ML20363A167

Application for Certificate of Compliance for the Industrial Nuclear Company Raw Material Shipping Container, Revision 0, Docket 71-9387

ML20363A167
Person / Time
Site:	07109387
Issue date:	12/18/2020
From:	Maret Rose Industrial Nuclear Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
WCAllen - NMSS/DFM/STL - 301.415.6877
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ML20363A166	List: ML20363A167
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I I

INDUSTRIAL NUCLEAR CO., INC.

December 18, 2020 Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards US Nuclear Regulatory Commission Washington, DC 20555-001

SUBJECT:

Application for Certificate of Compliance for the Industrial Nuclear Company Outer Pack-Raw Material Shipping Container, Revision 0, Docket 71-9387

Dear Sir/Madam:

Industrial Nuclear Company (INC) hereby submits this application for a Certificate of Compliance (C of C) for the INC Outer Pack-Raw Material Shipping Container (OP RMSC) package. Enclosed is one electronic copy of the Safety Analysis Report (SAR).

The enclosed SAR includes all test data and analyses for the certification of this shipping container package as required by Title 10, Energy, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 1-1-2018 Edition.

The OP-RMSC is INC's first shipping container to contain no Depleted Uranium for shielding, and is used to transport bulk raw materials from material irradiation services to the manufacturer for processing.

Please contact Mike Rose at 510.352.6766 if you have any questions.

Sincerely, Mike Rose, QA Manager/AR-SO Industrial Nuclear Company CC: William Allen 0 14320 Wicks Blvd., San Leandro, CA 945TT Tel: (510) 352-6767 Fax: (510) 352-6772 0 3E NDT, LLC 300 Hwy 146N, La Porte, TX TT571 Tel: (281)470-2010 Fax: (281)470-2024 www. ir100.ccm

SAFETY ANALYSIS REPORT OUTER PACKAGE-RAW MATERIAL SHIPPING CONTAINER Docket No. 71-9387 Revision 0 December 2020 Industrial Nuclear Company, Inc.

14320 Wicks Blvd.

San Leandro, California 94577 (510) 352-6767

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 TABLE OF CONTENTS 1.0 General Information ............................................................................................................. I 1.1 Introduction ...................................................................................................................... I L.2 Package Description ......................................................................................................... L 1.2. l Packaging ................................................................................................................... I 1.2.2 Contents of Packaging ............................................................................................... I 1.2.3 Special Requirements for Plutonium ......................................................................... 2 1.2.4 Operational Features .................................................................................................. 2 1.3 Appendices ....................................................................................................................... 5 1.3. I General Arrangement Drawings ................................................................................ 5 2.0 Structural Evaluation ......................................................................................................... 13

2. I Description of Structural Design .................................................................................... 13 2.1.1 Discussion ................................................................................................................ 13 2.1.2 Design Criteria ......................................................................................................... 16 2.1.3 Weights and Center of Gravity ................................................................................ 17 2.1.4 Identification of Codes and Standards for Package Design ..................................... 17 2.2 Materials ......................................................................................................................... 17 2.2. l Material Properties and Specifications .................................................................... 17 2.2.2 Chemical, Galvanic, or Other Reactions.................................................................. 19 2.2.3 Effects of Radiation on Materials ............................................................................ 19 2.3 Fabrication and Examination ......................................................................................... 19 2.3.1 Fabrication ............................................................................................................... 19 2.3.2 Examination ............................................................................................................. 19 2.4 General Requirements for All Packages ........................................................................ 19 2.4.1 Minimum Package Size ........................................................................................... 19 2.4.2 Tamper Indicating Device........................................................................................ 20 2.4.3 Positive Closure ....................................................................................................... 20 2.4.4 Valves ...................................................................................................................... 20 2.4.5 Package Design ........................................................................................................ 20 2.4.6 External Temperatures ............................................................................................. 20 2.4.7 Venting ..................................................................................................................... 20 2.5 Lifting and Tie-down Devices for All Packages ............................................................ 20

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.5. l LiftingDevices......................................................................................................... 20 2.5.2 Tie-Down Devices ................................................................................................... 21 2.6 Normal Conditions of Transport .................................................................................... 21 2.6. l Heat .......................................................................................................................... 21 2.6.2 Cold.......................................................................................................................... 21 2.6.3 Reduced External Pressure ...................................................................................... 22 2.6.4 Increased External Pressure ..................................................................................... 22 2.6.5 Vibration .................................................................................................................. 22 2.6.6 Water Spray ............................................................................................................. 22 2.6.7 Free Drop ................................................................................................................. 22 2.6.8 CornerDrop ............................................................................................................. 22 2.6.9 Compression ............................................................................................................ 22 2.6.10 Penetration ............................................................................................................... 23 2.7 Hypothetical Accident Conditions ................................................................................. 23 2.7.1 FreeDrop ................................................................................................................. 24 2.7.2 Crush ........................................................................................................................ 24 2.7.3 Puncture ................................................................................................................... 25 2.7.4 Thermal .................................................................................................................... 26 2.7.5 Immersion- Fissile Material ................................................................................... 26 2.7.6 Immersion -All Packages ....................................................................................... 26 2.7.7 Deep Water Immersion Test (for Type B Packages Containing More than l 0 5 A2)26 2.7.8 Summary of Damage ............................................................................................... 26 2.8 Accident Conditions for Air Transport of Plutonium .................................................... 28 2.9 Accident Conditions for Fissile Material Packages for Air Transport ........................... 28 2.10 Special Form ............................................................................................................... 28 2.11 Fuel Rods .................................................................................................................... 28 2.12 Appendix .................................................................................................................... 29 2.12.1 Certification Tests .................................................................................................... 29 2.12.1 Certification Tests .................................................................................................... 30 3.0 Thermal Evaluation............................................................................................................ 59

3. I Description of Thermal Design ...................................................................................... 59 3.1.1 Design Features ........................................................................................................ 59 3.1.2 Content's Decay Heat .............................................................................................. 59 II

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 3.1.3 Summary Tables of Temperatures ........................................................................... 59 3.1.4 Summary Tables of Maximum Pressures ................................................................ 59 3.2 Material Properties and Component Specifications ....................................................... 59 3.2.1 Material Properties ................................................................................................... 59 3.2.2 Component Specifications ....................................................................................... 60 3.3 Thermal Evaluation under Normal Conditions of Transport ......................................... 60 3.3.1 Heat and Cold .......................................................................................................... 60 3.3.2 Maximum Normal Operating Pressure .................................................................... 64 3.4 Thermal Evaluation under Hypothetical Accident Conditions ...................................... 64 3.4.1 Initial Conditions ..................................................................................................... 64 3.4.2 Fire Test Conditions ................................................................................................. 65 3.4.3 Maximum Temperatures and Pressures ................................................................... 65 3.4.4 Maximum Thermal Stresses .................................................................................... 65 3.4.5 Accident Conditions for Fissile Material Packages for Air Transport .................... 65 3.5 Appendix ........................................................................................................................ 66 3.5.1 Sample of ANSYS Input Files ............................................................................... 66 4.0 Containment ....................................................................................................................... 76 5.0 Shielding Evaluation .......................................................................................................... 77 5.1 Description of Shielding Design .................................................................................... 77 5.1.1 Design Features........................................................................................................ 77 5.1.2 Summary Table of Maximum Radiation Levels ...................................................... 77 5.2 Source Specification....................................................................................................... 78 5.2.1 Gamma Source ......................................................................................................... 78 5.2.1 Neutron Source ........................................................................................................ 78 5.3 Shielding Model ............................................................................................................. 79 5.3.I Configuration of Source and Shielding .................................................................... 79 5.3.2 Material Properties ................................................................................................... 81 5.4 Shielding Evaluation ...................................................................................................... 81 5.4.1 Methods .................................................................................................................... 81 5.4.2 Input and Output Data.............................................................................................. 82 5.4.3 Flux-to-Dose-Rate Conversions............................................................................... 82 5.4.4 External Radiation Levels ........................................................................................ 83 5.5 Appendix ........................................................................................................................ 85 iii

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 5.5.l Sample MCNP Input File (RMSC_Co60_up.i) ....................................................... 85 6.0 Criticality Evaluation ......................................................................................................... 92 7.0 Package Operations ............................................................................................................ 93

7. I Package Loading ............................................................................................................ 93 7.1.1 Preparation of the OP-RMSC for Loading .............................................................. 93 7.1.2 Loading the Special Form Contents into the RMSC ............................................... 93 7.1.3 Preparation for Transport ......................................................................................... 93 7.2 Package Unloading ......................................................................................................... 94 7.2.1 Receipt of OP-RMSC Package from Carrier ........................................................... 94 7.2.2 Removal of Special Form Contents from the RMSC .............................................. 94 7.3 Preparation of Empty OP-RMSC Package for Transport .............................................. 95 8.0 Acceptance Tests and Maintenance Program .................................................................... 96 8.1 Acceptance Tests ............................................................................................................ 96

8. l. l Visual Inspections and Measurements ..................................................................... 96 8.1.2 Weld Examinations .................................................................................................. 96 8.1.3 Structural and Pressure Tests ................................................................................... 96 8.1.4 Leakage Tests........................................................................................................... 96 8.1.5 Component and Material Tests ................................................................................ 96 8.1.6 Shielding Tests ......................................................................................................... 96 8.1.7 Thermal Tests........................................................................................................... 96 8.1.8 Miscellaneous Tests ................................................................................................. 96 8.2 Maintenance Program .................................................................................................... 97 8.2.1 Structural and Pressure Tests ................................................................................... 97 8.2.2 Leakage Tests........................................................................................................... 97 8.2.3 Component and Material Tests ................................................................................ 97 8.2.4 Thermal Tests ........................................................................................................... 97 8.2.5 Miscellaneous Tests - Shielding .............................................................................. 97 IV

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 1.0 GENERAL INFORMATION This chapter ofthe Outer Package, Raw Material Shipping Container (hereto referred to as the OP-RMSC) Safety Analysis Report presents a general introduction and description of the OP RMSC package. A detailed description of the major packaging and payload components is presented in the following sections. Detailed drawings are presented in Appendix 1.3.1, General Arrangement Drawings.

1.1 Introduction The OP-RMSC package is a transportation package designed to transport the Raw Material Shipping Container (RMSC) raw material special form capsules containing either cobalt-60 (Co-60), iridium-I 92 (Ir-I 92), or selenium-75 (Se-75) radioactive material. The RMSC will carry up to four (4) special forma capsules that contain the radioactive material. The design is optimized to provide maximum safety during both operations and transport conditions. Both the OP-RMSC and the RMSC consist of a welded cylindrical shell with bolted closure lids. Since the OP-RMSC package does not possess the primary gamma shielding, only the RMSC payload, which utilizes tungsten gamma shields, is relied upon for performing the shielding safety function. Therefore, no shielding credit is assigned to the OP-RMSC package itself.

Authorization is sought for shipment of raw material special form source capsules containing Co-60, Ir-I 92, or Se-75 isotopes as a T7pe B(U)-96, special form material package per the definitions delineated in t O CFR §71.4 . The transport index (TI) for the package, determined in accordance with the definition of IO CFR §71.4, is determined for each shipment. The TI is based on the radiation dose rate at I meter (3.3 feet) from the external surface of the package (method for the transport index is defined in Chapter 7 .0, Package Operations).

1.2 Package Description 1.2.1 Packaging The OP-RMSC is a Type B(U)-96 package designed for transportation of only special form radioactive materials, which are contained in the RMSC payload. The maximum gross weight of the package is 650 pounds, and its primary components of construction are identified in Figure 1.2-1 and Figure 1.2-2. The radioactive payloads in the RMSC are raw material special form capsules, and are described in Section 1.2.2, Contents ofPackaging. Primary shielding is provided by tungsten shields in the RMSC payload, which is illustrated in Figure 1.2-3. The tungsten shields are machined solid form castings, and are illustrated in Figure 1.2-4. Detailed drawings of the OP-RMSC packaging are provided in Appendix 1.3.1, General Arrangement Drawings.

1.2.2 Contents of Packaging The OP-RMSC is designed to transport the RMSC payload. The RMSC is designed to carry up to four (4) raw material special form capsules, each containing a maximum of4,000 Ci (173 TBq) of lr-192, or 4,000 Ci (173 TBq) ofSe-75. The maximum radioactive content ofCo-60 per shipment 1 Title 10, Code of Federal Regulations, Part 71 ( 10 CFR 71 ), Packaging and Transportation of Radioactive Material, 1-1-20 Edition.

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 is limited to 2 Ci (0.07 TBq). For the total four raw material special form capsules, the maximum radioactive content for the OP-RMSC package is 16,000 Ci (592 TBq).

The maximum decay heat for the OP-RMSC package is I 00 W (341 Btu/hr).

1.2.3 Special Requirements for Plutonium This section does not apply, since plutonium is not transported in the OP-RMSC package.

1.2.4 Operational Features There are no operationally complex features of the OP-RMSC package. The radioactive material contents (described in Section l .2.2, Contents ofPackaging) are confined in special fonn capsules that are within the RMSC cavity, which is surrounded by tungsten gamma shields. The gamma shields are contained in a welded pipe with a bolted closure lid, as shown in Figure 1.2-4.

The RMSC payload is then placed in the OP-RMSC payload cavity and a separate inner closure lid is installed and secured utilizing eight (8) I /2-13 UNC hex bolts, as shown in Figure 1.2-2. A vented outer closure lid is then secured to the OP-RM SC body by eight (8) I /2-13 UNC hex bolts. The OP-RMSC package outer closure lid is fitted with a 3/8- I 6 UNC threaded hole to attach a standard lifting device to facilitate handling. Sequential steps of operation are provided in Chapter 7.0, Package Operations.

CLOSURE UD 1/2" CLOSRE LJD BOLTS (8 PLACES)

TAMP ER INDICATED SEALS BODY Figure 1.2 Isometric View of the OP-RMSC Packaging 2

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 1.2 Sectional View of the OP-RMSC Packaging HOIST RING CLOSURE LID BODY Figure 1.2 Isometric View of the RMSC Payload 3

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 3/8" CLOSURE LID BOLTS (6 PLACES)

PAYLOAD CAVITY

( <l) 1 1/2" X 3.0" H)

TUNGSTEN SHIELDING Figure 1.2 Sectional View of the RMSC Payload 4

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 1.3 Appendices 1.3.1 General Arrangement Drawings 5

Drawings Withheld per 10 CFR 2.390 INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.0 STRUCTURAL EVALUATION This chapter presents the structural design criteria, weights, mechanical properties of material, and structural evaluations that demonstrate that the Outer Package, Raw Material Shipping Container (OP-RMSC) package meets all applicable structural criteria for transportation as defined in 10 CFR 712

• 2.1 Description of Structural Design The primary evaluation of the OP-RMSC package is performed with various full-scale tests. The results of the tests are provided in the following sections. Analyses of non-tested structural aspects are also provided.

The OP-RMSC package consists of four major fabricated components: I) a welded, outer stainless steel pipe assembly that is welded to an inner stainless steel pipe, which forms the payload cavity,

2) a bolted vented closure lid that is secured to the outer pipe, 3) a bolted inner closure lid that covers the payload cavity, and 4) polyurethane foam between the inner and outer pipes.

The RMSC payload consists of three major fabricated components: I) a welded stainless steel pipe assembly that is welded to a smaller pipe assembly, which forms the payload cavity, 2) a tungsten shield that covers and shields the payload cavity, 3) a bolted closure lid that covers the cavity tungsten shield, and 4) a fixed tungsten shield between the outer pipe and inner pipe assemblies.

2.1.1 Discussion The OP-RMSC is a welded and bolted assembly that consists of an outer 0 \ 8-inch x 223/4 inch high, Schedule IOS stainless steel pipe and an inner 010-inch x 121/4 inch high, Schedule IOS stainless steel pipe. The inner pipe forms the payload cavity. The annular space between the inner and outer pipes is filled with approximately 32 pounds of rigid polyurethane foam that provides limited impact protection of the payload, which is a RMSC. A 3/8-inch thick, 133/4 inch diameter stainless steel plate, which is secured with eight (8) 1/2-inch hex bolts, encloses the payload cavity. Above the inner lid, a 3/4-inch thick, 171/2 inch diameter stainless steel closure lid is secured to the outer 18-inch diameter stainless steel pipe body with eight (8) I/2-13 UNC hex bolts. The outer lid is slotted to dissipate decay heat from the payload cavity via convective heat transfer. Within the payload cavity, there are four (4) 3/8-inch thick stainless steel vertical bars welded to the inner cavity wall. The bars are circumferentially located at 90-degrees to minimize the clearance between the RMSC payload and the cavity wall. The maximum tare and gross weight of the OP-RMSC package is 270 pounds (122 kg) and 650 pounds (295 kg),

respectively, and is illustrated in Figure 2.1-1 and Figure 2.-2.

The RMSC is designed to transport up to 2 Ci (0.07 TBq) ofCo-60, or 16,000 Ci (592 TBq) of lr-192, or Se-75 isotopes in raw material special form capsules. The RMSC payload consists of a welded outer 8-inch diameter Schedule IOS stainless steel pipe that surrounds a tungsten shield that contains a I1/2 inch diameter x 3 inch high payload cavity. Above the payload cavity is a 4.2-inch diameter x 3.6 inch high tungsten gamma shield that is placed over the cavity. The closure lid is 2

Title I0, Code of Federal Regulations, Part 71 (IO CFR 71 ), Packaging and Transportation of Radioactive Material, 1-1-20 Edition.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 then placed over the tungsten shield and secured to the body by six (6) hex head bolts. The RMSC payload weighs approximately 380 pounds (172 kg). and is illustrated in Figure 2.1-3.

CLOSURE LID 1/2' CLOSRE LID SOLTS (8 PLACES)

TAMPER INDICATED SEALS BODY Figure 2.1 Isometric View of the OP-RMSC Packaging 14

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.2 Sectional View of the OP-RMSC Packaging 15

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 318" CLOSURE LID BOLTS (6 PLACES)

PAYLOAD CAVITY

($1 1/2" X 3.0" H)

TUNGSTEN SHIELDING Figure 2.3 Sectional View of the RMSC Payload 2.1.2 Design Criteria 2.1.2.1 Basic Design Criteria The OP-RMSC package is primarily demonstrated to satisfy the requirements of 10 CFR 71 via full-scale tests. For evaluation of a lifting attachment, the design criteria is that the structural lifting features do not exceed the material's yield strength when subjected to the requirements of 10 CFR §71.45(a).

2.1.2.2 Miscellaneous Structural Failure Modes 2.1.2.2.1 Brittle Fracture The structural materials of the OP-RMSC packaging include stainless steel and tungsten. Each material is not susceptible to brittle fracture at temperatures as low as -20 °F (-29 °C) as described below.

The OP-RMSC packaging and the RMSC payload are fabricated from austenitic stainless steel pipe, plate, and bar. This material does not undergo a ductile-to-brittle transition in the temperature range of interest [i.e., down to -40 °F (-40 °C)], and thus does not require evaluation for brittle fracture.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 The tungsten shield material, which is enclosed by the welded stainless steel pipe assembly, was free drop and puncture tested at temperatures less than-20 °F (-29 °C). As documented in the certification test report', the tungsten gamma shields in the RMSC payload passed all the drop tests, which included cumulative damage effects, with no loss of shielding or confinement capability. Based on the low temperature testing of the OP-RMSC package, brittle fracture of the tungsten gamma shields in the RMSC payload is not a concern.

The closure lid bolts are hex bolts fabricated from ASTM A320, Grade L43 or L 7 materials.

These materials are specifically intended for low-temperature service applications. The Charpy impact tests for this material are recommended to be perform at -150 °F (-10 l 0C)4 for these material grades. Therefore, brittle fracture of the closure lid bolts is not a concern.

2.1.2.2.2 Fatigue Because the OP-RMSC package is an essentially a rigid body, no structural failures of the confinement boundary due to fatigue will occur.

2.1.2.2.3 Buckling The OP-RMSC package provides only a confinement boundary. For normal condition and hypothetical accident conditions, the RMSC confinement boundary (i.e., the tungsten gamma shields) will not buckle due to free or puncture drops. This conclusion has been demonstrated via full-scale tests of the OP-RMSC package.

2.1.3 Weights and Center of Gravity The maximum gross weight of the OP-RMSC package is 650 pounds (295 kg). The center of gravity of the assembled package is along the vertical centerline axis, approximately 13.4 inches above the bottom of the package. Because the overall mass is dominated by the tungsten gamma shields, the package center of gravity is near the center of gravity for the RMSC payload.

2.1.4 Identification of Codes and Standards for Package Design Since the package contains limited quantities of radioactive material, and does not contain a pressure boundary, the OP-RMSC package is only designed to industrial metal fabrication standards.

2.2 Materials 2.2.1 Material Properties and Specifications Mechanical properties for the materials utilized for the structural components of the OP-RM SC package are provided in this section. Temperature-dependent material properties for the austenitic stainless steel structural components are obtained from Section TI, Part D, of the 3 Ora110 Federal Services LLC, Document TR-3023626-000, Certification Test Reportfor the OP-RMSC Package, Revision 0, August 17, 2020.

4 American Society ofTesting and Materials (ASTM) International, Standard Specification for Alloy-Steel and Stainless Steel Bolting Materials for Low-Temperature Service, A320/A320M- I 8.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 ASME Boiler and Pressure Vessel (B&PV) Code5 . Since the evaluation of the OP-RMSC package is primarily via full-scale tests, only the material properties that are used in the analysis portion of the evaluation are given. Table 2.2-1 presents the properties of the structural materials for Type 304 stainless steel utilized in the package.

The tungsten gamma shields that are utilized in the RMSC payload are a tungsten heavy alloy, which is 93%- 97% tungsten alloyed with nickel (Ni) and iron (Fe). The addition of the nickel and iron improves the machinability compared to pure tungsten. Typical room temperature properties are provided in Table 2.2-2. Since the tungsten gamma shields are not a primary structural material for the RMSC payload, these typical properties are provided for information only.

Table 2.2 Type 304 Stainless Steel Material Properties Design Coefficient of Yield Ultimate Stress Elastic Thermal Strength Strength Intensity Modulus, Expansion, x10 ,

4 Material Temperature, (Sy), psi (Su), psi (Sm), psi x10'* psi in/inl"F Specification °F © (3) (5)

-40 30,000 75,000 20,000 28.8 8.1

-20 30,000 75,000 20,000 28.7 8.2 70 30,000 75,000 20,000 28.3 8.5 Type 304 100 30,000 75,000 20,000 28.J 8.6 Stainless Steel 200 25,000 71,000 20,000 27.5 8.9 300 22,400 66,200 20,000 27.0 9.2 400 20,700 64,000 18,600 26.4 9.5 Notes:

CD ASME B&PV Code,Section II, Part D, Table Y-I

@ ASME B&PV Code,Section II, Part D, Table U

@ ASME B&PV Code, Section H, Part D, Table 2A

@ ASME B&PV Code,Section II, Part D, Table TM-I, Material Group G G> ASME B&PV Code,Section II, Part D, Table TE- I, Material Group 3, Mean

@ When necessary, values are linearly interpolated or extrapolated and given in bold text.

(i) The weight density and Poisson's ratio for stainless steel are 0.285 lb./in3 and 0.29, respectively Table 2.2 Tungsten Heavy Metal Material Typical Room Temperature Properties*

Elastic Coefficient of Density, Yield Ultimate Modulus,x10' Thermal Expansion Alloy lb.Jin Strength, psi Strength, psi psi -&

x10 ,in/inl'F 176 0.636 89,900 126,900 52.2 2.95 185 0.668 87,000 J 16,000 55.8 2.78

• Source: www.plansee.com, Densimet <<>

176 & 185 heavy metals 5

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section H, Materials, Part A - Ferrous Material Specifications, and Materials, Part D - Properties, 2017 Edition.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 2.2.2 Chemical, Galvanic, or Other Reactions The RMSC payload that fully surrounds the tungsten gamma shields is fabricated from Type 304 stainless steel. Since tungsten and Type 304 stainless steel materials are very near each other on the galvanic corrosion chart, and with no electrolyte present, there will not be a significant galvanic reaction between these two materials. Additionally, the stainless steel of the OP-RMSC package does not have significant reactions with the interfacing components, air, or water.

2.2.3 Effects of Radiation on Materials The gamma radiation associated with the radioactive material will have no effect on the austenitic stainless steel or the tungsten shields comprising the structural and shielding materials of the OP-RMSC package. As discussed in Section 2. I. I, Discussion, the polyurethane foam provides only limited impact protection of the RMSC payload. The effect of the radiation on the polyurethane foam to provide this minimal protection is negligible.

2.3 Fabrication and Examination 2.3.1 Fabrication Both the OP-RMSC package and RMSC payload are fabricated utilizing conventional metal forming and joining techniques. Materials are procured in accordance with the standards delineated on the drawings in Appendix 1.3.1, General Arrangement Drawings. All welding procedures and welding personnel are 1ualified in accordance with Section IX of the ASME Boiler and Pressure Vessel (B&PV) Code 2.3.2 Examination The primary safety function of the OP-RMSC package is to provide protection of the RMSC payload that contains the gamma shielding for the special form radioactive material. To verify this function, each tungsten gamma shield is examined by performing a shielding test, as delineated in Section 8.1.6, Shielding Tests, prior to being utilized in the fabrication of a RMSC payload. In addition, all specified welds are visually inspected in accordance with the notes identified in Appendix 1.3. l, General Arrangement Drawings.

2.4 General Requirements for All Packages The OP-RMSC package is evaluated, with respect to the general standards for all packaging specified in l O CFR §71.432

• Results of the evaluations are discussed in the following sections.

2.4.1 Minimum Package Size The smallest overall dimension of the OP-RMSC package is the 18 inch diameter of the body.

This dimension is greater than the minimum dimension of 4 inches (10 cm) specified in IO CFR

§71.43(a). Therefore, the requirements of IO CFR §71.43(a) are satisfied.

6 American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section IX, Qualification Standardfor Welding and Brazing Procedures, Welders, Brazers, and Welding and Brazing Operators, 2017 Edition.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.4.2 Tamper Indicating Device A tamper indicating seal (wire/lead security seal) is attached to a pair of the closure lid bolts (refer to Figure 2.1-1 ), which provide visual evidence that the closure lid was not tampered during transportation. Therefore, the requirements of IO CFR §71.43(b) are satisfied.

2.4.3 Positive Closure The OP-RMSC package cannot be opened inadvertently. Positive closure of the OP-RMSC package is provided by the bolted closure lid. Therefore, the requirements of IO CFR §71.43(c) are satisfied.

2.4.4 Valves Because the OP-RMSC package is a confinement system and designed to transport only special form radioactive materials, there are no valves or other pressure retaining devices on the package. Therefore, the requirements of IO CFR §71.43(e) are satisfied.

2.4.5 Package Design As shown in Section 2.6, Normal Conditions of Transport, 3.3, Thermal Evaluation Under Normal Conditions of Transport, and 5.4, Shielding Evaluation, the OP-RMSC package design satisfies the requirements of 10 CFR §71.71. Therefore, the requirements of 10 CFR §71.43(t) are satisfied.

2.4.6 External Temperatures The maximum decay heat load of the special form capsules is l00 watts (341 Btu/hr) for the maximum radioactive content of 16,000 Ci (592 TBq). With this decay heat, the maximum accessible surface temperature of the package in still air and shade is 265 °F (129 °C), which exceeds the temperature limit of 122 °F (50 °C) for a nonexclusive use shipment. With this high surface temperature, an expanded metal personnel barrier is installed over the OP-RMSC package after it is secured to its shipping pallet. The maximum temperature of the accessible surface of the personnel barrier is 115 °F (46 °C). Therefore, the requirements of IO CFR

§7l .43(g) are satisfied by the OP-RMSC package with the personnel barrier.

2.4.7 Venting With special form source capsules encapsulating the radioactive material, the OP-RMSC package does not incorporate any feature that would permit continuous venting during transport.

Therefore, the requirements of 10 CFR §71.43(h) are satisfied by the OP-RMSC package.

2.5 Lifting and Tie-down Devices for All Packages 2.5.1 Lifting Devices The OP-RMSC package is lifted by attaching a standard lift ring or other standard lifting component to the 3/8-16 UNC-28 threaded hole in the center of the 3/4-inch thick closure lid (refer to Figure 2.1-1). For the maximum gross package weight of 650 pounds (295 kg}, the threaded hole will support the total weight. For added conservatism, a weight of700 pounds will be applied to the threaded hole as a tensile load, which results in shear stresses in the internal threads.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 The closure lid is a 3/4-inch thick, Type 304 steel plate. A 3/8-16 UNC-2 B internal thread has a shear area of 0 .8280 in2/in. Conservatively assuming only half the lid thickness for the thread engagement, the developed shear stress in the internal threads will be:

700 T31 16 = = 2 254 psi s- ( l /2)(3/4)(0.8280)

From Chapter 3.0, Thermal Evaluation, the maximum package surface temperature on the closure lid is 308 °F (153 °C). For this evaluation, a conservative temperature of 400 °F will be utilized. At this temperature, the minimum tensile yield strength for Type 304 stainless steel is 20,700 psi (from Table 2.3-1 ). The shear allowable is taken as 0 .6 of the tensile yield strength at temperature, or 0.6 (20,700) = 12,420 psi. Therefore, the minimum factor of safety (F.S.) for lifting is:

12 420 =

F.S. = * +5.51 >3.0 2,254 Additionally, any possible failure of a 3/8 threaded fastener for a lifting component will not impair the ability of the OP-RMSC package to perform its shielding and confinement functions since those safety functions are provided by the RMSC payload. Therefore, the requirements of 10 CFR §71 .45(a) are satisfied.

2.5.2 Tie-Down Devices The OP-RMSC package is secured to a pallet for transport by straps, cargo net, or other standard tie-down equipment that does not attach to the package. The 3/8-16 UNC threaded hole in the closure lid that is utilized for lifting is disabled during transport. Since the design does not contain any tie-down devices that are a structural part of the package, the requirements of 10 CFR §71. 4 5(b) are not applicable to the OP-RMSC package.

2.6 Nonnal Conditions of Transport 2.6.1 Heat The maximum steady state temperature of any component in an ambient environment of I 00 °P (38 °C) and full insolation for the OP-RMSC package is 752 °F (400 °C), which occurs in the stainless steel special form capsules. During the certification drop testing, the OP-RMSC package was exposed to a temperature greater than of 160 °P (71 °C) for several hours in an environmental chamber. There was no loss in operational capability or damage to the test units from the free and puncture drop tests performed at the hot test temperature. For the predicted higher temperatures with the I 00 W (341 Btu/hr) decay heat load, there would also be no loss in operational capability or damage to the package.

2.6.2 Cold For NCT cold condition, a -40 °P (-40 °C) steady state ambient condition is utilized per 10 CFR

§7l .7l(c)(2), without insulation and any decay heat. This results in a uniform temperature of

-40 °P (-40 °C) throughout the package. The OP-RMSC package was exposed to temperatures less than -22 °P (-30 °C) for several hours in an environmental chamber without negative effects.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.6.3 Reduced External Pressure The OP-RMSC package is a confinement boundary for a special form payload and does not have a pressure boundary. Therefore, the effect of reduced external pressure per 10 CFR §71. 71 (c)(3) is not applicable.

2.6.4 Increased External Pressure The OP-RMSC package is a confinement boundary for special form payload and does not have a pressure boundary. Therefore, the effect of increased external pressure per 10 CFR §71.7l(c)(4) is not applicable.

2.6.5 Vibration The OP-RMSC package is a welded stainless steel package that surrounds the RMSC payload, which contains the gamma shields. The only components of the package that are bolted and removable are the outer and inner closure lids. The closure lids are secured to the body by eight (8) I /2-13 UNC hex head bolts that are tightened to a minimum of 75 lbrft torque, and fitted with a tamper indicating seal. The closure lid for the RMSC payload is secured by six (6) 3/8-16 UNC hex head cap screws that are tightened to a minimum of 35 lbrft torque. As evidence by the certification drop testing, the package is essentially rigid, and hence, has a very high natural frequency. Based on the certification testing, the OP-RMSC package will not experience any damage or detrimental effects due to vibration normally incident to normal conditions of transport identified in JO CFR §71.7l(c)(5).

2.6.6 Water Spray The stainless steel materials of construction utilized for the OP-RMSC package are such that the water spray test identified in 10 CFR § 71. 71(c)(6) will have a negligible effect on the package.

2.6.7 Free Drop Since the gross weight of the OP-RMSC package is less than 11,000 pounds (5,000 kg), a 4-foot (1.2 meter) free drop is required per IO CFR §71.71.(c)(7). As discussed in Appendix 2.12.1, Certification Tests, a NCT, 4-foot (1.2-meter) free drop with impact on the package closure lid was performed on a OP-RMSC certification test unit (CTIJ-1) as an initial condition for the subsequent hypothetical accident condition (HAC) tests. As noted in the appendix, there was no significant visible deformation to the OP-RMSC test unit. A radiation survey following all certification testing demonstrated the ability of the OP-RM SC packaging to maintain the shielding and confinement integrity of the RMSC payload. Therefore, the requirements of10 CFR §71.71 (c)(7) are satisfied.

2.6.8 Corner Drop This test does not apply, since the materials of construction do not include wood or fiberboard, as delineated in 10 CFR §7l.7l(c)(8).

2.6.9 Compression A 3,390-pound (1,538 kg) force, which is greater than five times the gross package weight, was applied to the OP-RMSC package while sitting in its normal upright position for a period of24 22

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 hours (refer to Figure 2.6-4). No observable deformation and damage was detected. Therefore, the requirements of JO CFR §71.71 (c)(9) are satisfied.

Figure 2.6 View of OP-RMSC Package Compression Test After 24 Hours 2.6.1 O Penetration Per IO CFR §71.71(c)(IO), a I1/4 inch (3.2 cm) diameter, 13 pound (6 kg), hemispherical end steel rod is required to be dropped from a height of 40 inches (I meter) onto the exposed surface of a package that is expected to be most vulnerable to puncture. The OP-RMSC package was puncture tested more severely in accordance with the hypothetical accident conditions (HAC) per

§71.73(c)(3), which requires the heavier package to be dropped 40 inches (I meter) onto a 6-inch (15 cm) diameter bar in the most vulnerable orientation. As noted in Appendix 2.12.1, Certification Tests, there was no visible significant damage from any of the puncture drops.

Therefore, the requirements of IO CFR §71.71(c)(IO) are satisfied by the HAC puncture drop tests.

2.7 Hypothetical Accident Conditions When subjected to the hypothetical accident conditions as specified in IO CFR §71.73, the OP-RM SC package meets the performance requirements specified in Subpart E of IO CFR 71.

This conclusion is demonstrated in the following subsections, where each accident condition is addressed and the package is demonstrated to meet the applicable design criteria. The method of demonstration is primarily by test. The tests specified in IO CFR §71.73 are applied sequentially, per Regulatory Guide 7.8.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Test results are summarized in Section 2.7.7, Summary ofDamage, with details provided in Appendix 2.12.1, Certification Tests.

2.7.1 Free Drop Subpart F of IO CFR 71 requires performing a free drop test in accordance with the requirements of 10 CFR §71.73(c)(1). The free drop test involves performing a 30 foot (9 meter) free drop onto a flat, essentially unyielding, horizontal surface, with the package striking the surface in an orientation for which the maximum damage is expected. For the OP-RMSC, the free drop is addressed by test, in which several orientations are utilized. The free drop precedes both the puncture and thermal tests.

2.7.1.1 Technical Basis for the Free Drop Tests The drop orientations selected for testing are intended to maximize the damage to the OP-RMSC package and cause a potential separation of the RMSC payload from the inner cavity. Once it separates from the OP-RMSC package, potential damage to the RMSC payload may occur from the subsequent puncture drop event, which could affect the tungsten gamma shielding. Should this condition occur, regulatory radiation limits might be exceeded. Therefore, the primary objective of the 30 foot (9 meter) HAC free drops is to damage the OP-RMSC package that results in the separation of the RMSC payload from the package body.

2.7.1.2 Test Sequence for the Selected Tests Based on the above discussion, the OP-RMSC package was tested for three specific, HAC 30 foot (9 meter) free drop orientations: 1) an impact on the top, 2) an impact on the side, and 3) an impact with CG-over-the top comer. Although only a single "worst-case" 30 foot (9 meter) drop is required per 10 CFR §71.73(c)(\), multiple tests were performed on each test unit to ensure that the most vulnerable package features were subjected to "worst-case" impact forces and deformations. The specific conditions selected for the OP-RMSC Certification Test Units (CTUs) are summarized in Table 2.7-1.

2.7.1.3 Summary of Results from the Free Drop Tests Successful HAC free drop testing of the CTUs indicates that the various OP-RMSC package features are adequately designed to withstand the HAC 30 foot (9 meter) free drop event. The most important result of the testing program was the demonstrated ability of the OP-RMSC package to retain the RMSC payload, which provides the shielding integrity and confinement of the raw material special form capsules, within the inner cavity. Significant results of the free drop testing are as follows:

• No significant damage to the OP-RMSC package structure from the free drop impacts.

• The RMSC payload did not separate from the OP-RMSC package.

Further details of the free drop test results are provided in Appendix 2.12.1, Certification Tests.

2.7.2 Crush Subpart F of l O CFR 71 requires performing a free drop test in accordance with the requirements of IO CFR §71.73(c )(I). The free drop test involves performing a 30 foot (9 meter) free drop onto a flat, essentially unyielding, horizontal surface, with the package striking the surface in an 24

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, J 2/2020 orientation for which the maximum damage is expected. The crush test is required only when the specimen has mass not greater than I,100 lbm ( 500 kg), an overall density not greater than 62.4 lbn/tt' (1,000 kg/m\ and radioactive contents greater than l,000 A2, not as sial form. Since the density of the OP-RMSC package is greater than 62.4 lbn/ft' (1,000 kg/m ), and the radioactive payload is special form, the dynamic crush test is not applicable to the OP-RMSC package.

2.7.3 Puncture Subpart F of IO CFR 71 requires performing a puncture test in accordance with the requirements of IO CFR §71.73(c)(3). The puncture test involves a 40 inch ( I meter) drop onto the upper end of a solid, vertical, cylindrical, mild steel bar mounting on an essentially unyielding, horizontal surface. The bar must be 6 inches ( 15 cm) in diameter, with the top surface horizontal and its edge rounded to a radius of not more than 1/4 inch (6 mm). The minimum length of the bar is to be 8 inches (20 cm). The ability of the OP-RMSC package to adequately withstand this specified drop condition is demonstrated via testing of two full-scale, OP-RMSC CTUs.

2.7.3.1 Technical Basis for the Puncture Drop Tests The drop orientations selected for testing are intended to maximize the damage to the OP-RMSC package and cause potential separation of the RMSC payload from the inner cavity. Once it separates from the OP-RMSC package, potential damage to the RMSC payload may occur, which could affect the tungsten gamma shielding. Should this condition occur, the regulatory radiation limits might be exceeded. Therefore, the primary objective of the 40 inch (I meter) HAC puncture drop is to cause further damage from the 30 foot (9 meter) free drop damage to the OP-RMSC package that could cause significant damage to or separation of the RMSC payload.

2.7 .3.2 Test Sequence for the Selected Tests Based on the above general discussion, the CTUs were specifically tested for three HAC puncture drop orientations that attempted to worsen the damage from the 30 foot (9 meter) free drop as part of the certification test program. Although only a single worst-case" puncture drop is required by JO CFR §7l.73(c)(3), multiple puncture tests were performed to ensure that the most vulnerable package features were subjected to worst-case" impact forces and deformations. The specific conditions selected for the OP-RMSC Certification Test Units (CTUs) are summarized in Table 2.7-1.

2.7.3.3 Summary of Results from the Puncture Drop Tests Successful HAC puncture drop testing of the CTUs indicates that the OP-RMSC design features are adequately designed to withstand the HAC puncture drop event. The most important result of the testing program was the demonstrated ability of the OP-RMSC to contain its RMSC payload for shielding integrity. Significant results of the puncture drop testing are as follows:

• No evidence of any significant damage to the OP-RMSC body due to the impact with the puncture bar.

• The RMSC payload did not separate from the OP-RMSC package.

Further details of the free drop test results are provided in Appendix 2.12.1, Certification Tests.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.7.4 Thermal Subpart P of IO CPR 71 requires performing a thermal test in accordance with the requirements of 10 CFR §71.73(c)(4), which requires a package to be exposed to a hydrocarbon fuel/air fire with a minimum temperature of 1,475 °P (800 °C) for 30 minutes. As discussed in Section 2.7.1, Free Drop, and Section 2.7.3, Puncture, there was no separation of the RMSC payload from the OP-RMSC package. Additionally, all of the structural and shielding materials, which are Type 304 stainless steel and tungsten for the OP-RMSC package and the RMSC payload have melting temperatures of 2,550 - 2,640 °P (1,400 - 1,450 °C) and 6,191 °P (3,422 °C), respectively.

These melting temperatures are significantly higher than the specified fire temperature of 1,475 0

P (800 °C). The only combustible materials in the OP-RMSC package are the non-structural polyurethane foam, which fills the annulus between the payload cavity and the outer pipe body, and the gasket between the inner closure lid and the payload cavity. The combustion of the foam or the gasket material has no effect on the structural or shielding materials of either the OP RMSC package or the RMSC payload. Therefore, the OP-RMSC package satisfies the requirements of 10 CFR §71.73(c)(4).

2.7.5 Immersion - Fissile Material The OP-RMSC package does not transport fissile material. Therefore, 10 CFR §71.73(c)(5) does not apply.

2. 7 .6 Immersion - All Packages The OP-RMSC package is a confinement boundary for special form payload and does not have a pressure boundary. Therefore, the effect of pressure per 10 CPR §71. 73(c)(6) is not applicable.

2.7.7 Deep Water Immersion Test (for Type B Packages Containing More than 105 A2)

The OP-RMSC package contains a maximum of2 Ci (0.07 TBq) ofCo-60, 16,000 Ci (592 TBq) of Ir-192 or Se-75 isotopes, which have A2 values of 11 Ci (.4 TBq), 16 Ci (0.6 TBq) [lr-192] and 81 Ci (3.0 TBq), respectively. Since the OP-RMSC package does not contain more than I 05 A2 quantities of radioactive material, deep immersion per IO CFR §71.6 I is not applicable.

2.7.8 Summary of Damage As discussed in the previous sections, the cumulative damaging effects of free drop and puncture drop tests were satisfactorily withstood by the full-scale OP-RMSC certification testing.

Additionally, the thermal event has no effect on the metallic OP-RMSC package or the RMSC payload. Subsequent radiation post-test surveys of the RMSC CTIJ payloads confirmed that shielding integrity was maintained throughout the test series. Therefore, the requirements of I 0 CPR §71. 73 have been adequately demonstrated by the full-scale testing of the OP-RMSC package.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Table 2.7 Summary of OP-RMSC Certification Test Unit (CTU) Tests and Results Test Unit Angular Orientation Test Test Description Longltudlnal Axis Circumferential Axis No. (Certification Test Unit No.) (0 ° = upright) (0 ° = as marked) Test Results 4 foot, Top Down l

(CTU-1) 180 ° NIA No visible damage was observed.

Inner lid bolts failed, resulting in lid contacting 30 foot, Top Down 2 (CTU-1) 180 ° NIA the closure lid. RMSC remained within the OP-RMSC. No other damaged observed.

Impact created ~4 inch wide flat along the side.

30 foot, Side Drop 3 90 ° oo One closure lid bolt failed. No other damaged (CTU-2) observed.

Impact resulted in a~ 1 /2-inch fold on outer shell.

30 foot, CG-over-Top Comer Five (5) of the closure lid bolts were sheared, 4 132 ° 180 ° (CTU-2) with two (2) bolts remaining on opposite side.

Closure lid remain attached.

Puncture Drop, Top Down, Puncture bar impacted center of closure lid with 5

(CTU-1) 180 ° NIA no observed additional damage.

Puncture bar struck side of package, resulting in Puncture Drop, Side Drop 90 ° oo small deformation of outer shell. No other (CTU-2) damaged observed.

Puncture Drop, Top Down, Puncture bar struck outer shell/closure lid 7 CG-over-Comer 138 ° 180 ° interface, resulting in a small "half-moon" (CTU-2) deformed area. No other damaged observed.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.8 Accident Conditions for Air Transport of Plutonium This section does not apply, since plutonium is not transported in the OP-RMSC package.

2.9 Accident Conditions for Fissile Material Packages for Air Transport This section does not app\y, since ftssi\e materia\ is not transported in the OP-RMSC package.

2.10 Special Fonn The contents of the OP-RMSC package are a maximum of four (4) raw material special form source capsules. All four source capsules are limited to a maximum of 16,000 Ci (592 TBq) per shipment. One certification for an Ir-192 raw material special form capsule that would be transported in OP-RMSC is listed below. Other raw material capsules may be transported in the OP-RMSC provided the capsules are certified as special form.

Manufacture Model Number Certification Number Industrial Nuclear Co., Inc. INC-SFC-1 USA/0798/S-96 2.11 Fuel Rods This section does not apply, since fuel rods are not transported in the OP-RMSC package.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.12 Appendix 2.12.1 Certification Tests 29

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, J 2/2020 2.12.1 Certification Tests Presented herein are the results of normal conditions of transport (NCT) and hypothetical accident condition (HAC) tests that address free drop, puncture, and thermal test performance requirements of 10 CFR 717* The certification tests are fully documented in the certification test report8

• 2.12.1.1 Introduction The OP-RMSC, when subjected to the sequence ofHAC tests specified in 10 CFR §71.73, subsequent to the NCT tests specified in IO CFR §71.71, is demonstrated to satisfy the performance requirements specified in Subpart E of 10 CFR 71. As indicated in the introduction to Chapter 2.0, Structural. Evaluation, the primary proof of performance for the HAC tests is via the use of full-scale testing. In particular, free drop and puncture testing ofOP-RMSC CTUs confirms that the packaging will retain its shielding integrity following a worst-case HAC sequence.

2.12.1.2 Summary As seen in the figures presented in Section 2.12.1.7, Test Results, successful testing of the CTUs indicates that the various OP-RMSC packaging design features are adequately designed to withstand the HAC tests specified in IO CFR §71.73. The most important result of the testing program was the demonstrated ability of the OP-RMSC packaging to maintain its shielding integrity.

Significant results of the free drop tests are as follows:

• No significant damage to the OP-RMSC package structure from the free drop impacts.

• No separation of the RMSC payload from the OP-RMSC package.

Significant results of the puncture drop testing are as follows:

• No evidence of any significant damage to the OP-RMSC body due to the impact with the puncture bar.

• No separation of the RMSC payload from the OP-RMSC package.

2.12.1.3 Test Facilities The free and puncture drop testing was performed utilizing a horizontal concrete slab, which is approximately 9-12 inches thick x IO feet x 15 feet. The concrete slab is setting on a parking lot concrete slab that has an approximate thickness of91/2 inches. A 2 inch x 48 inch x 48 inch steel plate was placed on top of the concrete slab, grouted, and secured to the concrete slab by four (4) 5/8-inch anchor bolts. To increase the effective mass of the impact surface, a 5 inch thick steel plate was placed on top of the 2 inch thick plate and welded to the grouted plate. Considering only the concrete directly underneath the steel plates as being effective with a total thickness of 181/2 inches for the concrete slabs, the mass of the drop pad (concrete and steel plates) is conservatively 7 Title 10, Code ofFederal Regulations, Part 71 (10 CFR 71) Packaging and Transportation of Radioactive Material, 1-1-20 Edition.

8 Orano Federal Services LLC, Document TR-3023626-000, Certification Test Reportfor the OP-RMSC Package, Revision 0, August 17, 2020.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 estimated to be 8,100 lbm, which is more than 10 times the mass of the OP-RMSC CTUs. Based on these characteristics, the drop pad satisfied the requirement of 10 CFR §§71.71 and 71.73 for an essentially unyielding, horizontal surface.

The puncture bar assembly for the puncture tests was a 6-inch (15 cm) diameter x 251/2 inch (65 cm) long bar that was welded to a 3/4-inch (19-mm) thick square steel plate. The top circumferential edge of the bar was rounded to a maximum of l /4-inch (6-mm) radius. The free length of the bar was 251/2 inches (65 cm) (i.e., height above the base plate), thus ensuring an adequate length to facilitate maximum damage to the CTlJ as required by l O CFR §71.73(c)(3). Following the 30-foot (9-meter) free drop tests, the 3/4-inch ( 19 mm) thick plate of the puncture bar assembly was welded to the 5-inch (13 cm) thick steel plate on the drop pad. This configuration ensured that the puncture bar assembly was fully restrained for the puncture drop tests.

2.12.1.4 Certification Test Unit Description The OP-RMSC package is a welded and bolted assembly that consists of an outer 018-inch x 223/4 inch high, Schedule 10S stainless steel pipe and an inner 010-inch x 121/4 inch high, Schedule I OS stainless steel pipe. The inner pipe forms the payload cavity for the RMSC payload. The annular space between the inner and outer pipes is filled with rigid polyurethane foam that provides limited impact protection of the RMSC payload. A 3/8-inch thick, 133/4 inch diameter stainless steel plate, which is secured with eight (8) l/2-inch hex bolts, encloses the payload cavity. Above the inner lid, a 3/4-inch thick, 171/2 inch diameter stainless steel closure lid is secured to the outer 18-inch diameter stainless steel pipe body with eight (8) 1/2-13 UNC hex head bolts. The outer lid is slotted to dissipate decay heat from the payload cavity via convective heat transfer. Within the payload cavity, there are four (4) 3/8-inch thick stainless steel vertical bars welded to the inner cavity wall. The bars are circumferentially located at 90-degrees to minimize the clearance between the RMSC payload and the cavity wall.

The RMSC payload consists of a welded stainless steel pipe assembly that is welded to a smaller pipe assembly, which forms the payload cavity. A fixed tungsten gamma shield is installed between the outer and inner pipe assemblies. A tungsten gamma shield is installed over the payload cavity to provide shielding of the payload cavity, and then a bolted closure lid is installed to retain the cavity tungsten gamma shield over the cavity.

Prior to free drop and puncture testing, the two RMSC CTUs were loaded with dummy raw material source capsules and a holder to simulate the special form capsules, and then loaded into the OP-RMSC CTUs. The actual pre-test weights ofCTU-l and CTU-2 were 646 pounds and 647 pounds, respectively. The CTUs differed slightly from the OP-RMSC packaging design depicted in Appendix 1.3.1, General Arrangement Drawings as follows:

• A neoprene gasket was utilized under the inner lid rather than the specified silicone gasket.

• The tampering indicating seal/safety wire between two of the closure lid bolts was not installed in the CTUs.

Neither of these minor differences had any effect on the response of the CTUs to the free drop and puncture drop tests.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 2.12.1.5 Technical Basis for Tests For the confinement system to fail, the OP-RMSC package would need to fail and allow the RMSC payload to separate from the package. This potential failure mode may only occur if either of the following conditions occurs:

I. Both the inner and outer lids of the OP-RMSC fail, resulting in the RMSC payload being ejected and sustain significant damage and,

2. The RMSC closure lid fails and the cavity tungsten gamma shield separates from the body.

For either of these potential conditions to occur, the OP-RMSC package would need to sustain significant damage due to the normal and hypothetical accident condition free drops, and then sustain further damage due to the 40-inch (I-meter) drop onto a 6 inch (15 cm) diameter vertical steel bar. Therefore, the primary objective of the 4 foot (1.2 meter) normal condition and the 30-foot (9-meter) hypothetical accident condition (HAC) free drops is to damage the OP-RMSC package that causes the RMSC payload to separate and possibly be damaged by the subsequent puncture drop. A secondary objective of the 9-meter (30-foot) HAC free drops is to attempt to damage the RMSC such that the tungsten gamma shields would become exposed, which could result in a loss of shielding.

The following sections provide the technical basis for the chosen test orientations and sequences for the OP-RMSC CTUs.

2.12.1.5.1 Temperature Both cold and hot conditions for the free drops were utilized for the OP-RMSC certification testing. To maximize impact decelerations, a CTU was chilled to below -20 °F (-29 °C). To maximize deformations, a CTIJ was heated to over 160 °F (71 °C). The results of the package testing demonstrated that extreme temperatures had no effect on the shielding integrity of the OP-RMSC package. In addition, the austenitic stainless steel and tungsten materials are not susceptible to brittle fracture, as delineated in Section 2.1.2.2. l, Brittle Fracture.

For the puncture tests, ambient temperatures were utilized for the OP-RMSC certification testing.

2.12.1.5.2 Free Drop Tests The OP-RMSC is qualified primarily by full-scale testing, with acceptance criterion being the ability to demonstrate shield integrity. Per 10 CFR §7l .73(c)(l ), the package is required to "strike an essentially unyielding surface in a position for which maximum damage is expected."

Therefore, for determining the drop orientations that satisfy the regulatory "maximum damage" requirement, attention is focused predominately on the issue of shield integrity of the RMSC payload.

To maximize the damage to the OP-RMSC package and potentially separating the RMSC payload, three orientations have been selected for the free drop testing:

1. Vertical, Top: This orientation targets the OP-RMSC closure lid and the inner closure lid.

Should this impact be sufficiently severe, both of the OP-RMSC lids may fail and eject the RMSC payload from the cavity. The intent of this drop orientation is also to simulate a probable orientation that could occur in actual use in the field.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020

2. Side: This orientation again targets both the OP-RMSC closure lid and the inner closure lid.

Should this impact be sufficiently severe, the OP-RMSC lid assemblies could become damaged and result in a possible ejection of the RMSC payload. Additionally, should the RMSC outer pipe and/or the closure lid fail, the tungsten gamma shielding would be exposed, which could possibly release or expose the special form radioactive sources.

3. CG-Over-Top Corner: This orientation targets the OP-RMSC closure lid and the inner closure lid. The intent of this orientation is to attempt to damage the tungsten gamma shields of the RMSC, and the closures of the payload packages. Should this impact be sufficiently severe, the OP-RMSC closure and inner cavity lids may fail and result in the ejection of the RMSC payload package. Additionally, should the RMSC closure lid fail, the special form radioactive sources could be released or exposed, which would result in unshielded radioactive sources.

2.12.1.5.3 Puncture Drop Tests 10 CFR §71.73(c)(3) requires a free drop of the specimen through a distance of 40 inches (1 meter) onto a puncture bar "in a position for which maximum damage is expected." As in Section 2.12.1.5.2, Free Drop Tests, the "maximum damage" criterion is evaluated primarily in terms of loss of shielding integrity. Loss of shielding integrity could occur should the RMSC payload be ejected from the OP-RMSC body, and subsequent damage of the tungsten gamma shields occurs.

The orientations selected for the puncture tests were the side and CG-over-top corner tests as discussed in Section 2.12. 1 .5.2, Free Drop Tests. The intent of these orientations is to accumulate puncture damage with the damage from the 30-foot free drops for the same orientations.

2.12.1.6 Test Sequence for Selected Free Drop and Puncture Drop Tests The following sections establish the selected free drop, puncture drop, and thermal test sequence for the OP-RMSC CTUs based on the discussions provided in Section 2.12.1.5, Technical Basis for Tests. The tests sequences are summarized in Table 2.12.1-1 and illustrated in Figure 2.12.1-1 and Figure 2.12.1-2.

2.12.1.6.1 Certification Test Unit No. 1 (CTU-1)

Free Drop No. 1 is a NCT free drop from a height of four feet, impacting the top of the package. The 4 foot ( 1.2 meter) drop height is based on the requirements of IO CFR §71.71(c)(7) for a package

[D weighing less than 11,000 pounds. The purpose of this test was intended to cause maximum damage to the packaging in its most probable orientation to possibly eject the RMSC payload. This test was performed at a cold temperature.

Free Drop No. 2 is a HAC free drop from a height of30 feet (9 meter), impacting the top of the package, which is the same impact /77777 point as the NCT Free Drop No. I. In this way, NCT and HAC free drop damage is cumulative. The 30 foot (9 meter) drop height is based on the requirements of 10 CFR §71.73(c)(1 ). The purpose of this test was intended to cause maximum damage to the packaging in its most probable orientation to possibly eject the RMSC payload.

This test was performed at a cold temperature.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Puncture Drop No. 5 impacts directly onto the damage created by Free Drop Test 2, directly on the closure lid. The puncture drop height is based on the requirements of 10 CFR §71.73(c)(3). The purpose of Puncture Drop No. 5 is to cause maximum damage to the closure lid, and possibly result in the ejection of the RMSC payload from the OP-RMSC package.

2.12.1.6.2 Certification Test Unit No. 2 (CTU-2)

EJ Free Drop No. 3 is a HAC free drop from a height of 30 feet, impacting the side. The 30 foot (9 meter) drop height is based on the requirements of 10 CFR §71.73(c)(I). The purpose of this test was intended to cause maximum damage to the closure lid, and possibly damage the RMSC payload. This test was performed at a hot temperature.

/77777 Free Drop No. 4 is a HAC free drop from a height of 30 feet, impacting the top corner, The 30 foot (9 meter) drop height is based on the requirements of 10 CFR §71.73(c)(I ). The purpose of this test was intended to cause maximum damage to the closure lid and possibly separate the RMSC payload. This test was performed at a hot temperature.

/77777 Puncture Drop No. 6 impacts directly onto the damage created by Free Drop Test No. 3, directly on the side of the package. The puncture drop height is based on the requirements of IO CFR

§71.73(c)(3). The purpose of Puncture Drop No. 6 is to cause maximum damage to the closure lid, and possibly damage the RMSC payload.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Puncture Drop No. 7 impacts directly onto the damage created by Free Drop Test No. 4, directly on the top comer. The puncture drop height is based on the requirements of IO CFR §71.73(c)(3). The purpose ofPuncture Drop No. 7 is to cause maximum damage to the closure lid, and possibly damage the RMSC payload.

2.12.1.7 Test Results The following sections report the results offree drop, puncture drop, and thermal tests following the sequence provided in Section 2.12.1.6, Test Sequence for Selected Free Drop, Puncture Drop, and Thermal Tests. Results are summarized in Table 2.12.1-2 (refer also to Figures 2.12.1-1 and 2.12.1-2).

Figures 2.12.1-3 through 2.12.1-23 sequentially photo-documents the certification testing process for the OP-RMSC CTUs.

2.12.1.7.1 Certification Test Unit No. 1 (CTU-1) 2.12.1.7.1.1 CTU-1 Free Drop Test No. 1 Free Drop No. 1 is a NCT free drop from a height of four feet, impacting the top ofthe package.

As shown in Figure 2.12.1-3, the CTU was oriented vertically with respect to the horizontal impact surface (longitudinal angle 180°). The following list summarizes the test parameters:

• verified longitudinal angle as I 80° +/- I 0

• verified drop height as 4 feet (1.2 meter), +2/-0 inches

• measured surface temperature ofinner shell wall as -22 °F at time oftest

• conducted test at 6:37 p.m. on Tuesday, 7/7/2020 time oftest The package rebounded (bounced) upon impact off the drop pad, and remained upright. No external damage was noted. The impact and post-test package are shown in Figures 2.12.1-4 and 2.12.1-5, respectively.

2.12.1.7.1.2 CTU-1 Free Drop Test No. 2 Free Drop No. 2 is a HAC free drop from a height of30 feet, impacting the top ofthe package (closure lid). As shown in Figure 2.12.1-6, the CTU was oriented vertically with respect to the horizontal impact surface (longitudinal angle 180°). The following list summarizes the test parameters:

• verified longitudinal angle as 180 ° +/- I 0

• verified drop height as 30 feet (9 meter), +3/-0 inches

• measured surface temperature ofinner shell wall as-22 °F at time oftest 35

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020

• conducted test at 6:48 p.m. on Tuesday, 7/7/2020 The package impacted the drop pad and did not rebound (bounce). The package remained upright on drop pad. No external damage was noted. The bolts securing the inner lid failed, allowing the inner lid to contact the closure lid. The RMSC payload remained within the OP-RMSC. The impact damage is shown in Figure 2.12.1-7 and Figure 2.12.1-8.

2.12.1.7.1.3 CTU-1 Puncture Drop Test No. 5 Puncture Drop No. 5 impacted directly onto the damage created by Free Drop Test 2, directly on the closure lid. As shown in Figure 2.12.1-9, the CTU was oriented vertically with the top down with respect to the impact pad so that the puncture bar would strike the damage from the 30-foot free drop. The following list summarizes the test parameters:

• verified longitudinal angle as 180° +/-2°

• verified drop height as 40 inches (l meter), +3/-0 inches

• measured surface temperature of outer shell of OP-RMSC as 92 - 94 ° F at time of test

• conducted test at l0:55 a.m. on Wednesday, 7/8/2020 The package rebounded (bounced) off the puncture bar immediately following impact, and fell to its side. The impact struck the previous damage from the 30-foot free drop. No measureable damage was observed from the impact. The post-test condition is shown in Figure 2.12.1-10.

2.12.1.7.1.4 CTU-1 Post-Test Disassembly Post-test disassembly ofCTU-1 was performed on Wednesday, 7/22/20. After removing the OP-RMSC lid, all ofthe hex bolts securing the inner lid were found to have failed. However, there was no damage to the RMSC payload, as shown in Figures 2.12.1-1 I and 2.12.1-12.

2.12.1.7.1.5 CTU-1 Post-Test Radiation Survey Post-test radiation survey ofRMSC CTU-1 was performed on Wednesday, 7/22/20. The post test radiation survey was performed utilizing [r-192 special form radioactive capsules. The total radioactive payload on the day ofthe survey for the post-test survey was 4,297 Curies (Ci) [159 TBq]. To account for the maximum design radioactive payload of16,000 Ci (592 TBq), the measured values were adjusted upward by the ratio of16,000/4,297 or 3.724 to determine the dose rate for the maximum radioactive content. The post-test measured dose rates for the maximum radioactive content of 16,000 Ci (592 TBq) are as follows:

Maximum Dose Rate (Top/Bottom/Side] (mrem/hr)

Test Unit No. Surface 1-meter 2-meters CTU-1 15 I 19 I 123 4 I 0 I 4 0 I 0 I 0 As indicated above, the radiation dose levels were well below the requirements of10 CFR

§7l .47(a) for NCT and 10 CFR §71.5 l (a)(2) for HAC for a non-exclusive use shipment.

36

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 2.12.1.7.2 Certification Test Unit No. 2 (CTU-2) 2.12.1.7.2.1 CTU-2 Free Drop Test No. 3 Free Drop No. 4 is a HAC free drop from a height of 30 feet, impacting the package side. As shown in Figure 2.12.1-13, the CTU was oriented parallel to the horizontal impact surface (longitudinal angle 90°, circumferential angle 0°). The following list summarizes the test parameters:

• verified longitudinal angle as 90° +/- I 0

• verified circumferential angle as 0° +/-2 °

• verified drop height as 30 feet (9 meter), +3/-0 inches

• measured surface temperature of inner shell wall as I 69+ ° F at time of test

• conducted test at 11:01 a.m. on Tuesday, 7/7/2020 The package rebounded (bounced) upon impact off the drop pad, and fell to its side. Impact created a-4 inch wide flat along the side of the outer shell. One closure lid bolt on the impact side failed. No other external damage was noted. The impact damage is shown in Figure 2.12.1-14.

2.12.1.7.2.2 CTU-2 Free Drop Test No. 4 Free Drop No. 4 is a HAC free drop from a height of 30 feet, impacting the top comer of the package. As shown in Figure 2.12.1-15, the CTlJ was oriented 48° with respect to the horizontal impact surface (longitudinal angle 132°, circumferential angle 180°). The following list summarizes the test parameters:

• verified longitudinal angle as 132° +/- l 0

• verified circumferential angle as 180° +/-2°

• verified drop height as 30 feet (9 meter), +3/-0 inches

• measured surface temperature of inner shell wall greater than I 71 °F at time of test

• conducted test at 11 :25 a.m. on Tuesday, 7/7/2020 The package rebounded (bounced) upon impact off the drop pad, and fell to its side. The impact produced a-1/2 inch buckle/fold on the outer shell. Five (5) of the remaining seven (7) closure lid bolts failed. However, the closure lid did not separate from the body. No other damage was visible or noted. The impact damage is shown in Figure 2.12.1-16.

2.12.1.7.2.3 CTU-2 Puncture Drop Test No. 6 Puncture Drop No. 6 was intended to impact directly onto the damage created by Free Drop Test 3, directly impacting the side of the package. As shown in Figure 2.12.1-17, the CTU was oriented parallel to the horizontal impact surface (longitudinal angle 90°, circumferential angle 0°). The following list summarizes the test parameters:

• verified longitudinal angle as 90° +/- I 0

• verified circumferential angle as 0 ° +/-2° 37

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020

• verified drop height as 40 inches (I meter). +2/-0 inches

• measured surface temperature ofouter shell ofOP-RMSC as 84 °F at time of test

• conducted test at 11 :30 a.m. on Wednesday, 7/8/2020 The package rebounded (bounced) off the puncture bar immediately following impact. The impact struck the previous damage from the 30-foot free drop, resulting in a small deformed area of the outer shell. No other external damage was noted. The impact damage is shown in Figure 2.12.1-18.

2.12.1.7.2.4 CTU-2 Puncture Drop Test No. 7 Puncture Drop No. 7 was intended to impact directly onto the damage created by Free Drop Test 4, directly impacting the top corner of the package. As shown in Figure 2.12.1-19, the CTIJ was oriented 42° with respect to the horizontal impact surface (longitudinal angle 138°, circumferential angle 180°). The following list summarizes the test parameters:

• verified longitudinal angle as 138° +/- 1 °

• verified circumferential angle as 180° +/-2°

• verified drop height as 40 inches (I meter), +2/-0 inches

• measured surface temperature of outer shell of OP-RMSC as I 00 - 103 °F at time of test

• conducted test at 11:58 a.m. on Wednesday, 7/8/2020 The package rebounded (bounced) off the puncture bar immediately following impact. The impact struck the previous damage from the 30-foot free drop with no measureable deformation.

No other external damage was noted. The impact damage is shown in Figure 2.12.1-20.

2.12.1.7.2.5 CTU-2 Post-Test Disassembly Post-test disassembly of CTU-2 was performed on Wednesday, 7/22/20. After removing the OP-RMSC lid, and the hex bolt securing the inner lid, the 1/4-20 hex bolt that attaches the RMSC hoist ring to the lid was sheared. However, the RMSC payload was not damaged from any of the free drop and puncture drop tests. The post-test views of the RMSC payload are shown in Figures 2.12.1-21 thru 2.12.1-23.

2.12.1.7.2.6 CTU-2 Post-Test Radiation Survey Post-test radiation survey ofRMSC CTIJ-2 was performed on Wednesday, 7/22/20. The post test radiation survey was performed utilizing lr-192 special form radioactive capsules. The total radioactive payload on the day ofthe survey for the post-test survey was 4,297 Curies (Ci) [159 TBq]. To account for the maximum design radioactive payload of16,000 Ci (592 TBq), the measured values were adjusted upward by the ratio of l 6,000/4,297 or 3.724 to determine the dose rate for the maximum radioactive content. The post-test measured dose rates for the maximum radioactive content of 16,000 Ci (592 TBq) are as follows:

Maximum Dose Rate !Top/Bottom/Side/End] (mrem/br)

Test Unit No. Surface I-meter 2-meters CTU-2 11 I 15 I 123 4 I 4 I 4 0 I 0 I 0 38

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 As indicated above, the radiation dose levels were below the requirements of 10 CFR §7 I .47(a) for NCT and IO CFR §71.51 (a)(2) for HAC for a non-exclusive use shipment.

Based on the test results, the OP-RMSC package design has been demonstrated to satisfy the requirements of Subpart F of 10 CFR 71 for the transportation of special form radioactive material.

39

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Table 2.12.1 Summary of OP-RMSC Certification Tests in Sequential Order 1 Test Unit Angular Orientation Test Unit Test Test Description Longitudinal A.xis1 Circumferential Axis3 Temperature No. (Certification Test Unit No.) (00 = horizontal) (0° = upright) (as measured) Test Results

-22 Of 1 4 foot, Top Down (CTU-1) 180° NIA (inner shell)

No visible damage was observed.

Inner lid bolts failed, resulting in lid

-22 °P contacting the closure lid. RMSC 2 30 foot, Top Down (CTU-1) 180 ° NIA (inner shell) remained within the OP-RMSC. No other damaged observed.

>169 °P Impact created ~4 inch wide flat along 3 30 foot, Side (CTU-2) 90° oo (inner shell) the side. One closure lid bolt failed.

No other damaged observed.

Impact resulted in a ~1/2-inch fold on 30 foot, CG-over-Top Corner >171 Of other shell. Five (5) of the closure lid 4 132 ° 180 ° (CTU-2) (inner shell) bolts were sheared, with two (2) bolts remaining on opposite side.

Puncture Drop, Top Down 92-94 °P Puncture bar impacted center of closure 5 (CTU-1) 180° NIA (outer surface) lid with no observed additional damage.

Puncture bar struck side of package, Puncture Drop, Side (CTU-2) 84 Of 90 ° oo (outer surface) resulting in small deformation of outer shell. No other damaged observed.

Puncture bar struck outer shell/closure Puncture Drop, CG-over-Top 100-103 ° F lid interface, resulting in a small "half-7 ]380 180 ° (outer surface)

Comer (CTU-2) moon" deformed area. No other damaged observed.

Notes:

1. Tested 7/7/2020 and 7/8/2020.

2. Longitudinal angle is relative to vertical axis of packaging (i.e., 0° is upright).

3. Circumferential angle is relative to rotation of package around vertical axis.

40

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 0

Figure 2.12.1 Schematic Summary of CTU-1 Testing 41

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 0

Figure 2.12.1 Schematic Summary of CTU-2 Testing 42

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-1 Free Drop Test No. 1: View of Test Setup 43

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1 CTU-1 Free Drop Test No. 1: View of Test Unit at Impact 44

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, J 2/2020 Figure 2.12.1 CTU-1 Free Drop Test No. 1 : Close-up View of Lid Impact Area 45

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1 CTU-1 Free Drop Test No. 2: View of Test Setup 46

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-1 Free Drop Test No.2: View of Test Unit at Impact 47

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-1 Free Drop Test No. 2: Close-up View of Failed Inner Lid Bolt 48

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1 CTU-1 Puncture Drop Test No. 5: View of Test Setup 49

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-1 Puncture Drop Test No. 5: Close-up View of Impact Closure Lid 50

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-1 Post-Test Disassembly: Overall View of RMSC Payload 51

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-1 Post-Test Disassembly: View of Dummy Sources, RMSC Payload 52

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-2 Free Drop Test No. 3: View of Test Setup 53

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1 CTU-2 Free Drop Test No. 3: Close-up View of Deformed Side Flat

(~4 inch Width), Failed Closure Lid Bolt 54

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1-15-CTU-2 Free Drop Test No. 4: View of Test Setup 55

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, I 2/2020 Figure 2.12.1 CTU-2 Free Drop Test No. 4: View of Failed Closure Lid Bolts, Deformed Shell/Lid Interface 56

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-2 Puncture Drop Test No. 6: View of Test Setup 57

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1 CTU-2 Puncture Drop Test No. 6: Close-up View of Impact Area 58

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-2 Puncture Drop Test No. 7: View of Test Setup 59

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-2 Puncture Drop Test No. 7: Close-up View of Impact Area 60

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1-21-CTU-2 Post-Test Disassembly: View of OP-RMSC Closure Lid w/ CG-Over-Top Corner Impact Damage 61

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 2.12.1 CTU-2 Post-Test Disassembly: View of OP-RMSC Cavity w/ Side Impact Damage to Inner Wall (Left Side) 62

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 2.12.1 CTU-2 Post-Test Disassembly: Overall View of RMSC Payload 63

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 3.0 THERMAL EVALUATION This chapter establishes the compliance ofthe OP-RMSC transporting a payload ofup to 16,000 Ci (592 TBq) oflr-192 or Se-75, and 2 Ci (0.07 TBq) ofCo-60 in special form with the thermal requirements of IO CFR 719

• 3.1 Description of Thennal Design 3.1.1 Design Features The OP-RMSC package does not contain any specific thermal design features. The thermal performance of the package is demonstrated by test. Therefore, this section does not apply.

3.1.2 Content's Decay Heat The OP-RMSC may contain up to 16,000 Ci (592 TBq) oflr-192 or Se-75 in special form. The radiolytic decay heat oflr-192 is 7.03 x 10-3 W/Ci 10* The radiolytic decay heat of2.41 x 10-3 W/Ci 9 for Se-75. Since the radiolytic decay heat of Ir-192 is greater than the radiolytic decay heat ofCo-60 or Se-75, the heat load oflr-192 payload bounds the two other payloads. For the limited Co-60 payload of3 Ci (0.11 TBq), the maximum decay heat load is only 0.05 W (0.17 Btu/hr), which is negligible compared to the other two isotopes. Therefore, the maximum decay heat load for the OP-RMSC package is 100 W (341 Btu/hr) from the Ir-J 92 payload.

3.1.3 Summary Tables of Temperatures The maximum surface temperature ofthe OP-RMSC is 374 °f (198 °C), as documented in Section 3.3, Thermal Evaluation under Normal Conditions of Transport, in full sunlight.

3.1.4 Summary Tables of Maximum Pressures The containment ofthe OP-RMSC package is provided by the special form payload. Gas can freely move from the internal cavity to the environment during all phases ofoperation. Therefore, there are no internal pressures to be determined, since the OP-RMSC does not contain any pressure boundaries.

3.2 Material Properties and Component Specifications 3.2.1 Material Properties The OP-RM SC package is constructed primarily of stainless steel pipe and plate welded assembly that surrounds a tungsten gamma shield. Since the structural integrity ofthe package is established by testing, the only pertinent temperature limits on the components is established by their melting temperatures for the fire based Hypothetical Accident Condition (HAC). The melting temperatures for tungsten and stainless steel are 6,192 °f (3,422 °C), and 2,800 °f (1,538 °C), respectively.

The payload was qualified per Qualification ofSpecial Form Radioactive Material, in IO CFR §71.75(b)(4).

9 Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 1-1-20 Edition.

10 ORJGEN-S Decay Data Library and Half-Life Uncertainties, 0. W. Hermann, P.R. Daniel, and J.C. Ryman, Oak Ridge National Laboratory, ORNLrrM-13624, September 1998.

59

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 3.2.2 Component Specifications The OP-RMSC package does not contain any component or material that is important to the thermal performance ofthe package. The two primary structural materials are austenitic stainless steel and the tungsten gamma shielding. As noted in Section 2.1.2.2.1, Brittle Fracture, both materials have been tested to temperatures below -20 °F (-29 °C) with no loss of structural or shielding capability. The limiting temperatures for the stainless steel structural and tungsten shielding materials are their respective melting temperatures, which are 2,800 °F (1,538 °C) and 6,191 °F (3,422 °C), respectively.

3.3 Thermal Evaluation under Normal Conditions of Transport This section presents the thermal evaluation of the OP-RMSC package under the normal conditions of transport (NCT) per IO CFR §71.71.

3.3.1 Heat and Cold Since the total decay heat load of the OP-RMSC package is 100 W (341 Btu/hr), a detailed thermal analysis ofthe package with the RMSC payload was performed. The internal temperatures will very closely match those on the surface ofthe package. To determine theNCT maximum package temperatures with and without insolation, a 3-D, half-symmetry thermal model was created utilizing ANSYS finite element analysis (FEA) program 11

• A plot ofthe ANSYS thermal model is provided in Figure 3.3-1.

Per 10 CFR §71. 71(c)(I), the worst-case high temperature condition for the package consists of an ambient temperature of I 00 °F (38 °C) with maximum insolation. For this condition, the maximum surface temperature of the OP-RMSC is 374 °F (198 °C). The maximum surface temperature of the OP-RMSC in shade with an ambient temperature of 100 °F (38 °C) is 265 °P (123 °C). This temperature is greater than the maximum acceptable surface temperature of 122 0

P (50 °C) for non-exclusive use shipments, as stipulated in IO CFR §7 I .43(g). Therefore, an expanded metal personnel barrier with a minimum open area of 75% is installed over the OP-RMSC after the package is secured to the transport pallet. With the personnel barrier installed, the maximum accessible surface temperature is 115 °F (46 °C), which allows the package to be shipped as a non-exclusive use shipment. Figure 3.3-2 provides the configuration of the package with the personnel barrier.

The maximum temperature for any component in the OP-RMSC package with the I 00 W (341 Btu/hr) in an ambient temperature of 100 °F (38 °C) with maximum insolation is 752 °F (400 °C),

which occurs in the stainless steel special form capsules in the RMSC payload cavity. A summary ofthe maximum component temperatures forNCT is provided in Table 3.3.1-1.

The ANSYSNCT thermal model results are illustrated in Figure 3.3-3 and Figure 3.3-4 with and without insolation, respectively.

For the cold condition with zero decay heat, the package surface temperature will be equal to the low temperature ambient conditions of-20 °P (-29 °C) and -40 °P (-40 °C). For the structural and shielding materials utilized in the OP-RMSC package, the sub-zero temperature has no effect on the ability of the package to maintain its confinement and shielding safety functions.

11 ANSYS@ Finite Element Analysis Program, Version 19.2, ANSYS Inc.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 ANSYS R19.2 nctsolar.3 PLOT NO. 18 NCT Package Elerrents Figure 3.3 ANSYS Thermal Model of OP-RMSC Package 61

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 Figure 3.3-2 -OP-RMSC Package with Personnel Barrier Table 3.3.1-1 -Summary of Maximum NCT Component Temperatures Temperature (° F)

NCT, 100 °F, NCT, 100 °F, Component Shade Solar Closure Lid 212 308 Outer Shell 265 374 Tungsten Shields 616 680 Special Form Capsules 680 752 Personnel Barrier 115 NIA 62

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 ANSYS Rl9.2 nctsolar.9 PLITT ID. 21 100 245 390 534.9 172.5 317.5 462.4 607.4 752.4 NCT Package Temperatures - Less Basket Figure 3.3 OP-RMSC NCT Hot Temperature Profile with lnsolation 63

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 ANSYS R19.2 nctshade.19 PLOT ID. 21 100 228.9 357.8 486.8 615.7 164.5 293.4 422.3 551.2 680.2 NCT Package Terrperatures - Less fusket Figure 3.3 OP-RMSC NCT Hot Temperature Profile without lnsolation 3.3.2 Maximum Normal Operating Pressure This section does not apply, since the OP-RMSC package does not contain any pressure boundaries. Therefore, there is no maximum normal operating pressure (MNOP) for the OP-RMSC package.

3.4 Thermal Evaluation under Hypothetical Accident Conditions The thermal performance of the OP-RMSC package under Hypothetical Accident Conditions (HAC) in accordance with IO CFR §71.73 requires that a test specimen must be exposed to a fully engulfing hydrocarbon fuel/air fire with an average flame temperature of 1,475 °F (800 °C) for a period of 30 minutes. The only combustible materials in the OP-RMSC packaging are the polyurethane foam and the silicone gasket, which are not a structural or shielding material. Since all of the structural and shielding materials (stainless steel and tungsten) have melting temperatures of 2,800 °f (1,538 °C) and 6,191 °f (3,422 °C), respectively, the OP-RMSC package is unaffected by the lower 1,475 °F (800 °C) temperature for the HAC fire event.

3.4.1 Initial Conditions As noted in Appendix 2.12.1, Certification Tests, an OP-RMSC package certification test unit (CTUs) was uniformly heated above 160 °f (71 °C) as an initial condition for the 30-foot (9-meter) free drop. There was no rupturing of the stainless steel body to expose the tungsten 64

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 gamma shield. Therefore, the limiting temperature for the OP-RMSC package is the melting temperatures of the structural and shielding materials, which significantly exceeds the HAC fire event temperature.

3.4.2 Fire Test Conditions As noted above, there was no failure of the OP-RM SC package structure that exposed the RMSC payload that contains the tungsten gamma shield shielding. Therefore, the peak package temperatures would not exceed the 1,475 °f (800 °C) fire temperature, which is well below the melting temperatures ofeither the stainless steel (2,800 °f) or the tungsten (6,191 °f).

The special form qualification of the payload certifies that it could withstand the fire test without degradation or rupture.

3.4.3 Maximum Temperatures and Pressures Based on the certification tests performed on the OP-RMSC package, none of the components exceeds its temperature limit as described in Section 3.2.1, Material Properties. Specifically, the maximum package temperatures fall more than 500 °f (260 °C) below the lowest melting point of the stainless steel. Additionally, the special form payload does not exceed the temperature for the special form certification per IO CFR §7l.75(b)(4).

The containment of the OP-RMSC package is provided by the special form payload. Gas can freely move from the internal cavity to the environment during all phases of operation, so determination ofinternal pressures is not required.

Therefore, the OP-RMSC package satisfies the HAC thermal requirements set forth in 10 CfR §71.73(c).

3.4.4 Maximum Thermal Stresses The effects ofHAC thermal stresses on the OP-RMSC package are minimal for the single event of the HAC fire. The maximum fire temperature for the welded package would not exceed 1,475 0

f (800 °C), which would not result in any metal fatigue or detrimental condition that affects the shielding and confinement safety functions of the package. In addition, the thermal expansion coefficient for stainless steel is over three times the thermal expansion coefficient for tungsten heavy metal. Since the tungsten shields are not rigidly attached to the RMSC stainless steel, no significant thermal stresses will develop within the RMSC payload due to the maximum 1,475 °F (800 °C) fire temperature.

3.4.5 Accident Conditions for Fissile Material Packages for Air Transport This section does not apply, since the OP-RMSC does not contain fissile material.

65

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 3.5 Appendix 3.5.1 Sample of ANSYS Input Files

! = DIMENSIONS

/PREP?

! (All dimensions are nominal) esizeI = 0.5  ! nominal element size esize2 = 0.25  ! vertical element size SELTOL,.0001 tol=0.0005  ! tolerance for merging the nodes ndiv = 2  ! multiplication factor on division

! Top Assembly (OP-RMSC-TA-1-2) hOOO I = 22.25  ! height of package from base to top oflid ((22.25) - OP_RMSC-OBA-1) r0001 = 18.00/2  ! outer radius of package ((18.00)- OP-RMSC-OB-1) h0002 = 0.125 - 0.013  ! neoprene gasket thickness minus 10% compression (OP-RMSC-TA-1-2, Item 4) r0002 = 13.75/2  ! neoprene gasket outer radius (ILA-I radius)(OP-RMSC-TA-1-2, Item 4) r0003 = 10.75/2 - 0.165  ! neoprene gasket inner radius (BICA-I Item #2 IR, 0 10" sch !OS pipe)

!-- OP RMSC Dimensions----------------

! Outer Body Assembly h0801 = 0.75  ! CR offset from OBW top edge h0802 = 3.50  ! BIP offset from top of CR

! Body inner cavity assembly (OP-RMSC-BICA-1) h090 I = 12.63  ! height h0902 = 1.13  ! RS offset from top of assembly

! Closure Ring (OP-RMSC-CR-1) h I 00 I = 1.0  ! height (stock thickness) r1001 = 17.59/2  ! outer radius rl002 = 14.84/2  ! inner radius

! Outer Body (OP-RMSC-0B-I hi 101 = 22.00  ! height rt IOl = 18.00/2  ! outer radius, ([1]8" dia. Schedule IOS Pipe) ti I01 = 0.188  ! wall thickness, was .19 rl 102 = rl IOI - ti 101  ! inner radius

! Closure Ring (OP-RMSC-BIP-1) hl201 = 0.75  ! height (stock thickness) r1201 = 17.46/2  ! outer radius rl 202 = I0.78/2  ! inner radius

! Inner Plate (OP-RMSC-IP-1) h1301 = 0.38  ! height (stock thickness) rl301 = 13.75/2  ! outer radius

! Inner Lid Ring (OP-RMSC-ILR-1) 66

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 hl401 =0.50  ! height (stock thickness) rl40I = 10.36/2  ! outer radius rl402 =9.36/2  ! inner radius

! Closure Lid (OP-RMSC-CL-1) h 150 I =0.75  ! height (stock thickness) r1501 =17.5/2  ! outer radius rl502 =7.00  ! inner radius

! Perforated Sheet (OP-RMSC-PS-1) rl60 I = 14.5/2  ! radius of plate hl601 =0.06  ! stock thickness pct! 60I = 58  ! percentage of open area

! Bottom Plate Body (OP-RMSC-BBP-1) h 170I =0.38  ! plate stock thickness rt 70I =17.59/2  ! outer radius

! Bottom Base Channel (OP-RMSC-BBC-3)

LI 801 =7.5  ! length Wl80I =2.0  ! stock dimension H 180 I =1.0  ! stock dimension t180I =1/8  ! stock thickness

! Inner Cavity Bottom Plate (OP-RMSC-ICBP-1) h 190 I =0.38  ! plate stock thickness rl901 = 10.75/2  ! outer radius

! Inner Cavity Container Body (OP-RMSC-ICC-1) h200I =12.25  ! height r2001 =10.75/2  ! outer radius, (10" dia. Schedule IOS Pipe) t200 I =0.165  ! wall thickness r2002 =r200I - t2001  ! inner radius

! Radial Spacer (OP- RMSC-RS-4) h2101 =10.00  ! height w2101 =0.75  ! width t2101 =0.25  ! stock thickness ophtdim = 17

• dim,op_ht,,ophtdim op_ht() 5) =h000 I  ! top surface op_ht(l4)= op_ht(l5)-h1501  ! bottom ofclosure lid op_ht( 16) = op_ht(l4)- hi 601  ! bottom of perforated plate op_ht( 13)=op_ht()4)- hlO0I  ! bottom ofclosure ring op_ht(l1)= op_ht(14)- h0802  ! top of inner closure ring op_ht(l 7)= op_ht(II)+ h0002  ! top of neoprene gasket op_ht(l2) =op_ht(l7) + hl301  ! top of inner closure plate op_ht(JO)= op_ht(l 1)- hl401  ! botom of inner lid ring op_ht(9) =op_ht(ll)-h1201  ! bottom of inner closure ring op_ht(8) =op_ht(11)- h0902  ! top ofradial spacer 67

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 op_ht(7) =op_ht(8) - h2l0l  ! bottom ofradial spacer op_ht(6) = op_ht(l 1)- h2001  ! bottom cavity plate top op_ht(5) = op_ht(6) - hl90l  ! bottom cavity plate bottom op_ht(4) =hl801 + h1701  ! bottom plate top op_ht(3) = hl80l  ! bottom plate bottom op_ht(2) = h000l - hl lOl  ! bottom of body tube op_ht(l) =0.00  ! bottom ofpackage raddiml = 13

• dim,rad_op,,raddiml rad_op(l) = r2002 - w2l01 ! inner edge ofradial spacers rad_op(2) = rl402  ! inner radius of inner lid ring rad_op(3) = rl40l  ! outer radius ofinner lid ring rad_op(4) =r2002  ! inner cavity container body inner radius rad_op(5) =r200l  ! inner cavity outer radius rad_op(6) =rl301  ! inner lid outer radius rad_op(7) =rl002  ! outer lid bolt flange inner radius rad_op(8) =rl50l  ! outer lid outer radius rad_op(9) = rll02  ! outer shell inner radius rad_op(IO)= rl I 01  ! outer shell outer radius rad_op(ll)=7.000  ! outer radius oflid vents rad_op(l2)=2.500  ! approximate inner radius oflid vents rad_op(l3)= rl60I  ! radius of perforated plate

!-- RMSC Dimensions-----------------

feltg =0 !0.l25  ! felt pad layer

! Stainless Steel Pipe Outer Shell (RMSC-BODY-l) h0I0I =10.75  ! height r0I 01 = 8.63/2  ! outer radius, (8" dia. Schedule JOS Pipe) t0IOI =0.148 !wall thickness rOI 02 =rOI01 - tOI0l  ! inner radius

! Body Upper Center Pipe (RMSC-BUCP-1) h020l =3.55  ! height r0201 =4.50/2  ! outer radius, (4" dia. Schedule !OS Pipe) t0201 =0.120  ! wall thickness r0202 =r020I - t020 l  ! inner radius

! Body Top Plate (RMSC-BTP-1) h030l = 0.75  ! height (stock thickness) r030I = 8.30/2  ! outer radius r0302 = 4.50/2  ! inner radius

! Tungsten body shield (RMSC-TBS-I) h0401 =9.70  ! height h0402 = 5.75  ! cavity depth h0403 =2.75  ! cavity shield hole depth r040I =1.50/2  ! inner radius 68

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 r0402 = 4.60/2  ! cavity shield hole radius r0403 = 8.20/2  ! outer radius

! Body Shell Bottom Plate (RMSC-BBP-1 )

h0501 = 0.25  ! plate stock thickness r050 I = 8.20/2  ! outer radius

! Lid Top Plate (RMSC-LTP-1) h0601 = 0.63  ! height (stock thickness) r060I = 8.63/2  ! outer radius

! Tungsten cavity shield (plug) (RMSC-TNGS-1) h0701 = 3.55  ! height r070I = 4.20/2  ! radius

! Special Form Capsule Basket (SPFC Basket) h220I = 2.000  ! height r2201 = 1.375/2  ! outer radius plgap 0.0 l 0

=  ! contact from sfc to rmsc - replaced with 1220I - amr 12201 = .035  ! thickness of basket base and side = 2.035 amr

! Payload h320I = h220 I  ! Height r3201 = .5/2  ! payload radius rmschtdim = 11  ! added basket bottom plate

• dim,rmsc_ht,,rmschtdim rmsc_ht(I) = feltg  ! felt top/bottom plate bottom surface nnsc_ht(2) = hOSO\ + nnsc_ht(l)  ! bottom plate top surface nnsc_ht(3) = nnsc_ht(2) + h0401 - h0402 ! TS cavity bottom rrnsc_ht(4) = rmsc_ht(3) + plgap  ! bottom of payload basket rrnsc_ht(5) = rrnsc_ht(4) + t220l  ! bottom of payload - amr rrnsc_ht(6) = rmsc_ ht(4) + h2201  ! top of payload rmsc_ht(7) = rmsc_ht(2) + h0401 - h0403 ! TS plug bottom rrnsc_ht(8) = rmsc_ht(2) + h040I  ! TS top nnsc_ht(9) = hOIOI - h030I  ! rrnsc body top plate bottom rrnsc_ht(l 0) = hOI 01  ! rmsc body top plate top rmsc_ht( 11) = hOIOI + h060I  ! rmsc lid top plate top raddim2 = 10

• dim,rad_ nnsc,,raddim2 rad_rmsc( I) = r220I - t220I  ! payload basked inner radius - amr rad_rmsc(2) = r220I  ! payload basket outer radius - amr rad_rmsc(3) = r0401  ! TBS inner cavity radius rad_rmsc(4) = r070 I  ! plug radius rad_rmsc(5) = r0202  ! BUCP inner radius rad_rmsc(6) = r020 l  ! BUCP outer radius rad_rmsc(7) = r0402  ! TBS shield hole radius rad_rmsc(8) = r0403  ! TBS outer radius rad_rmsc(9) = r0102  ! Body inner radius 69

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 rad_rmsc(IO) = rOIOI  ! BODY/lid outer radius

! offset rmsc to outer package bottom cavity plate top

• do,i, 1,rmschtdim nnsc_ht(i) = nnsc_ht(i) + op_ht(6)

• enddo

!-- axial meshing array----------------

heightdim = ophtdim + rmschtdim

• DIM,height,,heightdim

• do,i,I ,ophtdim, height(i) = op_ht(i)

• enddo

• do,i,ophtdim+ 1,heightdim height(i) = rmsc_ht(i-ophtdim)

• enddo

! .. bubblesort ................................................................

• do,i,(heightdim),1,-1

• do,j,2,i,I

• if,heightG-1 ),gt,heightG),then

/COM,heights were out of order - Fixed!

temp = heightG-1) heightG-1 )=heightG) heightG)=temp

• endif

• enddo

• enddo

!-- radial meshing array---------------

raddim = raddim I + raddim2

• dim,radius,,raddim

• do,i, 1,raddim I, radius(i) = rad_op(i)

• enddo

• do,i,raddimI+1,raddim radius(i) = rad_rmsc(i-raddiml)

• enddo

! .. bubblesort (error check/fix).............................................. .

• do,i,(raddim),1,-1

• doj,2,i,I

• if,radiusG-1),gt,radiusG),then

/COM,radii out of order temp = radiusG- \)

radiusG-1 )=radiusG) radiusG)=temp

• endif 70

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020

• enddo

• enddo finish

!= MESHING ELEMENT SETTINGS

.1 - added insolation shell elements

/prep7 ET,1,PLANE55  ! 2-D thermal ET,2,SOLID70  ! 3-D solid thermal KEYOPT,2,2,1 KEYOPT,2,4,0 KEYOPT,2,7,0 KEYOPT,2,8,0 ET,3,SURF152

!KEYOPT,3,1,0

!KEYOPT,3,2,0 KEYOPT,3,3,2 KEYOPT,3,4,1 KEYOPT,3,5,0

!KEYOPT,3,6,0 KEYOPT,3,7,0 KEYOPT,3,8,3 KEYOPT,3,9,0 ET,4,SHELL131 KEYOPT,4,2,l KEYOPT,4,3,2 ET,5,SHELL131 KEYOPT,5,3,2 ET,6,MATRIXS0 KEYOPT,6,1, 1 ET,7,SURFl 52 ! Shell for insolation horizontal flat surfaces KEYOPT,7,1,0 KEYOPT,7,2,0 KEYOPT,7,3,0 KEYOPT,7,4,1 KEY OPT, 7,5,0 KEYOPT,7,6,0 KEYOPT,7,7,0 KEYOPT, 7,8, l KEYOPT,7,9,0 ET,8,SURF152 ! Shell for insolation horizontal perfsheet KEYOPT,8,1,0 KEYOPT,8,2,0 71

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 KEYOPT,8,3,0 KEYOPT,8,4, I KEYOPT,8,5,0 KEYOPT,8,6,0 KEYOPT,8,7,0 KEYOPT,8,8,l KEYOPT,8,9,0 ET,9,SURF 152 ! Shell for insolation vertical surfaces (outer shell and lid vent surfaces)

KEYOPT,9,1,0 KEYOPT,9,2,0 KEYOPT,9,3,0 KEYOPT,9,4, I KEYOPT,9,5,0 KEYOPT,9,6,0 KEYOPT,9,7,0 KEYOPT,9,8, I KEYOPT,9,9,0 ET, I 0,SURF152  ! Shell for insolation inner lid vertical surfaces KEYOPT, I 0, 1,0 KEYOPT, I 0,2,0 KEYOPT,10,3,0 KEYOPT, I 0,4,1 KEYOPT, 10,5,0 KEYOPT, I 0,6,0 KEYOPT,10,7,0 KEYOPT, I 0,8, I KEYOPT,10,9,0 ET,l 1,SURF152  ! Shell for convection KEYOPT,11,4,1 KEYOPT,11,5,0 KEYOPT,11,7,0 KEYOPT,11,8,3  ! evaluates heat flux at surface temp (TS)

KEYOPT,11,9,0 R,1, R,5,,,,,,

RMORE,.001 ! dummy thickness for 152 surface elements finish

/prep?

mptemp,,

mpdele,all,all,all

! air ------------------

! Handbook of Applied Thermal Design, Eric C. Guyer, Part 5, Chapter 3, Table 3.1 72

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020

! T = {F}, kxx = {BTU/(hr-in-F)}

mptemp,,

mptemp, 1,-40, 0, 50, I 00, 200, 300 mptemp, 7, 400, 500,600, 700, 800, 900 mpdata,kxx, l , 1, l.009E-3, l.093E-3, l.195E-3, l.294E-3, l .482E-3, l.66 l e-3 mpdata,kxx,1, 7, 1.833E-3, 2.000E-3, 2.162E-3, 2.320E-3, 2.474E-3, 2.625e-3

! cask body (304 SST)-------------

! kxx: ASME B&PV Code,Section II, Part D, Table TCD, Material Group J

! T = {F}, kxx = {BTU/(hr-in-F)}

mptemp,,

mptemp, 1, 70, 100, 200, 300, 400, 500 mptemp, 7, 600,700, 800, 900,1000,1100 mptemp,13,1200,1300,1400, 1500 mpdata,kxx,2, 1,0.717,0.725,0.775,0.817,0.867,0.908 mpdata,kxx,2, 7,0.942,0.983,1.025,1.058,1.092,1.133 mpdata,kxx,2,13,1.167,1.208, 1.242,1.275

! polyurethane foam (10 pct)------------

! General Plastics, Design Guide for use of LAST _A_FOAM(R) FR-3700 for Crash &

! Fire Protection of Radioactive Material Shipping Containers, issue 5

! T = {F}, kxx = {BTU/(hr-in-F)}

mptemp,,

mp, kxx,3,2.424e-3  ! BTU/(h-in-F)

! inner lid (304 SST)-------------

MPCOPY,,2,4 TBCOPY ,all,2,4

! outer lid (304 SST)-------------

MPCOPY,,2,5 TBCOPY,all,2,5

! rmsc body tube (304 SST)-----------

MPCOPY,,2,6 TBCOPY ,all,2,6

! rmsc lid (304 SST)-------------

MPCOPY,,2,7 TBCOPY,all,2,7

! tungsten shield (Densimet 185) -----------

! https://www.plansee.com/en/materials/tungsten-heavy-metal.html

! Densimet 185 is a 97% Tungsten sintered alloy with the remainder consistsing

! ofa binder oflron and Nickel. T = {F}, kxx = {BTU/(hr-in-F)}

mptemp,,

!mptemp, 1, 2\2, 392, 752, \ 1 \2, \472  ! °F

!mp, kxx,8,4.334  ! BTU/h/in/F (90 W/m-K) at 500 deg C mp, kxx,8,4.141  ! BTU/h/in/F (86 W/m-K) at 500 deg C

!mpdata,kxx,8, 1, 5.296, 4.863, 4.333, 3.948, 3.659  ! Btu/hr-in-F 73

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020

! tungsten plug--------------

MPCOPY,,8,9 TBCOPY,all,8,9

! payload ----------------

MPCOPY ,,2,10 TBCOPY ,all,2, l 0

! payload felt material------------

mp,dens, 11, 20.6/1728 ! lb/in"3 mp, kxx, 11, 0.03/12 ! BTU/h/in/F (90 W/m-K) at 500 deg C

! radial/axial TS shield gaps (air)---------

MPCOPY,,1,12 TBCOPY,all, I , 12

! Perforated Sheet ---------------

! kxx: ASME B&PV Code,Section II, Part D, Table TCD, Material Group J

! T = {F}, kxx = {BTU/(hr-in-F)}

! conductivity multiplied by 2 and density by 1/2 for 50% open area.

mptemp,,

mptemp, I , 70, I 00, 200, 300, 400, 500 mptemp, 7, 600, 700, 800, 900, I 000,1100 mptemp,13,1200,1300,1400,1500 mpdata,kxx,13, 1,2*0. 717,2*0.725,2*0. 775,2*0.817,2*0.867,2*0.908 mpdata,kxx,13, 7,2*0.942,2*0.983,2*1.025,2*1.058,2*1.092,2*1.133 mpdata,kxx,13,13,2*\ .167,2* l.208,2* l.242,2* 1.275

! upper cavity air -------------

! See material 1 for references

! T = {F}, kxx = {BTU/(hr-in-F)}

MPCOPY,,1,14 TBCOPY ,all,1,14

!mptemp, 1,-IO0, 0, 32, 68, 100, 200

!mptemp, 7, 300, 400, 500, 600, 800,1000

!mptemp,13, l 200, 1400,1600

!mptemp,,

! Conductivity scaled up by factor of IO to account for convection

!mpdata,kxx,14, 1, 8.700E-3, 1.092E-2, I.I 59E-2, 1.234E-2, 1.297E-2, 1.483E-2

!mpdata,kxx,I4, 7, 1.661E-2, 1.833E-2, 2.001E-2, 2. 163E-2, 2.469E-2, 2.769E-2

!mpdata,kxx,14,13, 3.060E-2, 3.331E-2, 3.631E-2

! axial payload contactgap (air)----------

MPCOPY,,1, 15 TBCOPY,all, I, 15

! -- Closure Lid Seal (Neoprene/Chloroprene Rubber)--------

! https://www.makeitfrom.com/material-properties/Chloroprene-Rubber-CR-Neoprene mptemp,,

mp,c ,16,.27  ! lb/in"3 74

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 mp, kxx,16,0.0167 ! Btu/(h-in-F) mp,dens, 16,0.069 ! lb/in"3

! - 51, 52 - shells to be deleted------------

mpcopy, ,2,51 tbcopy,all,2,51 mpcopy, ,2,52 tbcopy,all,2,52 mpcopy, ,2,53 tbcopy,all,2,53 mpcopy, ,2,54 tbcopy,all,2,54 mpcopy, ,2,55 tbcopy,all,2,55 mpcopy, ,2,56 tbcopy ,all,2,56 mpcopy, ,2,57 tbcopy,all,2,57

! -- finish-------------------

75

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 4.0 CONTAINMENT The OP-RMSC package is designed as a confinement boundary for raw material special form source capsules. Containment of radioactive material is provided by the special form construction of the payloads. The DOT-IAEA Certification Number for one raw material special form capsule that would be transported in OP-RM.SC is as follows:

Manufacture Model Number Certification Number Industrial Nuclear Co., Inc. INC-SFC-1* USA/0798/S-96

• Limited to 4,000 Ci (148 TBq) of lr-192 per capsule.

Other raw material special form capsules may be transported in the OP-RMSC provided the capsules comply with the radioactive content limits specified in 1.2.2, Contents ofPackaging.

Since the OP-RMSC package does not provide containment, subsequent sections of this chapter are not applicable.

76

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 5.0 SHIELDING EVALUATION This section demonstrates the shielding capability of the OP-RMSC package design for the authorized special fonn contents. For the lr-192 and Se-75 payloads, the shielding evaluation is demonstrated via prototypic testing in lieu ofan analytical evaluation. For the Co-60 payload, a MCNP shielding model was created to perform the shielding evaluation of a I Ci (0.04 TBq) source in order to determine the maximum Curie content for the RMSC payload.

5.1 Description of Shielding Design 5.1.1 Design Features The OP-RMSC package is a welded stainless steel structure that contains the RMSC payload, which contains the tungsten gamma shields and the radioactive content. Four (4) stainless steel raw material special form capsules, which each contain a maximum of 4,000 Ci (148 TBq) of lr-192 or Se-75 isotope, are placed in the cavity of the RMSC payload. For the Co-60 isotope payload, a maximum total of2 Ci (0.07 TBq) in special form may be placed in the RMSC cavity.

The RMSC payload cavity that is surrounded by the tungsten gamma shields provides the maximum attenuation of the gamma radiation.

5.1.2 Summary Table of Maximum Radiation Levels Table 5.1-1 provides the maximum measured external radiation levels for the RMSC payload with the maximum payload content of lr-192 (16,000 Ci [592 TBq]) for a non-exclusive use shipment.

Table 5.1-2 provides the maximum calculated external radiation levels for the maximum payload content of Co-60 (2 Ci [0.07 TBq]) for a non-exclusive use shipment.

Table 5.1 Maximum Measured External Radiation Levels for lr-192 (Non-Exclusive Use)

Nonnal Conditions of Transport Hvoothetical Accident Conditions Measurement Measured

. 10 CFR §71.47(a)

Limit Measured 10 CFR §71.51(a)(2)

Limit Location mrem/hr (mSv/hr) mrem/hr (mSv/hr) mrem/hr (mSv/hr) mrem/hr (mSv/hr)

Surface 123 (1.2) 200 (2) NIA NIA 40 inches (1 Meter) 3 (0.0) 10 (0.1) 4 (0.0) 1000 (10) from Surface

• Note: Normal condition maximum measured values are for CTU-2 and are adjusted to account for the maximum 16,000 Ci (592 TBq) radioactive content. Measurements were performed post-test following the hypothetical accident conditions tests per IO CFR §71.73.

Table 5.1 Maximum Calculated External Radiation Levels for Co-60 (Non-Exclusive Use)

Nonnal Conditions of Transoort Hvoothetical Accident Conditions 10 CFR §71.47(a) 10 CFR §71.51(a)(2)

Calculated Limit Calculated Limit Package Location mrern/hr (mSv/hr) mrern/hr (mSv/hr) mrern/hr (mSv/hr) mrem/hr (mSv/hr)

Surface 198 (2.0) 200 (2) NIA NIA 40 inches (1 Meter) 2 (0.0) 10 (0.1) 2 (0.0) 1000 (10) from Surface 77

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 5.2 Source Specification 5.2.1 Gamma Source The radioactive content of the OP-RMSC package is limited to either 2 Ci (0.07 TBq) ofCo-60, or 16,000 Ci (592 TBq) oflr-192 or Se-75 isotopes. Since the photon energy oflr-192 (0.380 MeV average) is greater than Se-75 (0.280 MeV average), lr-192 results in a higher unit dose than Se-75 per curie of activity, as tabulated in Table 5.2-1. Therefore, the Ir-192 payload bounds Se-75 payload for the maximum 16,000 Ci (592 TBq) content. Because actual Ir-192 special form capsules are utilized to determine the acceptance of the tungsten gamma shields, the tabulation of gamma decay source strengths for the raw material special form capsules for lr-192 or Se-75 is not required for the RMSC payload.

Table 5.2-l - Specific Gamma Ray Constants for Raw Material 1sotopes 12 Specific Gamma Ray Constant Radionuclide (R-m 2/hr-Ci) lridium-192 0.460 Selenium-75 0.203 The Co-60 gamma spectrum is presented in Table 5.2-1. The Co-60 gamma spectrum is extracted from ORJGEN discrete gamma data file origen.rev04.mpdxgam, which is included with SCALE 6.2. J 13. ORJGEN decay data is based on ENDF/8-Vll. J evaluations. The total gamma source strength, S, is calculated as a function of the average gammas per decay, l:P(y),

and the isotopic activity, A. One Curie of Co-60 results in 7.3948 x 10 10 gammas/sec, as shown:

, = ,I.P(r) * (1 Ct* 102')

A, =(1.9'900-'"-)

' = 7.3946

• 10 :J..O _l w

5.2.1 Neutron Source This section does not apply, since the OP-RMSC package does not contain neutron sources.

12 "Exposure Rate Constants and Lead Shielding Values for Over 1,100 Radionuclides", David S. Smith and Michael G. Stabin, Department of Radiology and Radiological Sciences, Vanderbilt University, Nashville, TN, Health Physics Society Journal, March 2012 issue.

13 "ORNLffM-2005/39, SCALE Code System, Oak Ridge National Laboratory, Version 6.2.1, August 2016, RSICC Package ID C00834MNYCP02.

78

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Table 5.2 Co-60 Discrete Gamma Spectrum Gamma Energy Probability of Gamma (MeV) per Isotope Decay 7.5l00E-04 1.6946£-06 8.5234E-04 8.0SS0E-07 8.7689E-04 1.3826£-08 8.8364£-04 5.6638E-07 7.4l 78E-03 3.1894E-05 7.4358£-03 6.2286£-05 8.2223E-03 3.9005E-06 8.2246E-03 7.6481E-06 8.2879E-03 3.3435E-09 8.2881£-03 4.8594£-09 3.4714E-01 7.S000E-05 8.2610E-01 7.6000E-05 l.1732E+00 9.9850E-01 1.3325E+00 9.9983E-0I 2.l586E+00 l.2000E-05 2.5057£+00 2.0000E-08 5.3 Shielding Model 5.3.1 Configuration of Source and Shielding The shielding capability of the RMSC payload for the OP-RM SC package design is primarily demonstrated by physical tests of prototypic packages for the maximum Curie content for the Ir-192 isotope. For the 2 Ci (0.07 TBq) of Co-60 isotope payload, a MCNP model was created, and utilized to demonstrate the shielding capability of the RMSC payload. All relevant design features of the RMSC payload were modeled in MCNP. The model for the RMSC payload is shown in Figures 5.3-1 and 5.3-2.

The Co-60 source is concentrated within a single special form capsule located against the payload cavity radial wall. The source is modeled as a homogenous cylinder filling the capsule, with no credit taken for the source material.

79

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 Figure 5.3 RMSC Payload, MCNP Model Axial Cross-Section Figure 5.3 RMSC Payload, MCNP Model Radial Cross-Section 80

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 5.3.2 Material Properties The RMSC payload is constructed of stainless steel and tungsten alloy. The stainless steel composition utilized in the MCNP models is tabulated in Table 5.4-1. The tungsten alloy is Densimet 176 (tungsten cavity shield) and Densimet 185 (tungsten body shield), with the product numbers corresponding to densities of 17.6 g/cm3 and 18.5 g/cm3 , respectively. The Densimet alloys 14 are predominantly tungsten with trace amounts of nickel and iron (3-7%). The alloy is modeled as 93 wt.% tungsten with equal parts nickel and iron (3.5 wt.% each). The tungsten alloy composition is tabulated in Table 5.3-2.

Table 5.3 Type 304 Stainless Steel Composition (Density= 8.00 g/cm 3) 15 Weight Element ZAID Fraction C 6000 0.000400 Si 14000 0.005000 p 15000 0.000230 s 16000 0.000150 Cr 24000 0.190000 Mn 25000 0.010000 Fe 26000 0.701730 Ni 28000 0.092500 Table 5.3 Densimet Composition (Density= 17.6 g/cm 3 or 18.5 g/cm3 )

Weight Element ZAID Fraction Fe 26000 0.035 Ni 28000 0.035 w 74000 0.035 5.4 Shielding Evaluation 5.4.1 Methods The method utilized to demonstrate the shielding performance of the OP-RM SC package for the lr-192 and Se-75 isotopes is primarily via prototypic testing utilizing special form capsules containing radioactive Jr-192 material, which bounds the Se-75 isotope.

For the Co-60 isotope, a shielding model utilized MCNP6.2 and ENDF/B-V 1.8 photon cross-section was developed in order to determine the maximum regulatory dose rates. The model was analyzed in two separate runs, with the special form capsule shifted up or down to determine the maximum dose rates. The NCT and HAC cases were evaluated in the same model 14 "Plansee Product Data, Tungsten heavy alloys, https://www.plansee.com/en/materials/tungsten-heavy-metal.html.

15 "PNNL-15870, Compendium of Material Composition Datafor Radiation Transport Modeling, Pacific Northwest National Laboratory, Revision I, March 2011.

81

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 since there was no damage or change in configuration to the RMSC payload from the HAC free and puncture drop tests, as noted in Section 2. 7.8, Summary ofDamage.

5.4.2 Input and Output Data For the MCNP model, the key dimensions relevant to the modeled container and a typical special form capsule are summarized in Table 5.4-1 and Table 5.4-2, respectively. Drawing tolerances are applied to all dimensions such that the tungsten shielding material is minimized. Pipe tolerances were extracted from the ASTM specification identified on the drawings in Appendix 1.3.1, General Arrangement Drawings.

A sample of the MCNP input file is provided Appendix 5.5. l, Sample MCNP Input File (RMSC_Co60_up. i).

Table 5.4 RMSC Key Model Dimensions Item Dimension {in)

Payload Cavity Diameter 1.52 Side Tungsten Outer Diameter 8.18 Body Shell Pipe Outer Diameter 8.63 Body Shell Pipe Wall Thickness 0.13 Bottom Tungsten Thickness 3.91 Bottom Plate Thickness 0.22 Cavity Shield Tungsten Thickness 3.53 Lid Top Plate Thickness 0.60 Table 5.4 Special Form Capsule Key Model Dimensions Item Dimension {in)

Inner Diameter 0.429 Outer Diameter 0.495 Cap Thickness 0.370 Bottom Thickness 0.060 Source Height 1.565 5.4.3 Flux-to-Dose-Rate Conversions ANSI/ANS-6.1.1-197? 16 photon flux-to-dose rate conversion factors were utilized in this analysis for the Co-60 payload. The conversion factors in the ANIS/ANS reference have been multiplied by a factor of I 000 to generate dose rates in units of mrem/hr rather than rem/hr. The conversion factors are provided in Table 5.4-1.

16 "ANSI/ANS-6.1.1-1977, American National Standard Neutron and Gamma-Ray Flux-to-Dose-Rate Factors, March 1977.

82

INC OP-RMSC Safety Analysis Report Docket No. 7 1 -9387 Revision 0, 12/2020 Table 5.4 ANSI/ANS-6.1.1-1977 Photon Flux-to-Dose Rate Conversion Factors Energy, E DF(E Energy, E DF(E)

)

(MeV) (mrem/hr)/(y/cm 2-s (MeV) (mrem/hr)/(y/cm2-s)

)

0.0 3.96E-03 1.40 2.51E-0 1 3 0.03 5.82E-04 1.80 2.99E-03 0.05 2.90E-04 2. 2 0 3.42E-03 0.0 7 2.58E-04 2. 60 3.82E-03 0.10 2.83E-04 2. 80 4.01E-03 0.15 3.79E-04 3. 25 4.41E-03 0.20 5.0IE-04 3. 75 4.83E-03 0.25 6.31E-04 4. 25 5.23E-03 0.30 7.59E-04 4. 75 5 60E-03 0.35 8.78E-04 5. 00 5.80£-03 0.40 9.85E-04 5. 25 6.0IE-03 0.45 l.08E-03 5. 75 6.37E-03 0.50 I .I 7E-03 6. 25 6.74E-03 0.55 l.27E-03 6. 75 7.1 IE-03 0.60 l.36E-03 7.50 7.66E- 03 0.65 l .44E -03 9. 00 8.77E-03 1 00 1.03E-02 0.70 l.52E-03 1 .

0.80 l.68E-03 13. 00 I. I 8E-02 1.00 l.98E-03 15. 00 l.33E-02 5.4. 4 External Radiation Levels Following the specified tests of a prototypic package with 16, 000 C (592 TBq) of Ir-192 pay load i

per 2.6, Normal Conditions of Transport, and 2.7, Hypothetical Accident Conditions, the adjusted maximum measured radiation level on the surface and at I-meter of the RMSC pa yloads is 123 mrem/hr (l.23 mSv/hr) and 2 mrem/hr (0. 0 mSv/hr), respectively. As noted in Table 5.1- 1 these levels are below the regulatory limits of 10 CFR §7 l .47(a) and 10 CFR §71.51 (a)(2) .

For the Co-60 payload, the MCNP tallies were subdivided into sub-tallies to ensure all local maximum dose rates are properly captured. All side tallies were vertically segmented into ---0.4 inch (-1 cm) subdivisions. Similarly, top and bottom tallies were radially segmented into---0.4 inch (-1 cm) subdivisions. At I meter, for mesh locations away from the expected maximum dose rate locations (i.e., along package diagonals), larger subdivisions (---4 inch/-10 cm, either axially or

° radially) were utilized. All mesh tallies were rotationally segmented into four 90 subdivisions.

For NCT, surface dose rates were captured using three mesh tallies at the following locations:

top surface, side surface, and bottom surface. For NCT and HAC, the \-meter dose rates were captured using the same three mesh tallies at similar locations: I meter from top surface, I meter from side surface, and I meter from bottom surface.

83

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 The maximum dose rates for each location resulting from a 1 Ci Co-60 source are tabulated in Table 5.4-2. Based on the resulting dose rates, the maximum possible Co-60 source strength that can be shipped in the RMSC is 2.1 Ci. However, the maximum allowable source strength is set at 2 Ci for the OP-RMSC package for operational reasons.

Table 5.4-2-Tally Maximum Dose Rates, 1 Ci Co-60 Capsule Dose Rate Relative Max Curies Location Position (mrem/hr) Error until Limit NCT, Top Surface Up 38.3 0.2% 5.2 NCT, Side Surface Up 99.0 0.2% 2.0 NCT, Bottom Surface, Bottom Down 16.5 0.1% 12.1 NCT/HAC, Top at I meter Up 0.4 5.7% 23.9 NCT/HAC, Side at I meter Up 0.8 0.8% 13.2 NCT/HAC, Bottom at I meter Down 0.1 4.7% 71.l 84

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 5.5 Appendix 5.5.1 Sample MCNP Input File (RMSC_Co60_up.i)

INC RMSC, Co-60 Source C *** Cell Cards ***

C ----- RMSC 1 2 -8.00 1 3 imp:p =l fill =12 2 1 -18.5 2 3 (-6:9) (-7: 8) imp:p=l fill=ll 3 1 -17.6 6 12 (-13:14) imp:p = l fil1=13 4 2 -8.00 6 -11 17 -16 imp:p = l fill =l2 5 2 -8.00 1 -11 19 -18 imp:p=l fill=12 6 2 -8.00 21 -11 16 -19 imp:p=l fi11 =12 7 2 -8.00 (11 18): (13 14) imp:p=l fil1 =12 8 0 (1 -21 3 -19):

(5 -21 16 -3):

(6 -5 16 -9):

(6 -11 12 -17) imp:p =l 9 0 7 8 imp:p= l fill=l (1.3 0 2.54)

C c ===== Source Capsule 11 2 -8.00 25 29 (-27:31:28) imp:p=l u=l 12 0 27 28 imp:p =l u= l 13 0 -25:26:29 imp:p =l u=l C

C ------ Problem Boundary 98 0 (-1:23:18) -33 imp:p =l 99 0 33 imp:p =0 C

C ----- Importance Splitting C Down 101 1 -18.5 -80 101 -70 u=ll imp:p=l.00e+00 102 1 -18.5 -80 102 -101 u =ll imp:p=4.65e+00 103 1 -18.5 -80 103 -102 u =ll imp:p =l.62e+0l 104 1 -18.5 -80 104 -103 u=ll imp:p=5.29e+0l 105 1 -18.5 -80 105 -104 u=ll imp:p =l.69e+02 106 1 -18.5 -80 106 -105 u= ll imp:p=5.27e+02 107 1 -18.5 -80 107 -106 u=ll imp:p =l.60e+03 108 1 -18.5 -80 108 -107 u=ll imp:p =4.56e+03 109 1 -18.5 -80 109 -108 u=ll imp:p =l.35e+04 110 1 -18.5 -80 -109 u =ll imp:p=4.5le+04 C

111 2 -8.00 -80 -109 u=l2 imp:p=l.90e+05 C

C Side 201 1 -18.5 70 -60 -201 u =ll imp:p=l.O0e+00 202 1 -18.5 70 -60 -202 201 u =ll imp:p=l.66e+00 203 1 -18.5 70 -60 -203 202 u= ll imp:p =4.46e+00 204 1 -18.5 70 -60 -204 203 u=ll imp:p=l.19e+0l 205 1 -18.5 70 -60 -205 204 u=ll imp:p=3.15e+0l 206 1 -18.5 70 -60 -206 205 u=ll imp:p=8.45e+0l 207 1 -18.5 70 -60 -207 206 u=ll imp:p =2.28e+02 208 1 -18.5 70 -60 -208 207 u=ll imp:p =5.99e+02 209 1 -18.5 70 -60 208 u= ll imp:p=l.63e+03 C

210 2 -8.00 70 -60 u=12 imp:p =3.92e+03 C

C Down Diagonal 301 1 -18.5 80 -70 -301 u= ll imp:p= l.00e+00 302 1 -18.5 80 -70 -302 301 u=ll imp:p=l.00e+00 303 1 -18.5 80 -70 -303 302 u= ll imp:p = l.43e+O0 304 1 -18.5 80 -70 -304 303 u=ll imp:p=2.36e+00 305 1 -18.5 80 -70 -305 304 u=ll imp:p=4.16e+00 306 1 -18.5 80 -70 -306 305 u=ll imp:p=7.63e+00 85

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 307 1 -18.5 80 -70 -307 306 u= ll imp:p= l.43e+Ol 308 1 -18.5 80 -70 -308 307 u= ll imp:p=2.70e+Ol 309 1 -18.5 80 -70 -309 308 u =ll imp:p=5.23e+Ol 310 1 -18.5 80 -70 -310 309 u =ll imp:p=l.00e+02 311 1 -18.5 80 -70 -311 310 u=ll imp:p=2.0le+02 312 1 -18.5 80 -70 -312 311 u=ll imp:p=4.07e+02 313 1 -18.5 80 -70 -313 312 u=ll imp:p=8.62e+02 314 1 -18.5 80 -70 -314 313 u = ll imp:p=l.77e+03 315 1 -18.5 80 -70 -315 314 u= ll imp:p=4.03e+03 316 1 -18.5 80 -70 -316 315 u=ll imp:p=8.06e+03 317 1 -18.5 80 -70 -317 316 u =ll imp:p=l.93e+04 318 1 -18.5 80 -70 -318 317 u=ll imp:p=5.46e+04 319 1 -18.5 80 -70 318 u =ll imp:p = l.64e+05 C

410 2 -8.00 80 -70 -310 309 u=l2 imp:p=l.00e+02 411 2 -8.00 80 -70 -311 310 u =l2 imp:p=2.0le+02 412 2 -8.00 80 -70 -312 311 u=l2 imp:p=4.07e+02 413 2 -8.00 80 -70 -313 312 u=12 imp:p=8.62e+02 414 2 -8.00 80 -70 -314 313 u=12 imp:p=l. 77e+03 415 2 -8.00 80 -70 -315 314 u =12 imp:p=4.03e+03 416 2 -8.00 80 -70 -316 315 u=l2 imp:p=8.06e+03 417 2 -8.00 80 -70 -317 316 u = 12 imp:p= l.93e+04 418 2 -8.00 80 -70 -318 317 u=12 imp:p=5.46e+04 419 2 -8.00 80 -70 318 u=12 imp:p=l.64e+05 C

c Up 501 1 -17.6 -80 -501 u=13 imp:p=l.OOe+OO 502 1 -17.6 -80 -502 501 u=13 imp:p=2.21e+OO 503 1 -17.6 -80 -503 502 u= l3 imp:p=6.32e+OO 504 1 -17.6 -80 -504 503 u=13 imp:p=l.79e+Ol 505 1 -17.6 -80 -505 504 u=13 imp:p=5.02e+Ol 506 1 -17.6 -80 -506 505 u=13 imp:p=l.40e+02 507 1 -17.6 -80 -507 506 u =13 imp:p=3.90e+02 508 1 -17. 6 -80 -508 507 u =l3 imp:p=l.13e+03 509 1 -17.6 -80 -509 508 u=13 imp:p=2.91e+03 510 1 -17.6 -80 509 u= l3 imp:p=8.73e+03 C

511 2 -8.00 510 509 u=12 imp:p=l.15e+04 512 2 -8.00 -80 510 u=12 imp:p=l.42e+04 C

609 2 -8.00 508 109 u = 12 imp:p=2.91e+03 610 2 -8.00 509 508 u =l2 imp:p=8.73e+03 C

C Up Diagonal 701 1 -17.6 80 -701 u=l3 imp:p=l.OOe+OO 702 1 -17.6 80 -702 701 u =13 imp:p=l.OOe+OO 703 1 -17.6 80 -703 702 u =13 imp:p=l.28e+OO 704 1 -17.6 80 -704 703 u=13 imp:p=l.95e+OO 705 1 -17.6 80 -705 704 u=13 imp:p=3.00e+OO 706 1 -17.6 80 -706 705 u=13 imp:p=4.77e+OO 707 1 -17.6 80 -707 706 u=13 imp:p=8.18e+OO 708 1 -17.6 80 -708 707 u=13 imp:p=l.40e+Ol 709 1 -17.6 80 -709 708 u =13 imp:p= 2.47e+Ol 710 1 -17.6 80 -710 709 u = 13 imp:p= 4.35e+Ol 711 1 -17.6 80 -711 710 u =13 imp:p=8.00e+Ol 712 1 -17.6 80 -712 711 u =13 imp:p=l.48e+02 713 1 -17.6 80 -713 712 u =13 imp:p=2.99e+02 C

714 2 -8.00 80 -714 713 u =12 imp:p=4.96e+02 715 2 -8.00 80 -715 714 u = 12 imp:p=7.98e+02 716 2 -8.00 80 -716 715 u=12 imp:p=l.22e+03 717 2 -8.00 80 -717 716 u=12 imp:p=l.92e+03 718 2 -8.00 80 -718 717 u =12 imp:p=3.17e+03 719 2 -8.00 80 -719 718 u =12 imp:p=6.60e+03 720 2 -8.00 80 719 u =12 imp:p=2.lle+04 C

86

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 805 2 -8.00 80 60 -705 u=l2 imp:p=3.00e+OO 806 2 -8.00 BO 60 -706 705 u=l2 imp:p=4.77e+OO 807 2 -8.00 80 60 -707 706 u=l2 imp:p=8.18e+OO BOB 2 -8.00 BO 60 -708 707 u=l2 imp:p=l. 40e+Ol 809 2 -8.00 80 60 -709 708 u=12 imp:p=2.47e+Ol 810 2 -8.00 80 60 -710 709 u=l2 imp:p =4.35e+Ol 811 2 -8.00 BO 60 -711 710 u=l2 imp:p=B.OOe+Ol 812 2 -8.00 80 60 -712 711 u=l2 imp:p=l.4Be+02 813 2 -8.00 80 60 -713 712 u= l2 imp:p= 2.99e+02 C

905 1 -18.5 80 60 -705 u=ll imp:p =3.00e+OO 906 1 -18.5 80 60 -706 705 u=ll imp:p =4.77e+OO 907 1 -18.5 80 60 -707 706 u=ll imp:p=8.18e+OO 908 1 -18.5 BO 60 -708 707 u=ll imp:p =l.40e+Ol 909 1 -18.5 80 60 -709 708 u=ll imp:p=2.47e+Ol 910 1 -18.5 80 60 -710 709 u=ll imp:p =4.35e+Ol 911 1 -18.5 BO 60 -711 710 u=ll imp:p=B.OOe+Ol 912 1 -18.5 BO 60 -712 711 u=ll imp:p=l.48e+02 913 1 -18.5 80 60 -713 712 u=ll imp:p =2.99e+02 914 1 -18.5 80 60 -714 713 u=ll imp:p=4.96e+02 915 1 -18.5 80 60 -715 714 u=ll imp:p =7.98e+02 916 1 -18.5 80 60 715 u= ll irnp:p = l.22e+03 C *** Surface Cards ***

c ===== RMSC c Body Shell Bottom Plate 1 pz 0 2 pz 0.5588 $ 0.25" (-0.03") height 3 CZ 10.3886 $ 8.20" (-0.02") diameter, match tungsten diameter for simplicity C

c Tungsten Body Shield 5 pz 25.146 $ 9.70" (-0.02") height 6 pz 18 .2118 $ 2.75" (-0.02") shield plug height 7 pz 10.4902 $ 5.75" (+0.02") shield plug and cavity height 8 CZ 1.9304 $ 1.50" (+O .02") cavity diameter 9 CZ 5.8166 $ 4 .60" (-0.02") shield plug diameter C

c Tungsten Cavity Shield Plug 11 pz 27 .178 $ 3.55" (-0.02") height 12 CZ 5.3086 $ 4 .20" (-0.02") diameter 13 pz 25.654 $ 0. 6" depth screw hole 14 CZ 0.396875 $ 0.3125" diameter (5/16-18 UNC major diameter)

C c Body Upper Center and Outer Shell Pipes 16 CZ 5.715 $ 4.5" outer diameter, 4" Schedule lOS 17 CZ 5.4483 $ 0.120" (-12.5%) wall thickness 18 CZ 10.95375 $ 8.625" outer diameter, 8" Schedule lOS 19 CZ 10.62482 $ 0.148" (-12.5%) wall thickness C

c Body Top Plate 21 pz 25.3492 $ 0.75" (-0.03") thick C

c Lid Top Plate 23 pz 28.702 $ 0.63" (-0.03") thick C

c ===== Source Capsule C Special Form Capsule 25 pz 10.6 26 pz 15.6673 $ 2.000" (-0.005") height 27 pz 10.7524 $ 1.930" (+0.005") from top 28 CZ 0.54483 $ 0.429" (+0.000") inner diameter 29 CZ 0.62865 $ 0.500" (-0.005") outer diameter C

c Special Form Capsule Plug 31 pz 14.7275 $ 0.375" (-0.005") height C

87

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 c ===== Problem Boundary 33 so 1000 C

c ===== Importance Splitting c Offset surfaces to avoid chaining 60 pz 18.2119 70 pz 10.5919 80 CZ 1.8797 C

c Down 101 pz 9.5 102 pz 8.5 103 pz 7.5 104 pz 6.5 105 pz 5.5 106 pz 4.5 107 pz 3.5 108 pz 2.5 109 pz 1.5 C

c Side 201 CZ 2.5 202 CZ 3.5 203 CZ 4.5 204 CZ 5.5 205 CZ 6.5 206 CZ 7.5 207 CZ 8.5 208 CZ 9.5 C

c Down Diagonal 301 z 9.5 1.8796 10.5918 2.5 302 z 8.5 1.8796 10.5918 3.5 303 z 7.5 1.8796 10.5918 4.5 304 z 6.5 1.8796 10.5918 5.5 305 z 5.5 1.8796 10.5918 6.5 306 z 4.5 1.8796 10.5918 7.5 307 z 3.5 1.8796 10.5918 8.5 308 z 2.5 1.8796 10.5918 9.5 309 z 1.5 1.8796 10.5918 10.5 310 z 0.5 1.8796 10.5918 11.5 311 z -0.5 1.8796 10.5918 12.5 312 z -1.5 1.8796 10.5918 13.5 313 z -2.5 1.8796 10.5918 14.5 314 z -3.5 1.8796 10.5918 15.5 315 z -4.5 1.8796 10.5918 16.5 316 z -5.5 1.8796 10.5918 17 .5 317 z -6.5 1.8796 10.5918 18.5 318 z -7.5 1.8796 10.5918 19.5 C

c Up 501 pz 19 502 pz 20 503 pz 21 504 pz 22 505 pz 23 506 pz 24 507 pz 25 508 pz 26 509 pz 27 510 pz 28 C

c Up Diagonal 701 z 19 1.8796 18.2118 2.5 702 z 20 1.8796 18.2118 3.5 703 z 21 1.8796 18.2118 4.5 88

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 704 z 22 1.8796 18. 2118 5.5 705 z 23 1.8796 18.2118 6.5 706 z 24 1. 8796 18.2118 7.5 707 z 25 1.8796 18.2118 8.5 708 z 26 1.8796 18.2118 9.5 709 z 27 1. 8796 18.2118 10.5 710 z 28 1.8796 18.2118 11.5 711 z 29 1.8796 18. 2118 12.5 712 z 30 1.8796 18.2118 13.5 713 z 31 1.8796 18.2118 14.5 714 z 32 1.8796 18.2118 15.5 715 z 33 1.8796 18.2118 16.5 716 z 34 1.8796 18. 2118 17.5 717 z 35 1.8796 18.2118 18.5 718 z 36 1. 8796 18. 2118 19.5 719 z 37 1.8796 18.2118 20.5 c *** Data Cards ***

c ===== Materials C =========================================== ====

c Densimet Tungsten Alloy c Density = 17.6 or 18.5 g/cmA 3 c

Reference:

Supplier product sheet C ============== ===========================-====

ml 26000 -0.035 28000 -0.035 74000 -0.930 C ==================== ================= ==========

c Stainless Steel 304 c Density = 8.00 g/cm A 3 c

Reference:

PNNL-15870 Rev. 1 C ====================-=--==--------------------

m2 6000 -0.000400 14000 -0.005000 15000 -0.000230 16000 -0.000150 24000 -0.190000 25000 -0.010000 26000 -0. 701730 28000 -0.092500 C

c ===== Source Definition sdef par=p cel=dl pos= O O 10.7524 rad=d2 ext=d3 axs= O O 1 erg =d4 wgt=7.3948el0 dir=d5 vec= O O 1 C

sil L (12<9) spl D 1 C

si2 H 0 0.54483 sp2 D -21 1 C

si3 H 0 3.9751 sp3 D 0 1 C

c Energy distribution taken from SCALE 6.2.1. discrete gamma data

1. si4 sp4 L D 7.5100e-04 l.6946e-06 8.5234e-04 8.055e-07 8.7689e-04 l.3826e-08 8.8364e-04 5.6638e-07 7.4178e-03 3.1894e-05 7.4358e-03 6.2286e-05 8.2223e-03 3.9005e-06 89

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 8.2246e-03 7.6481e-06 8.2879e-03 3.3435e-09 8.2881e-03 4.8594e-09 3.4714e-01 7.5e-05 8.2610e-01 7.6e-05 l.1732e+OO 0.9985 1.3325e+OO 0.99983 2.1586e+OO l.2e-05 2.5057e+OO 2e-08 C

C Source directionality (biasing only), 10 deg increments

1. si5 sp5 sb5 A D D

-1.000 1 100

-0.985 1 50

-0.940 1 25

-0.866 1 12

-0.766 1 1

-0.643 1 1

-0.500 1 1

-0.342 1 1

-0.174 1 1 0.000 1 1 0.174 1 1 0.342 1 1 0.500 1 1 0.643 1 1 0.766 1 1 0.866 1 12 0.940 1 25 0.985 1 50 1.000 1 100 C

C ----- Dose Tallies c ANSI/ANS-6.1.1-1977 Flux-to-Dose Rate, Photons, (mrem/hr)/lp/cm**2/s) deO 0.01 0.03 0.05 0.07 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45 0.50 0.55 0.60 0.65 0.70 0.80 1.00 1.40 1. 80 2.20 2.60 2.80 3.25 3.75 4.25 4.75 5.00 5.25 5.75 6.25 6.75 7.50 9.00 11.0 13.0 15.0 dfO 3.96-3 5.82-4 2.90-4 2.58-4 2.83-4 3.79-4 5.01-4 6.31-4 7.59-4 8.78-4 9.85-4 1.08-3 1.17-3 1.27-3 1.36-3 1.44-3 1.52-3 1.68-3 1.98-3 2.51-3 2.99-3 3.42-3 3.82-3 4.01-3 4.41-3 4.83-3 5.23-3 5.60-3 5.80-3 6.01-3 6.37-3 6.74-3 7.11-3 7.66-3 8.77-3 1.03-2 1.18-2 1. 33-2 C

fc104 Top Surface Tally fmeshl04:p geom =cyl origin= O O 28.702 axs=O O 1 vec= -1 1 0 imesh=l0.95375 iints=ll jmesh=l jints= l kmesh=l kints=4 C

fcll4 Side Surface Tally fmesh114:p geom=cyl origin =O O O axs =O O 1 vec=-1 1 0 imesh = l0.95375 11.95375 iints = l 1 jmesh=28.702 jints =29 kmesh= l kints=4 C

fcl24 Bottom Surface Tally fmesh124:p geom=cyl origin=O O -1 axs =O O 1 vec=-1 1 0 imesh= l0.95375 iints= ll jmesh=l jints= l kmesh=l kints=4 C

fc204 Top lm Tally fmesh204:p geom=cyl origin=O O 128.702 axs =O O 1 vec=-1 1 0 90

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 imesh=l0.95375 110.95375 iints=ll 10 jmesh=l jints=l kmesh=l kints=4 C

fc214 Side lm Tally fmesh214:p geom=cyl origin =0 0 -100 axs=0 0 1 vec= -1 1 0 imesh= ll0.95375 111.95375 iints= l 1 jmeshl00 128.702 228.702 jints = l0 29 10 kmesh=l kints= 4 C

fc224 Bottom lm Tally fmesh224:p geom=cyl origin= 0 0 -101 axs =0 0 1 vec= -1 1 0 imesh=l0.95375 110.95375 iints=ll 10 jmesh= l jints =l kmesh=l kints =4 C

c fc444 DEBUG MESH c fmesh444:p geom=xyz origin= 11 0 c imesh=ll iints=44 c jmesh= ll jints=44 c kmesh= 29 kints= 58 C

c ===== Run Options mode p prdmp 4e8 4e7 0 2 4e8 nps 4e8 rand gen=2 stride=l52917123 $ Use larger period and stride 91

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020

6.0 CRITICALITY EVALUATION

The OP-RMSC package does not transport fissile material; therefore, this section does not apply.

92

INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 7.0 PACKAGE OPERATIONS 7.1 Package Loading This section delineates the procedures for loading the RMSC payload into the OP-RMSC package.

Hereafter, reference to specific OP-RMSC components may be found in Appendix 1.3.1, General Arrangement Drawings.

7.1.1 Preparation of the OP-RMSC for Loading I) Visually inspect the OP-RMSC package for damage and/or missing parts.

2) Remove the eight (8) hex bolts/washers and the closure lid from the OP-RMSC package body.

3) Remove the eight (8) hex bolts/washers and the inner closure lid.

4) Attach appropriate rigging to the hoist ring and remove the RMSC from the OP-RMSC cavity.

5) Visually inspect the RMSC for damage and/or missing parts.

7.1.2 Loading the Special Fonn Contents into the RMSC l) Loosen the six (6) hex bolts/washers so that they may be easily removed in a remote handling operation.

2) Place the RMSC in an appropriate hot cell or shielded cell.

3) Remove the six (6) hex bolts/washers. Using an appropriate lifting device, remove the closure lid from the RMSC body, and place it in a secure location in the cell.

4) Thread an appropriate lift device into the threaded hole in the cavity tungsten shield and remove it from the payload cavity. Store the tungsten shield in a secure location in the cell.

5) Insert up to four (4) raw material source capsules and holder into the RMSC cavity.

6) Re-install the cavity tungsten shield over the payload cavity. Remove the lifting device from the shield and place it in a secure location.

7) lnstall the closure lid and the hex bolts/washers. Tighten the hex bolts to a hand tight condition.

8) Remove the RMSC from the hot cell or shielded cell.

9) Survey the RMSC to ensure that the dose rate is within acceptable limits.

10) Tighten the six (6) closure lid hex bolts to 40 +/-5 lbr-ft torque.

7.1.3 Preparation for Transport I) Attach appropriate rigging to the hoist ring, lift the RMSC payload and insert it into the OP-RMSC payload cavity. Remove the rigging from the hoist ring.

2) Install the inner lid and the eight (8) hex bolts/washers. Tighten the hex bolts to 80 +/-5 lbr-ft torque.

3) Install the closure lid and the eight (8) hex bolts/washers to the OP-RMSC package body.

Tighten the closure lid bolts to 80 +/-5 lb,-ft torque.

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4) Install a tamper-indicating seal (security wire/lead seals) to a pair of the closure lid bolts.

5) Install an appropriate lifting device into the 3/8-16 UNC threaded hole, lift and place the OP-RMSC package onto the transport skid. Secure the package utilizing nylon straps or other securement system.

6) Remove the lifting device from the threaded hole, and install a threaded fastener to prevent the hole from being utilized as a tie-down. Tighten the fastener to a snug-tight condition.

7) Monitor external radiation per the guidelines of 49 CFR § 173 .441 17*

8) Determine the shielding transport index for the loaded OP-RMSC package per the guidelines of 49 CFR § l 73.403.

9) Install the personnel barrier over the OP-RMSC package, and secure it to the transport skid with the fasteners.

10) Complete all necessary shipping papers in accordance with Subpart C of 49 CFR I 72 18*

I l ) OP-RMSC package marking shall be in accordance with 10 CFR §71.85(c) and Subpart D of 49 CFR 172. Package labeling shall be in accordance with Subpart E of 49 CFR 172.

Packaging placarding shall be in accordance with Subpart F of 49 CFR 172.

7.2 Package Unloading This section delineates the procedures for unloading the RMSC payload from the OP-RMSC package. Hereafter, reference to specific OP-RMSC components may be found in Appendix 1.3.1, General A rrangement Drawings.

7.2.1 Receipt of OP-RMSC Package from Carrier I) Remove the fasteners that secure the personnel barrier to the skid, and remove the barrier from the conveyance.

2) Remove the straps or system that secures the OP-RMSC package to the transport conveyance.

3) Monitor the external radiation to ensure that the OP-RMSC package was not damaged during shipment.

4) Remove the fastener from the 3/8-16 threaded hole, and install an appropriate lifting device.

5) Utilizing appropriate rigging equipment, lift the OP-RMSC package from the transport conveyance, and place in a secure position for unloading the RMSC payload.

7.2.2 Removal of Special Form Contents from the RMSC

1) Remove the tamper-indicating seals from the closure lid bolts.

2) Remove the closure Jid bolts/washers and the closure lid.

3) Remove the inner closure lid bolts/washers and the inner closure lid.

17 Title 49, Code of Federal Regulations, Part 173 (49 CFR 173), Shippers-General Requirementsfor Shipments and Packagings, 10-1-20 Edition.

18 Title 49, Code of Federal Regulations, Part 172 (49 CFR 172), Hazardous Materials Tables and Hazardous Communications Regulations, 10-1-20 Edition.

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4) Attach appropriate rigging to the hoist ring, lift the RMSC payload from the OP-RMSC cavity.

5) Perform a radiation survey and smear test of the RMSC payload to ensure the package is acceptable for unloading in a hot cell.

6) Loosen the six (6) hex bolts/washers so that they may be easily removed in a remote handling operation.

7) Place the RMSC payload in an appropriate hot cell or shielded cell.

8) Remove the six (6) hex bolts/washers. Using an appropriate lifting device, remove the closure lid from the RMSC body, and place it in a secure location in the cell.

9) Thread an appropriate lift device into the threaded hole in the cavity tungsten shield and remove it from the payload cavity. Store the tungsten shield in a secure location in the cell.

10) Utilizing appropriate remote handling tools, remove the raw material special form capsules and holder from the RMSC cavity, and place the capsules/holder in a secure location.

I I) Install the closure lid and the hex bolts/washers. Tighten the hex bolts to a hand tight condition.

12) Remove the RMSC from the hot cell or shielded cell. Tighten the hex bolts to a snug-tight condition.

13) Perform a radiation survey and smear test of the RMSC payload to ensure the package is acceptable for loading into the OP-RMSC.

14) Attach appropriate rigging to the hoist ring, lift the RMSC payload and insert it into the OP-RMSC payload cavity. Remove the rigging from the hoist ring.

15) Install the inner closure lid and the eight (8) hex bolts/washers. Tighten the hex bolts to a snug-tight condition.

16) Install the closure lid and the eight (8) hex bolts/washers to the OP-RMSC package body.

Tighten the closure lid bolts to a snug-tight condition.

7.3 Preparation of Empty OP-RMSC Package for Transport Previously used and empty OP-RMSC packages shall be prepared and transported per the requirements of 49 CFR § 173.428.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision 0, 12/2020 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 Acceptance Tests Per the requirements of 10 CFR §71.85(c), this section discusses the inspections and tests to be performed prior to first use of the OP-RMSC package.

8.1.1 Visual Inspections and Measurements All materials of construction for the OP-RMSC package shall be examined in accordance with the requirements delineated on the drawings in Appendix 1.3.1, General Arrangement Drawings, per the requirements of IO CFR §7 l.85(a).

8.1.2 Weld Examinations All OP-RMSC package welds shall be examined in accordance with the requirements delineated on the drawings in Appendix l .3.1, General Arrangement Drawings, per the requirements of l O CFR

§71.85(a).

8.1.3 Structural and Pressure Tests The OP-RMSC package does not contain any lifting/tie-down devices or pressure boundaries that require testing. Therefore, this section does not apply.

8.1.4 Leakage Tests The OP-RMSC package does not contain any seals or containment boundaries that require leakage testing. Therefore, this section does not apply.

8.1.5 Component and Material Tests The OP-RMSC package does not contain any additional components or materials that require acceptance testing. Therefore, this section does not apply.

8.1.6 Shielding Tests A radiation profile shall be performed on each tungsten gamma shield assembly prior to being utilized in the fabrication of a RMSC payload. These measured survey results are ratioed to determine the expected radiation levels for the maximum authorize source strength of 16,000 Ci (592 TBq) for the Ir-192 isotope. Any radiation profile of a tungsten gamma shield that results in a dose rate that exceeds the requirements of 49 CFR §173 .441 with the maximum authorized payload shall not be utilized in the manufacture of a RMSC payload.

8.1. 7 Thermal Tests The OP-RMSC package does not contain any thermal features or systems that require testing.

Therefore, this section does not apply.

8.1.8 Miscellaneous Tests There are no additional tests required to utilize the OP-RMSC package. Therefore, this section does not apply.

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INC OP-RMSC Safety Analysis Report Docket No. 71-9387 Revision O, 12/2020 8.2 Maintenance Program This section describes the maintenance program used to ensure continued performance of the OP-RMSC package.

8.2.1 Structural and Pressure Tests The OP-RMSC package does not contain any lifting/tie-down devices or pressure boundaries that require load testing. Therefore, this section does not apply.

8.2.2 Leakage Tests The OP-RMSC package does not contain any seals or containment boundaries that require testing. Therefore, this section does not apply.

8.2.3 Component and Material Tests All threaded components shall be inspected quarterly for deformed or stripped threads. Damaged components shall be repaired or replaced prior to further use.

The silicone gasket on the inner closure lid shall be inspected quarterly for damage and/or excessive wear. A damaged gasket shall be replacement prior to further use.

8.2.4 Thermal Tests No thermal tests are necessary to ensure continued performance of the OP-RMSC package.

8.2.5 Miscellaneous Tests- Shielding Prior to each shipment, a radiation survey of the RMSC payload is performed to ensure that the radiation dose levels do not exceed the requirements of 49 CFR § \ 73.44 l. This survey confirms that the tungsten gamma shields have maintained their shielding function.

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