ML20266G183

Enclosure 1 - OPTIMUS-L Safety Analysis Report, Revision 20A. (Non-Proprietary Version)

ML20266G183
Person / Time
Site:	OPTIMUS-L
Issue date:	08/31/2020
From:	NAC International
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML20266G181	List: ML20266G182 ML20266G183
References
ED20200118
Download: ML20266G183 (501)

Text

August 2020 Revision 20A ,

1 " !

ANAC

~I INTERNATIONAL Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www,nacintl.com

NAC PROPRIETARY INFORMATION Enclosure I to ED20200118 Page I of2 Enclosure 1

-Supporting Calculations OPTIMUS-L SAR, Revision 20A

NAG PROPRIETARY INFORMATION Enclosure 1 to ED20200118 Page 2 of2

• Enclosure 1 Contents

1. CN-16007-111 Rev. 2

2. CN-16007-211 Rev. 0

3. CN-16007-212 Rev. 1

4. CN-16007-213 Rev. 0

5. CN-16007-214 Rev. 1

6. CN-16007-215 Rev. 1

7. CN-16007-216 Rev. 0

8. CN-16007-311 Rev. 1

9. CN-16007-401 Rev. 1

10. CN-16007-501 Rev. 1

11. CN-16007-512 Rev. 2

12. CN-16007-601 Rev. 2

13. CN-16007-612 Rev. 0 CALCULATIONS WITHHELD IN THEIR ENTIRETY

- --*-- PER 10 CFR 2.390

Enclosure 2 to ED20200118 Page I of I Enclosure 2 OPTIMUS-L SAR, Revision 20A

OPTIMUS-L Safety Analysis Report August 2020 Docket No. 71-9390 Revision 20A List of Effective Pages Chapter I Chapter 5 Page 1-i thm I-ii ..................... Revision 20A Page 5-i thru 5-iii .................... Revision 20A Page 1-1 .................................. Revision 20A Page 5-1 .................................. Revision 20A Page I.I-I thm 1.1-2 ............... Revision 20A Page 5.1-1 thm 5.1-4 ............... Revision 20A Page 1.2-1 thm 1.2-14............. Revision 20A Page 5.2-1 thm 5.2-4 ............... Revision 20A Page 1.3-1 thm 1.3-3 ............... Revision 20A Page 5.3-1 thm 5.3-10 ............. Revision 20A Page 5.4-1 thm 5.4-29 ............. Revision 20A 12 drawings (see Section 1.3) Page 5.5-1 thm 5.5-28 ............. Revision 20A Chapter 2 Chapter 6 Page 2-i thm 2-vi .................... Revision 20A Page 6-i thm 6-v...................... Revision 20A Page 2-1 .................................. Revision 20A Page 6-1 .................................. Revision 20A Page 2.1-1 thm 2.1-20............. Revision20A Page 6.1-1 thm 6.1-2 ............... Revision 20A Page 2.2-1 thm 2.2-10 ............. Revision 20A Page 6.2-1 thm 6.2-3 ............... Revision20A Page 2.3-1 thm 2.3-4 ............... Revision 20A Page 6.3-1 thm 6.3-20 ............. Revision 20A Page 2.4-1 ............................... Revision 20A Page 6.4-1 thm 6.4-15 ............. Revision 20A Page 2.5-1 thm 2.5-14............. Revision 20A Page 6.5-1 thru 6.5-14 ............. Revision 20A Page 2.6-1 thm 2.6-37 ............. Revision 20A Page 6.6-1 thm 6.6-15 ............. Revision 20A Page 2.7-1 thru 2.7-52 ..-........... Revision 20A Page 6.7-1 ............................... Revision 20A

__* __________Page ~~8~1 _:_:_:::=*_:_:_::::=~~~* Rev~~on_20A__ Page 6~8~1-_thm 6_.8=1~~~-:=**~:~_Re~s~on 20~- _____ _

Page 2.9-1 ............................... Revts1on 20A Page 6.9-1 thm 6.9-2 ............... Rev1s1on 20A Page 2.10-1 ............................. Revision 20A Page 2.11-1 ............................. Revision 20A Chapter?

Page 2.12-1 thm 2.12-9 ........... Revision20A Page 7-i ................................... Revision 20A Page 7-1 .................................. Revision 20A Chapter3 Page 7.1-1 thm Page 7 .1-5 ...... Revision 20A Page 3-i thru 3-iii .................... Revision 20A Page 7.2-1 thm 7.2-2 ............... Revision 20A Page 3-1 .................................. Revision 20A Page 7.3-1 thru 7.3-2 ............... Revision 20A Page 3.1-1 thru 3.1-4............... Revision 20A Page 7.4-1 ............................... Revision 20A Page 3.2-1 thm 3.2-4............... Revision 20A Page 7.5-1 thm 7.5-4 ............... Revision20A Page 3.3-1 thru 3.3-20 ............. Revision 20A Page 3.4-1 thm 3.4-15 ............. Revision 20A Chapter8 Page 3.5-1 thm 3.5-6 ............... Revision 20A Page 8-i thm 8-ii ..................... Revision 20A Page 8-1 .................................. Revision 20A Chapter 4 Page 8.1-1 thm 8.1-5 ............... Revision 20A Page 4-i thm 4-ii ..................... Revision 20A Page 8.2-1 thru 8.2-8 ............... Revision 20A Page 4-1 .................................. Revision 20A Page 8.3-1 ............................... Revision 20A Page 4.1-1 thru 4.1-3 ............... Revision 20A Page 4.2-1 ............................... Revision 20A Page 4.3-1 ............................... Revision 20A Page 4.4-1 ............................... Revision 20A Page 4.5-1 thm 4.5-13 .............. Revision 20A Page I of I

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• ,August 2020

Revi-sion 20A OPTIMUS-L (OPTlmal ,Modular Yniversal

§.hipping Cask)

SAFETY

• ANALYSIS REPORT NON-PROPRIETARY VERSION

• Do*c'ket N'o. 71-93*90 ANAC

• ii INTERNATIONAL Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.naclntl.com

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 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 Contents ..................................................................................................... 1.2-8 1.2.3 Special Requirements for Plutonium ....................................................... 1.2-10 1.2.4 Operational Features ................................................................................ 1.2-10 1.3 Appendix ...................................................................................................................... 1.3-1 1.3.1 References .................................................................................................. 1.3-1 1.3.2 Glossary of Terms and Acronyms ............................................................. 1.3-2 1.3 .3 Packaging General Arrangement Drawings ............................................... 1.3-3

• NAC International 1-i

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A List of Figures Figure 1.1 Expanded View of OPTilvillS-L Packaging ................................................. 1.1-2 Figure 1.2 CCV Packaging Components ........................................................................ 1.2-13 Figure 1.2 Packaging Containment System .................................................................... 1.2-14 List of Tables Table 1.2 TRU Waste FGE Limits .................................................................................. 1.2-11 Table 1.2 IFW Waste FEM Limits .................................................................................. 1.2-l l Table 1.2 TRUWaste and IFW Activity Limits ............................................................. 1.2-12 NAC International 1-ii

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 1 GENERAL INFORMATION This chapter of the Safety Analysis Report (SAR) presents a general introduction to, and description of, the OPTimal Modular Universal §_hipping cask for 1_ow activity contents (OPTIMUS-L). An expanded view of the packaging is shown in Figure 1.1-1. Descriptions of the packaging, including the packaging features, contents, and operational features, are presented in Section 1.2. A glossary of the general terminology and acronyms used throughout this SAR is presented in Appendix 1.3.2. The packaging General Arrangement Drawings are included in Appendix 1.3 .3.

As demonstrated by this SAR, the OPTIMUS-L package satisfies the regulatory requirements of the United States Nuclear Regulatory Commission (NRC) regulations, namely Title 10, Part 71 of the Code of Federal Regulations (10 CFR 71) .

• NAC International 1-1

This page intentionally left blank.

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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 greater than 3000A2. Accordingly, 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 in an open conveyance. 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 Nl 4.5-2014 [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 CC\C The OP also insulates the CGV from the direct effects of-the-fire during the HAC thermal test.

A Shield Insert Assembly (SIA) may be included inside the CCV for contents that require additional shielding. SIAs used in the OPTIMUS-L packaging are provided in I-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.

This 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)(l) and 10 CFR 71.5l(a)(2) .

• NAC International 1.1-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

' . ~ OP Lift Lug OP Lid OP Lid

[)J I

~ r~

1 I

• Closure Bolts CCV Closure Bolts

~ j I

~ CCV Port Cover CCV Lid O-rings CCV Body OP Body

\ Tiedown Arm Figure 1.1 Expanded View of OPTIMUS-L Packaging NAC International 1.1-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 1.2 Package Description 1.2.1 Packaging The OPTIMUS-L packaging consists of a Cask Containment Vessel (CCV), a CCV bottom support plate, and an Outer Packaging (OP) assembly. The CCV bottom support plate is a free-standing carbon steel plate positioned at the bottom end of the CCV cavity below the contents. The CCV fits within the cavity of the OP. An expanded view of the packaging components is shown in Figure 1.1-1. The packaging may also include an optional Shield Insert Assembly (SIA) within the cavity of the CCV and provides additional shielding.

The CCV is the packaging containment system. It is a stainless steel cylindrical vessel that includes a body weldment, bolted lid, bolted port cover, and 0-ring seals. An expanded view of the CCV assembly is shown in Figure 1.2-1. The CCV has an outer diameter of 34.5 inches (876 mm), which expands to 39.0 inches (991 mm) at the bolt flange and lid, and an overall height of 51.38 inches (1,305 mm). The internal cavity of the CCV is 032.5 inches (0826 mm) by 47.0 inches (1,194 mm) high; large enough to accommodate a 110-gallon drum. The CCV lid, which is thick, is fastened to the CCV body b -

• socket head cap screws (e.g., CCV closure bolts). The CCV~? _in_c!u~s ~ ~01! u_se~ ror}n~~i!!g

- - the EEV caviry- ana -contents~--ifiequired~ A bolted pent- cover is used to seal the CCV port during transport. The CCV closure devices are discussed further in Section 1.2.1.5, Packaging Closure Devices.

The CCV bottom support plate is a free-standing coated carbon steel plate that is positioned at the bottom end of the CCV cavity below the contents. The CCV bottom support plate is designed to spread the loading on the CCV bottom end plate from the contents under NCT and HAC bottom end drop conditions. The CCV bottom support plate is discussed further in Section 1.2.1.5, Internal Support and Positioning Features.

The CCV is fully encased in the cavity of the cylindrical-shaped OP during transport. The OP has a 49.0-inch (1,245 mm) outer diameter and is 70.0-inch (1,778 mm) high, with a cavity that is sized to accommodate a CCV with sufficient radial and axial clearances to permit free differential thermal expansion of the CCV during NCT and HAC. The OP base and lid consist of energy-absorbing closed-cell polyurethane foam cores sealed inside stainless steel inner and outer shells. The OP is discussed further in Section 1.2.1.5, Energy-Absorbing Features. The OP lid is secured to the overpack base by high-strength steel bolts, as shown in Figure 1.1-1.

The SIA is a coated carbon steel container inside the CCV cavity to provide supplemental

• gamma shielding. The SIA configurations used in the OPTIMUS-L packaging include only an NAC International 1.2-1

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A open-top body, is provided in two (2) thicknesses; 1-inch and 21/4-inch thick. The internal cavity of the SIA is 024.0 inches (0610 mm) by 35.25 inches (895 mm) high; large enough to accommodate a 55-gallon (208 liter) drum. A thick annular spacer plate is placed underneath the bottom of the 21/4-inch thick SIA to position it near the top of the CCV cavity to facilitate loading operations.

The SIA is also not relied upon for thermal or containment functions. Although no structural credit is taken for the SIA in the structural evaluation of the other packaging components, the SIA is designed to withstand the most severe regulatory tests (e.g., free drop) without structural failure. Shielding integrity is maintained for those conditions where the SIA is credited in the shielding evaluation.

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.

General arrangement drawings showing the packaging dimensions and materials of construction are included in Appendix 1.3.3.

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 049.0 inches (01,245 mm) by 70.0-inch (1,778 mm) high which is greater than the minimum package dimension of 10 cm required by 10 CFR 71.43(a). The nominal weight of the empty packaging is approximately 6,050 pounds (2,744 kg). The gross weight of the package, including the maximum contents weight, is approximately 9,200 pounds (4,172 kg).

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 0-ring seal, and the port cover and its closure bolts and containment 0-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 C C ~ ) thick stainless steel shell, the OP inner shell, and a thick OP outer shell, for a combined steel thickness of 1.27 inches

• NAC International 1.2-2

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A (32 mm). 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 thick carbon steel CCV bottom support plate (positioned at the bottom end of the CCV cavity), the CCV I 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 3.14 inches (80 mm). The packaging thick stainless steel CCV closure lid, a - g e OP inner top end plate, the OP top foam cover shell, and the thick OP outer end plate, for a combined steel thickness of 3.72 inches (94 mm).

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

1.2.1.4 Criticality Control Features 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 049-inch (01225 mm) by 70-inch (1778 mm) 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 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 NAC International 1.2-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A bottom end plates are all constructed from shells are constructed fro 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 t h e - 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.

Internal Supports or Positioning Features The CCV bottom support plate is a free-standing thick coated carbon steel 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.

• 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 (124 cm) outer diameter (excluding lifting lugs and tiedown arms) and 70-inch (178 cm) 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 International 1.2-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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 b y _

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 lid's 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 The CCV lid h a ~ bolt holes 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, contents are packaged in secondary containers (e.g., drums or liners). In addition, shoring may be used to prevent significant movement of the 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. Furthermore, the combined weight of the contents and any secondary components (including the CCV bottom support plate) may not exceed the payload limit of 3,500 pounds (1,587 kg).

1.2.1.7 Internal Support Components Not applicable.

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 70000.14-502 in Section 1.3, to meet the requirement for tamper-indicating features as specified in 10 CFR 71.43(6). See Section 2.4.2 for more details .

• NAC International 1.2-5

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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 [l-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 I, 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.

1.2.1.11 Heat Transfer Features of the package heat transfer features is provided in Chapter 3.

1.2.1.12 Containment Features The packaging has a simple, robust containment system design. Containment ofradioactive 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 NAC International 1.2-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 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.

O-rings with a continuous operating temperature range of -40°F (-40°C) to 400°F (204°C) .

• ~~~ CCV i~ design~d,_ fabricated, examined, tested, -and inspeeted in accordance witlrthe -

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.

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 stainless steel CCV lid, the stainless steel OP lid inner and outer end plates and the OP lid end foam. Optionally, additional gamma shielding is provided on the package side and bottom by a carbon steel SIA. Shielding credit for the SIA is taken only for NCT, conservatively assuming that the contents escape the secondary container cavity and the SIA following the HAC free drop. Neutron shielding is not necessary for the specified radioactive material contents .

• NAC International 1.2-7

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 1.2.1.14 Coolants Not applicable.

1.2.2 Contents The acceptable contents of the package includes transuranic (TRU) waste and irradiated fuel waste, consisting of LEU uranium fuel and metal structural components (e.g. cladding, liners, baskets, etc.). The acceptable 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 ofTRU 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.

Maximum Quantity ofTRU 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 gamma-emitting contents (e.g., Co-60, Cs-137 and Ba-137m) and neutron-emitting contents (e.g., Cf-252 and Cm-244) shall not exceed the activity limits in Table 1.2-3 for the shipping configuration used, where acceptable activity is determined in accordance with Chapter 7, Attachment 7.5-1.

NAC International 1.2-8

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

6. Total quantity of radioactive material can exceed 3,000 A2.

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%.

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

5. Maximum weight of 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.; cladaing,-liners~ oasl<efs, etc:) meetin£the following requirements and restrictions.

Type and Form of IFW Waste Material:

1. LEU fuel.

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

Maximum Quantity ofIFW 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.).

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

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

4. IFW gamma-emitting contents and neutron-emitting contents shall not exceed the activity limits in Table 1.2-3 for the shipping configuration used, where acceptable activity is determined in accordance with Chapter 7, Attachment 7.5-1.

NAC International 1.2-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Loading Restrictions:

I. 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 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).

1.2.3 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 packaging's operational features.

NAC International 1.2-10

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 1.2 TRU Waste FGE Limits FGE Criticality Configuration Description Chemically or FGE Limit Machine Weight% Minimum Mechanically g 23spu Config. ID Compactedl2l Beryllium 240 Pu Credit Bound (g 23sU)l1J FGE-1 S1 340 (528)

FGE-2a S1 350 (544)

FGE-2b S1 375 (583}

FGE-2c S1 395 (614)

FGE-3 >1 121 (188)

FGE-5 S1 250 (388)

Note:

<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.

121 Uncompacted or manually compacted TRU waste must not provide better equivalent moderation than a 15% polyethylene/84% water/1% beryllium mixture per Table 6.2-3. Machine compacted TRU waste must not provide better equivalent moderation than 100% polyethylene per Table 6.2-3.

Table 1.2 IFW Waste FEM Limits LEU Waste Criticality Configuration Description Weight% Enrichment Limit, Uranium Mass Limit, Config. ID Beryllium (wto/o 235U) lbs. (kg)

FEM-1 S1 s 0.90 wt0/4 2500 (1134}

Note: Contents must be non-machine compacted and must not provide better equivalent moderation than a 15% polyethylene/84% water/1% beryllium mixture per Table 6.2-4 .

• NAC International 1.2-11

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 1.2-3 TRU Waste and IFW Activity Limits Activity Limits111, TBq (Ci)

Isotope Base Base+ 1-inch SIA Base + 21/4-inch SIA Method 1 Method 21 21 Method 1 Method 21 21 Method 1 Method 21 21 2x5 Package Array Co-60 1.050E-03 3.033E-03 N/Al3l N/Al3l N/A13l N/Al3l (2.837E-02) (8.197E-02)

Cs-137 3.590E+OO 9.350E+OO N/A13l N/Al3l N/Al3l N/A1 3l (9.702E+01) (2.527E+02)

Ba-137m 5.223E-03 1.423E-02 N/A1 3l N/Al3l N/Al3l N/Al 3l (1.412E-01) (3.846E-01)

Cf-252 1.443E-04 4.501E-04 N/Al 3l N/A13l N/A13l N/Al 3l (3.901 E-03) (1.217E-02)

Cm-244 4.545E+OO 1.413E+01 N/A(31 N/Al3l N/Al3l N/Al31 (1.228E+02) (3.820E+02) 1x6 Package Array Co-60 1.571 E-03 3.033E-03 3.244E-03 6.036E-03 8.724E-03 1.585E-02 (4.245E-02) (8.197E-02) (8.767E-02) (1.631 E-01) (2.358E-01) (4.284E-01)

Cs-137 5.273E+OO 9.350E+OO 2.926E+01 4.804E+01 1.700E+02 1.700E+02 (1.425E+02) (2.527E+02) (7.907E+02) (1.298E+03) (4.594E+03) (4.594E+03)

Ba-137m 7.626E-03 1.423E-02 2.165E-02 3.764E-02 9.009E-02 1.478E-01 (2.061 E-01) (3.846E-01) (5.852E-01) (1.017E+OO) (2.435E+OO) (3.995E+OO)

Cf-252 2.312E-04 4.501 E-04 2.556E-04 4.771 E-04 2.980E-04 5.436E-04 (6.250E-03) (1.217E-02) (6.908E-03) (1.289E-02) (8.054E-03) (1.469E-02)

Cm-244 7.267E+OO 1.413E+01 8.080E+OO 1.507E+01 9.440E+OO 1.722E+01 (1.964E+02) (3.819E+02) (2.184E+02) (4.074E+02) (2.551 E+02) (4.654E+02)

Notes:

<1> Activity limits for all isotopes provided in Chapter 5.

< > Method 2 activity limits shown for a single package.

2

<3> SIA not evaluated for 2x5 package array.

NAC International 1.2-12

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A PORT COVER BOLTS PORT COVER PORT COVER 0-RING SEALS PORT QUICK-CONNECT VALVE (INNER- CONTAINMENT)

(OUTER - TEST)

CCV CLOSURE BOLT (CAPTURED)

LID 0-RING SEALS (INNER - CONTAINMENT)

(OUTER - TEST)

CCV BODY Figure 1.2 CCV Packaging Components

• NAC International

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A CCV PORT COVER CCV PORT COVER OUTER O-RING CCVLID CCVLID OUTER O-RING CCV BODY Cross Section View Figure 1.2-2 Packaging Containment System NAC International 1.2-14

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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 N 14.5-2014, 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-, SubsectionNB,-C/asf-1 Components~-20l0Ediffon with 2of1 -

Addenda.

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

[1.7] NUREG/CR-5502, Engineering Drawings for JO 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 International 1.3-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 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 CSI Criticality Safety Index FEM Fissile Equivalent Mass (of 235 U)

FGE Fissile Gram Equivalent (of 239Pu)

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

Payload Radioactive contents and dunnage RAM Radioactive Material SAR Safety Analysis Report (this document)

SIA Shield Insert Assembly TRU Transuranic Waste NAC International 1.3-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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.

70000.14-502 Packaging Assembly - OPTIMUS-L 1 70000.14-510 CCV Assembly- OPTINIUS 6 70000.14-511 CCV Body Weldment- OPTIMUS 7 70000.14-512 CCV Lid - OPTIMUS 7 70000.14-513 Port Cover - OPTIMUS 2 70000.14-514 CCV Bottom Supp011 Plate - OPTIMUS-L 1 70000.14-540 Outer Packaging Assembly- OPTIMUS-L 1

-- -- - - -- - - ~ --- ---

70000.l4-54f - bu.fer Packaging Base - OPTIMUS-L 3 70000.14-542 Outer Packaging Lid- OPTIMUS-L 3 70000.14-550 1-Inch Shield Insert Assembly (SIA) - OPTIMUS 3 70000.14-551 21/4-Inch Shield Insert Assembly (SIA)- OPTIMUS 3 70000.14-553 21/4-Inch SIA Annular Spacer Plate -OPTIMUS-L 1 DRAWINGS ARE PROPRIETARY AND WITHHELD IN THEIR ENTIRETY PER IO CFR 2.390

• NAC International 1.3-3

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Chapter 2 Structural Evaluation Table of Contents 2 STRUCWRALEVALUATION ................................................................................... 2-1 2.1 Description of Structural Design ................................................................................. 2.1-1 2.1.1 Discussion .................................................................................................. 2.1-1 2.1.2 DesignCriteria ........................................................................................... 2.1-2 2.1.3 Weights and Centers of Gravity ............................................................... 2.1-11 2.1.4 Identification of Codes and Standards for Packaging .............................. 2.1-11 2.2 Materials ...................................................................................................................... 2.2-1 2.2.1 Material Properties and Specifications ...................................................... 2.2-1 2.2.2 Chemical, Galvanic or Other Reactions ..................................................... 2.2-2 2.2.3 Effects of Radiation on Materials .............................................................. 2.2-3 2.3 Fabrication and Examination ....................................................................................... 2.3-1 2.3.1 Fabrication ................................................................................................. 2.3-1 2.3.2 Examination ............................................................................................... 2.3-3

• 2.4 2.5 General Requirements for All Packages ...................................................................... 2.4-1 2.4.1 2.4.2 2.4.3 Minimum Package Size ............................................................................. 2.4-1 Tamper-Indicating Feature ......................................................................... 2.4-1 Positive Closure ......................................................................................... 2.4-1 Lifting and Tie-Down Standards for All Packages ...................................................... 2.5-l 2.5.1 Lifting Devices........................................................................................... 2.5-1 2.5.2 Tie-Down Devices ..................................................................................... 2.5-5 2.6 Normal Conditions ofTransport .................................................................................. 2.6-1 2.6.1 Heat ............................................................................................................ 2.6-1 2.6.2 Cold ............................................................................................................ 2.6-8 2.6.3 Reduced External Pressure ........................................................................ 2.6-8 2.6.4 Increased External Pressure ..................................................................... 2.6-12 2.6.5 Vibration .................................................................................................. 2.6-12 2.6.6 Water Spray ............................................................................................. 2.6-12 2.6.7 Free Drop ................................................................................................. 2.6-13 2.6.8 Comer Drop ............................................................................................. 2.6-37 2.6.9 Compression ............................................................................................ 2.6-37 2.6.10 Penetration ....... .'....................................................................................... 2.6-37 2.7 Hypoth_etical Accident Conditions ............................................................................... 2.7-1 2.7.1 Free Drop ............*....................................................................................... 2.7-1 2.7.2 CnlSh ........................................................................................................ 2.7-37 2.7.3 Puncture ................................................................................................... 2.7-37

• 2.7.4 2.7.5 NAC International Thermal .................................................................................................... 2.7-44 Immersion-Fissile Material ................................................................... 2.7-47 2-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.7.6 Immersion -All Packages ....................................................................... 2.7-47 2.7.7 Deep-Water Immersion Test (for Type B Packages Containing more than I 05 Az) ..........................................................*................................... 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 Com uter Code Descri tions ................................................................... 2.12-3 2.12.3 *************************************2.12-4 2.12.4 Development of Equivalent Static Loads ................................................ 2.12-6 NAC International 2-ii

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Figures Figure 2.1-1 - CCV Stress Evaluation Locations .................................................................. 2.1-19 Figure 2.1-2 - Package Mass Properties Schematic .............................................................. 2.1-20 Figure 2.2-1 - Foam Upper and Lower-Bound Dynamic Stress-Strain Curves ........... 2.2-10 Figure 2.2-2 - f Foam Upper and Lower-Bound Dynamic Stress-Strain Curves ......... 2.2-10 Figure 2.5-1 - L1 g Attachment Loading Diagram ........................................................... 2.5-12 Figure 2.5-2 - Package Tiedown Configuration ................................................................... 2.5-13 Figure 2.5-3 - Tiedown Ann Loading Diagram.................................................................... 2.5-14 Figure 2.6-1 - 1/2-Symmetry CCV FEA Stress Analysis Model.. ............................................ 2.6-6 Figure 2.6-2 - Bounding NCT Heat Temperature Distribution .............................................. 2.6-7 Figure 2.6-3 - NCT 4-Foot (1.2 m) Free Drop Impact Orientations ..................................... 2.6-28 Figure 2.6-4 - Drop Analysis 1/2-Symmetty Model - Isometric View .................................. 2.6-29 Figure 2.6-5 - Cold/Hard NCT Bottom End Drop (Case NBEl) Impact Limiter Deformation .............................................................................................. 2.6-30 Figl.U"e 2.6 Cold/Hard NCT Bottom End Drop (Case NBEl) Rigid-Body Acceleration Time-History ....................................................................... 2.6-30 Figure 2.6 Cold/Hard NCT Top End Drop (Case NTEl) Impact Limiter Deformation .............................................................................................. 2.6-31 Figure 2.6 Cold/Hard NCT Top End Drop (Case NTEl) Rigid-Body Acceleration Time-History ............................................................................................. 2.6-31

• Figure 2.6 Cold/Hard NCT Bottom Comer Drop (Case NBCl) Impact Limiter Deformation .............................................................................................. 2.6-32 Figure 2.6 Cold/Hard NCT Bottom Corner Drop (Case NBCl) Rigid-Body Acceleration Time-History ....................................................................... 2.6-32 Figure 2.6 Cold/Hard NCT Top Comer Drop (Case NTCl) Impact Limiter Deformation ..........*.................................................................................... 2.6-33 Figure 2.6 Cold/Hard NCT Top Comer Drop (Case NTCl) Rigid-Body Acceleration Time-Histo1y ....................................................................... 2.6-33 Figure 2.6 Cold/Hard NCT Side Drop (Case NSl) Impact Limiter Deformation ........ 2.6-34 Figure 2.6 Cold/Hard NCT Side Drop (Case NSl) Rigid-Body Acceleration Time-History ............................................................................................. 2.6-34 Figure 2.6 Cold/Hard NCT Side Drop (Case NSl) OP Bolt Average Tensile Stress Time-Histo1y .................................................................................. 2.6-35 Figure 2.6 SIA 1/8-Symmetry Finite Element Models ................................................. 2.6-36 Figure 2.7 HAC Free Drop Impact Orientations ............................................................... 2.7-5 Figure 2.7 HAC Hot/Soft Bottom End Drop (Case HBE2) OP Deformation. ................ 2.7-12 Figure 2.7 HAC Hot/Soft Top End Drop (Case HTE2) OP Deformation ...................... 2.7-13 Figure 2. 7 HAC Cold/Hard Bottom End Drop (Case HBEl) Rigid-Body Acceleration Time-Histo1y ....................................................................... 2.7-14 Figure 2.7 HAC Cold/Hard Top End Drop (Case HTEl) Rigid-Body Acceleration Time-History ....................................................................... 2. 7-14 Figure 2.7 HAC Cold/Hard Top End Drop (Case HTEl) OP Bolt Average Tensile Stress Time-History ..................................................................... 2.7-15

• Figure 2.7 Hot/Soft HAC Side Drop (Case HS2) OP Deformation ................................ 2.7-20 NAC International 2-iii

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cold/Hard HAC Side Drop (Case HSI) Rigid-Body Acceleration Time-History ............................................................................................. 2.7-20 Figure 2.7 Cold/Hard HAC Side Drop (Case HS 1) OP Bolt Average Tensile Stress Time-History .................................................................................. 2.7-21 Figure 2.7 Hot/Soft HAC Bottom Corner Drop (Case HBC2) OP Deformation .......... 2.7-26 Figure 2.7 Hot/ Soft HAC Top Corner Drop (Case HTC2) OP Deformation .............. 2.7-27 Figure 2.7 Cold/Hard HAC Bottom Corner Drop (Case HBCl) Rigid-Body Acceleration Time-History ....................................................................... 2.7-28 Figure 2.7 Cold/Hard HAC Top Corner Drop (Case HTCl) Rigid-Body Acceleration Time-History ....................................................................... 2.7-28 Figure 2.7 Cold/Hard HAC Top Corner Drop (Case HTCl) OP Bolt Average Tensile Stress Time-History ..................................................................... 2.7-29 Figure 2.7 Cold/Hard HAC 10° Bottom Oblique Drop (Case HBOl) OP Deformations ............................................................................................. 2.7-33 Figure 2.7 Cold/Hard HAC 10° Top End Oblique Drop (Case HTOl) OP Deformation .............................................................................................. 2.7-33 Figure 2.7 Cold/Hard HAC 10° Bottom End Oblique Drop (Case HBOl) Rigid-Body Acceleration Time-History .............................................................. 2.7-34 Figure 2.7 Cold/Hard HAC 10° Top End Oblique Drop (Case HTOl) Rigid-Body Acceleration Time-History .............................................................. 2.7-34 Figure 2.7 HAC Puncture Drop Orientations ................................................................ 2.7-40 Figure 2.7 .

C~;~l:~~~~r~~.~~~:~~~~~.~ ~~~*~*~*~*~~~ ~~~.~.~~~.~~-~~~~~~~~

Figure 2.7 Cumulative OP Deformation - Hot/Soft HAC Top Off-Center

. ..... 2 .7_41

• Puncture (Case PTE2) ............................................................................... 2.7-42 Figure 2.7 Cumulative OP Deformation - Hot/Soft HAC Side Puncture (Case PSI) ........................................................................................................... 2.7-43 Figure 2.12 Benchmark Comparison ofHAC Side Drop Analysis and Test Results ....................................................................................................... 2.12-5 Figure 2.12 DLF Curve for Half-Sine Pulse ................................................................... 2.12-9 Figure 2.12 CCV Shell Bottom End 1/2-Symmetry Finite Element Model ..................... 2.12-9 NAC International 2-iv

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Tables Table 2.1-1 - Load Combinations for N01mal Conditions of Transport ............................... 2.1-13 Table 2.1-2 - Load Combinations for Hypothetical Accident Conditions ............................ 2.1-14 Table 2.1-3 - Containment System Allowable Stress Design Criteria.................................. 2.1-15 Table 2.1-4 - Non-Containment Component Allowable Stress Design Criteria .................. 2.1-16 Table 2.1-5 - CCV Shell Buckling Geometric Parameters ................................................... 2.1-17 Table 2.1-6 - CCV Shell Buckling Reduction Factors and Theoretical Buckling Stresses ...................................................................................................... 2.1-17 Table 2.1-7 - CCV Shell Allowable Buckling Stresses ........................................................ 2.1-18 Table 2.1-8 - Package Weight and Center of Gravity Summary .......................................... 2.1-18 Table 2.2-1 - Packaging Stmctural Material Specifications ................................................... 2.2-5 Table 2.2-2 - Mechanical Prope1iies of SA-182, Type F304/F316 Stainless Steel (t > 5 in.)***************************************************************************************************** 2.2-6 Table 2.2 Mechanical Properties of A240/SA-240 or A479/SA-479, Type 304/316 Stainless Steel ............................................................................... 2.2-6 Table 2.2 Mechanical Properties of SA-320, Grade U3 Alloy Steel Bolts (t '.5 4 in.) ***************************************************************************************************** 2.2-7 Table 2.2 Mechanical Properties of SA-193, Grade B8, Class 1 Stainless Steel Bolts ............................................................................................................ 2.2-7 Table 2.2 Mechanical Properties of A36/SA-36 Carbon Steel ......................................... 2.2-8 Table 2.2 Mechanical Properties of A240/SA-240 or A479/SA-479, Type XM-19

• Stainless Steel ............................................................................................. 2.2-8 Table 2.2 Mechanical Properties of A574/SA-574Alloy Steel Socket-Head Cap Scre,vs ......................................................................................................... 2.2-9 Table 2.2 9 - Mechanical Prope1iies of A516, Grade 70 Carbon Steel .................................. 2.2-9 Table 2.5 Lifting Attachment Stress Summm.y ............................................................... 2.5-11 Table 2.5 Tiedown Attachment Stress Summary ............................................................ 2.5-11 Table 2. 6 Reduced External Pressme Stress Summm.y................................................... 2.6-11 Table 2.6 Summary ofNCT Free Drop Cases Evaluated ............................................... 2.6-24 Table 2.6 NCT Free Drop hnpact Analysis Results ........................................................ 2.6-24 Table 2.6 NCT End Drop Stress Summary ..................................................................... 2.6-25 Table 2.6 NCT Side Drop Stress Sulllillary .................................................................... 2.6-26 Table 2.6 NCT Top Corner Drop Stress SU1Drnary ......................................................... 2.6-26 Table 2.6 CCV Shell NCT Free Drop Buckling Evaluation Stress Summary ................ 2.6-27 Table 2.6 CCV Shell Buckling Evaluation Results for NCT Free Drop ......................... 2.6-27 Table 2.7 Summary ofHAC Free Drop Cases Evaluated ................................................. 2.7-4 Table 2.7 HAC End Drop hnpact Limiter Analysis Results ........................................... 2.7-10 Table 2.7 HAC End Drop Stress Summary..................................................................... 2.7-10 Table 2.7 CCV Shell HAC End Drop Buckling Evaluation Stress SU1Ililla1y ................ 2.7-11 Table 2.7 CCV Shell Buckling Evaluation Results forHAC Bottom End Drop ............ 2.7-11 Table 2.7 HAC Side Drop hnpact Limiter Analysis Results .......................................... 2.7-19 Table2.7 HAC Side Drop Stress Summary .................................................................... 2.7-19 Table 2. 7 HAC Corner Drop hnpact Limiter Analysis Results ...................................... 2. 7-25 Table 2. 7 HAC Top Corner Drop Stress Summary ........................................................ 2. 7-25 Table 2. 7 HAC Oblique Drop Impact Limiter Analysis Results .................................. 2. 7-32 Table 2.7 SU1nmaiy ofHAC P1mctlll*e Cases Evaluated ............................................... 2.7-40 NAC International 2-v

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.7 HAC Pressure Stress Summary ..................................................................... 2.7-46 Table 2.7 Deep Water Immersion Test Stress Summary .............................................. 2.7-49 Table 2.7 CCV Shell Bucklin Summar for Dee Water Immersion Test.. ............... 2.7-50 Table 2.12 2.12-5 Table 2.12 Summary of Free Drop DLFs and Equivalent Static Accelerations ............. 2.12-8 NAC International 2-vi

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2 STRUCTURAL EVALUATION The structural evaluation of the OPTIMUS-L packaging demonstrates compliance with the applicable performance requirements of IO 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.

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.Sl(a)(l). 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 .

• NAC International 2-1

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NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.1 Description of Structural Design 2.1.1 Discussion The principal structural members important to the safe operation of the packaging, shown on General Arrangement Drawing 70000.14-502, are the cask containment vessel (CCV) and outer packaging (OP). The CCV is the central component of the packaging that provides containment of the radioactive contents. The OP limits the impact loads imparted to the CCV under NCT and HAC free drop tests and insulates the CCV from the effects of the HAC thermal test. An optional shield insert assembly (SIA) may be used inside the CCV to provide additional shielding for high activity contents. The structural design of these assemblies is described in the following sections.

2.1.1.1 Cask Containment Vessel The primary structural components of the Cask Containment Vessel (CCV) assembly, shown on General Arrangement Drawing 70000.14-510, are the CCV body weldment, the CCV lid and its

- closure bolts, and the CCV port cover and its - closure bolts. The CCV lid is placed in the top end of the CCV body and captured by the closure lid bolts. The internal cylindrical cavity volume, formed by the CCV body weldment and CCV lid, houses the payload.

• The CCV body weldment, shown on General Arrangement Drawing 70000.14-511, is constructed entirely from austenitic stainless steel material and is formed from three pieces that are connected by complete joint penetration welds: a cylindrical shell, a bolting flange, and a bottom plate. The bolting flange includes - threaded holes for the CCV closure bolts.

The CCV lid, shown on General A1nngement Drawing 70000.14-512, is a stepped circular plate that includes twelve (12) holes for captured bolts, dovetail grooves for the lid's containment and test O-rings, two (2) lid O-ring test ports, a vent/fill port, and threaded holes used to lift the CCV lid or the loaded CCV assembly. The lower portion of the CCV lid fits tightly into the opening of the bolt flange, acting as a shear key to prevent significant lateral shifting of the lid relative to the bolt flange due to impact loads. This feature prevents any significant shear loading of the CCV closure bolts. The closure lid bolt holes also include a scalloped recess at the top to protect the closure bolts from shear loading. The vent/fill port, which includes a quick-connect fitting that is not relied upon for containment, is used to evacuate the CCV cavity and contents of air and backfill with helium gas. The vent/fill port is closed and sealed by the CCV port cover described below. The leak-test ports in the CCV lid are used to perform fabrication acceptance, maintenance, and periodic leakage rate tests of the CCV lid containment seal, and the pre-shipment leakage rate test prior to each shipment. A sealed plug is installed in each test port prior to shipment to prevent debris or water from entering the leak-test port cavity .

NAC International 2.1-1

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A The CCV port cover, shown on General Arrangement Drawing 70000.14-513, is a circular plate that includes f o u r - for the closure bolts, dovetail grooves for the port cover containment and test O-rings, a n d - port cover O-ring test ports. The port cover bolt holes include recessed holes for the heads of the port cover closure bolts to protect them from shear loading under impact loading. The leak-test ports in the CCV port cover are used to perform fabrication acceptance, maintenance, and periodic leakage rate tests of the CCV lid containment seal, and the pre-shipment leakage rate test prior to each shipment. A sealed plug is installed in each port cover test port prior to shipment to prevent debris or water from entering the test port cavity.

2.1.1.2 Outer Packaging The outer packaging (OP) assembly shown on General Arrangement Drawings 70000.14-540, which fully encases the CCV in its internal cavity, is designed to limit the impact loading on the CCV and contents from the NCT free drop, HAC free drop, and HAC puncture drop tests and to provide thermal protection of the CCV and contents during the HAC thermal (fire) test. The OP base and lid, shown on General Arrangement Drawings 70000.14-541 and 70000.14-542, are constructed of fully welded stainless steel shells filled with closed-cell rigid polyurethane foam.

The foam deforms and provides energy absorption during impact. - high-strength bolts are provided to connect the OP lid to the OP base.

• 2.1.1.3 Shield Inserts The I-inch and 21/4-inch shield insert assembly (SIA) shown on General Arrangement Drawings 70000.14-550 and 70000.14-551 are used in the OPTIMUS-L package for contents with increased activities that require additional shielding to satisfy regulatory dose rate limits. Only the body of the 21/4-inch SIA is used in the OPTIMUS-L package because the SIA lid is not required for shielding purposes in this configuration. An annular spacer plate is placed between the CCV bottom support plate and the 21/4-inch SIA body to position the top end of the SIA body near the top of the CCV cavity.

Although no structural credit is taken for the SIA in the structural evaluation of the other packaging components, the SIA is designed to withstand the most severe regulatory tests (e.g.,

free drop) without structural failure, such that shielding integrity is maintained for those conditions in which the SIAs are credited in the shielding evaluation. Additional discussion of the fabrication and examination requirements for the SIAs is provided in Section 2.3.

2.1.2 Design Criteria The design criteria used for the structural design of the packaging is selected in accordance with

• the codes and standards identified in Section 2.1.4. Structural analyses of the packaging are NAC International 2.1-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A performed for the applicable NCT tests (i.e., 10 CFR 71.71) and HAC tests (i.e., 10 CFR 71.73).

The combination of initial conditions used for the structural evaluation of each NCT and HAC test are discussed in Section 2.1.2.1. The stresses in the packaging structural components are calculated for the NCT and HAC load combinations and compared to the allowable stress design criteria described in Section 2.1.2.2. Other structural failure modes, such as buckling, fatigue, and brittle fracture, are evaluated using the design criteria discussed in Sections 2.1.2.3 through 2.1.2.5.

2.1.2.1 Load Combinations The load combinations used for the structural evaluation of the packaging are developed in accordance with Regulatory Guide 7.8 [2.5]. The load combinations are based on Table 2.1-1 of Regulatory Guide 7.8, with additional load combinations for intermediate initial conditions that could possibly create a more limiting case for the packaging design. The NCT and HAC load combinations are summarized in Table 2.1-1 and Table 2.1-2, respectively.

2.1.2.2 Allowable Stresses In accordance with Regulatory Guide 7.6 [2.13], the pressure-retaining components of the packaging containment system, which consist of the CCV body weldment and closure lid, are designed in accordance with the requirements of Section III, Subsection NB of the ASME Code

[2.1]. The CCV closure bolts are designed in accordance with the allowable stress design criteria ofNUREG/CR-6007 [2.23]. Level A and Level D Service Limits are used for NCT and HAC, respectively. The containment system stress intensity limits for NCT are developed in accordance with Figures NB-3221-1 and NB-3222-1 and summarized in Table 2.1-3. Per NB-3224, the containment system stress intensity limits for HAC are developed in accordance with Appendix F of the ASME Code [2.6], as summarized in Table 2.1-3.

All packaging structural components that are not relied upon for containment, except for the OP shells and foam cores, are designed in accordance with the allowable stress design criteria for Class 2 plate- and shell-type supports from Subsection NF of the ASME Code [2.2]. The NCT and HAC allowable stress design criteria for the packaging non-containment components are summarized in Table 2.1-4.

Subsections NF and NB of the ASME Code impose stress limitations on primary membrane, local membrane, membrane (primary or local) plus bending, and primary plus secondary stress intensities. To demonstrate conformance to the ASME Code limits, it is necessary to determine the required code stress intensities at the critical cross-sections of the packaging. Since the

• critical cross-section locations are load-condition-dependent, several "stress evaluation sections" are established to ensure that all critical locations have been evaluated for every load condition.

NAC International 2.1-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The stress evaluation sections selected for the CCV are illustrated in Figure 2.1-1. Multiple sections are selected in the high stress regions near the ends of the shells. For evaluation of conditions producing a stress distribution in the packaging that is not axisymmetric, section stress evaluations are performed at multiple circumferential locations to assure that the maximum stresses are captured. For the CCV shell buckling evaluation, membrane stress components at the mid-length of the CCV shell (section C9) are used.

The section stresses at each stress evaluation location are obtained using the The stress linearization provides membrane, bending, membrane plus bending, peak, and total stress intensities at each section. These stresses are classified in accordance with the ASME Code for comparison to the applicable allowable stress design criteria as follows:

Membrane Stress Intensity The membrane stress intensities are classified as primary membrane (Pm) or local membrane (P1) based upon the location in the structure and the nature of the stress. Membrane stresses occurring at a structural discontinuity (e.g., at the transition inner shell thickness transitions and at the shell-to-flange transitions) are classified as local membrane, provided that the distance over which the membrane stress intensity exceeds the Pm limit does not exceed l.O(Rt) 112 , where R is the minimum mid-surface radius of curvature and t is the minimum thickness in the region considered. Membrane stresses at all other sections are classified as primary.

Membrane Plus Bending Stress Intensity The membrane plus bending stress intensities at each section are classified as either primary (Pm+Pb) or secondary (Pm+Pb +Q) based upon the location in the structure. Bending stresses at gross structural discontinuities, such as flange-to-shell junctions and junctions between shells of different diameters or thickness, are classified as secondary. Membrane plus bending stress intensities at all other stress sections are classified as primary.

Total Stress Intensity Total stress intensities include primary plus secondary plus peak stresses. In accordance with the ASME Code, these stresses are objectionable only as a possible source of a fatigue crack or a brittle fracture. As shown in Section 2.1.2.4, evaluation of cyclic loading is not required for the packaging components other than bolts.

Using the critical sections from each load case, minimum design margins are calculated and reported for all bounding load combinations. The design margin (D.M.) is defined as follows:

NAC International 2.1-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A D.M. = ( AllowableValue 1- l;

~ CalculatedValue) where the allowable and calculated values are in consistent units.

The impact limiter shells are designed to deform plastically and absorb the kinetic energy when subjected to the NCT free drop, HAC free drop, and HAC puncture drop load conditions.

Therefore, strain-based design criteria are used for the impact limiter. The maximum crush depth of the polyurethane foam in the impact limiter is generally limited to 70% of the nominal foam section thickness. In cases of highly localized foam crush, e.g., that due to the HAC hot comer drop impact, the maximum foam crush depth may not exceed 80% of the nominal foam section thickness 2.1.2.3 Buckling The CCV shell is evaluated for buckling in accordance with the requirements of ASME Code Case N-284-1 [2.7]. The geometric parameters of the CCV shell used for the buckling evaluation are summarized in Table 2.1-5. Capacity reduction factors are calculated in accordance with Section -1511 of ASME Code Case N-284-1 to account for possible reductions in the capacity of the CCV shell due to imperfections and nonlinearity in geometry and boundary conditions.

Plasticity reduction factors, which account for nonlinear material properties when the product of the classical buckling stresses and capacity reduction factors exceed the proportional limit, are calculated in accordance with Section -1610 of ASME Code Case N-284-1. The theoretical buckling stresses of the CCV shell under uniform stress fields are calculated in accordance with Section -1712.1.1 of ASME Code Case N-284-1. CCV shell lower-bound material properties at an upper-bound temperature of 350°F (l 77°C) are conservatively used to determine the buckling factors and theoretical buckling stresses. The capacity reduction factors, plasticity reduction factors, and theoretical buckling stresses for the packaging inner and outer shells are summarized in Table 2.1-6.

The allowable elastic and inelastic buckling stresses for NCT and HAC are calculated in accordance with the formulas given in Section -1713.1.1 and Section -1713.2.1 of ASME Code Case N-284-1. The allowable buckling stresses include factors of safety of 2.0 for NCT and 1.34 for HAC in accordance with Section -1400 of ASME Code Case N-284-1.

Table 2.1-7 provides a summary of the CCV shell elastic and inelastic buckling stresses for NCT and HAC. Buckling interaction ratios are calculated for the CCV shell for all NCT and HAC tests that load the shell in compression. The interaction ratios for elastic buckling and inelastic

• buckling are calculated using the highest values of compressive stress and shear stress in NAC International 2.1-5

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A accordance with the formulas given in Section -1713.1.1 and Section -1713.2.1 of ASME Code Case N-284-1.

2.1.2.4 Fatigue 2.1.2.4.1 Structural Components Other Than Bolts Analysis of the packaging structural components for cyclic service is not required because the conditions stipulated in NB-3222.4( d)(l) through (6) are met. The analysis is conservatively based on the assumption that the packaging will be used for 20 years of service and be used for one shipment per week, for a total of 1,040 shipments. This analysis is summarized as follows:

1. The number of atmospheric to operating pressure cycles, which is equal to the number of shipments (1,040 cycles), is less than 2,750 cycles, corresponding to a Sa value of 3Sm = 60.0 ksi (414 MPa) for Type 304 and Type 316 stainless steel over the temperature range of interest. Thus, condition (1) ofNB-3222.4(d) is met.

2. Normal service pressure fluctuation cycles in the packaging result from diurnal fluctuations in ambient conditions (temperature and insolation). Thus, it is assumed that the packaging will experience one normal operating pressure fluctuation per day, or 7,300 cycles over its 20-year service life. A significant pressure fluctuation (SPF) is 89 psi (614 kPa) based on a

• bounding design pressure of 100 psi (690 kPa) gauge, an Sa value of 53.4 ksi (368 MPa) at 104 cycles per Table I-9.2 of Appendix I [2.9] of the ASME Code, and Sm of 20.0 ksi (138 MPa) for Type 304 and Type 316 stainless steel over the temperature range of interest.

Due to the relatively large thermal mass of the package, variation of package temperatures sufficient to cause an internal pressure fluctuation of this magnitude are not considered credible. Thus, condition (2) of NB-3222.4( d) is met.

3. The temperature difference between any two adjacent points on the CCV shell during startup and shutdown is limited to l 66°F (92°C). This is based on a Sa value of 82.2 ksi (567 MPa) for 1,040 startup shutdown cycles and the elastic modulus and mean coefficient of thermal expansion for the CCV shell Type 304 and Type 316 stainless steel material at room temperature. The thermal evaluation of the packaging shows that temperature differences between any two adjacent points on the CCV is less than 166°F (92°C) under any NCT thermal condition. Thus, condition (3) ofNB-3222.4(d) is met.

4. Normal operating temperature fluctuation cycles in the packaging result from diurnal fluctuations in ambient conditions (temperature and insolation). Thus, it is assumed that the packaging will experience one normal operating temperature fluctuation per day, or 7,300 cycles over its 20-year service life. The packaging's significant temperature fluctuation (STF) is over 100°F (38°C) based on a Sa value of 53.4 ksi (368 MPa) at 104 cycles and the NAC International 2.1-6

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A elastic modulus and mean coefficient of thermal expansion for the CCV shell Type 304 and Type 316 stainless steel material at room temperature. Due to the relatively large thermal mass of the package, it is not credible that diurnal fluctuation in ambient temperature will cause any temperature fluctuations in the packaging that exceed the STF. Thus, condition (4) ofNB-3222.4(d) is met.

5. Except for the closure bolts, the CCV does not have any dissimilar materials. Thus, condition (5) ofNB-3221.9(d) is met.

6. The only significant cyclic mechanical loads, excluding pressure, that the packaging is subjected to during normal operation are those resulting from NCT vibration. It is assumed that the packaging will experience a total of 106 cycles of significant vibration loading (i.e.,

2g vertical acceleration) over the 20-year service life. The value of Sa for austenitic stainless steels for 106 cycles, is 18.3 ksi (126 MPa) per Table I-9.2 of Appendix I [2.9] of the ASME Code. Based on comparison to the results of the NCT end drop, the stresses in the packaging due to a 2g vertical vibration load are less than the Sa value for the total number mechanical load cycles. Thus, condition (6) ofNB-3221.9(d) is met.

2.1.2.4.2 CCV Closure Bolts

• The CCV closure bolts are subjected to cyclic loading due to startup-shutdown cycles of bolt pre load, temperature, and pressure loading, normal fluctuation cycles of pressure and temperature, and cyclic loading due to vibration normally incident to transport. In accordance with the requirements ofNB-3232.3(b), the CCV closure bolts, which have an ultimate tensile strength of 125.0 ksi (862 MPa), are evaluated for fatigue failure due to cyclic loading by the methods ofNB-3222.4(e) using the design fatigue curve for of Figure I-9.4 based on a maximum nominal stress not exceeding 2. 7Sm. Furthermore, in accordance with the requirements of NB-3232(c), a fatigue strength reduction factor of 4.0 is used for the CCV closure bolt fatigue evaluation. Finally, in accordance with the requirements ofNB-3232(d), the alternating stress, Salt, is multiplied by the ratio of the modulus of elasticity given on the design fatigue curve (i.e.,

E = 30 x 106 psi) to the value of the elastic modulus used in the analysis (i.e., E = 27.06 x 106 psi at an upper-bound CCV closure bolt temperature of 210°F).

The fatigue analysis is conservatively based on the assumption that the CCV closure bolts will be replaced after 5 years of service and the packaging will be used for one shipment per week, for a total of 260 shipments over the life of the CCV closure bolts.

Startup-Shutdown Cycles The CCV closure bolts are conservatively assumed to undergo 260 startup-shutdown cycles, assuming one shipment per week over a 5-year period. As discussed in Section 2.6.1.2.2, the NAC International 2.1-7

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A maximum stress intensity at the periphery of the CCV closure bolt due to all NCT heat is 62.1 ksi (428 MPa). The minimum stress in the CCV closure bolt for staitup-shutdown cycles is zero. Thus, the alternating stress in the CCV closure bolts for startup shutdown cycles, including a fatigue reduction factor of 4 and an adjustment for the ratio of fatigue curve elastic modulus to the bolt elastic modulus at design temperature is 137.7 ksi (949 MPa). The corresponding allowable number of startup-shutdown cycles is 538 per Figure I-9.4 of Appendix I [2.9] of the ASME Code. Therefore, the CCV closure bolt usage factor for startup-shutdown cycles (U1) is 0.48.

Thermal and Pressure Fluctuations - Normal Operating Cycles Normal operating temperature and pressure fluctuations in the packaging result from diurnal ambient temperature fluctuations. The packaging is conservatively assumed to undergo one normal operating cycle for every day over a 5-year period, or 1,825 cycles. The pressure and temperature fluctuations are conservatively based on a diurnal ambient temperature variation of 140°F (78°C), assuming the ambient temperature varies from a maximum of 100°F (38°C) during the day to -40°F (-40°C) at night. The CCV bolt stresses are not affected by fluctuation of the internal pressure load because MNOP is not large enough to overcome the bolt preload.

However, temperature fluctuations of the packaging produce alternating stress in the CCV bolts by differential thermal expansion between the bolt and lid materials.

The range of stress in the CCV closure bolt for normal service temperature fluctuations is 11.9 ksi (82 MPa). Thus, the alternating stress in the CCV closure bolts for service temperature fluctuations, including a fatigue reduction factor of 4 and adjusting for the ratio of the elastic modulus from the fatigue curve to elastic modulus used in the bolt analysis, is 25.9 ksi (179 MPa). The corresponding allowable number of normal operating cycles is approximately 24,091 per Figure I-9.4 of Appendix I [2.9] of the ASME Code. Therefore, the CCV closure bolt usage factor for normal operating thermal and pressure cycles (U2) is 0.08 (l,825/24,091).

Vibration Cycles The results of the CCV closure bolt evaluation show that NCT vibration loading results in only a 0.4 ksi (3 MPa) increase in the CCV closure bolt stress. Thus, the alternating stress in the CCV closure bolts for NCT vibration cycles, including a fatigue reduction factor of 4 and adjusting for the ratio of the elastic modulus from the fatigue curve to elastic modulus used in the bolt analysis, is Sa1t3 = 0.9 ksi (6 MPa). Based on the fatigue curve in Figure I-9.4 of Appendix I [2.9]

of the ASME Code there is no fatigue limit for an alternating stress this low, and therefore the usage factor for NCT vibration is zero.

NAC International 2.1-8

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Cumulative Usage Factor The cumulative usage factor for cyclic loading of the CCV closure bolts is:

U = U1+U2+U3=0.56 Since the cumulative usage factor is less than 1.0, the CCV closure bolt will not fail due to fatigue during their 5-year design life.

2.1.2.4.3 OP Closure Bolts The OP closure bolts are subjected to cyclic loading due to startup-shutdown cycles of bolt preload, temperature, normal fluctuation cycles of temperature, and cyclic loading due to vibration normally incident to transport. The OP closure bolts are not subject to high cycle

(> 20,000) fatigue loading and do not require evaluation for fatigue failure per NF-3331.1 [2.2].

The OP closure bolts will be replaced after 5 years of service and, assuming the packaging will be used for one shipment per week, the OP closure bolts will be subjected to a total of 260 startup-shutdown cycles and 1,825 normal operating (diurnal fluctuations) cycles. Although the number of significant vibration cycles may exceed 20,000, vibration loading does not produce significant stress in the OP closure bolts. Therefore, the OP closure bolts will not fail

• due to fatigue during their 5-year design life .

2.1.2.5 2.1.2.5.1 Brittle Fracture CCV Assembly The CCV assembly, which is the containment vessel of the package, is designed in accordance with the fracture toughness requirements of Regulatory Guide 7.11 [2.10] and NUREG/CR 1815

[2.11] for Category I containers, since it is designed to transport normal form content with a maximum activity greater than 3,000 A2 or greater than 30,000 Ci. The criteria for Category I containers assure that the fracture toughness is sufficient to arrest large cracks under dynamic loading and that general yielding will precede facture failure.

The entire CCV body and closure lid are fabricated from austenitic stainless steels, which do not undergo a ductile-to-brittle transition down to -40°F (-40°C) and, thus, do not need to be evaluated for brittle fracture. As stated in Regulatory Guide 7 .11, "Since austenitic stainless steels are not susceptible to brittle failure at temperatures encountered in transport, their use in containment vessels is acceptable to the staff and no tests are needed to demonstrate resistance to brittle fracture."

The CCV closure bolts are fabricated from SA-320, Grade L43 stainless steel bolting material

• that is intended for low-temperature service. Per Section 5 of NUREG/CR-1815 [2.11], bolts are generally not considered as fracture critical components because multiple load paths exist, and NAC International 2.1-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A bolting systems are generally redundant. However, the SA-320, Grade L43 bolting material is required to have a minimum impact energy absorption of 20 ft-lbf (27 N-m) at a temperature of -101 °C (-150°F). For purposes of comparison with the requirements ofNUREG/CR-1815, the nil-ductility transition (NDT) temperature of the CCV closure bolts is calculated as follows.

A fracture toughness value for SA-320, Grade L43 bolting material is calculated using the following empirical relationship from Section 4.2 of NUREG/CR 1815:

KID = .JscvE = 54 ksi-in 112 (59 MPa-m 112 )

where Cv is 20 ft-lbf and Eis 28.8x10 6 psi (199 MPa) at -150°F (-101 °C) from Table TM-1, Material Group B of Section II, Part D, of the ASME Code [2.12].

The dynamic fracture toughness is conservatively translated to an equivalent NDT temperature by using the Design Reference Km curve provided in Figure 2 ofNUREG/CR-1815. By interpolation, the temperature relative to NDT (i.e., T - NDT) is approximately 32°F (18°C).

Accordingly, the NDT temperature is:

NDT = -150°F - (32°F) = -182°F (-119°C)

For Category I fracture critical components with a minimum section thickness of I-inch and a

• yield strength of 100 ksi (690 MPa), Figure 3 ofNUREG/CR 1815 gives the minimum offset "A" as approximately 44°F (7°C). Thus, for Lowest Service Temperature (LST) of -40°F

(-40°C), the maximum NDT temperature value is:

TNDT = LST-A = -40°F- (44°F) = -84°F (-64°C)

The closure bolts experience a ductile-to-brittle transition temperature at -182°F (-1 l 9°C),

whereas the criterion ofNUREG/CR-1815 prescribes a maximum NDT temperature of -84 °F

(-64°C). The 98°F (55°C) margin provides conservative assurance that brittle fracture will not occur in the CCV closure bolts.

2.1.2.5.2 OP Assembly The OP assembly provides impact and thermal protection of the CCV but does not provide containment. Accordingly, the OP assembly is designed in accordance with the Category III fracture toughness requirements ofNUREG/CR-1815 [2.11], which provide sufficient fracture toughness to prevent fracture initiation at minor defects typical of good fabrication practices.

The OP shell assemblies are fabricated entirely from austenitic stainless steels, which does not undergo a ductile-to-brittle transition down to -40°F (-40°C) and, thus, does not need to be evaluated for brittle fracture.

NAC International 2.1-10

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The bolts used to attach the OP lid to the OP base are fabricated from A574 alloy steel. In accordance with the Category III requirements ofNUREG/CR-1815, fracture toughness testing of normalized steel made to "fine grade practice" or better is not required.

2.1.2.5.3 Shield Inserts The shield insert assembly (SIA) provides radiation shielding, but has no structural, thermal or containment function, except it is designed not to fail or collapse such that it would load the waste container or alter the shielding configuration for NCT. Accordingly, the SIA assembly is designed in accordance with the Category III fracture toughness requirements of NUREG/CR-1815 [2.11], which provide sufficient fracture toughness to prevent fracture initiation at minor defects typical of good fabrication practices.

2.1.3 Weights and Centers of Gravity The weight and center of gravity of the package, including each of the major individual packaging subassemblies and contents, are summarized in Table 2.1-8. The reference point for the center of gravity is at the bottom centerline of the OP base assembly, as shown in Figure 2.1-2. The loaded package with the heaviest contents has a nominal gross weight of 9.20 kip

• (4,172 kg) and a center of gravity located at 35.8 inches (91 cm) above the bottom end of the OP base, which is close the geometric center of the package. The center of gravity of the contents provided in Table 2.1-8 is assumed at the geometric center of the CCV cavity. Variations in the content mass distribution within the CCV cavity will not significantly shift the package center of gravity.

2.1.4 Identification of Codes and Standards for Packaging The package, which is designed to transport normal form content with a maximum activity greater than 3,000 A2, is designed, fabricated, tested, and maintained in accordance with codes and standards that are appropriate for transportation packages with Category I container contents.

The codes and standards are selected based on guidance provided in Regulatory Guide 7.6 [2.13]

and NUREG/CR-3854 [2.14].

The package containment system is designed in accordance with the applicable requirements of the ASME Code,Section III, Division 1, Subsection NB [2.1]. The non-containment structural components of the packaging are designed in accordance with the applicable requirements for plate- and shell-type Class 2 supports from the ASME Code,Section III, Division 1, Subsection NF [2.2]. The design criteria for the packaging is discussed in Section 2.1.2. The load combinations used in the packaging structural evaluation are developed in accordance with

• Regulatory Guide 7 .8 [2. 7], as discussed in Section 2.1.2.1. The buckling evaluation of the packaging cylindrical shells is performed in accordance with ASME Code Case N-284-1 [2.7],

NAC International 2.1-11

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A as discussed in Section 2.1.2.3. Fracture toughness of the packaging components is evaluated in accordance with the requirements of Regulatory Guide 7.11 [2.1 O] and NUREG/CR-1815 [2.11]

for Category I containers.

The packaging containment system is fabricated in accordance with the applicable requirements of Subsection NB of Section III, Division 1, of the ASME Code [2.1]. The non-containment structural components of the packaging are fabricated in accordance with the applicable requirements of Subsection NF [2.2] of the ASME Code for plate- and shell-type Class 2 supports.

The polyurethane foam material that fills the OP base and lid shells is fabricated, installed, and tested in accordance with the foam vendors' standard practices. The foam segments are manufactured with the foam rise parallel to the longitudinal axis of the package and encased in the stainless steel shells. Foam specimens from each foam batch are tested to assure that the foam has the specified physical characteristics, including density, crush strength, flame retardancy, intumescences, and leachable chlorides.

NAC International 2.1-12

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.1 Load Combinations for Normal Conditions of Transport Initial Conditions< 1>

Ambient Decay Internal NCT Test Temperature< 2> lnsolation< 3> Heat Pressure<4 > Fabrication Condition 100°F -40°F Max. Zero Max. Zero Max. Min. Stress<5 >

Hot Environment X X X X (100°F ambient)

Cold Environment X X X X

(-40°F ambient)

Reduced External X X X X X Pressure Increased X X X X X External Pressure X X X X X Vibration X X X X X X X X X X Free Drop X X X X X Notes:

1. Initial packaging temperature distribution considered to be at steady-state.

2. Lower bound ambient temperature of -40°C conservatively used.

3. Maximum insolation in accordance with §71.71(c)(l).

4. Internal pressure is consistent with the other initial conditions being considered. Minimum internal pressure is taken as atmospheric pressure.

5. Stresses due to assembly of the major components of the packaging, including stresses due to bolt preload .

• NAC International 2.1-13

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.1 Load Combinations for Hypothetical Accident Conditions Initial Conditions<1 >

Ambient Internal Temperature<2> lnsolation<3 l Decay Heat Pressure<4 > Fabrication HAC Test Condition 100°F -40°C Max. Zero Max. Zero Max. Min. Stress<5>

X X X X X Free Drop X X X X X X X X X X Puncture X X X X X Thermal X X X xcsi X Notes:

I. Initial packaging temperature distributions are at steady-state.

2. Lower bound ambient temperature of -40°C conservatively used.

3. Maximum insolation in accordance with §71.7l(c)(l).

4. Internal pressure is consistent with the other initial conditions being considered. Minimum internal pressure is taken as atmospheric pressure.

5. Stresses due to assembly of the major components of the packaging, including stresses due to bolt preload.

6. Maximum internal pressure for the HAC thermal condition includes increased pressure due to increased fill gas temperatures during the fire transient.

NAC International 2.1-14

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.1 Containment System Allowable Stress Design Criteria Allowable Stress Limits<1 >

Stress Type NCT HAC Other Than Bolts Primary Membrane Stress Intensity Lesser of 2.4Sm and Sm (Pm) 0.7Su Primary+ Bending Stress Intensity 1.5Sm 150% of Pm limit (PL or PL + Pb)

Primary + Secondary Stress Intensity N/A(2l 3.0Sm (PL+ Pb+ Q)

Average Bearing Stress Sy Not required Average Shear Stress 0.6Sm 0.42Su Bolts1 3l Lesser of 0.7Su and Tension, Average Stress Sm Sy Lesser of 0.42Su and Shear, Average Stress 0.6Sm 0.6Sy Tension plus Shear(4 l Rt2 + Rs2:,; 1 Rt2 + Rs2:,; 1 1.35Sm(5l (6)

Maximum Stress Intensity Notes:

I. Stress limits applicable for components and systems evaluated using elastic system analysis.

2. Evaluation of secondary stress is not required for HAC.

3. Per NUREG/CR-6007, Table 6.1 [2.23].

4. R1 and Rs are the stress ratios (i.e., computed stress/allowable stress) for average tensile stress and average shear stress, respectively.

5. Limit for direct tension plus shear plug bending plus residual torsion at periphery of bolt, excluding stress concentrations, for bolts having an ultimate tensile strength, Su, greater than I 00 ksi at operating temperature.

6. Evaluation not required by NUREG/CR-6007 [2.23] for HAC .

• NAC International 2.1-15

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.1 Non-Containment Component Allowable Stress Design Criteria Allowable Stress Limits1 1l Stress Type NCT HAC Other Than Bolts Primary Membrane Stress Intensity Greater of 1.2Sy and Sm (Pm) 1.5Sm, but :::;Q_ ?Su Primary Membrane + Bending Stress Intensity 1.5Sm 150% of Pm allowable (PL or Pm + Pb)

(2)

Average Bearing Stress Sy Average Shear Stress 0.6Sm 0.42Su Bolts Ftb = Su/2 Lesser of 0.7Su Tensile Stress (ft)

(ferritic steels) and spi Fvb = 0.62Su/3 Lesser of 0.42Su and Shear Stress (fv)

(ferritic steels) 0.6Sy f2 f2 f2 f2 Combined Tensile & Shear Stress _t_ + ~ < I _t_+~<l 2 2 - 2 2 -

Ftb Fvb Ftb Fvb Notes:

1. Stress limits applicable for components and systems evaluated using elastic system analysis.

2. Evaluation of secondary stress is not required for HAC.

3. Limit applies to average tensile stress across the entire bolt cross-section. For high-strength bolts (Su>

100 ksi), the maximum value of tensile stress at the periphery of the bolt cross-section resulting from direct tension plus bending and excluding stress concentrations shall not exceed Su.

NAC International 2.1-16

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.1 CCV Shell Buckling Geometric Parameters Geometric Parameter Value Outside Diameter (in) 34.50 Inside Diameter (in) 32.50 Length, L (in) 48.25 Mean Radius, R (in) 16.75 Shell Thickness, t (in) 1.00 R/t 16.75 Unsupported Axial Length, '"' (in) 48.25 Unsupported Circumferential Length, le (in) 105.24 11.80 Me=le/ Rt 25.73 M = smaller of Mq, and Me 11.80

• Table 2.1 CCV Shell Buckling Reduction Factors and Theoretical Buckling Stresses Calculation Capacity Reduction Factors

(-1511)

Parameter CXq,l CXel Value 0.216 0.800 CXq,el 0.800 Plasticity Reduction Factors Ll=CXq,l*crq,el/cry 9.40

(-1610)

Ll=CXel*creel/cry 5.01 Ll=CXq,el*crq,eel/cry 12.66 T]q, 0.106 T]e 0.200 T]q,0 0.047 Theoretical Buckling Values C 0.605

(-1712.1.1) crq,el (ksi) 975.2 Cer 0.087 creel =crrel (ksi) 140.2 Ceh 0.082 creel =crhel (ksi) 132.2 C<1>e 0.220 crq,eel (ksi) 354.6 NAC International 2.1-17

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.1 CCV Shell Allowable Buckling Stresses Buckling Allowable Buckling Stress (ksi)

Regime Stress Type NCT HAC Elastic Axial Compression, crxa 105.3 157.2 Buckling Hydrostatic Pressure, O"ha 52.9 78.9 Hoop Compression, crra 56.1 83.7 In-Plane Shear, a.a 141.8 211.7 Inelastic Axial Compression, O"xc 11.2 16.7 Buckling Radial External Pressure, crrc 11.2 16.7 In-Plane Shear, cr,c 6.7 9.9 Table 2.1 Package Weight and Center of Gravity Summary Center of Gravity<2 >

Package Component or Assembly Weight<1 > (kip) (in)

CCV Assembly 3.12 42.2 CCV Body Assy. 2.08 34.1 CCV lid Assy. & Bolts 1.04 58.5 CCV Bottom Support Plate 0.35 10.4 OP Base Assembly 1.67 21.5 OP Lid Assembly 0.92 58.9 Empty Package 6.05 37.2 5.0 Contents<3> 3.15 33.2 Package Gross Weight 9.20 35.8 Notes:

1. Nominal weights of packaging components are rounded to the nearest 10 pound increment.

2. Vertical distance from the bottom end centerline of the OP base to the center of gravity of the individual packaging subassembly or assembly, as shown in Figure 2.1-2.

3. Maximum weight of contents including dunnage or cribbing, as required.

NAC International 2.1-18

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.1 CCV Stress Evaluation Locations

• NAC International 2.1-19

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

{:}:}:{:/:}:{:~:~}\}/f ((:{:{:{:}:}{}:/:~{}?

           ...............................................................................                   CCV LID ASSY. & BOLTS I                                             I i

I i I OP LID ASSY. & BOLTS i i' "°.~.... 1*..,..

               ..............--"'1..                                                           cc-;-;-

i I I I iI I CONTENTS II I *********** C.G.

                                                                                   !I ;..........
                                                                                         ;;;;;;;:;;.         CCV BODY ASSY.
                                                                                    ~   :::::::::::

OP BASE ASSY. CCV BOTTOM SUPPORT PLATE

{::/:::::::\/::::?:\:\:\:/:/:\:l//:/:/:\:/\::::::/:/:::::::/:\:

Figure 2.1 Package Mass Properties Schematic NAC International 2.1-20

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.2 Materials 2.2.1 Material Properties and Specifications The specifications for the packaging materials of construction are summarized in Table 2.2-1. The mechanical properties of the packaging materials that are used in the structural evaluation are described in this section. The material properties for all steel structural components of the packaging are described in Section 2.2.1.1. The crush strength properties of the impact limiter foam material are described in Section 2.2.1.2. 2.2.1.1 Structural Materials The structural components of the packaging are fabricated from stainless steel, carbon steel and alloy steel bolting material. Type 304 and/or Type 316 austenitic stainless steels in the form of plates (SA-240), forgings (SA-182), or bars and shapes (SA-479) are used to fabricate the structural components of the CCV and OP. SA-320, Grade L43 alloy steel is used for the CCV closure bolts. SA-193, Grade B8, Class 1 bolting steel is used for the port cover bolts. A574 alloy steel is used for the OP closure bolts. A516, Grade 70 carbon steel is used for the SIA.

• Table 2.2-1 provides a summary of the material specifications used for the different structural components of the packaging and the corresponding tables that provide the material properties.

The structural evaluation of the packaging is performed using mechanical properties of materials that are appropriate for the anticipated service conditions. The temperature range of interest for NCT is -40°F (-40°C) to 500°F (260°C). Temperature dependent mechanical properties for the structural material of the packaging, including design stress intensity (Sm) or allowable stress (S), yield strength (Sy), tensile strength (Su), modulus of elasticity (E), and mean coefficient of thermal expansion (a), are summarized in Table 2.2-2 through Table 2.2-8. 2.2.1.2 Impact Limiter Energy-Absorbing Materials The OP base and lid are filled with rigid, closed-cell polyurethane foam. A nominal foam is used in the end region of the OP lid and a nominal foam density of is used in the comer/side regions of the OP base and lid. The foam pieces are oriented with the direction-of-rise parallel to the longitudinal axis of the package. The dynamic stress versus strain data for the polyurethane foam materials, used for the NCT and HAC free drop test evaluations, are developed based on data provided by a foam manufacturer [2.15]. Upper-bound and lower-bound dynamic stress-versus-strain curves are developed for each crush direction, i.e., parallel or perpendicular to the direction of foam rise; considering NAC International 2.2-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A temperature effects, strain rate, and manufacturing tolerance on foam crush strength. The minimum and maximum foam temperatures considered for foam crush strength properties are - 40°F (-40°C) and 180°F (82°C), respectively. These temperatures represent the range of temperatures the foam will experience under all initial conditions for the NCT and HAC free drop tests. The nominal static crush strength of foam at the NCT cold temperature of -40°F (-40°C) and the NCT hot temperature of 180°F (82°C), both parallel and perpendicular to the direction of rise, are based on test data provided by the foam manufacturer [2 .15]. The average static compressive strength of polyurethane foams at room temperature are required to be within  %, respectively, of the nominal value for crushing parallel and perpendicular to the direction of foam rise. The dynamic crush strength of foam is calculated from the static crush strength stress-strain data, adjusted for temperature effects and fabrication tolerance, using the dynamic crush strength regression coefficients provided by the foam manufacturer [2.15]. The data shows little difference between the crush strength due to crush direction. Therefore, the foam is treated as an isotropic material in the drop analysis using stress-strain curves that bound the data for parallel and perpendicular-to-rise directions. The stress-strain curves used to evaluate the upper-bound cold conditions are based on the maximum stress values from the parallel and perpendicular-to-rise directions, whereas the stress-strain curves used to evaluate the lower-bound hot conditions are based on the minimum stress values from the parallel and perpendicular-to-rise directions. The resulting upper-bound and lower-bound dynamic crush strength-versus-strain curves of foam densities are summarized in Figure 2.2-1 and Figure 2.2-2, respectively. 2.2.2 Chemical, Galvanic or Other Reactions The packaging's materials of construction, consisting primarily of stainless steel, carbon steel and polyurethane foam, will not cause significant chemical, galvanic, or other reactions in the operating environment. No significant interactions are expected to occur between the contents of the package, which consist of fuel waste or TRU waste contained in drums or irradiated fuel waste and the packaging materials to which they are exposed. The packaging materials have been used in other radioactive material (RAM) packaging for transport of similar contents without incident. This ensures the packaging integrity will not be compromised by any chemical, galvanic, or other reaction. The exposed surfaces ofthe OP and CCV assemblies are all constructed of Type 304 or 316 austenitic stainless steel, with high corrosion resistance in the operating environments of the packaging. Typically, the contents are packaged in secondary containers, such as drums or NAC International 2.2-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A liners, which limits the chemical interaction between the payload and CCV. Since corrosives are prohibited from the payload, there are no chemical, galvanic, or other reactions between the contents and the CCV of concern. The CCV bottom support plate and SIA carbon steel surfaces are coated with epoxy coating, which is commonly used in the nuclear industry for similar applications, is highly resistant to chemical reactions and has very good abrasion resistance. The coated surfaces of the CCV bottom support plate and SIA assembly contact the stainless steel surfaces of the CCV. Therefore, no chemical, galvanic, or other reactions are expected between the coated surfaces of the CCV bottom support plate or SIA and stainless steel. The polyurethane foam material used for the cores of the OP base and lid has a long history of use in RAM packages without any adverse reactions. The foam material is very low in free-halogen content and leachable chlorides. The closed-cell polyurethane foam material is sealed inside the cavity of the impact limiter stainless steel shells in a dry environment. In the unlikely event moisture was to enter the impact limiter cavity, it could not penetrate the closed-cell structure of the foam to cause leaching of chlorides. Therefore, no chemical, galvanic, or other reactions are expected between the foam and stainless steel. The Fluorocarbon-Viton rubber O-ring material that contacts the stainless steel base material of the CCV contains no corrosives to adversely affect the packaging. This material is organic in nature and has not had any chemical, galvanic, or other reactions with stainless steel. 2.2.3 Effects of Radiation on Materials The packaging is designed using materials to withstand damaging effects from radiation. Durable materials of construction such as austenitic stainless steel, carbon steel and ferritic bolting steel are unaffected by the radiation levels in this package. The polyurethane foam material used for the OP base and lid cores is unaffected by gamma radiation exposure up to 2x 108 rad, equivalent to 1,000 rad/hour for a period of 20 years. At radiation exposure up to 2x 10 8 rad, testing shows no effect on density or crush strength ([2.15], Table 4). Furthermore, the resistance of the polyurethane foam material to water absorption is unaffected by radiation exposure up to Ix 107 rad ([2.15], Table 5). Fluorocarbon polymer O-ring material has good radiation-resistance properties [2.15]. Radiation exposure below 106 rad, a level attained only after many years of operation, produces no change to the physical properties of the O-ring material. Therefore, normal wear, as opposed to radiation

• exposure is the main factor affecting their replacement frequency.

NAC International 2.2-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The O-rings are coated with a thin film of silicone-based lubricant to help protect the O-ring from damage by abrasion, pinching, or cutting. The lubricant also helps to seat the O-ring properly and protect the polymer from environmental damage. Because the O-ring lubricant is frequently cleaned and replaced, and because most of the lubricant's benefit occurs during installation, radiation damage is not a concern. A nickel-based thread lubricant is specified for threaded fasteners. This material is commonly used for nuclear applications and is suitable for use in radiation environments. None of the packaging fasteners are in high exposure areas, and the lubricant is frequently cleaned and replaced, so the lubricant is not subject to radiation damage. NAC International 2.2-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 2.2-5

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.2 Mechanical Properties of A240/SA-240 or A479/SA-479, Type 304/316 Stainless Steel NAC International 2.2-6

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 2.2-7

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.2 Mechanical Pro erties of A36/SA-36 Carbon Steel Table 2.2 Mechanical Properties of A240/SA-240 or A479/SA-479, Type XM-19 Stainless Steel NAC International 2.2-8

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.2 Mechanical Pro erties of A574/SA-574 Allo Steel Socket-Head Ca Screws

• Table 2.2 Mechanical Pro erties of A516, Grade 70 Carbon Steel
• NAC International 2.2-9

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.2 Foam Upper and Lower-Bound Dynamic Stress-Strain Curves Figure 2.2 - Foam Upper and Lower-Bound Dynamic Stress-Strain Curves NAC International 2.2-10

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.3 Fabrication and Examination 2.3.1 Fabrication Fabrication of the packaging is performed under NAC's 10 CFR 71, Subpart H quality assurance program, NRC approval number 0018. The packaging containment system is fabricated in accordance with the applicable requirements of ASME Subsection NB [2.1]. Use of an NPT Certificate Holder and an Authorized Inspection Agency is not required for the construction of the packaging containment system. The non-containment structural components of the packaging are fabricated in accordance with the applicable requirements of ASME Subsection NF [2.2] for plate- and shell-type Class 1 supports. Standard industry practices are used for the fabrication of the OP assembly polyurethane foam cores. All components that form the packaging containment system are fabricated from materials permitted by ASME Subsection NB [2.1] and included in ASME Section II, Part D [2.12]. All other non-containment structural components of the packaging are fabricated from ASTM materials that are equivalent to ASME materials, as permitted by NUREG/CR-3854 [2.14]. The quality category of the weld material is required be equal to or greater than the higher quality

• category of the components being joined. A certified material test report (CMTR) is provided for all steel materials, including weld filler metals, used to fabricate the packaging containment system.

Consumables, such as threaded inserts and elastomeric O-rings, are procured from commercial suppliers and commercially dedicated in accordance with the requirements of the NAC QA program, commensurate with their safety functions. All Category A and B materials, components, and assemblies used for the fabrication of the packaging, including the weld filler metal, are labeled to maintain control and traceability of materials throughout the fabrication process. Marking of materials, components, and assemblies is done using methods that do not result in harmful contamination or sharp discontinuities or infringe upon the minimum required material thickness. All operations associated with the fabrication and assembly of the packaging are included in written shop instructions, e.g., fabrication travelers and/or procedures. All welding is performed in accordance with a written welding procedure specification (WPS) that is qualified in accordance with the applicable requirements of the ASME Code. All personnel performing welding are qualified to use the welding procedure, and their qualifications are documented in accordance with the applicable requirements of Section IX of the ASME Code [2.17] . NAC International 2.3-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A The general processes used to fabricate each finished assembly of the packaging are described as follows: NAC International 2.3-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.3.2 Examination Examination and testing of the packaging is performed under NAC's NRC approved QA program. The components and assemblies of the packaging are inspected to assure that the packaging satisfies the dimensional requirements shown on the general arrangement drawings in Appendix 1.3 .3 and are examined using non-destructive techniques to assure quality of workmanship. In addition, materials, components, and assemblies are tested to assure that they have the required critical characteristics and that they satisfy the acceptance criteria for all required functional tests. All operations associated with the examination and testing of the packaging are included in written shop instructions, e.g., fabrication travelers and/or procedures, and performed by personnel that are trained and qualified, or approved, in accordance with the requirements of the NAC QA program and the requirements of the applicable codes and standards using calibrated measuring and test equipment (M&TE). Witness and hold points are included in the written shop instructions for activities that require QA inspection or oversight. Copies of all written shop instructions, personnel training and qualification records, and M&TE calibration records are maintained with the final records package. The processes used for the examination and testing of the packaging are described as follows: Material Tests The steel materials used to fabricate the components and assemblies of the packaging containment system are furnished CMTRs that assure that the materials possess the critical characteristics that are required to perform their safety functions. No additional examination or testing of these steel materials is required prior to fabrication .

• NAC International 2.3-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Fabrication Tests and Examinations The dimensions of the components and assemblies of the packaging are measured with calibrated M&TE to assure compliance with the dimensional requirements shown on the general arrangement drawings in Appendix 1.3 .3. In addition, the weights of the finished packaging components are measured to assure that they meet the weight requirements. All welded joints receive a workmanship visual examination and liquid penetrant (PT) or magnetic particle (MT) non-destructive examination (NDE) to assure that they do not include visible surface defects, such as lack of fusion, linear or crack like indications, or porosity. In addition, the full-penetration welds that form the CCV body weldment are examined using either radiography (RT) or ultrasonic testing (UT) methods to assure that they do not include any indications of weld flaws. Examinations of welded joints are performed in accordance with the applicable requirements of Section V of the ASME Code [2.8], Subsection NB of the ASME Code for the CCV assembly and Subsection NF of the ASME Code for all other components. Areas of surface defect removal and completed weld repairs require thickness checks, using either a mechanical or UT device, by qualified personnel to verify compliance with the minimum thickness requirements. Written reports of each weld examination are prepared and maintained with the final records package. The components of the finished containment system, i.e., the CCV body, lid, closure bolts, and containment O-ring seal are leak-tested in accordance with ANSI N14.5 to demonstrate leak-tight containment, in accordance with the requirements of Section 8.1.4. The CCV is also tested for an internal pressure not less than 150% of the MNOP in accordance with the requirements of NB-6220 to verify the structural integrity of the containment system, in accordance with the requirements of Section 8.1.3 .2. The OP lifting lugs that are used to lift the package are subjected to load tests before the first use of the packaging, in accordance with the requirements of Section 8.1.3 .1. Functional Tests Functional tests are performed to assure proper fit up of the packaging components. NAC International 2.3-4

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.4 General Requirements for All Packages 2.4.1 Minimum Package Size In accordance with the requirement of 10 CFR 71.43(a), the smallest overall dimension of a package may not be less than 10 cm. The OPTIMUS-L package has an overall height of approximately 70 inches (178 cm) and an outside diameter of 49 inches (124 cm). Therefore, the package meets the minimum package size requirement of 10 CFR 71.43(a). 2.4.2 Tamper-Indicating Feature In accordance with the requirement of 10 CFR 71.43(6), the outside of a package must incorporate a feature, such as a seal, that is not readily breakable and that, while intact, would be evidence that the package has not been opened by unauthorized persons. Two one-piece wire cable tamper-indicating seals are attached between the OP base and lid. Each seal is looped through holes in the alignment tabs located on the OP lid flange and under the tiedown arm located on the OP base flange. The tamper-indicating seal must be removed to open the package and cannot be removed by unauthorized persons without damaging the seal or the package. The location of the seal and its materials of construction minimize the potential for accidental damage

• during transport. Thus, the package satisfies the tamper indicating feature requirements of 10 CFR 71.43 (b). The tamper indicating seal is not required to be installed for empty shipments.

2.4.3 Positive Closure In accordance with the requirement of 10 CFR 71.43(c), the package must include a containment system securely closed by a positive fastening device that cannot be opened unintentionally or by a pressure than may arise within the package. The CCV is completely enclosed inside the OP assembly, which include tamper indicating seals, as discussed in Section 2.4.2. The tamper indicating seals prevent the upper and lower impact limiters from being unintentionally removed from the package. Furthermore, both the OP and CCV are secured by closure bolts. Since tools are required to remove these closure bolts, the package containment system cannot be unintentionally opened. The containment system does not include any covers, valves, or other access that could be inadvertently opened. The package containment system is evaluated for internal pressure loads that arise during NCT and HAC in Section 2.6 and Section 0, respectively. The evaluations demonstrate that the CCV closure bolts satisfy the applicable allowable stress design criteria and that the containment seal remains intact under NCT and HAC. Hence, the package containment system satisfies the positive closure requirements of 10 CFR 71.43( c) .

• NAC International 2.4-1

- - -- -- - This page intentionally left bhink.- --- -- -------

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.5 Lifting and Tie-Down Standards for All Packages 2.5.1 Lifting Devices In accordance with the requirements of §71.45(a), the lifting attachments that are structural parts of the package are designed with a minimum factor of safety of three against yield when used to lift the package in the intended manner. The lifting attachments are also designed so that failure of any lifting device under excessive load would not impair the ability of the package to meet the other requirements of 10 CFR 71 Subpart E. The lifting attachments of the OPTIMUS-L package are designed in accordance with the requirements of ANSI N14.6 [2.21] for special lifting devices for critical lifts. The ANSI N14.6 design limits for lifting devices are lower than the criteria of §71.45(a) and, therefore, compliance with ANSI N14.6 also demonstrates compliance with §71.45(a). Because the package lifting attachments do not include dual-load paths, the lifting attachments are designed to lift the package without generating a combined shear stress or maximum normal stress at any point in the lifting attachment more than Sy/6 or Su/10. In accordance with ANSI Nl4.6, the shear stress and normal stress due to direct load are taken as an average value over the

• cross-section, and normal stress due to bending loads is assumed to vary linearly over the cross-section. In cases where normal stress (cr) and shear stress ('t) occur at the same stress section, they are combined using the von Mises equivalent stress, where the maximum equivalent stress is calculated as:

The gross weight of the packaging with the heaviest contents is approximately 9.2 kip (41 kN). A bounding load of 10 kip (44 kN) is conservatively assumed, which includes an allowance for the pallet and tiedown devices that are permitted to remain attached to the package when lifted. The bounding weight is conservatively increased by an additional 15% to account for possible dynamic amplification due to crane hoist

• motion. Therefore, a vertical design lift load of 11.5 kip (51 kN), or 3.83 kip (17 kN) per lift lug, NAC International 2.5-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A is conservatively used for the lifting device evaluation. The resulting tensile force, F, acting along the axis of the lifting lug is 4.08 kip (18 kN). NAC International 2.5-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 2.5-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 2.5-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The results of the lifting attachment analysis described above are summarized in Table 2.5-1. The minimum design margin is +0.04 for the maximum equivalent stress resulting from shear tear-out. Therefore, the OP lift lug satisfies the stress limits of ANSI N14.6 and §71.45(a) .

• Furthermore, under excessive loading the OP lift lug will fail due to shear tear-out, which would not impair the ability of the package to meet the other requirements of 10 CFR 71 Subpart E.

Therefore, the over-load requirement of §71.45(a) is satisfied when the package is lifted by the OP lift lugs. In accordance with the requirements of §71.45(a), any other structural part of the package that could be used to lift the package must be capable of being rendered inoperable for lift the package during transport or must be designed with strength equivalent to that required for lifting attachments. There are no other structural parts of the packaging that can be used to lift the package during transport. Therefore, the lifting requirements of §71.45(a) are met. 2.5.2 Tie-Down Devices In accordance with the requirements of §71.45(b), the package tie-down devices are designed to withstand a static force applied to the package center gravity with a 2g vertical load component, a 5g lateral load component, and a 10g longitudinal (i.e., horizontal component along the direction in which the vehicle travels) load component, without generating stress in any material of the package more than its yield strength .

• NAC International 2.5-5

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A The reaction loads on the package tiedowns due to the 2g vertical load, 5g lateral load, and a 1Og longitudinal loads are determined using the principal of static equilibrium assuming that the package is chocked to prevent the bottom end from sliding on the conveyance and that the package rotates as a rigid-body about the bottom edge of the OP base. The maximum reaction loads in tiedowns resulting from combination of the 1Og longitudinal load and 2g vertical load and from the 5g lateral load are determined separately and combined by SRSS to determine the maximum tie-down load. The results show that the maximum tiedown tensile force is 39.2 kip (174 kN). A bounding 40 kip (178 kN) tiedown load is conservatively used to evaluate the tie-down attachments. NAC International 2.5-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• • NAC International 2.5-7

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 2.5-8

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 2.5-9

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Summary: The results of the tiedown attachment stress analysis described above are summarized in Table 2.5-2. The minimum design margin in the tiedown attachments due to a 40 kip (178 kN) tiedown reaction is +0.04 for the maximum equivalent stress at the base of the tiedown arm (Section 3 in Figure 2.5-3). Therefore, the tiedown attachments satisfy the requirements of §71.45(b). The results show that the design margin at the base of the tiedown arm is less than the design margin in the tiedown arm attachment weld. Therefore, under excessive loading, the tiedown arm will fail at the base of the tiedown arm. Because the tie-down arms are not relied upon for other safety functions, their loss would not impair the ability of the package to meet the other requirements of 10 CFR 71 Subpart E. Therefore, the over-load requirement of §71.45(b)(3) is satisfied. In accordance with the requirements of §71.45(b)(2), any other structural part of the package that could be used to tie-down the package must be capable of being rendered inoperable for tying down the package during transport or must be designed with strength equivalent to that required for tie-down devices. The only other structural part of the package that could be used for tiedowns are the lifting lugs located at the top of the OP lid. In order to prevent the lifting lugs from mistakenly being used for tiedowns, they are disableq during transport. NAC International 2.5-10

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.5 Liftin Attachment Stress Summa Table 2.5 Tiedown Attachment Stress Summa

• NAC International 2.5-11

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.5 Lifting Attachment Loading Diagram NAC International 2.5-12

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• Figure 2.5 Package Tiedown Configuration
• NAC International 2.5-13

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.5 Tiedown Arm Loading Diagram NAC International 2.5-14

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.6 Normal Conditions of Transport This section presents the structural evaluation of the package that demonstrates compliance with the requirements of 10 CFR 71.43(f) and 10 CFR 71.Sl(a)(l) when subjected to the NCT tests specified in 10 CFR 71.71. In accordance with 10 CFR 71.71(a), the package is required to be evaluated for each NCT test individually based on the most unfavorable initial conditions, including an ambient temperature between -20°F (-29°C) and 100°F (38°C) and an internal pressure between zero and the MNOP. The OPTIMUS-L package is conservatively evaluated for NCT using a lower bound initial ambient temperature of 40°F (-40°C). The structural evaluation shows that there would be no loss or dispersal of radioactive contents, no significant increase in external surface radiation levels, and no substantial reduction in the effectiveness of the packaging. 2.6.1 Heat In accordance with 10 CFR 71.7l(c)(l), the package is subjected to an ambient temperature of 100°F (38°C) in still air and insolation. The packaging maximum internal pressure and temperatures resulting from NCT heat conditions are summarized in Section 2.6.1.1. Differential thermal expansion between the packaging components under NCT heat loading is evaluated in Section 2.6.1.2. The packaging stresses due to NCT heat loading are evaluated in Section 2.6.1.3. The results of the NCT heat structural evaluation demonstrate that the packaging satisfies the applicable structural design criteria. 2.6.1.1 Summary of Pressures and Temperatures The maximum temperatures of the packaging components for NCT thermal conditions from Chapter 3 are summarized in Table 3 .1-1. The maximum package temperatures for NCT result from the maximum content total heat load of 100 watts with an ambient air temperature of 100°F (38°C) and insolation. For this case the maximum temperatures of the accessible surface of the package and the CCV assembly are l 12°F (45°C) and 213°F (100°C), respectively. The allowable stress intensities used for the structural evaluation of the packaging lifting and tiedown attachments, which are all located on the package exterior, are conservatively based on an upper-bound temperature of 200°F (93°C). The allowable stresses used for the structural evaluation of the CCV bottom plate, shell, and lid are conservatively based on an upper-bound temperature of 300°F (149°C). The allowable stresses used for the structural evaluation of the CCV closure bolts are conservatively based on an upper-bound temperature of 2 l 0°F (99°C) .

• NAC International 2.6-1

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A As discussed in Section 3.3.2, the maximum gauge pressure that would develop in the package containment system in a period of one year under the heat conditions (MNOP) is 21.8 psi (150 kPa) gauge. A bounding internal pressure of 100 psi (690 kPa) gauge is used to perform the packaging structural analysis for NCT. 2.6.1.2 Differential Thermal Expansion Differential thermal expansion of the packaging components is evaluated considering possible interference resulting from a reduction in gap sizes. The differential thermal expansion evaluation includes radial and longitudinal differential thermal expansion between the CCV assembly and the OP cavity and between the SIA and the CCV cavity. The results of the evaluation of differential thermal expansion show that the CCV expands freely within the OP cavity and the SIA expands freely within the CCV cavity under NCT thermal loading under NCT thermal loading. 2.6.1.2.1 Differential Thermal Expansion Between CCV and OP The package is designed with enough clearance between the OP cavity and the outside surfaces of the CCV to permit free thermal expansion of the CCV under NCT and HAC. Nominal radial clearances are provided between the OP cavity and the outside surfaces of the CCV. As shown in Chapter 3, the maximum temperatures of the CCV and the exterior surface of the OP for the NCT heat condition are 213°F (100°C) and 112°F (45°C), respectively. The differential thermal expansion between the CCV and OP is evaluated using- - conservatively assuming an upper-bound temperature of220°F (104°C) for the CCV and a lower-bound temperature of 100°F (38°C) for the OP. The results show that differential thermal expansion of the between the CCV and OP reduces the nominal axial and radial clearances to respectively. Therefore, the CCV will expand freely within the OP cavity under NCT heat. 2.6.1.2.2 Differential Thermal Expansion Between SIA and CCV The package is designed with sufficient clearances between the CCV cavity and the outside surfaces of the SIA to permit free thermal expansion of the SIA under NCT and HAC. Nominal radial clearances are provided between the CCV cavity and the outside surfaces of the SIA. As shown in Chapter 3, the maximum temperature of the SIA (conservatively taken as the maximum average content and fill gas temperature) results NAC International 2.6-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A from the HAC text with the maximum TRU waste decay heat load of 50 watts and air fill gas. The results show that the maximum temperatures of the SIA (contents) is 281 °F (139°C). The differential thermal expansion between the SIA and CCV is evaluated using-

 -             conservatively assuming an upper-bound temperature of 700°F (3 71 °C) for the SIA and 70°F (21 °C) for the CCV. The results show that differential thermal expansion of the between the SIA and CCV reduces the nominal axial and radial clearances to respectively. Therefore, the SIA will expand freely within the CCV cavity under NCT heat.

2.6.1.3 Stress Calculations The OPTIMUS-L package is designed to withstand the effects of the hot environment (i.e., NCT heat) in accordance with 10 CFR 71.71(c)(l). Per Table 2.1-1, NCT heat consists of a 100°F (3 8°C) ambient temperature combined with maximum decay heat, maximum insolation, maximum internal pressure, and fabrication stresses. The OP and SIA are not included in the NCT heat stress evaluation because they are designed in accordance with the allowable stress design criteria of ASME Subsection NF, which does not require evaluation of secondary stress, such as those stresses resulting from temperature-induced loading .

• NAC International 2.6-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A intensity in the CCV due to NCT heat loading is 24.5 ksi (169 MPa), occurring at the bottom end of the containment shell (section C6 in Figure 2 1). The maximum Pm+Pb+Q stress intensity in the packaging containment system for NCT is limited to 3.0Sm. The minimum value of Sm for the packaging shell materials at a bounding design temperature of 300°F (149°C) is 20.0 ksi (138 MPa). Therefore, the allowable Pm+Pb+Q stress intensity for the containment system is 60.0 ksi (414 MPa) and the minimum design margin in the packaging containment system due to NCT heat loading is +l.45. The results of the NCT heat stress analysis also show that the maximum average tensile stress in the CCV closure bolts is 57.9 ksi (399 MPa) and maximum stress intensity at the periphery of the CCV closure bolts, neglecting stress concentrations, is 62.l ksi (428 MPa). From Table 2.1-3, the average tensile stress and maximum stress intensity in the CCV closure bolts for NCT are limited to Sm and l .35Sm, respectively. The design stress, Sm, for the CCV closure bolt SA-320, Grade L43 material at a bounding temperature of 210°F (99°C), based on linear interpolation of the values shown in Table 2.2-4, is 65.8 ksi (454 MPa). Therefore, the allowable average tensile stress and allowable stress intensity in the CCV closure bolts forNCT are 65.8 ksi (454 MPa) and 88.8 ksi (612 MPa), respectively. The corresponding minimum margins of safety for average tensile stress and maximum stress intensity at the periphery of the CCV closure bolts for NCT heat are +0.14 and +0.45, respectively. NAC International 2.6-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.6.1.4 Comparison with Allowable Stresses The results of the NCT heat structural evaluation demonstrate the packaging satisfies the applicable NCT allowable stress design criteria. NCT heat loading does not cause any permanent deformation of the package, nor does it substantially reduce the effectiveness of the packaging. Furthermore, since the evaluation shows that the containment seal is maintained under NCT heat loading, there would be no loss or dispersal of radioactive contents. Finally, the configuration of the package under NCT heat loading is bounded by that considered in the shielding evaluation. The NCT heat loading does not cause any significant increase in external surface radiation levels. Therefore, the package complies with the requirements of 10 CFR 71.43(:f) and 10 CFR 71.5 l(a)(l) when subjected to the NCT heat test specified in §71.71(c)(l). The structural evaluation of the package for reduced external pressure, increased external pressure, vibration normally incident to transport, and NCT free drop tests is discussed in the following sections. Each NCT test is evaluated in combination with the initial conditions expected to cause maximum package damage. The structural evaluation demonstrates that the package satisfies the applicable performance requirements specified in the regulations under all NCT tests. The evaluation of the packaging for cyclic service under NCT, which is presented in Section 2.1.2.4, demonstrates that the package satisfies the applicable fatigue design criteria of the ASME Code .

• NAC International 2.6-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.6 1/2-Symmetry CCV FEA Stress Analysis Model NAC International 2.6-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.6 Bounding NCT Heat Temperature Distribution

• NAC International 2.6-7

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.6.2 Cold The package is designed to withstand the effects of a steady state ambient temperature of -40°F (-40°C) in still air and shade in accordance with 10 CFR 71.7l(c)(2). Per Table 2.1-1, the NCT cold environment is evaluated in combination with zero insolation, zero decay heat, and zero internal pressure. Therefore, the NCT cold environment results in a uniform temperature of -40°F (-40°C) throughout the package. The CCV assembly, which is made from austenitic stainless steel, is contained inside the cavity of the OP assembly, which is also made from austenitic stainless steel. Therefore, no differential thermal expansion between the CCV and OP cavity is expected under NCT cold conditions. The only thermal stresses in the packaging due to NCT cold are those resulting from differential thermal expansion of the closure bolts and lids, which are made of dissimilar materials. - Therefore, the CCV closure seal will be maintained under NCT cold loading. Furthermore, it is concluded that the closure bolt stresses due to NCT cold are bounded by those resulting from other NCT load combinations. The NCT cold structural evaluation concludes that the packaging satisfies the applicable NCT allowable stress design criteria. NCT cold loading does not cause any permanent deformation of the packaging, nor does it substantially reduce the effectiveness of the packaging. Furthermore, since the containment seal is maintained under NCT cold loading, there would be no loss or dispersal of radioactive contents. Finally, the configuration of the package under N CT cold loading is bounded by that considered in the shielding evaluation. Therefore, NCT cold loading does not cause any significant increase in external surface radiation levels. The package thus complies with the requirements of 10 CFR 71.43(+/-) and 10 CFR 71.51(a)(l) when subjected to the NCT cold test specified in §71.7l(c)(2). 2.6.3 Reduced External Pressure In accordance with 10 CFR 71.7l(c)(3), the package is designed to withstand the effects of a reduced external pressure of3.5 psi (25 kPa) absolute. Per Table 2.1-1, reduced external pressure loading is considered in combination with MNOP, NCT heat, and fabrication stresses. The OP stresses are not included in the reduced external pressure evaluation because it is not a pressure-retaining component. NAC International 2.6-8

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Under NCT heat conditions, MNOP does not exceed 100 psi (690 kPa) gauge. Therefore, the greatest pressure difference between the inside and outside of the containment system is 111.2 psi (767 kPa). The only significant fabrication stresses in the package are those resulting from closure bolt preload. Therefore, the following load combinations are considered for the evaluation of reduced external pressure loading: (A) Reduced External Pressure+ MNOP + Bolt Preload (B) Reduced External Pressure+ MNOP + Bolt Preload + NCT Heat Thermally induced stress intensities are classified as secondary in accordance with the ASME Code since they are self-limiting. Therefore, the stress intensities obtained from load combination (B) are compared to the stress limits for primary plus secondary (Pm+Pb+Q) stress intensity . The maximum stresses in the CCV components resulting from the reduced external pressure load combinations are summarized in Table 2.6-1, along with the corresponding allowable stress intensities and minimum design margins. The results show that the maximum stress intensities in the CCV due to reduced external pressure loading are lower than the corresponding allowable stress intensities. The minimum design margin for stresses in the CCV body and lid due to reduced external pressure loading is +0.67 for primary membrane plus bending stress intensity (Pm+Pb) at the center of the bottom end plate (section Cl in Figure 2 1). The minimum design margin in the CCV closure bolts is +0.15 for average tensile stress. Zero separation between the CCV lid and bolting flange at the location of the containment O-ring results from NCT reduced external pressure loading. Therefore, the CCV containment seal will be maintained under NCT reduced external pressure loading. The results of the NCT reduced external pressure structural evaluation demonstrate that the

• package containment system satisfies the applicable NCT allowable stress design criteria.

NAC International 2.6-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Reduced external pressure loading does not cause any permanent deformation of the package, substantially reduce the effectiveness of the packaging, result in any loss or dispersal of radioactive contents, or cause any significant increase in external surface radiation levels. Therefore, the package complies with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(l) when subjected to the NCT reduced external pressure test specified in 10 CFR 71.7l(c)(3). NAC International 2.6-10

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.6 Reduced External Pressure Stress Summary

• NAC International 2.6-11

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.6.4 Increased External Pressure In accordance with §71.71(c)(4), the package is designed to withstand the effects of an increased external pressure of 20 psi (140 kPa) absolute. The OP assembly, which is not a pressure-retaining component, is not affected by increased external pressure. The SIA, contained inside the CCV cavity, is also not affected by increased external pressure. Furthermore, the effect of increased external pressure on the CCV is considered negligible. This conclusion is evident by comparison to the results of the evaluation of the deep-water immersion test discussed in Section 2.7.7. The magnitude of the external pressure load for deep-water immersion is 14.5 times greater than the reduced external pressure, whereas the ratio of HAC-to-NCT allowable stress limits is slightly greater than 2. 2.6.5 Vibration In accordance with 10 CFR 71.71(c)(5), the package is subjected to vibration normally incident to transport. The package is transported by truck in a vertical orientation. The package is supported by the bottom end of the OP base and tied down by the four tiedown arms located on the OP assembly. As shown in Table 2 of ANSI N14.23 [2.18], the peak vibration accelerations for truck transport are much lower than those resulting from the NCT free drop evaluated in Section 2.6.7. Therefore, it is concluded that the packaging stresses due to NCT vibration satisfy the allowable stress design criteria for NCT. The primary concern for NCT vibration is fatigue failure of the packaging, which is discussed in Section 2.1.2.4. Therefore, it is concluded that the packaging satisfies the applicable NCT allowable stress design criteria for NCT vibration. NCT vibration loading does not cause any permanent deformation of the package, nor does it substantially reduce the effectiveness of the packaging. Finally, the configuration of the package under NCT vibration loading is bounded by that considered in the shielding evaluation. Therefore, NCT vibration loading does not cause any significant increase in external surface radiation levels. The package thus complies with the requirements of 10 CFR 71.43(f) and 10 CFR 71.51(a)(l) when subjected to the NCT vibration test specified in 10 CFR 71.71(c)(5). 2.6.6 Water Spray In accordance with the requirements of 10 CFR 71.7l(c)(6), the package must be subjected to a water spray that simulates exposure to rainfall of approximately 2 in/h (5 cm/h) for at least 1 hour. Quenching effects due to the water spray test will not significantly affect the package. The CCV assembly is isolated from the quenching effects of the water spray by the OP assembly, NAC International 2.6-12

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A which insulates the CCV from sudden environmental changes. Therefore, this condition is not significant in the structural design of the package and is not analyzed. 2.6.7 Free Drop In accordance with 10 CFR 71.71(c)(7), the package, which weighs less than 11,000 pounds (5,000 kg), is subjected to a free drop through from 4 feet (1.2 m) "onto aflat, essentially unyielding, horizontal surface, striking in a position for which maximum damage is expected." In accordance with the requirements of Regulatory Guide 7.8 [2.5], the worst-case initial conditions are considered for the NCT free drop test. These initial conditions include ambient temperatures that range from -40°F (-40°C) with zero decay heat and zero insolation (i.e., "cold" thermal condition) to an ambient temperature of 100°F (38°C) with maximum decay heat and maximum insolation (i.e., "hot" thermal condition). The free drop for the "cold" thermal condition is evaluated using the upper-bound dynamic crush strength properties of the impact limiter foam to determine the maximum loads imparted to the packaging, whereas the free drop for the "hot" thermal condition is evaluated using the lower-bound dynamic crush strength properties of the impact limiter foam to determine the maximum damage to the packaging (i.e., impact limiter crush depth) .

• A drop loads analysis is performed to predict the acceleration loading on the CCV and the damage to the packaging resulting from each NCT free drop impact orientation, as discussed in Section 2.6.7.1. The LS-DYNA explicit dynamic finite element code, which is described in Section 2.12.2.2, is used for the drop loads analysis. In addition to determining the package accelerations and damage, this analysis demonstrates the structural adequacy of the OP closure bolts for the NCT free drop tests. The maximum tensile stresses in the OP closure bolts are shown to satisfy the applicable allowable stress design criteria. Furthermore, the maximum crush depth of the OP assembly polyurethane foam due to each NCT free drop is much less than the allowable crush depth.

A detailed stress analysis of the CCV is performed using linear-elastic static finite element analysis methods. The ANSYS computer program, which is described in Section 2.12.2.1, is used for this analysis. Bounding equivalent-static acceleration design loads are applied to the finite element model for each NCT free drop orientation. The bounding equivalent-static acceleration design loads are determined by multiplying the cask peak rigid-body accelerations determined in Section 2.6.7.1 by dynamic load factors (DLFs) to account for possible dynamic amplification within the cask. The maximum stresses in the CCV due to each NCT free drop are calculated and shown to satisfy the applicable allowable stress design criteria of Subsections NB

• [2.1] of the ASME Code. In addition, the compressive stresses in the CCV shells due the NCT NAC International 2.6-13

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A bottom end drop, which produces the highest compressive stresses in the CCV shell, is evaluated in accordance with ASME Code Case N-284-1 [2.7] and shown to satisfy the applicable buckling design criteria. The packaging NCT free drop stress analysis and buckling analysis are discussed further in Sections 2.6.7.2 and 2.6.7.2.2, respectively. The stress analyses of the SIA are performed using a combination of classical hand calculations and finite element analyses. The maximum stresses at the critical sections of the SIA due to each NCT free drop are calculated and shown to satisfy the applicable allowable stress design criteria of Subsections NF [2.2] of the ASME Code. The results of the NCT free drop structural evaluation demonstrate that the packaging satisfies the applicable NCT allowable stress design criteria. NCT free drop loading does not cause any significant permanent deformation of the packaging, except for the OP assembly, nor does it substantially reduce the effectiveness of the packaging. Furthermore, since the evaluation shows that the containment seal is maintained under NCT free drop loading, there would be no loss or dispersal ofradioactive contents. Finally, the configuration of the package under NCT free drop loading is bounded by that considered in the shielding evaluation. Therefore, NCT free drop loading does not cause any significant increase in external surface radiation levels. Thus, the package complies with the requirements of 10 CFR 71.43(+/-) and 10 CFR 71.51 (a)(l) when subjected to the NCT free drop test. 2.6.7.1 Drop Loads Evaluation The drop loads evaluation of the package for the NCT free drop test is performed using the LS-DYNA explicit dynamic finite element code and the 3-D half-symmetry finite element model shown in Figure 2.6-4. The finite element model includes detailed representations of the OP base, OP lid, OP closure bolts, CCV body, CCV closure lid, and CCV closure bolts. Design features that are considered important for the structural response of the OP bolted closure, including the bolt pockets in the OP lid, bolt through-holes in the OP lid flange, and stepped OP lid flanges that prevent excessive shear loading of the closure bolts, are modeled. Minor design features that do not affect the structural response of the package, such as the CCV test and fill ports, are not modeled. All components are modeled based on the nominal design dimensions. The LS-DYNA model is constructed using 3-D fully-integrated selectively reduced solid 8-node brick elements and 3-D fully-integrated 4-node shell elements. Brick elements are primarily used to model the CCV and contents, OP base and lid foam cores, OP base and lid bolt flange rings, and OP closure bolts, whereas shell elements are used to model the steel plates and sheet metal of the OP base and lid that encases the foam cores. The CCV and contents are modeled as

• NAC International 2.6-14

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A a rigid-body for the NCT free drop analysis. The nonlinear contact between the various components of the packaging are modeled using the smface-to-smface contact type. The foam cores of the OP base and lid are modeled using the LS-DYNA crushable foam material model. The dynamic compressive stress-strain properties used for the 5 pcf and 24 pcf foam cores are based on the upper-bound curves shown in Figure 2.2-1 and Figure 2.2-2, respectively. The tensile cut-off value for the foam materials (i.e., the limit on tensile stress) is conservatively set to Opsi. The piecewise-linear plasticity material model, which allows for the input of the stress-strain and define failure based on the plastic strain, is used for the steel components of the OP assembly. The true stress-hue strain data used for stainless steel are developed in accordance with Section VIII, Division 2, Annex 3.D of the ASME Code [2.22] conservatively using the material The OP bolts are modeled usin linear elastic material For the drop loads analysis, the "cold" thermal condition (i.e., an ambient temperatme of-40°F (-40°C) with zero decay heat and no insolation) is the worst case since it results in the lowest package temperatures, the highest crush strength of the impact limiter foam, and the highest acceleration loads. The "hot" the1mal condition (i.e., an ambient temperature of I 00°F (38°C) with maximum decay heat and insolation), for which the package temperatures are highest and the foam crush strength is lowest, are not considered in the NCT free drop impact analysis since the accelerations will be bounded by those under "cold" thermal conditions and because there is The package is evaluated for five. different NCT free drop impact orientations, as shown in Figure 2.6-3. These include bottom end drop, top end drop, bottom comer drop, top comer drop,

• and side drop. NCT oblique drops are not evaluated since they are expected to be bounded by NAC International 2.6-15

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A the side drop acceleration loads because the OPTIMUS-L package has a very small aspect ratio (i.e., height to diameter). The NCT free drop evaluation is performed using the heaviest contents, weighing 3,500-pound (1,587 kg) including the weight of the CCV bottom support plate. A summary of the NCT free drop cases evaluated in provided in Table 2.6-2. The maximum impact limiter deformation and peak rigid-body accelerations resulting from each NCT free drop cases evaluated are summarized in Table 2.6-3. The impact limiter deformation and rigid-body acceleration time history resulting from each of the NCT free drop orientations evaluated are shown in Figure 2.6-5 through Figure 2.6-14. The impact limiter damage resulting from the NCT free drop is minimal and will not affect the ability of the package to withstand the HAC tests required by required by 10 CPR 71.73. bolt stresses resulting from the NCT free drop satisfy the applicable allowable stress design criteria. 2.6.7.2 Stress Evaluation 2.6.7.2.1 CCV The stresses in the CCV due to NCT free drop loading are determined using finite element analysis methods. Equivalent-static linear-elastic analyses are performed for those NCT bottom and top end drops, NCT side drop, and NCT top comer drop. The NCT bottom comer drop is not evaluated because it is expected to be bounded by the NCT top comer drop, which produces higher stresses in the CCV lid and closure bolts and is most critical for the CCV containment. The equivalent static acceleration loads for each NCT free drop orientation are equal to the peak rigid body accelerations of the package multiplied by a DLF that accounts for dynamic amplification within the packaging. As discussed in Section 2.12.4, the DLF for each NCT free drop case is determined using the DLF curve for an undamped single degree of freedom system subjected to a half-sine pulse. As shown in Figure 2.12-2, the DLF is a function of the t/T ratio, where the load pulse duration (t) is taken from the rigid-body acceleration time-history curve for the drop case and the corresponding highest natural period (T) is based on the lowest NAC International 2.6-16

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A For the NCT free drop stress evaluation, the maximum package accelerations calculated for the "cold" thermal conditions are used to determine the maximum stresses in the packaging. These stresses are conservatively compared to the lower bound allowable stresses that are based on a design temperature that bounds the peak temperatures of the CCV under the "hot" thermal conditions. In accordance with Regulatory Guide 7.8 [2.5], NCT free drop loads are evaluated in combination with MNOP, NCT heat, and fabrication stresses. The only significant fabrication stresses in the package are those resulting from closure bolt preload. Upper-bound bolt preloads are conservatively used for the CCV stress evaluation. Therefore, the following load combinations are considered for each NCT free drop load orientation evaluated:

• (A)

(B) NCT Free Drop + Bolt Preload + MNOP NCT Free Drop+ Bolt Preload +Max.Internal Pressure+ NCT Heat Thermally induced stress intensities are classified as secondary in accordance with the ASME Code since they are self-limiting. Therefore, the stress intensities obtained from load combination (B) are compared to the stress limits for primary plus secondary (Pm+Pb+Q) stress intensity. The stresses in the CCV due for the NCT free drop load combinations are calculated using the 3-D half symmetry finite element model described in Section 2.6.1.2.2. Surface-to-surface contact elements are included between the CCV lid and flange to simulate the non-linear contact behavior of the seal region under NCT free drop conditions. Elastic foundation elements (i.e., spring supports) are added to the surfaces of the CCV that are support by the OP base and lid, as applicable, to simulate the reaction loads from the OP assembly for the NCT free drop. For the NCT end corner drops spring elements are added to the impacted end surface of the CCV assembly and for the NCT side and corner drops, spring elements are added to the top and bottom regions of the CCV that interface with the OP base and lid. The elastic foundation stiffness for the side drop is assumed to vary with a cosine distribution over a 90° half-angle, where the average spring stiffness value is derived based on a foam crush strength at 70% strain . NAC International 2.6-17

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A combination. The membrane, membrane plus bending, and total stress intensity at each of the stress evaluation locations shown in Figure 2.1-1 are evaluated for each NCT free drop load combination. The maximum stresses and corresponding design margins in the CCV components resulting from the NCT end drop, NCT side drop, and NCT corner drop orientations are summarized in Table 2.6-4, Table 2.6-5, and Table 2.6-6 respectively. The results show that the minimum design margin in the CCV is +0.04 for the maximum stress intensity at the periphery of the CCV closure bolt due to the NCT top corner drop. The lowest design margin in the CCV body and lid is +0.24 for primary membrane plus bending (Pm+Pb) stress intensity at the center of the CCV lid (at stress section C16) due to the NCT top end drop. The minimum design margin for membrane plug bending stress intensity (Pm+Pb) at the center of the CCV bottom suppo1i plate for the NCT bottom end drop is+ 1.58. Therefore, the packaging satisfies the applicable allowable stress design criteria for the NCT free drop. NAG International 2.6-18

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.6.7.2.2 Shield Inserts The stresses in the 1-inch and 21/4-inch SIA due to NCT free drop loading are determined using a combination of hand calculations and finite element analyses. Stresses are calculated for NCT top end, bottom end, and side drop orientations. The stresses in the SIAs due to the NCT top and bottom corner drop are bounded by those due to the NCT end and side drop orientations. This conclusion is based on the comparison of the results of the NCJ:' drop analysis summarized in Table 2.6-3, which show that the NCT top and bottom corner drop acceleration load are

• approximately 113 rd or less of the NCT end and side drop acceleration loads.

In accordance with Regulatory Guide 7.8 [2.5], NCT free drop loads are combined with MNOP, NCT heat, and fabrication stresses. MNOP does not cause any stresses in the SIA 1;,ecause it is not pressure-retaining. In addition, the shield inserts are designed in accordance with ASME Subsection NF, which does not require evaluation of thermal stresses. Finally, no significant fabrication stresses are expected in the SIA. Therefore, stresses in the SIA due to the NCT free drop need not combined be with any other stresses .

• NAC International 2.6-19

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 2.6-20

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 2.6-21

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.6.7.3 Buckling Evaluation 2.6.7.3.1 Buckling evaluation of the CCV shell is performed for the NCT free drop test in accordance with the requirements of ASME Code Case N-284-1 [2.7]. Bounding stresses in the CCV shell are determined for combined NCT free drop, NCT heat, and NCT increased external pressure loads, conservatively neglecting internal pressure because it results in tensile stresses in the CCV shell that increase the margin of safety for buckling. As discussed in Section 2.1.2.3, elastic and inelastic buckling interaction ratios are calculated based on the NCT allowable buckling stresses shown in Table 2.1-7, which include a factor of safety of 2.0. The maximum interaction ratios must not exceed 1.0. The maximum combined stresses used for the CCV shell buckling analysis are summarized in Table 2.6-7. NAG International 2.6-22

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A The allowable stresses and interaction ratios for elastic and inelastic buckling are summarized in Table 2.6-8. The highest buckling interaction ratio in the CCV shell for the NCT free drop, including both elastic and inelastic buckling, is 0.57 for inelastic buckling due to axial compression plus shear, which is less than the limit of 1.0. Therefore, the minimum margin of safety against buckling of the CCV shell for the NCT bottom end drop is +0.75. The results demonstrate that the CCV shell satisfies the buckling design criteria of ASME Code Case N-284-1 for the NCT bottom end drop. Subsection NF of the ASME Code [2.2], for normal conditions (i.e., Service Level A) the stress is limited to 1/2 of the critical buckling stress. Stated differently, the minimum factor of safety required against buckling is 2. Therefore, the minimum margins of safety against buckling of the

• I-inch and 2 1/4-inch SIAs for the NCT bottom end drop are +5 .20 and+ 1.50, respectively. These analyses demonstrate that the I-inch and 21/4-inch SIA both satisfy the buckling design criteria for the NCT bottom end drop .
• NAC International 2.6-23

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.6 NCT Free Drop Impact Analysis Results NAC International 2.6-24

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.6 NCT End Drop Stress Summary

• NAC International 2.6-25

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.6 NCT Side Drop Stress Summary NAC International 2.6-26

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.6 CCV Shell Buckling Evaluation Results for NCT Free Drop

• NAC International 2.6-27

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Case NBE1 Case NTE1 Case NS1 NCT Bottom End Drop NCT Top End Drop NCT Side Drop Case NBC1 Case NTC1 NCT Bottom Comer Drop NCT Top Comer Drop Figure 2.6 NCT 4-Foot (1.2 m) Free Drop Impact Orientations NAC International 2.6-28

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.6 Drop Analysis 1/2-Symmetry Model - Isometric View

• NAC International 2.6-29

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.6 Cold/Hard NCT Bottom End Drop (Case NBEl) Impact Limiter Deformation Figure 2.6 Cold/Hard NCT Bottom End Drop (Case NBEl) Rigid-Body Acceleration Time-History NAC International 2.6-30

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• Figure 2.6 Cold/Hard NCT Top End Drop (Case NTEl)

Impact Limiter Deformation Figure 2.6 Cold/Hard NCT Top End Drop (Case NTEl) Rigid-Body Acceleration Time-History

• NAC International 2.6-31

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.6 Cold/Hard NCT Bottom Corner Drop (Case NBCl) Impact Limiter Deformation

• Figure 2.6 Cold/Hard NCT Bottom Corner Drop (Case NBCl)

Rigid-Body Acceleration Time-History NAC International 2.6-32

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• Figure 2.6 Cold/Hard NCT Top Corner Drop (Case NTCl)

Impact Limiter Deformation Figure 2.6 Cold/Hard NCT Top Corner Drop (Case NTCl) Rigid-Body Acceleration Time-History

• NAC International 2.6-33

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.6 Cold/Hard NCT Side Drop (Case NSl) Impact Limiter Deformation Figure 2.6 Cold/Hard NCT Side Drop (Case NSl) Rigid-Body Acceleration Time-History NAC International 2.6-34

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.6 Cold/Hard NCT Side Drop (Case NSl) OP Bolt Average Tensile Stress Time-History

• NAC International 2.6-35

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.6 SIA 1/8-Symmetry Finite Element Models NAC International 2.6-36

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.6.8 Corner Drop In accordance with 10 CFR 71. 71 (c)(8), fiberboard, wood, or fissile material rectangular packages not exceeding 110 pounds (50 kg) and fiberboard, wood, or fissile material cylindrical packages not exceeding 220 pounds (100 kg) must be subjected to a free drop onto each comer of the package in succession, or in the case of a cylindrical package onto each quarter of each rim, from a height of 1 foot (0.3 m) onto a flat, essentially unyielding, horizontal surface. The package is not a fiberboard, wood, or fissile material package and it weighs more than 220 pounds (100 kg). Therefore, the comer drop test requirements of 10 CFR 71.71(c)(8) are not applicable to the package. 2.6.9 Compression In accordance with 10 CFR 71.7l(c)(9), packages weighing up to 11,000 pounds (5,000 kg) must be subjected to a compressive load, applied uniformly to the top and bottom of the package in a position in which the package would normally be transported, for a period of 24 hours. The compressive load is equal to the greater of the equivalent of: (1) 5 times the weight of the package, and (2) 2 psi (13 kPa) multiplied by the vertically projected area of the package . Although the package gross weight is less than 11,000 pounds (5,000 kg), the lifting attachments located on the OP lid prevent stacking of packages. Furthermore, the package operating procedures do not allow stacking. Therefore, the package is not evaluated for the compression test. 2.6.10 Penetration In accordance with 10 CFR 71.71(c)(l0), the package must be subjected to an impact of the hemispherical end of a vertical steel cylinder of 1.25 inch (3.2 cm) diameter and weighing 13 pounds (6 kg), dropped from a height of 40 inches (1 m) onto the exposed surface of the package that is expected to me most vulnerable to puncture. Per Regulatory Guide 7.8 [2.7], the penetration test is not structurally limiting for large packages without unprotected valves. The OPTIMUS-L package is relatively large and does not have any vulnerable locations on the package surface. Thus, the package need not be evaluated for NCT penetration .

• NAC International 2.6-37

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NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.7 Hypothetical Accident Conditions The package meets the standards specified in 10 CFR 71.5l(a)(2) when subjected to the HAC tests specified in 10 CFR 71.73. In accordance with Regulatory Guide 7.6 [2.13], "design by analysis" is used for the stmctural evaluation of the package. The stmctural evaluation for HAC is based on sequential application of the HAC tests specified in 10 CFR 71.73(c) to detennine the cumulative effect on the package, in accordance with SSR-6, §726 and 10 CFR 71.73(a). As discussed in Section 2.6, no significant package damage results from the NCT tests of IO CFR 71. 71. Thus, the evaluation of the package for the HAC test sequence is performed sta11ing with an undamaged specimen. The package is evaluated for the most unfavorable initial conditions specified in 10 CFR 71.73(b). The HAC load combinations considered in the structural evaluation are developed in accordance with Regulatory Guide 7 .8 [2.5] and summarized in Section 2.1.2.1. The results of the stmctural evaluation show that the package satisfies the applicable allowable stress design criteria of the ASME Code when subjected to the HAC tests of IO CFR 71. 73. A summary of the cumulative package damage resulting from the HAC tests is provided in Section 2.7.8. The predicted package damage is considered in the package thermal, containment, and shielding HAC evaluations. TI1e containment and shielding evaluations of the package show that the cumulative package damage resulting from the RAC test sequence results in no escape of other radioactive material exceeding a total amount of A2 in one week and no external radiation dose rate exceeding 1 mrem/h (IO mSv/h) at 40 in (1 m) from the external surface of the package, in accordance with 10 CFR 71.51(a)(2). 2.7.1 Free Drop In accordance with 10 CFR 71.73(c)(l), the package is subjected to a free drop of 30 feet (9 m)

 "onto a flat, essential~y unyielding, h01izontal su,face, striking in a position for which maximum damage is expected." In accordance with the requirements of Regulatory Guide 7.8 [2.5], the worst-case initial conditions are considered for the RAC free drop test. These initial conditions include ambient temperatures that range from -40°F (-40°C) with zero decay heat and zero insolation (i.e., "cold" thermal condition) to an ambient temperature of 100°F

• NAC International 2.7-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A A drop loads analysis is performed to predict the acceleration loading on the CCV and the damage to the packaging for seven (7) different HAC free drop impact orientations, including a bottom end drop, top end drop, bottom corner drop, top corner drop, horizontal side drop, 10-degree bottom end oblique drop, and 10-degree top end oblique drop. The HAC free drop conditions evaluated are summarized in Table 2.7-1 and shown in Figure 2.7-1. For each HAC free drop impact orientation considered, upper bound and lower bound analyses are performed. The upper-bound analyses are performed using the impact limiter material upper-bound strength properties for the "cold" thermal condition temperature of -40°F (-40°C). This case, which is referred to as the "cold/hard" case, generally produces the maximum peak rigid-body package accelerations. The lower-bound analyses are performed using the impact limiter material lower-bound strength properties for the "hot" thermal condition ambient temperature of 100°F (38°C), maximum decay heat, and insolation. This case, which is referred to as the "hot/soft" case, generally produces the maximum impact limiter deformation and the lowest peak rigid body package acceleration, are evaluated to assure that the impact limiter will not "bottom-out," causing large impact loads to be imparted to the package. For all HAC free drop cases evaluated, the maximum content weight of 3,500 pounds (1,587 kg) is used. Although lower content weights can produce higher package accelerations, the resulting drop forces (equal to the mass times the acceleration) and packaging stresses are generally lower. The LS-DYNA explicit dynamic finite element code, which is described in Section 2.12.2.2, is used for the drop loads analysis. In addition to determining the package accelerations and damage, this analysis demonstrates the structural adequacy of the OP closure bolts for the HAC free drop tests. The maximum tensile stresses in the OP closure bolts are shown to satisfy the applicable allowable stress design criteria. Furthermore, the maximum crush depth of the OP assembly polyurethane foam due to each HAC free drop is less than the allowable crush depth. The drop loads analysis of the package for each HAC free drop impact orientation are discussed in the following sections. Detailed stress analyses of the CCV for HAC free drop loading are performed using linear-elastic equivalent static finite element analysis methods. The ANSYS computer program, which is described in Section 2.12.2.1, is used for this analysis. Stresses in the I-inch and 21/4-inch SIAs are not evaluated for HAC free drop loading because they are not credited for shielding under HAC. Bounding equivalent-static acceleration design loads are applied to the finite element models for each HAC free drop orientation. The bounding equivalent-static acceleration design loads are determined by multiplying the packaging peak rigid body accelerations for each HAC free drop condition by a DLF to account for possible dynamic amplification within the packaging. A bounding DLF of 1.16 is derived in Section 2.12.4 based on the dynamic response of the CCV assembly to the various NCT and HAC free drop impact orientations. NAC International 2.7-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A In accordance with Regulatory Guide 7.8 [2.5], HAC free drop loads are evaluated in combination with internal pressure (MNOP), and fabrication stresses. MNOP of 100 psi (690 kPa) gauge is evaluated in combination with the HAC free drop loads. The only significant fabrication and assembly stresses in the packaging are those resulting from closure bolt preload. Upper-bound bolt preloads are conservatively used for the CCV stress evaluation. Thermally induced stress intensities are classified as secondary stresses, which do not require evaluation under Service Level D accident conditions in accordance with the ASME Code since they are self-limiting. The maximum stresses in the CCV due to each HAC free drop are calculated and shown to satisfy the applicable allowable stress design criteria from Table 2.1-3. In addition, the compressive stresses in the CCV shell due to HAC free drop loading are evaluated in accordance with ASME Code Case N-284-1 and shown to satisfy the applicable buckling design criteria. Buckling of the CCV shell is evaluated for the HAC bottom end drop impact orientation only because the HAC end drop results in the highest overall acceleration loading and the bottom end impact results in the highest axial compressive stresses in the CCV shell. The results of the HAC bottom end drop buckling evaluation bound all other HAC free drop impact orientations. The packaging stress and buckling analyses for each HAC impact orientation are discussed further in

• the following sections.

The results of the HAC free drop structural evaluation demonstrate that the packaging satisfies the applicable HAC allowable stress design criteria. HAC free drop loading does not cause any significant permanent deformation of the packaging, except for the OP assembly, nor does it substantially reduce the effectiveness of the packaging. The evaluation shows that, under HAC free drop loading, the containment seal is maintained, and there is no loss or dispersal of radioactive contents. The damage to the OP assembly resulting from HAC free drop loading is considered in the HAC shielding evaluation, which demonstrates that the external dose rate limit requirement of 10 CFR 71.5 l(a)(2) are satisfied. Therefore, the package complies with the requirements of 10 CFR 71.5l(a)(2) when subjected to the HAC free drop test of 10 CFR 71.73(c)(l) .

• NAC International 2.7-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.7 Summary of HAC Free Dro Cases Evaluated NAC International 2.7-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Cases HBE1-HBE2 Cases HTE 1-HTE2 Cases HS1-HS2 HAC Bottom End Drop HAC Top End Drop HAC Side Drop Cases HBC1-HBC2 Cases HTC1-HTC2 HAC Bottom Comer Drop HAC Top Comer Drop Case HBO1 Case HTO1 HAC 10° Bottom Oblique HAC 10° Top Oblique Drop (Slapdown) Drop (Slapdown) Figure 2.7 HAC Free Drop Impact Orientations

• NAC International 2.7-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.7.1.1 End Drop The package is evaluated for a 30-foot (9 m) HAC end drop, occurring on either the top or bottom end of the package, considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.5]. Explicit dynamic drop analyses are performed to predict the rigid-body acceleration loading on the CCV and the damage to the OP resulting from the HAC end drops, as discussed in Section 2. 7 .1.1. l. Linear-elastic static analyses are performed to determine the stresses in the CCV resulting from the HAC end drops, as discussed in Section 2. 7 .1.1.2. Finally, the CCV shell is evaluated for potential buckling failure resulting from the HAC end drops in accordance with ASME Code Case N-284-1 [2.7], as discussed in Section 2.7.1.1.3. 2.7.1.1.1 Drop Loads Evaluation Drop analyses of the package for the HAC end drop orientations are performed using LS-DYNA, an explicit dynamic finite element code, and the same 3-D half symmetry finite element model used for the NCT end drop evaluation, as described in Section 2.6.7.1. As discussed in Section 2.7.1, HAC end drop analyses are performed for both bottom and top end drop orientations, considering "cold/hard" and "hot/soft" foam properties each orientation. NAC International 2.7-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The stresses in the CCV due to HAC top end drop loads are determined using the same 3-D half-symmetry finite element model used for the NCT end drop stress evaluation, as described in Section 2.6.7.2. The HAC top end drop loading is applied to the finite element model in the same manner as the loads for the NCT end drop stress analysis, as described in Section 2.6.7.2, but scaled based on the HAC end drop equivalent static loads discussed above. In accordance with Regulatory Guide 7.8 [2.5], HAC end drop loads are evaluated in combination with MNOP and fabrication stresses. The only significant fabrication stresses in the package are those resulting from closure bolt preload. An upper-bound preload of 27.9 kip ( 124 kN) is applied to each CCV closure bolt using AN SYS pretension elements (PRETS 179). MNOP of 100 psi (690 kPa) gauge is applied to the inner surfaces of the CCV containment boundary. Thermally-induced stress intensities, such as those resulting from the NCT heat thermal gradient, are classified as secondary in accordance with the ASME Code since they are self-limiting, and do not require evaluation for Service Level D conditions (i.e., HAC) in accordance with the ASME Code. NAC International 2.7-7

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The maximum stresses in the CCV components due to the HAC bottom end and top end drops, along with the corresponding allowable stresses and minimum design margins, are summarized in Table 2.7-3. The minimum design margin is +0.35 for primary membrane plus bending stress intensity (Pm+Pb) at the bottom end of the CCV shell (section C6 in Figure 2.1-1) due to the HAC bottom end drop. The minimum design margin in the CCV closure bolt is +0.67 for average tensile stress due to the HAC top end drop. The minimum design margin for membrane plug bending stress intensity (Pm+Pb) at the center of the CCV bottom support plate for the HAC bottom end drop is +0.37. The results of the HAC end drop stress evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress design criteria of the ASME Code. 2.7.1.1.3 CCV Shell Buckling Evaluation Buckling evaluations of the CCV shell are performed for the maximum HAC end drop in accordance with the requirements of ASME Code Case N-284-1 [2.7]. The maximum compressive stresses and shear stresses near the mid-length of the CCV shell (i.e., Section C9 in Figure 2.1-1) are used for the CCV shell buckling evaluation. As discussed in Section 2.1.2.3, elastic and inelastic buckling interaction ratios are calculated based on the HAC allowable buckling stresses shown in Table 2.1-7, which include a factor of safety of 1.34. The maximum interaction ratios must not exceed 1.0. The maximum axial compressive stress at the mid-length the CCV shell (i.e., Section C9 in Figure 2.1-1) results from the HAC bottom end impact because the CCV shell supports its own mass plus the entire mass of the CCV body bolt flange and CCV lid (2.2 kips) for the bottom end drop, whereas it only supports its own mass plus the mass of the CCV body bottom plate (1.0 kips) for a top end drop. For the CCV shell buckling evaluation, the bounding equivalent static acceleration load is determined based on a lower bound content weight of 500 pounds as opposed to the maximum content weight of 3,500 pounds. The peak rigid-body acceleration load for the cold/hard HAC

• NAC International 2.7-8

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A bottom end drop with the lighter content weight is 368.7g. Applying a bounding DLF of 1.16, as The CCV shell stresses due to the HAC bottom end drop are combined with the stresses at the mid-length of the CCV shell (i.e., Section C9 in Figure 2.1-1) resulting from NCT increased external pressure and NCT heat. For increased external pressure loading the internal pressure is

                                                               . The maximum combined stresses used for the CCV shell HAC end drop buckling analysis are summarized in Table 2.7-4.

The allowable buckling stresses and elastic and inelastic buckling interaction ratios for the HAC bottom end drop buckling evaluation are summarized in Table 2.7-5. The highest buckling interaction ratio in the CCV shell for the HAC bottom end drop is 0.58 for inelastic buckling due to axial compression, which is less than the limit of 1.0. Therefore, the minimum margin of safety against buckling of the CCV shell for the HAC bottom end drop is +o. 72. The results demonstrate that the CCV shell satisfies the buckling design criteria of ASME Code Case N-284-1 for the HAC bottom end drop .

• NAC International 2.7-9

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.7 HAC End Drop Impact Limiter Analysis Results NAC International 2.7-10

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.7 CCV Shell HAC End Drop Buckling Evaluation Stress Summary Table 2.7 CCV Shell Buckling Evaluation Results for HAC Bottom End Drop

• NAC International 2.7-11

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 HAC Hot/Soft Bottom End Drop (Case HBE2) OP Deformation NAC International 2.7-12

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 HAC Hot/Soft Top End Drop (Case HTE2) OP Deformation

• NAC International 2.7-13

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 HAC Cold/Hard Bottom End Drop (Case HBEl) Rigid-Body Acceleration Time-History Figure 2.7 HAC Cold/Hard Top End Drop (Case HTEl) Rigid-Body Acceleration Time-History NAC International 2.7-14

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 HAC Cold/Hard Top End Drop (Case HTEl)

• OP Bolt Average Tensile Stress Time-History
• NAC International 2.7-15

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.7.1.2 Side Drop The package is evaluated for a 30-foot (9 m) HAC side drop considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.5]. Explicit dynamic drop analyses are performed to predict the rigid-body acceleration loading on the CCV and the damage to the OP resulting from the HAC side drop, as discussed in Section 2. 7 .1.2.1. Linear-elastic static analyses are performed to determine the stresses in the CCV resulting from the HAC side drop, as discussed in Section 2. 7. l .2.2. 2.7.1.2.1 Drop Loads Evaluation Drop analyses of the package for the HAC side drop orientation are performed using LS-DYNA, an explicit dynamic finite element code, and the same 3-D half symmetry finite element model used for the NCT side drop evaluation, described in Section 2.6.7.1. As discussed in Section 2.7.1, HAC side drop analyses are performed for both "cold/hard" and "hot/soft" foam properties. history analysis is performed for a duration that is sufficient to capture the primary impact.

• resulting from the hot/soft HAC side drop (Case HS2) is shown in Figure 2.7-7.

is characterized as a half-sine pulse with an approximate period of 8E-3 seconds. The maximum average tensile stress in the OP closure bolts resulting from each HAC side drop case evaluated are also summarized in Table 2.7-6 .

                                        . Figure 2.7-9 shows a time-history plot of the average tensile stress in each of the OP closure bolts for the cold/hard HAC side drop (Case HSI). The

• NAC International 2.7-16

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A maximum bolt tensile stresses occur in bolt #4, which is located 90-degrees from the impact. The tensile stresses in the other closure bolts are significantly lower Therefore, the OP closure bolt stresses resulting from the HAC side drop satisfy the applicable allowable stress design criteria. 2.7.1.2.2 CCV Stress Evaluation The stresses in the CCV resulting from the HAC side drop are determined using equivalent-static linear-elastic finite element analysis methods the cold/hard HAC side drop is 416.0g. The stresses in the CCV due to HAC side drop loading are determined using the same 3-D half-symmetry finite element model used for the NCT side drop stress evaluation, as described in

• Section 2.6.7.2. The HAC side drop loading is applied to the finite element model in the same manner as the loads for the NCT side drop stress analysis, as described in Section 2.6.7.2, but scaled based on the HAC side drop equivalent static load discussed above.

As discussed in Section 2. 7 .1, bolt pre load and MNOP are evaluated in combination with the HAC side drop loading. Upper-bound preloads of27.9 kip (124 kN) per CCV closure bolt are applied to the model using AN SYS pretension elements (PRETS 179). MNOP of 100 psi (690 kPa) gauge is applied to the inner surfaces of the CCV containment boundary. On the impacted side of the CCV cavity, this pressure load is added to the applied pressure that accounts for the payload inertial load due to the HAC side drop acceleration. Thermally-induced stress intensities, such as those resulting from the NCT heat thermal gradient, are classified as secondary in accordance with the ASME Code since they are self-limiting, and do not require evaluation for Service Level D conditions (i.e., HAC) in accordance with the ASME Code. The maximum stress intensities in the CCV components due to the HAC side drop, along with the corresponding allowable stress intensities and minimum design margins, are summarized in Table 2.7-7. The results show that the minimum design margin in the CCV is +0.12 for average tensile stress in the CCV closure bolt. The lowest design margin in the CCV body and lid for the HAC side drop is +0.25 for primary membrane plus bending stress intensity (Pm+Pb) at the top

• end of the CCV shell (section C12 in Figure 2.1-1). The results of the HAC side drop stress NAC International 2.7-17

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress design criteria of the ASME Code. NAC International 2.7-18

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 2.7-19

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Hot/Soft HAC Side Drop (Case HS2) OP Deformation Figure 2.7 Cold/Hard HAC Side Drop (Case HSl) Rigid-Body Acceleration Time-History NAC International 2.7-20

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cold/Hard HAC Side Drop (Case HSl) OP Bolt Average Tensile Stress Time-History

• NAC International 2.7-21

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.7.1.3 Corner Drop The package is evaluated for a 30-foot (9 m) HAC comer drop, occurring on either the top or bottom end of the package, considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.5]. Explicit dynamic drop analyses are performed to predict the rigid-body acceleration loading on the CCV and the damage to the OP resulting from the HAC comer drops, as discussed in Section 2.7.1.1.1. The stress and buckling evaluations of the CCV for the HAC comer drops are discussed in Section 2.7.1.1.2 and Section 2.7.1.1.3, respectively. 2.7.1.3.1 Drop Loads Evaluation The structural evaluation of the packaging for the HAC comer drop orientations is performed using LS-DYNA, an explicit dynamic finite element code, and the 3-D half symmetry finite element model used for the NCT comer drop evaluations, described in Section 2.6. 7 .1. As discussed in Section 2.7.1, RAC comer drop analyses are performed for both bottom and top end drop orientations, considering "cold/hard" and "hot/soft" foam propel1ies each orientation. Therefore, the impact limiter will not experience excessive deformation that would allow the CCV to "bottom-out" under the most severe RAC comer drop conditions. The OP deformation resulting from the hot/soft HAC bottom and top comer drops (Cases HBC2 andHTC2) are shown in Figure 2.7-10 and Figure 2.7-11, respectively. acceleration time-history curves for the cold/hard RAC bottom and top comer drops (Cases HBC! and HTC!) are shown in Figure 2.7-12 and Figure 2.7-13, respectively. The maximum tensile forces developed in the OP closm-e bolts are also summarized in Table 2.7-8. NAC International 2.7-22

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• The stresses in the CCV due to HAC top corner drop loads are determined using the same 3-D half-symmetry finite element model used for the NCT end drop stress evaluation, as described in Section 2.6.7.2. The HAC top corner drop loading is applied to the finite element model in the same manner as the loads for the NCT top corner drop stress analysis, as described in Section 2.6.7.2, but scaled based the ratio of the HAC-to-NCT top corner drop equivalent static acceleration loads.

In accordance with Regulatory Guide 7.8 [2.5], HAC top corner drop loads are evaluated in combination with MNOP and fabrication stresses. The only significant fabrication stresses in the package are those resulting from closure bolt preload. An upper-bound preload of 27.9 kip (124 kN) is applied to each CCV closure bolt using ANSYS pretension elements (PRETSI 79). MNOP of 100 psi (690 kPa) gauge is applied to the inner surfaces of the CCV containment boundary. Thermally-induced stress intensities, such as those resulting from the NCT heat thermal gradient, are classified as secondary in accordance with the ASME Code since they are self-limiting, and do not require evaluation for Service Level D conditions (i.e., HAC) in accordance with the ASME Code. The maximum stresses in the CCV components due to the HAC top corner drop, along with the

• corresponding allowable stresses and minimum design margins, are summarized in Table 2.7-9 .

The results show that the minimum design margin in the CCV is +0.62 for average tensile stress NAC International 2.7-23

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A in the CCV closure bolt. The lowest design margin in the CCV body and lid for the HAC top comer drop is +2.82 for primary membrane plus bending stress intensity (Pm+Pb) near the top end of the CCV shell (section ClO in Figure 2.1-1). The results of the HAC top comer drop stress evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress 2.7.1.3.3 CCV Shell Buckling Evaluation The buckling evaluation of the CCV shell presented in Section 2. 7 .1.1.3 for the bounding cold/hard/light HAC bottom end drop load shows that the margin of safety against buckling is large (i.e., +0.72). As shown in Table 2.7-8, the cold/hard HAC bottom corner drop results in a peak rigid-body acceleration load of 118.lg, which resolves into a 98g axial load and an 66g transverse load. The longitudinal acceleration load from the cold/hard HAC bottom corner drop is less than 27% of the peak rigid-body acceleration load from the cold/hard/light HAC bottom end drop. Therefore, it is concluded that the CCV shell buckling for the HAC comer drop is bounded by that of the HAC end drop. NAC International 2.7-24

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• I * .

_____, ~*--.,*....*----- I

• Table 2.7 HAC Top Corner Drop Stress Summary
• NAC International 2.7-25

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 Hot/Soft HAC Bottom Corner Drop (Case HBC2) OP Deformation NAC International 2.7-26

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 Hot/ Soft HAC Top Corner Drop (Case HTC2) OP Deformation

• NAC International 2.7-27

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cold/Hard HAC Bottom Corner Drop (Case HBCl) Rigid-Body Acceleration Time-History Figure 2.7 Cold/Hard HAC Top Corner Drop (Case HTCl) Rigid-Body Acceleration Time-History NAC International 2.7-28

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cold/Hard HAC Top Corner Drop (Case HTCl) OP Bolt Average Tensile Stress Time-History

• NAC International 2.7-29

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.7.1.4 Oblique Drop The package is evaluated for a 30-foot (9 m) HAC oblique drop considering the worst-case initial conditions in accordance with Regulatory Guide 7.8 [2.5]. The stmctural evaluation of the package for the HAC oblique drop test is described in the following sections. 2.7.1.4.1 Drop Loads Evaluation The stmctural evaluation of the packaging for the HAC oblique drop orientations is performed using the LS-DYNA finite element code and the 3-D half symmetry fmite element model described in Section 2.6.7.1. As discussed in Section 2.7.1, HAC oblique drop analyses are pe1formed for both bottom and top end drop orientations, considering only the "cold/hard" material condition. The evaluation demonstrates that the package deformations, accelerations, and OP closure bolt stresses are bounded by those calculated for the cold/hard HAC side drop. An initial oblique drop impact angle of 10° from horizontal is evaluated to determine the effect on the package accelerations. The maximum foam compression, CCV peak rigid-body accelerations, and OP closure bolt average tensile stresses resulting from each HAC oblique drop test case evaluated are summarized in Table 2.7-10. The packaging defonnations resulting from the cold/hard HAC 10° bottom oblique drop (Case HBOl) and cold/hard HAC 10° top oblique drop (Case HTOl) are sUllllllarized in Table 2.7-10 and shown in Figure 2.7-15 and Figure 2.7-16, respectively. The rigid-body acceleration time-histo1y curves for the cold/hard HAC 10° bottom oblique drop (Case HBOI) and cold/hard HAC 10° top oblique drop (Case HTOl) are shown in Figure 2.7-17 and Figure 2. 7-18, respectively. These plots show that the highest peak rigid-body accelerations occur during the primaiy impact rather than the secondaiy impact, as is expected for a package NAC International 2.7-30

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A OP closure bolts are shown to satisfy the applicable structural design criteria for the bounding HAC side drop. Thus, the HAC oblique drop test will not result in failure of any OP closure bolts. A separate HAC oblique drop impact analysis for the cold/hard HAC 10° bottom oblique drop is performed to evaluate the effect of delayed impacts between the top end of contents and the CCV lid and between the top end of the CCV and the OP lid. This drop orientation is considered

• because the rotation of the package following the primary impact thrusts the contents and CCV toward the top end of the package and the resulting delayed impacts between the contents, CCV, and OP lid are expected to produce the highest tensile stresses in the CCV and OP closure bolts.

The results show the maximum tensile stress in the CCV closure bolts is low and the maximum tensile stresses in the OP closure bolts due to the delayed impacts are bounded by that resulting from the slapdown impact. These results also confirm that the maximum bolt stresses resulting from the HAC oblique drop are bounded by those resulting from the HAC side drop. 2.7.1.4.2 CCV Stress Evaluation The results presented in Section 2.7.1.4.1 show the peak rigid-body acceleration loads resulting from the cold/hard HAC oblique drop are less than 40% of those resulting from the cold/hard HAC side drop. Therefore, based on the significant difference in the peak rigid-body acceleration loads, it is concluded the stresses in the packaging due to the HAC oblique drop will be bounded by those due to the HAC side drop . NAC International 2.7-31

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 2.7-32

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cold/Hard HAC 10° Bottom Oblique Drop (Case HBOl) OP Deformations Figure 2.7 Cold/Hard HAC 10° Top End Oblique Drop (Case HTOl) OP Deformation

• NAC International 2.7-33

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cold/Hard HAC 10° Bottom End Oblique Drop (Case HBOl) Rigid-Body Acceleration Time-History Figure 2.7 Cold/Hard HAC 10° Top End Oblique Drop (Case HTOl) Rigid-Body Acceleration Time-History NAC International 2.7-34

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.7.1.5 Summary of Results The structural evaluation of the packaging for the HAC free drop test of 10 CFR 71.73(c)(l) shows that the applicable structural design criteria is satisfied for all cases analyzed. The HAC free drop does not cause any significant permanent deformation in the CCV. The only significant package damage resulting from the HAC free drop occurs in the OP outer shells and foam. The OP damage resulting from each HAC free drop orientation is described as follows: HAC End Drop: The deformed shape of the OP assembly following the hot/soft HAC bottom and top end drops (Cases HBE2 and HTE2) are shown in Figure 2.7-2 and Figure 2.7-3, respectively. The OP deformation due to the HAC end drops is primarily from "inside-out" crush of the OP assembly (i.e., the piston action from the CCV assembly results in elongation of the CCV cavity). As such, the extent of damage observed from the external surfaces of the package will be minimal, consisting of localized buckling or bulging of portions of the OP outer shells. The hot/soft HAC bottom end drop crushes the OP bottom end foam and outer shell to a depth of 3 .3 8 inches (8.6 cm), or 42% of the bottom end foam thickness, whereas the hot/soft HAC top end drop

• crushes the OP top end foam and outer shell to a depth of 3.31 inches (8.4 cm), or 38% of the top end foam thickness.

The maximum stresses in the CCV components due to the HAC bottom end and top end drops, along with the corresponding allowable stresses and minimum design margins, are summarized in Table 2.7-3. The minimum design margin is +0.35 for primary membrane plus bending stress intensity (Pm+Pb) at the bottom end of the CCV shell (section C6 in Figure 2.1-1) due to the HAC bottom end drop. The minimum design margin in the CCV closure bolt is +0.67 for average tensile stress due to the HAC top end drop. The minimum design margin for membrane plug bending stress intensity (Pm+Pb) at the center of the CCV bottom support plate for the HAC bottom end drop is +0.37. The results of the HAC end drop stress evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress design criteria of the ASME Code. The results also show that the separation between the CCV lid and bolting flange at the location of the containment O-ring is minimal and that the CCV containment seal will be maintained under HAC end drop loading. The allowable buckling stresses and elastic and inelastic buckling interaction ratios for the HAC bottom end drop buckling evaluation are summarized in Table 2.7-5. The highest buckling interaction ratio in the CCV shell for the HAC bottom end drop is 0.58 for inelastic buckling due to axial compression, which is less than the limit of 1.0. Therefore, the minimum margin of

• safety against buckling of the CCV shell for the HAC bottom end drop is +0.72. The results NAC International 2.7-35

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A demonstrate that the CCV shell satisfies the buckling design criteria of ASME Code Case N-284-1 for the HAC bottom end drop. HAC Side Drop: The deformed shape of the OP assembly following the hot/soft HAC side drop (Case HS2) is shown in Figure 2.7-7. The deformation of the OP due to the HAC side drop is from a combination of "inside-out" (i.e., ovalling of the OP inner shells) and "outside-in" (i.e., flattening of the OP outer surface) crush of the OP assembly. As a result, the total extent of damage to the OP following an HAC side drop will not be evident from the package exterior. The hot/soft HAC side drop results in a maximum permanent deformation of the OP side foam and outer shell of 2.98 inches (7.6 cm), or 66% of the OP lid side foam thickness. The maximum stress intensities in the CCV components due to the HAC side drop, along with the corresponding allowable stress intensities and minimum design margins, are summarized in Table 2.7-7. The results show that the minimum design margin in the CCV is +0.12 for average tensile stress in the CCV closure bolt. The lowest design margin in the CCV body and lid for the HAC side drop is +0.25 for primary membrane plus bending stress intensity (Pm+Pb) at the top end of the CCV shell (section C12 in Figure 2.1-1). The results of the HAC side drop stress evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress design criteria of the ASME Code. The results also show that the separation between the CCV lid and bolting flange at the location of the containment O-ring is minimal and that the CCV containment seal will be maintained under HAC side drop loading. HAC Corner Drop: The deformed shape of the OP assembly following the hot/soft HAC bottom and top comer drops (Cases HBC2 and HTC2) are shown in Figure 2.7-10 and Figure 2.7-11, respectively. The OP deformation due to the HAC comer drops is primarily from "outside-in" crush of the OP assembly (i.e., flattening of the OP outer surface.) The hot/soft HAC bottom comer drop crushes the OP base comer foam and outer shell to a depth of 8.47 inches (21.5 cm), or 76% of the OP base comer foam thickness, whereas the hot/soft HAC top comer drop crushes the OP lid comer foam and outer shell to a depth of 8.12 inches (20.6 cm), or 78% of the OP lid comer foam thickness. The maximum stresses in the CCV components due to the HAC top comer drop, along with the corresponding allowable stresses and minimum design margins, are summarized in Table 2.7-9. The results show that the minimum design margin in the CCV is +0.62 for average tensile stress in the CCV closure bolt. The lowest design margin in the CCV body and lid for the HAC top comer drop is +2.82 for primary membrane plus bending stress intensity (Pm+Pb) near the top

• NAC International 2.7-36

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A end of the CCV shell (section C 10 in Figure 2.1-1 ). The results of the HAC top corner drop stress evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress design criteria of the ASME Code. The results also show that the separation between the CCV lid and bolting flange at the location of the containment O-ring is minimal and that the CCV containment seal will be maintained under HAC top corner drop loading. HAC Oblique Drop: The results of the HAC oblique drop analysis show that the damage to the OP assembly and the package rigid body acceleration loads are bounded by the HAC end, side, and corner drops. 2.7.2 Crush The crush test of 10 CFR 71.73(c)(2) is required only when the specimen has a mass not greater than 1,100 pounds (500 kg), an overall density not greater than 62.4 lb/ft3 (1,000 kg/m 3) based on external dimensions, and radioactive contents greater than 1,000 A2 not as a special form radioactive material. The OPTIMUS-L package weighs more than 1,100 pounds (500 kg). Therefore, the crush test is not required. 2.7.3 Puncture

• In accordance with 10 CFR 71.73(c)(3), the package is evaluated for "afree drop through a distance of 1 m (40 in) in a position for which maximum damage is expected, onto the upper end of a solid, vertical, cylindrical, mild steel bar, mounted on an essentially unyielding horizontal surface. The bar must be 15 cm (6 in) in diameter, with the top horizontal and its edge rounded to a radius of not more than 6 mm (0.25 in), and a length as to cause maximum damage to the package, but not less than 20 cm (8 in) long." The puncture drop test is performed in sequence following the HAC free drop test in accordance with 10 CFR 71.73(a). Therefore, the package damage resulting from the HAC free drop is considered in the HAC puncture drop evaluation.

The maximum extent of damage sustained by the impact limiter for each HAC free drop orientation is discussed in Section 2. 7 .1.5. In accordance with the requirements of Regulatory Guide 7.8 [2.5], the worst-case initial conditions are considered for the HAC puncture test. For the HAC puncture analysis, the "hot" thermal condition (i.e., an ambient temperature of 100°F (38°C) with maximum decay heat and insolation) is the worst case since it results in the highest package temperatures, the lowest crush strength of the impact limiter foam, and maximum damage to the packaging. The "cold" thermal condition (i.e., an ambient temperature of -40°F (-40°C) with zero decay heat and no insolation), for which the package temperatures are lowest and the foam crush strength is highest, are not evaluated since the packaging material strength properties are significantly higher than under NAC International 2.7-37

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A "hot" thermal conditions and there is less potential for the OP outer shells to be perforated or for the CCV to "bottom out" on the puncture bar. The primary interest for the HAC puncture test is damage to the OP lid that could expose the CCV top end to the subsequent HAC thermal test. In addition, potential plastic deformation of the CCV shell resulting from a side puncture impact is of interest. Therefore, the packaging is evaluated for three (3) different HAC puncture impact cases, as shown in Figure 2.7-19; (1) hot/soft HAC top end center impact (Case PTEl), (2) hot/soft HAC top end off-center impact (Case PTE2), and (3) hot/soft HAC side impact (Case PS 1). All HAC puncture impact orientations position the package center of gravity directly above the impacted surface of the puncture bar to maximize the impact energy imparted to the packaging for maximum packaging damage. All HAC puncture impact cases are evaluated for the maximum allowable content weight of 3,500 pounds (1,587 kg), which includes the weight of the CCV bottom support plate. The HAC puncture conditions evaluated are summarized in Table 2. 7-11. The HAC puncture evaluations are performed using the 3-D half-symmetry LS-DYNA explicit dynamic finite element model described in Section 2.6.7.1. The CCV components are modeled using plastic material properties and the contents are modeled as a "soft" elastic cylinder to maximize the potential damage to the CCV. The puncture pin is conservatively modeled as a rigid-body using the dimensions of the regulation. Coupled analyses are performed to determine the cumulative damage resulting from the HAC free drop and HAC puncture test. For the hot/soft HAC top end center and off-center impacts (Cases PTEl and PTE2), the puncture impact is preceded by the hot/soft HAC top end free drop and for the hot/soft HAC side impact (Case PSl) the puncture impact is preceded by the hot/soft HAC side free drop. The results of the HAC puncture analyses are as follows: Top End Center Impact CCV peak rigid-body acceleration and CCV closure bolt maximum average tensile stress resulting from the puncture impact are significantly lower than those resulting from the preceding HAC top end drop. Therefore, the extent of package damage resulting from the top NAC International 2.7-38

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A end center impact is limited to local deformation (i.e., denting) of the OP lid outer shell and end foam. acceleration and CCV closure bolt maximum average tensile stress resulting from the puncture impact are significantly lower than those resulting from the preceding HAC top end drop. Therefore, the extent of package damage resulting from the top end off-center impact is limited to local deformation (i.e., denting) of the OP lid outer shell and end foam . acceleration and CCV closure bolt maximum average tensile stress resulting from the puncture impact are significantly lower than those resulting from the preceding HAC side drop. Therefore, the extent of package damage resulting from the side impact is limited to local deformation (i.e., denting) of the OP base outer shell and side foam and minimal plastic deformation of the CCV shell.

• NAC International 2.7-39

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Case PTE1 CasePTE2 Case PS1 Top Center Puncture Top Oblique Puncture Side Puncture Figure 2.7 HAC Puncture Drop Orientations NAC International 2.7-40

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cumulative OP Deformation-Hot/Soft HAC Top Center Puncture (Case PTEl)

• NAC International 2.7-41

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cumulative OP Deformation - Hot/Soft HAC Top Off-Center Puncture (Case PTE2) NAC International 2.7-42

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 2.7 Cumulative OP Deformation - Hot/Soft HAC Side Puncture (Case PSl)

• NAC International 2.7-43

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.7.4 Thermal In accordance with 10 CPR 71.73(c)(4), the package is designed to withstand the 30-minute fire with the flame temperature of l,475°F (800°C). This section presents the structural evaluation of the package for the HAC thermal loading. The package temperatures and pressure resulting from the HAC thermal test are discussed in Section 2.7.4.1. Differential thermal expansion between the packaging components due to the HAC thermal loading is discussed in Section 2.7.4.2. The stresses in the packaging components due to the HAC thermal loading are evaluated in Section

2. 7.4.3. Compliance with the applicable structural design criteria and the applicable regulatory performance requirements is discussed in Section 2.7.4.4.

2.7.4.1 Summary of Pressures and Temperatures The CCV is insulated from the full effects of the HAC fire by the OP. The thermal evaluation of the package for the HAC fire shows that, while the outer surface of the OP reaches a peak temperature of approximately 1,473 °F (801 °C) during the HAC fire transient, the peak temperature of the CCV only reaches 361 °F (183°C). The CCV maximum internal pressure during the HAC fire is less than the HAC design pressure of225 psi (1,551 kPa) gauge. 2.7.4.2 Differential Thermal Expansion Stress Differential thermal expansion in the packaging components due to the HAC therrrial loading causes the clearances between the packaging components to increase. The HAC thermal evaluation shows that the temperature of the OP shells is higher than that of the CCV shell during the fire event. Following the fire event, the temperature gradients between the CCV and OP remain bounded by those resulting from NCT heat. Therefore, the differential thermal expansion between the CCV and OP during the HAC fire will be bounded by the results for NCT heat from Section 2.6.1.2. 2.7.4.3 Stress Calculations The stresses in the package resulting from temperature loading are classified as secondary and need not be evaluated for HAC in accordance with the ASME Code. The only significant primary stresses in the packaging resulting from the HAC fire are due to increased internal pressure loading resulting from elevated temperature of the cavity contents and fill gas during the fire transient. As discussed in Section 3.4.3.2, the maximum internal pressure resulting from the HAC fire is 38.9 psi (268 kPa) gauge. A bounding HAC internal pressure load of 225 psi (1,551 kPa) gauge is conservatively used for the CCV stress analysis. NAC International 2.7-44

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The maximum stress intensities in the CCV components and maximum average tensile stress in the CCV closure bolts due to the HAC internal pressure, along with the corresponding allowable stresses and minimum design margins, are summarized in Table 2.7-12. The results show that the minimum design margin in the CCV is +0.60 for average tensile stress in the CCV closure bolt. The lowest design margin in the CCV body and lid for HAC internal pressure is +0.65 for primary membrane plus bending stress intensity (Pm+Pb) at the center of the CCV bottom plate (section Cl in Figure 2.1-1). The results of the HAC internal pressure stress evaluation show that the stresses in the CCV satisfy the applicable HAC allowable stress design criteria of the ASME Code. The results also show that the maximum stresses in the CCV closure bolts due to HAC internal pressure remain well below the bolt material yield strength. Therefore, no inelastic deformation of the CCV closure bolts will result from the HAC thermal test. 2.7.4.4 Comparison with Allowable Stresses The results of the structural evaluation for the HAC thermal test demonstrate the packaging satisfies the applicable HAC allowable stress design criteria. The HAC thermal loading does not cause any significant permanent deformation of the CCV, nor does it substantially reduce the effectiveness of the packaging. The evaluation shows that no inelastic deformation of the CCV closure bolts results from the HAC thermal loading. Thus, containment will be maintained under HAC thermal loading, and there will be no loss or dispersal of radioactive contents. The damage to the impact limiters resulting from HAC free drop loading is considered in the HAC shielding evaluation, which demonstrates that the external dose rate limit requirement of 10 CFR 71.51 (a)(2) are satisfied. Therefore, the package complies with the requirements of 10 CFR 71.5l(a)(2) when subjected to the HAC thermal test of 10 CFR 71.73(c)(4) .

• NAC International 2.7-45

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.7 HAC Pressure Stress Summary NAC International 2.7-46

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.7.5 Immersion - Fissile Material The criticality evaluation presented in Chapter 6 considers the effect of water in-leakage. Thus, the requirement of 10 CFR 71. 73 (c)( 5) do not apply. 2.7.6 Immersion - All Packages In accordance with 10 CFR 71.73(c)(6), an undamaged package is subjected to a water pressure equivalent to immersion under a head of water of at least 50 feet (15 m), or an equivalent external pressure load of21.7 psi (150 kPa) gauge. A 21.7 psi (150 kPa) gauge external pressure load has negligible effects on the CCV and is bounded by the 290 psi (2 MPa) external pressure load evaluated in Section 2. 7. 7. Therefore, no further evaluation is required for this test. 2.7.7 Deep-Water Immersion Test (for Type B Packages Containing more than 105 A2) In accordance with 10 CFR 71.61, at Type B package containing more than 10 5 A2 must be designed so that its undamaged containment system can withstand an external water pressure of 290 psi (2 MPa) for a period of not less than 1 hour without collapse, buckling, or inleakage of water. This section provides the analysis of the package containment system that demonstrates compliance with the deep-water immersion test requirements of 10 CFR 71.61 .

• NAC International 2.7-47

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The maximum stress intensities in the CCV due to the 290 psi (2 MPa) external pressure loading are evaluated using the accident condition allowable stress design criteria of Subsection NB of the ASME B&PV Code. In addition, the maximum stresses in the closure seal region (i.e., closure lid and top ring forging) are limited to the material yield strength to assure that the in-leakage requirements are met. The accident condition allowable stress intensities used for this evaluation are conservatively based on an upper bound temperature of 300°F (l 49°C). As shown in Table 2.7-13, the minimum design margin in the CCV for the deep-water immersion test is +0.32 for membrane plus bending stress intensity at the center of the CCV bottom plate (Section Cl in Figure 2.1-1). The minimum design margin for average tensile stress in the CCV closure bolts is +0.76. Therefore, the CCV meets the allowable stress design criteria for the deep-water immersion test of 10 CFR 71.61. Buckling Evaluation Buckling evaluations of the CCV shell are performed for the deep immersion pressure test in accordance with the requirements of ASME Code Case N-284-1 [2.7]. The maximum compressive stresses and shear stresses near the mid-length of the CCV shell (i.e., Section C9 in Figure 2.1-1) are used for the CCV shell buckling evaluation. As discussed in Section 2.1.2.3, elastic and inelastic buckling interaction ratios are calculated based on the HAC allowable buckling stresses shown in Table 2.1-7, which include a factor of safety of 1.34. The maximum interaction ratios must not exceed 1.0. Using hand calculations, the axial compressive stress, hoop compressive stress, and shear stress at the mid-length of the CCV shell resulting from 290 psig external pressure load are shown to be 2.3 ksi (16 MPa), 4.6 ksi (32 MPa), and 1.2 ksi (8 MPa), respectively. The theoretical buckling values and reduction factors are shown in Table 2.1-6, and the buckling evaluation results are shown in Table 2.7-14. As specified in Code Case N-284-1 [2.7], the applicable factor of safety of 1.34 is used for the HAC conditions. The maximum bucking interaction ratio in the CCV shell for the deep-water immersion test pressure loading is 0.29 for inelastic buckling due to combined hoop compression and shear stresses, which is less than the limit of 1.0. Therefore, the CCV shell meets the buckling design criteria of Code Case N-284-1 for the deep-water immersion test of 10 CFR 71.61. NAC International 2.7-48

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 2.7 Deep Water Immersion Test Stress Summary

• NAC International 2.7-49

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 2.7-50

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

2. 7 .8 Summary of Damage The preceding structural evaluation demonstrates the package satisfies the applicable structural design criteria and the performance requirements for the HAC test sequence of 10 CFR 71.73.

The condition of the package after each test of the HAC sequence, based on the sequential application of the free drop, puncture, and thermal tests, is summarized as follows. HAC Free Drop The HAC free drop of 10 CFR 71.73(c)(l) does not cause any significant permanent deformation in the CCV. No inelastic deformation of the CCV closure bolts results from the HAC free drop test. The only significant package damage resulting from the HAC free drop occurs in the OP assembly, according to its design function. The OP assembly damage resulting from each of the HAC free drop orientations is discussed in Section 2.7.3. The HAC corner drop is shown to cause the greatest extent of damage to the OP. The hot/soft HAC top corner drop results in a maximum crush depth of 8.12 inches (20.6 cm), or 78% of the OP lid corner foam thickness. HAC Puncture The package is subjected to the HAC puncture test of 10 CFR 71.73(c)(3), considering the damage sustained from the HAC free drop of 10 CFR 71.73(c)(l). The damage to the package resulting from the HAC free drop does not affect the package's ability to withstand the HAC puncture. As discussed in Section 2.7.3, the extent of package damage resulting from the HAC puncture test is limited to primarily to local deformation (i.e., denting) of the OP outer shells and foam. The puncture bar will not pierce the OP outer shells. No plastic deformation of the CCV lid and minimal plastic deformation (<l % equivalent plastic strain) of the CCV shell results from the HAC puncture test. HACThermal The package is subjected to the HAC thermal test of 10 CFR 71.73(c)(4), considering the damage sustained from the HAC free drop of 10 CFR 71.73(c)(l) and HAC puncture of 10 CFR 71.73(c)(3). The extent of package damage resulting from the HAC free drop and HAC puncture tests does not affect the package's ability to withstand the HAC thermal test. This is demonstrated by the HAC thermal evaluation, which considers the cumulative package damage resulting from the HAC free drop and HAC puncture tests. The OP assembly thermal relief plugs are designed to fail during the HAC thermal test to allow gases generated by the foam material to escape. The HAC thermal test will cause some charring to the outer portion of the OP foam. However, the foam will provide sufficient thermal protection to prevent the temperatures in the

• CCV from exceeding the temperature limits. The structural evaluation of the packaging for the temperature and pressure loads resulting from the HAC thermal test shows that no additional NAC International 2.7-51

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A damage of the CCV will result from the RAC thermal test. As discussed in Section 2.7.4.3, the CCV bolts satisfy the applicable RAC allowable stress design criteria and will maintain leak-tight containment under the worst-case RAC thermal loading. NAC International 2.7-52

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.8 Accident Conditions for Air Transport of Plutonium Not applicable .

• NAC International 2.8-1

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 2.9 Accident Conditions for Fissile Material Packages for Air Transport Not applicable .

• NAC International 2.9-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.10 Special Form The packaging containment system is leaktight and no credit is taken for special form contents. Therefore, this section is not applicable .

• NAC International 2.10-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.11 Fuel Rods Containment of the radioactive materials is provided by the CCV containment boundary, as defined in Chapter 4 of this SAR. Analyses of the CCV containment boundary for all NCT and HAC demonstrate containment will not be breached. As discussed in Chapter 6 of this SAR, no credit is taken for geometry control provided by fuel rods or other non-fuel components of fuel waste contents of the package. Therefore, no further evaluation of fuel rod integrity is required .

• NAC International 2.11-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.12 Appendices 2.12.1 References [2.1] 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. [2.2] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NF, Supports, 2010 Edition with 2011 Addenda. [2.3] Regulatory Guide 7 .9, Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material, Revision 2, March 2005. [2.4] Interim Staff Guidance - 21 (ISG-21), Use of Computational Modeling Software, U.S. Nuclear Regulatory Commission, Spent Fuel Project Office, April 2006. [2.5] Regulatory Guide 7 .8, Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material, Revision 1, U.S. Nuclear Regulatory Commission, Office of Standards Development, March 1989. [2.6] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 1, Appendix F, Rules for Evaluation ofService Loadings with Level D Service Limits, 2010 Edition with 2011 Addenda. [2.7] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 1, Code Cases: Nuclear Components, Case N-284-1, Metal Containment Shell Buckling Design Methods, Class MC, 2010 Edition with 2011 Addenda. [2.8] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section V, Nondestructive Examination, Current Edition. [2.9] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1, Appendix I, Design Stress Intensity Values, Allowable Stresses, Material Properties, and Design Fatigue Curves, 2010 Edition with 2011 Addenda. [2.1 O] Regulatory Guide 7 .11, Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inch (0.1 m), U.S. Nuclear Regulatory Commission, Office of Standards Development, June 1991. [2.11] Holman, W.R., and Langland, R. T., Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick, NUREG/CR-1815, UCRL-53013, U.S. Nuclear Regulatory Commission, August 1981. [2.12] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section II, Part D, Materials, 2010 Edition with 2011 Addenda. NAC International 2.12-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A [2.13] Regulatory Guide 7.6, Design Criteria for the Structural Analysis ofShipping Cask Containment Vessels, Revision 1, March 1978. [2.14] Fischer, L. E., and Lai, W., Fabrication Criteria for Shipping Containers, NUREG/CR-3854, UCRL-53544, U.S. Nuclear Regulatory Commission, March 1985. [2.15] General Plastics Manufacturing Co., Design Guide for Use of LAST-A-FOAM FR-3700 for Crash and Fire Protection of Radioactive Material Shipping Containers, Revision 02.20.12, 2012. [2.16] Parker Hannifin Corporation, Parker O-Ring Handbook, ORD 5700/USA, 2001. [2.17] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section IX, Welding and Brazing Qualifications. Latest Edition. [2.18] ANSI Nl 4.23, Design Basis for Resistance to Shock and Vibration of Radioactive Material Packages Greater Than One Ton in Truck Transport, American National Standards Institute, Inc., New York, 1980. [2.19] Blevins, R. D., Formulas for Natural Frequency and Mode Shape, Van Nostrand Reinhold Company, 1979. [2.20] NUREG/CR-3966, Methods for Impact Analysis ofShipping Containers, UCID-20639,

• U.S. Nuclear Regulatory Commission, November 1987.

[2.21] ANSI N14.6, Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More, American National Standards Institute, Inc., New York, 1993. [2.22] American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section VIII, Division 2, Annex 3.D, Strength Parameters," 2010 Edition with 2011 Addenda. [2.23] Mok, G. C., et al., Stress Analysis of Closure Bolts for Shipping Casks, NUREG/CR-6007, UCRL-ID-110637, U.S. Nuclear Regulatory Commission, April 1992. [2.24] W. C. Young, Roark's Formulas for Stress & Strain, McGraw-Hill Book Company, Sixth Edition. . NAC International 2.12-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 2.12-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 2.12-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.12 Benchmark Comparison of HAC Side Drop Analysis and Test Results

• NAC International 2.12-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2.12.4 Development of Equivalent Static Loads The stresses in the CCV due to NCT and HAC free drop loading are calculated using equivalent-static linear-elastic finite element analyses. The equivalent-static acceleration loads for each NCT and HAC free drop test are equal to the peak rigid body accelerations of the packaging multiplied by a DLF that accounts for possible dynamic amplification within the packaging. The DLF is a function of the general shape of the rigid-body acceleration time-history pulse and the ratio of the duration of the rigid body acceleration time-history to the packaging period (t/T) . NAC International 2.12-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 2.12-2 provides a summary of the DLFs and equivalent static acceleration loads for the NCT and HAC free drop orientations that are considered in the packaging stress analysis. The DLF used for each free drop case taken from Figure 2.12-2 at the corresponding t/T ratio, where the load pulse duration (t) is taken from the rigid-body acceleration time-history curve for the drop case and the corresponding highest natural period (T) is based on the lowest fundamental frequency of the CCV for the drop orientation, as discussed previously. The results show that the DLFs for the NCT and HAC free drops range between 1.11 and 1.16, depending on the t/T ratios. Therefore, for the purpose of the packaging structural analyses, a bounding DLF of 1.16 is conservatively used to calculate the equivalent static accelerations for all free drops .

• NAC International 2.12-7

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A of Free Dro DLFs and E uivalent Static Accelerations NAC International 2.12-8

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 2.12 DLF Curve for Half-Sine Pulse Figure 2.12 CCV Shell Bottom End 1/2-Symmetry Finite Element Model

• NAC International 2.12-9

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Chapter 3 Thermal Evaluation Table of Contents 3 TIIERMALEVALUATION ........................................................................................... 3-1 3.1 Description of Thermal Design ..................................................................................... 3.1-1 3.1.1 Design Features ................................................................................................. 3.1-1 3 .1.2 Content's Decay Heat ....................................................................................... 3 .1-1 3.1.3 Summary Table of Temperatures...................................................................... 3.1-1 3.1.4 Summary Table of Maximum Pressures ........................................................... 3 .1-3 3 .2 Material Properties and Component Specifications ...................................................... 3 .2-1 3.2.1 Material Properties ............................................................................................ 3.2-1 3.2.2 Component Specifications ................................................................................ 3 .2-1 3.3 The1mal 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 ............................................................................. 3.4-6 3.4.5 Accident Conditions for Fissile Material Packages for Air Transport ............. 3.4-6 3.5 Appendix ....................................................................................................................... 3.5-1 3.5.1 References ......................................................................................................... 3.5-1 3.5.2 Sensitivity Analyses of Modeling Parameters .................................................. 3.5-3

• NAC International 3-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Figures Figure 3.3 Package 3-D 1/2-Symmetry Thermal Model for NCT .................................... 3.3-16 Figure 3.3 Expanded View of the CCV with Contents Modeled in 110-Gallon Drum ............................................................................................................... 3.3-17 Figure 3.3 Application of Convection Boundary Conditions for NCT (and Shade) ....... 3.3-18 Figure 3.3 Heat Transfer Coefficients for General Standards (shade) and NCT ............ 3.3-19 Figure 3.3 NCT Heat Temperature Contour Plot- 100W Volumetric Heat Source ...... 3.3-20 Figure 3.4 Package 3-D 1/2-Symmetry Thermal Model for HAC ...................................... 3.4-8 Figure 3.4 Convection Boundary Conditions for HAC ..................................................... 3.4-9 Figure 3.4 Heat Transfer Coefficients for HAC Analyses (Fire) .................................... 3.4-10 Figure 3.4 Heat Transfer Coefficients for HAC Analyses (Post-Fire Cool Down) ........ 3.4-11 Figure 3.4 Charred Polyurethane Foam at End of the Fire ............................................. 3.4-12 Figure 3.4 HAC Fire Temperature Time-Histories (l00W Volumetric Heat Source, Helium Fill Gas, CCV at Top) ........................................................... 3.4-13 Figure 3.4 HAC Fire Temperature Time-Histories (100W Surface Heat Flux, Helium Fill Gas, CCV at Top) ........................................................................ 3.4-13 Figure 3.4 HAC Transient Analysis Temperature Contour Plots (l00W Volumetric Heat Load, Helium Fill Gas, CCV at Top) .................................. 3.4-14 Figure 3.4 HAC Transient Analysis Temperature Contour Plots (100W Surface Figure 3.5-1 Heat Flux, CCV at Top) .................................................................................. 3.4-15

            - Modified Damage HAC Thermal Model.. ....................................................... 3.5-6 NAC International                                     3-ii

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Tables Table 3.1-1 - Summary of Packaging Temperatures for NCT ................................................ 3.1-4 Table 3.1-2 - Summary of Packaging Temperatures for HAC ............................................... 3.1-4 Table 3.1-3 - Summary of Maximum Pressures ..................................................................... 3.1-4 Table 3 .2 Thermal Properties of Stainless Steel ............................................................... 3 .2-2 Table 3.2-2 - Thermal Propert~es o f ~ ..................................................... 3.2-2 Table 3.2-3 - Thermal Properties o f -..................................................... 3.2-2 Table 3.2-4 - Thermal Properties of Dry Air at Standard Pressure ........................................ 3.2-3 Table 3.2-5 - Thermal Properties of Helium Gas at Standard Pressure .................................. 3.2-4 Table 3.2-6 - Temperature Limits of Packaging Components ................................................ 3.2-4 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 forNCT .................................................... 3.3-15 Table 3.4-1 - Maximum Package Temperatures for HAC ...................................................... 3.4-7 Table 3.4-2 - Summary ofHAC Pressures ............................................................................. 3.4-7 Table 3.5-1 - Maximum HAC Package Temperatures vs. CCV Position in OP Cavity ......... 3.5-5 Table 3.5-2 - Maximum HAC Package Temperatures vs. Damage Model ............................ 3.5-5

• NAC International 3-iii

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 3 THERMAL EVALUATION This section summarizes the thermal evaluation of the OPTIMUS-L package. The results of the thermal evaluation demonstrate that the packaging will remain within the applicable thermal limits, demonstrating the package's structural, containment and shielding integrity is not negatively affected during the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) prescribed by 10 CFR 71 .

• NAC International 3-1

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NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 3.1 Description of Thermal Design The OPTIMUS L packaging, shown in Figme 1.1-1, consists of a Cask Containment Vessel (CCV) within an Outer Packaging (OP). Nan-ative descriptions of these components are provided in Section 3 .1.1. 3.1.1 Design Features Containment of the radioactive contents is provided by the CCV. Impact and thermal protection for the CCV is provided by the OP. All details and relevant dimensions of the packaging components are provided in the Licensing Drawings in Appendix 1.3 .3. CCV Design Features The CCV is the inne1most vessel of the packaging, that serves as the primaiy containment boundary of the package The CCV lid is machined to include operating and containment features, such as a port for evacuation and backfill of the cavity with inert gas and 0-ring grooves to

• provide a lealctight seal.

OP Design Features The OP is comprised of a base and lid that f01m an internal cavity inside which the CCV is placed. The OP base and lid are both constmcted of stainless steel shells that are filled with polyurethane foam to provide impact and thermal protection for the CCV. The polyurethane foam components ar

 -           The OP lid is attached to the OP base with stmctural evaluation presented in Chapter 2 shows the OP bolts do not fail during the HAC free drop and HAC puncture tests.

3; 1.2 Content's Decay Heat The total decay heat of the contents is limited to 100 watts. For contents with a total decay heat that exceeds 50 watts the CCV cavity must be filled with helium gas. When the total content heat load does not exceed 50 watts the CCV cavity may be filled with air. 3.1.3 Summary Table of Temperatures Thermal design criteria are specified for the packaging components that are significant to the

• shielding and containment design. All operating temperature limits are based on the NAC International 3.1-1

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A performance requirements of the individual packaging components. These operating temperature limits of the package components that are significant to the shielding and containment design are outlined in Table 3.2 6, including the temperature requirements for maximum temperature on the package accessible surfaces that are specified in I0CFR71.43(g). Note that temperature limit is not required for the waste contents. Normal Conditions of Transport Per the requirements of 10 CFR 71.7l(c)(l), the package is evaluated for NCT. Specifically, steady-state thermal analyses are performed simulating exposure of the package to a 100°F temperature with insolation. As discussed in Section 3.3.1, the package is evaluated for NCT using the maximum allowable total content heat load of 100 watts with helium fill gas inside the CCV cavity and a reduced total content heat load of 50 watts with air filling the CCV cavity. Furthermore, analyses are performed for the 100 watt content heat load using a uniformly distributed volumetric heat source from waste filling a 100 gallon drum and a uniformly distributed surface heat flux on the inside of the CCV cavity. The maximum temperatures of several key packaging components for NCT heat are summarized and compared with their allowable temperatures in Table 3.1-1. As shown in Table 3.1-1, all packaging components remain well below their allowable temperatures for NCT. The results show that the maximum temperature of the CCV assembly is only 213°F (100°C) for NCT, which is much lower than the 800°F (427°C) temperature limit for stainless steel. The results also show that maximum temperature of the CCV O-ring seal, which is of primary interest for NCT, is only 207°F (97°C), compared to the continuous service temperature limit of 400°F (204°C) for Therefore, when exposed to NCT, the structural, containment, and shielding performances of the package will not be adversely affected by the temperatures experienced under these conditions. The maximum volumetric average temperature of the contents/CCV fill gas for NCT heat is 235°F (l 13°C) for the maximum content decay heat of 100 watts with helium fill gas in the CCV cavity and 248°F (120°C) for content decay heat of 50 watts with air in the CCV cavity. These temperatures are used to determine the maximum internal pressure developed inside the CCV for NCT heat, as discussed in Section 3.3.2. The maximum temperature of the accessible surface of the package, when exposed to an ambient temperature of 100°F in still air and shade, is 112°F (45°C). These temperatures are below the 185°P (85°C) exclusive use temperature limit required by 10 CFR 71.43(g). Hypothetical Accident Conditions Per the requirements of 10 CPR 71. 73 (c )(4), the package with TRU waste is evaluated for the HAC thermal test (i.e., HAC fire). As discussed in Section 3.4.3, the package is evaluated for NAC International 3.1-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A the HAC fire using the maximum allowable total content heat load of 100 watts with helium fill gas inside the CCV cavity and a reduced total content heat load of 50 watts with air filling the CCV cavity. Furthermore, analyses are performed for the HAC fire with a 100 watt content heat load using a uniformly distributed volumetric heat source from waste filling a 100 gallon drum and a uniformly distributed surface heat flux on the inside of the CCV cavity. In addition, because the package may be in any orientation during the HAC fire, analyses are performed for the HAC fire with the CCV positioned at both ends of the OP cavity. The maximum temperatures of several key packaging components for the HAC fire are summarized and compared to their allowable temperatures in Table 3.1-2. The polyurethane foam is not required to survive the HAC fire; therefore, it is not included in the summary. The impact limiter shells/plates are only required to maintain confinement of the polyurethane foam; therefore, they are only required to remain below their respective melting temperatures during the HAC fire. As shown in Table 3.1-2, the packaging components remain below their allowable temperatures for the HAC fire. The results show that the CCV assembly reaches a peak temperature of 361 °F (183°C) during the HAC fire transient, which is much lower than the 800°F (427°C) temperature limit for stainless steel. The results also show that the maximum temperature of the CCV O-ring seal only reaches 229°F (110°C) during the HAC fire, compared to the continuous service temperature limit of 400°F (204°C) for fluorocarbon compound (Viton). Therefore, when exposed to HAC, the structural, containment, and shielding performance of the package will not be adversely affected by the temperatures experienced under these conditions. The maximum volumetric average temperature of the contents/CCV fill gas during the HAC fire is 271 °F (133°C) for the maximum content decay heat of 100 watts with helium fill gas in the CCV cavity and 281 °F (139°C) for content decay heat of 50 watts with air in the CCV cavity. These temperatures are used to determine the maximum internal pressure developed inside the CCV for HAC, as discussed in Section 3.4.3.2. 3.1.4 Summary Table of Maximum Pressures The summary of maximum pressures is provided in Table 3.1-3 for NCT and HAC, based on the pressure calculation results presented in Sections 3.3.2 and 3.4.3.2, respectively. The maximum internal pressure temperature for the package containing TRU waste contents is 21.8 psi (150 kPa) gauge for NCT and 36.8 psi (254 kPa) gauge for HAC. The Maximum Normal Operating Pressure (MNOP) of the package is 100 psi (690 kPa) gauge. The maximum HAC pressure calculated in Section 4.3.1 and used in the structural evaluation in Chapter 2 is 225 psi (1,551 kPa) gauge .

• NAC International 3.1-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.1 Summary of Packaging Temperatures for NCT Table 3.1 Summary of Maximum Pressures NAC International 3.1-4

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 3.2 Material Properties and Component Specifications 3.2.1 Material Properties The packaging is fabricated primarily from Type 304 or Type 316 stainless steel and polyurethane foam materials. Table 3 .2-1 provides the thermal properties for stainless steel that are used for the CCV and OP material properties in the thermal model. The properties for polyurethane foams are provided in the manufacturer's catalog. The properties used in the thermal model for the polyurethane foam are presented in Table 3.2-2. The thermal properties of the are presented in Table 3.2-3. The thermal properties for air and helium gas used in the thermal model are presented in Table 3.2-4 and Table 3.2-5, respectively. 3.2.2 Component Specifications The package components that are significant to the containment and shielding design are primarily stainless steel. The maximum temperature limits of these components are summarized in Table 3.2-6. Otherwise, component maximum temperature limits are defined as the melting temperature of the material of construction. The minimum temperature limit for all components

• is -40°C (-40°F).

The fluorocarbon (Viton) O-ring seal material used as the containment boundary O ring seals for the CCV lid and port cover has a continuous operating temperature range of -40.°F (-40°C) to 400°F (204°C) [3.1].

• NAC International 3.2-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.2 Thermal Properties of Stainless Steel Temperature, Thermal Conductivity, k, Specific Heat, Cp, Emissivity, K (°F} W/m*K (Btu/h*in*°F} J/kg*K (Btu/lbm*°F} E 200 (-99) 12.6 (0.607) 402 (0.096) 0.22 300 (81} 14.9 (0.717) 477 (0.114) 0.22 400 (261) 16.6 (0.799) 515 (0.123) 0.22 600 (621) 19.8 (0.953) 557 (0.133) 0.24 800 (981) 22.6 (1.088) 582 (0.139) 0.28 1000 (1341) 25.4 (1.223) 611 (0.146) 0.35 1100 (1521) 26.7 (1.286} 626 (0.150} 0.39 Notes:

1. Density is 0.290 lb/in3 (8,030 kg/m 3).

NAC International 3.2-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.2 Thermal Properties of Dry Air at Standard Pressure Thermal Kinematic Thermal Density, Specific Prandtl Temp Conductivity, k Viscosity, Diffusivity, p (OF) Heat, Cp Number, (E-3, V a (E-5, (Btu/lbm*°F) Pr Btu/h*in*°F) (E+2, in 2/h) (E+2, in 2/h) lb/in 3 )

   -99        0.872          0.424            0.575         0.2405     0.737       6.31
    -9        1.074          0.638            0.887         0.2403     0.720       5.04 81        1.266          0.887             1.26         0.2405     0.707       4.20 171        1.445           1.17             1.67         0.2410     0.700       3.59 261        1.627           1.47             2.14         0.2422     0.690       3.15 351        1.796           1.81             2.63         0.2439     0.686       2.80 441        1.960           2.16             3.16         0.2460     0.684       2.52 531        2.114           2.54             3.72         0.2484     0.683       2.29 621        2.258           2.94             4.29         0.2510     0.685       2.10 711        2.393           3.36             4.87         0.2539     0.690       1.93 801        2.523           3.80             5.47         0.2568     0.695       1.80 891        2.643           4.26             6.08         0.2596     0.702        1.68 981        2.759           4.74             6.70         0.2625     0.709        1.57 1071        2.870           5.23             7.31         0.2651     0.716        1.48 1161        2.985           5.74             7.98         0.2678     0.720        1.40 1251        3.096           6.26             8.65         0.2701     0.723        1.32 1341        3.212           6.80             9.37         0.2725     0.726        1.26 1521        3.443           7.91             10.9         0.2768     0.728        1.14

• NAC International 3.2-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.2 Thermal Properties of Helium Gas at Standard Pressure Thermal Kinematic Thermal Prandtl Temperature Density, p (OF) Conductivity, k Viscosity, v Diffusivity, a Number, (E-6, lb/in 3 ) (E-3, Btu/h*in*°F) (E+2, in 2/h) (E+2, in 2/h) Pr

     -63                 5.93                 4.03               5.97         0.675          8.006 9                 6.60                 5.36               7.87         0.682          6.774 81                 7.32                 6.81              10.04         0.680          5.871 261                  9.00                11.10              16.46         0.675          4.404 441                 10.59                16.18              24.22         0.668          3.524 801                 13.39                28.01              42.85         0.654          2.518 1341                17.05                51.00              78.12         0.654          1.763 1472                17.79                57.52              88.32         0.654          1.647

References:

[3.7] All Properties: Table A.4, Page 997. Notes: Specific heat is 1.24 Btu/lbm*°F for all temperatures. Table 3.2 Temperature Limits of Packaging Components Maximum Temperature Limit, °F (°C) 100°F Ambient Temperature Component or Material in Shade NCT HAC Stainless Steel (CCV) N/A 800( 1) (427) 800( 1) (427) Stainless Steel (OP) N/A 800( ) (427) 1 2546(2) (1120) Polyurethane Foam (OP) N/A 250(3} (121) N/A CCV Seal (O-ring) N/A 400(4 ) (204) 400(4) (204) Accessible Surfaces of the PackaQe < 185( ) (85) 5 N/A N/A Notes:

1. Maximum temperature from ASME Section II Part D [3.2].

2. Melting temperature of stainless steel [3.3].

3. Maximum allowable temperature based on upper range of strength data provided by foam manufacturer.

4. Maximum continuous service temperature of fluorocarbon (Viton) elastomer [3.6].

5. Exclusive use requirement per 10 CFR 71.43(g).

NAC International 3.2-4

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 3.3 Thermal Evaluation Under Normal Conditions of Transport This section describes the thermal evaluation of the package under NCT. The evaluation is conducted using analytical methods in accordance with 10 CFR 71 and Regulatory Guide 7 .8 for the applicable NCT thermal loads. The results are compared with the allowable limits of temperature and pressure for the package components.

• Thermal Model Description
• NAC International 3.3-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A NAC International 3.3-2

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Application of Content Heat Generation via Volumetric Heat Generation

• NAC International 3.3-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 3.3-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 3.3-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 3.3-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 3.3-7

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 3.3-8

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 3.3-9

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 10 CFR 71.71 specifies the insolation values for a 12-hour period. This 12-hour period represents a 12-hour long "day" in a 24-hour day/night cycle. Since the solar heat flux is constant in the steady-state analyses, the

• insolation value should be time averaged over 24 hours in order to maintain the proper total heat flux to the package over the full day/night.

NAC International 3.3-10

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 3.3-11

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 3.3.1 Heat and Cold Per the requirements of 10 CFR 71. 71 (c)( 1), the packaging and contents are evaluated for NCT heat. Specifically, steady-state thermal analyses are performed simulating exposure of the package to a 100°F (38°C) temperature with insolation in accordance with 10 CFR 71.7l(c)(l). The1mal analyses of the package for NCT heat are performed for the mav,.-..,nm content total heat load of 100 watts and a reduced heat load of 50 watts. The packaging temperatures for NCT heat are summarized in Table 3.3-2. A representative temperature contour plot of the packaging for NCT heat with the 100 watt volumetric heat source is shown in Figure 3.3-5. The results show that the temperature of all packaging components remain well below their allowable temperatures for NCT. Therefore, when exposed to NCT, the structural, containment, and shielding performance of the package will not be adversely affected by the temperatures experienced under these conditions In accordance with the requirements of IO CFR 7 l .43(g), the package is also evaluated for an ambient temperature of 100°F (38°C) in still air and shade. The results show that the maximum temperature of the accessible surface of the package under these conditions is l 12°F (45°C), which is well below the 185°F (85°C) temperature limit for exclusive-use shipments. 3.3.2 Maximum Normal Operating Pressure The max* NAC International 3.3-12

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 3.3-13

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A NAC International 3.3-14

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.3 Nusselt Number Calculation Constants of a Cylinder in Cross Flow Table 3.3 Maximum Package Temperatures for NCT Heat

• NAC International 3.3-15

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.3 Package 3-D 1/2-Symmetry Thermal Model for NCT NAC International 3.3-16

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.3 Expanded View of the CCV with Contents Modeled in 110-Gallon Drum

• NAC International 3.3-17

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.3 Application of Convection Boundary Conditions for NCT (and Shade) NAC International 3.3-18

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 3.3 Heat Transfer Coefficients for General Standards (shade) and NCT

• NAC International 3.3-19

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.3 NCT Heat Temperature Contour Plot- lOOW Volumetric Heat Source NAC International 3.3-20

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 3.4 Thermal Evaluation Under Hypothetical Accident Conditions 3.4.1 Initial Conditions The thermal performance of the package for the HAC fire prescribed in IO CFR 71.73(c)(4) is assessed by performing transient heat transfer analyses on a finite element representation of the package. The model represents the package with damage following a 30-foot HAC free drop followed by a 40-inch drop onto a 06-inch puncture bar. The general-purpose finite element code ANSYS, release 14.5, is used to analyze the package for the 30-minute HAC fire. Drop Damage The finite element model of the package used for the HAC thermal analysis accounts for packaging damage resulting from a 30-foot HAC free drop followed by a 40-inch free drop onto a puncture pin. For the HAC thermal analysis, damage to the top end of the packaging is of most interest because it maximizes the heat input to the top end of the CCV during the 30-minute fire and results in the maximum temperature of the CCV lid containment 0-ring seal. As discussed in Chapter 2, the hot/soft HAC top end drop (Case HTE2) results a maximum crush depth of the

• to the OP lid corner foam of 3.31 inches (8.4 cm), or 38% of its original thickness, and the subsequent hot/soft HAC top off-center puncture fully compresses the OP lid end foam to create a conical depression (dent) in the OP lid outer end plate and end foam steel liner, but the OP lid outer end plate is not perforated. Following the HAC puncture, spring-back OP lid outer end plate due to the small amount of elastic deformation in the OP shells will result an air gap between the OP outer shell and the OP end foam steel liner. This air gap, combined with the ceramic fiber paper attached to the inside surface of the OP lid outer end plate, will provide some thermal protection of the packaging during the HAC fire transient.
• NAC International 3.4-1

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A As discussed in Section 3.5.2.3, additional analysis of the package for the HAC thermal test are performed modeling the cumulative damage from the HAC side drop and HAC top center puncture impact. The results of this analysis demonstrate that the peak packaging temperatures do not vary significantly with the two different damage models. In all cases, the peak components of the packaging remain well within the applicable temperature limits. 3.4.2 Fire Test Conditions NAC International 3.4-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 3.4-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 3.4.3 Maximum Temperatures and Pressure 3.4.3.1 Maximum HAC Temperatures Results NAC International 3.4-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 3.4-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The results of the HAC fire analyses with a 100 watt heat load and helium fill gas show that the CCV O-ring reaches a maximum temperature of229°P (110°C), and the contents/helium fill gas reaches a maximum volumetric average temperature of 2 71 °P (133 °C). The results of the HAC thermal analysis also show for a heat load of 50 watts with air fill gas, the maximum temperatures of the packaging are bounded by those for the 100 watt heat load cases with helium fill gas, but the maximum volumetric average temperature of the contents/air fill gas reaches 281 °F (139°C), which is slightly higher than the result for the 100 watt heat load with helium fill gas. 3.4.3.2 Maximum HAC Pressure Results The maximum pressures for HAC are determined using the same equations as for the MNOP calculations in Section 3.3.2, but considering the increased internal temperatures from a fire accident. As shown in Table 3.4-1, the peak volume-average fill gas temperature (T2) during the HAC fire transient is 281 °P (411 K) for contents having a total decay heat of 50 watts with air fill gas and 271 °F (406K) for contents having a total decay heat of 100 watts with helium fill gas. The coITesponding gas pressures, Pg, due to the addition of radiolytic gases and heating of the CCV during the HAC fire transient are 161.8 kPa (23.5 psia) and 166.3 kPa (24.1 psia), respectively. Also shown in Table 3.4-1, the peak area-average temperature of the CCV cavity surface (Tw) during the HAC fire transient is 221 °F (378K) for contents having a total decay heat of 50 watts with air fill gas helimn fill gas. 3.4.4 Maximum Thermal Stresses Thermal stresses of the package are addressed in Section 2. 7.4. 3.4.5 Accident Conditions for Fissile Material Packages for Air Transport Not applicable. NAC International 3.4-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.4 Maximum Package Temperatures for HAC Table 3.4 Summary of HAC Pressures

• NAC International 3.4-7

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.4 Package 3-D 1/2-Symmetry Thermal Model for HAC NAC International 3.4-8

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.4 Convection Boundary Conditions for HAC

• NAC International 3.4-9

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 3.4 Heat Transfer Coefficients for HAC Analyses (Fire) NAC International 3.4-10

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.4 Heat Transfer Coefficients for HAC Analyses (Post-Fire Cool Down)

• NAC International 3.4-11

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 3.4 Charred Polyurethane Foam at End of the Fire NAC International 3.4-12

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 3.4 HAC Fire Temperature Time-Histories (100W Volumetric Heat Source, Helium Fill Gas, CCV at Top) Figure 3.4 HAC Fire Temperature Time-Histories (100W Surface Heat Flux, Helium Fill Gas, CCV at Top)

• NAC International 3.4-13

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.4 HAC Transient Analysis Temperature Contour Plots (100W Volumetric Heat Load, Helium Fill Gas, CCV at Top) NAC International 3.4-14

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.4 HAC Transient Analysis Temperature Contour Plots (100W Surface Heat Flux, CCV at Top)

• • NAC International 3.4-15

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 3.5 Appendix 3.5.1 References [3.1] Parker, "O-Ring Handbook," ORD 5700, 2007. [3.2] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section II, Part D, Materials, 2010 Edition with 2011 Addenda. [3.3] F. P. Incropera and D. P. DeWitt, in Fundamentals of Heat and Mass Transfer, Fifth ed., New York, John Wiley & Sons, Inc., 2002. [3.4] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 1, Code Cases: Nuclear Components, Case N-670-1, Use of Ductile Cast Iron Conforming to ASTM A 874/A 874M-98 or JIS 05504-2005 for Transport and Storage Containments, January 4, 2008. [3.5] ASM International Handbook Committee, Metals Handbook, Volume 1, Properties and Selection: Irons, Steels, and High-Performance Alloys, Tenth ed., Materials Park, OH: ASM International, 1990. [3.6] Parker Hannifin Corporation, "Technical Bulletin No. ORD 5746, "VM835-75 for Aerospace Applications"," Lexington, KY, 2006. [3.7] F. P. Incropera, D. P. DeWitt, T. L. Bergman and A. S. Lavine, "Fundamentals of Heat and Mass Transfer," Seventh Edition, 2011. [3.8] High Temperatures - High Pressures, "Thermal Conductivity of Nonporous Polyurethane," 2000. [3.9] SAS IP, Inc., "ANSYS, Release 14.5," UP20120918, 2012. [3.10] Skolnik Industries, Inc., Part No. STJ JOIN, Rev. A, I JO Gallon Open Head Drum, Chicago, IL, 2012. [3.11] Falcon Structures, "Conex Shipping Container Dimensions," [Online]. Available: https://www.falconstructures.com/falcon-box-plans (see Appendix D). [Accessed 9 December 2017]. [3.12] J. H. Lienhard IV and J. H. Lienhard V, in A Heat Transfer Textbook, Fourth ed., Cambridge, Massachusetts: Phlogiston Press, 2012. [3.13] E. C. Guyer, Ed., in Handbook ofApplied Thermal Design, New York, McGraw-Hill, 1989. [3.14] General Plastics Manufacturing Company, "General Plastics LAST-A-FOAM FR-3700 for Crash and Fire Protection of Nuclear Material Shipping Containers," ML0504 I 0066, 1991. NAC International 3.5-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A [3.15] UNIFRAX, "Fiberfrax Duraboard Products," FFX/DB/001/E/R2, 2005. [3.16] UNIFRAX, "Fiberfrax Durablanket S," U-111 EN, Rev.0, 2009. NAC International 3.5-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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 International 3.5-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 3.5-4

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 3.5 Maximum HAC Package Temperatures vs. CCV Position in OP Cavity Table 3.5 Maximum HAC Package Temperatures vs. Damage Model

• NAC International 3.5-5

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 3.5 Modified Damage HAC Thermal Model NAC International 3.5-6

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Chapter 4 Containment Table of Contents 4 CONTAINMENT ............................................................................................................ 4-1 4.1 Description of the Containment System ....................................................................... 4.1-1 4.2 Containment Under Normal Conditions of Transport .................................................. 4.2-1 4.2.1 NCT Pressurization of the Containment Vessel ............................................... 4.2-1 4.2.2 NCT Containment Criterion ............................................................................. 4.2-1 4.2.3 Compliance with NCT Containment Criterion ................................................. 4.2-1 4.3 Containment Under Hypothetical Accident Conditions ............................................... 4.3-1 4.3 .1 HAC Pressurization of the Containment Vessel ............................................... 4.3-1 4.3 .2 HAC Containment Criterion ............................................................................. 4.3-1 4.3 .3 Compliance with HAC Containment Criterion ................................................. 4.3-1 4.4 Leakage Rate Tests for Type B Packages ..................................................................... 4.4-1 4.4.1 Fabrication Leakage Rate Test.. ........................................................................ 4.4-1 4.4.2 Maintenance Leakage Rate Test ....................................................................... 4.4-1 4.4.3 Periodic Leakage Rate Test .............................................................................. 4.4-1 4.4.4 Pre-shipment Leakage Rate Test ...................................................................... 4.4-1 4.5 *Appendices .................................................................................................................... 4.5-1 4.5 .1 References ......................................................................................................... 4.5-1 4.5.2 Flammable Gas Calculations/ Requirements ................................................... 4.5-2 4.5.3 Chemical Compatibility of TRU Waste Contents ............................................ 4.5-3 4.5.4 Hydrogen Concentration Calculations .............................................................. 4.5-4 4.5.5 Pressure Calculations for TRU Waste ........................................................... 4.5-12

• NAC International 4-i

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Figures Figure 4.1 Packaging Containment System ...................................................................... 4.1-3 List of Tables Table 4.5 TRU Waste Contents - Flammability Limits .................................................. 4.5-13 Table 4.5 TRU Waste Maximum Hydrogen G-Values and Activation Energies .......... .4.5-13 Table 4.5 TRU Waste Minimum Hydrogen Release Rates ............................................ 4.5-13 NAC International 4-ii

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 4 CONTAINMENT In accordance with the requirements of and 10 CFR 71.43(+/-) and, the package is designed, constructed, and prepared for shipment to assure no loss or dispersal of radioactive contents as demonstrated to a sensitivity of 10-6 A2 per hour in accordance with 10 CFR 71.Sl(a)(l), no significant increase in external surface radiation levels, and no substantial reduction on the effectiveness of the packaging under the NCT tests specified in 10 CFR 71.71. In addition, the package is designed, constructed, and prepared for shipment to assure no escape of Krypton-85 exceeding 10A2 in 1 week, no escape of radioactive material exceeding a total amount A2 in 1 week, and no external radiation dose rate exceeding 10 mSv/h (1 rem/h) at 1 m (40 in) from the external surface of the package under the HAC tests specified in 10 CFR 71.73, in accordance with the requirements of 10 CFR 71.Sl(a). This chapter describes the packaging's containment system design and how it meets the containment requirements under NCT and HAC tests and defines the criteria for leak rate testing during package fabrication, use, maintenance, and repair. The appendices in this chapter provide guidance for chemical compatibility and flammability requirements of the contents .

• NAC International 4-1

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NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 4.1 Description of the Containment System The packaging has a simple, robust containment system design. Containment of radioactive material for the packaging is provided by the Cask Containment Vessel (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. In accordance with the requirements of IO CFR 71.51 (c) , the packaging does not rely on any filter or mechanical cooling system to meet containment requirements, nor does it include any vents or valves that allow 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 4.1-1, with the pressure-retaining boundary is 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 body is a solid austenitic stainless steel (Type 304 or 316) weldment con i tin I-inch thick cylindrical shell, a I-inch thick bottom plate, and a bolt flange .

• NAC International 4.1-1

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A The CCV is designed, fabricated, examined, tested, and inspected in accordance with the applicable requirements of Subsection NB of the ASME Code [4.1] with certain exceptions discussed in Chapter 2. The containment system materials of construction are evaluated in Section 2.2.1 and selected to avoid chemical, galvanic, or other reactions, discussed in Section 2.2.2. The materials of construction are compatible with each other and the chemical form of the payload. NAC International 4.1-2

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 4.1 Packaging Containment System

• NAC International 4.1-3

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 4.2 Containment Under Normal Conditions of Transport 4.2.1 NCT Pressurization of the Containment Vessel The package maximum normal operating pressure (MNOP) is 100 psi (690 kPa) gauge, based on the definition of a Type B(U) packaging. Section 3.3.2 further discusses the NCT pressurization. 4.2.2 NCT Containment Criterion The package is designed to a "leaktight" containment criterion per ANSI N14.5 [4.3]. Therefore, the containment criterion is 10-7 ref cm 3/s. 4.2.3 Compliance with NCT Containment Criterion Compliance with the NCT containment criterion is demonstrated by analysis. The structural evaluation in Section 2.6 shows there would be no loss or dispersal of radioactive contents, and that the containment boundary, seal region, and closure bolts do not undergo any inelastic deformation when subjected to the conditions of 10 CPR 71. 71. The thermal evaluation in Section 3 .3 .1 shows the seals, bolts and containment system materials of construction do not exceed their temperature limits when subjected to the conditions of 10 CPR 71. 71 .

• NAC International 4.2-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 4.3 Containment Under Hypothetical Accident Conditions 4.3.1 HAC Pressurization of the Containment Vessel The containment evaluation for HAC is performed assuming the maximum package pressure is 225 psi (1,551 kPa) gauge. 4.3.2 HAC Containment Criterion The packaging is designed to a "leaktight" containment criterion per ANSI N14.5 [4.3]. Therefore, the containment criterion is 10-7 ref cm 3/s. 4.3.3 Compliance with HAC Containment Criterion Compliance with the HAC containment criterion is demonstrated by analysis. The structural evaluation in Section 2.7 shows there would be no loss or dispersal ofradioactive contents, and that the containment boundary, seal region, and closure bolts do not undergo any inelastic deformation when subjected to the conditions of 10 CFR 71. 73. The thermal evaluation in Section 3 .4.3 shows the seals, bolts and containment system materials of construction do not exceed their temperature limits when subjected to the conditions of 10 CFR 71. 73 .

• NAC International 4.3-1

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 4.4 Leakage Rate Tests for Type B Packages 4.4.1 Fabrication Leakage Rate Test The CCV assembly is tested during fabrication, prior to first use, to demonstrate the leakage rate of the containment system, as fabricated, does not exceed 10-7 ref-cm 3/s. The maximum allowable sensitivity for the fabrication leakage rate test is half of the required 10-7 ref-cm 3/s test criterion (i.e. 5xl0-8 ref-cm 3/s). The fabrication leakage rate test requirements are further described in Section 8.1.4. 4.4.2 Maintenance Leakage Rate Test The CCV assembly is tested after maintenance of the CCV assembly to confirm the leakage rate of the containment system after maintenance, repair, or replacement of components does not exceed 10-7 ref-cm 3/s. The maximum allowable sensitivity for the maintenance leakage rate test is half of the required 10-7 ref-cm 3/s test criterion (i.e. 5xl0- 8 ref-cm 3/s). The maintenance leakage rate testing and the replacement or repair activities requiring a maintenance leak rate test are further described in Section 8.2.2.2. 4.4.3 Periodic Leakage Rate Test

• The CCV assembly is tested within 12 months prior to each shipment to confirm the leakage rate of the containment system does not exceed 10-7 ref-cm 3/s. The maximum allowable sensitivity for the maintenance leakage rate test is half of the required 10-7 ref-cm 3/s test criterion (i.e.

5xl0-8 ref-cm 3/s). The periodic leakage rate test requirements are further described in Section 8.2.2.2. 4.4.4 Pre-shipment Leakage Rate Test Each packaging is tested prior to shipment to confirm the containment system is properly assembled for shipment. The pre-shipment leakage rate test is performed using the gas pressure rise method in ANSI N14.5, Section A.5.2, following the steps outlined in Section 7.1.3. The acceptance criterion for the pre-shipment leak test is no detected leakage when tested to a sensitivity of at least 10-3 ref-cm 3/s. The pre-shipment leakage rate test requirements are further described in Section 8.2.2.3 .

• NAO International 4.4-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 4.5 Appendices 4.5.1 References [4.1] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, Class I Components, 2010 Edition with 2011 Addenda. [4.2] Parker Hannifin Corporation, Parker O-Ring Handbook, ORD 5700/USA, 2007. [4.3] ANSI N14.5-2014, American National Standard for Radioactive Materials -Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014. [4.4] U.S. Nuclear Regulatory Commission (NRC), "Standard Review Plan for Transportation Packages for Radioactive Material, "NUREG-1609, March 1999. [4.5] U.S. Nuclear Regulatory Commission (NRC), "Clarifications of Conditions for Waste Shipments Subject to Hydrogen Gas Generation," IN87-72, 1984 . [4.6] U.S. Environmental Protection Agency (EPA), "A Method for Determining the Compatibility of Hazardous Waste," EPA-600/2-80-076, 1980. [4.7] U.S. Department of Energy (DOE), "Transuranic Waste Acceptance Criteria for The Waste Isolation Pilot Plant," DOE/WIPP-02-3122, Rev.8, 2016. [4.8] Lawrence Livermore National Laboratory, "Hydrogen Generation in TRU Waste Transportation Packages," NUREG/CR-6673, May 2000. [4.9] U.S. Department of Energy (DOE), "RH-TRU Payload Appendices," Revision 3, 2014. [4.10] Oak Ridge National Laboratory, "SCALE Code System," ORNL/TM-2005/39 Version 6.2.2, 2017 .

• NAC International 4.5-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 4.5.2 Flammable Gas Calculations / Requirements TRU waste contents present a potential risk for the introduction of flammable gases from hydrogen gas through radiolysis (all TRU waste contents). For all TRU waste contents, limits are set to ensure there is no risk of a flammable gas mixture in any confinement region in the TRU waste contents due to radiolysis or the release of aerosol propellant gases. Hydrogen gas generation from mechanisms other than radiolysis are insignificant. Hydrogen gas from chemical reactions is prohibited (see discussion in Section 4.5.3). As shown in Table 3.3-8, the maximum bulk-average temperature of the TRU waste contents in the CCV during normal transport is 248°F (120°C), which is well below the 302°F (150°C) threshold temperature at which gas would be generated through thermal decomposition of plastics and other polymer waste materials in air. Given the estimated transportation time, nature of the waste, and environment of the payload, biological mechanisms are considered insignificant. The following subsections outline the limits for each content type to preclude the generation of a flammable gas mixture in the CCV. 4.5.2.1 Oxidant Control As required by the operating procedure described in Section 7 .1.2, a package with a total heat load exceeding 50 watts must be evacuated to an oxygen content of 1% (by volume) or less and backfilled with helium gas prior to shipment. This reduces the quantity of oxygen inside the CCV below the threshold at which a flammable gas mixture can develop in the CCV during the shipping period. After evacuation of the gas from the CCV cavity, the CCV cavity is monitored to assure that any oxygen potentially trapped within the contents has been evacuated below the limiting oxidant concentration (LOC). The inerting process may be skipped if the decay heat of the contents is less than 50 watts. However, if the inerting process is skipped, the hydrogen concentration limit is set at a lower point (see Section 4.5.2.2). With the requirement for flammability control based on oxidant removal to below the LOC, the primary concern for potential flammability during transport of the package is from oxidant reintroduction from radiolysis of water generating oxygen. All oxidant control requirements for the package (see Section 4.5.2.2) are equated to hydrogen concentrations (based on the radiolysis of water), as the limits for any TRU waste content are based on a hydrogen concentration. This is discussed further in Section 4.5.4. NAC International 4.5-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 4.5.2.2 Content Limits Table 4.5-1 provides a summary of the flammability limits for TRU waste content based on the initial quantity of oxygen in the CCV at package closure and radiolysis of water. For contents that are inerted at closure, the only gaseous fuel introduced is hydrogen from radiolysis. As such, the oxidant concentration is limited to 5 vol% oxygen in any confinement region in accordance with IN 84-72(1 )(b) [4.5]. Since the initial quantity of oxygen in the system is limited to I vol% oxygen for greater than 50 watt contents, to limit the oxygen concentration to below the 5 vol%, the quantity of oxygen added from radiolysis is limited to 4 vol3/4. With the added oxygen concentration limited to 4 vol%, the corresponding hydrogen concentration limit, based on the radiolysis of water, is 8 vol%, resulting in total radiolysis gases of 12.0 vol%. When the inerting process is skipped for TRU waste contents having a heat load of 50 watts or less, the hydrogen fuel from radiolysis is limited to 5 vol3/4 in accordance with NUREG-1609, Section 4.5.2.3 [4.4]. Based on the radiolysis of water, the maximum oxygen introduced to the system from radiolysis is 2.5 vol%, resulting in total radiolysis gases of 7.5 vol3/4. 4.5.3 Chemical Compatibility of TRU Waste Contents

• Each TRU waste stream is defined by a content code, with a chemical list for the contents, based on process knowledge. Any chemical not included in the chemical list for the specific content code is limited to less than 1 wt.%, and the total quantity of trace materials is restricted to less than 5 wt.%. The chemical compatibility for a respective content code shall be addressed per the requirements outlined in EPA-600/2-80-076 [4.6] and Appendix H.3 of the WIPP Waste Acceptance Criteria [4.7]. All materials from the specified content code shall be chemically compatible (unless only present in trace amounts) to preclude chemical reactions resulting in:

1. Heat Generation

2. Fire

3. Explosion

4. Formation of toxic fumes

5. Formation of flammable gases

6. Volatilization of toxic or flammable substances

7. Formation of substances of greater toxicity

8. Formation of shock and friction sensitive compounds

9. Pressurization in closed vessels

10. Solubilization of toxic substances NAC International 4.5-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

11. Dispersal of toxic dusts mists and particles

12. Violent polymerization 4.5.4 Hydrogen Concentration Calculations As stated in Section 4.5.2, regardless of whether the flammability control limit is based on fuel or oxidant restrictions, all limits are equated to a limiting hydrogen gas concentration based on the radiolysis of water (see Table 4.5-1). Thus, for all TRU waste contents it is necessary to calculate the concentrations of hydrogen gas in the confinement layers of the TRU waste containers over time, to demonstrate compliance with the imposed limits. The hydrogen gas calculations are not restricted to the radiolysis of water only, but all hydrogenous materials that could generate hydrogen gas through radiolysis must be considered.

The requirements for hydrogen gas generation calculations to meet the hydrogen concentration limit are outlined in the following subsections. Compliance with the hydrogen gas limits must be demonstrated for each shipment of the package with TRU waste contents. Note that Volatile Organic Compounds (VOCs) are limited to a concentration of 500 ppm in the headspace of the container. With VO Cs restricted to below this limit, they do not affect the flammability of the gaseous mixture in the contents. The following methods for hydrogen concentration calculations

• are based on the guidance provided in NUREG/CR-6673 [4.8].

4.5.4.1 G-value Data The G-values used for flammable gas generation calculations are specific to the contents in a given payload, based on the chemical properties of the materials. The bounding G-values shall be used for the calculations of a given content based on the materials present, and must be selected from acceptable industry standard references, such as Appendix D ofNUREG/CR-6673. The following factors are neglected from consideration for G-values based on the information in Section 2.4 of NUREG/CR-6673:

1. The Linear Energy Transfer (LET) Effect. The difference between radiations from LET are small and reference values are based on bounding conditions.

2. Pressure. G-values decrease with increasing pressure. The internal pressure of the CCV will always be greater than 1 atm, basing the G-values on experiments at 1 atm or in vacuum is bounding.

3. Atmosphere. G-values are maximized at vacuum conditions, thus as long as the reference G-values are from experiments in vacuum they are bounding.

NAC International 4.5-4

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

4. Total Absorbed Dose (matrix-depletion effect). G-values decrease with increasing total dose.

Neglecting this effect maximizes the calculated flammable gas generation rate. However, this effect may be considered as outlined in Section 2.2 of the DOE document RH-TRU Payload Appendices [4.9]. Per this document, the dose dependent G-values are applicable after 0.012 watt-years.

5. Dose Rate. The elevated dose rate and thermal effects are mitigated by removing oxygen from the system before the irradiated materials are heated. For content heat loads exceeding 50 watts, the CCV is always evacuated and backfilled with helium prior to transport, removing nearly all oxygen from the system.

6. Material Composition. Maximum G-values are measured for commercial materials to provide more realistic upper bounds for radiolytic gas generation than for pure polymers.

Radiation Based G-values The G-value for a given material, can vary depending on the fraction of the alpha, beta, and gamma energy, when dose dependent G-values are used. If the bounding G-values are used, there is no calculation required for the G-value based on the radiation emitted in the waste. This

• case maximizes the hydrogen generation, and consequently the hydrogen concentration, in the innermost confinement layer. With this assumption, no adjustment of the G-values is necessary for the fractions of a, J3, and y radiation emitted from the contents, and the referenced bounding G-values can be used for the hydrogen gas calculations. For this case, the effective G-value of the contents is calculated as the maximum value of the materials present in the TRU waste:

Where, Geff Effective G-value of contents (molecules/ 100 eV) Gi = Maximum G-value of material i (molecules I I 00 eV) M Total number of hydrogen generating materials in the contents For the dose dependent G-values (applicable for any contents loaded for> 0.012 watt-years) the effective G-value can be calculated depending on the materials and portions of the radiation particles emitted (a, y, or J3), per the guidance of Section 3.3.1 in NUREG/CR-6673 and the information in Appendix 2.2 of the DOE document RH-TRU Payload Appendices [4.9]. This calculation assumes that all energy emerges from the radioactive particles and is absorbed into

• the material M. The G-value for each particle type (GM,p) is selected based on the material with the greatest G-value for the respective particle. For example, for contents with polyethylene and NAC International 4.5-5

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A cellulose, the GM,a and GM,p are based on cellulose, but GM,y are based on polyethylene (see values listed in Table 4.5-2).

Where, Gerr = Effective G-value of contents (molecules/ 100 eV)

Ap = Fraction of decay energy from particle type p GM,p = G-value of material M based on incident particle type p (molecules/ 100 eV) M = Material with the largest hydrogen gas G-value for particle type p. p = Particle type (a, f3, or y) Temperature Adjustment The sources for G-values typically provide the data at 70°F. Thus, these values must be adjusted to account for the temperature effect on radiolytic gas generation. This temperature effect is accounted for using the following equation (based on EQN 2.2 in NUREG/CR-6673). It can be noted the higher the temperature is the greater the increase in the G-value will be. Thus, the adjustment is based on the maximum gas temperature in the CCV calculated for NCT. Note that dose dependent G-values for a and f3 particles are not temperature dependent, and thus do not need to be adjusted for temperature.

Where, Gn = G-value at Temperature Tz (molecules/100 eV)

Gr1 = G-value at Temperature T1 (molecules/100 eV) Ea = activation energy for gas generating material (kcal/mol) R = l .9858775E-3 kcal/mol-K, Gas law constant Tz = Maximum Cavity Temperature (in K) forNCT (see "Content/CCV Fill Gas, Avg." in Table 3.3-2)

           =   294.26 K (or temperature from G-value source data)

NAC International 4.5-6

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Some of the typical G-values of hydrogenous materials present in TRU waste streams are provided in the DOE document RH-TRU Payload Appendices [4.9]. The G-values and activation energies of the materials in Table 4.5-2 are based on the information in Tables 2.2-1 and 2.2-2 of Reference [4.9]. For other solid organic materials not listed in this table it is acceptable to use the value for polyethylene as a bounding value. Solidified organics are not acceptable as contents in the package. Flammable gas generation rate Using the effective G-value and decay heat of the contents, the flammable gas generation rate (FGGR) for the specific TRU waste contents can be calculated: FGGR = __g__ * ( (Geff) ) lOO (NA)* ( 1.602E - 19 ~~ s) Where, FGGR = Flammable gas generation rate (moles/s)

• Q NA

            =
            =

Decay heat of radioactive contents (W) Avogadro's number (6.023E23 molecules/mole) The decay heat of the contents is determined based on the radionuclide inventory of the contents in the TRU waste container and a standard reference for isotopic decay heat values (e.g. the ORIGEN module in the SCALE code package [4.10]). 4.5.4.2 Release Rate Data The release rates used for calculating the concentration of flammable gas are specific to the materials of the confinement layers in a given payload. The release rates used for the calculations of a given content are based on the confinement layers present in the TRU waste container. Note that any items that allow the free release of hydrogen (e.g. open or punctured bags) are not confinement layers. The sources for release rates typically provide the data at 25°C (77°F). Thus, these values must be adjusted to account for the temperature effect on release rates for each confinement barrier. The release rates vary with temperature to the 1.75 power ([4.9], Section 2.5.3), with lower temperatures further restricting the release of hydrogen, and increasing the hydrogen concentration. The temperature effect is accounted for using the following equation: NAC International 4.5-7

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

Where, RRT2 = Release rate at T2 (mol/s/mol fraction)

RRT1 = Release rate at T1 (mol/s/mol fraction) Temperature 2: Minimum Temperature for NCT 233 K (-40°C) Temperature 1: 298K (or temperature from Release Rate source data) Based on the information provided in Table 2.5-1 of the RH-TRU Payload Appendices, the release rates provided in Table 4.5-3 are acceptable for use in hydrogen gas calculations for the package with RH-TRU contents. Any confinement layer not listed in Table 4.5-3 shall be demonstrated ato have a hydrogen release rate greater than or equal to one of the values specified in Table 4.5-3, through testing or analysis. For a heat-sealed bag, the hydrogen release rate can be calculated as follows:

Where, RR=

pApPg Xp mole 22,400 cm 3 (STP) RR = Release Rate of hydrogen (mole/sec/mol fraction H2) p = Hydrogen permeability (cm3 (STP) cm- 1 (cm Hgt 1 s- 1), PVC=3.6E-10 / poly=8.6E-10 Ap = Permeable surface area (cm2) Pg = Gas Pressure (76 cm Hg) Xp = Bag thickness (cm) The release rates of all leaking confinement layers in a TRU waste container can be combined into an effective release rate, Teff, or an effective resistance, Reff. The resistance of a layer is calculated as the inverse of the release rate. The effective resistance or release rate can be calculated as follows: Il r-iRR-T - I I eff - "r-i RR-I L..1 NAC International 4.5-8

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Where, Terr = Effective release rate of all confinement layers (mole/sec/mol fraction H2) Reff = Effective resistance to the release of hydrogen RRi = Release Rate of confinement layer i N Total number of confinement layers in the contents 4.5.4.3 Hydrogen Gas Accumulation Calculations For the calculation of the hydrogen gas concentration in the TRU waste contents, the package may use the method outlined in Section 4.2 ofNUREG/CR-6673, or the simplified approach outlined in this section. NUREG/CR-6673 Calculation Section 4.2 in the NUREG outlines the hydrogen mole balance equations for multiple configurations of TRU waste containers (i.e. nested leaking enclosures in a non-leaking

• enclosure). More specifically, sections 4.2.2.1 and 4.2.2.5 ofNUREG/CR-6673 provide the approaches for calculating the hydrogen concentration in nested leaking enclosures, with a non-leaking outer enclosure at a given time, t. With the equations outlined in these sections, and the Content specific hydrogen limits listed in Table 4.5-1, the time to reach the hydrogen concentration limit can be calculated based on the TRU waste container confinement volumes and release rates. Section 4.2.2.5 in the NUREG provides a generalized approach for a single content that combines all leaking confinement regions into a single effective leaking confinement layer. For this calculation rn and m are the number of moles of gas in the innermost confinement region and in the region between the CCV and TRU waste container, respectively. All volumes between confinement regions are considered to be zero. The void volume in the innermost confinement region is based on the geometry and free space of the region. If this volume is unknown or cannot be determined, it can be set to a bounding value of one (1) L, as discussed in Section 2.5.3 of the RH-TRU Payload Appendices. The void volume in the CCV is calculated based on the total void in the empty CCV (638.9 L), minus the total TRU waste container volume (e.g., 55 gallon [208 L] drum volume), minus the maximum allowable shoring volume (assumed at 2 ft 3 [56 L], per section 1.2.1.5). Both volumes are used to calculate the number of moles of gas using the ideal gas law, based on initial loading conditions (P=l atm and T=294.26 K) .
• NAC International 4.5-9

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Per EQN 4.35 in Section 4.2.2.5 of the NUREG: A*S A* S

• e-t*(A+B) B*S*t Xi (t) = -(A-+-B)-2 (A + B) 2 + (A + B)

Where, Xi(t) = Hydrogen volume fraction in the innermost confinement region at time t.

S = FGGR/n1 A = Teff/Ill B = Teff/n2 The initial conditions for this calculation is Xi(O) = 0, which is considered appropriate, as the evacuation process removes nearly all gas from the system, and the 1 vol% oxygen initial condition is considered in the set limits (See Section 4.5.2.2). With the equation above, the time at which the volume fraction of hydrogen in the innermost confinement region reaches the limit for the respective content can be determined. Per the requirement of IN84-72, the calculated shipment time, t, must be cut in half to set the allowable

• shipment time for the specific TRU waste content analyzed.

Simplified Calculation Method This simplified calculation can be used in lieu of the NUREG/CR-6673 calculation for an unquantified innermost confinement region volume. For the initial conditions of the simplified approach, it is assumed that the concentration and flow of hydrogen through the confinement layers of the TRU waste contents has reached steady state, prior to CCV closure. At steady state condition, the flow of hydrogen across all confinement layers is equal to the hydrogen generation rate. This assumption neglects the removal of nearly all hydrogen from the system during the evacuation process, prior to shipment. Once the CCV is closed, with the TRU waste contents inside, the hydrogen concentrations in the confinement layers and the CCV increase, as it is now a closed system. The mole fraction of hydrogen accumulating in the CCV is calculated by assuming that all the hydrogen generated is released into the CCV cavity. The total moles of hydrogen that will accumulate in the CCV cavity at time, t, is: NAC International Nccv = (FGGR) (t) 4.5-10

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Where, Nccv = Total moles of hydrogen accumulated in the CCV (moles) FGGR = Flammable gas generation rate (moles/s) t = Shipment time (s) The total mole fraction in the CCV at time, t, is set as the ratio of the total moles of hydrogen generated to the initial number of moles in the CCV cavity upon closure. With hydrogen treated as an ideal gas, this equation can be reduced to: Nccv Nccv (FGGR)(t) Xccv =-- =- - - - - No (P)(Vvoict)/RT (P)(Vvoict)/RT Where, Xccv = Total hydrogen mole fraction in the CCV No = Total moles of gas in the CCV at time of closure (moles)

• p Vvoid R

            =
            =
            =

Pressure inside CCV, assumed to be isobaric at 1 atm Void volume in the CCV, i.e. Vccv - Vcontents - Vshoring (Liters) Gas constant (0.082057 atm*L/mol*K) T = Absolute temperature of air at the time CCV closure, assumed to be 70°F (294.26 K) The void volume in the CCV, Vvoid, is calculated based on the total void in the empty CCV (638.9 L), minus the total TRU waste container volume (e.g. 55 gallon drum volume), minus the maximum allowable shoring volume (56 L, per section 1.2.1.5), minus the shoring volume (assumed at 2 ft 3 [56 L]). The total hydrogen mole fraction in the innermost container can be calculated as follows: Where, Xi = Hydrogen mole fraction in the innermost container (content specific limit) Reff = Effective resistance to the release of hydrogen (sec/mole) NAC International 4.5-11

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Rearranging this equation for Xccv, and plugging it into the previous equation, results in the following (with values for P, R, and T combined): (FGGR)(t) Xi - (FGGR)(Reff) = (0 *04141. VVoid. ) The above equation can be solved for time, t, to determine the shipment time required to reach a hydrogen gas concentration at the limit for the respective content in the innermost confinement layer: Per the requirement of IN84-72, the calculated shipment time, t, must be cut in half to set the allowable shipment time for the specific TRU waste content analyzed. Also, for both the NUREG/CR-6673 and simplified calculation method, as opposed to a single bounding calculation considering the G-value at the maximum temperature and the release rates at the minimum temperature, it is acceptable to perform two separate calculations. One calculation with both the G-value and release rates at the minimum temperature of -40°C (233K) and one with both the G-value and release rates at the maximum temperature of 248 °F (393 K). The transport time is then based on the limiting case between the hot and cold calculations. 4.5.5 Pressure Calculations for TRU Waste Pressure calculations for TRU waste under NCT and HAC are presented in Sections 3.3.2 and 3 .4.3 .2, respectively. NAC International 4.5-12

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 4.5 TRU Waste Contents - Flammability Limits Oxygen from Hydrogen from Total Radiolysis Flammability Cavity Gas Radiolysis Radiolysis Gases Limit (vol% 02) (vol% H2) (vol%) Helium 5.0 vol% 02 4.0 8.0 12.0 Air 5.0 vol% H2 2.5 5.0 7.5 Table 4.5 TRU Waste Maximum Hydrogen G-Values and Activation Energies Dose Dependent Bounding Hydrogen Activation Material Hydrogen Gas G-Value1 1l Gas G-Value12l Energy (molecules/100 eV @70°F) (molecules/100 eV @70°F) (kcal/mole) Water 1.6x 3 1.6x 3 Polyethylene 0.64 4.1 0.8 Polyvinyl Chloride 0.50 0.7 3.0 Cellulose 1.09 3.2 2.1 Organic Resins 1.09 1.7 2.1 Other Polymers 1.09 4.1 0.8 Notes:

1. Used for dose dependent G-values for a and p radiation.

2. Used for non-dose dependent G-values and dose dependent G-values for y radiation.

3. x is the mass fraction of water in the waste.

Reference [4.9], Tables 2.2-1 and 2.2-2 Table 4.5 TRU Waste Minimum Hydrogen Release Rates Hydrogen Diffusion Coefficient Confinement Layer (Release Rate) at 298 K (25°C) (mole/sec/mole fraction) Breather Vent on Can 5.18E-06 Filtered Bag 1.08E-05 Fold-and Tape or twist-and tape liner bag 4.67E-06< 1l Heat Sealed Bag See Equation Above Inner drum liner filter 3.70E-06 Drum Filter 3.70E-06 Fixed lid canister filter (high diffusivity) 9.34E-05 Fixed lid canister filter 1.48E-05 Removable lid canister filter 1.48E-05 Notes:

• 1. Release rate is valid for all temperatures .

Reference [4.9], Table 2.5-1 NAC International 4.5-13

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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.l 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 ............................................................................................ 5.3-3 5.4 Shielding Evaluation ..................................................................................................... 5.4-1 5.4.1 Methods ............................................................................................................. 5.4-1 5.4.2 Input and Output Data ....................................................................................... 5.4-6 5.4.3 Flux-to-Dose Rate Conversion .......................................................................... 5.4-6 5.4.4 External Radiation Levels ................................................................................. 5.4-6 5.5 Appendix ....................................................................................................................... 5.5-1 5.5.1 References ......................................................................................................... 5.5-1 5.5.2 Shielding Analysis for 1 x 6 Package Array ..................................................... 5.5-2 5.5.3 Example Cases ................................................................................................. 5.5-24

• NAC International 5-i

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 List of Figures Revision 20A Figure 5.3 MCNP Shielding Models - Package Geometries ............................................ 5.3-7 Figure 5.3 MCNP Shielding Model - NCT Source Configuration ................................... 5.3-7 Figure 5.3 MCNP Shielding Model -HAC Source Configuration .................................. 5.3-8 Figure 5.3 MCNP Shielding Model-NCT Method 1 Tally Locations ............................. 5.3-9 Figure 5.3 MCNP Shielding Model - NCT Method 2 Tally Locations .......................... 5.3-10 Figure 5.3 MCNP Shielding Model - HAC Tally Locaiton ........................................... 5.3-10 Figure 5.4 Method 2 2-meter DRCF Distances - 10 Package Configuration .................. 5.4-26 Figure 5.4-lA - Method 2 meter DRCF Distances - 6 package Configuration .............. 5.4-26 Figure 5.4 MCNP Sample Input File ................................................................................ 5.4-27 Figure 5.5-1 -MCNP Models with I-inch SIA (left) and 21/4-inch SIA (right) ..................... 5.5-21 Figure 5.5-2 -Method 1 Package Array and Cell Tally Locations (top view) ................ 5.5-22 Figure 5.5 Method 2 - Cell Tally Locations - 6 Package Array ...................................... 5.5-23 NAC International 5-ii

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Tables Table 5.1 Package Shielding Design Features .................................................................. 5.1-3 Table 5.1 Method 1 Maximum External Dose Rates Examples ....................................... 5.1-3 Table 5.1 Method 2 Single Pakage Maximum External Dose Rates Examples ............... 5.1-4 Table 5 .1 Method 2 Package Array Maximum External Dose Rates Examples ............... 5 .1-4 Table 5.2 Photon Source Energy Group Structure ............................................................ 5.2-3 Table 5.2 Neutron Source Energy Group Structure .......................................................... 5.2-4 Table 5.3 Primary MCNP Model Package Dimensions .................................................... 5.3-4 Table 5.3 Directional OP Stainless Steel Shell Combined Thickness .............................. 5.3-4 Table 5.3 MCNP Shielding Model - Tally Locations ...................................................... 5.3-5 Table 5.3 Material Compositions ...................................................................................... 5.3-5 Table 5.3 MCNP Material Definitions .............................................................................. 5.3-6 Table 5.4 ANSI/ANS-6.1.1 1977 Flux-to-Dose Conversion Factors ............................. 5.4-11 Table 5 .4 Method 2 2-meter DRCFs - 10 Package Configuration .................................. 5.4-12 Table 5.4 Method 2 2-meter DRCFs-6 Package Configuration ................................... 5.4-12 Table 5.4 MCNP Method 1 Gamma Dose Rate Summary ............................................. 5.4-13 Table 5.4 MCNP Method 1 Neutron Dose Rate Summary ............................................. 5.4-14 Table 5.4 MCNP Method 2 Gamma Dose Rate Summary ............................................. 5.4-15 Table 5.4 MCNP Method 2 Neutron Dose Rate Summary ............................................. 5.4-16 Table 5.4 ORIGEN Grouped Cf-252 Spectra ................................................................. 5.4-17 Table 5 .4 Method 1 - Cf-252 2-meter Dose Rate/Ci and Activity Limit Calculation .... 5 .4-18 Table 5 .4 Method 2 - Cf-252 2-meter Dose Rate/Ci and Activity Lim_it Calculation .. 5 .4-19 Table 5 .4 Bare Cask Dose Rate/Ci and Maximum Activities ( 6 Pages) ....................... 5 .4-20 Table 5.5 SIA Design Shielding Thicknesses ................................................................... 5.5-4 Table 5.5 MCNP Tally Locations - 1 x 6 Package Array ................................................ 5.5-4 Table 5.5 MCNP NCT Gamma Dose Rates with No SIA ............................................... 5.5-5 Table 5.5 MCNP NCT Neutron Dose Rates with No SIA ............................................... 5.5-6 Table 5.5 MCNP NCT Gamma Dose Rates with 1-inch SIA ........................................... 5.5-7 Table 5.5 MCNP NCT Neutron Dose Rates with 1'..inch SIA .......................................... 5.5-8 Table 5.5 MCNP NCT Gamma Dose Rates with 21/4-SIA ................................................ 5.5-9 Table 5.5 MCNP NCTNeutron Dose Rates with 21/4-inch SIA ..................................... 5.5-10 Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) ........ 5.5-11 Table 5.5 Example Method 1 Compliance Calculations ............................................... 5.5-26 Table 5.5 Example Method 2 Single Package Dose Rate Calculation .......................... 5.5-26 Table 5.5 Example Method 2 Single Package Compliance Calculation ....................... 5.5-27 Table 5.5 Example Method 2 Multiple Package Dose Rate Calculation ...................... 5.5-27 Table 5.5 Example Method 2 Multiple Package Compliance Calculation ................... 5.5-28

• NAC International 5-iii

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OPTIMUS-L Package SAR August 2020

• Docket No. 71-9390 5 SHIELDING EVALUATION Revision 20A 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 CPR 71.47(b),

10 CPR 71.51(a)(l) and 10 CPR 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 CPR 71.

• NAC International 5-1

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NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020

• Docket No. 71-9390 5.1 5.1.1 Description of Shielding Design Shielding Design Features Revision 20A The packaging design is comprised of two primary components: the cask containment vessel (CCV), a protective outer packaging (OP). The assembly of these components is shown in Figure 1-1. Narrative descriptions of these components are provided below in Sections 5 .1.1.1 and 5.1.1.2. The design features of the packaging that are credited for radiation shielding are listed in Table 5 .1-1.

The CCV and OP body and lid components are composed of ASME plate and forging materials. Thus, based on Note 1 of Table Al .1, in Annex A.l of ASME SA-20/SA-20M [5.1], the permissible variation under the specified thickness for ASME plate material is 0.01 inches. 5.1.1.1 CCV Shielding Design Features The CCV is the inner vessel that serves as the primary containment boundary of the package .

• 5.1.1.2 Outer Packaging Shielding Design Features The OP is comprised of two parts: a base and lid. Both the OP Base and OP Lid are comprised of inner and outer stainless steel shells encapsulating structural support components (e.g. foam and support plates). Any radiation shielding provided by the polyurethane foam and any supporting components beyond the minimum stainless steel thickness is neglected (See discussion in Section 5.3.1.1).

5.1.1.3 Supplemental Shield Insert Assemblies The I-inch and 21/4-inch thick Shield Insert Assembly (SIA) designs may be used to provide additional shielding and increase the isotopic activity limits for the 1x6 package array. Note only the body of the 21/4-inch SIA is installed in the packaging, not the lid. The shielding analysis of the 1x6 package array with the SIAs is provided in Appendix 5.5.2. 5.1.2 Summary of Maximum Radiation Levels The package is transported solely as an exclusive use shipment; thus, no transportation index is calculated. Instead, the dose rate limits specified in 10 CFR 71.4 7(6) are met for NCT and the dose rate limits specified in 10 CFR 71.51(a)(2) are met forHAC. The trailer surface, 2-meter, NAC International 5.1-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A and cab (occupied position) dose rates are only calculated from the side of the package, as the package is only transported in the upright position. Because the contents of the package are variable, and the final isotope inventory is different for each TRU waste drum or irradiated fuel waste liner, the maximum dose rates are strongly dependent on the specific contents. As an example, maximum dose rates are calculated for the maximum allowable quantity of two individual isotopes. The two isotopes considered are Co-60 and Cf-252. Examples of the maximum activity in each package of the conveyance that would result in a sum of the fractions of 1 for the respective compliance Method 1 or maximum permissible dose rate for compliance Method 2 are provided in Table 5.1-2 through Table 5.1-4, along with the resulting total dose rates at each regulatory location. It should be noted from these tables that, due to the relatively thin layers of shielding provided by the packaging, the maximum isotopic activities permissible in the contents are very limited. The primary content intended for transport in the package is drums of TRU waste with relatively low activity. Thus, the relative hazard of the contents is limited. NAC International 5.1-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020

• Docket No. 71-9390 Table 5.1 Package Shielding Design Features Revision 20A Table 5.1 Method 1 Maximum External Dose Rates Examples Method Dose Rate Limit Case< 11 Condition Location (Activity< 2l) (mrem/hr) (mrem/hr)

NCT Package Surface 62.30 200 Trailer Surface 55.08 200 Co-60 1 2-meter 9.00 10 (2.837E-02 Ci) Cab 1.01 2 HAC 1-meter 16.83 1000 NCT Package Surface 57.72 200 Trailer Surface 53.96 200 Cf-252 2 2-meter 9.00 10 (3.901 E-03 Ci) Cab 0.98 2 HAC 1-meter 16.31 1000 Notes:

1. Method 1 dose rates listed are for two separate cases: one case with 10 packages containing a maximum activity of Co-60, and one case with all packages containing a maximum activity of Cf-252.

2. Isotope activity in each of the 10 packages .

• NAC International 5.1-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Table 5.1 Method 2 Single Pakage Maximum External Dose Rates Examples Casel 1l Isotope Condition Location Dose Rate Revision 20A Limit (Activity) (mrem/hr) (mrem/hr) NCT Package Surface 180.00 200 Trailer Surface 30.96 200 Co-60 1 2-meter

• 4.65 10 (8.197E-02 Ci)

Cab<2l 1.34 2 HAC 1-meter 48.63 1000 NCT Package Surface 180.00 200 Trailer Surface 30.66 200 Cf-252 2 2-meter 4.50 10 (1.217E-02 Ci) Cab<2l 1.28 2 HAC 1-meter 50.87 1000 Notes:

1. Method 2 dose rates listed are for two separate cases: a case with one package containing a maximum activity of Co-60, and a case with one package containing a maximum activity of Cf-252.

2. Single packages must be shipped with a Cab distance of at least 20 ft.

Table 5.1 Method 2 Package Array Maximum External Dose Rates Examples Casel 1l Isotope (Activity12l) Condition NCT Location Package Surface Dose Rate (mrem/hr) 43.52 Limit (mrem/hr) 200 Trailer Surface 47.31 200 Co-60 1 2-meter 8.17 10 (1.982E-02 Ci) Cab 1.59 2 HAC 1-meter 11.76 1000 NCT Package Surface 44.83 200 Trailer Surface 47.82 200 Cf-252 2 2-meter 8.17 10 (3.030E-03 Ci) Cab 1.56 2 HAG 1-meter 12.67 1000 Notes:

1. Method 2 Dose rates listed are for two separate cases: one case with 10 packages containing a maximum activity of Co-60, and one case with 10 packages containing a maximum activity of Cf-252

2. Isotope activities based on an equal activity in .each of the 10 packages that would result in a Method 2 Total 2-meter dose rate of 9 mrem/hr (see Section 5.4.1.4.2).

NAC International 5.1-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.2 Source Specification The radioactive contents of the package are restricted to TRU materials. As such, the radionuclide inventories of the contents are highly variable and dependent on the individual TRU waste container. Thus, the neutron and gamma sources are dependent on the isotopic inventory of the contents. The isotopic inventory in each TRU waste container is characterized individually and is based on the waste materials in the specific contents. The neutron and gamma sources used for the dose rate analysis of the package are generic, so that the dose rates of specific contents can be determined based on the generic source terms analyzed. Dose rates are calculated individually for gamma and neutron energy groups, so that with the calculated energy group dose rates and the isotopic inventory from a specific content, bounding dose rates can be calculated individually for each shipment. The individual dose rate calculations are for each energy group, G, based on the photon and neutron source spectra groups listed below in Table 5.2-1 and Table 5.2-2. The dose rate calculation for each energy group considers a monoenergetic source at the upper bound of the group (e.g., for the 0.1 to 0.2 MeV group, the source energy is 0.2 MeV). For each TRU waste container, the contents are characterized, such that there is a specific

• isotopic inventory per contents. For each isotope in the contents, a dose rate is determined based on the calculated energy group dose rates and a grouped source spectrum of the isotope, as calculated in the ORI GEN module of the SCALE code package, version 6.2 [5.2]. With the dose rate contribution of each isotope calculated, an activity limit is determined for each isotope for Method 1. Then the isotopic inventory specific to the contents is used to demonstrate compliance with external dose rate limits through the sum of the fractions method for Method 1.

Compliance for Method 2 is verified through a calculation of dose rates at each regulatory location. The isotopic inventories of the characterized contents are considered current at the time of transport. Thus, there is no concern of an increase in source term over time during the transport. 5.2.1 Gamma Source The gamma energy groups shown in Table 5 .2-1 are based on a generic grouping structure developed for this package. The source of each isotope in the contents is determined based on 1 Ci of activity, using the ORI GEN code. ORI GEN groups the gamma emissions into the energy groups shown in Table 5.2-1 for a defined gamma source from 1 Ci of the specific isotope, accounting for both gammas that are directly emitted and from Bremsstrahlung. Using the bounding calculated dose rates for each energy group, the dose rate contribution from each

• isotope is determined, and with the isotopic inventory of the contents, the total external dose NAC International 5.2-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A rates can be calculated. As an example, the ORIGEN grouped Cf-252 gamma source is shown in Table 5.2-1. 5.2.2 Neutron Source The neutron energy groups shown in Table 5.2-2 are based on a generic grouping structure developed for this package. The source of each isotope in the contents is determined based on 1 Ci of activity, using the ORI GEN code. ORI GEN groups the neutron emissions into the energy groups shown in Table 5.2-2 for a defined neutron source from 1 Ci of the specific isotope, accounting for neutrons from both spontaneous fission and a,n reactions. Using the bounding calculated dose rates for each energy group, the dose rate contribution from each isotope is determined, and with the isotopic inventory of the contents, the total external dose rates can be calculated. As an example, the ORIGEN grouped Cf-252 neutron source is shown in Table 5.2-2. NAC International 5.2-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.2 Photon Source Energy Group Structure Boundaries (MeV) Cf-252 Spectrum Group Upper Lower (y/s/Ci) 1 12 10 1.9100E+05 2 10 8.0 2.6093E+06 3 8.0 6.0 2.3082E+07 4 6.0 4.0 2.0419E+08 5 4.0 3.0 4.5451E+08 6 3.0 2.5 4.9616E+08 7 2.5 2.0 8.5568E+08 8 2.0 1.8 4.3330E+08 9 1.8 1.5 1.2390E+09 10 1.5 1.34 7.2360E+08 11 1.34 1.2 9.3690E+08 12 1.2 1.0 2.1195E+09 13 1.0 0.9 1.0598E+09 14 0.9 0.8 1.0598E+09 15 0.8 0.7 1.0561E+09 16 0.7 0.67 3.1575E+08 17 0.67 0.6 7.3675E+08 18 0.6 0.5 1.0525E+09 19 0.5 0.4 1.0525E+09 20 0.4 0.3 1.0525E+09 21 0.3 0.2 5.2625E+08 22 0.2 0.1 5.6748E+06 23 0.1 0.075 0.0000E+00 24 0.075 0.050 0.0000E+00

• NAC International 5.2-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.2 Neutron Source Energy Group Structure Boundaries (MeV) Cf-252 Spectrum Group Upper Lower (n/s/Ci) 1 20.0 15.0 2.7589E+05 2 15.0 10.0 1.1338E+07 3 10.0 7.50 5.6069E+07 4 7.50 5.00 2.8751E+08 5 5.00 4.00 3.0533E+08 6 4.00 3.00 5.2541E+08 7 3.00 2.50 3.7627E+08 8 2.50 2.25 2.2137E+08 9 2.25 2.00 2.4451E+08 10 2.00 1.75 2.6755E+08 11 1.75 1.50 2.8937E+08 12 1.50 1.25 3.0832E+08 13 14 15 16 17 1.25 1.10 1.00 0.90 0.80 1.10 1.00 0.90 0.80 0.70 1.9202E+08 1.2995E+08 1.3076E+08 1.3076E+08 1.2976E+08 18 0.70 0.60 1.2754E+08 19 0.60 0.50 1.2377E+08 20 0.50 0.40 1.1801 E+08 21 0.40 0.30 1.0960E+08 22 0.30 0.20 9.7417E+07 23 0.20 0.10 7.9088E+07 24 0.10 0.05 2.9046E+07 NAC International 5.2-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.3 Shielding Model The following subsections describe the MCNP shielding model geometiy and source configuration for all dose rnte calculations of the package. 5.3.1 Configuration of Source and Shielding 5.3.1.1 MCNP Shielding Model - Package Geometry The MCNP model package geometiy for the dose rate calculations is based on the dimensions provided in the package licensing drawings. Additional features and attachments of the OP are neglected (tie-downs, foam, supp01t plates, etc.). All bolts and inserts in the CCV lid are modeled as the same material as the component (stainless steel). The resultant localized reductions in the shielding effectiveness of the CCV are considered negligible. Credit for the offset provided by the OP is only taken for NCT and HAC, based on an impact limiter deformation bOlmding of the maximum defo1mations resulting from the HAC free drop, as discussed in Chapter 2. In addition, a minimum foam thickness is credited for NCT, based on the minimum thickness of the polyurethane foam in the OP lid. The components of the CCV and OP consist of ASME plates and forgings with tight under-

• thickness tolerances. Per Note I ofTable Al.I, in Annex A.I ofAS1vIE SA-20/SA-20M [5.1],

the peimissible variation under the specified thickness for ASME plate material is 0.01 inches. Thus, these small tolerances are neglected for in the MCNP geometry. The package MCNP model geometi-ies for NCT and HAC are shown below in Figure 5.3-1, including all significant axial and radial shield thickness dimensions, with dimensions listed in Table 5.3-1. The stainless steel of the OP is modeled as a single stainless steel shell with a thickness that bounds the minimum combined stainless steel thickness in any direction, as deteimined in Table 5.3-2. For the HAC model, the foam of the OP credited for NCT is removed from the model. This bounds the maximum damage to the OP resulting from the HAC drop and puncture tests, as discussed in Chapter 2. Otherwise, the package geometry for the HAC and NCT shielding models is identical. As discussed in Chapter 2, the OP provides sufficient protection for the CCV so that it remains undamaged based on the sequence of HAC tests. Thus, for the HAC model the nominal CCV is modeled undamaged, and the I-meter dose rate is measured from the surface of the OP shell. 5.3.1.2 MCNP Shieldin Model - Source Geomet

• NAC International 5.3-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Multiple assumptions and approaches are used in the dose rate analysis to ensure bounding dose rate calculations, as discussed in Section 5.4.1. 5.3.1.3 MCNP Shielding Model - Tally Locations The MCNP dose rate calculations utilize cell tallies that determine the particle flux at the location of interest. The cell tallies are small void volumes, such that they do not affect the transport of particles in MCNP and the flux is not averaged over too large of an area. The cell tallies are approximately 100 cm 3 (i.e. 10 cm wide x 10 cm tall x 1 cm thick). The side package surface tally is formed with an arc with a 10° inner angle. The distances and locations for the MCNP tallies used to calculate external dose rates and establish compliance with all regulatory dose rates are determined based on the method of dose rate compliance used. Separate NCT dose rate models are used for Method 1 and Method 2 for dose rate calculations. These different methods are explained in detail in Section 5 .4.1.4. But for the purpose of tally locations, Method 1 models an array of the maximum number of packages (10) with the minimum allowable spacing on a trailer and Method 2 models a single package. All tally locations are based on the minimum allowable spacing between the package(s) and the respective regulatory dose rate location, as provided in Table 5.3-3. Note that in this table, all listed NCT dimensions are from the center the of the CCV cavity and the HAC dimension is from the outside of the CCV wall. The minimum spacing between the packages tied down on a trailer is an administratively set limit. The set requirement i minimum spacing will be guaranteed by the use of a pallet sized to these dimensions or measurements made when the packages are secured to the trailer. The MCNP models for the Method 1 and Method 2 NCT dose rate calculations showing the tally locations (shown in red) and distances are shown in Figure 5.3-4 and Figure 5.3-5, respectively. Note that the package surface dose rate for both methods is calculated using the Method 2 model. The MCNP model for the HAC dose rate calculations showing the tally location (shown in red) and distances is shown in Figure 5.3-6. The NCT package surface and HAC I-meter dose rates are only calculated out the side of the package because the top and bottom of the package provide a significantly larger shielding thickness (primarily from the CCV lid out the top and the support plate out the bottom) and distance between the source and dose location. NAC International 5.3-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.3.2 Material Properties The only material defined for the MCNP shielding model is Type 304 stainless steel (SS304) and polyurethane foam. The composition and density of this material is summarized in Table 5.3-4 and the MCNP neutron and photon input cards are shown in Table 5.3-5 .

• NAC International 5.3-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

                         - Primary MCNP Model Packa e Dimensions Table 5.3 Directional OP Stainless Steel Shell Combined Thickness NAC International                       5.3-4

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.3 MCNP Shielding Model - Tally Locations Regulatory Transport Distance to Tally Dose Rate Description Condition (cm) Location Package 54.16 On Side of deformed IL 12l Surface NCT!1l Trailer Surface 63.50 Based on minimum package spacing 13l 2-meter 263.50 Trailer Surface plus 2-meters Driver cab 609.60 Min. 20 ft required 141 HAC 1-meter 100.00 From Side of the OP outer shell Notes:

1. For Method 1, the package surface, trailer surface, and 2-meter cab distances are on the x-axis from the center of the middle package and the driver cab is the distance on the y-axis from the center front pair (See Figure 5.3-4). For Method 2, all distances are from the center of the package (See Figure 5.3-5).

2. Deformed from NCT drop (bounding deformation assumes 65% crush of OP foam).

3. Minimum Lateral Spacing of 50 in. requires at least 25 in. to trailer side.

4. Front package centerline spaced a minimum of 20 feet from driver cab .

• Table 5.3 Material Compositions 5S304 (8.00 g/cm 3 ) Polyurethane Foam (0.384 g/cm 3 )

Element Composition (wt3/4) Element Composition (wt3/4) C 4.0000E-04 H 4.1000E-02 Si 5.0000E-03 C 5.4400E-01 p 2.3000E-04 N 1.2100E-01 s 1.5000E-04 0 2.9400E-01 Cr 1.9000E-01 Mn 1.0000E-02 Fe 7.0173E-01 Ni 9.2500E-02

• NAC International 5.3-5

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.3 MCNP Material Definitions Photon Input Polyurethane Foam Carbon Steel SS304 (8.00 g/cm 3 ) (0.384 g/cm 3 ) (7.82 g/cm 3 ) 6000.84p -4.0000E-04 1000.84p -0.041 6000.84p -5.0000E-03 14000.84p -5.0000E-03 6000.84p -0.544 26000.84p -9.9500E-01 15000.84p -2.3000E-04 7000.84p -0.121 16000.84p

               -1.5000E-04       8000.84p       -0.294 24000.84p 25000.84p     -1.9000E-01 26000.84p     -1.0000E-02 28000.84p     -7.0173E-01
               -9.2500E-02 Neutron Input Polyurethane Foam             Carbon Steel SS304 (8.00 g/cm 3 )

(0.384 g/cm 3 ) (7.82 g/cm 3 ) 6000.80c -4.0000E-04 1001.80c -0.041 6000.80c -5.0000E-03 14028.80c -4.5933E-03 6000.80c -0.544 26054.80c -5.8158E-02 14029.80c -2.4168E-04 7014.80c -0.121 26056.80c -9.1295E-01 14030.80c -1.6499E-04 8016.80c -0.294 26057.80c -2.1084E-02 15031.80c -2.3000E-04 26058.80c -2.8059E-03 16032.80c -1.4207E-04 16033.80c -1.1568E-06 16034.80c -6.7534E-06 16036.80c -1.6825E-08 24050.80c -7.9300E-03 24052.80c -1.5903E-01 24053.80c -1.8380E-02 24054.80c -4.6614E-03 25055.80c -1.0000E-02 26054.80c -3.9617E-02 26056.S0c -6.4490E-01 26057.80c -1.5160E-02 26058.80c -2.0529E-03 28058.80c -6.2158E-02 28060.80c -2.4768E-02 28061.80c -1.0946E-03 28062.S0c -3.5472E-03 28064.80c -9.3254E-04 NAC International 5.3-6

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 5.3 MCNP Shielding Models -Package Geometries Figure 5.3 MCNP Shielding Model - NCT Source Configuration

• NAC International 5.3-7

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 5.3 MCNP Shielding Model - HAC Source Configuration NAC International 5.3-8

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 20 ft. I 2-rneters SO in *

• Figure 5.3 MCNP Shielding Model - NCT Method 1 Tally Locations NAC International 5.3-9

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 5.3 MCNP Shielding Model - NCT Method 2 Tally Locations Figure 5.3 MCNP Shielding Model - HAC Tally Locaiton NAC International 5.3-10

NAG PROPRIETARY )NFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.4 Shielding Evaluation 5.4.1 Methods For this dose rate analysis, the MCNP6 particle transport code is used to calculate external dose rates for the package and to demonstrate compliance with the regulatory dose rate limits in 10 CFR 71. Multiple assumptions and approaches are used in the dose rate analysis to ensure bounding dose rate calculations. The most significant approaches/assumptions are:

1. All 10 CFR 71 dose rate limits are reduced by 10%. This provides direct margin to the set activity limits.

2. The radioactive source material for TRU waste is generally distributed throughout attenuating media in the waste. Additionally, TRU waste is contained in a metal drum and/or liner which is secured in the cavity with additional shoring to provide structural stability for the contents.

• 3.

4. The energy grouping of the source spectra is evaluated by rounding up of all photon and neutron energies to the upper bound of each group. While the effect of rounding up of energies is strongly dependent on the spectrum of each isotope individually, it will always result in overestimated dose rates.

Additionally, NCT dose rates are measured prior to shipment. Pre-shipment dose rate measurements are not relied upon as a means for demonstrating compliance with §71.47 dose rate limits. However, these measurements are conducted prior to every shipment to provide assurance that the external dose rates are below the regulatory limits. Thus, the pre-shipment dose rate measurements are a helpful tool and support that the calculated dose rates in the shielding analysis are conservative and bounding .

• NAC International 5.4-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.4.1.1 Computer Codes - MCNP6 Dose rate calculations for this analysis are performed using MCNP6 [5.3] with the photon transport library MCPLIB84, which compiles data from the ENDF/B-VI.8 libra1y and the neutron transport library ENDF71x, which compiles data from the ENDFN-VII.l library [5.4]. MCNP is a Monte Carlo radiation-transport code that tracks multiple particle types. For the dose rates detennined herein, MCNP is used to tally neutron and photon fluxes in specific regions of interest, to calculate the resulting dose rates at each regulat01y dose rate location. 5.4.1.2 5.4.1.3 Dose Rate Calculations The dose rate, normalized per emitted particle, is calculated in MCNP by tallying the particle flux at each dose rate location and applying flux-to-dose rate conversion factors (see Table 5.4-1): D x,G,p [

                        - -*s mrem hr Emitted Particle
                                     ]
                                       =

cf>x,E,p [ Particles cm2 Emitted Particle l I

• DF p,E

                                                                               -  -]

mrem hr

                                                                               ~~~~l:

[EQN.1]

Where, Dx.G.p = MCNP output dose rate at location X, for particle type p from group G

        <j,X,E.p =    MCNP calculated flux at location X, for pm1icle type p tallied at energy E DFp.E =        flux-to-dose rate conversion factor for particle type p at energy E NAC International                                      5.4-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A To account for the uncertainty in the result of the statistical MCNP calculation, the calculated dose rate is increased by 2cr:

                                    -  -*s mrem hr Particle DerX,G,p [ Emitted l= DX,G,p + 2

• DX,G,p
• crX,G,p [EQN. 2]

Where, DfG,p = Dose rate at location X, for particle type p from group G including uncertainty Dx,G,p = MCNP output dose rate at location X, for particle type p from group G crx,G,p = Fractional standard deviation at location X, for particle type p from group G Using the MCNP calculated dose rates and the neutron and gamma source spectra of an isotope, a dose rate per curie of each isotope can be calculated for each location:

• mrem]

DR X,1- [ hr Where, Ci ( m

                      = N * ~ DerX,G,n

• E*1,G,n

[Emitted s Ci nl + m

                                                                ~ DerX,G,y

• E*1,G,y

[Emitted s Ci y]) [EQN. 3] DRx*,I Dose rate at location X from 1 Ci of isotope i N = Number of packages modeled (i.e., 10 for Method 1 and 1 for Method 2) Dxcr,G,n = Dose rate at location X, for neutrons from group G including uncertainty Dx,G,y = Dose rate at location X, for gammas from group G including uncertainty Emitted neutrons per second in energy group G, from 1 Ci of isotope i E*I,G,y = Emitted gammas per second in energy group G, from 1 Ci of isotope i m Number of neutron/gamma energy groups

• NAC International 5.4-3

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A With individual dose rate per curie values calculated, compliance is determined based on the regulatory dose rate limit and the dose rate per curie for the dose rate location and the respective isotope, as shown in Section 5.4.4.3. 5.4.1.4 Compliance Methods Compliance with regulatory dose rate limits may be demonstrated through one of two established methods. These methods are described below and are labeled 'Method 1' and 'Method 2'. It should be noted that for almost every case, the 2-meter dose rate location is bounding (i.e. the external dose rate at the 2-meter location reaches the regulatory limit at a lower activity than any other location). The only exception to this case is for shipments of 1 or 2 high activity packages under Method 2, where the package surface location may be limiting. However, this possibility is accounted for in Method 2. 5.4.1.4.1 Method 1 As discussed in Section 5.3.1.3 and shown in Figure 5.3-4, the MCNP shielding model for Method 1 analyzes an array of 6 or 10 packages arranged as they would be on a trailer, spaced apart based on the minimum required spacing. Each package has an equal source such that, for this method, the calculated dose rate is based on the same activity in each package. For example, a dose rate calculation for a 1 Curie source would be the resultant dose rate from 1 Curie of activity in each of the 10 packages. Thus, the activity limit calculated for each isotope is based on the limiting activity in all 10 packages. Because the activity limits are based on the maximum load in all 6 or 10 packages, compliance with regulatory dose rate limits for a given content through the sum of the fractions method can be demonstrated for each package on a conveyance, individually. As long as the sum of the fractions for each package in a conveyance is less than 1, individually, compliance with external dose rate limits has been demonstrated. Method 1 is considered the general method that is intended for use the majority of the time. This method minimizes the effort for the package user and allows for demonstration of compliance without knowing the specifics of a consignment (i.e. which packages and the arrangement on the trailer) ahead of time. The user requirements for demonstrating compliance with Method 1 are provided in Section 5.4.4.3.1 and an example of demonstrating compliance this method is provided in Appendix 5.5.2. NAC International 5.4-4

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 5.4.1.4.2 Method 2 As discussed in Section 5.3.1.3 and shown in Figure 5.3-5, the MCNP shielding model for Method 2 analyzes a single package with tally locations based on the minimum allowable spacing to each regulatory location. As this method analyzes a single package, the activity limit calculated for each isotope is based on the limiting activity in a single package. For Method 2, compliance is demonstrated based on a specified conveyance. For each package in the conveyance, the package surface, 2-meter, and HAC I-meter dose rates are calculated by the package user. When considering the whole conveyance, a Dose Rate Correction Factor (DRCF) is applied to the 2-meter dose rate from each package to account for the additional spacing between each package and the tally location. The corrected 2-meter dose rates are combined to determine the conveyance's 2-meter Total Dose Rate and demonstrate compliance. The inverse square law is used to determine the 2-meter DRCFs in order to account for the difference in dose rate contributions (due to reduced particle flux) from packages that are farther from the dose rate location of interest. To adjust the activity limit fraction (fn) for each package due to the additional spacing, the distance from the closest package used in the dose rate calculations (n) and the distance from the package of interest (n) are used to determine the 2-meter DRCF for each package (DRCF=ri2/ri2). When summing the activity limit fraction (fn) values to demonstrate compliance, the highest sum of the fraction value (fi) is multiplied by the largest DRCF. The second highest sum of the fraction value (fz) is multiplied by the second largest DRCF, and so on. This considers the worst-case arrangement of packages in the conveyance, with the highest activity packages closest to the 2-meter dose rate location. The distances used for determining the 10 package 2-meter DRCFs are shown in Figure 5.4-1, with the determined DRCFs are provided in Table 5.4-2. The distances used for determining the 6 package 2-meter DRCFs are shown in Figure 5.4-lA, with the determined DRCFs provided in Table 5.4-3. Depending on the different activities of the packages in the consignment, the peak 2-meter dose rate location could be directly in front of the center package or between the two highest activity packages. To account for this, as shown in Figure 5.4-1 and Figure 5.4-lA, the DRCFs are based on the minimum distance from each package to the closest of these two locations (i.e. straight out from package 1, or between packages 1 and 2). Method 2 is considered a more specific method that is intended for use when there is a package that does not pass using Method 1 (i.e. a sum of the fractions greater than 1). For this instance, it may be possible to still ship this package alone or paired with other very low activity packages using Method 2. This method requires the package user to set the packages in a consignment

• prior to demonstrating compliance with dose rate limits. The 10-package array (2x5) does not have a requirement on the exact arrangement of packages on the trailer, as Method 2 considers NAC International 5.4-5

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A the worst-case arrangement. However, for the 6-package array (1 x6) demonstrating compliance via Method 2, the arrangement of the packages on the trailer has requirements, as outlined in Appendix 5.5.2. The user requirements for demonstrating compliance with Method 2 are provided in Section 5.4.4.3.1 and an example of demonstrating compliance with this method is provided in Appendix 5.5.2. 5.4.2 Input and Output Data Input data for source terms and geometry/materials are summarized in Sections 5.2 and 5.3, respectively. A sample MCNP input file for 1.0 MeV neutron emission under NCT with side detectors is shown in Figure 5.4-2. The tally fluctuation chart and probability density function plot were studied for each MCNP tally to ensure proper tally bin convergence. This, along with a check of the reported fractional standard deviation (cr) for each tally bin and the additional statistical information reported for MCNP tallies, ensures the reliability of all MCNP calculated dose rate results. 5.4.3 Flux-to-Dose Rate Conversion Consistent with guidance of Section 5.5.4.3 ofNUREG-1617 [5.5], the ANSI/ANS-6.1.1 1977 [5.6] gamma and neutron flux-to-dose rate conversion factors are used. The specific values are listed in Table 5.4-1. 5.4.4 External Radiation Levels 5.4.4.1 Calculated NCT and HAC Radiation Levels Table 5.4-4 and Table 5.4-5 list the calculated 10 package Method 1 dose rates for each energy group for photons and neutrons, respectively. Table 5 .4-6 and Table 5.4-7 list the calculated 10 package Method 2 dose rates for each energy group for photons and neutrons, respectively. The 6 package dose rates are listed in Appendix 5.6. The results in these tables are based directly on the results from MCNP and include the 2cr uncertainty. Thus, the units are in (mrem/hr)*(s/emittedparticle), where the emitted particle is either neutrons or gammas (see EQN 1 in Section 5 .4.1.3). When these values are multiplied by the source spectrum of a given isotope, which has units of (emitted particle/s)/Ci, the resulting value is a dose rate per curie, in (mrem/hr)/Ci. NAO International 5.4-6

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.4.4.2 Calculating Isotopic Dose Rate/Ci Values and Activity Limits As MCNP calculates dose rates for energy groups for individual gamma and neutron energies, additional calculations are required to demonstrate compliance with the 10 CPR 71 dose rate requirements. To calculate the contribution to external dose rates from an individual isotope, a dose rate/Ci value is calculated for each isotope at each dose rate location. To do this, the ORIGEN code in the SCALE6.2 code package is used to determine grouped neutron and gamma energy spectra from 1 Ci of the isotope of interest. This code can be used to group the neutron and gamma spectra into the group structures shown in Table 5.2-1 and Table 5.2-2. By default, the grouped energy spectra for the isotope output by the ORI GEN code account for secondary particles (Bremsstrahlung and a.,n) based on interactions in a UO2 matrix. As an example, the grouped spectrum for 1 Ci of Cf-252 from the ORI GEN code is shown in Table 5.4-8. Using the grouped source spectrum from 1 Ci of the isotope, the dose rate/Ci of the isotope at a dose rate location can be calculated by multiplying the emissions in each energy group by the respective dose rate per emitted particle at the dose rate location of interest (see EQN 3 in Section 5.4.1.3). For Method 1, the isotopic dose rate/Ci value is then used to determine the activity limit of the isotope (see EQN 4 in Section 5.4.4.3). As an example, the dose rate/Ci and activity limit calculation of Cf-252 is shown in Table 5 .4-9 for Method 1. By summing the total neutron and photon dose rates calculated in the table, the Method 1 total 2-meter dose rate/Ci of Cf-252 is 2,307 mrem/hr/Ci (i.e. 64 + 2,243). With the calculated dose rate/Ci values, the Cf-252 activity limits for Method 1 are calculated (see EQN 4 in Section 5.4.4.3). The overall activity limit for each isotope is set based on the bounding 2-meter location. Thus, the Method 1 activity limit for Cf-252 is 3.901E-03 Ci (i.e. 9 7 2,307). For Method 2, the isotopic dose rate/Ci value is then used to determine the package surface, 2-meter dose rate, and HAC I-meter dose rates for the isotope at the regulatory dose location. The 2-meter DRCFs are then applied to the 2-meter dose rate contribution of each package to determine the consignment's 2-meter Total Dose Rate. As an example, the dose rate/Ci and activity limit calculation of Cf-252 is shown in Table 5 .4-10 for Method 2. By summing the total neutron and photon dose rates calculated in the table, the Method 2 2-meter dose rate/Ci of Cf-252 is 572 mrem/hr/Ci (i.e. 18 + 554). With the calculated dose rate/Ci values, compliance under Method 2 for Cf-252 can be determined based on the radionuclide inventory of the package and consignment per Section 5.4.4.3.2 . NAC International 5.4-7

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A If an isotope has no significant emissions in the ORI GEN source (i.e. all gamma and neutron emissions less than the respective lower energy bound) or the calculated isotope activity limit is greater than IE+08 Ci, the activity limit for the isotope may be considered unlimited and it may be neglected from dose rate calculations. However, all radionuclides in a package must be considered for the calculation of the total decay heat of the contents. 5.4.4.3 Demonstrating Compliance with 10 CFR 71 Dose Rate Requirements Any contents that are to be transported in the package must be characterized, such that there is a determined activity, in Ci, of each isotope present. Using the activity of each isotope in the contents and the respective activity limit for Method 1 and dose rates per Curie for Method 2, determined as described in Section 5.4.4.2, compliance with regulatory dose rate limits is demonstrated. The exact process of demonstrating compliance using Method 1 or Method 2 is described below. 5.4.4.3.1 Compliance with Method 1 When using Method 1, each package is considered individually. For each package, compliance with external dose rates is demonstrated by using the sum of the fractions method (See EQN 5 in Section 5.4.1.3) with the source term of the contents and the Method 1 activity limits for each respective isotope. The activity limit is set based on the minimum value calculated across all regulatory dose rate locations: [mrem] DRx,Limit h r ALimit,i[Ci] = Min [EQN. 4] mrem] DRx,i [ t

Where, ALimit,i = Activity limit of isotope i, in Ci DRx,Limit = 90% ofregulatory dose rate limit at location X (e.g., 9 mrem/hr for 2m)

DRx,i Dose rate at location X from 1 Ci of isotope i Compliance with dose rates is demonstrated through the sum of fractions method, using the activity limit and known activity for each isotope in the contents. As long as the sum of the fractions is less than 1, external dose rates will be less than the regulatory limits: NAC International 5.4-8

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A [EQN. 5] Where, Ai = Activity of isotope i, in Ci ALimit,i = Activity limit of isotope i, in Ci I = Number of isotopes If the sum of the fractions is less than 1 for every package, individually, compliance with external dose rate limits has been demonstrated and the packages can be shipped in any combination. Note, that if any value is rounded, it should always be rounded up to ensure that the actual sum never exceeds 1 due to rounding. 5.4.4.3.2 Compliance with Method 2 When using Method 2, a consignment of packages is analyzed as a group. For Method 2, a multiplier (DRCF) is applied to the 2-meter dose rate of each of the individual packages to determine the consignment's combined, bounding 2-meter dose rate. Using the dose rates per Curie in Table 5.4-11 for the 2x5 package group and Table 5 .5-9 for the 1x6 package group, the resulting dose rate for a given content is calculated at the package surface, 2-meter, and HAC I-meter regulatory dose rate locations as: mrem I [mreml

                                                       ~          .                        [EQN. 6]

DRxn[-]= ~DRxi - . *Ai[c1]

                             '     hr      L i=l
                                                    '    C1 Where, DRx,n         Total dose rate at regulatory location X for package n DRx,i         Dose Rate at location X from 1 Ci of isotope i
                    =  Activity limit of isotope i, in Ci I          =  Number of isotopes in package n To demonstrate compliance with the 2-meter dose rate location, the 2-meter Total Dose Rate is determined using the 2-meter DRCFs calculated in Table 5.4-2, which are applied to the 2-meter dose rates for each of the packages in the consignment. The 2-meter dose rates from each

• individual package (fn) are always arranged in the table in decreasing order to maximize the NAO International 5.4-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A calculated total and ensure a bounding calculation. Thus, compliance with the 2-meter dose rate requirement is demonstrated as: N

                        ~

L [mrem] DRx,n ~

• DRCFn :s; 9 ~

[mrem] [EQN. 7] n=l

Where, fn = Total dose rate at regulatory location X for package n DRCFn Method 2 meter Dose Rate Correction Factor for package n N = Number of packages in the conveyance If the 2-meter Total Dose Rate value calculated using EQN 7 is less than 9 mrem/hr, and the maximum package surface and HAC 1-meter dose rates of the consignment are less than 180 mrem/hr and 900 mrem/hr, respectively, compliance with external dose rate limits has been demonstrated and the packages in the analyzed conveyance can be shipped in any arrangement.

Note that, if any value is rounded, it should always be rounded up to ensure that the calculated dose rates never exceed their respective limits due to rounding. NAC International 5.4-10

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 ANSI/ANS-6.1.11977 Flux-to-Dose Conversion Factors Gamma Conversion Factors Neutron Conversion Factors Gamma Energy Conversion Factor Neutron Energy Conversion Factor (MeV) (mrem/hr)/(y/cm 2 -s) (MeV) (mrem/hr)/(n/cm 2 -s) 0.01 3.96E-03 2.50E-08 3.67E-03 0.03 5.82E-04 1.00E-07 3.67E-03 0.05 2.90E-04 1.00E-06 4.46E-03 0.07 2.58E-04 1.00E-05 4.54E-03 0.10 2.83E-04 1.00E-04 4.18E-03 0.15 3.79E-04 1.00E-03 3.76E-03 0.20 5.01E-04 1.00E-02 3.56E-03 0.25 6.31E-04 1.00E-01 2.17E-02 0.30 7.59E-04 5.00E-01 9.26E-02 0.35 8.78E-04 1.00E+00 1.32E-01 0.40 9.85E-04 2.50E+00 1.25E-01 0.45 1.08E-03 5.00E+00 1.56E-01 0.50 1.17E-03 7.00E+00 1.47E-01 0.55 1.27E-03 1.00E+01 1.47E-01 0.60 1.36E-03 1.40E+01 2.08E-01 0.65 1.44E-03 2.00E+01 2.27E-01 0.70 1.52E-03 --- --- 0.80 1.68E-03 --- --- 1.00 1.98E-03 --- --- 1.40 2.51E-03 --- --- 1.80 2.99E-03 --- --- 2.20 3.42E-03 --- --- 2.60 3.82E-03 --- --- 2.80 4.01E-03 --- --- 3.25 4.41 E-03 --- --- 3.75 4.83E-03 --- --- 4.25 5.23E-03 --- --- 4.75 5.60E-03 --- --- 5.00 5.80E-03 --- --- 5.25 6.01 E-03 --- --- 5.75 6.37E-03 --- --- 6.25 6.74E-03 --- --- 6.75 7.11 E-03 --- --- 7.50 7.66E-03 --- --- 9.00 8.77E-03 --- --- 11.0 1.03E-02 --- --- 13.0 1.18E-02 --- --- 15.0 1.33E-02 NAC International 5.4-11

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.4 Method 2 meter DRCFs - 10 Package Configuration Package# Distance to Tally (cm) DRCF (n) X y rn 1 263.5 0 263.50 1 2 263.5 91.44 278.91 0.893 3 263.5 182.88 320.74 0.675 4 263.5 274.32 380.37 0.480 5 390.5 0 390.50 0.455 6 390.5 91.44 401.06 0.432 7 390.5 182.88 431.20 0.373 8 263.5 365.76 450.79 0.342 9 390.5 274.32 477.22 0.305 10 390.5 365.76 535.04 0.243 Table 5.4 Method 2 meter DRCFs - 6 Package Configuration Package# Distance to Tally (cm) DRCF (n) X y rn 1 327.0 0 327.00 1.000 2 327.0 91.44 339.54 0.927 3 327.0 182.88 374.67 0.762 4 327.0 274.32 426.83 0.587 5 327.0 365.76 490.62 0.444 6 327.0 457.20 562.10 0.338 NAC International 5.4-12

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 MCNP Method 1 Gamma Dose Rate Summary Dose Rates (mrem/hr*s/emitted y) Energy NCT HAC (MeV) Package Surface Trailer Surface 2-Meter Driver Cab 1-meter 12.00 1.750E-07 1.662E-07 2.822E-08 3.343E-09 4.434E-08 10.00 1.522E-07 1.445E-07 2.442E-08 2.922E-09 3.861 E-08 8.00 1.293E-07 1.225E-07 2.080E-08 2.478E-09 3.295E-08 6.00 1.061 E-07 1.002E-07 1.691 E-08 1.996E-09 2.718E-08 4.00 8.030E-08 7.486E-08 1.258E-08 1.482E-09 2.078E-08 3.00 6.493E-08 6.010E-08 1.002E-08 1.147E-09 1.695E-08 2.50 5.612E-08 5.138E-08 8.539E-09 9.687E-10 1.474E-08 2.00 4.625E-08 4.196E-08 6.969E-09 7.810E-10 1.228E-08 1.80 4.205E-08 3.786E-08 6.248E-09 7.145E-10 1.117E-08 1.50 3.524E-08 3.150E-08 5.139E-09 5.687E-10 9.441 E-09 1.34 3.142E-08 2.788E-08 4.558E-09 5.115E-10 8.474E-09 1.20 2.797E-08 2.463E-08 4.022E-09 4.524E-10 7.570E-09 1.00 2.287E-08 1.991E-08 3.240E-09 3.514E-10 6.235E-09 0.90 2.026E-08 1.754E-08 2.824E-09 3.156E-10 5.535E-09 0.80 1.760E-08 1.512E-08 2.429E-09 2.721E-10 4.814E-09 0.70 1.489E-08 1.276E-08 2.042E-09 2.195E-10 4.091E-09 0.67 1.407E-08 1.204E-08 1.917E-09 2.083E-10 3.867E-09 0.60 1.215E-08 1.034E-08 1.650E-09 1.781E-10 3.334E-09 0.50 9.262E-09 7.851E-09 1.235E-09 1.335E-10 2.551E-09 0.40 6.391E-09 5.382E-09 8.499E-10 9.528E-11 1.772E-09 0.30 3.499E-09 2.929E-09 4.459E-10 4.917E-11 9.684E-10 0.20 9.864E-10 8.393E-10 1.274E-10 1.449E-11 2.691 E-10 0.10 2.074E-12 1.767E-12 2.815E-13 2.737E-14 5.625E-13 0.075 6.886E-16 6.075E-16 8.640E-17 9.584E-18 1.970E-16

• NAC International 5.4-13

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.4 MCNP Method 1 Neutron Dose Rate Summary Dose Rates (mrem/hr*s/emitted n) Energy NCT HAC (MeV) Package Surface Trailer Surface 2-Meter Driver Cab 1-meter 20.00 6.019E-06 5.958E-06 1.009E-06 1.171E-07 1.631E-06 15.00 5.377E-06 5.226E-06 8.812E-07 1.008E-07 1.452E-06 10.00 3.993E-06 3.853E-06 6.452E-07 7.326E-08 1.057E-06 7.50 4.108E-06 3.907E-06 6.547E-07 7.210E-08 1.104E-06 5.00 4.108E-06 3.907E-06 6.547E-07 7.198E-08 1.104E-06 4.00 3.884E-06 3.679E-06 6.130E-07 6.678E-08 1.049E-06 3.00 3.792E-06 3.620E-06 6.061E-07 6.572E-08 1.011 E-06 2.50 3.712E-06 3.509E-06 5.844E-07 6.209E-08 9.898E-07 2.25 3.643E-06 3.448E-06 5.767E-07 6.209E-08 9.879E-07 2.00 3.568E-06 3.352E-06 5.600E-07 6.166E-08 . 9.879E-07 1.75 3.494E-06 3.226E-06 5.427E-07 5.890E-08 9.510E-07 1.50 3.382E-06 3.169E-06 5.256E-07 5.839E-08 9.510E-07 3.334E-06 3.089E-06 5.124E-07 5.751E-08 9.580E-07 1.25 1.10 3.199E-06 2.920E-06 4.820E-07 5.311 E-08 9.580E-07 1.00 3.120E-06 2.835E-06 4.672E-07 5.045E-08 9.515E-07 0.90 3.120E-06 2.835E-06 4.672E-07 5.045E-08 9.530E-07 0.80 2.946E-06 2.648E-06 4.408E-07 4.704E-08 9.530E-07 0.70 2.647E-06 2.437E-06 4.012E-07 4.465E-08 8.646E-07 0.60 2.346E-06 2.121 E-06 3.567E-07 3.996E-08 7.974E-07 0.50 1.969E-06 1.737E-06 2.886E-07 3.178E-08 7.368E-07 0.40 1.489E-06 1.303E-06 2.201E-07 2.348E-08 5.665E-07 0.30 1.077E-06 9.372E-07 1.585E-07 1.711 E-08 4.319E-07 0.20 6.877E-07 5.974E-07 1.003E-07 1.039E-08 2.972E-07 0.10 3.247E-07 2.847E-07 4.852E-08 4.986E-09 1.420E-07 NAC International 5.4-14

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 MCNP Method 2 Gamma Dose Rate Summary Dose Rates (mrem/hr*s/emitted y) Energy NCT HAC (MeV) Package Surface Trailer Surface 2-Meter Driver Cab 1-meter 12.00 1.750E-07 1.265E-07 7.401 E-09 1.395E-09 4.434E-08 10.00 1.522E-07 1.099E-07 6.440E-09 1.215E-09 3.861E-08 8.00 1.293E-07 9.329E-08 5.460E-09 1.031 E-09 3.295E-08 6.00 1.061 E-07 7.635E-08 4.460E-09 8.398E-10 2.718E-08 4.00 8.030E-08 5.753E-08 3.353E-09 6.334E-10 2.078E-08 3.00 6.493E-08 4.637E-08 2.695E-09 5.087E-10 1.695E-08 2.50 5.612E-08 3.997E-08 2.317E-09 4.376E-10 1.474E-08 2.00 4.625E-08 3.282E-08 1.891 E-09 3.550E-10 1.228E-08 1.80 4.205E-08 2.977E-08 1.709E-09 3.199E-10 1.117E-08 1.50 3.524E-08 2.483E-08 1.415E-09 2.657E-10 9.441 E-09 1.34 3.142E-08 2.209E-08 1.253E-09 2.339E-10 8.474E-09 1.20 2.797E-08 1.962E-08 1.110E-09 2.086E-10 7.570E-09 2.287E-08 1.599E-08 8.945E-10 1.671 E-10 6.235E-09 1.00 0.90 2.026E-08 1.414E-08 7.888E-10 1.459E-10 5.535E-09 0.80 1.760E-08 1.224E-08 6.786E-10 1.261E-10 4.814E-09 0.70 1.489E-08 1.034E-08 5.688E-10 1.049E-10 4.091E-09 0.67 1.407E-08 9.757E-09 5.342E-10 9.953E-11 3.867E-09 0.60 1.215E-08 8.402E-09 4.583E-10 8.384E-11 3.334E-09 0.50 9.262E-09 6.400E-09 3.459E-10 6.387E-11 2.551E-09 0.40 6.391E-09 4.410E-09 2.341 E-10 4.310E-11 1.772E-09 0.30 3.499E-09 2.415E-09 1.269E-10 2.351 E-11 9.684E-10 0.20 9.864E-10 6.827E-10 3.559E-11 6.573E-12 2.691 E-10 0.10 2.074E-12 1.465E-12 7.533E-14 1.389E-14 5.625E-13 0.075 6.886E-16 4.931E-16 2.537E-17 4.654E-18 1.970E-16

• NAC International 5.4-15

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Energy Table 5.4 MCNP Method 2 Neutron Dose Rate Summary Dose Rates (mrem/hr*s/emitted n) NCT Revision 20A HAC (MeV) Package Surface Trailer Surface 2-Meter Driver Cab 1-meter 20.00 6.019E-06 4.191 E-06 2.409E-07 4.514E-08 1.631 E-06 15.00 5.377E-06 3.743E-06 2.137E-07 3.954E-08 1.452E-06 10.00 3.993E-06 2.761E-06 1.558E-07 2.871E-08 1.057E-06 7.50 4.108E-06 2.833E-06 1.604E-07 2.930E-08 1.104E-06 5.00 4.108E-06 2.833E-06 1.604E-07 2.930E-08 1.104E-06 4.00 3.884E-06 2.674E-06 1.494E-07 2.757E-08 1.049E-06 3.00 3.792E-06 2.613E-06 1.458E-07 2.703E-08 1.011E-06 2.50 3.712E-06 2.550E-06 1.420E-07 2.618E-08 9.898E-07 2.25 3.643E-06 2.512E-06 1.398E-07 2.540E-08 9.879E-07 2.00 3.568E-06 2.454E-06 1.379E-07 2.522E-08 9.879E-07 1.75 3.494E-06 2.400E-06 1.339E-07 2.448E-08 9.510E-07 1.50 3.382E-06 2.342E-06 1.320E-07 2.442E-08 9.510E-07 1.25 3.334E-06 2.300E-06 1.278E-07 2.350E-08 9.580E-07 1.10 3.199E-06 2.191 E-06* 1.226E-07 2.241E-08 9.580E-07 1.00 3.120E-06 2.138E-06 1.190E-07 2.195E-08 9.515E-07 0.90 3.120E-06 2.138E-06 1.190E-07 2.195E-08 9.530E-07 0.80 2.946E-06 2.019E-06 1.130E-07 2.070E-08 9.530E-07 0.70 2.647E-06 1.828E-06 1.036E-07 1.895E-08 8.646E-07 0.60 2.346E-06 1.619E-06 9.086E-08 1.674E-08 7.974E-07 0.50 1.969E-06 1.351 E-06 7.541E-08 1.392E-08 7.368E-07 0.40 1.489E-06 1.025E-06 5.727E-08 1.044E-08 5.665E-07 0.30 1.077E-06 7.355E-07 4.146E-08 7.554E-09 4.319E-07 0.20 6.877E-07 4.716E-07 2.606E-08 4.740E-09 2.972E-07 0.10 3.247E-07 2.240E-07 1.257E-08 2.264E-09 1.420E-07 NAC International 5.4-16

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 ORIGEN Grouped Cf-252 Spectra Photon Spectrum Neutron Spectrum Energy Emissions Energy Range Emissions Group Range Group (y/s/Ci) (MeV) (n/s/Ci) (MeV) 1 (10-12) 1.9100E+05 1 (15-20) 2.7589E+05 2 (8.0-10) 2.6093E+06 2 (10-15) 1.1338E+07 3 (6.0- 8.0) 2.3082E+07 3 (7.5 - 10) 5.6069E+07 4 (4.0- 6.0) 2.0419E+08 4 (5.0 - 7.5) 2.8751E+08 5 (3.0 -4.0) 4.5451E+08 5 (4.0 - 5.0) 3.0533E+08 6 (2.5- 3.0) 4.9616E+08 6 (3.0 -4.0) 5.2541E+08 7 (2.0-2.5) 8.5568E+08 7 (2.5 -3.0) 3.7627E+08 8 (1.8 - 2.0) 4.3330E+08 8 (2.25 -2.5) 2.2137E+08 9 (1.5-1.8) 1.2390E+09 9 (2.0-2.25) 2.4451E+08 10 (1.34 - 1.5) 7.2360E+08 10 (1.75-2.0) 2.6755E+08 11 (1.2 - 1.5) 9.3690E+08 11 (1.5-1.75) 2.8937E+08 12 (1.0-1.2) 2.1195E+09 12 (1.25 -1.5) 3.0832E+08 13 (0.9- 1.0) 1.0598E+09 13 (1.1-1.25) 1.9202E+08 14 (0.8 - 0.9) 1.0598E+09 14 (1.0-1.1) 1.2995E+08 15 (0.7- 0.8) 1.0561E+09 15 (0.9 -1.0) 1.3076E+08 16 (0.67 - 0.7) 3.1575E+08 16 (0.8 - 0.9) 1.3076E+08 17 (0.6 - 0.67) 7.3675E+08 17 (0.7 - 0.8) 1.2976E+08 18 (0.5 - 0.6) 1.0525E+09 18 (0.6 - 0.7) 1.2754E+08 19 (0.4- 0.5) 1.0525E+09 19 (0.5 -0.6) 1.2377E+08 20 (0.3- 0.4) 1.0525E+09 20 (0.4 - 0.5) 1.1801E+08 21 (0.2- 0.3) 5.2625E+08 21 (0.3 - 0.4) 1.0960E+08 22 (0.1 - 0.2) 5.6748E+06 22 (0.2 -0.3) 9.7417E+07 23 (0.075 - 0.1) 0.0000E+00 23 (0.1 - 0.2) 7.9088E+07 24 (0.05 - 0.075) 0.0000E+00 24 (0.05- 0.1) 2.9046E+07 Total 1.5406E+10 Total 4.2910E+09

• NAC International 5.4-17

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.4 Method 1 - Cf-252 2-meter Dose Rate/Ci and Activity Limit Calculation Photon Dose Rate Neutron Dose Rate Emissions MCNP 2m DR Total 2m DR Emissions MCNP 2m DR Total 2m DR Group Group (y/s/Ci) (mrem/hr-s/y) (mrem/hr/Ci) (n/s/Ci) (mrem/hr-s/n) (mrem/hr/Ci) 1 1.9100E+05 2.822E-08 5.390E-03 1 2.7589E+05 1.009E-06 2.784E-01 2 2.6093E+06 2.442E-08 6.372E-02 2 1.1338E+07 8.812E-07 9.991E+00 3 2.3082E+07 2.080E-08 4.801E-01 3 5.6069E+07 6.452E-07 3.618E+01 4 2.0419E+08 1.691E-08 3.453E+00 4 2.8751E+08 6.547E-07 1.882E+02 5 4.5451E+08 1.258E-08 5.718E+00 5 3.0533E+08 6.547E-07 1.999E+02 6 4.9616E+08 1.002E-08 4.972E+00 6 5.2541E+08 6.130E-07 3.221E+02 7 8.5568E+08 8.539E-09 7.307E+00 7 3.7627E+08 6.061E-07 2.281E+02 8 4.3330E+08 6.969E-09 3.020E+00 8 2.2137E+08 5.844E-07 1.294E+02 9 1.2390E+09 6.248E-09 7.741E+00 9 2.4451E+08 5.767E-07 1.410E+02 10 7.2360E+08 5.139E-09 3.719E+00 10 2.6755E+08 5.600E-07 1.498E+02 11 9.3690E+08 4.558E-09 4.270E+00 11 2.8937E+08 5.427E-07 1.570E+02 12 2.1195E+09 4.022E-09 8.525E+00 12 3.0832E+08 5.256E-07 1.621E+02 13 1.0598E+09 3.240E-09 3.434E+00 13 1.9202E+08 5.124E-07 9.839E+01 14 1.0598E+09 2.824E-09 2.993E+00 14 1.2995E+08 4.820E-07 6.264E+01 15 1.0561 E+09 2.429E-09 2.565E+00 15 1.3076E+08 4.672E-07 6.109E+01 16 3.1575E+08 2.042E-09 6.448E-01 16 1.3076E+08 4.672E-07 6.109E+01 17 7.3675E+08 1.917E-09 1.412E+00 17 1.2976E+08 4.408E-07 5.720E+01 18 1.0525E+09 1.650E-09 1.737E+00 18 1.2754E+08 4.012E-07 5.117E+01 19 1.0525E+09 1.235E-09 1.300E+00 19 1.2377E+08 3.567E-07 4.415E+01 20 1.0525E+09 8.499E-10 8.945E-01 20 1.1801E+08 2.886E-07 3.406E+01 21 5.2625E+08 4.459E-10 2.347E-01 21 1.0960E+08 2.201E-07 2.412E+01 22 5.6748E+06 1.274E-10 7.230E-04 22 9.7417E+07 1.585E-07 1.544E+01 23 0.0000E+00 2.815E-13 0.000E+00 23 7.9088E+07 1.003E-07 7.933E+00 24 0.0000E+00 0.0000E+00 0.000E+00 24 2.9046E+07 4.852E-08 1.409E+00 Total 6.449E+01 Total 2.243E+03 NAC International 5.4-18

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.4 Method 2 - Cf-252 2-meter Dose Rate/Ci and Activity Limit Calculation Photon Dose Rate Neutron Dose Rate Emissions MCNP 2m DR Total 2m DR Emissions MCNP 2m DR Total 2m DR Group Group (y/s/Ci) (mrem/hr-s/y) (mrem/hr/Ci) (n/s/Ci) (mrem/hr-s/n) (mrem/hr/Ci) 1 1.9100E+05 7.401 E-09 1.414E-03 1 2.7589E+05 2.409E-07 6.646E-02 2 2.6093E+06 6.440E-09 1.680E-02 2 1.1338E+07 2.137E-07 2.423E+00 3 2.3082E+07 5.460E-09 1.260E-01 3 5.6069E+07 1.558E-07 8.736E+00 4 2.0419E+08 4.460E-09 9.107E-01 4 2.8751 E+08 1.604E-07 4.612E+01 5 4.5451 E+08 3.353E-09 1.524E+00 5 3.0533E+08 1.604E-07 4.897E+01 6 4.9616E+08 2.695E-09 1.337E+00 6 5.2541E+08 1.494E-07 7.850E+01 7 8.5568E+08 2.317E-09 1.983E+00 7 3.7627E+08 1.458E-07 5.486E+01 8 4.3330E+08 1.891 E-09 8.194E-01 8 2.2137E+08 1.420E-07 3.143E+01 9 1.2390E+09 1.709E-09 2.117E+00 9 2.4451 E+08 1.398E-07 3.418E+01 10 7.2360E+08 1.415E-09 1.024E+00 10 2.6755E+08 1.379E-07 3.690E+01 11 9.3690E+08 1.253E-09 1.174E+00 11 2.8937E+08 1.339E-07 3.875E+01 12 2.1195E+09 1.110E-09 2.353E+00 12 3.0832E+08 1.320E-07 4.070E+01

• 13 14 15 16 1.0598E+09 1.0598E+09 1.0561E+09 3.1575E+08 8.945E-10 7.888E-10 6.786E-10 5.688E-10 9.480E-01 8.360E-01 7.167E-01 1.796E-01 13 14 15 16 1.9202E+08 1.2995E+08 1.3076E+08 1.3076E+08 1.278E-07 1.226E-07 1.190E-07 1.190E-07 2.454E+01 1.593E+01 1.556E+01 1.556E+01 17 7.3675E+08 5.342E-10 3.936E-01 17 1.2976E+08 1.130E-07 1.466E+01 18 1.0525E+09 4.583E-10 4.824E-01 18 1.2754E+08 1.036E-07 1.321 E+01 19 1.0525E+09 3.459E-10 3.641 E-01 19 1.2377E+08 9.086E-08 1.125E+01 20 1.0525E+09 2.341 E-10 2.464E-01 20 1.1801E+08 7.541E-08 8.899E+00 21 5.2625E+08 1.269E-10 6.678E-02 21 1.0960E+08 5.727E-08 6.277E+00 22 5.6748E+06 3.559E-11 2.020E-04 22 9.7417E+07 4.146E-08 4.039E+00 23 0.O000E+00 7.533E-14 O.000E+O0 23 7.9088E+07 2.606E-08 2.061E+00 24 0.000OE+00 2.537E-17 0.000E+00 24 2.9046E+07 1.257E-08 3.651 E-01 Total 1.762E+01 Total 5.540E+02
• NAC International 5.4-19

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.4 Bare Cask Dose Rate/Ci and Maximum Activities (6 Pages) Activity Limit NCT Dose Rate HAC Dose Rate (Ci) (mrem/hr/Ci) (mrem/hr/Ci) Isotope Method 2 Method 1 1-meter Package Surface 2-meter Ac225 2.516E+01 2.738E+00 1.003E-01 7.520E-01 Ac227 5.870E+03 1.181E-02 4.299E-04 3.239E-03 Ac228 8.324E-02 7.639E+02 2.986E+01 2.076E+02 Aq108 2.353E+00 2.844E+01 1.067E+00 7.819E+00 Aq108m 4.821E-02 1.369E+03 5.215E+01 3.758E+02 Aq109m 2.336E+04 2.839E-03 1.031E-04 7.701E-04 Aq110 8.218E-01 8.056E+01 3.049E+00 2.209E+01 Aq110m 2.659E-02 2.407E+03 9.395E+01 6.548E+02 Am241 3.091E+03 2.160E-02 7.970E-04 5.922E-03 Am242 1.926E+01 3.616E+00 1.306E-01 9.878E-01 Am242m 2.387E+03 2.926E-02 1.057E-03 8.001E-03 Am243 2.629E+02 2.642E-01 9.551E-03 7.209E-02 Am245 4.803E+00 1.460E+01 5.292E-01 4.023E+00 Am246 1.076E-01 6.132E+02 2.337E+01 1.683E+02 At217 4.758E+02 1.405E-01 5.262E-03 3.867E-02 Au198 2.003E-01 3.367E+02 1.258E+01 9.272E+01 Ba133 3.064E-01 2.213E+02 8.103E+O0 6.135E+01 Ba137m 1.412E-01 4.680E+02 1.777E+01 1.286E+02 Ba140 4.682E-01 1.423E+02 5.344E+00 3.910E+01 Be10 9.660E+01 7.196E-01 2.611E-02 1.979E-01 Bi207 4.817E-02 1.320E+03 5.165E+01 3.585E+02 Bi210 1.386E+01 4.939E+00 1.814E-01 1.360E+00 Bi211 2.198E+00 3.080E+01 1.128E+00 8.536E+00 Bi212 6.263E-01 1.019E+02 3.984E+00 2.762E+01 Bi213 6.525E-01 1.031E+02 3.860E+00 2.837E+01 Bi214 4.599E-02 1.351E+03 5.381E+01 3.630E+02 Bk247 1.491 E+00 4.725E+01 1.712E+00 1.305E+01 Bk249 1.677E+05 3.702E-04 1.392E-05 1.037E-04 Bk250 7.613E-02 8.285E+02 3.265E+01 2.250E+02 C14 3.470E+04 2.008E-03 7.244E-05 5.477E-04 Ca45 2.207E+03 3.160E-02 1.140E-03 8.627E-03 Cd113 9.249E+02 7.546E-02 2.725E-03 2.064E-02 Cd113m 9.458E+01 7.351 E-01 2.668E-02 2.022E-01 Cd115m 1.507E+00 4.278E+01 1.653E+00 1.167E+01 Ce139 2.408E+00 2.894E+01 1.044E+00 7.897E+00 Ce141 3.874E+00 1.799E+01 6.493E-01 4.910E+00 Ce144 1.700E+01 4.102E+00 1.480E-01 1.119E+00 Cf249 3.403E-01 1.992E+02 7.291E+00 5.519E+01 Cf250 1.971 E-01 2.969E+02 1.145E+01 8.808E+01 Cf251 2.105E+00 3.325E+01 1.202E+00 9.120E+00 Cf252 Cf253 NAC International 3.901 E-03 1.623E+03 1.480E+04 4.298E-02 5.4-20 5.716E+02 1.q51 E-03 4.182E+03 1.174E-02

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 Bare Cask Dose Rate/Ci and Maximum Activities (6 Pages) Activity Limit NCT Dose Rate HAC Dose Rate (Ci) (mrem/hr/Ci) (mrem/hr/Ci) Isotope Method 2 Method 1 1-meter Package Surface 2-meter Cf254 1.386E-04 4.221E+05 1.628E+04 1.253E+05 Cl36 4.527E+01 1.524E+00 5.563E-02 4.193E-01 Cm240 3.027E+03 1.958E-02 7.468E-04 5.461 E-03 Cm242 2.136E+03 2.749E-02 1.057E-03 7.735E-03 Cm243 1.456E+00 4.834E+01 1.751E+00 1.334E+01 Cm244 1.228E+02 4.713E-01 1.820E-02 1.338E-01 Cm245 3.295E+00 2.116E+01 7.633E-01 5.772E+00 Cm246 5.536E-01 1.045E+02 4.037E+00 2.974E+01 Cm247 2.622E-01 2.577E+02 9.615E+00 7.100E+01 Cm248 1.796E-03 3.226E+04 1.245E+03 9.210E+03 Cm249 3.888E+00 1.713E+01 6.445E-01 4.708E+00 Cm250 7.075E-03 8.653E+03 3.476E+02 2.311E+03 Co57 1.929E+00 3.608E+01 1.304E+00 9.847E+00 Co58 7.243E-02 8.946E+02 3.468E+01 2.445E+02 Co60 2.837E-02 2.196E+03 8.737E+01 5.932E+02 Cr51 2.888E+00 2.343E+01 8.583E-01 6.496E+00

• Cs134 Cs135 Cs137 Cu64 Dy159 Es252 4.994E-02 7.932E+03 9.702E+01 3.970E-01 2.557E+04 4.171E-01 1.310E+03 8.786E-03 7.123E-01 1.665E+02 2.658E-03 1.564E+02 5.025E+01 3.170E-04 2.597E-02 6.296E+00 9.727E-05 6.020E+00 3.589E+02 2.397E-03 1.959E-01 4.566E+01 7.367E-04 4.276E+01 Es253 2.975E+02 2.208E-01 8.194E-03 6.181E-02 Es254 1.148E+02 5.888E-01 2.158E-02 1.634E-01 Es254m 2.890E-01 2.031E+02 7.842E+00 6.000E+01 Eu149 3.218E+00 2.115E+01 7.785E-01 5.846E+00 Eu150 5.382E-02 1.222E+03 4.643E+01 3.349E+02 Eu152 6.445E-02 9.828E+02 3.860E+01 2.665E+02 Eu154 5.819E-02 1.087E+03 4.276E+01 2.949E+02 Eu155 8.986E+00 7.757E+00 2.799E-01 2.116E+00 Fe55 UNLIMITED 4.672E-08 1.686E-09 1.275E-08 Fe59 5.720E-02 1.090E+03 4.336E+01 2.946E+02 Fr221 4.523E+00 1.558E+01 5.654E-01 4.310E+00 Fr223 3.679E+00 1.841E+01 6.860E-01 5.067E+00 Gd152 4.018E+06 1.533E-05 6.087E-07 4.191E-06 Gd153 9.004E+00 7.741E+00 2.793E-01 2.112E+00 Hf175 3.294E-01 2.055E+02 7.530E+00 5.695E+01 Hf181 2.026E-01 3.338E+02 1.242E+01 9.196E+01 HQ203 6.688E-01 1.056E+02 3.829E+00 2.923E+01 Ho166m 5.160E-02 1.266E+03 4.871E+01 3.463E+02 1129 6.883E+04 1.012E-03 3.652E-05 2.761E-04 1131 2.652E-01 2.542E+02 9.382E+00 7.031E+01 NAC International 5.4-21

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 Bare Cask Dose Rate/Ci and Maximum Activities (6 Pages) Activity Limit NCT Dose Rate HAC Dose Rate (Ci) (mrem/hr/Ci) (mrem/hr/Ci) Isotope Method 2 Method 1 1-meter Package Surface 2-meter ln113m 4.439E-01 1.525E+02 5.584E+00 4.226E+01 ln114 2.777E+00 2.410E+01 9.031 E-01 6.617E+00 ln114m 1.600E+00 4.135E+01 1.569E+00 1.132E+01 ln115 1.782E+02 3.908E-01 1.416E-02 1.073E-01 ln115m 6.242E-01 1.084E+02 3.972E+00 3.006E+01 lr194 6.935E-01 9.515E+01 3.594E+00 2.611E+01 K40 4.255E-01 1.457E+02 5.829E+00 3.908E+01 K42 1.658E-01 3.723E+02 1.490E+01 9.958E+01 Kr85 1.941E+01 3.479E+00 1.293E-01 9.563E-01 La140 2.870E-02 2.149E+03 8.609E+01 5.753E+02 Lu177 4.202E+00 1.675E+01 6.071E-01 4.627E+00 Lu177m 6.189E-01 1.098E+02 4.057E+00 3.028E+01 Mn54 8.617E-02 7.495E+02 2.918E+01 2.047E+02 Na22 3.213E-02 1.983E+03 7.731E+01 5.389E+02 Na24 1.602E-02 3.715E+03 1.524E+02 9.788E+02 Nb91 4.696E+01 1.411E+00 5.325E-02 3.873E-01 Nb94 4.637E-02 1.399E+03 5.423E+01 3.824E+02 Nb95 1.003E-01 6.499E+02 2.506E+01 1.778E+02 Nb95m 1.993E+00 3.542E+01 1.285E+00 9.803E+00 Nd144 4.446E+06 1.391E-05 5.542E-07 3.747E-06 Ni59 1.992E+05 3.325E-04 1.255E-05 9.128E-05 Ni63 UNLIMITED 9.354E-11 3.446E-12 2.676E-11 Np235 4.457E+02 1.563E-01 5.641E-03 4.265E-02 Np237 4.653E+01 1.503E+00 5.431E-02 4.11 BE-01 Np238 1.158E-01 5.446E+02 2.145E+01 1.479E+02 Np239 9.998E-01 6.997E+01 2.537E+00 1.929E+01 Np240 7.198E-02 9.007E+02 3.473E+01 2.463E+02 Np240m 2.364E-01 2.751E+02 1.056E+01 7.509E+01 Os185 1.253E-01 5.249E+02 2.002E+01 1.441E+02 Os194 1.136E+07 5.836E-06 2.120E-07 1.583E-06 P32 4.007E+00 1.688E+01 6.269E-01 4.643E+00 P33 2.444E+03 2.853E-02 1.029E-03 7.787E-03 Pa231 3.251E+00 2.094E+01 7.661E-01 5.802E+00 Pa233 5.113E-01 1.325E+02 4.854E+00 3.670E+01 Pa234 5.355E-02 1.199E+03 4.664E+01 3.268E+02 Pa234m 1.547E+00 4.235E+01 1.617E+00 1.157E+01 Pb209 7.941E+01 8.737E-01 3.175E-02 2.404E-01 Pb210 UNLIMITED 1.692E-11 6.364E-13 4.768E-12 Pb211 1.057E+00 6.233E+01 2.380E+00 1.709E+01 Pb212 1.086E+00 6.469E+01 2.348E+00 1.791E+01 Pb214 Pm145 NAC International 4.944E-01 9.769E+07 1.378E+02 7.343E-07 5.4-22 5.064E+00 2.705E-08 3.813E+01 2.101 E-07

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 Bare Cask Dose Rate/Ci and Maximum Activities (6 Pages) Activity Limit NCT Dose Rate HAC Dose Rate (Ci) (mrem/hr/Ci) (mrem/hr/Ci) Isotope Method 2 Method 1 1-meter Package Surface 2-meter Pm146 1.094E-01 6.037E+02 2.300E+01 1.656E+02 Pm147 4.602E+03 1.515E-02 5.465E-04 4.133E-03 Pm148 1.196E-01 5.285E+02 2.079E+01 1.429E+02 Pm148m 3.877E-02 1.688E+03 6.455E+01 4.625E+02 Po209 1.645E+01 3.964E+00 1.531 E-01 1.084E+00 Po210 6.116E+03 1.023E-02 3.973E-04 2.799E-03 Po211 9.943E+00 6.555E+O0 2.523E-01 1.794E+00 Po212 1.113E+04 5.135E-03 1.979E-04 1.406E-03 Po213 1.757E+03 3.638E-02 1.403E-03 9.955E-03 Po214 8.893E+02 7.261E-02 2.800E-03 1.986E-02 Po215 2.762E+02 2.423E-01 9.091E-03 6.668E-02 Po216 3.221E+03 1.938E-02 7.524E-04 5.297E-03 Po218 5.128E+03 1.209E-02 4.689E-04 3.305E-03 Pr143 2.405E+01 2.862E+00 1.047E-01 7.882E-01 Pr144 7.566E-01 8.546E+01 3.294E+00 2.323E+01 Pr144m 3.979E+01 1.573E+00 6.229E-02 4.243E-01

• Pu236 Pu238 Pu239 Pu240 Pu241 Pu242 4.373E+03 1.470E+04 2.757E+03 2.865E+03 3.244E+05 3.866E+01 1.498E-02 3.993E-03 2.427E-02 2.070E-02 2.148E-04 1.500E+00 5.543E-04 1.529E-04 8.957E-04 7.921 E-04 7.751 E-06 5.796E-02 4.099E-03 1.100E-03 6.690E-03 5.847E-03 5.861E-05 4.278E-01 Pu243 2.647E+01 2.576E+00 9.408E-02 7.117E-01 Pu244 1.703E-01 3.413E+02 1.318E+01 9.805E+01 Pu246 1.405E+00 5.001E+01 1.810E+00 1.377E+01 Ra223 1.453E+00 4.742E+01 1.732E+00 1.311 E+01 Ra224 1.315E+01 5.365E+O0 1.946E-01 1.485E+00 Ra225 8.342E+02 8.367E-02 3.023E-03 2.289E-02 Ra226 5.266E+01 1.323E+O0 4.775E-02 3.610E-01 Rb86 5.923E-01 1.069E+02 4.202E+00 2.902E+01 Rb87 1.827E+03 3.818E-02 1.378E-03 1.043E-02 Re188 1.156E+00 5.710E+01 2.165E+00 1.562E+01 Rh102 1.667E-01 3.969E+02 1.504E+01 1.089E+02 Rh106 2.480E-01 2.642E+02 1.008E+01 7.230E+01 Rn219 1.851E+00 3.707E+01 1.369E+00 1.023E+01 Rn220 1.280E+02 5.169E-01 1.951 E-02 1.419E-01 Rn222 1.921E+02 3.444E-01 1.300E-02 9.453E-02 Ru103 1.936E-01 3.479E+02 1.301 E+01 9.580E+01 S35 2.365E+04 2.947E-03 1.063E-04 8.039E-04 Sb124 3.734E-02 1.677E+03 6.640E+01 4.514E+02 Sb125 1.999E-01 3.337E+02 1.257E+01 9.181 E+01 Sb126 2.918E-02 2.252E+03 8.599E+01 6.181E+02 NAC International 5.4-23

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 Bare Cask Dose Rate/Ci and Maximum Activities (6 Pages) Activity Limit NCT Dose Rate HAC Dose Rate (Ci) (mrem/hr/Ci) (mrem/hr/Ci) Isotope Method 2 Method 1 1-meter Package Surface 2-meter Sb126m 5.279E-02 1.253E+03 4.754E+01 3.443E+02 Sc46 3.554E-02 1.784E+03 7.027E+01 4.849E+02 Se75 3.887E-01 1.793E+02 6.541E+00 4.947E+01 Se79 2.021E+04 3.447E-03 1.244E-04 9.405E-04 Sm145 5.907E+03 1.142E-02 4.267E-04 3.147E-03 Sm146 2.637E+06 2.302E-05 9.047E-07 6.478E-06 Sm147 3.436E+06 1.782E-05 7.047E-07 4.947E-06 Sm148 4.356E+06 1.419E-05 5.648E-07 3.836E-06 Sm151 UNLIMITED 1.095E-08 3.978E-10 2.976E-09 Sn113 2.580E+01 2.737E+00 9.924E-02 7.575E-01 Sn119m UNLIMITED 5.096E-09 1.877E-10 1.458E-09 Sn123 4.010E+00 1.639E+01 6.238E-01 4.482E+00 Sn126 4.878E+02 1.412E-01 5.110E-03 3.857E-02 Sr85 1.540E-01 4.302E+02 1.624E+01 1.181E+02 Sr89 5.500E+00 1.234E+01 4.569E-01 3.396E+00 Sr90 9.156E+01 7.590E-01 2.754E-02 2.087E-01 Ta182 5.591E-02 1.119E+03 4.438E+01 3.024E+02 Tb157 UNLIMITED 8.867E-08 3.267E-09 2.537E-08 Tb160 6.903E-02 9.230E+02 3.613E+01 2.512E+02 Tc97m 2.807E+05 2.362E-04 8.582E-06 6.408E-05 Tc99 1.357E+03 5.142E-02 1.856E-03 1.405E-02 Tc99m 2.146E+00 3.249E+01 1.172E+00 8.864E+00 Te121 1.487E-01 4.456E+02 1.681 E+01 1.223E+02 Te121m 5.167E-01 1.332E+02 4.922E+00 3.669E+01 Te123m 2.273E+00 3.067E+01 1.107E+00 8.369E+00 Te125m 6.821E+02 1.022E-01 3.687E-03 2.788E-02 Te127 1.354E+01 5.022E+O0 1.861E-01 1.384E+00 Te127m 8.552E+02 7.732E-02 2.932E-03 2.125E-02 Te129 1.248E+00 5.352E+01 2.015E+00 1.470E+01 Te129m 2.562E+00 2.559E+01 9.789E-01 7.024E+00 Th227 8.663E-01 8.045E+01 2.926E+00 2.227E+01 Th228 1.575E+02 4.466E-01 1.618E-02 1.232E-01 Th229 4.678E+00 1.497E+01 5.414E-01 4.108E+00 Th230 1.782E+03 3.897E-02 1.413E-03 1.069E-02 Th231 1.240E+02 5.624E-01 2.031E-02 1.538E-01 Th232 7.829E+03 8.745E-03 3.173E-04 2.387E-03 Th234 7.206E+02 9.656E-02 3.485E-03 2.634E-02 11206 1.707E+03 3.784E-02 1.472E-03 1.034E-02 11207 6.373E+00 1.058E+01 3.945E-01 2.908E+00 11208 1.980E-02 3.019E+03 1.231E+02 7.964E+02 Tl209 3.184E-02 1.943E+03 7.764E+01 5.197E+02 Tm168 6.776E-02 9.607E+02 3.708E+01 2.627E+02 NAC International 5.4-24

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.4 Bare Cask Dose Rate/Ci and Maximum Activities (6 Pages) Activity Limit NCT Dose Rate HAC Dose Rate (Ci) (mrem/hr/Ci) (mrem/hr/Ci) Isotope Method 2 Method 1 1-meter Package Surface 2-meter Tm170 2.351E+01 2.926E+00 1.0?0E-01 8.059E-01 Tm171 9.187E+07 7.424E-07 2.711E-08 2.054E-07 U232 1.716E+03 3.991E-02 1.451 E-03 1.094E-02 U233 9.427E+02 7.298E-02 2.659E-03 2.015E-02 U234 3.894E+03 1.751 E-02 6.363E-04 4.780E-03 U235 1.867E+00 3.744E+01 1.352E+00 1.025E+01 U236 7.667E+03 8.760E-03 3.198E-04 2.394E-03 U237 1.552E+00 4.518E+01 1.637E+00 1.245E+01 U238 4.211E+02 1.389E-01 5.353E-03 3.994E-02 U239 4.853E+00 1.365E+01 5.172E-01 3.744E+00 U240 2.014E+02 3.469E-01 1.253E-02 9.492E-02 W181 1.673E+03 4.166E-02 1.503E-03 1.137E-02 W185 2.965E+02 2.352E-01 8.510E-03 6.451E-02 W188 7.679E+01 9.185E-01 3.329E-02 2.539E-01 Xe127 4.973E-01 1.401E+02 5.092E+00 3.875E+01 1.933E-01 Xe131m 9.836E+01 7.087E-01 2.557E-02 Y88 2.522E-02 2.421E+03 9.760E+01 6.482E+02 Y89m 7.571E-02 8.392E+02 3.282E+01 2.287E+02 Y90 1.906E+00 3.507E+01 1.316E+00 9.630E+00 Y90m 1.562E-01 4.376E+02 1.621E+01 1.207E+02 Y91 4.074E+00 1.636E+01 6.149E-01 4.485E+00 Zn65 1.181E-01 5.307E+02 2.105E+01 1.437E+02 Zr88 2.942E-01 2.301E+02 8.426E+00 6.377E+01 Zr90m 2.814E-02 2.102E+03 8.680E+01 5.524E+02 Zr93 UNLIMITED 7.448E-11 2.744E-12 2.131E-11 Zr95 1.015E-01 6.424E+02 2.477E+01 1.758E+02 Notes: 0llsotopes with an activity limit exceeding 108 Ci are labeled as 'UNLIMITED' .

• NAC International 5.4-25

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A n1n (112.18cm) 501n (127cm) 251n (63.Scml

                                                                                                          *' i
                                                           '*                                           I
                                                                                                         *' j ;

I

                                                                                                      .' j;           *'

78.741n I I .' /

                                                                                                   * '         I       ,

(200cml  ! .' ,* _,.

                                                                                             ,{:,*

Figure 5.4 Method 2 meter DRCF Distances -10 Package Configuration I n1n (182.88 cm> *

      ....-- 1 *

(127tm) ' I * \

                                       \
                                         \

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f' 78.74 In 12oocm1

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Figure 5.4-lA - Method 2 meter DRCF Distances - 6 Package Configuration NAC International 5.4-26

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 5.4-27

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 5.4-28

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 5.4-29

This page intentionally left blank.

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 5.5 Appendix 5.5.1 References [5.1] American Society of Mechanical Engineers, "Specification for General Requirements for Steel Plates for Pressure Vessels," ASME SA20/SA-20M, 2007. [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 .

• NAC International 5.5-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 5.5.2 Shielding Analysis for 1x6 Package Array Revision 20A The purpose of this appendix is to determine response functions, dose rates and activity limits for a I x6 array of packages. The shielding evaluation considers configurations with no SIA (i.e., "bare") in addition to packages equipped with a I-inch or 21/4-inch Shield Insert Assembly (SIA). Views showing the significant shielding dimensions of the two SIAs and the MCNP geometry analyzed for each are shown in Figure 5.5-1. The minimum carbon steel wall thicknesses in each direction for both designs are set based on the plate thicknesses of the components in the licensing drawings, as listed in Table 5.5-1. Each SIA is named based on the radial shielding provided. The SIAs are comprised of standard carbon steel plate, limiting the tolerance of each to an insignificant value (see discussion in Section 5 .1 .1, ASTM carbon steel plates have the same 0.01-inch minus tolerance requirement on plate thickness). The material composition for the carbon steel SIA provided in Table 5.3-5 is based on the report PNNL-15870 [5.9]. The shielding evaluation of the I x6 package array assumes all packages to be centered on the trailer (i.e., package centerlines at SO-inches from edge of trailer) with 72-inch centerline spacing between adjacent packages. For Method 1, a minimum distance of 15-feet to the driver cab is required. For Method 2, the package closest to the cab must be secured to the trailer with at least 20-feet between the package centerline and driver cab. However, if the package resulting in the highest dose rates is not loaded closest to the driver cab, then the closest package to the cab may be secured at a minimum of 15-feet from the cab. The MCNP models and methods used are the same as described in Sections 5.3 and 5.4, respectively. The only changes to the models are the addition of the respective SIAs to the MCNP model, an axial shift of the point source to be centered in the SIA cavity, and a corresponding axial shift of the tallies to be centered on the new point source location. For both SIA designs, the bottom shoring is credited with maintaining the geometry of the SIA inside the CCV cavity under NCT. Accordingly, the bottom shoring is designed not to permanently deform or collapse under the bounding NCT bottom end drop load, as discussed in Chapter 2. However, for HAC no shielding credit is taken for the SIA, conservatively assuming the radioactive contents escape the SIA cavity. Thus, the NCT dose rates include the shielding provided by the SIA, but the HAC dose rates are based on the bare CCV values. For the lx6-package array, the distances to the MCNP tallies used to calculate external dose rates and establish compliance with regulatory dose rate locations are provided in Table 5.5-2. For the lx6 package array, the distances to the tally locations are from the package(s) with the highest source term. The tally locations and distances for the Method 1 and Method 2 dose rate locations are shown in Figure 5.6-2 and Figure 5.6-3, respectively. For Method 1, which assumes all NAC International 5.5-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A packages have identical source terms, the controlling trailer surface and 2-meter dose rate locations are based on the sum of the distance scaling factors. The NCT gamma and neutron dose rate results for the Ix6 package array with no SIA (i.e., bare CCV) are presented in Tables 5.5-2 and 5.5-3, respectively. The NCT gamma and neutron dose rate results for the Ix6 package array with the I-inch SIA are presented in Tables 5.5-4 and 5.5-5, respectively. For the 1.00-inch SIA, the cut-off for significant gamma emissions is higher than in the bare cask. Based on the dose rate drop-off, gammas below 0.075 MeV are neglected for I-inch SIA NCT dose rate calculations. The NCT gamma and neutron dose rate results for the lx6 package array with the 21/4-inch SIA are presented in Tables 5.5-6 and 5.5-7, respectively. For the 21/4-inch SIA, the cut-off for significant gamma emissions is higher than in the bare cask. Based on the dose rate drop-off, gammas below 0.10 MeV are neglected for 21/4-inch SIA NCT dose rate calculations. The isotopic dose rate per curie and activity limit values for the 1x6 package array are provided in Table 5.5-8 for most isotopes. The values in these tables are used to demonstrate compliance with external dose rates, as outlined in Section 5.4.4.3. Because compliance with external dose rates is demonstrated for each package individually, there are no restrictions or additional controls for transporting packages with different SIA configurations in the same Ix6 package array shipment. For example, a package including a 21/4-inch SIA may be transported with bare packages and/or packages including a I-inch SIA, without any additional controls, as long as compliance with external dose rate limits has been demonstrated for the isotopic contents of both packages, individually. Mixing of SIAs is not allowed in the 2x5 package array configuration .

• NAC International 5.5-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 MCNP Tally Locations - 1 x 6 Package Array Transport Regulatory Dose Distance to Tallies Description Condition Rate Location in. cm PackaQe Surface 21.32 54.16 On side of deformed IL (2> Trailer Surface 50.00 127.00 Based on minimum trailer width (3> NCT(1> 2-meter 128.74 327.00 Trailer Surface plus 2-meters Driver cab 180.00 457.20 Min. 15 ft required (4> HAC 1-meter 39.37 100.00 From side of deformed IL Notes:

      ~ l l y locations for Methods 1 and 2 shown in Figures 5.5-2 and 5.5-3, respectively.

(2> Bounding deformation assumes 65% crush of IL foam. (3 > Minimum trailer width of 100 in. (254 cm) requires 50 in. to trailer side for a centered package.

      <4> Front package centerline spaced a minimum of 15 feet from driver cab.

NAC International 5.5-4 L __

OPTIMUS-L Package SAR Docket No. 71-9390

• August2020
• Revision 20A Table 5.5 MCNP NCT Gamma Dose Rates with No SIA Dose Rates (mrem/hr*s/emitted particle)

Energy Method 1 Method 2 (MeV) Package Trailer Package Trailer 2-meter Driver Cab 2-meter Driver Cab Surface Surface Surface Surface 12.00 1.750E-07 6.015E-08 1.791 E-08 2.872E-09 1.750E-07 3.176E-08 4.815E-09 2.468E-09 10.00 1.522E-07 5.223E-08 1.560E-08 2.504E-09 1.522E-07 2.758E-08 4.194E-09 2.152E-09 8.00 1.293E-07 4.418E-08 1.317E-08 2.116E-09 1.293E-07 2.339E-08 3.552E-09 1.820E-09 6.00 1.061 E-07 3.611 E-08 1.074E-08 1.702E-09 1.061 E-07 1.911 E-08 2.900E-09 1.486E-09 4.00 8.030E-08 2.713E-08 8.094E-09 1.251 E-09 8.030E-08 1.435E-08 2.179E-09 1.121 E-09 3.00 6.493E-08 2.172E-08 6.539E-09 9.809E-10 6.493E-08 1.154E-08 1.757E-09 9.014E-10 2.50 5.612E-08 1.869E-08 5.633E-09 8.330E-10 5.612E-08 9.936E-09 1.510E-09 7.708E-10 2.00 4.625E-08 1.531 E-08 4.559E-09 6.636E-10 4.625E-08 8.131 E-09 1.230E-09 6.306E-10 1.80 4.205E-08 1.383E-08 4.125E-09 6.1OOE-10 4.205E-08 7.354E-09 1.109E-09 5.680E-10 1.50 3.524E-08 1.146E-08 3.449E-09 5.005E-10 3.524E-08 6.106E-09 9.204E-10 4.700E-10 1.34 3.142E-08 1.014E-08 3.033E-09 4.363E-10 3.142E-08 5.416E-09 8.163E-10 4.155E-10 1.20 2.797E-08 8.968E-09 2.701E-09 3.855E-10 2.797E-08 4.799E-09 7.183E-10 3.680E-10 1.00 2.287E-08 7.252E-09 2.169E-09 3.050E-10 2.287E-08 3.891E-09 5.833E-10 2.971E-10 0.90 2.026E-08 6.374E-09 1.928E-09 2.704E-10 2.026E-08 3.425E-09 5.124E-10 2.606E-10 0.80 1.760E-08 5.498E-09 1.642E-09 2.328E-10 1.760E-08 2.956E-09 4.402E-10 2.232E-10 0.70 1.489E-08 4.632E-09 1.387E-09 1.956E-10 1.489E-08 2.485E-09 3.663E-10 1.871 E-10 0.67 1.407E-08 4.357E-09 1.313E-09 1.839E-10 1.407E-08 2.345E-09 3.465E-10 1.768E-10 0.60 1.215E-08 3.731E-09 1.116E-09 1.576E-10 1.215E-08 2.009E-09 2.978E-10 1.506E-10 0.50 9.262E-09 2.818E-09 8.331E-10 1.153E-10 9.262E-09 1.527E-09 2.226E-10 1.133E-10 0.40 6.391E-09 1.930E-09 5.746E-10 8.070E-11 6.391E-09 1.044E-09 1.525E-10 7.684E-11 0.30 3.499E-09 1.048E-09 3.063E-10 4.297E-11 3.499E-09 5.700E-10 8.152E-11 4.111 E-11 0.20 9.864E-10 2.930E-10 8.664E-11 1.218E-11 9.864E-10 1.602E-10 2.298E-11 1.164E-11 0.10 2.074E-12 6.287E-13 1.943E-13 2.414E-14 2.074E-12 3.399E-13 4.853E-14 2.477E-14 0.075 6.886E-16 2.178E-16 7.834E-17 8.639E-18 6.886E-16 1.150E-16 1.627E-17 8.267E-18 NAC International 5.5-5

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.5 MCNP NCT Neutron Dose Rates with No SIA Dose Rates (mrem/hr*s/emitted particle) Energy Method 1 Method 2 (MeV) Package Trailer Package Trailer 2-meter Driver Cab 2-meter Driver Cab Surface Surface Surface Surface 20.00 6.019E-06 2.017E-06 6.0S0E-07 9.656E-08 6.019E-06 1.045E-06 1.558E-07 8.030E-08 15.00 5.377E-06 1.793E-06 5.418E-07 8.470E-08 5.377E-06 9.322E-07 1.386E-07 7.104E-08 10.00 3.993E-06 1.309E-06 3.919E-07 5.904E-08 3.993E-06 6.829E-07 1.011 E-07 5.102E-08 7.50 4.108E-06 1.336E-06 4.042E-07 5.822E-08 4.108E-06 7.028E-07 1.040E-07 5.196E-08 5.00 4.108E-06 1.336E-06 4.042E-07 5.822E-08 4.108E-06 7.028E-07 1.040E-07 5.196E-08 4.00 3.884E-06 1.257E-06 3.776E-07 5.325E-08 3.884E-06 6.574E-07 9.637E-08 4.917E-08 3.00 3.792E-06 1.236E-06 3.745E-07 5.325E-08 3.792E-06 6.450E-07 9.478E-08 4.823E-08 2.50 3.712E-06 1.206E-06 3.627E-07 5.037E-08 3.712E-06 6.275E-07 9.218E-08 4.660E-08 2.25 3.643E-06 1.184E-06 3.551E-07 5.083E-08 3.643E-06 6.224E-07 9.093E-08 4.614E-08 2.00 3.568E-06 1.164E-06 3.464E-07 5.083E-08 3.568E-06 6.072E-07 8.975E-08 4.540E-08 1.75 3.494E-06 1.124E-06 3.353E-07 4.894E-08 3.494E-06 5.931E-07 8.655E-08 4.355E-08 1.50 3.382E-06 1.107E-06 3.350E-07 4.894E-08 3.382E-06 5.788E-07 8.486E-08 4.342E-08 1.25 3.334E-06 1.077E-06 3.218E-07 4.608E-08 3.334E-06 5.685E-07 8.312E-08 4.230E-08 1.10 3.199E-06 1.020E-06 3.049E-07 4.425E-08 3.199E-06 5.386E-07 7.952E-08 3.984E-08 1.00 3.121E-06 1.001 E-06 2.954E-07 4.278E-08 3.121 E-06 5.302E-07 7.653E-08 3.849E-08 0.90 3.121E-06 1.001 E-06 2.954E-07 4.278E-08 3.121 E-06 5.302E-07 7.653E-08 3.849E-08 0.80 2.946E-06 9.381E-07 2.828E-07 3.943E-08 2.946E-06 5.024E-07 7.241E-08 3.663E-08 0.70 2.651E-06 8.660E-07 2.581E-07 3.669E-08 2.651E-06 4.524E-07 6.681E-08 3.405E-08 0.60 2.346E-06 7.548E-07 2.280E-07 3.255E-08 2.346E-06 3.995E-07 5.885E-08 2.982E-08 0.50 1.969E-06 6.282E-07 1.870E-07 2.648E-08 1.969E-06 3.347E-07 4.846E-08 2.460E-08 0.40 1.488E-06 4.783E-07 1.414E-07 1.938E-08 1.488E-06 2.555E-07 3.643E-08 1.870E-08 0.30 1.077E-06 3.421E-07 1.020E-07 1.449E-08 1.077E-06 1.844E-07 2.647E-08 1.344E-08 0.20 6.873E-07 2.208E-07 6.522E-08 8.932E-09 6.873E-07 1.190E-07 1.674E-08 8.462E-09 0.10 3.247E-07 1.067E-07 3.116E-08 4.215E-09 3.247E-07 5.769E-08 8.062E-09 4.105E-09 0.05 1.944E-07 6.496E-08 1.879E-08 2.455E-09 1.944E-07 3.478E-08 4.798E-09 2.416E-09 IC International

OPTIMUS-L Package SAR Docket No. 71-9390

• August2020*

Revision 20A Table 5.5 MCNP NCT Gamma Dose Rates with 1-inch SIA Dose Rates (mrem/hr*s/emitted particle) Energy Method 1 Method 2 (MeV) Package Trailer Package Trailer 2-meter Driver Cab 2-meter Driver Cab Surface Surface Surface Surface 12.00 1.125E-07 3.798E-08 1.150E-08 1.691 E-09 1.125E-07 2.021E-08 3.066E-09 1.569E-09 10.00 9.825E-08 3.316E-08 9.989E-09 1.482E-09 9.825E-08 1.764E-08 2.669E-09 1.368E-09 8.00 8.396E-08 2.836E-08 8.486E-09 1.254E-09 8.396E-08 1.504E-08 2.280E-09 1.167E-09 6.00 6.898E-08 2.313E-08 6.884E-09 1.008E-09 6.898E-08 1.231 E-08 1.868E-09 9.533E-10 4.00 5.127E-08 1.698E-08 5.085E-09 7.480E-10 5.127E-08 9.059E-09 1.370E-09 7.027E-10 3.00 4.024E-08 1.314E-08 3.970E-09 5.698E-10 4.024E-08 7.043E-09 1.069E-09 5.437E-10 2.50 3.376E-08 1.095E-08 3.314E-09 4.612E-10 3.376E-08 5.872E-09 8.834E-10 4.512E-10 2.00 2.659E-08 8.522E-09 2.592E-09 3.573E-10 2.659E-08 4.579E-09 6.862E-10 3.503E-10 1.80 2.356E-08 7.495E-09 2.251E-09 3.259E-10 2.356E-08 4.030E-09 6.028E-10 3.065E-10 1.50 1.872E-08 5.876E-09 1.765E-09 2.463E-10 1.872E-08 3.163E-09 4.694E-10 2.392E-10 1.34 1.608E-08 5.034E-09 1.513E-09 2.115E-10 1.608E-08 2.701 E-09 4.016E-10 2.033E-10 1.20 1.377E-08 4.267E-09 1.263E-09 1.740E-10 1.377E-08 2.290E-09 3.381E-10 1.712E-10 1.00 1.047E-08 3.166E-09 9.535E-10 1.385E-10 1.047E-08 1.723E-09 2.535E-10 1.281E-10 0.90 8.860E-09 2.664E-09 7.928E-10 1.154E-10 8.860E-09 1.446E-09 2.111E-10 1.069E-10 0.80 7.284E-09 2.169E-09 6.345E-10 9.669E-11 7.284E-09 1.176E-09 1.710E-10 8.706E-11 0.70 5.761E-09 1.701 E-09 5.023E-10 7.440E-11 5.761E-09 9.200E-10 1.340E-10 6.795E-11 0.67 5.319E-09 1.560E-09 4.623E-10 6.962E-11 5.319E-09 8.452E-10 1.235E-10 6.199E-11 0.60 4.306E-09 1.254E-09 3.729E-10 5.599E-11 4.306E-09 6.817E-10 9.818E-11 4.969E-11 0.50 2.934E-09 8.401E-10 2.485E-10 3.581 E-11 2.934E-09 4.602E-10 6.555E-11 3.329E-11 0.40 1.709E-09 4.839E-10 1.400E-10 1.951 E-11 1.709E-09 2.647E-10 3.809E-11 1.902E-11 0.30 7.022E-10 1.995E-10 5.629E-11 8.636E-12 7.022E-10 1.069E-10 1.488E-11 7.798E-12 0.20 1.004E-10 2.722E-11 8.046E-12 1.0S0E-12 1.004E-10 1.509E-11 2.132E-12 1.122E-12 0.10 2.699E-15 7.374E-16 2.314E-16 2.953E-17 2.699E-15 4.064E-16 5.625E-17 2.815E-17 0.075 0 0 0 0 1.823E-21 2.776E-22 3.959E-23 1.846E-23 NAC International 5.5-7

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 MCNP NCT Neutron Dose Rates with 1-inch SIA Dose Rates (mrem/hr*s/emitted particle) Energy Method 1 Method 2 (MeV) Package Trailer Trailer Package 2-meter Driver Cab 2-meter Driver Cab Surface Surface Surface Surface 20.00 5.763E-06 1.876E-06 5.626E-07 7.991E-08 5.763E-06 9.814E-07 1.449E-07 7.325E-08 15.00 5.012E-06 1.61 BE-06 4.847E-07 6.854E-08 5.012E-06 8.516E-07 1.242E-07 6.326E-08 10.00 3.760E-06 1.190E-06 3.561E-07 4.993E-08 3.760E-06 6.282E-07 9.138E-08 4.659E-08 7.50 3.814E-06 1.194E-06 3.597E-07 4.969E-08 3.814E-06 6.378E-07 9.232E-08 4.676E-08 5.00 3.814E-06 1.194E-06 3.597E-07 4.826E-08 3.814E-06 6.378E-07 9.232E-08 4.676E-08 4.00 3.675E-06 1.150E-06 3.422E-07 4.690E-08 3.675E-06 6.089E-07 8.772E-08 4.441 E-08 3.00 3.675E-06 1.150E-06 3.422E-07 , 4.690E-08 3.675E-06 6.089E-07 8.772E-08 4.441E-08 2.50 3.606E-06 1.117E-06 3.324E-07 4.513E-08 3.606E-06 5.950E-07 8.495E-08 4.292E-08 2.25 3.538E-06 1.115E-06 3.324E-07 4.508E-08 3.538E-06 5.874E-07 8.438E-08 4.283E-08 2.00 3.459E-06 1.088E-06 3.213E-07 4.465E-08 3.459E-06 5.750E-07 8.321E-08 4.204E-08 1.75 3.351E-06 1.041E-06 3.11 0E-07 4.446E-08 3.351E-06 5.578E-07 7.946E-08 4.002E-08 1.50 3.264E-06 1.036E-06 3.110E-07 4.446E-08 3.264E-06 5.485E-07 7.946E-08 4.002E-08 1.25 3.067E-06 9.599E-07 2.840E-07 3.925E-08 3.067E-06 5.102E-07 7.308E-08 3.701E-08 1.10 2.924E-06 9.041E-07 2.715E-07 3.771E-08 2.924E-06 4.843E-07 6.966E-08 3.544E-08 1.00 3.060E-06 9.515E-07 2.777E-07 3.910E-08 3.060E-06 5.0B0E-07 7.245E-08 3.633E-08 0.90 3.060E-06 9.515E-07 2.777E-07 3.910E-08 3.060E-06 5.0B0E-07 7.245E-08 3.633E-08 0.80 2.923E-06 9.053E-07 2.649E-07 3.583E-08 2.923E-06 4.883E-07 6.955E-08 3.545E-08 0.70 2.674E-06 8.499E-07 2.544E-07 3.546E-08 2.674E-06 4.516E-07 6.585E-08 3.382E-08 0.60 2.333E-06 7.401E-07 2.239E-07 3.165E-08 2.333E-06 3.946E-07 5.755E-08 2.916E-08 0.50 1.910E-06 5.952E-07 1.775E-07 2.532E-08 1.91 0E-06 3.206E-07 4.577E-08 2.327E-08 0.40 1.441E-06 4.474E-07 1.308E-07 1.877E-08 1.441 E-06 2.436E-07 3.446E-08 1.733E-08 0.30 1.017E-06 3.217E-07 9.400E-08 1.294E-08 1.017E-06 1.731E-07 2.426E-08 1.247E-08 0.20 6.373E-07 1.977E-07 5.833E-08 7.845E-09 6.373E-07 1.081E-07 1.520E-08 7.564E-09 0.10 3.124E-07 9.882E-08 2.870E-08 3.704E-09 3.124E-07 5.355E-08 7.508E-09 3.742E-09 0.05 1.925E-07 5.994E-08 1.737E-08 2.191E-09 1.925E-07 3.223E-08 4.413E-09 2.202E-09 IC w

• International

OPTIMUS-L Package SAR Docket No. 71-9390 August 2020 Revision 20A Table 5.5 MCNP NCT Gamma Dose Rates with 21/4-SIA Dose Rates (mrem/hr*s/emitted particle) Energy Method 1 Method 2 (MeV) Package Trailer Package Trailer 2-meter Driver Cab 2-meter Driver Cab Surface Surface Surface Surface 12.00 6.273E-08 2.112E-08 6.340E-09 9.194E-10 6.273E-08 1.118E-08 1.694E-09 8.682E-10 10.00 5.509E-08 1.851 E-08 5.614E-09 7.959E-10 5.509E-08 9.796E-09 1.485E-09 7.591E-10 8.00 4.730E-08 1.596E-08 4.721E-09 6.880E-10 4.730E-08 8.391E-09 1.274E-09 6.497E-10 6.00 3.875E-08 1.287E-08 3.819E-09 5.479E-10 3.875E-08 6.840E-09 1.038E-09 5.294E-10 4.00 2.791E-08 9.130E-09 2.735E-09 4.053E-10 2.791E-08 4.863E-09 7.328E-10 3.730E-10 3.00 2.087E-08 6.748E-09 2.025E-09 2.902E-10 2.087E-08 3.603E-09 5.409E-10 2.748E-10 2.50 1.675E-08 5.377E-09 1.605E-09 2.326E-10 1.675E-08 2.858E-09 4.245E-10 2.155E-10 2.00 1.230E-08 3.881E-09 1.159E-09 1.655E-10 1.230E-08 2.071E-09 3.066E-10 1.577E-10 1.80 1.050E-08 3.262E-09 9.908E-10 1.484E-10 1.050E-08 1.756E-09 2.586E-10 1.318E-10 1.50 7.716E-09 2.360E-09 7.216E-10 9.563E-11 7.716E-09 1.264E-09 1.850E-10 9.480E-11 1.34 6.285E-09 1.919E-09 5.737E-10 8.138E-11 6.285E-09 1.022E-09 1.487E-10 7.480E-11 1.20 5.081E-09 1.534E-09 4.587E-10 6.135E-11 5.081E-09 8.178E-10 1.185E-10 6.060E-11 1.00 3.480E-09 1.009E-09 3.081E-10 4.270E-11 3.480E-09 5.516E-10 7.983E-11 4.078E-11 0.90 2.764E-09 7.875E-10 2.451E-10 3.523E-11 2.764E-09 4.339E-10 6.219E-11 3.160E-11 0.80 2.105E-09 5.949E-10 1.810E-10 2.671 E-11 2.105E-09 3.255E-10 4.669E-11 2.393E-11 0.70 1.517E-09 4.250E-10 1.281E-10 1.724E-11 1.517E-09 2.311E-10 3.306E-11 1.713E-11 0.67 1.355E-09 3.775E-10 1.111E-10 1.401E-11 1.355E-09 2.053E-10 2.909E-11 1.507E-11 0.60 1.006E-09 2.847E-10 8.764E-11 1.206E-11 1.006E-09 1.520E-10 2.159E-11 1.106E-11 0.50 5.866E-10 1.558E-10 4.772E-11 6.406E-12 5.866E-10 8.795E-11 1.231 E-11 6.536E-12 0.40 2.740E-10 7.226E-11 2.070E-11 2.782E-12 2.740E-10 4.002E-11 6.011E-12 2.984E-12 0.30 7.742E-11 1.984E-11 5.873E-12 8.069E-13 7.742E-11 1.112E-11 1.708E-12 8.941E-13 0.20 4.609E-12 1.327E-12 3.891 E-13 5.237E-14 4.609E-12 6.484E-13 8.948E-14 4.523E-14 0.10 0 0 0 0 5.901E-19 8.775E-20 1.0BSE-20 4.359E-21 NAC International 5.5-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 MCNP NCT Neutron Dose Rates with 21/4-inch SIA Dose Rates (mrem/hr*s/emitted particle) Energy Method 1 Method 2 (MeV) Package Trailer Package Trailer 2-meter Driver Cab 2-meter Driver Cab Surface Surface Surface Surface 20.00 5.152E-06 1.632E-06 4.893E-07 6.575E-08 5.152E-06 8.671E-07 1.264E-07 6.311 E-08 15.00 4.348E-06 1.366E-06 4.099E-07 5.620E-08 4.348E-06 7.309E-07 1.054E-07 5.276E-08 10.00 3.281E-06 1.020E-06 3.029E-07 4.164E-08 3.281E-06 5.414E-07 7.742E-08 3.935E-08 7.50 3.281E-06 1.020E-06 3.029E-07 4.164E-08 3.281E-06 5.414E-07 7.742E-08 3.923E-08 5.00 3.266E-06 1.008E-06 2.963E-07 4.058E-08 3.266E-06 5.371E-07 7.636E-08 3.886E-08 4.00 3.245E-06 9.983E-07 2.930E-07 3.988E-08 3.245E-06 5.349E-07 7.583E-08 3.821 E-08 3.00 3.245E-06 9.983E-07 2.930E-07 3.988E-08 3.245E-06 5.349E-07 7.583E-08 3.821E-08 2.50 3.170E-06 9.775E-07 2.862E-07 3.886E-08 3.170E-06 5.194E-07 7.367E-08 3.727E-08 2.25 3.114E-06 9.639E-07 2.842E-07 3.886E-08 3.114E-06 5.145E-07 7.367E-08 3.727E-08 2.00 3.070E-06 9.490E-07 2.765E-07 3.719E-08 3.070E-06 5.056E-07 7.199E-08 3.653E-08 1.75 2.978E-06 9.318E-07 2.750E-07 3.854E-08 2.978E-06 4.967E-07 7.144E-08 3.618E-08 1.50 2.978E-06 9.318E-07 2.750E-07 3.854E-08 2.978E-06 4.967E-07 7.144E-08 3.618E-08 1.25 2.573E-06 8.042E-07 2.372E-07 3.153E-08 2.573E-06 4.279E-07 6.063E-08 3.067E-08 1.10 2.487E-06 7.628E-07 2.249E-07 3.013E-08 2.487E-06 4.102E-07 5.844E-08 2.971E-08 1.00 2.799E-06 8.694E-07 2.538E-07 3.498E-08 2.799E-06 4.662E-07 6.630E-08 3.325E-08 0.90 2.799E-06 8.694E-07 2.538E-07 3.498E-08 2.799E-06 4.662E-07 6.630E-08 3.325E-08 0.80 2.685E-06 8.316E-07 2.415E-07 3.272E-08 2.685E-06 4.495E-07 6.346E-08 3.202E-08 0.70 2.579E-06 8.099E-07 2.397E-07 3.272E-08 2.579E-06 4.338E-07 6.275E-08 3.202E-08 0.60 2.215E-06 6.944E-07 2.084E-07 2.894E-08 2.215E-06 3.724E-07 5.396E-08 2.665E-08 0.50 1.737E-06 5.345E-07 1.584E-07 2.180E-08 1.737E-06 2.912E-07 4.126E-08 2.079E-08 0.40 1.284E-06 4.063E-07 1.179E-07 1.656E-08 1.284E-06 2.199E-07 3.124E-08 1.557E-08 0.30 9.127E-07 2.919E-07 8.471E-08 1.171E-08 9.127E-07 1.570E-07 2.223E-08 1.127E-08 0.20 5.514E-07 1.735E-07 5.151 E-08 7.070E-09 5.514E-07 9.567E-08 1.338E-08 6.741 E-09 0.10 2.716E-07 8.593E-08 2.526E-08 3.236E-09 2.716E-07 4.678E-08 6.502E-09 3.312E-09 0.05 1.662E-07 5.196E-08 1.500E-08 1.948E-09 1.662E-07 2.808E-08 3.826E-09 1.898E-09 IC International

OPTIMUS-L Package SAR Docket No. 71-9390

• August2020
• Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages)

No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope Activity Method 2 Activity Method 2 Activity Method 2 (mrem/hr/Ci) Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Ac225 3.698E+0l 2.738E+00 6.474E-02 1.869E+02 5.779E-01 1.272E-02 l.151E+03 9.422E-02 2.014E-03 7.520E-01 Ac227 8.627E+03 1.181E-02 2.773E-04 5.378E+04 2.035E-03 4.423E-05 2.779E+0S 2.781E-04 5.931E-06 3.239E-03 Ac228 l.243E-01 7.639E+02 l.943E+0l 2.858E-01 3.452E+02 8.397E+00 8.431E-01 1.188E+02 2.771E+00 2.076E+02 Ag108 3.458E+00 2.844E+0l 6.909E-01 1.132E+0l 9.249E+00 2.117E-01 5.060E+0l 2.140E+00 4.632E-02 7.819E+00 Ag108m 7.103E-02 l.369E+03 3.377E+0l 1.999E-01 5.199E+02 l.205E+0l 7.912E-0l l.354E+02 2.949E+00 3.758E+02 Ag109m 3.383E+04 2.839E-03 6.643E-05 1.169E+06 3.695E-06 7.701E-08 1.169E+06 0.000E+00 0.000E+00 7.701E-04 Agll0 1.210E+00 8.056E+0l 1.976E+00 3.644E+00 2.827E+0l 6.591E-01 1.404E+01 7.487E+00 1.671E-01 2.209E+01 AgllOm 3.931E-02 2.407E+03 6.lOlE+0l 9.208E-02 l.080E+03 2.608E+0l 2.785E-01 3.615E+02 8.329E+00 6.548E+02 Am241 4.606E+03 2.160E-02 5.158E-04 1.587E+04 6.475E-03 1.489E-04 3.323E+04 3.049E-03 7.042E-05 5.922E-03 Am242 2.831E+0l 3.616E+00 8.435E-02 2.721E+02 4.112E-01 8.778E-03 9.111E+02 2.640E-02 5.389E-04 9.878E-01 Am242m 3.503E+03 2.926E-02 6.818E-04 3.251E+04 3.450E-03 7.329E-05 1.125E+0S 2.374E-04 4.964E-06 8.00lE-03 Am243 3.868E+02 2.642E-01 6.169E-03 3.542E+03 3.107E-02 6.719E-04 1.248E+04 3.998E-03 8.761E-05 7.209E-02 Am245 7.020E+00 1.460E+01 3.408E-01 4.394E+01 2.545E+00 5.424E-02 2.237E+02 2.682E-01 5.837E-03 4.023E+00 Am246 1.583E-01 6.132E+02 1.509E+01 4.525E-01 2.285E+02 5.315E+00 1.741E+00 6.068E+0l 1.334E+00 1.683E+02 At217 7.034E+02 1.405E-01 3.409E-03 2.188E+03 4.780E-02 1.090E-03 7.487E+03 1.386E-02 3.097E-04 3.867E-02 Au198 2.970E-01 3.367E+02 8.096E+00 9.924E-01 1.070E+02 2.393E+00 5.ll0E+00 2.160E+0l 4.546E-01 9.272E+0l Ba133 4.528E-01 2.213E+02 5.275E+00 1.880E+00 5.847E+01 1.301E+00 1.285E+01 9.276E+00 2.035E-01 6.135E+0l Ba137m 2.061E-01 4.680E+02 1.152E+01 5.852E-01 1.769E+02 4.108E+00 2.435E+00 4.506E+01 9.678E-01 1.286E+02 Ba140 6.924E-01 1.423E+02 3.468E+00 2.182E+00 4.794E+01 1.088E+00 9.759E+00 1.073E+01 2.299E-01 3.910E+01 BelO 1.418E+02 7.196E-01 1.686E-02 9.056E+02 1.227E-01 2.651E-03 4.549E+03 1.384E-02 2.987E-04 1.979E-01 Bi207 7.167E-02 1.320E+03 3.347E+0l 1.662E-01 S.965E+02 1.444E+0l 4.896E-01 2.037E+02 4.716E+00 3.585E+02 Bi210 2.040E+0l 4.939E+00 1.173E-01 9.198E+0l 1.176E+00 2.610E-02 5.548E+02 2.007E-01 4.340E-03 1.360E+00 Bi211 3.251E+00 3.080E+0l 7.348E-01 1.333E+0l 8.237E+00 1.836E-01 8.992E+0l 1.325E+00 2.906E-02 8.536E+00 Bi212 9.332E-01 1.019E+02 2.584E+00 2.168E+00 4.586E+01 1.114E+00 6.253E+00 1.596E+0l 3.736E-01 2.762E+0l Bi213 9.667E-01 1.031E+02 2.486E+00 3.184E+00 3.317E+0l 7.470E-01 1.545E+0l 7.049E+00 1.504E-01 2.837E+0l NAC International 5.5-11

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope (mrem/hr/Ci) Activity Method 2 Activity Method 2 Activity Method 2 Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Bi214 6.884E-02 l.351E+03 3.494E+0l 1.410E-01 6.817E+02 l.705E+0l 3.562E-01 2.734E+02 6.593E+00 3.630E+02 Bk247 2.174E+00 4.725E+0l l.lOlE+00 l.298E+0l 8.647E+00 l.832E-01 6.899E+0l 8.986E-01 l.971E-02 l.305E+0l Bk249 2.597E+0S 3.702E-04 9.012E-06 4.338E+0S 2.255E-04 5.358E-06 S.493E+0S l.801E-04 4.251E-06 l.037E-04 Bk250 l.135E-01 8.285E+02 2.120E+0l 2.506E-01 3.929E+02 9.585E+00 7.282E-01 l.381E+02 3.196E+00 2.250E+02 C14 5.100E+04 2.008E-03 4.678E-05 5.SSlE+0S 2.022E-04 4.295E-06 l.643E+06 9.287E-06 l.803E-07 S.477E-04 Ca45 3.242E+03 3.160E-02 7.363E-04 3.349E+04 3.352E-03 7.119E-05 l.043E+0S l.732E-04 3.450E-06 8.627E-03 Cdl13 l.358E+03 7.546E-02 l.759E-03 l.238E+04 9.060E-03 l.928E-04 4.361E+04 6.132E-04 l.275E-05 2.064E-02 Cdl13m 1.388E+02 7.351E-01 1.723E-02 8.640E+02 l.286E-01 2.778E-03 4.451E+03 l.481E-02 3.200E-04 2.022E-01 CdllSm 2.245E+00 4.278E+0l l.075E+00 5.646E+00 l.760E+0l 4.238E-01 l.786E+0l 5.673E+00 l.308E-01 1.167E+0l Ce139 3.540E+00 2.894E+0l 6.744E-01 3.812E+0l 2.945E+00 6.255E-02 l.140E+02 l.353E-01 2.626E-03 7.897E+00 Ce141 5.694E+00 1.799E+0l 4.193E-01 6.059E+0l l.852E+00 3.936E-02 l.833E+02 8.858E-02 l.733E-03 4.910E+00 Ce144 2.498E+0l 4.102E+00 9.557E-02 2.685E+02 4.181E-01 8.880E-03 8.043E+02 1.932E-02 3.756E-04 l.119E+00 Cf249 5.031E-01 l.992E+02 4.748E+00 2.092E+00 5.252E+0l l.170E+00 1.426E+0l 8.352E+00 l.832E-01 5.519E+0l Cf250 3.131E-01 2.969E+02 7.399E+00 3.438E-01 2.812E+02 6.748E+00 3.955E-01 2.490E+02 5.913E+00 8.808E+0l Cf251 3.084E+00 3.325E+0l 7.750E-01 2.446E+0l 4.587E+00 9.741E-02 9.868E+0l 3.730E-01 7.965E-03 9.120E+00 Cf252 6.250E-03 l.480E+04 3.699E+02 6.908E-03 l.396E+04 3.350E+02 8.054E-03 l.225E+04 2.895E+02 4.182E+03 Cf253 2.384E+03 4.298E-02 1.002E-03 2.328E+04 4.820E-03 l.024E-04 7.665E+04 2.923E-04 5.984E-06 l.174E-02 Cf254 2.202E-04 4.222E+0S l.052E+04 2.414E-04 4.00SE+0S 9.608E+03 2.774E-04 3.549E+0S 8.428E+03 l.253E+0S Cl36 6.654E+0l l.524E+00 3.596E-02 3.479E+02 3.143E-01 6.891E-03 2.146E+03 4.582E-02 9.874E-04 4.193E-01 Cm240 4.801E+03 1.959E-02 4.832E-04 6.137E+03 1.577E-02 3.768E-04 7.247E+03 l.364E-02 3.215E-04 5.461E-03 Cm242 3.391E+03 2.749E-02 6.839E-04 4.075E+03 2.374E-02 S.684E-04 4.861E+03 2.033E-02 4.798E-04 7.735E-03 Cm243 2.125E+00 4.834E+0l 1.126E+00 1.301E+0l 8.626E+00 1.829E-01 6.749E+0l 8.840E-01 1.937E-02 1.334E+0l Cm244 1.964E+02 4.713E-01 1.178E-02 2.184E+02 4.418E-01 1.060E-02 2.551E+02 3.868E-01 9.143E-03 1.338E-01 Cm245 4.843E+00 2.116E+0l 4.929E-01 S.201E+0l 2.158E+00 4.584E-02 1.559E+02 1.032E-01 2.023E-03 S.772E+00 Cm246 8.854E-01 1.045E+02 2.612E+00 9.791E-01 9.855E+0l 2.364E+00 1.140E+00 8.653E+0l 2.046E+00 2.974E+0l IC International

OPTIMUS-L Package SAR Docket No. 71-9390

• August2020
• Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages)

No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope Activity Method 2 Activity Method 2 Activity Method 2 (mrem/hr/Ci) Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Cm247 3.88SE-01 2.S77E+02 6.188E+00 1.322E+00 8.049E+0l l.796E+00 6.9S8E+00 l.S92E+0l 3.34SE-01 7.lO0E+0l Cm248 2.871E-03 3.226E+04 8.0S7E+02 3.173E-03 3.042E+04 7.298E+02 3.690E-03 2.674E+04 6.324E+02 9.210E+03 Cm249 S.70SE+00 1.713E+0l 4.181E-01 l.780E+0l S.861E+00 l.346E-01 7.82SE+0l l.38SE+00 2.976E-02 4.708E+00 Cm2S0 l.068E-02 8.6S3E+03 2.2S8E+02 2.08SE-02 4.SS1E+03 l.1SSE+02 4.877E-02 l.962E+03 4.8S8E+0l 2.311E+03 CoS7 2.83SE+00 3.608E+0l 8.420E-01 2.829E+0l 3.937E+00 8.433E-02 9.140E+0l 2.S84E-01 S.240E-03 9.847E+00 CoS8 l.062E-01 8.946E+02 2.2S3E+0l 2.6S0E-01 3.808E+02 9.030E+00 8.783E-01 l.1S6E+02 2.S94E+00 2.44SE+02 Co60 4.24SE-02 2.196E+03 S.674E+0l 8.767E-02 l.103E+03 2.73SE+0l 2.3S8E-01 4.202E+02 9.878E+00 S.932E+02 CrSl 4.272E+00 2.343E+0l S.S91E-01 l.7S3E+0l 6.26SE+00 l.397E-01 l.186E+02 1.00SE+00 2.204E-02 6.496E+00 Cs134 7.349E-02 l.310E+03 3.260E+0l l.9S7E-01 S.2SSE+02 l.232E+0l 7.143E-01 1.474E+02 3.2S2E+00 3.S89E+02 Cs13S l.166E+04 8.786E-03 2.047E-04 l.262E+0S 8.897E-04 l.890E-0S 3.7SSE+0S 4.089E-0S 7.939E-07 2.397E-03 Cs137 1.42SE+02 7.123E-01 l.678E-02 7.907E+02 l.386E-01 3.03SE-03 4.S94E+03 l.947E-02 4.206E-04 l.9S9E-01 Cu64 S.873E-01 1.66SE+02 4.091E+00 l.72SE+00 S.99SE+0l 1.374E+00 7.040E+00 1.4S8E+0l 3.164E-01 4.S66E+0l Dy1S9 3.774E+04 2.6S8E-03 6.328E-0S l.601E+0S 6.871E-04 1.S26E-0S l.109E+06 1.074E-04 2.3S6E-06 7.367E-04 Es2S2 6.171E-01 l.S64E+02 3.907E+00 l.631E+00 6.29SE+0l 1.482E+00 S.671E+00 l.834E+0l 4.090E-01 4.276E+0l Es2S3 4.470E+02 2.208E-01 S.316E-03 l.163E+03 8.840E-02 2.040E-03 2.286E+03 4.431E-02 l.034E-03 6.181E-02 Es2S4 l.700E+02 S.888E-01 1.404E-02 6.S63E+02 l.6S3E-01 3.702E-03 2.884E+03 3.821E-02 8.640E-04 l.634E-01 Es2S4m 4.S78E-01 2.031E+02 S.069E+00 S.137E-01 l.882E+02 4.S20E+00 S.982E-01 l.646E+02 3.910E+00 6.000E+0l Eu149 4.740E+00 2.llSE+0l S.0S0E-01 1.88SE+0l S.744E+00 1.278E-01 l.114E+02 l.002E+00 2.179E-02 S.846E+00 EulS0 7.977E-02 l.222E+03 3.0lOE+0l 2.27SE-01 4.Sl8E+02 1.0S4E+0l 8.471E-01 1.221E+02 2.741E+00 3.349E+02 Eu1S2 9.S87E-02 9.828E+02 2.S06E+0l 2.162E-01 4.S47E+02 l.lllE+0l 6.lllE-01 1.62SE+02 3.799E+00 2.66SE+02 Eu1S4 8.67SE-02 l.087E+03 2.779E+0l 1.928E-01 S.087E+02 1.244E+0l S.Sl9E-01 l.810E+02 4.213E+00 2.949E+02 EulSS 1.321E+0l 7.7S7E+00 l.807E-01 l.427E+02 7.868E-01 l.671E-02 4.2S3E+02 3.614E-02 7.0lSE-04 2.116E+00 Fess UNLIMITED 4.672E-08 l.089E-09 UNLIMITED 4.7S3E-09 1.0lOE-10 UNLIMITED 2.183E-10 4.238E-12 l.27SE-08 FeS9 8.SS3E-02 l.090E+03 2.814E+0l 1.777E-01 S.4SSE+02 l.3SlE+0l 4.793E-01 2.069E+02 4.8S8E+00 2.946E+02 Fr221 6.S90E+00 l.SS8E+0l 3.634E-01 3.498E+0l 3.197E+00 6.802E-02 2.088E+02 3.74SE-01 8.230E-03 4.310E+00 NAC International 5.5-13

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope (mrem/hr/Ci) Activity Method 2 Activity Method 2 Activity Method 2 Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Fr223 5.404E+00 l.841E+0l 4.437E-01 l.978E+0l 5.358E+00 l.217E-01 8.996E+0l 1.186E+00 2.627E-02 5.067E+00 Gd152 6.073E+06 l.533E-05 3.951E-07 l.124E+07 8.534E-06 2.127E-07 2.234E+07 4.345E-06 1.0SSE-07 4.191E-06 Gd153 l.323E+0l 7.741E+00 1.804E-01 1.430E+02 7.853E-01 l.668E-02 4.262E+02 3.607E-02 7.002E-04 2.112E+00 Hf175 4.872E-01 2.0SSE+02 4.903E+00 l.991E+00 5.SllE+0l 1.228E+00 l.337E+0l 8.890E+00 l.947E-01 5.695E+0l Hf181 3.00lE-01 3.338E+02 8.004E+00 l.066E+00 l.001E+02 2.234E+00 5.742E+00 l.937E+0l 4.081E-01 9.196E+0l Hg203 9.734E-01 l.056E+02 2.460E+00 5.298E+00 2.119E+0l 4.489E-01 3.079E+0l 2.336E+00 5.153E-02 2.923E+0l Ho166m 7.599E-02 l.266E+03 3.160E+0l 2.00SE-01 5.093E+02 l.199E+0l 6.950E-01 1.483E+02 3.313E+00 3.463E+02 1129 l.012E+0S l.012E-03 2.359E-05 l.104E+06 1.017E-04 2.161E-06 3.259E+06 4.671E-06 9.068E-08 2.761E-04 1131 3.913E-01 2.542E+02 6.103E+00 1.472E+00 7.342E+0l l.654E+00 8.365E+00 l.371E+0l 2.994E-01 7.031E+0l lnll3m 6.566E-01 l.525E+02 3.638E+00 2.694E+00 4.076E+0l 9.087E-01 l.823E+0l 6.538E+00 1.434E-01 4.226E+0l ln114 4.099E+00 2.410E+0l 5.848E-01 1.390E+0l 7.483E+00 l.725E-01 5.775E+0l l.820E+00 4.070E-02 6.617E+00 ln114m 2.365E+00 4.135E+0l l.018E+00 7.173E+00 l.448E+0l 3.351E-01 2.774E+0l 3.758E+00 8.242E-02 l.132E+0l lnllS 2.614E+02 3.908E-0l 9.142E-03 1.807E+03 6.169E-02 l.327E-03 8.384E+03 6.324E-03 l.362E-04 l.073E-01 lnllSm 9.232E-01 l.084E+02 2.587E+00 3.787E+00 2.900E+0l 6.464E-01 2.561E+0l 4.653E+00 l.021E-01 3.006E+0l lr194 l.026E+00 9.SlSE+0l 2.333E+00 3.120E+00 3.298E+0l 7.730E-01 l.167E+0l 8.904E+00 2.034E-01 2.611E+0l K40 6.336E-01 1.457E+02 3.790E+00 l.267E+00 7.554E+0l 1.890E+00 3.133E+00 .3.075E+0l 7.365E-01 3.908E+0l K42 2.498E-01 3.723E+02 9.664E+00 4.996E-0l l.909E+02 4.821E+00 l.199E+00 8.017E+0l 1.958E+00 9.958E+0l Kr85 2.862E+0l 3.479E+00 8.379E-02 1.070E+02 9.882E-01 2.223E-02 5.253E+02 2.007E-01 4.312E-03 9.563E-01 La140 4.322E-02 2.149E+03 5.586E+0l 8.582E-02 1.113E+03 2.806E+0l 2.073E-01 4.642E+02 1.133E+0l 5.753E+02 Lu177 6.128E+00 l.675E+0l 3.906E-01 3.553E+0l 3.156E+00 6.705E-02 1.945E+02 3.394E-01 7.453E-03 4.627E+00 Lu177m 9.lS0E-01 l.098E+02 2.621E+00 3.512E+00 3.067E+0l 6.821E-01 2.046E+01 5.520E+00 l.174E-01 3.028E+0l Mn54 1.262E-01 7.495E+02 1.896E+0l 3.069E-01 3.277E+02 7.807E+00 9.926E-01 1.022E+02 2.300E+00 2.047E+02 Na22 4.798E-02 1.983E+03 5.032E+0l 1.llOE-01 8.848E+02 2.147E+01 3.320E-01 3.001E+02 6.951E+00 5.389E+02 Na24 2.430E-02 3.715E+03 9.927E+01 4.238E-02 2.183E+03 5.695E+0l 8.857E-02 1.058E+03 2.686E+0l 9.788E+02 Nb91 6.944E+01 1.411E+00 3.460E-02 2.077E+02 5.003E-01 1.141E-02 8.839E+02 1.169E-01 2.509E-03 3.873E-01 IC International

OPTIMUS-L Package SAR Docket No. 71-9390

• August 2020*

Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope Activity Method 2 Activity Method 2 Activity Method 2 (mrem/hr/Ci) Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Nb94 6.822E-02 l.399E+03 3.521E+0l l.707E-01 5.965E+02 1.412E+0l 5.716E-01 l.799E+02 4.023E+00 3.824E+02 Nb95 1.484E-01 6.499E+02 l.626E+0l 3.840E-01 2.690E+02 6.314E+00 l.346E+00 7.772E+0l l.724E+00 1.778E+02 Nb95m 2.901E+00 3.542E+0l 8.256E-01 l.566E+0l 7.160E+00 l.519E-01 9.181E+0l 8.056E-01 l.776E-02 9.803E+00 Nd144 6.690E+06 l.391E-05 3.599E-07 l.339E+07 7.147E-06 l.794E-07 3.131E+07 3.082E-06 7.541E-08 3.747E-06 Ni59 2.947E+0S 3.325E-04 8.154E-06 8.815E+0S l.179E-04 2.688E-06 3.751E+06 2.755E-05 5.912E-07 9.128E-05 Ni63 UNLIMITED 9.354E-11 2.210E-12 UNLIMITED 7.617E-17 1.587E-18 UNLIMITED 0.000E+00 0.000E+00 2.676E-ll Np235 6.SS0E+02 l.563E-01 3.643E-03 7.111E+03 l.579E-02 3.353E-04 2.110E+04 7.251E-04 1.408E-05 4.265E-02 Np237 6.819E+0l l.503E+00 3.502E-02 5.695E+02 l.969E-01 4.181E-03 2.186E+03 l.609E-02 3.441E-04 4.118E-01 Np238 l.727E-01 5.446E+02 1.393E+0l 3.818E-01 2.579E+02 6.291E+00 l.ll0E+00 9.056E+0l 2.096E+00 1.479E+02 Np239 1.463E+00 6.997E+0l l.635E+00 8.923E+00 l.253E+0l 2.682E-01 4.667E+0l l.362E+00 2.973E-02 l.929E+0l Np240 l.065E-01 9.007E+02 2.257E+0l 2.719E-01 3.708E+02 8.800E+00 9.233E-01 1.112E+02 2.502E+00 2.463E+02 Np240m 3.S0SE-01 2.751E+02 6.859E+00 9.204E-01 l.097E+02 2.592E+00 3.095E+00 3.251E+0l 7.386E-01 7.509E+0l Os185 1.832E-01 5.249E+02 1.299E+0l 5.044E-01 2.042E+02 4.764E+00 l.973E+00 S.446E+0l l.184E+00 1.441E+02 Os194 l.645E+07 5.836E-06 l.366E-07 UNLIMITED 7.622E-09 l.589E-10 UNLIMITED l.972E-12 3.829E-14 l.583E-06 P32 5.904E+00 1.688E+0l 4.056E-01 2.231E+0l 4.751E+00 l.076E-01 l.078E+02 l.000E+00 2.194E-02 4.643E+00 P33 3.592E+03 2.853E-02 6.647E-04 3.750E+04 2.994E-03 6.359E-05 1.156E+0S l.507E-04 2.986E-06 7.787E-03 Pa231 4.798E+00 2.094E+0l 4.980E-01 2.042E+0l 5.388E+00 1.195E-01 1.417E+02 8.387E-01 l.839E-02 5.802E+00 Pa233 7.562E-01 1.325E+02 3.160E+00 3.122E+00 3.513E+0l 7.826E-01 2.092E+0l 5.664E+00 l.239E-01 3.670E+0l Pa234 7.938E-02 l.199E+03 3.031E+0l l.913E-01 5.214E+02 l.253E+0l 5.952E-01 l.696E+02 3.892E+00 3.268E+02 Pa234m 2.291E+00 4.235E+0l 1.047E+00 6.493E+00 1.564E+0l 3.703E-01 2.205E+0l 4.630E+00 1.060E-01 1.157E+0l Pb209 1.166E+02 8.737E-01 2.0SlE-02 6.991E+02 1.584E-01 3.435E-03 3.744E+03 l.931E-02 4.168E-04 2.404E-01 Pb210 UNLIMITED 1.692E-11 4.102E-13 UNLIMITED 7.272E-12 1.740E-13 UNLIMITED 6.390E-12 1.513E-13 4.768E-12 Pb211 1.557E+00 6.233E+0l l.540E+00 4.373E+00 2.350E+0l 5.477E-01 1.626E+0l 6.390E+00 l.417E-01 1.709E+0l Pb212 l.584E+00 6.469E+0l l.SllE+00 8.305E+00 1.347E+0l 2.877E-0l 5.026E+0l 1.589E+00 3.S00E-02 1.791E+0l Pb214 7.282E-01 l.378E+02 3.285E+00 2.975E+00 3.662E+0l 8.154E-01 1.814E+0l 6.295E+00 1.384E-01 3.813E+0l NAC International 5.5-15

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope (mrem/hr/Ci) Activity Method 2 Activity Method 2 Activity Method 2 Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Pm145 UNLIMITED 7.343E-07 l.735E-08 UNLIMITED l.927E-14 4.844E-16 UNLIMITED 7.946E-15 l.948E-16 2.l0lE-07 Pm146 l.619E-01 6.037E+02 1.488E+0l 4.576E-01 2.277E+02 5.264E+00 1.788E+00 5.933E+0l l.299E+00 l.656E+02 Pm147 6.764E+03 l.SlSE-02 3.529E-04 7.262E+04 l.546E-03 3.284E-05 2.178E+05 7.241E-05 1.412E-06 4.133E-03 Pm148 l.778E-01 5.285E+02 l.352E+0l 3.918E-01 2.490E+02 6.102E+00 l.079E+00 9.081E+0l 2.135E+00 1.429E+02 Pm148m 5.723E-02 l.688E+03 4.188E+0l l.SSlE-01 6.602E+02 l.545E+0l 5.727E-01 l.822E+02 4.031E+00 4.625E+02 Po209 2.407E+0l 3.964E+00 9.938E-02 6.208E+0l l.629E+00 3.858E-02 2.075E+02 4.905E-01 l.103E-02 l.084E+00 Po210 9.183E+03 1.023E-02 2.579E-04 1.709E+04 5.789E-03 l.380E-04 3.139E+04 3.185E-03 7.378E-05 2.799E-03 Po211 l.461E+0l 6.SSSE+00 l.639E-01 3.807E+0l 2.669E+00 6.272E-02 l.326E+02 7.687E-01 l.709E-02 l.794E+00 Po212 l.796E+04 5.135E-03 l.282E-04 1.970E+04 4.899E-03 1.172E-04 2.300E+04 4.314E-03 l.013E-04 1.406E-03 Po213 2.634E+03 3.638E-02 9.lO0E-04 5.682E+03 l.783E-02 4.208E-04 l.263E+04 8.0SlE-03 l.842E-04 9.955E-03 Po214 l.324E+03 7.261E-02 l.816E-03 3.116E+03 3.281E-02 7.723E-04 8.297E+03 l.238E-02 2.801E-04 l.986E-02 Po215 4.099E+02 2.423E-01 5.859E-03 l.267E+03 8.287E-02 1.874E-03 5.084E+03 2.l00E-02 4.559E-04 6.668E-02 Po216 4.847E+03 1.938E-02 4.884E-04 8.874E+03 1.113E-02 2.655E-04 l.597E+04 6.257E-03 1.450E-04 5.297E-03 Po218 7.761E+03 l.209E-02 3.043E-04 1.346E+04 7.320E-03 l.747E-04 2.257E+04 4.421E-03 l.027E-04 3.305E-03 Pr143 3.537E+0l 2.862E+00 6.765E-02 1.752E+02 6.231E-01 1.371E-02 l.142E+03 9.503E-02 2.0S0E-03 7.882E-01 Pr144 l.124E+00 8.546E+0l 2.135E+00 2.923E+00 3.396E+0l 8.210E-01 8.694E+00 l.141E+0l 2.708E-01 2.323E+0l Pr144m 5.953E+0l l.573E+00 4.036E-02 l.265E+02 7.654E-01 l.898E-02 3.333E+02 2.941E-01 7.049E-03 4.243E-01 Pu236 6.595E+03 1.498E-02 3.586E-04 l.837E+04 5.446E-03 l.270E-04 2.892E+04 3.449E-03 8.041E-05 4.099E-03 Pu238 2.338E+04 3.993E-03 9.902E-05 2.876E+04 3.371E-03 8.042E-05 3.443E+04 2.881E-03 6.771E-05 1.lO0E-03 Pu239 4.109E+03 2.427E-02 5.801E-04 1.372E+04 7.648E-03 1.735E-04 3.694E+04 2.808E-03 6.412E-05 6.690E-03 Pu240 4.532E+03 2.070E-02 5.124E-04 5.674E+03 1.706E-02 4.083E-04 6.725E+03 1.468E-02 3.470E-04 5.847E-03 Pu241 4.769E+0S 2.148E-04 5.006E-06 S.140E+06 2.183E-05 4.639E-07 1.536E+07 1.040E-06 2.035E-08 5.861E-05 Pu242 6.172E+0l 1.S00E+00 3.750E-02 6.874E+01 1.404E+00 3.370E-02 8.034E+0l 1.228E+00 2.905E-02 4.278E-01 Pu243 3.907E+0l 2.576E+00 6.112E-02 1.833E+02 6.00lE-01 1.330E-02 1.265E+03 9.0lSE-02 1.969E-03 7.117E-01 Pu244 2.716E-01 3.413E+02 8.524E+00 3.014E-01 3.204E+02 7.687E+00 3.SlOE-01 2.810E+02 6.653E+00 9.805E+0l IC International

OPTIMUS-L Package SAR Docket No. 71-9390

• August2020
• Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages)

No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope (mrem/hr/Ci) Activity Method 2 Activity Method 2 Activity Method 2 Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Pu246 2.053E+00 5.00lE+0l l.165E+00 1.377E+0l 8.156E+00 1.729E-01 6.538E+0l 7.749E-01 1.686E-02 1.377E+0l Ra223 2.136E+00 4.742E+0l 1.120E+00 9.902E+00 1.lllE+0l 2.434E-01 6.867E+0l 1.644E+00 3.575E-02 1.311E+0l Ra224 l.915E+0l 5.365E+00 1.251E-01 1.032E+02 1.086E+00 2.305E-02 6.061E+02 l.242E-01 2.740E-03 1.485E+00 Ra225 l.224E+03 8.367E-02 1.951E-03 l.083E+04 l.035E-02 2.204E-04 3.931E+04 7.412E-04 1.SSlE-05 2.289E-02 Ra226 7.741E+0l l.323E+00 3.084E-02 8.126E+02 l.378E-01 2.933E-03 2.493E+03 8.096E-03 l.643E-04 3.610E-01 Rb86 8.806E-01 1.069E+02 2.718E+00 2.0lSE+00 4.905E+0l 1.196E+00 5.775E+00 l.734E+0l 4.028E-01 2.902E+0l Rb87 2.684E+03 3.818E-02 8.896E-04 2.701E+04 4.156E-03 8.828E-05 8.632E+04 2.287E-04 4.607E-06 1.043E-02 Re188 1.709E+00 5.710E+0l l.402E+00 5.200E+00 1.961E+0l 4.611E-0l l.880E+0l 5.482E+00 l.244E-01 1.562E+0l Rh102 2.469E-01 3.969E+02 9.723E+00 7.234E-01 1.430E+02 3.293E+00 2.919E+00 3.581E+0l 7.846E-01 1.089E+02 Rh106 3.664E-0l 2.642E+02 6.538E+00 l.018E+00 1.002E+02 2.351E+00 3.661E+00 2.809E+0l 6.310E-01 7.230E+0l Rn219 2.726E+00 3.707E+0l 8.809E-01 l.065E+0l 1.012E+0l 2.230E-01 6.282E+0l 1.780E+00 3.773E-02 1.023E+0l Rn220 1.895E+02 5.169E-01 l.268E-02 5.577E+02 1.860E-01 4.246E-03 2.223E+03 4.632E-02 l.002E-03 l.419E-01 Rn222 2.844E+02 3.444E-01 8.445E-03 8.379E+02 1.238E-01 2.826E-03 3.353E+03 3.072E-02 6.642E-04 9.453E-02 Ru103 2.866E-01 3.479E+02 8.381E+00 9.446E-01 l.122E+02 2.516E+00 4.781E+00 2.309E+0l 4.864E-01 9.580E+0l 535 3.475E+04 2.947E-03 6.867E-05 3.775E+05 2.974E-04 6.317E-06 l.119E+06 l.366E-05 2.651E-07 8.039E-04 Sb124 5.576E-02 1.677E+03 4.310E+0l 1.180E-01 8.205E+02 2.040E+0l 3.069E-01 3.189E+02 7.655E+00 4.514E+02 Sb125 2.938E-01 3.337E+02 8.127E+00 9.00lE-01 1.163E+02 2.659E+00 4.069E+00 2.702E+0l 5.765E-01 9.181E+0l Sb126 4.298E-02 2.252E+03 5.561E+0l 1.186E-01 8.691E+02 2.024E+0l 4.568E-01 2.322E+02 5.088E+00 6.181E+02 Sb126m 7.765E-02 1.253E+03 3.070E+0l 2.242E-01 4.627E+02 l.069E+0l 9.284E-01 l.162E+02 2.515E+00 3.443E+02 Sc46 5.255E-02 1.784E+03 4.553E+0l l.183E-01 8.370E+02 2.032E+0l 3.456E-01 2.902E+02 6.684E+00 4.849E+02 Se75 5.692E-01 1.793E+02 4.209E+00 2.898E+00 3.801E+0l 8.210E-01 1.819E+0l S.175E+00 1.lllE-01 4.947E+0l Se79 2.971E+04 3.447E-03 8.033E-05 3.229E+0S 3.477E-04 7.386E-06 9.570E+0S 1.597E-05 3.l00E-07 9.405E-04 Sm145 8.758E+03 1.142E-02 2.746E-04 2.937E+04 3.618E-03 8.083E-05 1.529E+0S 7.233E-04 1.519E-05 3.147E-03 Sml46 4.047E+06 2.302E-05 S.862E-07 6.054E+06 1.593E-05 3.898E-07 8.926E+06 1.097E-05 2.628E-07 6.478E-06 Sm147 S.226E+06 1.782E-05 4.570E-07 8.782E+06 1.095E-05 2.707E-07 1.493E+07 6.535E-06 1.575E-07 4.947E-06 NAC International 5.5-17

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope (mrem/hr/Ci) Activity Method 2 Activity Method 2 Activity Method 2 Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Sm148 6.561E+06 1.419E-05 3.667E-07 1.291E+07 7.419E-06 1.859E-07 2.900E+07 3.333E-06 8.141E-08 3.836E-06 Sm151 UNLIMITED 1.095E-08 2.562E-10 UNLIMITED 1.370E-11 2.855E-13 UNLIMITED 0.000E+00 0.000E+00 2.976E-09 Sn113 3.756E+0l 2.737E+00 6.377E-02 2.040E+02 5.S0lE-01 1.166E-02 1.188E+03 6.094E-02 1.344E-03 7.575E-01 Sn119m UNLIMITED 5.096E-09 1.204E-10 UNLIMITED 0.000E+00 0.000E+00 UNLIMITED 0.000E+00 0.000E+00 1.458E-09 Sn123 5.933E+00 1.639E+0l 4.035E-01 1.752E+0l 5.814E+00 1.373E-01 6.0SlE+0l 1.691E+00 3.866E-02 4.482E+00 Sn126 7.134E+02 1.412E-01 3.296E-03 8.304E+03 1.349E-02 2.875E-04 2.333E+04 1.004E-03 2.113E-05 3.857E-02 Sr85 2.278E-01 4.302E+02 1.0SSE+0l 6.814E-01 1.525E+02 3.478E+00 2.899E+00 3.565E+0l 7.650E-01 1.181E+02 Sr89 8.lO0E+00 1.234E+0l 2.956E-01 3.194E+0l 3.337E+00 7.516E-02 1.628E+02 6.676E-01 1.457E-02 3.396E+00 Sr90 1.344E+02 7.590E-01 1.779E-02 8.490E+02 1.309E-01 2.828E-03 4.312E+03 1.492E-02 3.223E-04 2.087E-01 Ta182 8.355E-02 1.119E+03 2.880E+0l 1.764E-01 5.501E+02 1.360E+0l 4.786E-01 2.072E+02 4.866E+00 3.024E+02 Tb157 UNLIMITED 8.867E-08 2.095E-09 UNLIMITED 0.000E+00 0.000E+00 UNLIMITED 0.000E+00 0.000E+00 2.537E-08 Tb160 1.025E-01 9.230E+02 2.347E+0l 2.363E-01 4.186E+02 1.0lSE+0l 7.087E-01 1.421E+02 3.276E+00 2.512E+02 Tc97m 4.065E+0S 2.362E-04 5.528E-06 1.404E+07 3.075E-07 6.408E-09 1.404E+07 0.000E+00 0.000E+00 6.408E-05 Tc99 1.993E+03 5.142E-02 1.198E-03 1.924E+04 5.833E-03 1.240E-04 6.405E+04 3.524E-04 7.209E-06 1.405E-02 Tc99m 3.154E+00 3.249E+0l 7.570E-01 3.396E+0l 3.306E+00 7.021E-02 1.015E+02 1.518E-01 2.948E-03 8.864E+00 Tel21 2.199E-01 4.456E+02 1.092E+0l 6.587E-01 1.578E+02 3.597E+00 2.808E+00 3.682E+0l 7.901E-01 1.223E+02 Te121m 7.560E-01 1.332E+02 3.168E+00 3.061E+00 3.473E+0l 7.813E-01 1.437E+0l 7.314E+00 1.675E-01 3.669E+0l Te123m 3.341E+00 3.067E+0l 7.147E-01 3.597E+0l 3.121E+00 6.629E-02 1.075E+02 1.433E-01 2.783E-03 8.369E+00 Te125m 1.003E+03 1.022E-01 2.381E-03 1.080E+04 1.040E-02 2.208E-04 3.228E+04 4.775E-04 9.270E-06 2.788E-02 Tel27 2.002E+0l 5.022E+00 1.199E-01 7.606E+0l 1.410E+00 3.133E-02 4.291E+02 2.602E-01 5.495E-03 1.384E+00 Te127m 1.251E+03 7.732E-02 1.902E-03 3.599E+03 2.879E-02 6.667E-04 1.506E+04 7.235E-03 1.554E-04 2.125E-02 Tel29 1.847E+00 5.352E+0l 1.300E+00 5.832E+00 1.788E+01 4.093E-01 2.477E+01 4.283E+00 9.405E-02 1.470E+0l Te129m 3.778E+00 2.559E+0l 6.319E-01 1.038E+0l 9.936E+00 2.318E-01 3.935E+0l 2.683E+00 5.894E-02 7.024E+00 Th227 1.267E+00 8.045E+01 1.888E+00 6.301E+00 1.767E+0l 3.816E-01 4.041E+0l 2.279E+00 5.014E-02 2.227E+01 Th228 2.298E+02 4.466E-01 1.041E-02 1.351E+03 8.268E-02 1.759E-03 7.303E+03 1.054E-02 2.346E-04 1.232E-01 IC International

OPTIMUS-L Package SAR Docket No. 71-9390

• August2020 Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages)

No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope Activity Method 2 Activity Method 2 Activity Method 2 (mrem/hr/Ci) Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Th229 6.850E+00 1.497E+0l 3.489E-01 5.166E+0l 2.169E+00 4.611E-02 2.191E+02 l.909E-01 4.095E-03 4.108E+00 Th230 2.621E+03 3.897E-02 9.107E-04 l.572E+04 6.890E-03 1.503E-04 5.659E+04 l.816E-03 4.177E-05 l.069E-02 Th231 l.820E+02 5.624E-01 l.311E-02 l.721E+03 6.518E-02 1.386E-03 5.853E+03 4.217E-03 8.712E-05 l.538E-01 Th232 l.161E+04 8.745E-03 2.0S0E-04 6.817E+04 1.530E-03 3.440E-05 1.482E+0S 6.697E-04 l.565E-05 2.387E-03 Th234 l.059E+03 9.656E-02 2.250E-03 l.183E+04 9.486E-03 2.0lSE-04 3.417E+04 4.355E-04 8.454E-06 2.634E-02 Tl206 2.501E+03 3.784E-02 9.565E-04 6.109E+03 l.647E-02 3.923E-04 l.980E+04 5.127E-03 l.153E-04 l.034E-02 Tl207 9.372E+00 l.058E+0l 2.554E-01 3.406E+0l 3.090E+00 7.044E-02 l.538E+02 6.912E-01 l.523E-02 2.908E+00 Tl208 3.0llE-02 3.019E+03 8.019E+0l 5.408E-02 l.713E+03 4.469E+0l 1.129E-01 8.274E+02 2.120E+0l 7.964E+02 Tl209 4.803E-02 l.943E+03 5.030E+0l 9.661E-02 9.883E+02 2.491E+0l 2.334E-01 4.119E+02 l.006E+0l 5.197E+02 Tm168 9.967E-02 9.607E+02 2.406E+0l 2.575E-01 3.944E+02 9.321E+00 8.770E-01 l.171E+02 2.621E+00 2.627E+02 Tm170 3.458E+0l 2.926E+00 6.919E-02 1.702E+02 6.411E-0l 1.411E-02 l.117E+03 9.868E-02 2.129E-03 8.059E-01 Tml71 UNLIMITED 7.424E-07 l.743E-08 UNLIMITED 6.396E-10 l.334E-11 UNLIMITED l.306E-12 2.535E-14 2.054E-07 U232 2.540E+03 3.991E-02 9.380E-04 1.367E+04 7.782E-03 l.736E-04 3.868E+04 2.639E-03 6.088E-05 l.094E-02 U233 l.388E+03 7.298E-02 l.721E-03 6.498E+03 l.681E-02 3.700E-04 3.102E+04 3.521E-03 7.952E-05 2.0lSE-02 U234 5.785E+03 l.751E-02 4.lllE-04 3.117E+04 3.327E-03 7.516E-05 6.380E+04 l.561E-03 3.635E-05 4.780E-03 U235 2.739E+00 3.744E+0l 8.724E-01 2.395E+0l 4.686E+00 9.951E-02 8.782E+0l 3.328E-01 6.985E-03 l.025E+0l U236 l.147E+04 8.760E-03 2.067E-04 4.578E+04 2.213E-03 5.091E-05 7.422E+04 l.337E-03 3.134E-05 2.394E-03 U237 2.268E+00 4.518E+0l 1.0SSE+00 1.404E+0l 7.976E+00 l.701E-01 7.227E+0l 8.383E-01 1.831E-02 1.245E+0l U238 6.695E+02 1.389E-01 3.462E-03 7.623E+02 l.267E-01 3.040E-03 8.910E+02 l.107E-01 2.621E-03 3.994E-02 U239 7.144E+00 l.365E+0l 3.354E-01 2.172E+0l 4.745E+00 1.l0SE-01 8.339E+0l l.253E+00 2.788E-02 3.744E+00 U240 2.955E+02 3.469E-01 8.084E-03 2.617E+03 4.286E-02 9.llOE-04 9.482E+03 3.003E-03 6.282E-05 9.492E-02 W181 2.459E+03 4.166E-02 9.707E-04 2.650E+04 4.237E-03 9.000E-05 7.918E+04 1.946E-04 3.778E-06 1.137E-02 W185 4.350E+02 2.352E-01 5.493E-03 3.307E+03 3.380E-02 7.240E-04 1.395E+04 3.064E-03 6.SSSE-05 6.451E-02 W188 1.119E+02 9.185E-01 2.140E-02 6.353E+02 1.767E-01 3.745E-03 3.545E+03 1.902E-02 4.184E-04 2.539E-01 Xe127 7.279E-01 1.401E+02 3.287E+00 3.742E+00 2.976E+0l 6.427E-01 2.323E+0l 3.760E+00 8.257E-02 3.875E+0l NAC International 5.5-19

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 OPTIMUS-L Dose Rate/Ci and Maximum Activity Results (10 Pages) No SIA 1-inch SIA 21/4-inch SIA HAC Dose Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Method 1 NCT Dose Rate (mrem/hr/Ci) Rate Isotope (mrem/hr/Ci) Activity Method 2 Activity Method 2 Activity Method 2 Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter Limit (Ci) Pkg Surface 2-meter 1-meter Xe131m 1.446E+02 7.087E-01 l.651E-02 1.557E+03 7.210E-02 l.532E-03 4.655E+03 3.312E-03 6.429E-05 l.933E-01 Y88 3.810E-02 2.421E+03 6.348E+0l 7.269E-02 l.295E+03 3.282E+0l l.743E-01 5.534E+02 1.357E+0l 6.482E+02 Y89m 1.131E-01 8.392E+02 2.140E+0l 2.573E-01 3.841E+02 9.302E+00 7.962E-01 l.277E+02 2.929E+00 2.287E+02 Y90 2.813E+00 3.507E+0l 8.519E-01 9.416E+00 l.106E+0l 2.549E-01 3.894E+0l 2.700E+00 6.028E-02 9.630E+00 Y90m 2.304E-01 4.376E+02 l.043E+0l 8.651E-01 l.242E+02 2.746E+00 4.933E+00 2.261E+0l 4.777E-01 l.207E+02 Y91 6.024E+00 1.636E+0l 3.984E-01 1.980E+0l 5.199E+00 l.210E-01 7.703E+0l l.347E+00 3.053E-02 4.485E+00 Zn65 1.758E-01 5.307E+02 l.362E+0l 3.785E-01 2.594E+02 6.365E+00 l.048E+O0 9.514E+0l 2.216E+00 1.437E+02 Zr88 4.352E-01 2.301E+02 5.489E+00 l.786E+00 6.151E+0l l.371E+00 1.208E+0l 9.865E+00 2.164E-01 6.377E+0l Zr90m 4.265E-02 2.102E+03 5.655E+0l 7.255E-02 l.264E+03 3.307E+0l 1.498E-01 6.272E+02 1.589E+0l 5.524E+02 Zr93 UNLIMITED 7.448E-11 l.760E-12 UNLIMITED 0.000E+00 0.000E+00 UNLIMITED 0.000E+00 0.000E+00 2.131E-11 Zr95 l.S0lE-01 6.424E+02 l.607E+0l 3.885E-01 2.659E+02 6.240E+00 1.362E+00 7.682E+0l 1.704E+00 l.758E+02 Note: 1 Isotopes with an activity limit exceeding 108 Ci are labeled as 'UNLIMITED'. IC International

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 5.5-1 -MCNP Models with 1-inch SIA (left) and 21/4-inch SIA (right)

• NAC International 5.5-21

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 15 ft. Cab 2-meter Trailer Surface

• 72 in.

SO in. Figure 5.5 Method 1- 6-Package Array and Cell Tally Locations (top view) NAC International 5.5-22

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 5.5 Method 2 - Cell Tally Locations - 6 Package Array NAC International 5.5-23

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 5.5.3 Example Cases Revision 20A Examples of demonstrating compliance for a hypothetical group of packages via Method 1 and Method 2 are provided in Sections 5.5.3.1 through 5.5.3.3. The examples are for a 2x5 bare package array configuration (i.e., without SIAs). The same examples can be applied to a lx6 package array configuration, with or without SIAs, using the activity limits from Table 5.5-8. 5.5.3.1 Examples - Method 1 Compliance To provide an example of the demonstration of compliance using Method 1 for a group of packages, a group of 20 hypothetical packages with the listed isotope inventories was generated (labelled Content ID's 1-20), as shown in Table 5.5-1. The sum of the fractions for each of the hypothetical packages is calculated in the table using the Method I activity limits for each isotope, determined as specified in Section 5.4.4.2. The sum of the fractions for each of the packages, except package number 20, is less than I. As a result, a group of any 10 of these packages could be transported in any arrangement/grouping, with the exception of package 20. Because the sum of the fraction exceeds I for package 20, this package is not acceptable for transport under Method I. However, this package is acceptable for transport under Method 2, as shown in Sections 5.5.3.2 and 5.5.3.3. 5.5.3.2 Examples - Method 2 Compliance for a Single Package To provide an example of the demonstration of compliance using Method 2 for transporting a single package the hypothetical content load from package 20 in Table 5.5-8, which failed the Method 1 compliance check in Section 5.5.3.1, is used. The dose rates are calculated in Table 5.5-11 using the Method 2 dose rates per curie from Table 5.4-11. The calculated dose rates are then entered into the example compliance table to calculate the Total 2-meter Dose Rate using the DRCFs in Table 5.5-12. The results in this table demonstrate that no external dose rate would exceed the regulatory limit for the respective location. Thus, this package is acceptable for transport as a single package shipment using Method 2. It can be noted that Total 2-meter Dose Rate of 0.035 mSv/hr listed in Table 5.5-12 is significantly below the limit of 9 mrem/hr. This indicates that this package could be paired with a number of other packages with lower activity contents using Method 2 for multiple packages. An example of this potential pairing with other packages is shown in Section 5.5.3.3. 5.5.3.3 Examples - Method 2 Compliance for Multiple Packages To provide an example of the demonstration of compliance using Method 2 for transporting multiple packages, the hypothetical content loads from IO content IDs in Table 5.5-10 are used. The dose rates are calculated in Table 5.5-13 using the Method 2 dose rates per curie from Table 5.4-11. The calculated dose rates are then arranged from largest to smallest and entered into the NAC International 5.5-24

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A example compliance table to calculate the Total 2-meter Dose Rate using the DRCFs as shown in Table 5.5-14. The results in this table show that the final calculated value for the package surface and the Total Dose Rate for the 2-meter is less than the limit, indicating this group of packages would not exceed the 2-meter dose rate. In addition, the package surface and HAC 1-meter dose rates for each package are all below their respective dose rate limits. Thus, this specific group of 10 packages is acceptable for transport using Method 2, in any arrangement. It is noted in Table 5.5-14 that the packages selected to be grouped with Content ID 20 in this example are the lower activity Content IDs from Table 5.5-1. This group of example packages was generated with the distinct purpose of demonstrating that higher activity packages that fail the criterion of Method 1 may still be acceptable for shipment with a group of packages with lower activity contents using Method 2, with some additional effort from the package user .

• NAC International 5.5-25

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Content Table 5.5 Example Method 1 Compliance Calculations Isotope Activity in Ci (Method 1 Activity Limits Shown in Parentheses) Revision 20A Sum of the ID Th-228 Th-230 Co-60 Zn-65 Fe-59 Cr-51 Fractions (1.575E+02) (1.782E+03) (2.837E-02) (1.181E-01) (5.720E-02) (2.888E+00) 1 9.50 4.30 0.001 0.006 0.0001 0.640 0.38 2 22.60 10.23 0.002 0.001 0.0004 0.230 0.32 3 5.70 2.58 0.001 0.005 0.0003 0.201 0.20 4 20.50 9.28 0.006 0.006 0.0001 0.112 0.44 5 13.70 6.20 0.003 0.030 0.0002 0.632 0.68 6 18.90 8.55 0.002 0.006 0.0010 0.700 0.51 7 20.20 9.14 0.001 0.002 0.0012 0.911 0.53 8 8.80 3.98 0.004 0.003 0.0023 0.300 0.37 9 10.20 4.62 0.002 0.007 0.0050 0.205 0.36 10 17.80 8.06 0.005 0.017 0.0100 0.660 0.85 11 19.20 8.69 0.001 0.012 0.0046 0.104 0.39 12 20.70 9.37 0.001 0.030 0.0130 0.204 0.73 13 44.30 20.05 0.001 0.027 0.0101 0.245 0.82 14 10.10 4.57 0.004 0.014 0.0020 0.846 0.66 15 16 17 18 19 1.80 6.60 0.00 0.00 0.00 0.81 2.99 0.00 0.00 0.00 0.005 0.002 0.010 0.009 0.011 0.010 0.002 0.022 0.006 0.007 0.0031 0.0096 0.0046 0.0130 0.0160 0.246 0.356 0.654 0.365 0.235 0.42 0.43 0.85 0.73 0.81 20 11.50 5.21 0.020 0.005 0.0096 1.200 1.41 Table 5.5 Example Method 2 Single Package Dose Rate Calcuation Radionuclide Activity (Ci) Dose Rate (mrem/hr) Content NCT ID NCT HAC Th-228 Th-230 Co-60 Zn-65 Fe-59 Cr-51 Pkg. 2-meter 1-meter Surface 20 11.500 5.205 0.020 0.005 0.0096 1.200 3.492 90.492 24.678 NAC International 5.5-26

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 5.5 Example Method 2 Single Package Compliance Calculation Package# 2-meter Package Surface HAC 1-meter Dose Rate Dose Rate Dose Rate (n) DRCF Product (mrem/hr) (mrem/hr) (mrem/hr) 1 3.492 1.000 3.492 90.492 24.678 2 0.893 3 0.675 4 0.480 5 0.455 6 0.432 7 0.373 8 0.342 9 0.305 10 0.243 Totals 3.492 Max: 90.492 Max: 24.678 Limit 9 180 900

• Content ID Table 5.5 Example Method 2 Multiple Package Dose Rate Calcuation Th-228 Radionuclide Activity (Ci)

Th-230 Co-60 Zn-65 Fe-59 Cr-51 Dose Rate (mrem/hr) 2-meter Package Surface HAC 1-meter 1 9.50 4.30 0.001 0.006 0.0001 0.640 0.927 24.895 6.859 2 22.60 10.23 0.002 0.001 0.0004 0.230 0.791 21.239 5.836 3 5.70 2.58 0.001 0.005 0.0003 0.201 0.474 12.532 3.436 4 20.50 9.28 0.006 0.006 0.0001 0.112 1.096 28.610 7.803 8 8.80 3.98 0.004 0.003 0.0023 0.300 0.918 23.997 6.557 9 10.20 4.62 0.002 0.007 0,0050 0.205 0.886 23.095 6.303 11 19.20 8.69 0.001 0.012 0.0046 0.104 0.952 24.929 6.807 15 1.80 0.81 0.005 0.010 0.0031 0.246 1.023 26.265 7.145 16 6.60 2.99 0.002 0.002 0.0096 0.356 1.054 27.429 7.488 20 11.50 5.21 0.020 0.005 0.0096 1.200 3.492 90.492 24.678

• NAC International 5.5-27

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 5.5 Example Method 2 Multiple Package Compliance Calculation Package# 2-meter Package Surface HAC 1-meter Dose Rate Dose Rate Dose Rate (n) DRCF Product (mrem/hr) (mrem/hr) (mrem/hr) 1 3.492 1.000 3.492 90.492 24.678 2 1.096 0.893 0.979 28.610 7.803 3 1.054 0.675 0.711 27.429 7.488 4 1.023 0.480 0.491 26.265 7.145 5 0.952 0.455 0.433 24.929 6.807 6 0.927 0.432 0.401 24.895 6.859 7 0.918 0.373 0.342 23.997 6.557 8 0.886 0.342 0.303 23.095 6.303 9 0.791 0.305 0.241 21.239 5.836 10 0.474 0.243 0.115 12.532 3.436 Total 7.509 Max: 90.492 Max: 24.678 Limit 9 180 900 NAC International 5.5-28

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Chapter 6 Criticality Evaluation Table of Contents 6 CRITICALITY EVALUATION ..................................................................................... 6-1 6.1 Description of Criticality Design .................................................................................. 6.1-1 6.1.1 Design Features ................................................................................................. 6.1-1 6.1.2 Summary Table of Criticality Evaluation ......................................................... 6.1-1 6.1.3 Criticality Safety Index ..................................................................................... 6.1-1 6.2 Package Contents .......................................................................................................... 6.2-1 6.2.1 FGE Cases ......................................................................................................... 6.2-1 6.2.2 FEM Cases ........................................................................................................ 6.2-1 6.3 General Considerations ................................................................................................. 6.3-1 6.3.1 Model Configuration ......................................................................................... 6.3-1 6.3.2 Material Properties ............................................................................................ 6.3-5 6.3.3 Computer Codes and Cross-Section Libraries .................................................. 6.3-8 6.3.4 Demonstration of Maximum Reactivity ........................................................... 6.3-8 6.4 Single Package Evaluation ............................................................................................ 6.4-1 6.4.1 FGE Single Package Configuration .................................................................. 6.4-1 6.4.2 FGE Single Package Summary Results ............................................................ 6.4-1 6.4.3 FEM Single Package Configuration ................................................................. 6.4-9 6.4.4 FEM-1 Single Package Summary Results ........................................................ 6.4-9 6.5 Evaluation of Package Arrays Under Normal Conditions of Transport ....................... 6.5-1 6.5.1 FGE NCT Package Array Configuration .......................................................... 6.5-1 6.5.2 FGE NCT Package Array Results ..................................................................... 6.5-1 6.5.3 FEM NCT Package Array Configuration ......................................................... 6.5-8 6.5.4 FEM NCT Package Array Results .................................................................... 6.5-8 6.6 Package Arrays Under Hypothetical Accident Conditions ........................................... 6.6-1 6.6.1 FGE HAC Package Array Configuration ......................................................... 6.6-1 6.6.2 FGE HAC Package Array Results .................................................................... 6.6-1 6.6.3 FEM HAC Package Array Configuration ......................................................... 6.6-9 6.6.4 FEM-1 HAC Package Array Summary Results ................................................ 6.6-9 6.7 Fissile Material Packages for Air Transport ................................................................. 6.7-1 6.8 Benchmark Evaluation .................................................................................................. 6.8-1 6.8.1 Applicability of Benchmark Experiments ........................................................ 6.8-1 6.8.2 Bias Determination ........................................................................................... 6.8-4 6.9 Appendix ....................................................................................................................... 6.9-1

• 6.9.1 References ......................................................................................................... 6.9-1 NAC International 6-i

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A List of Figures Figure 6.3 MCNP6 Model Packaging Geometry .............................................................. 6.3-3 Figure 6.3 Single Package Model ..................................................................................... 6.3-4 Figure 6.3 Baseline Package Array Model... ..................................................................... 6.3-4 Figure 6.3 Single Package Fissile Shape Positions ......................................................... 6.3-16 Figure 6.3 Package Array Fissile Shape Positions .......................................................... 6.3-16 Figure 6.3 Fissile Sphere Positioning for NCT Package Arrays ..................................... 6.3-17 Figure 6.3 Fissile Sphere Positioning for HAC Package Arrays .................................... 6.3-17 Figure 6.3 Floodable Regions: (1) OP Region (2) Interspersed Region ......................... 6.3-18 Figure 6.3 FEM Homogeneous Volume Cases - Single Package and HAC Package Array ............................................................................................................... 6.3-18 Figure 6.3 FEM Homogeneous Volume Cases-NCT Package Array ........................ 6.3-18 Figure 6.3 FEM Fissile Heterogeneous Cylindrical Particle Cases .............................. 6.3-19 Figure 6.3 FEM Fissile Heterogeneous Spherical Particle Cases ................................. 6.3-20 Figure 6.4 FGE-1 Single Package Baseline Study ............................................................ 6.4-6 Figure 6.4 FGE-2a Single Package Baseline Study .......................................................... 6.4-6 Figure 6.4 FGE-2b Single Package Baseline Study .......................................................... 6.4-7 Figure 6.4 FGE-2c Single Package Baseline Study .......................................................... 6.4-7 Figure 6.4 FGE-3 Single Package Baseline Study ............................................................ 6.4-8 Figure 6.4 FGE-5 Single Package Baseline Study ............................................................ 6.4-8 Figure 6.4 FEM-1 Single Package Homogeneous Mass Study ...................................... 6.4-14 Figure 6.4 FEM-1 Single Package Heterogeneous Cylindrical Particle Study ............... 6.4-14 Figure 6.4 FEM-1 Single Package Heterogeneous Spherical Particle Study .................. 6.4-15 Figure 6.5 FGE-1 NCT Package Array Baseline Study .................................................... 6.5-5 Figure 6.5 FGE-2a NCT Package Array Baseline Study .................................................. 6.5-5 Figure 6.5 FGE-2b NCT Package Array Baseline Study .................................................. 6.5-6 Figure 6.5 FGE-2c NCT Package Array Baseline Study .................................................. 6.5-6 Figure 6.5 FGE-3 NCT Package Array Baseline Study .................................................... 6.5-7 Figure 6.5 FGE-5 NCT Package Array Baseline Study .................................................... 6.5-7 Figure 6.5 FEM-1 NCT Package Array Homogeneous Mass Study .............................. 6.5-13 Figure 6.5 FEM-1 NCT Package Array Heterogeneous Cylindrical Particle Study ....... 6.5-13 Figure 6.5 FEM-1 NCT Package Array Heterogeneous Spherical Particle Study .......... 6.5-14 Figure 6.6 FGE-1 HAC Package Array Baseline Study ................................................... 6.6-6 Figure 6.6 FGE-2a HAC Package Array Baseline Study .................................................. 6.6-6 Figure 6.6 FGE-2b HAC Package Array Baseline Study ................................................. 6.6-7 Figure 6.6 FGE-2c HAC Package Array Baseline Study .................................................. 6.6-7 Figure 6.6 FGE-3 HAC Package Array Baseline Study ................................................... 6.6-8 Figure 6.6 FGE-5 HAC Package Array Baseline Study ................................................... 6.6-8 Figure 6.6 FEM-I HAC Package Array Homogeneous Mass Study .............................. 6.6-14 Figure 6.6 FEM-I HAC Package Array Heterogeneous Cylindrical Particle Study ...... 6.6-14 Figure 6.6 FEM-I HAC Package Array Heterogeneous Spherical Particle Study ......... 6.6-15 Figure 6.8 keff vs. EALF - Plutonium Solution Systems without Beryllium Reflector .. 6.8-10 Figure 6.8 keffVS. H/(239Pu + 241 Pu)-Plutonium Systems without Beryllium Reflector .......................................................................................................... 6.8-1 O Figure 6.8 keff vs. Fissile Weight Percent - Plutonium Solution Systems without Beryllium Reflector ........................................................................................ 6.8-11 NAC International 6-ii

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.8 keff vs. EALF - Plutonium Solution Systems with Beryllium Reflector ....... 6.8-11 Figure 6.8 keffVS. H/(239Pu + 241 Pu)-Plutonium Solution Systems with Beryllium Reflector .......................................................................................................... 6.8-12 Figure 6.8 keffVS. Fissile Weight Percent-Plutonium Solution Systems with Beryllium Reflector ........................................................................................ 6.8-12 Figure 6.8 keff vs. EALF - Low-Enriched Uranium Systems ......................................... 6.8-13 Figure 6.8 keff vs. H/235U - Low-Enriched Uranium Systems ........................................ 6.8-13 Figure 6.8 keff vs. 235 U Weight Percent - Low-Enriched Uranium Systems ................... 6.8-14

• NAC International 6-iii

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A List of Tables Table 6.1 Summary Table ofFGE Criticality Evaluations ............................................... 6.1-2 Table 6.1 Summary Table of FEM Criticality Evaluations .............................................. 6.1-2 Table 6.2 Fissile Gram Equivalent Waste Content Cases ................................................. 6.2-2 Table 6.2 Fissile Equivalent Mass Waste Content Cases .................................................. 6.2-2 Table 6.2 Fissile Gram Equivalent Waste Content Case Description ............................... 6.2-3 Table 6.2 Fissile Equivalent Mass Waste Content Case Description ............................... 6.2-3 Table 6.3 OP Combined Directional Stainless Steel Thicknesses .................................... 6.3-2 Table 6.3 Packaging Axial Dimensions ............................................................................ 6.3-2 Table 6.3 Packaging Radial Dimensions ........................................................................... 6.3-3 Table 6.3 Nuclear Properties of Type 304 Stainless Steel ................................................ 6.3-6 Table 6.3 Nuclear Properties of Materials ........................................................................ 6.3-7 Table 6.3 NCT Package Array Homogeneous Fissile Volume Study Configurations ... 6.3-15 Table 6.4 FGE Result Summary - Single Package ............................................................ 6.4-3 Table 6.4 FGE-1 Baseline Configuration - Single Package ............................................. 6.4-3 Table 6.4 FGE-2a Baseline Configuration - Single Package ........................................... 6.4-3 Table 6.4 FGE-2b Baseline Configuration - Single Package ........................................... 6.4-4 Table 6.4 FGE-2c Baseline Configuration - Single Package ........................................... 6.4-4 Table 6.4 FGE-3 Baseline Configuration - Single Package ............................................. 6.4-4 Table 6.4 FGE-5 Baseline Configuration - Single Package ............................................. 6.4-5 Table 6.4 FGE Fissile Sphere Position Study Results - Single Package .......................... 6.4-5 Table 6.4 FGE Flooding Study Results - Single Package ................................................ 6.4-5

• Table 6.4 FEM-I Summary - Single Package .............................................................. 6.4-11 Table 6.4 FEM-I Homogeneous Sphere Results - Single Package .............................. 6.4-11 Table 6.4 FEM-I Bounding Case for Each Cylindrical Particle Size - Single Package ........................................................................................................... 6 .4-12 Table 6.4 FEM-I Bounding Cylindrical Particle Size- Single Package ...................... 6.4-12 Table 6.4 FEM-I Bounding Case for Each Spherical Particle Size - Single Package ........................................................................................................... 6.4-12 Table 6.4 FEM-I Bounding Spherical Particle Size - Single Package ......................... 6.4-13 Table 6.4 FEM-I Fissile Position Study Results - Single Package .............................. 6.4-13 Table 6.4 FEM-I Flooding Study Results - Single Package ........................................ 6.4-13 Table 6.5 FGE Result Summary - NCT Package Array ................................................... 6.5-3 Table 6.5 FGE-1, 2a, 2b, and 2c Baseline Configurations - NCT Package Array ........... 6.5-3 Table 6.5 FGE-3 Baseline Configuration - NCT Package Array ..................................... 6.5-3 Table 6.5 FGE-5 Baseline Configuration - NCT Package Array ..................................... 6.5-4 Table 6.5 FGE Fissile Sphere Position Study Results - NCT Package Array .................. 6.5-4 Table 6.5 FEM-I Summary - NCT Package Array ........................................................ 6.5-10 Table 6.5 FEM-I Homogeneous Sphere Results -NCT Package Array ........................ 6.5-10 Table 6.5 FEM-I Bounding Case for Each Cylindrical Particle Size -NCT Package Array ............................................................................................................... 6.5-11 Table 6.5 FEM-I Bounding Cylindrical Particle Size - NCT Package Array ................ 6.5-11 Table 6.5 FEM-I Bounding Case for Each Spherical Particle Size - NCT Package Array ............................................................................................................... 6.5-11 Table 6.5 FEM-I Bounding Spherical Particle Size-NCT Package Array ................. 6.5-12
• Table 6.5 FEM-I Fissile Position Study Results -NCT Package Array ...................... 6.5-12 NAC International 6-iv

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.6 Mass Limit Cases for FGE - HAC Package Array ........................................... 6.6-3 Table 6.6 FGE-1 Baseline Configuration - HAC Package Array ..................................... 6.6-3 Table 6.6 FGE-2a Baseline Configuration - HAC Package Array ................................... 6.6-3 Table 6.6 FGE-2b Baseline Configuration - HAC Package Array ................................... 6.6-4 Table 6.6 FGE-2c Baseline Configuration - HAC Package Array ................................... 6.6-4 Table 6.6 FGE-3 Baseline Configuration - HAC Package Array ..................................... 6.6-4 Table 6.6 FGE-5 Baseline Configuration - HAC Package Array ..................................... 6.6-5 Table 6.6 FGE Fissile Sphere Position Study Results - HAC Package Array ................. 6.6-5 Table 6.6 FGE Flooding Study Results - HAC Package Array ........................................ 6.6-5 Table 6.6 FEM-I Summary-RAC Package Array ...................................................... 6.6-l l Table 6.6 FEM-1 Homogeneous Sphere Results - HAC Package Array ..................... 6.6-11 Table 6.6 FEM-1 Bounding Case for Each Cylindrical Particle Size -HAC Package Array ................................................................................................. 6.6-12 Table 6.6 FEM-I Bounding Cylindrical Particle Size - HAC Package Array ............. 6.6-12 Table 6.6 FEM-I Bounding Case for Each Spherical Particle Size - HAC Package Array ................................................................................................. 6.6-12 Table 6.6 FEM-l Bounding Spherical Particle Size - HAC Package Array ................ 6.6-13 Table 6.6 FEM-1 Fissile Position Study Results - HAC Package Array ..................... 6.6-13 Table 6.6 FEM-I Flooding Study Results-RAC Package Array ................................ 6.6-13 Table 6.8 Criticality Safety Bias and USL Functions ....................................................... 6.8-6 Table 6.8 FGE Criticality Safety USL Functions ............................................................. 6.8-6 Table 6.8 FEM Criticality Safety USL Functions ............................................................. 6.8-6 Table 6.8 Critical Benchmark Experiments - Plutonium Cases ....................................... 6.8-7 Table 6.8 Critical Benchmark Experiments - Low-Enriched Uranium Cases ................. 6.8-7 Table 6.8 Plutonium Critical Experiment Area of Applicability ...................................... 6.8-8 Table 6.8 Low-Enriched Uranium Critical Experiment Area of Applicability ................. 6.8-8 Table 6.8 USL Functions for Plutonium without Beryllium Reflector Benchmarks ........ 6.8-8 Table 6.8 USL Functions for Plutonium with Beryllium Reflector Benchmarks ............. 6.8-9 Table 6.8 USL Functions for Low-Enriched Uranium Critical Benchmarks ................. 6.8-9

• NAC International 6-v

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6 CRITICALITY EVALUATION This chapter presents the criticality evaluation demonstrating the OPTIMUS-L package complies with the requirements of 10 CFR §71.55 and §71.59 for the contents specified in Section 1.2.2 and discussed in Section 6.2. Specifically, the criticality evaluation demonstrates compliance with the criticality requirements for TRU waste that satisfies the fissile gram equivalent (FGE) limits for 239Pu specified in Table 1.2-1 ~nd the fissile equivalent mass (FEM) limits for 235 U specified in Table 1.2-2. The results of the criticality evaluation are summarized in Section 6.1.2. No additional criticality evaluations are performed for the Shield Insert Assemblies (SIAs). Depending on the content, the use of the SIAs will have either a negligible or negative effect on the criticality of the system. The additional reflection provided by the SIAs is negligible, considering the reflection provided by the CCV and OP of the bare cask. The use of the SIAs will only further restrict the geometric configuration of the fissile contents. Thus, the use of the SIAs is bounded by the bare cask, as analyzed in this chapter.

• NAC International 6-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.1 Description of Criticality Design 6.1.1 Design Features The packaging consists of the stainless steel inner Cask Containment Vessel (CCV), which contains the contents, and the Outer Packaging (OP). The OP is a foam impact limiter with a steel shell that fully houses the CCV. The CCV and OP are responsible for the confinement credited in the analysis. In addition, credit is taken for the spacing provided by the damaged OP in the package array analyses. The package does not have any additional neutron absorbing or moderating materials other than the materials of construction. There are no flux traps and no credit is taken for spacers or dunnage in the payload. 6.1.2 Summary Table of Criticality Evaluation 6.1.2.1 Summary of FGE Criticality Evaluation As shown in Table 6.1-1, all mass limits shown for each fissile gram equivalent (FOE) case have keff+ 2cr below their respective upper subcritical limit (USL) for the single package, NCT package array, and HAC package array evaluations. The FOE cases are described in Section 6.2.1 . 6.1.2.2 Summary of FEM Criticality Evaluation As shown in Table 6.1-2, all most reactive cases for the fissile equivalent mass (FEM-1) case have keff + 2cr below their respective USLs for the single package, NCT package array, and HAC package array evaluations. The FEM cases are described in Section 6.2.2. 6.1.3 Criticality Safety Index Fifty (50) packages, 5N, analyzed in the NCT package array evaluation are subcritical and twenty (20) packages, 2N, analyzed in the HAC package array evaluation are subcritical. Per 10 CFR 71.59, the NCT and HAC array sizes equate to an "N" value of 10. Therefore, the CSI is 5.0 .

• NAC International 6.1-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.1 Summary Table of FGE Criticality Evaluations FGE 2aspu Package H12aspu Array Size kett + 2cr USL Case Mass (g) Configuration 900 Single Package -- 0.93258 FGE-1 340 604 NGT Array 50 0.84346 0.93930 900 HAG Array 20 0.93911 950 Single Package -- 0.93030 FGE-2a 350 587 NGT Array 50 0.83837 0.93930 900 HAG Array 20 0.93779 900 Single Package -- 0.93317 FGE-2b 375 547 NGT Array 50 0.83200 0.93930 900 HAG Array 20 0.93921 900 Single Package -- 0.93337 FGE-2c 395 520 NGT Array 50 0.82609 0.93930 950 HAG Array 20 0.93924 800 Single Package -- 0.93505 FGE-3 FGE-5 121 250 800 800 900 900 NGT Array HAG Array Single Package NGT Array 50 20 50 0.93470 0.93516 0.93318 0.93730 0.93680 0.93930 850 HAG Array 20 0.93763 Table 6.1 Summary Table of FEM Criticality Evaluations 235LJ FEM H12asu Package enrichment Array Size kett + 2cr USL Case Configuration (wt.%) 455.5 Single Package -- 0.93491 FEM-1 0.90 188.9 NGT Array 50 0.71919 0.94140 455.5 HAG Array 20 0.94002 NAC International 6.1-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.2 Package Contents Content cases for the FGE waste are defined in Table 6.2-1 and the FEM waste is defined in Table 6.2-2. A 239Pu FGE limit is determined for each plutonium waste content case listed and a 235 U wt.% FEM limit is analyzed for the FEM-I uranium content case. Manually compacted (i.e., not machine compacted) waste is bound by a 15% volumetric packing fraction for polyethylene. Report WP 08-PT.09 documents physical testing of manually compacted waste and determined a maximum polyethylene packing fraction of 13.36% [6.1]. The utilization of polyethylene as the bounding hydrogenous moderating material is justified by report SAIC-1322-001 [6.2], which concludes that polyethylene is the most reactive moderator that could credibly moderate the transuranic waste in a pure form. Additionally, it is assumed 1% by volume beryllium in the modeled waste matrix bounds the presence of up to 1 wt.% quantities of special reflectors that are randomly dispersed in the payload containers. Special reflectors are identified per report SAIC-1322-001, where Be is determined to be the bounding special reflector material. 6.2.1 FGE Cases

• Table 6.2-3 provides a description of each FGE content case. The FGE-1 and FGE-2 cases are general payloads applicable to manually compacted TRU waste material where the fissile nuclides (239Pu or FGEs of other fissile nuclides) are in any form or distribution. Depending on the content case, these wastes may be with or without 240Pu and must contain less than or equal to 1 vol.% of special reflectors that are not chemically or mechanically bound to the fissile material.

The FGE-3 case allows for manually compacted TRU waste with an increase in special reflector materials (i.e. greater than 1 vol.%) that may be distributed throughout the moderator (i.e. mixed with fissile material) and the reflector region (i.e. surrounding the fissile matrix). The FGE-5 case allows for machine compacted waste (i.e. greater than 15 vol.% polyethylene). This content type is represented in the criticality models by replacing all water with polyethylene. Special reflectors are not to exceed 1 vol.% for FGE 5. 6.2.2 FEM Cases Table 6.2-4 describes the FEM content case. The low-enriched uranium (LEU) contents are restricted to a maximum enrichment of 0.90-wt.% 235 U FEM. In addition, there are no particle size restrictions, special reflectors are limited to :Sl vol.%, and waste shall be manually

• compacted (i.e. not machine compacted) .

NAC International 6.2-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.2 Fissile Gram Equivalent Waste Content Cases Fissile Gram Fissile Gram Waste Contents Equivalent Equivalent Cases g239 pu Limits Manually compacted with ::;;1 % by weight Be FGE-1 340 Manually compacted .:: 5 g24opu FGE-2a 350 with ::;;1 % by weight Be o:: 15 g240 Pu FGE-2b 375 with minimum g240 Pu credit .:: 25 g240 Pu FGE-2c 395 Manually compacted with >1 % by weight Be FGE-3 121 Machine compacted with ::;;1 % by weight Be FGE-5 250 Table 6.2 Fissile Equivalent Mass Waste Content Cases Fissile 235 UWeight Contents Equivalent Percent Mass Cases Limits Manually compacted waste without a Manually compacted O.9Owt.%, particle size limit that is primarily with ::,1% Be, 15% unlimited uranium (in terms of the heavy metal polyethylene FEM-1 debris size, component) with waste matrix moderator, by U :s; 2500 lb distributed to not exceed enrichment volume (1134 kg) limit NAC International 6.2-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.2 Fissile Gram Equivalent Waste Content Case Description Fissile Content Special Method of Moderator Reflector Material Code (g240Pu)<JJ Reflector Compacting vol.% vol.% CH 2 - 15% CH2 - 15% Water: Water: FGE-1 239Pu Be :5 1 vol.% Manual NCT-1% <1> NCT-0% <1> HAC- 84% HAC- 84% Be-1% Be-1% CH 2 -15% CH2 - 15% 239Pu + Water: Water: FGE-2 a, b, c 24opu Be :5 1 vol.% Manual NCT-1%<1> NCT-0%<1> (5, 15, 25 g) HAC- 84% HAC- 84% Be-1% Be-1% CH 2 - 15% FGE-3 239Pu Be> 1 vol.% Manual Water<2> - 84% Be-100% Be-1% 239Pu CH2 - 99% FGE-5 Be :5 1 vol.% Machine CH2 - 100% Be-1%

• Notes:

1. 1 vol.% is equivalent to 6372g of water, which is the water limit of the CCV inner cavity for NCT. See Section 6.3.4.1.1.

2. NCT and HAC array studies have identical moderator configurations because 6372g water not reached in NCT analyses due to the much lower 239Pu mass limit for FGE-3. See Section 6.3 .4.1.1.

3. 24 °l>u mass listed is the minimum required quantity for the content case, i.e. FGE-1, 3, and 5 may contain any quantity of 240Pu and FGE-2a, 2b, and 2c must have at least Sg, 15g, or 25g of 240Pu, respectively.

Table 6.2 Fissile Equivalent Mass Waste Content Case Description Special Reflector Content Fissile Method of Moderator Reflector (chemically or Code Material Compacting vol.% vol.% mechanically bound?) CH 2 -15% CH 2 - 15% 235 U 0.90 wt.% Water: Water: Be :5 1 vol.% FEM-1 unlimited Manual NCT-1% <1> NCT-0% <1> (No) debris size HAC- 84% HAC- 84% Be-1% Be-1% Notes:

1. I vol.% is equivalent to 6372g of water, which is the water limit of the CCV inner cavity for NCT. See Section 6.3.4.1.1.

NAC International 6.2-3

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NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.3 General Considerations 6.3.1 Model Configuration The criticality safety model for the package is based on the dimensions provided in the package licensing drawings. Using the drawings, the dimensions as modeled are listed in Table 6.3-2 and Table 6.3-3, with the model shown in Figure 6.3-1. The steel components of the CCV and OP are composed of AS:ME plate and forging components that have tight, standardized tolerances. Per Note 1 of Table Al.I, in Annex A.1 of AS:ME SA-20/SA-20M [6.3], the permissible variation under the specified thickness for ASME plate material is 0.01 inches (0.0254 cm). The1*efore, no tolerances are considered for CCV dimensions. No credit is taken for separate bolt materials. Tue material of the CCV is modeled instead of separate bolts or voids in the bolt interface region. Except for the combined thicknesses of the inner and outer steel plates of the OP, as shown in Table 6.3-1, the remainde1* of the foam and steel that make up the OP is not modeled. For the package array evaluations, 35% of the top, bottom, and side OP foam thicknesses crush) are credited in the model for package array spacing. For the single package evaluation, only one model is analyzed, as the bounding HAC damage is considered for both NCT and HAC. Therefore, only one single package model is analyzed with 20 in. (50.8 cm) close, full-density water reflection on all sides of the package, as shown in Figure 6.3-2. Tue NCT package an-ay is modeled as a 50-package, triangular-pitched aITay with 20 in. (50.8 cm) close, full-density water reflection on all sides. The HAC package aITay is modeled as a 20-package, triangular-pitched array with 20 in. (50.8 cm) close, full-density water reflection on all sides. Tue model of each package in the rurny cases is as shown in Figure 6.3-3 .

• NAC International 6.3-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.3 OP Combined Directional Stainless Steel Thicknesses Table 6.3 Packaging Axial Dimensions

• NAC International 6.3-2

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.3 MCNP6 Model Packaging Geometry

• NAC International 6.3-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.3 Single Package Model Figure 6.3 Baseline Package Array Model NAC International 6.3-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.3.2 Material Properties The packaging material for the MCNP models is SS-304. The fissile contents are Pu-metal and U-metal and are considered to bound other plutonium and uranium compounds, respectively, based on density and absorption. Thus, all Pu and U compounds are acceptable as contents under the FGE and FEM limits, respectively. The moderator and reflector may be a combination oflight water, polyethylene, and Be, dependent on case. The compositions and densities of these materials are summarized in the tables below. No credit is taken for parasitic neutron absorption of the waste materials and other authorized payload components consisting of the canister, dunnage, and any packing materials, except to the extent that the fissile, moderator, and special reflector elements absorb neutrons. Material properties for stainless steel 304 are presented in Table 6.3-4. The S(a,~) thermal scattering cross section for Fe-56 (fe56.22t) is included for criticality calculations with MCNP. Material properties for light water, polyethylene, beryllium, plutonium, and uranium are presented in Table 6.3-5. The appropriate S(a,~) thermal scattering cross section is included for each material (i.e. lwtr.20t, poly.20t, and be.20t) .

• NAC International 6.3-5

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.3 Nuclear Properties of Type 304 Stainless Steel Mass Mass Photon Neutron Element Fraction Isotope Fraction ZA ZA (w~at) (w:Uat) C 6000 0.000400 C c1> 6000 4.0000E-04 Si-28 14028 4.5933E-03 Si 14000 0.005000 Si-29 14029 2.4168E-04 Si-30 14030 1.6499E-04 p 15000 0.000230 P-31 15031 2.3000E-04 S-32 16032 1.4207E-04 S-33 16033 1.1568E-06 s 16000 0.000150 S-34 16034 6.7534E-06 S-36 16036 1.6825E-08 Elemental Cr-50 24050 7.9300E-03 Composition Cr-52 24052 1.5903E-01 Cr 24000 0.190000 Cr-53 24053 1.8380E-02 Cr-54 24054 4.6614E-03 Mn 25000 0.010000 Mn-55 25055 1.0000E-02 Fe-54 26054 3.9617E-02 Fe-56 26056 6.4490E-01 Fe 26000 0.701730 Fe-57 26057 1.5160E-02 Fe-58 26058 2.0529E-03 Ni-58 28058 6.2158E-02 Ni-60 28060 2.4768E-02 Ni 28000 0.092500 Ni-61 28061 1.0946E-03 Ni-62 28062 3.5472E-03 Ni-64 28064 9.3254E-04 Density 8.00 (g/cm 3 )

References:

[6.5] Elemental Composition and Density: Material 298 - Steel, Stainless 304; Pages 285-286. [6.6] Isotopic Composition ofElements: Table 1. [6.7] Isotopic Masses: Table I, Pages 344-404. Notes: I. The ENDF/B-VII.l library includes neutron cross-section data for elemental carbon only. NAC International 6.3-6

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.3 Nuclear Properties of Materials Elemental Composition Density Material (g/cm 3 ) Isotope Neutron ZA Number of Atoms H-1 1001 2 Light Water 0.9982 0-16 (1) 8016 1 C (2> 6000 1 Polyethylene 0.93 H-1 1001 2 Beryllium Be 4009 1 1.848 Plutonium Pu-239 / Pu-240 94239 I 94240 1 19.84 (3) Uranium U-235 / U-238 92235 / 92238 1 19.05

References:

[6.5] Light Water Elemental Composition and Density: Material 354 - Water, Liquid; Pages 338-339 [6.5] Polyethylene Elemental Composition and Density: Material 248 - Polyethylene; Pages 239-240 [6.5] Beryllium Elemental Composition and Density: Material 24 -Beryllium; Pages 37-38 [6.5] Plutonium Density: Materials 238-244 - Misc. Plutonium Materials; Pages 230-237 [6.8] Uranium Density: ID 92000, Table M8.2.2, Page M8.2.70 Notes:

1. 0-17 has such a low abundance that it is not included. The ENDF/B-VIl. l library does not include data for 0-18.

2. The ENDF/B-VII.l library includes data for elemental carbon only.

3. Density is constant for plutonium Materials 238-244 .

• NAC International 6.3-7

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.3.3 Computer Codes and Cross-Section Libraries 6.3.3.1 MCNP6 The criticality safety analysis presented in this chapter was analyzed with MCNP6 [6.9] using the continuous-energy neutron data libraries from ENDF/B-VII.l and the ENDF/B-VII.0 thermal S(a,~) cross-sections [6.4]. These cross-section libraries are the most up-to-date cross-section libraries distributed with the MCNP6. l code. In addition, the isotopes from these libraries that are applicable to this analysis have been validated per Section 6.8. MCNP is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. For this criticality analysis, MCNP is used to evaluate neutron multiplication for low-enriched uranium and plutonium cases. To determine source convergence, the "Shannon entropy convergence" and the "w tests for normality" blocks in each output are examined. In general, the Shannon entropy should be converged, at least the minimum number of required cycles have been discarded, and most cases should be normal at 95% confidence for k(col), k(abs), and k(trk), with minimal cases showing normality at 99% confidence. For some cases, additional confidence in calculated results is gained through a closer inspection of the output to examine source data and the behavior of the keff result through the active portion of the run. Additionally, the results of all cases must be reasonable and fall in line with the developed trend based on other cases. 6.3.4 Demonstration of Maximum Reactivity The criticality safety analysis varies the mass of fissile material to determine the maximum quantity for content cases while demonstrating compliance with 10 CFR 71.55 and 10 CFR 71.59. All content limits are evaluated to ensure subcriticality ofkeff+ 2cr below the respective upper subcritical limit (USL). The package model credits 35% of the OP top, bottom, and side foam thicknesses for spacing for both NCT and HAC. A bounding outer OP steel plate thickness is modeled based on the combined thickness of the inner and outer OP shells. See Section 6.3 .1 for the full discussion of the MCNP model geometry. The single package model consists of a single package in isolation, with at least 20 in. (50.8 cm) of close, full water reflection on all sides. The NCT package array evaluation models a 50-package, triangular-pitched array stacked two packages high and with 20 in. (50.8 cm) of close, full water reflection at the array boundary. The HAC package array evaluation models a 20-package, triangular-pitched array stacked two packages high and with 20 in. (50.8 cm) of close, full water reflection at the array boundary. NAC International 6.3-8

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Base assessments are evaluated for each content case to establish a base model, and include the following studies:

• Positioning of the fissile material within the CCV
• HAC flooding in the foam region of the OP and interspersed between packages A 239Pu mass limit is established for each allowable FGE case and a 235 U enrichment limit is analyzed for the FEM case. The total 239Pu mass equates the fissile material content of a drum based on an FGE. The quantities of all fissile isotopes other than 239Pu present in the waste matrix may be converted to an FGE using the conversion factors based on the critical limits established by ANSI/ANS 8.1, 8.12, and 8.15 methods [6.10] [6.11] [6.12]. In this criticality safety analysis, the bounding mass limits are determined in the HAC package array analysis and are then applied to the single package and NCT package array evaluations.

For sensitivity studies, a statistically significant increase in keff is defined as a greater than 2cr increase in keff based on the cr of the initial case compared to the new keffvalue. In other words, to be classified as a statistically significant increase, the following must be true:

• 6.3.4.1 keff2 ~ keffi + 2a1 Fissile Gram Equivalent (FGE) Mass Limit Method For the FGE single package and package array evaluations, up to three studies are performed.

These studies are listed in the order they are examined. 6.3.4.1.1 Mass Determination - Base Study The first study is referred to as the baseline study. This study models a homogeneous sphere of the fissile and moderating material, with the remainder of the CCV cavity filled with the reflector material. The OP region and interspersed region are initially modeled as void. The H/239Pu of the sphere is varied by adjusting the size of the sphere while holding the 239Pu mass constant. This is repeated for five different 23 9Pu mass levels to determine the maximum 239Pu mass with keff + 2cr below the USL. Single Package and HAC Package Array For the single package and HAC package array FGE evaluations, the fissile volume is modeled as an optimally moderated sphere of a 239Pu-moderator mixture. The volume fractions of the components in the moderator are set based on the proportions defined in Table 6.2-3, with no limit on the quantity of water in the moderator. The size of the sphere is determined by the NAC International 6.3-9

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A H/2 39Pu number density ratio. This parameter is varied while holding the 239Pu mass constant to determine the optimally moderated configuration. NCT Package Array To be rated as compliant per the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant report, DOE/WIPP 02-3122 [6.13], TRU waste contents are allowed a maximum of 1% by volume of free-standing liquid. Thus, this requirement is imposed on the package and the NCT package array evaluation models up to a maximum quantity of 6372g of water (1 vol.% of the CCV inner cavity), as water in-leakage is not considered for NCT per 10 CFR 71.59(a)(l). Additionally, this water is modeled only in the fissile sphere to maximize reactivity. This criterion is credited to limit the water in the Package for NCT to obtain a larger fissile mass limit by crediting the liquid volume restriction of the package on the NCT configuration. To bound any drum size that can fit the CCV, the entire volume of the CCV cavity is used to determine the water mass limit and not a specific drum size (e.g. 110-gallon drum). For FGE-1, 2a, 2b, and 2c to evaluate the NCT water moderation limit, the NCT package array baseline study is done piecewise. The first portion of the baseline study case is identical to the content modeling of the single package and HAC package array. The fissile sphere increases in size with the volume fractions of the components in the moderator fixed, based on the proportions defined in Table 6.2-3, until the 6372g water limit is reached. Upon reaching this limit, the second portion of the baseline study case continues increasing the sphere size while modeling the water at a constant mass of 6372g. For this portion, the fissile sphere consists of the plutonium, 6372g of water, 15 vol.% polyethylene, and 1 vol.% Be. For FGE-3, the 6372g water limit is never reached in the NCT package array evaluation because FGE-3 has a comparatively low 239 Pu limit and the peak in H/239Pu is attained well before 6372g of water is modeled. For FGE-5, the moderator and reflector both contain no water, only polyethylene and beryllium, so the NCT water limit does not apply. 6.3.4.1.2 Fissile Sphere Position Study The fissile sphere position study models the fissile sphere in different positions inside the CCV. These additional positions are analyzed to determine the sensitivity of the system to shifting the fissile sphere around the CCV cavity. For the single package evaluations, four positions were examined: (1) the fissile sphere in the top comer of the CCV, (2) the fissile sphere in the bottom comer of the CCV, (3) the fissile sphere centered in the CCV, and (4) the fissile sphere in the top center of the CCV, as shown in Figure 6.3-4. For the package array evaluations, five positions were examined: (1) fissile spheres of top and bottom packages in the comers as close together as possible, (2) fissile spheres in the opposite corners of position 1, (3) fissile spheres fully centered in the CCV, (4) fissile spheres centered NAC International 6.3-10

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A radially but pushed together axially, and (5) fissile spheres of the top and bottom packages both in the top corner of the CCV cavity, as shown in Figure 6.3-5. For the positions where the fissile spheres are in corners, the fissile spheres are placed radially so as to be as close as possible to the neighboring packages in the array, as shown in Figure 6.3-6 for the NCT package array and in Figure 6.3-7 for the HAC package array. 6.3.4.1.3 Flooding Configuration The flooding configuration study is performed for all single package and HAC package array evaluations. For the single package evaluation, flooding in the OP region (Region 1 in Figure 6.3-8) is examined. In this study, the VF of the water in the OP region is varied from 0.0 to 1.0, while the VF of the water outside of the package (Region 2 in Figure 6.3-8) is constant at 1.0. For the HAC package array, the VFs of the water in the OP region (Region 1 in Figure 6.3-8) and the interspersed region (Region 2 in Figure 6.3-8) are varied simultaneously from 0.0 to 1.0. For each content case, the bounding flooding configuration from this study is applied to the remainder of the studies. 6.3.4.2 Fissile Equivalent Mass {FEM)- Enrichment Limit Method The FEM single package, NCT package array, and HAC package array arrangements are identical to the FGE arrangements. A uranium mass limit of 2500 lb (1134 kg) applies to all FEM cases. Three content configurations are analyzed for the FEM-1 case: 1) a homogeneous fissile shape, 2) a heterogeneous cylindrical particle lattice, and 3) a heterogeneous spherical particle lattice. For all three configurations, the uranium is held at its set enrichment and mass limits as the size of the fissile shape or particle lattice is varied. For the particle lattice configuration, the particle sizes are varied, as well. The enrichment selected ensures that any debris size is subcritical and below the USL. The spherical or cylindrical particle lattices are arranged in the shape of a cylinder with a height-to-diameter ratio (HID) of approximately 1 (see Figure 6.3-11 ). The cylindrical particle lattice configuration consists of a number of rods that span the length of the entire lattice, with variable radii. The spherical lattice configuration consists of multiple layers of spherical particles with variable radii. The number of cylinders or spheres per row and the pitch between cylindrical or spherical particles is varied while holding the uranium mass at its maximum and the lattice's HID at approximately 1. Using cylinders per row and spheres per row is a proxy for comparing different particle sizes. This naming convention was chosen because the cylindrical particles vary slightly in size to accommodate variations in the pitch of the lattice. Changing the pitch and maintaining an HID of 1 results in the lengthening or shortening cylindrical particles as the size of the lattice changes. If the radius of the cylindrical particles was held constant, the mass of uranium would fluctuate with the cylindrical particle pitch. Thus, to conserve the uranium mass NAC International 6.3-11

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A of the cylindrical particle lattice while varying the pitch, the radii of the cylindrical particles are slightly varied. See Section 6.3.4.2.2 for more information. 6.3.4.2.1 Homogeneous Fissile Volume Case Study Single Package and HAC Package Array The homogeneous fissile volume study determines the optimal H/235 U and verifies that the maximum enrichment results in keff+ 2cr less than the USL. A homogeneous sphere of uranium metal and moderating material is modeled in the CCV cavity, with the remainder of the CCV cavity filled with the reflector material, as listed in Table 6.2-4. The sphere radius is increased until it equals the inner radius of the CCV cavity. Upon reaching this maximum radius, a cylindrical section is introduced between the upper and lower hemispheres of the fissile sphere, which allows the H/2 35U to increase further and encompass the optimal moderation point (see Figure 6.3-9). The OP region and interspersed region of the HAC array are modeled as void. NCT Package Array The NCT package array homogeneous fissile volume case study is like the single package and HAC package array case study except for limiting the water in the fissile shape to the water mass equivalent of 1% of the CCV inner cavity's volume, 6372g (see Section 6.3.4.1.1). This limitation on the amount of water modeled affects how H/235U is varied. Like with the FGE NCT package array analysis, the fissile shape starts in the positions shown in Figure 6.3-6. The first stage of increasing the size of the fissile shape, thereby increasing H/235 U, starts with 2500 lb (1134 kg) of uranium, 0g of water, 15 vol.% polyethylene and 1 vol.% Be in the fissile sphere. Water is added until the 6372g water limit is reached. In this first stage of expansion, the fissile shape is at full density, i.e. no void. Upon reaching the water limit, the fissile shape continues to expand in size in the second stage, as the moderator is held at 15 vol.% polyethylene, 1 vol.% Be, and 6372g of water. The remaining space in the shape is void. When the fissile sphere's radius becomes equivalent to that of the CCV inner cavity, a solid cylinder is added between the upper and lower hemispheres of the fissile sphere. At this point (stage 3), H/235 U is increased by increasing the cylinder's height. When this shape's height is equivalent to that of the CCV inner cavity, one final stage is analyzed where the entirety of the CCV inner cavity is filled with the 2500 lb (1134 kg) of uranium with 15 vol.% polyethylene, 1 vol.% Be, and 6372g of water. For the NCT package array, the CCV cavity reflector always consists of 15 vol.% polyethylene and 1 vol.% Be with the remainder void. The 1 vol.% water limit (6372 g) is always modeled in the fissile sphere. The NCT homogeneous fissile volume case study is summarized in Table 6.3-6 and shown in Figure 6.3-10. NAC International 6.3-12

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Difference Between FGE and FEM Homogeneous Moderator Modeling In this criticality safety analysis, the polyethylene, water, and Be in the moderator of the fissile spheres are modeled at 15 vol.%, 84 vol.%, and 1 vol.%, respectively. Given that these values sum to 100%, these figures do not consider the volume of plutonium/uranium modeled. Thus, the overall VFs of the moderating components of the fissile region are slightly less than stated because the fissile component (plutonium/uranium) takes up some volume in the overall fissile sphere. However, as the volume of plutonium is miniscule in the FGE evaluations, this simplification in modeling the moderator is acceptable considering that (1) the reductions in the overall moderator volume fractions are very slight and (2) optimal moderation is achieved in the analyses. Due to the low enrichment limit and large uranium mass limit, the FEM evaluations model a significantly larger volume of uranium metal. For FEM, the FGE fissile sphere simplification is not acceptable, as it results in too large of reductions in the moderator material VFs when considering the volume of uranium metal. Therefore, for the FEM evaluation, the fissile sphere modeling is different. For the FEM evaluation, the polyethylene and beryllium are always held at 15 vol.% and 1 vol.% of the overall fissile sphere volume, as opposed to the moderator volume in the FGE cases, and the mass of uranium is fixed. Therefore, the water is then modeled as the remainder of the volume in the HAC package array and single package evaluations. The same is true for NCT package arrays except that the water is limited to 1 vol.% equivalent of the CCV cavity volume, with any remaining volume modeled as void. 6.3.4.2.2 Heterogeneous Cylindrical Particle Fissile Volume Case Study For heterogeneous cases, there are two configurations: (1) a cylindrical particle lattice and (2) a spherical particle lattice. In the cylindrical particle lattice case study, the uranium mass is held constant at 2500 lb (1134 kg) and the enrichment is 0.90-wt.% 235 U. Each cylindrical particle's length is equal to the full length of the lattice. The moderator and reflector are identical, as listed in Table 6.2-4, and the lattice is modeled as a triangular-pitched array. To determine the optimally moderated configuration, cylindrical particle radii from 0.33189 cm to 0.80041 cm are examined. The pitch of the lattice is the main variable of interest, which is varied to alter the Hl235 U of the system. Because varying the lattice pitch while holding HID = 1 changes the length of the rods, the particle radius must change slightly to conserve the mass of uranium with HID = 1. The range of pitches evaluated for each lattice particle quantity are then compared to determine which has the bounding case for the cylindrical particle configuration. Figure 6.3-11 shows the typical range of pitches analyzed for the cylindrical particle evaluation. For the NCT package array, the moderator is held to the 1 vol.% water limit and the reflector

• contains no water. Otherwise, the method of examination is identical to the single package and NAC International 6.3-13

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A HAC package array evaluations. The cylindrical particle size is varied from 0.76038 cm to 2.5797 cm. 6.3.4.2.3 Heterogenous Spherical Particle Fissile Volume Case Study The spherical particle lattice configuration is similar to the cylindrical particle lattice configuration. The lattice is triangular-pitched in the x-y plane and square-pitched in the z plane, i.e., each lattice cell is a hexagonal prism parallel to the z-axis. The spherical particle radius is constant in this configuration for a given lattice size because the lattice consists of discrete rows of spherical particles and not cylinders, so the particle size does not change with the size of the lattice. As previously stated, the lattice HID is held at approximately 1. Spherical particle radii from 0.44825 cm to 1.07624 cm are examined. The pitch of the lattice is the main variable of interest, which is varied to find the optimal moderation for that lattice size. All lattice sizes are then compared to determine which has the bounding case for the spherical particle configuration. Figure 6.3-12 shows the typical range of pitches evaluated for the spherical particle evaluation. 6.3.4.2.4 Sensitivity Studies Fissile Shape Position The positions analyzed for the FEM cases are the same as for the FGE cases. See Section 6.3.4.1.2 for a description of the positions analyzed. Flooding Configuration The flooding configurations analyzed for the FEM cases are the same as for the FGE cases. See Section 6.3.4.1.3 for a description of the flooding configurations analyzed. NAC International 6.3-14

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.3 NCT Package Array Homogeneous Fissile Volume Study Configurations Uranium Water Stage Shape Void Radius Height Mass Mass 2500Ib 1 Sphere (1134 kg) 0-6372 g No < 41.275 cm -- 2500Ib 2 Sphere (1134 kq) 6372 g Yes s 41.275 cm -- Hemispherical caps 2500Ib 3 6372 g Yes 41 .275 cm s 119.38 cm with cylindrical center (1134 kq) 2500Ib 4 Cylinder 6372 g Yes 41.275 cm 119.38 cm (1134 kg)

• NAC International 6.3-15

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A [ ] Fissile Sphere COi Cavity Reflector

                                        ,.J Stainless Steel 1                  2       3              4 Figure 6.3 Single Package Fissile Shape Positions
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                                ,J Stainless Steel 1                  2                   3           4          5 Figure 6.3 Package Array Fissile Shape Positions NAC International                              6.3-16

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

                                                                       ~ Fissile Sphere CCV Cavity Reflector Stainless Steel Full-Density H20

• Figure 6.3 Fissile Sphere Positioning for NCT Package Arrays j'.r:;:j Fissile Sphere CCV Cavity Reflector Stainless Steel Full-Density H20 Figure 6.3 Fissile Sphere Positioning for HAC Package Arrays
• NAC International 6.3-17

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 2 Inner cavity Reflector 304 Stainless Steel Figure 6.3 Floodable Regions: (1) OP Region (2) Interspersed Region

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Fissile Sphere CCV cavity Reflector Stainless Steel Figure 6.3 FEM Homogeneous Volume Cases - Single Package and HAC Package Array

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                                                           ~     ~                                CCV cavity Reflector Stainless Steel 1                          2                          3                   4 Figure 6.3 FEM Homogeneous Volume Cases-NCT Package Array NAC International                                            6.3-18

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A I I I I E2} Fissile CO/ cavity Reflector Stainless Steel Figure 6.3 FEM Fissile Heterogeneous Cylindrical Particle Cases

• NAC International 6.3-19

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Fissile COJ Cavity Reflector Stainless Steel Figure 6.3 FEM Fissile Heterogeneous Spherical Particle Cases NAC International 6.3-20

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.4 Single Package Evaluation 6.4.1 FGE Single Package Configuration The FGE single package MCNP model consists of one package in isolation surrounded with at least 20 in. (50.8 cm) of water to provide close reflection in every direction. For the initial single package evaluation, the floodable space in the OP is modeled as void. Once the most reactive moderator/reflector combination is determined for an FGE case, a study is done to determine the bounding flooding. 6.4.2 FGE Single Package Summary Results See Table 6.4-1 for the summary of the most reactive cases for each FGE content case. 6.4.2.1 FGE-1 Single Package Baseline FGE-1 simulates non-machine compacted waste that contains less than or equal to 1% Be special reflector. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.4-2 and Figure 6.4-1, a mass of 340g 239Pu, determined in the HAC package array evaluation, at H/2 39Pu of 900 is below the USL of 0.93930, with a keff + 2cr of 0.93069 . 6.4.2.2 FGE-2a Single Package Baseline FGE-2a credits 5g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.4-3 and Figure 6.4-2, a mass of 350g of 239Pu, determined with the HAC package array evaluation, at H/239Pu of 950 is below the USL of 0.93930, with a keff + 2cr of 0.92904. 6.4.2.3 FGE-2b Single Package Baseline FGE-2b credits 15g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.4-4 and Figure 6.4-3, a mass of 375g 239Pu, as determined in the HAC package array evaluation, at H/239Pu of 900 is below the USL of 0.93930, with a keff + 2cr of 0.93162. 6.4.2.4 FGE-2c Single Package Baseline FGE-2c credits 25g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.4-5 and Figure 6.4-4, a mass of 395g 239Pu, determined in the HAC package array evaluation, at H/2 39Pu of 900 results in the bounding configuration under the USL of 0.93930, with a keff + 2cr of 0.93164 . NAC International 6.4-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.4.2.5 FGE-3 Single Package Baseline FGE-3 simulates non-machine compacted waste with no limit on special reflector material. The moderator consists of a l 5%-to-84% ratio of light water to polyethylene, and 1% Be by volume. The CCV cavity reflector consists of 100% Be. As shown in Table 6.4-6 and Figure 6.4-5, a Be VF of 0.01, a mass of 121g 239Pu, determined with the HAC package array evaluation, and H/239Pu of 800 is under the USL of 0.93680, with a keff + 2cr of 0.93505. 6.4.2.6 FGE-5 Single Package Baseline FGE-5 simulates machine compacted waste. The moderator consists of 100% polyethylene and the reflector consists of 99% polyethylene and 1% Be. As shown in Table 6.4-7 and Figure 6.4-6, a mass of250g 239Pu, determined in the HAC package array evaluation, and H/239Pu of 900 is under the USL of 0.93930, with a keff + 2cr of 0.93159. 6.4.2.6.1 FGE Single Package Fissile Sphere Position Study In the baseline study for each case, the fissile sphere is modeled in the top comer. The only exception to this is FGE-3, where the initial position of the fissile sphere in the baseline study is centered in the CCV, as beryllium is a stronger reflector than the materials of construction of the packaging. Multiple positions were analyzed for each case to determine the sensitivity of keff to the sphere position and verify that the worst-case position is determined. The results of this study are provided in Table 6.4-8. This study verified that the position of the fissile sphere resulting in the highest value ofkeff is the top center for all cases but FGE-3. The highest value ofkefffor FGE-3 resulted from the centered sphere position. 6.4.2.6.2 FGE Single Package Flooding Configuration Study This study examines the sensitivity of the single package case to flooding in the OP region. As shown in Table 6.4-9, only FGE-1 and FGE-2b shows a statistically significant increase, as defined in Section 6.3.4, in kefffrom the flooding study. This increase is likely only due to the statistical nature of the MCNP code, and not a physical effect from partially flooding the OP region. However, the increased value ofkeffis selected for each case to be bounding. NAC International 6.4-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• NAC International 6.4-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.4 FGE-2c Baseline Configuration - Single Package Table 6.4 FGE-3 Baseline Configuration - Single Package NAC International 6.4-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.4 FGE-5 Baseline Configuration - Single Package

• NAC International 6.4-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.4 FGE-1 Single Package Baseline Study Figure 6.4 FGE-2a Single Package Baseline Study NAC International 6.4-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.4 FGE-2b Single Package Baseline Study Figure 6.4 FGE-2c Single Package Baseline Study NAC International 6.4-7

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.4 FGE-3 Single Package Baseline Study Figure 6.4 FGE-5 Single Package Baseline Study NAC International 6.4-8

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.4.3 FEM Single Package Configuration The FEM single package MCNP model consists of one Package in insolation surrounded with at least 20 in. (50.8 cm) of water to provide close reflection in every direction. For the initial single package evaluation, the floodable space in the OP is modeled as void. Once the bounding pitch and particle size combination, or optimal H/2 35 U, is determined for the FEM case, a study is done to determine the sensitivity to flooding. 6.4.4 FEM-1 Single Package Summary Results Table 6.4-10 shows a summary of the bounding FEM-I cases crediting a 15% polyethylene VF. The cases represent the limiting particle size for the particle configuration studies (i.e. spherical or cylindrical). All three cases model an enrichment of 0.90-wt. % 235 U and uranium mass of 2500 lb (1134 kg). The FEM-I spherical particle case results in the bounding system that is still acceptable per the USL. Thus, the FEM- I spherical particle case is the bounding case for the single package FEM-I analysis. 6.4.4.1 FEM-1 Homogeneous Fissile Shape Single Package Baseline The homogeneous volume configuration, as described in Section 6.3.4.2.1, varies H/2350 via the

• size of the fissile shape, with an enrichment of 0.90-wt.% 235U and uranium mass of2500 lb (1134 kg). As shown in Table 6.4-11 and Figure 6.4-7, a fissile radius of 40.8 cm and keff+ 2a of 0.86191, is the bounding homogeneous configuration. Its reactivity is significantly lower than the keff of the spherical particle configurations, so no further studies are analyzed.

6.4.4.2 FEM-1 Cylindrical Particle Single Package Baseline Table 6.4-13 shows the variation of half-pitch, thus moderator-to-uranium (MU) ratio and H/235 U, for the bounding set of cylindrical particles. Figure 6.4-8 shows the MU curves for each cylindrical particle set analyzed. For clarity, Table 6.4-13 shows only the bounding cylindrical particle set analyzed. Table 6.4-12 shows the maximum case from each set of cylindrical particles analyzed to show the peak in reactivity has been attained. The FEM-I, single package, cylindrical particle results show that unlimited cylindrical particle sizes at 0.90-wt. % 235U are subcritical below the USL of 0.94140 and are bounded by the HAC package array. The most reactive FEM-I, single package, cylindrical particle baseline case is results in keff+ 2a of 0.93088 (highlighted grey in Table 6.4-12 and Table 6.4-13). However, the FEM-I, single package, spherical particle analysis produces the bounding HAC package array configuration for FEM-I. Therefore, further studies are not analyzed for the cylindrical particle configuration .

• NAC International 6.4-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.4.4.3 FEM-1 Spherical Particle Single Package Baseline Table 6.4-15 shows the variation of half-pitch, thus MU ratio and H/235 U, for the bounding set of spherical particles. Figure 6.4-9 shows the MU curves for each spherical particle set analyzed. For clarity, Table 6.4-15 shows only the bounding spherical particle set analyzed. Table 6.4-14 shows the maximum case from each set of spherical particles analyzed to show the peak in reactivity has been attained. The FEM-1, single package, spherical particle results show that all particle sizes at 0.90-wt.% 235 U are subcritical below the USL of 0.94140 and are bounded by the HAC package array. The bounding FEM-1, single package, spherical particle baseline case results in keff + 2cr of 0.93341 (highlighted grey in Table 6.4-14 and Table 6.4-15). This case is the overall bounding FEM-1, single package case. 6.4.4.4 FEM-1 Fissile Shape Position Sensitivity In the baseline study, the fissile shape is modeled in the top comer of the CCV cavity. Multiple positions were analyzed in this study to determine the sensitivity of keff to the fissile position and verify that the worst-case position is determined. The number of spherical particles per row, MU, and spherical particle radius are held constant at the baseline values: 1027 spheres/row, MU of2.94, and spherical particle radius of 0.74107 cm. As shown in Table 6.4-16, modeling the fissile shape in the top center of the CCV cavity is the bounding position for the FEM-1 single package configuration, with keff+ 2cr of 0.93411. 6.4.4.5 FEM-1 Flooding Configuration Sensitivity This study examines the sensitivity of the FEM-1 case to flooding in the OP region. As shown in Table 6.4-17, a flooding VF of 0.01 results in a statistically significant increase in reactivity. Note that no strong trend exists for this study, verifying that any added reflection from flooding does not increase keff. However, as the 0.01 VF flooded case results in a statistically significant increase in keffper Section 6.3.4, this case is used the bounding case for the FEM-1 single package evaluation, with keff+ 2cr of 0.93491. NAC International 6.4-10

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.4 FEM-1 Summary- Single Package

• NAC International 6.4-11

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.4 FEM-1 Bounding Case for Each Cylindrical Particle Size-Single Packa e NAC International 6.4-12

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A herical Particle Size - Single Packa e

• NAC International 6.4-13

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.4 FEM-1 Single Package Homogeneous Mass Study Figure 6.4 FEM-1 Single Package Heterogeneous Cylindrical Particle Study NAC International 6.4-14

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.4 FEM-1 Single Package Heterogeneous Spherical Particle Study

• NAC International 6.4-15

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.5 Evaluation of Package Arrays Under Normal Conditions of Transport 6.5.1 FGE NCT Package Array Configuration The FGE, NCT package array MCNP6 model consists of a 5N hexagonally pitched array of packages, with no flooding in the packages, and at least 20 in. (50.8 cm) of water modeled around the array as close reflection. The NCT package array evaluation shows that the fissile mass limits, as determined in the HAC package array evaluation, produce acceptable results below the USL when applied to the NCT package array conditions. For the NCT package array, no more than 6372g of water (equivalent to 1% of the CCV volume) is allowed. For conservatism, this water is all modeled in the homogeneous fissile solution. 6.5.2 FGE NCT Package Array Results See Table 6.5-1 for the summary of the most reactive cases for each FGE content case. 6.5.2.1 FGE-1 NCT Package Array Baseline FGE-1 simulates non-machine compacted waste that contains special reflectors less than or equal to 1 vol.% Be. The moderator consists of 15% polyethylene, 84% light water, and 1% Be by

• volume. The reflector consists of 15% polyethylene, 1% Be, and 84% void, by volume. As shown in Table 6.5-2 and Figure 6.5-1, a mass of 340g 239Pu, determined in the FGE-1 HAC package array study, with H/239Pu of 604 is sufficiently under the USL of 0.93930, with a kerr+2cr of0.84346.

6.5.2.2 FGE-2a NCT Package Array Baseline FGE-2a credits 5g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator consists of 15% polyethylene, 84% light water, and 1% Be by volume. The reflector consists of 15% polyethylene, 1% Be, and 84% void, by volume. As shown in Table 6.5-2 and Figure 6.5-2, a mass of 350g of 239Pu at H/2 39Pu of 587 results in the bounding configuration under the USL of 0.93930, with a kerr+-2cr of 0.83837. As shown, the water limit of 6372g in a full-density fissile sphere is the bounding configuration. 6.5.2.3 FGE-2b NCT Package Array Baseline FGE-2b credits 15g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator consists of 15% polyethylene, 84% light water, and 1% Be by volume. The reflector consists of 15% polyethylene, 1% Be, and 84% void, by volume. As shown in Table 6.5-2 and Figure 6.5-3, a mass of 375g 239Pu, as determined in the HAC package array, at H/2 39Pu of 547 results in the bounding configuration under the USL of 0.93930, with a kerr+-2cr of 0.83200 . NAC International 6.5-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.5.2.4 FGE-2c NCT Package Array Baseline FGE-2c credits 25 g of 24°I>u in its analysis but is otherwise identical to FGE-1. The moderator consists of 15% polyethylene, 84% light water, and 1% Be by volume. The reflector consists of 15% polyethylene, 1% Be, and 84% void, by volume. As shown in Table 6.5-2 and Figure 6.5-4, a mass of 395g 239Pu, as determined in the HAC package array evaluation, at H/2 39Pu of 520 results in the bounding configuration under the USL of 0.93930, with a ketr+-2cr of 0.82609. 6.5.2.5 FGE-3 NCT Package Array Baseline FGE-3 simulates non-machine compacted waste that is not chemically or mechanically bound to the special reflector material. The moderator consists of a 15%-to-84% ratio of light water to polyethylene, and a minimum of I% Be by volume. Because the mass limit of 239Pu is comparatively quite low for FGE-3, the 1% water limit is not reached before the fissile sphere reaches optimum moderation. Therefore, the same contents model used in the HAC package array is used in the NCT package array. The CCV cavity reflector consists of 100% Be, by volume. As shown in Table 6.5-3 and Figure 6.5-5, a Be VF of 0.01, a mass of 121g 239Pu, determined in the HAC package array evaluation, and Hl239Pu of 800 results in the bounding configuration under the USL of 0.93680, with a ketr+-2cr of 0.934 70. 6.5.2.6 FGE-5 NCT Package Array Baseline FGE-5 simulates machine compacted waste. The moderator consists of 100% polyethylene and the reflector consists of 99% polyethylene and 1% Be. As no water is modeled in the fissile sphere or CCV cavity reflector for FGE-5, the same contents model in the HAC package array evaluation is used in the NCT package array evaluation. As shown in Table 6.5-4 and Figure 6.5-6, a mass of250g 23 9Pu and H/239Pu of 900 results in the original bounding configuration under the USL of 0.93930, with a ketr+-2cr of 0.93730. 6.5.2.6.1 FGE NCT Array Fissile Sphere Position Sensitivity In the baseline study for each case, the fissile sphere is modeled in the top corner. The only exception to this is FGE-3, where the initial position of the fissile sphere in the baseline study is centered in the CCV, as beryllium is a stronger reflector than the materials of construction of the packaging. Multiple positions were analyzed for each case to determine the sensitivity ofketrto the sphere position and verify that the worst-case position is determined. Note that for this study, the results for the FGE-1 case are considered to be representative of the FGE-2a, 2b, and 2c cases as well, due to the similarities of the systems. The results of this study are provided in Table 6.5-5. The results show that the position of the fissile spheres in the baseline cases are bounding in every case. NAC International 6.5-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.5 FGE Result Summary- NCT Package Array Table 6.5 FGE-3 Baseline Configuration - NCT Package Array

• NAC International 6.5-3

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.5 FGE-5 Baseline Configuration - NCT Package Array NAC International 6.5-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.5 FGE-1 NCT Package Array Baseline Study Figure 6.5 FGE-2a NCT Package Array Baseline Study NAC International 6.5-5

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.5 FGE-2b NCT Package Array Baseline Study Figure 6.5 FGE-2c NCT Package Array Baseline Study NAC International 6.5-6

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.5 FGE-3 NCT Package Array Baseline Study Figure 6.5 FGE-5 NCT Package Array Baseline Study NAC International 6.5-7

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.5.3 FEM NCT Package Array Configuration The FEM, NCT package array, MCNP6 model consists of a 5N hexagonally pitched array of packages, with no flooding in the packages, and at least 20 in. (50.8 cm) of water modeled around the array as close reflection. The NCT package array analysis evaluation shows that the fissile mass limits of 0.90-wt.% 235 U and 2500 lb (1134 kg) of uranium, produce acceptable results below the USL when applied to the NCT package array conditions. 6.5.4 FEM NCT Package Array Results Table 6.5-6 shows a summary of the bounding FEM-1 case crediting a 15% polyethylene VF; the cases represent the limiting particle size for the particle configuration studies (i.e. spherical or cylindrical). All three cases model an enrichment of 0.90-wt.% 235 U. The FEM-1 spherical particle case results in the bounding system that is still acceptable per the USL. 6.5.4.1 FEM-1 Homogeneous Fissile Shape NCT Package Array Baseline The homogeneous volume configuration, as described in Section 6.3.4.2.1, varies H/2 35 U via the size of the fissile shape at an enrichment of 0.90-wt.% 235 U with uranium mass of 2500 lb (1134 kg). As shown in Table 6.5-7 and Figure 6.5-7, a fissile radius of 41.275 cm and a height of 119.38 cm, is the bounding configuration (highlighted grey) with keff+ 2cr _of 0.68074. This shows that optimal moderation is not achieved with the 1% water limit. This result is bounded by the cylindrical particle and spherical particle configurations, so no further studies are analyzed. 6.5.4.2 FEM-1 Cylindrical Particle NCT Package Array Baseline Table 6.5-9 shows the variation of half-pitch, thus MU ratio and H/2 35U, for the bounding set of cylindrical particles. Figure 6.5-8 shows the MU curves for each cylindrical particle set analyzed. Note that these curves stop abruptly because, at that point, the cylindrical particle lattice has expanded to the CCV boundary and that no further radial expansion is possible. For clarity, Table 6.5-9 shows only the bounding cylindrical particle set analyzed. Table 6.5-8 shows the maximum case from each set of cylindrical particles analyzed to show the peak in reactivity has been attained. The FEM-1, NCT package array, cylindrical particle results show that unlimited cylindrical particle sizes at 0.90-wt.% 235 U, with I% water modeled, are subcritical below the USL of 0.94140. The most reactive FEM-I, cylindrical particle, NCT package array baseline case results in kert+2cr of 0.71326 (highlighted grey in Table 6.5-8 and Table 6.5-9). However, the FEM-1, NCT package array, spherical particle analysis produces the bounding NCT package array configuration for FEM 1. Therefore, further studies are not analyzed for the cylindrical particle configuration. NAC International 6.5-8

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.5.4.3 FEM-1 Spherical Particle NCT Package Array Baseline Table 6.5-11 shows the variation of half-pitch, thus MU ratio and H/235U, for the bounding set of spherical particles. Figure 6.5-9 shows the MU curves for each spherical particle set analyzed. Note that these curves stop abruptly because, at that point, the spherical particle lattice has expanded to the CCV boundary and that no further radial expansion is possible. For clarity, Table 6.5-11 shows only the bounding spherical particle set analyzed. Table 6.5-10 shows the maximum case from each set of spherical particles analyzed to show the peak in reactivity has been attained. The FEM-1, NCT package array, spherical particle results show that all particle sizes at an enrichment of 0.90-wt.% 235 U, and with 1% water, are subcritical below the USL of 0.94140 and are bounded by the HAC package array. The bounding FEM-1, NCT package array, spherical particle baseline case results in keft'r2cr of 0.71919 (highlighted grey in Table 6.5-10 and Table 6.5-11 ). Therefore, unlimited particle size at an enrichment of 0.90-wt. % 235 U is an acceptable content for the package. As the spherical particles result in the bounding configuration for the FEM-1, NCT package array, the bounding spherical particle case is used for the fissile position study.

• 6.5.4.4 FEM-1 NCT Array Fissile Shape Position Sensitivity In the baseline study, the fissile shapes of the top and bottom packages are modeled in the corners of the CCV cavity as close together as possible. Multiple positions were analyzed in this study to determine the sensitivity of ketr to the fissile position and verify that the worst-case position is determined. The number of spherical particles per row, MU, and spherical particle radius are held constant at the baseline values: 151 spherical particles/row, a MU of 6.33, and a spherical particle radius of 1.88730 cm. As shown in Table 6.5-12, modeling the fissile shapes in the close corner is the bounding position for the FEM-1, NCT package array configuration .
• NAC International 6.5-9

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 6.5-10

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Case for Each Cylindrical Particle Size- NCT Package

• Table 6.5 FEM-1 Bounding Case for Each Spherical Particle Size-NCT Package Arra
• NAC International 6.5-11

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A NAC International 6.5-12

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.5 FEM-1 NCT Package Array Homogeneous Mass Study Figure 6.5 FEM-1 NCT Package Array Heterogeneous Cylindrical Particle Study

• NAC International 6.5-13

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Figure 6.5 FEM-1 NCT Package Array Heterogeneous Spherical Particle Study NAC International 6.5-14

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.6 Package Arrays Under Hypothetical Accident Conditions 6.6.1 FGE HAC Package Array Configuration The FGE, HAC package array, MCNP6 model consists of a 2N hexagonally pitched array of packages, with the worst-case flooding in the packages considered, and at least 20 in. (50.8 cm) of water modeled around the array as close reflection. For the initial package array evaluation, all floodable spaces are modeled as void. Once the bounding moderator/reflector combination is determined for an FGE case, a study is done to determine the sensitivity of the system to flooding. 6.6.2 FGE HAC Package Array Results See Table 6.6-1 for the summary of the most reactive cases for each FGE content case. 6.6.2.1 FGE-1 HAC Package Array Baseline FGE-1 simulates non-machine compacted waste that contains less than or equal to 1% Be special reflector. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.6-2 and Figure 6.6-1, a mass of 340g 239Pu at H/ 239Pu of 900

• results in the bounding configuration under the USL of 0.93930, with a kert+2cr of 0.93911.

6.6.2.2 FGE-2a HAC Package Array Baseline FGE-2a credits 5g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.6-3 and Figure 6.6-2, a mass of 350g of 239Pu at H/239 Pu of 900 results in the bounding configuration under the USL of 0.93930, with a kert+2cr of 0.93779. 6.6.2.3 FGE-2b HAC Package Array Baseline FGE-2b credits 15g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.6-4 and Figure 6.6-3, a mass of 375g of 239Pu at H/23 9Pu of 900 results in the bounding configuration under the USL of 0.93930, with a kert+2cr of 0.93921. 6.6.2.4 FGE-2c HAC Package Array Baseline FGE-2c credits 25 g of 240Pu in its analysis but is otherwise identical to FGE-1. The moderator and reflector consist of 15% polyethylene, 84% light water, and 1% Be by volume. As shown in Table 6.6-5 and Figure 6.6-4, a mass of 395g of Z39Pu at H/Z 39Pu of 950 results in the bounding configuration under the USL of 0.93930, with a kert+2cr of 0.93924 . NAC International 6.6-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.6.2.5 FGE-3 HAC Package Array Baseline FGE-3 simulates non-machine compacted waste that is not chemically or mechanically bound to the special reflector material. The moderator consists of a 15%-to-84% ratio of light water to polyethylene, and I% Be by volume. The CCV cavity reflector consists of 100% Be. As shown in Table 6.6-6 and Figure 6.6-5, a Be VF of 0.01, a mass of 121g of2 39Pu, and H/239Pu of 800 results in the bounding configuration under the USL of 0.93680, with a kerrt2cr of 0.93516. 6.6.2.6 FGE-5 HAC Package Array Baseline FGE-5 simulates machine compacted waste. The moderator consists of 100% polyethylene and the CCV cavity reflector consists of 99% polyethylene and 1% Be, by volume. As shown in Table 6.6-7 and Figure 6.6-6, a mass of250g 239 Pu and H/23 9Pu of 850 results in the bounding configuration under the USL of 0.93930, with a ketr+ 2cr of 0.93763. 6.6.2.6.1 FGE HAC Array Fissile Sphere Position Sensitivity In the baseline study of each case except FGE-3, the fissile spheres of the top and bottom packages are modeled in the corners of the CCV cavity as close together as possible. For FGE-3, the initial position of the fissile spheres in the baseline study is centered in the CCV, as beryllium is a stronger reflector than the materials of construction of the packaging. Multiple positions were analyzed for each case to determine the sensitivity ofketrto the sphere position and verify that the worst-case position is determined. Note that for this study, the results for the FGE-1 case are considered to be representative of the FGE-2a, 26, and 2c cases as well, due to the similarities of the systems. The results of this study are provided in Table 6.6-8. The results show that the position of the fissile spheres in the baseline cases are bounding in every case. 6.6.2.6.2 FGE HAC Array Flooding Configuration Sensitivity This study examines the sensitivity of each case to flooding in both the OP region and interspersed region simultaneously. As shown in Table 6.6-9, no flooding configuration results in a more reactive case. Therefore, the unflooded case is the bounding flooding configuration for all FGE HAC package array cases. NAC International 6.6-2

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

                    - Mass Limit Cases for FGE - HAC Packa e Array

• NAC International 6.6-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.6 FGE-2b Baseline Configuration - HAC Package Array NAC International 6.6-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.6 FGE-5 Baseline Configuration - HAC Package Array Table 6.6 FGE Fissile Sphere Position Study Results - HAC Package Array Table 6.6 FGE Flooding Study Results - HAC Package Array

• NAC International 6.6-5

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.6 FGE-1 HAC Package Array Baseline Study Figure 6.6 FGE-2a HAC Package Array Baseline Study NAC International 6.6-6

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.6 FGE-2b HAC Package Array Baseline Study

• Figure 6.6 FGE-2c HAC Package Array Baseline Study NAC International 6.6-7

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.6 FGE-3 HAC Package Array Baseline Study Figure 6.6 FGE-5 HAC Package Array Baseline Study NAC International 6.6-8

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.6.3 FEM HAC Package Array Configuration The FEM, HAC package array, MCNP6 model consists of a 2N hexagonally pitched array of packages, with the worst-case flooding in the packages considered, and at least 20 in. (50.8 cm) of water modeled around the array as close reflection. For the initial package array evaluation, all floodable spaces are modeled as void. Once the bounding pitch and particle size combination, or optimal H/ 235 U, is determined for an FEM case, a study is done to determine the bounding flooding. 6.6.4 FEM-1 HAC Package Array Summary Results Table 6.6-10 shows a summary of the bounding FEM-1 case crediting a 15% polyethylene VF. The cases represent the limiting particle size for the particle configuration studies (i.e. spherical or cylindrical). All three cases model an enrichment of 0.90-wt.% 235 U and uranium mass of 2500 lb (1134 kg). The FEM-I spherical particle case results in the bounding system that is still acceptable per the USL. 6.6.4.1 FEM-1 Homogeneous Fissile Shape Baseline The homogeneous volume configuration, as described in Section 6.3 .4.2.1, varies H/235 U via the

• size of the fissile shape, at an enrichment limit of 0.90-wt. % 235 U and uranium mass of 2500 lb (1134 kg). As shown in Table 6.6-11 and Figure 6.6-7, a fissile radius of 40.4 cm and keff+ 2cr of 0.86555, is the bounding configuration. Its reactivity is significantly lower than the keff of the spherical particle configurations, so no further studies are analyzed.

6.6.4.2 FEM-1 Cylindrical Particle Baseline Table 6.6-13 shows the variation of half-pitch, thus MU ratio and H/ 235 U, for the bounding set of cylindrical pa11icles. Figure 6.6-8 shows the MU curves for each cylindrical particle set analyzed. For clarity, Table 6.6-13 shows only the bounding cylindrical particle set analyzed. Table 6.6-12 shows the maximum case from each set of cylindrical particles analyzed to show the peak in reactivity has been attained. The FEM-I, HAC package array, cylindrical particle results show that unlimited cylindrical particle sizes at 0.90-wt. % 235 U are subcritical below the USL of 0.94140. The most reactive FEM-I, cylinder HAC package array baseline case results in keff+ 2cr of0.93739 (highlighted grey in Table 6.6-12 and Table 6.6-13). However, the spherical particle analysis produces the bounding HAC package array configuration for FEM 1. Therefore, further studies are not analyzed for the cylindrical particle configuration .

• NAC International 6.6-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.6.4.3 FEM-1 Spherical Particle Baseline Table 6.6-15 shows the variation of half-pitch, thus MU ratio and H/235 U, for the bounding set of spherical particles. Figure 6.6-9 shows the MU curves for each spherical particle set analyzed. For clarity, Table 6.6-15 shows only the bounding spherical particle set analyzed. Table 6.6-14 shows the maximum case from each set of spherical particles analyzed. The FEM-I, HAC package array, spherical particle results show that unlimited spherical particle sizes at an enrichment of 0.90-wt.% 235 U are subcritical below the USL of0.94140. The bounding FEM-1, HAC package array, spherical particle baseline case results in keff+ 2cr of 0.94002 (highlighted grey in Table 6.6-14 and Table 6.6-15). Therefore, unlimited particle size at an enrichment of 0.90-wt. % 235 U is an acceptable content for the package. As the spherical particle results in the bounding configuration for the FEM-1 HAC package array, the bounding spherical particle case is used for the fissile position study and the flooding configuration study. 6.6.4.4 FEM-1 Fissile Shape Position Sensitivity In the baseline study, the fissile shapes of the top and bottom packages are modeled in the corners of the CCV cavity as close together as possible. Multiple positions were analyzed in this study to determine the sensitivity of keff to the fissile position and verify that the worst-case position is determined. The number of spherical particles per row, MU, and spherical radius are

• held constant at the baseline values: 1027 spherical particles/row, a MU of 2.94, and a spherical particle radius of 0.74107 cm. As shown in Table 6.6-16, modeling the fissile spheres in the baseline position is the bounding position for the FEM-1 HAC package array configuration.

6.6.4.5 FEM-1 Flooding Configuration Sensitivity This study examines the sensitivity of the FEM-1 case to flooding in both the OP region and interspersed region simultaneously. As shown in Table 6.6-17, no flooding configuration results in a more reactive case. Therefore, the unflooded case, with keff+ 2cr of 0.94002, is the bounding flooding configuration for the FEM-1 HAC package array. NAC International 6.6-10

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• NAC International 6.6-11

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.6 FEM-1 Bounding Case for Each Cylindrical Particle Size-HAC Package Table 6.6 FEM-1 Bounding Case for Each Spherical Particle Size-HAC Package Arra NAC International 6.6-12

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

• Table 6.6 FEM-1 Flooding Study Results-RAC Package Array
• NAC International 6.6-13

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Figure 6.6 FEM-1 HAC Package Array Homogeneous Mass Study Figure 6.6 FEM-1 HAC Package Array Heterogeneous Cylindrical Particle Study NAC International 6.6-14

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

• Figure 6.6 FEM-1 HAC Package Array Heterogeneous Spherical Particle Study
• NAC International 6.6-15

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.7 Fissile Material Packages for Air Transport The package is not presently authorized for air transport .

• NAC International 6.7-1

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.8 Benchmark Evaluation All benchmark experiments discussed and utilized in this section to determine the bias and USL of the FGE and FEM evaluations come from the International Handbook of Evaluated Criticality Safety Benchmark Experiments [6.14]. The bias and USL functions, as determined in this section, are summarized in Table 6.8-1. As the plutonium USL functions are not dependent on the trending parameter, the USL equations are equal to the final USLs. Thus, the USLs for the FGE content cases are shown in Table 6.8-2. The low-enriched uranium USL function is dependent on the trending parameter, thus the USL is calculated and presented in Table 6.8-3 along with the bounding H/ 235 U value. The administrative margin (~km) for FGE and FEM evaluations is 0.05. The applicability of the benchmark experiments and the bias determination are discussed in Sections 6.8.1 and 6.8.2, respectively. 6.8.1 Applicability of Benchmark Experiments 6.8.1.1 Plutonium Experiments The plutonium experiments selected for determining the bias and USL for the FGE cases are summarized in Table 6.8-4. The plutonium benchmark cases were selected to be as similar to the

• package FGE cases as possible. The FGE cases all consist of plutonium metal in solutions and the benchmark experiments selected consist of plutonium compounds in solution. While the Package analysis models approximately 95-100 wt.%

benchmarks all include 240 Pu, 239 Pu, with the remainder 240 Pu, the and some include trace amounts of 238Pu, 241 Pu, and 242 Pu. The presence of the trace amounts of 238Pu, 241 Pu, and 242 Pu plutonium isotopes is expected to have an insignificant effect in determining the bias and USL for plutonium solution systems. However, the fissile isotope 241 Pu is included in the calculation of the H/Xi ratio for the benchmarks, i.e., H/Xi = H/(2 39Pu + 241 Pu). While only some of the Package content cases credit 240 Pu, all plutonium shipped in the Package will likely have some amount of 240 Pu. Thus, it is acceptable that some Package content case analyses differ from the benchmark cases by excluding 240 Pu. Any small effect on the calculated bias from 240 Pu will be bounded by the effect on the calculated keff in the content case analyses by neglecting the neutron loss to 240 Pu absorption. These solution benchmarks also represent the thermal neutron population of the Package and its water moderation, with most cases also having water reflection. The plutonium solution, thermal, number 019 benchmark experiment (PU-SOL-THERM-019) includes a beryllium reflector, which is included in the FGE-3 content case. This helps to capture the effect of beryllium on determining the bias and USL.

• NAC International 6.8-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.8.1.2 Low-Enriched Uranium Experiments The low-enriched uranium experiments selected for determining the bias and USL for the FEM cases are summarized in Table 6.8-5. The low-enriched uranium benchmark cases were selected to be as similar to the package FEM cases as possible. All the low-enriched uranium benchmarks contain small amounts of 234 U and 236 U. Although the Package analysis models purely 235U and 238U, any uranium transported in the package will likely contain small or trace amounts of2 34U and 236U. This difference in uranium composition will have an insignificant effect in determining the bias and USL for low-enriched uranium systems. The low-enriched uranium metal, thermal, benchmark series number 006 (LEU-MET-THERM-006) models uranium metal tubes at 1.6 wt.% 235 U enrichment with light-water moderation and reflection. The Package will likely not carry pieces of uranium as large as these tubes (ID 7 .5 cm and OD 9.5 cm with a height of 59 cm). However, this benchmark series does capture a thermalized heterogeneous system predicted for the Package with water moderation and reflection. The low-enriched uranium compound, thermal benchmark series number 033 (LEU-COMP-THERM-033) models uranium tetrafluoride (Uf 4)-paraffin mixtures in single, large cubes for each experiment. These cubes either have polyethylene or paraffin side and top reflectors with a bottom Plexiglas reflector, or are bare systems. The benchmark cases are modeled as homogeneous systems, but the critical benchmark report states that the UF4-paraffin cubes are mixtures of very small Uf4 particles suspended in paraffin. However, the report determined that the bias between modeling the particle size explicitly versus a homogeneous mixture was insignificant. In addition, the cases modeled have a 235U enrichment of2 wt.%. In terms of reflector, moderator, and the approximate sizes of the cubes, these benchmark cases are the most like the package cases of the low-enriched uranium benchmark cases selected. Although the fissile material is UF 4, the geometry of a homogeneous system and the density of fissile material amongst the moderator is captured with the benchmark cases. Therefore, modeling a compound over bare metal is expected to have an insignificant impact. The low-enriched uranium solution, thermal benchmark series (LEU-SOL-THERM-001, 002, 003, 004, 007, 016, 017) model uranium compound-water solutions in tanks of spherical, parallelepiped, or cylindrical geometry. These cases capture the thermal neutron population expected in the Package analysis, are all water moderated, and have a mix of experiments with water reflection or no reflection. As stated, the fissile material is in the configuration of uranium compounds, but this is expected to have an insignificant effect in determining the bias and USL, as the fissile material is dispersed in a hydrogenous solution. NAC International 6.8-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 6.8.1.3 Area of Applicability The comparison of the relevant properties between the critical experiments and the package's limiting cases are shown in Table 6.8-6 for plutonium systems and Table 6.8-7 for uranium systems. The NCT package array cases are not considered in this applicability examination because the NCT systems are not optimally moderated systems like the benchmarks used to develop the USL. In addition, the NCT package array cases have large (~25%) margins with respect to the USL. As the USLs are developed using critical benchmarks, the parameters from cases with keffWell below 1 (i.e. NCT package array) are expected to be outside of the areas of applicability (AOA). For the plutonium FGE contents some of the package cases go slightly beyond the area of applicability (AOA), as shown in Table 6.8-6. The 'fissile content' range is a very small extrapolation outside of the AOA and would have no effect on the determined USL. The H/Xi range analyzed for the plutonium cases extends just beyond the upper limits of the H/Xi analyzed in the benchmarks. However, the limiting package cases all have an H/Xi inside the AOA. The only cases outside the AOA have keff + 2cr values well below the USL. Thus, any additional bias from being outside of the AOA is not expected to reduce the USL to a point where keff+ 2cr would exceed the USL.

• As shown in Table 6.8-7 for low-enriched uranium FEM-1 contents, some of the package cases go slightly beyond the AOA determined. For the fissile weight percent, cases are outside of the AOA of the LEU benchmarks analyzed. However, Figure 6.8-9 shows that the trend line is relatively flat for this parameter and the correlation coefficient for this trend line is very low (0.1062, Table 6.8-10). This indicates that there is not a strong correlation between the fissile weight percent and the bias in the calculated keff. For the EALF, there are a couple of cases where the EALF is just outside of the range of the LEU benchmarks. However, the limiting package cases all have an EALF inside the AOA. The only cases outside the AOA have keff + 2cr values well below the USL. Thus, any additional bias from being outside of the AOA is not expected to reduce the USL to a point where keff + 2cr would exceed the USL.

A comparison of the isotopes included in the benchmarks and the isotopes modeled in the package analysis was completed. All differences in isotopes modeled were addressed and determined to be acceptable. Therefore, in conjunction with a comparison of the areas of applicability (AOA), the USLs generated are applicable to the package criticality safety evaluation .

• NAC International 6.8-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.8.2 Bias Determination To determine a bias and calculate a corresponding USL, the selected benchmark experiments were modeled and analyzed in MCNP6. Section 4.1 ofNUREG/CR-6361 [6.15] explains two methods of determining the USL. The first method applies a statistical calculation of the bias and its uncertainty, plus an administrative margin, to a linear fit of critical experiment benchmark data. This method is known as Method 1: Confidence Band with Administrative Margin. In the second method, statistical techniques with a rigorous basis are applied to determine a combined lower confidence band plus subcritical margin. This method is known as Method 2: Single-Sided Uniform Width Closed Interval Approach. USLSTATS is a program that calculates USL correlations with these methods outlined and was used in this analysis. For this analysis, Method 1 is applied, and Method 2 is used as a verification of Method 1 such that the USL function of Method 1 (USL,) must be less than the USL function of Method 2 (USL2). If the minimum margin of subcriticality, C*s(p) - W, calculated for Method 2 is less than the administrative margin selected for Method 1 (0.05), the administrative margin selected is sufficient. This verifies that the selected administrative margin bounds the statistical margin determined by Method 2. In addition, NUREG/CR-6361 mentions that the correlation between a trending parameter and the critical data is the primary criterion to select the parameter that will

• define the USL. USL equations for the FGE and FEM evaluations were developed using USL Method 1. For each content type the trending parameters analyzed for the bias determination are H/Xi, fissile weight percent, and EALF.

6.8.2.1 Plutonium Solutions without Beryllium Reflector USL Function The USL calculations for each of the trending parameters for plutonium systems without a beryllium reflector are provided in Table 6.8-8 and the USLSTATS plots are provided in Figure 6.8-1 through Figure 6.8-3. The administrative margin (~km) selected was 0.05, which is greater than C*s(p)- W calculated for each trending parameter; therefore, the selected administrative margin is acceptable. Based on the results of these analyses, the USL function determined with H/Xi as the trending parameter is selected as the USL function for the Package's plutonium contents without beryllium reflector. The H/Xi trending parameter has the largest Correlation Coefficient, (r), at 0.4197, as shown highlighted in gray in Table 6.8-8 and in Figure 6.8-2. 6.8.2.2 Plutonium Solution with Beryllium Reflector USL Function The USL calculations for each of the trending parameters for plutonium systems with a beryllium reflector are provided in Table 6.8-9 and the USLSTATS plots are provided in Figure 6.8-4 through Figure 6.8-6.

• NAC International 6.8-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A The administrative margin (~km) selected was 0.05, which is greater than C*s(p)- W calculated for each trending parameter; therefore, the selected administrative margin is acceptable. Based on the results of these analyses, the USL function determined with fissile weight percent as the trending parameter is selected as the USL function for the Package's plutonium contents with beryllium reflector. The fissile weight percent trending parameter has the largest Correlation Coefficient, (r), at 0.3385, as shown in Table 6.8-9 and in Figure 6.8-6. 6.8.2.3 Low-Enriched Uranium System USL Function The USL calculations for each of the trending parameters for low-enriched uranium systems are provided in Table 6.8-10 and the USLSTATS plots are provided in Figure 6.8-7 through Figure 6.8-9. The administrative margin (~km) selected was 0.05, which is greater than C*s(p)- W calculated for each trending parameter; therefore, the selected administrative margin is acceptable. Based on the results of these analyses, the USL function determined with H/ 235 U as the trending parameter is selected as the USL function for the low-enriched uranium contents of the Package. The H/235 U trending parameter has the largest Correlation Coefficient, (r), at 0.3275, as shown in Table 6.8-10 and in Figure 6.8-8 .

• NAC International 6.8-5

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 6.8 Criticality Safety Bias and USL Functions Correlation Trending Trending USL Equation (Method 1) C*s(p)-W Coefficient Parameter Parameter Range (r) Plutonium Solution Systems without Beryllium Reflector H/(239 Pu + 241Pu) 0.9393 90.9 ::;; X::;; 1061.1 1.6390E-2 -0.4197 Plutonium Solution Systems with Beryllium Reflector Fissile Wt. 0.9368 95.3 ::;; X ::;; 99.5 1.9699E-2 0.3385 Percent Low-Enriched Uranium Systems H/235LJ 0.9444 - 3.9539-6 *X (X > 760.35) 179.4::;; X::;; 1437.5 1.2563E-2 -0.3275 0.9414 (X::;; 760.35) Table 6.8 FGE Criticality Safety USL Functions FGE USL Functions FGE Configurations USL Plutonium Solution Systems FGE-1; FGE-2a, b, c; 0.9393 without Bervllium Reflector FGE-5 Plutonium Solution Systems FGE-3 0.9368 with Beryllium Reflector Table 6.8 FEM Criticality Safety USL Functions Content Limiting Case H/23SU USL FEM1 FEM1 S_HAC_ 1027_0.99 455.5 0.9414 NAC International 6.8-6

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.8 Critical Benchmark Experiments - Plutonium Cases Selected/ Fissile Fissile H/(23spu + 241Pu) Report (1l Available Weight Moderation Reflector Configuration Experiments Percent (2l PuHNO3 PST-001 6/6 95.3 Water Water 90.9-370.2 Solution PuHNO3 PST-002 717 96.9 Water Water 308.9 - 524.3 Solution PuHNO3 PST-003 8/8 96.9-98.2 Water Water 714.3 - 788.0 Solution PuHNO3 PST-004 13/13 96.6-99.5 Water Water 592.4 - 987.0 Solution PuHNO3 PST-005 9/9 95.6-96.0 Water Water 580.6 - 902.8 Solution PuHNO3 PST-006 3/3 96.9 Water Water 940.1 -1061 Solution PuHNO3 PST-007 8/8 95.3 Water Bare 109.2 - 284.1 Solution PuHNO3 PST-010 14/14 . 97.1 -97.2 Water Water 266.9-849.7 Solution Pu(SO4)2 BeO/ PST-019 11/11 98.2 Water 864.6- 1129.7 Solution Graphite Notes: I. PST - PU-SOL-THERM

2. Fissile weight percent includes 239Pu + 2

• 1Pu, when applicable.

Table 6.8 Critical Benchmark Experiments - Low-Enriched Uranium Cases Selected/ Fissile Enrichment H/23su Report (1l Available Moderation Reflector Configuration (wt.%) Experiments LMT-006 14/30 U Metal Tubes 1.60 Water Water 179.4-337.3 Paraffin, Uh-Paraffin Mixture Polyethylene, LCT-033 40/52 modeled as 2.00 Paraffin 195.6 - 972.8 Plexiglas, or Homogeneous Bare LST-001 1/1 UO2F2 Solution 4.94 Water Bare 453.9 LST-002 3/3 UO2F2 Solution 4.89 Water Bare/ Water 1001.3 - 1098.3 LST-003 9/9 UO2(NO3)2 Solution 10.07 Water Bare 770.3-1437.5 LST-004 7/7 UO2(NO3)2 Solution 9.97 Water Water 719.0-1017.6 LST-007 5/5 UO2(NO3)2 Solution 9.97 Water Bare 709.3 - 942.2 LST-016 7/7 UO2(NO3)2 Solution 9.97 Water Water 468.7 - 771.8 LST-017 6/6 UO2(NO3)2 Solution 9.97 Water Bare 468.7 - 729.0 Notes: I. LMT- LEU-MET-THERM I LCT - LEU-COMP-THERM I LST - LEU-SOL-THERM NAC International 6.8-7

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.8 Plutonium Critical Experiment Area of Applicability Plutonium Solutions Plutonium Solutions Parameter OPTIMUS-L without Beryllium with Beryllium Fissile Material 239 Pu and 241 Pu 239Pu and 241 Pu 239Pu Fissile Content 95.32- 99.46 95.32 - 99.46 94.05- 100.0 (1) (wt.%) Water, Beryllium, Moderation Water Water Polvethvlene Steel, Water, Bare, Water, BeO + Reflector Bare, Water Beryllium, Graphite Polvethvlene EALF (eV} <2> 0.0516- 0.3414 0.0497-0.3414 0.0524 - 0.0714 H/Xi<3> 90.9-1061.1 90.9-1129.7 100-1100 Notes:

1. Lower bound fissile weight percent calculated from FGE-2c limit case with 395 g239Pt.1 and 25 g240Pu.

2. As detenruned in MCNP6.

3. H/Xi includes both 239Pu and 241 Pt.1 fissile isotopes for the two USL series.

Table 6.8 Low-Enriched Uranium Critical Experiment Area of Applicability Parameter Low-Enriched Uranium OPTIMUS-L Fissile Material 235LJ 235LJ Fissile Wt. Percent 1.60-10.1 0.90 Water, Beryllium, Moderation Water, Paraffin Polvethvlene Bare, Water, Polyethylene, Steel, Water, Beryllium, Reflector Paraffin, Plexiglas Polyethylene EALF (eV} <1> 0.0341 -0.6746 0.1204 - 0.7960 H/Xi<2> 179.4 - 1437.5 310-634 Notes:

1. As determined in MCNP6, for the limiting cases.

2. As calculated for the limiting cases.

Table 6.8 USL Functions for Plutonium without Beryllium Reflector Benchmarks USL Correlation Trending Trending USLSTATS Parameter Equation Parameter Range C*s(p)-W Coefficient Plot (Method 1) (r) EALF 0.9374 0.0516 s X s 0.3414 1.9711E-2 0.2209 Figure 6.8-1

                                                                                      -0.0666 NAC International                                            6.8-8

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Table 6.8 USL Functions for Plutonium with Beryllium Reflector Benchmarks USL Correlation Trending Equation Trending Parameter C*s(p) - Coefficient USLSTATS Parameter (Method 1) Range w (r) Plot EALF 0.9344 0.0497 s X s 0.3414 2.3967E-2 -0.0405 Figure 6.8-4 H/(239f'u + Z*"Pu) 0.9365 90.9 s XS 1129.7 2.0085E-2 0.1674 Figure 6.8-5 Fissile Wl 0.9368 95.3 s X s 99.5 1.9699E-2 0.3385 Figure 6.8-6 Percent Table 6.8 USL Functions for Low-Enriched Uranium Critical Benchmarks Correlation Trending Trending Parameter USLSTATS USL Equation (Method 1) C*s(p}-W Coefficient Parameter Range Plot (r) 0.9428- 7.2106E-3"X (X > 0.2267) EALF o.0341 sxso.6746 1.3275E-2 -0.2872 Figure 6.8-7 0.9411 (X s 0.2267) 0.9444- 3.9539E-6"X (X > 760.35) H/=U 179.4 sxs 1437.5 1.2563E-2 -0.3275 Figure 6.8-8 0.9414 (X s 760.35)

• Fissile Wt.

Percent 0.9414 1.60 s X s 10.07 1.19TTE-2 0.1062 Figure 6.8-9

• NAC International 6.8-9

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 0.990 Jr.-etr values Jr.(X) 0.985 k(X) - Y(r) Jr.(r) -W ustm USL<2l 0.965 0.960 0.95S 0.950 0.945 0.940 0.935 0.930 0.10 0.15 0.20 0.25 0.30 Trending Parameter, x Figure 6.8 kerrvs. EALF - Plutonium Solution Systems without Beryllium Reflector 0.990 z

0.985 0.980 0.975 0.970 k-etrvalues

• 0.96S k(I) ----*

Jr.(X)-Y(r) 0.960 k(r)*W ******. * **** 0.9S5 USL(l) --* -- IJSLnl 0 .950 0.94S 0.940 u.:::.=-'-=1"-=..;.c

                                      * -=-=-=*-     * =~=-=:z..:..::="-'--===-==-='-'--==-=:.:..Z:=c;..::=-=a.==-===-=-:::.,
                                               = -='-~

0.1E03 0.2£03 0.38>3 0.4£03 0.SE03 0.6E03 0.7E03 0.8E03 0.9£03 1.0E03 Trending Parameter, x Figure 6.8 kerr vs. H/(239Pu + 241 Pu) - Plutonium Systems without Beryllium Reflector NAC International 6.8-10

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 0 .990 0 .98S

             ~
             ~

0 .9811) 0.975 0.970 0 .965 0.9(50 k-efT values

• k(X) - - ---

0.95S k(l) - Y(X) -- -- k(l)-W . *.. .. .* ... . 0.950 USL(l) --* -- USL 0.945 95.S 96.0 96.S 97.0 97.S 98.0 98.S 99.0 Trending Parameter, x Figure 6.8 k etr vs. Fissile Weight Percent - Plutonium Solution Systems without Beryllium Reflector 0.9SS

t:

0.980 k-i!t!' values k(l)

          ~   0.975 I                                                                             k(X) - Y(X)
         ~    0 .970                                                                     k(X)  -w USL(l) 0.9&5                                                                      USL 0 .9(50 0.955 0.950 0.945 0.940 0 .935 0 .930 0.925 -*    --

• _ - *-- * - _ *- . * - - * - - .*

0 .05 0 .10 0.15 0.20 0 .25 0 .30 Trending Parameter, x Figure 6.8 k etr vs. EALF - Plutonium Solution Systems with Beryllium Reflector

• NAC International 6.8-11

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 0.99S 0990 -*--*- t= 0.985 k-etr values k(X) z 0.980 0.975 lr.(X) -Y(XJ k(X) -W USL(l) USLl2l 0.970 0.96S 0.960 0.95S 0.950 0.94S 0.940 0.1103 0.2£03 0.3F.03 0.4£03 O.SE03 0 6E03 0.7E03 0.8E03 0.9E03 1.0E03 1.1E03 Trending Parameter, x Figure 6.8 k,rr vs. Hl{239Pu + 241 Pu) - Plutonium Solution Systems with Beryllium Reflector 0.990 t= 0.98S k-etr values k(X) f 0.980 k(X) - Y(X)

         .ll:                                                                             k(X) -W 0.975                                                                       USL(l)

USL(2) 0.970 0.965 0.960 0.95S 0 .950 0.945 0 .940 95.S 96.0 96.S 97.0 97.S 98.0 985 99.0 Trending Parameter, x Figure 6.8 k,,rvs. Fissile Weight Percent - Plutonium Solution Systems with Beryllium Reflector NAC International 6.8-12

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 1.015 T

                                      +

0985 l

         ~

0.980 0.975 0.970 0.965 0 .960 0.955 k-elT values k(lc) ----*

• 0.9SO k(X)
• W(I<)

k(X) . w -- --* 0945 USL(l) USLl21

                         -t.0E-02  ME-02 8.0li-02                     2.0li-01                   * .0E-01          6.011-01 Trending Parameter, x Figure 6.8 k,rrvs. EALF- Low-Enriched Uranium Systems
         ~    0.980 i:.. .
         .::: 0.97S
                           =*- - - - - - - -                       -- - -       - -*-*-         - --- -*---

0970 096S k-elT values k(X)

• k(le)
• W(IC) 0.960 k(l)
• W USL(l) 0.95S USLl2l 0.950 0.945 -

0.9401-' - - - --~ - - - - - - * ......_-....: __ ___ _ 0.2E03 o.*E03 0.6!!03 0.8E03 1.0£03 1.2E03 1.4£03 Trending Parameter, x Figure 6.8 k,rr vs. Hl235 U - Low-Enriched Uranium Systems

• NAC International 6.8-13

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 1.01S 1.010 1005

1. -----------t------------------- -

0.98S z 0.980 0.97S 0.970 0.965 k~vatues k(x) 0.960 k(x) - Y(X) k(X) -W 09SS USL(l) USL/2) 0.950 0.945 2.0 3.0 4.0 5.0 6.0 7.0 8 .0 9.0 10.0 Trending Parameter, x Figure 6.8 kerrvs. 2350 Weight Percent- Low-Enriched Uranium Systems NAC International 6.8-14

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 6.9 Appendix 6.9.1 References [6.1] Washington TRU Solutions LLC, "Test Plan to determine the TRU Waste Polyethylene Packing Fraction," WP 08-PT.09, Rev. 0, 2003. [6.2] SAIC, "Reactivity Effects of Moderator and Reflector Materials on a Finite Plutonium System," SAIC-1322-001 Rev. I, 2004. [6.3] ASTM International, "Specification for General Requirements for Steel Plates for Pressures Vessels," SA-20/SA-20M, 2007. [6.4] Los Alamos National Laboratory, "Listing of Available ACE Data Tables," LA-UR 21822 Rev. 4, 2014. [6.5] Pacific Northwest National Laboratory, "Compendium of Material Composition Data for Radiation Transport Modeling," PNNL-15870 Rev. 1,201 I. [6.6] American Institute of Physics, "Isotopic Compositions of the Elements, 200 l ," 2005. [6.7] Atomic Mass Data Center, "The Ame2003 Atomic Mass Evaluation," Nuclear Physics A 729 (2003) 336-676, December 22, 2003. [6.8] Oak Ridge National Laboratory, "Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design," ORNL/TM-2005/39 Version 6.1, 20 11. [6.9] Los Alamos National Laboratory, "Initial MCNP 6 Release Overview- MCNP6 Version 1.0," LA-UR-13-22934, 2013. [6.1 O] American Nuclear Society, "Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors," ANSI/ANS-8.1-2014, 2014. [6.11] American Nuclear Society, "Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors," ANSI/ANS-8.12-1987, R2016. [6.12] American Nuclear Society, "Nuclear Criticality Safety Control of Special Actinide Nuclides," ANSI/ANS-8.15-2014, 2014. [6.13] U.S. Department of Energy, "Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant," DOE/WIPP-02-3122 Rev. 8, 2016 [6.14] Organization for Economic Cooperation and Development - Nuclear Energy Agency, "International Handbook of Evaluated Criticality Safety Benchmark Experiments," NEA/NSC/DOC(95)03, 2014 .

• NAC International 6.9-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A [6.15] Oak Ridge National Laboratory, "Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, NUREG/CR-6361, ORNL/TM-13211," NUREG/CR-6361, ORNL/TM-13211, 1997. NAC International 6.9-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Chapter 7 Package Operations Table of Contents 7 PACKAGE OPERATIONS ............................................................................................. 7-1 7.1 Package Loading ........................................................................................................... 7 .1-1 7 .1.1 Preparation for Loading .................................................................................... 7 .1-1 7 .1.2 Loading of Contents .......................................................................................... 7 .1-3 7 .1.3 Preparation for Transport. ................................................................................. 7 .1-4 7.2 Package Unloading ....................................................................................................... 7 .2-1 7.2.1 Receipt of Package from Carrier. ...................................................................... 7.2-1 7.2.2 Removal of Contents ......................................................................................... 7.2-1 7.3 Preparation of Empty Packaging for Transport ............................................................ 7.3-1 7.4 Other Operations ........................................................................................................... 7.4-1 7.5 Appendix ....................................................................................................................... 7.5-1 7.5.1 References ......................................................................................................... 7.5-1 Attachment 7.5 Determination of Acceptable Activity ........................................... 7.5-2 Attachment 7.5 Example CCV Pre-Shipment Inerting Procedure .......................... 7.5-3 List of Figures Figure 7.5-1 Pre-Shipment Inerting Apparatus Schematic .................................................... 7.5-4 List of Tables TBD

• NAC International 7-i

- - -- -- - This page intentionally left bhink.- --- -- -------

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 7 PACKAGE OPERATIONS This chapter outlines the operations used to load the OPTIMUS-L transportation package and prepare it for transport (Section 7.1), unload the package (Section 7.2), and prepare the empty package for transport (Section 7.3). It presents the fundamental operating steps in the order in which they are performed. The operating steps are intended to ensure that the package is properly prepared for transport, consistent with the package evaluation in Chapters 2 through 6, and to ensure that occupational exposure rates are as low as reasonably achievable (ALARA). The package shall be operated in accordance with detailed written procedures that are based on, and consistent with, the operations described in this section. To provide a comprehensive description of the package operations, this chapter describes a sequence for steps and refers to specific facility areas. The specific sequence and locations in the detailed written operating procedures may be tailored to meet facility requirements. Furthermore, the operating procedures in this section use standard rigging (e.g., swivel hoist rings and 3-leg bridles) to lift the packaging components. The use of alternative lifting devices in detailed written procedures is also acceptable, provided they satisfy the applicable site requirements. It is the responsibility of the user of the packaging to prepare detailed operating procedures based on the operating procedures described in this chapter, the requirements of the Certificate of Compliance, and any applicable site requirements. The maximum permissible activity for gamma emitting radionuclides is the maximum activity determined per Attachment 7.5-1. For other radionuclide contents, the maximum activity is that which meets the decay heat limit of 100 watts. For TRU waste contents that could radiolytically generate combustible gases (Content 1-1), the criteria of Sections 4.5.2 and 4.5.3 must be addressed. For TRU waste, compliance with the flammable gas concentration limits shall be demonstrated by the methods discussed in Appendix 4.5.4 .

• NAC International 7-1

This page intentionally left blank.

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 7.1 Package Loading This section describes loading-related preparations, tests, and inspections for the package. These include the inspections made before loading the package to determine that it is not damaged, and that radiation and surface contamination levels are within the regulatory limits. 7.1.1 Preparation for Loading This section describes the operations for preparing the package for loading. It is the responsibility of the user of the packaging to verify that the contents are authorized in accordance with the package approval and that the package is loaded and closed in accordance with detailed written procedures that are based on the operating procedures described in this chapter, the requirements of the Certificate of Compliance, and any applicable site requirements. The OPTIMUS-L transportation package is transported by truck in a vertical orientation. The package may either be tied down to a custom-designed pallet that is secured to a trailer deck or tied down directly to the trailer deck. For some operations, the different tiedown, conveyance, and lifting/handling configurations require differences in the procedural steps, which are described in the following procedure. Loading operations for the OPTIMUS-L transportation package shall be performed in a precipitation-free environment, or measures shall be taken to prevent precipitation from entering the package cavities, such as performing loading operations under a protective cover. If standing water collects inside the CCV cavity and/or SIA cavity (if used), absorbent materials or another suitable method, such as a vacuum system, shall be used to remove the free-standing water from the CCV cavity and/or SIA cavity (if used), which may require the contents to be unloaded. The only special equipment required for the loading and unloading operations of the package, other than standard sockets and wrenches for fasteners, equipment used to lift the packaging components, a radioactive contamination detector, and a radiation survey meter, are the pre-shipment inerting and leakage rate testing apparatuses. Appropriate controls shall be used for all loading and unloading operations to prevent the spread of radioactive contamination and protect personnel from exposure to excessive radiation. The general procedure for preparing the package for loading is as follows:

1. Upon receipt of the package, perform radiation and removable contamination surveys of the package in accordance with facility procedures and the requirements of 49 CFR 173.441 and 49 CFR 173.443. Clean or decontaminate the package as necessary in accordance with facility procedures .

• NAC International 7.1-1

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

2. Move the transport vehicle with the package(s) to the receiving area and secure the transport vehicle.

3. Visually inspect the exterior surfaces of the package for any signs of damage to verify that the package is in unimpaired physical condition.

4. If required, detach the tiedowns and/or trailer securements and move the package from the trailer to the loading area.

5. Remove the tamper-indicating seal from the OP.

6. Remove the OP lid bolts.

7. Using 3-legged bridle (or other suitable rigging) attached to the OP lid lifting lugs, lift the OP lid vertically, exposing the top end of the CCV, and move the OP lid to the storage location.

8. Loosen a l - ) CCV closure bolts.

9. Attach swivel hoist rings (SHRs) to the CCV lid and torque SHRs in accordance with the manufacturer's instructions.

10. Attach suitable rigging to the SHRs on the CCV lid.

11. Verify that the captured lid bolts are completely disengaged from the threaded holes in the CCV bolt flange.

Caution: When handling the CCV lid, protect the O-rings and associated sealing surfaces from damage.

12. Lift the CCV lid vertically and move it to the temporary storage location.

Caution: When handling the CCV port cover, protect the O-rings and associated sealing surface from damage.

13. If required, loosen and remove all - CCV port cover bolts and remove the CCV port cover and place it in the temporary storage location.

14. Remove the plugs from the CCV lid and port cover test ports and place them in the temporary storage location.

NAC International 7.1-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 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, 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 and SIA 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) .

NAC International 7.1-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A

4. 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), ifremoved, 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.

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

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

7. Remove the SHRs from the CCV lid.

8. 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.

9. 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.

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

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.

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.

• NAC International 7.1-4 L__

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

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(6).

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

12. Verify the exterior surface of the package does not exceed 85°C (l 85°F) in accordance with the requirement of 49 CFR 173.442(6)(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) .
• NAC International 7.1-5

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NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 7.2 Package Unloading This section describes the package unloading operations, including the inspections, tests, and preparations of the OPTIMUS-L package for unloading. 7.2.1 Receipt of Package from Carrier This section describes the procedure for receiving a loaded package, including radiation and contamination surveys and inspection of tamper-indicating devices. The general procedure for receipt of a loaded package from a Carrier is as follows:

1. Perform a radiation survey of the package. If the external surface radiation levels exceed 200 mrem/hr, then notify the Consignor immediately and investigate the cause of the high radiation levels before proceeding.

2. Perform a contamination survey of the external surfaces of the package to confirm that the levels of non-fixed (removable) radioactive contamination does not exceed the limits specified in 49 CFR 173.443. If contamination levels exceed the limits, then notify the Consignor immediately and decontaminate the exterior surfaces, as necessary.

• 3. Visually verify that the tamper-indicating seals are intact. If it is NOT intact, investigate the cause and take actions per facility procedures.

4. Move the transport vehicle with the package(s) to the receiving area and secure the transport vehicle.

5. Remove the tamper-indicating seals from the upper impact limiter.

7.2.2 Removal of Contents This section describes the procedure for opening and removing the contents from a loaded package. The general procedure for opening each loaded package and removing its contents is as follows:

1. Loosen and remove a l l - OP lid bolts.

2. Attach suitable rigging to the OP lid lifting lugs.

3. Lift the OP lid vertically and move it to the temporary storage location.

4. Loosen a l - ) CCV closure bolts.

• 5. Attach swivel hoist rings (SHRs) to the CCV lid and torque SHRs in accordance with the manufacturer's instructions.

NAC International 7.2-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

6. Attach suitable rigging to the SHRs on the CCV lid.

7. Verify that the captured lid bolts are completely disengaged from the threaded holes in the CCV bolt flange.

Caution: When handling the CCV lid, protect the O-rings and associated sealing surfaces from damage.

8. Lift the CCV lid vertically and move it to the temporary storage location.

9. Remove the contents from the packaging.

NAC International 7.2-2

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 7.3 Preparation of Empty Packaging for Transport This section describes the procedure for preparing a previously used and empty package for transport, including the inspections, tests, and special preparations needed to ensure that the packaging is verified to be empty, is properly closed, and that the radiation and contamination levels are within the applicable allowable limits. The general procedure for preparing each empty package for transport is as follows:

1. Visually inspect the CCV cavity or SIA cavity to confirm that it has been emptied of its contents as far as practical.

2. Survey the interior of the internal surfaces of the package (i.e., CCV bottom support plate, CCV cavity, CCV flange, and underside of the CCV lid) and any empty payload internals (e.g., SIA body and dunnage, if used) to be shipped to verify that the interior contamination limits of 49 CFR 173.428(d) are satisfied. If the non-fixed surface contamination exceeds the limits for empty package shipment, then decontaminate the interior surfaces, as necessary.

3. Visually inspect the readily accessible surfaces of the packaging components for any signs of damage that may have occurred during prior use to verify that the package is in unimpaired

• physical condition.

4. Apply thread lubricant to the threaded fasteners of the package.

5. Install the CCV closure lid and tighten each of t h e - CCV lid bolts, in the sequence shown on the CCV lid, to a torque of 300 +/- 15 ft-lbs, then repeat the sequence to verify that all CCV lid bolts are tightened to the required torque.

6. Remove the SHRs from the CCV lid.

7. If the CCV port cover has been removed from the CCV lid, install the CCV port cover and torque each o f t h ~ port cover bolts to 15 +/- 1 in-lbs.

8. Place the OP lid onto the OP base.

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

10. Ifrequired, move the package from the inspection area to the trailer.

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

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

NAC International 7.3-1

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A

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

14. Perform a radiation survey to confirm that the dose rates on the external surface of the package does not exceed 0.005 mSv/hour (0.5 mrem/hour) in accordance with the 49 CFR 71.421(a)(2).

15. Perform a contamination survey to confirm that the non-fixed (removable) radioactive surface contamination on the external surfaces of the package does not exceed the limits specified in 40 CFR 173.443(a). If the non-fixed surface contamination exceeds the limits, then decontaminate the interior surfaces, as necessary.

16. Cover the packaging marking and labelling with an "Empty" label as prescribed in 49 CFR 172.450.

17. Release the package to the Carrier for the return shipment.

NAC International 7.3-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 7.4 Other Operations Not applicable .

• NAC International 7.4-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 7.5 Appendix 7 .5.1 References [7 .1] ANSI N 14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, Inc., June 19, 2014. [7.2] Savannah River National Laboratory, Report No. SRNL-STI-2016-00674, Proof of Principle Testing For Inerting a 9978 Containment Vessel, November 2016 .

• NAO International 7.5-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Attachment 7.5-1 Determination of Acceptable Activity (see Section 5.4.4.3 for the discussion on demonstrating compliance with dose rate limits)

1. Determine the total activity of each isotope in the contents.

2. Calculate the Method 1 or Method 2 2-meter Dose Rate/Ci value of each isotope in the contents and the corresponding activity limit of each isotope using Method 1 or Method 2, per the guidance in Section 5.4.4.2.

3. Demonstrate compliance with 10CFR71 dose rate limits using Compliance Method 1 or Compliance Method 2.

Compliance Method 1 (see Section 5.4.4.3.1)

a. Calculate the sum of the fractions for the contents for each package in the conveyance, individually. For each isotope, divide the total activity determined in Step 1 by the Method 1 activity limit for the isotope calculated in Step 2. Sum the fractions from all isotopes in the contents to calculate the sum of the fractions.

b. To demonstrate compliance with all regulatory dose rate limits, the sum of the fractions

• from all isotopes in the contents must be less than 1.0 for each package, individually.

Compliance Method 2 (see Section 5.4.4.3.2)

a. Calculate the sum of the fractions for the contents for each package in the conveyance, individually. For each isotope, divide the total activity determined in Step 1 by the Method 2 activity limit for the isotope calculated in Step 2. Sum the fractions from all isotopes in the contents to calculate the sum of the fractions for each package.

Predetermined activity limits are provided in Table 5.4-11 for a 2x5 package array (without SIAs) and in Table 5.6-9 for a lx6 package array with no SIAs, I-inch SIAs, and/or 21/4-inch SIAs.

b. Determine the corrected package surface sum of the fractions using EQN 7 and the guidance in Section 5.4.4.3.2.

c. Calculate the sum of the fractions using EQN 8 and the guidance in Section 5.4.4.3.2.

The sum of the fractions for each package in the conveyance should be sorted from highest to lowest and the corresponding DRCFs applied before summing the values for each package to determine the total 2-meter sum of the fractions.

d. To demonstrate compliance with all regulatory dose rate limits, the sum of the fractions from all isotopes in the contents must be less than 1.0.

NAC International 7.5-2

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Attachment 7.5-2 Example CCV Pre-Shipment Inerting Procedure The following procedure is an example of an acceptable pre-shipment inerting procedure for the CCV, which is only required when shipping contents with a total decay heat load exceeding 50 watts. The following example procedure is based on process that has been proven effective for TRU waste contents through testing [7.2]. Alternate procedures that are proven effective in reducing the oxygen gas trapped inside the waste container confinement boundaries to I% or less are also acceptable.

1. Connect the inerting apparatus to the CCV lid quick connect fitting as shown in Figure 7.5-1.

2. Ensure that the Purge and Vacuum Valves are closed, the Helium Cylinder has adequate pressure, the vacuum pump is running, and the Pressure Regulator is set to 25 psig outlet pressure.

Note: Completion of the pump-down operation is indicated when the noise-level of the vacuum pump suddenly decreases.

3. Open the Vacuum Valve and monitor the pressure reading on the Pressure Gauge until it falls below 0.1 psia (5 torr), then close the Vacuum Valve.

4. Wait at least 10 minutes for potentially trapped gas to escape from the waste container confinement boundaries (e.g., bags and/or liners).

5. Open the Purge Valve and backfill the CCV cavity with 1 atm helium gas.

6. Wait at least 10 minutes for the helium fill gas to penetrate the waste container confinement boundaries.

7. Open the Vacuum Valve and monitor the pressure reading on the Pressure Gauge until it falls below 0.1 psia (5 torr), then close the Vacuum Valve.

8. Monitor the Pressure Gauge reading for at least 15 minutes to ensure that there is no detectable increase in the pressure reading.

9. If an increase in the pressure reading is detected, repeat Steps 5 through 8.

10. Open the Purge Valve and backfill the CCV cavity with 1 atm Helium.

11. Disconnect the inerting apparatus from the CCV lid quick connect fitting .

• NAC International 7.5-3

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A Pressure Vacuum Relief Valve Valve To Vacuum Pump Purge Valve CCV Port CCV He Supply Figure 75 Pre-Shipment Inerting Apparatus Schematic NAC International 7.5-4

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Chapter 8 Acceptance Tests and Maintenance Program Table of Contents 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM ...................................... 8-1 8.1 Acceptance Tests .......................................................................................................... 8.1-1 8.1.l Visual Inspections and Measurements .............................................................. 8.1-1 8.1.2 Weld Examinations ........................................................................................... 8.1-1 8.1.3 Structural and Pressure Tests ............................................................................ 8.1-1 8.1.4 Leakage Rate Tests ........................................................................................... 8.1-2 8.1.5 Component and Material Tests ......................................................................... 8.1-2 8.1.6 Shielding Tests .................................................................................................. 8.1-4 8.1.7 Thermal Tests .................................................................................................... 8.1-4 8.1.8 Miscellaneous Tests .......................................................................................... 8.1-4 8.2 Maintenance Program ................................................................................................... 8.2-1 8.2.1 Structural and Pressure Tests ............................................................................ 8.2-1 8.2.2 Leakage Rate Tests ........................................................................................... 8.2-1 8.2.3 Component and Material Tests ......................................................................... 8.2-3

• 8.3 8.2.4 Thermal Test ..................................................................................................... 8.2-6 8.2.5 Miscellaneous Tests .......................................................................................... 8.2-6 Appendix ....................................................................................................................... 8.3-1 8.3.1 References ......................................................................................................... 8.3-1
• NAC International 8-i

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A List of Figures TBD List of Tables Table 8.1 Foam Static Crush Strength Acceptance Criteria.............................................. 8.1-5 Table 8.2 Summary of Packaging Maintenance Requirements ........................................ 8.2-8 NAC International 8-ii

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM This chapter presents the acceptance tests and maintenance program for the OPTIMUS-L packaging. These activities assure that the packaging meets the requirements of 10 <;:FR 71, Subpart G .

• NAC International 8-1

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OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 8.1 Acceptance Tests This section describes the tests to be performed before the first use of each packaging. The acceptance tests confirm that each packaging is fabricated in accordance with the general arrangement drawings in the Certificate of Compliance. 8.1.1 Visual Inspections and Measurements Packaging components shall receive visual and mechanical inspections to verify the packaging has been fabricated and assembled in accordance with the general arrangement drawings in Section 1.3.3. The dimensions, tolerances, and surface finishes shown on the drawings shall be verified by measurement on each packaging. Nonconforming components shall be reworked or replaced. 8.1.2 Weld Examinations All packaging welds shall be examined to the requirements of the general arrangement drawings in Section 1.3.3. Nonconforming components shall be reworked or rejected. 8.1.3 Structural and Pressure Tests 8.1.3.1 Lifting Attachment Load Test The package, including the pallet and tiedowns, is designed to be lifted by the three lift lugs located at the top end of the Outer Packaging (OP) lid using a 3-legged bridle with slings oriented in line with the axis of the OP lifting lugs (i.e., approximately 70° from horizontal). The maximum service load for the OP lifting lugs is a vertical load of 10,000 pounds (44.5 kN), or 3,333 pounds (14.8 kN) per lifting lug. Prior to the initial use of the OP lid assembly, the OP lid lifting lugs shall be subjected to a vertical test load equal to 300% of the maximum service load, or 30,000 pounds (133.4 kN), or 10,000 pounds (44.5 kN) per lifting lug. The test load shall be sustained for a period of 10 minutes or more. Following the load test, the critical areas of the OP lid (e.g., around the lifting lug hole, at the bend, and at the welded connection to the outer shell) shall be visually examined for indications of plastic deformation and/or cracking and examined for surface discontinuities by means of liquid penetrant (PT) examination in accordance with the methods of ASME Code, Section V, Articles 1 and 6. [8.6]. Acceptance for the PT examined welds shall in accordance with NF-5350 [8.4]. Indications of distortion and/or cracking shall be recorded on a nonconformance report and dispositioned prior to final acceptance in accordance with the cognizant quality assurance program . NAC International 8.1-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 8.1.3.2 Hydrostatic Pressure Testing of the Containment Boundary In accordance with the requirements of §71.85(b), each Cask Containment Vessel (CCV) assembly shall be pressure tested to 150% of the packaging MNOP to verify the capability of the containment system to maintain its structural integrity at the test pressure. The MNOP of the CCV assembly is 100 psi (690 kPa) gauge. Therefore, each CCV assembly shall be pressure tested at 150 psi (1,034 kPa) gauge. In accordance with the requirements ofNB-6223 [8.1], the test pressure will be maintained for a minimum of 10 minutes prior to initiation of the examination for leakage. Following the application of the test pressure, the CCV assembly shall be visually examined for leakage in accordance with NB-6224 [8.1]. In addition, the welded connections of the CCV assembly shall be examined for cracking and/or distortion using visual and liquid penetrant (PT) methods in accordance with NB-5000 [8.1]. The acceptance criteria for the pressure test are no unacceptable leakage or distortion of the containment boundary. A nonconforming CCV assembly shall be reworked or rejected. 8.1.4 Leakage Rate Tests The CCV assembly (i.e., the packaging containment boundary) shall be leakage rate tested in accordance with Section 8 of ANSI N14.5 [8.5] to an acceptance criterion of 1x10-7 ref-cm 3/s. Leakage rate testing shall be performed using the Evacuated Envelope-Gas Detector method of ANSI N14.5, Section A.5.4, with helium as the tracer gas and a suitable helium leak detector with a sensitivity of at least 5 x 1o-s ref-cm 3/ s. Calibrated standard leaks shall have current calibration traceable to NIST. A CCV assembly that does not meet the acceptance criteria shall be reworked, replaced, or repaired, as required, and retested prior to acceptance. Separate acceptance leakage rate tests may be performed for the CCV body assembly, CCV lid assembly, and/or vent port plug assembly containment boundaries using test heads or manifolds, as appropriate. Furthermore, the acceptance leakage rate test of the packaging containment system may be performed using temporary seals, which must be replaced prior to final acceptance. All containment O-rings that are not used for the acceptance leakage rate test shall be subjected to the maintenance leakage rate testing described in Section 8.2.2.1 prior to their initial use. 8.1.5 Component and Material Tests 8.1.5.1 Elastomeric O-ring Seals Containment O-rings will be made from the Fluorocarbon-Viton compound specified on the General Arrangement Drawings that has been qualified based on testing to verify material NAC International 8.1-2

NAG PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A composition, physical properties (hardness, tensile strength, elongation, and specific gravity), low-temperature properties, and compression set at high temperature. In addition, each O-ring will be subjected to dimensional acceptance testing. 8.1.5.2 Impact Limiter Foam Each batch of closed-cell polyurethane foam used to construct the foam segments of the OP base and lid assemblies shall be tested for the following attributes. Foam not meeting the acceptance criteria shall be rejected. Leachable Chlorides Each foam formulation of closed-cell polyurethane foam used to construct the foam segments of the OP base and lid assemblies shall be tested to assure that it has no more than 1 ppm of leachable chlorides. Average Density The density of each pour from each batch of foam shall be tested at room temperature (i.e., 75°F

 +/- 10°F) in accordance with ASTM D 1622 [8.2]. The average apparent foam density from each

• pour, determined based on a minimum of three samples, shall be withi foam.

Static Crush Strength The static compressive strength of each pour from each batch of foam shall be tested in both the parallel-to-rise and perpendicular-to-rise directions at room temperature (i.e., 75°F +/- 10°F) in accordance with ASTM D1621 [8.3]. A minimum of three samples from each pour from each batch shall be tested for each orientation to determine the compressive stress at strains of 20%, 40%, and 60%. The average foam compressive stress results of the foam in each foam core shall meet the acceptance criteria in Table 8.1-1. Flame Retardancy Each batch of foam used to construct the foam segments of the OP base and lid assemblies shall be tested to assess the relative burning characteristics of the foam material under controlled laboratory conditions in accordance with the foam manufacturer's test procedures, which generally comply with the requirements for the Federal Aviation Regulation (FAR) 25.853 flame test. A minimum of three test samples from each batch of foam shall be tested. Each test sample shall have a thickness of 0.5-inch, a width of 3.0-inch, and a length (height) of 12 inches. A typical test applies a burner flame with a minimum temperature of 1550°F to the center of the

• lower edge of the foam specimen for at least 60 seconds. Following removal of the flame from NAC International 8.1-3

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A the specimen, the elapsed time for the foam specimen to extinguish, the elapsed time for all drips 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. lntumescence 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 manufacturer's 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% f o r - foam and 10% f o - foam. 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 International 8.1-4

NAC PROPRIETARY INFORMATION REMOVED OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 8.1 Foam Static Crush Strength Acceptance Criteria

• NAC International 8.1-5

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OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A 8.2 Maintenance Program The maintenance program includes periodic inspections, tests, and maintenance activities designed to ensure continued performance of the packaging. This section describes the periodic testing, inspection, and replacement schedules, as well as the criteria for replacement and repair of components and subsystems on an as-needed basis. The maintenance requirements are summarized in Table 8.2-1. 8.2.1 Structural and Pressure Tests The packaging does not require any routine structural or pressure tests. This includes the replacement of CCV closure bolts or threaded inserts which are exempted from the pressure test per NB-6111 [8.1]. The replacement requirements for threaded fasteners or inserts are presented in Section 8.2.3. 8.2.2 Leakage Rate Tests 8.2.2.1 Periodic and Maintenance Leakage Rate Testing Periodic leakage rate testing is performed in accordance with Section 7.5 of ANSI Nl4.5 [8.5] to

• confirm that the containment capabilities of the CCV assembly have not deteriorated over an extended period of use. A periodic leakage rate test is required to be performed on every containment seal of the packaging within the 12-month period prior to every shipment but need not be performed for packages that are out-of-service (e.g., placed into temporary storage). As discussed in Section 8.2.3.1, all packaging O-rings and fastener seals are required to be replaced within the 12-month period prior to any shipment and, therefore, the maintenance leakage rate testing of the replaced containment seals also satisfies the requirement for periodic leakage rate testing.

Maintenance leakage rate testing of all packaging containment seals is performed in accordance with Section 7.4 of ANSI N14.5 [8.5] prior to returning the package to service following maintenance, repair, or replacement of any components of the containment system to confirm that the CCV assembly is not degraded. As discussed in Sections 8.2.3.1 and 8.2.3.2, maintenance leakage rate testing is required after replacement of any packaging containment system O-ring or fastener seal and after repair of any containment sealing surface. Maintenance leakage rate testing need only be performed on the affected seal or sealing surface of the containment system. Leak-tight acceptance criteria of lxI0*7 ref-cm 3/s shall be used for the periodic and maintenance leakage rate tests. Periodic and maintenance leakage rate testing shall be performed using the

• Evacuated Envelope-Gas Detector method of ANSI Nl4.5, Section A.5.4, with helium as the NAC International 8.2-1

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A tracer gas and a suitable helium leak detector with a sensitivity of at least 5 x 1o- 8 ref-cm 3/s. Calibrated standard leaks shall have current calibration traceable to NIST. A CCV assembly that does not satisfy the periodic and maintenance leakage rate test acceptance criteria shall be reworked, replaced, or repaired, as required, and retested prior to returning the packaging to service. Periodic and maintenance leakage rate test results and any associated rework, replacement, or repairs shall be documented in a packaging maintenance log. 8.2.2.2 Pre-shipment Leakage Rate Testing Pre-shipment leakage rate testing of the CCV lid containment seal and the CCV vent port containment seal 1 of the loaded packaging is required before each shipment of a loaded package to verify that the containment system is properly assembled for shipment. The components that require pre-shipment leakage rate tests include the CCV lid and vent port plug containment O-ring seals. If a containment seal requires replacement during loading operations, maintenance leakage rate testing of the closure with a new containment seal is required prior to shipment in accordance with the requirements of Section 8.2.2.1. In this case, the maintenance leakage rate test of the closure with the new containment seal satisfies the requirement for pre-shipment leakage rate testing. Pre-shipment leakage rate tests shall be performed using the Gas Pressure Drop or Gas Pressure

• Rise methods described in Sections A.5.1 and A.5.2 of ANSI N14.5. The acceptance criterion for the pre-shipment leakage rate test is no detectable leakage when tested to a sensitivity of lx10-3 ref-cm 3/s. The pressure gauge used to perform the pre-shipment leakage rate test shall have an NIST traceable calibration and be accurate to within 1% or less of its full scale.

The procedure for the pre-shipment leakage rate test shall be qualified based on the guidance provided in Article 1, T-150(d) of the ASME Code, Section V, Subsection A [8.6] using a calibrated leak standard for the T-150(d)(2) test specimen to demonstrate that it will reliably produce a test sensitivity of lx10*3 ref-cm3/s or better. Alternatively, a leakage rate tes! procedure that relies upon detection of a system calibrated leak standard in each performance of the test does not require a separate procedure qualification, as it is inherently qualified each time it is performed. Any containment seal that does not satisfy the pre-shipment leakage rate test acceptance criteria shall be inspected, cleaned (if needed), reassembled, and retested prior to shipment. Any containment seal that does not satisfy the pre-shipment leakage rate test acceptance criteria after repeated attempts, may require replacement of the O-ring seal or fastener seal or repair of the Pre-shipment leakage rate testing of the CCV vent port containment seal is required before every Type B shipment, even if the CCV vent port cover was not removed during the loading process. NAC International 8.2-2

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A sealing surface. As discussed in Sections 8.2.3.1 and 8.2.3.2, a maintenance leakage rate test is required for all new/replaced containment O-ring and fastener seals and any repaired sealing surfaces for containment O-rings and fastener seals. Replacement of non-containment O-rings (i.e., test O-rings and the vent/drain port cap O-rings) and repair of sealing surfaces for non-containment O-rings does not require a maintenance leakage rate test. 8.2.3 Component and Material Tests The following sections describe the periodic tests and replacement schedules for packaging components used to ensure continued performance of the packaging. Additional maintenance may be required on an as-needed basis when wear or damage is noted during routine operations. When as-needed maintenance is performed, the associated repair, replacement, and record keeping activities shall follow the maintenance program requirements for the corresponding periodic maintenance activity. 8.2.3.1 O-ring Seals Prior to each shipment, all accessible packaging O-ring seals and fastener seals are visually inspected for any damage or defects (e.g., cracks, tears, cuts, or discontinuities) that may prevent them from sealing properly when the package is assembled. If the CCV vent port plug is not removed during the loading operations, the associated O-ring seals are not subjected to visual inspection. However, a pre-shipment leakage rate test is required for the CCV lid and vent port containment O-ring and fastener seals prior to each use to verify the package is properly assembled for shipment, as discussed in Section 8.2.2.2. Damaged or defective O-ring seals shall be replaced with new 0-ring seals that meet the requirements on the general arrangement drawing in Section 1.3.3 and the requirements of Section 8.1.5.1, as applicable. A maintenance leakage rate test is required for any replaced CCV lid or vent port containment O-ring, per Section 8.2.2.1. The CCV lid and vent port test O-rings and the CCV test port O-rings do not provide containment, and therefore, do not require a pre-shipment leakage rate test or maintenance leakage test when replaced. The O-ring seal inspection results and any necessary O-ring seal replacements and required leakage rate tests shall be documented in a packaging maintenance log. All packaging O-ring seals shall be replaced with new O-ring seals that meet the requirements on the general arrangement drawing in Section 1.3.3 and the requirements of Section 8.1.5.1, as applicable, within the 12-month period prior to any shipment. A maintenance leakage rate test is required for all CCV containment O-ring seals that are replaced, per Section 8.2.2.1. Test O-ring seals that are replaced do not require a maintenance leakage rate test, however, they may be used to perform the maintenance leakage rate test of the associated containment O-ring. The CCV test port O ring seals, which only serve as dust/weather seals, do not require any leakage rate testing NAC International 8.2-3

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A when replaced. The periodic replacement of 0-ring or fastener seal and the required leakage rate tests shall be documented in a packaging maintenance log. New 0-ring and fastener seals shall be lightly coated with a lightweight lubricant, such as Parker Super 0-Lube or equivalent, prior to installation to minimize deterioration or cracking of the elastomer during usage and the potential for tearing if removal from the dovetail groove is necessary for inspection. The exposed surfaces of installed 0-ring and fastener seals that do not require replacement shall also be coated with the lightweight lubricant prior to assembling the packaging to minimize deterioration or cracking of the seal during use. Remove excess lubricant from the 0-ring and fastener seals prior to assembling the packaging. 8.2.3.2 Sealing Surfaces Prior to each shipment and during period maintenance (which is required within the 12-month period prior to any shipment) the sealing surfaces for all CCV 0-rings and fastener seals shall be cleaned and visually inspected for wear and/or damage (e.g., scratches, gouges, nicks, cracks, etc.) that may prevent the containment 0-rings and fastener seals from sealing properly. Worn or damaged sealing surfaces may be repaired using emery cloth or other suitable polishing agent to restore the surface finish as required for proper sealing. A maintenance leakage rate test is required for all repaired CCV sealing surfaces for containment 0-rings, per Section 8.2.2.1. Repaired CCV sealing surfaces for non-containment 0-rings (i.e., test 0-rings and the vent/drain port cap 0-rings) do not require a maintenance leakage rate test. The inspection results and any necessary sealing surface repairs and leakage rate tests shall be documented in a packaging maintenance log. 8.2.3.3 Threaded Fasteners Prior to each shipment, all packaging threaded fasteners (e.g., CCV lid bolts, CCV vent port plug bolts, CCV test port plugs, and OP lid bolts) removed during package loading operations shall be visually inspected for excessive wear and/or damage. However, fasteners that are not removed during the unloading and loading operations do not require visual inspection prior to use. In addition, all packaging threaded fasteners, including those not removed during loading or unloading operations, shall be visually inspected for excessive wear and/or damage within the 12-month period prior to any shipment. Fasteners that have minor damage or wear may be refurbished by chasing the threads. Barbs may also be removed, taking care not to cause further thread damage. Minor surface corrosion on fasteners may be removed by polishing with an emery cloth or other fine abrasives. Fasteners that show visible signs of excessive wear or significant corrosion or damage shall be replaced with new fasteners that meet the requirements on the general arrangement drawing in

• Section 1.3 .3. All repaired or replaced threaded fasteners shall be functionally tested prior to use NAC International 8.2-4

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A to verify proper fit-up with the mating component of the packaging. Inspection results and any necessary fastener repairs and replacements shall be documented in a packaging maintenance log. Tapped holes for threaded fasteners do not require visual inspection. However, all fastener holes with threaded inserts shall be visually inspected within the 12-month period prior to any shipment to verify that the threaded inserts are not displaced or damaged. Tapped holes that do not fit-up properly with the mating fastener may be refurbished by chasing the threads or repaired as necessary using threaded inserts per the general arrangement drawing in Section 1.3.3. Displaced threaded inserts shall be re-positioned and secured in the hole or replaced with a new threaded insert, as necessary. Damaged threaded inserts shall be replaced with new threaded inserts that meet the applicable requirements on the general arrangement drawing in Section 1.3 .3. The associated assemblies shall be functionally tested to confirm proper fit and function of the threaded connections. The inspection results and any necessary thread insert repairs and replacements shall be documented in a packaging maintenance log. 8.2.3.4 Exposed Packaging Surfaces

• Prior to each shipment, the exterior of the OP lid and base assembly are visually inspected to verify its physical condition is unimpaired. Superficial defects on the exterior of the packaging, such as marks, scratches, or dents, do not require repair. However, any significant damage to the packaging exterior, such as holes in the OP outer shells, shall be repaired prior to shipment. The inspection results and any necessary repairs to the exterior of the packaging shall be documented in a packaging maintenance log.

All exposed interior and exterior surfaces of the OP base and lid assemblies, CCV body and lid assemblies, CCV vent and test port plugs, and SIA body assembly shall be visually inspected within the 12-month period prior to any shipment for damage or degradation that could impair the physical condition of the packaging. Superficial defects, such as minor surface corrosion, scratches, blemishes, and adhered material/particles, may be removed by polishing the packaging surfaces with emery cloth or other fine abrasives. Significant damage of the exposed surfaces of the packaging shall be repaired to restore the packaging to the applicable requirements on the general arrangement drawing in Section 1.3 .3 or the damaged components may be replaced. Replacement components shall satisfy the applicable requirements on the general arrangement drawing in Section 1.3.3 and the applicable acceptance tests described in Section 8.1. The inspection results and any necessary repairs to the packaging surfaces or replacement of packaging components shall be documented in a packaging maintenance log . NAC International 8.2-5

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Painted surfaces, identification markings, and match marks used for closure orientation shall be visually inspected within the 12-month period prior to any shipment, to ensure that painted surfaces are in good condition, identification markings are legible, and that match marks used for closure orientation remain legible and are easy to identify. Lifting attachments shall be inspected within the 12-month period prior to any shipment to verify that there is no evident permanent deformation and no obvious damage or defects. Damaged or defective lifting attachments shall be repaired or replaced in accordance with the applicable requirements on the general arrangement drawing in Section 1.3.3 and the applicable acceptance tests described in Section 8.1. 8.2.4 Thermal Test No periodic or routine thermal testing are required to be performed on the packaging. 8.2.5 Miscellaneous Tests The following subsections discuss the requirements following replacement of packaging components. These requirements apply to newly manufactured components (spares) or substituted components from other OPTIMUS-L packagings. For configuration management, the OP body is the host component because it bears the packaging nameplate. Other components may be substituted following these procedures. 8.2.5.1 OP Replacement or Repair If an OP lid or body must be replaced, the replacement OP lid or body shall be assembled with the mating OP body or lid, as applicable, to assure proper fit-up of the OP components. The replacement shall be noted in the packaging's maintenance log along with the test and inspection results. If an entire OP assembly must be replaced, the replacement shall be noted in the packaging's maintenance log. The replacement OP assembly must either be a unit currently in service, or another unit manufactured or refurbished to the requirements shown in the general arrangement drawings in Section 1.3.2. 8.2.5.2

• CCV Assembly Replacement or Repair If a CCV body, lid, or port cover must be replaced, the replaced CCV component shall be assembled with the mating CCV component to assure proper fit-up. A maintenance leakage rate test of the containment O-ring seal affected by the replacement shall be performed in accordance with Section 8.2.2.1. The replacement shall be noted in the packaging's maintenance log along with the test and inspection results.

If an entire CCV assembly must be replaced, the replacement shall be noted in the packaging's maintenance log. The replacement CCV assembly must either be a unit currently in service, or NAC International 8.2-6

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A another unit manufactured or refurbished to the requirements shown in the general arrangement drawings in Section 1.3.2 .

• NAC International 8.2-7

OPTIMUS-L Package SAR August 2020 Docket No. 71-9390 Revision 20A Table 8.2 Summary of Packaging Maintenance Requirements Inspection/Test/Mai ntena ncel 1J Reference Item SARP Each Replace/ Annual Section Repair1 2l Use CCV containment 0-rings (lid & port) 8.2.3.1 V,LTI LT2 R,LT2 CCV leak test 0-rings (lid & port) 8.2.3.1 V R CCV containment 0-ring sealing surfaces 8.2.3.2 V LT2 V CCV leak test 0-ring sealing surfaces 8.2.3.2 V V CCV lid bolts 8.2.3.3 V F V CCV port cover 8.2.3.3 V F V OP lid bolts 8.2.3.3 V F V Threaded inserts 8.2.3.3 F V Tapped holesC 3) 8.2.3.3 F Exposed packaging exterior surfaces Exposed interior and exterior surfaces Notes: 8.2.3.4 8.2.3.4 V V V

1. R = Replace, V = Visual Inspection, F = Functional Test, LTI = Pre-shipment leak test (Section 7.4.2),

LT2 = maintenance/periodic leak test (Section 8.2.2.1).

2. Tests or inspections necessary when items are replaced or repaired.

3. Tapped holes without threaded inserts: OP bolt holes, CCV vent and test ports.

NAC International 8.2-8

OPTIMUS-L Package SAR August2020 Docket No. 71-9390 Revision 20A 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 .
• NAC International 8.3-1

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