5.2-1 5.2.2 Neutron Source ................................................................................................. 5.2-1 5.3 Shielding Model ............................................................................................................ 5.3-1
5.3.1 Configuration of Source and Shielding............................................................. 5.3-1 5.3.2 Material Properties ............................................................................................ 5.3-2 5.4 Shielding Evaluation ..................................................................................................... 5.4-1
5.4.1 Methods............................................................................................................. 5.4-1 5.4.2 Input and Output Data ....................................................................................... 5.4-1 5.4.3 Flux-to-Dose Rate Conversion ......................................................................... 5.4-2 5.4.4 External Radiation Levels ................................................................................. 5.4-2 5.5 Appendices ................................................................................................................... 5.5-1 5.5.1 References ......................................................................................................... 5.5-1 5.5.2 Example Cases .................................................................................................. 5.5-2 NAC International 5-i
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Figures Figure 5.3-1 MCNP Shielding Model - Package Geometry ................................................. 5.3-4 Figure 5.3-2 MCNP Shielding Model - Axial Source/Shield Configuration ........................ 5.3-5 Figure 5.3-3 MCNP Shielding Model - Radial Source/Shield Configuration ...................... 5.3-5 Figure 5.4-1 Radial Surface Dose Rate Profile - F2 Tally .................................................... 5.4-5 Figure 5.4-2 Radial Surface Dose Rate Profile - Mesh Tally (mrem/hr) .............................. 5.4-6 Figure 5.4-3 Radial 2 meter Dose Rate Profile - F2 Tally .................................................... 5.4-7 Figure 5.4-4 Radial 2 meter Dose Rate Profile - Mesh Tally (mrem/hr) .............................. 5.4-8 NAC International 5-ii
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Tables Table 5.1-1 Package Shielding Design Features .................................................................. 5.1-2 Table 5.1-2 Package Maximum Dose Rates ........................................................................ 5.1-2 Table 5.2-1 Reactor Vessel Relative Source by Region ...................................................... 5.2-2 Table 5.2-2 Reactor Vessel Relative Axial Source .............................................................. 5.2-2 Table 5.3-1 Primary MCNP Model Package Dimensions ................................................... 5.3-3 Table 5.3-2 Material Compositions ...................................................................................... 5.3-3 Table 5.4-1 ANSI/ANS-6.1.1 1977 Flux-to-Dose Conversion Factors ............................... 5.4-3 Table 5.4-2 MCNP Dose Rate Summary ............................................................................. 5.4-4 NAC International 5-iii
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5 SHIELDING EVALUATION The PALADIN packaging is designed to provide adequate shielding to ensure that dose rates do not exceed the NCT and HAC limits specified in 10 CFR 71.47(b), 10 CFR 71.51(a)(1) and 10 CFR 71.51(a)(2), respectively. This chapter outlines the shielding design of the packaging and the shielding analysis that demonstrates compliance with the dose rate limits of 10 CFR 71.
NAC International 5-1
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.1 Description of Shielding Design 5.1.1 Shielding Design Features 7KHSDFNDJLQJGHVLJQLVFRPSULVHGRIWKHFRQWDLQPHQWYHVVHODQGLPSDFWOLPLWHUFRPSRQHQWV
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NAC International 5.1-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 5.1 Package Shielding Design Features Nominal Material of Density, Packaging Component Thickness, Construction (g/cm3)
(in [cm])
Body CV Bottom Plate Stainless Steel 8.03 Lid Table 5.1 Package Maximum Dose Rates Transport Dose Rate Location Dose Rate Limit Condition (mrem/hr) (mrem/hr)
NCT Side Surface of CV 33.0 1000 2m from Skid - Radial 8.8 10 Dose at Cab of Transport Vehicle* <0.2 2 HAC/TI Side 1m 14.7 1000
- The bottom surface detector is conservatively used for this dose rate location.
NAC International 5.1-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.2 Source Specification The radioactive contents of the package are based on activation and crud inventory of the various reactor vessel components. Crud contamination activity is not a significant source (Ci) component. Primary gamma emission source are the various metal activation components.
Co-60, Fe-55, and Ni-63 comprise 99+% of the source activity for the vessel with the Co-60 inventory accounting the only significant gamma source component.
5.2.1 Gamma Source Source magnitudes as a function of gamma energy bin are calculated in the ORIGEN module of the SCALE code package, version 6.2.4 [5.1] for the complete set of radionuclides. More than 99.9% of the gamma source (MeV/sec) occurs in the energy bins associated with Co-60 decay.
Rather than modeling the full source spectrum, only the source magnitude in the two high energy gamma bins associated with Co-60 decay (1.173 and 1.332 MeV) are retained (i.e., the 1.0 to 1.33 and 1.33 to 1.66 MeV ORIGEN bins). This will discard low magnitude and/or low energy
(<0.5 MeV) lines that will not significantly impact cask shielding evaluations. The source magnitude from the two bins, rounded up to is then evenly assigned to the Co-60 1.17 and 1.33 MeV gamma lines. The source is distributed by source region according to the factors in Tables 5.2-1 and 5.2-2.
5.2.2 Neutron Source There is no significant neutron source associated with the reactor vessel.
NAC International 5.2-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 5.2 Reactor Vessel Relative Source by Region Region Fraction Thickness (inch)
Core Barrel (Inner Cylinder) 0.7284 Thermal (Intermediate) Shield 0.2281 Vessel Clad 0.0169 Vessel 0.0266 Table 5.2 Reactor Vessel Relative Axial Source Vessel Source Region Axial Region Body Clad Upper (88.6-inch height) 0.01 0.03 Middle (88.7-inch height) 0.93 0.93 Lower (Hemisphere) 0.06 0.04 NAC International 5.2-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.3 Shielding Model The following subsections describe the MCNP shielding model geometry and source configuration for all dose rate calculations of the package.
5.3.1 Configuration of Source and Shielding 5.3.1.1 MCNP Shielding Model - Package Geometry The MCNP model package geometry for the dose rate calculations is based on the dimensions provided in the package licensing drawings. Additional features and attachments of the CV are neglected (trunnions, etc.). All bolts and inserts in the CV lid are modeled as the same material as the component (SS).
The thickness of the CV body side wall, base, and lid are modeled at their nominal thicknesses.
Section 5.4 documented dose rates are significantly below regulatory limits except for those associated with the lower shell section of the CV. This section is constructed from ASME SA240 4-inch stainless steel plate. This plate has a negligible (0.01 inch) negative thickness tolerance which would, even if applied, not significantly change reported dose rates.
The package MCNP model geometry is shown in Figure 5.3-1, including all significant axial and radial shield thickness dimensions, with dimensions listed in Table 5.3-1. As noted previously, the NCT and HAC models are identical. The large aluminum impact limiter sections are not included in the NCT and HAC analysis. Small amounts of aluminum present on the top shell and transition region to the lower shell are included in the NCT and HAC models. The removal of aluminum for HAC, as a result of the fire accident, would have no significant impact on the conclusion of the HAC shielding analysis.
5.3.1.2 MCNP Shielding Model - Source Geometry The axial and radial extent of the source regions listed in Table 5.2-1 are modeled explicitly as shown in Figures 5.3-2 and 5.3-3.
5.3.1.3 MCNP Shielding Model - Tally Locations The MCNP dose rate calculations utilize cylindrical F2 tallies at the CV surface and at distances of 1-meter, 2-meters, and 4-meters from the cask surface. The CV is also enclosed with a mesh (F4) detector to capture any azimuthal variations in dose rate, particularly due to the CV standoffs. An RZT mesh is used for the surface mesh detector. An XYZ mesh is used for the dose rate at 2m from the vertical planes projected by the outer edges of the vehicle. The radial (side) 2-meter tally location is based on a 13-foot trailer width.
NAC International 5.3-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.3.2 Material Properties The only materials defined for the MCNP shielding models is SS-304 and aluminum. The composition and density of these materials are summarized in Table 5.3-3.
NAC International 5.3-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 5.3 Primary MCNP Model Package Dimensions Dimension Dimension (in [cm])
Cavity Height Upper Cavity Diameter Lower Cavity Diameter CV Wall Thickness Base Thickness Lid Thickness Table 5.3 Material Compositions SS304 (8.03 g/cm3)
Element ZAID Composition (wt%)
C 6000 0.00080 Mn 25000 0.02000 P 15000 0.00045 S 16000 0.00030 Si 14000 0.01000 Cr 24000 0.19000 Ni 28000 0.09500 Fe 26000 0.68345 3
Aluminum (2.6989 g/cm )
Element ZAID Composition (wt%)
Al 13000 1.00000 NAC International 5.3-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 5.3 MCNP Shielding Model - Package Geometry NAC International 5.3-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 5.3 MCNP Shielding Model - Axial Source/Shield Configuration Figure 5.3 MCNP Shielding Model - Radial Source/Shield Configuration NAC International 5.3-5
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.4 Shielding Evaluation 5.4.1 Methods For this dose rate analysis, the MCNP6 particle transport code is used to calculate external dose rates for the package and to demonstrate compliance with the regulatory dose rate limits in 10 CFR 71.
5.4.1.1 Computer Codes - MCNP6 Dose rate calculations for this analysis are performed using MCNP6 [5.2]. MCNP is a Monte Carlo radiation-transport code that tracks multiple particle types. For the dose rates determined herein, MCNP is used to tally photon fluxes in specific regions of interest, to calculate the resulting dose rates at each regulatory dose rate location.
5.4.1.2 MCNP - Variance Reduction Due to the thick layers of shielding provided by the CV and to aid in the statistical convergence of all tallies, mesh-based weight windows are used. Mesh based weight windows provide particle weight control and aid in tally convergence by splitting or rouletting particles if they are outside the specified weight range in the spatial region of the model. Additional discussion on the weight window variance reduction method is provided in the MCNP manual.
5.4.1.3 Dose Rate Calculations Dose rates are calculated in MCNP as described below. The dose rate is calculated in MCNP by tallying the particle flux at each dose rate location and applying flux-to-dose rate conversion factors (see Table 5.4-1).
5.4.2 Input and Output Data Input data for source terms and geometry/materials are summarized in Sections 5.2 and 5.3, respectively. Due to the cylindrical and spherical source regions, separate MCNP runs are used to appropriately capture the source geometry and source strength of these regions.
The tally fluctuation chart and probability density function plot were studied for each MCNP tally to ensure proper tally bin convergence. This, along with a check of the reported fractional standard deviation () for each tally bin and the additional statistical information reported for MCNP tallies, ensures the reliability of all MCNP calculated dose rate results.
NAC International 5.4-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.4.3 Flux-to-Dose Rate Conversion Consistent with guidance of Section 5.5.4.3 of NUREG-1617 [5.3], the ANSI/ANS-6.1.1 1977
[5.4] gamma flux-to-dose rate conversion factors are used. The specific values are listed in Table 5.4-1.
5.4.4 External Radiation Levels Maximum and average dose rates are summarized in Table 5.4-2. As expected, axial dose rates are significantly smaller than radial dose rates. All dose rates meet 10 CFR 71 limits. As noted previously, there is no difference in models for NCT or HAC. Axial dose rate profiles on the radial (side) surface and at 2 meters from the transport vehicle are shown in Figures 5.4-1 and 5.4-3, respectively.
Due to source distribution and cask design, the maximum dose rate is seen below the midplane of the package with azimuthal peaking between the internal standoffs. The standoffs provide substantial additional shielding as they are solid bars and the surface dose rate profile plotted on a theta-z basis clearly shows these peaks (Figure 5.4-2). At the 2-meter plane, due to orientation of the standoffs and the cylindrical source and cask shape, the peak dose rate area takes an ellipsoid shape with a peak at the cask center (see Figure 5.4-4).
NAC International 5.4-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 5.4 ANSI/ANS-6.1.1 1977 Flux-to-Dose Conversion Factors Gamma Energy Conversion Factor (MeV) (mrem/hr)/(J/cm2-s) 0.01 3.96E-03 0.03 5.82E-04 0.05 2.90E-04 0.07 2.58E-04 0.10 2.83E-04 0.15 3.79E-04 0.20 5.01E-04 0.25 6.31E-04 0.30 7.59E-04 0.35 8.78E-04 0.40 9.85E-04 0.45 1.08E-03 0.50 1.17E-03 0.55 1.27E-03 0.60 1.36E-03 0.65 1.44E-03 0.70 1.52E-03 0.80 1.68E-03 1.00 1.98E-03 1.40 2.51E-03 1.80 2.99E-03 2.20 3.42E-03 2.60 3.82E-03 2.80 4.01E-03 3.25 4.41E-03 3.75 4.83E-03 4.25 5.23E-03 4.75 5.60E-03 5.00 5.80E-03 5.25 6.01E-03 5.75 6.37E-03 6.25 6.74E-03 6.75 7.11E-03 7.50 7.66E-03 9.00 8.77E-03 11.0 1.03E-02 13.0 1.18E-02 15.0 1.33E-02 NAC International 5.4-3
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 5.4 MCNP Dose Rate Summary Dose Rate Location Maximum Average (mrem/hr) (mrem/hr)
Side Surface of CV 2.80E+01* 1.21E+01 Top Surface of CV 1.62E-05 2.09E-06 Bottom Surface of CV 1.33E-01 1.80E-02 2m from Skid - Radial 8.62E+00 3.47E+00 Side 1m (Transport Index) 1.47E+01 5.82E+00 Azimuthal average is listed. The azimuthal peak is 33.0 mrem/hr.
Azimuthal average is listed. The azimuthal peak is 8.78 mrem/hr.
NAC International 5.4-4
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 5.4 Radial Surface Dose Rate Profile - F2 Tally 30 25 20 DoseRate(mrem/hr) 15 Total Cylinder Sphere 10 5
0 100 0 100 200 300 400 500 600 700 Z(cm)
NAC International 5.4-5
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 5.4 Radial Surface Dose Rate Profile - Mesh Tally (mrem/hr)
NAC International 5.4-6
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 5.4 Radial 2 meter Dose Rate Profile - F2 Tally 10 9
8 7
6 DoseRate(mrem/hr) 5 Total Cylinder Sphere 4
3 2
1 0
200 100 0 100 200 300 400 500 600 700 800 Z(cm)
NAC International 5.4-7
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Figure 5.4 Radial 2 meter Dose Rate Profile - Mesh Tally (mrem/hr)
NAC International 5.4-8
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.5 Appendices 5.5.1 References
[5.1] Oak Ridge National Laboratory, SCALE Code System, ORNL/TM-2005/39, Version 6.2.4, 2020.
[5.2] Los Alamos National Laboratory, MCNP Users Manual, Code Version 6.2, LA-UR-17-29981, Rev. 0, 2017.
[5.3] U.S. Nuclear Regulatory Commission, "Standard Review Plan for Transportation Packages for Spent Nuclear Fuel," NUREG-1617, 2000.
[5.4] American Nuclear Society, Neutron and Gamma Flux-To-Dose Conversion Factors, ANSI/ANS 6.1.1-1977, 1977.
[5.5] Pacific Northwest National Laboratory, Compendium of Material Composition Data for Radiation Transport Modeling, PNNL-15780, Rev. 2, 2021.
NAC International 5.5-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 5.5.2 Example Cases 5HVHUYHGIRU)XWXUH8VH NAC International 5.5-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 6 Criticality Evaluation Table of Contents 6 CRITICALITY EVALUATION ..................................................................................... 6-1 NAC International 6-i
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 6 CRITICALITY EVALUATION The PALADIN package complies with the fissile material exemption requirements of 10 CFR 71.15. Therefore, the fissile material requirements of 10 CFR 71.55 and 10 CFR 71.59 do not apply and a criticality evaluation is not required.
NAC International 6-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 7 Package Operations Table of Contents 7 PACKAGE OPERATIONS ............................................................................................. 7-1 7.1 Package Loading ........................................................................................................... 7.1-1 7.1.1 Preparation for Loading .................................................................................... 7.1-1 7.1.2 Loading of Contents.......................................................................................... 7.1-4 7.1.3 Preparation for Transport .................................................................................. 7.1-4 7.2 Package Unloading ....................................................................................................... 7.2-1 7.2.1 Receipt of Package from Carrier....................................................................... 7.2-1 7.2.2 Removal of Contents......................................................................................... 7.2-2 7.3 Preparation of Empty Packaging for Transport ............................................................ 7.3-1 7.4 Railcar Design and Certification Requirements ........................................................... 7.4-1 7.4.1 Railcar and Tie-Down Design Requirements ................................................... 7.4-1 7.4.2 Railcar Tie-Down Design Loadings ................................................................. 7.4-1 7.4.3 Railcar and Tie-Down Certification.................................................................. 7.4-1 7.5 Appendix ....................................................................................................................... 7.5-1 7.5.1 References ......................................................................................................... 7.5-1 NAC International 7-i
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 7 PACKAGE OPERATIONS This chapter outlines the operations used to load the PALADIN transportation packaging and prepare it for transport (Section 7.1), unload the package (Section 7.2), and prepare the empty packaging for transport (Section 7.3). It presents the fundamental operating steps in the order they are performed. The operating steps are intended to ensure the package is properly prepared for transport, consistent with the package evaluation in Chapters 2 through 6, and to ensure that occupational exposure rates are as low as reasonably achievable (ALARA).
These procedures are based on generic site conditions. Additional operations and/or modifications (i.e., sequence of operations, use of parallel operations, etc.) to these procedures to address site-specific conditions may be required for each users facility. These additional operations and/or modifications will be documented in site-specific procedures.
In addition, site-specific procedures may incorporate signoffs for activities or operational sequences as they are performed. Oversight organizations, such as Quality Assurance or Quality Control, may participate in certain package handling operations. The use of signoffs can assist the user in assuring critical steps are not overlooked, that the package is handled in accordance with the CoC and Package SAR (SAR), and that appropriate records are retained as required by 10 CFR 71.91.
It is the responsibility of the package user to prepare detailed operating procedures based on the operating procedures described in this chapter, the requirements of the Certificate of Compliance, and any applicable site specific conditions and requirements. In addition, each licensee is responsible for providing advance notification in accordance with 10 CFR 71.97(b) for Type B shipments of quantities of normal form radioactive material being transported across a state boundary enroute to a disposal facility or to a collection point for transport to a disposal facility exceeding 3000 A2.
All contents to be shipped shall satisfy the requirements for type and form of material, maximum quantity of contents per package, and loading restrictions described in Section 1.2.2.
Furthermore, the total radioactive decay heat of the contents shall not exceed watts.
When the package is handled in accordance with the procedures provided and loaded within the conditions of the CoC and the SAR, the resulting occupational exposures will be maintained as low as reasonably achievable (ALARA), as required by 10 CFR 20.1101(b)
NAC International 7-1
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 7.1 Package Loading This section describes loading-related preparations, tests, and inspections for the packaging.
These include the inspections made before loading the packaging to determine it is not damaged, and radiation and surface contamination levels are within the regulatory limits.
7.1.1 Preparation for Loading This section describes the operations for preparing the package for loading. It is the responsibility of the packaging user to verify the contents are authorized in accordance with the Certificate of Compliance (CoC) and the package is loaded and closed in accordance with detailed written procedures that are based on the operating procedures described in this chapter, the requirements identified in the Certificate of Compliance, and any applicable site requirements.
The PALADIN transportation package is transported by highway, rail and sea in a horizontal orientation. The package is tied down to a custom-designed transport skid and secured to a heavy-haul truck, railcar or barge. Stacking of PALADIN transportation packages is prohibited.
Loading operations for the PALADIN transportation package shall be performed in a precipitation-free environment, or measures shall be taken to prevent precipitation from entering the package cavities, such as performing loading operations under a protective cover. If standing water collects inside the CV cavity, absorbent materials or another suitable method, such as a vacuum system, shall be used to remove the free-standing water from the CV cavity and, which may require the contents to be unloaded.
The only special equipment required for the loading and unloading operations of the package, other than standard sockets and wrenches for fasteners, equipment used to lift the packaging components, a radioactive contamination detector, and a radiation survey meter, are the pre-shipment leakage rate testing apparatus, and the PALADIN CV lift adapter.
Appropriate controls shall be used for all loading and unloading operations to prevent the spread of radioactive contamination and ensure personnel exposure remains minimized.
The general procedure for preparing each packaging for loading is as follows:
- 1. Upon receipt of the packaging, perform radiation and removable contamination surveys of the packaging in accordance with facility procedures and the requirements of 49 CFR 173.441 and 49 CFR 173.443. Clean or decontaminate the packaging as necessary in accordance with facility procedures.
- 2. Move the transport vehicle with the packaging to the receiving area and secure the transport vehicle.
NAC International 7.1-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 3. Visually inspect the exterior surfaces of the packaging for any signs of damage to verify the packaging is in unimpaired physical condition.
- 4. Remove the tamper-indicating seal from the packaging.
- 5. Attach the upper impact limiter rigging to an upper impact limiter section.
- 6. Loosen and remove all hex head nuts from the upper impact limiter section.
- 7. Loosen and remove all threaded rods from the upper impact limiter section.
- 8. Detach the upper impact limiter section and move it to the designated storage location.
- 9. Remove the alignment pins from the upper impact limiter section.
- 10. Repeat Steps 5 through 9 until all upper impact limiter sections have been removed.
- 11. Attach the impact limiter lift yoke to the lower impact limiter.
- 12. Loosen and remove all hex head nuts from the lower impact limiter.
- 13. Loosen and remove all threaded rods from the lower impact limiter.
- 14. Detach the lower impact limiter and move it to the designated storage location.
- 15. Remove all lower impact limiter alignment pins.
- 16. Attach rigging to the center impact limiter.
- 17. Loosen and remove all hex head nuts from the center impact limiter.
- 18. Loosen and remove all threaded rods from the center impact limiter.
- 19. Lift the center impact limiter and move it to the designated storage location.
- 21. Attach rigging to the skid canopy.
- 22. Lift the skid canopy vertically and move it to the designated storage location.
- 23. Attach the CV lift adapter to the CV lid.
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 25. Rotate/lift the CV to the vertical orientation and raise the CV off the blocks of the rear support structure of the transport skid.
- 26. Place the CV in the vertical orientation in a decontamination area or other suitable location identified by the user.
- 27. Loosen and remove all CV lid closure bolts.
- 28. Lift the CV lift adapter and CV lid assembly to a designated storage location.
Caution: When handling the CV lid, the O-ring and associated sealing surfaces shall be protected from damage.
- 29. If required, loosen and remove all CV port cover bolts and remove the CV port cover and place it in the designated temporary storage location.
Caution: When handling the CV port cover, the O-ring and associated sealing surfaces shall be protected from damage.
- 30. If required, remove the plugs from the CV lid and port cover test ports and place them in the temporary storage location.
- 31. Visually inspect the CV lid O ring seals for signs of damage or defects (e.g., cracks, tears, cuts, or discontinuities) that may prevent them from sealing properly when the package is assembled. Also, if the CV port cover was removed, inspect the CV port cover O-ring seals. Replace any damaged or defective O-ring seals with new O-ring seals in accordance with the requirements of the Maintenance Program described in Section 8.2.3.1.
Note: A maintenance leakage rate test is required for any replaced CV lid or vent port containment O-ring, per Section 8.2.2.1.
- 32. Clean and visually inspect the sealing surface for the CV lid (i.e., the area of the CV body bolt flange inboard of the CV lid bolt holes), for wear and/or damage (e.g., scratches, gouges, nicks, cracks, etc.) that may prevent the containment O-rings from sealing properly. If the CV port cover was removed also clean and visually inspect the sealing surface (i.e., the area of the CV lid port opening inboard of the CV port cover bolt holes) for wear and/or damage (e.g., scratches, gouges, nicks, cracks, etc.) that may prevent the containment O-rings from sealing properly
- 33. If required, coat the exposed surfaces of the CV lid and CV port cover O-ring seals with vacuum grease prior to assembling the package to minimize deterioration or cracking of the NAC International 7.1-3
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A seal during use. Remove excess vacuum grease from the O-rings prior to assembling the package.
- 34. Visually inspect the CV lid bolts, CV port cover bolts, and test port plugs for signs of excessive wear and/or damage. Repair or replace any damaged bolts in accordance with the requirements of the Maintenance Program described in Section 8.2.3.3 [7.1].
7.1.2 Loading of Contents This section describes the operations for loading the contents into the package and closing the package. The general procedure for loading the contents into the package and closing each package is as follows:
- 1. Confirm that the contents to be loaded meet the requirements of the Certificate of Compliance.
- 2. Verify that the packaging internals (e.g., cribbing/dunnage) if required for the shipment are properly configured in the CV cavity.
Caution: When lowering the contents into the CV cavity, protect the CV body bolt flange sealing surface from damage (e.g., scratches or gouges).
- 3. Lower the contents into the CV cavity.
- 4. Ensure the CV closure bolt threads are appropriately coated with thread lubricant.
- 5. Lift the CV lid, position it over the alignment pins on the CV body, and carefully lower it onto the CV body.
- 6. Install and tighten each of the CV lid bolts to a torque of in three passes, using the torque sequence stamped on the CV lid.
- 7. If removed, install the CV port cover and torque the port cover bolts to 7.1.3 Preparation for Transport This section describes the operations for preparing the package for transport, including pre-shipment leakage rate tests, radiation and contamination surveys, measurement of the package surface temperature, securement of the package, and application of tamper-indicating devices. The general procedure for preparing each package for transport is as follows:
- 1. Lift the package from the CV lift adapter and move the package above the transport skid trunnions.
NAC International 7.1-4
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 2. Lower the package onto the transport skid by gently lowering the rotation trunnion recesses into the rear support. Carefully lower the package to the horizontal transport orientation resting on the front saddle by moving the crane as required to maintain package engagement to the rear supports.
- 3. Detach the CV lift adapter from the CV lid.
- 4. Attach rigging to skid canopy.
- 6. Install the skid canopy attachment devices.
- 7. Decontaminate the exterior top surface of the CV as necessary.
Note: A pre-shipment leakage rate test of the CV port cover O-ring seals is required prior to every shipment, even if the port cover is not removed for loading operations.
- 8. Perform the pre-shipment leakage rate test of the CV lid and port cover O-ring seals in accordance with a written procedure that satisfies the requirements of Section 8.2.2.2 [7.1].
- 9. Attach rigging to the center impact limiter.
- 10. Lift the center impact limiter and attach to the center of the bottom of the package.
- 11. Install and tighten all threaded rods to the center impact limiter.
- 12. Install and torque all inner hex head nuts to the center impact limiter to
- 13. Install and torque all outer hex head nuts to the center impact limiter to
- 14. Install all lower impact limiter alignment pins.
- 15. Attach the impact limiter yoke to the lower impact limiter.
- 16. Attach the lower impact limiter to the bottom of the package.
- 17. Install and tighten all threaded rods to the lower impact limiter.
- 18. Install and torque all inner hex head nuts to the lower impact limiter to
- 19. Install and torque all outer hex head nuts to the lower impact limiter to
- 20. Remove the impact limiter yoke from the lower impact limiter.
- 21. Install all upper impact limiter alignment pins.
NAC International 7.1-5
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 22. Attach the rigging to an upper impact limiter section.
- 23. Attach the upper impact limiter section to the top of the package.
- 24. Install and tighten all threaded rods to the upper impact limiter section.
- 25. Install and torque all inner hex head nuts to the upper impact limiter section to
- 26. Install and torque all outer hex head nuts to the upper impact limiter section to
- 27. Remove the rigging from the upper impact limiter section.
- 28. Repeat Steps 20 through 26 for all upper impact limiter sections.
- 29. Install the tamper-indicating device (TID) to an attachment point on the upper impact limiter.
- 30. Install the plugs in the leak test ports of the CV lid and CV port cover.
- 31. Verify external radiation levels do not exceed the limits of 49 CFR 173.441(b).
- 32. Verify the levels of non-fixed contamination on the package do not exceed the limits of 49 CFR 173.443(a)(1).
- 33. Verify the exterior surface of the package does not exceed 85°C (185°F) in accordance with the requirement of 49 CFR 173.442(b)(2).
- 34. Determine the transport index (TI) corresponding to the maximum dose rate at 1 meter from the package. Record on shipping documents.
- 35. Apply placards to the transport vehicle in accordance with 49 CFR 172.500.
- 36. Provide special instructions to the carrier/shipper for an Exclusive Use Shipment.
- 37. Complete the shipping documentation in accordance with 49 CFR Subchapter C.
NAC International 7.1-6
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 7.2 Package Unloading This section describes the package unloading operations, including the inspections, tests, and preparations of the PALADIN transportation package for unloading.
7.2.1 Receipt of Package from Carrier This section describes the procedure for receiving a loaded package, including radiation and contamination surveys and inspection of tamper-indicating devices. The general procedure for receipt of each loaded package from a Carrier is as follows:
- 1. Perform a radiation survey of the package. If the external surface radiation levels exceed 200 mrem/hr, notify the Consignor immediately and investigate the cause of the high radiation levels before proceeding.
- 2. Perform a contamination survey of the external surfaces of the package to confirm the levels of non-fixed (removable) radioactive contamination does not exceed the limits specified in 49 CFR 173.443. If contamination levels exceed the limits, then notify the Consignor immediately and decontaminate the exterior surfaces, as necessary.
- 3. Visually verify that the tamper-indicating seals are intact. If NOT intact take actions per facility procedures.
- 4. Move the transport vehicle with the package to the receiving area and secure the transport vehicle.
- 5. Remove the tamper-indicating seals from the packaging.
- 6. Attach the upper impact limiter rigging to an upper impact limiter section.
- 7. Loosen and remove all hex head nuts from the upper impact limiter section.
- 8. Loosen and remove all threaded rods from the upper impact limiter section.
- 9. Detach the upper impact limiter section and move it to the designated storage location.
- 10. Remove the alignment pins from the upper impact limiter section.
- 11. Repeat Steps 6 through 9 until all upper impact limiter sections have been removed.
- 12. Attach the impact limiter lift yoke to the lower impact limiter.
- 13. Loosen and remove all hex head nuts from the lower impact limiter.
- 14. Loosen and remove all threaded rods from the lower impact limiter.
NAC International 7.2-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 15. Detach the lower impact limiter and move it to the designated storage location.
- 16. Remove all lower impact limiter alignment pins.
- 17. Attach rigging to the center impact limiter.
- 18. Loosen and remove all hex head nuts from the center impact limiter.
- 19. Loosen and remove all threaded rods from the center impact limiter.
- 20. Lift the center impact limiter and move it to the designated storage location.
- 22. Attach rigging to the skid canopy.
- 23. Lift the skid canopy vertically and move it to the designated storage location.
- 24. Attach the CV lift adapter to the CV lid.
- 25. Install the CV lift adapter bolts and torque to
- 26. Rotate/lift the CV to the vertical orientation and raise the CV off the blocks of the rear support structure of the transport skid.
- 27. Place the CV in the vertical orientation in a decontamination area or other suitable location identified by the user.
7.2.2 Removal of Contents This section describes the procedure for opening and removing the contents from a loaded package. The general procedure for opening a loaded package and removing the contents from each package is as follows:
- 1. Loosen and remove all CV lid closure bolts.
- 2. Lift the CV lift adapter and CV lid assembly to a designated storage location.
Caution: When handling the CV lid, the O-ring and associated sealing surfaces shall be protected from damage.
- 3. Attach appropriate rigging to the contents.
- 4. Remove the contents from the packaging.
NAC International 7.2-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 7.3 Preparation of Empty Packaging for Transport This section describes the procedure for preparing a previously used, now empty packaging for transport, including the inspections, tests, and special preparations needed to ensure that the packaging is verified to be empty, is properly closed, and that the radiation and contamination levels are within the applicable allowable limits. The general procedure for preparing each empty package for transport is as follows:
- 1. Visually inspect the CV cavity to confirm it has been emptied of its contents as far as practical.
- 2. Survey the interior of the internal surfaces of the package (i.e., CV cavity, CV flange, and underside of the CV lid) and any empty payload internals (e.g., lid, and dunnage) (if used) to be shipped to verify that the interior contamination limits of 49 CFR 173.428(d) are satisfied. If the non-fixed surface contamination exceeds the limits for empty package shipment, then decontaminate the interior surfaces, as necessary.
- 3. Visually inspect the readily accessible surfaces of the packaging components for any signs of damage that may have occurred during prior use to verify that the package is in unimpaired physical condition.
- 4. If required, apply thread lubricant to the threaded fasteners of the package.
- 5. Install the CV closure lid and tighten each of the CV lid bolts to a torque of in three passes, using the torque sequence stamped on the CV lid.
- 6. If the CV port cover has been removed from the CV lid, install the CV port cover.
- 7. Torque each of the port cover bolts to
- 8. Install the plugs in the leak test ports of the CV lid and CV port cover.
- 9. Lift the package from the CV lift adapter and move the package above the transport skid trunnions.
- 10. Lower the package onto the transport skid by gently lowering the rotation trunnion recesses into the rear support. Carefully lower the packaging to the horizontal transport orientation resting on the front saddle by moving the crane as required to maintain package engagement to the rear supports.
- 11. Attach rigging to skid canopy.
NAC International 7.3-1
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 13. Install the skid canopy attachment devices.
- 14. Attach rigging to the center impact limiter.
- 15. Lift the center impact limiter and attach to the center of the bottom of the package.
- 16. Install and tighten all threaded rods to the center impact limiter.
- 17. Install and torque all inner hex head nuts to the center impact limiter to
- 18. Install and torque all outer hex head nuts to the center impact limiter to
- 19. Install all lower impact limiter alignment pins.
- 20. Attach the impact limiter yoke to the lower impact limiter.
- 21. Attach the lower impact limiter to the bottom of the package.
- 22. Install and tighten all threaded rods to the lower impact limiter.
- 23. Install and torque all inner hex head nuts to the lower impact limiter to
- 24. Install and torque all outer hex head nuts to the lower impact limiter to
- 25. Remove the impact limiter yoke from the lower impact limiter.
- 26. Install all upper impact limiter alignment pins.
- 27. Attach the rigging to an upper impact limiter section.
- 28. Attach the upper impact limiter section to the top of the package.
- 29. Install and tighten all threaded rods to the upper impact limiter section.
- 30. Install and torque all inner hex head nuts to the upper impact limiter section to
- 31. Install and torque all outer hex head nuts to the upper impact limiter section to
- 32. Remove the rigging from the upper impact limiter section.
- 33. Repeat Steps 19 through 25 for all upper impact limiter sections.
- 34. Install the tamper-indicating devices on the package.
NAC International 7.3-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A
- 35. Perform a radiation survey to confirm that the dose rates on the external surfaces of each package does not exceed 0.005 mSv/hour (0.5 mrem/hour) in accordance with 49 CFR 71.421(a)(2).
- 36. Perform a contamination survey to confirm that the non-fixed (removable) radioactive surface contamination on the external surfaces of each do not exceed the limits specified in 49 CFR 173.443(a). If the non-fixed surface contamination exceeds the limits, then decontaminate the interior surfaces, as necessary.
- 37. Cover the packaging marking and labelling with an Empty label as prescribed in 49 CFR 172.450.
- 38. Release the package to the Carrier for the return shipment.
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 7.4 Railcar Design and Certification Requirements The PALADIN packaging is designed for transport by rail, barge, and heavy haul vehicle. The PALADIN transport skid and tie-down systems will be designed in accordance with the U.S.
Department of Transportation (DOT) regulations applicable to the mode of transport to be utilized. The design requirements for the railcar and tie-down components are defined in the following sections.
7.4.1 Railcar and Tie-Down Design Requirements The railcar and package tie-down system to be used for transporting the PALADIN will be designed in accordance with the requirements of the Association of American Railroads (AAR)
Manual of Standards and Recommended Practices, Section C, Part II, M-1001, and the Field Manual of the AAR Interchange Rules, Rule Number 88 [7.2].
7.4.2 Railcar Tie-Down Design Loadings The railcar tie-down system for the PALADIN package will be designed to withstand the following transport loads acting simultaneously without generating stresses exceeding the tie-down material yield strength:
- Longitudinal: 7.5 g
- Vertical: 2 g
- Lateral: 2 g 7.4.3 Railcar and Tie-Down Certification The PALADIN railcar and tie-down system design will be submitted to the AAR Mechanical Division for certification and approval in accordance with the AAR rules and requirements.
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 7.5 Appendix 7.5.1 References
[7.1] ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014.
[7.2] Association of American Railroads, Interchange Rules, Section C, Requirements for Acceptance, Rule 88, 2017.
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Chapter 8 Acceptance Tests and Maintenance Program Table of Contents 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM ...................................... 8-1 8.1 Acceptance Tests .......................................................................................................... 8.1-1 8.1.1 Visual Inspections and Measurements .............................................................. 8.1-1 8.1.2 Weld Examinations ........................................................................................... 8.1-1 8.1.3 Structural and Pressure Tests ............................................................................ 8.1-1 8.1.4 Fabrication Leakage Rate Tests.......................................................................... 8.1-2 8.1.5 Component and Material Tests ......................................................................... 8.1-2 8.1.6 Shielding Tests .................................................................................................. 8.1-3 8.1.7 Thermal Tests.................................................................................................... 8.1-3 8.1.8 Miscellaneous Tests .......................................................................................... 8.1-3 8.2 Maintenance Program ................................................................................................... 8.2-1 8.2.1 Structural and Pressure Tests ............................................................................ 8.2-1 8.2.2 Leakage Rate Tests ........................................................................................... 8.2-1 8.2.3 Component and Material Tests ......................................................................... 8.2-3 8.2.4 Thermal Test ..................................................................................................... 8.2-6 8.2.5 Miscellaneous Tests .......................................................................................... 8.2-6 8.3 Appendix ....................................................................................................................... 8.3-1 8.3.1 References ......................................................................................................... 8.3-1 NAC International 8-i
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A List of Tables Table 8.2 Summary of Packaging Maintenance Requirements ........................................ 8.2-7
NAC International 8-ii
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM This chapter presents the acceptance tests and maintenance program for the PALADIN packaging. These activities assure that the packaging meets the requirements of 10 CFR 71, Subpart G.
NAC International 8-1
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 8.1 Acceptance Tests This section describes the tests to be performed before the first use of each packaging. The acceptance tests confirm that each packaging is fabricated in accordance with the general arrangement drawings in the Certificate of Compliance.
8.1.1 Visual Inspections and Measurements Packaging components shall receive visual and mechanical inspections to verify the packaging has been fabricated and assembled in accordance with the general arrangement drawings in Appendix 1.3.3. The dimensions, tolerances, and surface finishes shown on the drawings shall be verified by measurement on each packaging. Nonconforming components shall be reworked or replaced.
8.1.2 Weld Examinations All packaging welds shall be examined to the requirements of the general arrangement drawings in Appendix 1.3.3. Nonconforming components shall be reworked or rejected.
8.1.3 Structural and Pressure Tests 8.1.3.1 Lifting Attachment Load Test The packaging is designed to be lifted by a lifting adapter bolted to the CV lid. The lifting adapter, bolts, and interfacing threaded lift attachment points in the CV lid are designed and load tested in accordance with the critical load (non-redundant) lifting requirements of ANSI N14.6, Special Lifting Devices for Shipping Containers Weighing 10,000 lbs or More for Nuclear Materials [8.9] and 10 CFR 71.45(a) requirements. Prior to the initial use of the CV lid, the threaded attachment points shall be subjected to a vertical test load equal to 300% of the maximum service load (weight of the heaviest, loaded cask without the removable ILS components). The test load shall be sustained for a period of 10 minutes or more. Following the load test, the critical areas of the CV lid shall be examined for indications of plastic deformation and/or cracking in accordance with the requirements of ANSI N14.6. Any identified defects must be repaired and the load test repeated in accordance with the original test requirements and acceptance criteria prior to final acceptance.
8.1.3.2 Hydrostatic Pressure Testing of the Containment Boundary In accordance with the requirements of 10 CFR 71.85(b), each CV assembly shall be pressure tested to 150% of the packaging design pressure to verify the capability of the containment system to maintain its structural integrity at the test pressure. The design pressure of the CV assembly is Therefore, each CV assembly shall be pressure tested at NAC International 8.1-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A In accordance with the requirements of NB-6223 [8.1], the test pressure will be maintained for a minimum of 10 minutes prior to initiation of the examination for leakage. Following the application of the test pressure, the CV assembly shall be visually examined for leakage in accordance with NB-6224 [8.1]. In addition, the welded connections of the CV assembly shall be examined for cracking and/or distortion using visual and liquid penetrant (PT) methods in accordance with NB-5000 [8.1]. The acceptance criteria for the pressure test are no unacceptable leakage or distortion of the containment boundary. A nonconforming CV assembly shall be reworked or rejected.
8.1.4 Fabrication Leakage Rate Tests The CV assembly (i.e., the packaging containment boundary) shall be leakage rate tested in accordance with ANSI N14.5 [8.6] to an acceptance criterion of 1x10-7 ref-cm3/sec (2x10-7 cm3/sec helium). Leakage rate testing shall be performed using helium as the tracer gas and a suitable helium leak detector with a minimum sensitivity of 5x10-8 ref-cm3/sec (1x10-7 cm3/sec helium). The Calibrated standard leaks used shall have current calibration traceable to NIST. A CV assembly that does not meet the acceptance criteria shall be reworked, replaced, or repaired, as required, and retested prior to acceptance.
Separate acceptance leakage rate tests may be performed for the CV body assembly, CV lid assembly, and port cover assembly containment boundaries using test heads or manifolds, as appropriate. Furthermore, the acceptance leakage rate test of the packaging containment system may be performed using temporary seals, which must be replaced prior to final acceptance. All containment O-rings that are not used for the acceptance leakage rate test shall be subjected to the maintenance leakage rate testing described in Section 8.2.2.1 prior to their initial use.
8.1.5 Component and Material Tests 8.1.5.1 Elastomeric O-ring Seals Containment O-rings will be made from the Fluorocarbon-Viton compound specified on the General Arrangement Drawings that has been qualified based on testing to verify material composition, physical properties (hardness, tensile strength, elongation, and specific gravity),
low temperature properties, and compression set at high temperature. In addition, each O-ring will be subjected to dimensional acceptance testing.
8.1.5.2 Containment Boundary Stainless Steel The stainless steel materials used to fabricate the packaging containment system including the CV lid, port cover, and CV bodys upper flange, upper shell, transition ring, lower shell, and bottom plate are furnished with CMTRs that assure that the mechanical property requirements NAC International 8.1-2
NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A identified on the general arrangement drawings in Appendix 1.3.3 are obtained.
8.1.6 Shielding Tests The packaging does not require shielding acceptance testing because the credited shielding components are made from solid stainless steel. As such, the packaging does not require any special shielding features, such as a poured lead gamma shield.
8.1.7 Thermal Tests The packaging does not require thermal acceptance testing because it does not include any special thermal features and the material properties used for the thermal evaluation of the package are sufficiently conservative.
8.1.8 Miscellaneous Tests Not Applicable.
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PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 8.2 Maintenance Program The maintenance program includes periodic inspections, tests, and maintenance activities designed to ensure continued performance of the packaging. This section describes the periodic testing, inspection, and replacement schedules, as well as the criteria for replacement and repair of components and subsystems on an as-needed basis. The maintenance requirements are summarized in Table 8.2-1.
8.2.1 Structural and Pressure Tests The packaging does not require any routine structural or pressure tests. This includes the replacement of CV closure bolts or threaded inserts which are exempted from the pressure test per NB-6111 [8.1]. The replacement requirements for threaded fasteners or inserts are presented in Section 8.2.3.
8.2.2 Leakage Rate Tests 8.2.2.1 Periodic and Maintenance Leakage Rate Testing Periodic leakage rate testing is performed in accordance with Section 7.5 of ANSI N14.5 [8.6] to confirm that the containment capabilities of the CV assembly have not deteriorated over an extended period of use. A periodic leakage rate test is required to be performed on every containment seal of the packaging within the 12-month period prior to every shipment but need not be performed for packages that are out-of-service (e.g., placed into temporary storage). As discussed in Section 8.2.3.1, all packaging O-rings are required to be replaced within the 12-month period prior to any shipment and, therefore, the maintenance leakage rate testing of the replaced containment seals also satisfies the requirement for periodic leakage rate testing.
Maintenance leakage rate testing of all packaging containment seals are performed in accordance with Section 7.4 of ANSI N14.5 [8.6] prior to returning the package to service following maintenance, repair, or replacement of any components of the containment system to confirm that the CV assembly is not degraded. As discussed in Sections 8.2.3.1 and 8.2.3.2, maintenance leakage rate testing is required after replacement of any packaging containment system O-ring and after repair of any containment sealing surface. Maintenance leakage rate testing need only be performed on the affected seal or sealing surface of the containment system.
Leak-tight acceptance criteria of 1x10-7 ref-cm3/sec (2x10-7 cm3/sec helium) shall be used for the periodic and maintenance leakage rate tests. Periodic and maintenance leakage rate testing shall be performed in accordance with ANSI N14.5 [8.6] using helium as the tracer gas and a suitable helium leak detector with a sensitivity of at least 5x10-8 ref-cm3/sec (1x10-7 cm3/sec helium).
Calibrated standard leaks shall have current calibration traceable to NIST.
NAC International 8.2-1
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A A CV assembly that does not satisfy the periodic and maintenance leakage rate test acceptance criteria shall be reworked, replaced, or repaired, as required, and retested prior to returning the packaging to service. Periodic and maintenance leakage rate test results and any associated rework, replacement, or repairs shall be documented in a packaging maintenance log.
8.2.2.2 Pre-shipment Leakage Rate Testing Pre-shipment leakage rate testing of the CV lid containment seal and the CV port cover containment seal1 of the loaded packaging is required before each shipment of a loaded package to verify that the containment system is properly assembled for shipment. The components that require pre-shipment leakage rate tests include the CV lid and port cover containment O-ring seals. If a containment seal requires replacement during loading operations, maintenance leakage rate testing of the closure with a new containment seal is required prior to shipment in accordance with the requirements of Section 8.2.2.1. In this case, the maintenance leakage rate test of the closure with the new containment seal satisfies the requirement for pre-shipment leakage rate testing.
Pre-shipment leakage rate tests shall be performed using the Gas Pressure Drop or Gas Pressure Rise methods described in Sections A.5.1 and A.5.2 of ANSI N14.5 [8.6]. The acceptance criterion for the pre-shipment leakage rate test is no detectable leakage when tested to a sensitivity of 1x10-3 ref-cm3/sec. The pressure gauge used to perform the pre-shipment leakage rate test shall have an NIST traceable calibration and be accurate to within 1% or less of its full scale.
The procedure for the pre-shipment leakage rate test shall be qualified based on the guidance provided in Article 1, T-150(d) of the ASME Code,Section V, Subsection A [8.7] using a calibrated leak standard for the T-150(d)(2) test specimen to demonstrate that it will reliably produce a test sensitivity of 1x10-3 ref-cm3/sec or better. Alternatively, a leakage rate test procedure that relies upon detection of a system calibrated leak standard in each performance of the test does not require a separate procedure qualification, as it is inherently qualified each time it is performed.
Any containment seal that does not satisfy the pre-shipment leakage rate test acceptance criteria shall be inspected, cleaned (if needed), reassembled, and retested prior to shipment. Any containment seal that does not satisfy the pre-shipment leakage rate test acceptance criteria after repeated attempts, may require replacement of the O-ring seal or repair of the sealing surface.
As discussed in Sections 8.2.3.1 and 8.2.3.2, a maintenance leakage rate test is required for all new/replaced containment O-rings and any repaired sealing surfaces for containment O-rings.
1 Pre-shipment leakage rate testing of the CV port containment seal are required before every Type B shipment, even if the CV port cover was not removed during the loading process.
NAC International 8.2-2
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Replacement of non-containment O-rings (i.e., CV or port cover test O-rings) and repair of sealing surfaces for non-containment O-rings does not require a maintenance leakage rate test.
8.2.3 Component and Material Tests The following sections describe the periodic tests and replacement schedules for packaging components used to ensure continued performance of the packaging. Additional maintenance may be required on an as-needed basis when wear or damage is noted during routine operations.
When as-needed maintenance is performed, the associated repair, replacement, and record keeping activities shall follow the maintenance program requirements for the corresponding periodic maintenance activity.
8.2.3.1 O-ring Seals Prior to each shipment, all accessible packaging O-ring seals are visually inspected for any damage or defects (e.g., cracks, tears, cuts, or discontinuities) that may prevent them from sealing properly when the package is assembled. If the CV port cover is not removed during the loading operations, the associated O-ring seals are not subjected to visual inspection. However, a pre-shipment leakage rate test is required for the CV lid and port cover containment O-rings prior to each use to verify the package is properly assembled for shipment, as discussed in Section 8.2.2.2. Damaged or defective O-ring seals shall be replaced with new O-ring seals that meet the requirements on the general arrangement drawing in Appendix 1.3.3 and the requirements of Section 8.1.5.1, as applicable. A maintenance leakage rate test is required for any replaced CV lid or port cover O-ring, per Section 8.2.2.1. The CV lid and port cover test O-rings and the CV test port O-rings do not provide containment, and therefore, do not require a pre-shipment leakage rate test or maintenance leakage test when replaced. The O-ring seal inspection results and any necessary O-ring seal replacements and required leakage rate tests shall be documented in a packaging maintenance log.
All packaging O-ring seals shall be replaced with new O-ring seals that meet the requirements shown on the general arrangement drawing in Appendix 1.3.3 and the requirements of Section 8.1.5.1, as applicable, within the 12-month period prior to any shipment. A maintenance leakage rate test is required for all CV containment O-ring seals that are replaced per Section 8.2.2.1.
Test O-ring seals that are replaced do not require a maintenance leakage rate test, however, they may be used to perform the maintenance leakage rate test of the associated containment O-ring.
The CV test port O ring seals, which only serve as dust/weather seals, do not require any leakage rate testing when replaced. The periodic replacement of O-rings and the required leakage rate tests shall be documented in a packaging maintenance log.
New O-rings shall be coated with vacuum grease or lightweight lubricant prior to installation to aid in installation and minimize deterioration or cracking of the elastomer during usage and the NAC International 8.2-3
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A potential for tearing if removed from the dovetail groove is necessary for inspection. The exposed surfaces of installed O-rings that do not require replacement shall also be coated prior to assembling the packaging to minimize deterioration or cracking of the seal during use. Remove excess coating from the O-rings prior to assembling the packaging.
8.2.3.2 Sealing Surfaces Prior to each shipment and during periodic maintenance (which is required within the 12-month period prior to any shipment) the sealing surfaces for all O-rings shall be cleaned and visually inspected for wear and/or damage (e.g., scratches, gouges, nicks, cracks, etc.) that may prevent the containment O-rings from sealing properly. Worn or damaged sealing surfaces may be repaired by machining or with a suitable polishing agent to restore the surface finish as required for proper sealing. A maintenance leakage rate test is required for all repaired sealing surfaces for containment O-rings, per Section 8.2.2.1. Repaired sealing surfaces for non-containment O-rings (i.e., WHVWQLSSOHDQGSOXJ2ULQJV) do not require a maintenance leakage rate test. The inspection results and any necessary sealing surface repairs and leakage rate tests shall be documented in a packaging maintenance log.
8.2.3.3 Threaded Fasteners Prior to each shipment, all packaging threaded fasteners (e.g., impact limiter threaded rods and nuts, CV lid bolts, CV port cover bolts, and CV test port plugs) removed during package loading operations shall be visually inspected for excessive wear and/or damage. However, fasteners that are not removed during the unloading and loading operations do not require visual inspection prior to use. In addition, all packaging threaded fasteners, including those not removed during loading or unloading operations, shall be visually inspected for excessive wear and/or damage within the 12-month period prior to any shipment. However, bolts which are never meant to be removed for the life of the package should only have their torques confirmed but do not need to be removed or inspected (e.g., bottom reinforcement plate and transition impact limiter section bolts).
Fasteners that have minor damage or wear may be refurbished by chasing the threads. Barbs may also be removed, taking care not to cause further thread damage. Minor surface corrosion on fasteners may be removed by polishing with an emery cloth or other fine abrasives. Fasteners that show visible signs of excessive wear or significant corrosion or damage shall be replaced with new fasteners that meet the requirements on the general arrangement drawing in Appendix 1.3.3. All repaired or replaced threaded fasteners shall be functionally tested prior to use to verify proper fit-up with the mating component of the packaging. Inspection results and any necessary fastener repairs and replacements shall be documented in a packaging maintenance log.
NAC International 8.2-4
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Tapped holes for threaded fasteners do not require visual inspection. However, all fastener holes with threaded inserts shall be visually inspected within the 12-month period prior to any shipment to verify that the threaded inserts are not displaced or damaged. Tapped holes that do not fit-up properly with the mating fastener may be refurbished by chasing the threads or repaired as necessary using threaded inserts per the general arrangement drawing in Appendix 1.3.3.
Displaced threaded inserts shall be re-positioned and secured in the hole or replaced with a new threaded insert, as necessary. Damaged threaded inserts shall be replaced with new threaded inserts that meet the applicable requirements on the general arrangement drawing in Appendix 1.3.3. The associated assemblies shall be functionally tested to confirm proper fit and function of the threaded connections. The inspection results and any necessary thread insert repairs and replacements shall be documented in a packaging maintenance log.
8.2.3.4 Exposed Packaging Surfaces Prior to each shipment, the exterior of the packaging, including the impact limiters, is visually inspected to verify its physical condition is unimpaired. Superficial defects on the exterior of the packaging, such as marks, scratches, or dents, do not require repair. However, any significant damage to the packaging exterior shall be repaired prior to shipment. The inspection results and any necessary repairs to the exterior of the packaging shall be documented in a packaging maintenance log.
All exposed interior and exterior surfaces of the top and bottom impact limiter assemblies, CV body and lid assemblies, and CV port cover and test port plugs shall be visually inspected within the 12-month period prior to any shipment for damage or degradation that could impair the physical condition of the packaging. Superficial defects, such as minor surface corrosion, scratches, blemishes, and adhered material/particles, may be removed by polishing the packaging surfaces with emery cloth or other fine abrasives. Significant damage of the packaging exterior shall be repaired to restore the packaging to the applicable requirements on the general arrangement drawing in Appendix 1.3.3 or the damaged components may be replaced.
Replacement components shall satisfy the applicable requirements on the general arrangement drawing in Appendix 1.3.3 and the applicable acceptance tests described in Section 8.1. The inspection results and any necessary repairs to the packaging surfaces or replacement of packaging components shall be documented in a packaging maintenance log.
Painted surfaces, identification markings, and match marks used for closure orientation shall be visually inspected within the 12-month period prior to any shipment, to ensure that painted surfaces are in good condition, identification markings are legible, and that match marks used for closure orientation remain legible and are easy to identify.
NAC International 8.2-5
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Lifting attachments shall be inspected within the 12-month period prior to any shipment to verify that there is no evident permanent deformation and no obvious damage or defects. Damaged or defective lifting attachments shall be repaired or replaced in accordance with the applicable requirements on the general arrangement drawing in Appendix 1.3.3 and the applicable acceptance tests described in Section 8.1.
8.2.4 Thermal Test No periodic or routine thermal testing are required to be performed on the packaging.
8.2.5 Miscellaneous Tests The following subsections discuss the requirements following replacement of packaging components. These requirements apply to newly manufactured components (spares) or substituted components from other PALADIN packagings. Other components may be substituted following these procedures.
8.2.5.1 CV Replacement or Repair If a CV body, lid, or port cover must be replaced, the replaced CV component shall be assembled with the mating CV component to assure proper fit-up. A maintenance leakage rate test of the containment O-ring seal affected by the replacement shall be performed in accordance with Section 8.2.2.1. The replacement shall be noted in the packagings maintenance log along with the test and inspection results.
If an entire CV assembly must be replaced, the replacement shall be noted in the packagings maintenance log. The replacement CV assembly must either be a unit currently in service, or another unit manufactured or refurbished to the requirements shown in the general arrangement drawings in Appendix 1.3.3.
8.2.5.2 Impact Limiter Replacement or Repair If an impact limiter must be replaced, the replacement impact limiter shall be assembled to the CV with any applicable adjacent impact limiters also installed to assure proper fit-up. The replacement shall be noted in the packagings maintenance log along with the inspection results.
NAC International 8.2-6
PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A Table 8.2 Summary of Packaging Maintenance Requirements Inspection/Test/Maintenance(1)
Reference Item SAR Each Replace/ Annual Section Use Repair(2)
CV containment O-rings (lid & port) 8.2.3.1 V, LT1 LT2 R, LT2 CV leak test O-rings (lid & port) 8.2.3.1 V R CV containment O-ring sealing surfaces 8.2.3.2 V LT2 V CV leak test O-ring sealing surfaces 8.2.3.2 V V CV lid bolts 8.2.3.3 V F V Threaded inserts for CV lid bolts 8.2.3.3 F V CV port cover 8.2.3.3 V F V Tapped holes(3) 8.2.3.3 F Impact limiter attachments 8.2.3.3 V F V Exposed packaging exterior surfaces 8.2.3.4 V V Exposed interior and exterior surfaces 8.2.3.4 V Notes:
- 1. R = Replace, V = Visual Inspection, F = Functional Test, LT1 = Pre-shipment leak test (Section 8.2.2),
LT2 = maintenance/periodic leak test (Section 8.2.2.1).
- 2. Tests or inspections necessary when items are replaced or repaired.
- 3. Tapped holes without threaded inserts.
NAC International 8.2-7
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NAC PROPRIETARY INFORMATION REMOVED PALADIN Package SAR February 2023 Docket No. 71-9400 Revision 23A 8.3 Appendix 8.3.1 References
[8.1] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NB, Class 1 Components, 2013 Edition.
[8.2] ASTM International, D1622/D1622M-14, Standard Test Method for Apparent Density of Rigid Cellular Plastic.
[8.3] ASTM International, D1621-14, Standard Test Method for Compressive Properties of Rigid Cellular Plastic.
[8.4] ASTM International, E709-15, Standard Practice for Magnetic Particle Testing.
[8.5] ASTM International, E165/E165M-12, Standard Practice for Liquid Penetrant Examination for General Industry.
[8.6] ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014.
[8.7] ASME Boiler and Pressure Vessel Code,Section V, Nondestructive Examination, Subsection A, Nondestructive Methods of Examination, 2013 Edition, July 1, 2013.
[8.8] ASTM International, E23, Standard Test Method Plane-Strain Fracture Toughness of Metallic Materials, latest edition.
[8.9] ANSI N14.6-1993, Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More, American National Standards Institute, Inc., New York, 1993.
[8.12] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section II, Part A, Ferrous Material Specifications, 2013 Edition.
NAC International 8.3-1
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