ML21195A284

Daher-TLI, Application for Certificate of Compliance for the Versa-Pac Shipping Package, Revision 12

ML21195A284
Person / Time
Site:	07109342
Issue date:	02/28/2021
From:	Daher-TLI
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML21195A281	List: ML21195A282 ML21195A283 ML21195A284
References
LTR-20000-130-03
Download: ML21195A284 (433)

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DAHER-TLI Fulton, MD Application for Certificate of Compliance for the Versa-Pac Shipping Package NRC Certificate of Compliance USA/9342/AF-96 Docket 71-9342 REVISION 12 FEBRUARY 2021

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Record of Revisions - Revision 12 (February 2021)

General

• SI equivalent units added throughout (not marked by rev bars).

• Pages dated July 2021 in the header are change pages that have been modified since the original February 2021 issue of Revision 12 of the SAR due to RAIs issued by the NRC VP-55-LD

• Updated to Revision 4. Revised Notes 3 & 10 and added notes 15-17. All changes marked by 4 delta notes.

Chapter 1

• §1.1 Reorganized and renumbered tables to match criticality analyses in Chapter 6 and group like contents. Also added content limits for the hydrogen limited contents at enrichments other than 20 wt% and Hydrogen restricted loading table for the VP-55 with the 5-inch pipe (Table 1-4).

• §1.2 Revised content descriptions to point to Section 1.1, instead of Table 1-1 specifically and added explicit mentions of neutron absorbers in contents and sample tubes for shipping UF6 in quantities less than 0.1 kg.

• §1.4 Changed VP-55-LD to Revision 4. Updated cross-references in Section 1.4.6.

Chapter 2

• Complete consolidation and restructuring of chapter, but no technical changes made. Results of structural testing attachments summarized in chapter and provided as references, available upon request.

• §2.6.1.1 Summary of temperatures and pressures section clarified to state package cavity pressure rating remove wording stating that the package is not a sealed system.

Chapter 3

• §3.1.3 Summary tables added for comparisons between the temperatures for each of the three configurations analyzed (i.e., base, 1S/2S, no IG foam block).

• §3.1.4, §3.3.2, and §3.4.4 Pressure summary sections clarified to state package cavity pressure rating and maximum calculated pressures, and remove wording stating that the package is not a sealed system.

• Appendices: Appendix 3.5.3 to support the change to the Licensing Drawing allowing for the optional use of parts IG, GC, GE, and BF. Also moved all removed appendices, including Champion package fire testing report, to references.

Chapter 4

• Added reference to containment boundary figure in Figure 1-1 and welding/inspection standards in Section 1.4.2

• Clarified statements regarding permeation through the package seals. SAR no longer states that the package is not a sealed system, but refers to the high gas permeation rate through silicone seals.

• Moved statement regarding external radiation levels due to NCT tests to Chapter 5 i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 Record of Revisions - Revision 12 (February 2021)

Chapter 5

• Added statement previously in Chapter 4 regarding external radiation levels due to NCT tests Chapter 6

• Complete consolidation and re-write of chapter. Analyses in appendices moved up into body of chapter. (No change bars for re-write)

• The standard configuration analysis is redone to remove the SCALE 4.4 results for the 100 wt%

enrichment and to match the packaging models with the rest of the analyses.

• The Hydrogen Limited Contents analysis is expanded to cover 5 wt%, 10 wt%, and 100 wt%

enrichments (previously only 20 wt%).

• A new analysis was added for the 5-inch pipe with hydrogen limited contents at 10 wt% and 20 wt% enrichments.

• The benchmarking evaluation replaced with a single analysis that develops individual USL equations for each enrichment band (previously a single USL applied globally).

Chapter 7

• Added clarifications to section 7.1.2 regarding hydrogen limited contents and optional use of Versa-Pac parts

• Updated reference to DAHER-TLI QAPD to Revision 3 Chapter 8

• Revisions are clarifications or editorial in nature

• Updated reference to DAHER-TLI QAPD to Revision 3 ii

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 LIST OF EFFECTIVE PAGES Page Revision Page Revision Front Matter Chapter 4 All 12 All 12 Chapter 1 Chapter 5 1-i to 1-4 12 All 12 1-5 10 1-6 to 1-7 12 1-8 to 1-9 10 Chapter 6 1-10 12 All 12 1-11 10 1-12 to 1-13 12 1-14 to 1-20 10 Chapter 7 1-21 to 1-22 12 All 12 1-23 10 Chapter 8 Chapter 2 All 12 All 12 Chapter 3 3-i to 3-iii 12 3-1 to 3-2 12 3-3 10 3-4 to 3-5 12 3-6 to 3-8 10 3-9 to 3-12 12 3-13 10 3-14 to 3-56 12 3-57 10 3-59 to 3-62 12 iii

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 1 GENERAL INFORMATION ................................................................................ 1-1 2 STRUCTURAL EVALUATION ........................................................................... 2-1 3 THERMAL EVALUATION .................................................................................. 3-1 4 CONTAINMENT ................................................................................................. 4-1 5 SHIELDING EVALUATION ................................................................................ 5-1 6 CRITICALITY EVALUATION ............................................................................. 6-1 7 PACKAGE OPERATIONS ................................................................................. 7-1 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM .............................. 8-1 iv

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 1 GENERAL INFORMATION ................................................................................................................................ 1 1.1 Introduction ............................................................................................................................................ 1 1.2 Package Description............................................................................................................................... 4 1.2.1 Packaging..........................................................................................................................................................4 1.2.2 Contents ............................................................................................................................................................6 1.2.3 Special Requirements for Plutonium ...................................................................................................7 1.2.4 Operational Features ...................................................................................................................................7 1.3 References ............................................................................................................................................. 9 1.4 Appendices ......................................................................................................................................... 10 1.4.1 Versa-Pac Shipping Package Licensing Drawings ....................................................................... 11 1.4.2 General Notes .............................................................................................................................................. 16 1.4.3 UF-1 Polyurethane Closed Cell Foam Specification .................................................................... 18 1.4.4 Ceramic Fiber Insulation Specification............................................................................................. 19 1.4.5 Structural Fiberglass Component Specification ........................................................................... 20 1.4.6 Versa Pac VP-55 5-inch Pipe ................................................................................................................. 21 1.4.7 VP-55 5-inch Pipe Licensing Drawings ............................................................................................ 22 TABLES TABLE 1-1: U-235 LOADING TABLE FOR VP-55 AND VP-110 STANDARD CONFIGURATION ............................................................. 1 TABLE 1-2: HYDROGEN-LIMITED U-235 LOADING TABLE FOR MODEL NOS. VP-55 AND VP-110 .................................................. 1 TABLE 1-3: U-235 LOADING TABLE FOR THE VP-55 WITH 5-INCH PIPE ............................................................................................... 2 TABLE 1-4: HYDROGEN LIMITED LOADING TABLE FOR THE VP-55 WITH 5-INCH PIPE........................................................................ 2 TABLE 1-5: 1S/2S CYLINDER LIMITS FOR THE VP-55 (UP TO 20-WT.% U-235)................................................................................ 2 TABLE 1-6: 1S/2S CYLINDER LIMITS FOR THE VP-55 WITH 5-INCH PIPE (UP TO 100-WT.% U-235) ........................................... 3 TABLE 1-7: POLYURETHANE CLOSED CELL FOAM COMPONENT REQUIREMENTS ................................................................................ 18 TABLE 1-8: CERAMIC FIBER INSULATION REQUIREMENTS....................................................................................................................... 19 FIGURES FIGURE 1-1: VERSA-PAC COMPONENT ILLUSTRATION ................................................................................................................................. 8 1-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 1 GENERAL INFORMATION 1.1 Introduction The Versa-Pac is a drum type package that features a patented [1] design concept in combination with the familiar drum exterior packaging to provide enhanced structural protection to payloads during the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) [2]. Principal design of the Versa-Pac packaging maintains the use of an inner container positioned inside a 55-gallon (VP-55) or 110-gallon drum (VP-110). The Versa-Pac is used directly or in conjunction with pails, pipe containers, poly bottles, and a variety of smaller containers, inserts and vessels. The payload containment area of the 55-gallon version (VP-55) has an inside diameter of 15 inches (38.1 cm) and is 25-7/8 inches (65.72 cm) in length. The 110-gallon version (VP-110) has an inside diameter of 21 inches (53.34 cm) and is 29-3/4 inches (75.57 cm) in length. The package has two distinct areas of insulation for thermal and impact protection.

The Versa-Pac standard configuration shipping packages, model numbers VP-55 and VP-110, have been designed to transport Type A fissile materials limited to U-235 masses based on the loading limits in Table 1-1. The Criticality Safety Index (CSI) for the VP-55 and VP-110 in its standard configuration is 1.0.

Table 1-1: U-235 Loading Table for VP-55 and VP-110 Standard Configuration U-235 Mass Limit Enrichment U-(g) 235 (wt.%)

Ground/Vessel Air

£ 100 360 350

£ 20 445 410

£ 10 505 470

£5 610 580

£ 1.25 1650 --

For contents limited to 1 lb. (454 g) of hydrogenous packaging materials, the quantity of fissile material per package is limited to the U-235 masses listed in Table 1-2. Uranium compounds containing any hydrogen (e.g. hydrates or hydrides) are not permissible for contents limited by Table 1-2.

Table 1-2: Hydrogen-Limited U-235 Loading Table for Model Nos. VP-55 and VP-110 U-235 Mass Limit Enrichment U-235 (g)

(wt.%)

CSI=0.7 CSI=1.0 100 515 -

£ 20 605 635 10 685 -

5 800 -

1-1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 An additional Versa-Pac packaging configuration features a 5-inch steel inner container to facilitate the transport of greater quantities of U-235 and is fully described in Appendix 1.4.6. The VP-55 with 5-inch pipe configuration is designed to transport Type A fissile materials limited to U-235 masses based on the loading limits in Table 1-3, with all fissile contents loaded into a single 5-inch pipe. The CSI for the VP-55 with 5-inch pipe configuration is 0.7 for material up to 10-wt.%,

and 1.0 for material greater than 10-wt.% up to 100-wt.%.

Table 1-3: U-235 Loading Table for the VP-55 with 5-inch Pipe U-235 Mass Limit Enrichment U-(g) 235 (wt.%)

Ground/Vessel Air

£ 100 695 395

£ 20 1215 495

£ 10 Full Pipe 590

£5 Full Pipe 790 When utilizing the 5-inch pipe component with contents limited to 1.25 lb. (567 g) of hydrogenous packaging materials per pipe, the quantity of fissile material per package is limited only by the volume of the 5-inch pipe(s). The number of pipes per container and CSI of each content is listed in Table 1-4, below. Uranium compounds containing any hydrogen (e.g. hydrates or hydrides) are not permissible for contents limited by Table 1-4.

Table 1-4: Hydrogen Limited Loading Table for the VP-55 with 5-inch Pipe Enrichment U-235 Number of CSI (wt.%) Pipes 20% 1 CSI = 1.0 For all Uranium compounds CSI = 1.0 for Uranium Oxides 10% 2 CSI = 1.4 for all other Uranium compounds An added content for the VP-55 is ANSI N14.1 [2] compliant 1S and 2S cylinders filled with uranium hexafluoride (UF6). The VP-55 can ship 1S or 2S UF6 cylinders based on the 20-wt.%

U-235 limits provided in Table 1-5. Each shipment of this content type may only contain either 1S cylinders or 2S cylinders. Quantities of cylinders greater than the limits stated in Table 1-5, or combinations of 1S and 2S cylinders in a single package (e.g. one 1S cylinder and two 2S cylinders), are permissible if the total U-235 quantity meets the fissile limits, for the maximum enrichment, established in Table 1-1. The air transport U-235 mass limits in Table 1-5 are the lesser of the 1S/2S cylinder limits and the air transport limits determined in Section 6.7. For 1S/2S cylinder contents limited by Table 1-5, the CSI is 1.0.

Table 1-5: 1S/2S Cylinder Limits for the VP-55 (up to 20-wt.% U-235)

Maximum Mass UF6 per U-235 Mass Limit Air U-235 Mass Enrichment U-235 Content Cylinders per VP-55 per VP-55 Limit (wt.%)

VP-55 (lb/g) (g) (g) 1S Cylinder 7 7.0 / 3,175 £ 20 429.8 429.8 2S Cylinder 2 9.8 / 4,445 £ 20 600.8 495 1-2

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 Also, ANSI N14.1 compliant 1S and 2S cylinders filled with uranium hexafluoride (UF6) with U-235 enrichments up to 100-wt.% can be shipped in the VP-55 with 5-inch pipe configuration based on the limits provided in Table 1-6. For this configuration, each 1S or 2S cylinder is loaded into a 5-inch pipe and the 5-inch pipes are loaded into the VP-55 prior to shipment. Each shipment of this content type may only contain either 1S cylinders or 2S cylinders. Quantities of cylinders greater than the limits stated in Table 1-6, or combinations of 1S and 2S cylinders in a single package (e.g. one 1S cylinder and two 2S cylinders), are permissible if the total U-235 quantity meets the fissile limit, for the maximum enrichment, established in Table 1-1. The air transport U-235 mass limits in Table 1-6 are the lesser of the 1S/2S cylinder limits and the air transport limits determined in Section 6.7. For 1S/2S cylinder contents limited by Table 1-6, the CSI is 1.0.

Table 1-6: 1S/2S Cylinder Limits for the VP-55 with 5-inch Pipe (up to 100-wt.% U-235)

Maximum Mass UF6 per U-235 Mass Air U-235 Mass Cylinders Enrichment U-235 Content VP-55 Limit per VP-55 Limit per VP-55 (wt.%)

(lb/g) (g) (g)

(in 5-inch Pipe(s))

1S Cylinder 1a 1.0 / 454 £ 100 306 306 2S Cylinder 1 4.9 / 2,223 £ 100 1497 395 a

Notes: Limited to one cylinder based on fit inside of the VP-55 cavity with the required 2-inch thick foam liner.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 1.2 Package Description 1.2.1 Packaging Engineering Drawings are provided in Appendix 1.4.1. General notes pertaining to fabrication are provided in Appendix 1.4.2. An illustration of the packaging configuration is provided in Figure 1-1. Packaging markings are shown on the drawings in Appendix 1.4.1.

The exterior skin of the Versa-Pac consists of, at a minimum, a UN1A2/Y425/S for the VP-55.

The drums use a bolted closure ring, standard carbon steel lugs, 5/8 (1.59 cm) diameter, ASTM (American Society for Testing Materials) A429 bolts and nuts, and a closed-cell rubber lid gasket.

The overall outer dimensions of the 55-gallon drum are 23-3/16 (58.9 cm) OD x 34-3/4 (88.27 cm) in height to the top of the outer drum bolt ring. The drum cover is reinforced by a 10-gauge thick 22-3/8 (56.83 cm) OD x 18-3/8 (46.69 cm) ID plate, and four 1/2 (1.27 cm) bolts are provided to lend additional strength to the drum closure ring.

The VP-110 utilizes at a minimum a UN1A2/Y409/S. The drums use a bolted closure ring, standard carbon steel lugs, 5/8 (1.59 cm) diameter ASTM A429 bolts and nuts, and a closed-cell lid rubber gasket. The overall outer dimensions for the 110-gallon drum are 30-7/16 (77.31 cm)

OD x 42-3/4 (108.59 cm) in height to the top of the outer drum bolt ring. The drum cover is reinforced by a 10-gauge thick 29-3/4 (75.565 cm) OD x 27-1/4 (68.22 cm) ID plate and eight 1/2 (1.27 cm) bolts are provided to lend additional strength to the drum closure ring.

Both drums are further strengthened with vertical stiffeners fabricated from 1-1/4 (3.175 cm) carbon steel square tubing, two inner liners of rolled 16-gauge carbon steel insulated by ceramic fiber blanket (which encase the vertical tubing), and a 1/4 (0.64 cm) carbon steel reinforcing plate on the bottom.

The packages inner container is completely insulated with the appropriate layers of ceramic fiber blanket around the containment area with rigid polyurethane foam disk on the top and on the bottom to complete the insulation of the package. Specifications for the insulation are provided in Appendices 1.4.3 for the polyurethane foam and 1.4.4 for the ceramic fiber blanket. The primary function of both insulations is to provide thermal protection. Although the rigid polyurethane provides some impact protection, the frame of the packaging performs the majority of the required impact protection.

A 1/2 (1.27 cm) thick fiberglass ring is used as a thermal break at the payload cavity flange. The thermal break is sandwiched between the steel components, with twelve 1/2-inch (1.27 cm) bolts providing the connection between the structural members through the fiberglass. This break effectively limits the flow of heat to the payload cavity through the steel flange components. There are no moving parts to the thermal break, and its functionality is maintained as long as it separates the steel components FB, top stiffening ring, from FK, connection ring (See Drawings in Appendix 1.4.1). A specification for the fiberglass material is provided in Appendix 1.4.5.

The containment boundary of the package is defined as the payload vessel with its associated welds, payload vessel high temperature heat resistant silicone coated fiberglass gasket, payload vessel blind flanges, and reinforcing ring.

The payload vessel is comprised of a 10-gauge carbon steel sheet for the body and bottom. The upper end of the vessel is fitted with a 1/4 (0.64 cm) inner carbon steel flange ring with a 1/2 (1.27 cm) thick carbon steel blind flange. The vessel has three circumferential welds (two at the flange, one at the base) and one longitudinal weld. A 1/8 (0.32 cm) high temperature heat resistant silicone coated fiberglass gasket is used between the steel flange ring and blind flange. The 1-4

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 payload vessel blind flange is secured with twelve 1/2 (1.27 cm) bolts. There are no penetrations, valves or venting devices used within the containment boundary. The Versa-Pac meets the General Requirements for all packages, as specified in 10 CFR 71.43 [3].

Gross Weights The gross weights of the two Versa-Pac models are 750 pounds (340.2 kg) for the VP-55 and 965 pounds (437.7 kg) for the VP-110, see Section 2.1.3.

Materials of Construction The materials of construction of the Versa-Pac are provided in the Licensing Drawings parts list presented in Appendix 1.4.1.

Outer and Inner Protrusions There is one outer protrusion on the Versa-Pac consisting of carbon steel fitting which contains a 1 (2.54 cm) plastic plug on the side of the package. The plug is designed to melt and allow venting of any gases that might develop in the event of a fire. The protrusion extends less than 1/2 (1.27 cm) from the sidewall of the outer drum and does not impede the stacking or handling of the shipping package. There are no inner protrusions on the Versa-Pac.

Lifting and Tie-Down Devices The Versa-Pac may be handled by normal industry standards for the safe movement of drums; such equipment might include specifically designed devices, forklifts, pallet jacks or other methods as determined by the User. However, the Versa-Pac does not utilize any specific device or attachment for lifting. Additionally, there are no specific provisions for tie down of the package.

Shielding Neutron and gamma shields are not required for the Versa-Pac payloads.

Pressure Relief Systems There are no pressure relief systems other than the four 1/4 (0.64 cm) holes, closed with vinyl push plugs on the inner liner between the insulation and containment and one in the top cavity area used to vent gases that might be produced in the event of a fire. No special heat transfer mechanisms are provided or required.

Containment Features There are three individual points of closure employed by the Versa-Pac. The payload 1/2 (1.27 cm) inch thick closure plate provides a fastening and seal using twelve 1/2 (1.27 cm) bolts and a 1/8 (0.32 cm) thick silicone coated fiberglass gasket. A second closure is provided at the outer drum lid. The drum lid is secured using 1/2 (1.27 cm) bolts and is sealed with a 3/8 (0.95 cm) thick silicone rubber flat gasket. A standard drum ring, its rubber gasket, and a 5/8 (1.59 cm) tensioning bolt provide the final closure. A 1/8 (0.32 cm) hole is drilled in the end of the tensioning bolt for use with a security seal.

The primary containment boundary of the Versa-Pac is defined as the inner containment body, containment end plate, inner flange ring, silicone coated fiberglass gasket, 1/2(1.27 cm) blind flange, 1/2 (1.27 cm) bolts, washers and insert holders. Figure 1-1 further illustrates these components by text description enclosed within a text box.

Package Markings Package marking are shown in Appendix 1.4.1 and 1.4.2.

1-5

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 1.2.2 Contents All materials must be in solid form with no freestanding liquids; density is not limited. Material quantities may not exceed the fissile limits established in Section 1.1 in any non-pyrophoric form.

Materials that may be shipped in the Versa-Pac include uranium oxides (UyOx), uranium metal (U-metal), uranyl nitrate crystals (UNX), and other uranium compounds (e.g., Uranyl Fluorides and Uranyl Carbonates). The uranium compounds may also contain carbon or graphite (e.g., UC, U2C3 and UC2). UNX may be in the form of uranyl nitrate hexahydrate, trihydrate or dihydrate, and must be in solid form. The payload may be in homogeneous (powder or crystalline) or non-homogeneous form. The fissile contents may include neutron absorbers (e.g. boron, hafnium, erbium, or gadolinia). The contents are limited to Type A, normal form material per 10 CFR 71 [3].

Additionally, the Versa-Pac may be used to transport TRISO fuels and compacts composed of UCO kernels encased within layers of SiC to form TRISO particles. UCO kernels and TRISO particles are of unrestricted size, density, and uranium content per kernel/particle. UCO kernels and TRISO particles may be loose or mixed in a graphite matrix and pressed into various fuel forms (e.g. annular cylinders, planks, right circular cylinders, spheres, etc.).

The Versa-Pac is evaluated assuming optimum moderation using a bounding high-density polyethylene plastic (Density = 0.98 g/cc) and supports packaging applications containing both carbon (e.g., graphite and PTFE) and hydrogen based materials (e.g., water paraffin, and polyethylene). Non-fissile chemical impurities do not increase the reactivity of the system; therefore, they may be present in any quantity. The payload may be enriched in U-235 to 100-wt.% while maintaining the limits in Section 1.1. Because the payload decay heat is essentially zero (approximately 11.4 W, Section 3.4.2), there are no radiolytic decay products.

When using the 5-inch pipe configuration, all fissile contents must be loaded into a single 5-inch pipe or two 5-inch pipes, based on the limits presented in Section 1.1, and sealed per the instructions in Section 7. The fissile quantity for this configuration shall meet the limits in Table 1-3 or 1-4.

Additional contents include uranium hexafluoride (UF6) in ANSI N14.1 compliant 1S and 2S cylinders or in sample tubes, when in quantities less than 0.1 kg. For any shipments of UF6 contents, a foam insert (9 PCF polyethylene) shall be used to provide thermal protection for the cylinder. The minimum foam insert thickness shall be 2 inches, circumferentially between the 1S/2S cylinders and the cavity wall of the Versa-Pac. Cribbing or dunnage may be used inside the foam insert to restrict movement of the contents during transport, providing a snug fit for the 1S/2S cylinders or 5-inch pipe. The fissile quantity of material in any shipment of 1S/2S cylinders must meet one of the following requirements:

1. The number of cylinders in a single package shall meet the limitations in Table 1-5, or Table 1-6 when each cylinder is packaged into a separate 5-inch pipe. For this case, either 1S or 2S cylinders may be loaded into a single package (i.e., no mixing of cylinder types).

2. The total fissile mass (in grams of U-235) from all cylinders shall meet the limits set in Table 1-1. For this case, any number or combination of 1S and 2S cylinders is acceptable, so long as the U-235 mass limit is not exceeded. The U-235 mass limit for this case is established based on the cylinder with the highest enrichment (e.g. for two cylinders with enrichments of 5-wt.% and 15-wt.%, respectively, the U-235 mass limit is based on the 20-wt.% limit).

1-6

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 The payload material may be pre-packaged in hydrogenous or non-hydrogenous containers within the payload vessel. Hydrogenous pre-packaging materials may include polyethylene, polypropylene, and PVC (polyvinyl chloride). PTFE (Polytetrafluoroethylene) or Teflon pre-packaging material is also allowed. Metallic pre-packaging materials such as aluminum, stainless and carbon steel are allowed.

For contents limited to 1 lb. (454 g) of hydrogenous packaging materials, the quantity of fissile material per package is limited to the U-235 masses listed in Table 1-2. For contents limited to 1.25 lb. (567 g) of hydrogenous packaging materials loaded into the 5-inch pipe(s), fissile limits are listed in Table 1-4. Uranium contents shipped under the Table 1-2 or Table 1-4 fissile limits may not include uranium compounds containing any hydrogen (e.g. hydrates or hydrides).

Package contents are typically shipped in an axial array to fill the payload cavity. A fireproof perlite-like packing material is often used as dunnage to fill the voids between the cans and inner vessel wall. The Versa-Pac design allows for the use of two neoprene pads: a 1/8 inch (0.32 cm) bottom pad and a 3/8 inch (0.96 cm) top pad. The pads serve the purpose of protecting the inner containment shell during repeated use. The use of these pads is optional for packages not intended for reuse.

No materials, excluding the minimum steel wall thickness of the package, are credited as neutron absorbers or moderators.

The maximum payload capacity for the VP-55 is 350 pounds (158.8 kg). The maximum payload capacity for the VP-110 is 260 pounds (117.9 kg).

1.2.3 Special Requirements for Plutonium The Versa-Pac is not approved for the transport of Plutonium above minimum detectable quantities.

1.2.4 Operational Features The Versa-Pac provides for two individual closures and seals, with a third closure provided by the drum ring, to secure the payload within the inner containment area. Connections and closures are accomplished using bolt and gasket seals.

There are no operationally complex features of the Versa-Pac. All operational features are readily apparent from an inspection of the drawings provided in Appendix 1.4.1, Packaging General Arrangement Drawings. Operation procedures and instructions for loading, unloading, and preparing an empty Versa-Pac for transport are provided in Chapter 7.0, Operating Procedures.

1-7

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 Figure 1-1: Versa-Pac Component Illustration (Containment boundary components, as indicated in Section 1.2.1.7, are described in text boxes) 1-8 BLIND NUT W/INSERT HOLDER

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 1.3 References IAEA package design regulations, SSR-6, 2012 Ed. [4], has been incorporated by reference into 49 CFR 171.7 [5]. The design requirements for Type A packages are typically the same between the IAEA and NRC 10 CFR 71 [3] regulations, therefore, the package design maintains compliance to both regulatory references. Note the in-text references are specific to NRC regulations.

[1] U.S. Patent and Trademark Office (USPTO), "Patent No. 7,628,287 B1, Reusable Container Having Spaced Protective Housings," 2009.

[2] Nuclear Regulatory Commission (NRC), Title 10, Part 71-Packaging and Transportation of Radioactive Material.

[3] American National Standards Institute, "Uranium Hexafluoride - Packagings for Transport,"

ANSI N14.1-2012, 2012.

[4] International Atomic Energy Agency (IAEA), Regulations for the Safe Transport of Radioactive Material, SSR-6, 2012 Edition.

[5] United States Department of Transportation (USDOT), Title 49, Code of Federal Regulations Part 173, Subpart I - Class 7 (Radioactive) Materials.

[6] The American Society for Nondestructive Testing, Inc., "Recommended Practice No. SNT-TC-1A Personnel Qualification and Certification in Nondestructive Testing," 2006.

[7] The Engineering Tool Box, "Fuels and Chemicals - Auto Ignition Temperatures," [Online].

Available: http://www.engineeringtoolbox.com/fuels-ignition-temperatures-d_171.html.

1-9

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 1.4 Appendices 1.4.1 Versa-Pac Shipping Package Drawings Drawing No. VP-55-LD Rev. 4, VP-110-LD Rev. 3 1.4.2 General Notes 1.4.3 UF-1 Polyurethane Closed Cell Foam Specification 1.4.4 CFI-1 Ceramic Fiber Insulation Specification 1.4.5 Structural Fiberglass Component Specification 1.4.6 VP-55 5-inch Pipe Description 1.4.7 VP-55 5-inch Pipe Licensing Drawing 1-10

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 1.4.1 Versa-Pac Shipping Package Licensing Drawings (4 Sheets) 1-11

a,c 8 7 6 5 4 3 2 1 D D C C B B A A 8 7 6 5 4 3 2 1

a,c 8 7 6 5 4 3 2 1 D D C C B B A A 8 7 6 5 4 3 2 1

a,c 8 7 6 5 4 3 2 1 D D C C B B A A 8 7 6 5 4 3 2 1

a,c 8 7 6 5 4 3 2 1 D D C C B B A A 8 7 6 5 4 3 2 1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 1.4.2 General Notes

1. Paint all carbon steel surfaces with (2 mils.) of industrial primer. The drum exterior surface is to be painted with (2 mils.) of enamel top coat, touchup with spray enamel.

2. Placard as required.

3. Welding procedures and personnel shall be qualified in accordance with AWS D1.1, Structural Welding Code - Steel, and AWS D1.3, Structural Welding Code - Sheet Steel, as applicable.

4. NDT Personnel shall be qualified in accordance with SNT-TC-1A [6]. Visual personnel may be certified in addition or in lieu of SNT-TC-1A as an AWS (American Welding Society) CWI (Certified Welding Inspector) or CAWI (Certified Associate Welding Inspector).

5. Nameplates shall be attached after painting by spot welding and paint retouched.

6. General shop tolerances of +/-1/4 (0.64 cm) apply unless noted. Material tolerances are as required under the appropriate specification.

7. Equivalent components must be approved by engineering and submitted to the NRC for approval.

8. This package shall be manufactured under a Quality Assurance Program that meets the program requirements as outlined in 10CFR71 [3]. Quality Assurance shall perform visual inspections on all final welds and magnetic particle (MT) or liquid penetrant (PT) inspections on all final welds indicated as such in the VP-55 and VP-110 Licensing Drawings, per the requirements of AWS D1.1. Although the Licensing Drawings only specify MT, either MT or PT inspections are acceptable for all relevant welds.

9. The nameplate shall be a minimum of 6 (15.24 cm) x 6 (15.24 cm) x 22 gauge stainless steel, ASTM 300 Series. The letters shall be at least 1/2 (1.27 cm) high as follows and include at a minimum the following information:

Mfg. by:

S/N:

Versa-Pac VP-55 or VP-110 Type AF-96 Tare Wt: ________ LB

________ KG Max. Gross Wt: ________ LB

________ KG

10. Gaskets and Plugs shall be installed using the appropriate material as described on the licensing drawing parts list.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018

11. Ceramic fiber paper/blanket/boards and polyurethane foam products shall be in accordance with the specifications listed in Appendices 1.4.3 through 1.4.5.

12. Certifications, test reports and QA records shall be stored and maintained as required by the DAHER-TLI Quality Assurance Program.

13. Stenciling shall be in contrasting color and be a minimum of 1 (2.54 cm) in height unless noted and shall include at a minimum the following information:

Design ID Number: USA/9342/AF-96 Type A (2 Letters)

Model Number: Versa-Pac VP-(55 or 110)

Owners Name: ----------------------------------------

Owners Address: City, State, and/or Country RQ, Radioactive Material, Type A Package, Fissile Non-Special Form

14. For the minimum UN specification in Part DA, equivalency between X and Y packing groups is based off of the drop heights required for testing in 49CFR178.603(e). Packing group I (X) requires a test drop height of 1.8 meters and packing group II (Y) requires a test drop height of 1.2 meters. Based on the potential energy, the equivalent mass for the higher drop (X) is equal to (1.2/1.8)*425 = 283.3 kg for the VP-55 and (1.2/1.8)*409 =

272.7 kg for the VP-110. The minimum X specification for both of these is rounded up to 350 kg.

(Additional stenciling of the package is at the discretion of the customer. RQ may not be required since it is dependent on the payload contents.)

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 1.4.3 UF-1 Polyurethane Closed Cell Foam Specification This appendix provides the specification for all polyurethane closed cell foam products used in the Versa-Pac packaging. The basic physical property requirements for the polyurethane closed cell foam components of the Versa-Pac are listed in Table 1-7. The urethane foam resins, urethane foam components, and other raw processing materials should be stored at room temperature. The foam is a two-component rigid polyurethane system. The foam may be generated in place or with molds, however the process used shall incorporate proper controls to ensure that there are no abnormalities or voids in the foam blocks. All polyurethane foam components used in the Versa-Pac must have a hydrogen density less than that of water.

Table 1-7: Polyurethane Closed Cell Foam Component Requirements Parameter Requirement 1

Density 5 to 11 PCF (Test - ASTM D-1622)

Compressive Strength 80 to 300 PSI (Test - ASTM D-1621 or ASTM D-695)

Maximum Thermal Conductivity 0.274 BTU-in/hr-ft2-°F (Test - ASTM C-518)

Flame Retardancy Meet the minimum requirements of ASTM E84 Chloride Content Leachable chloride < 200 ppma a

Notes: This value shall be determined through independent laboratory testing.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 1.4.4 Ceramic Fiber Insulation Specification This appendix provides the specification for all ceramic fiber insulation products used in the Versa-Pac packaging. The ceramic fiber insulation components of the Versa-Pac shall be Morgan Thermal Ceramics Kaowool 500, or equivalent for paper products (12 to 14 PCF), and Morgan Thermal Ceramics Cerablanket (6 or 8 PCF), or equivalent for blanket products. Because the ceramic fiber paper and blanket products in the Versa-Pac are only necessary for thermal protection, equivalency is based on the composition, density, and thermal conductivity of the products.

Material -

For a paper or blanket product to be considered equivalent to the specified products, it must be composed of alumina and silica oxides.

Density -

Papers: 12 - 14 PCF Blankets: 6 - 8 PCF Thermal Conductivity -

Table 1-8: Ceramic Fiber Insulation Requirements Temperature Thermal Conductivity

(°F) (BTU-in/hr-ft2-°F) 500 0.47 1000 1.06 1500 1.90 1-19

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 1.4.5 Structural Fiberglass Component Specification This appendix provides the specification for all structural fiberglass insulation products used in the Versa-Pac packaging. The Structural Fiberglass components of the Versa-Pac shall be Strongwell Series 500/525 structural fiberglass, or equivalent. Because the structural fiberglass products in the Versa-Pac are only necessary for thermal protection, equivalency is based on the composition, density, and thermal conductivity of the products.

Material -

For a structural fiberglass product to be considered equivalent to the product specified, the material shall consist of a glass fiber reinforced polyester or vinyl ester resin matrix with glass reinforcements.

Density -

The density of any structural fiberglass component to be considered equivalent shall be in the following range: 0.062 - 0.070 lb/in3.

Thermal Conductivity -

The thermal conductivity of any structural fiberglass component to be considered equivalent shall be 4.0 BTU-in/hr-ft2-°F.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 1.4.6 Versa Pac VP-55 5-inch Pipe 1.4.6.1 VP-55 with 5-inch Pipe Packaging Description The 5-inch pipe container fits inside the VP-55 payload vessel. The payload vessel is described in Section 1.2.1. Licensing Drawings are provided in Section 1.4.1.

The 5-inch pipe container is fabricated from Schedule-40 carbon steel. There is a carbon steel plate welded to the bottom. The top is closed with a 5-inch threaded cap made from malleable iron. The pipe container is typically held in place during routine transport by a birdcage device that provides no structural support. It is considered dunnage. No credit is taken for the pipe maintaining a specific position within the payload cavity under non-routine conditions.

Handling instructions for the VP-55 5-inch Pipe are provided in Section 7.1.1. When utilized in the VP-55, the 5-inch pipe is simply used for geometric confinement of the fissile material in the contents. Although all radioactive material is confined inside the pipe during all transport conditions, the containment boundary of the package is always the inner vessel of the Versa-Pac package. The 5-inch pipe, contents, and any additional dunnage/cribbing are accounted for as the total content weight in the determination of the maximum payload weight for the VP-55 package (see Section 2.1.3).

1.4.6.2 VP-55 with 5-inch Pipe Contents The 5-inch pipe container and any additional dunnage/cribbing are considered contents of the VP-55 package in this configuration. All radioactive contents are loaded directly into the 5-inch pipe when shipping in this configuration. The material requirements for the 5-inch pipe configuration are identical to the standard VP-55 requirements. The fissile material limits for the VP-55 with 5-inch pipe configurations are provided in Table 1-3, Table 1-4, and Table 1-6.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 1.4.7 VP-55 5-inch Pipe Licensing Drawings (1 Sheet) 1-22

a,c 4 3 2 1 D D C C B B A A 4 3 2 1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 2 STRUCTURAL EVALUATION..................................................................................................... 2-1 2.1 Description of Structural Design ................................................................................. 2-1 2.1.1 Discussion ....................................................................................................................................2-1 2.1.2 Design Criteria ...........................................................................................................................2-2 2.1.3 Weights and Centers of Gravity ..........................................................................................2-6 2.1.4 Identification of Codes and Standards for Package Design ....................................2-6 2.2 Materials .............................................................................................................................. 2-7 2.2.1 Mechanical Properties of Materials ..................................................................................2-7 2.2.2 Chemical, Galvanic Reactions and Other Reactions ...................................................2-7 2.2.3 Effects of Radiation on Materials .......................................................................................2-8 2.3 Fabrication and Examination ....................................................................................... 2-9 2.3.1 Fabrication ...................................................................................................................................2-9 2.3.2 Examination ................................................................................................................................2-9 2.4 General Requirements for All Packages.................................................................... 2-9 2.4.1 Minimum Package Size ...........................................................................................................2-9 2.4.2 Tamper-Indicating Feature ..................................................................................................2-9 2.4.3 Positive Closure ...................................................................................................................... 2-10 2.5 Lifting and Tie-down Devices .................................................................................... 2-10 2.5.1 Lifting Devices ......................................................................................................................... 2-10 2.5.2 Tie-down Devices .................................................................................................................. 2-10 2.6 Normal Conditions of Transport (NCT) .................................................................. 2-10 2.6.1 Heat .............................................................................................................................................. 2-11 2.6.2 Cold .............................................................................................................................................. 2-12 2.6.3 Reduced External Pressure ............................................................................................... 2-12 2.6.4 Increased External Pressure ............................................................................................. 2-13 2.6.5 Vibration .................................................................................................................................... 2-13 2.6.6 Water Spray .............................................................................................................................. 2-13 2.6.7 Free Drop................................................................................................................................... 2-13 2.6.8 Corner Drop.............................................................................................................................. 2-13 2.6.9 Compression ............................................................................................................................ 2-14 2.6.10 Penetration ............................................................................................................................... 2-15 2.7 Hypothetical Accident Conditions (HAC) ............................................................... 2-16 2.7.1 Free Drop................................................................................................................................... 2-16 2.7.2 Crush ........................................................................................................................................... 2-22 2.7.3 Puncture..................................................................................................................................... 2-23 2.7.4 Thermal ...................................................................................................................................... 2-24 2.7.5 Immersion - Fissile Material ............................................................................................ 2-25 2.7.6 Immersion - All Packages .................................................................................................. 2-25 2.7.7 Deep Water Immersion Test ............................................................................................. 2-25 2.7.8 Summary of Damage............................................................................................................. 2-25 2.8 Accident Conditions for Fissile Material Packages for Air Transport.......... 2-30 2.9 Special Form .................................................................................................................... 2-30 2.10 Fuel Rods .......................................................................................................................... 2-30 2.11 References ........................................................................................................................ 2-31 2-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 TABLES TABLE 2-1. EVALUATION RESULTS ............................................................................................................................................ 2-3 TABLE 2-2. VERSA-PAC SHIPPING PACKAGE GROSS WEIGHTS ............................................................................................. 2-6 TABLE 2-3. MECHANICAL PROPERTIES OF MATERIALS.......................................................................................................... 2-8 TABLE 2-4. TEST MATRIX.......................................................................................................................................................... 2-11 2-ii

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 2 STRUCTURAL EVALUATION 2.1 Description of Structural Design 2.1.1 Discussion The Versa-Pac is a packaging designed for the shipment of radioactive materials containing less than or equal to the U-235 limits in Table 1-1 and Table 1-2, including uranium oxides (UyOx),

uranium metal (U-metal), uranyl nitrate crystals (UNX), and other uranium compounds (e.g.,

Uranyl Fluorides and Uranyl Carbonates). Tables 1-3 and 1-4 define the content requirements and restrictions for using the 5-inch pipe container. The ANSI N14.1 1S/2S cylinder [14] contents of the package are limited to the quantities specified in Table 1-5 and 1-6. The material may be pre-packaged in plastic, metal or Teflon containers.

The 55-gallon version of the Versa-Pac, the VP-55, consists of a 15 (38.1 cm) inner diameter by 25-7/8 (65.7 cm) inner height (IH) containment area centered within an insulated 55-gallon (200 liter) drum. Drawings of the VP-55 are provided in Appendix 1.4.1. The Versa-Pac design utilizes standard shop dimensions, tolerances, and structural materials as outlined in the drawings in Appendix 1.4.1 and the General Note Sheet found in Appendix 1.4.2. An illustration of the packaging is provided in Figure 1-1.

The overall nominal dimensions of the VP-55 are 23-1/16 (65.7 cm) Outside Diameter (OD) x 34-3/4 (88.3 cm) in height to the top of the outer drum bolt ring. The containment area is protected with a gasketed inner containment lid that is closed with twelve 1/2 (13 mm) bolts. A polyurethane insulation plug is encapsulated in 16-gauge (1.5 mm) carbon steel welded onto the drum lid (see Appendix 1.4.3). The gasketed drum lid is closed with four 1/2 (13 mm) bolts and a standard drum ring. A gasket at the drum lids stiffening ring provides an additional barrier against water in-leakage.

The 55-gallon (200 liter) drum is strengthened with four longitudinal stiffeners fabricated from 1-1/4 (3.2 cm) carbon steel square tubing equally spaced around the circumference of the drum.

A 16-gauge (1.5 mm) outer liner and a 16-gauge (1.5 mm) inner liner provide additional insulated radial stiffness to the drum. The volume between the inner liner and the 10-gauge (3.4 mm) containment body is filled with ceramic fiber insulation (see Appendix 1.4.4).

The VP-55 5-inch (12.7 cm) pipe configuration results in at least double the contents of the VP-55, dependent on uranium-235 enrichment. This configuration includes one or two 5-inch (12.7 cm) pipe container(s) located in the payload cavity that provides criticality control of the fissile contents.

The 5-inch (12.7 cm) pipe container will be secured in the containment for routine transport with a birdcage or basket type constraining device that provides no structural support; it is considered dunnage. The 5-inch pipe container also offers no structural support to the packaging; it is considered part of the contents. No credit is taken for the pipe container maintaining a specific position in the payload cavity under either NCT or HAC for the purposes of criticality control.

The 5-inch (12.7 cm) pipe container is based on the DOT-specification 2R container, as outlined in 49 CFR 178 § 178.360 [1]. A drawing of the container is provided in Appendix 1.4.5. The container consists of a 5.56 (14.1 cm) OD pipe with a 0.26 (6.6 mm) wall thickness. The bottom cap of the container is a 0.25 (6.4 mm)-thick steel plate, and the top cap is an iron malleable cap with a height of 2.3 (5.8 cm) and a 16.8 (42.7 cm) maximum OD. The container has an outer 2-1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 height (OH) of 21.0 (53.3 cm) with all eight threads fully engaged and a corresponding inner height (IH) of 20.5 (52.2 cm).

A Hypothetical Accident Conditions (HAC) drop test series was performed on the 5-inch (12.7 cm) pipe container to verify its ability to maintain structural integrity and preserve the confinement of the fissile materials. Only the HAC drop test series was performed as the HAC series bounds Normal Conditions of Transport (NCT) drop tests and analyses. The HAC drop test series is documented in a separate report in Reference [20].

The VP-110 consists of a 21 (53.3 cm) Inside Diameter (ID) x 32-3/4 (83.2) Inside Height (IH) containment area centered within an insulated 110-gallon drum. Drawings of the VP-110 are provided in Appendix 1.4.1. The Versa-Pac design utilizes standard shop dimensions, tolerances and structural materials as outlined in the drawings in Appendix 1.4.1 and the General Note Sheet in Appendix 1.4.2. An illustration of the packaging is provided in Figure 1-1.

The overall nominal dimensions of the VP-110 are 30-7/16 (77.3 cm) Outside Diameter (OD) x 42-3/4 (108.6 cm) in height to the top of the outer drum bolt ring. The containment area is protected with a gasketed inner containment lid that is closed with twelve 1/2 (1.3 cm) bolts. A polyurethane insulation plug is encapsulated in 16-gauge carbon steel welded onto the drum lid (see Appendix 1.4.3). The gasketed drum lid is closed with eight 1/2 (1.3 cm) bolts and a standard drum ring. A gasket at the drum lids stiffening ring provides an additional barrier against water in-leakage.

The 110-gallon (416 liter) drum is strengthened with eight longitudinal stiffeners fabricated from 1-1/4 (3.2 cm) carbon steel square tubing equally spaced around the circumference of the drum.

A 16-gauge (1.5 mm) outer liner and a 16-gauge (1.5 mm) inner liner provide additional insulated radial stiffness to the drum. The volume between the inner liner and the 10-gauge (3.4 mm) containment body is filled with ceramic fiber insulation (see Appendix 1.4.4).

The Versa-Pac design does not include lifting or tie down devices. Handling is accomplished using standard drum handling equipment and/or a forklift. Shielding and pressure relief devices are not required for the Versa-Pac payloads. Plastic plugs located on the inner liner and the acetate plug located on the exterior of the package are designed to vent any combustion products generated by the insulation under Hypothetical Accident Conditions. The containment boundary is the containment area, the containment area blind flange and containment flat gasket seal. The containment area is attached to the structural components of the Versa-Pac using 12 equally spaced 1/2 (1.3 cm) bolts through a 1/4 (6.4 mm) connection ring and a 1/2 (1.3 cm) thick fiberglass thermal break connected to the structural frame. Bolts are torqued and the bolt/nut connection spot-welded to prevent potential loss of the connection.

Performance of the package to the required regulations and design criteria is demonstrated through the analytical evaluations and prototype testing discussed in the remainder of this section.

The package performs as required to the applicable regulations, assuring safe transport of the payload. Table 2-1 provides a summary of the evaluations performed and their results.

2.1.2 Design Criteria The Versa-Pac was designed to meet all of the performance requirements of 10CFR71 [2] for fissile materials. The Versa-Pac is manufactured under a quality assurance program that meets the requirements of 10CFR71, Subpart H [3]. All welding is performed by qualified personnel in accordance with AWS D1.1 [4]. All inspections are conducted by personnel qualified under ASNT-2-2

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 TC-1A [5], and/or for visual inspection, certified as an AWS certified welding inspector or assistant.

The containment boundary is defined as the containment area, its seal and blind flange. The structural design criteria for the packaging under the Normal condition are:

• The packaging is maintained within the allowable temperature, pressure and stress ranges as stated in each Section and Table 2-1;

• VP The package outer diameter and the height are essentially maintained at their nominal as-built dimensions;

• VP-110 - The package outer diameter and the height are essentially maintained at their nominal as-built dimensions;

• Positive closure is maintained during transport;

• Moderators are evaluated inside the payload vessel (criticality control requirement);

• Chemical and galvanic reactions do not impair the function of the packaging within its 10-year design lifetime;

• The package is stackable and meets the applicable regulations; and

• Performance and design of the packaging meets other minimum regulatory requirements for licensure.

The design criteria under Hypothetical Accident Conditions are:

• The packaging is maintained within the allowable temperature, pressure and stress ranges as stated in each Section and Table 2-1;

• VP The average OD of the packaging is maintained greater than 21.1 (53.6 cm) and the minimum height of the packaging is maintained greater than 33.6 (85.3 cm) under all conditions (criticality control requirement);

• VP-110 - The average OD of the packaging is maintained greater than 28.5 (72.4 cm) and the minimum height of the packaging is maintained greater than 41.8 (106.2) under all conditions (criticality control requirement);

Table 2-1 provides a summary of the structural evaluation, design criteria, and results of the evaluation.

Table 2-1. Evaluation Results Minimum Evaluation Evaluation Result Evaluation Criteria Factor of Safety (FS)1 or Design Margin (DM)2 Minimum package Versa-Pac is N/A 10CFR71.43(a) size 24 (61 cm) x 35 (89 cm) Package is acceptable Tamperproof One per package, Closure Ring N/A 10CFR71.43(b) feature Bolt Package is acceptable 2-3

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 Table 2-1. Evaluation Results Minimum Evaluation Evaluation Result Evaluation Criteria Factor of Safety (FS)1 or Design Margin (DM)2 110 Gallon Versa-Pac uses 20 bolts to secure the packaging & N/A Positive Closure 10CFR71.43(c) the 55 Gallon Versa-Pac uses Package is acceptable 16 bolts The materials do not react Chemical & chemically, and galvanic N/A 10CFR71.43(d)

Galvanic reactions reactions are acceptable over Package is acceptable the packaging life N/A Lifting N/A 10CFR71.45(a)

Package is acceptable N/A Tie down N/A 10CFR71.45(b)(1)

Package is acceptable Foam maximum expansion Heat

~0.004 (0.1 mm)

(Differential thermal Yield strength FS ¥ Stress developed ~ 0 psi in both expansion) foam and steel components N/A Steel yield strength Heat Package uses a de-coupled Foam compressive FS ¥ (Thermal Stress) design that minimizes thermal strength stresses Packaging temperature = -40°F Minimum allowable, -40°F Cold FS = 1.0

(-40°C) (-40°C)

Reduced External Effective pressure differential = Containment rated to FS = 1.3 Pressure 11.2 psig (77 kPa gauge) 15 psig (103 kPa gauge)

Increased External Effective pressure differential = Containment rated to FS = 1.7 Pressure 9 psig (62 kPa gauge) 15 psig (103 kPa gauge)

No loss of containment, no loss N/A Transport Vibration 10CFR71.71(5) of packaging effectiveness Package is acceptable No effect on packaging N/A Water Spray 10CFR71.71(6) effectiveness Package is acceptable Normal Condition No effect on packaging N/A 10CFR71.71(7)

Free Drop effectiveness Package is acceptable 10CFR71.71(9)

Compression 623 psi (4.3 MPa) FS = 25.7 steel yield strength 2-4

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 Table 2-1. Evaluation Results Minimum Evaluation Evaluation Result Evaluation Criteria Factor of Safety (FS)1 or Design Margin (DM)2 No effect on packaging N/A Penetration 10CFR71.71(9) effectiveness Package is acceptable Hypothetical Accident Condition No effect on packaging N/A 10CFR71.73(1) and (3)

Free Drop and effectiveness Package is acceptable Puncture Drop 10CFR71.73(4)

Hypothetical Maximum payload vessel Maximum allowable DM = 71 °F Accident Condition temperature 429°F payload/seal temperature = FS = 1.16 Fire 500°F Fissile Immersion No in-leakage 10CFR71.73(5) N/A Immersion No in-leakage 10CFR71.73(6) N/A Notes:

1. The Factor of Safety is defined as the ratio of the allowable to the actual, rounded down the nearest tenth.

2. The Design Margin is defined as the allowable minus the actual.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 2.1.3 Weights and Centers of Gravity The weight of each model of the Versa-Pac is provided in Table 2-2. The allowable payload weight of the VP-55 is 350 lb (158 kg) and the maximum gross weight of the VP-55 is 750 lb (340 kg) per the drop-test report listed in Reference [21]. The center of gravity of an empty VP-55 is located approximately 20 (51 cm) from the absolute base of the package along a vertical axis in the geometric center of the package. The center of gravity of a loaded package will shift downward by approximately 1 (2.5 cm). The center of gravity of an empty VP-110 is located at approximately 18 (46 cm).

Table 2-2. Versa-Pac Shipping Package Gross Weights 55-Gallon Version - Model No. VP-55 Component Weight (kg) Weight (lb)

Versa-Pac Shipping Package (Nominal) 177 390 Maximum Payload 158 350 Maximum Gross Weight of Loaded Package 340 750 110-Gallon Version - Model No. VP-110 Component Weight (kg) Weight (lb)

Versa-Pac Shipping Package (Nominal) 321 705 Maximum Payload 119 260 Maximum Gross Weight of Loaded Package 439 965 2.1.4 Identification of Codes and Standards for Package Design The Versa-Pac is a Type A fissile package based on the maximum U-235 payloads outlined in Section 1.1. The 1S/2S UF6 cylinder contents are limited per the requirements in Tables 1-5 and 1-6.

The Versa-Pac was designed to meet the requirements of 10CFR71 [2] and IAEA Regulations for the Safe Transport of Radioactive Material, SSR-6 [6].

Fabrication and the assembly of the Versa-Pac are conducted in accordance with Daher-TLI Quality Assurance Program [7] and normal shop Standard Operating Procedures. Welding shall be performed by qualified personnel using approved procedures in accordance with AWS D1.1

[4].

Testing and inspection of the Versa-Pac Shipping Packages will be conducted in accordance with Standard Operating Procedures in compliance with the appropriate code, such as ASNT, ASME and AWS.

Maintenance and use of the Versa-Pac Shipping Package shall be conducted in accordance with Section 7.0, Operating Procedures and Section 8.0, Acceptance Tests and Maintenance Program and the Certificate of Compliance.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 2.2 Materials 2.2.1 Mechanical Properties of Materials The mechanical material properties used to evaluate the Versa-Pac performance are provided in Table 2-3. The thermal material properties used to evaluate the Versa-Pac performance are provided in Section 3.2.1.

2.2.2 Chemical, Galvanic Reactions and Other Reactions The compatibility of materials used to fabricate the Versa-Pac and the combination of these materials has been demonstrated not to experience significant material loss due to chemical and galvanic reactions [15].

There are two combinations of Versa-Pac materials of construction that have the potential for galvanic reaction. The first combination is steel, primer, ceramic fiber insulation, and polyurethane foam insulation. The second combination is steel and the payload. Other packages have successfully used this combination of materials without galvanic reactions and have done accelerated corrosion tests to support the combined use.

All of the insulation materials used in the construction of the Versa-Pac container have low chloride content. The fiber insulation used has been tested for its corrosive action on steel with acceptable results [15]. Therefore, the combination of materials is acceptable for use.

The payload material is pre-packaged to limit contact with the containment area. Therefore, a galvanic reaction with the payload is not considered credible. However, pre-shipment and maintenance inspections would identify any corrosion due to contact with the payload well before the structural integrity of the containment area would be compromised.

Additionally, the contents and plastic pre-packaging materials do not produce significant amounts of hydrogen gas by radiolysis, as the available decay to support the reaction is essentially zero.

The RTV (Silicone Rubber Compound) coated fibrous sleeve allows the permeation of gas, without passage of solids, to keep the containment at approximately atmospheric pressure.

For the 1S/2S cylinder contents, the potential of hydrofluoric (HF) acid contamination is minimal.

Prior to loading into the Versa-Pac, all 1S/2S cylinders are cleaned to be free of chemical contamination. Each 1S/2S cylinder is packed with proper shoring/cribbing to prevent shifting and are supported during the NCT and HAC free drop events. The weight of a single fully loaded 1S and 2S cylinder are restricted to a maximum gross weight of 2.75 lb (1.2 kg) and 9.1 lb (4.1 kg),

respectively (Ref. [14], Table 4). Since the mass of the 1S/2S cylinders are small and are supported within the package, the cylinders are expected to survive both NCT and HAC.

Therefore, the inleakage of water into the container holding the UF6 material and thus generation of HF acid is not a credible event. However, in the event of cylinder surface HF contamination, the corrosion of the Versa-Pac packaging components would not result in the release of fissile material.

Therefore, interactions among contents, packaging materials of construction and packing material satisfy the requirements of 10 CFR 71.43(d) [2].

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 2.2.3 Effects of Radiation on Materials The radiation produced by the authorized payloads is very low. The packaging materials used (steel, rigid polyurethane insulation products, ceramic fiber insulation products, silicone rubber, fluorocarbon) do not undergo significant changes in properties or performance due to their exposure to the authorized payloads.

Table 2-3. Mechanical Properties of Materials Carbon Steel Plate and Property/Material Carbon Steel Bolts Note 1 Sheet Note 1 Density (lb/ft3) 491 [8] N/A Thermal Expansion Coefficient (in/in/F) {9.22 x 10-6} N/A Min Yield Strength (psi x 1,000) {36} {81}

Min Tensile Strength (psi x 1,000) {58} {105}

Elongation in 2 (%)

{21*} {14}

• Elongation in 4D (%)

Property Impact Absorbing Foam Insulation Density (lb/ft3) 5.0 - 11.0 (Per Table 1-7)

Nominal Thermal Expansion Coefficient (in/in/F) 3.4 x 10-5 [9]

Compressive Strength (psi) 85 - 300 (Per Table 1-7)

Notes on Table 2-3:

1. Information provided in {brackets} is an average or nominal for the material used and is provided for comparison purposes only, as it is not used in any evaluation presented for the packaging.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 2.3 Fabrication and Examination 2.3.1 Fabrication The Versa-Pac is fabricated using Daher-TLI Standard Operating Procedures and Fabrication Control Records to document each step of the fabrication process (i.e., cutting of material, fitting, welding and other special processes). The Fabrication Control Records (FCR) become a part of the permanent Quality Assurance Record for the package. All welding is conducted in accordance with approved procedures, which are in compliance with the applicable code such as AWS D1.1 [4]. All insulation materials are procured in accordance with the requirements in Appendices 1.4.3, 1.4.4, and 1.4.5.

A typical fabrication sequence for the Versa-Pac Shipping Package begins with the cutting and forming of the individual components, which is carried out through the use of a Route Sheet system which provides the preparation group the details for all items. These items are inspected and once approved, released for production to begin the process of manufacturing the Versa-Pac.

The Fabrication Control Record (FCR) provides sequenced steps for the manufacturing of the Versa-Pac. These individual sequences give the quality assurance and production departments the instructions, standard operating procedures, welding procedures and inspection hold points for proper fabrication of the package.

Each sequence must be completed in order and the FCR step signed and dated by the individual responsible for that work, prior to moving to the next sequence. The FCR allows for QA or the customer to insert additional hold points at any location in the production process.

2.3.2 Examination All non-destructive examinations methods utilized in the fabrication of the Versa-Pac Shipping Package, are conducted in accordance with Daher-TLI Standard Operating Procedures, which are in accordance with appropriate codes, such as ASME [10] and AWS D1.1 [4] and/or D1.3 and applicable engineering specifications. Section 8 of this report specifies the requirements for fabrication acceptance and maintenance examinations of this package.

2.4 General Requirements for All Packages 2.4.1 Minimum Package Size The smallest overall dimension of the VP-55 is 22-1/2 inches in diameter and the smallest overall dimension of the VP-110 is 30-7/16 inches (77.3 cm) in diameter. The Versa-Pac thereby complies with the minimum package size requirement of 10 CFR 71.43(a) [2].

2.4.2 Tamper-Indicating Feature The Versa-Pac utilizes the outer drum ring closure bolt for installation of tamper indicating devices, typically individually numbered seals.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.4.3 Positive Closure The primary containment is closed by use of a gasketed 1/2 (1.3 cm)-thick blind flange with 12 carbon steel clad 1/2 (13 mm) bolts, flat washers and lock washers. The outer opening of the Versa-Pac is closed utilizing a reinforced insulated drum cover initially bolted through a gasketed surface with 4 carbon steel clad 1/2 (13 mm) bolts and flat washers on the VP-55 and 8 bolts on the VP-110. In addition, the standard drum closure ring with a 5/8 (16 mm) bolt. All closure bolts are torqued at 60 lb-ft (81.3 Nm).

2.5 Lifting and Tie-down Devices 2.5.1 Lifting Devices The Versa-Pac may be handled by normal industry standards for the safe movement of drums.

Such equipment might include specifically designed devices, forklifts, pallet jacks or other methods as determined by the user. However, the Versa-Pac does not utilize any specific device or attachment for lifting.

2.5.2 Tie-down Devices There are no specific provisions for tie-down of the Versa-Pac.

2.6 Normal Conditions of Transport (NCT)

The Versa-Pac meets the standards specified by 10 CFR 71 [2] when subjected to the conditions and tests required. The effectiveness of the package is maintained throughout all Normal Conditions of Transport.

Full-scale prototypes of both versions of the Versa-Pac Shipping Package were first tested in accordance with the (Structural) requirements specified by 10 CFR 71.71, Normal Conditions of Transport, and 10 CFR 71.73, Hypothetical Accident Conditions. Table 2-4 provides a matrix of all testing performed to certify the Versa-Pac design. The NCT testing program is further discussed in Section 2.7, where the NCT test is the precursor to the HAC test sequence.

Complete post-test measurements along with full photographic and written documentation is included in References [17], [18], [20] and [21].

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Table 2-4. NCT and HAC Test Matrix Test Test Description Test Date Reference Program #

1 Immersion Test July 2008 [16]

2 NCT and HAC Certification Test Series March 2009 [17]

Series 1 1A NCT 4' (1.2 m) Top End Drop 1B HAC 30' (9 m) Top End Drop 1C HAC 40 (1 m) Puncture - Side Series 2 2A NCT 4' (1.2 m) Side drop 2B HAC 30' (9 m) Side Drop 2C HAC 30' (9 m) Dynamic Crush - Side Series 3 3A NCT 4' (1.2 m) C.G. Over Drum Ring 3B HAC 30' (9 m) C.G. Over Drum Ring 3C HAC 30' (9 m) Shallow Angle Drop 3D HAC 40 (1 m) Puncture - C.G. Over Drum Ring 3 Shallow Angle Drop Tests September 2009 [18]

1-55-A NCT 4 (1.2 m) Shallow Angle Drop (slap down) 1-55-B HAC 30 (9 m) Shallow Angle Drop (slap down) 1-55-C HAC 40 (1 m) Puncture - C.G. Over Drum Ring 4 NCT Penetration and Stacking Tests December 2009 [19]

5 5 Pipe Container Drop Tests October 2015 [20]

9.1 HAC 30 (9 m) Shallow Angle Drop (slap down) 9.2 HAC 30' (9 m) Top End Drop 9.3 HAC 30' (9 m) C.G. Over Corner Drop (pipe cap) 6 NCT and HAC Test Series at 750 lb Max Gross Weight October 2017 [21]

2.1 HAC 4' (1.2 m) C.G. Over Drum Ring 2.2 HAC 30' (9 m) C.G. Over Drum Ring 2.3 HAC 30' (9 m) Dynamic Crush - Side 2.4 HAC 40 (1 m) Puncture - Lid Center Note: The packages used for the test series were fabricated as specified by the packaging drawings provided in Appendix 1.4.1.

2.6.1 Heat 2.6.1.1 Summary of Pressures and Temperatures The peak payload temperature of the packaging is 176°F (80°C), under Normal Conditions of Transport (see Section 3.3.1.1). The material properties of the packaging remain essentially nominal at this temperature. This is well below the maximum allowable temperature of 600°F (316°C) (defined in Section 3.1.3) for the contents. The Versa-Pac containment is rated for a maximum pressure of 15 psig (205 kPa), however, the silicone-coated fiberglass gasket of the Versa-Pac allows gases to permeate through, but not solids, to maintain near atmospheric pressure. Therefore, the maximum normal operating pressure is near atmospheric pressure.

2.6.1.2 Differential Thermal Expansion The Versa-Pac is constructed of steel and insulation components. Due to their relatively high thermal conductivity, and the relative uniformity of the heat application, the steel components do not independently develop significant stresses due to differential thermal expansion.

The blanket insulation used is compressible, and therefore is not damaged by thermal expansion effects.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 The linear thermal expansion coefficient of the rigid foam insulation is approximately four times that of the steel; therefore, it is possible that the foam insulation expands more than the steel shell. If the entire volume of the foam increases in temperature from 72°F (22°C) to the peak steady state surface temperature of 144°F (62°C), the average maximum linear differential thermal expansion of the foam is about 1/16. However, due to the cyclic loading of the insulation, the actual volume of foam at 144°F (62°C) is limited to less than 15% of the total foam volume and a more realistic estimate of the expansion is about 1/240 (0.1 mm). These very small expansion lengths are absorbed by the microstructure of the foam at the steel surface and by the allowable tolerances on the parts themselves. Therefore, no significant stresses are generated as a result of differential thermal expansion.

2.6.1.3 Thermal Stress Calculations Due to the decoupled design of the packaging, thermal stresses generated by the packaging are negligible.

2.6.1.4 Comparison with Allowable Stresses Not applicable.

2.6.2 Cold At an ambient temperature of -40°F (-40°C) with no insolation and zero decay heat generated by the contents, the package attains a uniform temperature of -40°F (-40°C). At this temperature, the foam insulation compression strength and compressive modulus are increased. The increased foam (top and bottom of the package) strength and modulus result in a stiffer package response under drop conditions, and therefore more of the load is transferred to the containment boundary on impact. Also, the carbon steel components may be brittle below -20°F (-29°C). Performance testing of the package was completed at low temperature, demonstrating that the packaging performs as required under cold conditions.

No observable differences in damage were noted by comparison of prototype testing of the package at normal ambient temperatures to the performance testing conducted at low temperatures. Therefore, low temperature effects have little impact on the Versa-Pac performance.

2.6.3 Reduced External Pressure Per 10 CFR 71.71(c), a reduced external pressure of 25 kPa (3.5 psi) absolute must be considered. Per Section 3.3.2, the maximum normal operating pressure (MNOP) is atmospheric (101 kPa, 14.7 psia). Therefore, a reduced external pressure of 25 kPa results in a net internal pressure of 11.2 psig (77 kPa gauge).

In addition, para. 621 of SSR-6 requires that the VP-55 be capable of withstanding a net internal pressure of MNOP plus 95 kPa (13.8 psi) for air transport. As the MNOP for the Versa-Pac is atmospheric, the max pressure differential for air transport is 95 kPa (13.8 psi). Both resultant pressures required by 10 CFR 71 and SSR-6 are within the containment design pressure of 15.0 psig (103 kPa gauge). Therefore, the Versa-Pac satisfies the reduced external pressure requirements.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.6.4 Increased External Pressure Per 10 CFR 71.71(d), an increased external pressure of 140 kPa (20 psi) absolute must be considered. Per Section 3.3.2, the MNOP is atmospheric (101 kPa, 14.7 psia). Therefore, an increased external pressure of 140 kPa results in a net internal pressure of 62 kPa gauge (9 psig).

This pressure differential is within the containment design pressure of 15.0 psig (103 kPa gauge).

Therefore, the Versa-Pac satisfies the increased external pressure requirement.

2.6.5 Vibration Vibration incident to transport does not produce settling, compaction or a loss of structural cohesion for any of the materials used in the packaging. Vibrational compaction of the payload does not impact the performance of the packaging, since the criticality evaluation (see Section 6) applies a variable payload density up to the theoretical limit to evaluate the optimum condition.

Vibration testing conducted on the outer drum during the performance design qualification test as set forth in 49 CFR 178.608 [11] were successfully performed with past experience indicating no failure to the drum ring closure. In addition, the Versa-Pac includes an additional bolted closure through the top lid attached to the internal structure. This bolted closure utilizes 1/2 bolts and locking washers that are torqued to a prescribed rating of 60 lb-ft. to prevent the loss of the bolts during transportation. Thus, normal vibration incident to transport does not impact the performance of the Versa-Pac.

2.6.6 Water Spray A one-hour water spray simulating rainfall at a rate of 2 in/hr. has no effect on the Versa-Pac, as the outer vessel is designed to withstand exterior pressure loads much higher than those applied by the water spray.

The Versa-Pac utilizes multiple seals to prevent the loss or dispersal of its contents. Because it is clear that the water spray test has no effect on the package or contents, it was not conducted during the performance test sequence.

2.6.7 Free Drop Per regulatory requirement, the package must maintain its integrity and effectiveness when subjected to a free drop from a height of 4 feet (1.2 meters) onto a flat, essentially unyielding horizontal surface. Although the damage from a 4-foot free drop results in some local deformation of the transport unit, the deformation is well within the allowable specified for criticality safety and structural stability. Three different drop orientations were conducted and the results of all five normal condition performance tests of the Versa-Pac are provided in Reference [17] and [21]. A summary of the NCT free drop performance is documented in Section 2.7.1.

2.6.8 Corner Drop A free drop onto each corner of the package in succession, or in the case of a cylindrical package onto each quarter of each rim, from a height of 1 ft (0.3 m) onto a flat, essentially unyielding, horizontal surface. This test applies only to fiberboard, wood, or fissile material rectangular packages not exceeding 110 lb (50 kg) and fiberboard, wood, or fissile material cylindrical packages not exceeding 220 lb (100 kg). This test is not applicable to the Versa-Pac packaging, since the minimum tare weight is 390 lb (177 kg).

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.6.9 Compression The primary load bearing members of the Versa-Pac are the steel 55 or 110-gallon drum shell, the vertical stiffeners, and the inner liner. These components, when assembled as a unit, can be analyzed as an axial member in compression. Assuming the metal thickness is 0.036 and 0.05 for the drum and inner liner, respectively, and using 1-1/4 x 1-1/4 x 0.12 for conservatism (the actual thicknesses are 0.06, 0.0598, and 0.135 respectively), the load-bearing cross-sectional area is approximated as:

(22.5 .)(0.036 in.) + (19.25 .)(0.05 in.) + 4(1.25 .! 1.01 .! ) = 7.738 .! (50 ! )

Five times the weight of the package is:

(5)(965 ) = 4,825 (2189 )

The compressive stress on the steel members is:

4,825 7.738 .! = 623 (4.3 )

The margin of safety against compressive failure is:

. . = E36,000F623G 1 = 56.7 For empty Packaging Five times the weight of the packaging is:

(5)(390 ) = 1,950 (885 )

The compressive stress on the steel members is:

1,950 7.738 .! = 252 (1738)

The margin of safety against compressive failure is:

. . = E36,000F252G 1 = 141.9 The structural members of the Versa-Pac are comprised of a variety of thicknesses of steel components, although when combined through the process of manufacturing act in conjunction with one another to produce an exceptionally strong unit. To further demonstrate that the Versa-Pac meets the requirements set forth in 10 CFR 71.71(c)(9) [2], the Versa-Pac was subjected to a load greater than 5 times the weight of the package for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without any damage.

The VP-55 was tested, and the results are provided in Reference [19]: NCT Versa-Pac Test Report for Compression and Penetration.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Conclusion Based upon the calculations providing a large margin of safety against compressive failure and the physical testing performed using the previously tested VP-55 described above and reported in Reference [19] NCT Versa-Pac Test Report for Compression and Penetration, the Versa-Pac meets and exceeds the requirements specified in 10 CFR 71.

2.6.10 Penetration The Versa-Pac was subject to the penetration test described in 10 CFR 71.71(10) [2]. The test was performed using a 1.25-inch diameter steel bar weighing 13.2 lb (6 kg) and dropped from a height of 40 inches (1 meter) onto several different areas of the test package considered to be the weakest parts of the package without measurable damage at the impact point. These results are supplied in Reference [19] NCT Versa-Pac Test Report for Compression and Penetration.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.7 Hypothetical Accident Conditions (HAC)

Full-scale prototypes of both versions of the Versa-Pac Shipping Package were first tested in accordance with the (Structural) requirements specified by 10 CFR 71.71, Normal Conditions of Transport, and 10 CFR 71.73, Hypothetical Accident Conditions.

The compliance testing demonstrated:

• The Versa-Pac provides sufficient thermal protection to prevent the internal temperature of the payload container from exceeding the maximum design temperature of the containment boundary (500°F) during and following HAC,

• The average OD of the package and the required package height are maintained under HAC, and

• Containment of the payload is maintained.

Therefore, the Versa-Pac provides adequate protection to the payload during HAC as defined by 10 CFR 71.73 [2].

2.7.1 Free Drop Full-scale representatives of the VP-55 and VP-110 containing a simulated payload were subjected to a variety of sequenced drops, punctures, shallow angle drops and crush test, specified by 10 CFR 71.71 and 10 CFR 71.73 [2]. Table 2-4 provides a matrix of free drop tests performed to certify the Versa-Pac design. Complete measurements along with full photographic and written documentation is included in References [17], [18], [20] and [21].

Test Program #2 - Series 1 The VP-55 and VP-110 test program is described in Reference [17]. The first drop series included the NCT 4 top end drop (1A) followed by the HAC 30 drop (1B) in sequence. This series also includes the HAC side puncture (1C). Prototypes of both the VP-55 and VP-110 were test with the final test article utilizing the VP-110 design. All drop tests were performed on the same 70-ton pad which is 10 x 10 x 10 deep reinforced with a grid of 3/4 re-bar spaced on 12 center and capped with an 8 x 10 x 1 thick steel plate which is embedded to the surface of the concrete and secured to it with fourteen 1-1/2 diameter x 16 long bolts. A quick-release mechanism was used to release the prototypes from the drop height without imparting rotational or translational motion to the prototype. For the puncture drop, a puncture ram was welded to the test pad. The ram is a 6 diameter by 18 long right circular cylinder, fabricated from mild steel and welded to the pad reinforcement plate. The solid steel plate used for the dynamic crush test weighs 500 kg and is 1m by 1m in cross section. The tests were video-taped and photographed, and post-drop damage measurements were recorded after each drop.

In order to determine the worst-case initial temperature conditions for the drop tests, the performance characteristics of the primary Versa-Pac fabrication materials were evaluated. The primary structural and sealing materials include carbon steel, polyurethane foam, and silicone rubber. Because carbon steel may exhibit brittle failure mechanisms at temperatures below 0°F and the other materials are essentially unaffected over the design temperature range, the initial condition temperature selected is -20°F. For consistency with the minimum design operating temperature specified by the regulations, the impact testing initial ambient condition selected is -40°F.

The payload utilized for the drop test series consisted of a 30-gallon drum that was filled with approximately 260 lb of different size gravel with an additional 1 to 1-1/2 lbs. of loose play sand, 2-16

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 which was placed on the top of the 30-gallon drum, combining for a test payload of 260 lbs. The blind flange was secured by tightening the bolts to an initial torque of 40 lb-ft. The decay heat generated by the contents is negligible; therefore, heat generated by the contents was not simulated. The Versa-Pac was then subjected to an ambient air temperature of approximately -40°F for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Upon removal from the conditioning chamber, the exterior skin of the shipping package recorded a temperature of -28°F at time of transport to the test pad.

Test Program #2 - Series 2 The second drop test series included the NCT 4 side drop (2A), HAC 30 side drop (2B) and HAC 30 dynamic crush test (2C) in sequence. Both previously dropped packages were inspected and measurements of height and diameter recorded on new testing records. The payloads were identical to the original test series, with 1.5 pounds of sand placed on top of and around the payload as before. The test articles were fitted with new 1/2-inch thick inner containment flanges with 3/8-inch-thick neoprene sponge rubber pads affixed to the inside of the inner flange lid prior to installation. The torque of the inner containment bolts was also increased to 60 lb-ft for a better seal on the 1.8-inch-thick silicone rubber coated fiberglass gasket. The outer container lid was put into place and bolts torqued to 60 lb-ft. The test articles were then placed in the cooling chamber for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> prior to the new drop tests.

With changes made to the inner blind flange closure design; increasing the thickness of the flange, increasing the torque of the bolts and reinstalling the containment flange pad, the Versa-Pac Shipping Package successfully completed the drop test evaluation series.

Test Program #2 - Series 3 The third drop test series included the NCT 4 C.G. over corner drop (3A), HAC 30 C.G. over corner drop (3B), HAC 30 shallow angle drop (3C) in sequence and HAC 1-meter puncture test (3D). The test article from Series 2 was repaired and resealed for the drop sequence.

With changes made to the inner blind flange closure design, increasing the thickness of the flange, increasing the torque of the bolts and reinstalling the containment flange pad, the Versa-Pac Shipping Package successfully completed the drop test evaluation series.

Test Program #3 This test program is described in Reference [18] and was performed on the VP-55 design to evaluate shallow angle drop orientations (slap down). Worst case drop orientations were determined by evaluating the results of previously tested drum type packages presented in References [12] and [13]. The most damaging configuration was further demonstrated through a preliminary series of tests conducted on both the VP-55 and VP-110 designs during March 2009 (Test Program #2, [17]). Following the test sequence, the test article was inspected and the outer closure was maintained with no openings, tears or failure noted that would lead to the loss of material from containment.

Test Program #5 The 5-inch pipe container (VP-55-2R) drop test program is described in Reference [20]. The drop test sequences were chosen in order from least severe to most based upon historical drop testing of other specimens, industry experience, and engineering experience. The test sequence included slap-down, end drop on pipe cap, and C.G. over top corner. The results of the test series show that the VP-55-2R is capable of maintaining the safe geometry of the confinement vessel without failure or loss of material.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Test Program #6 This drop testing program was performed to increase the minimum VP-55 payload capacity to 350 lb. This program included both NCT and HAC Free Drops and is presented in Reference [21].

The same test article was used for both the NCT and HAC test sequence. To achieve the increased payload capacity, the test article was loaded with sand and steel blocks. Ten pounds of flour and 4 ounces of fluorescein were also added as indicators. The NCT and HAC drop tests were performed in sequence. First, in an effort to loosen or dislodge the drum closure ring, the NCT 4-foot free drop was performed with the package's C.G. positioned over the drum lid closure ring bolt. Second, the package was dropped from 30 feet in the top C.G. over lid drum ring 180° from the closure bolt. Third, the dynamic crush test was performed by positioning the package on the drop test pad rotated 90 degrees from the previous point of impact. Fourth, the package was subjected to the 40-inch puncture test by dropping the package top end down onto the center of the lid.

Following each test, the package was inspected with a black light and no evidence of fluorescein around the lid closure was noted. Therefore, containment of material was maintained. Mechanical damage included localized tearing of the drum ring. However, the drum ring remained in place and no failure of the lid closure bolts occurred.

2.7.1.1 End Drop To satisfy the requirements of 10 CFR 71.73(c)(1) end drop, two test programs evaluated the performance of the package when subjected to the end drop.

Test Program #2 - Series 1 After cooling, the test article was positioned with the top end of the package positioned over the test pad at an angle of 0 degrees so as to impact the container directly onto the top surface of the package [17]. This drop test series was intended to test the top closure of the package and the internal containment closure components and to validate that the changes made to the inner containment flange would prove to correct the loss of materials previous found during the original drop testing.

NCT 4 Top End Drop This drop was made from a height of 4 onto the target pad (Test 1A), and the external damage was recorded and documented with both video and still photography. As result of the impact, no visible damage was noted. All welds, closures and bolts remained intact. The package was not opened after the Normal Condition Drop but was prepared for the 30 HAC Drop.

HAC 30 Top End Drop Following the Normal Conditions Drop, the package was positioned for the HAC 30 drop onto the same surface and orientation of 0 degrees (Test 1B). Post-drop inspection documented that the overall height of the package was reduced by 7/16 inch and that the drop test did not affect the diameter. All welds, closures and bolts remained intact.

Prior to opening the test article, the bolt torque of the outer closure was measured and found to be between 20 to 80 lb-ft. with all bolts intact. After opening the package photographs were taken and the interior well surfaces inspected with no damage found. The new thicker blind flange remained flat, sealed and no loss of payload contents were found outside the inner containment area. The bolts of the interior containment were torqued and found to be at a torque of 30 to 50 lb-ft. The gasket and payload were in good condition.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Test Program #5 A new pipe container is fabricated per drawing VP-55-2R and tested without the protection provided by the Versa-Pac container. Steel shot was used to simulate the contents with sufficient ullage to induce a piston action on the pipe cap during impact [20].

HAC 30 Top End Drop The test article was raised to a height of 30 feet as measured from the lowest point of the pipe container (Test 9.2). The pipe container was dropped in a vertical position directly on the pipe cap. After the drop, the pipe container was examined and no measurable or release of contents was visible.

2.7.1.2 Side Drop To satisfy the requirements of 10 CFR 71.73(c)(1) side drop, one test program evaluated the package performance when subjected to the side drop event.

Test Program #2 - Series 2 This drop series was designed to challenge the bolted closure and seal system during the side drop by targeting the drum ring closure bolt. After cooling, the test article was positioned in a level horizontal position over the test pad [17].

NCT 4 Side Drop The initial drop was made from a height of 4 onto the target pad (Test 2A), and the external damage was recorded and documented with both video and still photography. The result of the impact to the exterior surface of the package showed that the closure bolt pushed into the package sidewall approximately 5/8 inch. No reduction in height or diameter occurred. All welds, closures and bolts remained intact.

HAC 30 Side Drop The same test article was positioned for the HAC 30 drop into the same horizontal surface as the NCT test in an effort to account for the effect of accumulated damage in the side drop orientation (Test 2B). Resultant damage from this drop accounted for a buckling around the closure bolt area and on the lid and a decrease in the diameter of 1 inch in the drum ring closure bolt impact direction. There was no loss of bolts or seal and all welds remained intact. The package was then subjected to the dynamic crush drop described in Section 2.7.2.

2.7.1.3 Corner Drop To satisfy the requirements of 10 CFR 71.73(c)(1) corner drop, three test programs considered the effects of the corner drop on the closure system of the package.

Test Program #2 - Series 3 This drop series was designed to challenge the package and containment bolted closure and seal systems of the package when positioned in the center of gravity over drum closure ring orientation.

After cooling, the test article was positioned with the center of gravity impact to be through the package bolt closure over the test pad [17].

NCT 4 Center of Gravity Over Corner Drop The normal condition center of gravity drop from a height of 4 through the bolted closure at an 2-19

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 angle of 57 degrees was recorded and documented using both video and still photography (Test 3A). The impact resulted in a deformation on the closure bolt area with measurements of 1-3/16 inch deep by 2-1/4 inches long. All welds, bolts and closures remained intact.

HAC 30 Center of Gravity Over Corner Drop The package was repositioned in the same attitude of 57 degrees so as to impact the identical area tested in 3A above over the test pad at a height of 30 from the lowest point of the package (Test 3B). The impact resulted in a deformation of 2-9/16 deep by 20-1/2 inches long. All welds, bolts and closures remained intact. The package was then readied for the HAC oblique (Shallow) angle drop.

Test Program #5 A new pipe container is fabricated per drawing VP-55-2R and tested without the protection provided by the Versa-Pac container. Steel shot was used to simulate the contents with sufficient ullage to induce a piston action on the pipe cap during impact [20].

HAC 30 Center of Gravity Over Corner Drop The test article was raised to a height of 30 feet as measured from the lowest point of the pipe container (Test 9.3). The pipe container was dropped in the C.G. over corner position approximately 12.5° from the vertical position directly on the pipe cap. After the drop, the pipe container was examined and a dent measuring 1-1/2 x 3/8 at the point of impact with no measurable effect on the rest of the container or release of contents was visible.

Test Program #6 The purpose of this additional drop testing is to increase the allowable payload weight for the 55-gallon Versa-Pac to 350 lb [21]. The test subject was loaded with sand and steel blocks until the total package weight was 750 lb. Subtracting the 396-lb tare weight of the Versa-Pac Prototype

1. 2 from the gross weight, the tested payload weight was 354 lb. Testing was conducted on an unyielding surface under ambient temperature conditions.

NCT 4 Center of Gravity Drop The NCT corner drop was conducted by positioning the test article in the C.G. over corner in the top-down position and dropping onto a flat, essentially unyielding, horizontal surface, striking the drum ring closure bolt (Test 2.1). Damage during the 4-foot drop was observed at the corner of the package at the bolt connection of the drum ring. The drum ring and lid deformation was localized at the point of impact and did not significantly change the overall dimensions of the package. No release of material or breach of containment of the package was observed.

HAC 30 Center of Gravity Drop The HAC corner drop was conducted by positioning the test article in the C.G. over corner in the top-down position and dropping onto a flat, essentially unyielding, horizontal surface, striking the drum ring closure 180° from the NCT drop damage (Test 2.2). The deformation during the 30-foot drop was observed at the top corner of the package at the drum ring and the drum lid reinforcing plate. Observations of the deformed corner showed localized tearing where the drum ring impacted the pad. However, the drum ring remained intact and in position with no failure of the lid closure bolts noted. No release of material or breach of containment of the package was noted.

This drop was followed by the dynamic crush test described in Section 2.7.2.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.7.1.4 Oblique Drop To satisfy the requirements of 10 CFR 71.73(c)(1) oblique drop, three test programs considered the effects of slap down on the packages performance.

Test Program #2 - Series 3 The test article used in this test was previously used in the C.G. over corner described above and was positioned with the C.G. through the bolted connection at an angle of 56 degrees from horizontal (Test 3C) [17]. The package was raised to the drop height of 30 feet-1 inch above the test pad surface from the lowest point of the package.

HAC 30 Shallow Angle Drop (Slap Down)

The damage to the package exterior surface produced deformation on the initial top closure measuring 2-5/16 inches deep with a 1-inch crumple in the lid. Secondary impact produced damage measuring 5 inches in length on the bottom rim of the test article. Diameter of the package was reduced in the direction of the impact area through the bolt by approximately 1 inch.

Before opening the outer closure, the torque was measured and found to be less than 20 lb-ft.

Photographs were taken and inspection of the inner well area found only minor deformation within the sidewalls of the well area. No other damage was found. The inner flange was flat and sealed with no loss of contents form the internal containment area. Bolt torque of the inner flange ranged from 20 to 40 lb-ft.

Test Program #3 The package was positioned over the test pad at 17 degrees from the horizontal position so that initial contact occurred on the top closure with the resulting secondary impact at the bottom of the package [18]. This drop was also intended to test the inner containment area closure system. The drop angle of 17 degrees was chosen based upon previous drop history and drop information found in References [12] and [13].

NCT 4 Shallow Angle Drop (Slap Down)

The package was positioned such that the lowest point of the package was 4 from the target surface (Test 1-55-A). The damage to the package exterior surface was minimal, with an area 7-1/4 long at the widest points on the top closure end and 5-3/4 in width at the bottom edge.

Minor indentation along the outer drum rolling hoops was also noted. Both flattened areas were approximately 1/4 in depth. There was no tearing or opening of the package.

HAC 30 Shallow Angle Drop (Slap Down)

The same test package was then positioned over the test pad at 17 degrees from the horizontal position with the lowest point of the package 30 from the target surface (Test 1-55-B). Damage to the package consisted of a small ripple in the middle of the outer drum lid with minor flattening of the outer drum rolling hoops. Additional damage to the top closure, initial impact area was noted, increasing the length of the NCT damaged area to 11-1/2 long by 3/8 deep. Additional damage to the bottom closure impact area with secondary impact damage was noted, increasing to 10 long by 1/4 deep. The bolt closure ring of the outer drum was pushed into the sidewall of the outer drum, producing a small tear in the drum sidewall material at the top rolling hoop, but due to the design of the package there was no breach or tearing of the Versa-Pacs inner liner, which is adjacent to the outer drum. The drum closure ring lug was also broken with the impact, but the top closure remained intact and secure due to the top closure bolts of the package. The package was then readied for a puncture test described in Section 2.7.3.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Test Program #5 A new pipe container is fabricated per drawing VP-55-2R and tested without the protection provided by the Versa-Pac container. Steel shot was used to simulate the contents with sufficient ullage to induce a piston action on the pipe cap during impact.

HAC Shallow Angle Drop (Slap Down)

The test specimen was dropped from a height of 30 feet, measured from the top of the target to the lowest point of the specimen at an angle of 15.9° from horizontal (Test 9.1). After the drop, the damage consisted of a 1-3/16 x 3/16 dent to the container cap and a 1-3/8 x 1/16 dent to the bottom plate. The damage did not reduce the function of the container to confine the contents.

No loss of material was noted.

2.7.1.5 Summary of Results The free drop test results provided information showing that the package design is capable of withstanding multiple impacts with only minor damage to the exterior surfaces. The complete drop test summary of results is discussed in detail in Section 2.7.8.

2.7.2 Crush To satisfy the requirements of 10 CFR 71.73(c)(2), two test programs considered the dynamic crush test and were performed to challenge the package closure system by placing the package on the test pad in a horizontal attitude. The crush plate was positioned to impact the package directly on both the closure and top flange region of the package.

Test Program #2 - Series 2 The crush test was performed on the test article that experienced both the NCT 4-foot side drop and the HAC 30-foot side drop in sequence [17].

HAC 30 Dynamic Crush - Side Impact The crush plate was suspended at an angle of 0 degrees directly over the test package and lifted to a height of 30 feet from the lowest point of the test plate to the top of the test package surface (Test 2C). Upon impact, the overall diameter of the package in the direction of the impact was reduced by 2-1/2 inches from its original shape at its maximum point. A gap of 1/4 inch by 1-1/4 inch long was documented at the drum lid to drum rim interface. Due to the design of the closure lid, a metal-metal interface was visible with no direct opening to the internal structure or seals. The gaskets were intact with minimal damage. The payload drum did exhibit some crumpling at the lid, but all of the payload materials remained within the drum and payload cavity as required. Upon inspection, the inner cavity showed no visible damage.

Test Program #6 The purpose of this test program was to increase the VP-55 payload capacity to 350 lb [21]. The crush test was performed on the test article that experienced both the NCT and HAC corner drops on the drum closure ring in sequence.

HAC 30 Dynamic Crush - Side Impact For the this test, the VP-55 test article was laid on the test side opposite previous damage (Test 2.3). The 1141 lb (517 kg) crush plate was raised 30 feet (9 m) from the side of the package surface. The crush test resulted in flattening on both the side of the package resting against the 2-22

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 ground and the side that was directly impacted by the crush plate. Localized deformation due to the edge of the crush plate was also observed at the point of impact. No closure bolt failure was noted, the drum closure ring remained in position and no leakage of material was observed on the package outer surface.

2.7.3 Puncture To satisfy the requirements of 10 CFR 71.73(c)(3), prototypes of both the VP-55 and VP-110 were subjected to the puncture test in a variety of orientations including side, center of gravity through the bolt closure and lid center.

Test Program #2 - Series 2 The packages were lifted to a height of 41 inches above the top of the puncture ram, which was welded to the top surface of the drop test pad [17].

HAC 1 Meter Puncture Drop - Horizontal The suspended package was positioned level and horizontal (1 degree) so that the impact location was between two of the vertical stiffeners and in the middle of package (Test 1C). The test was recorded and documented using video and still photography. The deformation upon measurement was a maximum of 3/8 inch deep. The package sustained no tears as a result of the puncture drop.

HAC 1 Meter Puncture Drop - CG Over Drum Ring The package was positioned with the center of gravity through the bolted closure at an angle of 56 degrees from a height of 41 inches from the lowest point of the package to the top of the puncture pin (Test 3D). The drop test was recorded and documented using both video and still photography. The impact resulted in additional damage on the drum side at the closure bolt with a small separation of 1/4 inch by 3 inches long at the drum lid and drum rim interface. The opening was sealed by metal-metal contact between the flange and the drum lid insulation sheet metal cover and the top gasket material, which remained intact. The inner containment gasket was in good condition with only minimal damage to the outer closure gasket.

Test Program #3 The package was positioned with the center of gravity through the bolted closure at an angle of 56.5 degrees from a height of 41 inches from the lowest point of the package to the top of the puncture ram (Test 1-55-C) [18].

HAC 1 Meter Puncture Drop - CG Over Drum Ring After impact, the deformation of the test article was measured at an affected area of 8-3/8 wide with a diameter of 23 at the top of the closure area. There were no tears or opening of the package as a result of the puncture drop. The impact resulted in additional damage to the outer drum closure ring and lid interface with an impact deformation measuring 8-3/8 in diameter. The gaskets and internal containment cavity were found to be in good condition with no damage.

Test Program #6 The puncture test is the final test in the test sequence, which includes the dynamic crush test, to increase the VP-55 payload capacity to 350 lb [21]. For the HAC Puncture test, the VP-55 was dropped in the vertical lid down position such that the center of the lid would strike the puncture pin (Test 2.4).

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 HAC 1 Meter Puncture Drop - Vertical Lid Center The test was performed on the same package article that was dropped through the NCT and HAC Free Drop tests and the HAC Dynamic Crush test. The drum lid experienced a large local deformation, but the package was not breached. Also, the position of the outer drum ring was not affected such that the package height was not reduced. There was no leakage of material to the package outer surface.

2.7.4 Thermal A thermal test was not performed on the test prototype in its damaged condition following the drop test sequence. However, the package was analytically evaluated as indicated in Section 3. Based on testing of a similar package [16], the analytically calculated values are conservative.

2.7.4.1 Summary of Pressures and Temperatures The Versa-Pac was evaluated for HAC described in Section 3.4. The maximum temperature recorded at the payload cavity during the fire event was 429°F (221°C) at the top of the payload cavity, just below the polyurethane plug, as shown in Figure 3-16. This temperature is well below the maximum HAC allowable temperature of 600°F (316°C). The silicone fiberglass gasket of the containment allows for gas to permeate through to maintain near atmospheric pressure. The containment is rated for a pressure of 15 psi (103 kPa) gauge. In addition, the Versa-Pac features pressure plugs that will relieve any pressure build-up between the Versa-Pac inner and outer walls due to HAC.

To ensure the confinement of the fissile content, the structural performance of the 5-inch pipe is demonstrated via the bounding drop testing performed and detailed in Reference [20]. As stated above, the maximum temperature within the containment boundary of the Versa-Pac is 429°F (221°C). Thus, the temperature of the 5-inch pipe will be 429°F (221°C). Per Table 3-10 of Chapter 3, carbon steel is not expected to have a significant loss of thermal properties during NCT and HAC, as the temperature limit for carbon steel of 2600°F (1427°C) is well above this maximum experienced temperature. Since the 5-inch pipe can retain pressure, when the package heats up the pressure inside the pipe will increase slightly. Considering the pipe closed at 70°F (529.7°R) and heated to 429°F (888.7°R), the maximum pressure inside the pipe due to the increase in temperature is calculated using the ideal gas law as:

T! 888.7°R P! = P" = 14.7 psia = 25 psia = 10.3 psig T" 529.7°R The working pressure rating of standard 5-inch schedule 40 pipe and manufactured pipe cap is 580 psig. With the addition of the bottom plate, the pipe container forms a pressure retaining vessel. The maximum stress at the edge of the bottom plate [22], sxmax, is:

sxmax = $

x (&

= 955 psi

Where, a = 2.78 in, outside radius of bottom plate t = 0.25 in, thickness of bottom plate 2-24

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Comparing the maximum stress to the yield strength of 29,300 psi at 500°F for A36 carbon steel, the margin of safety is +30. Therefore, the ability of the 5-inch pipe to confine the fissile material will not be compromised due to the temperature increase from a fire accident.

2.7.4.2 Differential Thermal Expansion As discussed in Section 2.6.1.2, the materials used to fabricate the Versa-Pac and the arrangement of the packaging limit the effects of differential thermal expansion. No significant stresses are generated as a result of differential thermal expansion.

2.7.4.3 Stress Calculations Due to the decoupled design of the packaging, thermal stresses generated by the packaging are negligible.

2.7.5 Immersion - Fissile Material Moderator inleakage to the most reactive credible extent is assumed for the Versa-Pac and evaluated in Section 6.0. Thus, the fissile material immersion test is not required.

2.7.6 Immersion - All Packages A separate, undamaged specimen must be subjected to water pressure equivalent to immersion under a head of water of at least 50 ft (15 m). For test purposes, an external pressure of water of 21.7 lbf/in2 (150 kPa) gauge is considered to meet these conditions.

Test Program #1 As indicated in Reference [16], a similar damaged prototype was placed in an immersion chamber at 23 psig for 15 minutes. The package was removed from the immersion chamber with no damage to the outer structure. The outer drum lid was removed, and the inner vessel was inspected with no damage noted.

2.7.7 Deep Water Immersion Test This section is not applicable to the Versa-Pac Shipping Package.

2.7.8 Summary of Damage This section summarizes the condition of the package after each test sequence. Table 2-5 provides a summary of the test performed on the Versa-Pac and the final results. In all cases, the package results were acceptable and met the applicable acceptance standards. Table 2-6 provides a summary of the maximum damage resultant from all tests. These measurements are used as the basis for the NCT and HAC criticality safety models.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 Table 2-5. Summary of NCT and HAC Test Results Test Test Description Results Reference Program #

1 Immersion Test Passed [16]

2 NCT and HAC Certification Test Series Passed [17]

Series 1 1A NCT 4' (1.2 m) Top End Drop 1B HAC 30' (9 m) Top End Drop 1C HAC 40 (1 m) Puncture - Side Series 2 2A NCT 4' (1.2 m) Side Drop 2B HAC 30' (9 m) Side Drop 2C HAC 30' (9 m) Dynamic Crush - Side Series 3 3A NCT 4' (1.2 m) C.G. Over Drum Ring 3B HAC 30' (9 m) C.G. Over Drum Ring 3C HAC 30' (9 m) Shallow Angle Drop 3D HAC 40 (1 m) Puncture - C.G. Over Drum Ring 3 Shallow Angle Drop Tests Passed [18]

1-55-A NCT 4 (1.2 m) Shallow Angle Drop (slap down) 1-55-B HAC 30 (9 m) Shallow Angle Drop (slap down) 1-55-C HAC 40 (1 m) Puncture - C.G. Over Drum Ring 4 NCT Penetration and Stacking Tests Passed [19]

5 5 Pipe Container Drop Tests Passed [20]

9.1 HAC 30 (9 m) Shallow Angle Drop (slap down) 9.2 HAC 30' (9 m) Top End Drop 9.3 HAC 30' (9 m) C.G. Over Corner Drop (pipe cap) 6 NCT and HAC Test Series at 750 lb Max Gross Weight Passed [21]

2.1 HAC 4' (1.2 m) C.G. Over Drum Ring 2.2 HAC 30' (9 m) C.G. Over Drum Ring 2.3 HAC 30' (9 m) Dynamic Crush - Side 2.4 HAC 40 (1 m) Puncture - Lid Center 2.7.8.1 Test Program #1 - Immersion Test A prototype of a similar package using the same closure system and structural design was subjected to hydrostatic testing after thermal testing with pressures that exceed the immersion test requirement [16]. The results of the test showed the containment closure system was in good condition with no damage. No damage to the outer drum reinforcement or inner cavity was noted.

No inleakage of water into the containment cavity occurred.

2.7.8.2 Test Program #2 - Versa-Pac NCT and HAC Drop Testing Based upon the information obtained from prototype drop testing, design changes were made to increase the blind flange (PD) thickness to 1/2 inch, and the inner containment closure bolt torque was increased to 60 lb-ft [17].

Test Series #1 The series of test conducted included a 4-foot top end drop, a 30-foot top end drop and a horizontal side puncture drop. Prior to testing, all closure bolts recorded a torque of 60 lb-ft. Prior to opening of the test package, the outer bolts were torqued, and readings were found to be between 20 and 80 lb-ft. with all bolts intact. After opening the test article, photographs were taken 2-26

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 and the interior well surfaces inspected with no damage found. The flange remained flat, sealed and no loss of the payload contents was found outside the containment cavity. The bolts of the inner blind flange were torqued and found to have readings of between 30 to 50 lb-ft. The gaskets and payload cavity were in good condition. Following the side puncture, deformation in the side of the test article was measured at a depth of 3/8 inch. There were no tears as a result of the puncture drop.

Test Series #2 The test article series of drops included a 4-foot horizontal side drop, a 30-foot horizontal side drop and a 30-foot crush plate side drop. Although the outer drum ring became dislodged, the package remained closed and in place due to the additional top closure bolts. The outer closure bolts of the top cover were torqued and recorded a reading of 25 lb-ft. Upon removal of the outer lid, an inspection revealed a slight interior wall deformation in the upper plug well of the package.

There was no loss of contents. The containment flange was in good condition and the bolts recorded a torque of 25 lb-ft. Gaskets were in good condition. The containment lid exhibited some bending from the piston action of the internal gravel and sand acting on the blind flange. Upon removal of the inner containment payload, a visual inspection was conducted with no damage shown within the inner containment cavity.

Test Series #3 This series consisted of a 4-foot center of gravity drop, a 30-foot center of gravity drop, a 30-foot shallow angle drop, and a center of gravity puncture drop. Upon completion of these drops, the test package outer closure bolts were torqued with readings found to be less than 20 lb-ft.

Photographs were taken and an inspection of the inner well area found only minor deformation to the sidewalls no other damage was found. The inner containment blind flange was flat and sealed with no loss of materials from within the inner containment cavity. Bolt torque of the inner flange closure ranged from 20 to 40 lb-ft. The conclusion of this series is that the design changes of increasing the blind flange thickness, increasing the torque requirement and the reinstallation of the flange inside pad were found to provide acceptable results.

2.7.8.3 Test Program #3 - Versa-Pac VP-55 Shallow Angle and Puncture Drops This program consisted of the test sequence that included a 4-foot shallow angle drop (17° from horizontal), a 30-foot shallow angle drop, and 1 meter puncture positioned with center of gravity over drum closure ring bolt [18]. This series of testing was conducted to provide additional information and verification that the VP-55 design would meet the same requirements at the previously tested VP-110 when subjected to the effects of both NCT and HAC shallow angle drops (slap down) [18].

Results of the test series showed that the outer closure was retained with no openings, tears or failure that would lead to the loss of material, no open pathway to the insulation materials and no loss of the inner containment payload. The overall diameter of the package through the impact area was reduced by 1/2 but remained the same in the opposite direction. Outer closure bolts were recorded with a post-test torque of 42 to 55 lb-ft with the bolt at the impact area at 49 lb-ft.

The outer lid was removed and no loss of containment or damage to the inner containment blind flange was found. The bolt torque of the inner blind flange was found to range between 30-50 lb-ft.

The gaskets and the internal cavity of the containment were found to be in good condition with no damage. Therefore, the VP-55 design demonstrated that it is capable of meeting the requirements set forth in 10 CFR 71 [2].

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.7.8.4 Test Program #4 - NCT Penetration and Compression Test The test article previously used in Test Program #3 was used to evaluate the performance of the Versa-Pac for the NCT penetration and stacking tests [19].

The penetration device consisted of a 1.25-inch diameter carbon steel round bar, weighing 13.2 pounds. The test article was positioned horizontally on a flat concrete floor with the penetration bar positioned vertically directly over one of three target areas: the sidewall over vertical stiffener, sidewall between vertical stiffeners and top drum lid. The bar was lifted to a height 40 inches (1 meter) and allowed to be released through a 2-inch PVC guide tube to provide the correct impact on the surface of the test package. The result of this impact to the sidewall of the test articles resulted in un-measurable damage to the package impact area and only slight marring of the package paint.

For the compression test, the test article was positioned vertically so that the load was directly applied to the top of the package. The test article weighed 624.5 pounds. To meet the requirement of 5 times the weight of the package; a load of 3,200 pounds was loaded on the top surface of the package for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. No damage or buckling of the package was noted upon inspection of the test article.

Review of the penetration and compression test shows that the Versa-Pac complies with the applicable regulations.

2.7.8.5 Test Program #5 - HAC 5 Pipe Container Drop Tests A new pipe container is fabricated per drawing VP-55-2R and tested without the protection provided by the Versa-Pac container. Steel shot was used to simulate the contents with sufficient ullage to induce a piston action on the pipe cap during impact [20]. Three individual test articles in three different orientations were dropped from a height of 30 feet onto an unyielding surface.

The first test article was dropped from a height of 30 feet in an oblique orientation, measured from the top of the target to the lowest point of the specimen at an angle of 15.9° from horizontal onto the bottom plate. After the drop, the damage consisted of a 1-3/16x3/16 dent to the container cap and a 1-3/8x1/16 dent to the bottom plate. The second test specimen was dropped from a height of 30 feet in the top end down position, measured from the top of the target to the lowest point on the bottom surface of the specimen. The third test specimen was dropped from a height of 30 feet in the C.G. over corner position onto the pipe cap, measured from the top of the target to the lowest point on the bottom surface of the specimen. The angle of orientation of the specimen was measured 12.5° from vertical. After the drop, there was a small dent noted on the pipe cap measuring 1-1/2x3/8 with no measurable damage on the rest of the container. After all drop tests, no release of the contents was observed. The results of the test series show that the VP-55-2R is capable of maintaining the safe geometry of the confinement vessel without failure or loss of material.

2.7.8.6 Test Program #6 - NCT and HAC Test Series at 750 lb Max Gross Weight This drop testing program was performed to increase the minimum VP-55 payload capacity to 350 lb. This program includes both NCT and HAC Free Drops and is presented in Reference [21].

The same test article was used for both the NCT and HAC test sequence. The NCT and HAC drop tests were performed in sequence. First, in an effort to loosen or dislodge the drum closure ring, the NCT 4-foot free drop was performed with the packages C.G. positioned over the drum lid closure ring bolt. Second, the package was dropped from 30 feet in the top C.G. over drum lid 2-28

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 ring 180° from the closure bolt. Third, the dynamic crush test was performed by positioning the package on the drop test pad rotated 90 degrees from the previous point of impact. Fourth, the package was subjected to the 40-inch puncture test by dropping the package top end down onto the center of the lid.

Following each test, the package was inspected with a black light and no evidence of fluorescein around the lid closure was noted. Therefore, containment of material was maintained. Mechanical damaged included localized tearing of the drum ring. However, the drum ring remained in place and no failure of the lid closure bolts occurred.

Table 2-6. Versa-Pac Test Package Dimensional Changes Maximum Description Test Program Test Series Deformation in. (cm)

NCT Inner Container ID Outer Container OD 2 3A -1/8 (-0.318)

Drum Height HAC Inner Container ID 2 3 +1/8 (+0.318)

Outer Container OD 2 3B -1 3/16 (-3.016)

Drum Height 2 1B -1/4 (-0.635)

Note: denotes no dimensional change.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.8 Accident Conditions for Air Transport of Plutonium This section is not applicable to the Versa-Pac.

2.9 Accident Conditions for Fissile Material Packages for Air Transport This section is not applicable to the Versa-Pac. The criticality analysis for Versa-Pac packages transported by air assumes ejection of all contents from the packaging into a bounding configuration (See Section 6.7). Thus, no structural testing/analyses are necessary for Versa-Pac shipments via air transport.

2.10 Special Form Special form material as defined in 10 CFR 71 is not applicable to the Versa-Pac.

2.11 Fuel Rods This section is not applicable to the Versa-Pac.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, Feb 2021 2.12 References

[1] United States Department of Transportation (USDOT), "Code of Federal Regulations, Title 49:

Transportation," § 178.360, Washington, D.C., 2004.

[2] Nuclear Regulatory Commission (NRC), "Title 10, Part 71-Packaging and Transportation of Radioactive Material".

[3] Nuclear Regulatory Commission (NRC), "Title 10, Part 71-Packaging and Transportation of Radioactive Material, Subpart H - Quality Assurance".

[4] American Welding Society (AWS), "D1.1/D1.1M:2010, Structural Welding Code - Steel".

[5] The American Society for Nondestructive Testing, Inc., "Recommended Practice No. SNT-TC-1A Personnel Qualification and Certification in Nondestructive Testing," 2006.

[6] International Atomic Energy Agency (IAEA), "Regulations for the Safe Transport of Radioactive Material, SSR-6, 2012 Edition".

[7] Daher-TLI, "Quality Assurance Program Description," QAPD1, Rev. 3, 2020.

[8] R. B. Ross, Metallic Materials Specification Handbook, 4th Edition, London: Chapman and Hall, 1992.

[9] General Plastics, "Design Guide LAST-A-FOAM FR-3700 Crash & Fire Protection of Radioactive Material Shipping Containers".

[10] The American Society of Mechanical Engineers (ASME), "Boiler and Pressure Vessel Code, BPVC-IX -- Section IX, Welding and Brazing Qualifications," 2015.

[11] United States Department of Transportation (USDOT), "Title 49, Code of Federal Regulations Part 178, Specifications for Packagings, Subpart MTesting of Non-bulk Packagings and Packages".

[12] Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards, "Drop Test Results for the Combustion Engineering Model No. ABB-2901 Fuel Pellet Shipping Package,"

NUREG/CR-6818, Washington, D.C., 2003.

[13] Savannah River Site (SRS), "Drop Test for the 6M Specification Closure Investigation," M-TRT-A-00002 Rev. 0, Aiken, SC, 2003.

[14] American National Standards Institute, "Uranium Hexafluoride - Packagings for Transport," ANSI N14.1.

[15] MACTEC Engineering & Consulting, Inc., "Corrosion of Carbon and Stainless Steel in Contact with Foam," Project 6230-03-0989, Charlotte, NC, 2004.

[16] Daher-TLI, "Century Champion Type B Package Immersion Test as Analogue for the Versa-Pac Type A Package," TR-20000-130-001, Rev. 0, Fulton, MD, 2021.

[17] Century Industries, "Test Report Performance Test Series of Century Industries Model VP-55 & VP-110 Versa-Pac Shipping Container," Bristol, VA, 2009.

[18] Century Industries, "Test Report Performance Evaluation Test Series of Century Industries Model VP-55 Versa-Pac Shipping Container," Bristol, VA, 2009.

[19] Century Industries, "NCT Evaluation Test Series (Compression & Penetration) of Century Industries Versa-Pac Shipping Container," Bristol, VA, 2009.

[20] Daher-TLI, "5-Inch Container Drop Test Report," TR-20000-050-102, Rev. 0, Fulton, MD, 2015.

[21] Daher-TLI, "55 Gallon Versa-Pac Drop Test Deformation Measurement Report," TR-20000-100-001, Fulton, MD, 2017.

[22] P. John F. Harvey, Theory and Design of Pressure Vessels, Second Edition, New York: Van Nostrand Reinhold, 1991.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 CONTENTS 3 THERMAL EVALUATION ....................................................................................................... 3-1 3.1 Description of the Thermal Design ........................................................................................ 3-2 3.1.1 Design Features ........................................................................................................................................ 3-2 3.1.2 Contents Decay Heat .............................................................................................................................. 3-3 3.1.3 Summary Tables of Temperatures ................................................................................................... 3-4 3.1.4 Summary Tables of Maximum Pressures ...................................................................................... 3-5 3.2 Material Properties and Component Specifications ........................................................ 3-6 3.2.1 Material Properties ................................................................................................................................. 3-6 3.2.2 Component Specifications .................................................................................................................... 3-9 3.3 Thermal Evaluation for Normal Conditions of Transport (NCT) ............................... 3-11 3.3.1 Heat and Cold .......................................................................................................................................... 3-13 3.3.2 Maximum Normal Operating Pressure ........................................................................................ 3-21 3.4 Thermal Evaluation for Hypothetical Accident Conditions (HAC) ............................ 3-22 3.4.1 Initial Conditions ................................................................................................................................... 3-22 3.4.2 Fire Test Conditions ............................................................................................................................. 3-23 3.4.3 Maximum Temperatures and Pressure ....................................................................................... 3-25 3.4.4 Maximum Thermal Stresses ............................................................................................................. 3-28 3.4.5 Accident Conditions for Fissile Material Packages for Air Transport ............................ 3-28 3.5 Appendix ....................................................................................................................................... 3-29 3.5.1 References ................................................................................................................................................ 3-30 3.5.2 Thermal Analysis of 1S/2S UF6 Cylinders in the VP-55........................................................ 3-31 3.5.3 Thermal Analysis of the VP-55 with no Containment Insulation Plug .......................... 3-47 3.5.4 Supporting Classical Equations....................................................................................................... 3-59 3-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 TABLES TABLE 3-1 VERSA-PAC OVERALL AND THERMAL INSULATION DIMENSIONS ....................................................................................... 3-3 TABLE 3-2 NCT STEADY STATE THERMAL EVALUATION RESULTS - STANDARD VERSA-PAC CONFIGURATION .......................... 3-4 TABLE 3-3 HAC TRANSIENT THERMAL EVALUATION RESULTS - STANDARD VERSA-PAC CONFIGURATION ................................ 3-5 TABLE 3-4 THERMAL PROPERTIES OF ASTM A-36 CARBON STEEL .................................................................................................... 3-6 TABLE 3-5 THERMAL PROPERTIES OF SERIES 525 FIBERGLASS ............................................................................................................ 3-7 TABLE 3-6 THERMAL PROPERTIES OF CERABLANKET (6 PCF) ............................................................................................................... 3-7 TABLE 3-7 THERMAL PROPERTIES OF DRY AIR ........................................................................................................................................ 3-8 TABLE 3-8 THERMAL PROPERTIES OF 12-PCF POLYURETHANE FOAM ................................................................................................. 3-8 TABLE 3-9 THERMAL EMISSIVITY VALUES ................................................................................................................................................. 3-9 TABLE 3-10 TEMPERATURE LIMITS ......................................................................................................................................................... 3-10 TABLE 3-11

SUMMARY

OF NCT BOUNDARY CONDITIONS ................................................................................................................... 3-12 TABLE 3-12 INSOLATION DATA ................................................................................................................................................................ 3-13 TABLE 3-13 NCT STEADY STATE THERMAL EVALUATION RESULTS ................................................................................................. 3-18 TABLE 3-14 HAC TRANSIENT THERMAL EVALUATION

SUMMARY

RESULTS .................................................................................... 3-25 TABLE 3-15

SUMMARY

OF BOUNDARY CONDITIONS ............................................................................................................................. 3-32 TABLE 3-16 THERMAL PROPERTIES OF POLYETHYLENE FOAM .......................................................................................................... 3-33 TABLE 3-17 NCT STEADY STATE RESULTS - 1S/2S UF6 CYLINDER VP-55 CONFIGURATION .................................................... 3-36 TABLE 3-18 HAC FIRE TRANSIENT RESULTS - 1S/2S UF6 CYLINDER VP-55 CONFIGURATION ................................................ 3-42 TABLE 3-19

SUMMARY

OF BOUNDARY CONDITIONS ............................................................................................................................. 3-48 TABLE 3-20 NCT STEADY STATE THERMAL EVALUATION RESULTS -VP-55 CONFIGURATION WITHOUT CONTAINMENT INSULATION PLUG .............................................................................................................................................................................. 3-51 TABLE 3-21 HAC TRANSIENT THERMAL EVALUATION RESULTS - VP-55 CONFIGURATION WITHOUT CONTAINMENT INSULATION PLUG .............................................................................................................................................................................. 3-55 TABLE 3-22 CONSTANTS 'C' AND 'M' FOR THE NUSSELT NUMBER CALCULATION OF A CYLINDER IN CROSS FLOW .................. 3-61 3-ii

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 FIGURES FIGURE 3-1 VP-55 QUARTER SYMMETRY THERMAL MODEL ................................................................................................................. 3-1 FIGURE 3-2 QUARTER SYMMETRY FINITE ELEMENT MODEL OF THE VP-55 ................................................................................... 3-12 FIGURE 3-3 NCT BOUNDARY CONDITIONS FOR CASE I (HOT: INTERNAL WATTAGE + SOLAR INSOLATION) ............................ 3-14 FIGURE 3-4 NCT BOUNDARY CONDITIONS FOR CASE II (HOT: INTERNAL WATTAGE + NO SOLAR INSOLATION)..................... 3-15 FIGURE 3-5 NCT BOUNDARY CONDITIONS FOR CASE III (COLD: INTERNAL WATTAGE + NO INSOLATION) ............................. 3-16 FIGURE 3-6 NCT BOUNDARY CONDITIONS FOR CASE IV (COLD: NO INTERNAL WATTAGE + NO INSOLATION) ....................... 3-17 FIGURE 3-7 NCT TEMPERATURE CONTOUR-CASE I (HOT: INTERNAL WATTAGE + SOLAR INSOLATION) ................................... 3-19 FIGURE 3-8 NCT TEMPERATURE CONTOUR-CASE II (HOT: INTERNAL WATTAGE + NO INSOLATION)....................................... 3-19 FIGURE 3-9 NCT TEMPERATURE CONTOUR-CASE III (COLD: INTERNAL WATTAGE + NO INSOLATION) ................................... 3-20 FIGURE 3-10 NCT TEMPERATURE CONTOUR-CASE IV (COLD: NO INTERNAL WATTAGE + NO INSOLATION) .......................... 3-20 FIGURE 3-11 NCT RESULTS AS INITIAL CONDITIONS OF HAC ............................................................................................................ 3-22 FIGURE 3-12 HAC FIRE BOUNDARY CONDITIONS ................................................................................................................................. 3-23 FIGURE 3-13 HAC COOL-DOWN (POST-FIRE) BOUNDARY CONDITIONS .......................................................................................... 3-24 FIGURE 3-14 VP-55 HAC PACKAGE TEMPERATURE-TIME HISTORY PLOT .................................................................................... 3-26 FIGURE 3-15 VP-55 HAC CONTAINMENT TEMPERATURE-TIME HISTORY PLOT .......................................................................... 3-26 FIGURE 3-16 HAC THERMAL ANALYSIS MAXIMUM TEMPERATURE CONTOURS .............................................................................. 3-27 FIGURE 3-17 HAC THERMAL ANALYSIS MAXIMUM TEMPERATURE CONTOURS AT SEVERAL TIMES ........................................... 3-28 FIGURE 3-18 ANSI N14.1 1S CYLINDER ................................................................................................................................................ 3-31 FIGURE 3-19 ANSI N14.1 2S CYLINDER ................................................................................................................................................ 3-31 FIGURE 3-20 QUARTER SYMMETRY FINITE ELEMENT MODEL OF THE VERSA-PAC ........................................................................ 3-34 FIGURE 3-21 NCT BOUNDARY CONDITIONS ........................................................................................................................................... 3-35 FIGURE 3-22 NCT EVALUATION PACKAGE TEMPERATURE CONTOUR ............................................................................................... 3-37 FIGURE 3-23 NCT TEMPERATURE CONTOUR SHOWING INTERIOR SURFACE OF FOAM INSERT .................................................... 3-37 FIGURE 3-24 HAC FIRE INITIAL BODY TEMPERATURE ........................................................................................................................ 3-38 FIGURE 3-25 HAC FIRE BOUNDARY CONDITIONS ................................................................................................................................. 3-39 FIGURE 3-26 HAC POST FIRE COOL DOWN BOUNDARY CONDITIONS ............................................................................................... 3-40 FIGURE 3-27 VP-55 1S/2S UF6 CYLINDERS - CONTAINMENT INNER SURFACE TEMP. WITH FOAM LINERS .......................... 3-41 FIGURE 3-28 VP-55 1S/2S UF6 CYLINDERS ENTIRE PACKAGE HAC TEMPERATURE HISTORY................................................. 3-43 FIGURE 3-29 VP-55 1S/2S UF6 CYLINDERS PACKAGE CONTAINMENT HAC TEMPERATURE HISTORY ................................... 3-44 FIGURE 3-30 HAC THERMAL ANALYSIS MAXIMUM TEMPERATURE CONTOUR ................................................................................ 3-45 FIGURE 3-31 HAC THERMAL ANALYSIS PACKAGE MAXIMUM TEMPERATURE CONTOUR AT DIFFERENT TIMES....................... 3-46 FIGURE 3-32 VP-55 WITHOUT CONTAINMENT INSULATION PLUG (PART IG) ............................................................................... 3-47 FIGURE 3-33 FINITE ELEMENT MODEL OF THE VERSA PACK QUARTER SYMMETRY MODEL ........................................................ 3-49 FIGURE 3-34 NCT BOUNDARY CONDITIONS ........................................................................................................................................... 3-50 FIGURE 3-35 NCT EVALUATION PACKAGE TEMPERATURE CONTOUR ............................................................................................... 3-52 FIGURE 3-36 NCT TEMPERATURE CONTOUR INTERIOR SURFACE ..................................................................................................... 3-52 FIGURE 3-37 HAC FIRE BOUNDARY CONDITIONS ................................................................................................................................. 3-53 FIGURE 3-38 HAC POST FIRE COOL DOWN BOUNDARY CONDITIONS ............................................................................................... 3-54 FIGURE 3-39 VP-55 ENTIRE PACKAGE HAC TEMPERATURE HISTORY (WITHOUT CONTAINMENT INSULATION PLUG)

MAXIMUM TEMPERATURE HISTORY ............................................................................................................................................... 3-56 FIGURE 3-40 VP-55 (WITHOUT CONTAINMENT INSULATION PLUG) CONTAINMENT TEMPERATURE HISTORY ....................... 3-56 FIGURE 3-41 HAC THERMAL ANALYSIS CONTAINMENT MAXIMUM TEMPERATURE CONTOURS .................................................. 3-57 FIGURE 3-42 HAC THERMAL ANALYSIS PACKAGE MAXIMUM TEMPERATURE CONTOUR DURING FIRE AND COOL DOWN ..... 3-58 3-iii

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3 THERMAL EVALUATION This chapter documents the thermal performance of the Versa-Pac (Figure 3-1) during Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) per the requirements of 10 CFR 71.71 and 10 CFR 71.73, respectively [1]. The thermal analysis results show that the NCT maximum exterior surface temperature meets the non-exclusive use shipment requirement of 10 CFR 71 § 71.43(g). During HAC, the inner cavity stays below 600°F (316°C). Therefore, it can be predicted that the contents will remain in solid form because the radioactive content is a stable solid that does not undergo a change of state below 600°F (316°C). For the 1S/2S UF6 Cylinder configuration, the inner cavity temperature reaches a maximum temperature of 245°F (118°C) during HAC, which is less than the 250°F (121°C) limit established in Table 1 of ANSI N14.1 [2]. To transport 1S/2S cylinders, the inner cavity of the VP-55 must be lined with a minimum 2 inch (5.08 cm) thick polyethylene foam liner with a minimum foam density of 9 pcf (144 kg/m3). For the case where the containment insulation plug Part (IG) is removed, the maximum inner cavity temperature is 425°F (218°C) during HAC.

Drum Lid (Part DL)

Polyurethane Foam Plug (Part IC)

Containment Lid (Part PD)

Air Gaps Containment Foam Plug (Part IG) 55 Gallon Drum (Part DA)

Ceramic Blanket (Part IA)

Cavity Air Containment End Plate (Part PB)

Polyurethane Foam Plug (Part ID)

Ceramic Paper (Part ID)

Figure 3-1 VP-55 Quarter Symmetry Thermal Model 3-1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 3.1 Description of the Thermal Design 3.1.1 Design Features The VP-55 Versa-Pac consists of a 10ga containment body, with payload cavity nominal dimensions of a 15 diameter and 23-1/8 height, centered within an insulated 55-gallon drum.

Detail drawings of the VP-55 are provided in the VP-55 licensing drawing in Appendix 1.4.1.

The nominal exterior dimensions of the assembled VP-55 are 23-3/16 diameter and 34-3/4 height. The payload cavity is protected from water intrusion with a gasketed lid that is closed with twelve 1/2 diameter bolts. Under the containment lid, there is a 3 thick polyurethane insulation plug for added thermal insulation when the contents require extra protection. Exterior to the containment lid, the 55-gallon drum lid is modified with a 20ga steel encapsulated polyurethane insulation plug. The gasketed drum lid is closed with four 1/2 diameter bolts and a standard drum ring. A gasket at the drum lids stiffening ring provides a third barrier against water in-leakage.

The 55-gallon drum is strengthened with four longitudinal stiffeners fabricated from 1-1/4 carbon steel square tubing equally spaced around the circumference of the drum. The outer and inner liners provide additional radial stiffness to the drum. A 1/2 thick fiberglass ring and fiberglass spacers are used as thermal breaks at the payload cavity flange. The thermal breaks are sandwiched between the steel components and effectively limit the flow of heat to the payload cavity through the steel flange components. The volume between the inner liner and the 10ga containment body is filled with ceramic blanket insulation. Furthermore, the bottom of the containment body is insulated with polyurethane foam and the gap on the bottom, between the bottom reinforcing plate and the drum bottom, is filled with sheets of ceramic paper (Appendix 1.4.1).

The VP-110 consists of a 10ga containment body, with payload cavity nominal dimensions of 21 diameter and 29-3/4 height, centered within an insulated 110-gallon drum. Detail drawings of the VP-110 are provided in the VP-110 licensing drawing in Appendix 1.4.1. The nominal exterior dimensions of the assembled VP-110 package are 30-7/16 diameter and 42-3/4 height. The basic design of the VP-110 is identical to that of the 55-gallon Versa-Pac, except for the larger exterior dimensions and payload cavity dimensions. The thickness of the walls and insulation remain the same.

The Versa-Pac design allows for the use of two neoprene pads, a 1/8 bottom pad, and a 3/8 top pad. The pads serve the purpose of protecting the inner containment shell during repeated use.

The use of these pads is optional. The Versa-Pac overall and thermal insulating components dimensions are documented in Table 3-1 below.

As documented in this section, the basic design of the VP-110 is identical to that of the VP-55, except for the larger exterior diameter and payload cavity diameter. The thickness of the walls and insulation remain the same. Further, the payload heat decay in the VP-110 model is the same as that of the VP-55. However, because VP-110 is larger in size, the volumetric decay heat load is less than that of VP-55. Therefore, the VP-55 analysis bounds the VP-110.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 Table 3-1 Versa-Pac Overall and Thermal Insulation Dimensions Stock Part Name VP-55 VP-110 Number Payload Cavity Nominal N/A 15 ID x 23-1/8 21 ID x 29-3/4 Package Exterior Nominal N/A 23-3/16OD x 34-3/4 30-7/16OD x 42-3/4 Ceramic Blanket Insulation IA 1-1/2 - 2 thick 1-1/2 - 2 thick Fiberglass Ring IE 1/2 thick 1/2 thick Fiberglass Spacers IF 1/2 thick 1/2 thick Plug Insulator-Drum Lid IC 19 Dia. x 2-5/16 thick 26-4/8 Dia. x 3-7/16 thick Air Gap Above Containment Lid N/A 5/8 1 Containment Insulation Plug IG 14-7/8 Dia. x 3 thick 20-7/8 Dia. x 3 thick Plug Insulator-Bottom Body IB 2-3/4 thick 2-3/8 thick 1/8-thick sheets (at least 1/8 thick sheets (at least Ceramic Paper ID one sheet) one sheet)

Reference:

Appendix 1.4.1 3.1.2 Contents Decay Heat The decay heat for the payload is limited to 11.4 W total for the VP-55 and VP-110, with no single item having a decay heat greater than 20 W/m3.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.1.3 Summary Tables of Temperatures 3.1.3.1 NCT Temperature Summary Per the requirements of 10 CFR 71.71(c)(1), the Versa-Pac standard configuration, the VP-55 1S/2S UF6 cylinder configuration, and the VP-55 without the containment insulation plug part (IG) configuration are evaluated for Normal Conditions of Transport. This includes a steady-state thermal analysis simulating exposure to a 100°F (37.8°C) ambient temperature in still air and insolation as specified in Table 3-12. The temperatures of key components are summarized in Table 3-2 for the standard configuration, 1S/2S, and No IG, with the full NCT results in Section 3.3, Appendix 3.5.2.4, and Appendix 3.5.3.4, respectively.

Table 3-2 NCT Steady State Thermal Evaluation Results - Standard Versa-Pac Configuration Temperature °F (°C) Maximum Part Component Allowable Number VP-55 1S/2S No IG Temp °F (°C)

Containment body PA 147 (64) 139 (59) 147 (64)

Containment end plate PB 147 (64) 134 (57) 147 (64)

Containment insulation plug IG 177 (80) 139 (59) 270 (132)

Gasket GB 143 (61) 139 (59) 143 (62) 500 (260)

Containment lid (Blind flange) PD 143 (62) 139 (59) 143 (62)

Drum lid DL 154 (68) 154 (68) 154 (68)

Drum lid gasket GA 144 (62) 144 (62) 145 (63)

Drum DA 144 (62) 143 (62) 144 (62)

Package surface DA/DL 154 (68) 154 (68) 154 (68)

Air Volume Maximum 232 (111) 600 (316)

Air Volume Average 191 (88) 600 (316)

Containment Cavity Surface 147 (64) 600 (316)

Foam liner for 1S/2S Cylinder 138 (59) 250 (121) 3-4

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.1.3.2 HAC Temperature Summary The Versa-Pac must survive the HAC thermal analysis such that containment is maintained, and the structural integrity is sufficient for the criticality control credited in Section 6. The temperatures of key components are summarized in Table 3-3 for the standard configuration, 1S/2S, and No IG, with the full HAC results in Section 3.4., Appendix 3.5.2.5 and Appendix 3.5.3.5, respectively.

As shown in Table 3-3, the HAC fire does not adversely affect the Versa-Pacs structural or containment configurations. The Inner Cavity Air Volume remains below 600°F (316°C) for the Versa-Pac standard configuration. For the 1S/2S UF6 cylinder configuration results, the foam liner surface temperature remains below the maximum UF6 cylinder temperature of 250°F (121°C), as stated in Table 1 of ANSI N14.1-2012. For the case where the containment insulation plug Part (IG) is removed, the maximum inner cavity temperature is 425°F (218°C) which is also below 600°F (316°C) for the Versa-Pac standard configuration.

Table 3-3 HAC Transient Thermal Evaluation Results - Standard Versa-Pac Configuration Temperature °F (°C) Maximum Part Component Allowable Temp Number VP-55 1S/2S No IG °F (°C)

Air volume maximum 399 (204) 600 (316)

Air volume average 351 (177) 600 (316)

Foam liner average 221 (105) 250 (121)

Foam liner inner surface 245 (118) 250 (121)

Containment cavity surface 380 (193) 425 (218) 600 (316)

Containment plug surface IG 380 (193) 340 (171) 600 (316)

Containment lid (Blind flange) PD 423 (217) 413 (212) 433 (223) 2600 (1427)

Containment body PA 412 (211) 400 (204) 423 (217) 2600 (1427)

Containment Gasket GB 425 (219) 416 (213) 436 (224) 1000 (538)

Inner flange PH 434 (223) 425 (219) 445 (229) 2600 (1427)

Drum lid DL 1457 (792) 1456 (791) 1456 (791) 2600 (1427)

Drum DA 1461 (794) 1460 (793) 1460 (793) 2600 (1427) 3.1.4 Summary Tables of Maximum Pressures Due to permeation in the silicone coating of the cavity seal, the maximum normal and HAC operating pressure are expected to be near atmospheric pressure. However, based on the maximum cavity temperatures, the maximum hypothetical pressures for NCT and HAC are approximately 3.3 psig (124 kPa) and 9.8 psig (169 kPa), respectively. Both are well below the 15 psig (205 kPa) containment pressure rating. Thus, the Versa-Pac meets the requirements of 10 CFR 71 [1].

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 3.2 Material Properties and Component Specifications 3.2.1 Material Properties The thermal properties for the Versa-Pac are presented in the following subsections. When available, temperature-dependent properties were used in the analyses. These properties are listed for both the materials of construction of the Versa-Pac and the air fill gas in the inner cavity.

3.2.1.1 ASTM A-36 Carbon Steel The steel of the Versa-Pac is modeled as ASTM A-36 carbon steel with the temperature-dependent thermal conductivities, thermal diffusivities, and specific heats as listed in Table 3-4.

Table 3-4 Thermal Properties of ASTM A-36 Carbon Steel Thermal Thermal Temperature Density Specific Heat 2 Conductivity Diffusivity

(°F) 1 (lbm/ft3) (BTU/lbm*°F)

(BTU/hr*ft*°F) (ft2/hr) 70 (21) 34.9 0.700 0.103 100 (38) 34.7 0.676 0.106 250 (121) 33.0 0.585 0.117 300 (149) 32.3 0.560 0.119 500 (260) 483.84 29.4 0.474 0.128 700 (371) 26.6 0.394 0.140 900 (482) 23.8 0.318 0.155 1000 (538) 22.4 0.283 0.164 1500 (816) 15.5 0.166 0.193

Reference:

[3] Density: Table PRD, Carbon steels, Page 744.

[3] Thermal Properties: Table TCD, Material Group A - Plain Carbon, Page 726.

Note: 1 See Assumption 5.2.1.b regarding this gap in temperature data.

2 Specific Heat calculated using the following formula: SH = TC/*TD.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 3.2.1.2 Series 525 Fiberglass This fiberglass component is used to provide thermal break. The material consists of a glass fiber reinforced polyester or vinyl ester resin matrix with glass reinforcements. The thermal properties of this fiberglass are documented in Table 3-5. Because the density is provided with a tolerance band, the highest value is conservatively used in this thermal analysis.

Table 3-5 Thermal Properties of Series 525 Fiberglass Temperature Density Thermal Conductivity

°F (°C) (lbm/in3) (BTU*in/hr*ft2*°F) 75 (24) 0.062 - 0.070 4.0

Reference:

Appendix 1.4.5: Density and Thermal Conductivity.

3.2.1.3 Cerablanket Cerablanket is used as an insulating material with material properties as documented in Table 3-6. As documented in Section 1.4.4, the Cerablanket can be either 6 pcf or 8 pcf. Because the thermal conductivity of Cerablanket decreases as density increases (Appendix 1.4.4), the 6 pcf is assumed to let more heat into the package during hypothetical fire accident. Therefore, the 6 pcf foam is conservatively used in this analysis.

Table 3-6 Thermal Properties of Cerablanket (6 pcf)

Temperature Density Thermal Conductivity Specific Heat

°F (°C) lbm/ft3 BTU*in/(hr*ft2*°F) W/(m*k) J/(kg*K) BTU/lbm*°F 75 (24) 0.47 0.07 500 (260) 0.47 0.07 6.0 1130 0.270 1000 (538) 1.06 0.15 1500 (816) 1.90 0.27

Reference:

Appendix 1.4.4: Density and Thermal Conductivity.

[4] Specific Heat: Blanket Products Table, Cerablanket @1090°C.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 3.2.1.4 Dry Air The inner cavity fluid is modeled as dry air. No convection is modeled in this analysis, only conduction. The dry air properties are documented in Table 3-7.

Table 3-7 Thermal Properties of Dry Air Temperature Density Thermal Conductivity Specific Heat BTU*in/ BTU/

K °F kg/m³ lbm/ft³ W/(m*K) J/(kg*K) hr*ft2*°F lbm*°F 300 80 1.1614 7.250E-02 0.0263 0.182 1007 0.241 350 170 0.995 6.212E-02 0.03 0.208 1009 0.241 400 260 0.8711 5.438E-02 0.0338 0.234 1014 0.242 450 350 0.774 4.832E-02 0.0373 0.259 1021 0.244 550 530 0.6329 3.951E-02 0.0439 0.304 1040 0.248 650 710 0.5356 3.344E-02 0.0497 0.345 1063 0.254 750 890 0.4643 2.899E-02 0.0549 0.381 1087 0.260 850 1070 0.4097 2.558E-02 0.0596 0.413 1110 0.265 950 1250 0.3666 2.289E-02 0.0643 0.446 1131 0.270 1100 1520 0.3166 1.977E-02 0.0715 0.496 1159 0.277

Reference:

[5] Thermal Properties: Table A.4, Air, Page 995.

3.2.1.5 Polyurethane Foam Polyurethane foam is also used in providing thermal insulation. As specified in Appendix 1.4.3, the densities of the foam can range from 5 pcf to 11 pcf. Because thermal conductivity of the polyurethane foam increases with density [6], 12 pcf foam is conservatively used in this analysis.

The properties are documented in Table 3-8.

Table 3-8 Thermal Properties of 12-pcf Polyurethane Foam Temperature Density Thermal Conductivity Specific Heat

°F (°C) (lbm/ft3) (BTU*in/hr*ft2*°F) [W/(m*k)] (BTU/lbm*°F) 75 (24) 12.0 0.274 [0.04] 0.353

Reference:

Appendix 1.4.3: Thermal Conductivity.

[6] Density and Specific Heat: FR-3712 Rigid Polyurethane Foam (12 pcf).

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.2.1.6 Gasket Materials Gasket materials are not credited for thermal insulation and their properties are not explicitly modeled in this calculation. Because the gaskets will attain the temperature of the material around them, properties of the surrounding steel are used in this analysis.

3.2.1.7 Thermal Emissivity A painted surface is considered for NCT and pre-fire conditions. Fire and post-fire emissivity values are as provided in regulatory handbooks. All emissivity values and references are documented in Table 3-9.

Table 3-9 Thermal Emissivity Values HAC HAC Surface Condition Emissivity NCT (Fire) (Post Fire)

Painted surface 0.9 Painted Oxidized Fire Fire 0.9 surface Steel (0.9)

(0.9) (0.8)

Oxidized Steel 0.8

Reference:

[1] Emissivity HAC fire and post-fire, 10 CFR 71.73(c)(4)

[7] Emissivity of painted surface Black glass paint 3.2.2 Component Specifications The Versa-Pac is insulated to protect the containment boundary during Hypothetical Accident Conditions (HAC). The drum and the liner are separated by air gaps except at the locations of the vertical and horizontal stiffeners. The volume between the liner and the payload canister is filled with ceramic blanket insulation. A fiberglass thermal break is used to limit the flow of heat to the payload cavity through the steel flange components. The package containment is rated to an internal pressure of 15 psig. The relevant thermal material properties are provided in Section 3.2.1 above.

These insulators have been shown by the manufacturers to perform adequately over extended periods of time, with no shrinkage, settling, or loss of insulating properties. Additionally, these insulators do not burn. The melting point of the ceramic blanket insulation and the fiberglass thermal break are well above the temperature of the 1475°F (800°C) fire specified by 10 CFR 71.73. These insulation products are provided as fire-protection and are sacrificial components during a fire event. Steel components are serviceable to 800°F (427°C) per the ASME Code and have a melting point of about 2500°F (1371°C).

The payload cavity gaskets are rated for operating temperatures between -40°F (-40°C) and 1800°F (982°C); however, due to permeation in the silicone coating of the cavity seal, the maximum normal and HAC operating pressure are expected to be near atmospheric pressure during all conditions of transport.

The Versa-Pac design allows for the use of two neoprene pads: a 1/8-inch bottom pad, and a 3/8-inch top pad. The pads serve the purpose of protecting the inner containment shell during repeated use. As the use of these pads is optional, the neoprene material is not included in the thermal model. The flash point available in open literature for neoprene is approximately 500°F 3-9

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 (260°C). Since the internal temperature of the containment vessel has been shown not to exceed 400°F (204°C), the inclusion of neoprene does not increase the thermal load of the package.

Thermal design criteria are specified for separate regions throughout the Versa-Pac shipping package. Each region is limited to the temperature specified in Table 3-10. This table presents the maximum design temperatures of the components or materials that affect structural integrity, containment, and criticality control. Where available, temperature limits for the Versa-Pac components are obtained from manufacturers literature. Otherwise, the component temperature limits are defined as the melting temperature of the material of construction. NCT limits generally reflect the upper temperature limit listed for retention of structural integrity, continuous load ratings, or the maximum allowable temperature of the contents. HAC limits generally reflect melting temperatures, short-term (transient) material temperature limits, or the maximum allowable temperature of the contents.

Table 3-10 Temperature Limits NCT Temperature Limit HAC Temperature Limit Component or Material

°F (°C) °F (°C)

ASTM A-36 Carbon Steel ---a --- 2600 (1427) 525 Fiberglass b 150 (66) 1800 (982)

Cerablanket (6 pcf) 2150 (1177) 2400 (1316)

Polyurethane Foam (Containment insulation plug) 270 (132) 2000+c (1093)

High Temp., Heat Resistant, Silicone-Coated 500 (260) 1000 (538)

Fiberglass Gasket Inner Cavity - Standard and High-Capacity 600 d (316) 600 d (316)

Configurations Inner Cavity - 1S/2S UF6 Cylinder Configuration 250 (121) 250 (121) e Accessible Surfaces of Package 122 (50) --- ---

References:

[8] 525 Fiberglass, Carbon steel melting temperature.

[4] Cerablanket: Continuous use and Classification temperature rating, Page 16.

[6] Polyurethane Foam NCT Temp. Limit: Glass Transition.

[2] 1S/2S Inner Cavity Limit: Table 1 of ANSI N14.1-2012.

[1] Accessible Surfaces of Package: Non-exclusive use requirements per 10 CFR 71.43(g).

Notes:

a Carbon steel is not expected to have a significant loss of thermal properties during NCT.

b For NCT, 150°F is the temperature at which most FRPs begin to decompose. Some more specialized FRPs will begin decomposing at higher temperatures. For HAC, the reference states that, it is not uncommon for a fire retardant FRP product to be able to withstand a hydrocarbon fire at temperatures up to 1800°F for 30 minutes.

c In Reference [9], 2000+°F is the temperature at which the foams intumescent char will begin to decompose. This char, consisting of burned foam, serves as a secondary, insulating barrier for the remainder of the foam in a fire event.

d 600°F is the temperature limit specified for these configurations of the Versa-Pac.

e Based on 10 CFR 71.43(g) non-exclusive use limit, only applies for case in the shade (no solar insolation).

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.3 Thermal Evaluation for Normal Conditions of Transport (NCT)

The thermal performance of the Versa-Pac is analyzed for NCT by performing a steady-state heat transfer analysis on a finite element representation of the package. The general-purpose finite-element code ANSYS 19.1 is used to model and analyze the VP-55. In addition, supporting classical equations are documented in Appendix 3.5.4.

The bounding NCT case has a uniform heat flux is applied using steady state thermal analysis by exposing the package to a 38°C (100°F) ambient temperature and insolation as specified in Table 3-12. The results of the analysis are presented in Section 3.3.1, which includes the temperatures of the key package components.

Finite Element Model Because the VP-55 package is axially symmetrical, a quarter symmetry model of the package is used in this analysis. ANSYS Workbench is used to generate the Finite Element Model of the package. A combination of SOLID70, CONTA173, and TARGE170 element types are used to simulate the heat flow. Figure 3-2 shows the solid model, key components, and mesh.

The SOLID70 is a 3D, 8-node, single degree-of-freedom (DOF) thermal solid element. It is used to model heat flow through the solid and gaseous regions of the package via conduction heat transfer. Internal heat generation is applied to the SOLID70 elements of the interior air body and solar insolation and radiation are applied to the area faces of the exterior SOLID70 elements.

The CONTA173/TARGE170 pairs are 3D, 4-node, surface-to-surface contact elements that are overlaid onto area faces of the SOLID70 elements and are used to model heat flow across interfaces between contacting components or across interfaces between dissimilar meshes.

Bonded contact (perfect contact) is used to provide high thermal contact conductance.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Drum Lid (Part DL)

Polyurethane Foam Plug (Part IC)

Containment Lid (Part PD)

Air Gaps Containment Foam Plug (Part IG) 55 Gallon Drum (Part DA)

Ceramic Blanket (Part IA)

Cavity Air Containment End Plate (Part PB)

Polyurethane Foam Plug (Part ID)

Ceramic Paper (Part ID)

Figure 3-2 Quarter Symmetry Finite Element Model of the VP-55 Boundary Conditions The boundary conditions for all cases are listed in Table 3-11. Four NCT cases were analyzed simulating different combinations of ambient temperature, solar insolation, and internal heat generation to determine the bounding configuration. The four cases and their boundary conditions are also visualized in Figure 3-3 to Figure 3-6. The insolation modeled is per 10 CFR 71.71(c)(1) and is listed in Table 3-12.

Table 3-11 Summary of NCT Boundary Conditions Ambient Solar Internal Heat Case Temperature Convection Emissivity Insolation Generation

°F (°C)

Case I 100 (37.8) Yes Natural Surface Paint (0.9) 11.4 W Case II 100 (37.8) No Natural Surface Paint (0.9) 11.4 W Case III -40 (-40) No Natural Surface Paint (0.9) 11.4 W Case IV -40 (-40) No Natural Surface Paint (0.9) 0W 3-12

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 Table 3-12 Insolation Data Total Insolation for a 12-hour Period Form and location of surface (g cal/cm2)

Flat surfaces transported Base None horizontally; Other Surfaces 800 Flat surfaces not transported horizontally 200 Curved surfaces 400 3.3.1 Heat and Cold Regulations require testing the package for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of solar heating and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of shade conditions during NCT. This requires a transient thermal analysis. However, it can be simplified by calculating a uniform heat flux and using steady state analysis. The heat flux is calculated by distributing the given 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> total insolation value over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as stated in Thermal modeling of packages for normal conditions of transport with insolation in para. 657.3 of SSR-6 [10]:

" #$% ( ( )* 1*)*

1 = 41840 = 41840 * = 11.62

1. &' &' &' +,-- ./#. &'

4 567 =*>?

3-- 3-- <<.,9 3--<<.,9 1*)* 1 58' 8' 9: )*

= 9: )*

= 9: )**&'

= 387.41 &'

4 567

--  :--<<.,9 1*)* 1 58'

= = 193.7 9: )* 9: )** &' &'

4 567 9-- 9--<<.,9 1*)* 1 58' 9: )*

= 9: )**&'

= 96.85 &'

3-13

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Solar Insolation: Convection: Radiation:

W W Emissivity = 0.9 387.41 ! 5 !

m m * °C Solar Insolation:

W 193.7 !

m Convection: Internal Heat Generation:

W 5 ! Decay Heat = 170.24 W/m³ (11.4 W) m * °C Radiation:

Emissivity = 0.9 Adiabatic Bottom Ambient Temperature: 37.7°C Figure 3-3 NCT Boundary Conditions for CASE I (Hot: Internal wattage + Solar insolation) 3-14

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Solar Insolation: Convection: Radiation:

W W Emissivity = 0.9 0.0 ! 5 !

m m ' °C Solar Insolation:

W 0.0 !

m Convection: Internal Heat Generation:

W 5 ! Decay Heat = 170.24 W/m³ (11.4 W) m ' °C Radiation:

Emissivity = 0.9 Adiabatic Bottom Ambient Temperature: 37.7°C Figure 3-4 NCT Boundary Conditions for CASE II (Hot: Internal wattage + No solar insolation) 3-15

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Solar Insolation: Convection: Radiation:

W W Emissivity = 0.9 0.0 ! 5 !

m m ' °C Solar Insolation:

W 0.0 !

m Convection: Internal Heat Generation:

W 5 ! Decay Heat = 170.24 W/m³ (11.4 W) m ' °C Radiation:

Emissivity = 0.9 Adiabatic Bottom Ambient Temperature: -40 °C Figure 3-5 NCT Boundary Conditions for CASE III (Cold: Internal wattage + No Insolation) 3-16

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Solar Insolation: Convection: Radiation:

W W Emissivity = 0.9 0.0 ! 5 !

m m ' °C Solar Insolation:

W 0.0 !

m Convection: Internal Heat Generation:

W 5 ! Decay Heat = 0.0 W/m³ (0.0 W) m ' °C Radiation:

Emissivity = 0.9 Adiabatic Bottom Ambient Temperature: -40 °C Figure 3-6 NCT Boundary Conditions for CASE IV (Cold: No Internal wattage + No Insolation) 3-17

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.3.1.1 NCT Evaluation Results Results of the NCT evaluation show that a maximum exterior surface temperature in the shade (i.e. Case II) of 102°F (39°C) is observed on the drum. This meets the non-exclusive use shipment requirement of 10 CFR 71.43(g). The maximum interior air volume temperature is 232 °F (111°C).

NCT thermal evaluation temperature contour of the package for all cases are documented in Figure 3-7 to Figure 3-10. For select components, summary results of the NCT thermal evaluation for all cases are documented in Table 3-13. Temperature contours for Case I are shown in Figure 3-7, temperature contours for Case II are shown in Figure 3-8, temperature contours for Case III are shown in Figure 3-9, and temperature contours for Case IV are shown in Figure 3-10.

Table 3-13 NCT Steady State Thermal Evaluation Results Temperature °F (°C)

Hot Cold Component S.N.

Case I Case II Case III Case IV Max. Max. Max. Max. Min.

Containment body PA 147 (64) 113 (45) -27 -(33)

Containment end plate PB 147 (64) 114 (46) -26 -(32)

Containment insulation plug IG 177 (80) 139 (60) 0.5 -(18)

Gasket GB 143 (61) 104 (40) -35 -(37)

Containment lid (Blind flange) PD 143 (62) 104 (40) -35 -(37)

Drum lid DL 154 (68) 101 (39) -38 -(39) -40 (-40) -40 (-40)

Drum lid gasket GA 144 (62) 101 (39) -38 -(39)

Drum DA 144 (62) 102 (39) -38 -(39)

Package surface DA/DL 154 (68) 102 (39) -38 -(39)

Air Volume Ave N/A 191 (88) 158 (70) 23 (-5)

Air Volume Max N/A 232 (111) 201 (94) 73 (23) 3-18

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F Figure 3-7 NCT Temperature Contour-Case I (Hot: Internal wattage + Solar insolation)

Temperature °F Figure 3-8 NCT Temperature Contour-Case II (Hot: Internal Wattage + No Insolation) 3-19

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F Figure 3-9 NCT Temperature Contour-Case III (Cold: Internal Wattage + No Insolation)

Temperature °F Figure 3-10 NCT Temperature Contour-Case IV (Cold: No Internal Wattage + No Insolation) 3-20

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.3.2 Maximum Normal Operating Pressure Due to permeation in the silicone coating on the cavity seal, the maximum normal operating pressure is expected to be near atmospheric pressure. However, the maximum pressure increases from rising temperatures, considering the containment to be a perfectly sealed system, is approximately 3.3 psig (124 kPa) based on the average cavity NCT temperature of 191°F (88°C), recorded in Table 3-13.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.4 Thermal Evaluation for Hypothetical Accident Conditions (HAC)

A transient thermal analysis is performed on the VP-55 quarter model to simulate hypothetical accident fire conditions. This transient analysis simulates exposure of the package to a fully engulfed fire at 800°C for 30 minutes followed by a 7.5-hour cool down period, which is sufficient for package components to reach their maximum temperature.

The details of the HAC pre-fire, fire, and post-fire cool-down boundary conditions are documented in Sections 3.4.1 and 3.4.2 below. In addition, the supporting classical equations are documented in Appendix 3.5.4. The results of the HAC thermal evaluation are documented in Sections 3.4.3 and 3.4.4.

3.4.1 Initial Conditions The body temperature results of the NCT thermal analysis (hottest case: Case I) are used as the initial body temperature of the package for the HAC thermal analysis, see Figure 3-11. In addition, the ambient temperature before and after the fire is equal to 37.78°C (100°F) with insolation modeled as in Table 3-1.

Temperature °F Figure 3-11 NCT Results as Initial Conditions of HAC 3-22

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.4.2 Fire Test Conditions For the fire test, a transient thermal analysis is used. The modeled fire has an emissivity coefficient of 0.9 and a flame temperature of 800°C (1472°F). Forced convection film coefficients of 15.6 and 17.4 W/m²*°C are applied to the flat ends and cylindrical side surface, respectively.

As shown in Figure 3-12, HAC fire evaluation is conducted in a horizontal position for maximum fire exposure of the package.

Initial body temperature: NCT (Hot-Case I) results Environment fire temperature: 800°C Fire test position: Horizontal Internal Heat Generation:

Decay Heat = 170.24 W/m³ (11.4 W)

Convection:

Convection: Temperature = 800°C Temperature = 800°C Film Coefficient = 15.6 W/m²°C Film Coefficient = 15.6 W/m²°C Radiation:

Radiation: Temperature = 800°C Temperature = 800°C Emissivity = 0.9 Emissivity = 0.9 Convection: Radiation:

Temperature = 800°C Temperature = 800°C Film Coefficient = 17.4 W/m²°C Emissivity = 0.9 Figure 3-12 HAC Fire Boundary Conditions 3-23

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.4.2.1 Cool-Down (Post-Fire) Conditions At the end of the 30-minute fire, the environment temperature is dropped to 37.78°C (100°F).

Solar insolation is considered with the application of the NCT heat flux. Because the package is in a horizontal position during the fire, it stays in that position post fire. Therefore, both ends of the package are considered as vertical flat surfaces. Natural convection is also applied to the entire exterior surface with a convection coefficient of 5 W/m²*°C. Figure 3-13 shows the post fire boundary conditions.

Internal Heat Generation:

Decay Heat = 170.24 W/m³ (11.4 W)

Convection:

Convection: Temperature = 37.78°C Temperature = 37.78°C Film Coefficient = 5 W/m²°C Film Coefficient = 5 W/m²°C Radiation:

Radiation: Temperature = 37.78°C Temperature = 37.78°C Emissivity = 0.8 Emissivity = 0.8 Convection: Radiation:

Temperature = 37.78°C Temperature = 37.78°C Film Coefficient = 5 W/m²°C Emissivity = 0.8 Figure 3-13 HAC Cool-Down (Post-Fire) Boundary Conditions 3-24

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.4.3 Maximum Temperatures and Pressure The results of the HAC temperature evaluation are documented in a form of temperature-time history plots, temperature contours and tabulated values. Summary values for select components are documented in Table 3-14. The temperature-time history plots for selected parts are displayed in Figure 3-14 and Figure 3-15. Further, the temperature contours are shown in and .

As shown in Figure 3-16, the maximum temperature in the containment flange region is 434°F (223°C) and occurs at 1.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the post-fire cooldown. However, the containment cavity surface maximum temperature is 380°F (193°C), which is located at the top of the cavity adjacent to the containment plug (IG). As documented in Table 3-14, the average interior air temperature reaches 351°F (177°C). The containment region temperature-time history plot is displayed in Figure 3-15.

Due to permeation in the silicone coating of the cavity seal, the maximum normal operating pressure is expected to be near atmospheric pressure. However, the maximum pressure increase from rising temperatures, considering the containment to be a perfectly sealed system, is approximately 9.8 psig (154 kPa) based on the cavity surface HAC temperature of 425°F (219°C), recorded in Table 3-21. Additionally, it has been demonstrated that accounting for any thermal degradation of packaging materials could result in a marginal pressure increase, but not sufficient to exceed the 15 psig (205 kPa) cavity rating [12].

Table 3-14 HAC Transient Thermal Evaluation Summary Results Time at Max.

Component S.N. Max. Temp. °F (°C) Temp.

hr. (sec.)

Air volume max. --- 399 (204) 2.30 (8282)

Air volume average --- 351 (177) 2.30 (8282)

Containment plug bottom surface IG 380 (193) 1.40 (5042)

Containment cavity surface N/A 380 (193) 1.40 (5042)

Containment lid (Blind flange) PD 423 (217) 1.40 (5042)

Containment body PA 412 (211) 1.40 (5042)

Gasket GB 425 (219) 1.40 (5042)

Inner flange PH 434 (223) 1.40 (5042)

Drum lid DL 1457 (792) 0.5 (1802)

Drum DA 1461 (794) 0.5 (1802) 3-25

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Drum Drum lid Drum lid plug bottom surface Containment flange Gasket Containment body Containment plug bottom surface Containment end plate Air volume average 1600 1400 1200 1000 TEMPERATURE (°F) 800 600 400 200 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-14 VP-55 HAC Package Temperature-Time History Plot Containment flange (PH) Containment gasket (GB) Containment body (PA)

Containment lid (PD) Containment end plate (PB) Containment Inner Surface 500 450 400 350 300 TEMPERATURE (°F) 250 200 150 100 50 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-15 VP-55 HAC Containment Temperature-Time History Plot 3-26

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F a.) Package Maximum Temperature - 30 min Temperature °F b.) Containment Region Maximum Temperature - 1.4 hr Temperature °F c.) Inner Surface Maximum Temperature - 1.4 hr Figure 3-16 HAC Thermal Analysis Maximum Temperature Contours 3-27

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F a.) Package Maximum Temperature - 30 min Temperature °F b.) Containment Region Maximum Temperature - 2.3 hr Temperature °F c.) Inner Surface Maximum Temperature - 8.0 hr Figure 3-17 HAC Thermal Analysis Maximum Temperature Contours at Several Times 3-28

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.4.4 Maximum Thermal Stresses The performance of the Versa-Pac with respect to thermal stresses is demonstrated through a fire test performed for a similar package (see Reference [13]. The flexible construction of the connection between the payload cavity and the flange assures that thermal gradients do not impose excessive stress on the package joints.

3.4.5 Accident Conditions for Fissile Material Packages for Air Transport This section is not applicable. The criticality analysis for Versa-Pac packages transported by air assumes ejection of all contents from the packaging into a bounding configuration (see Section 6.7). Thus, no thermal testing/analyses are necessary for Versa-Pac shipments via air transport.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 3.5 Appendix The following appendices are included with Section 3:

3.5.1: References 3.5.2: Thermal Analysis of 1S/2S UF6 Cylinders in the VP-55 3.5.3: Thermal Analysis of the VP-55 with no Containment Insulation Plug 3.5.4: Supporting Classical Equations 3-29

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.1 References

[1] U.S. Nuclear Regulatory Commission, "Code of Federal Reguations Title 10, Part 71-Packaging and Transportation of Radioactive Material," 10 CFR 71, 2017.

[2] American National Standards Institute, "American National Standard for Nuclear Materials -

Uranium Hexafluoride - Packagings for Transport," ANSI N14.1-2012, 2012.

[3] American Society of Mechanical Engineers, "ASME Boiler and Pressure Vessel Code-Materials," Section II-Part D-Properties (Customary), 2010.

[4] Morgan Advanced Materials, "Thermal Products from Morgan Advanced Materials Product Data Book," 2017.

[5] T. L. Bergman, A. S. Lavine, I. P. Frank and D. P. Dewitt, Fundamentals of Heat and Mass Transfer, 7 ed., Jefferson City: John Wiley & Sons, 2011.

[6] General Plastics Manufacturing Company, "Last-a-Foam FR-3712 Rigid Polyurethane Foam," 2017.

[7] Mikron Instrument Company, Inc., "Table of Emissivity of Various Surfaces," 2017.

[8] Specialty Plastics, Inc., "Fiberglass Reinforced Plastic (FRP) Piping Systems: A Comparison to Traditional Metallic Materials," 1998.

[9] General Plastics Manufacturing Company, "Design Guide LAST-A-FOAM FR-3700 Crash

& Fire Protection of Radioactive Material Shipping Containers," 2012.

[10] Martin Marietta Systems, Inc., "Thermal Modeling of Packages for Normal Conditions of Transport with Insolation," CONF-951135-28, 1994.

[11] International Atomic Energy Agency, "IAEA Safety Standards: Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material," Specific Safety Guide No. SSG-26, 2012.

[12] DAHER-TLI, "Evaluation of Thermal Degradation of Packaging Material in Versa-Pac," CN-13002-301, Rev.2, 2013.

[13] Daher-TLI, "Century Champion Type B Package Immersion Test as Analogue for the Versa-Pac Type A Package," TR-20000-130-001, Rev. 0, Fulton, MD, 2021.

[14] ANSYS, Inc, "ANSYS 19.1," 2019.

[15] Sealed Air, "Ethafoam Polyethylene Foam Products, Typical Physical Properties," 2014.

[Online]. Available: https://sealedair.com/product-care/product-care-products/medium-and-high-density-foams.

[16] Almanza O., Rodriguez-Perez M. and Saja D.J., "Measurement of the Thermal Diffusivity and Specific Heat Capacity of Polyethylene Foams using the Transient Plane Source Technique," Polym Int 53:2038 - 2044, 2004.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2 Thermal Analysis of 1S/2S UF6 Cylinders in the VP-55 This appendix documents the thermal analysis necessary to allow for the shipment of 1S and 2S UF6 cylinders in the Versa-Pac, as shown in Figure 3-18 and Figure 3-19. The criterion for this analysis is the maximum allowable temperature of 250°F (121°C) for the 1S and 2S cylinders, as listed in Table 1 of ANSI N14.1-2012 [2]. The Versa-Pac inner cavity maximum temperature, 380°F (193°C), as documented in Table 3-14 above, is too great to allow for the shipment of 1S or 2S cylinders. To address this high cavity temperature issue, this appendix analyzes the addition of a polyethylene foam liner to the inner surface of the inner cavity to reduce the amount of heat transferred to the inner cavity. To determine the correct foam thickness, a study is conducted by gradually increasing the thickness of the polyethylene foam to the interior surface of the inner cavity until the interior surface temperature drops to the allowable range. This appendix has determined that a thickness of 2 inches (5 cm) of polyethylene foam with a minimum density of 9 pcf is sufficient to reduce the maximum Versa-Pac inner-cavity temperature to 245°F (118°C) and volumetric average temperature of 221°F (105°C).

Figure 3-18 ANSI N14.1 1S Cylinder Figure 3-19 ANSI N14.1 2S Cylinder 3-31

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2.1 Design Features and Boundary Conditions The Versa-Pac is modeled as described in Section 3 above. To accommodate the maximum temperature requirement of 250°F (121°C) for the 1S and 2S cylinders, a foam liner is used to reduce the heat that enters the inner cavity of the Versa-Pac. This foam has the properties as listed in Table 3-16.

The thermal response of the Versa-Pac 55 with foam liner for 1S and 2S UF6 cylinders is analyzed under both normal conditions of transport (NCT) and hypothetical accident conditions (HAC). As documented in Table 3-11, the NCT maximum heat input into the package occurs NCT Case I.

However, for the 1S/2S cylinder there is no internal heat generation. Thus, NCT Case V, as shown in Table 3-15 below, applies the maximum heat input into the package without internal heat generation. Therefore, HAC Case II is equivalent to the boundary condition presented in Section 3.4.2 without internal heat generation.

Table 3-15 Summary of Boundary Conditions Environment Solar Radiation Internal Heat Case Temperature Convection Insolation Emissivity Generation

°F (°C)

NCT Case V 100 (37.8) Yes Natural Surface Paint (0.9) 0W 1475 (800) No Forced Fire (0.9) 0W HAC Case II 100 (37.8) Yes Natural Steel Oxidized (0.8) 0W 3.5.2.2 Analysis Details The NCT evaluation of the Versa-Pac with 1S/2S UF6 cylinder contents was done with a steady-state, heat-transfer analysis using a finite-element model of the package. The finite-element code ANSYS 19.1 [14] was used to model and analyze the Versa-Pac under NCT. Upon completion of the NCT analysis, the resultant temperature distribution of the Versa-Pac was used as the initial conditions of the HAC analysis.

The HAC evaluation of the Versa-Pac with 1S/2S UF6 cylinder contents was performed with a transient heat-transfer analysis of the ANSYS model. The finite-element code ANSYS 19.1 [14]

was used to model and analyze the Versa-Pac under HAC. Damage from the mechanical tests was not simulated; however, local reductions in wall thickness were shown in the drop tests to be limited to the outer 1-3/16 of the package (see Table 2-6). Since this portion of the package quickly reaches the temperature of the fire, a local reduction is not expected to influence the temperature of the contents. Observation of the prototype fire test article after the drop test showed no rupture of the drum or inner support structure [13]. Therefore, the foam was not in direct contact with the flame and no charring or burning of the packaging foam will occurred.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2.3 Material Properties Density and thermal conductivity values are obtained from the foam providers website [15]. The densities are from (1.5 - 9.0) pcf, and the thermal conductivity ranges from 0.43 to 0.49 BTU*in/(hr*ft²*°F). While the low-density foams (1.5 - 1.8 pcf) provide higher thermal conductivity, the medium to high density foams (2.2 - 9.0 pcf) provide low thermal conductivity. In addition, the high-density foams provide better compressive strength and tear resistance. Therefore, polyethylene foam with a minimum density of 9 pcf must be used as the inner liner in the Versa-Pac because of the lowest thermal conductivity among the different foam densities.

Specific heat values of various polyethylene foams are also documented in Table 2 of Measurement of the Thermal Diffusivity and Specific Heat Capacity of Polyethylene Foams Using the Transient Plane Source Technique [16]. These values vary from 2285.5 to 2924.5 J/(kg*K).

Because the foam with a small specific heat capacity requires a small amount of heat energy to raise its temperature, the smallest value, 2285.5 J/kg*K, is conservatively used in this analysis.

Table 3-16 Thermal Properties of Polyethylene Foam Temperature Density Thermal Conductivity Specific Heat

°F (°C) (lbm/ft3) (BTU*in/hr*ft2*°F) [W/(m*k)] J/(kg*K) 75 (24) 9.0 0.43 [0.036] 2285.5 - 2924.5

References:

[15] Density: Ethafoam 900, Typical Physical Properties Table.

[15] Thermal Conductivity: Ethafoam 900, Typical Physical Properties Table.

[16] Specific Heat: Table 2.

3.5.2.4 NCT Thermal Evaluation 3.5.2.4.1 NCT Thermal Analysis Details The thermal performance of the Versa-Pac with 1S/2S UF6 cylinders is analyzed for NCT by performing a steady-state heat transfer analysis on a finite element representation of the package.

The general-purpose finite-element code ANSYS 19.1 is used to model and analyze the VP-55.

A uniform heat flux is applied using steady state thermal analysis by exposing the package to a 37.8°C (100°F) ambient temperature and insolation as specified in Table 2-1. The results of the analysis are presented in Section 3.5.2.4.2, which includes the temperatures of the key package components.

Because the VP-55 is axially symmetrical, a quarter symmetry model of the package is used in this analysis. ANSYS Workbench is used to generate the Finite Element Model of the package.

A combination of SOLID70, CONTA173, TARGE170 element types are used to simulate the heat flow. Figure 3-20 shows the solid model, key components, and mesh.

The SOLID70 is a 3D, 8-node, single degree-of-freedom (DOF) thermal solid element. It is used to model heat flow through the solid and gaseous regions of the package via conduction heat transfer. Internal heat generation is applied to the SOLID70 elements of the interior air body and solar insolation and radiation are applied to the area faces of the exterior SOLID70 elements.

The CONTA173/TARGE170 pairs are 3D, 4-node, surface-to-surface contact elements that are overlaid onto area faces of the SOLID70 elements and are used to model heat flow across interfaces between contacting components or across interfaces between dissimilar meshes.

Bonded (perfect contact) is used to provide high thermal contact conductance.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Drum Lid (Part DL)

Polyurethane Foam Plug (Part IC)

Containment Gasket (Part GB)

Air Gaps Containment Lid (Part PD) 55 Gallon Drum (Part DA)

Ceramic Blanket (Part IA)

Polyethylene Foam Insert Containment End Plate (Part PB)

Polyurethane Foam Plug (Part ID)

Ceramic Paper (Part ID)

Figure 3-20 Quarter Symmetry Finite Element Model of The Versa-Pac To simulate NCT, the following boundary conditions were used for the NCT model:

1. Solar insolation according to 10 CFR 71.71(c)(1). The 12-hour solar insolation values are used to calculate a 24-hour steady state heat flux on the exterior surface of the package.

2. An ambient temperature of 37.78°C (100°F) with natural convection (5.0 W/m2*°C, para.

728.30 [11]) applied to the package exterior surfaces.

3. Thermal radiation Specific boundary condition values are displayed in Figure 3-21 below.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Solar Insolation: Convection: Radiation:

W W Emissivity = 0.9 387.41 ! 5 !

m m * °C Solar Insolation:

W 193.7 !

m Convection:

W Internal Heat Generation:

5 ! Heat Flux = 0 W/m² m * °C Radiation:

Emissivity = 0.9 Adiabatic Bottom Ambient Temperature: 37.78°C Figure 3-21 NCT Boundary Conditions 3-35

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2.4.2 NCT Results Results of the NCT evaluation show that the maximum foam liner inner surface temperature is 138°F (59°C). The results for selected components are documented in Table 3-17 below and the overall body temperature is displayed in Figure 3-22 and Figure 3-23.

Table 3-17 NCT Steady State Results - 1S/2S UF6 Cylinder VP-55 Configuration Part Temperature Maximum Allowable Component Number °F (°C) Temperature °F (°C)

Containment body PA 139 (59) --

Containment end plate PB 134 (57) --

Containment insulation plug IG 139 (59) 270 (132)

Gasket GB 139 (59) 500 (260)

Containment lid (Blind flange) PD 139 (59) --

Drum lid DL 154 (68) --

Drum lid gasket GA 143 (62) --

Drum DA 143 (62) --

Package surface DA/DL 154 (68) --

Foam liner inner surface N/A 138 (59) 250 (121)

Note: See Table 3-10 for NCT temperature limits.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F Figure 3-22 NCT Evaluation Package Temperature Contour Temperature °F Figure 3-23 NCT Temperature Contour Showing Interior Surface of Foam Insert 3-37

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2.5 HAC Thermal Evaluation The results of the NCT thermal analysis are used as the initial conditions for the HAC thermal analysis, see Figure 3-24. In addition, the ambient temperature before and after the fire is equal to 37.78°C (100°F) with insolation modeled as in Table 3-12.

Temperature °F Figure 3-24 HAC Fire Initial Body Temperature 3-38

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2.5.1 Fire Test Conditions For the fire test, a transient thermal analysis is used. The modeled fire has an emissivity coefficient of 0.9, a flame temperature of 800°C (1472°F). Forced convection film coefficients of 15.6 and 17.4 W/m²*°C are applied to the flat ends and cylindrical side surface, respectively. As shown in Figure 3-25, the HAC fire evaluation is conducted in a horizontal position for maximum fire exposure of the package.

Initial body temperature: NCT results Environment fire temperature: 800°C Fire test position: Horizontal Internal Heat Generation:

Heat Flux = 0 W/m² Convection:

Convection: Temperature = 800°C Temperature = 800°C Film Coefficient = 15.6 W/m²°C Film Coefficient = 15.6 W/m²°C Radiation:

Radiation: Temperature = 800°C Temperature = 800°C Emissivity = 0.9 Emissivity = 0.9 Convection: Radiation:

Temperature = 800°C Temperature = 800°C Film Coefficient = 17.4 W/m²°C Emissivity = 0.9 Figure 3-25 HAC Fire Boundary Conditions 3-39

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.2.5.2 Cool-down (Post-fire) Conditions At the end of the 30-minute fire, the temperature is dropped to 37.78°C (100°F) and insolation is considered with the NCT heat flux values. Natural convection is also applied to the exterior surface with a convection coefficient of 5 W/m²*°C, see Figure 3-26.

Internal Heat Generation:

Heat Flux = 0 W/m² Convection:

Convection: Temperature: 37.78°C Temperature: 37.78°C Film Coefficient: 5 W/m²°C Film Coefficient: 5 W/m²°C Radiation:

Temperature = 37.78°C Radiation:

Emissivity = 0.8 Temperature = 37.78°C Emissivity = 0.8 Insolation:

Insolation: Heat Flux: 96.85 W/m² Heat Flux: 96.85 W/m² Convection: Radiation: Insolation Temperature: 37.78 °C Temperature: 37.78 °C Heat Flux: 193.7 W/m² Film Coefficient: 5 W/m²°C Emissivity = 0.8 Figure 3-26 HAC Post Fire Cool Down Boundary Conditions 3.5.2.5.3 HAC Results HAC requires determination of the minimum thickness sufficient to reduce the interior surface temperature to the acceptable range. Therefore, a study is conducted by gradually increasing the foam thickness to obtain the minimum thickness that can reduce the temperature of the inner cavity to the allowable limit.

The maximum allowable temperature for the shipment of 1S/2S UF6 cylinders is 250°F (121°C).

As shown in Figure 3-27 below, the foam thickness study predicts that 2-inch-thick foam is sufficient to reduce the cavity surface temperature to the acceptable range. Therefore, HAC analysis of the entire package is documented using the 2-inch-thick interior liner.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 2" Foam Liner Inner Surface 2" Foam liner body average 1" Foam Liner Inner Surface 350 300 250 TEMPERATURE (°F) 200 150 100 50 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-27 VP-55 1S/2S UF6 Cylinders - Containment Inner Surface Temp. with Foam Liners Maximum temperature values for selected components are documented in Table 3-18 below. In addition, the temperature-time histories of the package components are displayed in Figure 3-28 and Figure 3-29. The body temperature contour of the package is displayed in Figure 3-30 and Figure 3-31.

Table 3-18 HAC Fire Transient Results - 1S/2S UF6 Cylinder VP-55 Configuration Results Part Maximum Allowable Component Temperature Time Number Temperature °F (°C)

°F (°C) Hr. (Sec.)

Foam liner average N/A 221 (105) 4.10 (14761) 250 (121)

Foam liner inner surface maximum N/A 245 (118) 4.10 (14761) 250 (121)

Containment plug bottom surface IG 340 (171) 1.40 (5042) 2000 (1093)

Containment lid (Blind flange) PD 413 (212) 1.40 (5042) 2600 (1427)

Containment body PA 400 (204) 1.40 (5042) 2600 (1427)

Gasket GB 416 (213) 1.40 (5042) 1000 (538)

Inner flange PH 425 (219) 1.40 (5042) 2600 (1427)

Drum lid DL 1456 (791) 0.5 (1802) 2600 (1427)

Drum DA 1460 (793) 0.5 (1802) 2600 (1427) 3-41

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Foam liner inner surface Foam liner body average Drum Drum lid Drum lid plug bottom surface Inner flange Gasket Containment body Containment plug bottom surface Containment end plate 1600 1400 1200 1000 TEMPERATURE (°F) 800 600 400 200 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-28 VP-55 1S/2S UF6 Cylinders Entire Package HAC Temperature History Inner flange Gasket Containment body Containment lid Containment end plate Foam liner inner surface Foam liner body average 450 400 350 300 TEMPERATURE (° F) 250 200 150 100 50 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-29 VP-55 1S/2S UF6 Cylinders Package Containment HAC Temperature History 3-42

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F a.) Package Maximum Temperature - 30 min Temperature °F b.) Containment Region Maximum Temperature - 1.4 hr Temperature °F c.) Foam Liner Maximum Temperature - 1.4 hr Figure 3-30 HAC Thermal Analysis Maximum Temperature Contour 3-43

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F a.) Package Maximum Temperature - 30 min Temperature °F b.) Package Maximum Temperature - 4.1 hr Temperature °F c.) Package Maximum Temperature - 6.5 hr Figure 3-31 HAC Thermal Analysis Package Maximum Temperature Contour at Different Times 3-44

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3 Thermal Analysis of the VP-55 with no Containment Insulation Plug This appendix documents the thermal analysis of the 55-gallon Versa Pac (VP-55) with the containment insulation foam plug Part (IG) removed. The containment insulation foam plug (IG) is removed to accommodate higher volumes of non-heat generating low-density materials to be filled directly into the VP-55 inner cavity. Because the foam plug is removed, this thermal analysis shows that containment temperatures remain within the thermal limits of the contents.

Drum Lid (Part DL)

Polyurethane Foam Plug (Part IC)

Containment Gasket (Part GB)

Air Gaps Containment Lid (Part PD) 55 Gallon Drum (Part DA)

Ceramic Blanket (Part IA)

Containment Body (Part PA)

Containment End Plate (Part PB)

Polyurethane Foam Plug (Part ID)

Ceramic Paper (Part ID)

Figure 3-32 VP-55 Without Containment Insulation Plug (Part IG) 3-45

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3.1 Design Features and Boundary Conditions The thermal response of the Versa-Pac 55 without the containment insulation plug is analyzed under both normal conditions of transport (NCT) and hypothetical accident conditions (HAC). As documented in Table 3-11, the NCT maximum heat input is the same as NCT Case I. Therefore, NCT Case I, as shown in Table 3-19 below, applies the maximum heat input into the package with internal heat generation applied as a surface heat flux. Similarly, HAC Case I is equivalent to the boundary condition presented in Section 3.4.2.

Table 3-19 Summary of Boundary Conditions Environment Solar Radiation Internal Heat Case Temperature Convection Insolation Emissivity Generation

°F (°C)

NCT Case I 100 (37.8) Yes Natural Surface Paint (0.9) 11.4 W 1475 (800) No Forced Fire (0.9) 11.4 W HAC Case I 100 (37.8) Yes Natural Steel Oxidized (0.8) 11.4 W 3.5.3.2 Analysis Details The Versa-Pac is modeled as described in Section 3 above except the containment insulation plug Part (IG) is removed in this model.

The NCT evaluation of the Versa-Pac, without the containment insulation plug, was performed with a steady-state, heat-transfer analysis using a finite-element model of the package. The finite-element code ANSYS 19.1 [14] was used to model and analyze the Versa-Pac under NCT. Upon completion of the NCT analysis, the resultant temperature distribution of the Versa-Pac was used as the initial conditions of the HAC analysis.

The HAC evaluation of the Versa-Pac, without the containment insulation plug, was performed with a transient heat-transfer analysis using the finite element model. Damage from the mechanical tests was not simulated; however, local reductions in wall thickness were shown in the drop tests to be limited to the outer 1-3/16 of the package (See Table 2-6). Since this portion of the package quickly attains the temperature of the fire, a local reduction is not expected to influence the temperature of the contents. Further, observation of the test article after the drop test showed no rupture of the drum or inner support structure, hence no charring or burning of the packaging foam will occur under HAC (Appendix 2.13.7).

3.5.3.3 Material Properties and Component Specifications Material properties and component specifications are as documented in Section 3.2.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3.4 NCT Thermal Evaluation 3.5.3.4.1 NCT Thermal Analysis Details The thermal performance of the Versa-Pac, without containment insulation plug, is analyzed for NCT by performing a steady-state heat transfer analysis on a finite element representation of the package. The finite-element code ANSYS Workbench 19.1 [14] is used to generate the model and perform the analyses. Because the Versa-Pac is axisymmetric, a quarter symmetry model of the package is used for this evaluation. A combination of SOLID90, CONTA173, TARGE170 element types are used to simulate the heat flow. The SOLID90 is a 3D, 8-node, single degree-of-freedom (DOF) thermal solid element. It is used to model heat flow through the solid and gaseous regions of the package via conduction heat transfer. ANSYS CONTA173/TARGE170 pairs are 3D, 4-node, surface-to-surface contact elements that are overlaid onto area faces of the SOLID90 elements and are used to model heat flow across interfaces between contacting components or across interfaces between dissimilar meshes. Bonded (perfect contact) is used to provide high thermal contact conductance.

Figure 3-33 Finite Element Model of The Versa Pack Quarter Symmetry Model 3-47

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 To simulate NCT, the following boundary conditions were used for the NCT model:

1. Solar insolation according to 10 CFR 71.71(c)(1). The 12-hour solar insolation values are used to calculate a 24-hour steady state heat flux on the exterior surface of the package.

2. An ambient temperature of 37.78°C (100°F) with natural convection (5.0 W/m2*°C, para.

728.30 [11]) applied to the package exterior surfaces.

3. Thermal radiation Specific boundary condition values are displayed in Figure 3-34 below.

Figure 3-34 NCT Boundary Conditions 3-48

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3.4.2 NCT Results Results of the NCT evaluation show that the maximum overall temperature of 154°F (68°C) and interior cavity temperature is 147°F (64°C). The results for selected components are documented in Table 3-20 below and the overall body temperature is displayed in Figure 3-35, and the interior surface temperature is displayed in Figure 3-36.

Table 3-20 NCT Steady State Thermal Evaluation Results -VP-55 Configuration Without Containment Insulation Plug Part Temperature Maximum Allowable Component Number °F (°C) Temperature °F (°C)

Containment body PA 147 (64)

Containment end plate PB 147 (64)

Gasket GB 143 (62) 500 (260)

Containment lid (Blind flange) PD 143 (62) 600 (260)

Drum lid DL 154 (68)

Drum lid gasket GA 145 (63)

Drum DA 144 (62)

Package Surface DA/DL 154 (68)

Containment Inner Surface N/A 147 (64) 600 (316)

Note: See Table 3-10 for NCT temperature limits.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F Figure 3-35 NCT Evaluation Package Temperature Contour Temperature °F Figure 3-36 NCT Temperature Contour Interior Surface 3-50

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3.5 HAC Thermal Evaluation The results of the NCT thermal analysis are used as the initial conditions for the HAC thermal analysis, see Figure 3-35. In addition, the ambient temperature before and after the fire is equal to 37.78°C (100°F) with insolation modeled as in Table 3-12.

3.5.3.5.1 Fire Test Conditions For the fire test, a transient thermal analysis is used. The fire is modeled with an emissivity of 0.9 and a flame temperature of 800°C (1472°F). Forced convection film coefficients of 15.6 and 17.4 W/m²*°C are applied to the flat ends and cylindrical side surface, respectively. As shown in Figure 3-37, the HAC fire evaluation is conducted in a horizontal position for maximum fire exposure of the package.

Initial temperature: NCT steady-state results Environment fire temperature: 800°C Fire test position: Horizontal Internal Heat Generation:

Heat Flux = 11.3 W/m² Convection:

Convection:

Temperature = 800°C Temperature = 800°C Film Coefficient = 15.6 W/m²°C Film Coefficient = 15.6 W/m²°C Radiation:

Radiation:

Temperature = 800°C Temperature = 800°C Emissivity = 0.9 Emissivity = 0.9 Convection: Radiation:

Temperature = 800°C Temperature = 800°C Film Coefficient = 17.4 W/m²°C Emissivity = 0.9 Figure 3-37 HAC Fire Boundary Conditions 3-51

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3.5.2 Cool-down (Post-fire) Conditions At the end of the 30-minute fire, the temperature is dropped to 100°F (37.78°C) and insolation is considered with the NCT heat flux values. Natural convection is also applied to the exterior surface with a convection coefficient of 5 W/m²*°C, see Figure 3-38.

Internal Heat Generation:

Heat Flux = 11.3 W/m² Convection:

Convection: Temperature: 37.78°C Temperature: 37.78°C Film Coefficient: 5 W/m²°C Film Coefficient: 5 W/m²°C Radiation:

Temperature = 37.78°C Radiation:

Emissivity = 0.8 Temperature = 37.78°C Emissivity = 0.8 Insolation:

Insolation: Heat Flux: 96.85 W/m² Heat Flux: 96.85 W/m² Convection: Radiation: Insolation Temperature: 37.78 °C Temperature: 37.78 °C Heat Flux: 193.7 W/m² Film Coefficient: 5 W/m²°C Emissivity = 0.8 Figure 3-38 HAC Post Fire Cool Down Boundary Conditions 3-52

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.3.5.3 HAC Results The HAC results for the VP-55 without containment insulating plug is provide in Table 3-21.

Temperature-time history plots for select components of entire package and containment region are displayed in Figure 3-39 and Figure 3-40, respectively. Temperature contour plots are shown in Figure 3-41 and 3-42.

As shown in Figure 3-40, the maximum temperature in the containment region of 445°F (229°C) was recorded at 1.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. However, package component temperatures remain below the maximum allowable temperatures.

Table 3-21 HAC Transient Thermal Evaluation Results - VP-55 Configuration Without Containment Insulation Plug Results Maximum Part Component Temperature Time Allowable Number

°F (°C) Hr. (Sec.) Temperature °F (°C)

Containment cavity surface N/A 425 (218) 1.40 (5042) 600 (316)

Containment lid (Blind flange) PD 433 (223) 1.40 (5042) 2600 (1427)

Containment body PA 423 (217) 1.40 (5042) 2600 (1427)

Gasket GB 436 (224) 1.40 (5042) 1000 (538)

Inner flange PH 445 (229) 1.40 (5042) 2600 (1427)

Drum lid DL 1456 (791) 0.5 (1802) 2600 (1427)

Drum DA 1460 (793) 0.5 (1802) 2600 (1427)

Note: See Table 3-10 for HAC temperature limits.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Drum Drum lid Drum lid plug bottom surface Inner flange Gasket Containment body Containment end plate Containment inner surface 1600 1400 1200 1000 TEMPERATURE (°F) 800 600 400 200 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-39 VP-55 Entire Package HAC Temperature History (Without Containment Insulation Plug) Maximum Temperature History Inner flange Gasket Containment body Containment lid Containment end plate Containment inner surface 500 450 400 350 300 TEMPERATURE (°F) 250 200 150 100 50 0

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 TIME (HRS)

Figure 3-40 VP-55 (Without Containment Insulation Plug) Containment Temperature History 3-54

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F a.) Package Maximum Temperature - 30 min Temperature °F b.) Containment Region Maximum Temperature - 1.4 hr Temperature °F c.) Containment Interior Surface Maximum Temperature - 1.4 hr Figure 3-41 HAC Thermal Analysis Containment Maximum Temperature Contours 3-55

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 Temperature °F a.) Package Maximum Temperature - 30 min Temperature °F b.) Containment Region Maximum Temperature - 2.5 hr Temperature °F c.) Containment Interior Surface Maximum Temperature - 6.5 hr Figure 3-42 HAC Thermal Analysis Package Maximum Temperature Contour During Fire and Cool Down 3-56

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 10, March 2018 3.5.4 Supporting Classical Equations 3.5.4.1 Natural Convection The natural convection occurs on the still fluids on the exterior surface of the Versa-Pac and it is calculated with the following equation (Equation 6.4, Page 380 [5]):

qc = h0 (Ts - T) where, qc = convective heat flux (W/m2) h0 = convection heat transfer coefficient (W/m2*°C)

Ts = temperature of surface (°C)

T = temperature of environment (°C)

A heat transfer coefficient of 5 W/m²-°C is used for boundary conditions concerning natural convection. Additionally, this heat transfer coefficient can be defined with the following equations (Equation 9.24, Page 604 [5]):

CCCCD

@AB h0 = E where, NuE =

1. 1. 1. 1. 1. Nusselt Number L = characteristic length k = conduction heat transfer coefficient Depending on the orientation of the surface of concern, the Nusselt number will vary. The following equations give the Nusselt number for various geometries.

3.5.4.1.1 Vertical Plate The Nusselt number can be calculated for the entire range of Rayleigh number (Ra) by the following correlation (Equation 9.26, Page 605 [5]):

9

-.+3F G$D I H

00000 NuE = 0.825 + S O 'T J<K L M.NO' HI Q R P?

where, RaE = Rayleigh number Pr = Prandtl number An improved accuracy of the Nusselt number can be obtained for laminar flow with the following equation for RaL (Equation 9.27, Page 605):

00000 0.670 UVW 1/4 NuE = 0.68 + 4 for RaE 10d 9 9 J1+ Z0.492/b16 R 3-57

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.4.1.2 Horizontal Plate The Nusselt number calculated for a horizontal plate is as follows (Equations 9.30 - 9.32, Page 610 [5]):

Upper Surface of Hot Plate or Lower Surface of Cold Plate 00000 Nu; = 0.54 Ra1/4 104 Ra 107, Pr 0.7 00000 Nu; = 0.15 Ra1/3 107 Ra 1011, all Pr Lower Surface of Hot Plate or Upper Surface of Cold Plate 00000 Nu; = 0.52 Ra1/5 104 Ra 109, Pr 0.7 The above Horizontal Plate correlations are used when the characteristic length is to be defined as (Equation 9.29, Page 609 [5]):

L = As/P where, As = surface area P = perimeter The Rayleigh number to be used to calculate the Nusselt number values is formulated as (Equation 9.25, Page 605 [5]):

" L (NB ONC ) ;D RaL = QR where, g = gravity (9.81 m/s2) b = 1 / (Tf + 459.67)

Tf = film temperature Ts = surface temperature T = ambient temperature L = characteristic length n = air kinematic viscosity at Tf

= air thermal diffusivity at Tf Note that the film temperature is the average temperature between the surface temperature and ambient temperature, Tf = (Ts + T)/2, and all properties are obtained at this temperature.

3.5.4.2 Forced Convection During the HAC 30-minute fire, forced convection film coefficient (hc) are applied as boundary conditions to each external surface of the package. Temperature dependent hc values are calculated for the range from ambient, 100°F (37.78°C), to the fire the temperature of 1472°F (800°C) based on the geometry of the surface [5]. The maximum calculated hc values for the range are conservatively applied to the external surfaces of the ANSYS model.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 The forced convection coefficient is calculated using the following equation (Equation 9.24 [5]):

89 x 7 h# =  ;

where, Nu = Nusselt number, k = thermal conductivity of air at the film temperature, and L = characteristic length of the surface = .571 m.

The Nusselt number (Nu) is a function of the Reynolds number (Re) and the Prandtl number. The Reynolds number is, in turn, a function of surface geometry, temperature, flow velocity, and properties (density and viscosity) of the surrounding air, which is calculated using the following equation (Equation 6.45 [5]):

VL Re =

where, V = air free-stream velocity = 10 m/s (Reference [11], §728.30),

L = characteristic length = .571 m, n = air dynamic viscosity at Tf, Tf = film temperature = (Ts + T¥)/2, Ts = surface temperature, and T¥ = ambient temperature.

The VP-55 package surfaces are modeled using Nu correlations for a cylinder in cross flow or a flat plate with parallel flow depending on which surface and package orientation being evaluated.

These Nu correlations are giving in the following section.

3.5.4.2.1 Cylinder in Cross Flow The characteristic length, L, of a cylinder is its diameter, D. The Nusselt number for a cylinder in cross flow is calculated using the following equation (Equation 7.55b [5]):

Nu= C ReD m Pr1/3 where, ReD = Reynolds number, and Pr = Prandtl number.

The constants C and m in the previous equation are functions of the Reynolds number (ReD) and are listed in Table 3-21.

Table 3-22 Constants 'C' and 'm' for the Nusselt Number Calculation of a Cylinder in Cross Flow ReD C m 0.4 - 4 0.989 0.330 4 - 40 0.911 0.385 40 - 4,000 0.683 0.466 4,000 - 40,000 0.193 0.618 40,000 - 400,000 0.027 0.805

Reference:

[5] Table 7.2.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.4.2.2 Flat Plate with Parallel Flow For laminar flow (ReL 5x105 per Equation 6.24, [5]), the Nusselt number for external flow over a flat plate is calculated using the following equation (Equation 7.31, [5]):

Nu=0.664 ReL 1/2 Pr1/3 (5x105 ReL, Pr 0.6) where, ReL = Reynolds number, and Pr = Prandtl number.

For mixed parallel flow (laminar and turbulent), the Nusselt number for external flow over a flat plate is calculated using the following equation (Equation 7.44, [5]):

Nu=0.037 ReL 4/5 Pr1/3 (5x105 < ReL 108) where, ReL = Reynolds number, and Pr = Prandtl number.

To provide maximum heat input from the fire, the package is assumed to be laying in the horizontal position. Using the equations presented above, calculated forced convection film coefficients of 15.6 and 17.4 W/m²*°C are applied to the flat ends and cylindrical side surface of the package, respectively.

3.5.4.3 Radiation 3.5.4.3.1 Radiation with the Environment Thermal radiation occurs between a surface and its environment due to thermally excited conditions within the matter. The amount of radiation exchange depends on the temperature, emissivity and surface area:

Q)$T = A MT- 4 TU 4 P (Equation 13.27, Page 885 [5].)

where, e = emissivity, s = Stefan-Boltzmann constant (1.19 E -11 Btu/h-in²-°F),

A = surface area, Ts = surface temperature (°R), and T¥ = temperature of surroundings (°R).

This equation is read as the difference in the quantity of radiation emitting from the surface and the quantity of radiation entering the surface. Further, it may be advantageous to model the net heat exchange in a comparable manner to convection to linearize the rate equation as:

Q)$T = h) A (T- TU ) (Equation 1.8, Page 10 [5])

Setting the above radiation heat exchange equations equal to each other and performing some algebraic manipulation results in:

hr = MT- 3 + TU 3 P(T- + TU ) (Equation 1.9, Page 10 [5])

where, hr = radiation heat transfer coefficient 3-60

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.4.3.2 Radiation between surfaces The equation for radiation heat transfer between surfaces is:

VWN. 2 O N! 2 X QradS = .EF. . .EF! (Equation 13.23, Page 885 [5])

?  ?

F. G . G. H.! F! G !

where, T6 = Temperature of surface 1 T3 = Temperature of surface 2

= Stefan-Boltzmann constant A6 = Area of surface 1 A3 = Area of surface 2 6 = Emissivity of surface 1 3 = Emissivity of surface 2 F63 = View factor between surfaces 1 and 2 3.5.4.4 Conduction The conduction heat transfer on a body depends on the temperature difference of the material, the thermal conductivity (k) of the material and the area of heat transfer:

N QY = kA Y (Equation 2.1, Page 69 [5])

where, k = Thermal conductivity constant (W/m*K)

T = Temperature difference A = Area of heat transfer x = Length of the material in the direction of heat flow 3.5.4.5 Thermal Resistance 3.5.4.5.1 Thermal Resistance for Conduction The temperature change across boundaries where different materials meet may be considerable and is known as thermal contact resistance Rt,c, and is due to primarily surface roughness effects.

These rough areas create raised areas and therefore gaps as well between components.

The thermal resistance for conduction heat transfer is defined as:

NG ONI Rt,c = [J (Equation 3.6, Page 114 [5])

= 7\

where, T\ = Temperature of material A T] = Temperature of material B qx = Conduction heat transfer L = Length of wall A = Area normal to the direction of heat transfer 3-61

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, July 2021 3.5.4.5.2 Thermal Resistance for Convection The resistance for convection heat transfer is:

NB ONC Rt,conv = (Equation 3.9, Page 115 [5])

[

6

=

(\

where, T- = Surface temperature TU = Environment temperature q = Convection heat transfer A = Area of convection h = Convection coefficient 3.5.4.5.3 Thermal Resistance for Radiation The resistance for radiation heat transfer is:

NB ONBK+

Rt,rad = (Equation 3.13, Page 115 [5])

[+%L 6

= (+ \

where, T- = Surface temperature T-9) = Surrounding temperature Q)$T = Convection heat transfer A = Area of radiation h) = Radiation coefficient 3-62

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 4 CONTAINMENT .......................................................................................................................... 4-1 4.1 Description of the Containment System.................................................................................. 4-1 4.2 Containment under Normal Conditions of Transport ........................................................ 4-1 4.3 Containment Requirements for Hypothetical Accident Conditions .............................. 4-1 4.4 Leakage Rate Tests for Type B Packages ................................................................................ 4-2 4.5 References ......................................................................................................................................... 4-2 4.6 List of Appendices........................................................................................................................... 4-2 4-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 4 CONTAINMENT 4.1 Description of the Containment System The containment boundary of the package is defined as the payload vessel with its associated welds, payload vessel high temperature heat resistant fiberglass sleeve gasket, payload vessel blind flange, and reinforcing ring.

The payload vessel is comprised of a 10-gauge (0.3416 cm) carbon steel sheet for the body and bottom. The upper end of the vessel is fitted with a 1/4 (0.635 cm) inner carbon steel flange ring with a 1/2 (1.27 cm) thick carbon steel blind flange. The vessel has three circumferential welds (two at the flange, one at the base) and one longitudinal weld. A 1/8 (0.3175 cm) high temperature resistant silicone coated fiberglass gasket is used between the steel flange ring and blind flange.

The payload vessel blind flange is secured to the flange with twelve 1/2 (1.27 cm) bolts. There are no penetrations, valves or venting devices used within the containment boundary. An illustration showing the components of the containment system is provided in Figure 1-1.

Additionally, weld standards and codes are specified in the licensing drawing general notes in Section 1.4.2.

A specified torque is applied to the closure bolts and tightened as part of the closure steps defined within Section 7.1.2 to assure positive closure of the containment boundary. Given the mode of the closure, it cannot be opened unintentionally. The use of lock washers assures that the closure bolts are not loosened due to vibration during shipment. A location for installation of a tamper-indicating device is provided at the drum closure.

4.2 Containment under Normal Conditions of Transport The Versa-Pac is classified as a Type A Fissile package. Performance tests consistent with the requirements of 10 CFR 71.71 and 10 CFR 71.73 [1] have demonstrated that the Versa-Pac effectively prevents loss or dispersal of the radioactive contents under the postulated conditions of transport. Section 2.0 provides a description of the tests performed and analyses completed.

Section 6.0 demonstrates that the package remains subcritical under Normal and Hypothetical Accident Conditions.

Due to gas permeation through the silicone seal, the internal pressure is expected to be maintained near atmospheric pressure for all conditions of transport. (Note that the normal hot maximum temperature for the contents, reported in Section 3.1.3, is 147 °F.)

4.3 Containment Requirements for Hypothetical Accident Conditions As discussed in Section 4.2 and Section 2.0, performance tests consistent with the requirements of 10 CFR 71.71 and 10 CFR 71.73 [1] have demonstrated that the Versa-Pac effectively prevents loss or dispersal of the radioactive contents under the postulated conditions of transport. Section 6.0 demonstrates that the package remains subcritical under normal and hypothetical accident conditions.

Due to gas permeation through the silicone seal, the internal pressure of the package is expected to be maintained near atmospheric pressure for all conditions of transport, with pressure build up relieved through the package closure. However, as demonstrated in Section 3.0, pressure buildup does not affect the structural integrity of the containment system.

4-1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 4.4 Leakage Rate Tests for Type B Packages This section is not applicable.

4.5 References

[1] Nuclear Regulatory Commission (NRC), Title 10, Part 71-Packaging and Transportation of Radioactive Material.

4.6 List of Appendices No appendices.

4-2

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 5 SHIELDING ................................................................................................................................... 5-1 5.1 References ........................................................................................................................................... 5-1 5-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 5 SHIELDING Gamma and neutron shielding are not required for the materials transported in the Versa-Pac.

However, it is the responsibility of the shipper to assure compliance with 10 CFR 71.47 [1]

regarding radiation standards for each individual shipment. Performance tests have demonstrated that there is no substantial reduction in the effectiveness of the packaging during Normal Conditions of Transport; thus, there is no significant increase in external surface radiation levels resulting from the postulated conditions of transport.

5.1 References

[1] Nuclear Regulatory Commission (NRC), Title 10, Part 71-Packaging and Transportation of Radioactive Material.

5-1

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev. 12, February 2021 6.1.2 Summary Table of Criticality Evaluation As indicated in Section 6.3, the NCT and HAC configurations evaluated in this analysis were conservatively constructed based on the VP-55 to bound both the VP-55 and VP-110. While text throughout the SAR chapter may only explicitly reference the VP-55 or VP-110, the criticality analyses apply to, and bound, both Versa-Pac variants.

6.1.2.1 Standard Configuration Table 6.1.2-1 provides a summary of the results of the limiting cases from the criticality safety analysis that produced the additional enrichment level mass limits presented in Table 6.2.1-1. All results are less than their respective USLs. The USLs are calculated and presented in Section 6.1.2.6.

Table 6.1.2-1. Summary of the Standard Configuration Analysis 235 235 U Enrichment U Mass Array keff + 2 Reference (wt.%) (g) Size Single Package 100 360 -- 0.92927 Table 6.4.1-1 20 445 -- 0.92660 Table 6.4.1-5 10 505 -- 0.91766 Table 6.4.1-9 5 610 -- 0.90726 Table 6.4.1-15 1.25 1650 -- 0.86759 Table 6.4.1-20 NCT Package Array 100 360 252 0.93467 Table 6.5.1-5 20 445 252 0.94006 Table 6.5.1-6 10 505 252 0.93761 Table 6.5.1-12 5 610 252 0.93709 Table 6.5.1-22 1.25 1650 252 0.93844 Table 6.5.1-28 HAC Package Array 100 360 105 0.93743 Table 6.6.1-1 20 445 105 0.93651 Table 6.6.1-13 10 505 105 0.92851 Table 6.6.1-14 5 610 105 0.91936 Table 6.6.1-24 1.25 1650 105 0.92750 Table 6.6.1-31 6-2

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 7 PACKAGE OPERATIONS ..................................................................................................... 7-1 7.1 Package Loading.............................................................................................................................. 7-1 7.1.1 Preparation for Loading ........................................................................................................................ 7-1 7.1.2 Loading of Contents ................................................................................................................................ 7-2 7.1.3 Preparation for Transportation ......................................................................................................... 7-2 7.2 Package Unloading ......................................................................................................................... 7-3 7.2.1 Receipt of Package from Carrier........................................................................................................ 7-3 7.2.2 Removal of Contents ............................................................................................................................... 7-3 7.3 Preparation of Empty Package for Transport .................................................................... 7-3 7.4 Other Operations ............................................................................................................................ 7-3 7.5 References ......................................................................................................................................... 7-4 7.6 List of Appendices........................................................................................................................... 7-4 7-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 7 PACKAGE OPERATIONS The Versa-Pac Shipping Package is used to transport a variety of materials, typically by non-exclusive use. It is to be loaded, inspected and handled in accordance with standard, plant operating procedures. At a minimum, the operating procedure should include the steps described in the subsequent sections.

Due to the low specific activity and low abundance of gamma emitting radionuclides, dose rates from the contents of the package are minimal. As a result of the low dose rates, there are no special handling requirements for radiation protection. As a Type AF package, the contents of the Versa-Pac are always limited to be less than or equal to an A2 quantity, calculated per the guidance of 10CFR71 Appendix A. All radioisotopes in the contents shall be included in the A2 calculation (typically uranium isotopes: U-233, U-234, and U-236).

7.1 Package Loading 7.1.1 Preparation for Loading Prior to loading the Versa-Pac, the packaging is inspected to ensure that it is in unimpaired physical condition. The inspection looks for damage, dents, corrosion, and missing hardware.

Acceptance criteria and detailed loading procedures derived from this application are specified in user written procedures. These user procedures are specific to the authorized content of the package inspected to ensure packaging complies with Appendix 1.4.1, Packaging General Arrangement Drawings.

Components requiring repair will be fixed prior to shipping in accordance with approved procedures consistent with the quality program [1].

The User shall inspect the accessible surfaces of the closure and sealing devices in accordance with approved procedures prior to loading of the container to assure the following at a minimum:

a. Ensure that the most recent certification performed is in accordance with Section 8.2.

b. The contents are within the limits of the Certificate of Compliance.

c. The package inner and outer surfaces are visually free from damage that may impair the safe use of the package.

d. The Package is free of debris or other foreign matter that could interfere with the proper and safe use of the container.

e. Verify that the outer drum and visible inner plugs are in place.

f. Gaskets are in place and intact and are not deteriorated or damaged. Replace as needed.

g. The containment flange and outer drum cover and all mating surfaces are sound and fit properly.

h. Closure bolts are the proper type and size and that thread inserts are in working order.

i. Ensure that security seal holes are functional and capable of maintaining their integrity when seals are required.

j. When utilizing the 5-inch pipe configuration, visually inspect the threads for damage that would interfere with the appropriate operation of the cap and body connection obtaining the minimum 5 full turns of closure. If required, repair threads by an appropriate method or replace the component.

7-1

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 7.1.2 Loading of Contents All radioactive contents are loaded into the inner container. The maximum loading shall comply with the limits given in Section 1.2.2, Contents. The User shall load the packaging in accordance with in-plant approved, written procedures and at a minimum include the following items:

a. Verify that the steps previously outlined by Section 7.1.1 have been completed at a minimum.

b. If loading 1S/2S UF6 cylinder contents, verify the inner container cavity foam liner is in place at the bottom and side walls before loading the contents. The foam liner must be at least 2 inches (5.08 cm) thick at all sides, bottom and top. All 1S/2S cylinders should be cleaned of any contamination prior to loading.

c. The contents may be pre-packaged within plastic jars, sealed metal cans, plastic bags, drums or other appropriate forms; however, these items are not required for transport. Note: if using hydrogen limited content limits, verify that the total mass of hydrogenous material does not exceed the specified maximum.

d. If using the 5-inch pipe, screw the cap onto the containment vessel body until at least five but not more than eight threads are engaged.

e. Verify that the neoprene bottom pad is in place, if required (see Licensing Drawing NOTES for optional usage of part GC).

f. Verify that no freestanding liquids or other volatile compounds are present in the containment area prior to loading of contents.

g. Carefully load the package content into the inner container. If loading multiple 1S/2S UF6 cylinders or multiple 5-inch pipe contents, ensure each container is not in contact with one another. Cribbing or dunnage may be used to restrict movement of the contents during transport.

h. Position the neoprene sponge rubber top pad atop the contents, if required (see Licensing Drawing NOTES for optional usage of part GE).

i. If loading 1S/2S UF6 cylinder contents, verify foam liner top is in place.

j. If required, verify Containment insulation plug is in place before securing the inner container flange lid. (see Licensing Drawing NOTES for optional usage of part IG).

k. Place the inner container flange lid and gasket into place and tighten the bolts lock washers to the specified torque of 60+/-2 lb-ft.

l. Place the outer gasket and carefully install the outer reinforced insulated drum cover.

m. Install the appropriate bolts and washers and tighten to the specified torque of 60+/-2 lb-ft.

n. Secure the outer drum closure ring and tighten to 60+/-2 lb-ft and tighten the jam nut against the bolt lug.

7.1.3 Preparation for Transportation

a. Install the security seals and record their numbers, if applicable.

b. Complete a radiation and contamination survey in compliance with the applicable regulations.

c. Remove any old labels and re-label per the applicable regulations.

d. Records should be maintained in accordance with the appropriate regulations.

7-2

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 7.2 Package Unloading The User shall unload the Versa-Pac in accordance with in-plant approved, written procedures and at a minimum include the following items:

7.2.1 Receipt of Package from Carrier

a. Examine the package for visible external damage.

b. Complete a receiving report and complete any surveys that are appropriate.

c. Remove and record the package seal, if applicable.

7.2.2 Removal of Contents

a. Loosen and remove the outer drum lid closure ring, reinforcing ring bolts and insulated drum cover.

b. Loosen and remove the bolts from the inner container flange.

c. Remove the contents from the inner container and verify no contents are remaining.

7.3 Preparation of Empty Package for Transport Empty Versa-Pac packages are prepared and transported per the requirements of 49 CFR 173.428 [2]. Prior to shipping as an empty Versa-Pac packaging, the packaging is surveyed to ensure that contamination levels are within the 49 CFR 173.443 limits. The packaging is inspected to ensure that it is in an unimpaired condition and is securely closed so that there will be no leakage of material under conditions normally incident to transportation.

Any labels previously applied in conformance with 49 CFR 172 subpart E [3] are removed, obliterated, or covered and the Empty label prescribed in 49 CFR 172.450 [3] is affixed to the packaging.

7.4 Other Operations Not applicable.

7-3

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 7.5 References

[1] Daher-TLI, "QUALITY ASSURANCE PROGRAM DESCRIPTION," Rev. 3, 2020.

[2] United States Department of Transportation (USDOT), "Title 49, Code of Federal Regulations, Part 173: ShippersGeneral Requirements for Shipments and Packagings, Subpart I - Class 7 (Radioactive) Materials".

[3] United States Department of Transportation (USDOT), "Title 49, Code of Federal Regulations, Part 173: Hazardous Materials Table, Special Provisions, Hazardous Materials Communications, Emergency Reponse Information, Training Requirements, and Security Plans, Subpart E - Labeling".

7.6 List of Appendices Not applicable.

7-4

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 CONTENTS 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM ........................................ 8-1 8.1 Fabrication Acceptance Tests ..................................................................................................... 8-1 8.1.1 Visual Inspection and Measurements ............................................................................................. 8-1 8.1.2 Weld Examinations ................................................................................................................................. 8-1 8.1.3 Structural and Pressure Tests ............................................................................................................ 8-1 8.1.4 Leakage Tests ............................................................................................................................................ 8-1 8.1.5 Component and Materials Tests ........................................................................................................ 8-2 8.1.6 Tests for Shielding Integrity................................................................................................................ 8-2 8.1.7 Thermal Acceptance Tests ................................................................................................................... 8-2 8.1.8 Miscellaneous Tests ................................................................................................................................ 8-2 8.2 Maintenance Program ................................................................................................................... 8-3 8.2.1 Structural and Pressure Tests ............................................................................................................ 8-3 8.2.2 Leakage Tests ............................................................................................................................................ 8-3 8.2.3 Component and Material Tests .......................................................................................................... 8-3 8.2.4 Thermal Tests ............................................................................................................................................ 8-4 8.2.5 Miscellaneous Tests ................................................................................................................................ 8-4 8.3 References ......................................................................................................................................... 8-4 8.4 List of Appendices........................................................................................................................... 8-5 8-i

Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM Per the requirements of 10 CFR 71.85(c) [1], this section discusses the inspections and tests to be performed prior to first use of the Versa-Pac.

8.1 Fabrication Acceptance Tests All Versa-Pac packaging materials of construction shall be examined in accordance with the requirements delineated on the drawings in Appendix 1.4.1, Licensing Drawings, per the requirements of 10 CFR 71.85(a) [1].

Source inspections and final release of the package will be performed, verifying the quality characteristics were inspected and that the packaging is acceptable. Any characteristic that is out of specification must be reported. It will then be dispositioned according to procedure. The following tests are performed by the fabricator prior to release of the packaging for use by the User.

8.1.1 Visual Inspection and Measurements Prior to the initial use, a visual inspection is performed including the following items at a minimum:

a. Confirm that the package dimensions are in compliance with the appropriate drawings (This may be accomplished by a review of the Quality Assurance and Fabrication Records).

b. Ensure that all bolts and washers are the correct type and size per the drawing.

c. Ensure that all required gaskets are in place and are in compliance with the drawings.

d. Verify that the nameplates and markings are correct.

8.1.2 Weld Examinations As part of the normal course of fabrication, the Versa-Pac is subjected to visual inspections of all welds and magnetic particle inspection of those welds shown on the fabrication drawings to ensure that the welds of the package are in compliance with the applicable codes and standards required by the drawings and specifications of the Versa-Pac. These inspections are recorded on the Fabrication Control Record as part of the Quality Assurance program [2].

8.1.3 Structural and Pressure Tests The Versa-Pac does not contain any tie-down devices that are a structural part of the package.

The Versa-Pac is handled, loaded, and unloaded using standard handling equipment. The Versa-Pac containment is rated for 15 psig. However, the silicone gasket allows gas to permeate the seal, keeping the Versa-Pac at approximately atmospheric pressure. The Versa-Pac is not a pressure-retaining package and no per unit pressure testing is required prior to use.

No other Structural or Pressure testing is performed.

8.1.4 Leakage Tests The Versa-Pac does not contain any seals or containment boundaries that require leak testing.

Therefore, this section is not applicable.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 8.1.5 Component and Materials Tests The closed cell polyurethane foam, alumina silica paper, and gasket materials are accepted in accordance with the drawing requirements and material specifications outlined in Section 1.4.

Inspect package containment components for any damage that would prove detrimental to their ability to properly function as required.

8.1.6 Tests for Shielding Integrity Shielding tests are not applicable to the Versa-Pac. The Versa-Pac does not contain any biological shielding.

8.1.7 Thermal Acceptance Tests The material properties utilized in Section 3.0, Thermal, are consistently conservative for the Normal Conditions of Transport (NCT) and Hypothetical Accident Condition (HAC) thermal analyses. As such, with the exception of the tests required for specific packaging components, as discussed in Section 8.1.5, Component and Material Tests, specific acceptance tests for material thermal properties are not required or performed.

8.1.8 Miscellaneous Tests No other additional tests are required prior to use of the Versa-Pac.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 8.2 Maintenance Program This section describes the maintenance program used to ensure continued performance of the Versa-Pac. The Versa-Pac is maintained consistent with a 10 CFR 71 Subpart H Quality Assurance program [3]. Packages that do not conform to the license drawings are removed from service until they are brought back into compliance. Repairs are performed in accordance with approved procedures and consistent with the QA program.

The User shall establish written procedures for the periodic maintenance and inspection of the Versa-Pac requiring the following as a minimum:

8.2.1 Structural and Pressure Tests The Versa-Pac does not contain any lifting/tie-down devices that require load testing. No pressure tests are necessary to ensure continued performance of the Versa-Pac.

8.2.2 Leakage Tests No leakage tests are necessary to ensure continued performance of the Versa-Pac.

8.2.3 Component and Material Tests 8.2.3.1 Prior to Each Use The following items shall be performed as a minimum prior to each package use for shipment:

a. Visually inspect the outer and inner surfaces as appropriate for rust or other superficial discontinuities. Properly trained personnel should repair any adverse indications as necessary in accordance with the drawing requirements.

b. Visually inspect all gaskets and pads for wear and/or deterioration and replace as necessary. Inner containment pads may be removed, if desired, for one-time-only shipments where the container is buried or otherwise destroyed.

c. Inspect all sealing surfaces for damage that would interfere with the safe use of the package.

d. During visual inspection, the exterior surfaces of the package should be inspected for any corrosion. If found, these areas should be evaluated in accordance with 8.2.3.2(d) below.

e. When using the VP-55 with 5-inch pipe container, visually inspect the threads on the pipe containment vessel pipe body and pipe cap. If the threads are damaged continuously from the bottom of the thread to the top, reject the part. Repair minor damage using a thread-dressing tool.

f. If shipping 1S/2S UF6 cylinders, verify that the inner cavity foam liner is not damaged.

Damage means any significant piece of the foam liner is missing such that the thickness of the liner is less than 2 inches (5.08 cm) in any location. If large pieces of foam are missing, reject the part.

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 8.2.3.2 Every Five Years The Owner of the individual Versa-Pac shall perform and maintain a record of the following inspections at a minimum:

a. All inspections listed in Section 8.2.3.1.

b. Full visual inspection of all accessible surfaces and welds for the presence of cracks or other unacceptable discontinuities. Any questionable condition of a weld shall be subject to further examination to assure proper compliance. Any weld defects shall be repaired in accordance with the appropriate procedures.

c. Check flanges and covers for warping and/or distortion that prevent proper closure.

d. During the visual inspection of exterior surfaces, if areas are suspected of having corrosion, the inspection should ensure that corrosion has not reduced the outer package wall thickness by more than 10% of the nominal thickness over a 6 in.2 (38.7 cm2) square area.

When visual inspection cannot assure sufficient wall thickness, other methods of inspection should be utilized, such as ultrasonic testing, to assure acceptability.

e. All repairs shall be performed by sources that are competent and properly trained. Allowable repairs shall include repairs made to welds and base metal. Repairs that require welding shall be made by welders who are qualified in accordance with the ASME Boiler and Pressure Vessel Code [4] and/or Section 5 of AWS D1.1 [5]. Certification of weld procedures and welder qualifications shall be provided.

f. Weigh the container to verify that the container is within 10 lb. (4.54 kg) of the original fabrication weight recorded on the nameplate.

g. If the package contains payload or is in transit at the test due date, the inspection may be deferred to allow unloading and/or transport of the package, as necessary.

8.2.4 Thermal Tests No thermal tests are necessary to ensure continued performance of the Versa-Pac .

8.2.5 Miscellaneous Tests Localized deformations in the outer drum of the Versa-Pac are permitted up to 1 in. (2.54 cm) provided the shell material is not breached. The package may be repaired in accordance with the drawings in Appendix 1.4.1, Packaging General Arrangement Drawings.

8.3 References

[1] Nuclear Regulatory Commission (NRC), Title 10, Part 71-Packaging and Transportation of Radioactive Material.

[2] Daher-TLI, "QUALITY ASSURANCE PROGRAM DESCRIPTION," Rev.3, 2020.

[3] Nuclear Regulatory Commission (NRC), "Title 10, Part 71-Packaging and Transportation of Radioactive Material, Subpart H - Quality Assurance".

[4] The American Society of Mechanical Engineers (ASME), "Boiler and Pressure Vessel Code, BPVC-IX -- Section IX, Welding and Brazing Qualifications," 2015.

[5] American Welding Society (AWS), "D1.1/D1.1M:2010, Structural Welding Code - Steel".

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Docket No. 71-9342 Versa-Pac Safety Analysis Report Rev 12, February 2021 8.4 List of Appendices Not applicable.

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