ML24191A045

Proposed Changes for Certificate of Compliance Revision 4 Shielded Devices Application NAC OPTIMUS-L Safety Analysis Report, Revision 24A

ML24191A045
Person / Time
Site:	OPTIMUS-L
Issue date:	06/30/2024
From:	NAC International
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML24191A043	List: ML24191A044 ML24191A045
References
ED20240083
Download: ML24191A045 (1)

Text

Atlanta Corporate Headquarters: 2 Sun Court, Suite 220, Peachtree Corners, Georgia 30092 USA Phone 770-447-1144, www.nacintl.com June 2024 Docket No. 71-9390 OPTIMUS-L (OPTImal Modular Universal Shipping Cask)

SAFETY ANALYSIS REPORT Shielded Devices Application NON-PROPRIETARY VERSION Revision 24A to ED20240083 Page 1 of 3 Page 1 of 3 No. 71-9390 for OPTIMUS-L Proposed Changes for Certificate of Compliance Revision 4 Shielded Devices Application NAC OPTIMUS-L SAR, Revision 24A June 2024 to ED20240083 Page 2 of 3 Page 2 of 3 CoC Sections (revised)

CoC Page 2 of 7 5.(a)(3)

Drawings (continued) 70000.14-L502, Rev 1P Packaging Assembly OPTIMUS-L 70000.14-L595, Rev 1P Shielded Device Insert Assembly, OPTIMUS-L CoC Sections (new)

CoC Page 3 of 7 5.(b)(1)

Type and form of material (continued)

(vii)

Shielded Devices are shielded steel weldments containing sealed sources meeting the following specifications.

Parameter Shielded Device Maximum weight (Shielded Device) 2,200 lb. (997 kg ref.)

Maximum Surface Dose Rate (Shielded Device) 100 mrem/hr Maximum Dimensions Height 40 in. (101.6 cm ref.)

Diameter 14 in. excluding beam port, if present (35.56 cm ref.)

to ED20240083 Page 3 of 3 Page 3 of 3 CoC Page 6 of 7 5.(b)(2)

Maximum quantity of material per package (continued)

(ix)

For Shielded Devices, as described in Item 5.(b)(1)(vii):

Shielded Devices, contents, are limited to special and normal form sealed source content. The Shielded Device Insert Assembly is configured in the CCV cavity for transportation, shown General Arrangement Drawing 70000.14-L595. The insert consists of two (2) axial aluminum spacers, placed at the bottom and top of the configuration, with cellulosic fiberboard radial insert situated between the axial spacers.

CoC Page 6 of 7 5.(c)

Criticality Safety Index For, 5.(b)(2) (ix) Shielded Devices 0.0 to ED20240083 Page 1 of 2 Supporting Calculations Shielded Devices Application NAC OPTIMUS-L SAR, Revision 24A June 2024 to ED20240083 Page 2 of 2 List of Calculations

1. 70000.14-2110 Rev. 0

2. 70000.14-3003 Rev. 0

3. 70000.37-5201 Rev. 1

4. 70000.37-5202 Rev. 2 CACLULATIONS ARE PROPRIETARY AND WITHHELD IN THEIR ENTIRETY PER 10 CFR 2.390 to ED20240083 Page 1 of 3 List of SAR Changes Shielded Devices Application NAC OPTIMUS-L SAR, Revision 24A June 2024 to ED20240083 Page 2 of 3 List of Changes for the OPTIMUS-L SAR, Revision 24A Chapter 1 Pages 1-i thru 1-ii, modified Table of Contents, List of Figures and List of Tables to reflect changes within the chapter where indicated.

Page 1.1-1, added fifth paragraph in Section 1.1 where indicated.

Page 1.2-3, added five paragraphs to Section 1.2.1 where indicated.

Page 1.2-4, added second paragraph to Section 1.2.1.3 where indicated.

Page 1.2-5, text flow changes Page 1.2-6, added two paragraphs in the middle of the page where indicated.

Pages 1.2-7 thru 1.2-9, text flow changes.

Pages 1.2-10, modified text in Section 1.2.2 where indicated.

Pages 1.2-11 thru 1.2-13, text flow changes.

Page 1.2-14, added Section 1.2.2.4 where indicated.

Pages 1.2-15 thru 1.2-20, text flow changes.

Page 1.2-21, added Figure 1.2-4 where indicated.

Page 1.3-1, added Reference 1.9 where indicated.

Page 1.3-2 thru 1.3-3, added 4 Acronyms where indicated.

Page 1.3-4, added a row where indicated.

Chapter 2 Pages 2-ii, iv, v, and vii, modified Table of Contents, List of Figures and List of Tables to reflect changes within the chapter where indicated.

Page 2-1, added text to the end of the first paragraph in Section 2 where indicated.

Page 2.12-3, added References 2.32 thru 2.39 where indicated.

Pages 2.12-58 thru 2.12-85, added Section 2.12.6.

Chapter 3 Pages 3-i thru 3-iii, modified Table of Contents, List of Figures and List of Tables to reflect changes within the chapter where indicated.

Page 3-1, modified text in Section 3 where indicated.

Page 3.5-2, added References 3.18 and 3.19.

Page 3.5-3, modified text in Section 3.5.2.1 where indicated.

Page 3.5-4 thru 3.5-6, modified text where indicated.

Page 3.5-7, text flow change.

Page 3.5-8 thru 3.5-15, added Section 3.5.4 where indicated.

to ED20240083 Page 3 of 3 Chapter 4 No Changes Chapter 5 Pages 5-i thru 5-iii, modified Table of Contents, List of Figures and List of Tables to reflect changes within the chapter where indicated.

Page 5-1, added a sentence where indicated.

Page 5.5-1, added References 5.7, 5.8, and 5.9 where indicated.

Pages 5.5-14 thru 5.5-49, added Section 5.5.4.

Chapter 6 No Changes Chapter 7 Page 7.1-3, modified text in the middle of the page and #2 of Section 7.1.2 where indicated.

Page 7.1-4, added step #4 in Section 7.1.2.

Page 7.1-5, text flow changes.

Chapter 8 Page 8.1-4, added Section 8.1.5.3 where indicated.

Page 8.2-7, added Section 8.2.5.3 where indicated.

Page 8.3-1, added Reference 8.7 where indicated.

to ED20240083 Page 1 of 2 List of Drawing Changes Shielded Devices Application NAC OPTIMUS-L SAR, Revision 24A June 2024 to ED20240083 NAC PROPRIETARY INFORMATION REMOVED Page 2 of 2 Drawing 70000.14-502, Packaging Assembly OPTIMUS-L, Rev. 1P Drawing 70000.14-L595, Shielded Device Insert Assembly, OPTIMUS-L, Rev. 1P Initial Submittal Drawing 70000.14-L595, Shielded Device Insert Assembly, OPTIMUS-L, Rev. 0NP Initial Submittal to ED20240083 Page 1 of 1 List of Effective Pages and SAR Changed Pages Shielded Devices Application NAC OPTIMUS-L SAR, Revision 24A June 2024

Atlanta Corporate Headquarters: 2 Sun Court, Suite 220, Peachtree Corners, Georgia 30092 USA Phone 770-447-1144, www.nacintl.com June 2024 Docket No. 71-9390 OPTIMUS-L (OPTImal Modular Universal Shipping Cask)

SAFETY ANALYSIS REPORT NON-PROPRIETARY VERSION Revision 24A

OPTIMUS-L Safety Analysis Report June 2024 Docket No. 71-9390 Revision 24A List of Effective Pages Page 1 of 2 Chapter 1 Page 1-i thru 1-ii............... Revision 24A Page 1-1................................. Revision 1 Page 1.1-1......................... Revision 24A Page 1.1-2.............................. Revision 1 Page 1.2-1 thru 1.2-2.............. Revision 1 Page 1.2-3 thru 1.2-21....... Revision 24A Page 1.3-1 thru 1.3-4......... Revision 24A 15 drawings (see Section 1.3)

Chapter 2 Page 2-i.................................. Revision 1 Page 2-ii............................ Revision 24A Page 2-iii................................ Revision 1 Page 2-iv thru 2-v.............. Revision 24A Page 2-vi................................ Revision 1 Page 2-vii.......................... Revision 24A Page 2-1............................ Revision 24A Page 2.1-1 thru 2.1-20............ Revision 1 Page 2.2-1 thru 2.2-11............ Revision 1 Page 2.3-1 thru 2.3-4.............. Revision 1 Page 2.4-1.............................. Revision 1 Page 2.5-1 thru 2.5-14............ Revision 1 Page 2.6-1 thru 2.6-37............ Revision 1 Page 2.7-1 thru 2.7-52............ Revision 1 Page 2.8-1.............................. Revision 1 Page 2.9-1.............................. Revision 1 Page 2.10-1............................ Revision 1 Page 2.11-1............................ Revision 1 Page 2.12-1 thru 2.12-2.......... Revision 1 Page 2.12-3....................... Revision 24A Page 2.12-4 thru 2.12-57........ Revision 1 Page 2.12-58 thru 2.12-85. Revision 24A Chapter 3 Page 3-i thru 3-iii.............. Revision 24A Page 3-1............................ Revision 24A Page 3.1-1 thru 3.1-5.............. Revision 1 Page 3.2-1 thru 3.2-5.............. Revision 1 Page 3.3-1 thru 3.3-20............ Revision 1 Page 3.4-1 thru 3.4-18............ Revision 1 Page 3.5-1.............................. Revision 1 Page 3.5-2 thru 3.5-15....... Revision 24A Chapter 4 Page 4-i thru 4-ii.................... Revision 1 Page 4-1................................. Revision 1 Page 4.1-1 thru 4.1-3.............. Revision 1 Page 4.2-1.............................. Revision 1 Page 4.3-1.............................. Revision 1 Page 4.4-1.............................. Revision 1 Page 4.5-1 thru 4.5-24............ Revision 1 Chapter 5 Page 5-i thru 5-iii.............. Revision 24A Page 5-1............................ Revision 24A Page 5.1-1.............................. Revision 1 Page 5.1-2......................... Revision 23D Page 5.1-3.............................. Revision 1 Page 5.1-4......................... Revision 23D Page 5.2-1 thru 5.2-4.............. Revision 1 Page 5.3-1 thru 5.3-8.............. Revision 1 Page 5.4-1 thru 5.4-14............ Revision 1 Page 5.5-1......................... Revision 24A Page 5.5-2 thru 5.5-11............ Revision 1 Page 5.5-12 thru 5.5-13..... Revision 23D Page 5.5-14 thru 5.5-49..... Revision 24A Chapter 6 Page 6-i thru 6-vii.................. Revision 1 Page 6-1................................. Revision 1 Page 6.1-1 thru 6.1-2.............. Revision 1 Page 6.2-1 thru 6.2-4.............. Revision 1 Page 6.3-1 thru 6.3-23............ Revision 1 Page 6.4-1 thru 6.4-15............ Revision 1 Page 6.5-1 thru 6.5-18............ Revision 1 Page 6.6-1 thru 6.6-20............ Revision 1 Page 6.7-1.............................. Revision 1 Page 6.8-1 thru 6.8-20............ Revision 1 Page 6.9-1.............................. Revision 1 Page 6.9.1-1 thru 6.9.1-2........ Revision 1 Page 6.9.2-1 thru 6.9.2-2........ Revision 1 Page 6.9.3-1 thru 6.9.3-19...... Revision 1 Page 6.9.4-1........................... Revision 1 Page 6.9.5-1........................... Revision 1 Page 6.9.6-1........................... Revision 1 Page 6.9.7-1........................... Revision 1 Page 6.9.8-1 thru 6.9.8-7........ Revision 1

OPTIMUS-L Safety Analysis Report June 2024 Docket No. 71-9390 Revision 24A List of Effective Pages (contd)

Page 2 of 2 Page 6.10-1 thru 6.10-2.......... Revision 1 Chapter 7 Page 7-i.................................. Revision 1 Page 7-1 thru 7-3.................... Revision 1 Page 7.1-1 thru 7.1-2.............. Revision 1 Page 7.1-3 thru 7.1-5......... Revision 24A Page 7.2-1 thru 7.2-2.............. Revision 1 Page 7.3-1 thru 7.3-2.............. Revision 1 Page 7.4-1.............................. Revision 1 Page 7.5-1 thru 7.5-2.............. Revision 1 Page 7.5-3 thru 7.5-17....... Revision 23D Page 7.5-18 thru 7.5-24.......... Revision 1 Chapter 8 Page 8-i thru 8-ii.................... Revision 1 Page 8-1................................. Revision 1 Page 8.1-1 thru 8.1-3.............. Revision 1 Page 8.1-4......................... Revision 24A Page 8.1-5.............................. Revision 1 Page 8.2-1 thru 8.2-6.............. Revision 1 Page 8.2-7......................... Revision 24A Page 8.2-8.............................. Revision 1 Page 8.3-1......................... Revision 24A

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1-i Chapter 1 General Description Table of Contents 1

GENERAL INFORMATION......................................................................................... 1-1 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............................................................................... 1.2-10 1.2.3 Special Requirements for Plutonium....................................................... 1.2-15 1.2.4 Operational Features................................................................................ 1.2-15 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............................................... 1.3-4

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1-ii List of Figures Figure 1.1-1 - Expanded View of OPTIMUS-L Packaging................................................. 1.1-2 Figure 1.2-1 - CCV Packaging Components........................................................................ 1.2-18 Figure 1.2-2 - Packaging Containment System.................................................................... 1.2-19 Figure 1.2-3 - GEO Basket Assembly.................................................................................. 1.2-20 Figure 1.2-4 - Shielded Device Insert Assembly.................................................................. 1.2-21 List of Tables Table 1.2-1 - TRU Waste FGE Limits.................................................................................. 1.2-16 Table 1.2-2 - IFW Waste FEM Limits.................................................................................. 1.2-16 Table 1.2-3 - TRU Waste and IFW Activity Limits for Key Isotopes................................. 1.2-17

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.1-1 1.1 Introduction The OPTIMUS-L packaging is designated as Type B(U)F per 10 CFR 71.4. The package contents include Type B quantities of normal form transuranic (TRU) waste and fuel waste material. The packaging is classified as Category I in accordance with Regulatory Guide 7.11

[1.1]. The package is designed to be transported by highway, rail sea, and air. (Transportation by air is authorized for packages (except items specifically prohibited for air transport, e.g.,

fissile material)). The consignor must ship the package under exclusive use controls. The Maximum Normal Operating Pressure (MNOP) of the package is 100 psig (690 kPa).

The packaging, described in greater detail in Section 1.2.1, consists of a Cask Containment Vessel (CCV), a CCV bottom support plate, and an Outer Packaging (OP) assembly, as shown in Figure 1.1-1. The CCV is a stainless steel vessel with a bolted closure designed to provide leaktight containment in accordance with the criterion of ANSI N14.5-2014 [1.2]. The CCV bottom support plate (not shown in Figure 1.1-1) is a free-standing carbon steel plate that is positioned at the bottom end of the CCV cavity below the contents. The OP consists of a base and lid bolted together to fully encase the CCV. The OP is designed to crush and absorb the impact energy when subjected to NCT free drop and HAC free drop tests, thereby limiting the loads imparted to the CCV. The OP also insulates the CCV from the direct effects of the fire during the HAC thermal test.

The packaging may be configured with a Shield Insert Assembly (SIA) inside the CCV cavity for contents requiring additional shielding to demonstrate compliance with dose rate limits. SIAs used in the OPTIMUS-L packaging are provided in 1-inch and 21/4-inch thicknesses. The SIA is a painted carbon steel open-top container for additional shielding for dose rates on the side and bottom of the package.

The packaging is configured with the GEO basket assembly inside the CCV cavity when used to transport unirradiated TRI-structural ISOtropic (TRISO) fuel particle compact (i.e., TRISO compact) contents. In this configuration, the CCV bottom support plate is not included.

The packaging may be configured with a Shielded Device Insert Assembly (SDIA) inside the CCV cavity to transport shielded devices containing special and normal form sealed source content. The CCV Bottom Support Plate is not used in this configuration.

SAR demonstrates the packaging meets the applicable requirements of 10 CFR 71. The basis for qualification is the safety analysis contained herein. The package is shown to comply with the external temperature limits of 10 CFR 71.43 and external radiation standards of 0 CFR 71.47(b),

10 CFR 71.51(a)(1) and 10 CFR 71.51(a)(2).

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-3 The Shielded Device Insert Assembly is configured in the CCV cavity for transportation, shown in Figure 1.2-4. The insert consists of two (2) axial aluminum spacers, placed at the bottom and top of the configuration, with cellulosic fiberboard radial insert (CF-RI or RI) situated between the axial spacers.

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 PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-4 1.2.1.1 Overall Dimensions and Weights The nominal outer dimensions of the OPTIMUS-L packaging, excluding the lifting lugs and tiedown arms, is 49.0 inches by 70.0-inch high which is greater than the minimum package dimension of 10 cm required by 10 CFR 71.43(a). The gross weight of the package, including the maximum CCV contents weight, is approximately 9,200 pounds.

1.2.1.2 Containment Features The containment system is formed by CCV body (cylindrical shell, bottom plate, bolt flange, and all associated welds), CCV lid and its closure bolts and containment O-ring seal, and the port cover and its closure bolts and containment O-ring seal. A detailed description of the containment system is provided in Section 4.1.

1.2.1.3 Neutron and Gamma Shielding Features Gamma shielding on the side and bottom end of the packaging is provided primarily by stainless steel plates that form the CCV and OP inner and outer shells. The polyurethane foam on the side of the OP is only credited for shielding under NCT. The packaging radial surfaces includes the CCV stainless steel shell, the OP inner shell, and a thick OP outer shell, for a combined steel thickness of 1.27 inches. In addition, the minimum side foam thickness is included in the shielding model for NCT, but not for HAC. The packaging bottom end includes the 1.5-inch thick carbon steel CCV bottom support plate (positioned at the bottom end of the CCV cavity), the CCV 1-inch thick stainless steel bottom plate, the OP inner bottom plate, the OP bottom foam cover shell, and the thick OP outer bottom plate, for a combined steel thickness of

. The packaging top end includes a thick stainless steel CCV closure lid, a OP inner top end plate, the OP top foam cover shell, and the outer end plate, for a combined steel thickness of The Shielded Devices rely on the shielding of the shielded weldments which house the sources.

Lead provides gamma shielding from the sources. The Shielded Devices are limited to exterior surface dose rates of 100 mrem/hr.

Shielding specifically for neutrons is not necessary for the specified radioactive material contents.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-5 1.2.1.4 Criticality Control Features As discussed in Section 1.2.1.7, the GEO basket assembly supports and maintains the geometry of the TRISO compact to maintain subcriticality under NCT and HAC. Neutron absorbers for criticality control are not necessary for the specified radioactive material contents.

1.2.1.5 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 Tiedown Devices The fully-assembled package is designed to be lifted by a forklift from a pallet on which the package is mounted or using a 3-legged sling attached to OP lid lifting lugs. The OP lid lifting lugs are structural parts of the packaging and are analyzed accordingly in Chapter 2.

Energy-Absorbing Features The OP lid and base, shown in Figure 1.1-1, absorb energy from free drops and protect the CCV from impact damage. The external envelope of the OP, excluding the lid lifting lugs and tiedown arms, is 49-inch by 70-inch high. The OP is constructed from closed-cell polyurethane foam encased inside stainless steel shells. The OP is designed to crush and absorb energy for NCT free drop, HAC free drop, and HAC puncture tests to limit the shock loads imparted to the CCV and its contents.

The OP base and lid are constructed from stainless steel shells that completely encase energy-absorbing closed-cell polyurethane foam core components to create a sealed cavity to protect the foam core from the external environment. The OP outer shells and outer top and bottom end plates are all constructed from stainless steel plate. The inner shells are constructed from stainless steel sheet. The inner top and bottom end plates are constructed from thick stainless steel plate. The OP shells are designed to plastically deform under NCT and HAC free drop conditions, but not fail in any manner that would expose the OP foam to the ambient environment.

The OP foam cores are comprised of closed-cell polyurethane foam for optimal performance in the NCT and HAC free drop tests. The foam cores used in the top end of the OP does not provide an energy-absorbing function because it is not crushed under any NCT or HAC free drop conditions. All energy absorption is provided by the foam core used in the corner and overhang regions of the OP lid and base. The shear rings attached to the top inner end plate and the spoke support plate attached to the bottom inner end plate provide backing support for the corner foam under side, corner, and oblique drop impacts.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-6 Internal Supports or Positioning Features The CCV bottom support plate is a free-standing plate that is positioned at the bottom end of the CCV cavity below the contents. The CCV bottom support plate is designed to distribute the loading from the contents on the CCV bottom end plate under NCT and HAC bottom end drop conditions. The CCV bottom support plate is not required when using the 1-inch SIA or the GEO basket assembly.

The radial insert maintain the location of the Shielded Devices during routine and normal conditions of transport. The top and bottom axial spacers support and uniformly distribute the end drop loads imparted by the devices onto the base and lid of the CCV. Dunnage is placed below and above the Shielded Device to position the beam port within the Beam Port Cutout of the lower RI.

Shielded Devices with no beam port feature require the Port Spacer cut-out to be filled, either via a solid Port Spacer or a full-length lower segment.

Shoring must be placed between loose fitting contents and the CCV cavity to prevent excessive movement during transport. The shoring may be made from any material that does not react negatively with the packaging materials or contents. Shoring materials should also have a melting temperature above 300°F (149°C) to ensure shoring maintains its geometry under routine and normal conditions of transport.

Outer Packaging As shown in Figure 1.1-1, the OP consists of a body and lid, each made from foam-filled stainless steel shells. The OP has a 49.0-inch outer diameter (excluding lifting lugs and tiedown arms) and 70-inch overall height. The OP lid is secured to the OP base by high-strength steel bolts. When installed, the inner portion of the OP lid bolt flange is recessed inside the top end of the OP base bolt flange. The tight fit between the OP lid and base bolt flanges at this interface is designed to provide shear relief for the OP bolts. The OP cavity is sized to provide sufficient clearance to permit free differential thermal expansion of the CCV under all NCT and HAC conditions.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-7 Packaging Closure Devices The packaging closure devices include the bolted CCV lid, the bolted CCV port cover, and the bolted OP lid. The primary safety function of the CCV lid and CCV port cover is containment, but the OP lid is not part of containment boundary.

The CCV lid, shown in Figure 1.2-1, is a stepped plate secured to the CCV body by high strength stainless steel custom CCV lid bolts and sealed by an elastomeric O-ring. The design of the CCV lid prevents shear loading of the CCV lid bolt under NCT free drop, HAC free drop, and HAC puncture tests. The CCV lids inner plug, which fits tightly inside the top opening of the CCV body, prevents significant lateral movement of the CCV lid relative to the CCV body bolt flange to prevent shear loading of the CCV lid bolts. The CCV lid bolts are with scalloped pockets in which the CCV lid bolt heads are recessed and protected from impact loads.

During transport of the CCV port is plugged by the CCV port cover and sealed by an elastomeric O-ring. The CCV port cover is secured to the CCV lid by stainless steel socket head cap screws. The CCV port cover is recessed in a pocket within the CCV lid and protected from shear loading due to free drop and puncture tests.

1.2.1.6 Secondary Packaging Components As discussed in Section 1.2.2.1, radioactive contents are packaged in secondary containers (e.g.,

drums, equipment, liners, specialty bags, etc.) to prevent direct contact between the contents and packaging to minimize the spread of contamination and to facilitate content loading and unloading operations. In addition, shoring may be used to prevent significant movement of the radioactive contents within the CCV during transportation. Secondary packaging components are not considered licensed components but must be made from materials that do not adversely react with the packaging or component materials. Secondary containers may be any shape or size that fits within the cavity of the CCV. Each secondary container and each confinement boundary of the contents must have one or more venting mechanisms (e.g., filter, vent, permeable membrane, etc.) that satisfies the minimum hydrogen diffusivity rates in Table 4.5-3 to allow gases to readily flow into or out of each confinement region of the CCV and contents.

The hydrogen diffusivity rate of each venting mechanism shall be based on available product literature, published industry-accepted data, or test data, otherwise the minimum rates from Table 4.5-3 shall be assumed.

1.2.1.7 Internal Support Components The GEO basket assembly is a free-standing structure that is positioned inside the CCV cavity to support and maintain the geometry of the TRISO compact for criticality control under NCT and NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-8 HAC. The GEO basket assembly consists of an electroless nickel plated carbon steel basket weldment that accommodates two-hundred and forty (240) stainless steel fuel tubes with TRISO compact contents. The fuel tubes fit loosely within the basket weldment and are slightly shorter than the basket weldment cells to ensure that they do not support the weight of the basket weldment under NCT or HAC free drop impacts on the top end of the package. The fuel tubes are also designed with sufficient strength to prevent excessive deformation that could result in lateral compressive loading (i.e., pinching) of the TRISO compacts under the most severe transverse loading (i.e., HAC side drop).

1.2.1.8 Tamper-Indicating Features The OPTIMUS-L packaging has adjustable cable seal tamper indicating devices on the OP, as shown on general arrangement drawing 70000.14-L502 in Section 1.3, to meet the requirement for tamper-indicating features as specified in 10 CFR 71.43(b). See Section 2.4.2 for more details.

1.2.1.9 Packaging Markings The packaging nameplate is shown on the general arrangement drawing in Section 1.3.

1.2.1.10 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 discussed in Section 2.1.4, the package, which is designed to transport normal form content with a maximum activity greater than 3,000 A2 and greater than 30,000 Ci, is designed, fabricated, tested, and maintained in accordance with codes and standards that are appropriate for transportation packages with Category I container contents. Accordingly, the codes and standards used are based on Regulatory Guide 7.6 [1-3] and NUREG/CR-3854 [1-4].

The package containment system is designed in accordance with the applicable requirements of the ASME Code,Section III, Division 1, Subsection NB [1-5]. 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 [1-6]. However, the energy-absorbing foam materials used in the impact limiters are fabricated, installed, and tested in accordance with the applicable standard industry practices. 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.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-9 1.2.1.11 Heat Transfer Features 1.2.1.12 Containment Features The packaging has a simple, robust containment system design. Containment of radioactive material for the packaging is provided by the Cask Containment Vessel (CCV). Other than the CCV lid closure and port cover closure, there are no penetrations to the containment system, and no valves or pressure relief devices of any kind. The CCV does not rely on any filter or mechanical cooling system to meet containment requirements, nor does it include any vents or valves for continuous venting.

The CCV 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 CCV is included in Figure 1.2-2, with the pressure-retaining boundary outlined in red. The top view is simplified to only show the components significant to the containment system, removing details such as test ports, lifting hoist ring locations, and alignment pins.

The CCV is designed, fabricated, examined, tested, and inspected in accordance with the applicable requirements of the ASME Code with certain exceptions discussed in Chapter 2. A detailed description of the containment system is provided in Section 4.1.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-10 1.2.1.13 Neutron and Gamma Shielding Features Gamma shielding on the side and bottom end of the packaging is provided by stainless steel plates forming the CCV cylindrical shell and bottom plate plus the OP shells and foam. The packaging radial gamma shielding includes the stainless steel CCV cylindrical shell, the stainless steel OP inner and outer shell and the OP radial foam. The packaging bottom end gamma shielding includes the CCV stainless steel inner bottom plate and the stainless steel OP base inner and outer end plates. Gamma shielding in the top end of the cask is provided primarily by the thick stainless steel CCV lid, the stainless steel OP lid inner and outer end plates and the OP lid end foam. When required to demonstrate compliance with regulatory dose rate limits, the packaging is configured with an SIA. SIAs are only credited for shielding under NCT, conservatively assuming that the contents escape the secondary container and SIA cavity following the HAC free drop. Neutron shielding is not necessary for the specified radioactive material contents.

1.2.1.14 Coolants Not applicable.

1.2.2 Radioactive Contents The acceptable radioactive contents of the package includes transuranic (TRU) waste; irradiated fuel waste, consisting of LEU uranium fuel and metal structural components (e.g. cladding, liners, baskets, etc.); TRISO compacts; and Shielded Devices (with Sealed Sources). The acceptable radioactive contents are discussed further in the following sections.

1.2.2.1 Transuranic Waste Transuranic (TRU) waste is classified as intermediate-level radioactive waste exposed to alpha radiation or containing long-lived radionuclides in concentrations requiring isolation and containment for periods beyond several hundred years. It typically requires shielding during handling and interim storage. This type of waste includes refurbishment waste, ion-exchange resins and some radioactive sources used in radiation therapy. TRU waste shall meet the following requirements and restrictions.

Type and Form of TRU Waste Material:

1. By-product, source, or special nuclear material consisting of process solids or resins, either dewatered, solid, or solidified.

2. Neutron activated metals or metal oxides in solid form.

3. Miscellaneous radioactive solid waste materials, including special form materials.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-11 Maximum Quantity of TRU Waste Contents per Package:

1. Greater than Type A quantities of radioactive material in the form of solids or dewatered materials in secondary containers.

2. Greater than Type A quantities of radioactive material in the form of activated reactor components or segments of components of waste from a nuclear process or power plant.

3. That quantity of any radioactive material not generating spontaneously more than 100 thermal watts of radioactive decay heat.

4. TRU waste not exceeding the fissile gram equivalents (FGE) of fissile radioactive material in Table 1.2-1 for the specified criticality configuration limits.

5. TRU waste contents shall comply with regulatory dose rates, as demonstrated in accordance with Chapter 7, Attachment 7.5-1. Note: Maximum activity limits for key individual gamma-emitting contents (e.g., Co-60, Cs-137 and Ba-137) and neutron-emitting contents (e.g., Cf-252 and Cm-244) are provided in Table 1.2-3.

Loading Restrictions:

1. TRU waste contents shall be in secondary containers (e.g., drums or boxes).

2. TRU waste contents with a total decay heat exceeding 50 watts shall be inerted with helium gas.

3. Explosives, corrosives, non-radioactive pyrophorics, and sealed items containing compressed and/or flammable gas (e.g., aerosol cans, lecture bottles, etc.) are prohibited.

Pyrophoric radionuclides may be present only in residual amounts less than 1 wt%. All nonradioactive pyrophoric material be reacted (or oxidized) and/or otherwise rendered nonreactive prior to placement in a secondary container (e.g., drum).

4. Free liquids shall not exceed 1% of the CCV cavity volume.

5. Maximum weight of the CCV contents, including TRU waste, secondary containers, and internal structures (e.g., CCV bottom support plate, SIA, etc.) and dunnage or shoring shall not exceed 3,500 pounds (1,587 kg).

1.2.2.2 Irradiated Fuel Waste The materials in Irradiated Fuel Waste (IFW) are restricted to low enriched uranium (LEU) fuel and metal structural components (e.g., cladding, liners, baskets, etc.) meeting the following requirements and restrictions.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-12 Type and Form of IFW Waste Material:

1. LEU fuel.

2. Activated metal structural components (e.g., cladding, liners, baskets, etc.).

Maximum Quantity of IFW Contents per Package:

1. Greater than Type A quantities of radioactive material in the form of LEU fuel.

2. Greater than Type A quantities of radioactive material in the form of activated metal structural components (e.g., cladding, liners, baskets, etc.).

3. That quantity of any radioactive material not generating spontaneously more than 100 thermal watts of radioactive decay heat.

4. IFW not exceeding the Fissile Equivalent Mass (FEM) limits from Table 1.2-2 for the specified criticality configuration limits.

5. IFW contents shall comply with regulatory dose rates, as demonstrated in accordance with Chapter 7, Attachment 7.5-1. Note: Maximum activity limits for key individual gamma-emitting isotopes (e.g., Co-60, Cs-137 and Ba-137m) and neutron-emitting isotopes (e.g., Cf-252 and Cm-244) are provided in Table 1.2-3.

Loading Restrictions:

1. IFW contents shall be in secondary containers (e.g., drums or boxes).

2. IFW contents with a total decay heat exceeding 50 watts shall be inerted with helium gas.

3. Free liquids shall not exceed 1% of the CCV cavity volume.

4. Maximum weight of the CCV contents, including IFW waste, secondary containers, and internal structures (e.g., CCV bottom support plate, SIA, etc.) and dunnage or shoring shall not exceed 3,500 pounds (1,587 kg).

1.2.2.3 TRISO Compacts configured with the GEO basket assembly subject to the following requirements and restrictions:

Type and Form of TRISO Compacts:

1. TRISO compacts shall be solid right circular

2. TRISO compacts shall be unirradiated.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-13 Maximum Quantity of TRISO Compacts per Package:

1. Maximum total weight 581 pounds (263 kg).

2. Maximum enrichment 20% U-235.

3. Total mean uranium loading 68 kgU

4. Maximum mean matrix density 1.8 g/cc.

For TRISO Compacts, the fuel may originate from enriched slightly contaminated uranium with trace quantity limits. The following table shows the maximum concentrations of the content, including contaminants. U-238 is not listed as it is assumed to be the remainder of the uranium concentration.

Isotope Maximum content U-232 2.6 x 10-9 g/gU-235 U-234 1.00 x 10-2 g/gU-235 U-235 2.00 x 10-1 g/gU U-238 Balance of Uranium Np-237 3.85 x 10-6 g/gU-235 Pu-238 1.56 x 10-10 g/gU-235 Pu-239/Pu-240 4.29 x 10-8 g/gU-235 Fission Products 0.25 mCi/gU Loading Restrictions:

1. TRISO compacts shall be shipped in the GEO basket assembly.

2. TRISO compacts shall not protrude above the top end of the GEO basket fuel tubes.

3. TRISO compact shall be shipped dry (i.e., no free liquids).

4. Non-metallic components such as spacers and/or adhesive-backed seals or labels may be included, however, these components must have an auto-ignition temperature of 300°F or higher and must be evaluated for gas generation in accordance with Attachment 7.5-3 prior to shipment.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-14 1.2.2.4 Shielded Devices Shielded Devices are shielded steel weldments containing sealed sources. This includes, but are not limited to the below devices:

Manufacturer Device Hopewell G10-1-360 G10-2-360 G10-1-2600 G10-2-2600 G10-2-2600-BX G10-3-150-A The bounding conditions for Shielded Devices for transport within the OPTIMUS-L are the dimensions of the Shielded Device, the surface dose rate on the surface of the Shielded Device, and the maximum weight of the Shielded Device.

Shielded Device Restrictions:

1. Maximum Weight, Shielded Device: 2,200 lb. (997 kg ref.)

2. Maximum Surface Dose Rate, Shielded Device: 100 mrem/hr

3. Maximum Dimensions, Shielded Device:

a.

Height: 40 in. (101.6 cm ref.)

b. Diameter: 14 in. excluding beam port, if present (35.56 cm ref.)

The Shielded Device may have a beam port feature protruding radially from the main body of the Shielded Device. The beam port shall fit within the cutout of the SDIA and shall extend into the cutout section a maximum of 2.9. To reduce the effective port dimension (i.e., limiting the length the beam port extends into the cutout), the annular gap between the Shielded Devices and fiberboard sections may be filled with metal, wood, or fiberboard segments to provide a net radial compressive strength greater than or equal to Free space between the Shielded Device and radial wall of the Shielded Device Insert Assembly will have dunnage to limit the movement during routine transport conditions.

Axial dunnage shall be placed below and above the Shielded Device to ensure the beam port is within the bounds of the lower insert port cutout dimensions.

If the Shielded Device does not have a beam port feature, the beam port cutout shall be filled with a dunnage of equivalent material used in the upper and lower radial spacer.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-15 1.2.3 Special Requirements for Plutonium Plutonium contents in quantities greater than 0.74 TBq (20 Ci) must be in solid form.

1.2.4 Operational Features The packaging has no special or complex operational features. Chapter 7 describes the operational steps, including use of the packagings operational features.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-16 Table 1.2-1 - TRU Waste FGE Limits Config. ID FGE Criticality Configuration Description FGE Limit g 239Pu (g 235U)(1)

Machine Compacted(2)

Weight %

Special Reflector(3)

Minimum 240Pu Credit FGE-1 1

340 (528)

FGE-2a 1

5 g 350 (544)

FGE-2b 1

15 g 375 (583)

FGE-2c 1

25 g 395 (614)

FGE-3

> 1 121 (188)

FGE-5 1

250 (388)

Notes:

(1)

FGE equivalents determined as described in Section 6.3.4. FGE conversion based on a ratio of subcritical mass limits in ANSI/ANS-8.1 [1-8], Section 5.2 of 0.7 kg (1.5 lb) for 235U and 0.45 kg (1.0 lb) for 239Pu. (See Table 7-1).

(2)

For uncompacted or manually compacted TRU waste, materials with hydrogen density up to that of water (0.1117 g/cm3) are unlimited, but materials with hydrogen density greater than water are limited to the hydrogen density of polyethylene (0.1336 g/cm3) and may not exceed 15% of the total contents by volume. For machine compacted contents, hydrogenous materials in the contents are limited to the hydrogen density of polyethylene (0.1336 g/cm3) in an unlimited quantity.

(3)

Special reflector materials are defined as beryllium, beryllium oxide, carbon (graphite), heavy water, magnesium oxide, and depleted uranium. The weight% of the special reflector materials is calculated as the mass of all special reflector materials present divided by the total mass of all waste material contents inside the secondary container. For FGE-3, these materials are unlimited.

Table 1.2-2 - IFW Waste FEM Limits Config. ID(1)

LEU Waste Criticality Configuration Description Weight %

Special Reflector(2)

Enrichment Limit, (wt% 235U)

Uranium Mass Limit, lbs. (kg)

FEM-1 1

0.90 wt%

2500 (1134)

Notes:

(1)

IFW contents must be non-machine compacted. Materials with hydrogen density up to that of water (0.1117 g/cm3) are unlimited, but materials with hydrogen density greater than water are limited to the hydrogen density of polyethylene (0.1336 g/cm3) and may not exceed 15% of the total contents by volume.

(2)

Special reflector materials are defined as beryllium, beryllium oxide, carbon (graphite), heavy water, magnesium oxide, and depleted uranium. The weight% of the special reflector materials is calculated as the mass of all special reflector materials present divided by the total mass of all waste material contents inside the secondary container.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-17 Table 1.2-3 TRU Waste and IFW Activity Limits for Key Isotopes Isotope Activity Limits(1) for Package Configurations (Ci)

Bare(2) 1-inch SIA(3) 21/4-inch SIA(4)

Co-60 8.197E-02 1.632E-01 4.284E-01 Cs-137(5) 4.066E-01 1.077E+00 4.228E+00 Cf-252 1.217E-02 1.289E-02 1.469E-02 Cm-244 3.819E+02 4.074E+02 4.654E+02 Notes:

(1)

Maximum activity limits are provided for entire content in a package. The corresponding maximum resultant dose rates from these isotopes at the listed activity limits are shown for the bare case (i.e., package without an SIA) in Table 5.1-2. Compliance with external dose rate limits shall be demonstrated with the isotope inventory of the individual package contents using the dose rate per curie values listed in Tables 7.5-1 and 7.5-2, as outlined in.5.1.

(2)

Package configuration without an SIA inside the CCV cavity.

(3)

Package configured with the 1-inch SIA inside the CCV cavity.

(4)

Package configured with the 21/4-inch SIA inside the CCV cavity.

(5)

Includes Ba-137m daughter.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-18 Figure 1.2-1 - CCV Packaging Components

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-19 Figure 1.2-2 Packaging Containment System NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-20 Figure 1.2-3 GEO Basket Assembly NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.2-21 Figure 1.2-4 Shielded Device Insert Assembly NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.3-1 1.3 Appendix 1.3.1 References

[1.1]

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

[1.2]

ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014.

[1.3]

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

[1.4]

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

[1.5]

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.

[1.6]

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NF, Supports, 2010 Edition with 2011 Addenda.

[1.7]

NUREG/CR-5502, Engineering Drawings for 10 CFR Part 71 Package Approvals, U.S.

Nuclear Regulatory Commission, May 1998.

[1.8]

ANSI/ANS-8.1-2014, Nuclear Criticality Safety In Operations With Fissionable Materials Outside Reactors.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.3-2 1.3.2 Glossary of Terms and Acronyms 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 CCV Cask Containment Vessel CF-RI Cellulosic Fiberboard Radial Insert CSI Criticality Safety Index FEM Fissile Equivalent Mass (of 235U)

FGE Fissile Gram Equivalent (of 239Pu)

HAC Hypothetical Accident Conditions ICV Inner Containment Vessel ILS Impact Limiter System LEU Low-Enriched Uranium MNOP Maximum Normal Operating Pressure NCT Normal Conditions of Transport OP Outer Packaging Package The packaging with its radioactive contents (payload), as presented for transportation (10 CFR 71.4). Within this report, the package is denoted as the OPTIMUS-L package.

Packaging The assembly of components necessary to ensure compliance with packaging requirements (10 CFR 71.4). Within this report, the Packaging is denoted as the OPTIMUS-L packaging, or simply as the packaging.

Payload Radioactive contents and dunnage PVA Polyvinyl Acetate RAM Radioactive Material RI Radial Insert SAR Safety Analysis Report (this document)

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 1.3-3 SDIA Shielded Device Insert Assembly SIA Shield Insert Assembly TRISO TRI-structural ISOtropic (fuel particle)

TRU Transuranic Waste

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A 1.3.3 Packaging General Arrangement Drawings The following drawings show the general arrangement and design features of the OPTIMUS-L packaging in accordance with NUREG/CR-5502 [1.7]. 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.

70000.14-L502 Packaging Assembly - OPTIMUS-L 0NP 70000.14-L510 CCV Assembly - OPTIMUS 0NP 70000.14-L511 CCV Body Weldment - OPTIMUS 0NP 70000.14-L512 CCV Lid - OPTIMUS 0NP 70000.14-L513 Port Cover - OPTIMUS 0NP 70000.14-L514 CCV Bottom Support Plate - OPTIMUS-L 0NP 70000.14-L540 Outer Packaging Assembly - OPTIMUS-L 0NP 70000.14-L541 Outer Packaging Base - OPTIMUS-L 0NP 70000.14-L542 Outer Packaging Lid - OPTIMUS-L 0NP 70000.14-L550 1-Inch Shield Insert Assembly (SIA) - OPTIMUS 0NP 70000.14-L551 21/4-Inch Shield Insert Assembly (SIA) - OPTIMUS 0NP 70000.14-L553 21/4-Inch SIA Annular Spacer Plate - OPTIMUS-L 0NP 70000.14-L560 GEO Basket Assembly, OPTIMUS-L 0NP 70000.14-L561 GEO Basket Weldment, OPTIMUS-L 0NP 70000.14-L595 Shielded Device Insert Assembly, OPTIMUS-L 0NP

GROUP NAME DATE SHIELDED DEVICE INSERT ASSEMBLY, OPTIMUS-L 1

1 N/A 0NP 5/17/2024 N. T. S.

NEXT ASSEMBLY DRAWING TYPE ALL DIMENSIONS ARE IN INCHES.

DIMENSIONING AND TOLERANCING SHALL BE PER ASME Y14.5M-94.

ALL THREAD DEPTH CALLOUTS ARE TO BE CONSIDERED AS A MINIMUM DEPTH OF PERFECT THREADS.

MACHINED SURFACES TO BE OR BETTER 0NP INITIAL ISSUE

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2-ii 2.7.6 Immersion - All Packages....................................................................... 2.7-47 2.7.7 Deep-Water Immersion Test (for Type B Packages Containing more than 105 A2).............................................................................................. 2.7-47 2.7.8 Summary of Damage............................................................................... 2.7-51 2.8 Accident Conditions for Air Transport of Plutonium.................................................. 2.8-1 2.9 Accident Conditions for Fissile Material Packages for Air Transport........................ 2.9-1 2.10 Special Form.............................................................................................................. 2.10-1 2.11 Fuel Rods................................................................................................................... 2.11-1 2.12 Appendices................................................................................................................. 2.12-1 2.12.1 References................................................................................................ 2.12-1 2.12.2 Computer Code Descriptions................................................................... 2.12-4 2.12.3

..................................... 2.12-5 2.12.4 Development of Equivalent Static Loads................................................ 2.12-7 2.12.5 Structural Evaluation of GEO Basket Assembly for TRISO Compact Contents.................................................................................. 2.12-11 2.12.6 Structural Evaluation of CCV Containing a Shielded Device............... 2.12-58 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2-iv Figure 2.7-8 - Cold/Hard HAC Side Drop (Case HS1) Rigid-Body Acceleration Time-History............................................................................................. 2.7-20 Figure 2.7-9 - Cold/Hard HAC Side Drop (Case HS1) OP Bolt Average Tensile Stress Time-History.................................................................................. 2.7-21 Figure 2.7-10 - Hot/Soft HAC Bottom Corner Drop (Case HBC2) OP Deformation.......... 2.7-26 Figure 2.7-11 - Hot/ Soft HAC Top Corner Drop (Case HTC2) OP Deformation.............. 2.7-27 Figure 2.7-12 - Cold/Hard HAC Bottom Corner Drop (Case HBC1) Rigid-Body Acceleration Time-History....................................................................... 2.7-28 Figure 2.7-13 - Cold/Hard HAC Top Corner Drop (Case HTC1) Rigid-Body Acceleration Time-History....................................................................... 2.7-28 Figure 2.7-14 - Cold/Hard HAC Top Corner Drop (Case HTC1) OP Bolt Average Tensile Stress Time-History..................................................................... 2.7-29 Figure 2.7-15 - Cold/Hard HAC 10° Bottom Oblique Drop (Case HBO1) OP Deformations............................................................................................. 2.7-33 Figure 2.7-16 - Cold/Hard HAC 10° Top End Oblique Drop (Case HTO1) OP Deformation.............................................................................................. 2.7-33 Figure 2.7-17 - Cold/Hard HAC 10° Bottom End Oblique Drop (Case HBO1) Rigid-Body Acceleration Time-History.............................................................. 2.7-34 Figure 2.7-18 - Cold/Hard HAC 10° Top End Oblique Drop (Case HTO1) Rigid-Body Acceleration Time-History.............................................................. 2.7-34 Figure 2.7-19 - HAC Puncture Drop Orientations................................................................ 2.7-40 Figure 2.7-20 - Cumulative OP Deformation - Hot/Soft HAC Top Center Puncture (Case PTE1).............................................................................................. 2.7-41 Figure 2.7-21 - Cumulative OP Deformation - Hot/Soft HAC Top Off-Center Puncture (Case PTE2)............................................................................... 2.7-42 Figure 2.7-22 - Cumulative OP Deformation - Hot/Soft HAC Side Puncture (Case PS1)........................................................................................................... 2.7-43 Figure 2.12-1 - Benchmark Comparison of HAC Side Drop Analysis and Test Results....................................................................................................... 2.12-6 Figure 2.12-2 - DLF Curve for Half-Sine Pulse................................................................. 2.12-10 Figure 2.12-3 - CCV Shell Bottom End 1/2-Symmetry Finite Element Model................... 2.12-10 Figure 2.12.5-1 - GEO Basket Bottom Plate Finite Element Model.................................. 2.12-32 Figure 2.12.5-2 - GEO Basket Finite Element Model, 0° Orientation............................... 2.12-33 Figure 2.12.5-3 - GEO Basket Finite Element Model, 30° Orientation............................. 2.12-34 Figure 2.12.5-4 - Plate Section Locations for Stress Evaluations, 0° GEO Model............ 2.12-35 Figure 2.12.5-5 - Weld Section Locations for Stress Evaluations, 0° GEO Model............ 2.12-36 Figure 2.12.5-6 - Plate Section Locations for Stress Evaluations, 30° GEO Model.......... 2.12-37 Figure 2.12.5-7 - Weld Section Locations for Stress Evaluations, 30° GEO Model.......... 2.12-38 Figure 2.12.5-8 - GEO Basket Fule Tube Finite Element Models..................................... 2.12-39 Figure 2.12.5-9 - SDOF Transient Analysis Model Schematic.......................................... 2.12-54 Figure 2.12.5-10 - GEO Basket Details for Modal Analasys Model.................................. 2.12-55 Figure 2.12.5-11 - CCV and GEO Basket Model for Modal Analysis............................... 2.12-56 Figure 2.12.5-12 - GEO Basket Bottom Plate Model for Modal Analysis......................... 2.12-57 Figure 2.12.6-1 - CCV with Shielded Device Insert Assembly.......................................... 2.12-61 Figure 2.12.6-2 - Fiberboard Material Properties at Cold Temperature............................. 2.12-64 Figure 2.12.6-3 - Fiberboard Material Properties at Hot Temperature............................... 2.12-65

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2-v Figure 2.12.6-4 - Finite Element Model of Shielded Device Insert Assembly for Side Drop Evaluation...................................................................................... 2.12-76 Figure 2.12.6-5 - DLF Curve for a Sine Impulse............................................................... 2.12-77

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2-vii Table 2.7-12 - HAC Pressure Stress Summary..................................................................... 2.7-46 Table 2.7-13 - Deep Water Immersion Test Stress Summary.............................................. 2.7-49 Table 2.7-14 - CCV Shell Buckling Summary for Deep Water Immersion Test................. 2.7-50 Table 2.12-1 -

...... 2.12-6 Table 2.12-2 - Summary of Free Drop DLFs and Equivalent Static Accelerations............. 2.12-9 Table 2.12.5-1 - GEO Basket Allowable Stress Design Criteria........................................ 2.12-13 Table 2.12.5-2 - Package Weight and Center of Gravity Summary for GEO Basket and TRISO Compact Contents Configuration........................................ 2.12-13 Table 2.12.5-3 - Mechanical Properties of SA537, Class 1 Carbon Steel.......................... 2.12-16 Table 2.12.5-4 - Mechanical Properties of SA350, LF3 Carbon Steel............................... 2.12-16 Table 2.12.5-5 - GEO Basket NCT Side Drop Plate Stress Summary, Pm......................... 2.12-29 Table 2.12.5-6 - GEO Basket NCT Side Drop Plate Stress Summary, Pm + Pb................. 2.12-29 Table 2.12.5-7 - GEO Basket NCT Side Drop CJP Weld Stress Summary, Pm................. 2.12-30 Table 2.12.5-8 - GEO Basket NCT Side Drop CJP Weld Stress Summary, Pm + Pb......... 2.12-30 Table 2.12.5-9 - GEO Basket NCT Side Drop Fillet Weld Stress Summary..................... 2.12-31 Table 2.12.5-10 - GEO Basket Fuel Tube NCT Side Drop Radial Compressive Forces...................................................................................................... 2.12-31 Table 2.12.5-11 - GEO Basket HAC Side Drop Plate Stress Summary, Pm...................... 2.12-46 Table 2.12.5-12 - GEO Basket HAC Side Drop Plate Stress Summary, Pm + Pb............... 2.12-46 Table 2.12.5-13 - GEO Basket HAC Side Drop CJP Weld Stress Summary, Pm.............. 2.12-47 Table 2.12.5-14 - GEO Basket HAC Side Drop CJP Weld Stress Summary, Pm + Pb....... 2.12-47 Table 2.12.5-15 - GEO Basket HAC Side Drop Fillet Weld Stress Summary................... 2.12-48 Table 2.12.5-16 - GEO Basket Fuel Tube HAC Side Drop Radial Compressive Forces...................................................................................................... 2.12-48 Table 2.12.5-17 - Summary of End Drop DLFs................................................................. 2.12-53 Table 2.12.5-18 - Summary of Side Drop DLFs................................................................ 2.12-53 Table 2.12.5-19 - Summary of Equivalent Static Accellerations....................................... 2.12-54 Table 2.12.6-1 - Weight and C.G. Summary for Shielded Device Content....................... 2.12-60 Table 2.12.6-2 - Summary of CCV Force Evaluation for the NCT Side Drop.................. 2.12-78 Table 2.12.6-3 - Accelerations for Bolt Stress Evaluation for NCT Side Drop................. 2.12-78 Table 2.12.6-4 - Summary of Bolt Stress Evaluation for NCT Side Drop......................... 2.12-78 Table 2.12.6-5 - Summary of CCV Force Evaluation for HAC Side Drop........................ 2.12-85 Table 2.12.6-6 - Accelerations for Bolt Stress Evaluation for HAC Side Drop................. 2.12-85 Table 2.12.6-7 - Summary of Bolt Stress Evaluation for HAC Side Drop......................... 2.12-85 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2-1 2

STRUCTURAL EVALUATION The structural evaluation of the OPTIMUS-L packaging demonstrates compliance with the applicable performance requirements of 10 CFR 71. Compliance with the applicable general standards 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. Structural evaluation demonstrating compliance with the applicable performance requirements of 10 CFR 71 for the GEO basket assembly with TRISO compact contents is contained in Section 2.12.5 and for the Shielded Device Insert Assembly with shielded device contents is contained in Section 2.12.6.

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 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 [2.3], as supplemented by Interim Staff Guidance - 21 (ISG 21) [2.4]. 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. Descriptions of these computer programs, including discussion of validation of the computer codes, are provided in Section 2.12.2. The computer models used for the structural evaluation are identified and described in the following sections.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-3

[2.29] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NG, Core Support Structures, 2010 Edition with 2011 Addenda.

[2.30] Regulatory Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants, Revision 1, March 2007.

[2.31] Thomson, W.T., Theory of Vibrations with Applications, Prentice-Hall, 2nd Edition.

[2.32]

[2.33]

[2.34] Dynamics Of Structures, Clough and Penzien, 3rd Edition, Computers and Structures, Inc. 2003.

[2.35] Machinerys Handbook, 29th edition. 2012, Industrial Press, New York.

[2.36] ECSS-E-HB-32-23A, Space engineering -Threaded Fasteners Handbook, European Cooperation For Space Standardization, April 16, 2010, Noordwijk, The Netherlands.

[2.37] ASME Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Power Plant Components, Division 1, Appendices, 2010 Edition with 2011 Addenda.

[2.38] Roarks formulas for Stress and Strain, 9th edition.

[2.39] ISO-898-1 Mechanical properties of fasteners made of carbon steel and alloy steel, Part 1: Bolts, screws and studs with specified property classes - Coarse thread and fine pitch thread, 5th edition, 2013-01015.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-58 2.12.6 Structural Evaluation of CCV Containing a Shielded Device This appendix supplements the main body of this chapter, describing the structural evaluation of the OPTIMUS-L transportation cask configured for the shipment of a shielded device under NCT and HAC free drop test conditions. Figure 2.12.6-1 shows a representative CCV with the shielded device and the supporting Shielded Device Insert Assembly. The Shielded Device Insert Assembly is an internal support structure that positions and supports the shielded device within the CCV cavity. The Shielded Device Insert Assembly consists of cellulosic fiberboard inserts and aluminum spacer plates. Dunnage is used as necessary to axially space and fill remaining gaps between the shielded device and the Shielded Device Insert Assembly.

2.12.6.1 Description of Structural Design NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-59 2.12.6.1.1 Design Criteria The aluminum spacer plates are evaluated in accordance with the applicable stress requirements of ASME code,Section III, Subsection NF [2.2] and Appendix F [2.6]. The retaining bolts for the beam port lead shipping plug are evaluated using the applicable stress criteria in NUREG-6007 [2.23].

2.12.6.1.2 Weights and Centers of Gravity The nominal weight and center of gravity of the package containing a shielded device are summarized in Table 2.12.6-1.

2.12.6.1.3 Identification of Codes and Standards for Packaging The aluminum spacer plates are designed and fabricated in accordance with the applicable requirements of Section III, Subsection NF of the ASME Code [2.2].

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-60 Table 2.12.6 Weight and C.G. Summary for Shielded Device Content Item Weight (kips)

C.G. (in.) (1)

Cask Containment Vessel (CCV) Assembly (2) 3.12 42.2 Outer Package (OP) Assembly (2) 2.59 34.8 CCV Contents

- Shielded Device Insert Assembly 0.77 32.7

- Shielded Device and Dunnage (maximum) 2.73(3) 32.6 Unloaded Package (4) 6.48 38.1 Loaded Package 9.20 36.5 Notes:

(1)

C.G. is measured from the bottom surface of the OP Assembly.

(2)

Values are determined based on weights and C.G. shown in Table 2.1-8.

(3)

Maximum allowable weight.

(4)

The unloaded package includes the weight of the CCV, Outer Packaging, and Shielded Device Insert Assembly.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-61 Figure 2.12.6-1 CCV with Shielded Device Insert Assembly NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-62 2.12.6.2 Materials 2.12.6.2.1 Material Properties and Specifications 2.12.6.2.2 Chemical, Galvanic or Other Reactions The position of the shielded device is maintained by the Shielded Device Insert Assembly, which consists of cellulosic fiberboard inserts and aluminum spacer plates. The shielded devices are typically comprised of heavy lead shielding encased within a carbon steel and/or stainless steel shell with internal tungsten and stainless steel source rod/holder. The sealed source is typically fully encapsulated in stainless steel.

Shielded devices will be handled and loaded dry and during transportation, the CCV precludes the introduction of any moisture from the environment into its cavity. The absence of water NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-63 significantly reduces the potential for adverse chemical and galvanic reactions. The lead shielding in the body of the shielded device is fully encased in its steel/stainless steel weldment and cannot be affected by water, atmospheric moisture, or any of the other materials present within the CCV cavity. No mechanism for reaction between the cellulosic fiberboard/PVA adhesive and the materials of the CCV or shielded device has been identified. Therefore, no significant chemical, galvanic, or other reactions are expected between the CCV, the Shielded Device Insert Assembly, and the content (shielded device).

2.12.6.2.3 Effects of Radiation on Material The shielded devices are limited to a measured surface dose rate not to exceed 100 mrem/hr which ensures no significant fluence to any of the materials of the Shielded Device Insert Assembly. Therefore, no degradation of the Shielded Device Insert Assembly materials is expected.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-64 Figure 2.12.6-2 Fiberboard Material Properties at Cold Temperature NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-65 Figure 2.12.6-3 Fiberboard Material Properties at Hot Temperature NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-66 2.12.6.3 Fabrication and Examination 2.12.6.3.1 Fabrication 2.12.6.3.2 Examination The dimensions of the Shielded Device Insert Assembly components are measured to assure compliance with the dimensional requirements shown on the general arrangement drawing 70000.14-L595 in Section 1.3.3. In addition, the weights of the Shielded Device Insert Assemblies are measured to assure that they meet the weight requirements.

2.12.6.4 Normal Conditions of Transport The shielded device insert assembly in the CCV cavity provides radial and axial support for the shielded device. All components of the shielded device insert assembly can expand freely and, therefore, thermal stresses due to differential thermal expansion of the shielded device insert assembly are expected to be insignificant for the CCV for both Heat and Cold tests of the NCT.

NCT free drop loads significantly bound loads from vibration normally incident to transport (2g) and as such, stress in the CCV due to vibration is insignificant. Furthermore, the internal pressure for the CCV containing shielded device is significantly bounded by that presented in Section 2.6.1.1. Therefore, the evaluations of the reduced or increased external pressure, water spray, compression, or penetration tests for the CCV with shielded device are bounded by the evaluations presented in Sections 2.6.3 through 2.6.6. The following sections describe the structural evaluation of the CCV containing a bounding shielded device for NCT free drop tests.

As shown in Table 2.6-3, peak rigid-body acceleration for the NCT bottom corner and top corner drop orientations are significantly less than the top end, bottom end, and side drop orientations.

As such, the following evaluations are focused on the NCT end drop and side drop conditions.

The retaining bolts for the devices beam port shipping plug are evaluated for side drop using NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-67 applicable criteria from NUREG-6007 [2.23]. The spacer plates are evaluated for end drop condition using applicable stress criteria from ASME Code subsection NF [2.2].

2.12.6.4.1 NCT Side Drop Evaluations NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-68 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-69 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-70 2.12.6.4.2 NCT End Drop Evaluations NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-71 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-72 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-73 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-74 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-75 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-76 Figure 2.12.6-4 Finite Element Model of Shielded Device Insert Assembly for Side Drop Evaluation NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-77 Figure 2.12.6-5 DLF Curve for a Sine Impulse NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-78 Table 2.12.6-2 Summary of CCV Force Evaluation for the NCT Side Drop Table 2.12.6-3 Accelerations for Bolt Stress Evaluation for NCT Side Drop Table 2.12.6-4 Summary of Bolt Stress Evaluation for NCT Side Drop NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-79 2.12.6.5 Hypothetical Accident Conditions The governing HAC test for the OPIMUS-L packaging containing shielded device is the free drop test. As shown in Section 7.1, peak rigid-body acceleration for the HAC bottom corner, bottom oblique, top corner, and top oblique drop orientations are significantly less than the HAC top end, bottom end, and side drop orientations. As such, the following evaluations are focused on the HAC end drop and side drop conditions. The following sections describe the structural evaluation of the CCV with shielded device for HAC side drop and end drop conditions. The retaining bolts for the beam port shipping plug and the spacer plates are evaluated for side drop and end drop conditions, respectively, using applicable stress criteria from ASME Code, Appendix F [2.6], as shown in Table 2.1-3.

2.12.6.5.1 HAC Side Drop Evaluations NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-80 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-81 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-82 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-83 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-84 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 2.12-85 Table 2.12.6-5 Summary of CCV Force Evaluation for HAC Side Drop Table 2.12.6-6 Accelerations for Bolt Stress Evaluation for HAC Side Drop Table 2.12.6-7 Summary of Bolt Stress Evaluation for HAC Side Drop NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3-i 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 Contents Decay Heat....................................................................................... 3.1-2 3.1.3 Summary Table of Temperatures...................................................................... 3.1-2 3.1.4 Summary Table of Maximum Pressures........................................................... 3.1-4 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 Heat and Cold................................................................................................. 3.3-12 3.3.2 Maximum Normal Operating Pressure........................................................... 3.3-12 3.4 Thermal Evaluation Under Hypothetical Accident Conditions.................................... 3.4-1 3.4.1 Initial Conditions.............................................................................................. 3.4-1 3.4.2 Fire Test Conditions.......................................................................................... 3.4-2 3.4.3 Maximum Temperatures and Pressure.............................................................. 3.4-4 3.4.4 Maximum Thermal Stresses............................................................................. 3.4-7 3.4.5 Accident Conditions for Fissile Material Packages for Air Transport............. 3.4-7 3.5 Appendices.................................................................................................................... 3.5-1 3.5.1 References......................................................................................................... 3.5-1 3.5.2 Sensitivity Analyses of Modeling Parameters.................................................. 3.5-3 3.5.3 Thermal Evaluation for TRISO Compact Contents.......................................... 3.5-7 3.5.4 Thermal Evaluation for Shielded Devices Contents......................................... 3.5-8

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3-ii List of Figures Figure 3.3-1 - Package 3-D 1/2-Symmetry Thermal Models for NCT................................... 3.3-16 Figure 3.3-2 - Expanded View of the CCV with Contents Modeled in 110-Gallon Drum.............................................................................................................. 3.3-17 Figure 3.3-3 - Application of Convection Boundary Conditions for NCT (and Shade)....... 3.3-18 Figure 3.3-4 - Heat Transfer Coefficients for General Standards (shade) and NCT............ 3.3-19 Figure 3.3-5 - NCT Heat Temperature Contour Plot - 100W Volumetric Heat Source...... 3.3-20 Figure 3.4-1 - Package 3-D 1/2-Symmetry Thermal Models for HAC.................................... 3.4-9 Figure 3.4-2 - Convection Boundary Conditions for HAC................................................... 3.4-10 Figure 3.4-3 - Heat Transfer Coefficients for HAC Analyses (Fire).................................... 3.4-11 Figure 3.4-4 - Heat Transfer Coefficients for HAC Analyses (Post-Fire Cool Down)........ 3.4-12 Figure 3.4-5 - Charred Polyurethane Foam at End of the Fire............................................. 3.4-13 Figure 3.4-6 - HAC Fire Temperature Time-Histories (100W Volumetric Heat Source in 110-gallon Drum,, Helium Fill Gas)......................................................... 3.4-14 Figure 3.4-7 - HAC Fire Temperature Time-Histories (100W Surface Heat Flux, Helium Fill Gas)............................................................................................ 3.4-14 Figure 3.4-7A - HAC Fire Temperature Time-Histories (100W Volumetric Heat Source in 55-gallon Drum in SIA, Helium Fill Gas)................................................ 3.4-15 Figure 3.4-8 - HAC Transient Analysis Temperature Contour Plots (100W Volumetric Heat Load in 110-gallon Drum, Helium Fill Gas)........................................ 3.4-16 Figure 3.4-8A - HAC Transient Analysis Temperature Contour Plots (100W Volumetric Heat Load in 55-gallon Drum in SIA, Helium Fill Gas)............................... 3.4-17 Figure 3.4-9 - HAC Transient Analysis Temperature Contour Plots (100W Surface Heat Flux on CCV Cavity )........................................................................... 3.4-18 Figure 3.5.2-1 - Modified Damage HAC Thermal Model...................................................... 3.5-6 Figure 3.5.4-1 - Heat Transfer Channels from the Shielded Device to the CCV................. 3.5-15

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3-iii List of Tables Table 3.1-1 - Summary of Packaging Temperatures for NCT................................................ 3.1-5 Table 3.1-2 - Summary of Packaging Temperatures for HAC............................................... 3.1-5 Table 3.1-3 - Summary of Maximum Pressures..................................................................... 3.1-5 Table 3.2-1 - Thermal Properties of Stainless Steel............................................................... 3.2-2 Table 3.2-1A - Thermal Properties of Carbon Steel............................................................... 3.2-2 Table 3.2-2 - Thermal Properties of Polyurethane Foam....................................................... 3.2-3 Table 3.2-3 - Thermal Properties of

...................................................... 3.2-3 Table 3.2-4 - Thermal Properties of Dry Air at Standard Pressure........................................ 3.2-4 Table 3.2-5 - Thermal Properties of Helium Gas at Standard Pressure.................................. 3.2-5 Table 3.2-6 - Temperature Limits of Packaging Components................................................ 3.2-5 Table 3.3-1 - Nusselt Number Calculation Constants of a Cylinder in Cross Flow............. 3.3-15 Table 3.3-2 - Maximum Package Temperatures for NCT Heat............................................ 3.3-15 Table 3.3-3 - Summary of Maximum Pressures for NCT.................................................... 3.3-15 Table 3.4-1 - Maximum Package Temperatures for HAC...................................................... 3.4-8 Table 3.4-2 - Summary of HAC Pressures............................................................................. 3.4-8 Table 3.5.2-1 - Maximum HAC Package Temperatures vs. CCV Position in OP Cavity...... 3.5-5 Table 3.5.2-2 - Maximum HAC Package Temperatures vs. Damage Model......................... 3.5-5 Table 3.5.4-1 - Fiberboard Insert Temperatures................................................................... 3.5-14 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3-1 3

THERMAL EVALUATION This section summarizes the thermal evaluation of the OPTIMUS-L package. TRU waste and irradiated fuel waste contents are evaluated for the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) prescribed by 10 CFR 71 in Sections 3.3 and 3.4.

TRISO compact contents, which are limited to fresh (unirradiated) fuel, have no appreciable decay heat load. As such, maximum packaging component temperatures for TRISO contents are significantly lower than the maximum temperatures for TRU waste and irradiated fuel waste contents and no detailed thermal evaluation is required. Further discussion on thermal considerations for the TRISO compact contents is included in Section 3.5.3. The OPTIMUS-L package may also be configured for transport of one shielded device. Shielded devices are lead shielded steel weldments containing sealed radioactive sources. Thermal evaluation of the packaging for the shielded device configuration is presented in Section 3.5.4.

The results of the thermal evaluation demonstrate that the packaging will remain within the applicable thermal limits, demonstrating the packages structural, containment and shielding integrity is not negatively affected during NCT and HAC.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-2

[3.14] General Plastics Manufacturing Company, "General Plastics LAST-A-FOAM FR-3700 for Crash and Fire Protection of Nuclear Material Shipping Containers," ML050410066, 1991.

[3.15] UNIFRAX, "Fiberfrax Duraboard Products," FFX/DB/001/E/R2, 2005.

[3.16] UNIFRAX, "Fiberfrax Durablanket S," U-111 EN, Rev.0, 2009.

[3.17] ANSYS, Inc., Release 2020-R2, 2020.

[3.18] Frank Kreith, Raj M. Manglik, Mark S. Bohn, Principles of Heat Transfer, 7th Edition, 2010.

[3.19]

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-3 3.5.2 Sensitivity Analyses of Modeling Parameters The finite element model used to evaluate the package for general packaging standards, NCT, and HAC was developed based on various assumptions that affect the predicted thermal response of the package. The purpose of this appendix is to evaluate the sensitivity of the thermal response to some of the key modeling assumptions used in the thermal analyses.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-4 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-5 Table 3.5.2-1 - Maximum HAC Package Temperatures vs. CCV Position in OP Cavity Table 3.5.2-2 - Maximum HAC Package Temperatures vs. Damage Model NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-6 Figure 3.5.2-1 - Modified Damage HAC Thermal Model NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-7 3.5.3 Thermal Evaluation for TRISO Compact Contents NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-8 3.5.4 Thermal Evaluation for Shielded Devices Content The OPTIMUS-L package may be configured for transport of shielded devices which are shielded steel weldments containing sealed sources. A shielded device insert assembly, which consists of fiberboard inserts and aluminum spacer plates, is used to fill the void between the shielded device and the CCV inner surfaces. Dunnage will be used as necessary within the cavity of the shielded device insert assembly to position the shielded device and limit potential movement during transport. The heat load of the shielded device is limited to less than 13.5 watts. As such, packaging component temperatures for CCV and OP in this configuration are bounded by those for the design basis condition of 50 watts content decay heat with air fill gas as shown in Table 3.3-2 for NCT and Table 3.4-1 for HAC. No further thermal analysis is required for the CCV and OP. Using a heat load of 13.5 watts, thermal evaluation is performed in this section to determine the maximum temperatures of the shielded device insert assembly, as well as the shielded device. Note that the evaluation uses the shielded device dimensions corresponding to the Hopewell G10-1-360 irradiator configuration, which has the shortest length of the shielded device casing for all the identified G10 devices.

3.5.4.1 Shielded Device Insert Assembly Temperature NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-9 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-10 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-11 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-12 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-13 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-14 Table 3.5.4 Fiberboard Insert Temperatures NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 3.5-15 Figure 3.5.4-1 Heat Transfer Channels from the Shielded Device to the CCV NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5-i 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.................................................................................................. 5.2-2 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....................................................................................... 5.4-4 5.4.3 Flux-to-Dose Rate Conversion.......................................................................... 5.4-4 5.4.4 External Radiation Levels................................................................................. 5.4-4 5.5 Appendix....................................................................................................................... 5.5-1 5.5.1 References......................................................................................................... 5.5-1 5.5.2 Shielding Analysis for Centered Packages and SIAs........................................ 5.5-2 5.5.3 Example Cases................................................................................................. 5.5-12 5.5.4 Shielded Device Shielding Evaluation............................................................ 5.5-14

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5-ii List of Figures Figure 5.3-1 - MCNP Shielding Models - Package Geometries............................................ 5.3-6 Figure 5.3-2 - MCNP Shielding Model - NCT Source Configuration................................... 5.3-6 Figure 5.3-3 - MCNP Shielding Model - HAC Source Configuration.................................. 5.3-7 Figure 5.3-4 - MCNP Shielding Model - NCT Tally Locations............................................ 5.3-7 Figure 5.3-5 - MCNP Shielding Model - HAC Tally Locaiton............................................. 5.3-8 Figure 5.4-1 - MCNP Sample Input File.............................................................................. 5.4-12 Figure 5.5-1 - MCNP Models with 1-inch SIA (left) and 21/4-inch SIA (right).................... 5.5-11 Figure 5.5-2 - Cell Tally Locations - Centered Package...................................................... 5.5-11 Figure 5.5-3 - Schematic and VISED Slices of G10-1-360.................................................. 5.5-24 Figure 5.5-4 - Schematic and VISED Slices of G10-2-360.................................................. 5.5-25 Figure 5.5-5 - Schematic and VISED Slices of G10-1-2600................................................ 5.5-26 Figure 5.5-6 - Schematic and VISED Slices of G10-2-2600................................................ 5.5-27 Figure 5.5-7 - Schematic and VISED Slices of G10-2-2600-BX......................................... 5.5-28 Figure 5.5-8 - Schematic and VISED Slices of G10-3-150-A.............................................. 5.5-29 Figure 5.5-9 - Global RZT Mesh Plot of G10-1-360, Radial Biasing, 60Co (XZ)................ 5.5-35 Figure 5.5-10 - Global RZT Mesh Plot of G10-1-360, Radial Biasing, 60Co (XY)............. 5.5-36 Figure 5.5-11 - 2-meter Mesh Plot of G10-2-2600, Radial Biasing, 60Co............................ 5.5-37 Figure 5.5-12 - Top Surface Mesh Plot of G10-2-2600-BX, 137Cs...................................... 5.5-38 Figure 5.5-13 - Bottom Surface Mesh Plot of G10-2-360, 60Co........................................... 5.5-39 Figure 5.5-14 - VISED Slices of G10-1-360 with 1.75 Lead Reduction............................ 5.5-40 Figure 5.5-15 - Global RZT Mesh Plot of G10-1-360, Radial Biasing, 137Cs (XZ) - NCT Reduced Lead............................................................................................... 5.5-41 Figure 5.5-16 - Global RZT Mesh Plot of G10-1-360, Radial Biasing, 137Cs (XY) - NCT Reduced Lead............................................................................................... 5.5-42 Figure 5.5-17 - 2-meter Mesh Plot of G10-2-2600, Radial Biasing, 137Cs - NCT Reduced Lead.............................................................................................................. 5.5-43 Figure 5.5-18 - Top Surface Mesh Plot of G10-2-2600, 137Cs - NCT Reduced Lead........ 5.5-44 Figure 5.5-19 - Bottom Surface Mesh Plot of G10-1-360, 60Co - NCT Reduced Lead....... 5.5-45 Figure 5.5-20 - Global RZT Mesh Plot of G10-1-360, Radial Biasing, 137Cs (XZ) - HAC Reduced Lead............................................................................................... 5.5-46

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5-iii List of Tables Table 5.1-1 - Package Shielding Design Features.................................................................. 5.1-3 Table 5.1-2 - Maximum External Dose Rates Examples........................................................ 5.1-4 Table 5.2-1 - Photon Source Energy Group Structure............................................................ 5.2-3 Table 5.2-2 - Neutron Source Energy Group Structure.......................................................... 5.2-4 Table 5.3-1 - Primary MCNP Model Package Dimensions.................................................... 5.3-3 Table 5.3-2 - Directional OP Stainless Steel Shell Combined Thickness.............................. 5.3-3 Table 5.3-3 - MCNP Shielding Model - Tally Locations...................................................... 5.3-4 Table 5.3-4 - Material Compositions...................................................................................... 5.3-4 Table 5.3-5 - MCNP Material Definitions.............................................................................. 5.3-5 Table 5.4-1 - ANSI/ANS-6.1.1 1977 Flux-to-Dose Conversion Factors............................... 5.4-7 Table 5.4-2 - MCNP Gamma Dose Rate Summary................................................................ 5.4-8 Table 5.4-3 - MCNP Neutron Dose Rate Summary............................................................... 5.4-9 Table 5.4-4 - ORIGEN Grouped Cf-252 Spectra................................................................. 5.4-10 Table 5.4-5 - Cf-252 2-meter Dose Rate/Ci Calculation...................................................... 5.4-11 Table 5.5-1 - SIA Design Shielding Thicknesses................................................................... 5.5-4 Table 5.5-2 - MCNP Tally Locations - Centered Package.................................................... 5.5-4 Table 5.5-3 - MCNP NCT Gamma Dose Rates with No SIA............................................... 5.5-5 Table 5.5-4 - MCNP NCT Neutron Dose Rates with No SIA............................................... 5.5-6 Table 5.5-5 - MCNP NCT Gamma Dose Rates with 1-inch SIA........................................... 5.5-7 Table 5.5-6 - MCNP NCT Neutron Dose Rates with 1-inch SIA.......................................... 5.5-8 Table 5.5-7 - MCNP NCT Gamma Dose Rates with 21/4-SIA................................................ 5.5-9 Table 5.5-8 - MCNP NCT Neutron Dose Rates with 21/4-inch SIA..................................... 5.5-10 Table 5.5-9 - Sample Dose Rate Calculations...................................................................... 5.5-13 Table 5.5-10 - G10 Source Device Content Description..................................................... 5.5-16 Table 5.5-11 - Summary of Maximum OPTIMUS-L Dose Rates - Minimum Device Shielding - 100 mrem/hr Device Surface Limit Not Applied....................... 5.5-16 Table 5.5-12 - Summary of Maximum OPTIMUS-L Dose Rates........................................ 5.5-17 Table 5.5-13 - 60Co Source Spectrum................................................................................... 5.5-19 Table 5.5-14 - 137Cs Source Spectrum.................................................................................. 5.5-20 Table 5.5-15 - G10 Device Common Dimensions................................................................ 5.5-30 Table 5.5-16 - G10 Device Variable Dimensions................................................................. 5.5-31 Table 5.5-17 - Material Properties Used in Source Device Shielding Evaluation................ 5.5-31 Table 5.5-18 - OPTIMUS-L Maximum Dose Rates (mrem/hr)........................................... 5.5-47 Table 5.5-19 - Device Bottom Dose Rates with Minimum Lead......................................... 5.5-47 Table 5.5-20 - G10 360 Device Bottom Dose Rates with 3 Inches of Lead......................... 5.5-48 Table 5.5-21 - Governing Dose Rates Prior to Lead Reduction........................................... 5.5-48 Table 5.5-22 - G10-1-360 Radial and Bottom Dose Rates with 1.75 Lead Reduction....... 5.5-48 Table 5.5-23 - G10-2-2600 Co60dn Radial Dose Rates with 1.75 Lead Reduction........... 5.5-49 Table 5.5-24 - G10-2-2600-BX Co60dn Top Dose Rates with 1.75 Lead Reduction........ 5.5-49 Table 5.5-25 - G10 HAC 1 meter Dose Rates with 2.6 Lead Reduction............................ 5.5-49

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5-1 5

SHIELDING EVALUATION The packaging is designed to provide adequate shielding and its contents are limited to ensure dose rate limits 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.

The shielding evaluation of shielded devices is documented in Section 5.5.4.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-1 5.5 Appendix 5.5.1 References

[5.1]

American Society of Mechanical Engineers, "Specification for General Requirements for Flat-Rolled Stainless and Heat-Resisting Steel Plate, Sheet, and Strip," ASME SA-480/

SA-480M, 2010 Edition with 2011 Addenda.

[5.2]

Oak Ridge National Laboratory, "SCALE Code System," ORNL/TM-2005/39, Version 6.2.2, 2017.

[5.3]

Los Alamos National Laboratory, "Initial MCNP 6 Release Overview - MCNP6 Version 1.0," LA-UR-13-22934, Rev.0, 2013.

[5.4]

Los Alamos National Laboratory, "Listing of Available ACE Data Tables," LA-UR 21822 Rev. 4, 2014.

[5.5]

U.S. Nuclear Regulatory Commission, "Standard Review Plan for Transportation Packages for Spent Nuclear Fuel," NUREG-1617, 2000.

[5.6]

American Nuclear Society, "Neutron and Gamma Flux-To-Dose Conversion Factors,"

ANSI/ANS 6.1.1-1977, 1977.

[5.7]

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

[5.8]

Los Alamos National Laboratory, "MCNP Users Manual, Code Version 6.2, LA-UR-17-29981, Rev. 0, 2017.

[5.9]

Pacific Northwest National Laboratory, "Compendium of Material Composition Data for Radiation Transport Modeling," PNNL-15870 Rev. 2, 2021

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-14 5.5.4 Shielded Device Shielding Evaluation This section documents the shielding evaluation of shielded devices in the OPTIMUS-L.

5.5.4.1 Description of Shielding Design The only difference in the NCT and HAC models of the OPTIMUS-L is the foam of the outer packaging. As the source devices are gamma sources only, this foam will have a minimal effect on dose rates. Therefore, the HAC model (consisting of the CCV without foam) is used to compute dose rates.

The shielded devices are composed of a source rod located in the device cavity steel tube. A bolted closure plate assures that the source rod remains within the device cavity. The device primary shielding is composed of lead within a cylindrical stainless steel structure. The source rod typically contains one or more 137Cs or 60Co regions, and tungsten axial shielding. Devices typically have a beam port.

5.5.4.1.1 Shielding Design Features 5.5.4.1.2 Summary of Maximum Radiation Levels NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-15 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-16 Table 5.5 G10 Source Device Content Description Table 5.5 Summary of Maximum OPTIMUS-L Dose Rates - Minimum Device Shielding - 100 mrem/hr Device Surface Limit Not Applied*

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-17 Table 5.5 Summary of Maximum OPTIMUS-L Dose Rates NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-18 5.5.4.2 Source Specification NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-19 Table 5.5 60Co Source Spectrum NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-20 Table 5.5 137Cs Source Spectrum NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-21 5.5.4.3 Shielding Model The only difference in the NCT and HAC models of the OPTIMUS-L is the foam of the outer packaging. As the source devices are gamma sources only, this foam will have a minimal effect on dose rates. Therefore, the HAC model (consisting of the CCV without foam) is used to compute dose rates.

Two cask models are used to compute dose rates.

5.5.4.3.1 Configuration of Source and Shielding NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-22 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-23 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-24 Figure 5.5 Schematic and VISED Slices of G10-1-360 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-25 Figure 5.5 Schematic and VISED Slices of G10-2-360*

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-26 Figure 5.5-5 Schematic and VISED Slices of G10-1-2600 NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-27 Figure 5.5 Schematic and VISED Slices of G10-2-2600*

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-28 Figure 5.5 Schematic and VISED Slices of G10-2-2600-BX*

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-29 Figure 5.5 Schematic and VISED Slices of G10-3-150-A*

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-30 Table 5.5 G10 Device Common Dimensions NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-31 Table 5.5 G10 Device Variable Dimensions Table 5.5 Material Properties Used in Source Device Shielding Evaluation NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-32 5.5.4.4 Shielding Evaluation 5.5.4.4.1 Methods For this dose rate analysis, the MCNP6.2 [5.8] 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.

Dose rate results are based on F4 mesh tallies. Surface cylindrical mesh detectors use 4 cm divisions on the perpendicular and parallel planes to the surface of interest. The radial cylindrical detectors use 36 azimuthal divisions, while the top and bottom cylindrical detectors apply 18 azimuthal divisions at 2 meters and under.

XYZ meshes are used to evaluate the planes at the surface of the vehicle and 2 meters from the vehicle. The vehicle surface tally uses an 8 cm spacing in the y and z direction. The vehicle surface detector is based on half of the pallet width, rounded down to 25 inches (63.5 cm).

5.5.4.4.2 Input and Output Data Problem convergence is accelerated by using exponential transform and weight windows.

The tally fluctuation chart and probability density function plot were reviewed 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.

5.5.4.4.3 Flux-to-Dose Rate Conversion Flux to dose rate conversion factors are defined in Section 5.4.3.

5.5.4.4.4 External Radiation Levels Design Minimum Lead Thickness Results for the design minimum lead thicknesses are presented in Table 5.5-18. Bottom dose rates are shown for both the steel CCV bottom support plate initially evaluated and the SDIA aluminum plate that was part of the final insert design; bottom dose rates are bounding for the evaluated devices. In general, the 60Co sources are governing.

For the evaluated devices, maximum radial surface and 2-meter dose rates are from the 1-360 and 2-2600, Co60dn* configurations, respectively. Maximum top surface and 2-meter dose rates are from the 2-2600-BX, Co60dn configuration. Maximum bottom dose rates are from the 2-360,

• And Cs137up.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-33 Co60dn configuration. Mesh plots are shown in Figure 5.5-9 through Figure 5.5-13. The minimum margin is for the bottom surface dose rate. While Table 5.5-18 shows a significant range of results for the various devices, significant margin to regulatory limits exist with only the bottom surface approaching regulatory limits within an order of magnitude.

Based on the margins in Table 5.5-18, modeling a centered device for HAC is an acceptable configuration (for the device relative to the OPTIMUS-L).

Dose rates on the OPTIMUS-L surfaces and at 2-meters are significantly below regulatory limits for all evaluated configurations.

Applying Device Surface Dose Rate Limit of 100 mrem/hr As shown in the mesh plots referenced above, the 100 mrem/hr device surface dose rate limit is exceeded with the design maximum activity levels and design minimum lead thickness.

Table 5.5-19 lists the dose rate results immediately below the bottom surface of the device to illustrate how far above the 100 mrem/hr device surface limit a minimum lead analysis results are.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-34 Reduced Lead Thickness NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-35 Figure 5.5 Global RZT Mesh Plot of G10-1-360, Radial Biasing, 60Co (XZ)

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-36 Figure 5.5 Global RZT Mesh Plot of G10-1-360, Radial Biasing, 60Co (XY)

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-37 Figure 5.5-11 2-meter Mesh Plot of G10-2-2600, Radial Biasing, 60Co NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-38 Figure 5.5-12 Top Surface Mesh Plot of G10-2-2600-BX, 137Cs NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-39 Figure 5.5-13 Bottom Surface Mesh Plot of G10-2-360, 60Co NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-40 Figure 5.5-14 VISED Slices of G10-1-360 with 1.75 Lead Reduction NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-41 Figure 5.5-15 Global RZT Mesh Plot of G10-1-360, Radial Biasing, 137Cs (XZ) - NCT Reduced Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-42 Figure 5.5-16 Global RZT Mesh Plot of G10-1-360, Radial Biasing, 137Cs (XY) - NCT Reduced Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-43 Figure 5.5-17 2-meter Mesh Plot of G10-2-2600, Radial Biasing, 137Cs - NCT Reduced Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-44 Figure 5.5-18 Top Surface Mesh Plot of G10-2-2600, 137Cs - NCT Reduced Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-45 Figure 5.5-19 Bottom Surface Mesh Plot of G10-1-360, 60Co - NCT Reduced Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-46 Figure 5.5-20 Global RZT Mesh Plot of G10-1-360, Radial Biasing, 137Cs (XZ) - HAC Reduced Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-47 Table 5.5 OPTIMUS-L Maximum Dose Rates (mrem/hr)

Table 5.5-19 Device Bottom Dose Rates with Minimum Lead NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-48 Table 5.5-20 G10 360 Device Bottom Dose Rates with 3 Inches of Lead Table 5.5-21 Governing Dose Rates Prior to Lead Reduction Table 5.5-22 G10-1-360 Radial and Bottom Dose Rates with 1.75 Lead Reduction NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 5.5-49 Table 5.5-23 G10-2-2600 Co60dn Radial Dose Rates with 1.75 Lead Reduction Table 5.5-24 G10-2-2600-BX Co60dn Top Dose Rates with 1.75 Lead Reduction Table 5.5-25 G10 HAC 1 meter Dose Rates with 2.6 Lead Reduction NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 7.1-3 Note:

A maintenance leakage rate test is required for any replaced CCV lid or vent port containment O-ring, per Section 8.2.2.1.

15. Visually inspect the 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.

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.

16. Coat the exposed surfaces of the CCV lid and CCV port cover O-ring seals with vacuum grease prior to assembling the package to minimize deterioration or cracking of the seal during use. Remove excess vacuum grease from the O-ring and fastener seals prior to assembling the package.

17. Visually inspect the CCV lid bolts, CCV 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.

Caution: When lowering packaging internals inside the CCV cavity, protect the CCV body bolt flange sealing surface from damage (e.g., scratches or gouges).

18. If packaging internals (e.g., cribbing/dunnage, SIA body, Shielded Device Insert Assembly (SDIA), etc.) required for the shipment are not inside the CCV cavity, use suitable rigging to lift and lower the required internals into the CCV cavity.

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 the 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, SIA, and SDIA components) required for the shipment are properly configured in the CCV cavity.

Caution: When lowering the contents into the CCV or SIA cavity, protect the CCV body bolt flange sealing surface from damage (e.g., scratches or gouges).

3. Lower the contents into the CCV cavity or SIA cavity (if used).

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 7.1-4

4. Add additional pieces of any inserts that fit around the payload and/or any dunnage necessary for the shipment.

5. Clean and visually inspect the sealing surface for the CCV lid (i.e., the area of the CCV body bolt flange inboard of the CCV lid bolt holes) and the CCV port cover (i.e., the area of the CCV lid port opening inboard of the CCV port cover bolt holes), if removed, for wear and/or damage (e.g., scratches, gouges, nicks, cracks, etc.) that may prevent the containment O-rings and fastener seals from sealing properly.

6. Coat the CCV closure bolt threads with thread lubricant.

7. Lift the CCV lid, position it over the alignment pins on the CCV body, and carefully lower it onto the CCV body.

8. Remove the SHRs from the CCV lid.

9. Tighten each of the CCV lid bolts, in the sequence shown on the CCV lid, to a torque of 300 +/- 15 ft-lbs and repeat the sequence to verify that all CCV lid bolts are tightened to the required torque.

10. If the package is loaded with contents having a total heat load greater than 50 watts evacuate the CCV cavity and contents to an oxygen content of 1% or less, then backfill with helium gas.

11. If removed, install the CCV port cover and torque the port cover bolts to 15+/- 1 in-lbs1.

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:

Note:

A pre-shipment leakage rate test of the CCV port cover O-ring seals is required prior to every shipment, even if the port cover is not removed for loading operations.

1. Perform the pre-shipment leakage rate test of the CCV lid and port cover O-ring seals in accordance with a written procedure that satisfies the requirements of Section 8.2.2.2.

1 Torque applies to CCV port cover bolts made from SA193, Gr. B8, Class 1 material. When CCV port cover bolts made from SA-320, Grade L7 or L43 material are used, torque the port cover bolts to 45 +/- 3 in-lbs.

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 7.1-5

2. Install the plugs in the leak test ports of the CCV lid and CCV port cover.

3. Decontaminate the exterior top surface of the CCV as necessary.

4. Place the OP lid onto the OP base.

5. Tighten each of the OP lid bolts to a torque of 50 +/- 5 ft-lbs.

6. If required, move the package from the loading area to the trailer.

7. Verify that the package tiedowns are installed and the package is secured to the trailer.

8. Install the tiedown disabling devices on the OP lid lifting lugs.

9. Install the tamper-indicating devices on the package.

10. Verify external radiation levels do not exceed the limits of 49 CFR 173.441(b).

11. Verify the levels of non-fixed contamination on the package do not exceed the limits of 49 CFR 173.443(a)(1).

12. 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).

13. Verify the package marking and labeling meets the requirements of 49 CFR 172.

14. Provide specific written instructions for maintenance of the exclusive use shipment controls to the carrier in accordance with the requirements of 49 CFR 173.441(c).

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 8.1-4 from the foam to extinguish, and the burn length are measured. The acceptance criteria for the flame retardancy test is an average elapsed time no greater than 15 seconds for the foam specimen to extinguish, the average elapsed time no greater than 3 seconds for all drips from the foam to extinguish, and average burn length no greater than 6 inches.

Intumescence Each batch of foam used to construct the foam segments of the OP base and lid assemblies shall be tested to determine its average intumescence in accordance with the foam manufacturers test procedures. A minimum of three test samples from each batch of foam shall be tested. A typical test subjects a 2-inch cubic test sample of foam, which mounted on the face of a fiberboard with the foam direction of rise perpendicular to the fiberboard surface, to the heat from a furnace at 1,475°F. The foam sample is removed from the heat after 90 seconds, any flames on the sample are gently extinguished, and the sample is cooled to room temperature. The intumescence is calculated as the percentage of the original foam thickness remaining. The acceptance criteria for the test is an average intumescence of the foam samples no less than 50% for 24 pcf foam and 10% for 5 pcf foam.

8.1.5.3 Cellulosic Fiber Insulating Board Each lot of cellulosic fiber insulating board used to construct the segments of the shielded device insert assembly shall be tested for density. Cellulosic fiber insulating board not meeting the acceptance criteria shall be rejected.

8.1.6 Shielding Tests The packaging does not require shielding acceptance testing because the shielding component are made from solid steel. The packaging does not in include any special shielding features, such as a poured lead gamma shield, and the material properties used for the shielding evaluation of the package are sufficiently conservative.

8.1.7 Thermal Tests Thermal acceptance testing of the packaging is not required because the packaging does not include any special thermal features that require thermal acceptance testing and the material properties used for the thermal evaluation of the package are sufficiently conservative.

8.1.8 Miscellaneous Tests Not Applicable.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 8.2-7 another unit manufactured or refurbished to the requirements shown in the general arrangement drawings in Section 1.3.2.

8.2.5.3 Cellulosic Fiber Insulating Board Segment Repair NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR June 2024 Docket No. 71-9390 Revision 24A NAC International 8.3-1 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, 2010 Edition with 2011 Addenda.

[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]

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NF, Supports, 2010 Edition with 2011 Addenda.

[8.5]

ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014

[8.6]

ASME Boiler and Pressure Vessel Code,Section V, Nondestructive Examination, Subsection A, Nondestructive Methods of Examination, 2013 Edition, July 1, 2013.

[8.7]

NAC PROPRIETARY INFORMATION REMOVED