ML19273B561

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Enclosure 3 - NUHOMS-MP197HB SAR, Revision 20, Replacement Pages and Drawings
ML19273B561
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Site: 07109302
Issue date: 09/30/2019
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Orano USA, TN Americas LLC
To:
Office of Nuclear Material Safety and Safeguards
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ML19273B552 List:
References
E-55004 NUH09.0101
Download: ML19273B561 (32)
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Enclosure 3 to E-55004 NUHOMS-MP197HB SAR, Revision 20, Replacement Pages and Drawings (Public Version)

NON-PROPRIETARY NUHOMS-MP197 TRANSPORTATION PACKAGING SAFETY ANALYSIS REPORT NUH09.0101 Revision 20 September 2019

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 Revision Log Rev.

No.

Date Description 0

4/2001 Original Issue for CoC Revision 0 1

1/2002 Various Changes CoC Revision 0 2

2/2002 Various Changes CoC Revision 0 3

4/2002 Various Changes CoC Revision 0 4

5/2002 Various Changes CoC Revision 0 5

3/2009 Application for CoC Revision 3 Added Appendix A for the MP197HB 6

6/2009 Various Changes for CoC Revision 3 7

4/2010 Various Changes for CoC Revision 3 8

7/2010 Various Changes for CoC Revision 3 9

3/2011 Various Changes for CoC Revision 3 10 8/2011 Consolidated SAR Submittal for CoC Revision 3 11 9/2011 Various Changes for CoC Revision 4 12 2/2012 Application for CoC Revision 7 13 8/2012 Various Changes for CoC Revision 7 14 8/2013 Various Changes for CoC Revision 7 15 1/2014 Various Changes for CoC Revision 7 16 3/2014 Various Changes for CoC Revision 7 17 4/2014 Various Changes for CoC Revision 7 18 4/2017 Application for CoC Revision 8 Revised pages as follows:

SAR pages A.1.4.8-3a, A.1.4.8.13a, A.1.4.8-14, A.1.4.9-i, A.1.4.9-2, A.1.4.9-2a, A.1.4.9-3, A.1.4.9-9, A.1.4.9-9a, A.1.4.9-10, A.1.4.10-1, A.1.4.10-6 SAR pages A.2.13.11-ii, A.2.13.11-1 through A.2.13.11-6, A.2.13.11-12, A.2.13.11-13, A.2.13.11-18, A.2.13.11-22 through A.2.13.11-24, A.2.13.11-31, A.2.13.11-41, A.2.13.11-43 SAR pages A.3-i through A.3-v, A.3-1, A.3-3, A.3-4, A.3-6, A.3-7, A.3-28, A.3-55, A.3-62, A.3-77, A.3-78, A.3-80, A.3-81, A.3-97, A.3-98, A.3-99, A.3-102, A.3-175, A.3-176 SAR pages A.5-i through A.5-v, A.5-1, A.5-2, A.5-3, A.5-5, A.5-7, A.5-8, A.5-11, A.5-12d, A.5-16, A.5-16a, A.5-16b, A.5-20b, A.5-29a, A.5.-29c, A.5-29d through A.5-29h, A.5-32b, A.5-34, A.5-37, A.5-38, A.5-40, A.5-41, A.5-41a, A.5-70, A.5-75, A.5-80l, A.5-80m, A.5-80p, A.5-80q, A.5-80t, A.5-105 NUH09.0101 i

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 Revision Log Rev.

No.

Date Description Revised drawings as follows:

Drawing MP197HB-71-1005 Drawing NUH69BTH-71-1004 New pages as follows:

Proprietary Information Notice Revision Log Appendix A Master Table of Contents, pages i through xix SAR pages A.1.4.9-9b through A.1.4.9-9g, A.1.4.9-15a SAR pages A.3-60a, A.3-102a, A.3-102b SAR pages A.5-2a, A.5-29i, A.5-38a, A.5-41b, A.5-41c, A.5-42a, A.5-79b, A.5-102a 19 04/2019 Application for CoC Revision 9 Revised pages as follows:

SAR cover page P, SAR cover page NP Proprietary Information Notice Revision Log, MP197 SAR Overall TOC SAR pages 1-i, 1-13, 1-14, 1-15, 1-16 SAR pages 3-1 to 3-38 SAR pages 6-i to 6-11 Appendix A Master Table of Contents pages ii, v, vi, x, xi, xvii, and xix SAR pages A.1-2, A.1-3, A.1-4, A.1-8, A.1-9, A.1.4.9Ai, A.1.4.9A-1 through A.1.4.9A-5, A.1.4.10-i, A.1.4.10-1, and A.1.4.10-6 SAR pages A.2-3, A.2-6, A.2-7, A.2-13, A.2-16, A.2-23, A.2.13.1-3, A.2.13.2-1, A.2.13.2-4, A.2.13.2-13, A.2.13.2-15, A.2.13.2-18, A.2.13.2-30, A.2.13.2-31, A.2.13.5-18, A.2.13.5-20, A.2.13.5-22, A.2.13.5-26, A.2.13.5-29, A.2.13.7-i, A.2.13.7-ii, A.2.13.7-1, A.2.13.7-3a, A.2.13.7-4, A.2.13.7-4a, A.2.13.7-5, A.2.13.7-6, A.2.13.7-6a, A.2.13.7-7, A.2.13.7-8, A.2.13.7-8a, A.2.13.7-9, A.2.13.7-10, A.2.13.7-11, A.2.13.7-13, A.2.13.7-14, A.2.13.7-40, A.2.13.7-43, A.2.13.7-43a, A.2.13.7-43b, A.2.13.7-43c, A.2.13.7-44, A.2.13.7-48, A.2.13.7-48a, A.2.13.7-49, A.2.13-7-49a, NUH09.0101 ii

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 Revision Log Rev.

No.

Date Description A.2.13.7-57a, A.2.13.9-2, A.2.13.9-4, A.2.13.9-6, A.2.13.9-7, A.2.13.9-9, A.2.13.9-12, A.2.13.12-10, A.2.13.12-18, A.2.13.14-5, and A.2.13.14-7 SAR pages A.3-27, A.4-i, A.4-1, A.4-3, A.4-4, A.4-5, and A.4-6 SAR pages A.5-i, A.5-iv, A.5-1b, A.5-1c, A.5-3, A.5-3a, A.5-6, A.5-6a. A.5-6b, A.5-38a, A.5-38b, A.5-80a, A.5-80v, and A.5-80w SAR pages A.7i, A.7.ii, A.7-1a, A.7-2, A.7-3, A.7-3a, A.7-4, A.7-4a, A.7-5b, A.7-5c, A.7-6, A.7-6a, A.7-7, A.7-8, A.7-8a, A.7-9 through A.7-14, A.7-17, A.7-18, A.7-18a, A.7-18b, A.7-18c, A.7-21, A.7.7.10.i, and A.7.7.10-1 through A.7.7.10-3 SAR pages A.8-i, A.8-3, A.8-4, A.8-4a, A.8-5, A.8-15, A.8-15a, A.8-16, and A.8-17 Revised drawings as follows:

MP197HB-71-1001, MP197HB-71-1002, MP197HB-71-1003, MP197HB-71-1004, MP197HB-71-1005, MP197HB-71-1006, MP197HB-71-1008, MP197HB-71-1009, MP197HB-71-1011, MP197HB-71-1014 and NUHRWC-71-1001 New pages as follows:

Section cover pages for drawings listed in Section 1.4 and Appendix A.1.4.10.

SAR page A.1.4.9A-3a and A.1.4.9A-5 SAR pages A.2.13.7-3a, A.2.13.7-4a, A.2.13.7-6a, A.2.13.7-8a, A.2.13.7-43a, A.2.13.7-43b, A.2.13.7-43c, A.2.13.7-48a, A.2.13.7-49a, and A.2.13.7-57a SAR pages A.4.6.1-i and A.4.6.1-1 through A.4.6.1-11 SAR pages A.5-1b, A.5-1c, A.5-3a, A.5-6a, A.5-6b, A.5-38a, A.5-38b, A.5-80u, A.5-80v, and A.5-80w SAR pages A.7-3a, A.7-4a, A.7-6a, A.7-18a, A.7-18b, and A.7-18c SAR pages A.8-4a and A.8-15a NUH09.0101 iii

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 Revision Log Rev.

No.

Date Description Deleted Pages as follows:

A.1.4.10-7, A.1.4.10-24, A.1.4.10-42, A.1.4.10-77, A.1.4.10-113, A.1.4.10-159, A.1.4.10-194, A.1.4.10-229, A.1.4.10-244, A.1.4.10-274, and A.1.4.10-308 Deleted Drawings as follows:

MP197HB-71-1007, NUHRWC-71-1002, and NUHRWC-71-1003 20 09/2019 Application for CoC Revision 10 Revised pages as follows:

SAR cover page P, SAR cover page NP Revision Log, MP197 Appendix A TOC (pages ii and viii)

SAR page A.1-5 SAR pages A.2-2, A2-29, A.2-32 and A.2-49 SAR page A.2.13.12-24 SAR pages A.7-2, A.7-12 and A.7-18 SAR Appendix A.1.4.10 SAR Appendix A.2.13.18 (new)

Revised SAR Drawings as follows:

MP197HB-71-1002, MP197HB-71-1008 and MP197HB-71-1009 NUH09.0101 iv

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 Appendix A.1.4.6 A.1.4.6.1 NUHOMS-37PTH DSC Description................................................................... A.1.4.6-1 A.1.4.6.2 NUHOMS-37PTH DSC Fuel Basket................................................................... A.1.4.6-1 A.1.4.6.3 NUHOMS-37PTH DSC Contents....................................................................... A.1.4.6-2 A.1.4.6.4 References.............................................................................................................. A.1.4.6-3 Appendix A.1.4.7 A.1.4.7.1 NUHOMS-61BT DSC Description..................................................................... A.1.4.7-1 A.1.4.7.2 NUHOMS-61BT Fuel Basket.............................................................................. A.1.4.7-1 A.1.4.7.3 NUHOMS-61BT DSC Contents.......................................................................... A.1.4.7-2 A.1.4.7.4 References.............................................................................................................. A.1.4.7-2 Appendix A.1.4.8 A.1.4.8.1 NUHOMS-61BTH DSC Description................................................................... A.1.4.8-1 A.1.4.8.2 NUHOMS-61BTH DSC Fuel Basket.................................................................. A.1.4.8-1 A.1.4.8.3 NUHOMS-61BTH DSC Contents....................................................................... A.1.4.8-2 A.1.4.8.4 References............................................................................................................ A.1.4.8-3a Appendix A.1.4.9 A.1.4.9.1 NUHOMS-69BTH DSC Description................................................................... A.1.4.9-1 A.1.4.9.2 NUHOMS-69BTH Fuel Basket........................................................................... A.1.4.9-1 A.1.4.9.3 NUHOMS-69BTH DSC Contents....................................................................... A.1.4.9-2 A.1.4.9.4 References............................................................................................................ A.1.4.9-2a Appendix A.1.4.9A A.1.4.9A.1 Radioactive Waste Canister Description............................................................ A.1.4.9A-1 A.1.4.9A.2 RWC Contents.................................................................................................... A.1.4.9A-2 A.1.4.9A.3 References........................................................................................................... A.1.4.9A-4 Appendix A.1.4.10 A.1.4.10.1 NUHOMS-MP197HB Drawings....................................................................... A.1.4.10-2 A.1.4.10.2 NUHOMS 24PT4 DSC Drawings...................................................................... A.1.4.10-2 A.1.4.10.3 NUHOMS 32PT DSC Drawings........................................................................ A.1.4.10-3 A.1.4.10.4 NUHOMS 24PTH DSC Drawings..................................................................... A.1.4.10-3 A.1.4.10.5 NUHOMS 32PTH DSC Drawings..................................................................... A.1.4.10-4 A.1.4.10.6 NUHOMS 32PTH1 DSC Drawings................................................................... A.1.4.10-5 A.1.4.10.7 NUHOMS 37PTH DSC Drawings..................................................................... A.1.4.10-5 A.1.4.10.8 NUHOMS 61BT DSC Drawings....................................................................... A.1.4.10-6 A.1.4.10.9 NUHOMS 61BTH DSC Drawings.................................................................... A.1.4.10-6 A.1.4.10.10 NUHOMS 69BTH DSC Drawings.................................................................... A.1.4.10-7 A.1.4.10.11 Radioactive Waste Canister Drawing.................................................................. A.1.4.10-7 ii

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 A.2.13.12.9 Sensitivity Studies of MP197HB Impact Limiter Analysis............................. A.2.13.12-13 A.2.13.12.10 Baseline g Loads for Structural Evaluations.................................................... A.2.13.12-17 A.2.13.12.11 Impact Limiter Bolt Evaluation....................................................................... A.2.13.12-17 A.2.13.12.11.1 Stress Calculations............................................................................... A.2.13.12-18 A.2.13.12.11.2 Minimum Engagement Length for Attachment Bolt and Block.......... A.2.13.12-22 A.2.13.12.11.3 Bolt Torque.......................................................................................... A.2.13.12-24 A.2.13.12.11.4 Conclusions.......................................................................................... A.2.13.12-24 A.2.13.12.12 References........................................................................................................ A.2.13.12-25 Appendix A.2.13.13 A.2.13.13.1 Introduction........................................................................................................ A.2.13.13-1 A.2.13.13.2 References.......................................................................................................... A.2.13.13-1 Appendix A.2.13.14 A.2.13.14.1 Finite Element Model........................................................................................ A.2.13.14-1 A.2.13.14.2 Boundary and Initial Conditions........................................................................ A.2.13.14-4 A.2.13.14.3 Results................................................................................................................ A.2.13.14-5 A.2.13.14.4 Conclusion......................................................................................................... A.2.13.14-6 A.2.13.14.5 References.......................................................................................................... A.2.13.14-6 Appendix A.2.13.15 A.2.13.15.1 Stress Analysis for 290 psig External Pressure.................................................. A.2.13.15-1 A.2.13.15.2 Buckling Analysis for 290 psig External Pressure............................................. A.2.13.15-1 A.2.13.15.3 Fatigue Evaluation during Storage prior to Transportation............................... A.2.13.15-3 A.2.13.15.4 Conclusion................................................................................................. A.2.13.15-5 A.2.13.15.5 References.......................................................................................................... A.2.13.15-6 Appendix A.2.13.16 A.2.13.16.1 Detailed LS-DYNA Model Description (for Confirmatory Analyses).............. A.2.13.16-2 A.2.13.16.2 Detailed Impact Limiter Attachment Bolt Description...................................... A.2.13.16-2 A.2.13.16.3 Data Reduction and Filtering............................................................................. A.2.13.16-3 A.2.13.16.4 Confirmatory Analysis Acceleration Results..................................................... A.2.13.16-4 A.2.13.16.5 Confirmatory Analysis Stress Results............................................................... A.2.13.16-4 A.2.13.16.6 Sensitivity Analysis Results............................................................................... A.2.13.16-4 A.2.13.16.7 References.......................................................................................................... A.2.13.16-6 Appendix A.2.13.17 A.2.13.17.1 Purpose.............................................................................................................. A.2.13.17-1 A.2.13.17.2 Model Description and Methodology................................................................ A.2.13.17-1 A.2.13.17.3 Results and Conclusion...................................................................................... A.2.13.17-3 A.2.13.17.4 References.......................................................................................................... A.2.13.17-5 Appendix A.2.13.18 A.2.13.18.1 LS-DYNA Model Description (for Sensitivity Analyses).................................... A.2.13.18-1 A.2.13.18.2 Analysis Results................................................................................................. A.2.13.18-2 viii

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 Noncontainment welds are inspected in accordance with the NDE acceptance criteria of ASME B&PV Code Subsection NF [8].

The structural analysis of the NUHOMS-MP197HB cask body is presented in Chapter A.2.

A.1.2.1.2 Tiedown and Lifting Devices There are four trunnion sockets on the cask; two front trunnion sockets, and two rear trunnion sockets. They accommodate removable trunnions for handling, lifting, and rotating the cask.

These trunnion sockets are attached to the structural shell. Two types of trunnions are provided for the NUHOMS-MP197HB transport package lifting. One type of trunnion has a double shoulder (non-single failure proof). The other type of trunnion has a single shoulder (single failure proof). The front (lifting) set of trunnions could be either type, depending on site and transfer operation requirements. The rear set of trunnions may also be of either type. The trunnions are fabricated and tested in accordance with ANSI N14.6 [7]. During transport, four trunnion plugs, containing neutron shielding material, are bolted to the four trunnion sockets.

When the cask is in the horizontal position, a shear key receptacle on the bottom of the cask reacts the longitudinal tiedown loads. The shear key receptacle is welded to the structural shell and protrudes through the neutron shield. During transport the receptacle interfaces with the shear block attached to the transport skid.

A.1.2.1.3 Impact Limiters The front and rear impact limiters, shown in Drawings MP197HB-71-1001, -1002, -1003, -1008, and -1009, absorb energy during impact events by crushing balsa and redwood. The two impact limiters are identical. Each has an outside diameter of 126 inches and a height of 58 inches. The inner and outer shells are Type 304 stainless steel joined by radial gussets of the same material.

The gussets limit the stresses in the 0.25 in. thick stainless steel outer cylinder and end plates due to pressure differentials caused by elevation and temperature changes during normal transport.

The metal structure locates, supports, confines, and protects the wood energy absorption material.

Each impact limiter is attached to the NUHOMS-MP197HB cask by twelve (12) attachment bolts. The attachment bolts are designed to keep the impact limiters attached to the cask body during all normal conditions of transport and hypothetical accident conditions.

Each impact limiter is provided with seven fusible plugs that are designed to melt during a fire accident, thereby relieving excessive internal pressure. Each impact limiter has three hoist rings for handling, and two support angles for supporting the impact limiter in a vertical position during storage. The hoist rings are threaded into the impact limiter shell, while the support angles are welded to the shell. Prior to transport, the impact limiter hoist rings are removed and replaced with bolts.

An aluminum thermal shield is added to each impact limiter to reduce the impact limiter wood temperature. Due to the low maximum allowable heat load for the secondary containers, i.e.

5 kW compared to 32 kW for DSCs, secondary containers such as the RWC can be transported using the thermal shield designed for DSCs or the RWC specific thermal shield. The details of the thermal shield including the RWC-only option thermal shield are included in Drawing MP197HB-71-1002, -1003 and -1009.

NUH09.0101 A.1-5

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-i Appendix A.1.4.10 Drawings of Transport Packaging and DSCs TABLE OF CONTENTS A.1.4.10.1 NUHOMS-MP197HB Drawings........................................................................ A.1.4.10-2 A.1.4.10.2 NUHOMS 24PT4 DSC Drawings...................................................................... A.1.4.10-2 A.1.4.10.3 NUHOMS 32PT DSC Drawings........................................................................ A.1.4.10-3 A.1.4.10.4 NUHOMS 24PTH DSC Drawings..................................................................... A.1.4.10-3 A.1.4.10.5 NUHOMS 32PTH DSC Drawings..................................................................... A.1.4.10-4 A.1.4.10.6 NUHOMS 32PTH1 DSC Drawings................................................................... A.1.4.10-5 A.1.4.10.7 NUHOMS 37PTH DSC Drawings..................................................................... A.1.4.10-5 A.1.4.10.8 NUHOMS 61BT DSC Drawings........................................................................ A.1.4.10-6 A.1.4.10.9 NUHOMS 61BTH DSC Drawings..................................................................... A.1.4.10-6 A.1.4.10.10 NUHOMS 69BTH DSC Drawings..................................................................... A.1.4.10-7 A.1.4.10.11 Radioactive Waste Canister Drawing.................................................................. A.1.4.10-7

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-2 A.1.4.10.1 NUHOMS-MP197HB Drawings The following drawings for the NUHOMS-MP197HB Cask are included in Section A.1.4.10.1.

Drawing Number Title MP197HB-71-1001 Rev 5 NUHOMS-MP197HB Packaging Transport Configuration (2 sheets)

MP197HB-71-1002 Rev 9 NUHOMS-MP197HB Packaging Parts List (2 sheets)

MP197HB-71-1003 Rev 3 NUHOMS-MP197HB Packaging General Arrangement (1 sheet)

MP197HB-71-1004 Rev 7 NUHOMS-MP197HB Packaging Cask Body Assembly (1 sheet)

MP197HB-71-1005 Rev 9 NUHOMS-MP197HB Packaging Cask Body Details (3 sheets)

MP197HB-71-1006 Rev 5 NUHOMS-MP197HB Packaging Lid Assembly and Details (1 sheet)

MP197HB-71-1008 Rev 5 NUHOMS-MP197HB Packaging Impact Limiter Assembly (1 sheet)

MP197HB-71-1009 Rev 5 NUHOMS-MP197HB Packaging Impact Limiter Details (1 sheet)

MP197HB-71-1011 Rev 1 NUHOMS-MP197HB Packaging Transport Configuration Outer Sleeve With Fins Option (1 sheet)

MP197HB-71-1014 Rev 3 NUHOMS-MP197HB Packaging Internal Sleeve Design (1 sheet)

A.1.4.10.2 NUHOMS 24PT4 DSC Drawings The following drawings for the NUHOMS 24PT4 DSC are included in Section A.1.4.10.2.

Drawing Number Title NUH24PT4-71-1001 Rev 0 NUHOMS 24PT4 Transportable Canister For PWR Fuel Basket Assembly (5 sheets)

NUH24PT4-71-1002 Rev 0 NUHOMS 24PT4 Transportable Canister For PWR Fuel Main Assembly (8 sheets)

NUH24PT4-71-1003 Rev 0 NUHOMS 24PT4 Transportable Canister For PWR Fuel Failed Fuel Can (4 sheets)

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-3 A.1.4.10.3 NUHOMS 32PT DSC Drawings The following drawings for the NUHOMS 32PT DSC are included in Section A.1.4.10.3.

Drawing Number Title NUH32PT-71-1000 Rev 0 NUHOMS 32PT Transportable Canister For PWR Fuel Summary Dimensions (1 sheet)

NUH32PT-71-1001 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel Main Assembly (5 sheets)

NUH32PT-71-1002 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel Shell Assembly (3 sheets)

NUH32PT-71-1003 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel A Basket Assembly (16 Poison/16 Compartment Plates) (8 sheets)

NUH32PT-71-1004 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel Aluminum Transition Rail - R90 (2 sheets)

NUH32PT-71-1005 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel Aluminum Transition Rail - R45 (1 sheet)

NUH32PT-71-1006 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel A/B/C/D Basket Assembly (20 Poison/12 Compartment Plates) (6 sheets)

NUH32PT-71-1007 Rev 1 NUHOMS 32PT Transportable Canister For PWR Fuel A/B/C/D Basket Assembly (24 Poison/8 Compartment Plates) (8 sheets)

A.1.4.10.4 NUHOMS 24PTH DSC Drawings The following drawings for the NUHOMS 24PTH DSC are included in Section A.1.4.10.4.

Drawing Number Title NUH24PTH-71-1000 Rev 1 NUHOMS 24PTH Transportable Canister For PWR Fuel Main Assembly (5 sheets)

NUH24PTH-71-1001 Rev 1 NUHOMS 24PTH Transportable Canister For PWR Fuel Basket-Shell Assembly (4 sheets)

NUH24PTH-71-1002 Rev 1 NUHOMS 24PTH Transportable Canister For PWR Fuel Shell Assembly (4 sheets)

NUH24PTH-71-1003 Rev 2 NUHOMS 24PTH Transportable Canister For PWR Fuel Basket Assembly (8 sheets)

NUH24PTH-71-1004 Rev 1 NUHOMS 24PTH Transportable Canister For PWR Fuel Transition Rails (4 sheets)

NUH24PTH-71-1008 Rev 1 NUHOMS 24PTHF Transportable Canister For PWR Fuel Failed Fuel Can (2 sheets)

NUH24PTH-71-1009 Rev 1 NUHOMS 24PTHF Transportable Canister For PWR Fuel Basket Assembly (8 sheets)

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-4 A.1.4.10.5 NUHOMS 32PTH DSC Drawings The following drawings for the NUHOMS 32PTH DSC and the 32PTH Type 1 DSC are included in Section A.1.4.10.5.

Drawing Number Title NUH32PTH-71-1001 Rev 2 NUHOMS32PTH Transportable Canister for PWR Fuel Parts List (1 Sheet)

NUH32PTH-71-1002 Rev 1 NUHOMS32PTH Transportable Canister for PWR Fuel Main Assembly (1 Sheet)

NUH32PTH-71-1003 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Siphon Pipe Details (1 Sheet)

NUH32PTH-71-1004 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Inner Top Cover Details (2 sheets)

NUH32PTH-71-1005 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Outer Top Cover Details (1 Sheet)

NUH32PTH-71-1006 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Shell Assembly (1 Sheet)

NUH32PTH-71-1007 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Shell Bottom Details (1 Sheet)

NUH32PTH-71-1008 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Grapple Ring Details (1 Sheet)

NUH32PTH-71-1009 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Basket Assembly (1 Sheet)

NUH32PTH-71-1010 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Basket Assembly Details (1 Sheet)

NUH32PTH-71-1011 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Basket Assembly Details (1 Sheet)

NUH32PTH-71-1012 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Basket Assembly - Details (1 Sheet)

NUH32PTH-71-1013 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Basket Rail A180 (1 Sheet)

NUH32PTH-71-1014 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Basket Rail A90 (1 Sheet)

NUH32PTH-71-1015 Rev 0 NUHOMS32PTH Transportable Canister for PWR Fuel Damaged Fuel End Caps (1 Sheet)

NUH32PTH Type 1-71-1000 Rev 1 NUHOMS 32PTH Type 1 Transportable Canister For PWR Fuel Main Assembly (4 sheets)

NUH32PTH Type 1-71-1001 Rev 2 NUHOMS 32PTH Type 1 Transportable Canister For PWR Fuel Basket Shell Assembly (4 sheets)

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-5 NUH32PTH Type 1-71-1002 Rev 1 NUHOMS 32PTH Type 1 Transportable Canister For PWR Fuel Shell Assembly (4 sheets)

NUH32PTH Type 1-71-1003 Rev 2 NUHOMS 32PTH Type 1 Transportable Canister For PWR Fuel Basket Assembly (7 sheets)

NUH32PTH Type 1-71-1004 Rev 2 NUHOMS 32PTH Type 1 Transportable Canister For PWR Fuel Transition Rails (4 sheets)

NUH32PTH Type 1-71-1010 Rev 1 NUHOMS 32PTH Type 1 Transportable Canister For PWR Fuel Alternate Top Closure (6 sheets)

A.1.4.10.6 NUHOMS 32PTH1 DSC Drawings The following drawings for the NUHOMS 32PTH1 DSC are included in Section A.1.4.10.6.

Drawing Number Title NUH32PTH1-71-1000 Rev 1 NUHOMS 32PTH1 Transportable Canister For PWR Fuel Main Assembly (4 sheets)

NUH32PTH1-71-1001 Rev 1 NUHOMS 32PTH1 Transportable Canister For PWR Fuel Basket Shell Assembly (5 sheets)

NUH32PTH1-71-1002 Rev 1 NUHOMS 32PTH1 Transportable Canister For PWR Fuel Shell Assembly (4 sheets)

NUH32PTH1-71-1003 Rev 2 NUHOMS 32PTH1 Transportable Canister For PWR Fuel Basket Assembly (8 sheets)

NUH32PTH1-71-1004 Rev 1 NUHOMS 32PTH1 Transportable Canister For PWR Fuel Transition Rails (7 sheets)

NUH32PTH1-71-1010 Rev 1 NUHOMS 32PTH1 Transportable Canister For PWR Fuel Alternate Top Closure (6 sheets)

A.1.4.10.7 NUHOMS 37PTH DSC Drawings The following drawings for the NUHOMS 37PTH DSC are included in Section A.1.4.10.7.

Drawing Number Title NUH37PTH-71-1001 Rev 2 NUHOMS 37PTH Transportable Canister For PWR Fuel Main Assembly (4 sheets)

NUH37PTH-71-1002 Rev 3 NUHOMS 37PTH Transportable Canister For PWR Fuel Basket Shell Assembly (5 sheets)

NUH37PTH-71-1003 Rev 3 NUHOMS 37PTH Transportable Canister For PWR Fuel Shell Assembly (4 sheets)

NUH37PTH-71-1004 Rev 3 NUHOMS 37PTH Transportable Canister For PWR Fuel Alternate Top Closure (6 sheets)

NUH37PTH-71-1011 Rev 2 NUHOMS 37PTH Transportable Canister For PWR Fuel Basket Assembly (7 sheets)

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-6 Drawing Number Title NUH37PTH-71-1012 Rev 1 NUHOMS 37PTH Transportable Canister For PWR Fuel Transition Rails (7 sheets)

NUH37PTH-71-1015 Rev 0 NUHOMS 37PTH Transportable Canister For PWR Fuel Damaged Fuel End Caps (1 sheet)

A.1.4.10.8 NUHOMS 61BT DSC Drawings The following drawings for the NUHOMS 61BT DSC are included in Section A.1.4.10.8.

Drawing Number Title NUH61BT-71-1000 Rev 1 NUHOMS 61BT Transportable Canister For BWR Fuel Parts List (1 sheet)

NUH61BT-71-1001 Rev 1 NUHOMS 61BT Transportable Canister For BWR Fuel Basket Assembly (1 sheet)

NUH61BT-71-1002 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel Basket Details (1 sheet)

NUH61BT-71-1003 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel General Assembly (1 sheet)

NUH61BT-71-1004 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel General Assembly (1 sheet)

NUH61BT-71-1005 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel Shell Assembly (1 sheet)

NUH61BT-71-1006 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel Shell Assembly (1 sheet)

NUH61BT-71-1007 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel Canister Details (1 sheet)

NUH61BT-71-1008 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel Canister Details (1 sheet)

NUH61BT-71-1009 Rev 0 NUHOMS 61BT Transportable Canister For BWR Fuel Basket Details (1 sheet)

NUH61BT-71-1010 Rev 1 NUHOMS 61BT Transportable Canister For BWR Fuel Additional Basket Details - Damaged Fuel (4 sheets)

A.1.4.10.9 NUHOMS 61BTH DSC Drawings The following drawings for the NUHOMS 61BTH DSC are included in Section A.1.4.10.9.

Drawing Number Title NUH61BTH-71-1000 Rev 1 NUHOMS 61BTH Type 1 Transportable Canister For BWR Fuel Main Assembly (5 sheets)

NUH61BTH-71-1100 Rev 2 NUHOMS 61BTH Type 2 Transportable Canister For BWR Fuel Main Assembly (7 sheets)

NUH61BTH-71-1101 Rev 1 NUHOMS 61BTH Type 2 Transportable Canister For BWR Fuel Shell Assembly (2 sheets)

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.1.4.10-7 NUH61BTH-71-1102 Rev 2 NUHOMS 61BTH Type 2 Transportable Canister For BWR Fuel Basket Assembly (8 sheets)

NUH61BTH-71-1103 Rev 1 NUHOMS 61BTH Type 2 Transportable Canister For BWR Fuel Transition Rails (2 sheets)

NUH61BTH-71-1104 Rev 1 NUHOMS 61BTH Type 2 Transportable Canister For BWR Fuel Damaged Fuel End Caps (1 sheet)

NUH61BTH-71-1105 Rev 1 NUHOMS 61BTHF Type 2 Transportable Canister For BWR Fuel Failed Fuel Can (2 sheets)

NUH61BTH-71-1106 Rev 2 NUHOMS 61BTH Type 2 Transportable Canister For BWR Fuel Top Grid Assembly Alternate 3 (2 sheets)

A.1.4.10.10 NUHOMS 69BTH DSC Drawings The following drawings for the NUHOMS 69BTH DSC are included in Section A.1.4.10.10.

Drawing Number Title NUH69BTH-71-1001 Rev 3 NUHOMS 69BTH Transportable Canister For BWR Fuel Main Assembly (4 sheets)

NUH69BTH-71-1002 Rev 3 NUHOMS 69BTH Transportable Canister For BWR Fuel Basket -

Shell Assembly (4 sheets)

NUH69BTH-71-1003 Rev 3 NUHOMS 69BTH Transportable Canister For BWR Fuel Shell Assembly (4 sheets)

NUH69BTH-71-1004 Rev 6 NUHOMS 69BTH Transportable Canister For BWR Fuel Alternate Top Closure (7 sheets)

NUH69BTH-71-1011 Rev 3 NUHOMS 69BTH Transportable Canister For BWR Fuel Basket Assembly (5 sheets)

NUH69BTH-71-1012 Rev 4 NUHOMS 69BTH Transportable Canister For BWR Fuel Transition Rail Assembly And Details (6 sheets)

NUH69BTH-71-1013 Rev 4 NUHOMS 69BTH Transportable Canister For BWR Fuel Holddown Ring Assembly (2 sheets)

NUH69BTH-71-1014 Rev 2 NUHOMS 69BTH Transportable Canister For BWR Fuel Damaged Fuel Modification (1 sheet)

NUH69BTH-71-1015 Rev 2 NUHOMS 69BTH Transportable Canister For BWR Fuel Damaged Fuel End Caps (1 sheet)

A.1.4.10.11 Radioactive Waste Canister Drawing The following drawing for the Radioactive Waste Canister is included in Section A.1.4.10.11.

Drawing Number Title NUHRWC-71-1001 Rev 5 NUHOMS System Radioactive Waste Canister (2 sheets)

Proprietary and Security Related Information for Drawing MP197HB-71-1002 Rev 9 Withheld Pursuant to 10 CFR 2.390

Proprietary and Security Related Information for Drawing MP197HB-71-1008 Rev 5 Withheld Pursuant to 10 CFR 2.390

Proprietary and Security Related Information for Drawing MP197HB-71-1009 Rev 5 Withheld Pursuant to 10 CFR 2.390

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.2-2 Appendix A.2.13.3 NUHOMS-MP197HB Cask Lead Slump and Containment Boundary Buckling Analysis Appendix A.2.13.4 NUHOMS-MP197HB Structural Analysis of the Shield Shell Appendix A.2.13.5 NUHOMS-MP197HB Cask Lifting and Tie-Down Devices Structural Evaluation Appendix A.2.13.6 NUHOMS-MP197HB Cask Containment Boundary Fatigue Evaluation Appendix A.2.13.7 NUHOMS-MP197HB DSC (Shell Assembly) Structural Evaluation Appendix A.2.13.8 NUHOMS-MP197HB DSC (Basket) Structural Evaluation Appendix A.2.13.9 NUHOMS-MP197HB Dynamic Load Factor Determination Appendix A.2.13.10 NUHOMS-MP197HB Transport Package Thermal Expansion Evaluation Appendix A.2.13.11 NUHOMS-MP197HB Evaluation of Fuel Assembly Appendix A.2.13.12 MP197HB Transport Package Impact Limiter Analysis using LS-DYNA Appendix A.2.13.13 NUHOMS-MP197HB ASME Code Alternatives Appendix A.2.13.14 MP197HB Lid Closure Evaluation Due to Delayed Impact Appendix A.2.13.15 NUHOMS-MP197HB DSC Shell Buckling Analysis under Deep Water Immersion and Fatigue Evaluation during Storage Appendix A.2.13.16 NUHOMS -MP197HB Package Impact Sensitivity Analyses Appendix A.2.13.17 NUHOMS -MP197HB Cask Puncture Evaluation Using LS-DYNA Appendix A.2.13.18 NUHOMS-MP197HB Package Impact Limiter Bolt Tunnel Sensitivity Analyses A.2.1.1.1 Transportation Package (Cask)

Drawing MP197HB-71-1001 shows the overall transport configuration of the NUHOMS-MP197HB packaging. Drawings MP197HB-71-1002 and 1003 show the parts list and the general arrangement, respectively, of the NUHOMS-MP197HB packaging. Drawing MP197HB-71-1004 shows the cask body assembly. Drawings MP197HB-71-1005 and -1006 show the cask body and lid assembly and details. Drawing MP197HB-71-1007 presents the regulatory plate. Drawings MP197HB-71-1008 and -1009 provide the assembly and details of the impact limiter. The external fin and internal sleeve are shown on drawings MP197HB 1011 and -1014. ASME Code compliance and alternatives are provided in Section A.2.1.4 and Appendix A.2.13.13.

The shell or cask body cylinder assembly is an open ended (at the top) cylindrical unit with an integral closed bottom end. This assembly consists of concentric inner and outer shells, both SA-203 Gr E, welded to a massive closure flange (SA-350 LF3) at the lid end and a flat steel plate (SA-350 LF3) at the bottom end. The closure lid material is SA-350 LF3 or SA-203 Gr E. The

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 A.2.7 Hypothetical Accident Conditions Overview This section describes the response of the NUHOMS-MP197HB package to the hypothetical accident condition loads specified by 10CFR71.73. The design criteria established for the NUHOMS-MP197HB packaging for the HAC are described in Section A.2.1.2. These criteria are selected to ensure that the packaging performance standards specified by 10CFR71.51 are satisfied.

The presentation of the HAC analyses and results is accomplished in the same manner as that used for the NCT analysis. Table A.2-9 provides an overview of the performance evaluations presented in this section. The detailed analyses of the various packaging components under different loading conditions are presented in the Appendices to this Chapter. The limiting results for the specified HAC load are taken from the Appendices and summarized here along with comparisons with the established design criteria. In all cases, the acceptability of the NUHOMS-MP197HB packaging design with respect to HAC loads is demonstrated.

An analytical evaluation of the impact limiters is presented in Appendix A.2.13.12, supplemented by Appendix A.2.13.18. The analytical results are used to determine the baseline g loads used in the cask, canister and basket structural evaluations.

Reporting Method for Containment Vessel Stresses Appendix A.2.13.1 provides the detailed description of the structural analyses of the NUHOMS-MP197HB cask body. Table A.2-9 provides a matrix of the loads that were analyzed to determine the cask body stresses for the hypothetical accident conditions. The combined load cases for the accident conditions of transport were performed in load cases 27 -

42, as shown in Table A.2-9. The stress results are presented in Table A.2.13.1-32 to A.2.13.1-47 of Appendix A.2.13.1. Refer to Section A.2.13.1.10 of Appendix A.2.13.1 for the method of obtaining the stress results from the ANSYS runs.

A.2.7.1 Free Drop The response of the NUHOMS-MP197HB Packaging is evaluated for a free drop from a height of 30 feet onto an unyielding surface at various orientations. The inertial loading applied to the NUHOMS-MP197HB components is determined in the dynamic analysis presented in Appendix A.2.13.12.

The stresses in the cask body are reported for the following drop orientations:

End drop onto bottom end End drop onto lid end Side drop C. G. over corner drop on bottom end C. G. over corner drop on lid end 10° slap down impact on lid end 10° slap down impact on bottom end NUH09.0101 A.2-29

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 shown to meet the ASME Code allowable stress limits for plastic analysis, as shown in Table A.2.13.1-45.

A.2.7.1.6 Lid and Ram Access Cover Plate Bolts The lid bolts are analyzed for the following loadings: operating pre-load, gasket seating load, internal pressure, temperature changes, impact loads, and puncture loads. The analysis is based on NUREG/CR 6007 [16].

The lid bolt preload is calculated to withstand the worst case load combination and to maintain a clamping (compressive) force on the closure joint. Based upon the load combination results (see Appendix A.2.13.2, Section A.2.13.2.9) it is shown that a positive (compressive) load is maintained on the clamped joint for all load combinations except for the accident condition impact plus pressure load. A more detailed finite element analysis is performed in Section A.2.13.2 7 of Appendix A.2.13.2. It is concluded that there is no decompression of the seal during the accident condition impact plus pressure loading condition. Since the seal exists all along the circumference of the cask lid seal, the internal contents will not leak during the worst case loading condition.

A summary of the calculated stresses is listed in the Table A.2.13.2-7 of Appendix A.2.13.2. The lid bolt evaluation due to delayed impact is presented in Appendix A.2.13.14.

The ram access cover plate bolts are also evaluated (Section A.2.13.2.9) using the same methodology as described above. The results show the bolt loads are bounded by the preload and that the bolt stresses remain below allowables.

A.2.7.1.7 Impact Limiter Attachments The impact limiters must remain attached to the cask body before, during, and after each HAC drop. The limiting loading condition for the impact limiter attachments is the secondary impact (slap-down) associated with the 10° slap down 30 foot drop. This loading condition applies the greatest separating moment between the impact limiter and cask body interface. Although this loading condition is not limiting with respect to any other cask component, an evaluation of the attachments is performed to demonstrate that the effected impact limiter remains in place to insulate the cask during the subsequent hypothetical thermal accident.

The analysis and results are provided in detail in Section A.2.13.12.11 of Appendix A.2.13.12, supplemented by Appendix A.2.13.18.

The analysis concludes that the impact limiter attachment design is sufficiently strong to ensure that the impact limiters remain attached to the cask body during and following all HAC loads.

A.2.7.1.8 Cask Lead Slump and Containment Buckling Analyses In the event of a drop of the NUHOMS-MP197HB package, permanent deformation of the lead gamma shield may result for certain impact orientations. An analysis is performed to evaluate the inner cylindrical shell stability and lead slump when subject to the end drop impact loads.

NUH09.0101 A.2-32

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 A.2.13 Appendices The detailed structural analyses of the NUHOMS-MP197HB packaging are included in the following appendices:

Appendix A.2.13.1 NUHOMS-MP197HB Cask Body Structural Evaluation Appendix A.2.13.2 NUHOMS-MP197HB Cask Lid Bolt/Ram Access Closure Plate Bolt Analyses Appendix A.2.13.3 NUHOMS-MP197HB Cask Lead Slump and Containment Boundary Buckling Analysis Appendix A.2.13.4 NUHOMS-MP197HB Structural Analysis of the Shield Shell Appendix A.2.13.5 NUHOMS-MP197HB Cask Lifting and Tie-Down Devices Structural Evaluation Appendix A.2.13.6 NUHOMS-MP197HB Cask Containment Boundary Fatigue Evaluation Appendix A.2.13.7 NUHOMS-MP197HB DSC (Shell Assembly) Structural Evaluation Appendix A.2.13.8 NUHOMS-MP197HB DSC (Basket) Structural Evaluation Appendix A.2.13.9 NUHOMS-MP197HB Dynamic Load Factor Determination Appendix A.2.13.10 NUHOMS-MP197HB Transport Package Thermal Expansion Evaluation Appendix A.2.13.11 NUHOMS-MP197HB Evaluation of Fuel Assembly Appendix A.2.13.12 MP197HB Transport Package Impact Limiter Analysis using LS-DYNA Appendix A.2.13.13 NUHOMS-MP197HB ASME Code Alternatives Appendix A.2.13.14 MP197HB Lid Closure Evaluation Due to Delayed Impact Appendix A.2.13.15 NUHOMS-MP197HB DSC Shell Buckling Analysis under Deep Water Immersion and Fatigue Evaluation during Storage Appendix A.2.13.16 NUHOMS -MP197HB Package Impact Sensitivity Analyses Appendix A.2.13.17 NUHOMS -MP197HB Cask Puncture Evaluation Using LS-DYNA Appendix A.2.13.18 NUHOMS-MP197HB Package Impact Limiter Bolt Tunnel Sensitivity Analyses NUH09.0101 A.2-49

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.2.13.12-24 The minimum threaded length is 2.0 in, which ensures an engagement length greater than 1.86 in since the bolt length is sized to ensure the bolt threads are completely engaged with the thread insert in the attachment block.

A.2.13.12.11.3 Bolt Torque A bolt tensile stress t of 15,000 psi is assumed.

lb 075 21 405 1

000 15

=

x

=

x

=

t t

a A

F

Where At is the bolt tensile stress area.

ft.lb 356 in.lb 268

,4 075 21 50 1

135 0

=

=

x x

=

x x

=

a b

F D

K Q

Where Fa is the bolt force, Q is the applied torque, K is the nut factor, and Db the nominal bolt diameter at the threads.

A bolt torque of 350 to 375 ft.lb is specified.

For a bolt torque of 350 ft.lb:

lb 741 20 50 1

135 0

12 350

=

x x

=

x

=

b a

D K

Q F

For a bolt torque of 375 ft.lb:

lb 222 22 50 1

135 0

12 375

=

x x

=

x

=

b a

D K

Q F

Therefore, the maximum tensile stress in the bolt is:

ksi 8

15 405 1

222 22

=

=

s This is less than the yield stress of the bolts, 144 ksi.

A.2.13.12.11.4 Conclusions The stresses are summarized in Table A.2.13.12-10. All of the stresses calculated for the impact limiter bolts, attachment bolt blocks, and lifting lugs are less than the allowable stresses regardless of the method used. Additional confirmatory analysis is performed using a detailed LS-DYNA model of the attachment bolts and the bolt tunnels is provided in Appendix A.2.13.16 and A.2.13.18. Therefore, the NUHOMS - MP197HB impact limiter attachments are structurally adequate.

The required engagement length is 1.86 in, which is less than the threaded length of 2.0 in.

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 Page A.2.13.18-i Appendix A.2.13.18 NUHOMS-MP197HB Package Impact Limiter Bolt Tunnel Sensitivity Analyses TABLE OF CONTENTS A.2.13.18.1 LS-DYNA Model Description (for Sensitivity Analyses)..................... A.2.13.18-1 A.2.13.18.2 Analysis Results..................................................................................... A.2.13.18-2 LIST OF TABLES Table A.2.13.18-1 Summary of Bolt Stresses and Combined Loading Stress Ratios for the Detailed Bolt Model Sensitivity Study............... A.2.13.18-3 LIST OF FIGURES Figure A.2.13.18-1 Bolt Forces Around Top and Bottom Impact Limiters for 10º Slap Down Drop........................................................................ A.2.13.18-4

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 Page A.2.13.18-1 Appendix A.2.13.18 is newly added as a result of CoC Revision 10.

Appendix A.2.13.18 NUHOMS-MP197HB Package Impact Bolt Tunnel Sensitivity Analyses Sensitivity studies are performed to address the impact of the increased ID of the inner bolt tunnel (SAR Drawing MP197HB-71-1002, Part #23V) on the impact limiter attachment bolts.

The following analyses are performed:

Sensitivity Analysis #1 Impact Limiter Bounding Case: The impact limiter attachment bolts are evaluated in Appendix A.2.13.12.11. The worst loading occurs during the second impact of a shallow angle slap-down drop. This case is reevaluated increasing the ID of the inner bolt tunnel. The bolt forces are compared to the original analysis.

Sensitivity Analysis #2 Detailed Bolt Model Analysis: The impact limiter bolts sensitivity analysis using detailed bolt model is performed in Appendix A.2.13.16. The bolt stress results are compared to the original analysis. This case is reevaluated increasing the ID of the inner bolt tunnel. The bolt combined stress ratios are compared to the original analysis.

A.2.13.18.1 LS-DYNA Model Description (for Sensitivity Analyses)

The LS-DYNA models which were originally developed for use in the delayed impact of a shallow angle slap-down drop were modified for the two Sensitivity Analyses described above.

The details about the LS-DYNA models are presented in Appendix A.2.13.12 and A.2.13.16.

The modifications to the LS-DYNA models are noted below.

Based on Note 4 in Drawing MP197HB-71-1009, the inner diameter Ø1.75" of item 23V may be enlarged up to Ø2.00" over a length of up to 8" on the cask side. However, in Sensitivity Analysis # 1 and 2, conservatively, the entire length of the Inner Bolt Tunnel diameter is enlarged. In addition, Appendix A.2.13.16 model evaluated a smaller bolt shank diameter of 1.125 which is also updated to match the actual bolt shank diameter of 1.293 for Sensitivity Analysis # 2.

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 Page A.2.13.18-2 Appendix A.2.13.18 is newly added as a result of CoC Revision 10.

A.2.13.18.2 Analysis Results A.2.13.18.2.1 Sensitivity Analysis #1 - Impact Limiter Bounding Case The sensitivity analysis bolt forces at various positions around the impact limiter are plotted for the bounding Slap Down 10º case in Figure A.2.13.18-1. For the original analysis the bolt forces are plotted in Figure A.2.13.12-51. The results show that there is no significant adverse effect on the bolt tensile forces as a result of increase in the bolt tunnel ID. The maximum tensile force for the bolt was considered to be 210,000 lb in the bolt stress evaluation in A.2.13.12.11.1, which remains bounding.

A.2.13.18.2.2 Sensitivity Analysis #2 - Detailed Bolt Model Analysis The combined bolt stress results for the detailed bolt model sensitivity analysis are shown in Table A.2.13.18-1. The bolt stress results indicate that all of the attachment bolts on the bottom limiter (first impact) and 8 attachment bolts on the top limiter (second impact) remain below allowable stress values. The combined ratio results conservatively use the peak axial and shear forces throughout the length of each bolt, even though they may occur at different points in time and at different locations along the bolt. This ensures that the impact limiters will remain attached to the cask body during the worst-case 30-foot drop accident condition.

The results show that there is no significant adverse effect on the impact limiter bolts as a result of increase in the bolt tunnel ID.

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 Page A.2.13.18-3 Appendix A.2.13.18 is newly added as a result of CoC Revision 10.

Table A.2.13.18-1 Summary of Bolt Stresses and Combined Loading Stress Ratios for the Detailed Bolt Model Sensitivity Study Bolt Axial Stress (psi)

Axial Allowable (psi)

Axial Ratio Shear Stress (psi)

Shear Allowable (psi)

Shear Ratio Combined Ratio Strain Min Ave Max Bottom 0º 47,770 140,700 0.34 57,100 84,420 0.68 0.76 0.00 0.02 0.05 30º 40,200 140,700 0.29 57,500 84,420 0.68 0.74 0.00 0.00 0.02 60º 53,300 140,700 0.38 70,500 84,420 0.84 0.92 0.00 0.00 0.00 90º 49,000 140,700 0.35 63,400 84,420 0.75 0.83 0.00 0.00 0.00 120º 46,800 140,700 0.33 29,400 84,420 0.35 0.48 0.00 0.00 0.00 150º 34,100 140,700 0.24 43,900 84,420 0.52 0.57 0.00 0.00 0.01 180º 29,000 140,700 0.21 69,300 84,420 0.82 0.85 0.00 0.01 0.02 Top 0º 118,000 140,700 0.84 31,400 84,420 0.37 0.92 0.00 0.03 0.07 30º 116,000 140,700 0.82 57,800 84,420 0.68 1.07 0.01 0.02 0.06 60º 137,000 140,700 0.97 60,000 84,420 0.71 1.21 0.06 0.10 0.15 90º 70,700 140,700 0.50 71,800 84,420 0.85 0.99 0.01 0.01 0.02 120º 28,000 140,700 0.20 44,900 84,420 0.53 0.57 0.00 0.00 0.00 150º 13,600 140,700 0.10 48,200 84,420 0.57 0.58 0.00 0.02 0.07 180º 13,100 140,700 0.09 60,500 84,420 0.72 0.72 0.00 0.02 0.05

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 Page A.2.13.18-4 Appendix A.2.13.18 is newly added as a result of CoC Revision 10.

Figure A.2.13.18-1 Bolt Forces Around Top and Bottom Impact Limiters for 10º Slap Down Drop

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.7-2

1.

Remove the impact limiters from the cask.

2.

NOT USED.

3.

Remove the transportation skid personnel barrier and tie down assembly.

4.

Take contamination smears on the outside surfaces of the cask. If necessary, decontaminate the cask.

5.

Elastomer O-ring seals may be reused. Metallic seals shall be discarded after each use.

6.

Install the front and rear trunnions, if required, and torque the bolts as specified in Drawing MP197HB-71-1002, Chapter A.1, Appendix A.1.4.10.1 following the torquing sequence shown in Figure A.7-1.

7.

Lift the cask and place it on the onsite transfer trailer or upending frame, or lift the cask/transport skid and place them in the appropriate location.

8.

NOT USED.

9.

If transporting a DSC, verify that each impact limiter has been configured with the appropriate Thermal Shield. The RWC-Only option shall not be used with DSC shipments.

10.

If transporting any of the smaller diameter DSC models (NUHOMS-24PT4, 32PT, 24PTH, 61BT, or 61BTH) or an RWC, verify that the MP197HB cask has been fitted with an internal sleeve. This step, if required, can be performed at any time prior to placing the DSC or RWC in the cask.

11.

If transporting a NUHOMS-69BTH DSC with heat load greater than 26 kW, verify that the removable external aluminum fins are available to be fitted to the cask after the cask is closed (Refer to Drawing MP197HB-71-1011 provided in Appendix A.1.4.10.1). Note that fins are not required to meet the 10 CFR 71 requirements and are optional.

12.

For a specific DSC model to be loaded inside the MP197HB cask, verify the canister/basket type (A, B, C, D, E, or F as applicable) is appropriate for the fuel to be transported.

13.

The candidate intact, damaged and failed fuel assemblies to be transported in a specific DSC model must be evaluated (by plant records or other means) to verify that they meet the criteria of the applicable fuel specification as listed in Table A.7-2a.

14.

For the transportation of fuel within the NUHOMS-32PT, 24PTH, 32PTH, 32PTH1, or 37PTH DSCs where burnup credit is employed for criticality safety, additional administrative controls to prevent misloading are also outlined in the applicable appendices of this chapter.

A.7.1.2 NUHOMS-MP197HB Cask Wet Loading NOTE: The wet loading procedure described in this section is applicable only when using the MP197HB cask for loading fuel from a spent fuel pool into any one of the DSCs listed in Chapter A.1 or for loading irradiated waste into a RWC. This section also provides steps for closure of the DSC/RWC.

Site specific conditions and requirements may require the use of different equipment and ordering of steps than those described below to accomplish the same objectives or acceptance criteria which must be met to ensure the integrity of the package.

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.7-12 A.7.4.2 Pre-shipment Verification Leakage Testing of the NUHOMS-MP197HB Cask Containment Boundary The procedure for assembly verification leakage testing of the cask containment boundary prior to shipment is given in this section. Assembly verification leakage testing shall conform to the requirements of ANSI N14.5 [1] or ISO -12807 [11]. A flow chart of the assembly verification leakage test for DSC shipments is provided in Figure A.7-2. The order in which the leakage tests of the various seals are performed may vary. If more than one leakage detector is available then more than one seal may be tested at a time. Personnel performing the leakage test shall be specifically trained in leakage testing in accordance with SNT-TC-1A [7]. The acceptance criterion for pre-shipment leakage rate testing shall be either (a) a leakage rate of not more than the reference air leakage rate, or (2) no detected leakage when tested to a sensitivity of at least 10-3 ref-cm3/s.

The following steps present one method of performing the pre-shipment verification leakage testing. Alternate methods and order of testing are acceptable as long as the above criteria is satisfied for the MP197HB containment boundary seals.

1.

Remove the port plugs from the lid test port, vent port, drain port, and the bottom test port.

2.

Attach a suitable vacuum pump to the cask lid test port.

3.

Evacuate the volume between the lid O-rings and perform the pre-shipment leak test in accordance with Section A.8.2.2. If either O-ring was replaced, the maintenance leak test in Section A.8.2.2 shall be performed.

4.

After meeting the leak test criteria, disconnect the vacuum pump and either tighten the port bolt, or verify it has been tightened, in accordance with Drawing MP197HB-71-1002 in Chapter A.1.

5.

Install the port plug.

6.

Repeat steps 2-5 for the bottom test port.

7.

Attach a suitable vacuum pump to the vent port.

8.

Either tighten the port bolt, of verify it has been tightened, in accordance with Drawing MP197HB-71-1002 in Chapter A.1.

9.

Evacuate the volume outside of the closed port bolt seal and perform the pre-shipment leak test in accordance with Section A.8.2.2. If the O-ring was replaced, the maintenance leak test in Section A.8.2.2 shall be performed.

10.

After meeting the leak test criteria, disconnect the vacuum pump and install the port plug.

11.

Repeat steps 7-10 for the drain port.

This concludes the assembly verification leakage test procedure.

MP197 Transportation Packaging Safety Analysis Report Rev. 20, 09/19 NUH09.0101 A.7-18 Table A.7-2a Applicable Fuel Specification for Various DSCs DSC MODEL Applicable Fuel Specification from Chapter A.1 NUHOMS-24PT4 Tables A.1.4.1-1 and A.1.4.1-2 NUHOMS-32PT Table A.1.4.2-2 NUHOMS-24PTH Table A.1.4.3-2 NUHOMS-32PTH Table A.1.4.4-2 NUHOMS-32PTH1 Table A.1.4.5-2 NUHOMS-37PTH Table A.1.4.6-2 NUHOMS-61BT Table A.1.4.7-2 NUHOMS-61BTH Table A.1.4.8-2 NUHOMS-69BTH Table A.1.4.9-1 Table A.7-2b Applicable Content Specification for RWC Type and Form of Material The NUHOMS-MP197HB packaging is designed for shipment of various types of irradiated and contaminated reactor hardware. The payload will vary from shipment to shipment. Typical composition of the payload consists of the following components either individually or in combinations:

1.

BWR Control Rod Blades

2.

BWR Local Power Range Monitors (LPRMs)

3.

BWR Fuel Channels

4.

BWR Poison Curtains

5.

PWR Burnable Poison Rod Assemblies (BPRAs)

6.

PWR and BWR Reactor Vessel and Internals Decay Heat load 5 kW Loading Components with high specific activity are generally placed near the center of the RWC. For each shipment, the RWC is normally filled to capacity, which prevents shifting of the contents during transport. If the RWC is not full, appropriate component spacers or shoring is used to prevent significant movement of the contents.

Maximum Quantity of Material per Package (a)

For containment, the quantity of radioactive material is limited to a maximum of 8, 182 A2. The radioactive material is primarily in the form of neutron activated metals, or metal oxides in solid form. Surface contamination may also be present on the irradiated components. When a wet load procedure (i.e., in-pool) is followed for cask loading, the cask cavity and RWC are drained and dried to ensure that there are no free liquids in the package during transport.

(b)

The NUHOMS-MP197HB packaging is designed to transport a payload of up to 56.0 tons of dry irradiated and/or contaminated non-fuel bearing solid materials in the RWC. The center of gravity (CG) of the loaded NUHOMS-MP197HB package is to be 102 +/- 4 inches from the bottom of the cask.

(c)

The quantity of radioactive material is limited to a maximum of 90,000 Ci of cobalt-60 or equivalent, except for MP197HB Unit 01 where the limit is reduce to 70,000 Ci of cobalt-60 or equivalent. Equivalent activity limits as a function of gamma energy for isotopes other than Co-60 are shown in Table A.7-2c for the 90,000 Ci limit and Table A.7-2d for the 70,000 Ci limit.

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