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{{#Wiki_filter:APPENDIX 6.1
{{#Wiki_filter:APPENDIX 6.1 NUCLEAR CRITICALITY SAFETY EVALUATION:
9975 SHIPPING PACKAGE WITH PLUTONIUM OXIDE CONTENTS FOR NRC SAFETY ANALYSIS REPORT Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 1 of 90


NUCLEAR CRITICALITY SAFETY EVALUATION:
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9975 SHIPPING PACKAGE WITH PLUTONIUM OXIDE CONTENTS FOR NRC SAFETY ANALYSIS REPORT


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9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 2 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 2 of 87 DISCLAIMER This document was prepared by Savannah River Nuclear Solutions LLC (SRNS), under contract with the United States Department of Energy (DOE).
Release to and Use by Third Parties. As it pertains to releases of this document to third parties, and the use of or reference to this document by such third parties in whole or in part, neither SRNS, DOE, nor their respective officers, directors, employees, agents, consultants or personal services contractors (i) make any warranty, expressed or implied, (ii) assume any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product or process disclosed herein or (iii) represent that use of the same will not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trademark, name, manufacture or otherwise, does not necessarily constitute or imply endorsement, recommendation, or favoring of the same by SRNS, DOE or their respective officers, directors, employees, agents, consultants or personal services contractors. The views and opinions of the authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 4 of 90


DISCLAIMER This document was prepared by Savannah River Nuclear Solutions LLC (SRNS), under contract with the United States Department of Energy (DOE).
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 3 of 87 REVISION  
Release to and Use by Third Parties. As it pertains to releases of this document to third parties, and the use of or reference to this document by such third parties in whole or in part, neither SRNS, DOE, nor their respective officers, directors, employees, agents, consultants or personal services contractors (i) make any warranty, expressed or implied, (ii) assume any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product or process disclosed herein or (iii) represent that use of the same will not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trademark, name, manufacture or otherwise, does not necessarily constitute or imply endorsement, recommendation, or favoring of the same by SRNS, DOE or their respective officers, directors, employees, agents, consultants or pers onal services contractors. The views and opinions of the authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 3 of 87
 
REVISION  


==SUMMARY==
==SUMMARY==
Rev. # Author Changes Date 0 M. D. Harris Initial issuance. March 2013 1 M. D. Harris Address flooding the primary containment vessel (SCV) and secondary September 2014 containment vessel (SCV) with fissile solution.
Rev. #
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 4 of 87
Author Changes Date 0
M. D. Harris Initial issuance.
March 2013 1
M. D. Harris Address flooding the primary containment vessel (SCV) and secondary containment vessel (SCV) with fissile solution.
September 2014 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 5 of 90


TABLE OF CONTENTS
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 4 of 87 TABLE OF CONTENTS Page  
 
Page


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
............................................................................................................10
............................................................................................................10  


==2.0 DESCRIPTION==
==2.0 DESCRIPTION==
................................................................................................................10 2.1 9975 Shipping Packages........................................................................................10 2.2 Plutonium Content Envelope.................................................................................13 2.3 3013 and Convenience Can...................................................................................13 2.4 9975 and 3013 Materials of Construction and Fissile Material Composition.......15 3.0 REQUIREMENTS DOCUMENTATION.....................................................................16 4.0 METHODOLOGY..........................................................................................................16 4.1 Computer Codes.....................................................................................................16 4.2 Code Validation and Bias......................................................................................16 4.2.1 Plutonium Solution....................................................................................17 4.2.2 Plutonium Oxide........................................................................................18 4.3 Material Compositions...........................................................................................18 5.0 DISCUSSION OF CONTINGENCIES..........................................................................19 6.0 EVALUATIONS AND RESULTS.................................................................................19 6.1 Model Descriptions................................................................................................19 6.1.1 Modeling Approximations.........................................................................19 6.1.2 Single Unit, NCT, and HAC Dimensions..................................................20 6.1.3 Single Unit Model......................................................................................21 6.1.4 NCT Model................................................................................................24 6.1.5 HAC Model................................................................................................25 6.2 Plutonium Oxide Content Envelope......................................................................27 6.3 Single Unit Analyses..............................................................................................27 6.3.1 Convenience Can Intact.............................................................................27 6.3.2 Convenience Can Damaged.......................................................................28 6.3.3 Damaged Containment and Flooding 6-inch SCV....................................33 6.4 Normal Conditions of Transport Array Anal yses..................................................40
................................................................................................................10 2.1 9975 Shipping Packages........................................................................................10 2.2 Plutonium Content Envelope.................................................................................13 2.3 3013 and Convenience Can...................................................................................13 2.4 9975 and 3013 Materials of Construction and Fissile Material Composition.......15 3.0 REQUIREMENTS DOCUMENTATION.....................................................................16 4.0 METHODOLOGY..........................................................................................................16 4.1 Computer Codes.....................................................................................................16 4.2 Code Validation and Bias......................................................................................16 4.2.1 Plutonium Solution....................................................................................17 4.2.2 Plutonium Oxide........................................................................................18 4.3 Material Compositions...........................................................................................18 5.0 DISCUSSION OF CONTINGENCIES..........................................................................19 6.0 EVALUATIONS AND RESULTS.................................................................................19 6.1 Model Descriptions................................................................................................19 6.1.1 Modeling Approximations.........................................................................19 6.1.2 Single Unit, NCT, and HAC Dimensions..................................................20 6.1.3 Single Unit Model......................................................................................21 6.1.4 NCT Model................................................................................................24 6.1.5 HAC Model................................................................................................25 6.2 Plutonium Oxide Content Envelope......................................................................27 6.3 Single Unit Analyses..............................................................................................27 6.3.1 Convenience Can Intact.............................................................................27 6.3.2 Convenience Can Damaged.......................................................................28 6.3.3 Damaged Containment and Flooding 6-inch SCV....................................33 6.4 Normal Conditions of Transport Array Analyses..................................................40 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 6 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 5 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 5 of 87 TABLE OF CONTENTS (continued)
 
Page 6.5 Hypothetical Accident Conditions Analyses.........................................................41 6.6 Criticality Safety Index..........................................................................................44 7.0 ADMINISTRATIVELY CONTROLLED LIMITS AND REQUIREMENTS.........45 8.0  
TABLE OF CONTENTS ( continued)
Page
 
6.5 Hypothetical Accident Conditions Analyses.........................................................41 6.6 Criticality Safet y Index..........................................................................................44 7.0 ADMINISTRATIVELY CONTROLLED LIMITS AND REQUIREMENTS.........45 8.0  


==SUMMARY==
==SUMMARY==
AND CONCLUSIONS..............................................................................46
AND CONCLUSIONS..............................................................................46  


==9.0 REFERENCES==
==9.0 REFERENCES==
.................................................................................................................46 APPENDIX A SENSITIVITY STUDIES........................................................................48 APPENDIX B SAMPLE INPUT FILES.........................................................................51
.................................................................................................................46 APPENDIX A SENSITIVITY STUDIES........................................................................48 APPENDIX B SAMPLE INPUT FILES.........................................................................51 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 7 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 6 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 6 of 87 LIST OF TABLES Page Table 1.
Geometric Specifications for the 9975 Shipping Packages.................................. 11 Table 2.
Plutonium Oxide Contents.................................................................................... 13 Table 3.
Types of Convenience Cans and 3013 Containers............................................... 14 Table 4.
Material Specifications for the 9975 and 3013 Containers................................... 15 Table 5.
ksafe Values for Plutonium..................................................................................... 18 Table 6.
Drum and Celotex Dimensions for Different KENO Models............................ 21 Table 7.
Fire and Drop Test Data for the HAC Model....................................................... 26 Table 8.
Base Case Single Unit Cases Without Flooding................................................... 28 Table 9.
Single Unit Cases Flooding the Convenience Can............................................... 29 Table 10.
Single Unit Cases Flooding the Convenience Can - Beryllium........................... 29 Table 11.
Single Unit Cases Flooding the Convenience Can - No 3013 Containers........... 30 Table 12.
Single Unit Cases Flooding the Convenience Can with Beryllium - No 3013..... 30 Table 13.
Single Unit Cases Flooding the Convenience Can with Carbon.......................... 31 Table 14.
Single Unit Cases Flooding the PCV, SCV, and Celotex - Inner 3013 Flooded................................................................................................................. 31 Table 15.
Single Unit Cases Flooding the PCV, SCV, and Celotex - Outer 3013 Flooded................................................................................................................. 32 Table 16.
Single Unit Cases Flooding the PCV, SCV, and Celotex - Both 3013 Containers Flooded............................................................................................... 32 Table 17.
Single Unit Cases Flooding the PCV, SCV, and Celotex - No 3013 Containers............................................................................................................. 33 Table 18.
Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water................... 35 Table 19.
Filling 5-inch PCV and 6-inch SCV with PuO2, Beryllium and Flooding Water..................................................................................................................... 36 Table 20.
Filling 5-inch PCV and 6-inch SCV with PuO2, Carbon and Flooding Water..... 37 Table 21.
Filling 5-inch PCV and 6-inch SCV with PuO2 - Celotex Flooded.................... 39 Table 22.
9975 Array Model - NCT Cases.......................................................................... 40 Table 23.
9975 Array Model - HAC Cases.......................................................................... 43 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 8 of 90


LIST OF TABLES
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 7 of 87 LIST OF TABLES (continued)
Page Table 24.
9975 Array Model - Flooded Convenience Can HAC Cases............................... 43 Table 25.
CSI Calculation..................................................................................................... 45 Table 26.
Plutonium Oxide Contents.................................................................................... 45 Table A1.1.
Variation of keff with Celotex Density................................................................ 48 Table A1.2.
Stainless Steel Composition.................................................................................. 49 Table A1.3.
Variation of keff with Stainless Steel Composition............................................... 49 Table A1.4.
Variation of Dimensional Tolerances on PCV and SCV - Single Unit............... 50 Table A1.5.
Stainless Steel Sleeve Sensitivity Calculation...................................................... 50 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 9 of 90


Page
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 8 of 87 LIST OF FIGURES Page Figure 1.
General Schematic of the 9975 Shipping Package (convenience can not shown)............................................................................................................. 22 Figure 2.
9975 Single Unit with Convenience Can/3013 Combination............................... 23 Figure 3.
9975 Single Unit with 6-inch SCV and 5-inch PCV Flooded.............................. 24 Figure 4.
Normal Condition Transport Infinite Array.......................................................... 25 Figure 5.
2x2x2, Hypothetical Accident Condition............................................................. 26 Figure 6.
HAC Array (2x2x2) Model, Plan View................................................................ 27 Figure 7.
Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water................... 34 Figure 8.
2x2x2 Closest Contact Model (Case 1)................................................................ 42 Figure 9.
2x2x2 Symmetrical Model (Case 5)..................................................................... 43 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 10 of 90


Table 1. Geometric Specifications for the 9975 Shipping Packages.................................. 11 Table 2. Plutonium Oxide Contents.................................................................................... 13 Table 3. Types of Convenience Cans and 3013 Containers............................................... 14 Table 4. Material Specifications for the 9975 and 3013 Containers................................... 15 Table 5. ksafe Values for Plutonium..................................................................................... 18 Table 6. Drum and Celotex Dimensions for Different KENO Models............................ 21 Table 7. Fire and Drop Test Data for the HAC Model....................................................... 26 Table 8. Base Case Single Unit Cases Without Flooding................................................... 28 Table 9. Single Unit Cases Flooding the Convenience Can............................................... 29 Table 10. Single Unit Cases Flooding the Convenience Can - Beryllium........................... 29 Table 11. Single Unit Cases Flooding the Convenience Can - No 3013 Containers........... 30 Table 12. Single Unit Cases Flooding the Convenience Can with Beryllium - No 3013..... 30 Table 13. Single Unit Cases Flooding the Convenience Can with Carbon.......................... 31 Table 14. Single Unit Cases Flooding the PCV, SCV, and Celotex - Inner 3013 Flooded................................................................................................................. 31 Table 15. Single Unit Cases Flooding the PCV, SCV, and Celotex - Outer 3013 Flooded................................................................................................................. 32 Table 16. Single Unit Cases Flooding the PCV, SCV, and Celotex - Both 3013 Containers Flooded............................................................................................... 32 Table 17. Single Unit Cases Flooding the PCV, SCV, and Celotex - No 3013 Containers............................................................................................................. 33 Table 18. Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water................... 35 Table 19. Filling 5-inch PCV and 6-inch SCV with PuO2, Beryllium and Flooding Water..................................................................................................................... 36 Table 20. Filling 5-inch PCV and 6-inch SCV with PuO2, Carbon and Flooding Water..... 37 Table 21. Filling 5-inch PCV and 6-inch SCV with PuO2 - Celotex Flooded.................... 39 Table 22. 9975 Array Model - NCT Cases.......................................................................... 40 Table 23. 9975 Array Model - HAC Cases.......................................................................... 43
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 9 of 87 ACRONYMS AND ABBREVIATIONS AEG Average Energy Group AOA Area of Applicability CC Convenience Can CSACC Criticality Safety Advanced Computing Center CSI Criticality Safety Index HAC Hypothetical Accident Condition LTB Lower Tolerance Band MSM Minimum Subcritical Margin NCSE Nuclear Criticality Safety Evaluation NCT Normal Condition of Transport NRC Nuclear Regulatory Commission PCV Primary Containment Vessel SARP Safety Analysis Report for Packaging SCV Secondary Containment Vessel SRNS Savannah River Nuclear Solutions SS Stainless Steel Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 11 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 7 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 10 of 87  
 
LIST OF TABLES (continued)
 
Page
 
Table 24. 9975 Array Model - Flooded Convenience Can HAC Cases............................... 43 Table 25. CSI Calculation..................................................................................................... 45 Table 26. Plutonium Oxide Contents.................................................................................... 45 Table A1.1. Variation of keff with Celotex Density................................................................ 48 Table A1.2. Stainless Steel Composition.................................................................................. 49 Table A1.3. Variation of keff with Stainless Steel Composition............................................... 49 Table A1.4. Variation of Dimensional Tolerances on PCV and SCV - Single Unit............... 50 Table A1.5. Stainless Steel Sleeve Sensitivity Calculation...................................................... 50
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 8 of 87
 
LIST OF FIGURES
 
Page
 
Figure 1. General Schematic of the 9975 Shipping Package (convenience can not shown)............................................................................................................. 22 Figure 2. 9975 Single Unit with Convenience Can/3013 Combination............................... 23 Figure 3. 9975 Single Unit with 6-inch SCV and 5-inch PCV Flooded.............................. 24 Figure 4. Normal Condition Transport Infinite Array.......................................................... 25 Figure 5. 2x2x2, Hypothetical Accident Condition............................................................. 26 Figure 6. HAC Array (2x2x2) Model, Plan View................................................................ 27 Figure 7. Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water................... 34 Figure 8. 2x2x2 Closest Contact Model (Case 1)................................................................ 42 Figure 9. 2x2x2 Symmetrical Model (Case 5)..................................................................... 43
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 9 of 87
 
ACRONYMS AND ABBREVIATIONS
 
AEG Average Energy Group AOA Area of Applicability CC Convenience Can CSACC Criticality Safety Advanced Computing Center CSI Criticality Safet y Index HAC Hypothetical Accident Condition LTB Lower Tolerance Band MSM Minimum Subcritical Margin NCSE Nuclear Criticality Safety Evaluation NCT Normal Condition of Transport NRC Nuclear Regulatory Commission PCV Primary Containment Vessel SARP Safety Anal ysis Report for Packaging SCV Secondar y Containment Vessel SRNS Savannah River Nuclear Solutions SS Stainless Steel
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 10 of 87


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
This Nuclear Criticalit y Safety Evaluation (NCSE) demonstrates the safe configurations of the 9975 shipping package for plutonium oxide material loading under various conditions in support of the Nuclear Regulatory Commission (NRC) Safety Anal ysis Report.
This Nuclear Criticality Safety Evaluation (NCSE) demonstrates the safe configurations of the 9975 shipping package for plutonium oxide material loading under various conditions in support of the Nuclear Regulatory Commission (NRC) Safety Analysis Report.
 
Criticality safety analysis of the 9975 shipping package in support of the Safety Analysis Report for Packaging (SARP) was previously documented in N-NCS-F-00087, Rev. 2, 9975 Shipping Container Analysis with Revised Contents for SARP, Revision 0. The previous evaluation demonstrated that contents up to 4.4 kg of plutonium as metal, which was described as a bounding material, with up to 100 grams of plastics could be safely shipped in the 9975 shipping package. This evaluation performs an explicit analysis for the plutonium oxide (PuO2) material shipped in a convenience can.
Criticality safety anal ysis of the 9975 shipping package in support of the Safety Anal ysis Report for Packaging (SARP) was previousl y documented in N-NCS-F-00087, Rev. 2, 9975 Shipping Container Analysis with Revised Contents for SARP, Rev ision 0. The previous evaluation demonstrated that contents up to 4.4 kg of plutonium as metal, which was described as a bounding material, with u p to 100 grams of plastics could be safel y shipped in the 9975 shipping package. This evaluation performs an explicit analysis for the plutonium oxide ( PuO2) material shipped in a convenience can.
The evaluation in this NCSE demonstrates that the 9975 shipping package is subcritical with adherence to the design features, limits, and controls specified in Section 7.0.  
 
The evaluation in this NCSE demonstrates that the 9975 shipping package is subcritical with adherence to the design features, limits, and controls specified in Section 7.0.


==2.0 DESCRIPTION==
==2.0 DESCRIPTION==
The following sections describe the geometry and materials of construction of the 9975 shipping package and the convenience can/3013 configuration.
The following sections describe the geometry and materials of construction of the 9975 shipping package and the convenience can/3013 configuration.
2.1 9975 SHIPPING PACKAGES The 9975 shipping package consists of two concentric stainless steel cylindrical containment vessels, a 35-gallon stainless steel drum, cane fiberboard insulation (Celotex), aluminum bearing plates, lead shield, and aluminum honeycomb spacers. The inner containment vessel is called the primary containment vessel (PCV), and the outer containment vessel is called the secondary containment vessel (SCV). The SCV is surrounded on the sides and the bottom by 1/2 inch of lead shielding. Low-density cane fiberboard (Celotex) surrounds the shield to fill the remainder of the 35-gallon drum. Other components of the package include a 1/2-inch thick aluminum lid to cover the lead shield and two 1/2-inch thick aluminum bearing plates - one below the lead shield and one on top of the aluminum lid. Nuclear fuel material contained in product cans (3013 and convenience can) is loaded into the PCV, which is sealed with a stainless steel plug and locking nut.
Table 1 lists dimensions of various components of the 9975 shipping package and the as-modeled dimensions of each component. The Specification column of Table 1 indicates the nominal dimensions of each component.
Per ASTM A312, Specification for Seamless and Welded Austenitic Stainless Steel Pipes, there is a tolerance of +22.5% / -12.5% on the wall thickness and a tolerance on the outer diameter of
+1/16 / -1/32 inch for the PCV and the SCV. A sensitivity study (as shown in Appendix A) was performed on the variation of dimensional tolerances of the PCV and the SCV. It was determined that there was statistically no significant variations among the keff values calculated with nominal, minimum, and maximum wall thicknesses. Table 1 also gives the tolerance on drum radius.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 12 of 90


2.1 9975 SHIPPING PACKAGES
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 11 of 87 The base KENO model was developed from the component specifications listed in Table 1 (see Section 6.1 for description of the KENO models).
 
Table 1.
The 9975 shipping package consists of two concentric stainless steel cylindrical containment vessels, a 35-gallon stainless steel drum, cane fiberboard insulation (Celotex ), aluminum bearing plates, lead shield, and aluminum honeycomb spacers. The inner containment vessel is called the primar y containment vessel (PCV), and the outer containment vessel is called the secondar y containment vessel (SCV). The SCV is surrounded on the sides and the bottom by 1/2 inch of lead shielding. Low-densit y cane fiberboard (Celotex) surrounds the shield to fill the remainder of the 35-gallon drum. Other components of the package include a 1/2-inch thick aluminum lid to cover the lead shield and two 1/2-inch thick aluminum bearing plates - one below the lead shield and one on top of the aluminum lid. Nuclear fuel material contained in product cans (3013 and convenience can) is loaded into the PCV, which is sealed with a stainless steel plug and locking nut.
Geometric Specifications for the 9975 Shipping Packages Component Parameter Specification Inch (cm)
 
KENO Model (cm)
Table 1 lists dimensions of various components of the 9975 shipping package and the as -
PCV Internal Height 18.63 - 1.88 - 0.37 -
modeled dimensions of each component. The S pecification column of Table 1 indicates the nominal dimensions of each component.
0.258 = 16.122 (40.95 cm) 40.95 PCV Bottom Thickness 0.258 (0.655 cm) 0.655 PCV Top Thickness 1.88 - 0.5 = 1.38 (3.505 cm) 3.505 PCV Top Nut Height (top portion) 0.5 (1.27 cm) 1.270 PCV Leg Height 0.37 (0.94 cm) 0.94 PCV Inner Radius 5.047*0.5 (6.410 cm) 6.410 PCV Outer Radius 5.563*0.5 (7.065 cm) 7.065 SCV Top Aluminum Spacer Height 1.80 (4.572 cm) 4.572 SCV Void Space Height 24.0 - 1.88 - 0.38 -
 
0.28-1.0 - 18.63 + 0.5  
Per ASTM A312, Specification for Seamless and Welded Aust enitic Stainless Steel Pipes, there is a tolerance of +22.5% / -12.5% on the wall thickness and a tolerance on the outer diameter of
- 1.8 = 0.53 (1.35 cm) 1.35 SCV Top Thickness 1.88 - 0.5 = 1.38 (3.505 cm) 3.505 SCV Top Nut Height (top portion) 0.5 (1.27 cm) 1.27 SCV Bottom Aluminum Honeycomb Spacer Height 1.0 (2.54 cm) 2.54 SCV Bottom Thickness 0.28 (0.711 cm) 0.711 SCV Leg Height 0.38 (0.965 cm) 0.965 SCV Inner Radius 6.065*0.5 (7.7026 cm) 7.703 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 13 of 90
+1/16 / -1/32 inch for the PCV and the SCV. A sensitivity study ( as shown in Appendix A) was performed on the variation of dimensional tolerances of the PCV and the SCV. It was determined that there was statistically no significant variations among the k eff values calculated with nominal, minimum, and maximum wall thicknesses. Table 1 also gives the tolerance on drum radius.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 11 of 87
 
The base KENO model was developed from the component specifications listed in Table 1 (see Section 6.1 for description of the KENO models).
 
Table 1. Geometric Specifications for the 9975 Shipping Packages
 
Specification KENO Model Component Parameter Inch (c m) ( c m)
PCV Internal Height 18.63 - 1.88 - 0.37 - 40.95 0.258 = 16.122 (40.95 cm)
PCV Bottom Thickness 0.258 0.655 (0.655 cm)
PCV Top Thickness 1.88 - 0.5 = 1.38 3.505 (3.505 cm)
PCV Top Nut Height (top portion) 0.5 1.270 (1.27 cm)
PCV Leg Height 0.37 0.94 (0.94 cm)
PCV Inner Radius 5.047*0.5 6.410 (6.410 cm)
PCV Outer Radius 5.563*0.5 7.065 (7.065 cm)
SCV Top Aluminum Spacer 1.80 4.572 Height (4.572 cm)
 
SCV Void Space Height 24.0 - 1.88 - 0.38 - 1.35 0.28-1.0 - 18.63 + 0.5
- 1.8 = 0.53 (1.35 cm)
SCV Top Thickness 1.88 - 0.5 = 1.38 3.505 (3.505 cm)
SCV Top Nut Height (top portion) 0.5 1.27 (1.27 cm)
SCV Bottom Aluminum 1.0 2.54 Honeycomb Spacer Height (2.54 cm)
 
SCV Bottom Thickness 0.28 0.711 (0.711 cm)
SCV Leg Height 0.38 0.965 (0.965 cm)
SCV Inner Radius 6.065*0.5 7.703 (7.7026 cm) 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 12 of 87
 
Specification KENO Model Component Parameter Inch (c m) ( c m)
SCV Outer Radius 6.625*0.5 8.414 (8.414 cm)
SCV Spacer Inner/Outer Radius 3.7*0.5/5.8*0.5 4.699/7.366 (4.699/7.366 cm)
Drum Inner Radius (18.25 +/- 0.06)*0.5 18.19 *0.5, min 21.466
= 9.095 (calculated NCT value)
(23.101 cm)
Drum Outer Radius (23.101 + 0.122) cm 23.223*.93 (23.223 cm) =21.597 (NCT Value)
Drum Top Void Thickness 34.75 - 33.90 = 0.85 2.16 (nominal) (2.16 cm)
 
Drum Top Wall Thickness 0.048 0.122 (0.122 cm)
Drum Bottom Void Thickness 0 0 (0 cm)
Drum Bottom Wall Thickness 0.048 0.122 (0.122 cm)
Drum Top Wall Thickness 0.048 0.122 (0.122 cm)
Aluminum Lid for Thickness 0.5 1.27 Lead Shield (1.27 cm)
 
Drum Inner Height 34.75 Used to calculate top void (88.265 cm) thickness in drum
 
Lead Shield Thickness 0.506, min1.285 (1.285 cm)
(lead thickness includes two 0.036-inch SS304 liners)
Lead Shield Inner Radius 7.25*0.5 = 3.625 9.208 (9.208 cm)
Lead Shield Outer Radius 3.625+0.506 = 4.131 10.493 (10.493 cm)
Aluminum Outer Radius 5.6 14.224 Plate (14.224 cm)
 
Aluminum Bearing Height 0.5 1.27 Plate, Top (1.27 cm) 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 13 of 87
 
Specification KENO Model Component Parameter Inch (c m) ( c m)
Aluminum Bearing Height 0.5 1.27 Plate, Bottom (1.27 cm)
 
Celotex Top Thickness 3.7 9.398 (9.398 cm)
Celotex Bottom Thickness 3.8 9.652 (9.652cm)
Celotex Outer Radius 18.1*0.5 = 9.05 22.987 (Single Unit (22.987 cm) Model) 21.466 (NCT Model)
(used 21.466 to match inner diameter of drum)
 
2.2 PLUTONIUM C ONTENT E NVELOPE


The fissile material evaluated to be shipped in a 9975 shipping package consists of a maximum of 5.0 kg plutonium oxide contained within a convenience can. The plutonium isotopic composition is conservatively chosen as 100% 239Pu. Beryllium and carbon are anal yzed assuming up to 500 grams of beryllium or 1,000 grams of carbon as a moderator mixed with the fissile material. When beryllium or carbon are added to the model, the mass of the PuO2 is decreased to maintain the 5.0 kg net weight of the contents. Beryllium metal has a density of 1.85 g/cc, and the carbon has a densit y of 2.3 g/cc. See Table 2 for contents.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 12 of 87 Component Parameter Specification Inch (cm)
KENO Model (cm)
SCV Outer Radius 6.625*0.5 (8.414 cm) 8.414 SCV Spacer Inner/Outer Radius 3.7*0.5/5.8*0.5 (4.699/7.366 cm) 4.699/7.366 Drum Inner Radius (18.25 +/- 0.06)*0.5 18.19 *0.5, min
= 9.095 (23.101 cm) 21.466 (calculated NCT value)
Drum Outer Radius (23.101 + 0.122) cm (23.223 cm) 23.223*.93
=21.597 (NCT Value)
Drum Top Void Thickness (nominal) 34.75 - 33.90 = 0.85 (2.16 cm) 2.16 Drum Top Wall Thickness 0.048 (0.122 cm) 0.122 Drum Bottom Void Thickness 0
(0 cm) 0 Drum Bottom Wall Thickness 0.048 (0.122 cm) 0.122 Drum Top Wall Thickness 0.048 (0.122 cm) 0.122 Aluminum Lid for Lead Shield Thickness 0.5 (1.27 cm) 1.27 Drum Inner Height 34.75 (88.265 cm)
Used to calculate top void thickness in drum Lead Shield Thickness 0.506, min (1.285 cm)
(lead thickness includes two 0.036-inch SS304 liners) 1.285 Lead Shield Inner Radius 7.25*0.5 = 3.625 (9.208 cm) 9.208 Lead Shield Outer Radius 3.625+0.506 = 4.131 (10.493 cm) 10.493 Aluminum Plate Outer Radius 5.6 (14.224 cm) 14.224 Aluminum Bearing Plate, Top Height 0.5 (1.27 cm) 1.27 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 14 of 90


Table 2. Plutonium Oxide Contents
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 13 of 87 Component Parameter Specification Inch (cm)
 
KENO Model (cm)
Material Mass (kg)
Aluminum Bearing Plate, Bottom Height 0.5 (1.27 cm) 1.27 Celotex Top Thickness 3.7 (9.398 cm) 9.398 Celotex Bottom Thickness 3.8 (9.652cm) 9.652 Celotex Outer Radius 18.1*0.5 = 9.05 (22.987 cm) 22.987 (Single Unit Model) 21.466 (NCT Model)
(used 21.466 to match inner diameter of drum) 2.2 PLUTONIUM CONTENT ENVELOPE The fissile material evaluated to be shipped in a 9975 shipping package consists of a maximum of 5.0 kg plutonium oxide contained within a convenience can. The plutonium isotopic composition is conservatively chosen as 100% 239Pu. Beryllium and carbon are analyzed assuming up to 500 grams of beryllium or 1,000 grams of carbon as a moderator mixed with the fissile material. When beryllium or carbon are added to the model, the mass of the PuO2 is decreased to maintain the 5.0 kg net weight of the contents. Beryllium metal has a density of 1.85 g/cc, and the carbon has a density of 2.3 g/cc. See Table 2 for contents.
Table 2.
Plutonium Oxide Contents Material Mass (kg)
PuO2 5.0 Beryllium 0.5 Carbon 1.0 This evaluation, based on plutonium oxide, also bounds contents with mixtures of plutonium and uranium oxide of the same total mass.
PuO2 5.0 Beryllium 0.5 Carbon 1.0 This evaluation, based on plutonium oxide, also bounds contents with mixtures of plutonium and uranium oxide of the same total mass.
2.3 3013 AND CONVENIENCE CAN A convenience can is used to contain the fissile material. The convenience can is housed in the 3013 containers of the 9975 during transport. The 3013 container consists of two nested and sealed containers which isolate the fissile material. The 3013 containers and the convenience cans are fabricated of stainless steel. Table 3 lists three types of convenience cans with their associated 3013 containers, along with their dimensions, used for shipment of oxide powder.
The bounding dimensions for the reference convenience can and 3013 containers developed for the KENO model are also shown in Table 3. The KENO model used in this analysis has Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 15 of 90


2.3 3013 AND C ONVENIENCE C AN
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 14 of 87 dimensions consistent with the volume of the Rocky Flats configuration due to its slightly larger volume.
 
Table 3.
A conveniencecan is used to contain the fissile material. The convenience can is housed in the 3013 containers of the 9975 during transport. The 3013 container consists of two nested and sealed containers which isolate the fissile material. The 3013 containers and the convenience cans are fabricated of stainless steel. Table 3 lists threet ypes of convenience cans with their associated 3013 containers, along with their dimensions, used for shipment of oxide powder.
Types of Convenience Cans and 3013 Containers Parameter Nominal Dimensions (cm)
 
Rocky Flats Hanford SRS Reference Dimension for KENO Model Convenience Can Outer Diameter 11.00 10.85 11.16 11.00 Outer Diameter -
The bounding dimensions for the reference convenience can and 3013 container s developed for the KENO model are also shown in Table 3. The KENO model used in this analysis has 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 14 of 87
Inner Diameter Difference 0.05 0.31 0.21 0.05 Top Lid /Bottom Thickness 0.025/
 
0.025 0.305/
dimensions consistent with the volume of the Rocky Flats configuration due to its slightly larger volume.
0.635 0.163/
 
0.152 0.025/
Table 3. Types of Convenience Cans and 3013 Containers
0.025 External Height 20.75 20.40 18.80 20.75 Internal Height 20.70 19.46 18.48 20.70 Material SS 316 SS 304/304L SS 304/304L Reference M-PV-F-0015 R-R4-F-0144 R-R1-F-0098 Inner Can Outer Diameter 11.35 11.68 11.16 11.35 Outer Diameter -
 
Inner Diameter Difference 0.30 0.30 0.21 0.30 Top Lid /Bottom Thickness 0.20/0.15 0.152/0.635 0.163/152 0.20/0.15 External Height 23.10 22.00 18.80 23.10 Inner Height 22.75 21.21 18.48 22.75 Material SS 316 SS 304L SS 304L Reference M-PV-F-0016 R-R4-F-0107 R-R4-F-0107 Outer Can Outer Diameter 25.40 25.40 25.40 25.40 Outer Diameter -
Reference Nominal Dimensions Dimension for Parameter ( c m) Rocky Flats Hanford SRS KENO Model Convenience Can Outer Diameter 11.00 10.85 11.16 11.00 Outer Diameter -
Inner Diameter Difference 0.62 0.62 0.62 0.62 Top Lid /Bottom Thickness 1.91/0.90 1.91/0.90 1.91/0.90 1.91/0.90 External Height 25.40 25.40 25.40 25.40 Internal Height 22.59 22.59 22.59 22.59 Material SS 316 SS 316 SS 316 Reference M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 16 of 90
Inner Diameter 0.05 0.31 0.21 0.05 Difference Top Lid /Bottom 0.025/ 0.305/ 0.163/ 0.025/
Thickness 0.025 0.635 0.152 0.025
 
External Height 20.75 20.40 18.80 20.75 Internal Height 20.70 19.46 18.48 20.70 Material SS 316 SS 304/304L SS 304/304L Reference M-PV-F-0015 R-R4-F-0144 R-R1-F-0098 Inner Can Outer Diameter 11.35 11.68 11.16 11.35 Outer Diameter -
Inner Diameter 0.30 0.30 0.21 0.30 Difference
 
Top Lid /Bottom Thickness 0.20/0.15 0.152/0.635 0.163/152 0.20/0.15
 
External Height 23.10 22.00 18.80 23.10 Inner Height 22.75 21.21 18.48 22.75 Material SS 316 SS 304L SS 304L Reference M-PV-F-0016 R-R4-F-0107 R-R4-F-0107 Outer Can Outer Diameter 25.40 25.40 25.40 25.40 Outer Diameter -
Inner Diameter 0.62 0.62 0.62 0.62 Difference
 
Top Lid /Bottom Thickness 1.91/0.90 1.91/0.90 1.91/0.90 1.91/0.90
 
External Height 25.40 25.40 25.40 25.40 Internal Height 22.59 22.59 22.59 22.59 Material SS 316 SS 316 SS 316 Reference M-PV-F-0017M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 15 of 87
 
2.4 9975 AND 3013 MATERIALS OF CONSTRU CTION AND FISSILE MATERIAL COMPOSITION
 
The convenience can, 3013 containers, PCV, SCV, and the drum are made of 304L or 316 stainless steel (SS). However, the anal ysis used a standard stainless steel, SS 304 with a density of 7.92 g/cc. The small difference in composition between SS 304, SS 304L, and SS 316 will have a negligible effect on reactivity (see the sensitivity study in Appendix A ).
 
As described in Appendix A, Celotex insulation with a nominal density of 0.22 to 0.26 g/cc has the elemental composition of cellulose (C 6H10O5). In addition, Appendix A shows that k eff increases as the Celotex density is decreased. Thus, to account for void spaces between layers, this analysis will use a Celotex density of 0.20 g/cc. See sensitivity studies documented in Appendix A.


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 15 of 87 2.4 9975 AND 3013 MATERIALS OF CONSTRUCTION AND FISSILE MATERIAL COMPOSITION The convenience can, 3013 containers, PCV, SCV, and the drum are made of 304L or 316 stainless steel (SS). However, the analysis used a standard stainless steel, SS 304 with a density of 7.92 g/cc. The small difference in composition between SS 304, SS 304L, and SS 316 will have a negligible effect on reactivity (see the sensitivity study in Appendix A).
As described in Appendix A, Celotex insulation with a nominal density of 0.22 to 0.26 g/cc has the elemental composition of cellulose (C6H10O5). In addition, Appendix A shows that keff increases as the Celotex density is decreased. Thus, to account for void spaces between layers, this analysis will use a Celotex density of 0.20 g/cc. See sensitivity studies documented in Appendix A.
Water density is conservatively taken as 1.0 g/cc instead of a nominal value of 0.9982 g/cc at 20ºC to cover temperatures as low as 0ºC.
Water density is conservatively taken as 1.0 g/cc instead of a nominal value of 0.9982 g/cc at 20ºC to cover temperatures as low as 0ºC.
Aluminum honeycomb spacer density is selected as 0.28 g/cc (estimated density using simplistic calculations). Any variation of aluminum honeycomb spacer density will have a negligible effect on the system reactivity. Standard material densities of lead and aluminum bearing plates are used (see Table 4).
Table 4.
Material Specifications for the 9975 and 3013 Containers Components Material Density(g/cc)
(as-modeled)*
Reference Water H2O 0.9982 at 20°C 0.99998 at 4°C used 1.0 g/cc PCV 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 SCV 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 Drum 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 Aluminum Lid & Plates Aluminum 2.70 Lead Shield Lead 11.34 ORNL/TM-2005/39 Celotex C6H10O5 (0.22 - 0.26 g/cc)
(used 0.20 g/cc)
Appendix A 3013, Outer Can 316L-SS (used SS 304) 7.92 ORNL/TM-2005/39 3013, Inner Can 316-SS (used SS 304) 7.92 ORNL/TM-2005/39 Convenience Can 316-SS / 304L-SS (used SS-304) 7.92 ORNL/TM-2005/39 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 17 of 90


Aluminum honeycomb spacer density is selected as 0.28 g/cc ( estimated density using simplistic calculations). An y variation of aluminum honeycomb spacer density will have a negligible effect on the system reactivity. Standard material densities of lead and aluminum bearing plates are used (see Table 4).
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 16 of 87 3.0 REQUIREMENTS DOCUMENTATION This NCSE is prepared in accordance with SCD-3, Revision 27, Nuclear Criticality Safety Manual; SRNS-IM-2009-00035, Revision 2, Criticality Safety Methods Manual; and 10 CFR Part 71, Packaging and Transportation of Radioactive Material.
 
NUREG/CR-5661, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, for criticality safety evaluation of transportation packages was also followed.
Table 4. Material Specifications for the 9975 and 3013 Containers
4.0 METHODOLOGY The following sections provide a high level overview of the criticality safety computer codes used in this analysis, justify the lower tolerance limit and the minimum subcritical margin (MSM), define the area of applicability (AOA), and justify a value for ksafe for this analysis.
 
Other sections address material compositions and various analysis methods utilized in this analysis.
Density(g/cc)
4.1 COMPUTER CODES The SCALE 5 code system, ORNL/TM-2005/39, Version 5, SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, operating on the SRNS Criticality Safety Advanced Computing Center (CSACC) was used to calculate keff values for this study. The SCALE system is under configuration control, SRNS-RP-2008-00150, Revision 1, Software Configuration and Control Guidance for SCALE on SRS Personal Computers (U), and SRNS-RP-2008-00151, Revision 1, SCALE Test Report for SRS Personal Computers (U). The CSAS26 driver was used. It calls the BONAMI and CENTRM modules for the generation of a problem-dependent cross sections library (accounting for resonance self-shielding) and then calls the KENO-VI module to perform the Monte Carlo keff calculations. All calculations used the 238-group ENDF/B-V cross section set (ORNL/TM-12370, The LAW-238 Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations). Calculations were performed using numbers of generations and neutrons per generation to achieve a calculated statistical uncertainty () less than 0.002.
Components Material (as-modeled)* Reference Water H2O 0.9982 at 20° C 0.99998 at 4° C used 1.0 g/cc PCV 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 SCV 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 Drum 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 Aluminum Lid & Plates Aluminum 2.70 Lead Shield Lead 11.34 ORNL/TM-2005/39 Celotex C6H10O5 (0.22 - 0.26 g/cc) Appendix A (used 0.20 g/cc) 3013, Outer Can 316L-SS (used SS 304) 7.92 ORNL/TM-2005/39 3013, Inner Can 316-SS (used SS 304) 7.92 ORNL/TM-2005/39 Convenience Can 316-SS / 304L-SS (used SS -304) 7.92 ORNL/TM-2005/39
4.2 CODE VALIDATION AND BIAS SCALE 5 has been validated for Pu solution and Pu oxide systems (SRNS-RP-2008-00153, Rev. 0, SCALE 5.0 Validation for SRNS Personal Computers (U)) on the SRNS CSACC system.
 
No critical experiments similar to the 9975 shipping package systems with Pu/U metal/oxide are available. Therefore a wide set of validation experiments was chosen for this study. Table 5 shows the bias and ksafe values for different systems. NUREG/CR-5661 specifies a minimum required margin of subcriticality of 0.05 for packaging applications. Because a large MSM has been used for the 9975 analysis using common fissile materials and drum components, no additional margin due to areas of applicability is necessary.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 16 of 87
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 18 of 90
 
3.0 REQUIREMENTS DOCUMENTATION
 
This NCSE is prepared in accordance with SCD -3, Revision 27, Nuclear Criticality Safety Manual; SRNS -IM-2009-00035, Revision 2, Criticality Safety Methods Manual ; and 10 CFR Part 71, Packaging and Transportation of Radioactive Material.
 
NUREG/CR-5661, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages,for crit icalit y safet y evaluation of transportation packages was also followed.
 
4.0 METHODOLOGY
 
The following sections provide a high level overview of the criticality safety computer codes used in this analysis, justify the lower tolerance limit and the minimum subcr itical margin (MSM), define the area of applicability (AOA), and justify a value for ksafe for this anal ysis.
Other sections address material compositions and various anal ysis methods utilized in this anal ysis.
 
4.1 COMPUTER CODES
 
The SCALE 5 code s ystem, ORNL/TM-2005/39, Version 5, SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, operating on the SRNS Criticality Safet y Advanced Computing Center ( CSACC) was used to calculate k eff values for this study. The SCALE s ystem is under configuration control, SRNS-RP-2008-00150, Revision 1, Software Configuration and Control Guidance for SCALE on SRS Personal Computers (U), and SRNS-RP-2008-00151, Revision 1, SCALE Test Report for SRS Personal Computers (U). The CSA S26 driver was used. It calls the BONAMI and CENTRM modules for the generation of a problem-dependent cross sections library (accounting for resonance self -
shielding) and then calls the KENO-VI module to perform the Monte Carlo k eff calculations. All calculations used the 238-group ENDF/B-V cross section set (ORNL/TM-12370, The LAW -238 Library - A Multigroup Cross -Section Library for Use in Radioactive Waste Analysis Calculations). Calculations were performed using numbers of generations and neutrons per generation to achieve a calculated statistical uncertainty () less than 0.002.
 
4.2 CODE VALIDATION AND BIAS
 
S C A LE 5 has been validated for Pu solution and Pu oxide systems ( SRNS-RP-2008-00153, Rev. 0, SCALE 5.0 Validation for SRNS Personal Computers (U) ) on the SRNS CSACC s ys t e m.
No critical experiments similar to the 9975 shipping package systems with Pu/U metal/oxide are available. Therefore a wide set of validation experiments was chosen for this study. Table 5 shows the bias and ksafe values for different systems. NUREG/CR -5661specifies a minimum required margin of subcriticality of 0.05 for packaging applications. Becausea large MSM has been used for the 9975 analysis using common fissile materials and drum components, no additional margin due to areas of applicability is necessar y.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 17 of 87
 
SCD-3 provides guidance to determine an upper bound of system reactivity, called ksafe, which is determined using the following equation:


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 17 of 87 SCD-3 provides guidance to determine an upper bound of system reactivity, called ksafe, which is determined using the following equation:
ksafe = 1 - B - AOA - MSM (1)
ksafe = 1 - B - AOA - MSM (1)
Where:
Where:
 
ksafe is a conservative upper bound for which a system can be said to be safely subcritical.
ksafe is a conservative upper bound for which a s ystem can be said to be safel y subcritical.
B is an upper bound for the bias. This term accounts for the bias and its uncertainty and is generally dependent on the system being evaluated.
 
AOA is a margin associated with the area of applicability for the system being evaluated. This term is used to compensate for relevant differences that may be encountered between the system being evaluated and the selected set of validation studies used in determining B.
B is an upper bound for the bias. This term accounts for the bias and its uncertainty and is generall y dependent on the system being evaluated.
 
AOA is a margin associated with the area of applicability for the s ystem being evaluated. This term is used to compensate for relevant differences that may be encountered between the system being evaluated and the selected set of validation studies used in determining B.
This term is called the area of applicability margin.
This term is called the area of applicability margin.
MSM is a minimum subcritical margin, an arbitrary margin that is used to ensure subcriticality and, unlike AOA, is independent of the fissile configuration, but rather its magnitude relies in part on the complexity of the entire process being evaluated. This term provides a buffer that is judged to be sufficient to compensate for relevant uncertainties or lack of confidence in understanding the entire process.
MSM is a minimum subcritical margin, an arbitrary margin that is used to ensure subcriticality and, unlike AOA, is independent of the fissile configuration, but rather its magnitude relies in part on the complexity of the entire process being evaluated. This term provides a buffer that is judged to be sufficient to compensate for relevant uncertainties or lack of confidence in understanding the entire process.
In the validation studies documented in SRNS-RP-2008-00153, the bias and its uncertainty are provided in terms of the lower tolerance band (LTB), and are related to B by the following:
In the validation studies documented in SRNS-RP-2008-00153, the bias and its uncertainty are provided in terms of the lower tolerance band (LTB), and are related to B by the following:
LTB = 1 - B (2)
LTB = 1 - B (2)
Using the definition for LTB from Equation (2) with Equation (1) and removing the AOA per above discussion yields the following equation for ksafe:
Using the definition for LTB from Equation (2) with Equation (1) and removing the AOA per above discussion yields the following equation for ksafe:
 
ksafe = LTB - MSM (3) 4.2.1 Plutonium Solution For the plutonium solution fuels, the validation in SRNS-RP-2008-00153, Revision 0, utilized critical experiments involving plutonium nitrate solution. The biased keff values were taken from the validation reference and were based on LTB for the system(s) considered. The LTB values recommended are based on Equation (4) for which the values of H/239Pu atom ratio is calculated from the multiple calculations performed.
ksafe = LTB - MSM (3)
 
4.2.1 Plutonium Solution
 
For the plutonium solution fuels, the validation in SRNS-RP-2008-00153, Revision 0, utilized critical experiments involving plutonium nitrate solu tion. The biased k eff values were taken from the validation reference and were based on LTB for the system(s) considered. The LTB values recommended are based on Equation (4) for which the values of H/ 239Pu atom ratio is calculated from the multiple calculations performed.
 
LTB (PuSol) = 0.99341 + [0.0000053803
LTB (PuSol) = 0.99341 + [0.0000053803
* H/ 239Pu] + [-0.0000000009576 * (H/ 239Pu)2] (4)
* H/239Pu] + [-0.0000000009576 * (H/239Pu)2] (4)
 
Where H/239Pu is the hydrogen to 239Pu atom ratio and the constants are those provided by the quoted reference. The lowest calculated LTB value for plutonium solution is 0.9934.
Where H/ 239Pu is the hydrogen to 239Pu atom ratio and the constants are those provided by the quoted reference. The lowest calculated LTB value for plutonium solution is 0.9934.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 19 of 90
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 18 of 87
 
4.2.2 Plutonium Oxide
 
For the plutonium oxide fuels, the validation in SRNS-RP-2008-00153, Revision 0, utilized critical experiments involving plutonium oxide. The biased k eff values were taken from the validation reference and were based on LTB for the system(s) considered. The LTB values recommended are based on Equation (5) for which the values of AEG (Average Energy Group) are taken from the multiple calculations performed.


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 18 of 87 4.2.2 Plutonium Oxide For the plutonium oxide fuels, the validation in SRNS-RP-2008-00153, Revision 0, utilized critical experiments involving plutonium oxide. The biased keff values were taken from the validation reference and were based on LTB for the system(s) considered. The LTB values recommended are based on Equation (5) for which the values of AEG (Average Energy Group) are taken from the multiple calculations performed.
LTB (PuO2) = 0.99529 + [0.000086341
LTB (PuO2) = 0.99529 + [0.000086341
* AEG] + [-0.00000069867 * (AEG) 2] (5)
* AEG] + [-0.00000069867 * (AEG)2]
 
(5)
Where AEG is the energy of a neutron causing fission and the constants are those provided by the quoted reference. The lowest calculated LTB value plutonium oxide is 0.9953.
Where AEG is the energy of a neutron causing fission and the constants are those provided by the quoted reference. The lowest calculated LTB value plutonium oxide is 0.9953.
 
Table 5.
Table 5. ksafe Values for Plutonium
ksafe Values for Plutonium System LTB MSM
 
= ksafe Plutonium Solution 0.99340 0.05 0.943 Plutonium Oxide, dry 0.99530 0.05 0.945 The validations for the plutonium oxide and plutonium solution critical experiments in SRNS-RP-2008-00153 are used to determine the ksafe value applicable to this analysis. Table 5 shows that the ksafe value of 0.943 derived for plutonium solution experiments is bounding.
System LTB M SM = ksafe Plutonium Solution 0.99340 0.05 0.943 Plutonium Oxide, dry 0.99530 0.05 0.945
4.3 MATERIAL COMPOSITIONS Table 4 provides a specification of materials used in this analysis and the material density as modeled. The following is a brief discussion of the modeling choices made for this analysis.
 
The validations for the plutonium oxide and plutonium solution critical experiments in SRNS -
RP-2008-00153 are used to determine the k safe value applicable to this analysis. Table 5 shows that the k safe value of 0.94 3 derived for plutonium solution experiments is bounding.
 
4.3 MATERIAL COMPOSITIONS
 
Table 4 provides a specification of materials used in this analysis and the material densit y as modeled. The following is a brief discussion of the modeling choices made for this anal ysis.
* Plutonium oxide was modeled as Pu with 100% by weight 239Pu.
* Plutonium oxide was modeled as Pu with 100% by weight 239Pu.
In ANSI/ANS-8.1, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, 239Pu limits apply to isotopic mixtures of plutonium provided that the concentration of 240Pu exceeds that of 241Pu and all isotopes are considered to be 239Pu.
In ANSI/ANS-8.1, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, 239Pu limits apply to isotopic mixtures of plutonium provided that the concentration of 240Pu exceeds that of 241Pu and all isotopes are considered to be 239Pu.
The package contents meet this restriction. Therefore, the content envelope is conservatively modeled as 100% 239Pu.
The package contents meet this restriction. Therefore, the content envelope is conservatively modeled as 100% 239Pu.
* The compositions of lead, aluminum, SS 304, and water used the Standard Composition Librar y in SCALE.
* The compositions of lead, aluminum, SS 304, and water used the Standard Composition Library in SCALE.
* Aluminum used the standard composition library except in the case of the honeycomb spacer, which uses a lower densit y per Section 2.4.
* Aluminum used the standard composition library except in the case of the honeycomb spacer, which uses a lower density per Section 2.4.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 19 of 87
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 20 of 90
 
5.0 DISCUSSION OF CONTINGENCIES
 
10 CFR 71 specifies the contingencies that are to be considered in the shipping package criticality anal ysis. Specifically, the objective of this evaluation is to demonstrate compliance with the performance requirements for each content envelope as specified in:
 
a) 10 CFR 71.55 - General requirement s for fissile material packages
 
b) 10 CFR 71.59 - Standards for arr ays of fissile material packages
 
The requirements of 10 CFR 71 are thorough and ensure that the maximum value of keff is found in the anal ysis based on prescribed configurations. These configurations are related to and are bounding of the conditions (including accident scenarios) a shipping package may be subjected to during its use. 10 CFR 71 requires that the s ystem keff remain s less than k safe for each of the prescribed configurations. Thus, 10 CFR 71 does not require a contingency anal ysis.


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 19 of 87 5.0 DISCUSSION OF CONTINGENCIES 10 CFR 71 specifies the contingencies that are to be considered in the shipping package criticality analysis. Specifically, the objective of this evaluation is to demonstrate compliance with the performance requirements for each content envelope as specified in:
a) 10 CFR 71.55 - General requirements for fissile material packages b) 10 CFR 71.59 - Standards for arrays of fissile material packages The requirements of 10 CFR 71 are thorough and ensure that the maximum value of keff is found in the analysis based on prescribed configurations. These configurations are related to and are bounding of the conditions (including accident scenarios) a shipping package may be subjected to during its use. 10 CFR 71 requires that the system keff remains less than ksafe for each of the prescribed configurations. Thus, 10 CFR 71 does not require a contingency analysis.
The following specific scenarios are analyzed based on the requirements:
The following specific scenarios are analyzed based on the requirements:
 
i)
i) Single unit - dry and flooded
Single unit - dry and flooded ii)
 
Normal condition of transport (NCT) array iii)
ii) Normal condition of transport (NCT) array
Hypothetical accident condition (HAC) array 6.0 EVALUATIONS AND RESULTS Calculations and evaluations were performed to demonstrate that the 9975 shipping packages evaluated with 5 kg of PuO2 with no more than 500 grams of beryllium and 1,000 grams of carbon can be safely transported.
 
6.1 MODEL DESCRIPTIONS 6.1.1 Modeling Approximations The KENO models for single unit, NCT arrays, and HAC arrays include the following simplifications:
iii) Hypothetical accident condition (HAC) array
 
6.0 EVALUATIONS AND RESULTS
 
Calculations and evaluations were performed to demonstrate that the 9975 shipping packages evaluated with 5 kg of PuO2 with no more than 500 grams of beryllium and 1,000 grams of carbon can be safel y transported.
 
6.1 MODEL DESCRIPTIONS
 
6.1.1 Modeling Approximations
 
The KENO models for single unit, NCT arrays, and HAC arrays include the following simplifications:
* PCV and SCV are approximated as right circular cylinders.
* PCV and SCV are approximated as right circular cylinders.
* Aluminum honeycomb spacer inside the PCV is neglected.
* Aluminum honeycomb spacer inside the PCV is neglected.
* Rolling hoops and the drum lid closure are ignored.
* Rolling hoops and the drum lid closure are ignored.
* The two SS 304 sleeves in the lead shield aremodeled as lead and included in the lead thickness.
* The two SS 304 sleeves in the lead shield are modeled as lead and included in the lead thickness.
 
Per Table 1, nominal 9975 component dimensions (except the drum diameter) were used, since the dimensional tolerances were small and their effects on reactivity were shown to be Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 21 of 90
Per Table 1, nominal 9975 component dimensions (except the drum diameter) were used, since the dimensional tolerances were small and their effects on reactivity were shown to be 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 20 of 87
 
insignificant. But the lower tolerance value was used for the drum diameter to conservativel y estimate the array pitch and, thus, to maximize the interaction effect among the fissile units in different packages. In this analysis, the two rolling hoops and bolted ring closure of the 9975 containers were neglected. Neglecting these geometric details reduces the effective drum diameter, which in turn conservativel y models the array pitch.
 
6.1.2 Single Unit, NCT, and HAC Dimensions
 
Table 6 shows the 9975 drum and Celotex dimensions used for the single unit, NCT, and HAC model.


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 20 of 87 insignificant. But the lower tolerance value was used for the drum diameter to conservatively estimate the array pitch and, thus, to maximize the interaction effect among the fissile units in different packages. In this analysis, the two rolling hoops and bolted ring closure of the 9975 containers were neglected. Neglecting these geometric details reduces the effective drum diameter, which in turn conservatively models the array pitch.
6.1.2 Single Unit, NCT, and HAC Dimensions Table 6 shows the 9975 drum and Celotex dimensions used for the single unit, NCT, and HAC model.
The single unit model used the base shipping package dimensions, which are shown in Table 6.
The single unit model used the base shipping package dimensions, which are shown in Table 6.
For the NCT array model (rectangular pitch), the outer nominal drum radius is reduced by 7%.
For the NCT array model (rectangular pitch), the outer nominal drum radius is reduced by 7%.
NUREG/CR-5661 shows that a rectangular pitch drum array, with the drum radius reduced by 7%, is equivalent to a triangular pitch drum array. To preserve the drum wall mass, the drum wall thickness was adjusted (see Table 6).
NUREG/CR-5661 shows that a rectangular pitch drum array, with the drum radius reduced by 7%, is equivalent to a triangular pitch drum array. To preserve the drum wall mass, the drum wall thickness was adjusted (see Table 6).
For the HAC array model, the drum radius was decreased corresponding to a specified amount due to the damage from a prescribed drop, and then was further reduced by 7% to simulate a triangular pitch array. A triangular pitch array model places fissile material units (drums) as close as possible, maximizing the areal density of fissile units, and thereby increasing the reactivity effect due to interaction.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 22 of 90


For the HAC array model, the drum radius was decreased corresponding to a specified amount due to the damage from a prescribed drop, and then was further reduced by 7% to simulate a triangular pitch array. A triangular pitch array model places fissile material units (drums) as close as possible, maximizing the areal densit y of fissile units, and thereby increasing the reactivit y effect due to interaction.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 21 of 87 Table 6.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 21 of 87
Drum and Celotex Dimensions for Different KENO Models Dimension Specification (cm)
 
Single Unit Model (cm)
Table 6. Drum and Celotex Dimensions for Different KENO Models
NCT Model (cm)
 
HAC Model (cm)
Specification Single Unit Model NCT Model HAC Model Dimension ( c m) ( c m) ( c m) ( c m)
Drum Outer Radius 23.101+0.122  
Drum Outer 23.101+0.122 23.101 + 0.122 23.223 *0.93 19.235 Radius =23.223 cm =23.223 cm = 21.597 (23.223-2.54)*0.93 Note:
=23.223 cm 23.101 + 0.122  
=23.223 cm 23.223 *0.93
= 21.597 19.235 (23.223-2.54)*0.93 Note:
1.0 inch (2.54 cm) drum radial reduction due to impact (see Table 7)
1.0 inch (2.54 cm) drum radial reduction due to impact (see Table 7)
Drum Wall (0.048 inch) 0.122 cm 0.131 ** 0.147 Thickness 0.122 cm (** 0.122 cm thickness is changed to 0.131 cm to conserve mass of drum wall)
Drum Wall Thickness (0.048 inch) 0.122 cm 0.122 cm 0.131 **
Drum Inner (18.25+/-0.06)*0.5 (18.19*0.5 = 21.597- 0.131 19.088 Radius inches (cm) 9.095 inches) =21.466 23.101cm Celotex 18.1*0.5 22.987 cm 21.466 to match the 22.987 - 6.35 Outer Radius = 9.05 inches inner diameter of drum =16.637 22.987 cm Note:
(** 0.122 cm thickness is changed to 0.131 cm to conserve mass of drum wall) 0.147 Drum Inner Radius (18.25+/-0.06)*0.5 inches (cm)
2.5 inches (6.35 cm) of Celotex loss due to fire (see Table 7)
(18.19*0.5 =
9.095 inches) 23.101cm 21.597-0.131  
=21.466 19.088 Celotex Outer Radius 18.1*0.5  
= 9.05 inches 22.987 cm 22.987 cm 21.466 to match the inner diameter of drum 22.987 - 6.35  
=16.637 Note:
2.5 inches (6.35 cm) of Celotex loss due to fire (see Table 7) 6.1.3 Single Unit Model Figure 1 shows a schematic of the 9975 shipping package (convenience can/3013 containers not shown), and Figure 2 shows the corresponding KENO model. The 9975 drum overall size is about 34 inches in height and 18 inches in diameter. The base case model analyzed the fissile material as a mixture of plutonium oxide and 0.5% of water to account for moisture content. The fissile material is configured as a right circular cylinder, inside a convenience can, with a height/diameter ratio equal to 1 to maximize reactivity since formation of a perfectly spherical configuration is not credible for oxide material. This base case 9975 model assumed no additional water or flooding with the 3013, PCV, and SCV remaining dry.
10 CFR 71.55 requires single unit analysis to account for the most reactive configurations, including moderation by water to the most reactive credible extent. Therefore, to simulate water inleakage, subsequent variations of the base case modeled water flooding into the convenience can, 3013, PCV, and SCV while keeping the amount of fissile material constant. This parametric study included variations of water flooding into the convenience can, 3013, PCV, and SCV.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 23 of 90


6.1.3 Single Unit Model
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 22 of 87 Figure 1.
General Schematic of the 9975 Shipping Package (convenience can not shown)
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 24 of 90


Figure 1 shows a schematic of the 9975 shipping package (convenience can/3013 containers not shown), and Fi gure 2 shows the corresponding KENO model. The 9975 drum overall size is about 34 inches in height and 18 inches in diameter. The base case model analyzed the fiss ile material as a mixture of plutonium oxide and 0.5% of water to account for moisture content. The fissile material is configured as a right circular cylinder, inside a convenience can, with a height/diameter ratio equal to 1 to maximize reactivity sinceformation of a perfectly spherical configuration is not credible for oxide material. This base case 9975 model assumed no additional water or flooding with the 3013, PCV, and SCV remaining dry.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 23 of 87 Figure 2.
9975 Single Unit with Convenience Can/3013 Combination The convenience can or 3013 containers are not considered a containment boundary, therefore, subsequent variations of the base case model removed the convenience can or 3013 containers.
The first series of cases will have the PCV containing a mixture of water and plutonium oxide.
As water enters the PCV, a plutonium oxide solution is created with water reflection above the solution, until the entire volume of the PCV is filled. As the plutonium oxide-water mixture volume increases, the water reflection above the mixture decreases and the space between the SCV and the stainless steel of the PCV is initially filled with water.
These cases were modeled with the SCV and PCV in position containing water or plutonium oxide solution, removing the stainless steel of the convenience can and 3013 containers. The stainless steel PCV, being credited as a containment boundary, will remain in the SCV, as it is not credible for the PCV to be absent from the shipping package. However, all aluminum within the SCV, which has minimal neutronic impact on criticality, has been replaced with either water or fissile solution, depending on the case being evaluated.
The next series of cases will have the primary containment vessel and secondary containment vessel both containing a plutonium oxide solution. Thus, as water is added to the shipping package, the plutonium oxide-water solution will fill the total volume (height and diameter) of the SCV, minus the space occupied by the steel of the PCV, keeping the fissile mass constant.
Thus, as the PCV fills with fissile solution, the spillage fills the gap between the SCV and the stainless steel of the PCV (Figure 3). And, as the plutonium oxide-water mixture volume increases, the water reflection around or above the mixture decreases. This parametric study is illustrated in Figure 3 as a cylinder of plutonium oxide-water mixture (magenta), filling the SCV (cyan) and PCV (cyan). For this single package analysis, the outer container (drum) was reflected with 30 cm of water on all sides.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 25 of 90


10 CFR 71.55 requires si ngle unit analysis to account for the most reactive configurations, including moderation by water to the most reactive credible extent. Therefore, t o simulate water inleakage, subsequent variations of the base case modeled water flooding into the convenience can, 3013, PCV, and SCV while keeping the amount of fissile material constant. This parametric study included variations of water flooding into the convenience can, 3013, PCV, and SCV.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 24 of 87 Figure 3.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 22 of 87
9975 Single Unit with 6-inch SCV and 5-inch PCV Flooded 6.1.4 NCT Model 10 CFR 71.55 requires the NCT analysis to address undamaged packages in an array. Therefore, for the NCT model, an infinite array of undamaged 9975 shipping packages was analyzed with the convenience can containing the plutonium oxide, in dry conditions (the 0.5% for moisture content is included as dry conditions). This model is similar to the base case single unit model but with an infinite array of 9975 drums containing fissile material.
In the infinite models, there is no leakage from the system (the 3013, PCV, and SCV remain dry), and reflection is irrelevant. Thus, a single 9975 package was modeled inside a tight fitting cuboid with mirror boundary conditions defined for the four x and y faces. In addition, periodic boundary conditions were defined for the z faces of the cuboid using standard KENO options (Figure 4). These boundary conditions reflected all incident neutrons back into the system, thus simulating an infinite square pitch array of packages.
Although the NCT analysis evaluates undamaged packages, cases were analyzed to account for water being present in the Celotex.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 26 of 90


Figure 1. General Schematic of the 9975 Shipping Package (convenience can not shown) 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 23 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 25 of 87 Figure 4.
Normal Condition Transport Infinite Array 6.1.5 HAC Model The HAC model is required per 10 CFR 71.55 to address the most credible configuration of damaged packages, thus an infinite array of 2x2x2 clusters of damaged 9975 packages was used in this analysis. The 2x2x2 array configuration was modeled inside a tight fitting cuboid with mirror boundary conditions defined for the four x and y faces. In addition, periodic boundary conditions were defined for the z faces of the cuboid using standard KENO options (Figure 5).
The damaged HAC array model used conservative assumptions regarding the radial and axial reduction of drum dimensions to address a drop and the amount of Celotex charred due to fire, as shown in Table 7. Additional reduction factors were added to the burn and drop test data for conservatism, also shown in Table 7. As previously stated and as documented in Appendix A, Celotex inhibits neutronic interaction between packages and removing the outer layers of Celotex increases the keff for array calculations; thus, modeling less Celotex is conservative.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 27 of 90


Figure 2. 9975 Single Unit with Convenience Can/3013 Combination
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 26 of 87 Table 7.
 
Fire and Drop Test Data for the HAC Model Dimension Celotex Burn Test Data (inch)
The convenience can or 3013 containers are not considered a containment boundary, therefore, subsequent variations of the base case model removed the convenience can or 3013 containers.
HAC Model (inch)
The first series of cases will have thePCV contain ing a mixture of water and plutonium oxide.
Drop Test Data (inch)
As water enters the PCV, a plutonium oxide solution is created with water reflection above the solution, until the entire volume of the PCV is filled. As the plutonium oxide-water mixture volume increases, the water reflection above the mixture decreases and t he spacebetween the SCV and the stainless steel of the PCV is initially filled with water.
HAC Model (inch)
 
Radial 2.3 2.5 0.5 1.0 Axial (top/bottom) 1.4/2.0 2.0/2.0 1 (total) 1.0/1.0 Reference WSRC-SA-7, Revision 14, Safety Analysis Report -
These c ases were modeled with the SCV and PCV in position containing water or plutonium oxide solution, removing the stainless steel of the convenience can and 3013 containers. The stainless steel PCV, being credited as a containment boundary, will remain in the SCV, as it is not credible for the PCV to be absent from the shipping package. However, all aluminum within the SCV, which has minimal neutronic impacton criticality, has been replaced with either water or fissile solution, depending on the case being evaluated.
 
The next series of cases will have the primar y containment vessel and secondary containment vessel both containing a plutonium oxide solution. Thus, as water is added to the shipping package, the plutonium oxide-water solution will fill t he total volume (height and diameter ) of the SCV, minus the space occupied by the steel of the PCV, keeping the fissile mass constant.
Thus, as the PCV fills with fissile solution, the spillage fills the gap between the SCV and the stainless steel of the PCV (Figure 3). And, as the plutonium oxide-water mixture volume increases, the water reflection around or above the mixture decreases. This parametric study is illustrated in Figure 3 as a cylinder of plutonium oxide-water mixture (magenta), filling the SCV (c yan) and PCV (c yan ). For this single package a nal ys i s, the outer container (drum) was reflected with 30 cm of water on all sides.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 24 of 87
 
Figure 3. 9975 Single Unit with 6-inch SCV and 5-inch PCV Flooded
 
6.1.4 NCT Model
 
10 CFR 71.55 requires the NCT anal ysis to address undamaged packages in an array. Therefore, for the NCT model, an infinite array of undamaged 9975 shipping packages was anal yzed with the convenience can containing the plutonium oxide, in dry conditions (the 0.5% for moisture content is included as dry conditions). This model is similar to the base case single unit model but with an infinite array of 9975 drums containing fissile material.
 
In the infinite models, there is no leakage from the system (the 3013, PCV, and SCV remain dr y), and reflection is irrelevant. Thus, a single 997 5 package was modeled inside a tight fitting cuboid with mirror boundary conditions defined for the four x and y faces. In addition, periodic boundary conditions were defined for the z faces of the cuboid using standard KENO options (Figure 4). These boundary conditions reflected all incident neutrons back into the system, thus simulating an infinite square pitch array of packages.
 
Although the NCT anal ysis evaluates undamaged packages, cases w ereanalyzed to account for water being present in the Celotex.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 25 of 87
 
Figure 4. Normal Condition Transport Infinite Array
 
6.1.5 HAC Model
 
The HAC model is required per 10 CFR 71.55 to address the most credible configuration of damaged packages, thus an infinite array of 2x2x2 clusters of damaged 9975 packages was used in this analysis. The 2x2x2 array configuration was modeled inside a tight fitting cuboid with mirror boundary conditions defined for the four x and y faces. In addition, periodic boundary conditions were defined for the z faces of the cuboid using standard KENO options (Figure 5).
 
The damaged HAC array model used conservative assumptions regarding the radial and axial reduction of drum dimensions to address a drop and the amount of Celotex charred due to fire,
as shown in Table 7. Additional reduction factors were added to the burn and drop test data for conservatism, also shown in Table 7. As previously stated and as documented in Appendix A, Celotex inhibits neutronic interaction between packages and removing the outer layers of Celotex increases the k eff for array calculation s; thus, modeling less Celotex is conservative.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 26 of 87
 
Table 7. Fire and Drop Test Data for the HAC Model
 
Celotex Burn Test Data HAC Model Drop Test Data HAC Model Dimension (inch) (inch) (inch) (inch)
Radial 2.3 2.5 0.5 1.0 Axial 1.4/2.0 2.0/2.0 1 (total) 1.0/1.0 (top/bottom)
Reference WSRC-SA-7, Revision 14, WSRC-SA-7, Chapter Safety Analysis Report - 2.0.
Packages 9965, 9968, 9972 -
Packages 9965, 9968, 9972 -
9975 Packages (U), Appendix 3.7, Thermal Test.
9975 Packages (U), Appendix 3.7, Thermal Test.
WSRC-SA-7, Chapter 2.0.
This section describes the basic HAC model, shown in Figure 5. Section 6.5 discusses the variations of the basic model.
Figure 5.
2x2x2, Hypothetical Accident Condition The drum dimensions are reduced based on the test data, as shown in Table 6. The Celotex outer dimensions are also reduced based on fire data. Charred Celotex is assumed to be completely vaporized.
To address the fissile units at close contact, a conservative HAC model is constructed by assuming maximum movement of the inner containment vessels (Figure 6). The Celotex has also moved and is off-center. The fissile material is in the dry configuration of the single unit base case model, which is contained in the volume of the convenience can. This is shown in Figure 6, as indicated in red.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 28 of 90


This section describes the basic HAC model, shown in Figure 5. Section 6.5 discusses t he variations of the basic model.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 27 of 87 Figure 6.
 
HAC Array (2x2x2) Model, Plan View 6.2 PLUTONIUM OXIDE CONTENT ENVELOPE The fissile material evaluated to be shipped in a 9975 shipping package consists of a maximum of 5.0 kg plutonium oxide contained within a convenience can. The plutonium isotopic composition is conservatively chosen as 100% 239Pu. Beryllium and carbon are analyzed assuming up to 500 grams of beryllium or 1,000 grams of carbon as a moderator mixed with the fissile material. As indicated in Section 2, when beryllium or carbon is added to the model the mass of the PuO2 is decreased to maintain the 5.0 kg net weight of the contents. Beryllium metal has a density of 1.85 g/cc, and the carbon has a density of 2.3 g/cc.
Figure 5. 2x2x2, Hypothetical Accident Condition
6.3 SINGLE UNIT ANALYSES 10 CFR 71.55 contains the following requirements for single package analyses:
 
The drum dimensions are reduced based on the test data, as shown in Table 6. The Celotex outer dimensions are also reduced based on fire data. Charred Celotex is assumed to be completely vaporized.
 
To address the fissile units at close contact, a conservative HAC model is constructed by assuming maximum movement of the inner contain ment vessels (Figure 6). The Celotex has also moved and is off-center. The fissile material is in the dry configuration of the single unit base case model, which is contained in the volume of the convenience can. This is shown in Figure 6, as indicated in red.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 27 of 87
 
Figure 6. HAC Array (2x2x2) Model, Plan View
 
6.2 PLUTONIUM OXIDE CONTENT ENVELOPE
 
The fissile material evaluated to be shipped in a 9975 shipping package consists of a maximum of 5.0 kg plutonium oxide contained within a convenience can. The plu tonium isotopic composition is conservatively chosen as 100% 239Pu. Beryllium and carbon are anal yzed assuming up to 500 grams of beryllium or 1,000 grams of carbon as a moderator mixed with the fissile material. As indicated in Section 2, when beryllium or carbon is added to the model the mass of the PuO2 is decreased to maintain the 5.0 kg net weight of the contents. Beryllium metal has a densit y of 1.85 g/cc, and the carbon has a density of 2.3 g/cc.
 
6.3 SINGLE UNIT ANALYSES
 
10 CFR 71.55 contains the following requirements for single p ackageanalyses:
 
(b) Except as provided in paragraph (c) or (g) of this section, a package used for the shipment of fissile material must be so designed and constructed and its contents so limited that it would be subcritical if water were to leak into the containment system, or liquid contents were to leak out of the containment system so that, under the following conditions, maximum reactivity of the fissile material would be attained:
(b) Except as provided in paragraph (c) or (g) of this section, a package used for the shipment of fissile material must be so designed and constructed and its contents so limited that it would be subcritical if water were to leak into the containment system, or liquid contents were to leak out of the containment system so that, under the following conditions, maximum reactivity of the fissile material would be attained:
(1) The most reactive credible configuration consistent with the chemical and physical form of the material; (2) Moderation by water to the most reactive credible extent; and (3) Close full reflection of the containment s ystem by water on all sides, or such greater reflection of the containment system as may additionally be provided by the surrounding material of the packaging.
(1) The most reactive credible configuration consistent with the chemical and physical form of the material; (2) Moderation by water to the most reactive credible extent; and (3) Close full reflection of the containment system by water on all sides, or such greater reflection of the containment system as may additionally be provided by the surrounding material of the packaging.
 
6.3.1 Convenience Can Intact The single unit base case model was developed with a maximum of 5.0 kg plutonium oxide and 0.5% water fissile mixture contained in the convenience can. The convenience can and 3013 containers are assumed to be leak tight, thus the fissile material remains dry. Cases were Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 29 of 90
6.3.1 Convenience Can Intact
 
The single unit base case model was developed with a maximumof 5.0 kg plutonium oxide and 0.5% water fissile mixture contained in the convenie nce can. The convenience can and 3013 containers are assumed to be leak tight, thus the fissile materialremains dry. Cases were 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 28 of 87
 
modeled with and without the 3013 container. Table 8 summarizes the resultant k eff values.
Figure 2 shows the fissile material and convenience can /3013 combination in the 9975 shipping package.
 
Table 8. Base Case Single Unit Cases Without Flooding
 
Case No. File ID Description keff keff +2
: 1. nrc_su.cyl3013.out: Base Case with 3013, dry oxide 0.5922 0.0010 0.595
: 2. nrc_su.cyl3013be.out: Base Case with 3013 and mixed with beryllium, dry oxide 0.4805 0.0009 0.483
: 3. nrc_su.cylno3013.out: Base Case with no 3013, dry oxide 0.5796 0.0010 0.582
: 4. nrc_su.cylno3013be.out: Base Case with no 3013 and mixed with beryllium, dry oxide 0.4669 0.0009 0.469
: 5. nrc_su.cyl3013c12.out: Base Case with 3013 and mixed with carbon, dry oxide 0.3880 0.0007 0.390
 
As seen in Table 8, the base case (Case 1) with a convenience can containing dry plutonium oxide, with the 3013 containers in place, yields a maximum k eff value of 0.595. In addition, Table 8 shows that the addition of beryllium or carbon does not cause an increase in keff above the base case with dry plutonium oxide in an intact convenience can/3013 configuration (Case1).
 
6.3.2 Convenience Can Damaged
 
To address damage to the convenience can and flooding, a parametric study was performed filling the convenience can with water while maintaining the fissile material constant at 5.0 kg plutonium oxide. As discussed earlier, the height/diameter ratio is equal to 1 to maximize reactivity until the fissile cylinder fills the diameter of the inner container. Then the height of the cylinder will be increased until the inner container is full. Therefore, the fissile solution fills the entire width of the convenience can and the water level is varied (Table 9).


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 28 of 87 modeled with and without the 3013 container. Table 8 summarizes the resultant keff values.
Figure 2 shows the fissile material and convenience can/3013 combination in the 9975 shipping package.
Table 8.
Base Case Single Unit Cases Without Flooding Case No.
File ID Description keff keff +2
: 1.
nrc_su.cyl3013.out:
Base Case with 3013, dry oxide 0.5922 0.0010 0.595
: 2.
nrc_su.cyl3013be.out:
Base Case with 3013 and mixed with beryllium, dry oxide 0.4805 0.0009 0.483
: 3.
nrc_su.cylno3013.out:
Base Case with no 3013, dry oxide 0.5796 0.0010 0.582
: 4.
nrc_su.cylno3013be.out:
Base Case with no 3013 and mixed with beryllium, dry oxide 0.4669 0.0009 0.469
: 5.
nrc_su.cyl3013c12.out:
Base Case with 3013 and mixed with carbon, dry oxide 0.3880 0.0007 0.390 As seen in Table 8, the base case (Case 1) with a convenience can containing dry plutonium oxide, with the 3013 containers in place, yields a maximum keff value of 0.595. In addition, Table 8 shows that the addition of beryllium or carbon does not cause an increase in keff above the base case with dry plutonium oxide in an intact convenience can/3013 configuration (Case 1).
6.3.2 Convenience Can Damaged To address damage to the convenience can and flooding, a parametric study was performed filling the convenience can with water while maintaining the fissile material constant at 5.0 kg plutonium oxide. As discussed earlier, the height/diameter ratio is equal to 1 to maximize reactivity until the fissile cylinder fills the diameter of the inner container. Then the height of the cylinder will be increased until the inner container is full. Therefore, the fissile solution fills the entire width of the convenience can and the water level is varied (Table 9).
Tables 9 through 17 present these single unit results.
Tables 9 through 17 present these single unit results.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 30 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 29 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 29 of 87 Table 9.
Single Unit Cases Flooding the Convenience Can Case No.
File ID Description keff keff +2
: 1.
nrc_su.cyl3013_100.out:
Base Case with 3013, dry oxide - 0.1 liter water added 0.5602 0.0010 0.563
: 2.
nrc_su.cyl3013_200.out:
Same as #1 - 0.2 liter water added 0.5513 0.0010 0.554
: 3.
nrc_su.cyl3013_300.out:
Same as #1 - 0.3 liter water added 0.5541 0.0010 0.557
: 4.
nrc_su.cyl3013_400.out:
Same as #1 - 0.4 liter water added 0.5637 0.0010 0.566
: 5.
nrc_su.cyl3013_400w.out:
Same as #1 - 0.4 liter water added, diameter of convenience can (CC) 0.5657 0.0010 0.568
: 6.
nrc_su.cyl3013_500w.out:
Same as #5 - 0.5 liter water added 0.5692 0.0011 0.572
: 7.
nrc_su.cyl3013_750w.out:
Same as #5 - 0.75 liter water added 0.5897 0.0013 0.593
: 8.
nrc_su.cyl3013_1000w.out:
Same as #5 - 1.0 liter water added 0.6017 0.0011 0.604
: 9.
nrc_su.cyl3013_1100w.out:
Same as #5 - 1.1 liters water added 0.6062 0.0012 0.609
: 10. nrc_su.cyl3013_1200w.out:
Same as #5 - 1.2 liters water added 0.6098 0.0011 0.612
: 11. nrc_su.cyl3013_ccfull.out Same as #5 CC full 0.6260 0.0013 0.629 Table 10.
Single Unit Cases Flooding the Convenience Can - Beryllium Case No.
File ID Description keff keff +2
: 1.
nrc_su.cyl3013be_100.out:
Base Case with 3013 and mixed with beryllium, dry oxide - 0.1 liter water added 0.4770 0.0010 0.479
: 2.
nrc_su.cyl3013be_200.out:
Same as #1 - 0.2 liter water added 0.4888 0.0010 0.491
: 3.
nrc_su.cyl3013be_200w.out:
Same as #1 - 0.2 liter water added, diameter of CC 0.4891 0.0009 0.491
: 4.
nrc_su.cyl3013be_300w.out:
Same as #3 - 0.3 liter water added 0.5009 0.0011 0.504
: 5.
nrc_su.cyl3013be_500w.out:
Same as #3 - 0.5 liter water added 0.5228 0.0012 0.526
: 6.
nrc_su.cyl3013be_750w.out:
Same as #3 - 0.75 liter water added 0.5448 0.0012 0.548
: 7.
nrc_su.cyl3013be_1000w.out Same as #3 - 1.0 liter water added 0.5586 0.0011 0.561
: 8.
nrc_su.cyl3013be_1100w.out:
Same as #3 - CC full 0.5670 0.0013 0.570 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 31 of 90


Table 9. Single Unit Cases Flooding the Convenience Can
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 30 of 87 Table 11.
Single Unit Cases Flooding the Convenience Can - No 3013 Containers Case No.
File ID Description keff keff +2
: 1.
nrc_su.cylno3013_100.out:
Base Case with no 3013, dry oxide - 0.1 liter water added 0.5470 0.0010 0.549
: 2.
nrc_su.cylno3013_200.out:
Same as #1 - 0.2 liter water added 0.5338 0.0010 0.536
: 3.
nrc_su.cylno3013_300.out:
Same as #1 - 0.3 liter water added 0.5348 0.0009 0.537
: 4.
nrc_su.cylno3013_400.out:
Same as #1 - 0.4 liter water added 0.5418 0.0011 0.544
: 5.
nrc_su.cylno3013_400w.out:
Same as #1 - 0.4 liter water added, diameter of CC 0.5391 0.0012 0.542
: 6.
nrc_su.cylno3013_500w.out:
Same as #5 - 0.5 liter water added 0.5493 0.0010 0.552
: 7.
nrc_su.cylno3013_750w.out:
Same as #5 - 0.75 liter water added 0.5618 0.0012 0.565
: 8.
nrc_su.cylno3013_1000w.out:
Same as #5 - 1.0 liter water added 0.5717 0.0012 0.575
: 9.
nrc_su.cylno3013_1100w.out:
Same as #5 - 1.1 liters water added 0.5782 0.0012 0.581
: 10. nrc_su.cylno3013_1200w.out:
Same as #5 - 1.2 liters water added 0.5790 0.0011 0.582
: 11. nrc_su.cylno3013_1300w.out:
Same as #5 - 1.3 liters water added 0.5870 0.0011 0.59
: 12. nrc_su.cylno3013_ccfull.out Same as #5 - CC full 0.6190 0.0012 0.622 Table 12.
Single Unit Cases Flooding the Convenience Can with Beryllium - No 3013 Case No.
File ID Description keff keff +2
: 1.
nrc_su.cylno3013be_100.out:
Base Case with no 3013 and mixed with beryllium, dry oxide - 0.1 liter water added 0.4632 0.0009 0.465
: 2.
nrc_su.cylno3013be_200.out:
Same as #1 - 0.2 liter water added 0.4685 0.0010 0.471
: 3.
nrc_su.cylno3013be_200w.out:
Same as #1 - 0.2 liter water added, diameter of CC 0.4695 0.0009 0.472
: 4.
nrc_su.cylno3013be_300w.out:
Same as #3 - 0.3 liter water added 0.4795 0.0010 0.482
: 5.
nrc_su.cylno3013be_500w.out:
Same as #3 - 0.5 liter water added 0.4959 0.0011 0.499
: 6.
nrc_su.cylno3013be_750w.out:
Same as #3 - 0.75 liter water added 0.5172 0.0012 0.520
: 7.
nrc_su.cylno3013be_1000w.out:
Same as #3 - 1.0 liter water added 0.5320 0.0010 0.534
: 8.
nrc_su.cylno3013be_1100w.out:
Same as #3 - CC full 0.5375 0.0012 0.540 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 32 of 90


Case No. File ID Description keff keff +2
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 31 of 87 Table 13.
: 1. nrc_su.cyl3013_100.out: Base Case with 3013, dry oxide - 0.1 liter 0.0010 0.563 water added 0.5602
Single Unit Cases Flooding the Convenience Can with Carbon Case No.
: 2. nrc_su.cyl3013_200.out: Same as #1 - 0.2 liter water added 0.5513 0.0010 0.554
File ID Description keff keff +2
: 3. nrc_su.cyl3013_300.out: Same as #1 - 0.3 liter water added 0.5541 0.0010 0.557
: 1.
: 4. nrc_su.cyl3013_400.out: Same as #1 - 0.4 liter water added 0.5637 0.0010 0.566
nrc_su.cyl3013c12_100.out:
: 5. nrc_su.cyl3013_400w.out: Same as #1 - 0.4 liter water added, 0.0010 0.568 diameter of convenience can (CC) 0.5657
Base Case with 3013 and mixed with carbon, dry oxide - 0.1 liter water added 0.4033 0.0009 0.406
: 6. nrc_su.cyl3013_500w.out: Same as #5 - 0.5 liter water added 0.5692 0.0011 0.572
: 2.
: 7. nrc_su.cyl3013_750w.out: Same as #5 - 0.75 liter water added 0.5897 0.0013 0.593
nrc_su.cyl3013c12_100w.out:
: 8. nrc_su.cyl3013_1000w.out: Same as #5 - 1.0 liter water added 0.6017 0.0011 0.604
Same as #1 - 0.1 liter water added, diameter of CC 0.4003 0.0009 0.402
: 9. nrc_su.cyl3013_1100w.out: Same as #5 - 1.1 liters water added 0.6062 0.0012 0.609
: 3.
: 10. nrc_su.cyl3013_1200w.out: Same as #5 - 1.2 liters water added 0.6098 0.0011 0.612
nrc_su.cyl3013c12_200w.out:
: 11. nrc_su.cyl3013_ccfull.out Same as #5 CC full 0.6260 0.0013 0.629
Same as #2 - 0.2 liter water added 0.4093 0.0009 0.412
: 4.
nrc_su.cyl3013c12_300w.out:
Same as #2 - 0.3 liter water added 0.4227 0.0010 0.425
: 5.
nrc_su.cyl3013c12_400w.out:
Same as #2 - 0.4 liter water added 0.4406 0.0010 0.443
: 6.
nrc_su.cyl3013c12_500w.out:
Same as #2 - 0.5 liter water added 0.4549 0.0014 0.458
: 7.
nrc_su.cyl3013c12_750w.out:
Same as #2 - 0.75 liter water added 0.4786 0.0012 0.481
: 8.
nrc_su.cyl3013c12_1000w.out:
Same as #2 - 1.0 liter water added 0.5012 0.0011 0.504 As shown above, Tables 9 through 13 compare the keff values for a single unit to examine the effects of flooding the convenience can while forming a homogenized solution, with or without the 3013 container in place. As shown in Table 9, the highest keff of 0.629 is achieved when the convenience can is completely full of fissile solution (plutonium oxide plus flooding water) in a convenience can/3013 combination (Case 11).
Based on Tables 8 through 13, the most reactive cases are achieved with the convenience cans fully flooded with water. Thus, additional cases were run varying water flooding into the various compartments (PCV, SCV, Celotex) of the 9975 shipping package. Tables 14 through 17 list this comparison.
Table 14.
Single Unit Cases Flooding the PCV, SCV, and Celotex - Inner 3013 Flooded Case No.
File ID Description keff keff +2
: 1.
nrc_su.cyl3013_ccfull_3013inn.out:
CC - full of solution 3013 - inner flooded with water 0.6598 0.0014 0.663
: 2.
nrc_su.cyl3013_ccfull_3013inner_PCV.out:
Same as #1 - PCV contains water 0.6633 0.0013 0.666
: 3.
nrc_su.cyl3013_ccfull_3013inner_PCVSCV.out:
Same as #1 -
PCV/SCV contains water 0.6979 0.0012 0.701
: 4.
nrc_su.cyl3013_ccfull_3013inner_SCV.out:
Same as #1 - SCV contains water 0.6849 0.0012 0.688 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 33 of 90


Table 10. Single Unit Cases Flooding the Convenience Can - Beryllium
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 32 of 87 Table 15.
Single Unit Cases Flooding the PCV, SCV, and Celotex - Outer 3013 Flooded Case No.
File ID Description keff keff +2
: 1.
nrc_su.cyl3013_ccfull_3013outer.out:
CC - full of solution 3013 - outer flooded with water 0.6352 0.0013 0.638
: 2.
nrc_su.cyl3013_ccfull_3013outer_PCV.out:
Same as #1 - PCV contains water 0.6490 0.0013 0.652
: 3.
nrc_su.cyl3013_ccfull_3013outer_PCVSCV.out:
Same as #1 -
PCV/SCV contains water 0.6782 0.0013 0.681
: 4.
nrc_su.cyl3013_ccfull_3013outer_SCV.out:
Same as #1 - SCV contains water 0.6654 0.0014 0.669 Table 16.
Single Unit Cases Flooding the PCV, SCV, and Celotex - Both 3013 Containers Flooded Case No.
File ID Description keff keff +2
: 1. nrc_su.cyl3013_ccfull_3013both.out:
CC - full of solution 3013 - inner/outer flooded with water 0.6693 0.0013 0.672
: 2. nrc_su.cyl3013_ccfull_3013both_PCV.out:
Same as #1 - PCV contains water 0.6834 0.0014 0.687
: 3. nrc_su.cyl3013_ccfull_3013both_PCVSCV.out:
Same as #1 -
PCV/SCV contains water 0.7049 0.0014 0.708
: 4. nrc_su.cyl3013_ccfull_3013both_SCV.out:
Same as #1 -SCV contains water 0.6920 0.0012 0.695
: 5. nrc_su.cyl3013_ccfull_3013both_PCV_Celo.out:
Same as #1 - PCV/
Celotex as water 0.7158 0.0013 0.719
: 6. nrc_su.cyl3013_ccfull_3013both_ALL.out:
Same as #1 -
PCV/SCV/
Celotex as water 0.7325 0.0015 0.736 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 34 of 90


Case No. File ID Description keff keff +2 Base Case with 3013 and mixed with
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 33 of 87 Table 17.
: 1. nrc_su.cyl3013be_100.out: beryllium, dry oxide - 0.1 liter water 0.4770 0.0010 0.479 added
Single Unit Cases Flooding the PCV, SCV, and Celotex - No 3013 Containers Case No.
: 2. nrc_su.cyl3013be_200.out: Same as #1 - 0.2 liter water added 0.4888 0.0010 0.491
File ID Description keff keff  
: 3. nrc_su.cyl3013be_200w.out: Same as #1 - 0.2 liter water added, 0.0009 0.491 diameter of CC 0.4891
+2
: 4. nrc_su.cyl3013be_300w.out: Same as #3 - 0.3 liter water added 0.5009 0.0011 0.504
: 1.
: 5. nrc_su.cyl3013be_500w.out: Same as #3 - 0.5 liter water added 0.5228 0.0012 0.526
nrc_su.cylno3013_ccfull.out:
: 6. nrc_su.cyl3013be_750w.out: Same as #3 - 0.75 liter water added 0.5448 0.0012 0.548
CC - full of solution No 3013 0.6204 0.0012 0.623
: 7. nrc_su.cyl3013be_1000w.out Same as #3 - 1.0 liter water added 0.5586 0.0011 0.561
: 2.
: 8. nrc_su.cyl3013be_1100w.out: Same as #3 - CC full 0.5670 0.0013 0.570
nrc_su.cylno3013_ccfull_PCV.out:
Same as #1 - PCV contains water 0.6847 0.0015 0.688
: 3.
nrc_su.cylno3013_ccfull_PCVSCV.out:
Same as #1 - PCV/SCV contains water 0.7097 0.0013 0.713
: 4.
nrc_su.cylno3013_ccfull_SCV.out:
Same as #1 -SCV contains water 0.6219 0.0015 0.625
: 5.
nrc_su.cylno3013_ccfull_PCVSCV_ALL.out:
Same as #1 - PCV/SCV/
Celotex as water 0.7353 0.0013 0.738 Tables 14 through 17 show that a 9975 shipping package with a convenience can containing plutonium oxide, with or without the 3013 container, with water flooding in all compartments of the 9975 shipping package is subcritical. The highest keff + 2 of 0.738 was achieved for the case with a homogenized fissile cylinder modeled the width of the convenience can, no 3013 containers, with the PCV, SCV, and Celotex regions fully flooded with water (Table 17, Case 5).
6.3.3 Damaged Containment and Flooding 6-inch SCV To address damage to the convenience can and 3013 containers, with water flooding into the PCV and SCV, single package models were created filling the 6-inch SCV and 5-inch PCV with water, creating a fissile solution. The fissile mass remains constant at 5.0 kg plutonium oxide as water is added. Thus, convenience can and 3013 containers that are internal to the PCV are removed. In addition, the volumes occupied by the aluminum spacers and aluminum absorbers will be assumed as volumes available to be filled with water and solution. Therefore, the maximum usable volumes (using the volumes occupied by the non-stainless material inside the SCV and PCV) were used.
Removing the convenience can, the 3013 containers and all aluminum material in the SCV is conservative in that the steel would have separated the fissile solution, absorbed neutrons, and occupied space resulting in less fissile solution. In addition, the volume of the aluminum spacers and absorbers within the SCV, which have minimal neutronic impact, would occupy space also resulting in less fissile solution.
A parametric study was performed with water entering the 9975 shipping package assuming the aluminum, convenience can, and 3013 containers are removed. This results in filling the 5-inch PCV with water while maintaining the fissile mass constant at 5.0 kg plutonium oxide. As water is added, the height of the plutonium oxide-water mixture will increase as the mixture fills the diameter and height of the 5-inch PCV. This is depicted in Figure 7, with the data points labeled with 5 PCV. At this point, the volume between the SCV and PCV is filled with water.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 35 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 30 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 34 of 87 After the PCV fills to maximum height with plutonium oxide solution, the fissile solution spills into the SCV, until the SCV is completely full. This is depicted in Figure 7, with the data points labeled with 6 SCV. Thus, the SCV only contains the SS PCV and the filling plutonium oxide solution of both containment vessels.
 
Figure 7, and Tables 18 through 21, show the results of this analysis. As shown in Figure 7, the results without the symbols indicate the PCV filling with plutonium oxide solution until full, with water in the volume between the SCV and PCV. The results with the symbols indicate the PCV full with plutonium oxide solution and the volume between the SCV and PCV filling with plutonium oxide solution, until full.
Table 11. Single Unit Cases Flooding the Convenience Can - No 3013 Containers
Figure 7.
 
Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water 0.40 0.45 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 0
Case No. File ID Description keff keff +2
1 2
: 1. nrc_su.cylno3013_100.out: Base Case with no 3013, dry oxide - 0.1 0.0010 0.549 liter water added 0.5470
3 4
: 2. nrc_su.cylno3013_200.out: Same as #1 - 0.2 liter water added 0.5338 0.0010 0.536
5 6
: 3. nrc_su.cylno3013_300.out: Same as #1 - 0.3 liter water added 0.5348 0.0009 0.537
7 8
: 4. nrc_su.cylno3013_400.out: Same as #1 - 0.4 liter water added 0.5418 0.0011 0.544
k e
: 5. nrc_su.cylno3013_400w.out: Same as #1 - 0.4 liter water added, 0.0012 0.542 diameter of CC 0.5391
f f
: 6. nrc_su.cylno3013_500w.out: Same as #5 - 0.5 liter water added 0.5493 0.0010 0.552
+
: 7. nrc_su.cylno3013_750w.out: Same as #5 - 0.75 liter water added 0.5618 0.0012 0.565
2
: 8. nrc_su.cylno3013_1000w.out: Same as #5 - 1.0 liter water added 0.5717 0.0012 0.575
: 9. nrc_su.cylno3013_1100w.out: Same as #5 - 1.1 liters water added 0.5782 0.0012 0.581
: 10. nrc_su.cylno3013_1200w.out: Same as #5 - 1.2 liters water added 0.5790 0.0011 0.582
: 11. nrc_su.cylno3013_1300w.out: Same as #5 - 1.3 liters water added 0.5870 0.0011 0.59
: 12. nrc_su.cylno3013_ccfull.out Same as #5 - CC full 0.6190 0.0012 0.622
 
Table 12. Single Unit Cases Flooding the Convenience Canwith Beryllium - No 3013
 
Case No. File ID Description keff keff +2 Base Case with no 3013 and mixed with
: 1. nrc_su.cylno3013be_100.out: beryllium, dry oxide - 0.1 liter water 0.4632 0.0009 0.465 added
: 2. nrc_su.cylno3013be_200.out: Same as #1 - 0.2 liter water added 0.4685 0.0010 0.471
: 3. nrc_su.cylno3013be_200w.out: Same as #1 - 0.2 liter water added, 0.0009 0.472 diameter of CC 0.4695
: 4. nrc_su.cylno3013be_300w.out: Same as #3 - 0.3 liter water added 0.4795 0.0010 0.482
: 5. nrc_su.cylno3013be_500w.out: Same as #3 - 0.5 liter water added 0.4959 0.0011 0.499
: 6. nrc_su.cylno3013be_750w.out: Same as #3 - 0.75 liter water added 0.5172 0.0012 0.520
: 7. nrc_su.cylno3013be_1000w.out: Same as #3 - 1.0 liter water added 0.5320 0.0010 0.534
: 8. nrc_su.cylno3013be_1100w.out: Same as #3 - CC full 0.5375 0.0012 0.540 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 31 of 87
 
Table 13. Single Unit Cases Flooding the Convenience Canwith Carbon
 
Case No. File ID Description keff keff +2
: 1. nrc_su.cyl3013c12_100.out: Base Case with 3013 and mixed with carbon, dry oxide - 0.1 liter water added 0.4033 0.0009 0.406
: 2. nrc_su.cyl3013c12_100w.out: Same as #1 - 0.1 liter water added, 0.0009 0.402 diameter of CC 0.4003
: 3. nrc_su.cyl3013c12_200w.out: Same as #2 - 0.2 liter water added 0.4093 0.0009 0.412
: 4. nrc_su.cyl3013c12_300w.out: Same as #2 - 0.3 liter water added 0.4227 0.0010 0.425
: 5. nrc_su.cyl3013c12_400w.out: Same as #2 - 0.4 liter water added 0.4406 0.0010 0.443
: 6. nrc_su.cyl3013c12_500w.out: Same as #2 - 0.5 liter water added 0.4549 0.0014 0.458
: 7. nrc_su.cyl3013c12_750w.out: Same as #2 - 0.75 liter water added 0.4786 0.0012 0.481
: 8. nrc_su.cyl3013c12_1000w.out: Same as #2 - 1.0 liter water added 0.5012 0.0011 0.504
 
As shown above, Tables 9 through 13 compare the keff values for a single unit to examine the effects of flooding the convenience can while forming a homogenized solution, with or without the 3013 container in place. As shown in Table 9, the highest keff of 0.629 is achieved when the convenience can is completely full of fissile solution (plutonium oxide plus flooding water) in a convenience can/3013 combination (Case 11).
 
Based on Tables 8 through 13, the most reactive cases are achieved with the convenience cans fully flooded with water. Thus, additional cases were run var ying water flooding into the various compartments (PCV, SCV, Celotex ) of the 9975 shipping package. Tables 14 through 17 list this comparison.
 
Table 14. Single Unit Cases Flooding the PCV, SCV, and Celotex - Inner 3013 Flooded
 
Case No. File ID Description keff keff +2 CC - full of solution
: 1. nrc_su.cyl3013_ccfull_3013inn.out: 3013 - inner flooded 0.6598 0.0014 0.663 with water
: 2. nrc_su.cyl3013_ccfull_3013inner_PCV.out: Same as #1 - PCV 0.0013 0.666 contains water 0.6633 Same as #1 -
: 3. nrc_su.cyl3013_ccfull_3013inner_PCVSCV.out: PCV/SCV contains 0.6979 0.0012 0.701 water
: 4. nrc_su.cyl3013_ccfull_3013inner_SCV.out: Same as #1 - SCV 0.0012 0.688 contains water 0.6849
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 32 of 87
 
Table 15. Single Unit Cases Flooding the PCV, SCV, and Celotex - Outer 3013 Flooded
 
Case No. File ID Description keff keff +2 CC - full of solution
: 1. nrc_su.cyl3013_ccfull_3013outer.out: 3013 - outer flooded 0.6352 0.0013 0.638 with water
: 2. nrc_su.cyl3013_ccfull_3013outer_PCV.out: Same as #1 - PCV 0.0013 0.652 contains water 0.6490 Same as #1 -
: 3. nrc_su.cyl3013_ccfull_3013outer_PCVSCV.out: PCV/SCV contains 0.6782 0.0013 0.681 water
: 4. nrc_su.cyl3013_ccfull_3013outer_SCV.out: Same as #1 - SCV 0.0014 0.669 contains water 0.6654
 
Table 16. Single Unit Cases Flooding the PCV, SCV, and Celotex - Both 3013 Containers Flooded
 
Case No. File ID Description keff keff +2 CC - full of solution
: 1. nrc_su.cyl3013_ccfull_3013both.out: 3013 - inner/outer 0.6693 0.0013 0.672 flooded with water
: 2. nrc_su.cyl3013_ccfull_3013both_PCV.out: Same as #1 - PCV contains water 0.6834 0.0014 0.687 Same as #1 -
: 3. nrc_su.cyl3013_ccfull_3013both_PCVSCV.out: PCV/SCV contains 0.7049 0.0014 0.708 water
: 4. nrc_su.cyl3013_ccfull_3013both_SCV.out: Same as #1 - SCV contains water 0.6920 0.0012 0.695
: 5. nrc_su.cyl3013_ccfull_3013both_PCV_Celo.out: Same as #1 - PCV/
Celotex as water 0.7158 0.0013 0.719 Same as #1 -
: 6. nrc_su.cyl3013_ccfull_3013both_ALL.out: PCV/SCV/ 0.7325 0.0015 0.736 Celotex as water
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 33 of 87
 
Table 17. Single Unit Cases Flooding the PCV, SCV, and Celotex - No 3013 Containers
 
Case keff No. File ID Description keff +2
: 1. nrc_su.cylno3013_ccfull.out: CC - full of solution No 3013 0.6204 0.0012 0.623
: 2. nrc_su.cylno3013_ccfull_PCV.out: Same as #1 - PCV contains 0.0015 0.688 water 0.6847
: 3. nrc_su.cylno3013_ccfull_PCVSCV.out: Same as #1 - PCV/SCV 0.0013 0.713 contains water 0.7097
: 4. nrc_su.cylno3013_ccfull_SCV.out: Same as #1 - SCV contains 0.0015 0.625 water 0.6219
: 5. nrc_su.cylno3013_ccfull_PCVSCV_ALL.out: Same as #1 - PCV/SCV/ 0.0013 0.738 Celotex as water 0.7353
 
Tables 14 through 17 show that a 9975 shipping package with a convenience can containing plutonium oxide, with or without the 3013 container, with water flooding in all compartments of the 9975 shipping package is subcritical. The highest k eff + 2 of 0.738 was achieved fo r the case with a homogenized fissile cylinder modeled the width of the convenience can, no 3013 containers, with the PCV, SCV, and Celotex regions fully flooded with water (Table 17, Case 5).
 
6.3.3 Damaged Containment and Flooding 6-inch SCV
 
To address damage to the convenience can and 3013 containers, with water flooding into the PCV and SCV, single package models were created filling the 6-inch SCV and 5-inch PCV with water, creating a fissile solution. The fissile mass remains constant at 5.0 kg plutonium oxide as water is added. Thus, convenience can and 3013 containers that are internal to the PCV are removed. In addition, the volumes occupied by the aluminum spacers and aluminum absorbers will be assumed as volumes available to be filled with water and solution. Therefore, the maximum usable volumes (using the volumes occupied by the non-stainless material inside the SCV and PCV) were used.
 
Removing the convenience can, the 3013 containers and all aluminum material in the SCV is conservative in that the steel would have separated the fissile solution, absorbed neutrons, and occupied space resulting in less fissile solutio n. In addition, the volume of the aluminum spacers and absorbers within the SCV, which have minimal neutronic impact, would occupy space also resulting in less fissile solution.
 
A parametric study was performed with water entering the 9975 shipping package assuming the aluminum, convenience can, and 3013 containers areremoved. Th is result s in filling the 5-inch PCV with water while maintaining the fissile mass constant at 5.0 kg plutonium oxide. As water is added, the height of the plutonium oxide-water mixture will increase as the mixture fills the diameter and height of the 5-inch PCV. This is depicted in Figure 7, with the data points labeled with 5 PCV. At this point, t he volume between the SCV and PCV is filled with water.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 34 of 87
 
After the PCV fills to maximum height with plutonium oxide solution, the fissile solution spills into the SCV, until the SCV is completely full. This is depicted in Figure 7, with the data points labeled with 6 SCV. Thus, the SCV only contains the SS PCV and the filling plutonium oxide solution of both containment vessels.
 
Figure 7, and Tables 18 through 21, show the results of this analysis. As shown in Figure 7, the results without the symbols indicate the PCV filling with plutonium oxide solution until full, with water in the volume between the SCV and PCV. The results with the symbols indicate the PCV full with plutonium oxide s olution and the volume between the SCV and PCV filling with plutonium oxide solution, until full.
 
1.00
 
0.95
 
0.90
 
0.85


k 0.80 e k-safe f 0.75 5" PCV f 0.70 Be 5" PCV
Amount (liters) of water added to PuO2 k-safe 5" PCV Be 5" PCV C 5" PCV 5" PCV - FLD Celo 6" SCV Be 6 "SCV C 6" SCV 6" SCV - FLD Celo Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 36 of 90
+ 0.65 C 5" PCV 5" PCV - FLD Celo 2 0.60 6" SCV


0.55 Be 6 "SCV C 6" SCV 0.50 6" SCV - FLD Celo 0.45
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 35 of 87 Table 18.
 
Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water Case No.
0.40 0 1 2 3 4 5 6 7 8 Amount (liters) of water added to PuO2
Filename Description PuO2
 
: Density, g/cc keff keff +2
Figure 7. Filling 5-inch PCV and 6 -inch SCV with PuO 2 and Flooding Water 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 35 of 87
: 1.
 
nrc_su._PuO_fld_5PCV_noBe_ful.100.out PCV intact. CC, 3013 removed.
Table 18. Filling 5-inch PCV and 6 -inch SCVwith PuO 2 and Flooding Water
PuO2 dry. Water between SCV-PCV.
 
10.8921 0.6639 0.0011 0.667
Case PuO2 No. Filename Description Density, keff keff +2 g/cc PCV intact. CC, 3013 removed.
: 2.
: 1. nrc_su._PuO_fld_5PCV_noBe_ful.100.out PuO2 dry. Water between SCV-10.8921 0.6639 0.0011 0.667 PCV.
nrc_su._PuO_fld_5PCV_noBe_ful.110.out Same as #1 - 1 liter water added to PCV 4.1131 0.7182 0.0012 0.721
: 2. nrc_su._PuO_fld_5PCV_noBe_ful.110.out Same as #1 - 1 liter water added 4.1131 0.7182 0.0012 0.721 to PCV
: 3.
: 3. nrc_su._PuO_fld_5PCV_noBe_ful.120.out Same as #2 - 2 liters water 2.8466 0.7649 0.0013 0.768 added to PCV
nrc_su._PuO_fld_5PCV_noBe_ful.120.out Same as #2 - 2 liters water added to PCV 2.8466 0.7649 0.0013 0.768
: 4. nrc_su._PuO_fld_5PCV_noBe_ful.130.out Same as #2 - 3 liters water 2.3123 0.7903 0.0014 0.794 added to PCV
: 4.
: 5. nrc_su._PuO_fld_5PCV_noBe_ful.140.out Same as #2 - 4 liters water 2.0176 0.8047 0.0014 0.808 added to PCV 4.826 L water added to PCV
nrc_su._PuO_fld_5PCV_noBe_ful.130.out Same as #2 - 3 liters water added to PCV 2.3123 0.7903 0.0014 0.794
: 6. nrc_su._PuO_fld_5PCV_noBe_ful.4826.out (totally full). PCV intact. CC 1.8584 0.8107 0.0015 0.814 and 3013 removed.
: 5.
 
nrc_su._PuO_fld_5PCV_noBe_ful.140.out Same as #2 - 4 liters water added to PCV 2.0176 0.8047 0.0014 0.808
PCV intact. CC and 3013
: 6.
: 7. nrc_su._PuO_fld_6SCV_noBe_ful.5450.out removed. 5.540 L water added to 1.7675 0.8110 0.0015 0.814 PCV, solution spilling into SCV.
nrc_su._PuO_fld_5PCV_noBe_ful.4826.out 4.826 L water added to PCV (totally full). PCV intact. CC and 3013 removed.
PCV intact. CC and 3013
1.8584 0.8107 0.0015 0.814
: 8. nrc_su._PuO_fld_6SCV_noBe_ful.5746.out removed. 5.746 L water added to 1.7308 0.8231 0.0014 0.826 PCV, solution spilling into SCV.
: 7.
PCV intact. CC and 3013
nrc_su._PuO_fld_6SCV_noBe_ful.5450.out PCV intact. CC and 3013 removed. 5.540 L water added to PCV, solution spilling into SCV.
: 9. nrc_su._PuO_fld_6SCV_noBe_ful.6042.out removed. 6.042 L water added to 1.6975 0.8334 0.0014 0.837 PCV, solution spilling into SCV.
1.7675 0.8110 0.0015 0.814
PCV intact. CC and 3013
: 8.
: 10. nrc_su._PuO_fld_6SCV_noBe_ful.6338.out removed. 6.338 L water added to 1.6670 0.8460 0.0015 0.849 PCV, solution spilling into SCV.
nrc_su._PuO_fld_6SCV_noBe_ful.5746.out PCV intact. CC and 3013 removed. 5.746 L water added to PCV, solution spilling into SCV.
PCV intact. CC and 3013
1.7308 0.8231 0.0014 0.826
: 11. nrc_su._PuO_fld_6SCV_noBe_ful.6689.out removed. 6.689 L water added to 1.6341 0.8538 0.0015 0.857 PCV, solution spilling into SCV.
: 9.
PCV intact. CC and 3013
nrc_su._PuO_fld_6SCV_noBe_ful.6042.out PCV intact. CC and 3013 removed. 6.042 L water added to PCV, solution spilling into SCV.
: 12. nrc_su._PuO_fld_6SCV_noBe_ful.7123.out removed. 7.123 L water added to 1.5978 0.8542 0.0016 0.858 PCV, solution spilling into SCV.
1.6975 0.8334 0.0014 0.837
PCV intact. CC and 3013
: 10.
: 13. nrc_su._PuO_fld_6SCV_noBe_ful.7793.out removed. 7.793 L water added to 1.5491 0.8510 0.0017 0.855 PCV, solution spilling into SCV.
nrc_su._PuO_fld_6SCV_noBe_ful.6338.out PCV intact. CC and 3013 removed. 6.338 L water added to PCV, solution spilling into SCV.
1.6670 0.8460 0.0015 0.849
: 11.
nrc_su._PuO_fld_6SCV_noBe_ful.6689.out PCV intact. CC and 3013 removed. 6.689 L water added to PCV, solution spilling into SCV.
1.6341 0.8538 0.0015 0.857
: 12.
nrc_su._PuO_fld_6SCV_noBe_ful.7123.out PCV intact. CC and 3013 removed. 7.123 L water added to PCV, solution spilling into SCV.
1.5978 0.8542 0.0016 0.858
: 13.
nrc_su._PuO_fld_6SCV_noBe_ful.7793.out PCV intact. CC and 3013 removed. 7.793 L water added to PCV, solution spilling into SCV.
SCV completely full.
SCV completely full.
1.5491 0.8510 0.0017 0.855 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 37 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 36 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 36 of 87 Table 19.
 
Filling 5-inch PCV and 6-inch SCV with PuO2, Beryllium and Flooding Water Case No.
Table 19. Filling 5-inch PCV and 6 -inch SCV with PuO 2, Beryllium and Flooding Water
Filename Description PuO2
 
: Density, g/cc keff keff +2
Case PuO2 No. Filename Description Density, keff keff +2 g/cc
: 1.
: 1. nrc_su._PuO_fld_5PCV_Be_ful.100.out PCV intact. CC, 3013 removed. 7.2986 0.5899 0.0011 0.593 PuO2 dry. Added 500 g Be.
nrc_su._PuO_fld_5PCV_Be_ful.100.out PCV intact. CC, 3013 removed.
: 2. nrc_su._PuO_fld_5PCV_Be_ful.110.out Same as #1 - 1 liter water added to 3.5611 0.6865 0.0016 0.690 PCV
PuO2 dry. Added 500 g Be.
: 3. nrc_su._PuO_fld_5PCV_Be_ful.120.out Same as #2 - 2 liters water added to 2.6068 0.7454 0.0015 0.749 PCV
7.2986 0.5899 0.0011 0.593
: 4. nrc_su._PuO_fld_5PCV_Be_ful.130.out Same as #2 - 3 liters water added to 2.1704 0.7709 0.0013 0.774 PCV
: 2.
: 5. nrc_su._PuO_fld_5PCV_Be_ful.140.out Same as #2 - 4 liters water added to 1.9202 0.7849 0.0014 0.788 PCV 4.599 L water added to PCV
nrc_su._PuO_fld_5PCV_Be_ful.110.out Same as #1 - 1 liter water added to PCV 3.5611 0.6865 0.0016 0.690
: 6. nrc_su._PuO_fld_5PCV_Be_ful.4599.out (totally full). PCV intact. CC and 1.8157 0.7905 0.0016 0.794 3013 removed.
: 3.
nrc_su._PuO_fld_5PCV_Be_ful.120.out Same as #2 - 2 liters water added to PCV 2.6068 0.7454 0.0015 0.749
: 4.
nrc_su._PuO_fld_5PCV_Be_ful.130.out Same as #2 - 3 liters water added to PCV 2.1704 0.7709 0.0013 0.774
: 5.
nrc_su._PuO_fld_5PCV_Be_ful.140.out Same as #2 - 4 liters water added to PCV 1.9202 0.7849 0.0014 0.788
: 6.
nrc_su._PuO_fld_5PCV_Be_ful.4599.out 4.599 L water added to PCV (totally full). PCV intact. CC and 3013 removed.
1.8157 0.7905 0.0016 0.794
: 7.
nrc_su._PuO_fld_6SCV_Be_ful.5223.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 5.223 L water added to PCV, solution spilling into SCV.
1.7294 0.7950 0.0018 0.799
: 8.
nrc_su._PuO_fld_6SCV_Be_ful.5519.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 5.519 L water added to PCV, solution spilling into SCV.
1.6945 0.8029 0.0015 0.806
: 9.
nrc_su._PuO_fld_6SCV_Be_ful.5815.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 5.815 L water added to PCV, solution spilling into SCV.
1.6628 0.8212 0.0015 0.825
: 10.
nrc_su._PuO_fld_6SCV_Be_ful.6111.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 6.111 L water added to PCV, solution spilling into SCV.
1.6338 0.8333 0.0016 0.837
: 11.
nrc_su._PuO_fld_6SCV_Be_ful.6463.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 6.463 L water added to PCV, solution spilling into SCV.
1.6026 0.8399 0.0017 0.844
: 12.
nrc_su._PuO_fld_6SCV_Be_ful.6896.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 6.896 L water added to PCV, solution spilling into SCV.
1.5680 0.8415 0.0015 0.845
: 13.
nrc_su._PuO_fld_6SCV_Be_ful.7567.out PCV intact. CC and 3013 removed.
PuO2 mixed with 500 g Be. 7.567 L water added to PCV, solution spilling into SCV. SCV completely full.
1.5217 0.8398 0.0015 0.843 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 38 of 90


PCV intact. CC and 3013 removed.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 37 of 87 Table 20.
: 7. nrc_su._PuO_fld_6SCV_Be_ful.5223.out PuO2 mixed with 500 g Be. 5.223 L 1.7294 0.7950 0.0018 0.799 water added to PCV, solution spilling into SCV.
Filling 5-inch PCV and 6-inch SCV with PuO2, Carbon and Flooding Water Case No.
PCV intact. CC and 3013 removed.
Filename Description PuO2
: 8. nrc_su._PuO_fld_6SCV_Be_ful.5519.out PuO2 mixed with 500 g Be. 5.519 L 1.6945 0.8029 0.0015 0.806 water added to PCV, solution spilling into SCV.
: Density, g/cc keff keff +2
PCV intact. CC and 3013 removed.
: 1.
: 9. nrc_su._PuO_fld_6SCV_Be_ful.5815.out PuO2 mixed with 500 g Be. 5.815 L 1.6628 0.8212 0.0015 0.825 water added to PCV, solution spilling into SCV.
nrc_su._PuO_fld_5PCV_C_ful.100.out PCV intact. CC, 3013 removed. PuO2 dry. Added 1000 g Carbon.
PCV intact. CC and 3013 removed.
6.2065 0.5101 0.0009 0.512
: 10. nrc_su._PuO_fld_6SCV_Be_ful.6111.out PuO2 mixed with 500 g Be. 6.111 L 1.6338 0.8333 0.0016 0.837 water added to PCV, solution spilling into SCV.
: 2.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_C_ful.110.out Same as #1 - 1 liter water added to PCV 3.3232 0.6327 0.0014 0.636
: 11. nrc_su._PuO_fld_6SCV_Be_ful.6463.out PuO2 mixed with 500 g Be. 6.463 L 1.6026 0.8399 0.0017 0.844 water added to PCV, solution spilling into SCV.
: 3.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_C_ful.120.out Same as #2 - 2 liters water added to PCV 2.4948 0.7003 0.0015 0.704
: 12. nrc_su._PuO_fld_6SCV_Be_ful.6896.out PuO2 mixed with 500 g Be. 6.896 L 1.5680 0.8415 0.0015 0.845 water added to PCV, solution spilling into SCV.
: 4.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_C_ful.130.out Same as #2 - 3 liters water added to PCV 2.1016 0.7399 0.0017 0.744
PuO2 mixed with 500 g Be. 7.567 L
: 5.
: 13. nrc_su._PuO_fld_6SCV_Be_ful.7567.out water added to PCV, solution 1.5217 0.8398 0.0015 0.843 spilling into SCV. SCV completely full.
nrc_su._PuO_fld_5PCV_C_ful.140.out Same as #2 - 4 liters water added to PCV 1.8720 0.7597 0.0014 0.763
: 6.
nrc_su._PuO_fld_5PCV_C_ful.4478.out 4.478 L water added to PCV (totally full). PCV intact. CC and 3013 removed.
1.7930 0.7649 0.0015 0.768
: 7.
nrc_su._PuO_fld_6SCV_C_ful.5102.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 5.102 L water added to PCV, solution spilling into SCV.
1.7090 0.7728 0.0015 0.776
: 8.
nrc_su._PuO_fld_6SCV_C_ful.5398.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 5.398 L water added to PCV, solution spilling into SCV.
1.6751 0.7812 0.0014 0.784
: 9.
nrc_su._PuO_fld_6SCV_C_ful.5694.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 5.694 L water added to PCV, solution spilling into SCV.
1.6443 0.7972 0.0016 0.801
: 10.
nrc_su._PuO_fld_6SCV_C_ful.5990.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 5.990 L water added to PCV, solution spilling into SCV.
1.6161 0.8110 0.0016 0.815
: 11.
nrc_su._PuO_fld_6SCV_C_ful.6342.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 6.342 L water added to PCV, solution spilling into SCV.
1.5857 0.8180 0.0015 0.821 12 nrc_su._PuO_fld_6SCV_C_ful.6775.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 6.775 L water added to PCV, solution spilling into SCV.
1.5521 0.8198 0.0014 0.823
: 13.
nrc_su._PuO_fld_6SCV_C_ful.7446.out PCV intact. CC and 3013 removed.
PuO2 mixed with 1000 g carbon. 7.446 L water added to PCV, solution spilling into SCV. SCV completely full.
1.5071 0.8183 0.0016 0.822 As can be seen from Figure 7 and Tables 18 through 20, the plutonium oxide mixed with water in the PCV and SCV remains subcritical as the added water causes the density of the solution to decrease by holding the mass of the plutonium oxide constant. All cases in Tables 18 through 20 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 39 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 37 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 38 of 87 initially have water mixing with the plutonium oxide in the shipping package, creating a plutonium oxide solution in the PCV and water only in the SCV. As the PCV fills with solution, spillage fills the SCV until totally full with the plutonium oxide solution.
The cases with the plutonium oxide solution filling the PCV are shown to be subcritical, achieving a maximum keff + 2 = 0.814, Table 18, Case 6. In these cases, no plutonium oxide solution is in the SCV, only water from filling the shipping package.
As increasing amounts of water mix with the plutonium oxide in the shipping package, the PCV overflows filling the SCV with the plutonium oxide solution. Thus, you have plutonium oxide solution in the PCV as well as the SCV. The cases of filling the PCV and SCV with plutonium oxide solution remains below ksafe with a maximum at keff + 2 = 0.858, Table 18, Case 12. In this case (Table 18, Case 12), approximately 7.123 L water is added to the plutonium oxide in the shipping package, which completely fills the PCV, but only partially fills the SCV, with plutonium oxide solution. Totally filling both the PCV and SCV (approximately 7.793 L water added to the plutonium oxide in the shipping package) with the plutonium oxide solution has also been demonstrated to be below ksafe with a keff + 2 = 0.855, Table 18, Case 13. In addition, when impurities (Be or C) are mixed with the oxide, the fissile mass of the mixture is reduced and consequently lowers the keff of the system, as shown in Tables 19 through 20.
To fully demonstrate that single package flooding is safely subcritical, additional models were developed to flood all of the remaining compartments of the 9975 shipping package. As shown in Table 18 through Table 20, the cases without impurities yielded the highest keff and have the SCV and PCV flooded with plutonium oxide solution. Therefore, this series of cases was modified to also flood the Celotex insulation with water and the results are presented in Table
: 21. In these cases, the Celotex is being replaced with water only, as the fissile solution is judged to remain in the primary and secondary containment vessels.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 40 of 90


Table 20. Filling 5-inch PCV and 6 -inch SCV with PuO 2, Carbon and Flooding Water
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 39 of 87 Table 21.
 
Filling 5-inch PCV and 6-inch SCV with PuO2 - Celotex Flooded Case No.
Case PuO2 No. Filename Description Density, keff keff +2 g/cc
Filename Description PuO2
: 1. nrc_su._PuO_fld_5PCV_C_ful.100.out PCV intact. CC, 3013 removed. PuO2 6.2065 0.5101 0.0009 0.512 dry. Added 1000 g Carbon.
: Density, g/cc keff keff +2
: 2. nrc_su._PuO_fld_5PCV_C_ful.110.out Same as #1 - 1 liter water added to 3.3232 0.6327 0.0014 0.636 PCV
: 1.
: 3. nrc_su._PuO_fld_5PCV_C_ful.120.out Same as #2 - 2 liters water added to 2.4948 0.7003 0.0015 0.704 PCV
nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.100.out PCV intact. CC, 3013 removed. PuO2 dry. Water between SCV-PCV.
: 4. nrc_su._PuO_fld_5PCV_C_ful.130.out Same as #2 - 3 liters water added to 2.1016 0.7399 0.0017 0.744 PCV
10.8921 0.6802 0.0013 0.683
: 5. nrc_su._PuO_fld_5PCV_C_ful.140.out Same as #2 - 4 liters water added to 1.8720 0.7597 0.0014 0.763 PCV 4.478 L water added to PCV (totally
: 2.
: 6. nrc_su._PuO_fld_5PCV_C_ful.4478.out full). PCV intact. CC and 3013 1.7930 0.7649 0.0015 0.768 removed.
nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.110.out Same as #1 - 1 liter water added to PCV 4.1131 0.7455 0.0013 0.749
 
: 3.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.120.out Same as #2 - 2 liters water added to PCV 2.8466 0.7955 0.0015 0.799
: 7. nrc_su._PuO_fld_6SCV_C_ful.5102.out PuO2 mixed with 1000 g carbon. 5.102 1.7090 0.7728 0.0015 0.776 L water added to PCV, solution spilling into SCV.
: 4.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.130.out Same as #2 - 3 liters water added to PCV 2.3123 0.8214 0.0016 0.825
: 8. nrc_su._PuO_fld_6SCV_C_ful.5398.out PuO2 mixed with 1000 g carbon. 5.398 1.6751 0.7812 0.0014 0.784 L water added to PCV, solution spilling into SCV.
: 5.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.140.out Same as #2 - 4 liters water added to PCV 2.0176 0.8346 0.0016 0.838
: 9. nrc_su._PuO_fld_6SCV_C_ful.5694.out PuO2 mixed with 1000 g carbon. 5.694 1.6443 0.7972 0.0016 0.801 L water added to PCV, solution spilling into SCV.
: 6.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.4826.out 4.826 L water added to PCV (totally full). PCV intact. CC and 3013 removed. Celotex flooded.
: 10. nrc_su._PuO_fld_6SCV_C_ful.5990.out PuO2 mixed with 1000 g carbon. 5.990 1.6161 0.8110 0.0016 0.815 L water added to PCV, solution spilling into SCV.
1.8584 0.8407 0.0016 0.844
PCV intact. CC and 3013 removed.
: 7.
: 11. nrc_su._PuO_fld_6SCV_C_ful.6342.out PuO2 mixed with 1000 g carbon. 6.342 1.5857 0.8180 0.0015 0.821 L water added to PCV, solution spilling into SCV.
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.5450.out PCV intact. CC and 3013 removed. 5.5450 L water added to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013 removed.
1.7675 0.8448 0.0014 0.848
12 nrc_su._PuO_fld_6SCV_C_ful.6775.out PuO2 mixed with 1000 g carbon. 6.775 1.5521 0.8198 0.0014 0.823 L water added to PCV, solution spilling into SCV.
: 8.
PCV intact. CC and 3013 removed.
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.5746.out PCV intact. CC and 3013 removed. 5.746 L water added to PCV, solution spilling into SCV. Celotex flooded.
PuO2 mixed with 1000 g carbon. 7.446
1.7308 0.8587 0.0015 0.862
: 13. nrc_su._PuO_fld_6SCV_C_ful.7446.out L water added to PCV, solution 1.5071 0.8183 0.0016 0.822 spilling into SCV. SCV completely full.
: 9.
 
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6042.out PCV intact. CC and 3013 removed. 6.042 L water added to PCV, solution spilling into SCV. Celotex flooded.
As can be seen from Figure 7 and Tables 18 through 20, the plutonium oxide mixed with water in the PCV and SCV remains subcritical as the added water causes the density of the solution to decrease by holding the mass of the plutonium oxide constant. All cases in Tables 18 through 20 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 38 of 87
1.6975 0.8875 0.0015 0.891
 
: 10.
initially havewater mixing with the plutonium oxide in the shipping package, creating a plutonium oxide solution in the PCV and water only in the SCV. As the PCV fil ls with solution, spillage fills the SCV u ntil totally fullwith the plutonium oxide solution.
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6338.out PCV intact. CC and 3013 removed. 6.338 L water added to PCV, solution spilling into SCV. Celotex flooded.
 
1.6670 0.9076 0.0015 0.911
The cases with the plutonium oxide solution filling the PCV are shown to be subcritical, achieving a maximum k eff + 2 = 0.814, Table 18, Case 6. In these cases, no plutonium oxide solution is in the SCV, only water from filling the shipping package.
: 11.
 
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.out PCV intact. CC and 3013 removed. 6.689 L water added to PCV, solution spilling into SCV. Celotex flooded.
As increasing amounts of water mix with the plutonium oxide in the shipping package, the PCV overflows filling the SCV with the plutonium oxide solution. Thus, you have plutonium oxide solution in the PCV as well as the SCV. The cases of filling the PCV and SCV with plutonium oxide solution remains below ksafe with a maximum at k eff + 2 = 0. 858, Table 18, Case 12. In this case (Table 18, Case 12), approximately 7.123 L water is added to the plutonium oxide in the shipping package, which completel y fills the PCV, but only partially fills the SCV, with plutonium oxide solution. Totally filling both the PCV and SCV (approximately 7.793 L water added to the plutonium oxide in the shipping package) with the plutonium oxide solution has also been demonstrated to be below ksafe with a k eff + 2 = 0. 855, Table 18, Case 13. In addition, when impurities (Be or C) are mixed with the oxide, the fissile mass of the mixture is reduced and consequently lowers the keff of the s ys t em, as shown in Tables 19 through 20.
1.6341 0.9124 0.0017 0.916
 
: 12.
To fully demonstrate that single package flooding is safely subcritical, additional models were developed to flood all of the remaining compartments of the 9975 shipping package. As shown in Table 18 through Table 20, the cases without impurities yielded the highest keff and have the SCV and PCV flooded with plutonium oxide solution. Theref ore, this series of cases was modified to also flood the Celotex insulation with water and the results are presented in Table
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.7123.out PCV intact. CC and 3013 removed. 7.123 L water added to PCV, solution spilling into SCV. Celotex flooded.
: 21. In these cases, the Celotex is being replaced with water onl y, as the fissile solution is judged to remain in the primar y and secondary containment vessel s.
1.5978 0.9096 0.0015 0.913
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 39 of 87
: 13.
 
nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.7793.out PCV intact. CC and 3013 removed. 7.793 L water added to PCV, solution spilling into SCV. SCV completely full.
Table 21. Filling 5-inch PCV and 6 -inch SCVwith PuO 2 - Celotex Flooded
 
Case PuO2 No. Fi lena me Description Density, keff keff +2 g/cc PCV intact. CC, 3013
: 1. nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.100.out removed. PuO2 dry. Water 10.8921 0.6802 0.0013 0.683 between SCV-PCV.
: 2. nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.110.out Same as #1 - 1 liter water 4.1131 0.7455 0.0013 0.749 added to PCV
: 3. nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.120.out Same as #2 - 2 liters water 2.8466 0.7955 0.0015 0.799 added to PCV
: 4. nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.130.out Same as #2 - 3 liters water 2.3123 0.8214 0.0016 0.825 added to PCV
: 5. nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.140.out Same as #2 - 4 liters water 2.0176 0.8346 0.0016 0.838 added to PCV 4.826 L wa t er added to PCV
: 6. nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.4826.out (totally full). PCV intact. CC 1.8584 0.8407 0.0016 0.844 and 3013 removed. Celotex flooded.
 
PCV intact. CC and 3013
: 7. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.5450.out removed. 5.5450 L wa t er 1.7675 0.8448 0.0014 0.848 added to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013
: 8. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.5746.out removed. 5.746 L wat er added 1.7308 0.8587 0.0015 0.862 to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013
: 9. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6042.out removed. 6.042 L wat er added 1.6975 0.8875 0.0015 0.891 to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013
: 10. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6338.out removed. 6.338 L wat er added 1.6670 0.9076 0.0015 0.911 to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013
: 11. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.out removed. 6.689 L wat er added 1.6341 0.9124 0.0017 0.916 to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013
: 12. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.7123.out removed. 7.123 L wat er added 1.5978 0.9096 0.0015 0.913 to PCV, solution spilling into SCV. Celotex flooded.
PCV intact. CC and 3013 removed. 7.793 L water added
: 13. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.7793.out to PCV, solution spilling into 1.5491 0.9086 0.0015 0.912 SCV. SCV completely full.
Celotex flooded.
Celotex flooded.
1.5491 0.9086 0.0015 0.912 As shown in Figure 7 and Table 21, for the series of cases with an additional layer of reflection created by replacing the Celotex with water, all cases remain subcritical. The highest keff + 2
= 0.916 (Table 21, Case 11) is achieved when approximately 6.689 L water is added to the Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 41 of 90


As shown in Figure 7 and Table 21, for the series of cases with an additional layer of reflection created b y replacing the Celotex with water, all cases remain subcritical. The highest k eff + 2
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 40 of 87 plutonium oxide in the shipping package, completely filling the PCV, but only partially filling the SCV, with plutonium oxide solution. In addition, Table 21 shows that adding approximately 7.793 L water to the plutonium oxide in the shipping package, completely filling the PCV and SCV with plutonium oxide solution, remains below ksafe with a keff + 2 = 0.912, Table 21, Case
= 0.916 (Table 21, Case 11) is achieved when approximately 6.689 L water is added to the 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 40 of 87
: 13.
 
plutonium oxide in the shipping package, completely filling the PCV, but only partially filling the SCV, with plutonium oxide solution. In addition, Table 21 shows that adding approximately 7.793 L water to the plutonium oxide in the shipping package, completely filling the PCV and SCV with plutonium oxide solution, remains below ksafe with a k eff + 2 = 0.912, Table 21, Case 13.
 
Therefore all keff + 2 values in Tables 8 through 21 are below ksafe of 0.943, which satisfies the 10 CFR 71.55(b) requirements related to a flooded single package.
Therefore all keff + 2 values in Tables 8 through 21 are below ksafe of 0.943, which satisfies the 10 CFR 71.55(b) requirements related to a flooded single package.
 
6.4 NORMAL CONDITIONS OF TRANSPORT ARRAY ANALYSES 10 CFR 71.55 contains the following requirements for NCT criticality safety analyses:
6.4 NORMAL CONDITIONS OF TRANSPORT ARRAY ANALYSES
(d) A package used for the shipment of fissile material must be so designed and constructed and its contents so limited that under the tests specified in § 71.71 ("Normal conditions of transport") --
 
10 CFR 71.55 contains the following requirements for NCT criticalit y safety analyses:
 
(d) A package used for the shipment of fissile material must be s o designed and constructed and its contents so limited that under the tests specified in § 71.71 ("Normal conditions of transport") --
(1) The contents would be subcritical; (2) The geometric form of the package contents would not be substantially altered; (3) There would be no leakage of water into the containment system unless, in the evaluation of undamaged packages under § 71.59(a)(1), it has been assumed that moderation is present to such an extent as to cause maximum reactivity consistent with the chemical and physical form of the material; and (4) There will be no substantial reduction in the effectiveness of the packaging, including:
(1) The contents would be subcritical; (2) The geometric form of the package contents would not be substantially altered; (3) There would be no leakage of water into the containment system unless, in the evaluation of undamaged packages under § 71.59(a)(1), it has been assumed that moderation is present to such an extent as to cause maximum reactivity consistent with the chemical and physical form of the material; and (4) There will be no substantial reduction in the effectiveness of the packaging, including:
(i) No more than 5 percent reduction in the total effective volume of the packaging on which nuclear safety is assessed; (ii) No more than 5 percent reduction in the effective spacing between the fissile contents and the outer surface of the packaging;
(i) No more than 5 percent reduction in the total effective volume of the packaging on which nuclear safety is assessed; (ii) No more than 5 percent reduction in the effective spacing between the fissile contents and the outer surface of the packaging; In the NCT undamaged drum array analysis, no water enters the PCV, 3013, or convenience can.
 
Thus, an infinite array of drums was analyzed with the convenience can containing dry plutonium oxide and 0.5% water fissile mixture, with or without the 3013 containers and additional cases with the Celotex flooded. As mentioned earlier, all array analyses were performed using the 7% reduced drum radius to utilize an equivalent rectangular array configuration.
In the NCT undamaged drum array anal ysis, no water enter s the PCV, 3013, or convenience can.
Table 22 presents the NCT results.
Thus, an infinite array of drums was anal yzed with the convenience can containing dry plutonium oxide and 0.5% water fissile mixture, with or without the 3013 containers and additional cases with the Celotex flooded. As mentioned earlier, all array anal yses were performed using the 7% reduced drum radius to utilize an equivalent rectangular array configuration.
Table 22.
 
9975 Array Model - NCT Cases Case No.
Table 22 presents t he NCT results.
File ID Description keff keff
 
+2
Table 22. 9975 Array Model - NCT Cases
 
Case keff No. File ID Description keff +2
: 1. nrc_nct.cyl3013.out Infinite drum array, dry fissile material 0.6520 0.0011 0.655
: 1. nrc_nct.cyl3013.out Infinite drum array, dry fissile material 0.6520 0.0011 0.655
: 2. nrc_nct.cyl3013_celofld.out Same as #1 water as Celotex 0.6099 0.0010 0.612 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 41 of 87
: 2. nrc_nct.cyl3013_celofld.out Same as #1 water as Celotex 0.6099 0.0010 0.612 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 42 of 90


Case keff No. File ID Description keff +2
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 41 of 87 Case No.
File ID Description keff keff
+2
: 3. nrc_nct.cyl3013_h2orefl.out Same as #1 w/water between drums 0.6102 0.0009 0.613
: 3. nrc_nct.cyl3013_h2orefl.out Same as #1 w/water between drums 0.6102 0.0009 0.613
: 4. nrc_nct.cyl3013_h2orefl_celofld.out Same as #1 w/water between drums, water as Celotex 0.6099 0.0010 0.612 Infinite drum array, dry
: 4. nrc_nct.cyl3013_h2orefl_celofld.out Same as #1 w/water between drums, water as Celotex 0.6099 0.0010 0.612
: 5. nrc_nct.cylno3013.out fissile material, no 3013 0.6524 0.0011 0.655 containers
: 5. nrc_nct.cylno3013.out Infinite drum array, dry fissile material, no 3013 containers 0.6524 0.0011 0.655
: 6. nrc_nct.cylno3013_celofld.out Same as #5, water as Celotex 0.6046 0.0010 0.607
: 6. nrc_nct.cylno3013_celofld.out Same as #5, water as Celotex 0.6046 0.0010 0.607
: 7. nrc_nct.cylno3013_h2orefl.out Same as #5, w/water between drums 0.6049 0.0012 0.608
: 7. nrc_nct.cylno3013_h2orefl.out Same as #5, w/water between drums 0.6049 0.0012 0.608
: 8. nrc_nct.cylno3013_h2orefl_celofld.out Same as #5 w/water between drums, water as Celotex 0.6042 0.0010 0.607
: 8. nrc_nct.cylno3013_h2orefl_celofld.out Same as #5 w/water between drums, water as Celotex 0.6042 0.0010 0.607 The cases in Table 22 demonstrate that the 9975 with plutonium oxide in convenience can, with and without the 3013 container, in dry conditions, is subcritical with the highest keff + 2 of 0.655 for a dry system (Cases 1 and 5). As the water is added to the Celotex and in between the shipping packages in an array, interaction is reduced, thus reducing the keff of the system as indicated in Table 21. Thus, water flooding of the Celotex is subcritical.
 
Therefore all keff + 2 values in Table 22 are below the ksafe of 0.943, which satisfies the 10 CFR 71.55(d) and 71.59(a)(1) requirements related to NCT analyses.
The cases in Table 22 demonstrate that the 9975 with plutonium oxide in convenience can, with and without the 3013 container, in dry conditions, is subcritical with the highest k eff + 2 of 0.655 for a dr y s ystem (Cases 1 and 5). As the water is added to the Celotex and in between the shipping packages in an array, interaction is reduced, thus reducing the keff of the system as indicated in Table 21. Thus, water flooding of the Celotex is subcritical.
6.5 HYPOTHETICAL ACCIDENT CONDITIONS ANALYSES 10 CFR 71.55 contains the following requirements for HAC criticality safety analyses:
 
Therefore all keff + 2 values in Table 22 are below the k safe of 0.943, which satisfies the 10 CFR 71.55(d) and 71.59(a)(1) requirements related to NCT analyses.
 
6.5 HYPOTHETICAL ACCIDENT CONDITIONS ANALYSES
 
10 CFR 71.55 contains the following requirements for HAC criticality safety analyses:
 
(e) A package used for the shipment of fissile material must be so designed and constructed and its contents so limited that under the tests specified in § 71.73 ("Hypothetical accident conditions"), the package would be subcritical. For this determination, it must be assumed that:
(e) A package used for the shipment of fissile material must be so designed and constructed and its contents so limited that under the tests specified in § 71.73 ("Hypothetical accident conditions"), the package would be subcritical. For this determination, it must be assumed that:
(1) The fissile material is in the most reactive credible configuration consistent with the damaged condition of the package and the chemical and physical form of the contents; (2) Water moderation occurs to the most reactive credible extent consistent with the damaged condition of the package and the chemical and physical form of the contents; and (3) There is full reflection by water on all sides, as close as is consistent with the damaged condition of the package.
(1) The fissile material is in the most reactive credible configuration consistent with the damaged condition of the package and the chemical and physical form of the contents; (2) Water moderation occurs to the most reactive credible extent consistent with the damaged condition of the package and the chemical and physical form of the contents; and (3) There is full reflection by water on all sides, as close as is consistent with the damaged condition of the package.
In the HAC analysis, damaged units are arranged in various configurations to demonstrate a most reactive configuration. The damaged HAC array model used a conservative radial and axial drum dimension reduction to address a drop and the amount of Celotex charred due to fire (see Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 43 of 90


In the HAC anal ysis, damaged units are arranged in various configurations to demonstrate a most reactive configuration. The damaged HAC array model used a conservative radial and axial drum dimension reduction to address a drop and the amount of Celotex charred due to fire (see 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 42 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 42 of 87 Table 7). A conservative infinite array, modeled as an infinite array of 2x2x2 clusters, was developed where the fissile material was moved together as close as possible. This model brought a cluster of four drums, stacked two high (eight packages total), to its closest contact position. In other words, although not credible, the radial movement is such that four drums together form the closest configuration (a quadrupole arrangement), as shown in Figure 8.
 
Figure 8.
Table 7). A conservative infinite array, modeled as an infinite array of 2x2x2 clusters, was developed where the fissile material was moved together as close as possible. This model brought a cluster of four drums, stacked two high (eight packages total), to its closest contact position. In other words, although not credible, the radial movement is such that four drums together form the closest configuration (a quadrupole arrangement), as shown in Figure 8.
2x2x2 Closest Contact Model (Case 1)
 
Figure 8. 2x2x2 Closest Contact Model (Case 1)
 
These models assume that the Celotex loss is localized around the periphery of the drum, and the 9975 is dropped during the accident. The inner containment (convenience can/3013/PCV/SCV) is moved inside the Celotex (keeping the Celotex volume constant) such that the lead shield is touching the drum at one point.
These models assume that the Celotex loss is localized around the periphery of the drum, and the 9975 is dropped during the accident. The inner containment (convenience can/3013/PCV/SCV) is moved inside the Celotex (keeping the Celotex volume constant) such that the lead shield is touching the drum at one point.
Although the close contact HAC model (Figure 8, Case 1) minimizes fissile spacing between the payloads in as many as eight packages, it increases fissile spacing between those packages and the packages surrounding them. Thus, it is not entirely obvious that a HAC model that only accounts for the destruction of Celotex but includes none of the material movements, is less reactive or not. Therefore, an additional symmetrical model was also developed (Figure 9, Case 5) to help determine the most reactive configuration. Case 5 (symmetrical model) is a damaged array scenario with the Celotex, containment, and fissile material in its normal, centered orientation, but the destruction of Celotex due to fire and reduction of drum diameter due to impact are included.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 44 of 90


Although the close contact HAC model (Figure 8, Case 1) minimizes fissile spacing between the payloads in as man y as eight packages, it increases fissile spacing between those packages and the packages surrounding them. Thus, it is not entirely obvious that a HAC model that only accounts for the destruction of Celotex but includes none of the material movements, is less reactive or not. Therefore, an additional s ymmetrical model was also developed (Figure 9, Case 5) to help determine the most reactive configuration. Case 5 (symmetrical model) is a damaged array scenario with the Celotex, containment, and fissile material in its normal, centered orientation, but the destruction of Celotex due to fire and reduction of drum diameter due to impact are included.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 43 of 87 Figure 9.
 
2x2x2 Symmetrical Model (Case 5)
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 43 of 87
Table 23 presents the HAC results.
 
Table 23.
Figure 9. 2x2x2 Symmetrical Model (Case 5)
9975 Array Model - HAC Cases Case No.
 
File ID Description keff keff +2
Table 23 presents t he HAC results.
 
Table 23. 9975 Array Model - HAC Cases
 
Case No. File ID Description keff keff +2
: 1. nrc_hac.cyl3013_2x2x2.out 2x2x2 cluster, inifinite array Fissile at closest position 0.7346 0.0011 0.737
: 1. nrc_hac.cyl3013_2x2x2.out 2x2x2 cluster, inifinite array Fissile at closest position 0.7346 0.0011 0.737
: 2. nrc_hac.cyl3013_2x2x2_PCVfl.out Same as #1, PCV flooded 0.7209 0.0012 0.724
: 2. nrc_hac.cyl3013_2x2x2_PCVfl.out Same as #1, PCV flooded 0.7209 0.0012 0.724
Line 797: Line 803:
: 6. nrc_hac.cyl3013_2x2x2_PCVfl_symm.out Same as #5, PCV flooded 0.7135 0.0010 0.716
: 6. nrc_hac.cyl3013_2x2x2_PCVfl_symm.out Same as #5, PCV flooded 0.7135 0.0010 0.716
: 7. nrc_hac.cyl3013_2x2x2_PCVSCVfl_symm.out Same as #5, PCV/SCV flooded 0.7008 0.0011 0.703
: 7. nrc_hac.cyl3013_2x2x2_PCVSCVfl_symm.out Same as #5, PCV/SCV flooded 0.7008 0.0011 0.703
: 8. nrc_hac.cyl3013_2x2x2_SCVfl_symm.out Same as #5, SCV flooded 0.7065 0.0013 0.710
: 8. nrc_hac.cyl3013_2x2x2_SCVfl_symm.out Same as #5, SCV flooded 0.7065 0.0013 0.710 Table 23 shows that all keff + 2 values are less than ksafe for the damaged array cases. This demonstrates that moving the fissile units closer together (Case 1, the bounding closest position case) only produces a slightly higher keff than when all of the fissile units are centered within the 9975 shipping package (Case 5, the bounding centered position case), on the order of 1.6%
 
difference. Thus, the base HAC model, the infinite array of 2x2x2 clusters with the fissile material units closest together (Case 1) within the array has the highest keff + 2 of 0.737.
Table 23 shows that all k eff + 2 values are less than k safe for the damaged array cases. This demonstrates that moving the fissile units closer together (Case 1, the bounding closest position case) onl y produces a slightl y higher keff than when all of the fissile units are centered with in the 9975 shipping package (Case 5, the bounding centered position case), on the order of 1.6%
Table 24.
difference. Thus, the base HAC model, the infinite array of 2x2x2 clusters with the fissile material units closest together (Case 1) within the array has the highest k eff + 2 of 0.737.
9975 Array Model - Flooded Convenience Can HAC Cases Case No.
 
File ID Description keff keff +2
Table 24. 9975 Array Model - Flooded Convenience Can HAC Cases
: 1. nrc_hac.cyl_CCfl_2x2x2.out:
 
Convenience can flooded Fissile at closest position 0.9149 0.0014 0.918
Case No. File ID Description keff keff +2
: 2. nrc_hac.cyl_CCfl_3013fl.out:
: 1. nrc_hac.cyl_CCfl_2x2x2.out: Convenience can flooded Fissile at closest position 0.9149 0.0014 0.918
Same as #1, 3013 flooded 0.9349 0.0013 0.938
: 2. nrc_hac.cyl_CCfl_3013fl.out: Same as #1, 3013 flooded 0.9349 0.0013 0.938
: 3. nrc_hac.cyl_CCfl_allfl.out:
: 3. nrc_hac.cyl_CCfl_allfl.out: Same as #1, 3013, PCV, SCV, water as Celotex 0.7875 0.0013 0.791
Same as #1, 3013, PCV, SCV, water as Celotex 0.7875 0.0013 0.791
: 4. nrc_hac.cyl_CCfl_3013dry_PCVSCVfl.out: Same as #1, 3013 dry, PCV, SCV flooded 0.8443 0.0015 0.848
: 4. nrc_hac.cyl_CCfl_3013dry_PCVSCVfl.out:
: 5. nrc_hac.cyl_CCfl_3013dry_allfl.out: Same as #1, 3013 dry, PCV, SCV, water as Celotex 0.7647 0.0014 0.768 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 44 of 87
Same as #1, 3013 dry, PCV, SCV flooded 0.8443 0.0015 0.848
: 6. nrc_hac.cyl_CCL_2x2x2_symm.out: Convenience can flooded Fissile at centered position 0.9038 0.0016 0.907
: 5. nrc_hac.cyl_CCfl_3013dry_allfl.out:
 
Same as #1, 3013 dry, PCV, SCV, water as Celotex 0.7647 0.0014 0.768 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 45 of 90
A conservative anal ysis was performed, with the results provided in Table 24, flooding the 9975 shipping package to the fullest extent while modeled as an infinite array. Various models were developed that flooded the different compartments (i.e., 3013, PCV, SCV, Celotex) of the 9975 shipping package, while flooding the convenience can containing the fissile solution. As seen in Table 23, for the base HAC analysis, the co nfiguration with the fissile units at their closest position (Table 23, Case 1) yields the highest keff + 2 which also hold true for the cases with the convenience can flooded. Thus, the study on flooding the 9975 shipping package compartments, Table 24, used this as the base case configuration. As shown in Table 24, the case where the convenience can/3013 configuration was flooded while the remainder of the 9975 shipping package remains dry (Case 2) yields a k eff + 2 of 0.938.
 
Therefore all k eff + 2 values for the HAC array analysis as shown in Table 23 and Table 24 are below the ksafe of 0.943, which satisfies the 10 CFR 71.55(e) and 71.59(a)(2) requirements related to HAC anal yses.
 
6.6 CRITICALITY SAFETY INDEX
 
The calculation of the Criticality Safet y Index (CSI) for the 9975 shipping package is required to follow the explicit equations specified in 10 CFR 71.59:


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 44 of 87
: 6. nrc_hac.cyl_CCL_2x2x2_symm.out:
Convenience can flooded Fissile at centered position 0.9038 0.0016 0.907 A conservative analysis was performed, with the results provided in Table 24, flooding the 9975 shipping package to the fullest extent while modeled as an infinite array. Various models were developed that flooded the different compartments (i.e., 3013, PCV, SCV, Celotex) of the 9975 shipping package, while flooding the convenience can containing the fissile solution. As seen in Table 23, for the base HAC analysis, the configuration with the fissile units at their closest position (Table 23, Case 1) yields the highest keff + 2 which also hold true for the cases with the convenience can flooded. Thus, the study on flooding the 9975 shipping package compartments, Table 24, used this as the base case configuration. As shown in Table 24, the case where the convenience can/3013 configuration was flooded while the remainder of the 9975 shipping package remains dry (Case 2) yields a keff + 2 of 0.938.
Therefore all keff + 2 values for the HAC array analysis as shown in Table 23 and Table 24 are below the ksafe of 0.943, which satisfies the 10 CFR 71.55(e) and 71.59(a)(2) requirements related to HAC analyses.
6.6 CRITICALITY SAFETY INDEX The calculation of the Criticality Safety Index (CSI) for the 9975 shipping package is required to follow the explicit equations specified in 10 CFR 71.59:
(a) A fissile material package must be controlled by either the shipper or the carrier during transport to assure that an array of such packages remains subcritical. To enable this control, the designer of a fissile material package shall derive a number "N" based on all the following conditions being satisfied, assuming packages are stacked together in any arrangement and with close full reflection on all sides of the stack by water:
(a) A fissile material package must be controlled by either the shipper or the carrier during transport to assure that an array of such packages remains subcritical. To enable this control, the designer of a fissile material package shall derive a number "N" based on all the following conditions being satisfied, assuming packages are stacked together in any arrangement and with close full reflection on all sides of the stack by water:
(1) Five times "N" undamaged packages with nothing between the packages would be subcritical; (2) Two times "N" damaged packages, if each package were subjected to the tests specified in § 71.73 ("Hypothetical accident conditions") would be subcritical with optimum interspersed hydrogenous moderation; and (3) The value of "N" cannot be less than 0.5.
(1) Five times "N" undamaged packages with nothing between the packages would be subcritical; (2) Two times "N" damaged packages, if each package were subjected to the tests specified in § 71.73 ("Hypothetical accident conditions") would be subcritical with optimum interspersed hydrogenous moderation; and (3) The value of "N" cannot be less than 0.5.
(b) The CSI must be determined by dividing the number 50 by the value of "N" derived using the procedures specified in paragraph (a) of this section. The value of the CSI may be zero provided that an unlimited number of packages are subcritical, such that the value of "N" is effectivel y equal to infinity under the procedures specified in paragraph (a) of this section.
(b) The CSI must be determined by dividing the number 50 by the value of "N" derived using the procedures specified in paragraph (a) of this section. The value of the CSI may be zero provided that an unlimited number of packages are subcritical, such that the value of "N" is effectively equal to infinity under the procedures specified in paragraph (a) of this section.
Any CSI greater than zero must be rounded up to the first decimal place.
Any CSI greater than zero must be rounded up to the first decimal place.
(c) For a fissile material package which is assigned a CSI value--
(c) For a fissile material package which is assigned a CSI value--
(1) Less than or equal to 50, that package may be shipped by a carrier in a nonexclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 50.
(1) Less than or equal to 50, that package may be shipped by a carrier in a nonexclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 50.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 45 of 87
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 46 of 90


(2) Less than or equal to 50, that package may be shipped by a carrier in an exclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 100.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 45 of 87 (2) Less than or equal to 50, that package may be shipped by a carrier in an exclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 100.
(3) Greater than 50, that package must be shipped by a carrier in an exclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 100.
(3) Greater than 50, that package must be shipped by a carrier in an exclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 100.
 
The CSI is conservatively computed for both the NCT and HAC, with the CSI calculation shown in Table 25.
The C S I is conservatively computed for both the NCT and HAC, with the CSI calculation shown in Table 25.
Table 25.
 
CSI Calculation Calculate the value of N for NCT:
Table 25. CSI Calculation
5*N = (infinite), so N = /5 =
 
The CSI is defined by 10 CFR 71.59 as, CSI 50/N = 50/ = 0.0 Rounding up to the first decimal we get, CSI = 0.0 Calculate the value of N for HAC:
Calculate the value of N for NCT: Calculate the value of N for HAC:
2*N = (infinite), so N = /2 =
 
The CSI is defined by 10 CFR 71.59 as, CSI 50/N = 50/ = 0.0 Rounding up to the first decimal we get, CSI = 0.0 The CSI calculation in Table 25 derives a CSI in the infinite array NCT and HAC configurations equal to 0.0 for the 9975 package with the plutonium oxide content envelope, as specified in Section 2.2.
5*N = (infinite), so N = / 5 = 2*N = (infinite), so N = /2 =  
7.0 ADMINISTRATIVELY CONTROLLED LIMITS AND REQUIREMENTS The following limits apply to the 9975 shipping packages evaluated in this analysis:
 
The CSI is defined by 10 CFR 71.59 as, The CSI is defined by 10 CFR 71.59 as,
 
CSI 50/N = 50/ = 0.0 CSI 50/N = 50/ = 0.0
 
Rounding up to the first decimal we get, Rounding up to the first decimal we get,
 
CSI = 0.0 CSI = 0.0
 
The CSI calculation in Table 25 derives a C S I in the infinite arr a y NCT and HAC configurations equal to 0.0 for the 9975 package with the plutonium oxide content envelope, as specified in Section 2.2.
 
7.0 ADMINISTRATIVELY CONTROLLED LIMITS AND REQUIREMENTS
 
The following limits apply to the 9975 shipping packages evaluated in this analysis:
: 1. The 9975 shipping package shall be used to transport the plutonium oxide material which has the content envelope described in Table 2 and shown again in Table 26.
: 1. The 9975 shipping package shall be used to transport the plutonium oxide material which has the content envelope described in Table 2 and shown again in Table 26.
Table 26.
Plutonium Oxide Contents Material Mass (kg)
PuO2 5.0 Beryllium 0.5 Carbon 1.0
*The 5.0 kg is the maximum payload for the shipping package. The addition of the beryllium or carbon reduces the fissile content.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 47 of 90


Table 26. Plutonium Oxide Contents
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 46 of 87 8.0  
 
Material Mass (kg)
PuO2 5.0 Beryllium 0.5 Carbon 1.0
*The 5.0 kg is the maximum payload for the shipping package. The addition of the b eryllium or c arbon reduces the fissile content.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 46 of 87
 
8.0  


==SUMMARY==
==SUMMARY==
AND CONCLUSIONS
AND CONCLUSIONS An evaluation was performed to address shipping the plutonium oxide content envelope, as specified in Section 2.2, in the 9975 shipping package.
 
Based on the analysis performed in Section 6.0, an infinite array of 9975 shipping packages with a 5.0 kg plutonium oxide content envelope is subcritical provided the limits and controls in Section 7.0 are maintained.
An evaluation was performed to address shipping the plutonium oxide content envelope, as specified in Section 2.2, in the 9975 shipping package.
This NCSE has demonstrated that 9975 shipping packages can be safely shipped carrying the plutonium oxide contents as described in Table 26, with a CSI of 0.0.  
 
Based on the anal ysis performed in Section 6.0, an infinite array of 9975 shipping packages with a 5.0 kg plutonium oxide content envelope is subcritical provided the limits and controls in Section 7.0 are maintained.
 
This NCSE has demonstrated that 9975 shipping packages can be safely shipped carr ying the plutonium oxide contents as described in Table 2 6, with a CSI of 0.0.


==9.0 REFERENCES==
==9.0 REFERENCES==
10 CFR 71, Packaging and Transportation of Radioactive Material, U.S. Nuclear Regulator y Commission, Washington, DC, January 2012.
10 CFR 71, Packaging and Transportation of Radioactive Material, U.S. Nuclear Regulatory Commission, Washington, DC, January 2012.
 
ANSI/ANS-8.1-1998, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, 1998.
ANSI/ANS-8.1-1998, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, 1998.
ASTM A312, Specification for Seamless and Welded Austenitic Stainless Steel Pipes, American Society for Testing and Materials, 1995.
ASTM A312, Specification for Seamless and Welded Austenitic Stainless Steel Pipes, American Society for Testing and Materials, 1995.
 
N-NCS-F-00087, Rev. 2, 9975 Shipping Container Analysis with Revised Contents for SARP, Revision 0 (U), Biswas, D., Westinghouse Safety Management Solutions, LLC, Aiken, SC, October 2003.
N-NCS-F-00087, Rev. 2, 9975 Shipping Container Analysis with Revised Contents for SARP, Revision 0 (U ), Biswas, D., Westinghouse Safety Management Solutions, LLC, Aiken, SC, October 2003.
 
NUREG/CR-5661, ORNL/TM-11936, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, Oak Ridge National Laboratory, Oak Ridge, TN, April 1997.
NUREG/CR-5661, ORNL/TM-11936, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, Oak Ridge National Laboratory, Oak Ridge, TN, April 1997.
 
ORNL/TM-12370, The LAW-238 Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations, Green, N.M., et al., Oak Ridge National Laboratory, Oak Ridge, TN, August 1994.
OR N L/ TM-12370, The LAW -238 Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations, Green, N.M., et al., Oak Ridge National Laboratory, Oak Ridge, TN, August 1994.
ORNL/TM-2005/39, Version 5, SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, Petrie, L.M., et al., Oak Ridge National Laboratory, Oak Ridge, TN, April 2005.
 
OR N L/ TM-2005/39, Version 5, SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, Petrie, L.M., et al., Oak Ridge National Laboratory, Oak Ridge, TN, April 2005.
 
SCD-3, Rev. 27, Nuclear Criticality Safety Manual (U), Savannah River Nuclear Solutions, Aiken, SC, December 2012.
SCD-3, Rev. 27, Nuclear Criticality Safety Manual (U), Savannah River Nuclear Solutions, Aiken, SC, December 2012.
SRNS-IM-2009-00035, Rev. 2, Criticality Safety Methods Manual, Savannah River Nuclear Solutions, Aiken, SC, September 2012.
SRNS-IM-2009-00035, Rev. 2, Criticality Safety Methods Manual, Savannah River Nuclear Solutions, Aiken, SC, September 2012.
SRNS-RP-2008-00150, Revision 1, Software Configuration and Control Guidance for SCALE on SRS Personal Computers (U), Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, May 2011.
SRNS-RP-2008-00150, Revision 1, Software Configuration and Control Guidance for SCALE on SRS Personal Computers (U), Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, May 2011.
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 47 of 87
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 48 of 90


SRNS-RP-2008-00151, Revision 1, SCALE Test Report for SRS Personal Computers (U),
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 47 of 87 SRNS-RP-2008-00151, Revision 1, SCALE Test Report for SRS Personal Computers (U),
Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, May 2011.
Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, May 2011.
SRNS-RP-2008-00153, Rev. 0, SCALE 5.0 Validation for SRNS Personal Computers (U),
SRNS-RP-2008-00153, Rev. 0, SCALE 5.0 Validation for SRNS Personal Computers (U),
Abney, L.M. and Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, January 2009.
Abney, L.M. and Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, January 2009.
WSRC-SA-7, Revision 14, Safety Analysis Report - Packages 9965, 9968, 9972 - 9975 Packages (U), Westinghouse Savannah River Company, Aiken, SC, October 2002.
WSRC-SA-7, Revision 14, Safety Analysis Report - Packages 9965, 9968, 9972 - 9975 Packages (U), Westinghouse Savannah River Company, Aiken, SC, October 2002.
WSRC-TR-2000-00444, Celotex Structural Properties Tests (U), Smith, C., and Vormelker, P.R., Savannah River National Laboratory, Aiken, SC, December 2000.
WSRC-TR-2000-00444, Celotex Structural Properties Tests (U), Smith, C., and Vormelker, P.R., Savannah River National Laboratory, Aiken, SC, December 2000.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 49 of 90


9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 48 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 48 of 87 APPENDIX A SENSITIVITY STUDIES
 
: 1. Variation of keff with Celotex density Celotex density is varied to determine the effect of Celotex density on keff. The density may vary substantially (WSRC-TR-2000-00444, Celotex Structural Properties Tests (U)).
APPENDIX A SENSITIVITY STUDIES
Table A1.1 shows that keff increases significantly with a reduction in Celotex density in the array scenario. This nominal density of Celotex is 0.24 g/cc and the density variation ranges from 0.22 g/cc to 0.26 g/cc (WSRC-TR-2000-00444). Therefore, a conservative Celotex density of 0.20 g/cc is chosen for this analysis.
: 1. Variation of keff with Celotex density
Table A1.1.
 
Variation of keff with Celotex Density Case No.
Celotex density is varied to determine the effect of Celotex density on keff. The densit y may vary substantially (WSRC-TR-2000-00444, Celotex Structural Properties Tests (U) ).
File ID Celotex Density (g/cc) keff keff +2
Table A1.1 shows that k eff increases significantly with a reduction in Celotex den sity in the array scenario. This nominal density of Celotex is 0.24 g/cc and the density variation ranges from 0.22 g/cc to 0.26 g/cc (WSRC -TR-2000-00444). Therefore, a conservative Celotex density of 0.20 g/cc is chosen for this analysis.
: 1. nrc_nct.cyl_celo_den_0.02.out:
 
NCT case, No 3013, Dry, Infinite array - 0.02 Density 0.97670 0.00120 0.980
Table A1.1. Variation of keff with Celotex Density
: 2. nrc_nct.cyl_celo_den_0.04.out:
 
Same as #1, Density 0.04 0.83600 0.00120 0.839
Case No. File ID Celotex Density (g/cc) keff keff +2
: 3. nrc_nct.cyl_celo_den_0.06.out:
: 1. nrc_nct.cyl_celo_den_0.02.out: NCT case, No 3013, Dry, Infinite array - 0.02 Density 0.97670 0.00120 0.980
Same as #1, Density 0.06 0.76810 0.00110 0.771
: 2. nrc_nct.cyl_celo_den_0.04.out: Same as #1, Density 0.04 0.83600 0.00120 0.839
: 4. nrc_nct.cyl_celo_den_0.08.out:
: 3. nrc_nct.cyl_celo_den_0.06.out: Same as #1, Density 0.06 0.76810 0.00110 0.771
Same as #1, Density 0.08 0.73130 0.00120 0.734
: 4. nrc_nct.cyl_celo_den_0.08.out: Same as #1, Density 0.08 0.73130 0.00120 0.734
: 5. nrc_nct.cyl_celo_den_0.10.out:
: 5. nrc_nct.cyl_celo_den_0.10.out: Same as #1, Density 0.10 0.70720 0.00110 0.710
Same as #1, Density 0.10 0.70720 0.00110 0.710
: 6. nrc_nct.cyl_celo_den_0.12.out: Same as #1, Density 0.12 0.68970 0.00100 0.692
: 6. nrc_nct.cyl_celo_den_0.12.out:
: 7. nrc_nct.cyl_celo_den_0.14.out: Same as #1, Density 0.14 0.67591 0.00097 0.678
Same as #1, Density 0.12 0.68970 0.00100 0.692
: 8. nrc_nct.cyl_celo_den_0.16.out: Same as #1, Density 0.16 0.66620 0.00120 0.669
: 7. nrc_nct.cyl_celo_den_0.14.out:
: 9. nrc_nct.cyl_celo_den_0.18.out: Same as #1, Density 0.18 0.65730 0.00100 0.660
Same as #1, Density 0.14 0.67591 0.00097 0.678
: 10. nrc_nct.cyl_celo_den_0.20.out: Same as #1, Density 0.20 0.65240 0.00100 0.655
: 8. nrc_nct.cyl_celo_den_0.16.out:
: 11. nrc_nct.cyl_celo_den_0.22.out: Same as #1, Density 0.22 0.64870 0.00100 0.651
Same as #1, Density 0.16 0.66620 0.00120 0.669
: 12. nrc_nct.cyl_celo_den_0.24.out: Same as #1, Density 0.24 0.64330 0.00100 0.646
: 9. nrc_nct.cyl_celo_den_0.18.out:
: 13. nrc_nct.cyl_celo_den_0.26.out: Same as #1, Density 0.26 0.63763 0.00097 0.640
Same as #1, Density 0.18 0.65730 0.00100 0.660
: 2. Variation of Stainless Steel Composition
: 10. nrc_nct.cyl_celo_den_0.20.out:
 
Same as #1, Density 0.20 0.65240 0.00100 0.655
Several kinds of stainless steel are used in the 9975/3013 system. To simplify the anal ysis, a standard composition of stainless steel corresponding to SS 304 from ORNL/TM -2005/39 is used. Table A1.2 shows the composition of several different types of stainless steel used in 9975/3013 components. It should be noted that there is a small variation of elemental compositions and density for each t ype of stainless steel. Table A1.3 shows the keff results for the base case of a NCT scenario using different stainless steel composition and another case with a variation in stainless steel density.
: 11. nrc_nct.cyl_celo_den_0.22.out:
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 49 of 87
Same as #1, Density 0.22 0.64870 0.00100 0.651
 
: 12. nrc_nct.cyl_celo_den_0.24.out:
Table A1.2. Stainless Steel Composition
Same as #1, Density 0.24 0.64330 0.00100 0.646
: 13. nrc_nct.cyl_celo_den_0.26.out:
Same as #1, Density 0.26 0.63763 0.00097 0.640
: 2. Variation of Stainless Steel Composition Several kinds of stainless steel are used in the 9975/3013 system. To simplify the analysis, a standard composition of stainless steel corresponding to SS 304 from ORNL/TM-2005/39 is used. Table A1.2 shows the composition of several different types of stainless steel used in 9975/3013 components. It should be noted that there is a small variation of elemental compositions and density for each type of stainless steel. Table A1.3 shows the keff results for the base case of a NCT scenario using different stainless steel composition and another case with a variation in stainless steel density.
Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 50 of 90


SS 304 SS 304L SS-316 Ele ment SCALE ID (wt. %) (wt. %) (wt. %)
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 49 of 87 Table A1.2.
Fe 26304 68.375 67.895 65.375 Cr 24304 19.00 19.00 17.00 Ni 28304 9.50 10.00 12.00 Mo 42000 - 2.50 Mn 25055 2.00 2.00 2.00 Si 14000 1.00 1.00 1.00 C 6012 0.08 0.030 0.08 P 15031 0.045 0.045 0.045 S 16000 0.03 0.03 -
Stainless Steel Composition Element SCALE ID SS 304 (wt. %)
total 100.00 100.00 100.00 Density g/cc 7.92++ 7.90 8.03
SS 304L (wt. %)
SS-316 (wt. %)
Fe 26304 68.375 67.895 65.375 Cr 24304 19.00 19.00 17.00 Ni 28304 9.50 10.00 12.00 Mo 42000 2.50 Mn 25055 2.00 2.00 2.00 Si 14000 1.00 1.00 1.00 C
6012 0.08 0.030 0.08 P
15031 0.045 0.045 0.045 S
16000 0.03 0.03 total 100.00 100.00 100.00 Density g/cc 7.92++
7.90 8.03  
  ++Note: ORNL/TM-2005/39 specifies the density of SS 304 as 7.94 g/cc. A density value of 7.92 g/cc was used in this analysis. The variation in steel density is shown to be negligible in Table A1.3.
  ++Note: ORNL/TM-2005/39 specifies the density of SS 304 as 7.94 g/cc. A density value of 7.92 g/cc was used in this analysis. The variation in steel density is shown to be negligible in Table A1.3.
Table A1.3.
Variation of keff with Stainless Steel Composition Case No.
File ID Description keff keff +2
: 1. nrc_nct.cylno3013.out:
NCT case, No 3013, Dry, Infinite array - SS 304 (7.92 g/cc) 0.65240 0.00110 0.655
: 2. nrc_nct.cylno3013_SS304_0.94.out:
Same as #1, SS 304 (7.94 g/cc) 0.65030 0.00120 0.653
: 3. nrc_nct.cylno3013_SS304L.out:
Same as #1, SS 304L 0.65200 0.00100 0.654
: 4. nrc_nct.cylno3013_SS316.out:
Same as #1, SS 316 0.64960 0.00100 0.652 Table A1.3 shows that the variation in keff by using different types of stainless steel is insignificant (within 1). It should be noted that for each of the models, it is assumed that all steel components are made of one kind of stainless steel.
: 3. Variation of Dimensional Tolerances on PCV and SCV The effect of uncertainties in the thickness of the PCV and SCV on the calculated keff was also considered in this analysis. The ASTM A312 standard indicates a tolerance of +22.5% /
-12.5% on the wall thickness and a tolerance of +1/16 / -1/32 inch on the outer diameter. This evaluation performed an analysis and determined that there is no statistical significance Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 51 of 90


Table A1.3. Variation of keff with Stainless Steel Composition
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 50 of 87 among the keff values calculated with nominal, minimum, and maximum wall thickness (Table A1.4). Therefore the nominal dimensions of PCV and SCV are used in this analysis.
 
Table A1.4.
Case No. File ID Description keff keff +2
Variation of Dimensional Tolerances on PCV and SCV - Single Unit Case No.
: 1. nrc_nct.cylno3013.out: NCT case, No 3013, Dry, Infinite array - SS 304 (7.92 g/cc) 0.65240 0.00110 0.655
File ID Description keff keff +2
: 2. nrc_nct.cylno3013_SS304_0.94.out: Same as #1, SS 304 (7.94 g/cc) 0.65030 0.00120 0.653
: 1. nrc_su.cyl3013.out: (From Table 8)
: 3. nrc_nct.cylno3013_SS304L.out: Same as #1, SS 304L 0.65200 0.00100 0.654
Nominal wall dimensions for PCV/SCV outer diameter 0.59217 0.00099 0.595
: 4. nrc_nct.cylno3013_SS316.out: Same as #1, SS 316 0.64960 0.00100 0.652
: 2. nrc_su.pos_PCV_pos_SCV.out:
 
Upper Tolerance PCV Upper Tolerance SCV 0.59145 0.00094 0.593
Table A1.3 shows that the variation in keff by using different types of stainless steel is insignificant (within 1). It should be noted that for each of the models, it is assumed that all steel components are made of one kind of stainless steel.
: 3. nrc_su.pos_PCV_neg_SCV.out:
: 3. Variation of Dimensional Tolerances on PCV and SCV
Upper Tolerance PCV Lower Tolerance SCV 0.59564 0.00099 0.598
 
: 4. nrc_su.neg_PCV_pos_SCV.out:
The effect of uncertainties in the thickness of the PCV and SCV on the calculated k eff was also considered in this analysis. The ASTM A312 standard indicates a tolerance of +22.5% /
Lower Tolerance PCV Upper Tolerance SCV 0.59510 0.00100 0.597
-12.5% on the wall thickness and a tolerance of +1/16 / - 1/32 inch on the outer diameter. This evaluation performed an anal ysis and determined that there is no statistical significance 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 50 of 87
: 5. nrc_su.neg_PCV_neg_SCV.out:
 
Lower Tolerance PCV Lower Tolerance SCV 0.59267 0.00091 0.594
among the keff values calculated with nominal, minimum, and maximum wall thickness (Table A1.4). Therefore the nominal dimensions of PCV and SCV are used in this analysis.
: 4. Stainless Steel Sleeve Sensitivity Calculation The 9975 shipping package has an outer and inner stainless steel sleeve surrounding the lead shield of the package. The sleeves are 20 gage, 0.036-inch thick SS 304. The minimum lead thickness is 0.434 inch. However, the lead shield body is modeled with overall thickness of 0.506 inch with the inner and outer skin of nominal 0.036-inch thickness. As shown in Table A1.5, neglecting the stainless steel sleeves and including the thickness as lead has a negligible effect and thus is neglected.
 
Table A1.5.
Table A1.4. Variation of Dimensional Tolerances on PCV and SCV - Single Unit
Stainless Steel Sleeve Sensitivity Calculation Case No.
 
File ID Description keff keff +2
Case No. File ID Description keff keff +2
: 1. nrc_su.cyl3013.out:
: 1. nrc_su.cyl3013.out: (From Table 8) Nominal wall dimensions for PCV/SCV outer diameter 0.59217 0.00099 0.595
SS sleeve thickness included as lead 0.59450 0.0010 0.597
: 2. nrc_su.pos_PCV_pos_SCV.out: Upper Tolerance PCV Upper Tolerance SCV 0.59145 0.00094 0.593
: 2. nrc_su.cyl3013_2ss_sleeve.out:
: 3. nrc_su.pos_PCV_neg_SCV.out: Upper Tolerance PCV Lower Tolerance SCV 0.59564 0.00099 0.598
SS sleeve thicknes modeled as SS 304 0.59406 0.00093 0.596 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 52 of 90
: 4. nrc_su.neg_PCV_pos_SCV.out: Lower Tolerance PCV Upper Tolerance SCV 0.59510 0.00100 0.597
: 5. nrc_su.neg_PCV_neg_SCV.out: Lower Tolerance PCV Lower Tolerance SCV 0.59267 0.00091 0.594
: 4. Stainless Steel Sleeve Sensitivity Calculation
 
The 9975 shipping package has an outer and inner stainless steel sleeve surrounding the lead shield of the package. The sleeves are 20 gage, 0.036-inch thick SS 304. The minimum lead thickness is 0.434 inch. However, the lead shield body is modeled with overall thickness of 0.506 inch with the inner and outer skin of nominal 0.036-inch thickness. As shown in Table A1.5, neglecting the stainl ess steel sleeves and including the thickness as lead has a negligible effect and thus is neglected.
 
Table A1.5. Stainless Steel Sleeve Sensitivity Calculation
 
Case No. File ID Description keff keff +2
: 1. nrc_su.cyl3013.out: SS sleeve thickness included as lead 0.59450 0.0010 0.597
: 2. nrc_su.cyl3013_2ss_sleeve.out: SS sleeve thicknes modeled as SS 304 0.59406 0.00093 0.596
 
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 51 of 87
 
APPENDIX B SAMPLE INPUT FILES


Sample input files: (for the plutonium oxide cases) :
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 51 of 87 APPENDIX B SAMPLE INPUT FILES Sample input files: (for the plutonium oxide cases):
: 1. nrc_su.cyl3013.in - Single unit case (Base Case with 3013, dry oxide ) - see Table 8.
: 1. nrc_su.cyl3013.in - Single unit case (Base Case with 3013, dry oxide) - see Table 8.
: 2. nrc_su.cylno3013_ccfull_PCVSCV_ALL.in - Single unit case ( convenience can flooded with water, PCV/SCV/Celotex as water ) - see Table 17.
: 2. nrc_su.cylno3013_ccfull_PCVSCV_ALL.in - Single unit case (convenience can flooded with water, PCV/SCV/Celotex as water) - see Table 17.
: 3. nrc_nct.cyl3013.in - NCT case ( Infinite drum array, dry fissile material ) - see Table 22.
: 3. nrc_nct.cyl3013.in - NCT case (Infinite drum array, dry fissile material) - see Table 22.
: 4. nrc_hac.cyl_CCfl_3013fl.in - HAC case ( infinite 2x2x2 cluster array, convenience can flooded/3013 flooded, fissile units at closest position ) - see Table 24.
: 4. nrc_hac.cyl_CCfl_3013fl.in - HAC case (infinite 2x2x2 cluster array, convenience can flooded/3013 flooded, fissile units at closest position) - see Table 24.
: 5. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in - Single unit case. PCV intact. CC and 3013 removed. 6.6689 L water added to shipping package, solution spilling into SCV.
: 5. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in - Single unit case. PCV intact. CC and 3013 removed. 6.6689 L water added to shipping package, solution spilling into SCV.
Celotex flooded - see Table 21.
Celotex flooded - see Table 21.
: 1. nrc_su.cyl3013.in
: 1. nrc_su.cyl3013.in  
 
'NRC PuO2 Single Unit Case - 12/2012  
'NRC PuO2 Single Unit Case - 12/2012
=csas26 parm=Centrm nrc_su 9975 - pu oxide - 3013 238groupndf5 read composition wtptpuo2 1 10.8921 3 94239 87.76187 1001 0.055698 8016 12.18243 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 4.187 -11.005 -19.380 cylinder 2 5.271 1.320 -19.380 cylinder 3 5.423 1.345 -19.405 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 53 of 90
=csas26 parm=Centrm nrc_su 9975 - pu oxide - 3013 238groupndf5 read composition wtptpuo2 1 10.8921 3 94239 87.76187 1001 0.055698 8016 12.18243 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 4.187 - 11.005 -19.380 cylinder 2 5.271 1.320 -19.380 cylinder 3 5.423 1.345 -19.405 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 52 of 87


cylinder 4 5.690 3.335 -19.415 cylinder 5 5.842 3.535 -19.565 cylinder 6 5.948 4.535 -19.575 cylinder 7 6.255 4.935 -20.475 cylinder 8 6.410 20.475 - 20.475 cylinder 9 7.065 20.475 - 21.130 cylinder 10 7.703 20.475 - 21.130 cylinder 11 8.414 20.475 - 21.130 cylinder 12 9.208 20.475 - 21.130 cylinder 13 10.493 20.475 -21.130 cylinder 14 22.987 20.475 -21.130 cylinder 15 23.101 20.475 -21.130 cylinder 16 23.223 20.475 -21.130 cuboid 17 23.223 - 23.223 23.223 -23.223 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 - 2 -1 media 0 1 4 - 3 -2 media 8 1 5 - 4 -3 media 2 1 6 - 5 -4 media 0 1 7 - 6 -5 media 3 1 8 - 7 -6 media 0 1 9 - 8 -7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 53 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 52 of 87 cylinder 4 5.690 3.335 -19.415 cylinder 5 5.842 3.535 -19.565 cylinder 6 5.948 4.535 -19.575 cylinder 7 6.255 4.935 -20.475 cylinder 8 6.410 20.475 -20.475 cylinder 9 7.065 20.475 -21.130 cylinder 10 7.703 20.475 -21.130 cylinder 11 8.414 20.475 -21.130 cylinder 12 9.208 20.475 -21.130 cylinder 13 10.493 20.475 -21.130 cylinder 14 22.987 20.475 -21.130 cylinder 15 23.101 20.475 -21.130 cylinder 16 23.223 20.475 -21.130 cuboid 17 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 3 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 1 media 0 1 4 2 media 8 1 5 3 media 2 1 6 4 media 0 1 7 5 media 3 1 8 6 media 0 1 9 7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 54 of 90


cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 - 23.223 23.223 - 23.223 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 - 2 -1 media 0 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 - 2 -1 media 2 1 4 - 3 -2 media 0 1 5 - 4 -3 media 3 1 6 - 5 -4 media 0 1 7 - 6 -5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 54 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 53 of 87 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 -23.223 23.223 -23.223 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 1 media 0 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 55 of 90


cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 - 4.191 cuboid 11 23.223 - 23.223 23.223 - 23.223 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 - 2 -1 media 9 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 - 0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 - 2.25 cylinder 5 22.987 0 - 2.25 cylinder 6 23.101 0 - 2.25 cylinder 7 23.223 0 - 2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 - 2 -1 media 8 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 - 2 -1 media 3 1 4 - 3 -2 media 0 1 5 - 4 -3 boundary 5 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 - 1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 - 11.044 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 55 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 54 of 87 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 -4.191 cuboid 11 23.223 -23.223 23.223 -23.223 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 22.987 0 -2.25 cylinder 6 23.101 0 -2.25 cylinder 7 23.223 0 -2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 1 media 3 1 4 2 media 0 1 5 3 boundary 5 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 -1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 -11.044 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 56 of 90


boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=''
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 55 of 87 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=''
fill 9
fill 9
7 6
7 6
Line 1,002: Line 982:
3 4
3 4
5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 end start end data end
5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 end start end data end
: 2. nrc_su.cylno3013_ccfull_PCVSCV_ALL.in
: 2. nrc_su.cylno3013_ccfull_PCVSCV_ALL.in  
 
'NRC PuO2 Single Unit Case - 12/2012  
'NRC PuO2 Single Unit Case - 12/2012
=csas26 parm=Centrm nrc_su 9975 - pu oxide - 3013 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 57 of 90
=csas26 parm=Centrm nrc_su 9975 - pu oxide - 3013 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 56 of 87


238groupndf5 read composition wtptpuo2 1 3.5862 3 94239 69.723859 1001 2.345257 8016 27.930885 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1.0 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 0.275 -20.450 cylinder 2 5.271 0.275 -20.450 cylinder 3 5.423 0.275 -20.475 cylinder 4 6.410 20.475 -20.475 cylinder 5 7.065 20.475 -21.130 cylinder 6 7.703 20.475 -21.130 cylinder 7 8.414 20.475 -21.130 cylinder 8 9.208 20.475 -21.130 cylinder 9 10.493 20.475 - 21.130 cylinder 10 22.987 20.475 - 21.130 cylinder 11 23.101 20.475 - 21.130 cylinder 12 23.223 20.475 - 21.130 cuboid 13 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 -4 -3 media 5 1 6 -5 -4 media 3 1 7 -6 -5 media 0 1 8 -7 -6 media 8 1 9 -8 -7 media 5 1 10 -9 -8 media 0 1 11 -10 -9 media 3 1 12 -11 -10 media 0 1 13 -12 -11 boundary 13 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 57 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 56 of 87 238groupndf5 read composition wtptpuo2 1 3.5862 3 94239 69.723859 1001 2.345257 8016 27.930885 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1.0 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 0.275 -20.450 cylinder 2 5.271 0.275 -20.450 cylinder 3 5.423 0.275 -20.475 cylinder 4 6.410 20.475 -20.475 cylinder 5 7.065 20.475 -21.130 cylinder 6 7.703 20.475 -21.130 cylinder 7 8.414 20.475 -21.130 cylinder 8 9.208 20.475 -21.130 cylinder 9 10.493 20.475 -21.130 cylinder 10 22.987 20.475 -21.130 cylinder 11 23.101 20.475 -21.130 cylinder 12 23.223 20.475 -21.130 cuboid 13 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 8 1 9 7 media 5 1 10 8 media 0 1 11 9 media 3 1 12 10 media 0 1 13 11 boundary 13 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 58 of 90


cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 5 1 2 -1 media 3 1 3 - 2 -1 media 0 1 4 - 3 -2 media 8 1 5 - 4 -3 media 5 1 6 - 5 -4 media 0 1 7 - 6 -5 media 3 1 8 - 7 -6 media 0 1 9 - 8 -7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 - 23.223 23.223 - 23.223 5.922 0 media 3 1 1 media 5 1 2 -1 media 9 1 3 - 2 -1 media 5 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 5 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 - 2 -1 media 5 1 4 - 3 -2 media 0 1 5 - 4 -3 media 3 1 6 - 5 -4 media 0 1 7 - 6 -5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 58 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 57 of 87 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 5 1 2 -1 media 3 1 3 1 media 0 1 4 2 media 8 1 5 3 media 5 1 6 4 media 0 1 7 5 media 3 1 8 6 media 0 1 9 7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 -23.223 23.223 -23.223 5.922 0 media 3 1 1 media 5 1 2 -1 media 9 1 3 1 media 5 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 5 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 5 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 59 of 90


cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -2 3.223 23.223 -23.223 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 5 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 - 4.191 cuboid 11 23.223 - 23.223 23.223 - 23.223 0 -4.191 media 5 1 1 media 3 1 2 -1 media 5 1 3 - 2 -1 media 9 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 5 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 - 0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 - 2.25 cylinder 5 22.987 0 - 2.25 cylinder 6 23.101 0 - 2.25 cylinder 7 23.223 0 - 2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 - 2 -1 media 8 1 4 - 3 -2 media 5 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 59 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 58 of 87 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 5 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 -4.191 cuboid 11 23.223 -23.223 23.223 -23.223 0 -4.191 media 5 1 1 media 3 1 2 -1 media 5 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 5 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 22.987 0 -2.25 cylinder 6 23.101 0 -2.25 cylinder 7 23.223 0 -2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 5 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 60 of 90


cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 5 1 2 -1 media 0 1 3 - 2 -1 media 3 1 4 - 3 -2 media 0 1 5 - 4 -3 boundary 5 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 - 1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 - 11.044 media 4 1 1 media 5 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=''
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 59 of 87 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 5 1 2 -1 media 0 1 3 1 media 3 1 4 2 media 0 1 5 3 boundary 5 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 -1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 -11.044 media 4 1 1 media 5 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=''
fill 9
fill 9
7 6
7 6
1 2
1 2
3 4
3 4
5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 60 of 87
5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 61 of 90
 
8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 end start end data end
: 3. nrc_nct.cyl3013.in
 
'NRC PuO2 NCT Case - 12/2012
=csas26 parm=Centrm nrc_nct 9975 - pu oxide - 3013 238groupndf5 read comp wtptpuo2 1 10.8921 3 94239 87.761870 1001 0.055698 8016 12.182430 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end comp read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg" cylinder 1 4.187 - 9.225 - 17.600 cylinder 2 5.271 3.100 -17.600 cylinder 3 5.423 3.125 -17.625 cylinder 4 5.690 5.115 -17.635 cylinder 5 5.842 5.315 -17.785 cylinder 6 5.948 6.315 -17.795 cylinder 7 6.255 6.705 -18.695 cylinder 8 6.410 20.475 -20.475 cylinder 9 7.065 20.475 -21.130 cylinder 10 7.703 20.475 - 21.130 cylinder 11 8.414 20.475 - 21.130 cylinder 12 9.208 20.475 - 21.130 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 61 of 87
 
cylinder 13 10.493 20.475 - 21.130 cylinder 14 21.466 20.475 - 21.130 cylinder 15 21.466 20.475 - 21.130 cylinder 16 21.597 20.475 - 21.130 cuboid 17 21.597 - 21.597 21.597 - 21.597 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 2 com='top of primary containment' cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 21.466 3.505 0 cylinder 7 21.466 3.505 0 cylinder 8 21.597 3.505 0 cuboid 9 21.597 -21.597 21.597 - 21.597 3.505 0 media 3 1 1 media 0 1 2 - 1 media 3 1 3 - 2 media 0 1 4 - 3 media 8 1 5 - 4 media 2 1 6 - 5 media 0 1 7 - 6 media 3 1 8 - 7 media 0 1 9 - 8 boundary 9 unit 3 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 21.466 5.922 0 cylinder 9 21.466 5.922 0 cylinder 10 21.597 5.922 0 cuboid 11 21.597 - 21.597 21.597 -21.597 5.922 0 media 3 1 1 media 0 1 2 - 1 media 9 1 3 - 2 -1 media 0 1 4 - 3 -2 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 62 of 87
 
media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 4 com='secondary containment top' cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 21.466 3.505 0 cylinder 5 21.466 3.505 0 cylinder 6 21.597 3.505 0 cuboid 7 21.597 -21.597 21.597 - 21.597 3.505 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 -1 media 2 1 4 - 3 -2 media 0 1 5 - 4 -3 media 3 1 6 - 5 -4 media 0 1 7 - 6 -5 boundary 7 unit 5 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 21.466 2.54 0 cylinder 6 21.466 2.54 0 cylinder 7 21.597 2.54 0 cuboid 8 21.597 -21.597 21.597 - 21.597 2.54 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 6 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 - 0.94 c ylinder 2 5.715 0 - 0.94 cylinder 3 7.703 0 - 0.94 cylinder 4 7.703 0 - 3.48 cylinder 5 8.414 0 - 4.191 cylinder 6 9.208 0 - 4.191 cylinder 7 10.493 0 -4.191 cylinder 8 21.466 0 -4.191 cylinder 9 21.466 0 -4.191 cylinder 10 21.597 0 - 4.191 cuboid 11 21.597 - 21.597 21.597 -21.597 0 -4.191 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 9 1 4 - 3 -2 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 63 of 87


media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 7 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 - 0.965 cylinder 3 9.208 0 - 0.965 cylinder 4 10.493 0 -2.25 cylinder 5 21.466 0 -2.25 cylinder 6 21.466 0 -2.25 cylinder 7 21.597 0 -2.25 cuboid 8 21.597 -21.597 21.597 - 21.597 0 - 2.25 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 8 1 4 - 3 1 media 2 1 5 - 4 2 media 0 1 6 - 5 3 media 3 1 7 - 6 4 media 0 1 8 - 7 5 boundary 8 unit 8 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 cylinder 2 21.466 10.668 0 cylinder 3 21.466 12.828 0 cylinder 4 21.597 12.95 0 cuboid 5 21.597 -21.597 21.597 - 21.597 12.95 0 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 9 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 cylinder 2 21.466 0 -10.922 cylinder 3 21.466 0 -10.922 cylinder 4 21.597 0 -11.044 cuboid 5 21.597 -21.597 21.597 - 21.597 0 - 11.044 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 global unit 10 cuboid 1 43.194 0 43.194 0 87.512 0 array 1 1 place 1 1 1 21.597 21.597 11.044 boundary 1 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square fill 9 7 6 1 2 3 4 5 8 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 64 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 60 of 87 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 end start end data end
: 3. nrc_nct.cyl3013.in
'NRC PuO2 NCT Case - 12/2012
=csas26 parm=Centrm nrc_nct 9975 - pu oxide - 3013 238groupndf5 read comp wtptpuo2 1 10.8921 3 94239 87.761870 1001 0.055698 8016 12.182430 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end comp read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg" cylinder 1 4.187 -9.225 -17.600 cylinder 2 5.271 3.100 -17.600 cylinder 3 5.423 3.125 -17.625 cylinder 4 5.690 5.115 -17.635 cylinder 5 5.842 5.315 -17.785 cylinder 6 5.948 6.315 -17.795 cylinder 7 6.255 6.705 -18.695 cylinder 8 6.410 20.475 -20.475 cylinder 9 7.065 20.475 -21.130 cylinder 10 7.703 20.475 -21.130 cylinder 11 8.414 20.475 -21.130 cylinder 12 9.208 20.475 -21.130 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 62 of 90


end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=800 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read bnds body=1 surface(1)=mirror surface(2)=mirror surface(3)=mirror surface(4)=mirror surface(5)=periodic surface(6)=periodic end bnds read start nst=0
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 61 of 87 cylinder 13 10.493 20.475 -21.130 cylinder 14 21.466 20.475 -21.130 cylinder 15 21.466 20.475 -21.130 cylinder 16 21.597 20.475 -21.130 cuboid 17 21.597 -21.597 21.597 -21.597 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 3 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 2 com='top of primary containment' cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 21.466 3.505 0 cylinder 7 21.466 3.505 0 cylinder 8 21.597 3.505 0 cuboid 9 21.597 -21.597 21.597 -21.597 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 3 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 21.466 5.922 0 cylinder 9 21.466 5.922 0 cylinder 10 21.597 5.922 0 cuboid 11 21.597 -21.597 21.597 -21.597 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 1 media 0 1 4 2 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 63 of 90


end start end data end
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 62 of 87 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 4 com='secondary containment top' cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 21.466 3.505 0 cylinder 5 21.466 3.505 0 cylinder 6 21.597 3.505 0 cuboid 7 21.597 -21.597 21.597 -21.597 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 5 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 21.466 2.54 0 cylinder 6 21.466 2.54 0 cylinder 7 21.597 2.54 0 cuboid 8 21.597 -21.597 21.597 -21.597 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 6 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 21.466 0 -4.191 cylinder 9 21.466 0 -4.191 cylinder 10 21.597 0 -4.191 cuboid 11 21.597 -21.597 21.597 -21.597 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 64 of 90
: 4. nrc_hac.cyl_CCfl_3013fl.in


'NRC PuO2 HAC Case - 12/2012
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 63 of 87 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 7 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 21.466 0 -2.25 cylinder 6 21.466 0 -2.25 cylinder 7 21.597 0 -2.25 cuboid 8 21.597 -21.597 21.597 -21.597 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 -1 media 2 1 5 3 -2 media 0 1 6 4 -3 media 3 1 7 5 -4 media 0 1 8 6 -5 boundary 8 unit 8 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 cylinder 2 21.466 10.668 0 cylinder 3 21.466 12.828 0 cylinder 4 21.597 12.95 0 cuboid 5 21.597 -21.597 21.597 -21.597 12.95 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 9 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 cylinder 2 21.466 0 -10.922 cylinder 3 21.466 0 -10.922 cylinder 4 21.597 0 -11.044 cuboid 5 21.597 -21.597 21.597 -21.597 0 -11.044 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 global unit 10 cuboid 1 43.194 0 43.194 0 87.512 0 array 1 1 place 1 1 1 21.597 21.597 11.044 boundary 1 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square fill 9 7 6 1 2 3 4 5 8 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 65 of 90
=csas26 parm=Centrm nrc_hac 9975 - pu oxide - 3013 238groupndf5 read comp wtptpuo2 1 3.7421 3 94239 70.843921 1001 2.203088 8016 26.952992 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 65 of 87


1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end comp read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=6.076 y= -6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=6.076 y= -6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=6.076 y= -6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=6.076 y= -6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=6.076 y= -6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=6.076 y= -6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=6.076 y= -6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y= -6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x=6.076 y= -6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x=1.732 y= -1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 -2 1.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 2 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 2 7.703 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 3 8.414 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 4 9.208 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 5 10.493 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 6 16.637 3.505 0 origin x=1.732 y= -1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 66 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 64 of 87 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=800 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read bnds body=1 surface(1)=mirror surface(2)=mirror surface(3)=mirror surface(4)=mirror surface(5)=periodic surface(6)=periodic end bnds read start nst=0 end start end data end
: 4. nrc_hac.cyl_CCfl_3013fl.in
'NRC PuO2 HAC Case - 12/2012
=csas26 parm=Centrm nrc_hac 9975 - pu oxide - 3013 238groupndf5 read comp wtptpuo2 1 3.7421 3 94239 70.843921 1001 2.203088 8016 26.952992 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 66 of 90


cuboid 9 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 media 0 1 2 - 1 media 3 1 3 - 2 media 0 1 4 - 3 media 8 1 5 - 4 media 2 1 6 - 5 media 0 1 7 - 6 media 3 1 8 - 7 media 0 1 9 - 8 boundary 9 unit 3 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=6.076 y= -6.076 z=0 cylinder 2 4.699 4.572 0 origin x=6.076 y= -6.076 z=0 cylinder 3 7.366 4.572 0 origin x=6.076 y= -6.076 z=0 cylinder 4 7.703 5.922 0 origin x=6.076 y= -6.076 z=0 cylinder 5 8.414 5.922 0 origin x=6.076 y= -6.076 z=0 cylinder 6 9.208 5.922 0 origin x=6.076 y= -6.076 z=0 cylinder 7 10.493 5.922 0 origin x=6.076 y= -6.076 z=0 cylinder 8 16.637 5.922 0 origin x=1.732 y= -1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 - 19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 - 1 media 9 1 3 - 2 media 0 1 4 - 3 media 3 1 5 - 4 media 0 1 6 - 5 media 8 1 7 - 6 media 2 1 8 - 7 media 0 1 9 - 8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 4 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 2 9.208 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 3 10.493 3.505 0 origin x=6.076 y= -6.076 z=0 cylinder 4 16.637 3.505 0 origin x=1.732 y= -1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 media 2 1 4 - 3 media 0 1 5 - 4 media 3 1 6 - 5 media 0 1 7 - 6 boundary 7 unit 5 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=6.076 y= -6.076 z=0 cylinder 2 9.208 1.27 0 origin x=6.076 y= -6.076 z=0 cylinder 3 10.493 1.27 0 origin x=6.076 y= -6.076 z=0 cylinder 4 10.493 2.54 0 origin x=6.076 y= -6.076 z=0 cylinder 5 16.637 2.54 0 origin x=1.732 y= -1.732 z=0 cylinder 6 19.088 2.54 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 67 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 65 of 87 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end comp read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=6.076 y=-6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=6.076 y=-6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=6.076 y=-6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=6.076 y=-6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=6.076 y=-6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=6.076 y=-6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 2 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 2 7.703 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 3 8.414 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 4 9.208 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 5 10.493 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 6 16.637 3.505 0 origin x=1.732 y=-1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 67 of 90


cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 - 19.235 2.54 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 media 4 1 4 - 3 media 2 1 5 - 4 media 0 1 6 - 5 media 3 1 7 - 6 media 0 1 8 - 7 boundary 8 unit 6 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 - 0.94 origin x=6.076 y= -6.076 z=0 cylinder 2 5.715 0 - 0.94 origin x=6.076 y=-6.076 z=0 cylinder 3 7.703 0 - 0.94 origin x=6.076 y= -6.076 z=0 cylinder 4 7.703 0 - 3.48 origin x=6.076 y= -6.076 z=0 cylinder 5 8.414 0 - 4.191 origin x=6.076 y= -6.076 z=0 cylinder 6 9.208 0 - 4.191 origin x=6.076 y=-6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=6.076 y= -6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=1.732 y= -1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 - 4.191 cuboid 11 19.235 - 19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 media 9 1 4 - 3 media 3 1 5 - 4 media 0 1 6 - 5 media 8 1 7 - 6 media 2 1 8 - 7 media 0 1 9 - 8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 7 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=6.076 y= -6.076 z=0 cylinder 2 7.065 0 - 0.965 origin x=6.076 y= -6.076 z=0 cylinder 3 9.208 0 - 0.965 origin x=6.076 y= -6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=6.076 y= -6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=1.732 y= -1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 - 19.235 0 - 2.25 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 media 8 1 4 - 3 media 2 1 5 -4 media 0 1 6 - 5 media 3 1 7 - 6 media 0 1 8 - 7 boundary 8 unit 8 com='al top plate and celotex plus top void plus drum lower' cylinder 1 14.224 1.27 0 origin x=3.438 y= -3.438 z=0 cylinder 2 16.637 1.27 0 origin x=1.732 y= -1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 68 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 66 of 87 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 3 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 2 4.699 4.572 0 origin x=6.076 y=-6.076 z=0 cylinder 3 7.366 4.572 0 origin x=6.076 y=-6.076 z=0 cylinder 4 7.703 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 5 8.414 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 6 9.208 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 7 10.493 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 8 16.637 5.922 0 origin x=1.732 y=-1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 -2 media 0 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 4 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 2 9.208 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 3 10.493 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 4 16.637 3.505 0 origin x=1.732 y=-1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 -2 media 2 1 4 -3 media 0 1 5 -4 media 3 1 6 -5 media 0 1 7 -6 boundary 7 unit 5 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 2 9.208 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 3 10.493 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 4 10.493 2.54 0 origin x=6.076 y=-6.076 z=0 cylinder 5 16.637 2.54 0 origin x=1.732 y=-1.732 z=0 cylinder 6 19.088 2.54 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 68 of 90


cuboid 5 19.235 -19.235 19.235 - 19.235 1.392 0 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 9 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=3.438 y= -3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=1.732 y= -1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 17.522 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 10 cuboid 1 38.47 0 38.47 0 164.864 0 array 1 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 13 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 - 19.380 origin x=6.076 y= -6.076 z=0 cylinder 2 5.271 1.320 - 19.380 origin x=6.076 y= -6.076 z=0 cylinder 3 5.423 1.345 - 19.405 origin x=6.076 y= -6.076 z=0 cylinder 4 5.690 3.335 - 19.415 origin x=6.076 y= -6.076 z=0 cylinder 5 5.842 3.535 - 19.565 origin x=6.076 y= -6.076 z=0 cylinder 6 5.948 4.535 - 19.575 origin x=6.076 y= -6.076 z=0 cylinder 7 6.255 4.935 - 20.475 origin x=6.076 y= -6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y= -6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y= -6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x=6.076 y= -6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x=1.732 y= -1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 69 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 67 of 87 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 -2 media 4 1 4 -3 media 2 1 5 -4 media 0 1 6 -5 media 3 1 7 -6 media 0 1 8 -7 boundary 8 unit 6 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=6.076 y=-6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=6.076 y=-6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=6.076 y=-6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=6.076 y=-6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=6.076 y=-6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=6.076 y=-6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=6.076 y=-6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=1.732 y=-1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 -2 media 9 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 7 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=6.076 y=-6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=6.076 y=-6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=6.076 y=-6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=6.076 y=-6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=1.732 y=-1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 -2 media 8 1 4 -3 media 2 1 5 -4 media 0 1 6 -5 media 3 1 7 -6 media 0 1 8 -7 boundary 8 unit 8 com='al top plate and celotex plus top void plus drum lower' cylinder 1 14.224 1.27 0 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 1.27 0 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 69 of 90


unit 16 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=3.438 y= -3.438 z=0 cylinder 2 16.637 10.16 0 origin x=1.732 y= -1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 - 19.235 17.522 0 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 17 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x= -6.076 y= -6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x= -6.076 y= -6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x= -6.076 y= -6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x= -6.076 y= -6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x= -6.076 y= -6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x= -6.076 y= -6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x= -6.076 y= -6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x= -6.076 y= -6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x= -6.076 y= -6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x= -6.076 y= -6.076 z=0 cylinder 11 8.414 20.475 -2 1.130 origin x=-6.076 y= -6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x= -6.076 y= -6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x= -6.076 y= -6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x= -1.732 y= -1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 18 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x= -6.076 y= -6.076 z=0 cylinder 2 7.703 3.505 0 origin x= -6.076 y= -6.076 z=0 cylinder 3 8.414 3.505 0 origin x= -6.076 y= -6.076 z=0 cylinder 4 9.208 3.505 0 origin x= -6.076 y =-6.076 z=0 cylinder 5 10.493 3.505 0 origin x= -6.076 y= -6.076 z=0 cylinder 6 16.637 3.505 0 origin x= -1.732 y= -1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 - 19.235 3.505 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 70 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 68 of 87 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 9 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 10 cuboid 1 38.47 0 38.47 0 164.864 0 array 1 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 13 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=6.076 y=-6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=6.076 y=-6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=6.076 y=-6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=6.076 y=-6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=6.076 y=-6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=6.076 y=-6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 70 of 90


media 3 1 1 media 0 1 2 - 1 media 3 1 3 - 2 media 0 1 4 - 3 media 8 1 5 - 4 media 2 1 6 - 5 media 0 1 7 - 6 media 3 1 8 - 7 media 0 1 9 - 8 boundary 9 unit 19 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=-6.076 y= -6.076 z=0 cylinder 2 4.699 4.572 0 origin x= -6.076 y= -6.076 z=0 cylinder 3 7.366 4.572 0 origin x= -6.076 y= -6.076 z=0 cylinder 4 7.703 5.922 0 origin x= -6.076 y= -6.076 z=0 cylinder 5 8.414 5.922 0 origin x= -6.076 y= -6.076 z=0 cylinder 6 9.208 5.922 0 origin x= -6.076 y= -6.076 z=0 cylinder 7 10.493 5.922 0 origin x= -6.076 y= -6.076 z=0 cylinder 8 16.637 5.922 0 origin x= -1.732 y= -1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 - 19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 - 1 media 9 1 3 - 2 media 0 1 4 - 3 media 3 1 5 - 4 media 0 1 6 - 5 media 8 1 7 - 6 media 2 1 8 - 7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 20 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x= -6.076 y= -6.076 z=0 cylinder 2 9.208 3.505 0 origin x= -6.076 y= -6.076 z=0 cylinder 3 10.493 3.505 0 origin x=-6.076 y= -6.076 z=0 cylinder 4 16.637 3.505 0 origin x= -1.732 y= -1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 -1 media 2 1 4 - 3 -2 media 0 1 5 - 4 -3 media 3 1 6 - 5 -4 media 0 1 7 - 6 -5 boundary 7 unit 21 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x= -6.076 y= -6.076 z=0 cylinder 2 9.208 1.27 0 origin x= -6.076 y= -6.076 z=0 cylinder 3 10.493 1.27 0 origin x= -6.076 y= -6.076 z=0 cylinder 4 10.493 2.54 0 origin x= -6.076 y= -6.076 z=0 cylinder 5 16.637 2.54 0 origin x= -1.732 y= -1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 71 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 69 of 87 unit 16 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 10.16 0 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 17 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=-6.076 y=-6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=-6.076 y=-6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=-6.076 y=-6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=-6.076 y=-6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=-6.076 y=-6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=-6.076 y=-6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=-6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 18 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 7.703 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 8.414 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 9.208 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 5 10.493 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 6 16.637 3.505 0 origin x=-1.732 y=-1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 71 of 90


cuboid 8 19.235 -19.235 19.235 - 19.235 2.54 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 22 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 - 0.94 origin x= -6.076 y= -6.076 z=0 cylinder 2 5.715 0 - 0.94 origin x= -6.076 y= -6.076 z=0 cylinder 3 7.703 0 - 0.94 origin x= -6.076 y= -6.076 z=0 cylinder 4 7.703 0 - 3.48 origin x= -6. 076 y=-6.076 z=0 cylinder 5 8.414 0 - 4.191 origin x= -6.076 y= -6.076 z=0 cylinder 6 9.208 0 - 4.191 origin x= -6.076 y= -6.076 z=0 cylinder 7 10.493 0 -4.191 origin x= -6.076 y= -6.076 z=0 cylinder 8 16.637 0 -4.191 origin x= -1.73 2 y=-1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 - 4.191 cuboid 11 19.235 - 19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 9 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 23 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x= -6.076 y= -6.076 z=0 cylinder 2 7.065 0 - 0.965 origin x=-6.076 y= -6.076 z=0 cylinder 3 9.208 0 - 0.965 origin x= -6.076 y= -6.076 z=0 cylinder 4 10.493 0 -2.25 origin x= -6.076 y= -6.076 z=0 cylinder 5 16.637 0 -2.25 origin x= -1.732 y= -1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 - 19.235 0 - 2.25 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 8 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 24 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x= -3.438 y= -3.438 z=0 cylinder 2 16.637 1.27 0 origin x= -1.732 y= -1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 - 19.235 1.392 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 72 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 70 of 87 media 3 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 19 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 4.699 4.572 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 7.366 4.572 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 7.703 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 5 8.414 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 6 9.208 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 7 10.493 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 8 16.637 5.922 0 origin x=-1.732 y=-1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 -2 media 0 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 20 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 9.208 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 10.493 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 16.637 3.505 0 origin x=-1.732 y=-1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 21 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 9.208 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 10.493 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 10.493 2.54 0 origin x=-6.076 y=-6.076 z=0 cylinder 5 16.637 2.54 0 origin x=-1.732 y=-1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 72 of 90


media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 25 com='al bottom plate and celotex plus bottom void plus drum' cylinder 1 14.224 0 -1.27 origin x= -3.438 y= -3.438 z=0 cylinder 2 16.637 0 -10.16 origin x= -1.732 y= -1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 17.522 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 28 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 - 19.380 origin x= -6.076 y= -6.076 z=0 cylinder 2 5.271 1.320 - 19.380 origin x= -6.07 6 y=-6.076 z=0 cylinder 3 5.423 1.345 - 19.405 origin x= -6.076 y= -6.076 z=0 cylinder 4 5.690 3.335 - 19.415 origin x= -6.076 y= -6.076 z=0 cylinder 5 5.842 3.535 - 19.565 origin x= -6.076 y= -6.076 z=0 cylinder 6 5.948 4.535 - 19.575 origin x= -6.076 y= -6.076 z=0 cylinder 7 6.255 4.935 - 20.475 origin x= -6.076 y= -6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x= -6.076 y= -6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x= -6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x= -6.076 y= -6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x= -6.076 y= -6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x= -6.076 y= -6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x=-6.076 y= -6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x=-1.732 y= -1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 31 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x= -3.438 y= -3.438 z=0 cylinder 2 16.637 10.16 0 origin x= -1.732 y= -1.732 z=0 cylinder 3 19.088 17.4 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 73 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 71 of 87 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 22 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=-6.076 y=-6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=-6.076 y=-6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=-6.076 y=-6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=-6.076 y=-6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=-6.076 y=-6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=-6.076 y=-6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=-6.076 y=-6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=-1.732 y=-1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 23 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=-6.076 y=-6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=-6.076 y=-6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=-6.076 y=-6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=-6.076 y=-6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=-1.732 y=-1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 24 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 1.27 0 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 73 of 90


cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 - 19.235 17.522 0 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 32 cuboid 1 38.47 0 38.47 0 164.864 0 array 2 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 33 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=6.076 y=6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=6.076 y=6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=6.076 y=6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=6.076 y=6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=6.076 y=6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=6.076 y=6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=6.076 z =0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21. 130 origin x=6.076 y=6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x=6.076 y=6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x=1.732 y=1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 34 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 2 7.703 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 3 8.414 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 4 9.208 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 5 10.493 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 6 16.637 3.505 0 origin x=1.732 y=1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 74 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 72 of 87 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 25 com='al bottom plate and celotex plus bottom void plus drum' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 28 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=-6.076 y=-6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=-6.076 y=-6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=-6.076 y=-6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=-6.076 y=-6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=-6.076 y=-6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=-6.076 y=-6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=-6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 31 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 10.16 0 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 17.4 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 74 of 90


media 0 1 2 - 1 media 3 1 3 - 2 media 0 1 4 - 3 media 8 1 5 - 4 media 2 1 6 - 5 media 0 1 7 - 6 media 3 1 8 - 7 media 0 1 9 - 8 boundary 9 unit 35 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 2 4.699 4.572 0 origin x=6.076 y=6.076 z=0 cylinder 3 7.366 4.572 0 origin x=6.076 y=6.076 z=0 cylinder 4 7.703 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 5 8.414 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 6 9.208 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 7 10.493 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 8 16.637 5.922 0 origin x=1.732 y=1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 - 19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 - 1 media 9 1 3 - 2 media 0 1 4 - 3 media 3 1 5 - 4 media 0 1 6 - 5 media 8 1 7 - 6 media 2 1 8 - 7 media 0 1 9 - 8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 36 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 2 9.208 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 3 10.493 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 4 16.637 3.505 0 origin x=1.732 y=1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 media 2 1 4 - 3 media 0 1 5 - 4 media 3 1 6 - 5 media 0 1 7 - 6 boundary 7 unit 37 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 2 9.208 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 3 10.493 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 4 10.493 2.54 0 origin x=6.076 y=6.076 z=0 cylinder 5 16.637 2.54 0 origin x=1.732 y=1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 - 19.235 2.54 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 75 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 73 of 87 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 32 cuboid 1 38.47 0 38.47 0 164.864 0 array 2 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 33 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=6.076 y=6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=6.076 y=6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=6.076 y=6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=6.076 y=6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=6.076 y=6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=6.076 y=6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 34 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 2 7.703 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 3 8.414 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 4 9.208 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 5 10.493 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 6 16.637 3.505 0 origin x=1.732 y=1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 75 of 90


media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 2 1 5 3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 38 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 - 0.94 origin x=6.076 y=6.076 z=0 cylinder 2 5.715 0 - 0.94 origin x=6.076 y=6.076 z=0 cylinder 3 7.703 0 - 0.94 origin x=6.076 y=6.076 z=0 cylinder 4 7.703 0 - 3.48 origin x=6.076 y=6.076 z=0 cylinder 5 8.414 0 - 4.191 origin x=6.076 y=6.076 z=0 cylinder 6 9.208 0 - 4.191 origin x=6.076 y=6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=1.732 y=1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 - 4.191 cuboid 11 19.235 - 19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 9 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 39 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 2 7.065 0 - 0.965 origin x=6.076 y=6.076 z=0 cylinder 3 9.208 0 - 0.965 origin x=6.076 y=6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=6.076 y=6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=1.732 y=1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 - 19.235 0 - 2.25 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 8 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 40 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 1.27 0 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 - 19.235 1.392 0 media 4 1 1 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 76 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 74 of 87 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 35 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 2 4.699 4.572 0 origin x=6.076 y=6.076 z=0 cylinder 3 7.366 4.572 0 origin x=6.076 y=6.076 z=0 cylinder 4 7.703 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 5 8.414 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 6 9.208 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 7 10.493 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 8 16.637 5.922 0 origin x=1.732 y=1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 -2 media 0 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 36 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 2 9.208 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 3 10.493 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 4 16.637 3.505 0 origin x=1.732 y=1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 -2 media 2 1 4 -3 media 0 1 5 -4 media 3 1 6 -5 media 0 1 7 -6 boundary 7 unit 37 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 2 9.208 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 3 10.493 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 4 10.493 2.54 0 origin x=6.076 y=6.076 z=0 cylinder 5 16.637 2.54 0 origin x=1.732 y=1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 76 of 90


media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 41 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 17.522 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 44 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 - 19.380 origin x=6.076 y=6.076 z=0 cylinder 2 5.271 1.320 - 19.380 origin x=6.076 y=6.076 z=0 cylinder 3 5.423 1.345 - 19.405 origin x=6.076 y=6.076 z=0 cylinder 4 5.690 3.335 - 19.415 origin x=6.076 y=6.076 z=0 cylinder 5 5.842 3.535 - 19.565 origin x=6.076 y=6.076 z=0 cylinder 6 5.948 4.535 - 19.575 origin x=6.076 y=6.076 z=0 cylinder 7 6.255 4.935 - 20.475 origin x=6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x=6.076 y=6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x=1.732 y=1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235-19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 47 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 10.16 0 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 77 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 75 of 87 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 38 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=6.076 y=6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=6.076 y=6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=6.076 y=6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=6.076 y=6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=1.732 y=1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 39 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=6.076 y=6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=1.732 y=1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 40 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 1.27 0 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 media 4 1 1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 77 of 90


cuboid 5 19.235 -19.235 19.235 - 19.235 17.522 0 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 -3 media 0 1 5 - 4 boundary 5 unit 48 cuboid 1 38.47 0 38.47 0 164.864 0 array 3 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 49 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x= -6.076 y=6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x= -6.076 y=6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x= -6.076 y=6.076 z=0 cylinder 4 5.690 19.415 -3.33 5 origin x=-6.076 y=6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x= -6.076 y=6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x= -6.076 y=6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x= -6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x= -6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x= -6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x= -6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x= -6.076 y=6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x= -6.076 y=6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x= -1.732 y=1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 50 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 2 7.703 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 3 8.414 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 4 9.208 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 5 10.493 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 6 16.637 3.505 0 origin x= -1.732 y=1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 media 0 1 2 - 1 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 78 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 76 of 87 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 41 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 44 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=6.076 y=6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=6.076 y=6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=6.076 y=6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=6.076 y=6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=6.076 y=6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=6.076 y=6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 47 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 10.16 0 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 78 of 90


media 3 1 3 - 2 media 0 1 4 - 3 media 8 1 5 - 4 media 2 1 6 - 5 media 0 1 7 - 6 media 3 1 8 - 7 media 0 1 9 - 8 boundary 9 unit 51 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x= -6.076 y=6.076 z=0 cylinder 2 4.699 4.572 0 origin x= -6.076 y=6.076 z=0 cylinder 3 7.366 4.572 0 origin x= -6.076 y=6.076 z=0 cylinder 4 7.703 5.922 0 origin x= -6.076 y=6.076 z=0 cylinder 5 8.414 5.922 0 origin x= -6.076 y=6.076 z=0 cylinder 6 9.208 5.922 0 origin x= -6.076 y=6.076 z=0 cylinder 7 10.493 5.922 0 origin x= -6.076 y=6.076 z=0 cylinder 8 16.637 5.922 0 origin x= -1.732 y=1.732 z=0 cylinder 9 19.088 5. 922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 - 19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 - 1 media 9 1 3 - 2 -1 media 0 1 4 - 3 -2 media 3 1 5 - 4 -3 media 0 1 6 - 5 -4 media 8 1 7 - 6 -5 media 2 1 8 - 7 -6 media 0 1 9 - 8 -7 media 3 1 10 -9 -8 media 0 1 11 -10 -9 boundary 11 unit 52 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 2 9.208 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 3 10.493 3.505 0 origin x= -6.076 y=6.076 z=0 cylinder 4 16.637 3.505 0 origin x= -1.732 y=1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 - 19.235 3.505 0 media 3 1 1 media 0 1 2 - 1 media 8 1 3 - 2 -1 media 2 1 4 - 3 -2 media 0 1 5 - 4 -3 media 3 1 6 - 5 -4 media 0 1 7 - 6 -5 boundary 7 unit 53 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x= -6.076 y=6.076 z=0 cylinder 2 9.208 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 3 10.493 1.27 0 origin x= -6.076 y=6.076 z=0 cylinder 4 10.493 2.54 0 origin x= -6.076 y=6.076 z=0 cylinder 5 16.637 2.54 0 origin x= -1.732 y=1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 - 19.235 2.54 0 media 3 1 1 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 79 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 77 of 87 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 48 cuboid 1 38.47 0 38.47 0 164.864 0 array 3 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 49 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=-6.076 y=6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=-6.076 y=6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=-6.076 y=6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=-6.076 y=6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=-6.076 y=6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=-6.076 y=6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=-6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 50 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 2 7.703 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 3 8.414 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 4 9.208 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 5 10.493 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 6 16.637 3.505 0 origin x=-1.732 y=1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 79 of 90


media 0 1 2 - 1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 54 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 - 0.94 origin x= -6.076 y=6.076 z=0 cylinder 2 5.715 0 - 0.94 origin x= -6.076 y=6.076 z=0 cylinder 3 7.703 0 - 0.94 origin x= -6.076 y=6.076 z=0 cylinder 4 7.703 0 - 3.48 originx= -6.076 y=6.076 z=0 cylinder 5 8.414 0 - 4.191 origin x= -6.076 y=6.076 z=0 cylinder 6 9.208 0 - 4.191 origin x= -6.076 y=6.076 z=0 cylinder 7 10.493 0 -4.191 origin x= -6.076 y=6.076 z=0 cylinder 8 16.637 0 -4.191 origin x= -1.732 y=1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 - 4.191 cuboid 11 19.235 - 19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 media 9 1 4 - 3 media 3 1 5 - 4 media 0 1 6 - 5 media 8 1 7 - 6 media 2 1 8 - 7 media 0 1 9 - 8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 55 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x= -6.076 y=6.076 z=0 cylinder 2 7.065 0 - 0.965 origin x=-6.076 y=6.076 z=0 cylinder 3 9.208 0 - 0.965 origin x= -6.076 y=6.076 z=0 cylinder 4 10.493 0 -2.25 origin x= -6.076 y=6.076 z=0 cylinder 5 16.637 0 -2.25 origin x= -1.732 y=1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19. 235 0 -2.25 cuboid 8 19.235 -19.235 19.235 - 19.235 0 - 2.25 media 0 1 1 media 3 1 2 - 1 media 0 1 3 - 2 -1 media 8 1 4 - 3 -2 media 2 1 5 - 4 -3 media 0 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 boundary 8 unit 56 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x= -3.438 y=3.438 z=0 cylinder 2 16.637 1.27 0 origin x= -1.732 y=1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 - 19.235 1.392 0 media 4 1 1 media 2 1 2 - 1 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 80 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 78 of 87 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 51 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 2 4.699 4.572 0 origin x=-6.076 y=6.076 z=0 cylinder 3 7.366 4.572 0 origin x=-6.076 y=6.076 z=0 cylinder 4 7.703 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 5 8.414 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 6 9.208 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 7 10.493 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 8 16.637 5.922 0 origin x=-1.732 y=1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 1 media 0 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 52 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 2 9.208 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 3 10.493 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 4 16.637 3.505 0 origin x=-1.732 y=1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 53 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 2 9.208 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 3 10.493 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 4 10.493 2.54 0 origin x=-6.076 y=6.076 z=0 cylinder 5 16.637 2.54 0 origin x=-1.732 y=1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 media 3 1 1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 80 of 90


media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 57 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x= -3.438 y=3.438 z=0 cylinder 2 16.637 0 -10.16 origin x= -1.732 y=1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 17.522 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 60 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 - 19.380 origin x= -6.076 y=6.076 z=0 cylinder 2 5.271 1.320 - 19.380 origin x= -6.076 y=6.076 z=0 cylinder 3 5.423 1.345 - 19.405 origin x= -6.076 y=6.076 z=0 cylinder 4 5.690 3.335 - 19.415 origin x= -6.076 y=6.076 z=0 cylinder 5 5.842 3.535 - 19.565 origin x= -6.076 y=6.076 z=0 cylinder 6 5.948 4.535 - 19.575 origin x= -6.076 y=6.076 z=0 cylinder 7 6.255 4.935 - 20.475 origin x= -6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x= -6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x= -6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x= -6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x= -6.076 y=6.076 z=0 cylinder 13 10.493 20.475 - 21.130 origin x=-6.076 y=6.076 z=0 cylinder 14 16.637 20.475 - 21.130 origin x=-1.732 y=1.732 z=0 cylinder 15 19.088 20.475 - 21.130 cylinder 16 19.235 20.475 - 21.130 cuboid 17 19.235 - 19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 0 1 8 - 7 -6 media 3 1 9 - 8 -7 media 0 1 10 -9 -8 media 3 1 11 -10 -9 media 0 1 12 -11 -10 media 8 1 13 -12 -11 media 2 1 14 -13 -12 media 0 1 15 -14 -13 media 3 1 16 -15 -14 media 0 1 17 -16 -15 boundary 17 unit 63 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x= -3.438 y=3.438 z=0 cylinder 2 16.637 10.16 0 origin x= -1.732 y=1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 - 19.235 17.522 0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 81 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 79 of 87 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 54 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=-6.076 y=6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=-6.076 y=6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=-6.076 y=6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=-6.076 y=6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=-6.076 y=6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=-6.076 y=6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=-6.076 y=6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=-1.732 y=1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 -2 media 9 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 55 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=-6.076 y=6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=-6.076 y=6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=-6.076 y=6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=-6.076 y=6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=-1.732 y=1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 56 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 1.27 0 origin x=-1.732 y=1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 media 4 1 1 media 2 1 2 -1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 81 of 90


media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 -4 boundary 5 unit 64 cuboid 1 38.47 0 38.47 0 164.864 0 array 4 1 place 1 1 1 19.235 19.235 17.522 boundary 1 global unit 65 com=^5 x 5 x 2 damaged array^
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 80 of 87 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 57 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=-1.732 y=1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 60 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=-6.076 y=6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=-6.076 y=6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=-6.076 y=6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=-6.076 y=6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=-6.076 y=6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=-6.076 y=6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=-6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 63 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 10.16 0 origin x=-1.732 y=1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 82 of 90
cuboid 1 7.694000E+01 0.000000E+00 7.694000E+01 0.000000E+00 1.648640E+02 0.000000E+00 array 5 1 place 1 1 1 0.00000E+00 0.00000E+00 0.00000E+00 boundary 1 unit 71 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=3.438 y= -3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=1.732 y= -1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 1.392 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 72 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x= -3.438 y= -3.438 z=0 cylinder 2 16.637 0 -1.27 origin x= -1.732 y= -1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 1.392 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 73 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 1.392 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 unit 74 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 ori gin x=-3.438 y=3.438 z=0 cylinder 2 16.637 0 -1.27 origin x= -1.732 y=1.732 z=0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 82 of 87


cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 - 19.235 0 - 1.392 media 4 1 1 media 2 1 2 - 1 media 0 1 3 - 2 media 3 1 4 - 3 media 0 1 5 - 4 boundary 5 end geometry read array ara=1 nux=1 nuy=1 nuz=18 typ=square fill 9 7 6 1 2 3 4 5 8 71 7 6 13 2 3 4 5 16 end fill ara=2 nux=1 nuy=1 nuz=18 typ=square fill 25 23 22 17 18 19 20 21 24 72 23 22 28 18 19 20 21 31 end fill ara=3 nux=1 nuy=1 nuz=18 typ=square fill 41 39 38 33 34 35 36 37 40 73 39 38 44 34 35 36 37 47 end fill ara=4 nux=1 nuy=1 nuz=18 typ=square fill 57 55 54 49 50 51 52 53 56 74 55 54 60 50 51 52 53 63 end fill ara=5 nux=2 nuy=2 nuz=1 fill 48 64 10 32 end fill end array read bound xyf=mirror zfc=periodic end bound read start nst=0 end start read plot scr=yes lpi=10 ttl='plot1 xy slice' xul=-10 xlr=100 yul=100 ylr= -10 zul=61 zlr=61 uax=1 vdn=-1 nax=600 end ttl='plot2 xy slice' xul=-10 xlr=240 yul=240 ylr= -10 zul=61 zlr=61 uax=1 vdn=-1 nax=600 end ttl='plot3 xslice' xul=-5 xlr=100 yul= 27 ylr= 27 zul=190 zlr= -5 uax=1 wdn=-1 nax=600 end ttl='plot4 xslice' xul=-5 xlr=300 yul= 19 ylr= 19 zul=190 zlr= -5 uax=1 wdn=-1 nax=800 end end plot end data end
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 81 of 87 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 64 cuboid 1 38.47 0 38.47 0 164.864 0 array 4 1 place 1 1 1 19.235 19.235 17.522 boundary 1 global unit 65 com=^5 x 5 x 2 damaged array^
: 5. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in
cuboid 1 7.694000E+01 0.000000E+00 7.694000E+01 0.000000E+00 1.648640E+02 0.000000E+00 array 5 1 place 1 1 1 0.00000E+00 0.00000E+00 0.00000E+00 boundary 1 unit 71 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 72 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 73 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 74 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=-1.732 y=1.732 z=0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 83 of 90


=csas26 parm=Centrm nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in 238groupndf5 read composition wtptpuo2 1 1.6341 3 94239 37.5962 1001 6.4198 8016 55.9839 1 300 end atom-celt 2 0.2 3 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 83 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 82 of 87 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 end geometry read array ara=1 nux=1 nuy=1 nuz=18 typ=square fill 9 7 6 1 2 3 4 5 8 71 7 6 13 2 3 4 5 16 end fill ara=2 nux=1 nuy=1 nuz=18 typ=square fill 25 23 22 17 18 19 20 21 24 72 23 22 28 18 19 20 21 31 end fill ara=3 nux=1 nuy=1 nuz=18 typ=square fill 41 39 38 33 34 35 36 37 40 73 39 38 44 34 35 36 37 47 end fill ara=4 nux=1 nuy=1 nuz=18 typ=square fill 57 55 54 49 50 51 52 53 56 74 55 54 60 50 51 52 53 63 end fill ara=5 nux=2 nuy=2 nuz=1 fill 48 64 10 32 end fill end array read bound xyf=mirror zfc=periodic end bound read start nst=0 end start read plot scr=yes lpi=10 ttl='plot1 xy slice' xul=-10 xlr=100 yul=100 ylr= -10 zul=61 zlr=61 uax=1 vdn=-1 nax=600 end ttl='plot2 xy slice' xul=-10 xlr=240 yul=240 ylr= -10 zul=61 zlr=61 uax=1 vdn=-1 nax=600 end ttl='plot3 xslice' xul=-5 xlr=100 yul= 27 ylr= 27 zul=190 zlr=-5 uax=1 wdn=-1 nax=600 end ttl='plot4 xslice' xul=-5 xlr=300 yul= 19 ylr= 19 zul=190 zlr=-5 uax=1 wdn=-1 nax=800 end end plot end data end
: 5. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in
=csas26 parm=Centrm nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in 238groupndf5 read composition wtptpuo2 1 1.6341 3 94239 37.5962 1001 6.4198 8016 55.9839 1 300 end atom-celt 2 0.2 3 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 84 of 90


6000 6 1001 10 8016 5 1 300 end ss304 3 den=7.92 1 300 end al 4 den=2.7 1 300 end h2o 5 den=1 1 300 end pb 8 den=11.34 1 300 end al 9 den=0.28 1 300 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="PuO2 mixture" cylinder 1 6.41 20.475 -20.475 cylinder 4 6.41 20.475 - 20.475 cylinder 5 7.065 20.475 -21.13 cylinder 6 7.703 20.475 -21.13 cylinder 7 8.414 20.475 -21.13 cylinder 8 9.208 20.475 -21.13 c ylinder 9 10.493 20.475 -21.13 cylinder 10 22.987 20.475 - 21.13 cylinder 11 23.101 20.475 - 21.13 cylinder 12 23.223 20.475 - 21.13 cuboid 13 23.223 - 23.223 23.223 - 23.223 20.475 -21.13 media 1 1 1
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 83 of 87 6000 6 1001 10 8016 5 1 300 end ss304 3 den=7.92 1 300 end al 4 den=2.7 1 300 end h2o 5 den=1 1 300 end pb 8 den=11.34 1 300 end al 9 den=0.28 1 300 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="PuO2 mixture" cylinder 1 6.41 20.475 -20.475 cylinder 4 6.41 20.475 -20.475 cylinder 5 7.065 20.475 -21.13 cylinder 6 7.703 20.475 -21.13 cylinder 7 8.414 20.475 -21.13 cylinder 8 9.208 20.475 -21.13 cylinder 9 10.493 20.475 -21.13 cylinder 10 22.987 20.475 -21.13 cylinder 11 23.101 20.475 -21.13 cylinder 12 23.223 20.475 -21.13 cuboid 13 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1  
' media 5 1 2 -1
' media 5 1 2 -1  
' media 3 1 3 -2 media 5 1 4 -1 media 3 1 5 -4 media 1 1 6 - 5 -4 media 3 1 7 - 6 -5 media 5 1 8 - 7 -6 media 8 1 9 - 8 -7 media 5 1 10 -9 -8 media 5 1 11 -10 -9 media 3 1 12 -11 -10 media 5 1 13 -12 -11 boundary 13 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 1 1 2 -1 media 3 1 3 - 2 -1 media 5 1 4 - 3 -2 media 8 1 5 - 4 -3 media 5 1 6 - 5 -4 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 84 of 87
' media 3 1 3 -2 media 5 1 4 -1 media 3 1 5 -4 media 1 1 6 4 media 3 1 7 5 media 5 1 8 6 media 8 1 9 7 media 5 1 10 8 media 5 1 11 9 media 3 1 12 10 media 5 1 13 11 boundary 13 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 1 1 2 -1 media 3 1 3 1 media 5 1 4 2 media 8 1 5 3 media 5 1 6 4 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 85 of 90


media 5 1 7 - 6 -5 media 3 1 8 - 7 -6 media 5 1 9 - 8 -7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 - 23.223 23.223 - 23.223 5.922 0 media 3 1 1 media 5 1 2 -1 media 5 1 3 - 2 -1 media 5 1 4 - 3 -2 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 8 1 7 - 6 -5 media 5 1 8 - 7 -6 media 5 1 9 - 8 -7 media 3 1 10 -9 -8 media 5 1 11 -10 -9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 5 1 2 -1 media 8 1 3 - 2 -1 media 5 1 4 - 3 -2 media 5 1 5 - 4 -3 media 3 1 6 - 5 -4 media 5 1 7 - 6 -5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 5 1 2 -1 media 8 1 3 - 2 -1 media 4 1 4 - 3 -2 media 5 1 5 - 4 -3 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 85 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 84 of 87 media 5 1 7 5 media 3 1 8 6 media 5 1 9 7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 -23.223 23.223 -23.223 5.922 0 media 3 1 1 media 5 1 2 -1 media 5 1 3 1 media 5 1 4 2 media 3 1 5 3 media 5 1 6 4 media 8 1 7 5 media 5 1 8 6 media 5 1 9 7 media 3 1 10 8 media 5 1 11 9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 5 1 2 -1 media 8 1 3 1 media 5 1 4 2 media 5 1 5 3 media 3 1 6 4 media 5 1 7 5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 5 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 5 1 5 3 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 86 of 90


media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 5 1 8 - 7 -6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 - 4.191 cuboid 11 23.223 -23.223 23.223 - 23.223 0 -4.191 media 1 1 1 media 3 1 2 -1 media 1 1 3 - 2 -1 media 1 1 4 - 3 -2 media 3 1 5 - 4 -3 media 5 1 6 - 5 -4 media 8 1 7 - 6 -5 media 5 1 8 - 7 -6 media 5 1 9 - 8 -7 media 3 1 10 -9 -8 media 5 1 11 -10 -9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 - 0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 - 2.25 cylinder 5 22.987 0 - 2.25 cylinder 6 23.101 0 - 2.25 cylinder 7 23.223 0 - 2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 5 1 1 media 3 1 2 -1 media 5 1 3 - 2 -1 media 8 1 4 - 3 -2 media 5 1 5 - 4 -3 media 5 1 6 - 5 -4 media 3 1 7 - 6 -5 media 5 1 8 - 7 -6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 5 1 2 -1 media 5 1 3 - 2 -1 media 3 1 4 - 3 -2 media 5 1 5 - 4 -3 boundary 5 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 86 of 87
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 85 of 87 media 5 1 6 4 media 3 1 7 5 media 5 1 8 6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 -4.191 cuboid 11 23.223 -23.223 23.223 -23.223 0 -4.191 media 1 1 1 media 3 1 2 -1 media 1 1 3 1 media 1 1 4 2 media 3 1 5 3 media 5 1 6 4 media 8 1 7 5 media 5 1 8 6 media 5 1 9 7 media 3 1 10 8 media 5 1 11 9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 22.987 0 -2.25 cylinder 6 23.101 0 -2.25 cylinder 7 23.223 0 -2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 5 1 1 media 3 1 2 -1 media 5 1 3 1 media 8 1 4 2 media 5 1 5 3 media 5 1 6 4 media 3 1 7 5 media 5 1 8 6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 5 1 2 -1 media 5 1 3 1 media 3 1 4 2 media 5 1 5 3 boundary 5 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 87 of 90


unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 - 1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 - 11.044 media 4 1 1 media 5 1 2 -1 media 5 1 3 -2 media 3 1 4 -3 media 5 1 5 -4 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=''
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 86 of 87 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 -1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 -11.044 media 4 1 1 media 5 1 2 -1 media 5 1 3 -2 media 3 1 4 -3 media 5 1 5 -4 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=''
fill 9
fill 9
7 6
7 6
1 2
1 2
3 4
3 4
5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 87 of 87
5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 88 of 90


end start end data end
9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 87 of 87 end start end data end Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 89 of 90


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Latest revision as of 12:48, 24 November 2024

Enclosure 3 - AMNMS-14-0038 Appendix 6.1
ML24255A841
Person / Time
Site: 07109975
Issue date: 09/16/2014
From:
Office of Nuclear Material Safety and Safeguards
To:
Shared Package
ML24255A837 List:
References
S-SAR-G-00001
Download: ML24255A841 (1)
v • d • e


Text

APPENDIX 6.1 NUCLEAR CRITICALITY SAFETY EVALUATION:

9975 SHIPPING PACKAGE WITH PLUTONIUM OXIDE CONTENTS FOR NRC SAFETY ANALYSIS REPORT Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 1 of 90

This page intentionally left blank Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 2 of 90

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 3 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 2 of 87 DISCLAIMER This document was prepared by Savannah River Nuclear Solutions LLC (SRNS), under contract with the United States Department of Energy (DOE).

Release to and Use by Third Parties. As it pertains to releases of this document to third parties, and the use of or reference to this document by such third parties in whole or in part, neither SRNS, DOE, nor their respective officers, directors, employees, agents, consultants or personal services contractors (i) make any warranty, expressed or implied, (ii) assume any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product or process disclosed herein or (iii) represent that use of the same will not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trademark, name, manufacture or otherwise, does not necessarily constitute or imply endorsement, recommendation, or favoring of the same by SRNS, DOE or their respective officers, directors, employees, agents, consultants or personal services contractors. The views and opinions of the authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 4 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 3 of 87 REVISION

SUMMARY

Rev. #

Author Changes Date 0

M. D. Harris Initial issuance.

March 2013 1

M. D. Harris Address flooding the primary containment vessel (SCV) and secondary containment vessel (SCV) with fissile solution.

September 2014 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 5 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 4 of 87 TABLE OF CONTENTS Page

1.0 INTRODUCTION

............................................................................................................10

2.0 DESCRIPTION

................................................................................................................10 2.1 9975 Shipping Packages........................................................................................10 2.2 Plutonium Content Envelope.................................................................................13 2.3 3013 and Convenience Can...................................................................................13 2.4 9975 and 3013 Materials of Construction and Fissile Material Composition.......15 3.0 REQUIREMENTS DOCUMENTATION.....................................................................16 4.0 METHODOLOGY..........................................................................................................16 4.1 Computer Codes.....................................................................................................16 4.2 Code Validation and Bias......................................................................................16 4.2.1 Plutonium Solution....................................................................................17 4.2.2 Plutonium Oxide........................................................................................18 4.3 Material Compositions...........................................................................................18 5.0 DISCUSSION OF CONTINGENCIES..........................................................................19 6.0 EVALUATIONS AND RESULTS.................................................................................19 6.1 Model Descriptions................................................................................................19 6.1.1 Modeling Approximations.........................................................................19 6.1.2 Single Unit, NCT, and HAC Dimensions..................................................20 6.1.3 Single Unit Model......................................................................................21 6.1.4 NCT Model................................................................................................24 6.1.5 HAC Model................................................................................................25 6.2 Plutonium Oxide Content Envelope......................................................................27 6.3 Single Unit Analyses..............................................................................................27 6.3.1 Convenience Can Intact.............................................................................27 6.3.2 Convenience Can Damaged.......................................................................28 6.3.3 Damaged Containment and Flooding 6-inch SCV....................................33 6.4 Normal Conditions of Transport Array Analyses..................................................40 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 6 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 5 of 87 TABLE OF CONTENTS (continued)

Page 6.5 Hypothetical Accident Conditions Analyses.........................................................41 6.6 Criticality Safety Index..........................................................................................44 7.0 ADMINISTRATIVELY CONTROLLED LIMITS AND REQUIREMENTS.........45 8.0

SUMMARY

AND CONCLUSIONS..............................................................................46

9.0 REFERENCES

.................................................................................................................46 APPENDIX A SENSITIVITY STUDIES........................................................................48 APPENDIX B SAMPLE INPUT FILES.........................................................................51 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 7 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 6 of 87 LIST OF TABLES Page Table 1.

Geometric Specifications for the 9975 Shipping Packages.................................. 11 Table 2.

Plutonium Oxide Contents.................................................................................... 13 Table 3.

Types of Convenience Cans and 3013 Containers............................................... 14 Table 4.

Material Specifications for the 9975 and 3013 Containers................................... 15 Table 5.

ksafe Values for Plutonium..................................................................................... 18 Table 6.

Drum and Celotex Dimensions for Different KENO Models............................ 21 Table 7.

Fire and Drop Test Data for the HAC Model....................................................... 26 Table 8.

Base Case Single Unit Cases Without Flooding................................................... 28 Table 9.

Single Unit Cases Flooding the Convenience Can............................................... 29 Table 10.

Single Unit Cases Flooding the Convenience Can - Beryllium........................... 29 Table 11.

Single Unit Cases Flooding the Convenience Can - No 3013 Containers........... 30 Table 12.

Single Unit Cases Flooding the Convenience Can with Beryllium - No 3013..... 30 Table 13.

Single Unit Cases Flooding the Convenience Can with Carbon.......................... 31 Table 14.

Single Unit Cases Flooding the PCV, SCV, and Celotex - Inner 3013 Flooded................................................................................................................. 31 Table 15.

Single Unit Cases Flooding the PCV, SCV, and Celotex - Outer 3013 Flooded................................................................................................................. 32 Table 16.

Single Unit Cases Flooding the PCV, SCV, and Celotex - Both 3013 Containers Flooded............................................................................................... 32 Table 17.

Single Unit Cases Flooding the PCV, SCV, and Celotex - No 3013 Containers............................................................................................................. 33 Table 18.

Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water................... 35 Table 19.

Filling 5-inch PCV and 6-inch SCV with PuO2, Beryllium and Flooding Water..................................................................................................................... 36 Table 20.

Filling 5-inch PCV and 6-inch SCV with PuO2, Carbon and Flooding Water..... 37 Table 21.

Filling 5-inch PCV and 6-inch SCV with PuO2 - Celotex Flooded.................... 39 Table 22.

9975 Array Model - NCT Cases.......................................................................... 40 Table 23.

9975 Array Model - HAC Cases.......................................................................... 43 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 8 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 7 of 87 LIST OF TABLES (continued)

Page Table 24.

9975 Array Model - Flooded Convenience Can HAC Cases............................... 43 Table 25.

CSI Calculation..................................................................................................... 45 Table 26.

Plutonium Oxide Contents.................................................................................... 45 Table A1.1.

Variation of keff with Celotex Density................................................................ 48 Table A1.2.

Stainless Steel Composition.................................................................................. 49 Table A1.3.

Variation of keff with Stainless Steel Composition............................................... 49 Table A1.4.

Variation of Dimensional Tolerances on PCV and SCV - Single Unit............... 50 Table A1.5.

Stainless Steel Sleeve Sensitivity Calculation...................................................... 50 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 9 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 8 of 87 LIST OF FIGURES Page Figure 1.

General Schematic of the 9975 Shipping Package (convenience can not shown)............................................................................................................. 22 Figure 2.

9975 Single Unit with Convenience Can/3013 Combination............................... 23 Figure 3.

9975 Single Unit with 6-inch SCV and 5-inch PCV Flooded.............................. 24 Figure 4.

Normal Condition Transport Infinite Array.......................................................... 25 Figure 5.

2x2x2, Hypothetical Accident Condition............................................................. 26 Figure 6.

HAC Array (2x2x2) Model, Plan View................................................................ 27 Figure 7.

Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water................... 34 Figure 8.

2x2x2 Closest Contact Model (Case 1)................................................................ 42 Figure 9.

2x2x2 Symmetrical Model (Case 5)..................................................................... 43 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 10 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 9 of 87 ACRONYMS AND ABBREVIATIONS AEG Average Energy Group AOA Area of Applicability CC Convenience Can CSACC Criticality Safety Advanced Computing Center CSI Criticality Safety Index HAC Hypothetical Accident Condition LTB Lower Tolerance Band MSM Minimum Subcritical Margin NCSE Nuclear Criticality Safety Evaluation NCT Normal Condition of Transport NRC Nuclear Regulatory Commission PCV Primary Containment Vessel SARP Safety Analysis Report for Packaging SCV Secondary Containment Vessel SRNS Savannah River Nuclear Solutions SS Stainless Steel Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 11 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 10 of 87

1.0 INTRODUCTION

This Nuclear Criticality Safety Evaluation (NCSE) demonstrates the safe configurations of the 9975 shipping package for plutonium oxide material loading under various conditions in support of the Nuclear Regulatory Commission (NRC) Safety Analysis Report.

Criticality safety analysis of the 9975 shipping package in support of the Safety Analysis Report for Packaging (SARP) was previously documented in N-NCS-F-00087, Rev. 2, 9975 Shipping Container Analysis with Revised Contents for SARP, Revision 0. The previous evaluation demonstrated that contents up to 4.4 kg of plutonium as metal, which was described as a bounding material, with up to 100 grams of plastics could be safely shipped in the 9975 shipping package. This evaluation performs an explicit analysis for the plutonium oxide (PuO2) material shipped in a convenience can.

The evaluation in this NCSE demonstrates that the 9975 shipping package is subcritical with adherence to the design features, limits, and controls specified in Section 7.0.

2.0 DESCRIPTION

The following sections describe the geometry and materials of construction of the 9975 shipping package and the convenience can/3013 configuration.

2.1 9975 SHIPPING PACKAGES The 9975 shipping package consists of two concentric stainless steel cylindrical containment vessels, a 35-gallon stainless steel drum, cane fiberboard insulation (Celotex), aluminum bearing plates, lead shield, and aluminum honeycomb spacers. The inner containment vessel is called the primary containment vessel (PCV), and the outer containment vessel is called the secondary containment vessel (SCV). The SCV is surrounded on the sides and the bottom by 1/2 inch of lead shielding. Low-density cane fiberboard (Celotex) surrounds the shield to fill the remainder of the 35-gallon drum. Other components of the package include a 1/2-inch thick aluminum lid to cover the lead shield and two 1/2-inch thick aluminum bearing plates - one below the lead shield and one on top of the aluminum lid. Nuclear fuel material contained in product cans (3013 and convenience can) is loaded into the PCV, which is sealed with a stainless steel plug and locking nut.

Table 1 lists dimensions of various components of the 9975 shipping package and the as-modeled dimensions of each component. The Specification column of Table 1 indicates the nominal dimensions of each component.

Per ASTM A312, Specification for Seamless and Welded Austenitic Stainless Steel Pipes, there is a tolerance of +22.5% / -12.5% on the wall thickness and a tolerance on the outer diameter of

+1/16 / -1/32 inch for the PCV and the SCV. A sensitivity study (as shown in Appendix A) was performed on the variation of dimensional tolerances of the PCV and the SCV. It was determined that there was statistically no significant variations among the keff values calculated with nominal, minimum, and maximum wall thicknesses. Table 1 also gives the tolerance on drum radius.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 12 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 11 of 87 The base KENO model was developed from the component specifications listed in Table 1 (see Section 6.1 for description of the KENO models).

Table 1.

Geometric Specifications for the 9975 Shipping Packages Component Parameter Specification Inch (cm)

KENO Model (cm)

PCV Internal Height 18.63 - 1.88 - 0.37 -

0.258 = 16.122 (40.95 cm) 40.95 PCV Bottom Thickness 0.258 (0.655 cm) 0.655 PCV Top Thickness 1.88 - 0.5 = 1.38 (3.505 cm) 3.505 PCV Top Nut Height (top portion) 0.5 (1.27 cm) 1.270 PCV Leg Height 0.37 (0.94 cm) 0.94 PCV Inner Radius 5.047*0.5 (6.410 cm) 6.410 PCV Outer Radius 5.563*0.5 (7.065 cm) 7.065 SCV Top Aluminum Spacer Height 1.80 (4.572 cm) 4.572 SCV Void Space Height 24.0 - 1.88 - 0.38 -

0.28-1.0 - 18.63 + 0.5

- 1.8 = 0.53 (1.35 cm) 1.35 SCV Top Thickness 1.88 - 0.5 = 1.38 (3.505 cm) 3.505 SCV Top Nut Height (top portion) 0.5 (1.27 cm) 1.27 SCV Bottom Aluminum Honeycomb Spacer Height 1.0 (2.54 cm) 2.54 SCV Bottom Thickness 0.28 (0.711 cm) 0.711 SCV Leg Height 0.38 (0.965 cm) 0.965 SCV Inner Radius 6.065*0.5 (7.7026 cm) 7.703 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 13 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 12 of 87 Component Parameter Specification Inch (cm)

KENO Model (cm)

SCV Outer Radius 6.625*0.5 (8.414 cm) 8.414 SCV Spacer Inner/Outer Radius 3.7*0.5/5.8*0.5 (4.699/7.366 cm) 4.699/7.366 Drum Inner Radius (18.25 +/- 0.06)*0.5 18.19 *0.5, min

= 9.095 (23.101 cm) 21.466 (calculated NCT value)

Drum Outer Radius (23.101 + 0.122) cm (23.223 cm) 23.223*.93

=21.597 (NCT Value)

Drum Top Void Thickness (nominal) 34.75 - 33.90 = 0.85 (2.16 cm) 2.16 Drum Top Wall Thickness 0.048 (0.122 cm) 0.122 Drum Bottom Void Thickness 0

(0 cm) 0 Drum Bottom Wall Thickness 0.048 (0.122 cm) 0.122 Drum Top Wall Thickness 0.048 (0.122 cm) 0.122 Aluminum Lid for Lead Shield Thickness 0.5 (1.27 cm) 1.27 Drum Inner Height 34.75 (88.265 cm)

Used to calculate top void thickness in drum Lead Shield Thickness 0.506, min (1.285 cm)

(lead thickness includes two 0.036-inch SS304 liners) 1.285 Lead Shield Inner Radius 7.25*0.5 = 3.625 (9.208 cm) 9.208 Lead Shield Outer Radius 3.625+0.506 = 4.131 (10.493 cm) 10.493 Aluminum Plate Outer Radius 5.6 (14.224 cm) 14.224 Aluminum Bearing Plate, Top Height 0.5 (1.27 cm) 1.27 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 14 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 13 of 87 Component Parameter Specification Inch (cm)

KENO Model (cm)

Aluminum Bearing Plate, Bottom Height 0.5 (1.27 cm) 1.27 Celotex Top Thickness 3.7 (9.398 cm) 9.398 Celotex Bottom Thickness 3.8 (9.652cm) 9.652 Celotex Outer Radius 18.1*0.5 = 9.05 (22.987 cm) 22.987 (Single Unit Model) 21.466 (NCT Model)

(used 21.466 to match inner diameter of drum) 2.2 PLUTONIUM CONTENT ENVELOPE The fissile material evaluated to be shipped in a 9975 shipping package consists of a maximum of 5.0 kg plutonium oxide contained within a convenience can. The plutonium isotopic composition is conservatively chosen as 100% 239Pu. Beryllium and carbon are analyzed assuming up to 500 grams of beryllium or 1,000 grams of carbon as a moderator mixed with the fissile material. When beryllium or carbon are added to the model, the mass of the PuO2 is decreased to maintain the 5.0 kg net weight of the contents. Beryllium metal has a density of 1.85 g/cc, and the carbon has a density of 2.3 g/cc. See Table 2 for contents.

Table 2.

Plutonium Oxide Contents Material Mass (kg)

PuO2 5.0 Beryllium 0.5 Carbon 1.0 This evaluation, based on plutonium oxide, also bounds contents with mixtures of plutonium and uranium oxide of the same total mass.

2.3 3013 AND CONVENIENCE CAN A convenience can is used to contain the fissile material. The convenience can is housed in the 3013 containers of the 9975 during transport. The 3013 container consists of two nested and sealed containers which isolate the fissile material. The 3013 containers and the convenience cans are fabricated of stainless steel. Table 3 lists three types of convenience cans with their associated 3013 containers, along with their dimensions, used for shipment of oxide powder.

The bounding dimensions for the reference convenience can and 3013 containers developed for the KENO model are also shown in Table 3. The KENO model used in this analysis has Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 15 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 14 of 87 dimensions consistent with the volume of the Rocky Flats configuration due to its slightly larger volume.

Table 3.

Types of Convenience Cans and 3013 Containers Parameter Nominal Dimensions (cm)

Rocky Flats Hanford SRS Reference Dimension for KENO Model Convenience Can Outer Diameter 11.00 10.85 11.16 11.00 Outer Diameter -

Inner Diameter Difference 0.05 0.31 0.21 0.05 Top Lid /Bottom Thickness 0.025/

0.025 0.305/

0.635 0.163/

0.152 0.025/

0.025 External Height 20.75 20.40 18.80 20.75 Internal Height 20.70 19.46 18.48 20.70 Material SS 316 SS 304/304L SS 304/304L Reference M-PV-F-0015 R-R4-F-0144 R-R1-F-0098 Inner Can Outer Diameter 11.35 11.68 11.16 11.35 Outer Diameter -

Inner Diameter Difference 0.30 0.30 0.21 0.30 Top Lid /Bottom Thickness 0.20/0.15 0.152/0.635 0.163/152 0.20/0.15 External Height 23.10 22.00 18.80 23.10 Inner Height 22.75 21.21 18.48 22.75 Material SS 316 SS 304L SS 304L Reference M-PV-F-0016 R-R4-F-0107 R-R4-F-0107 Outer Can Outer Diameter 25.40 25.40 25.40 25.40 Outer Diameter -

Inner Diameter Difference 0.62 0.62 0.62 0.62 Top Lid /Bottom Thickness 1.91/0.90 1.91/0.90 1.91/0.90 1.91/0.90 External Height 25.40 25.40 25.40 25.40 Internal Height 22.59 22.59 22.59 22.59 Material SS 316 SS 316 SS 316 Reference M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 M-PV-F-0017 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 16 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 15 of 87 2.4 9975 AND 3013 MATERIALS OF CONSTRUCTION AND FISSILE MATERIAL COMPOSITION The convenience can, 3013 containers, PCV, SCV, and the drum are made of 304L or 316 stainless steel (SS). However, the analysis used a standard stainless steel, SS 304 with a density of 7.92 g/cc. The small difference in composition between SS 304, SS 304L, and SS 316 will have a negligible effect on reactivity (see the sensitivity study in Appendix A).

As described in Appendix A, Celotex insulation with a nominal density of 0.22 to 0.26 g/cc has the elemental composition of cellulose (C6H10O5). In addition, Appendix A shows that keff increases as the Celotex density is decreased. Thus, to account for void spaces between layers, this analysis will use a Celotex density of 0.20 g/cc. See sensitivity studies documented in Appendix A.

Water density is conservatively taken as 1.0 g/cc instead of a nominal value of 0.9982 g/cc at 20ºC to cover temperatures as low as 0ºC.

Aluminum honeycomb spacer density is selected as 0.28 g/cc (estimated density using simplistic calculations). Any variation of aluminum honeycomb spacer density will have a negligible effect on the system reactivity. Standard material densities of lead and aluminum bearing plates are used (see Table 4).

Table 4.

Material Specifications for the 9975 and 3013 Containers Components Material Density(g/cc)

(as-modeled)*

Reference Water H2O 0.9982 at 20°C 0.99998 at 4°C used 1.0 g/cc PCV 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 SCV 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 Drum 304L-Stainless Steel (used SS 304) 7.92 ORNL/TM-2005/39 Aluminum Lid & Plates Aluminum 2.70 Lead Shield Lead 11.34 ORNL/TM-2005/39 Celotex C6H10O5 (0.22 - 0.26 g/cc)

(used 0.20 g/cc)

Appendix A 3013, Outer Can 316L-SS (used SS 304) 7.92 ORNL/TM-2005/39 3013, Inner Can 316-SS (used SS 304) 7.92 ORNL/TM-2005/39 Convenience Can 316-SS / 304L-SS (used SS-304) 7.92 ORNL/TM-2005/39 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 17 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 16 of 87 3.0 REQUIREMENTS DOCUMENTATION This NCSE is prepared in accordance with SCD-3, Revision 27, Nuclear Criticality Safety Manual; SRNS-IM-2009-00035, Revision 2, Criticality Safety Methods Manual; and 10 CFR Part 71, Packaging and Transportation of Radioactive Material.

NUREG/CR-5661, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, for criticality safety evaluation of transportation packages was also followed.

4.0 METHODOLOGY The following sections provide a high level overview of the criticality safety computer codes used in this analysis, justify the lower tolerance limit and the minimum subcritical margin (MSM), define the area of applicability (AOA), and justify a value for ksafe for this analysis.

Other sections address material compositions and various analysis methods utilized in this analysis.

4.1 COMPUTER CODES The SCALE 5 code system, ORNL/TM-2005/39, Version 5, SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, operating on the SRNS Criticality Safety Advanced Computing Center (CSACC) was used to calculate keff values for this study. The SCALE system is under configuration control, SRNS-RP-2008-00150, Revision 1, Software Configuration and Control Guidance for SCALE on SRS Personal Computers (U), and SRNS-RP-2008-00151, Revision 1, SCALE Test Report for SRS Personal Computers (U). The CSAS26 driver was used. It calls the BONAMI and CENTRM modules for the generation of a problem-dependent cross sections library (accounting for resonance self-shielding) and then calls the KENO-VI module to perform the Monte Carlo keff calculations. All calculations used the 238-group ENDF/B-V cross section set (ORNL/TM-12370, The LAW-238 Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations). Calculations were performed using numbers of generations and neutrons per generation to achieve a calculated statistical uncertainty () less than 0.002.

4.2 CODE VALIDATION AND BIAS SCALE 5 has been validated for Pu solution and Pu oxide systems (SRNS-RP-2008-00153, Rev. 0, SCALE 5.0 Validation for SRNS Personal Computers (U)) on the SRNS CSACC system.

No critical experiments similar to the 9975 shipping package systems with Pu/U metal/oxide are available. Therefore a wide set of validation experiments was chosen for this study. Table 5 shows the bias and ksafe values for different systems. NUREG/CR-5661 specifies a minimum required margin of subcriticality of 0.05 for packaging applications. Because a large MSM has been used for the 9975 analysis using common fissile materials and drum components, no additional margin due to areas of applicability is necessary.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 18 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 17 of 87 SCD-3 provides guidance to determine an upper bound of system reactivity, called ksafe, which is determined using the following equation:

ksafe = 1 - B - AOA - MSM (1)

Where:

ksafe is a conservative upper bound for which a system can be said to be safely subcritical.

B is an upper bound for the bias. This term accounts for the bias and its uncertainty and is generally dependent on the system being evaluated.

AOA is a margin associated with the area of applicability for the system being evaluated. This term is used to compensate for relevant differences that may be encountered between the system being evaluated and the selected set of validation studies used in determining B.

This term is called the area of applicability margin.

MSM is a minimum subcritical margin, an arbitrary margin that is used to ensure subcriticality and, unlike AOA, is independent of the fissile configuration, but rather its magnitude relies in part on the complexity of the entire process being evaluated. This term provides a buffer that is judged to be sufficient to compensate for relevant uncertainties or lack of confidence in understanding the entire process.

In the validation studies documented in SRNS-RP-2008-00153, the bias and its uncertainty are provided in terms of the lower tolerance band (LTB), and are related to B by the following:

LTB = 1 - B (2)

Using the definition for LTB from Equation (2) with Equation (1) and removing the AOA per above discussion yields the following equation for ksafe:

ksafe = LTB - MSM (3) 4.2.1 Plutonium Solution For the plutonium solution fuels, the validation in SRNS-RP-2008-00153, Revision 0, utilized critical experiments involving plutonium nitrate solution. The biased keff values were taken from the validation reference and were based on LTB for the system(s) considered. The LTB values recommended are based on Equation (4) for which the values of H/239Pu atom ratio is calculated from the multiple calculations performed.

LTB (PuSol) = 0.99341 + [0.0000053803

  • H/239Pu] + [-0.0000000009576 * (H/239Pu)2] (4)

Where H/239Pu is the hydrogen to 239Pu atom ratio and the constants are those provided by the quoted reference. The lowest calculated LTB value for plutonium solution is 0.9934.

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9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 18 of 87 4.2.2 Plutonium Oxide For the plutonium oxide fuels, the validation in SRNS-RP-2008-00153, Revision 0, utilized critical experiments involving plutonium oxide. The biased keff values were taken from the validation reference and were based on LTB for the system(s) considered. The LTB values recommended are based on Equation (5) for which the values of AEG (Average Energy Group) are taken from the multiple calculations performed.

LTB (PuO2) = 0.99529 + [0.000086341

  • AEG] + [-0.00000069867 * (AEG)2]

(5)

Where AEG is the energy of a neutron causing fission and the constants are those provided by the quoted reference. The lowest calculated LTB value plutonium oxide is 0.9953.

Table 5.

ksafe Values for Plutonium System LTB MSM

= ksafe Plutonium Solution 0.99340 0.05 0.943 Plutonium Oxide, dry 0.99530 0.05 0.945 The validations for the plutonium oxide and plutonium solution critical experiments in SRNS-RP-2008-00153 are used to determine the ksafe value applicable to this analysis. Table 5 shows that the ksafe value of 0.943 derived for plutonium solution experiments is bounding.

4.3 MATERIAL COMPOSITIONS Table 4 provides a specification of materials used in this analysis and the material density as modeled. The following is a brief discussion of the modeling choices made for this analysis.

  • Plutonium oxide was modeled as Pu with 100% by weight 239Pu.

In ANSI/ANS-8.1, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, 239Pu limits apply to isotopic mixtures of plutonium provided that the concentration of 240Pu exceeds that of 241Pu and all isotopes are considered to be 239Pu.

The package contents meet this restriction. Therefore, the content envelope is conservatively modeled as 100% 239Pu.

  • The compositions of lead, aluminum, SS 304, and water used the Standard Composition Library in SCALE.
  • Aluminum used the standard composition library except in the case of the honeycomb spacer, which uses a lower density per Section 2.4.

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9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 19 of 87 5.0 DISCUSSION OF CONTINGENCIES 10 CFR 71 specifies the contingencies that are to be considered in the shipping package criticality analysis. Specifically, the objective of this evaluation is to demonstrate compliance with the performance requirements for each content envelope as specified in:

a) 10 CFR 71.55 - General requirements for fissile material packages b) 10 CFR 71.59 - Standards for arrays of fissile material packages The requirements of 10 CFR 71 are thorough and ensure that the maximum value of keff is found in the analysis based on prescribed configurations. These configurations are related to and are bounding of the conditions (including accident scenarios) a shipping package may be subjected to during its use. 10 CFR 71 requires that the system keff remains less than ksafe for each of the prescribed configurations. Thus, 10 CFR 71 does not require a contingency analysis.

The following specific scenarios are analyzed based on the requirements:

i)

Single unit - dry and flooded ii)

Normal condition of transport (NCT) array iii)

Hypothetical accident condition (HAC) array 6.0 EVALUATIONS AND RESULTS Calculations and evaluations were performed to demonstrate that the 9975 shipping packages evaluated with 5 kg of PuO2 with no more than 500 grams of beryllium and 1,000 grams of carbon can be safely transported.

6.1 MODEL DESCRIPTIONS 6.1.1 Modeling Approximations The KENO models for single unit, NCT arrays, and HAC arrays include the following simplifications:

  • PCV and SCV are approximated as right circular cylinders.
  • Rolling hoops and the drum lid closure are ignored.

Per Table 1, nominal 9975 component dimensions (except the drum diameter) were used, since the dimensional tolerances were small and their effects on reactivity were shown to be Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 21 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 20 of 87 insignificant. But the lower tolerance value was used for the drum diameter to conservatively estimate the array pitch and, thus, to maximize the interaction effect among the fissile units in different packages. In this analysis, the two rolling hoops and bolted ring closure of the 9975 containers were neglected. Neglecting these geometric details reduces the effective drum diameter, which in turn conservatively models the array pitch.

6.1.2 Single Unit, NCT, and HAC Dimensions Table 6 shows the 9975 drum and Celotex dimensions used for the single unit, NCT, and HAC model.

The single unit model used the base shipping package dimensions, which are shown in Table 6.

For the NCT array model (rectangular pitch), the outer nominal drum radius is reduced by 7%.

NUREG/CR-5661 shows that a rectangular pitch drum array, with the drum radius reduced by 7%, is equivalent to a triangular pitch drum array. To preserve the drum wall mass, the drum wall thickness was adjusted (see Table 6).

For the HAC array model, the drum radius was decreased corresponding to a specified amount due to the damage from a prescribed drop, and then was further reduced by 7% to simulate a triangular pitch array. A triangular pitch array model places fissile material units (drums) as close as possible, maximizing the areal density of fissile units, and thereby increasing the reactivity effect due to interaction.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 22 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 21 of 87 Table 6.

Drum and Celotex Dimensions for Different KENO Models Dimension Specification (cm)

Single Unit Model (cm)

NCT Model (cm)

HAC Model (cm)

Drum Outer Radius 23.101+0.122

=23.223 cm 23.101 + 0.122

=23.223 cm 23.223 *0.93

= 21.597 19.235 (23.223-2.54)*0.93 Note:

1.0 inch (2.54 cm) drum radial reduction due to impact (see Table 7)

Drum Wall Thickness (0.048 inch) 0.122 cm 0.122 cm 0.131 **

(** 0.122 cm thickness is changed to 0.131 cm to conserve mass of drum wall) 0.147 Drum Inner Radius (18.25+/-0.06)*0.5 inches (cm)

(18.19*0.5 =

9.095 inches) 23.101cm 21.597-0.131

=21.466 19.088 Celotex Outer Radius 18.1*0.5

= 9.05 inches 22.987 cm 22.987 cm 21.466 to match the inner diameter of drum 22.987 - 6.35

=16.637 Note:

2.5 inches (6.35 cm) of Celotex loss due to fire (see Table 7) 6.1.3 Single Unit Model Figure 1 shows a schematic of the 9975 shipping package (convenience can/3013 containers not shown), and Figure 2 shows the corresponding KENO model. The 9975 drum overall size is about 34 inches in height and 18 inches in diameter. The base case model analyzed the fissile material as a mixture of plutonium oxide and 0.5% of water to account for moisture content. The fissile material is configured as a right circular cylinder, inside a convenience can, with a height/diameter ratio equal to 1 to maximize reactivity since formation of a perfectly spherical configuration is not credible for oxide material. This base case 9975 model assumed no additional water or flooding with the 3013, PCV, and SCV remaining dry.

10 CFR 71.55 requires single unit analysis to account for the most reactive configurations, including moderation by water to the most reactive credible extent. Therefore, to simulate water inleakage, subsequent variations of the base case modeled water flooding into the convenience can, 3013, PCV, and SCV while keeping the amount of fissile material constant. This parametric study included variations of water flooding into the convenience can, 3013, PCV, and SCV.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 23 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 22 of 87 Figure 1.

General Schematic of the 9975 Shipping Package (convenience can not shown)

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 24 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 23 of 87 Figure 2.

9975 Single Unit with Convenience Can/3013 Combination The convenience can or 3013 containers are not considered a containment boundary, therefore, subsequent variations of the base case model removed the convenience can or 3013 containers.

The first series of cases will have the PCV containing a mixture of water and plutonium oxide.

As water enters the PCV, a plutonium oxide solution is created with water reflection above the solution, until the entire volume of the PCV is filled. As the plutonium oxide-water mixture volume increases, the water reflection above the mixture decreases and the space between the SCV and the stainless steel of the PCV is initially filled with water.

These cases were modeled with the SCV and PCV in position containing water or plutonium oxide solution, removing the stainless steel of the convenience can and 3013 containers. The stainless steel PCV, being credited as a containment boundary, will remain in the SCV, as it is not credible for the PCV to be absent from the shipping package. However, all aluminum within the SCV, which has minimal neutronic impact on criticality, has been replaced with either water or fissile solution, depending on the case being evaluated.

The next series of cases will have the primary containment vessel and secondary containment vessel both containing a plutonium oxide solution. Thus, as water is added to the shipping package, the plutonium oxide-water solution will fill the total volume (height and diameter) of the SCV, minus the space occupied by the steel of the PCV, keeping the fissile mass constant.

Thus, as the PCV fills with fissile solution, the spillage fills the gap between the SCV and the stainless steel of the PCV (Figure 3). And, as the plutonium oxide-water mixture volume increases, the water reflection around or above the mixture decreases. This parametric study is illustrated in Figure 3 as a cylinder of plutonium oxide-water mixture (magenta), filling the SCV (cyan) and PCV (cyan). For this single package analysis, the outer container (drum) was reflected with 30 cm of water on all sides.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 25 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 24 of 87 Figure 3.

9975 Single Unit with 6-inch SCV and 5-inch PCV Flooded 6.1.4 NCT Model 10 CFR 71.55 requires the NCT analysis to address undamaged packages in an array. Therefore, for the NCT model, an infinite array of undamaged 9975 shipping packages was analyzed with the convenience can containing the plutonium oxide, in dry conditions (the 0.5% for moisture content is included as dry conditions). This model is similar to the base case single unit model but with an infinite array of 9975 drums containing fissile material.

In the infinite models, there is no leakage from the system (the 3013, PCV, and SCV remain dry), and reflection is irrelevant. Thus, a single 9975 package was modeled inside a tight fitting cuboid with mirror boundary conditions defined for the four x and y faces. In addition, periodic boundary conditions were defined for the z faces of the cuboid using standard KENO options (Figure 4). These boundary conditions reflected all incident neutrons back into the system, thus simulating an infinite square pitch array of packages.

Although the NCT analysis evaluates undamaged packages, cases were analyzed to account for water being present in the Celotex.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 26 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 25 of 87 Figure 4.

Normal Condition Transport Infinite Array 6.1.5 HAC Model The HAC model is required per 10 CFR 71.55 to address the most credible configuration of damaged packages, thus an infinite array of 2x2x2 clusters of damaged 9975 packages was used in this analysis. The 2x2x2 array configuration was modeled inside a tight fitting cuboid with mirror boundary conditions defined for the four x and y faces. In addition, periodic boundary conditions were defined for the z faces of the cuboid using standard KENO options (Figure 5).

The damaged HAC array model used conservative assumptions regarding the radial and axial reduction of drum dimensions to address a drop and the amount of Celotex charred due to fire, as shown in Table 7. Additional reduction factors were added to the burn and drop test data for conservatism, also shown in Table 7. As previously stated and as documented in Appendix A, Celotex inhibits neutronic interaction between packages and removing the outer layers of Celotex increases the keff for array calculations; thus, modeling less Celotex is conservative.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 27 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 26 of 87 Table 7.

Fire and Drop Test Data for the HAC Model Dimension Celotex Burn Test Data (inch)

HAC Model (inch)

Drop Test Data (inch)

HAC Model (inch)

Radial 2.3 2.5 0.5 1.0 Axial (top/bottom) 1.4/2.0 2.0/2.0 1 (total) 1.0/1.0 Reference WSRC-SA-7, Revision 14, Safety Analysis Report -

Packages 9965, 9968, 9972 -

9975 Packages (U), Appendix 3.7, Thermal Test.

WSRC-SA-7, Chapter 2.0.

This section describes the basic HAC model, shown in Figure 5. Section 6.5 discusses the variations of the basic model.

Figure 5.

2x2x2, Hypothetical Accident Condition The drum dimensions are reduced based on the test data, as shown in Table 6. The Celotex outer dimensions are also reduced based on fire data. Charred Celotex is assumed to be completely vaporized.

To address the fissile units at close contact, a conservative HAC model is constructed by assuming maximum movement of the inner containment vessels (Figure 6). The Celotex has also moved and is off-center. The fissile material is in the dry configuration of the single unit base case model, which is contained in the volume of the convenience can. This is shown in Figure 6, as indicated in red.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 28 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 27 of 87 Figure 6.

HAC Array (2x2x2) Model, Plan View 6.2 PLUTONIUM OXIDE CONTENT ENVELOPE The fissile material evaluated to be shipped in a 9975 shipping package consists of a maximum of 5.0 kg plutonium oxide contained within a convenience can. The plutonium isotopic composition is conservatively chosen as 100% 239Pu. Beryllium and carbon are analyzed assuming up to 500 grams of beryllium or 1,000 grams of carbon as a moderator mixed with the fissile material. As indicated in Section 2, when beryllium or carbon is added to the model the mass of the PuO2 is decreased to maintain the 5.0 kg net weight of the contents. Beryllium metal has a density of 1.85 g/cc, and the carbon has a density of 2.3 g/cc.

6.3 SINGLE UNIT ANALYSES 10 CFR 71.55 contains the following requirements for single package analyses:

(b) Except as provided in paragraph (c) or (g) of this section, a package used for the shipment of fissile material must be so designed and constructed and its contents so limited that it would be subcritical if water were to leak into the containment system, or liquid contents were to leak out of the containment system so that, under the following conditions, maximum reactivity of the fissile material would be attained:

(1) The most reactive credible configuration consistent with the chemical and physical form of the material; (2) Moderation by water to the most reactive credible extent; and (3) Close full reflection of the containment system by water on all sides, or such greater reflection of the containment system as may additionally be provided by the surrounding material of the packaging.

6.3.1 Convenience Can Intact The single unit base case model was developed with a maximum of 5.0 kg plutonium oxide and 0.5% water fissile mixture contained in the convenience can. The convenience can and 3013 containers are assumed to be leak tight, thus the fissile material remains dry. Cases were Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 29 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 28 of 87 modeled with and without the 3013 container. Table 8 summarizes the resultant keff values.

Figure 2 shows the fissile material and convenience can/3013 combination in the 9975 shipping package.

Table 8.

Base Case Single Unit Cases Without Flooding Case No.

File ID Description keff keff +2

1.

nrc_su.cyl3013.out:

Base Case with 3013, dry oxide 0.5922 0.0010 0.595

2.

nrc_su.cyl3013be.out:

Base Case with 3013 and mixed with beryllium, dry oxide 0.4805 0.0009 0.483

3.

nrc_su.cylno3013.out:

Base Case with no 3013, dry oxide 0.5796 0.0010 0.582

4.

nrc_su.cylno3013be.out:

Base Case with no 3013 and mixed with beryllium, dry oxide 0.4669 0.0009 0.469

5.

nrc_su.cyl3013c12.out:

Base Case with 3013 and mixed with carbon, dry oxide 0.3880 0.0007 0.390 As seen in Table 8, the base case (Case 1) with a convenience can containing dry plutonium oxide, with the 3013 containers in place, yields a maximum keff value of 0.595. In addition, Table 8 shows that the addition of beryllium or carbon does not cause an increase in keff above the base case with dry plutonium oxide in an intact convenience can/3013 configuration (Case 1).

6.3.2 Convenience Can Damaged To address damage to the convenience can and flooding, a parametric study was performed filling the convenience can with water while maintaining the fissile material constant at 5.0 kg plutonium oxide. As discussed earlier, the height/diameter ratio is equal to 1 to maximize reactivity until the fissile cylinder fills the diameter of the inner container. Then the height of the cylinder will be increased until the inner container is full. Therefore, the fissile solution fills the entire width of the convenience can and the water level is varied (Table 9).

Tables 9 through 17 present these single unit results.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 30 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 29 of 87 Table 9.

Single Unit Cases Flooding the Convenience Can Case No.

File ID Description keff keff +2

1.

nrc_su.cyl3013_100.out:

Base Case with 3013, dry oxide - 0.1 liter water added 0.5602 0.0010 0.563

2.

nrc_su.cyl3013_200.out:

Same as #1 - 0.2 liter water added 0.5513 0.0010 0.554

3.

nrc_su.cyl3013_300.out:

Same as #1 - 0.3 liter water added 0.5541 0.0010 0.557

4.

nrc_su.cyl3013_400.out:

Same as #1 - 0.4 liter water added 0.5637 0.0010 0.566

5.

nrc_su.cyl3013_400w.out:

Same as #1 - 0.4 liter water added, diameter of convenience can (CC) 0.5657 0.0010 0.568

6.

nrc_su.cyl3013_500w.out:

Same as #5 - 0.5 liter water added 0.5692 0.0011 0.572

7.

nrc_su.cyl3013_750w.out:

Same as #5 - 0.75 liter water added 0.5897 0.0013 0.593

8.

nrc_su.cyl3013_1000w.out:

Same as #5 - 1.0 liter water added 0.6017 0.0011 0.604

9.

nrc_su.cyl3013_1100w.out:

Same as #5 - 1.1 liters water added 0.6062 0.0012 0.609

10. nrc_su.cyl3013_1200w.out:

Same as #5 - 1.2 liters water added 0.6098 0.0011 0.612

11. nrc_su.cyl3013_ccfull.out Same as #5 CC full 0.6260 0.0013 0.629 Table 10.

Single Unit Cases Flooding the Convenience Can - Beryllium Case No.

File ID Description keff keff +2

1.

nrc_su.cyl3013be_100.out:

Base Case with 3013 and mixed with beryllium, dry oxide - 0.1 liter water added 0.4770 0.0010 0.479

2.

nrc_su.cyl3013be_200.out:

Same as #1 - 0.2 liter water added 0.4888 0.0010 0.491

3.

nrc_su.cyl3013be_200w.out:

Same as #1 - 0.2 liter water added, diameter of CC 0.4891 0.0009 0.491

4.

nrc_su.cyl3013be_300w.out:

Same as #3 - 0.3 liter water added 0.5009 0.0011 0.504

5.

nrc_su.cyl3013be_500w.out:

Same as #3 - 0.5 liter water added 0.5228 0.0012 0.526

6.

nrc_su.cyl3013be_750w.out:

Same as #3 - 0.75 liter water added 0.5448 0.0012 0.548

7.

nrc_su.cyl3013be_1000w.out Same as #3 - 1.0 liter water added 0.5586 0.0011 0.561

8.

nrc_su.cyl3013be_1100w.out:

Same as #3 - CC full 0.5670 0.0013 0.570 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 31 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 30 of 87 Table 11.

Single Unit Cases Flooding the Convenience Can - No 3013 Containers Case No.

File ID Description keff keff +2

1.

nrc_su.cylno3013_100.out:

Base Case with no 3013, dry oxide - 0.1 liter water added 0.5470 0.0010 0.549

2.

nrc_su.cylno3013_200.out:

Same as #1 - 0.2 liter water added 0.5338 0.0010 0.536

3.

nrc_su.cylno3013_300.out:

Same as #1 - 0.3 liter water added 0.5348 0.0009 0.537

4.

nrc_su.cylno3013_400.out:

Same as #1 - 0.4 liter water added 0.5418 0.0011 0.544

5.

nrc_su.cylno3013_400w.out:

Same as #1 - 0.4 liter water added, diameter of CC 0.5391 0.0012 0.542

6.

nrc_su.cylno3013_500w.out:

Same as #5 - 0.5 liter water added 0.5493 0.0010 0.552

7.

nrc_su.cylno3013_750w.out:

Same as #5 - 0.75 liter water added 0.5618 0.0012 0.565

8.

nrc_su.cylno3013_1000w.out:

Same as #5 - 1.0 liter water added 0.5717 0.0012 0.575

9.

nrc_su.cylno3013_1100w.out:

Same as #5 - 1.1 liters water added 0.5782 0.0012 0.581

10. nrc_su.cylno3013_1200w.out:

Same as #5 - 1.2 liters water added 0.5790 0.0011 0.582

11. nrc_su.cylno3013_1300w.out:

Same as #5 - 1.3 liters water added 0.5870 0.0011 0.59

12. nrc_su.cylno3013_ccfull.out Same as #5 - CC full 0.6190 0.0012 0.622 Table 12.

Single Unit Cases Flooding the Convenience Can with Beryllium - No 3013 Case No.

File ID Description keff keff +2

1.

nrc_su.cylno3013be_100.out:

Base Case with no 3013 and mixed with beryllium, dry oxide - 0.1 liter water added 0.4632 0.0009 0.465

2.

nrc_su.cylno3013be_200.out:

Same as #1 - 0.2 liter water added 0.4685 0.0010 0.471

3.

nrc_su.cylno3013be_200w.out:

Same as #1 - 0.2 liter water added, diameter of CC 0.4695 0.0009 0.472

4.

nrc_su.cylno3013be_300w.out:

Same as #3 - 0.3 liter water added 0.4795 0.0010 0.482

5.

nrc_su.cylno3013be_500w.out:

Same as #3 - 0.5 liter water added 0.4959 0.0011 0.499

6.

nrc_su.cylno3013be_750w.out:

Same as #3 - 0.75 liter water added 0.5172 0.0012 0.520

7.

nrc_su.cylno3013be_1000w.out:

Same as #3 - 1.0 liter water added 0.5320 0.0010 0.534

8.

nrc_su.cylno3013be_1100w.out:

Same as #3 - CC full 0.5375 0.0012 0.540 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 32 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 31 of 87 Table 13.

Single Unit Cases Flooding the Convenience Can with Carbon Case No.

File ID Description keff keff +2

1.

nrc_su.cyl3013c12_100.out:

Base Case with 3013 and mixed with carbon, dry oxide - 0.1 liter water added 0.4033 0.0009 0.406

2.

nrc_su.cyl3013c12_100w.out:

Same as #1 - 0.1 liter water added, diameter of CC 0.4003 0.0009 0.402

3.

nrc_su.cyl3013c12_200w.out:

Same as #2 - 0.2 liter water added 0.4093 0.0009 0.412

4.

nrc_su.cyl3013c12_300w.out:

Same as #2 - 0.3 liter water added 0.4227 0.0010 0.425

5.

nrc_su.cyl3013c12_400w.out:

Same as #2 - 0.4 liter water added 0.4406 0.0010 0.443

6.

nrc_su.cyl3013c12_500w.out:

Same as #2 - 0.5 liter water added 0.4549 0.0014 0.458

7.

nrc_su.cyl3013c12_750w.out:

Same as #2 - 0.75 liter water added 0.4786 0.0012 0.481

8.

nrc_su.cyl3013c12_1000w.out:

Same as #2 - 1.0 liter water added 0.5012 0.0011 0.504 As shown above, Tables 9 through 13 compare the keff values for a single unit to examine the effects of flooding the convenience can while forming a homogenized solution, with or without the 3013 container in place. As shown in Table 9, the highest keff of 0.629 is achieved when the convenience can is completely full of fissile solution (plutonium oxide plus flooding water) in a convenience can/3013 combination (Case 11).

Based on Tables 8 through 13, the most reactive cases are achieved with the convenience cans fully flooded with water. Thus, additional cases were run varying water flooding into the various compartments (PCV, SCV, Celotex) of the 9975 shipping package. Tables 14 through 17 list this comparison.

Table 14.

Single Unit Cases Flooding the PCV, SCV, and Celotex - Inner 3013 Flooded Case No.

File ID Description keff keff +2

1.

nrc_su.cyl3013_ccfull_3013inn.out:

CC - full of solution 3013 - inner flooded with water 0.6598 0.0014 0.663

2.

nrc_su.cyl3013_ccfull_3013inner_PCV.out:

Same as #1 - PCV contains water 0.6633 0.0013 0.666

3.

nrc_su.cyl3013_ccfull_3013inner_PCVSCV.out:

Same as #1 -

PCV/SCV contains water 0.6979 0.0012 0.701

4.

nrc_su.cyl3013_ccfull_3013inner_SCV.out:

Same as #1 - SCV contains water 0.6849 0.0012 0.688 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 33 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 32 of 87 Table 15.

Single Unit Cases Flooding the PCV, SCV, and Celotex - Outer 3013 Flooded Case No.

File ID Description keff keff +2

1.

nrc_su.cyl3013_ccfull_3013outer.out:

CC - full of solution 3013 - outer flooded with water 0.6352 0.0013 0.638

2.

nrc_su.cyl3013_ccfull_3013outer_PCV.out:

Same as #1 - PCV contains water 0.6490 0.0013 0.652

3.

nrc_su.cyl3013_ccfull_3013outer_PCVSCV.out:

Same as #1 -

PCV/SCV contains water 0.6782 0.0013 0.681

4.

nrc_su.cyl3013_ccfull_3013outer_SCV.out:

Same as #1 - SCV contains water 0.6654 0.0014 0.669 Table 16.

Single Unit Cases Flooding the PCV, SCV, and Celotex - Both 3013 Containers Flooded Case No.

File ID Description keff keff +2

1. nrc_su.cyl3013_ccfull_3013both.out:

CC - full of solution 3013 - inner/outer flooded with water 0.6693 0.0013 0.672

2. nrc_su.cyl3013_ccfull_3013both_PCV.out:

Same as #1 - PCV contains water 0.6834 0.0014 0.687

3. nrc_su.cyl3013_ccfull_3013both_PCVSCV.out:

Same as #1 -

PCV/SCV contains water 0.7049 0.0014 0.708

4. nrc_su.cyl3013_ccfull_3013both_SCV.out:

Same as #1 -SCV contains water 0.6920 0.0012 0.695

5. nrc_su.cyl3013_ccfull_3013both_PCV_Celo.out:

Same as #1 - PCV/

Celotex as water 0.7158 0.0013 0.719

6. nrc_su.cyl3013_ccfull_3013both_ALL.out:

Same as #1 -

PCV/SCV/

Celotex as water 0.7325 0.0015 0.736 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 34 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 33 of 87 Table 17.

Single Unit Cases Flooding the PCV, SCV, and Celotex - No 3013 Containers Case No.

File ID Description keff keff

+2

1.

nrc_su.cylno3013_ccfull.out:

CC - full of solution No 3013 0.6204 0.0012 0.623

2.

nrc_su.cylno3013_ccfull_PCV.out:

Same as #1 - PCV contains water 0.6847 0.0015 0.688

3.

nrc_su.cylno3013_ccfull_PCVSCV.out:

Same as #1 - PCV/SCV contains water 0.7097 0.0013 0.713

4.

nrc_su.cylno3013_ccfull_SCV.out:

Same as #1 -SCV contains water 0.6219 0.0015 0.625

5.

nrc_su.cylno3013_ccfull_PCVSCV_ALL.out:

Same as #1 - PCV/SCV/

Celotex as water 0.7353 0.0013 0.738 Tables 14 through 17 show that a 9975 shipping package with a convenience can containing plutonium oxide, with or without the 3013 container, with water flooding in all compartments of the 9975 shipping package is subcritical. The highest keff + 2 of 0.738 was achieved for the case with a homogenized fissile cylinder modeled the width of the convenience can, no 3013 containers, with the PCV, SCV, and Celotex regions fully flooded with water (Table 17, Case 5).

6.3.3 Damaged Containment and Flooding 6-inch SCV To address damage to the convenience can and 3013 containers, with water flooding into the PCV and SCV, single package models were created filling the 6-inch SCV and 5-inch PCV with water, creating a fissile solution. The fissile mass remains constant at 5.0 kg plutonium oxide as water is added. Thus, convenience can and 3013 containers that are internal to the PCV are removed. In addition, the volumes occupied by the aluminum spacers and aluminum absorbers will be assumed as volumes available to be filled with water and solution. Therefore, the maximum usable volumes (using the volumes occupied by the non-stainless material inside the SCV and PCV) were used.

Removing the convenience can, the 3013 containers and all aluminum material in the SCV is conservative in that the steel would have separated the fissile solution, absorbed neutrons, and occupied space resulting in less fissile solution. In addition, the volume of the aluminum spacers and absorbers within the SCV, which have minimal neutronic impact, would occupy space also resulting in less fissile solution.

A parametric study was performed with water entering the 9975 shipping package assuming the aluminum, convenience can, and 3013 containers are removed. This results in filling the 5-inch PCV with water while maintaining the fissile mass constant at 5.0 kg plutonium oxide. As water is added, the height of the plutonium oxide-water mixture will increase as the mixture fills the diameter and height of the 5-inch PCV. This is depicted in Figure 7, with the data points labeled with 5 PCV. At this point, the volume between the SCV and PCV is filled with water.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 35 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 34 of 87 After the PCV fills to maximum height with plutonium oxide solution, the fissile solution spills into the SCV, until the SCV is completely full. This is depicted in Figure 7, with the data points labeled with 6 SCV. Thus, the SCV only contains the SS PCV and the filling plutonium oxide solution of both containment vessels.

Figure 7, and Tables 18 through 21, show the results of this analysis. As shown in Figure 7, the results without the symbols indicate the PCV filling with plutonium oxide solution until full, with water in the volume between the SCV and PCV. The results with the symbols indicate the PCV full with plutonium oxide solution and the volume between the SCV and PCV filling with plutonium oxide solution, until full.

Figure 7.

Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water 0.40 0.45 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 0

1 2

3 4

5 6

7 8

k e

f f

+

2

Amount (liters) of water added to PuO2 k-safe 5" PCV Be 5" PCV C 5" PCV 5" PCV - FLD Celo 6" SCV Be 6 "SCV C 6" SCV 6" SCV - FLD Celo Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 36 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 35 of 87 Table 18.

Filling 5-inch PCV and 6-inch SCV with PuO2 and Flooding Water Case No.

Filename Description PuO2

Density, g/cc keff keff +2
1.

nrc_su._PuO_fld_5PCV_noBe_ful.100.out PCV intact. CC, 3013 removed.

PuO2 dry. Water between SCV-PCV.

10.8921 0.6639 0.0011 0.667

2.

nrc_su._PuO_fld_5PCV_noBe_ful.110.out Same as #1 - 1 liter water added to PCV 4.1131 0.7182 0.0012 0.721

3.

nrc_su._PuO_fld_5PCV_noBe_ful.120.out Same as #2 - 2 liters water added to PCV 2.8466 0.7649 0.0013 0.768

4.

nrc_su._PuO_fld_5PCV_noBe_ful.130.out Same as #2 - 3 liters water added to PCV 2.3123 0.7903 0.0014 0.794

5.

nrc_su._PuO_fld_5PCV_noBe_ful.140.out Same as #2 - 4 liters water added to PCV 2.0176 0.8047 0.0014 0.808

6.

nrc_su._PuO_fld_5PCV_noBe_ful.4826.out 4.826 L water added to PCV (totally full). PCV intact. CC and 3013 removed.

1.8584 0.8107 0.0015 0.814

7.

nrc_su._PuO_fld_6SCV_noBe_ful.5450.out PCV intact. CC and 3013 removed. 5.540 L water added to PCV, solution spilling into SCV.

1.7675 0.8110 0.0015 0.814

8.

nrc_su._PuO_fld_6SCV_noBe_ful.5746.out PCV intact. CC and 3013 removed. 5.746 L water added to PCV, solution spilling into SCV.

1.7308 0.8231 0.0014 0.826

9.

nrc_su._PuO_fld_6SCV_noBe_ful.6042.out PCV intact. CC and 3013 removed. 6.042 L water added to PCV, solution spilling into SCV.

1.6975 0.8334 0.0014 0.837

10.

nrc_su._PuO_fld_6SCV_noBe_ful.6338.out PCV intact. CC and 3013 removed. 6.338 L water added to PCV, solution spilling into SCV.

1.6670 0.8460 0.0015 0.849

11.

nrc_su._PuO_fld_6SCV_noBe_ful.6689.out PCV intact. CC and 3013 removed. 6.689 L water added to PCV, solution spilling into SCV.

1.6341 0.8538 0.0015 0.857

12.

nrc_su._PuO_fld_6SCV_noBe_ful.7123.out PCV intact. CC and 3013 removed. 7.123 L water added to PCV, solution spilling into SCV.

1.5978 0.8542 0.0016 0.858

13.

nrc_su._PuO_fld_6SCV_noBe_ful.7793.out PCV intact. CC and 3013 removed. 7.793 L water added to PCV, solution spilling into SCV.

SCV completely full.

1.5491 0.8510 0.0017 0.855 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 37 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 36 of 87 Table 19.

Filling 5-inch PCV and 6-inch SCV with PuO2, Beryllium and Flooding Water Case No.

Filename Description PuO2

Density, g/cc keff keff +2
1.

nrc_su._PuO_fld_5PCV_Be_ful.100.out PCV intact. CC, 3013 removed.

PuO2 dry. Added 500 g Be.

7.2986 0.5899 0.0011 0.593

2.

nrc_su._PuO_fld_5PCV_Be_ful.110.out Same as #1 - 1 liter water added to PCV 3.5611 0.6865 0.0016 0.690

3.

nrc_su._PuO_fld_5PCV_Be_ful.120.out Same as #2 - 2 liters water added to PCV 2.6068 0.7454 0.0015 0.749

4.

nrc_su._PuO_fld_5PCV_Be_ful.130.out Same as #2 - 3 liters water added to PCV 2.1704 0.7709 0.0013 0.774

5.

nrc_su._PuO_fld_5PCV_Be_ful.140.out Same as #2 - 4 liters water added to PCV 1.9202 0.7849 0.0014 0.788

6.

nrc_su._PuO_fld_5PCV_Be_ful.4599.out 4.599 L water added to PCV (totally full). PCV intact. CC and 3013 removed.

1.8157 0.7905 0.0016 0.794

7.

nrc_su._PuO_fld_6SCV_Be_ful.5223.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 5.223 L water added to PCV, solution spilling into SCV.

1.7294 0.7950 0.0018 0.799

8.

nrc_su._PuO_fld_6SCV_Be_ful.5519.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 5.519 L water added to PCV, solution spilling into SCV.

1.6945 0.8029 0.0015 0.806

9.

nrc_su._PuO_fld_6SCV_Be_ful.5815.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 5.815 L water added to PCV, solution spilling into SCV.

1.6628 0.8212 0.0015 0.825

10.

nrc_su._PuO_fld_6SCV_Be_ful.6111.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 6.111 L water added to PCV, solution spilling into SCV.

1.6338 0.8333 0.0016 0.837

11.

nrc_su._PuO_fld_6SCV_Be_ful.6463.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 6.463 L water added to PCV, solution spilling into SCV.

1.6026 0.8399 0.0017 0.844

12.

nrc_su._PuO_fld_6SCV_Be_ful.6896.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 6.896 L water added to PCV, solution spilling into SCV.

1.5680 0.8415 0.0015 0.845

13.

nrc_su._PuO_fld_6SCV_Be_ful.7567.out PCV intact. CC and 3013 removed.

PuO2 mixed with 500 g Be. 7.567 L water added to PCV, solution spilling into SCV. SCV completely full.

1.5217 0.8398 0.0015 0.843 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 38 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 37 of 87 Table 20.

Filling 5-inch PCV and 6-inch SCV with PuO2, Carbon and Flooding Water Case No.

Filename Description PuO2

Density, g/cc keff keff +2
1.

nrc_su._PuO_fld_5PCV_C_ful.100.out PCV intact. CC, 3013 removed. PuO2 dry. Added 1000 g Carbon.

6.2065 0.5101 0.0009 0.512

2.

nrc_su._PuO_fld_5PCV_C_ful.110.out Same as #1 - 1 liter water added to PCV 3.3232 0.6327 0.0014 0.636

3.

nrc_su._PuO_fld_5PCV_C_ful.120.out Same as #2 - 2 liters water added to PCV 2.4948 0.7003 0.0015 0.704

4.

nrc_su._PuO_fld_5PCV_C_ful.130.out Same as #2 - 3 liters water added to PCV 2.1016 0.7399 0.0017 0.744

5.

nrc_su._PuO_fld_5PCV_C_ful.140.out Same as #2 - 4 liters water added to PCV 1.8720 0.7597 0.0014 0.763

6.

nrc_su._PuO_fld_5PCV_C_ful.4478.out 4.478 L water added to PCV (totally full). PCV intact. CC and 3013 removed.

1.7930 0.7649 0.0015 0.768

7.

nrc_su._PuO_fld_6SCV_C_ful.5102.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 5.102 L water added to PCV, solution spilling into SCV.

1.7090 0.7728 0.0015 0.776

8.

nrc_su._PuO_fld_6SCV_C_ful.5398.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 5.398 L water added to PCV, solution spilling into SCV.

1.6751 0.7812 0.0014 0.784

9.

nrc_su._PuO_fld_6SCV_C_ful.5694.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 5.694 L water added to PCV, solution spilling into SCV.

1.6443 0.7972 0.0016 0.801

10.

nrc_su._PuO_fld_6SCV_C_ful.5990.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 5.990 L water added to PCV, solution spilling into SCV.

1.6161 0.8110 0.0016 0.815

11.

nrc_su._PuO_fld_6SCV_C_ful.6342.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 6.342 L water added to PCV, solution spilling into SCV.

1.5857 0.8180 0.0015 0.821 12 nrc_su._PuO_fld_6SCV_C_ful.6775.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 6.775 L water added to PCV, solution spilling into SCV.

1.5521 0.8198 0.0014 0.823

13.

nrc_su._PuO_fld_6SCV_C_ful.7446.out PCV intact. CC and 3013 removed.

PuO2 mixed with 1000 g carbon. 7.446 L water added to PCV, solution spilling into SCV. SCV completely full.

1.5071 0.8183 0.0016 0.822 As can be seen from Figure 7 and Tables 18 through 20, the plutonium oxide mixed with water in the PCV and SCV remains subcritical as the added water causes the density of the solution to decrease by holding the mass of the plutonium oxide constant. All cases in Tables 18 through 20 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 39 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 38 of 87 initially have water mixing with the plutonium oxide in the shipping package, creating a plutonium oxide solution in the PCV and water only in the SCV. As the PCV fills with solution, spillage fills the SCV until totally full with the plutonium oxide solution.

The cases with the plutonium oxide solution filling the PCV are shown to be subcritical, achieving a maximum keff + 2 = 0.814, Table 18, Case 6. In these cases, no plutonium oxide solution is in the SCV, only water from filling the shipping package.

As increasing amounts of water mix with the plutonium oxide in the shipping package, the PCV overflows filling the SCV with the plutonium oxide solution. Thus, you have plutonium oxide solution in the PCV as well as the SCV. The cases of filling the PCV and SCV with plutonium oxide solution remains below ksafe with a maximum at keff + 2 = 0.858, Table 18, Case 12. In this case (Table 18, Case 12), approximately 7.123 L water is added to the plutonium oxide in the shipping package, which completely fills the PCV, but only partially fills the SCV, with plutonium oxide solution. Totally filling both the PCV and SCV (approximately 7.793 L water added to the plutonium oxide in the shipping package) with the plutonium oxide solution has also been demonstrated to be below ksafe with a keff + 2 = 0.855, Table 18, Case 13. In addition, when impurities (Be or C) are mixed with the oxide, the fissile mass of the mixture is reduced and consequently lowers the keff of the system, as shown in Tables 19 through 20.

To fully demonstrate that single package flooding is safely subcritical, additional models were developed to flood all of the remaining compartments of the 9975 shipping package. As shown in Table 18 through Table 20, the cases without impurities yielded the highest keff and have the SCV and PCV flooded with plutonium oxide solution. Therefore, this series of cases was modified to also flood the Celotex insulation with water and the results are presented in Table

21. In these cases, the Celotex is being replaced with water only, as the fissile solution is judged to remain in the primary and secondary containment vessels.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 40 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 39 of 87 Table 21.

Filling 5-inch PCV and 6-inch SCV with PuO2 - Celotex Flooded Case No.

Filename Description PuO2

Density, g/cc keff keff +2
1.

nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.100.out PCV intact. CC, 3013 removed. PuO2 dry. Water between SCV-PCV.

10.8921 0.6802 0.0013 0.683

2.

nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.110.out Same as #1 - 1 liter water added to PCV 4.1131 0.7455 0.0013 0.749

3.

nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.120.out Same as #2 - 2 liters water added to PCV 2.8466 0.7955 0.0015 0.799

4.

nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.130.out Same as #2 - 3 liters water added to PCV 2.3123 0.8214 0.0016 0.825

5.

nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.140.out Same as #2 - 4 liters water added to PCV 2.0176 0.8346 0.0016 0.838

6.

nrc_su._PuO_fld_5PCV_noBe_ful_fld_celo.4826.out 4.826 L water added to PCV (totally full). PCV intact. CC and 3013 removed. Celotex flooded.

1.8584 0.8407 0.0016 0.844

7.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.5450.out PCV intact. CC and 3013 removed. 5.5450 L water added to PCV, solution spilling into SCV. Celotex flooded.

1.7675 0.8448 0.0014 0.848

8.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.5746.out PCV intact. CC and 3013 removed. 5.746 L water added to PCV, solution spilling into SCV. Celotex flooded.

1.7308 0.8587 0.0015 0.862

9.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6042.out PCV intact. CC and 3013 removed. 6.042 L water added to PCV, solution spilling into SCV. Celotex flooded.

1.6975 0.8875 0.0015 0.891

10.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6338.out PCV intact. CC and 3013 removed. 6.338 L water added to PCV, solution spilling into SCV. Celotex flooded.

1.6670 0.9076 0.0015 0.911

11.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.out PCV intact. CC and 3013 removed. 6.689 L water added to PCV, solution spilling into SCV. Celotex flooded.

1.6341 0.9124 0.0017 0.916

12.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.7123.out PCV intact. CC and 3013 removed. 7.123 L water added to PCV, solution spilling into SCV. Celotex flooded.

1.5978 0.9096 0.0015 0.913

13.

nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.7793.out PCV intact. CC and 3013 removed. 7.793 L water added to PCV, solution spilling into SCV. SCV completely full.

Celotex flooded.

1.5491 0.9086 0.0015 0.912 As shown in Figure 7 and Table 21, for the series of cases with an additional layer of reflection created by replacing the Celotex with water, all cases remain subcritical. The highest keff + 2

= 0.916 (Table 21, Case 11) is achieved when approximately 6.689 L water is added to the Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 41 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 40 of 87 plutonium oxide in the shipping package, completely filling the PCV, but only partially filling the SCV, with plutonium oxide solution. In addition, Table 21 shows that adding approximately 7.793 L water to the plutonium oxide in the shipping package, completely filling the PCV and SCV with plutonium oxide solution, remains below ksafe with a keff + 2 = 0.912, Table 21, Case

13.

Therefore all keff + 2 values in Tables 8 through 21 are below ksafe of 0.943, which satisfies the 10 CFR 71.55(b) requirements related to a flooded single package.

6.4 NORMAL CONDITIONS OF TRANSPORT ARRAY ANALYSES 10 CFR 71.55 contains the following requirements for NCT criticality safety analyses:

(d) A package used for the shipment of fissile material must be so designed and constructed and its contents so limited that under the tests specified in § 71.71 ("Normal conditions of transport") --

(1) The contents would be subcritical; (2) The geometric form of the package contents would not be substantially altered; (3) There would be no leakage of water into the containment system unless, in the evaluation of undamaged packages under § 71.59(a)(1), it has been assumed that moderation is present to such an extent as to cause maximum reactivity consistent with the chemical and physical form of the material; and (4) There will be no substantial reduction in the effectiveness of the packaging, including:

(i) No more than 5 percent reduction in the total effective volume of the packaging on which nuclear safety is assessed; (ii) No more than 5 percent reduction in the effective spacing between the fissile contents and the outer surface of the packaging; In the NCT undamaged drum array analysis, no water enters the PCV, 3013, or convenience can.

Thus, an infinite array of drums was analyzed with the convenience can containing dry plutonium oxide and 0.5% water fissile mixture, with or without the 3013 containers and additional cases with the Celotex flooded. As mentioned earlier, all array analyses were performed using the 7% reduced drum radius to utilize an equivalent rectangular array configuration.

Table 22 presents the NCT results.

Table 22.

9975 Array Model - NCT Cases Case No.

File ID Description keff keff

+2

1. nrc_nct.cyl3013.out Infinite drum array, dry fissile material 0.6520 0.0011 0.655
2. nrc_nct.cyl3013_celofld.out Same as #1 water as Celotex 0.6099 0.0010 0.612 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 42 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 41 of 87 Case No.

File ID Description keff keff

+2

3. nrc_nct.cyl3013_h2orefl.out Same as #1 w/water between drums 0.6102 0.0009 0.613
4. nrc_nct.cyl3013_h2orefl_celofld.out Same as #1 w/water between drums, water as Celotex 0.6099 0.0010 0.612
5. nrc_nct.cylno3013.out Infinite drum array, dry fissile material, no 3013 containers 0.6524 0.0011 0.655
6. nrc_nct.cylno3013_celofld.out Same as #5, water as Celotex 0.6046 0.0010 0.607
7. nrc_nct.cylno3013_h2orefl.out Same as #5, w/water between drums 0.6049 0.0012 0.608
8. nrc_nct.cylno3013_h2orefl_celofld.out Same as #5 w/water between drums, water as Celotex 0.6042 0.0010 0.607 The cases in Table 22 demonstrate that the 9975 with plutonium oxide in convenience can, with and without the 3013 container, in dry conditions, is subcritical with the highest keff + 2 of 0.655 for a dry system (Cases 1 and 5). As the water is added to the Celotex and in between the shipping packages in an array, interaction is reduced, thus reducing the keff of the system as indicated in Table 21. Thus, water flooding of the Celotex is subcritical.

Therefore all keff + 2 values in Table 22 are below the ksafe of 0.943, which satisfies the 10 CFR 71.55(d) and 71.59(a)(1) requirements related to NCT analyses.

6.5 HYPOTHETICAL ACCIDENT CONDITIONS ANALYSES 10 CFR 71.55 contains the following requirements for HAC criticality safety analyses:

(e) A package used for the shipment of fissile material must be so designed and constructed and its contents so limited that under the tests specified in § 71.73 ("Hypothetical accident conditions"), the package would be subcritical. For this determination, it must be assumed that:

(1) The fissile material is in the most reactive credible configuration consistent with the damaged condition of the package and the chemical and physical form of the contents; (2) Water moderation occurs to the most reactive credible extent consistent with the damaged condition of the package and the chemical and physical form of the contents; and (3) There is full reflection by water on all sides, as close as is consistent with the damaged condition of the package.

In the HAC analysis, damaged units are arranged in various configurations to demonstrate a most reactive configuration. The damaged HAC array model used a conservative radial and axial drum dimension reduction to address a drop and the amount of Celotex charred due to fire (see Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 43 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 42 of 87 Table 7). A conservative infinite array, modeled as an infinite array of 2x2x2 clusters, was developed where the fissile material was moved together as close as possible. This model brought a cluster of four drums, stacked two high (eight packages total), to its closest contact position. In other words, although not credible, the radial movement is such that four drums together form the closest configuration (a quadrupole arrangement), as shown in Figure 8.

Figure 8.

2x2x2 Closest Contact Model (Case 1)

These models assume that the Celotex loss is localized around the periphery of the drum, and the 9975 is dropped during the accident. The inner containment (convenience can/3013/PCV/SCV) is moved inside the Celotex (keeping the Celotex volume constant) such that the lead shield is touching the drum at one point.

Although the close contact HAC model (Figure 8, Case 1) minimizes fissile spacing between the payloads in as many as eight packages, it increases fissile spacing between those packages and the packages surrounding them. Thus, it is not entirely obvious that a HAC model that only accounts for the destruction of Celotex but includes none of the material movements, is less reactive or not. Therefore, an additional symmetrical model was also developed (Figure 9, Case 5) to help determine the most reactive configuration. Case 5 (symmetrical model) is a damaged array scenario with the Celotex, containment, and fissile material in its normal, centered orientation, but the destruction of Celotex due to fire and reduction of drum diameter due to impact are included.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 44 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 43 of 87 Figure 9.

2x2x2 Symmetrical Model (Case 5)

Table 23 presents the HAC results.

Table 23.

9975 Array Model - HAC Cases Case No.

File ID Description keff keff +2

1. nrc_hac.cyl3013_2x2x2.out 2x2x2 cluster, inifinite array Fissile at closest position 0.7346 0.0011 0.737
2. nrc_hac.cyl3013_2x2x2_PCVfl.out Same as #1, PCV flooded 0.7209 0.0012 0.724
3. nrc_hac.cyl3013_2x2x2_PCVSCVfl.out Same as #1, PCV/SCV flooded 0.7120 0.0010 0.714
4. nrc_hac.cyl3013_2x2x2_SCVfl.out Same as #1, SCV flooded 0.7144 0.0011 0.717
5. nrc_hac.cyl3013_2x2x2_symm.out 2x2x2 cluster, inifinite array Fissile at centered position 0.7287 0.0010 0.731
6. nrc_hac.cyl3013_2x2x2_PCVfl_symm.out Same as #5, PCV flooded 0.7135 0.0010 0.716
7. nrc_hac.cyl3013_2x2x2_PCVSCVfl_symm.out Same as #5, PCV/SCV flooded 0.7008 0.0011 0.703
8. nrc_hac.cyl3013_2x2x2_SCVfl_symm.out Same as #5, SCV flooded 0.7065 0.0013 0.710 Table 23 shows that all keff + 2 values are less than ksafe for the damaged array cases. This demonstrates that moving the fissile units closer together (Case 1, the bounding closest position case) only produces a slightly higher keff than when all of the fissile units are centered within the 9975 shipping package (Case 5, the bounding centered position case), on the order of 1.6%

difference. Thus, the base HAC model, the infinite array of 2x2x2 clusters with the fissile material units closest together (Case 1) within the array has the highest keff + 2 of 0.737.

Table 24.

9975 Array Model - Flooded Convenience Can HAC Cases Case No.

File ID Description keff keff +2

1. nrc_hac.cyl_CCfl_2x2x2.out:

Convenience can flooded Fissile at closest position 0.9149 0.0014 0.918

2. nrc_hac.cyl_CCfl_3013fl.out:

Same as #1, 3013 flooded 0.9349 0.0013 0.938

3. nrc_hac.cyl_CCfl_allfl.out:

Same as #1, 3013, PCV, SCV, water as Celotex 0.7875 0.0013 0.791

4. nrc_hac.cyl_CCfl_3013dry_PCVSCVfl.out:

Same as #1, 3013 dry, PCV, SCV flooded 0.8443 0.0015 0.848

5. nrc_hac.cyl_CCfl_3013dry_allfl.out:

Same as #1, 3013 dry, PCV, SCV, water as Celotex 0.7647 0.0014 0.768 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 45 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 44 of 87

6. nrc_hac.cyl_CCL_2x2x2_symm.out:

Convenience can flooded Fissile at centered position 0.9038 0.0016 0.907 A conservative analysis was performed, with the results provided in Table 24, flooding the 9975 shipping package to the fullest extent while modeled as an infinite array. Various models were developed that flooded the different compartments (i.e., 3013, PCV, SCV, Celotex) of the 9975 shipping package, while flooding the convenience can containing the fissile solution. As seen in Table 23, for the base HAC analysis, the configuration with the fissile units at their closest position (Table 23, Case 1) yields the highest keff + 2 which also hold true for the cases with the convenience can flooded. Thus, the study on flooding the 9975 shipping package compartments, Table 24, used this as the base case configuration. As shown in Table 24, the case where the convenience can/3013 configuration was flooded while the remainder of the 9975 shipping package remains dry (Case 2) yields a keff + 2 of 0.938.

Therefore all keff + 2 values for the HAC array analysis as shown in Table 23 and Table 24 are below the ksafe of 0.943, which satisfies the 10 CFR 71.55(e) and 71.59(a)(2) requirements related to HAC analyses.

6.6 CRITICALITY SAFETY INDEX The calculation of the Criticality Safety Index (CSI) for the 9975 shipping package is required to follow the explicit equations specified in 10 CFR 71.59:

(a) A fissile material package must be controlled by either the shipper or the carrier during transport to assure that an array of such packages remains subcritical. To enable this control, the designer of a fissile material package shall derive a number "N" based on all the following conditions being satisfied, assuming packages are stacked together in any arrangement and with close full reflection on all sides of the stack by water:

(1) Five times "N" undamaged packages with nothing between the packages would be subcritical; (2) Two times "N" damaged packages, if each package were subjected to the tests specified in § 71.73 ("Hypothetical accident conditions") would be subcritical with optimum interspersed hydrogenous moderation; and (3) The value of "N" cannot be less than 0.5.

(b) The CSI must be determined by dividing the number 50 by the value of "N" derived using the procedures specified in paragraph (a) of this section. The value of the CSI may be zero provided that an unlimited number of packages are subcritical, such that the value of "N" is effectively equal to infinity under the procedures specified in paragraph (a) of this section.

Any CSI greater than zero must be rounded up to the first decimal place.

(c) For a fissile material package which is assigned a CSI value--

(1) Less than or equal to 50, that package may be shipped by a carrier in a nonexclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 50.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 46 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 45 of 87 (2) Less than or equal to 50, that package may be shipped by a carrier in an exclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 100.

(3) Greater than 50, that package must be shipped by a carrier in an exclusive use conveyance, provided the sum of the CSIs is limited to less than or equal to 100.

The CSI is conservatively computed for both the NCT and HAC, with the CSI calculation shown in Table 25.

Table 25.

CSI Calculation Calculate the value of N for NCT:

5*N = (infinite), so N = /5 =

The CSI is defined by 10 CFR 71.59 as, CSI 50/N = 50/ = 0.0 Rounding up to the first decimal we get, CSI = 0.0 Calculate the value of N for HAC:

2*N = (infinite), so N = /2 =

The CSI is defined by 10 CFR 71.59 as, CSI 50/N = 50/ = 0.0 Rounding up to the first decimal we get, CSI = 0.0 The CSI calculation in Table 25 derives a CSI in the infinite array NCT and HAC configurations equal to 0.0 for the 9975 package with the plutonium oxide content envelope, as specified in Section 2.2.

7.0 ADMINISTRATIVELY CONTROLLED LIMITS AND REQUIREMENTS The following limits apply to the 9975 shipping packages evaluated in this analysis:

1. The 9975 shipping package shall be used to transport the plutonium oxide material which has the content envelope described in Table 2 and shown again in Table 26.

Table 26.

Plutonium Oxide Contents Material Mass (kg)

PuO2 5.0 Beryllium 0.5 Carbon 1.0

  • The 5.0 kg is the maximum payload for the shipping package. The addition of the beryllium or carbon reduces the fissile content.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 47 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 46 of 87 8.0

SUMMARY

AND CONCLUSIONS An evaluation was performed to address shipping the plutonium oxide content envelope, as specified in Section 2.2, in the 9975 shipping package.

Based on the analysis performed in Section 6.0, an infinite array of 9975 shipping packages with a 5.0 kg plutonium oxide content envelope is subcritical provided the limits and controls in Section 7.0 are maintained.

This NCSE has demonstrated that 9975 shipping packages can be safely shipped carrying the plutonium oxide contents as described in Table 26, with a CSI of 0.0.

9.0 REFERENCES

10 CFR 71, Packaging and Transportation of Radioactive Material, U.S. Nuclear Regulatory Commission, Washington, DC, January 2012.

ANSI/ANS-8.1-1998, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, 1998.

ASTM A312, Specification for Seamless and Welded Austenitic Stainless Steel Pipes, American Society for Testing and Materials, 1995.

N-NCS-F-00087, Rev. 2, 9975 Shipping Container Analysis with Revised Contents for SARP, Revision 0 (U), Biswas, D., Westinghouse Safety Management Solutions, LLC, Aiken, SC, October 2003.

NUREG/CR-5661, ORNL/TM-11936, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, Oak Ridge National Laboratory, Oak Ridge, TN, April 1997.

ORNL/TM-12370, The LAW-238 Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations, Green, N.M., et al., Oak Ridge National Laboratory, Oak Ridge, TN, August 1994.

ORNL/TM-2005/39, Version 5, SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, Petrie, L.M., et al., Oak Ridge National Laboratory, Oak Ridge, TN, April 2005.

SCD-3, Rev. 27, Nuclear Criticality Safety Manual (U), Savannah River Nuclear Solutions, Aiken, SC, December 2012.

SRNS-IM-2009-00035, Rev. 2, Criticality Safety Methods Manual, Savannah River Nuclear Solutions, Aiken, SC, September 2012.

SRNS-RP-2008-00150, Revision 1, Software Configuration and Control Guidance for SCALE on SRS Personal Computers (U), Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, May 2011.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 48 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 47 of 87 SRNS-RP-2008-00151, Revision 1, SCALE Test Report for SRS Personal Computers (U),

Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, May 2011.

SRNS-RP-2008-00153, Rev. 0, SCALE 5.0 Validation for SRNS Personal Computers (U),

Abney, L.M. and Bridges, A.H., Savannah River Nuclear Solutions, Aiken, SC, January 2009.

WSRC-SA-7, Revision 14, Safety Analysis Report - Packages 9965, 9968, 9972 - 9975 Packages (U), Westinghouse Savannah River Company, Aiken, SC, October 2002.

WSRC-TR-2000-00444, Celotex Structural Properties Tests (U), Smith, C., and Vormelker, P.R., Savannah River National Laboratory, Aiken, SC, December 2000.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 49 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 48 of 87 APPENDIX A SENSITIVITY STUDIES

1. Variation of keff with Celotex density Celotex density is varied to determine the effect of Celotex density on keff. The density may vary substantially (WSRC-TR-2000-00444, Celotex Structural Properties Tests (U)).

Table A1.1 shows that keff increases significantly with a reduction in Celotex density in the array scenario. This nominal density of Celotex is 0.24 g/cc and the density variation ranges from 0.22 g/cc to 0.26 g/cc (WSRC-TR-2000-00444). Therefore, a conservative Celotex density of 0.20 g/cc is chosen for this analysis.

Table A1.1.

Variation of keff with Celotex Density Case No.

File ID Celotex Density (g/cc) keff keff +2

1. nrc_nct.cyl_celo_den_0.02.out:

NCT case, No 3013, Dry, Infinite array - 0.02 Density 0.97670 0.00120 0.980

2. nrc_nct.cyl_celo_den_0.04.out:

Same as #1, Density 0.04 0.83600 0.00120 0.839

3. nrc_nct.cyl_celo_den_0.06.out:

Same as #1, Density 0.06 0.76810 0.00110 0.771

4. nrc_nct.cyl_celo_den_0.08.out:

Same as #1, Density 0.08 0.73130 0.00120 0.734

5. nrc_nct.cyl_celo_den_0.10.out:

Same as #1, Density 0.10 0.70720 0.00110 0.710

6. nrc_nct.cyl_celo_den_0.12.out:

Same as #1, Density 0.12 0.68970 0.00100 0.692

7. nrc_nct.cyl_celo_den_0.14.out:

Same as #1, Density 0.14 0.67591 0.00097 0.678

8. nrc_nct.cyl_celo_den_0.16.out:

Same as #1, Density 0.16 0.66620 0.00120 0.669

9. nrc_nct.cyl_celo_den_0.18.out:

Same as #1, Density 0.18 0.65730 0.00100 0.660

10. nrc_nct.cyl_celo_den_0.20.out:

Same as #1, Density 0.20 0.65240 0.00100 0.655

11. nrc_nct.cyl_celo_den_0.22.out:

Same as #1, Density 0.22 0.64870 0.00100 0.651

12. nrc_nct.cyl_celo_den_0.24.out:

Same as #1, Density 0.24 0.64330 0.00100 0.646

13. nrc_nct.cyl_celo_den_0.26.out:

Same as #1, Density 0.26 0.63763 0.00097 0.640

2. Variation of Stainless Steel Composition Several kinds of stainless steel are used in the 9975/3013 system. To simplify the analysis, a standard composition of stainless steel corresponding to SS 304 from ORNL/TM-2005/39 is used. Table A1.2 shows the composition of several different types of stainless steel used in 9975/3013 components. It should be noted that there is a small variation of elemental compositions and density for each type of stainless steel. Table A1.3 shows the keff results for the base case of a NCT scenario using different stainless steel composition and another case with a variation in stainless steel density.

Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 50 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 49 of 87 Table A1.2.

Stainless Steel Composition Element SCALE ID SS 304 (wt. %)

SS 304L (wt. %)

SS-316 (wt. %)

Fe 26304 68.375 67.895 65.375 Cr 24304 19.00 19.00 17.00 Ni 28304 9.50 10.00 12.00 Mo 42000 2.50 Mn 25055 2.00 2.00 2.00 Si 14000 1.00 1.00 1.00 C

6012 0.08 0.030 0.08 P

15031 0.045 0.045 0.045 S

16000 0.03 0.03 total 100.00 100.00 100.00 Density g/cc 7.92++

7.90 8.03

++Note: ORNL/TM-2005/39 specifies the density of SS 304 as 7.94 g/cc. A density value of 7.92 g/cc was used in this analysis. The variation in steel density is shown to be negligible in Table A1.3.

Table A1.3.

Variation of keff with Stainless Steel Composition Case No.

File ID Description keff keff +2

1. nrc_nct.cylno3013.out:

NCT case, No 3013, Dry, Infinite array - SS 304 (7.92 g/cc) 0.65240 0.00110 0.655

2. nrc_nct.cylno3013_SS304_0.94.out:

Same as #1, SS 304 (7.94 g/cc) 0.65030 0.00120 0.653

3. nrc_nct.cylno3013_SS304L.out:

Same as #1, SS 304L 0.65200 0.00100 0.654

4. nrc_nct.cylno3013_SS316.out:

Same as #1, SS 316 0.64960 0.00100 0.652 Table A1.3 shows that the variation in keff by using different types of stainless steel is insignificant (within 1). It should be noted that for each of the models, it is assumed that all steel components are made of one kind of stainless steel.

3. Variation of Dimensional Tolerances on PCV and SCV The effect of uncertainties in the thickness of the PCV and SCV on the calculated keff was also considered in this analysis. The ASTM A312 standard indicates a tolerance of +22.5% /

-12.5% on the wall thickness and a tolerance of +1/16 / -1/32 inch on the outer diameter. This evaluation performed an analysis and determined that there is no statistical significance Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 51 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 50 of 87 among the keff values calculated with nominal, minimum, and maximum wall thickness (Table A1.4). Therefore the nominal dimensions of PCV and SCV are used in this analysis.

Table A1.4.

Variation of Dimensional Tolerances on PCV and SCV - Single Unit Case No.

File ID Description keff keff +2

1. nrc_su.cyl3013.out: (From Table 8)

Nominal wall dimensions for PCV/SCV outer diameter 0.59217 0.00099 0.595

2. nrc_su.pos_PCV_pos_SCV.out:

Upper Tolerance PCV Upper Tolerance SCV 0.59145 0.00094 0.593

3. nrc_su.pos_PCV_neg_SCV.out:

Upper Tolerance PCV Lower Tolerance SCV 0.59564 0.00099 0.598

4. nrc_su.neg_PCV_pos_SCV.out:

Lower Tolerance PCV Upper Tolerance SCV 0.59510 0.00100 0.597

5. nrc_su.neg_PCV_neg_SCV.out:

Lower Tolerance PCV Lower Tolerance SCV 0.59267 0.00091 0.594

4. Stainless Steel Sleeve Sensitivity Calculation The 9975 shipping package has an outer and inner stainless steel sleeve surrounding the lead shield of the package. The sleeves are 20 gage, 0.036-inch thick SS 304. The minimum lead thickness is 0.434 inch. However, the lead shield body is modeled with overall thickness of 0.506 inch with the inner and outer skin of nominal 0.036-inch thickness. As shown in Table A1.5, neglecting the stainless steel sleeves and including the thickness as lead has a negligible effect and thus is neglected.

Table A1.5.

Stainless Steel Sleeve Sensitivity Calculation Case No.

File ID Description keff keff +2

1. nrc_su.cyl3013.out:

SS sleeve thickness included as lead 0.59450 0.0010 0.597

2. nrc_su.cyl3013_2ss_sleeve.out:

SS sleeve thicknes modeled as SS 304 0.59406 0.00093 0.596 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 52 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 51 of 87 APPENDIX B SAMPLE INPUT FILES Sample input files: (for the plutonium oxide cases):

1. nrc_su.cyl3013.in - Single unit case (Base Case with 3013, dry oxide) - see Table 8.
2. nrc_su.cylno3013_ccfull_PCVSCV_ALL.in - Single unit case (convenience can flooded with water, PCV/SCV/Celotex as water) - see Table 17.
3. nrc_nct.cyl3013.in - NCT case (Infinite drum array, dry fissile material) - see Table 22.
4. nrc_hac.cyl_CCfl_3013fl.in - HAC case (infinite 2x2x2 cluster array, convenience can flooded/3013 flooded, fissile units at closest position) - see Table 24.
5. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in - Single unit case. PCV intact. CC and 3013 removed. 6.6689 L water added to shipping package, solution spilling into SCV.

Celotex flooded - see Table 21.

1. nrc_su.cyl3013.in

'NRC PuO2 Single Unit Case - 12/2012

=csas26 parm=Centrm nrc_su 9975 - pu oxide - 3013 238groupndf5 read composition wtptpuo2 1 10.8921 3 94239 87.76187 1001 0.055698 8016 12.18243 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 4.187 -11.005 -19.380 cylinder 2 5.271 1.320 -19.380 cylinder 3 5.423 1.345 -19.405 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 53 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 52 of 87 cylinder 4 5.690 3.335 -19.415 cylinder 5 5.842 3.535 -19.565 cylinder 6 5.948 4.535 -19.575 cylinder 7 6.255 4.935 -20.475 cylinder 8 6.410 20.475 -20.475 cylinder 9 7.065 20.475 -21.130 cylinder 10 7.703 20.475 -21.130 cylinder 11 8.414 20.475 -21.130 cylinder 12 9.208 20.475 -21.130 cylinder 13 10.493 20.475 -21.130 cylinder 14 22.987 20.475 -21.130 cylinder 15 23.101 20.475 -21.130 cylinder 16 23.223 20.475 -21.130 cuboid 17 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 3 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 1 media 0 1 4 2 media 8 1 5 3 media 2 1 6 4 media 0 1 7 5 media 3 1 8 6 media 0 1 9 7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 54 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 53 of 87 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 -23.223 23.223 -23.223 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 1 media 0 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 55 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 54 of 87 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 -4.191 cuboid 11 23.223 -23.223 23.223 -23.223 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 22.987 0 -2.25 cylinder 6 23.101 0 -2.25 cylinder 7 23.223 0 -2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 1 media 3 1 4 2 media 0 1 5 3 boundary 5 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 -1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 -11.044 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 56 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 55 of 87 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=

fill 9

7 6

1 2

3 4

5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 end start end data end

2. nrc_su.cylno3013_ccfull_PCVSCV_ALL.in

'NRC PuO2 Single Unit Case - 12/2012

=csas26 parm=Centrm nrc_su 9975 - pu oxide - 3013 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 57 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 56 of 87 238groupndf5 read composition wtptpuo2 1 3.5862 3 94239 69.723859 1001 2.345257 8016 27.930885 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1.0 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 0.275 -20.450 cylinder 2 5.271 0.275 -20.450 cylinder 3 5.423 0.275 -20.475 cylinder 4 6.410 20.475 -20.475 cylinder 5 7.065 20.475 -21.130 cylinder 6 7.703 20.475 -21.130 cylinder 7 8.414 20.475 -21.130 cylinder 8 9.208 20.475 -21.130 cylinder 9 10.493 20.475 -21.130 cylinder 10 22.987 20.475 -21.130 cylinder 11 23.101 20.475 -21.130 cylinder 12 23.223 20.475 -21.130 cuboid 13 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 8 1 9 7 media 5 1 10 8 media 0 1 11 9 media 3 1 12 10 media 0 1 13 11 boundary 13 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 58 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 57 of 87 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 5 1 2 -1 media 3 1 3 1 media 0 1 4 2 media 8 1 5 3 media 5 1 6 4 media 0 1 7 5 media 3 1 8 6 media 0 1 9 7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 -23.223 23.223 -23.223 5.922 0 media 3 1 1 media 5 1 2 -1 media 9 1 3 1 media 5 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 5 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 5 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 59 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 58 of 87 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 5 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 -4.191 cuboid 11 23.223 -23.223 23.223 -23.223 0 -4.191 media 5 1 1 media 3 1 2 -1 media 5 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 5 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 22.987 0 -2.25 cylinder 6 23.101 0 -2.25 cylinder 7 23.223 0 -2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 5 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 60 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 59 of 87 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 5 1 2 -1 media 0 1 3 1 media 3 1 4 2 media 0 1 5 3 boundary 5 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 -1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 -11.044 media 4 1 1 media 5 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=

fill 9

7 6

1 2

3 4

5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 61 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 60 of 87 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 end start end data end

3. nrc_nct.cyl3013.in

'NRC PuO2 NCT Case - 12/2012

=csas26 parm=Centrm nrc_nct 9975 - pu oxide - 3013 238groupndf5 read comp wtptpuo2 1 10.8921 3 94239 87.761870 1001 0.055698 8016 12.182430 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end comp read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg" cylinder 1 4.187 -9.225 -17.600 cylinder 2 5.271 3.100 -17.600 cylinder 3 5.423 3.125 -17.625 cylinder 4 5.690 5.115 -17.635 cylinder 5 5.842 5.315 -17.785 cylinder 6 5.948 6.315 -17.795 cylinder 7 6.255 6.705 -18.695 cylinder 8 6.410 20.475 -20.475 cylinder 9 7.065 20.475 -21.130 cylinder 10 7.703 20.475 -21.130 cylinder 11 8.414 20.475 -21.130 cylinder 12 9.208 20.475 -21.130 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 62 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 61 of 87 cylinder 13 10.493 20.475 -21.130 cylinder 14 21.466 20.475 -21.130 cylinder 15 21.466 20.475 -21.130 cylinder 16 21.597 20.475 -21.130 cuboid 17 21.597 -21.597 21.597 -21.597 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 3 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 2 com='top of primary containment' cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 21.466 3.505 0 cylinder 7 21.466 3.505 0 cylinder 8 21.597 3.505 0 cuboid 9 21.597 -21.597 21.597 -21.597 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 3 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 21.466 5.922 0 cylinder 9 21.466 5.922 0 cylinder 10 21.597 5.922 0 cuboid 11 21.597 -21.597 21.597 -21.597 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 1 media 0 1 4 2 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 63 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 62 of 87 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 4 com='secondary containment top' cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 21.466 3.505 0 cylinder 5 21.466 3.505 0 cylinder 6 21.597 3.505 0 cuboid 7 21.597 -21.597 21.597 -21.597 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 5 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 21.466 2.54 0 cylinder 6 21.466 2.54 0 cylinder 7 21.597 2.54 0 cuboid 8 21.597 -21.597 21.597 -21.597 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 6 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 21.466 0 -4.191 cylinder 9 21.466 0 -4.191 cylinder 10 21.597 0 -4.191 cuboid 11 21.597 -21.597 21.597 -21.597 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 64 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 63 of 87 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 7 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 21.466 0 -2.25 cylinder 6 21.466 0 -2.25 cylinder 7 21.597 0 -2.25 cuboid 8 21.597 -21.597 21.597 -21.597 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 -1 media 2 1 5 3 -2 media 0 1 6 4 -3 media 3 1 7 5 -4 media 0 1 8 6 -5 boundary 8 unit 8 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 cylinder 2 21.466 10.668 0 cylinder 3 21.466 12.828 0 cylinder 4 21.597 12.95 0 cuboid 5 21.597 -21.597 21.597 -21.597 12.95 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 9 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 cylinder 2 21.466 0 -10.922 cylinder 3 21.466 0 -10.922 cylinder 4 21.597 0 -11.044 cuboid 5 21.597 -21.597 21.597 -21.597 0 -11.044 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 global unit 10 cuboid 1 43.194 0 43.194 0 87.512 0 array 1 1 place 1 1 1 21.597 21.597 11.044 boundary 1 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square fill 9 7 6 1 2 3 4 5 8 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 65 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 64 of 87 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=800 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read bnds body=1 surface(1)=mirror surface(2)=mirror surface(3)=mirror surface(4)=mirror surface(5)=periodic surface(6)=periodic end bnds read start nst=0 end start end data end

4. nrc_hac.cyl_CCfl_3013fl.in

'NRC PuO2 HAC Case - 12/2012

=csas26 parm=Centrm nrc_hac 9975 - pu oxide - 3013 238groupndf5 read comp wtptpuo2 1 3.7421 3 94239 70.843921 1001 2.203088 8016 26.952992 1 300 end atom-celt 2 0.2 3 6000 6 1001 10 8016 5 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 66 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 65 of 87 1 293 end ss304 3 den=7.92 1 293 end al 4 den=2.7 1 293 end h2o 5 den=1 1 293 end pb 8 den=11.34 1 293 end al 9 den=0.28 1 293 end end comp read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=6.076 y=-6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=6.076 y=-6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=6.076 y=-6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=6.076 y=-6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=6.076 y=-6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=6.076 y=-6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 2 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 2 7.703 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 3 8.414 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 4 9.208 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 5 10.493 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 6 16.637 3.505 0 origin x=1.732 y=-1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 67 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 66 of 87 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 3 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 2 4.699 4.572 0 origin x=6.076 y=-6.076 z=0 cylinder 3 7.366 4.572 0 origin x=6.076 y=-6.076 z=0 cylinder 4 7.703 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 5 8.414 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 6 9.208 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 7 10.493 5.922 0 origin x=6.076 y=-6.076 z=0 cylinder 8 16.637 5.922 0 origin x=1.732 y=-1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 -2 media 0 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 4 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 2 9.208 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 3 10.493 3.505 0 origin x=6.076 y=-6.076 z=0 cylinder 4 16.637 3.505 0 origin x=1.732 y=-1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 -2 media 2 1 4 -3 media 0 1 5 -4 media 3 1 6 -5 media 0 1 7 -6 boundary 7 unit 5 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 2 9.208 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 3 10.493 1.27 0 origin x=6.076 y=-6.076 z=0 cylinder 4 10.493 2.54 0 origin x=6.076 y=-6.076 z=0 cylinder 5 16.637 2.54 0 origin x=1.732 y=-1.732 z=0 cylinder 6 19.088 2.54 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 68 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 67 of 87 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 -2 media 4 1 4 -3 media 2 1 5 -4 media 0 1 6 -5 media 3 1 7 -6 media 0 1 8 -7 boundary 8 unit 6 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=6.076 y=-6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=6.076 y=-6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=6.076 y=-6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=6.076 y=-6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=6.076 y=-6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=6.076 y=-6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=6.076 y=-6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=1.732 y=-1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 -2 media 9 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 7 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=6.076 y=-6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=6.076 y=-6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=6.076 y=-6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=6.076 y=-6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=1.732 y=-1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 -2 media 8 1 4 -3 media 2 1 5 -4 media 0 1 6 -5 media 3 1 7 -6 media 0 1 8 -7 boundary 8 unit 8 com='al top plate and celotex plus top void plus drum lower' cylinder 1 14.224 1.27 0 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 1.27 0 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 69 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 68 of 87 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 9 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 10 cuboid 1 38.47 0 38.47 0 164.864 0 array 1 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 13 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=6.076 y=-6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=6.076 y=-6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=6.076 y=-6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=6.076 y=-6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=6.076 y=-6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=6.076 y=-6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 70 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 69 of 87 unit 16 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 10.16 0 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 17 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=-6.076 y=-6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=-6.076 y=-6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=-6.076 y=-6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=-6.076 y=-6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=-6.076 y=-6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=-6.076 y=-6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=-6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 18 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 7.703 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 8.414 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 9.208 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 5 10.493 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 6 16.637 3.505 0 origin x=-1.732 y=-1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 71 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 70 of 87 media 3 1 1 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 19 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 4.699 4.572 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 7.366 4.572 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 7.703 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 5 8.414 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 6 9.208 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 7 10.493 5.922 0 origin x=-6.076 y=-6.076 z=0 cylinder 8 16.637 5.922 0 origin x=-1.732 y=-1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 -2 media 0 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 20 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 9.208 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 10.493 3.505 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 16.637 3.505 0 origin x=-1.732 y=-1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 21 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 2 9.208 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 3 10.493 1.27 0 origin x=-6.076 y=-6.076 z=0 cylinder 4 10.493 2.54 0 origin x=-6.076 y=-6.076 z=0 cylinder 5 16.637 2.54 0 origin x=-1.732 y=-1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 72 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 71 of 87 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 22 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=-6.076 y=-6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=-6.076 y=-6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=-6.076 y=-6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=-6.076 y=-6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=-6.076 y=-6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=-6.076 y=-6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=-6.076 y=-6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=-1.732 y=-1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 23 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=-6.076 y=-6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=-6.076 y=-6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=-6.076 y=-6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=-6.076 y=-6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=-1.732 y=-1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 24 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 1.27 0 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 73 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 72 of 87 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 25 com='al bottom plate and celotex plus bottom void plus drum' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 28 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=-6.076 y=-6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=-6.076 y=-6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=-6.076 y=-6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=-6.076 y=-6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=-6.076 y=-6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=-6.076 y=-6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=-6.076 y=-6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=-6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=-6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=-1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 31 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 10.16 0 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 17.4 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 74 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 73 of 87 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 32 cuboid 1 38.47 0 38.47 0 164.864 0 array 2 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 33 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=6.076 y=6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=6.076 y=6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=6.076 y=6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=6.076 y=6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=6.076 y=6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=6.076 y=6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 34 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 2 7.703 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 3 8.414 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 4 9.208 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 5 10.493 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 6 16.637 3.505 0 origin x=1.732 y=1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 75 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 74 of 87 media 0 1 2 -1 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 35 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 2 4.699 4.572 0 origin x=6.076 y=6.076 z=0 cylinder 3 7.366 4.572 0 origin x=6.076 y=6.076 z=0 cylinder 4 7.703 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 5 8.414 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 6 9.208 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 7 10.493 5.922 0 origin x=6.076 y=6.076 z=0 cylinder 8 16.637 5.922 0 origin x=1.732 y=1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 -2 media 0 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 36 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 2 9.208 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 3 10.493 3.505 0 origin x=6.076 y=6.076 z=0 cylinder 4 16.637 3.505 0 origin x=1.732 y=1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 -2 media 2 1 4 -3 media 0 1 5 -4 media 3 1 6 -5 media 0 1 7 -6 boundary 7 unit 37 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 2 9.208 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 3 10.493 1.27 0 origin x=6.076 y=6.076 z=0 cylinder 4 10.493 2.54 0 origin x=6.076 y=6.076 z=0 cylinder 5 16.637 2.54 0 origin x=1.732 y=1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 76 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 75 of 87 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 38 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=6.076 y=6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=6.076 y=6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=6.076 y=6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=6.076 y=6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=6.076 y=6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=1.732 y=1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 9 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 39 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=6.076 y=6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=6.076 y=6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=1.732 y=1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 40 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 1.27 0 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 media 4 1 1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 77 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 76 of 87 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 41 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 44 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=6.076 y=6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=6.076 y=6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=6.076 y=6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=6.076 y=6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=6.076 y=6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=6.076 y=6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 47 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 10.16 0 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 78 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 77 of 87 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 48 cuboid 1 38.47 0 38.47 0 164.864 0 array 3 1 place 1 1 1 19.235 19.235 17.522 boundary 1 unit 49 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 19.380 -1.320 origin x=-6.076 y=6.076 z=0 cylinder 2 5.271 19.380 -1.320 origin x=-6.076 y=6.076 z=0 cylinder 3 5.423 19.405 -1.345 origin x=-6.076 y=6.076 z=0 cylinder 4 5.690 19.415 -3.335 origin x=-6.076 y=6.076 z=0 cylinder 5 5.842 19.565 -3.535 origin x=-6.076 y=6.076 z=0 cylinder 6 5.948 19.575 -4.535 origin x=-6.076 y=6.076 z=0 cylinder 7 6.255 20.475 -4.925 origin x=-6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 50 com='top of primary containment' cylinder 1 7.455 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 2 7.703 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 3 8.414 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 4 9.208 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 5 10.493 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 6 16.637 3.505 0 origin x=-1.732 y=1.732 z=0 cylinder 7 19.088 3.505 0 cylinder 8 19.235 3.505 0 cuboid 9 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 79 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 78 of 87 media 3 1 3 -2 media 0 1 4 -3 media 8 1 5 -4 media 2 1 6 -5 media 0 1 7 -6 media 3 1 8 -7 media 0 1 9 -8 boundary 9 unit 51 com='primary containment nut and al honeycomb' cylinder 1 3.175 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 2 4.699 4.572 0 origin x=-6.076 y=6.076 z=0 cylinder 3 7.366 4.572 0 origin x=-6.076 y=6.076 z=0 cylinder 4 7.703 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 5 8.414 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 6 9.208 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 7 10.493 5.922 0 origin x=-6.076 y=6.076 z=0 cylinder 8 16.637 5.922 0 origin x=-1.732 y=1.732 z=0 cylinder 9 19.088 5.922 0 cylinder 10 19.235 5.922 0 cuboid 11 19.235 -19.235 19.235 -19.235 5.922 0 media 3 1 1 media 0 1 2 -1 media 9 1 3 1 media 0 1 4 2 media 3 1 5 3 media 0 1 6 4 media 8 1 7 5 media 2 1 8 6 media 0 1 9 7 media 3 1 10 8 media 0 1 11 9 boundary 11 unit 52 com='secondary containment top' cylinder 1 9.042 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 2 9.208 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 3 10.493 3.505 0 origin x=-6.076 y=6.076 z=0 cylinder 4 16.637 3.505 0 origin x=-1.732 y=1.732 z=0 cylinder 5 19.088 3.505 0 cylinder 6 19.235 3.505 0 cuboid 7 19.235 -19.235 19.235 -19.235 3.505 0 media 3 1 1 media 0 1 2 -1 media 8 1 3 1 media 2 1 4 2 media 0 1 5 3 media 3 1 6 4 media 0 1 7 5 boundary 7 unit 53 com='scv nut and al shield top' cylinder 1 3.175 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 2 9.208 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 3 10.493 1.27 0 origin x=-6.076 y=6.076 z=0 cylinder 4 10.493 2.54 0 origin x=-6.076 y=6.076 z=0 cylinder 5 16.637 2.54 0 origin x=-1.732 y=1.732 z=0 cylinder 6 19.088 2.54 0 cylinder 7 19.235 2.54 0 cuboid 8 19.235 -19.235 19.235 -19.235 2.54 0 media 3 1 1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 80 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 79 of 87 media 0 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 54 com='pcv legs, al honeycomb and scv bottom' cylinder 1 5.113 0 -0.94 origin x=-6.076 y=6.076 z=0 cylinder 2 5.715 0 -0.94 origin x=-6.076 y=6.076 z=0 cylinder 3 7.703 0 -0.94 origin x=-6.076 y=6.076 z=0 cylinder 4 7.703 0 -3.48 origin x=-6.076 y=6.076 z=0 cylinder 5 8.414 0 -4.191 origin x=-6.076 y=6.076 z=0 cylinder 6 9.208 0 -4.191 origin x=-6.076 y=6.076 z=0 cylinder 7 10.493 0 -4.191 origin x=-6.076 y=6.076 z=0 cylinder 8 16.637 0 -4.191 origin x=-1.732 y=1.732 z=0 cylinder 9 19.088 0 -4.191 cylinder 10 19.235 0 -4.191 cuboid 11 19.235 -19.235 19.235 -19.235 0 -4.191 media 0 1 1 media 3 1 2 -1 media 0 1 3 -2 media 9 1 4 -3 media 3 1 5 -4 media 0 1 6 -5 media 8 1 7 -6 media 2 1 8 -7 media 0 1 9 -8 media 3 1 10 -9 media 0 1 11 -10 boundary 11 unit 55 com='scv legs and bottom of lead shield' cylinder 1 6.41 0 -0.965 origin x=-6.076 y=6.076 z=0 cylinder 2 7.065 0 -0.965 origin x=-6.076 y=6.076 z=0 cylinder 3 9.208 0 -0.965 origin x=-6.076 y=6.076 z=0 cylinder 4 10.493 0 -2.25 origin x=-6.076 y=6.076 z=0 cylinder 5 16.637 0 -2.25 origin x=-1.732 y=1.732 z=0 cylinder 6 19.088 0 -2.25 cylinder 7 19.235 0 -2.25 cuboid 8 19.235 -19.235 19.235 -19.235 0 -2.25 media 0 1 1 media 3 1 2 -1 media 0 1 3 1 media 8 1 4 2 media 2 1 5 3 media 0 1 6 4 media 3 1 7 5 media 0 1 8 6 boundary 8 unit 56 com='al top plate and celotex plus top void plus drum' cylinder 1 14.224 1.27 0 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 1.27 0 origin x=-1.732 y=1.732 z=0 cylinder 3 19.088 1.27 0 cylinder 4 19.235 1.392 0 cuboid 5 19.235 -19.235 19.235 -19.235 1.392 0 media 4 1 1 media 2 1 2 -1 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 81 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 80 of 87 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 57 com='al bottom plate and celotex plus bottom void (zero, new model) plus drum' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 0 -10.16 origin x=-1.732 y=1.732 z=0 cylinder 3 19.088 0 -17.4 cylinder 4 19.235 0 -17.522 cuboid 5 19.235 -19.235 19.235 -19.235 0 -17.522 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 60 com="pu cylinder, 5.0 kg PuO2" cylinder 1 5.271 1.320 -19.380 origin x=-6.076 y=6.076 z=0 cylinder 2 5.271 1.320 -19.380 origin x=-6.076 y=6.076 z=0 cylinder 3 5.423 1.345 -19.405 origin x=-6.076 y=6.076 z=0 cylinder 4 5.690 3.335 -19.415 origin x=-6.076 y=6.076 z=0 cylinder 5 5.842 3.535 -19.565 origin x=-6.076 y=6.076 z=0 cylinder 6 5.948 4.535 -19.575 origin x=-6.076 y=6.076 z=0 cylinder 7 6.255 4.935 -20.475 origin x=-6.076 y=6.076 z=0 cylinder 8 6.410 20.475 -20.475 origin x=-6.076 y=6.076 z=0 cylinder 9 7.065 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 10 7.703 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 11 8.414 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 12 9.208 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 13 10.493 20.475 -21.130 origin x=-6.076 y=6.076 z=0 cylinder 14 16.637 20.475 -21.130 origin x=-1.732 y=1.732 z=0 cylinder 15 19.088 20.475 -21.130 cylinder 16 19.235 20.475 -21.130 cuboid 17 19.235 -19.235 19.235 -19.235 20.475 -21.13 media 1 1 1 media 0 1 2 -1 media 3 1 3 -2 media 5 1 4 -3 media 3 1 5 3 media 5 1 6 4 media 3 1 7 5 media 0 1 8 6 media 3 1 9 7 media 0 1 10 8 media 3 1 11 9 media 0 1 12 10 media 8 1 13 11 media 2 1 14 12 media 0 1 15 13 media 3 1 16 14 media 0 1 17 15 boundary 17 unit 63 com='al top plate and celotex plus top void plus drum upper' cylinder 1 14.224 1.27 0 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 10.16 0 origin x=-1.732 y=1.732 z=0 cylinder 3 19.088 17.4 0 cylinder 4 19.235 17.522 0 cuboid 5 19.235 -19.235 19.235 -19.235 17.522 0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 82 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 81 of 87 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 64 cuboid 1 38.47 0 38.47 0 164.864 0 array 4 1 place 1 1 1 19.235 19.235 17.522 boundary 1 global unit 65 com=^5 x 5 x 2 damaged array^

cuboid 1 7.694000E+01 0.000000E+00 7.694000E+01 0.000000E+00 1.648640E+02 0.000000E+00 array 5 1 place 1 1 1 0.00000E+00 0.00000E+00 0.00000E+00 boundary 1 unit 71 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=3.438 y=-3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=1.732 y=-1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 72 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=-3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=-1.732 y=-1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 73 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=3.438 y=3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=1.732 y=1.732 z=0 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 unit 74 com='al bot plate and celotex plus top void plus drum lower' cylinder 1 14.224 0 -1.27 origin x=-3.438 y=3.438 z=0 cylinder 2 16.637 0 -1.27 origin x=-1.732 y=1.732 z=0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 83 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 82 of 87 cylinder 3 19.088 0 -1.27 cylinder 4 19.235 0 -1.392 cuboid 5 19.235 -19.235 19.235 -19.235 0 -1.392 media 4 1 1 media 2 1 2 -1 media 0 1 3 -2 media 3 1 4 -3 media 0 1 5 -4 boundary 5 end geometry read array ara=1 nux=1 nuy=1 nuz=18 typ=square fill 9 7 6 1 2 3 4 5 8 71 7 6 13 2 3 4 5 16 end fill ara=2 nux=1 nuy=1 nuz=18 typ=square fill 25 23 22 17 18 19 20 21 24 72 23 22 28 18 19 20 21 31 end fill ara=3 nux=1 nuy=1 nuz=18 typ=square fill 41 39 38 33 34 35 36 37 40 73 39 38 44 34 35 36 37 47 end fill ara=4 nux=1 nuy=1 nuz=18 typ=square fill 57 55 54 49 50 51 52 53 56 74 55 54 60 50 51 52 53 63 end fill ara=5 nux=2 nuy=2 nuz=1 fill 48 64 10 32 end fill end array read bound xyf=mirror zfc=periodic end bound read start nst=0 end start read plot scr=yes lpi=10 ttl='plot1 xy slice' xul=-10 xlr=100 yul=100 ylr= -10 zul=61 zlr=61 uax=1 vdn=-1 nax=600 end ttl='plot2 xy slice' xul=-10 xlr=240 yul=240 ylr= -10 zul=61 zlr=61 uax=1 vdn=-1 nax=600 end ttl='plot3 xslice' xul=-5 xlr=100 yul= 27 ylr= 27 zul=190 zlr=-5 uax=1 wdn=-1 nax=600 end ttl='plot4 xslice' xul=-5 xlr=300 yul= 19 ylr= 19 zul=190 zlr=-5 uax=1 wdn=-1 nax=800 end end plot end data end

5. nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in

=csas26 parm=Centrm nrc_su._PuO_fld_6SCV_noBe_ful_fld_celo.6689.in 238groupndf5 read composition wtptpuo2 1 1.6341 3 94239 37.5962 1001 6.4198 8016 55.9839 1 300 end atom-celt 2 0.2 3 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 84 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 83 of 87 6000 6 1001 10 8016 5 1 300 end ss304 3 den=7.92 1 300 end al 4 den=2.7 1 300 end h2o 5 den=1 1 300 end pb 8 den=11.34 1 300 end al 9 den=0.28 1 300 end end composition read parameter tme=300 gen=425 nsk=25 plt=no end parameter read geometry unit 1 com="PuO2 mixture" cylinder 1 6.41 20.475 -20.475 cylinder 4 6.41 20.475 -20.475 cylinder 5 7.065 20.475 -21.13 cylinder 6 7.703 20.475 -21.13 cylinder 7 8.414 20.475 -21.13 cylinder 8 9.208 20.475 -21.13 cylinder 9 10.493 20.475 -21.13 cylinder 10 22.987 20.475 -21.13 cylinder 11 23.101 20.475 -21.13 cylinder 12 23.223 20.475 -21.13 cuboid 13 23.223 -23.223 23.223 -23.223 20.475 -21.13 media 1 1 1

' media 5 1 2 -1

' media 3 1 3 -2 media 5 1 4 -1 media 3 1 5 -4 media 1 1 6 4 media 3 1 7 5 media 5 1 8 6 media 8 1 9 7 media 5 1 10 8 media 5 1 11 9 media 3 1 12 10 media 5 1 13 11 boundary 13 unit 2 com="top of primary containment" cylinder 1 7.455 3.505 0 cylinder 2 7.703 3.505 0 cylinder 3 8.414 3.505 0 cylinder 4 9.208 3.505 0 cylinder 5 10.493 3.505 0 cylinder 6 22.987 3.505 0 cylinder 7 23.101 3.505 0 cylinder 8 23.223 3.505 0 cuboid 9 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 1 1 2 -1 media 3 1 3 1 media 5 1 4 2 media 8 1 5 3 media 5 1 6 4 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 85 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 84 of 87 media 5 1 7 5 media 3 1 8 6 media 5 1 9 7 boundary 9 unit 3 com="primary containment nut and al honeycomb" cylinder 1 3.175 1.27 0 cylinder 2 4.699 4.572 0 cylinder 3 7.366 4.572 0 cylinder 4 7.703 5.922 0 cylinder 5 8.414 5.922 0 cylinder 6 9.208 5.922 0 cylinder 7 10.493 5.922 0 cylinder 8 22.987 5.922 0 cylinder 9 23.101 5.922 0 cylinder 10 23.223 5.922 0 cuboid 11 23.223 -23.223 23.223 -23.223 5.922 0 media 3 1 1 media 5 1 2 -1 media 5 1 3 1 media 5 1 4 2 media 3 1 5 3 media 5 1 6 4 media 8 1 7 5 media 5 1 8 6 media 5 1 9 7 media 3 1 10 8 media 5 1 11 9 boundary 11 unit 4 com="secondary containment top" cylinder 1 9.042 3.505 0 cylinder 2 9.208 3.505 0 cylinder 3 10.493 3.505 0 cylinder 4 22.987 3.505 0 cylinder 5 23.101 3.505 0 cylinder 6 23.223 3.505 0 cuboid 7 23.223 -23.223 23.223 -23.223 3.505 0 media 3 1 1 media 5 1 2 -1 media 8 1 3 1 media 5 1 4 2 media 5 1 5 3 media 3 1 6 4 media 5 1 7 5 boundary 7 unit 5 com="scv nut and al shield top" cylinder 1 3.175 1.27 0 cylinder 2 9.208 1.27 0 cylinder 3 10.493 1.27 0 cylinder 4 10.493 2.54 0 cylinder 5 22.987 2.54 0 cylinder 6 23.101 2.54 0 cylinder 7 23.223 2.54 0 cuboid 8 23.223 -23.223 23.223 -23.223 2.54 0 media 3 1 1 media 5 1 2 -1 media 8 1 3 1 media 4 1 4 2 media 5 1 5 3 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 86 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 85 of 87 media 5 1 6 4 media 3 1 7 5 media 5 1 8 6 boundary 8 unit 6 com="pcv legs, al honeycomb and scv bottom" cylinder 1 5.113 0 -0.94 cylinder 2 5.715 0 -0.94 cylinder 3 7.703 0 -0.94 cylinder 4 7.703 0 -3.48 cylinder 5 8.414 0 -4.191 cylinder 6 9.208 0 -4.191 cylinder 7 10.493 0 -4.191 cylinder 8 22.987 0 -4.191 cylinder 9 23.101 0 -4.191 cylinder 10 23.223 0 -4.191 cuboid 11 23.223 -23.223 23.223 -23.223 0 -4.191 media 1 1 1 media 3 1 2 -1 media 1 1 3 1 media 1 1 4 2 media 3 1 5 3 media 5 1 6 4 media 8 1 7 5 media 5 1 8 6 media 5 1 9 7 media 3 1 10 8 media 5 1 11 9 boundary 11 unit 7 com="scv legs and bottom of lead shield" cylinder 1 6.41 0 -0.965 cylinder 2 7.065 0 -0.965 cylinder 3 9.208 0 -0.965 cylinder 4 10.493 0 -2.25 cylinder 5 22.987 0 -2.25 cylinder 6 23.101 0 -2.25 cylinder 7 23.223 0 -2.25 cuboid 8 23.223 -23.223 23.223 -23.223 0 -2.25 media 5 1 1 media 3 1 2 -1 media 5 1 3 1 media 8 1 4 2 media 5 1 5 3 media 5 1 6 4 media 3 1 7 5 media 5 1 8 6 boundary 8 unit 8 com="al top plate and celotex plus top void plus drum" cylinder 1 14.224 1.27 0 cylinder 2 22.987 10.668 0 cylinder 3 23.101 12.828 0 cylinder 4 23.223 12.95 0 cuboid 5 23.223 -23.223 23.223 -23.223 12.95 0 media 4 1 1 media 5 1 2 -1 media 5 1 3 1 media 3 1 4 2 media 5 1 5 3 boundary 5 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 87 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 86 of 87 unit 9 com="al bottom plate and celotex plus bottom void (zero, new model) plus drum" cylinder 1 14.224 0 -1.27 cylinder 2 22.987 0 -10.922 cylinder 3 23.101 0 -10.922 cylinder 4 23.223 0 -11.044 cuboid 5 23.223 -23.223 23.223 -23.223 0 -11.044 media 4 1 1 media 5 1 2 -1 media 5 1 3 -2 media 3 1 4 -3 media 5 1 5 -4 boundary 5 global unit 10 com="global unit 10 references array 1" cuboid 1 46.446 0 46.446 0 87.512 0 array 1 1 place 1 1 1 23.223 23.223 11.044 cuboid 2 76.446 -30 76.446 -30 117.512 -30 media 5 1 2 -1 boundary 2 end geometry read array ara=1 nux=1 nuy=1 nuz=9 typ=square com=

fill 9

7 6

1 2

3 4

5 8 end fill end array read plot scr=yes ttl='plot1 xy slice' pic=mixtures xul=-10 yul=60 zul=39 xlr=60 ylr=-10 zlr=39 nax=600 clr=1 200 200 200 2 0 0 205 3 0 229 238 4 0 238 0 5 205 205 0 8 150 150 150 9 240 200 220 12 0 255 127 13 255 255 224 end color uax=1 vdn=-1 end end plot read start nst=0 Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 88 of 90

9975 Shipping Package with Plutonium Oxide Contents for N-NCS-A-00029 NRC Safety Analysis Report Rev. 1 Page 87 of 87 end start end data end Revision 1 S-SAR-G-00001 Appendix 6.1 - Page 89 of 90

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