ML18227A163

Enclosure 3 to E-51276, Replacement Pages for ANUH-01.0150, Standardized Advanced NUHOMS UFSAR, Revision 8

ML18227A163
Person / Time
Site:	07201029
Issue date:	08/13/2018
From:	TN Americas LLC
To:	Office of Nuclear Material Safety and Safeguards, Orano USA
Shared Package
ML18227A192	List: ML18227A162 ML18227A163
References
E-51276 ANUH-01.0150, Rev. 8
Download: ML18227A163 (84)

Text

• to E-51276 Replacement Pages for ANUH-01.0150, Standardized Advanced NUHOMS UFSAR, Revision 8 (Public Version)

NON-PROPRIETARY UPDATED FINAL SAFETY ANALYSIS REPORT FOR THE STANDARDIZED ADVANCED NUHOMS HORIZONTAL MODULAR STORAGE SYSTEM FOR IRRADIATED NUCLEAR FUEL By TN Americas LLC(JJ Columbia, MD August 2018 ANUH-01.0150 Revision 8 (J) TN Americas LLC, formerly AREVA TN, and Transnuclear, Inc. (herein referred to as TN Americas LLC, AREVA TN, Transnuclear, Inc., Transnuclear, or TN)

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 7, 08/16 I The proprietary notice is withheld from this public SAR version.

ANUH-01.0150

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I REVISION LOG SHEET UFSAR Date Record of Changes/FCNs Changed Pages Revision 0

3/19/03 None All 1

3/21/05 FCNs 721029-39, 40, 62, 65, 81, 89, See List of Effective Pages 92,124,126,165, 169& 175 FCNs 721029-182, 185, 103 R-1, 162 2

8/17/06 R-1, 166, 173 R-1, 176 R-1,177 and See List of Effective Pages 204 3

8/15/08 FCNs 721029-202, 205,206,208,215, See List of Effective Pages 220,222Rl,232,239,246,257,272 4

8/12/10 FCNs 721029-275, 280 R-1, 285,294, See List of Effective Pages 303,311,312 R-1, 316 5

8/13/12 FCNs 721029-339, 348 R-1, 351 R-1, See List of Effective Pages 352,353,354,356,364 6

8/13/14 FCN 721029-385 See List of Effective Pages FCN 721029-374 R-1, 378 R-1, 7

8/11/16 386 R-1, 394, 407 R-1, 414, 415, See List of Effective Pages 416 R-1, 417 8

8/13/18 FCN 721029-418, 419 R-1, 420 R-1, See List of Effective Pages 421,422 11

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Executive Summary This Updated Final Safety Analysis Report (UFSAR) provides the generic safety analysis for the standardized Advanced NUHOMS1 System for dry storage of light water reactor spent nuclear fuel assemblies.

This system provides for the safe dry storage of spent fuel in a passive Independent Spent Fuel Storage Installation (ISFSI) which fully complies with the requirements of 10 CFR Part 72 and ANSI 57.9.

The UFSAR describes the design and forms the basis for generic NRC certification of the standardized Advanced NUHOMS System and will be used by 10 CFR Part 50/10 CFR Part 72 general license holders in accordance with 10 CFR 72 Subparts K and L. It is also suitable for reference in 10 CFR Part 72 site specific license applications.

The principal features of the standardized Advanced NUHOMS System which differ from the previously approved NUHOMS Systems are:

L Modification to the C of C No. 1004 HSM (development of Advanced HSM, AHSM) to support qualification for sites with high seismic spectra and/or requirements for a significant reduction in ISFSI dose (e.g., due to congested reactor sites).

2. The AHSM.configuration requires a minimum of three AHSMs tied together to limit sliding and uplift during a seismic event.

3. The Dry Shielded Canister used in this application, the 24PT1-DSC, is a modification to the FO-DSC (associated with C of C No. 9255 and Rancho Seco Materials License SNM-2510, Docket No. 72-11) with additional provisions allowing storage of intact and damaged fuel assemblies, along with control components in a single DSC.

The NUHOMS System provides long-term interim storage for spent fuel assemblies which have been out of the reactor for a sufficient period of time and which comply with the criteria set forth in this UFSAR. The fuel assemblies are confineq in a helium atmosphere by a dry shielded canister. The canister is protected and shielded by a massive reinforced concrete module. Decay heat is removed from the canister and the concrete module by a passive natural draft convection ventilation system.

The canisterized spent fuel assemblies are transferred from the plant's spent fuel pool to the concrete storage modules located at the ISFSI in a transfer cask. The cask is aligned with the storage module and the canister is inserted into the module by means of a hydraulic ram. The NUHOMS System is a totally passive installation that is designed to provide shielding and safe confinement of spent fuel for a range of postulated accident conditions and natural phenomena.

Auxiliary equipment and the transfer system, including the transfer casks, were previously certified under C of C 1004 and are not considered part of the standardized Advanced NUHOMs9 System subject to approval under C of C 1029. Sufficient information for the transfer system and auxiliary equipment is included in this UFSAR to demonstrate that means for safe operation of the system are provided.

Revision I of this UFSAR incorporates modifications implemented under the provisions of 10 CFR 72.48 from March 20, 2003 through March 20, 2005.

1 NUHOMS is a registered trademark of Transnuclear, Inc.

ANUH-01.0150 IV

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Revision 2 of this UFSAR incorporates changes implemented due to the approval of CoC 1029 Amendment 1, effective May 16, 2005. It also incorporates modifications implemented per 10 CFR 72.48 from March 21, 2005 through August 15, 2006.

Revision 3 of this UFSAR incorporates modifications implemented per 10 CFR 72.48 from August 16, 2006 through August 15, 2008. This revision also includes a full list of effective pages.

Revision 4 of this UFSAR incorporates modifications implemented per 10 CFR 72.48 from August 16, 2008 through August 12, 2010.

Revision 5 of this UFSAR incorporates modifications implemented per 10 CFR 72.48 from August 13, 2010 through August 13, 2012.

Revision 6 of this UFSAR incorporates modifications implemented per 10 CFR 72.48 from August 14, 2012 through August 13, 2014.

Revision 7 of this UFSAR incorporates changes implemented due to the approval of CoC 1029 Amendment 3, effective February 23, 2015. It also incorporates modifications implemented per 10 CFR 72.48 from August 14, 2014 through August 'i 1, 2016.

Revision 8 of this UFSAR incorporates modifications implemented per 10 CFR 72. 48 from August 12, 2016 through August 13, 2018.

ANUH-01.0150 V

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 TABLE OF CONTENTS Page PROPRIETARY INFORMATION NOTICE............................................................................. i REVISION LOG SHEET............................................................................................................. ii INTENTIONALLY BLANK...................................................................................................... iii EXECUTIVE

SUMMARY

......................................................................................................... iv LIST OF ACRONYMS............................................................................................................... vi TABLE OF CONTENTS............................................................................................................ ix LIST OF TABLES.................................................................................................................... xvii LIST OF FIGURES................................................................................................................. xxiii LIST OF EFFECTIVE PAGES....................................................................................... LOEP-1

1.

GENERAL INFORMATION............................................................................................ 1-1 1.1 Introduction............................................................................................................ 1.1-1 1.2 General Description of the Advanced NUHOMS System................................ 1.2-1 1.2.1 Advanced NUHOMS System Characteristics............................................ 1.2-1 1.2.2 Operational Features..................................................................................... 1.2-4 1.2.3 24PT1-DSC Contents................................................................................... 1.2-8 1.3 Identification of Agents and Contractors............................................................. 1.3-1 1.4 Generic Cask Arrays.............................................................................................. 1.4-1 1.5 Supplemental Data................................................................................................. 1.5-l

• 1.5.1 *References.................................................................................................... 1.5-l 1.5.2 Drawings....................................................................................................... 1.5-1

2.

PRINCIPAL DESIGN CRITERIA................................................................................. 2.1-1 2.1 Spent Fuel to be Stored... *....................................................................................... 2.1-1 2.1.1 Detailed Payload Description....................................................................... 2.1-1 2.2 Design Criteria for Environmental Co.nditions and Natural Phenomena........ 2.2-1 2.2.1 Tornado and Wind Loadings........................................................................ 2.2-1 2.2.2 Water Level (Flood) Design................ ;........................................................ 2.2-3 2.2.3 Seismic Design*********************************************************************:*********************** 2.2-3 2.2.4 Snow and Ice Loadings................................................................................ 2.2-4 2.2.5 Tsunami........................................................................................................ 2.2-4 2.2.6 Lightning........................................................................................... :.......... 2.2-4 2.2.7 Combined Load Criteria............................................................................... 2.2-4 2.2.8 Burial Un.der Debris.............'........................................................................ 2.2-5 2.2.9 Thermal Conditions...................................................................................... 2.2-5 2.3 Safety Protection Systems............................................................................ ;......... 2.3-1

.2.3.1 General.......................................*......................................................... ;....... 2.3-1 ANUH-01.0150 IX

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 2.3.2 Protection by Multiple Confinement Barriers and Systems......................... 2.3-1 2.3.3 Protection by Equipment and Instrumentation Selection............................. 2.3-3 2.3.4 Nuclear Criticality Safety............................................................................. 2.3-3 2.3.5 Radiological Protection................................................................................ 2.3-4 2.3.6 Fire and Explosion Protection...................................................................... 2.3-5 2.3.7 Acceptance Tests and Maintenance............................................................. 2.3-6 2.4 Decommissioning Considerations......................................................................... 2.4-1 2.5 Structures, Systems and Components Important to Safety............................... 2.5-1 2.5.1 Dry Shielded Canister.................................................................................. 2.5-1 2.5.2 Advanced Horizontal Storage Module............... :......................................... 2.5-1 2.5.3 ISFSI Basemat and Approach Slabs............................................................. 2.5-1 2.5.4 Transfer Equipment...................................................................................... 2.5-2 2.5.5 Auxiliary Equipment.................................................................................... 2.5-2 2.6 Supplemental Information..................................................................................... 2.6-1 2.6.1 References.................................................................................................... 2.6-1

3.

STRUCTURAL EVALUATION................................................................................... 3.1-1 3.1 Structural Design.................................................................................................... 3.1-1 3.1.1 Discussion.................................................................................................... 3.1-1 3.1.2 24PT1-DSC and AHSM Design Criteria..................................................... 3.1-5 3.2 Weights and Centers ofGravity.................................................. :......................... 3.2-1 3.3 Mechanical Properties of Materials...................................................................... 3.3-1 3.3.1 24PT1-DSC Material Properties.................................................................. 3.3-1 3.3.2 AHSM Material Properties........................................................................... 3.3-2 3.3.3 Materials Durability..................................................................................... 3.3-2 3.4 General Standards for 24PT1-DSC and AHSM.................................................. 3.4-1 3.4.1 Chemical and Galvanic Reactions................................................................ 3.4-1 3.4.2 Positive Closure............................................................................................ 3.4-3 3.4.3 Lifting Devices............................................................................................. 3.4-4 3.4.4 Heat...........................................................,.................................................. 3.4-4 3.4.5 Cold.............................................................................................................. 3.4-6 3.5 Fuel Rods General Standards for 24PT1-DSC..................................................... 3.5-1 3.5.1 Fuel Rod Temperature Limits...................................................................... 3.5-1 3.5.2 Fuel Assembly Thermal and Irradiation Growth......................................... 3.5-2 3.5.3 Fuel Rod Integrity During Drop Scenario.................................................... 3.5-2 3.5.4 Fuel Unloading............................................................................................. 3.5-5 ANUH-01.0150 X

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 3.6 Supplemental Data................................................................................................. 3.6-1 3.6.1 24PT1-DSC Structural Analysis.................................................................. 3.6-1 3.6.2 Structural Analysis of the AHSM.............................................................. 3.6-11 3.6.3 References.................................................................................................. 3.6-58

4.

THERMAL EVALUATION...............,............................................................................. 4-1 4.1 Discussion................................................................................................................ 4.1-1 4.1.1 Overview and Purpose of Thermal Analysis................................................ 4.1-1 4.1.2 Thermal Load Specification/Ambient Temperature....................................... 4.1-2 4.2 Summary of Thermal Properties of Materials.................................................... 4.2-1 4.3 Specifications for Components.............................................................................. 4.3-1 4.4 Thermal Evaluation for Normal Conditions of Storage and Transfer............. 4.4-1 4.4.1 Overview of Thermal Analysis for Normal Conditions of Storage and Transfer.................................................................................................. 4.4-1 4.4.2 Thermal Model of the 24PT1-DSC Inside the AHSM................................. 4.4-1 4.4.3 Thermal Model of24PT1-DSC in the Transfer Cask.................................. 4.4-7 4.4.4 24PT1-DSC Basket Thermal Model............................................................ 4.4-8

'4.4.5 Test Model.................................................................................................. 4.4-12 Maximum Temperatures............................................................................ 4.4-12 Minimum Temperatures............................................................................. 4.4-12 4.4.6 4.4.7 4.4.8 Maximum Internal Pressure....................................................................... 4.4-13 4.4.9 Maximum Thermal Stresses....................................................................... 4.4-14 4.4.10 Evaluation of System Performance for Normal Conditions of Storage and Transfer.................................................................................. 4.4-14 4.5 Thermal Evaluation for Off-Normal Conditio-ns................................................ 4.5-1 4.5.1 Overview of Off-Normal Analysis............................................................... 4.5-1 4.5.2 Thermal Analysis Results............................................................................. 4.5-1 4.5.3 Maximum Pressure..................................,.................................................... 4.5-1 4.5.4 Evaluation of System Performance for Off-Normal Conditions of Storage and Transfer.................................................................................... 4.5-2 4.6 Thermal Evaluation for Accident Conditions...................................................... 4.6-1 4.6.1 Accident Ambient Conditions...................................................................... 4.6-1 4.6.2 Blockage of AHSM Inlet and Outlet Vents.................................................. 4.6-1 4.6.3 Transfer Cask Loss of Neutron Shield and Sunshade.................................. 4.6-2 4.6.4 Fire Accident Evaluation.............................................................................. 4.6-3 4.6.5 Flood Accident............................................................................................. 4.6-5 4.6.6 Maximum Pressure....................................................................................... 4.6-5 ANUH-01.0150 Xl

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 4.6.7 Evaluation of System Performance for Accident Conditions of Storage and Transfer *****************************************:****************************************** 4.6-5 4.7 Thermal Evaluation for Loading/Unloading Conditions.................................... 4.7-1 4.7.1 Vacuum Drying Thermal Analysis............................................................... 4.7-1

4. 7.2 Pressure During Unloading of Cask............................................................. 4. 7-2 4.7.3 Cask Heatup Analysis.................................................................................. 4.7-2 4.7.4 Pressure During Loading of Cask................................................................ 4.7-3 I

4.8 Supplemental Information..................................................................................... 4.8-1 4.8.1 References.................................................................................................... 4.8-1 4.8.2 Computer Code............................................................................................. 4.8-3 4.8.3 Validation of the Thermal Analysis Methodology Using

.HEATING? Model for 24PT1-DSC Basket................................................ 4.8-3 4.8.4 Alternative Confirmatory Thermal Analysis of the 24PT1-DSC.................. 4.8-5

5.

SHIELDING EVALUATION............................................................................................ 5-1 5.1 Discussion and Results........................................................................................... 5.1-1 5.2 Source Specification............................................................................................... 5.2-1 5.2.1 Gamma Sources............................................................................................ 5.2-3 5.2.2 Neutron Source............................................................................................. 5.2-4 5.2.3 Evaluation of Effect of Uncertainty in Minimum Initial Enrichment.......... 5.2-4 5.3 Model Specification................................................................................................ 5.3-1 5.3.1 Description of the Radial and Axial Shielding Configurations.................... 5.3-1 5.3.2 Shield Regional Densities............................................................................ 5.3-3 5.4 Shielding Evaluation.............................................................................................. 5.4-1 5.4.1 Computer Programs...................................................................................... 5.4-1 5.4.2 Flux-to-Dose-Rate Conversion........... :......................................................... 5.4-2 5.5 Supplemental Information..................................................................................... 5.5-1 5.5.1 References........,........................................................................................... 5.5-1 5.5.2 Validation of Shielding Analysis................................................................. 5.5-2

6.

CRITICALITY EVALUATION.................................................................................... 6.1-1 6.1 Discussion and Results........................................................................................... 6.1-2 6.2 Spent Fuel Loading........................................... :.................................................... 6.2-1 6.2.1 WE 14x14 SC Fuel Assemblies................................................................... 6.2-1 6.2.2 WE 14x14 MOX Fuel Assemblies............................................................... 6.2-1 6.3 Model Specification................................................................................................. 6.3-1 6.3.1 Description of Criticality Analysis Model................................................... 6.3-1 ANUH-01.0150 xii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 6.3.2 Neutron Absorber Panel Material Efficacy.................................................. 6.3-6 6.4 Criticality Calculation............................................................................................ 6.4-1 6.4.1 Calculational Method..........,........................................................................ 6.4-1 6.4.2 Fuel Loading Optimization.......................................................................... 6.4-1 6.4.3 Criticality Results........................................................................................'. 6.4-4 6.4.4 Evaluation of Effect of Uncertainty in Maximum Initial Enrichment......... 6.4-5 6.4.5 Effect of Fuel Parameter Tolerances on Reactivity...................................... 6.4-5 6.5 Critical Benchmark Experiments......................................................................... 6.5-1 6.5.1 Benchmark Experiments and Applicability................................................. 6.5-1 6.5.2 Results of the Benchmark Calculations........................................................ 6.5-2 6.6 Supplemental Information..................................................................................... 6.6-1 6.6. l References.................................................................................................... 6.6-1 6.6.2 KENO Input Files......................................................................................... 6.6-2

7.

CONFINEMENT............................................................................................................. 7.1-1 7.1 Confinement Boundary.......................................................................................... 7.1-1 7.1.1 Confinement Vessel..................................................................................... 7.1-1 7.1.2 Confinement Penetrations.......................................................................... -.. 7.1-2 7.1.3 Seals and Welds............................................................................................ 7.1-2 7.1.4 Closure.......................................................................................................... 7.1-2 7.1.5 Leak Testing Requirements.......................................................................... 7.1-2 7.2 Requirements for Normal Conditions of Storage................................................ 7.2-1 7.2.1 Release of Radioactive Material.................................................................. 7.2-1 7.2.2 Pressurization of Confinement Vessel......................................................... 7.2-1 7.3 Confinement Requirements for Hypothetical Accident Conditions.................. 7.3-1 7.3.1 Fission Gas Products.................................................................................... 7.3-1 7.3.2 Release of Contents...................................................................................... 7.3-1 7.4 Supplemental Data................................................................................................. 7.4-1 7.4.1 Confinement Monitoring Capability............................................................ 7.4-1 7.4.2 References.................................................................................................... 7.4-1

8.

OPERATING PROCEDURES......................................................................................... 8-1 8.1 Procedures for Loading the 24PT1-DSC and Transfer to the AHSM.............. 8.1-1 8.1.1 Narrative Description.............. :........... :........................................................ 8.1-1 8.2 Procedures for Unloading the 24PT1-DSC.................... :..................................... 8.2-1 8.2.1 24PT1-DSC Retrieval from the AHSM....................................................... 8.2-1 8.2.2 Removal of Fuel from the 24PT1-DSC........................................................ 8.2-2 ANUH-01.0150 xiii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 8.3 Supplemental Information..................................................................................... 8.3-1 8.3.1 Other Operating Systems.............................................................................. 8.3-1 8.3.2 Operation Support System............................................................................ 8.3-1 8.3.3 Control Room and/or Control Areas............................................................ 8.3-1 8.3.4 Analytical Sampling..................................................................................... 8.3-1 8.3.5 References.................................................................................................... 8.3-1

9.

ACCEPTANCE TESTS AND MAINTENANCE PROGRAM................................... 9.1-1 9.1 Acceptance Criteria................................................................................................ 9.1.. 1 9.1.1 Visual Inspection*.......................................................................................... 9.1-1 9.1.2 Structural...................................................................................................... 9.1-1 9.1.3 Leak Tests and Hydrostatic Pressure Tests.................................................. 9.1-2 9.1.4 Components.................................................................................................. 9.1-2 9.1.5 Shielding Integrity........................................................................................ 9.1-3 9.1.6 Thermal Acceptance.................................... :................................................ 9.1-3 9.1.7 Neutron Absorber Tests................................................................................ 9.1-3 9.2 Pre-Operational Testing and Maintenance Program......................................... 9.2-1 9.2.1 Subsystems Maintenance............................................................................. 9.2-1 9.2.2 Valves, Rupture Discs, and Gaskets on Confinement Vessel...................... 9.2-4 9.3 Training Program................................................................................................... 9.3-1 9.3.1 Program Description...................................................................................... 9.3-1 9.3.2 Retraining Program...................................................................................... 9.3-1 9.3.3 Administration and Records......................................................................... 9.3-2 9.4 Supplemental Information..................................................................................... 9.4-1 9.4.1 References.................................................................................................... 9.4-1

10. RADIATION PROTECTION..................................................................................... 10.1-1 10.1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)...................................................................... 10.1-1 10.1.1 Policy Considerations............................................................................ 10.1-1 10.1.2 Design Considerations........................................................................... 10.1-1 10.1.3 Operational Considerations.................................................................... 10.1-3 10.2 Radiation Protection Design Features................................................................ 10.2-1 10.2.1 Advanced NUHOMS System Design Features................................... 10.2-1 10.2.2 10.2.3 10.2.4 ANUH-01.0150 Radiation Dose Rates....................................... :..................................... 10.2-1 AHSM Dose Rates................................................................................. 10.2-4 ISFSI Array............................................................................................ 10.2-4 XIV

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 10.3 Estimated Onsite Collective Dose Assessment................................................... 10.3-1 10.3.1 Occupational Exposures........................................................................ 10.3-1 10.3.2 Public Exposure..................................................................................... 10.3-2 10.4 Supplemental Information................................................................................... 10.4-1 10.4.1 References.............................................................................................. 10.4-1

11. ACCIDENT ANALYSES................................................................................................ 11-1 11.1 Off-Normal Operations*******************************************************************:******************** 11.1-1 11.1.1 Off-Normal Transfer Loads................................................................... 11.1-1 11.1.2 Extreme Ambient Temperatures............................................................ 11.1-2 11.1.3 Radiological Impact from Off-Normal Operations................................ 11.1-3 11.2 Postulated Accidents............................................................................................ 11.2-1 11.2.1 Earthquake............................................................................................. 11.2-2 11.2.2 Tornado Wind Pressure and Tornado Missiles....................... *............. 11.2-11 11.2.3 Flood........-............................................................................................ 11.2-21 11.2.4 Fire/Explosion...................................................................................... 11.2-23 11.2.5 Accidental Drop of the 24PT1-DSC Inside the Transfer Cask............ 11.2-24 11.2.6 Lightning.............................................................................................. 11.2-27 11.2.7 Blockage of Air Inlet and Outlet Openings......................................... 11.2-28 11.2.8 Accidental Pressurization of the 24PT1-DSC..................................... 11.2-28 11.2.9 Burial........................ *........................................................................... 11.2-29 11.2.10 Inadvertent Loading of a Newly Discharged Fuel Assembly.............. 11.2-29 11.3 Supplemental Information................................................................................... 11.3-l.

11.3.1 References.............................................................................................. 11.3-1

12. OPERATING CONTROLS AND LIMITS................................................................... 12-1 12.1.0 Technical Specifications..................................................... :..................... 12-1 12.2.0 Functional and Operating Limits.............................................................. 12-4 12.3.0 Limiting Condition for Operation (LCO) and Surveillance

• Requirements (SR) Applicability.............................................................. 12~5 12.3.0 Surveillance Requirement (SR) Applicability.......................................... 12-8

13. QUALITY ASSURANCE................................................................................................ 13-1 13.1 Introduction.......................................................................................................... 13.1-1 13.2 "Important-to-Safety & "Safety Related" Advanced NUHOMS System Components.......................................................................................................... 13.2-1 13.3 Description of TN 10 CFR 72, Subpart G QAProgram................................... 13.3-l 13.3.1 Project Organization.............................................................................. 13.3-1 13.3.2 QA Program........................................................................................... 13.3-1 ANUH-01.0150 xv

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 13.3.3 Design Control....................................................................................... 13.3-1 13.3.4 Procurement Document Control............................................................ 13.3-2 13.3.5 Procedures, Instructions, and Drawings................................................ 13.3-2 13.3.6 Document Control.................................................................................. 13.3-2 13.3.7 Control of Purchased Items and Services.............................................. 13.3-2 13.3.8 Identification and Control of Materials, Parts, and Components.......... 13.3-3 13.3.9 Control of Special Processes.................................................................. 13.3-3 13.3.10 Inspection............................................................................................... 13.3-3 13.3.11 Test Control............................................................................................ 13.3-3 13.3.12 Control of Measuring and Test Equipment............................................ 13.3-3 13.3.13 Handling, Storage and Shipping............................................................ 13.3-3 13.3.14 Inspection and Test Status..................................................................... 13.3-4 13.3.15 Control of Nonconforming Items........................................................... 13.3-4 13.3.16 Corrective Action................................................................................... 13.3-4 13.3.17 Records.................................................................................................. 13.3'-4 13.3.18 Audits and Surveillances...................................................... :................ 13.3-4 13.4 Conditions of Approval Records......................................................................... 13.4-1 13.5 Supplemental Information................................................................................... 13.5-l 13.5.1 References.............................................................................................. 13.5-1

14. DECOMMISSIONING................................................................................................. 14.1-1 14.1 Decommissioning Considerations....................................................................... 14.1-1 14.2 Supplemental Informational.................................,............................................. 14.2-1 14.2.1 References.............................................................................................. 14.2-1 APPENDIX A APPENDIXB ANUH-01.0150 (24PT4-DSC) See Separate Table of Contents in Appendix A (32PTH2 DSC and AHSM-HS) See Separate Table of Contents in AppendixB XVI

Advanced NUHOMS System Updated Final Safety"Analysis Report Rev. 8, 08/18 I LIST OF TABLES Table 1.2-1 Key Design Parameters of the Advanced NUHOMS System Components................................................................................................... 1.2-9 Table 1.2-2 Known Fabricated NUHOMS Transfer Casks Licensed for Use Under CoC 1029.......................................................................................... 1.2-9a Table 2.1-1 Spent Fuel Assembly Physical Characteristics.............................................. 2.1-4 Table 2.1-2 Spent Fuel Assembly Thermal and Radiological Characteristics.................. 2.1-5 Table 2.1-3 Non-Fuel Assembly Hardware Thermal and Radiological Characteristics................................................................................................ 2.1-6 Table 2.5-1 Advanced NUHOMS System Major Components and Safety Classification................................................................................................. 2.5-3 Table 3.1-1 Codes and Standards for the Fabrication and Construction of Principal Components.................................................................................. 3.1-14 Table 3.1-2 Summary of Stress Criteria for Components Evaluated Using Subsection NB............................................................................................. 3.1-15 Table 3.1-3 Stress Criteria for Partial Penetration Pressure Boundary Welds................ 3.1-16 Table 3.1-4 Summary of Stress Criteria for Components Evaluated Using Subsection NG............................................................................................. 3.1-17 Table 3.1-5 Table 3.1-6 24PT1-DSC Load Combinations and Service Levels.................................. 3.1-18 24PT1-DSC Internal Pressure Loads........................................................... 3.1-20 Table 3.1-7 24PT1-DSC External Pressure Loads.......................................................... 3.1-21 Table 3.1-8 24PT1-DSC Thermal Conditions................................................................. 3.1-22 Table 3.1-9 AHSM Ultimate Strength Reduction Factors.............................................. 3.1-23 Table 3.1-10 Concrete Structure-Load Combinations.................................................... 3.1-24 Table3.l-11 Steel Structures Allowable Stress Design - Load Combinations................ 3.1-25 Table 3.1-12 Structural Design Criteria for DSC Support Structure................................ 3.1-26 Table 3.1-13 Overturning and Sliding - Load Combinations............................................ 3.1-27 Table 3.1-14 ASME Code Exceptions for the 24PT1-DSC (NB)..................................... 3.1-28 Table 3.1-15 ASME Code Exceptions for the 24PT1-DSC (NG/NF).............................. 3.1-29 Table 3.2-1 Weights and Centers of Gravity of the 24PT1-DSC...................................... 3.2-2 Table 3.3-1 ASME Code Material Properties for SA-240 Type 316 Stainless Steel........ 3.3~3 Table 3.3-2 Material Properties for ASTM A36 Carbon Steel......................................... 3.3-4 Table 3.3-3 ASME Code Material Properties for SA-240 Type 304 Stainless Steel........ 3.3-5 Table 3.3-4 ASME Code Material Properties for SA-537 Class 2 Carbon Steel.............. 3.3-6 Table 3.3-5 ASME Code Material Properties for SA-564 Type 630 Steel....................... 3.3-7 Table 3.3-6 Concrete Material Properties at Temperature................................................ 3.3-8 Table 3.3-7 Reinforcing Steel Material Properties at Temperature.................................. 3.3-9 ANUH-01.0150 xvii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table 3.5-1 Table 3.5-2 Table 3.5-3 Table 3.5-4 Table 3.5-5 Table 3.5-6 Table 3.6-1 Table 3.6-2 Table 3.6-3 Table 3.6-4 Table 3.6-5 Table 3.6-6 Table 3.6-7 Table 3.6-8 Table 3.6-9 Table 3.6-10 Table 3.6-11 Table 3.6-12 Table 3.6-13 Table 3.6-14 Table 3.6-15 Table 3.6-16 Table 3.6-17 Table 3.6-18 Table 3.6-19 Table 3.6-20 Table 3.6-21 Table 4.1-1 Table 4.1-2 ANUH-01.0150 Fuel Rod Parameters Used to Determine Fuel Cladding Short and Long Term Temperature Limits..................................................................... 3.5-6 Fuel Cladding Temperature Limits................................................................ 3.5-7 Summary of Fuel Assembly Thermal and Irradiation Growth Calculations................................................................................................... 3.5-8 Fuel Assembly Properties.............................................................................. 3.5-9 Fuel Cladding Material Properties............................................................... 3.5-10 Fuel Assembly Loads.................................................................................. 3.5-11 24PT1-DSC On-Site Load Combinations.................................................... 3.6-20 24PT1-DSC Shell Assembly Normal and Off-Normal Operating Condition Maximum Stress Intensities........................................................ 3.6-22 24PT1-DSC Shell Assembly Accident Condition Maximum Stress Intensities..................................................................................................... 3.6-23 24PT1-DSC Shell Assembly Results for Normal and Off-Normal Load Combinations...................................................................................... 3.6-24 24PT1-DSC Shell Assembly Results for Accident Level C Load Combinations............................................................................................... 3.6-25 24PT1-DSC Shell Assembly Results for Accident Level D Load Combinations............................................................................................... 3.6-26 Summary of Spacer Disc Maximum Stress Ratios...................................... 3.6-27 Summary of Guidesleeve Assembly Maximum Stress Ratios.................... 3.6-28 Summary of Results for Support Rod Assemblies...................................... 3.6-29 Summary of AHSM Design Loading.......................................................... 3.6-30 Design Pressures for Tornado Wind Loading.............................................. 3.6-31 AHSM Concrete Load Combinations.......................................................... 3.6-32 AHSM Support Steel Structure Load Combinations................................... 3.6-33 Ultimate Capacities of Concrete Components............................................. 3.6-34 Comparison of Highest Combined Shear Forces/Moments with the Capacities..................................................................................................... 3.6-35 Maximum/Minimum Forces/Moments in the Rail Components in the Local System................................................................................................ 3.6-37 Maximum/Minimum Forces/Moments in the Rail Extension Plates in the Local System.......................................................................................... 3.6-38 Maximum/Minimum Axial Forces in the Cross Member Components...... 3.6-39 Rail Component, Results of Evaluation....................................................... 3.6-40 Extension Plates and Cross Members, Results of Evaluation..................... 3.6-41 Computed Forces and Capacities of Ties and Keys.................................... 3.6-42 Ambient Temperatures and Insolations Considered in Thermal Analysis......................... ;............................................. '.................................. 4.1-3 Temperature Variation for Extreme Summer Ambient Conditions............... 4.1-4 xvm

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Table 4.1-3 Table 4.1-4 Table 4.1-5 Table 4.1-6 Table 4.4-1 Table 4.4-2 Table 4.4-3 Table 4.4-4 Table 4.4-5,

Table 4.4-6 Table 4.4-7 Table 4.4-8 Table 4.4-9 Table 4.4-10 Table 4.4-11 Table 4.4-12 Table 4.7-1 Table 4.7-2 Table 4.7-3 Table 4.8-1 Table 4.8-2 Table 4.8-3 Table 5.1-1 Table 5.1-2 Table 5.1-3 Table 5.1-4 Table 5.1-5 ANUH-01.0150 Component Minimum and Maximum Temperatures in the Advanced NUHOMS System (Storage or Transfer Mode) for Normal Conditions...................................................................................................... 4.1-5 Component Minimum and Maximum Temperatures in the Advanced NUHOMS System (Storage or Transfer Mode) for Off-Normal Conditions...................................................................................................... 4.1-6 Component Minimum and Maximum Temperatures in the Advanced NUHOMS System (Storage and Transfer) for Accident Conditions..........4.1-7 Limiting Canister Heat Loads for DSC Components.................................... 4.1-8 Advanced NUHOMS System Bulk Air Temperatures.............................. 4.4-15 Heat Generations Used in the Thermal Model of the 24PT1-DSC in the AHSM.................................................................................................... 4.4-16 AHSM Thermal Analysis Results Summary............................................... 4.4-17 24PT1-DSC Shell Results, 16 and 14 kW at Hottest Cross Section............ 4.4-18 24PT1-DSC Maximum Shell Temperatures at 24 kW................................ 4.4-19 24PT1-DSC Basket Temperature Results.................................................... 4.4-20 Maximum Fuel Cladding Temperature Results, 16 kW.............................. 4.4-21 Summary of Cases Considered for Thermal Stress Analysis...................... 4.4-22 Fuel Assembly Characteristics for Pressure Analysis................................. 4.4-23 Control Component Characteristics for Pressure Analysis.......................... 4.4-24 24PT1-DSC Cavity Pressure Analysis Summary........................................ 4.4-25 Technical Specifications 5.2.5.b Temperature Monitoring Limits for the 24 PTl-DSC............. *............................................................................. 4. 4-25a Steady State Vacuum Drying Results............................................................ 4. 7-4 Transient Vacuum Drying Results for the Spacer Disc................................. 4.7-5 Summary of Water Heatup Calculation......................................................... 4.7-6 Comparison of DSC Component Temperatures for NUHOMS-7P, Test Measurements vs Calculated from Appendix B of Reference [4.17]............ 4.8-4 Comparison of24PT1-DSC Component Temperatures, UFSAR Analysis vs. Confirmatory Analysis with Internal Convection..................... 4.8-7 Comparison of DSC Component Temperatures for NUHOMS-7P, Test Measurements vs. Confirmatory Analysis............................................. 4.8-7 Advanced NUHOMS System Shielding Materials...................................... 5.1-2 Summary AHSM Dose Rates........................................................................ 5.1-3 Transfer Cask (Loading/Unloading/Transfer Operations) Side Dose Rate Summary................................................................................................ 5.1-4 Transfer Cask (Loading/Unloading/Transfer Operations) Top End Dose Rate Summary...................................................................................... 5.1-5 Transfer Cask (Loading/Unloading/Transfer Operations) Bottom End Dose Rate Summary....................................................................................... 5.1-6 XIX

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Table 5.2-1 Flux Factor By Fuel Assembly Region.......................................................... 5.2-6 Table 5.2-2 WE 14x14 SC Assembly Materials and Masses............................................ 5.2-7 Table 5.2-3 Table 5.2-4 Table 5.2-5 Table 5.2-6 Table 5.2-7 Table 5.2-8 Table 5.2-9 Table 5.2-10 Table 5.2-11 Table 5.2-12 Table 5.2-13 WE 14x14 MOX Assembly Materials and Masses....................................... 5.2-8 Thimble Plug Assemblies Materials and Masses.......................................... 5.2-9 RCCA Materials and Masses....................................................................... 5.2-10 Neutron Source Assembly Materials and Masses........................................ 5.2-11 CASK-81 Neutron and Gamma Group Structure........................................ 5.2-12 SAS2H Gamma Sources for 45 GW d/MTU, 10-Year Cooled WE 14x14 SC Fuel Per Fuel Assembly.............................................................. 5.2-13 SAS2H Gamma Sources for 40 GWd/MTU, 10-Year Cooled WE 14x14 SC Fuel Per Fuel Assembly.............................................................. 5.2-14 SAS2H Gamma Sources for 35 GWd/MTU, 10-Year Cooled WE 14x14 SC Fuel Per Fuel Assembly.............................................................. 5.2-15 SAS2H Gamma Sources for 25 GWd/MTU, 20-Year Cooled WE 14x14 MOX Fuel Per Fuel Assembly.......................................................... 5.2-16 Gamma Source Term for Thimble Assembly, Eleven Cycles Active Fuel, 10 Year Cooled Per Assembly............................................................ 5.2-17 Gamma Source Term for RCCA, Eleven Cycles Active Fuel, 10 Year Cooled Per Assembly................................................................................... 5.2-18 Table 5.2-14 Gamma Source Term for Neutron Source Assemblies, Four Cycles Table 5.2-15 Table 5.2-16 Table 5.2-17 Table 5.2-18 Table 5.2-19 Table 5.3-1 Table 5.3-2 Table 5.3-3 Table 5.3-4 Table 5.4-1 Table 5.5-1 Table 5.5-2 Table 5.5-3 ANUH-01.0150 Active Fuel, 10 Year Cooled Per Assembly................................................ 5.2-19 Design Basis Volumetric Gamma Source Terms........................................ 5.2-20 Calculated Total Neutron Sources per Fuel Assembly................................ 5.2-21 Design Basis Volumetric Neutron Source Term......................................... 5.2-22 Elemental Composition of L WR Structural Materials................................ 5.2-23 Comparison of Design Basis Shielding Analysis Source Term to Fuel Qualification Table Source Terms............................................................... 5.2-24 Materials Composition and Atom.Number Densities.................................... 5.3-5 Density Calculations for Concrete................................................................. 5.3-6 Materials Composition and Atom Densities During Decontamination and Wet Welding Stage Calculation.............................................................. 5.3-7 ANSI Standard-6.1.1-1977 Flux-to-Dos~ Factors************************************:**** 5.3-8 Normalized Conservative Bum-Up Shape on WE 14x14 Fuel Assembly........................................................................................................ 5.4-3 Comparison of DORT and MCNP Maximum and Averaged Dose Rate Values on Surfaces of AHSM............................................................... 5.5-2 Comparison of Calculated MCNP Dose Rates Verses Measured Dose Rates - No. 1 HSM........................................................................................ 5.5-3 Comparison of Calculated MCNP Dose Rates Verses Measured Dose Rates - No. 2 HSM........................................................................................ 5.5-3 xx

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Table 6.1-1 Table 6.2-1 Table 6.2-2 Table 6.3-1 Table 6.3-2 Table 6.3-3 Table 6.4-1 Table 6.4-2 Table 6.4-3 Table 6.4-4 Table 6.4-5 Table 6.4-6 Table 6.4-7 Table 6.5-1 Table 6.5-2 Table 6.5-3 Jable 6.5-4 Summary of Limiting Criticality Evaluations for the WE 14x14 SC Fuel Assemblies and the WE MOX Fuel Assemblies................................... 6.1-4 Design Parameters for Criticality Analysis of the WE 14x14 SC Fuel Assemblies..................................................................................................... 6.2-2 Design Parameters for Criticality Analysis of the WE 14x14 MOX Fuel Assemblies............................................................................................. 6.2-3 Geometrical Parameters Used in the Criticality Analysis............................. 6.3-8 Design Parameters for WE 14x14 SC Fuel Assembly Criticality Analysis....................................................................................................... 6.3-11 Design Parameters for WE 14x14 MOX Fuel Assembly Criticality Analysis....................................................................................................... 6.3-12 Results for the WE 14x14 SC Fuel Assembly............................................... 6.4-6 Results for the WE 14x14 MOX Fuel Assembly........................................... 6.4-9 Results for the Damaged Fuel Assemblies.................................................. 6.4-12 Bounding Criticality Analysis Analyzed for 4.05 weight% U-235............ 6.4-14 Clad OD Sensitivity Evaluation................................................................... 6.4-14 Clad Thickness Sensitivity Evaluation........................................................ 6.4-15 Pellet Diameter Sensitivity Evaluation........................................................ 6.4-15 Benchmark Results........................................................................................ 6.5-3 USL-1 Results................................................................................................ 6.5-6 Fuel Assembly Design Parameters Used in Criticality Benchmarks............. 6.5-7 Limiting Upper Subcritical Limit Based on Method 1 for the WE 14x14 SC Fuel Assemblies and the WE 14x14 MOX Fuel Assemblies....... 6.5-8 Table 8.1-1 Instrumentation Used During Advanced NUHOMS System Loading Operations.................................................................................................... 8.1-11 Table 10.2-1 Dose Rates at Postulated Site Boundary from One AHSM..............,.......... 10.2-6 Table 10.2-2 Dose Rates at Postulated Site Boundary from One AHSM......................... 10.2-7 Table 10.2-3 Dose Rates at Postulated Site Boundary from a Single AHSM.................. 10.2-8 Table 10.2-4 Dose Rates at Postulated Site Boundary from a 2x10 Array of AHSMs.....................................................,.................................................. 10.2-9 Table 10.2-5 Dose Rates at Postulated Site Boundary from a 2xl O Array Of AHSMs.................................................................... ;................................. 10.2-10 Table 10.2-6 AHSM Gamma-Ray Spectrum Calculation Results.................................. 10.2-11 Table 10.2-7 AHSM Neutron Spectrum Calculations.................................................... 10.2-12 Table 10.2-8 Summary of AHSM Surface Activities..................................................... 10.2-13 Table 10.2-9 ANISN Model Details............................................................................... 10.2-14 Table 10.3-1 Advanced NUHOMS System Operations Estimated Time for Occupational Dose Calculations.................................................................. 10.3-4 Table 11.2-1 Postulated Accident Loading Identification.............................................. 11.2-32 Table 11.2-2 Summary of AHSM Sliding/Uplift Displacements................................... 11.2-33 ANUH-01.0150 XXl

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Table 12-1 Cross-Reference Index of 24PT1 System Technical Specifications vs.

Historical UFSAR References........................................................................ 12-2 Table 13.1-1 Matrix of 10 CFR72 Subpart G Criteria v/s TN QA Manual Implementing Sections................................................................................. 13.1-2 ANUH-01.0150 XXll

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I LIST OF FIGURES Page Figure 1.1-1 Advanced NUHOMS System Horizontal Storage Module......................... 1.1-3 Figure 1.1-2 Advanced NUHOMS System 24PT1-DSC................. '................................ 1.1-4 Figure 1.2-1 Advanced NUHOMS System Components, Structures, and Transfer Equipment - Elevation View (Typical)....................................................... 1.2-10 Figure 1.2-2 Advanced NUHOMS System Components, Structures, and Transfer Equipment - Plan View (Typical)............................................................... 1.2-11 Figure 1.2-3 24PT1-DSC ASME Code Boundaries......................................................... 1.2-12 Figure 1.4-1 Typical Double Module Row Advanced NUHOMS System ISFSI Layout............................................................................................................ 1.4-2 Figure 1.4-2 Typical Single Module Row Advanced NUHOMS System ISFSI Layout............................................................................................................ 1.4-3 Figure 1.4-3 Typical Combined Single and Double Module Row Advanced NUHOMS System ISFSI Layout..... ;........................................................... 1.4-4 Figure 2.2-1 AHSM Base Input Horizontal Response Spectra for 1.5 g ZP A.................... 2.2-8 Figure 2.2-2 AHSM Base Input Vertical Response Spectra for 1.0g ZP A........................ 2.2-9 Figure 3.1-1 Advanced NUHOMS System 24PT1-DSC Canister Shell Assembly....... 3.1-30 Figure 3.1-2 24PT1-DSC Pressure Boundary Location................................................... 3.1-31 Figure 3.1-3 Advanced NUHOMS System 24PT1-DSC Canister Basket (Side View)............................................................................................................ 3.1-32 Figure 3.1-4 Advanced NUHOMS System 24PT1-DSC Canister Basket & Shell (Side and End View).................................................................................... 3.1-33 Figure 3.1-5 Prefabricated AHSM -- Longitudinal Section............................................ '. 3.1-34 Figure 3.1-6 Prefabricated AHSM -- Cross Section......................................................... 3.1-35 Figure 3.1-7 Shop Fabricated 24PT1-DSC Support Structure......................................... 3.1-36 Figure 3.2-1 Schematic Location of Center of Gravity of the 24PT1-DSC....................... 3.2-3 Figure 3.2-2 Schematic Location of Center of Gravity of the 24PT1-DSC in the AHSM............................................................................................................ 3.2-4 Figure 3.6-1 24PT1-DSC Shell Assembly Top End 90° ANSYS Model......................... 3.6-43 Figure 3.6-2 24PT1-DSC Shell Assembly Bottom End 90° ANSYS Model................... 3.6-44 Figure 3.6-3 24PT1-DSC Load Support for Shell and Spacer Disc Analyses................. 3.6-45 Figure 3.6-4 24PT1-DSC Spacer Disc Side Drop ANSYS Model (Half Symmetry)...... 3.6-46 Figure 3.6-5 24PT1-DSC Spacer Disc Side Drop ANSYS Model (Full Symmetry)....... 3.6-47 Figure 3.6-6 24PT1-DSC Spacer Disc ANSYS Model for Axial Loads (Quarter Symmetry).................................................................................................... 3.6-48 Figure 3.6-7 ANSYS Model of the AHSM...................................................................... 3.6-49 Figure 3.6-8 ANSYS Model of the DSC and the DSC Support Structure....................... 3.6-50 ANUH-01.0150 XXlll

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Figure 3.6-9 Figure 3.6-10 Figure 3.6-11 Figure 3.6-12 Figure 3.6-13 Figure 3.6-14 Figure 3.6-15 Figure 4.4-1 Figure 4.4-2 Figure 4.4-3 Figure 4.4-4 Figure 4.4-5 Figure 4.4-6 Figure 4.4-7 Figure 4.4-8 Figure 4.6-1 Figure 4. 7-1 Figure 4.7-2 Figure 4.8-1 Figure 4.8-2 Figure 4.8-3 Figure 5.1-1 Figure 5.1-2 Figure 5.1-3 Figure 5.1-4 Figure 5.4-1 Figure 5.4-2 Figure 5.4-3 Figure 5.4-4 Figure 5.4-5 Figure 5.4-6 Figure 5.4-7 Figure 5.4-8 ANUH-01.0150 ANSYS Model of the AHSM Base Storage Block for Thermal Stress Analysis....................................................................................................... 3.6-51 ANSYS Model of the AHSM Top Shield Block for Thermal Stress Analysis....................................................................................................... 3.6-52 Concrete Components in the Lower Base Storage Block............................ 3.6-53 Concrete Components in the Upper Base Storage Block............................ 3.6-54 Concrete Components in the Top Shield Block........................................... 3.6-55 Symbolic Notations of Force and Moment Capacities (Also for Computed Forces and Moments)................................................................. 3.6-56 Components of AHSM Support Structure................................................... 3.6-57 Illustration of Air Flow Paths through AHSM............................................ 4.4-26 AHSM HEA TING7 Model; Cross Section Along x=O.O............................ 4.4-27 Details 1, 2 and 3 From AHSM HEATING? Model................................... 4.4-28 Sections A-A and B-B From AHSM HEATING? Model........................... 4.4-29 AHSM HEATING? Model; 24PT1-DSC and Heat Shield......................... 4.4-30 Cross Section of 24PT1-DSC Basket Model............................................... 4.4-31 24PT1-DSC Basket Model; Fuel Regions 1 and 2 with Surrounding Regions........................................................................................................ 4.4-32 Simplified Axial View of24PT1-DSC Basket Model................................. 4.4-33 OS 197 Cask and 24PT1-DSC Response to Fire Accident............................ 4.6-6 Vacuum Drying Transient Response of Spacer Disc..................................... 4.7-7 Results of the Water Heatup Calculations..................................................... 4.7-8 Comparison of Predicted SINDA/FLUINT' Temperatures to KHI Test Results.................................................................................................... 4.8-8

• Comparison of Predicted vs. Test Results (PNL-7327) for NUHOMS-7P..................................................................*............................ 4.8-9 General Flow Patterns Expected within Canister........................................ 4.8-10 Advanced NUHOMS System Shielding Configuration.............................. 5.I-7 Dry Shielded Canister Shielding Configuration............................................ 5.1-8 Right Elevation Cross Section View of AHSM............................................. 5.1-9 Shielding Configuration of the OS197 Transfer Cask................................. 5.1-10 NDORT R-Z Floor Model............................................................................. 5.4-4 DORT R-Z Roof Model................................................................................. 5.4-7 DORT X-Z Midplane Model....................................................................... 5.4-10 Zone Number by Material in TC Model at Transfer-Storage Stage............ 5.4-13 Zone Number by Material in TC Model at Decontamination Stage............ 5.4-17 Zone Number by Material in TC Model at Wet Welding Stage.................. 5.4-18 Zone Number by Material in TC Model at Dry Welding Stage.................. 5.4-19 AHSM Roof DORT Shielding Analysis Model.......................................... 5.4-20 XXIV

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Figure 5.4-9 Figure 5.4-10 Figure 5.4-11

• Figure 5.4-12 Figure 6.3-1 Figure 6.3-2 Figure 6.3-3 Figure 6.3-4 Figure 6.3-5 Figure 6.3-6 Figure 6.3-7 Figure 6.3-8 Figure 6.3-9 Figure 6.3-10 Figure 6.4-1 Figure 6.4-2

• Figure 6.4-3 Figure 7.1-1 Figure 8.1-1 Figure 8.1-2 Figure 8.2-1 Figure 10.2-1 Figure 10.2-2 Figure 11.2-1 Figure 11.2-2 Figure 11.2-3 Figure 11.2-4 Figure 11.2-5 Figure 11.2-6 Figure 11.2-7 Figure 11.2-8 Figure 11.2-9 AHSM Floor DORT Shielding Analysis Model.......................................... 5.4-21 AHSM Side DORT Shielding Analysis Model........................................... 5.4-22 AHSM Front/Back DORT Shielding Analysis Model................................ 5.4-23 OSI97 DORT Shielding Analysis Model.................................................... 5.4-24 KENO Model of the 24PT1-DSC Basket.................................................... 6.3-13 Exploded View of KENO Model................................................................. 6.3-14 Structure of KENO Model-UNIT 33........................................................ 6.3-15 Structure of KENO Model-UNIT 34........................................................ 6.3-16 Cross Section of the Design Basis WE 14x14 SC Fuel Assembly.............. 6.3-17 Cross Section of the Design Basis WE 14x14 MOX Fuel Assembly.......... 6.3-18 Guidesleeve and Fuel Assembly Cross Section........................... :..........,... 6.3-19 Fuel Assemblies Located in the Inner Guidesleeve Comer Closest to the DSC Centerline (Assembly in Case)...................................................... 6.3-20 The Fuel Assemblies Moved Radially Outwards from the Center of the DSC (As~embly Out Case).................................................................... 6.3-21 The Fuel Assemblies Are Moved Towards the Upper Left Comer of Each Guidesleeve Assembly Upper Left Comer Case................................ 6.3-22 Rod Pitch Study: Figure Shows Maximum Rod Pitch Allowed.................. 6.4-16 Single-Ended Rod Shear Example.............................................................. 6.4-17 Double-Ended Rod Shear Example............................................................ 6.4-18 24PT1-DSC Confinement Boundary Welds.................................................. 7.1-3 Advanced NUHOMS System Loading Operations Flow Chart......... :...... 8.1-12 Cask Loading Operations......................,...................................................... 8.1-15 Advanced NUHOMS System Retrievai Operations Flow Chart................. 8.2-7 Total Annual Exposure from a Single AHSM as a Function of Distance..................................................................................................... 10.2-15 Total Annual Exposure from a 2x10 AHSM Array as a Function of Distance..................................................................................................... 10.2-16 LS-DYNA AHSM Seismic Stability Model.............................................. 11.2-34 Horizontal Time History Hl, Set 1 (Taiwan, 1999).................................. 11.2-35 Horizontal Time History H2, Set 1 (Taiwan, 1999).................................. 11.2-36 Vertical Time History V, Set 1 (Taiwan 1999)......................................... 11.2-37 Horizontal Time History Hl, Set 2 (Tabas 1978)...................................... 11.2-38 Horizontal Time History H2, Set 2 (Tabas 1978)...................................... 11.2-39 Horizontal Time History V, Set 2 (Tabas 1978)........................................ 11.2-40 Horizontal Time History Hl, Set 3 (Landers/Lucem 1992)...................... 11.2-41 Horizontal Time History H2, Set 3 (Landers/Lucem 1992)...................... 11.2-42 Figure 11.2-10 Vertical Time History V, Set 3 (Landers/Lucem 1992)............................ 11.2-43 Figure 11.2-11 AHSM Sliding Response X-Direction....................................................... 11.2-44 ANUH-01.0150 XXV

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Figure 11.2-12 AHSM Sliding Response Y-Direction....................................................... 11.2-45 Figure 11.2-13 AHSM Uplift Response Z-Direction......................................................... 11.2-46 Figure 11.2-14 24PT1-DSC Stability Evaluation............................................................... 11.2-47 Figure 11.2-15 AHSM Dimension for Missile Impact Stability Analysis......................... 11.2-48 Figure 11.2-16 Analysis Case 2 (THl-2): AHSM Sliding Response X-Direction............ 11.2-49 Figure 11.2-17 Analysis Case 3 (TH2-1): AHSM Sliding Response X-Direction............ 11.2-50 Figure 11.2-18 Analysis Case 4 (TH2-2): AHSM Sliding Response X-Direction............ 11.2-51 Figure 13.1-1 Project Organization Chart.......................................................................... 13.1-3 ANUH-01.0150 XXVI

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Pa2e or descriotion Rev.

Title Page 8

i 8

ii 8

llI 7

iv

.. ;}!,, *.

8 lj:

V 8

vi 5

vii 5

viii 5

IX 8

X

."°:),.

. 8.. *. hi xi 8

xn

8.

xiii 8

XlV 8

xv 8

X\\'l

.* /{

s xvii 8

xviii 8

XlX 8

xx 8

XX!

8 xxii

'8

• • y.

xxiii 8

xxiv 8

XXV 8

xxvi 8

LOEP0 l

" ' ;,;v.

8 LOEP-2 8

LOEP-3 8

LOEP-4 8

.LOEP-5 8

LOEP-6 8

LOEP-7 8

• . /

LOEP-8 8

LOEP-9 8

LOEP-10 8

.LOEP-11 8

LOEP-12 8

",LOEP-13

. 8*..

LOEP-14 8

LOEP-15 8

LOEP-16 8

LOEP-17 8

LOEP-18 8

. :iibEJJ-19 8.. *.* ::::;'

LOEP-20 8

LOEP-21 8

LOEP-22 8

ANUH-01.0150 List Of Effective Pages Date Aue:ust 2018 08/18 08/18 08/16 08118..

08/18 08/12 08/12 08/12 08/18 0 08/18 08/18 08/18

• 08/18 08/18 08/18 08118' 08/18 08/18 08118 08/18 08/18 08//8 08/18 08/18.

08/18 08/18 08/18' 08/18 08/18 08/18 08/18 08118 08/18 08/18 08/18 08/18 08il8*

08/18

. 08/18 08/18 08/18 08/18 08/18 08/18 08/18.

08/18 08/18 08/18 Pa2e or description Rev.

Date 1-1 7

08/16 1-la

7.

08/16 1.1-1 5

08/12 1.1-2

.. 5

• 0:8/12 1.1-3 0

02/03 1.1-4"

~ '

0

.. 02/03 1.2-1 5

08/12 1.2-2 5

. 08/12 1.2-3 7

08/16 1.2-4

,./5 08/12

• 1.2-5 0

02/03

• 1.2-6'....

. 0

• . **.*.** 02/03 '.

1.2-7 2

08/06 1.2-8 5

08/12 1.2-9 5

08/12 1.2°9a

.;,']:

• ,; ;.. 08/16 1.2-10 0

02/03 1.2-11 0

02/03.

1.2-12 0

02/03 1.2-13

• 2 08/06 1.3-1 7

08/16 lAcI 5

08/12.

1.4-2 0

02/03

• 1.4°3 0

*, ' : 02/03 LOEP-1 1.4-4 0

02/03 1.5-1 8

08/18.

DWG: (sh. 1 of6) 61 7/18/18 NUH-05-4010 DWG:(sh,. ~of6)

01..

• Nofshown NUH-05:-4010 DWG: (sh. 3 of 6) 61 Not shown NUH-05-4010 DWG: (sh. 4 of 6)

,61 Not shown NUH-05.:4010 DWG: (sh. 5 of6) 61 Not shown NUH-05-4010 DWG: (sh. 6 of6) 61 Notshowri NUH-05-4010 DWG: (sh. 1 of9) 81 7/18/18 NUH-03-4011 DWG: (sh,.,,2 of9)

... ;,.1]1;

• • Not shown NUH,03'.:4011 DWG: (sh. 3 of 9) 81 Not shown NUH-03-4011 DWG: (sh. 4 of9)

. 81

.Not shown NUH-03°4011 DWG: (sh. 5 of9) 81 Not shown NUH-03-4011 1 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Pa!!:e or descriotion Rev.

Date Pa!!:e or description Rev.

Date

DWG: (sh. 6 of9) 81 Not shown 3.1-14 0

02/03

. NUH-03-4011 3.1-15 0

02/03 DWG: (sh. 7 of9) 81 Not shown 3.1-16 0

, 02/03 NUH-03-4011 3.1-17 0

02/03 f>WG: (sh. 8 o{9)

• Bl Not showni

'NUH-03"4011 I\\

3.U.8 jf:

. ft 02/03 3.1-19 0

02/03 DWG: (sh. 9 of 9) 81 Not shown 3.1 ~20 0

02/03 NUH-03-4011 3.1-21 0

02/03 3.1-22 5

08/12 2.1-1 7

08/16 3.1-23 0

02/03

• 2:J. 01a 7

08/16 3.1-24,;::

'";O

{,

\\02/03,

2.1-2 5

08/12 3.1-25 0

02/03 2.1-3 0

02/03 3.1-26 o*

02/03 2.1-4 5

08/12 3.1-27 0

02/03 2.1-5 5

08/12 3.1-28

.5 08/12 2.1-6 0

02/03 3.1-29 5

08/12

• J.l-30*>

• • ':O.

,>:;;, 02/0.3 i 2.2-1 5

08/12 3.1-31 2

08/06 2.. ~~2 0

02/03 3.1-32 0

',' 02/03 2.2-3 5

08/12 3.1-33 0

02/03

).2-4 0

02/03' 3.1-34 0

02/03 2.2-5 0

02/03 3.1-35 0

02/03 2'.2-6:

.o 02/03,:

,'\\

3.l~:36"'

+*'

0

> 02/03

2.2-7 0

02/03 3.2-1 0

02/03 2.2-8 0

02/03 2.2-9 0

02/03 3.2-2 5

08/12 3.2-3 0

02/03

. 2.3-l 0

02/03 3.2-4 0

02/03 2.3-2 2

08/06 3.3-1 5

08/12

,2::H 5

08/12 3.3,2 *..

,O.,

02/03 2.3-4 5

08/12 3.3-3 0

02/03

,2.3-5 0

02/03 3.3-4 b

02/03 2.3-6 I

03/05 3.3-5 0

02/03

• 2.4-1 5

08/12'*

D-6 Q

,02/03 2.5-1 5

08/12 3.3-7 0

02/03 2.5-2

5,,

08/1:t 33-8 \\*~

'O'..

" '02/03 '

2.5-3 8

08/18 3.3-9 0

02/03 2.6.:1 2

08/06 3.4-1 0

02/03 2.6-2 2

08/06 3.4-2 0

02/03 j.4~3

• • 2 08/06 3.1-1 7

08/16 3.4-4 0

02/03 u~2.

'\\

0 ':;

02/03, 3.4-5:*

,;(} ;

• ~02/()3 3.1-3 3

08/08 3.4-6 0

02/03 3:1-4, 0

02/03 3.5-1 5

08/12 3.1-5 5

08/12 3.5-2 0

02/03 3.1-6 2

08/06 3.5-3.

• o 02/03 3.1-7 5

08/12 3.5-4 0

02/03

'J.,h8:...

.,::/:

5 1 *., : :

08/12.

J;5°5,

,...... Q.,..., :*

'*'*\\/ ':,02/03 :

3.1-9 5

08/12 3.5-6 0

02/03

$.l-10 5

08/12 3.5-7 *

• o

• ',' 02/03 3.1-11 0

02/03 3.5-8 5

08/12 3.1-12 I

03/05 3.1-13 0

02/03 3.5~9 0

', 02/03 3.5-10 0

02/03 ANUH~Ol.0150 LOEP-2

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date 3.5-11 0

02/03

'3.6-52 0

02/03 3.6-1 5

08/12 3.6-53 0

02/03 3.6-2 0

02/03 3.6-54 0

02/03 3.6-3 0

02/03 3.6-55 0

02/03

,3..6-4 0

".(:::'

02103:

3:6-56 0 '

02/03 3.6-5 5

08/12 3.6-57 0

02/03 3.6;.6 0

02/03 3.6-58 2

08/06 3.6-7 5

08/12 3.6-59 5

08/12 3.6-8 0

02/03 3.6-60

'* 5.

08/12 3.6-9 5

08/12

3:6,10

'iC 5

l* :,,

• 08/12

~

4~l.

+::,

.1;7

. :,/i 08/16.

3.6-11 5

08/12 4.1-1 5

08/12 3.6-12 0

02/03 4.1-2 0

02/03 3.6-13 0

02/03 4.1-3 0

02/03 3.6-14 0

02/03 4.1-4 0

02/03 :

3.6-15 0

02/03 4.1-5 0

02/03

.3:6cl6 0

02/03 4.1.i.6 0

,;.,02/03 3.6-17 0

02/03 4.1-7 0

02/03 3.6-i8 0

02/03 4.1~8 0

02/03,

3.6-19 0

02/03 4.2-1 0

02/03 3.6-20 2

08/06,*

4.2-2 0

02/03 3.6-21 0

02/03 4.2-3 0

02/03 l3:6s22

/,0,:,,

0 02103:*

4.2:.4:, y,

.'.:jy

':':\\02/03' 3.6-23 0

02/03 4.2-5 0

02/03 3.6-24 0

02/03 3.6-25 0

02/03 4.2-6 5

08/12 '.

4.2-7 0

02/03

, 3;.6-26 0

02/03 4.3-1

• o 02/03 3.6-27 5

08/12 4.4-1 8

08/18 3},~28

.o 02103..

4.4-2

,,,()

' '(

• 0,2/03,*

3.6-29 0

02/03 4.4-3 5

08/12 3:6-30 5

08/12 4.4-4 0

02/03 3.6-31 0

02/03 4.4-5 0

02/03 3.6-32 0

02/03 4.4~6 8

.,08/18 3.6-33 0

02/03 4.4-6a 1

03/05 3.6~34 0

I\\,. }/.

. 02/03,'

4.4~ 7. '

8

i?: LQ8/]8

• 3.6-35 0

02/03 4.4-8 0

02/03 3.6-36 0

02/03 4.4-9 8

08/18 3.6-37 0

02/03 4.4-10 8

08/18 3:6<l8 1.'

03/05 4.4-11 i O

,,()2/03 3.6-39 0

02/03 4.4-12 0

02/03 3.6-40

o

\\";c

02/03 J

4.4-T3 : "'

"' :f

',? I.08/I2:

3.6-41 0

02/03 4.4-14 0

02/03

,3,6-42 5

08/12 4.4-15 0

02/03 3.6-43 0

02/03 4.4-16 0

02/03 3.6-44 0

02/03 4.4-i7

o

','*, 02/03 3.6-45 0

02/03 4.4-18 0

02/03

'3.6°46 0

' \\

y 02/()3 4.4-19 '* i

,; (),**,

,, .()2/()3,

3.6-47 0

02/03 4.4-20 0

02/03 3.6-48 0

02/03 4.4-21 0

02/03 3.6-49 0

02/03 4.4-22 0

02/03 3.6-50 0

02/03 3.6-51 0

02/03 4.4-23

.o 02/03 4.4-24 0

02/03 ANillI-01.0150 LOEP-3

Advan_ced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages 5.2-4 5

08/12 0

02/03 ANUH-01.0150 LOEP--4

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Pa2e or description Pa2e or description Rev.

Date Rev.

Date

• 6;5°1 2'

08/06:

6.4-18* :*..,,

",:0

,02703,

5.5-2 0

02/03 6.5-1 0

02/03 5.5~3

0.

02/03 6.5-2, ',

• o

.. 02/03

• 5.5-4 0

02/03 6.5-3 0

02/03

£/f.

}';.

',...... ;,}'

.*r.::

6.1-1 7

08/16 6.5-5 0

02/03 6.1-la 7

08/16

02/03

• 6.1-2 5

08/12 6.5-7 0

02/03 6~1,3*

0 02/03

',,, '* 02/03 6.1-4 0

02/03 6.6-1.

2 08/06

t6;,i~1* ' ','

,' /:, ; :

Oi *j.*;;*t.

'*021()3*,

6.2-2 0

02/03 6.6-3 0

02/03 6.2-3

'Y 0

02/0J

', 6.6-4.

• • • ,_. 02/03.*

6.3-1 5

08/12 6.6-5 0

02/03 6.3."2

'1,*

0

• 'a

. 02/03.

6;6-6,,

..,o*.

. 02/03 6.3-3 0

02/03 6.6-7 0

02/03

'16'::h{'

' ti J£. :- o*..

z;, ',,..,,

02/03.,

6.3-5 0

02/03 6.6-9 0

02/03

.6+6 0

02/03

• 6,6-10. ',,,

0

. 02/03.

6.3-7 0

02/03 6.6-11 0

02/03

.6.'.Hi.

0 02/03

• ' 02/03 :

6.3-9 0

02/03 6.6-13 0

02/03 6.3-10'

)ij:t:',

o*:".* 1i'."'.,r.**.****

i.02/03 6.3-11 0

02/03 6.6-15 0

02/03

'6.3-12 0

02/03 6.3-13 0

02/03

.6.6~16,' ;

02/03.

6.6-17 0

02/03 6'.3-14.

• O 02/0{

6.3-15 0

02/03 6.6-19 0

02/03

{'<ts:16

• • :-, '?

. O* <, '*j:J;'. *' 02/03,'

6.3-17 0

02/03 6.6-21 0

02/03

• 6'.3-18 0

02/03

• 02/03 6.3-19 0

02/03 6.6-23 0

02/03 J>.3.-20 0

02/03.

6.6-24'. *.. *

. o*

• '.02/03 6.3-21 0

02/03 6.6-25 0

02/03 6',3~22

,, *,,,,, :c':,;;1s;:

0..

.. I:,'.\\*'

02/03'1 6.4-1 0

02/03 6.6-27 0

02/03

" 6.4°2 0

02i03.

6.6~28*.

. ()2/03 0

6.4-3 0

02/03 6.6-29 0

02/03

,,(d:4.

0 02/03 6.4-5 0

02/03 6.6-31 0

02/03

>.ii;{'.6

• ,,::,*:*:t;\\::*.

0

• 02/03'.

,, n,.

6.4-7 0

02/03 6.6-33 0

02/03 6.4-8

.0 02/03 6.6-34 0.

02/03 6.4-9 0

02/03 6.6-35 0

02/03

6:'4-10 0

02/03:

6.6-36' * *, '

6.4-11 0

02/03 6.6-37 0

02/03

?6'.4-12 O' ' :,, /"'

1,',*r

'02103<

6.4-13 0

02/03 6.6-39 0

02/03 6'.4-14 5

08/12 6.6-40 * *'

• • • ,, 02/03 6.4-15 0

02/03 6.6-41 0

02/03

• 6.4-16 0

02/03 6.4-17 0

02/03 6.6-42,

,,._()2/03.

6.6-43 0

02/03 ANillI-01.0150 LOEP-5

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date

• 6.6-44

,0 02/03, 7.1-la

_7 08/16 6.6-45 0

02/03 7.1-2 5

08/12 6.6~46

? '

0 02/03 7.l-2a

• 5 08/12 6.6-47 0

02/03 7.1-3 0

02/03 6.6-48 0

02/03 7.2-1 2

08/06 6.6-49 0

02/03 7.3-1 2

08/06 6.6-50 0

02/03 7.4-1 2

08/06 6.6-51 0

02/03 6.6-52 0

02/03

. 8-1

},

08/16 '

6.6-53 0

02/03 8.1-1 1

03/05 6;6-'54.

0 02/03:

8.1-2

../~V*,'

08/12 6.6-55 0

02/03 8.1-3 5

08/12 6.6-56 0

02103:_

8.1-4

-*o-02/03 _,

6.6-57 0

02/03 8.1-5 1

03/05 6.6-58 0

02/03 8.1-6 5

08/12

• 6.6-59 0

02/03 8.1-7 5

08/12 6.6-60 0

02/03

• 8.1-8 3

08/08 6.6-61 0

02/03 8.1-9 08/08

.)

6.6-62 0

02/03 8.1-10 1

03/05 6.6-63 0

02/03 8.1-11 0

02/03 6.6-64 0

02/03, 8.ls12 ff, 02/03 6.6-65 0

02/03 8.1-13 2

08/06 6'6..:66 -

• c.

'i 0

< 02/03 8.1-14

', 2 08/06 6.6-67 0

02/03 8.1-15 0

02/03 6:6-68

- - i.. -'

0 01/03 6.6-69 0

02/03

- 8.1-16 0

- 02/03

• 8.2-1 5

08/12 6.6-70

• o

-02/03' 8.2-2 5

08/12 6.6-71 0

02/03 8.2-3 5

08/12 6.6-72 0

02/03 8.2-4 0

02/03 6.6-73 0

02/03 8.2-5 0

02/03 6.6-74 0

02/03 8.2-6 0

02/03 -

6.6-75 0

02/03 8.2-7 0

02/03 6.6-76

~,.,

0 02i03 8.2~8

,,0

_- 02/03 i 6.6-77 0

02/03 8.2-9 0

02/03 6.6-78 0

02103:;_

8.3-1

. 02103*

• _,,_,,0 6.6-79 0

02/03 6.6-80 o*

02/0f 9.1-1 f--

08/16

• 6.6-81 0

02/03 9.1-la 7

08/16 6.6-82 _

0 02/03, 9.1-2 2

08/06 6.6-83 0

02/03 9.1-3 0

02/03 6.6-84 0

02/03 9.1-4 0

02/03 6.6-85 0

02/03 9.2-1 5

08/12 6:6-86 0

02/03

. 9.2-2 0

02/03 6.6-87 0

02/03 9.2-3 0

02/03 6;6'-88 0

02/03 9.2-4 O*

02/03 6.6-89 0

02/03 9.3-1 5

08/12 6.6-90

' '-' ',?'.;,,,,

.0 61/03

'9.3.-.2 o,

02703 6.6-91 0

02/03 9.4-1 5

08/12 6.6-92 0

02/03 6.6-93 0

02/03 10.1-1 7

08/16 7.1-1 7

08/16 IO.I-fa 7

08/16 10.1-2 5

08/12 ANUH-01.0150 LOEP-6

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date 10.1-3 5

08/12 11.2-25 5

08/12 10.2-1 2

08/06 11.2-26 5

08/12 10.2-2 5

08/12 11.2:27 0

02/03 10.2-3 0

02/03 11.2-28 0

02/03

'.J0:2-4

'. :;'-* : /'

5 08/:12, n.2-29::

• . *:::,;~,o :*,

>02/03) 10.2-5 5

08/12 11.2-30 5

08/12 10.2-6 0

02/03 11:2-31 0

02/03 10.2-7 0

02/03 11.2-32 0

02/03 10$8 0

02/03 Ll.2~33 0

02/03 10.2-9 0

02/03 11.2-34 0

02/03 fI0.2-10 0

02/03*

11.2~35;;;:

0',

,,' < 02103 10.2-11 0

02/03 11.2-36 0

02/03 10.2-12 0

02/03 11.2-37 0

02/03 10.2-13 0

02/03 11.2-38 0

02/03 10.2-14

,5 08/12 11.2-39 0

,,02/03 10.2-15 0

02/03 11.2-40 0

02/03 lJ).2-16 0

02/03 11.2-4:E

',,' *O'*'

,; *02103:

10.3-1 5

08/12 11.2-42 0

02/03 10.3-2 5

08/12 11.2-43 0

02/03 10.3-3 5

08/12 11.2-44 0

02/03 10.3-4 2

08/06 11.2-45 0

02/03 10.3-5 2

08/06 11.2-46 0

02/03 J0.4-'1 0

02/03 H.2c47

• "',,O' :,

, c'02/03

'1 11.2-48 0

02/03 11-1 7

08/16 11.1-1 0

02/03 11.2-49 0

02/03 11.2-50 0

02/03 11.1-2 0

02/03 11.2-51 0

02/03,

11.1-3 0

02/03 11.3-1 0

02/03 (r'J" 1 5*

08/f2 1u;2' 'C'

":,' 2

.,-,, ',08/06 i 11.2-2 0

02/03 11.2-3 0

02/03 12-1 7

08/16 11.2-4 0

02/03 12-2 5

08/12 11.2-5 0

02/03 12-3 5

• ,08112 11.2-6 0

02/03 12-4 5

08/12

, (1.2-7 0

,, 0.2/03,

, 12-5

.,'~

.*,.' 08/12 I 11.2-8 0

02/03 12-6 5

08/12 11.2-9 0

02/03 12-7

• 5

'08i12 11.2-10 0

02/03 12-8 5

08/12 I 1.2-11 5

08/12 12~9 5

08/12 11.2-12 0

02/03 12-10 5

08/12

• 11,2-13 0

','I 02/03'.'

12-11.

~.,5,

"',:~vr, ;'08/12

.<. ' h1

',.~

11.2-14 0

02/03 12-12 5

08/12 11.2-15 0

02/03 12~13 5

08/12 11.2-16 0

02/03 12-14 5

08/12 11.2-17

• o 02/03 12:15 5

08/12 11.2-18 0

02/03 T1,2~19,. ',.:

0 02/03' 13~1 *...

.,_*'7.

i;,:,, 08/i6 11.2-20 0

02/03 13.1-1 5

08/12 l 1.2-21 5

08/12 13.1-2 5

08/12 11.2-22 0

02/03 13.1-3 1

03/05 l 1.2-23 0

02/03 11.2-24 5

08/12 13.2:1 5

08/12 13.2-2 5

08/12 ANUH-01.0150 LOEP-7

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages DWG: (sh. 3 of8)

ANUH-01-4001 Not shown 1 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

2 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

ANUH-01.0150 LOEP-8 3 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

4 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

5 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

6 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

7 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

8 Because SAR drawings were revised throughout the licensing period, their revision level may be higher than the overall UFSAR revision level.

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date A.2.3-2 5

08/12 A.3.6-7 2

08/06 A.2.3-3 5

08/12 A.3.6-8 2

08/06 A.2.3-4 5

08/12 A.3.6-8a 2

08/06 A.2.3-5 5

08/12 A.3.6-9 2

08/06 A.2.4-1 5

08/12 A.3.6-10 2

08/06

• 'A.2;5-1 5

08/lz.

• A.3.6~ri..

2'

,* 08/06 A.2.5-2 5

08/12 A.3.6-12 2

08/06 A.2.5-3 8

08/18 A.3.6-13 2

08/06 A.2.6-1 2

08/06 A.3.6-14 2

08/06 A.3.6-15 2

• '. 08/06

• A.3.1-1 5

08/12 A.3.6-16 5

08/12 A.3.1.2 0/..

3'...

. 08/0.8 A.3.ii'-17

. :s*..

**08/12.

A.3.1-3 5

08/12 A.3.6-17a 2

08/06 A.3.1-4 5

08/12 A.3.6-18 2

08/06 A.3.1-5 5

08/12 A.3.6-19 2

08/06 A.3.1~6 C

2*

08/06.

A.3.6-20..

2 08/06 1 A.3.1-7 2

08/06 A.3.6-21 2

08/06

• A.3.1-8 2*

08/06 A.3:<i-22 2"

<.'<'...08/06.

A.3.1-9 2

08/06 A.3.6-23 2

08/06 A.tl-10 2

08/06 A.3.6-24 2

08/06 A.3.1-11 5

08/12 A.3.6-25 5

08/12 A.3.1-12 5

-08/12 A.3.6-26.... '

2

• • ,.,.. 08/06 A.3.1-13 2

08/06 A.3.6-27 2

08/06 A.3,.1-14 2

08/06 A.3.6-2.7a 2

'"08/06 A.3.1-15 2

08/06 A.3.1-16 2

08/06 A.3.6-27b 2

08/06 A.3.6-27c 2

08/06 A.3.2-1 2

08/06 A.3.6-27d 2

08/06 A.3.2~2 5

08/12 A.3.6-21e

,2 08/06 A.3.2-3 2

08/06 A.3.6-28 2

08/06

, A.3.2-4 2

08/06.

A.3.6-29 '

2

. '**o8/06 A.3.3-1 5

08/12 A.3.6-30 2

08/06 A.3.3-2 5

08/12 A.3.6-31 2

08/06 A.3.3-3 2

08/06 A.3.6-32 2

08/06 A,.3.3-4 2

08/06 A.3*.q-33:

':.,2

• • • .. 08/06 A.3.3-5 2

08/06 A.3.6-34 2

08/06 A.3.°4-1 5*

08/12 A.3.7-1

,* 5

'.*' *-08/12 A.3.4-2 2

08/06 A.3.7-2

.2 08/06 A.3.4-3 2

08/06, A.3.4-4 2

08/06 A.4-1 5

08/12 A.3:5-1 5

08/12.

A.4:l~l

>:2

• • L 08/06 A.3.5-2 5

08/12 A.4.1-2 2

08/06 A.3.5s3 2

08/06' A.4.1-3 2

08/06 A.3.5-4 5

08/12 A.4.1-4 2

08/06 A.3.5a5 2

08/06' A.4.1-5 2

08/06 A.3.5-6 5

08/12 A.4.2-1 2

08/06 A.3.5-7 2

08/06 A.4.2~2 *

,2

, :,08/06..

A.3.6-1 2

08/06 A.4.2-3 2

08/06

. A.3.6-2 2

08/06.

A.4.2c4 2

08/06

• A.3.6-3 5

08/12 A.4.3-1 2

08/06 A.3.6-4 2

08/06 A.4.4-1

' 2 08/06 A.3.6-5 2

08/06

-A.3.6-6.

5*

08/.12' A.4.4-2 2

08/06 A.4.4"3,

,2

,. i,08/06

• ANUH-01.0150 LOEP-9

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date A.4.4-4 2

08/06 A.4.6-4 2

08/06 A.4.4-5 2

08/06 A.4.6-5 2

08/06 A.4.4-6 2

08/06 A.4.6-6 2

08/06

.A.4.4-7 2

08/06° A.4.. 6°7.*

2

,, *. 08/06 A.4.4-8 2

08/06 A.4.7-1 2

08/06

'A.4.4-9

. *{

2 08/06 A.4.7-2..

2*

.. 08/06 A.4.4-10 2

08/06 A.4.7-3 2

08/06 A.4.4-11 2

08/06 A.4.7~4 2

08/06 A.4.4-12 2

08/06 A.4.7-5 2

08/06

A.4.4-13 2

. 08/06 A.4.7-6 5

.,. 08/12,

... c A.4.4-14 2

08/06 A.4.7-7 2

08/06 A.4.4-15 2

08/06.

A.4.7-8 2

08/06 A.4.4-16 2

08/06 A.4.7-9 5

08/12 A.4.4-17 2

08/06 A.4.7-Hf 2

08/06 A.4.4-18 2

08/06 A.4.7-11 2

08/06 A.4:4-lQ 2

08/06 *

.. A.4.7-12..

.2'.

08/06.

A.4.4-20 2

08/06 A.4.7-13 2

08/06 A.4.4-21 4

08/10" A.4.7-14*

• 2

. 08/06 A.4.4-22 4

08/10 A.4.7-15 2

08/06 A.4.4-23 8

08/18 A.4.7-16 2

08/06 A.4.4-24 2

08/06 A.4.7-17 2

08/06

.AA.4-25 2

. 08/06 A.4.7-18 5

08/'12,

A.4.4-26 2

08/06 A.4.8-1 2

08/06

'AA.4-27 2

08/06' AA.9~1 **

.,i 5

• 0.8/12 A.4.4-28 2

08/06 A.4.4-29 2

08/06' A.4.9-2 2

08/06 A.4.9-3

.. 2 08/06 A.4.4-30 2

08/06 A.4.9-4 2

08/06 A.4.4-31 2

08/06:

A.4.9-.5 5

'08/12 A.4.4-32 2

08/06 A.4.9-6 2

08/06 A.4.4-33 2

08/06 A.4'.9-7

2.

... 08/06 A.4.4-34 2

08/06 A.4.9-8 2

08/06 A.4.4-35 2

08/06 A.4.9-9 2

08/06 A.4.4-36 2

08/06 A.4.10-1 2

08/06 A.4.4-37 2

08/06 A.4.10;2*

,2

..,;, 08/06 :

A.4.4-38 2

08/06 A.4.10-3 2

08/06 A.4.4:.39.

2 08/06 A.4.10~4 2

08/06 A.4.4-40 2

08/06 A.4.10-5 2

08/06 A.4.4-41 2

08io6

• A.4.10-6 2

08/06 A.4.4-42 2

08/06 A.4.10-7 2

08/06 A.4.4-43 2

08/0'6 A.4.10a8 2

,.*.. 08/06.

A.4.4-44 2

08/06 A.4.10-9 2

08/06 A.4.4-45 2

08/06 '.

AA.ro~to*

2

. 08/06 :

A.4.4-46 2

08/06 A.4.10-11 2

08/06 A.4.4-47 2

08/06 A.4.10°12 2

08/06 A.4.4-48 2

08/06 A.4.10-13 2

08/06 A:4.4-49 2

08/06 A.4:lOsM 2

• , ;08/06:

A.4.4-50 2

08/06 A.4.10-15 2

08/06 A.4.4-51 2

08/06' A.4.IO-i6

..

• 2 08/06 A.4.5-1 2

08/06 A.4.10-17 2

08/06 A.4.6-1 2

08/06.

A.4.10~18 2

08/06 A.4.6-2 2

08/06

• A,4.6-3 2

08/06 A.4.10-19 2

08/06 A.4)0-20...

..,2.

08/06 ANUH-01.0150 LOEP-10

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Pa2:e or description Rev.

Date Page or description Rev.

Date A.4.11-1 5

08/12 A.5.4-11 2

08/06 A.4.11-2 5

08/12 A.5.4-12 2

08/06 A.4.11-3 4

08/10 A.5.4-13 2

08/06 A.5.5-1 2.

• .* 08/06 A.5.1-1 5

08/12 A.5.5-2 2

08/06

.. A.5.1:2 i/:

2 08/06 A.5.5-'.3:.

2 08/06 A.5.1-3 5

08/12 A.5.5-4 2

08/06 A.5.1-4 2

08/06 A.5.5-5 2

08/06 A.5.1-5 2

08/06 A.5.5-6 2

08/06 A.5.1-6 2

08/06

. A.5.5-7

/

.**. 2

' 08/.06 A.5.1-7 2

08/06 A.5.5-8 2

08/06 A.5.1-8 2

08/06.

A.5S9

r

.,. 08/06.:

A.5.1-9 2

08/06 A.5.5-10 2

08/06 A.5.1-10 2

08/06 A.5.5-li 2

08/06 A.5.1-11 2

08/06 A.5.5-12 2

08/06

,;\\.5.2-1 5

. /

08/12 A.5.5-13

' 2

..,;' 08/0.6..

A.5.2-2 2

08/06 A.5.5-14 2

08/06 A.5.2-3 5

08712 A.5Sl5 2

',.08/06 A.5.2-3a 2

08/06 A.5.5-16 2

08/06 A.5.2-4 5

08/12 A.5.5-17 2

08/06 A.5.2-5 2

08/06 A.5.5-18 2

08/06 A.5.2-6 2

08/06 A,5.5.-19

... 2

.i' 08/06 A.5.2-7 5

08/12 A.5.5-20 2

08/06 A.5.2-8 2

08/06 A.5.5-21 2

08/06 A.5.2-9 5

08/12 A.5.2-10 2

08/0p A.5.5-22 2

08/06 A.5.5-23 2

.08/06 A.5.2-11 5

08/12 A.5.5-24 2

08/06 A.s.2-12

.5 08/lZ

• A.5.5_-25 2

.. 08/06,

A.5.2-13 2

08/06 A.5.5-26 2

08/06 A,5.2-14 2

08/06 A.5.5:21.*

2

• 03106

• A.5.2-15 2

08/06 A.5.5-28 2

08/06 A.5.2-16 2

'08/06 A.5.5-29 2

08/06 A.5.2-17 5

08/12 A.5.5-30 2

08/06 A.5.2-18 5*

08/12 A.5.5_-31 2

' 08/06.

~

A.5.3-1 2

08/06 A.5.5-32 2

08/06 A'.5.3-2 2

C 08/06 A.5.5 733

• 2 08/06 A.5.3-3 2

08/06 A.5.5-34 2

08/06 A.5.3-4 5

08/12 A.S:5-35 2

08/06 A.5.3-5 5

08/12 A.5.5-36 2

08/06 A.5.3-6 5

08/l4

/

A.5S37

.2

• 08/06 :

A.5.3-7 5

08/12 A.5.5-38 2

08/06 A.5.3-8 2

08/06 A.5.5-39 2

03106.

A.5.4-1 2

08/06 A.5.5-40 2

08/06 A.5.4~2 2

08/06 A.5.5-41 2

08/06 A.5.4-3 2

08/06 A.5.5-42 2

08/06

.A,5.4-4

• ,e

• 2 08/06 A.5.5-43.

2

• • 08/06.

A.5.4-5 2

08/06 A.5.5-44 2

08/06 A.5:4-6

/. ;

2 08/06, A.5.5-45 2

08/06 A.5.4-7 2

08/06 A.5.5-46 2

08/06 A.5.4-8 2

08/06 A.5.5-47 2

.**. 08/06 A.5.4-9 2

08/06 A.5.4-10 2.

08/06 A.5.5-48 2

08/06 A.5:5-49

.2 08/06 ANUH-01.0150 LOEP-11

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Pae:e or description Rev.

Date Pae:e or description Rev.

Date A.5.5-50 2

08/06 A.5.5-102 2

08/06 A.5.5-51 2

08/06 A.5.5-103 2

08/06 A.5.5-52 2

08/06 A.5.5-104 2

08/06 A.5.5-53 2

08/06

• A.5.5-105 2

08/06 A.5.5-54 2

08/06 A.5.5-106 2

08/06 A.5.5-55 2

08/06 A.5.5-107 2

08/06 A.5.5-56 2

08/06 A.5.5-108 2

08/06 A.5.5-51

• 2 08/06 A.5.5-109 2

0.8/06 A.5.5-58 2

08/06 A.5.5-110 2

08/06 A.5.5-59

c,*.(,.

2.*..

08/06

,A.5.5*111.

.. *:2

. 08/06 A.5.5-60 2

08/06 A.5.5-112 2

08/06 A.5.5-61 2

08/06:

A.5.5-62 2

08/06 A.6-1 5

08/12 A.5.5-63 2

08/06 A.6.1-1 5

08/12 A.5.5-64 2

08/06 A.6.1-2 5

08/12 A.5.5-65 2

08/06.

A.6.2-1 5

08/12.

A.5.5-66 2

08/06 A.6.2-2 5

08/12 A.5.5-67 2

08/06 A.6.3-1 5

08/12.

A.5.5-68 2

08/06 A.6.3-2 5

08/12 A.5.5-.69 2

08/06 A.6.3-3

5 08/12 A.5.5-70 2

08/06 A.6.3-4 5

08/12 A.5.5-71 **

2

'0.8/0,6 A:6.3-5

.}5'.t..,.*

.. 08/12 *.

A.5.5-72 2

08/06 A.6.3-6 5

08/12 A.5.5-73 2

08/06 A.6.3-7 2

08/06 A.5.5-74 2

08/06 A.5.5-75 2

08/06 A.6.3-8 2

08/06 A.6.3-9

• 2 08/06 A.5.5-76 2

08/06 A.6.3-10 5

08/12 A.5.5-77 2

08/06 A.6.3-11 3

08/08 A.5.5-78 2

08/06 A.6.3-12 2

08/06 A.5.5-79 2

08/06 A.6.3-13 5*

08/12 A.5.5-80 2

08/06 A.6.3-14 2

08/06 A.5.5-81 2

• 08/06 A.6.3-15

2.

08/06 A.5.5-82 2

08/06 A.6.3-16 2

08/06 A,5;5-83 2

08/06.'.

A:6.3-17

.* 2 08/06 A.5.5-84 2

08/06 A.6.3-18 2

08/06 A.5.5-85 2

08/06, A.6A:1 f

08/12 A.5.5-86 2

08/06 A.6.4-2 5

08/12 A.5.5-87 2

08/06 A.6.4-3

',5 08/12 A.5.5-88 2

08/06 A.6.4-4 5

08/12 A.5.5-89 2

. 08/06 A.6.4-5 5'

08/12 A.5.5-90 2

08/06 A.6.4-6 5

08/12 A.5.5-91 2

08/06

• A.6.4-7 2

08/06 A.5.5-92 2

08/06 A.6.4-8 5

08/12 A.5.5~93 2

08/06 A:6.4-9 5

08/12 A.5.5-94 2

08/06 A.6.4-10 5

08/12 A.5.5-95..*... * :J~ ;

I

.. 2 08/06 A.6.4-11.

5,'

08/12 A.5.5-96 2

08/06 A.6.4-12 5

08/12 A.5.5-97 2

• Q8/06' A.6.4-13

5' 08/12 A.5.5-98 2

08/06 A.6.4-14 5

08/12 A.5.5-99 2

08/06 A.6.4-15 5

08/12 A.5.5-100 2

08/06 A.5.5-101 2

08/06 A.6.4-16 5

08/12 A.6.4-17 5

08/12 ANUH-01.0150 LOEP-12

Advanced NUHOMS System Updated Final Safety Analysis Report Rev.

5 ANUH-01.0150 List Of Effective Pages Date 08/12 08/06

z*to8/0,(}Ii 08/06 08/06 oa100 **

08/06 LOEP-13 Rev. 8, 08/18 Rev.

Date 2

08/06

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date A.6.6-74 2

08/06 A.10.2-6 2

08/06 A.6:6-75 2

08/06 A.10.2-7 2

08/06 A.6.6-76 2

08/06 A.10.2-8 2

08/06

,A.6,6*77

/

2 08/06\\

A.10.2-9 *

.2'

• • ..

• 08/06

• A.6.6-78 2

08/06 A.10.2-10 2

08/06 A.6.6-79 2

08/06 A.io.2-n 2

08/06.

A.10.2-12 2

08/06 A.7.1-1 5

08/12

.A.10.2-13 5

08/12 A.7.1-2

.5 08/12 A.10.2-14 2

08/06

A,7.1-3 5

08/12; A.10.. 2~J5...

2

,.()8/06 A.7.1-4 2

08/06 A.10.3-1 5

08/12 A.7.2-1

• 5 08/12 A.HU:2 2

.. 08/06 A.7.3-1 5

08/12 A.10.3-3 5

08/12 A.7.4-1 5

08/12

• A.10.3-4 2*

08/06 A.10.3-5 2

08/06 A.8.1-1 5

08/1)

A.10.471 2

~08/06 A.8.1-2 2

08/06 A.8.1-3 5

08/12 A.11-1 5

08/12

• A.8.1-4 2

08/06 A.11.1-1 5

08/12 A8.1~5 2

08/06 A.11.1-2 5

08/12 A.8.1-6 5

08/12 A.11.2-1 5

08/12

.A:8.1-6a 5

08/12,.

A.11.2~2 5,

', 08/12

• A.8.1-7 3

08/08 A.11.2-3 5

08/12 A.8.1-8 5

08/12 A.il.2-4.

5 08/12 A.8.1-9 2

08/06 A:8.1-10 3

08/08 A.11.2-5 5

08/12 A.11.3-1 2

08/06 A.8.1-11 2

08/06

A.8.2-1 5

08/12.:

A.12-1

. ' ',, 5

? 08112 A.8.2-2 2

08/06 A.12-2 5

08/12 A.8.2-3 5

08/12 A.12-3

• 5 08/12' A.8.2-4 2

08/06 A.12-4 5

08/12 A.8.2-5 2

08/06 A.12-5

.5 08/12 A.8.2-6 2

08/06 A.12-6 5

08/12 A.8.277 2

.. 08/06 A.12-7.

i5

..i" : 08/12,.

A.8.2-8 2

08/06 A.12-8 5

08/12 A.8.3-1 5

08/12 A.12-9 5

08/12 A.12-10 5

08/12 A.9.1-1 5

08/12 A.12-11.

5 08/12 A.9.1-2 5

08/12 A.12-12 5

08/i2 A.9.1-3

' 5 08/12 A.12,J)::;.,,

5

'* *,,. \\08/12:

A.9.1-4 5

08/12 A.12-14 5

08/12 A.9.2-1 5

• . 08/12 A.9.2-la 5

08/12 A.13-1 2

08/06 A.9.3-1 5

08/12 A.9.4-1 2

08/06 A.14.1-1 5

08/12 y..

A.14.1-2.

5

'08/12

• A.10.1-1 5

08/12 A.14.1-3 2

08/06 A.16.2-1 2

08/06.

A.14.2~1 2

'08/66 A.10.2-2 5

08/12 A.10.2-3 2

08/06 B-i 7

08/16 A.10.2-4 2

08/06 A.10.2-5 5

. 08/12 B-ii 7

08/16 B-iii

.,}

.08/16 ANUH-01.0150 LOEP-14

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 DWG: (sh. 5 of 6)

ANUH-01-4002 ANUH-01.0150 Rev.

7 List Of Effective Pages Date 08/16 Pa e or descri tion Rev.

DWG: (sh. 2 of 4)

ANUH-01-4004 rniil~:~\\t~:f~~~ ***

DWG: (sh. 4 of 4)

ANUH-01-4004

i~Itrli%t!lJt~

DWG: (sh. 2 of 4)

ANUH-01-4005 DWG: (sh. 4 of 4)

ANUH-01-4005

~B!t~jJ~i~!

DWG: (sh. 1 of 14)

NUH-03-4012 Date 8/9/16

~~~fR!:;-c;-c~;-c;-c~,;;,,--:~]:ToJm~

DWG: (sh. 3 of 14)

NUH-03-4012

" *wG~;J~If 1\\fQf,:If+)~, *

• . -03~#012 lti*t/***~

DWG: (sh. 5 of 14)

NUH-03-4012

zpWGt(shi:~Jff,1'4~*t:i

NVfr~03

ii40J2.::U;. ***

DWG: (sh. 7 of 14)

NUH-03-4012 DWG: (sh. 11 of 14 NUH-03-4012

'.~~,9~t~Htt~~gi}ff****

,,L4, NO;HcOl:JJ.012;,fi'*.

DWG: (sh. 13 of

14) NUH-03-4012 LOEP-15

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Pa!!e or description Rev.

Date Pae:e or description Rev.

Date DWG: (sh. 3 of 6) 0 8/9/16 B.3.1-14 7

08/16 NUH-03-4013 B.3.1-15 7

08/16 DWG: (sh. 4 of6) 0 8/9/16 B.3.1-16 7

08/16 NUHs03-4013.

B.3.1-1.T '*

7 08/16 DWG: (sh. 5 of 6) 0 8/9/16 B.3.1-18 7

08/16 NUH-03-4013 DWG:(sh. 6 of6) 0 8/9/16 B.3.1-19.

,*:7

.,. \\08/16 :

B.3.1-20 7

08/16 NUH-03-4013 B.3.1~21 7

08/16 B.3.1-22 7

08/16

/B.2.1-1 7

08/16

B

3:I-23 7

08/16 B.2.1-2 7

08/16 B.3.1-24 7

08/16

.$:2.1-3 7

08/l6:

B.3J,c25 *

• 7

. **: -c {)8/16 :

B.2.1-4 7

08/16 B.3.1-26 7

08/16

}3.2.1-5 7

08/16 B.3.1-27 7

08/16 B.2.1-6 7

08/16 B.3.1-28 7

08/16 B.2.1-7 7

08/16 B.3.1.-.29, 7

'..,. c,,08/16 B.2.1-8 7

08/16 B.3.1-30 7

08/16 oB.2.1-9 7

08/16 B:3.l.'.31 7

.. -:. :()8/16 :

B.2.1-10 7

08/16 B.3.1-32 7

08/16 B:2.1,11 7

08/16 B.3.1-33 7

08/16 B.2.1-12 7

08/16 B.3.1-34 7

08/16 B.2.1-13 7

08/16 B.3.1-35",

'.7

'-,08/16 B.2.1-14 7

08/16 B.3.1-36 7

08/16 B.2.1-15 7

08/16 B.3.1-37

'1.

.. '08/16 B.2.2-1 7

08/16 B.2.2-2 7

08/16 B.3.1-38 7

08/16 B.3.1-39 7

08/16 B.2.2-3 7

08/16 B.3.1-40 7

08/16 B.2:2-4 7

08/16.

B.3.l-41, 7

:;:,08/16 B.2.3-1 7

08/16 B.3.2-1 7

08/16

'.s.z.s~2 7

08/16*

B.3.2~2: '.. '..

,,7 08/16 B.2.3-3 7

08/16 B.3.2-3 7

08/16 13.2.3-4 7

08/16 B.3.2-4 7

08/16 B.2.4-1 7

08/16 B.3.3-1 7

08/16

B.2.5-1 7

08/16 I3,3.3;).

7

, 08/16. :

B.2.5-2 7

08/16 B.3.3-3 7

08/16 B.2.5-3 8

08/18 B.3.3-4*

7 p

08/16 B.2.6-1 7

08/16 B.3.3-5 7

08/16 B.2.6-2 7

08/16 B.3.3-6 7

08/16 B.3.3-7 7

08/16

.B.3.1-1 7

08/16 B.3.3'~8-

7.

08/16 B.3.1-2 7

08/16 B.3.3-9 7

08/16 B'..3.1-3 7

08/16, B.3.4~1

'7 08/16.

B.3.1-4 7

08/16 B.3.4-2 7

08/16 B.3.1-5 7

08/16 B.3.4-3 7

• 08/16 B.3.1-6 7

08/16 B.3.4-4 7

08/16

• .B.3.1-7 7

08/16 B.3.4-5, 7

08/16

• B.3.1-8 7

08/16 B.3.4-6 7

08/16 K3.l-9

~,* '

7

~

08/16 B.3.4-7 7

08/16 B.3.1-10 7

08/16 B.3.4-8 7

08/16 B.3.1-11 7

08/16 B.3.4°9 7

08/16 B.3.1-12 7

08/16

.B.3.H3

'.7

• 08/l(j B.3.4-10 7

08/16 B.3.4-11 7

.08/16 ANUH-01.0150 LOEP-16

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date B.3.4-12 7

08/16 B.3.6-23 7

08/16 B.3.4-13 7

08/16

• B.3.6-24 7

08/16,

B.3.4-14 7

08/16 B.3.6-25 7

08/16 B.3.4-15 7'

08/16:

B:3.6-26 7

08/16 B.3.4-16 7

08/16 B.3.6-27 7

08/16 B.3.4~17 7

08/16 B:3.6-28 7

08/16 :

B.3.5-1 7

08/16 B.3.6-29 7

08/16 B.3.5-2 7...

08/16.,

B.3.6-30 7

08/16 B.3.5-3 7

08/16 B.3.6-31 7

08/16 B.3.5-4.

• 7 08/16

}3;3.6-32 7

08tl6 B.3.5-5 7

08/16 B.3.6-33 7

08/16 B.3.5c6 7

08/16 B.3.6-34

7 08/16.

B.3.5-7 7

08/16 B.3.6-35 7

08/16 B.3.S8 7

08/16 B.3.6-36.

7 08/16 B.3.5-9 7

08/16 B.3.6-37 7

08/16 B.3.5"10 7

08/16 B.3.6-38 7

08/16

• B.3.5-11 7

08/16 B.3.6-39 7

08/16 B.3.5~1.2

7.

08/16 B;3.6-4Q 7

.08/16,

B.3.5-13 7

08/16 B.3.6-41 7

08/16 B.3:5-14 7

08/16 B.3.6-42 7

08/16 B.3.5-15 7

08/16 B.3.6-43 7

08/16 B.3.5-16 7

08/16 B.3.6-44 7*

08/16,

B.3.5-17 7

08/16 B.3.6-45 7

08/16 B.3.5~18 7

08/16 B.3.6-46

'7 08/,16 B.3.5-19 7

08/16 B.3.5-20 7,*

08/16 B.3.6-47 7

08/16 B.3.6-48

.. 7

. 08h16.

B.3.5-21 7

08/16 B.3.6-49 7

08/16 B.3.5~22 7

08/16 B:3.6-50 7

08/16:

B.3.5-23 7

08/16 B.3.6-51 7

08/16 B.3.5°24 7

08/16 B.)i,-52 7

08/1.6,

B.3.6-1 7

08/16 B.3.6-53 7

08/16 B.3:6-'2 7

08/16 B.3.6°54

'7 08/16

• B.3.6-3 7

08/16 B.3.6-55 7

08/16 B.3.6-4 7

08/16 B.3.6-56 7,.

08/16, B.3.6-5 7

08/16 B.3.6-57 7

08/16 B.3.6-6 7

,.

• 08/16 B.3.6-58 7

08/16 B.3.6-7 7

08/16 B.3.6-59 7

08/16 B.'.3'6-8 7

08/16:

B.3.6-60

.. 7

. 08/16 B.3.6-9 7

08/16 B.3.6-61 7

08/16 B.3.6-1()

7

• 08/16 B.3.6-62 7

08/16 B.3.6-11 7

08/16 B.3.6-63 7

08/16 B.3.6-12 7

08/16 B.3.6-64 7

p 08/16

• B.3.6-13 7

08/16 B.3.6-65 7

08/16 B.3.6-14 7

08/16 B.3.6~66 7

08/16 B.3.6-15 7

08/16 B.3.6-67 7

08/16 B.3.6°16 7

08/16 B.3:6-68

,,,,7 08/i6,

B.3.6-17 7

08/16 B.3.6-69 7

08/16 B'.3.6-18 7 '

08/16 B:3.6-70 7

08/16 B.3.6-19 7

08/16 B.3.6-71 7

08/16 B,3.6~20 7

08/16 B:3.6-72 7

08716 B.3.6-21 7

08/16 B.3,6-22 7

08/16 B.3.6-73 7

08/16 B.3.6-74 7

08/16,

ANUH-01.0150 LOEP-17

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Pae;e or description Rev.

Date Page or description Rev.

Date B.3.6-75 7

08/16 B.4.5-6 7

08/16

B.3

6-76

,; *7

• 08/16 B.4.5-7

7.

.. *..

• 08/16:

B.3.6-77 7

08/16 B.4.5-8 7

08/16 B.3.6-78 7

08/16 B.4.5:-9 7

08/16.

B.3.6-79 7

08/16 B.4.5-10 7

08/16 B.3.6-80.

7 08/16 B.4.5-11

1

. 08/16 B.3.6-81 7

08/16 B.4.5-12 7

08/16

.. B.3,6-82" i;;',7

,,.'I*

\\,;:,08/16 B.4:5-13'

'{ 7

. [';

• ..*. : 08/16

B.3.7-1 7

08/16 B.4.5-14 7

08/16 B.3.7-2 7

08/16 B.4.5-15 7

08/16 B.3.7-3 7

08/16 B.4.5-16 7

08/16

. B.3.7-4.

7 08/16

• B.4.5-1 /

7 08/16 '1 B.4.5-18 7

08/16 B.4-1

.:*7

'<z, 08/16 B.4.5-19.*

7

• .*;; 08/161 B.4.1-1 7

08/16 B.4.5-20 7

08/16 B.4.1-2 7

08/16*

B.4.5-21 7

'* 08/16' B.4.1-3 7

08/16 B.4.5-22 7

08/16 B.4.1-4 7

. ' 08/16 B.4.5-23

.. 7 08/16 B.4.1-5 7

08/16 B.4.5-24 7

08/16 B.4.2~1

! 0.8/16 I B.4.5-25*.

• • 7

.. 08/167 B.4.2-2 7

08/16 B.4.5-26 7

08/16 B.4.2-3 7

08/16 B.4.5-27

.7 08/16 B.4.2-4 7

08/16 B.4.5-28 7

08/16 B.4.2-5

.1 08/16 B.4.5-29 7

08/16 B.4.2-6 7

08/16 Jt4.2c7 *

'7 08/16 B.4.5-30 7

08/16 B.4.5-31

'7

. 08/16;:

B.4.3-1 7

08/16 B.4.5-32 7

08/16 B.4.3-2 7

08/16

• B.4.5-33

• 7 08/16 B.4.4-1

7.

08/16 B.4.5-34 7

08/16 B.4.4-2

• 7 08/16 B.4.5-35 7

08/16 B.4.4-3 7

08/16 B.4.5-36 7

08/16 B.4.4-4 7

08/16

B.4.5-37..

7

/

08/16'.

B.4.4-5 7

08/16 B.4.5-38 7

08/16 B.4.4-6 7

08/16 B.4.5-39 7

08/16 I B.4.4-7 7

08/16 B.4.5-40 7

08/16 B.4.4-8

• 7

'* 08/16

]3.4.5-41

.7 I

08/16 *.

B.4.4-9 7

08/16 B.4.5-42 7

08/16

'B.4.4-10 7*

' * "08/16

"'B.4.5-43

• 7

• 0,8/16 B.4.4-11 7

08/16 B.4.6-1 7

08/16 B.4.4-12 7

08/16

'B.4.6-2 7

08/1.6*,

B.4.4-13 7

08/16 B.4.6-3 7

08/16 B.4.4-14 7

08/16 B.4.6A 7

08/16 B.4.4-15 7

08/16 B.4.6-5 7

08/16 B.4.4-.16

'*7 08/16

• B.4.6-6

'7

.08/16' B.4.4-17 7

08/16 B.4.6-7 7

08/16 B.4.4-1,8 7

08/16 B.4.6-8

,7 08/16.

B.4.4-19 7

08/16 B.4.6-9 7

08/16 B.4.5-1.. *'

7

,,* '08/16 B.4.6-10 7

08/16 B.4.5-2 7

08/16 B.4.6-11 7

08/16 B.4.5-3 7

• 08/16

. B.4.6-12 7

08/1.6.

B.4.5-4 7

08/16 B.4.5-5 7

08/16 B.4.6-13 7

08/16

. B.4,6al4 7

08/16.

ANUH-01.0150 LOEP-18

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 Pa e or descri tion Rev.

List Of Effective Pages Date Date Rev.

B.4.6-15 7

08/16 7

08/16 ANUH-01.0150 LOEP-19

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Pa2e or description Rev.

Date B.5.5-9 7

08/16 B.5.5-61 7

08/16 B.5.5-10 7,

08/1.6 B.5.5-:62 7

08/16 B.5.5-11 7

08/16 B.5.5-63 7

08/16 B.5.5-12

,;P 7

08/16.

B.5.5-64 7

.... 08/16 B.5.5-13 7

08/16 B.5.5-65 7

08/16 B.5.5-14 7

08/16 B.5.5-66

,*., 7 08/16 B.5.5-15 7

08/16 B.5.5-67 7

08/16 B.5.5-16 7

08/16.

B.5.5~68 7

08/16 B.5.5-17 7

08/16 B.5.5-69 7

08/16

,B.5.5-18 7

08/16.

. B.5.5-70.

.7

.. *;, 08/16 B.5.5-19 7

08/16 B.5.5-71 7

08/16

'B.5.5-20 7

08/16 B.5.F72.'

'.7 08/16 B.5.5-21 7

08/16 B.5.5-73 7

08/16 B.5.5-22 7

08/16 B.5.5-74 7

08/16 B.5.5-23 7

08/16 B.5.5-75 7

08/16

'B.5.5-24 7

08/16

. B.5.5~76*',..

• ..,]'

. 08/.16.

B.5.5-25 7

08/16 B.5.5-77 7

08/16 B.5:5-26 7

08/16 B.5.5-78 7

,. 08/16.

B.5.5-27 7

08/16 B.5.5-79 7

08/16 B.5.5-28 7

08/16 B.5.5-80 7

• , 08/16 B.5.5-29 7

• 08/16 B.5.5-81 7

08/16 B:5.5-30 7

08/16 B.5.5-82

.7

• , 08/16 B.5.5-31 7

08/16 B.5.5-83 7

08/16 B.5.5-32 7

08/16 B.5.5-84 7

08/16 B.5.5-33 7

08/16 B.5.5-34 7

08/16 B.5.5-85 7

08/16 B.5.5-86 7

08/16 B.5.5-35 7

08/16 B.5.5-87 7

08/16 B,5.5-36 7

08/16**

B.5.5-88

.7

.08/16 B.5.5-37 7

08/16

.B.5.5-38 7

Q8/16 B.6-1 7

08/16 B.5.5-39 7

. 08/16 B.6.1-1 7

08/16 B.5.5-40 7

08/16 B.6.2-1 7

08/16 B.5.5-41 7

08/16 B.6.3-1 7

08/16

.B.5.5-42 7

08/16 B.6.3~2..<:

7

\\<<, 08/.16

• B.5.5-43 7

08/16 B.6.3-3 7

08/16 B.5;'5c44 7

08/16 B.6.4-1 7

08/16 B.5.5-45 7

08/16 B.6.4-2 7

08/16 B.5.5-46 7

08/1,6 B.6.4-3 7

08/16 B.5.5-47 7

08/16 B.6.4-4 7

08/16 B.5:5-48 7,

08/16, B.6.4-5

.7'

.08/16 B.5.5-49 7

08/16 B.6.4-6 7

08/16 B.5.5-50 7

. 08/16 B.6.44 7...

08/16

• B.5.5-51 7

08/16 B.6.4-8 7

08/16 B.5.5-52 7

08/16 B.6.4-9

• 7

• 08/16 B.5.5-53 7

08/16 B.6.4-10 7

08/16

B,.5.5-54 7

08/lp<

B.6.4-11 7

08/16.

B.5.5-55 7

08/16 B.6.4-12 7

08/16

]3.5.5-56 7

08/16 B.6.4-13 7

'08/16 B.5.5-57 7

08/16 B.6.4-14 7

08/16 B.5.5-58 7

08/16 B.6.5-1 7

08/16 B.5.5-59 7

08/16 B.5.5-60 7

08/16 B.6.5-2 7

08/16 B.6.6-1 7

.08/1.6.

ANUH-01.0150 LOEP-20

Advanced NUHOMS System Updated Final Safety Analysis Report List Of Effective Pages Pa e or descri tion Rev.

B.6.6-54 7

ANUH-01.0150 LOEP-21 Rev. 8, 08/18 Date 08/16 I I

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 List Of Effective Pages Page or description Rev.

Date Page or description Rev.

Date B.10.1-1 7

08/16 B.11.2-21 7

08/16 B.10.1-2 *

< '):,. ',v7.,:,,'.

08/J6

, B..Jl.2~22....*..,.**.*. *, '

,**7{

\\' ;.*0&/16'

'h,},

B.10.1-3 7

08/16 B.11.2-23 7

08/16 B.i'0:2~1*

7

' \\'.,;

08/1'6, Rll.2~24.

.'.,],'.,.

08/J6 B.10.2-2 7

08/16 B.11.2-25 7

08/16 Jl:10.2~3 f/.

08/16 B.11.2*26. J

.7..

. ' : ';;,, '08/f6' B.10.2-4 7

08/16 B.11.2-27 7

08/16 B.102~5 7.,,.

08716 Rll.2-28 i.,

,, 7..

08/16 B.10.2-6 7

08/16 B.11.2-29 7

08/16

.:BJ0.277'":

7 08/16' B.11.2-30:' ; :

• 7;

"'**.. )6&/16:l B.10.2-8 7

08/16 B.11.2-31 7

08/16 JI.10.2-9

I:* **. 7 08/fo

.B.ll.2,~2.

• .. : 7

)

• ,,,,, 08/;l 6 B.10.2-10 7

08/16 B.11.2-33 7

08/16 B.10.2~11. **

Q8/l6;

' *: 7 Bt11,2::a4.

• ,.. '.T'..,

';' '*. '08/16 B.10.2-12 7

08/16 B.11.3-1 7

08/16 RI0.2tJ3 7

.. 0&/16,

?<<,"'

,'/; :,:

I

,;r,,, **'::. ,,

,

/

B.10.2-14 7

08/16 B.12-1 7

08/16

.B,{0.2~}5:'*

7

".*.()8/16 J\\12-2

'* 1:* \\..*i*. : * :: ';:;. ', ~Q&/1~ :

B.10.2-16 7

08/16 B.12-3 7

08/16 B.10.2-l 7,.*.

7,,,

'.;:'08/16

.s.12~4

• 7";' !. ',:<,ti,, ',I '*' 08/:i'i:i:

B.10.2-18 7

08/16 B.12-5 7

08/16 B;l0.3~( *::,*.:

7****.

08ll6

.*B.12~6:,,,.. *:.*,,,,,

>7

• 08/16 B.10.3-2 7

08/16 B.12-7 7

08/16 B;I0.373'

" 7 /.<

08£1,6 B.12-8

• 7.

08/16 B.10.3-4 7

08/16

.]3J0.3-5 7

08/16 B.12-9 7

08/16 B:12."10 7

O&!l.6 I B.10.4-1 7

08/16 B.12-11 7

08/16 B.12.~1':2

\\

" 7/;

• ,*. 0'8/Hi*

B.11-1 7

08/16 B.12-13 7

08/16 B.ll.J7*1

.:,-r,:*:

08716 B.12-14

,:7

• 08/1§:

B.11.1-2 7

08/16 B.12-15 7

08/16 B'.H.+3:.,

7,

* '. 08/16..

13.12~16

)

\\1 ',; " ::*. 08i'l6.'

B.11.2-1 7

08/16 B.12-17 7

08/16

• B.11.2.. 2 i}

08/Hi *

<7 '. '

JU2-l8,

• 7

.. QS/16.i B.11.2-3 7

08/16 B.12-19

- 7 08/16 B,11.:2'-'4 7

08716.

Y'j I* :'.\\'

B.11.2-5 7

08/16 B.13-1 7

08/16 BJl.J,.,6**

7 ".'

08/J6 I'

1* *,

B.11.2-7 7

08/16 B.14.1-1 7

08/16 BAJ,2-8..

7. '

08/16

BJ4:.J-2

'7 08/16 B.11.2-9 7

08/16 B.14.1-3 7

08/16 B.11,2-10

• A

7 '\\ :*

• 08/16.

B.14,2~1

.7.',.,,

\\.08D~*.

B.11.2-11 7

08/16

. B.if.2-12..*.

7

,08/16 B.11.2-13 7

08/16 B.11.2-14

.7 08/16 B.11.2-15 7

08/16 BJL2-l6 i

08/16 B.11.2-17 7

08/16 B.l 1..2-18,

,.i7,*,,*,

08/16 B.11.2-19 7

08/16 B~H*:2~20

• 7 08/16 :*

-' ~,. ' '

ANUH-01.0150 LOEP-22

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 1.5 Supplemental Data 1.5.1 References

[1.1]

10 CFR Part 72, Rules and Regulations, Title 10, Code of Federal Regulations - Energy, U.S. Nuclear Regulatory Commission, Washington, D.C., "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste."*

[1.2]

U.S. Nuclear Regulatory Commission, Regulatory Guide 3.61, Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask, February 1989.

[1.3]

U.S. Nuclear Regulatory Commission, "Standard Review Plan for Dry Cask Storage Systems," NUREG 1536, U.S. NRC (January 1997).

[1.4]

Nuclear Regulatory Commission, Safety Evaluation Report of Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, December 1994, USNRC Docket No. 72-1004, File NUH003.0103.02.

[1.5]

TN, Safety Analysis Report for the NUHOMS MP187 Multi-Purpose Cask, NUH-005, Revision 17, July 2003, USNRC Docket No. 71-9255.

[1.6]

TN, Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 9, February 2006, File NUH003.0103,'USNRC Docket No. 72-1004.

[1.7]

Rancho Seco Independent Spent Fuel Storage Installation, Final Safety Analysis Report, Revision 0, November 2000, USNRC Docket No. 72-11.

[1.8]

10 CFR Part 71, Rules and Regulations, Title 10, Code of Federal Regulations - Energy, U.S. Nuclear Regulatory Commission, Washington, D.C., "Packaging and Transportation of Radioactive Material."

[1.9]

NRC Certificate of Compliance 72-1004, NUHOMS General License Spent Fuel Storage System, Amendment No. 8, December 2005.

1.5.2 Drawings

- 24PT1-DSC: NUH-05-4010, Rev. 6 (PROPRIETARY)

-AHSM: NUH-03-4011, Rev. 8 (PROPRIETARY)

ANUH-01.0150 1.5-1

8 I

H G

F E

D C

B A

8 I

7 I

6 I

5 l

4 I

3 I

2 I

Proprietary and Security Related Information for Drawing NUH-05-4010-SAR, Rev. 6 Withheld Pursuant to 10 CFR 2.390 7

I 6

I 5

T 4

I 3

I 2

I H

F E

+-

D C

B A

8 I

H G

F E

D C

B A

8 I

7 I

6 I

5 1

4 I

3 I

2 I

Proprietary and Security Related Information for Drawing NUH-03-4011-SAR, Rev. 8 Withheld Pursuant to 10 CFR 2.390 7

I 6

I 5

T 4

I 3

I 2

I H

G j

F E

D C

B A

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table 2.5-1 Advanced NUHOMS System Maior Components and Safety Classification Component<3J Dry Storage Canister (24PT1 -DSC)

Guidesleeves Spacer Discs Support Rods Shield Plugs (Top and Bottom)

Shell Cover Plates (Top and Bottom)

DSC Support Ring Siphon and Vent Block Siphon and Vent Port Cover Plates Grapple Ring and Grapple Support Weld Filler Metal Failed Fuel Can Electroless nickel coating Horizontal Storage Module (AHSM)

Reinforced Concrete 24PT1 -DSC Support Structure Thermal Instrumentation AHSM/Cask Restraint Galvanized and zinc rich coatings ISFSI Basemat and Approach Slabs Transfer Equipment On-site Transfer Cask Cask Lifting Yoke Transfer Trailer/Skid Ram Assembly Dry Film Lubricant Auxiliary Equipment Vacuum Drying System Automatic Welding System Transfer Cask/DSC Annulus Seal 10 CFR Part 72 Classification<1>

Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Jmportant to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Not Important to Safety Important to Safety Important to Safety Not Important to Safety Important to Safety Not Important to Safety Not Important to Safety Important to Safety Safety Related<2>

Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety (1)

Structures, systems and components "important to safety" are defined in 10 CFR 72.3 as those features of the ISFSI whose function is (1) to maintain the conditions required to store spent fuel safely, (2) to prevent damage to the spent fuel container during handling and storage, or (3) to provide reasonable assurance that spent fuel can be received, handled, packaged, stored, and retrieved without undue risk to the health and safety of the public.

(2)

Yoke and rigid or sling lifting members are classified as "Safety Related" in accordance with 1 O CFR Part 50.

(3)

For safety classification of individual parts, see the drawings in Section 1.5.2.

ANUH-01.0150 2.5-3

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 4.4 Thermal Evaluation for Normal Conditions of Storage and Transfer 4.4.1 Overview of Thermal Analysis for Normal Conditions of Storage and Transfer This section of the UFSAR describes the thermal analysis of the AHSM and 24PT1-DSC. The analytical models of the AHSM, the 24PT1-DSC, and the transfer cask are described and the calculation results are summarized below. The thermophysical properties of the Advanced NUHOMS System components used in the thermal analysis are listed in Section 4.2. The following evaluations are performed for the Advanced NUHOMS System:

1.

Thermal Analysis of the 24PT1-DSC in the AHSM (Section 4.4.2),

2.

Thermal Analysis of the 24PT1-DSC in the Transfer Cask (Section 4.4.3),

3.

Thermal Analysis of the 24PT1-DSC basket (Section 4.4.4).

4.4.2 Thermal Model of the 24PT1-DSC Inside the AHSM For normal condition of storage, the Advanced NUHOMS System components are evaluated for a range of design basis ambient temperatures. The system components are evaluated for the average ambient temperatures given in Table 4.1-1. Ambient temperatures within this range are assumed to occur for a sufficient duration to cause a steady-state temperature distribution in the Advanced NUHOMS System components. The lifetime average ambient temperature for the 40 year service life is taken as 70 °F. The "stress-free" temperature for material properties is also 70 °F.

The AHSM is cooled by a natural draft of air entering through the air inlet opening located in the lower front wall of the AHSM, and exiting through the air outlet opening located in the top of the AHSM. Cooler air at the prevailing ambient conditions is drawn into the AHSM. The cooler air flows from the bottom of the AHSM along the outer 24PT1-DSC surface where it is warmed by the decay heat of the spent fuel inside the 24PT1-DSC. The warmed air flows along the ceiling of the AHSM and exits through the air outlet opening. The AHSM vent geometries and flow paths for ventilation air are illustrated in Figure 4.4-1.

The AHSM roof and front wall are the primary concrete surfaces conducting heat to the outside environment. For the analytical purpose of calculating maximum temperatures, an AHSM centered in a group of AHSMs, each loaded with a 24PT1-DSC, is assumed. Rows of modules are assumed to exist back to back for this model. For the analytical purpose of calculating maximum concrete temperature gradients, an AHSM alone, with no adjacent modules or rear shield wall, is assumed.

A metal heat shield is placed around the upper half of the 24PTI-DSC to shield the AHSM concrete surfaces above and to the side of the 24PT1-DSC from thermal radiation effects. The location and geometry of the heat shield is shown in Figure 4.4-6 and on the AHSM drawings contained in Chapter 1. The heat shield protects the AHSM surfaces above and to the side of the 24PT1-DSC from direct thermal radiation emanating from the 24PT1-DSC surface and significantly increases' the combined surface area for convection cooling inside the AHSM. The ANUH-01.0150 4.4-1

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 temperature calculated in two consecutive iterations indicating that stable convergence is achieved. The remaining thermal-hydraulic parameters used in the AHSM heat transfer calculations are given in Section 4.4.3.

The results of the HEATING7 analysis for the AHSM are in the form of temperature distribution profiles. The resulting temperature profiles show the steady state temperature distribution of the 24PT1-DSC shell assembly at various locations throughout the AHSM.

The calculated AHSM concrete temperatures are used in the structural analysis for long term thermal loads which occur during normal operating conditions. The AHSM thermal analysis results are also used to obtain steady state temperature distributions for the outer surface of the 24PT1-DSC for the range of design basis ambient conditions. These steady state surface temperatures are used as a temperature boundary condition for the 24PT1-DSC model, described in Section 4.4.4.

4.4.2.3 Description of Cases Evaluated for the AHSM The AHSM thermal analyses are performed for the design basis normal ambient air temperatures defined in Section 4.1. These include a total of three cases with ambient air entering and/or surrounding the AHSM at the temperatures listed in Table 4.4-1, noting that a daily average of the maximum summer ambient condition was used in accordance with Section 4.1.

Temperature distributions of the concrete are used to determine thermal stresses in the structure for all three normal cases.

The AHSM thermal model also includes the 24PT1-DSC shell, top and bottom plates and shield plugs, as shown in Figure 4.4-2 and Figure 4.4-5. The temperature profiles generated for the top and bottom cover plates and shield plugs, as well as the cylindrical shell are used to determine thermal stresses within these components. The normal case-s which are considered are listed in Table 4.4-8.

4.4.2.4 AHSM Thermal Model Results The results of the AHSM thermal analysis.are shown in Table 4.4-3 for the heat shield, support steel and concrete for a heat load of24 kW. The maximum temperatures are compared to their material limits in Table 4.1-3 for normal operation. The 24PT1-DSC shell results for lower decay heats of 16 and 14 kW, which are used tci generate the 24PT1-DSC basket temperature profiles, are given in Table 4.4-4.

The maximum temperature results for the 24PT1-DSC shell assembly are given in Table 4.4-5 for a heat load of24 kW. Maximum temperatures of the 24PT1-DSC shell assembly are verified to be within their material limits, as defined in the ASME B&PV Code [ 4. 7] in Table 4.1-3 ( data provided in this table are the enveloping temperatures for the storage and transfer cases).

ANUH-01.0150 4.4-6

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 4.4.3 Thermal Model of24PT1-DSC in the Transfer Cask 4.4.3.1 Model Description The transfer cask analysis for the OS197 transfer cask has already been performed for 24 kW

[ 4.17]. For the current fuel types and heat loads considered, the same model is utilized with the ambient conditions consistent with Table 4.1-1. This model is an axisymmetric two dimensional model which includes the cask and the 24PT1-DSC shell assembly. The 24PT1-DSC cavity is modeled as a homogenous region. The 24PT1-DSC shell l:!-ssembly dimensions are nearly identical to those used in the previous analysis. The cover plates and shell assembly in the old model are stainless steel, type 304, as opposed to stainless steel, type 316 for the 24PT1-DSC design. But based on Section 4.4.3, the difference in thermal conductivity of these two materials is very small and would have a negligible impact on the results.

4.4.3.2 Description of Cases Evaluated for the 24PT1-DSC Inside OS 197 Transfer Cask The transfer cask normal thermal analyses are performed for the range of design basis ambient air temperatures defined in Section 4.1 for normal conditions. The transfer cask thermal analysis is not performed for the design life average temperature since this case is needed only for the storage in the AHSM to ensure the integrity of the fuel cladding and is enveloped by the other normal cases. In accordance with NUREG-1536 [4.5], the short term fuel cladding temperature limit applies to all transfer cask operations.

The thermal stress analysis of the 24PT1-DSC shell assembly is based on the temperature results from the previous analysis of the OS 197 cask and shell assembly with 24 kW heat load [ 4.17].

Three dimensional temperature profiles of the 24PT1-DSC shell and top and bottom cover plates and shield plugs are used from the prior results of the OS 197 transfer cask analysis with 24 kW heat load for use in thermal stress calculations. The cases which are used to determine thermal stresses for normal conditions are listed in Table 4.4-8.

New cases are performed only in order to provide 24PT1-DSC shell temperature boundary conditions for the 24PT1-DSC basket thermal model. A single temperature for the 24PT1-DSC shell is extracted from the results of the transfer cask thermal analysis for use in the 24PT1-DSC basket thermal analysis.

4.4.3.3 Transfer Cask Thermal Model Results The maximum temperature results for the shell assembly during transfer operations are presented in Table 4.4-5. These results are for 24 kW heat load, and are from the previous thermal analysis of the OS 197 transfer cask [ 4.17]. These results are used in the structural analysis described in Chapter 3. The maximum temperature of the 24PT1-DSC shell for 16 kW decay heat, which bounds the design basis decay heat of 14 kW, is given in Table 4.4-4. These temperatures are used as boundary conditions in the 24PT1-DSC basket thermal analysis presented in Section 4.4.5.

ANUH-01.0150 4.4-7

Advanced NUHOMS System Updated Final Safety Analysis Report ANUH-01.0150 Proprietary Information on This Page Withheld Pursuant to 10 CFR.2.390 4.4-9 Rev. 8, 08/18 I

Advanced NUHOMS System Updated Final Safety Analysis Report ANUH-01.0150 Proprietary Information on This Page Withheld Pursuant to 10 CFR 2.390 4.4-10 Rev. 8, 08/18 I

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table 4.4-12 Technical Specifications 5.2.5.b Temperature Monitoring Limits for the 24PT1-DSC Max Temp (°F)

Max Temp Rise (°F)

(in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

Single Thermocouple (y = 34.5", x = 0, z = 4.75")

225 801 Dual Thermocouple (y = 60", x = +/-15", z = -11.25")

175 82

1.

Based on a 24 kW DSC heat load, as noted in Technical Specification Section 5.2.5.b at the analyzed location in the AHSM base.

2.

Based on a 14 kW DSC heat load, at the dual "as-built" thermocouple locations provided in the AHSM roof. A limit of 3 °F applies if the surveillance period is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> instead of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ANUH-01.0150 4.4-25a

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 4.5 Thermal Evaluation for Off-Normal Conditions 4.5.1 Overview of Off-Normal Analysis For off-normal conditions of storage, the Advanced NUHOMS System components are evaluated for a range of extreme ambient temperatures listed in Table 4.1-1. Should these extreme conditions ever occur, they would be expected to last for a very short time.

Nevertheless, these ambient temperatures are conservatively assumed to occur for a sufficient duration to cause a steady-state temperature distribution in the Advanced NUHOMS System components. For off-normal and accident summer ambient conditions, 123 BTU/hr.-ft2, is conservatively applied to the AHSM roof surface. The enveloping solar heat flux of 123 Btu/hr-ft2 Reference [ 4.20] for the extreme off-normal case is based on a flat horizontal surface averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day [ 4.5]. Solar heat loads are conservatively neglected for the AHSM thermal analysis for off-normal winter ambient conditions. The solar heat loads are listed in Table 4.1-1.

The same models are used for the 24PT1-DSC inside the AHSM, the 24PT1-DSC inside the transfer cask, and the 24PT1-DSC basket as described in Sections 4.4.2, 4.4.3 and 4.4.4, respectively. For the transfer cask, a sunshade is required to be placed over the cask for temperatures above 100°F. This requirement is listed in Reference [ 4.17].

4.5.2 Thermal Analysis Results The maximum AHSM temperatures for this condition are listed Table 4.4-3. The maximum 24PT1-DSC shell assembly temperatures for off-normal conditions are given in Table 4.4-5 for 24 kW, and Table 4.4-4 for 16 and 14 kW. The maximum 24PT1-DSC basket assembly temperatures for the 14 and 16 kW cases are given in Table 4.4-6. The maximum fuel cladding temperature results for off-normal conditions is given in Table 4.4-7. The AHSM, 24PT1-DSC, and fuel cladding maximum temperatures are compared against their limits in Table 4.1-4 or off-normal conditions.

The cases providing data for thermal stress analyses are given in Table 4.4-8.

4.5.3 Maximum Pressure The methodology for calculating the maximum pressure in the 24PT1-DSC cavity during off-normal conditions is described in Section 4.4.8. The criterion for the off-normal pressure is established by accounting for the possible presence of fission gases in the 24PT1-DSC cavity which will reduce the effective cover gas conductivity, and thus increase temperatures and pressures.

Based on the basket temperature results in Table 4.4-6 and the fuel cladding temperature results of Table 4.4-7, the maximum pressure in the 24PTI-DSC cavity for off-normal conditions will occur while it is in the transfer cask during the maximum normal summer ambient conditions.

These temperatures bound the maximum off-normal ambient temperature case because of the required sunshade over the cask. The resulting maximum average helium temperature for the off-normal case is given in Table 4.4-11.

ANUH-01.0150 4.5-1

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I maximum 24PT1-DSC basket component and fuel cladding temperatures with a steady state

• evaluation of the 24PT1-DSC basket.

The initial conditions for the transient analysis correspond to the steady state temperatures calculated at the off-normal analysis extreme ambient temperatures. The heat source included in the analysis is 24 kW for the qualification of the concrete and 14 kW for the qualification of the 24PT1-DSC. The solution is carried out to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. At that time, corrective action is required to restore natural circulation air flow to the AHSM. The maximum concrete temperature during the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> blocked vent condition is given in Table 4.4-3. The maximum 24PT1-DSC shell assembly and basket component temperatures for the blocked vent accident are given in Table 4.4-5 and Table 4.4-6, respectively. The maximum fuel cladding temperature for the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> blocked vent accident are given in Table 4.4-7.

These temperatures are below the associated safety limits for the AHSM or 24PT1-DSC. The short time exposure of the 24PT1-DSC and the spent fuel assemblies to the elevated temperatures will not cause any damage. The maximum 24PT1-DSC internal pressure during this event is calculated in Section 4.6.6.

In order to calculate the maximum thermal stresses in the concrete, additional runs were made with the side surfaces of the AHSM exposed to the prevailing ambient conditions to maximize gradients in the concrete, as discussed in Section 4.4.2.2. The thermal-induced stresses for the blocked vent case are presented for the AHSM in Chapter 3. Temperature profiles for both extreme ambient conditions were derived for the AHSM concrete for determining thermal stresses. These cases are listed in Table 4.4-8.

4.6.3 Transfer Cask Loss of Neutron Shield and Sunshade The transfer cask and 24PT1-DSC are analyzed for a postulated accident in which the transfer cask loses the water annular neutron shielding and the required sunshade during transfer at the extreme off-normal summer ambient condition given in Table 4.1-1. Even though such a scenario would likely result in immediate corrective action, the duration of the accident is conservatively assumed to result in steady state temperature distributions in the transfer cask and 24PT1-DSC. This analysis was performed previously to support the addition of the OS197 transfer cask to the NUHOMS design described in Reference [ 4.17]. Therefore, the cask has already been analyzed for such an event. As described in Section 4.4.3, an identical model was used with a conservative heat load of 16 kW to determine the 24PT1-DSC shell temperatures so that an analysis of the 24PT1-DSC basket could be performed. The resulting maximum shell temperature is listed Table 4.4-4 for a conservative heat load of 16 kW. The 24PT1-DSC basket model used to determine the maximum fuel cladding and 24PT1-DSC basket component maximum temperatures is identical to that described in Section 4.4.4. This model is analyzed with 14 kW heat load for the shell temperature boundary condition derived for 16 kW heat load.

The resulting maximum 24PT1-DSC basket component temperatures are listed in Table 4.4-6.

The results in Table 4.4-6 show that this accident is bounded by the blocked vent analysis so that end point criteria for the 24PT1-DSC, such as cavity pressure, fuel cladding integrity, compliance of the 24PT1-DSC structural materials with ASME B&PV Code temperature limit criteria of the blocked vent scenario can be used.

ANUH-01.0150 4.6-2

Advanced NUHOMS System Updated Final Safety Analysis Report Rev.8,08/18 I 4.6.4 Fire Accident Evaluation The Advanced NUHOMS System will be stored on a concrete basemat away from combustible material. Therefore, a credible fire would be very small and of short duration such as that due to a fire or explosion from a vehicle or portable crane. A hypothetical *fire accident is evaluated for the Advanced NUHOMS System based on a fuel fire, the source of fuel being a ruptured fuel tank of the canister transporter tow vehicle or any other source of combustible fuel. The bounding capacity of combustible fuel is assumed to be 300 gallons and the bounding hypothetical fire is an engulfing fire. In addition, the postulated fire can only occur during transfer operations when personnel will be present to rapidly effect extinguishment of the fire.

From IAEA requirements [4.23] for a transport (10 CFRPart 71) condition, the "pool" of fuel is assumed to extend 1 meter beyond the ends of the cask. For this analysis, a pool diameter of 201.5 inches, which is approximately 6 inches shorter than the nominal length of the cask is conservatively assumed to engulf the entire cask. The thickness of this fuel pool would be 2.17 inch. A fuel consumption rate of 0.15 in/min. was selected from a Sandia Report [4.24]

concerning gasoline/tractor kerosene experimental burning rates. Therefore, the 300 gallons of fuel will sustain a fire for about 14 minutes and hence a 15 minute fire is conservatively evaluated. The fire parameters, other than time duration, from 10 CFR 71.73 [4.20] are used.

The recommended fire temperature is 1475°F. Forced convection from the fire to the cask is described by using a constant heat transfer coefficient of 5.21E-4 Btu/min-in2-°F, which is conservative based on measurements made at fire tests [ 4.24]. The recommendations of 10 CFR 71.73 are also used to determine the radiation heat transfer from the fire to the cask.

This conservative fire evaluation is only performed to demonstrate the confinement integrity and fuel retrievability of the Advanced NUHOMS System.

The model of the 24PT1-DSC inside the OS197 transfer cask which is described in Section 4.4.3 is used to determine the response of the DSC to the fire described above. The external boundary conditions of the OS 197 transfer cask are set to the fire temperature and forced convection

• boundary conditions during the fire. Following the fire, the cask is subjected to the prevailing maximum off-normal ambient conditions. The initial temperature distribution is conservatively calculated at steady state conditions at the maximum off-normal ambient temperature with no sunshade. The transient analysis was performed in two steps; the fifteen-minute fire followed by a post fire heatup of the OS197 transfer cask and 24PT1-DSC. During the post fire heatup period, complete loss of the water in the annular neutron shield of the OS197 cask is assumed.

Chapter 11 provides an evaluation of the effect on doses as a result of the potential loss of the neutron shield. The points monitored in the OS197 cask and 24PT1-DSC shell assembly are; (1) cask annular water neutron shield region, (2) cask structural steel, (3) the cask lead, (4) the 24PT1-DSC shell assembly, and (5) the cask lid.

The results of the analysis show that the cask neutron shields will be compromised as a result of the fire, but this will not impact the retrievability of the fuel, since the 24PT1-DSC shell assembly components are well within allowable temperatures. The maximum calculated DSC shell temperature for this conservative fire condition is 467 °F. Comparing this to the results for the 24PT1-DSC in Table 4.4-4 shows that this extremely conservative fire accident is bounded ANUH-01.0150 4.6-3

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I 4.7 Thermal Evaluation for Loading/Unloading Conditions All fuel transfer operations occur when the 24PT1-DSC is in the spent fuel pool. The fuel is always submerged in free-flowing pool water permitting heat dissipation. After fuel loading is complete, the 24PT1-DSC is removed from the pool, drained, dried, and backfilled with helium.

The two loading conditions evaluated for the Advanced NUHOMS System are the heatup of the 24PT1 ~DSC before its cavity can be backfilled with helium and the vacuum drying transient.

Transient thermal analyses are performed to predict the heatup time history for the 24PT1-DSC components during these events.

The unloading operation considered is the reflood of the 24PT1-DSC with water.

4.7.1 Vacuum Drying Thermal Analysis Analyses were performed for the vac,uum drying condition in order to ensure that the fuel cladding and 24PT1-DSC structural component temperatures remain below the maximum allowable limits shown in Table 4.7-1. For every component except the spacer disc, steady state temperature distributions gave satisfactory results. To show compliance with the ASME B&PV Code [ 4. 7] temperature limits for the spacer disc material, transient analyses were performed to determine the time to reach 700°F, the temperature limit for SA-537, Class 2 plate. These time limits for the vacuum drying case are shown in Table 4.7-2.

For the steady state analysis, the model is similar to the model described in Section 4.4.3 and shown in Figure 4.4-6, Figure 4.4-7, and Figure 4.4-8. The exception is that the helium regions are replaced with air. Assuming that the cavity is filled with air during the vacuum drying operation provides conservative results since during the majority of the vacuum drying operation, the 24PT1-DSC cavity void volume is filled with a mixture of air, water and water vapor, and no credit is taken for evaporation of water, which is a strong cooling mechanism that takes place during this operation. Air thermal conductivity does not change significantly at lower pressures, therefore, the use of a thermal conductivity for a pressure higher than 3 Torr is acceptable. In accordance with Chapter 8, water is required to be in the annulus between the 24PT1-DSC and the transfer cask during the vacuum drying process. Therefore, the 24PT1-DSC shell boundary is set to a temperature of 230°F as a conservative estimate of the shell wall temperature during this operation. A heat load of 14 kW is considered in computing the maximum fuel cladding temperature. The 14 kW heat load is also used to calculate the maximum 24PT1-DSC component temperatures. The resulting maximum temperatures are tabulated in Table 4.4-6 and Table 4.4-7 for the basket structural components and fuel cladding respectively.

For the transient analysis, the model from Section 4.4.4 is used with the constant temperature boundary condition described above and the change to the helium regions described above. The density and specific heat of the basket materials and fuel assembly from Section 4.2 are also used in the HEATING7 model. The time transient is measured from the beginning of the blowdown procedure to the beginning of the final helium backfill procedure. Therefore, the initial temperature of the basket is conservatively set to the saturation temperature of water as an initial condition. The transient vacuum drying case is performed for heat loads of 13 and 14 kW.

ANUH-01.0150 4.7-1

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 The Advanced NUHOMS System finite difference model discussed in Section 4.4.3 is modified for this transient analysis. The 24PT1-DSC inside the transfer cask model is modified to omit the top and bottom 24PT1-DSC cover plates and the top and bottom cask cover plates. Hence, the model conservatively does not credit any heat transfer in the axial direction. Homogenized effective thermal properties of the 24PT1-DSC cavity are calculated based on the weight, volume and material of the components. Radiation heat transfer within the 24PT1-DSC cavity is neglected. All temperatures in the 24PT1-DSC are initially assumed to be at the maximum spent fuel pool temperature. The exterior of the cask is assumed to radiate and convect heat to the prevailing ambient conditions of the fuel building. The analyses are performed for two separate maximum building and fuel pool conditions, which are given in Table 4.7-3. The results are tabulated in Table 4.7-3 and shown in Figure 4.7-2 for canister decay heat loads ranging from 10 to 14 kW for the 2 cases.

4. 7.4 Pressure During Loading of Cask The maximum pressure during cask blowdown is 20 psig (hydrostatic pressure of DSC water is balanced by hydrostatic pressure of DSC cask annulus). This is discussed in Chapter 3.

ANUH-01.0150 4.7-3

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j TABLE OF CONTENTS Page A.I GENERAL INFORMATION.................................................................................................. A.I.1-1 A.2 A. I. I Introduction............................................................................................................. A.1.1-2 A.1.2 General Description of the Advanced NUHOMS System.................................... A.1.2-1 A.1.3 A.1.4 A.I.5 A. l.2.1 Advanced NUHOMS System Characteristics.................................. A.1.2-1 A.1.2.2 Operational Features.......................................................................... A.1.2-2 A.1.2.3

• 24PT4-DSC Contents......................................................................... A.1.2-3 Identification of Agents and Contractors................................................................ A.1.3-1 Generic Cask Arrays............................................................................................... A.1.4-1 Supple1nental Data.................................................................................................. A.1.5-I A.1.5.1 References.......................................................................................... A. I.5-1 A.1.5.2 Drawings............................................................................................ A.I.5-1 PRINCIPAL DESIGN CRITERIA................................................. :....................................... A.2.1-1 A.2. I Spent Fuel*to be Stored........................................................................................... A.2.1-1 A.2.1.1 Detailed Payload Description............................................................. A.2.1-1 A.2.2 Design Criteria for Environmental Conditions and Natural Phenomena................ A.2.2-1 A.2.2.1 Tornado and Wind Loadings.............................................................. A.2.2-I A.2.2.2 Water Level (Flood) Design.............................................................. A.2.2-1 A.2.2.3 Seismic Design................................................................................... A.2.2-2 A.2.2.4 Snow and Ice Loadings...................................................................... A.2.2-2 A.2.2.5 Tsunami.............................................................................................. A.2.2-2 A.2.2.6 Lightning............................................................................................ A.2.2-2 A.2.2.7 Combined Load Criteria..................................................................... A.2.2-2 A.2.2.8 Burial Under Debris........................................................................... A.2.2-3 A.2.2.9 Thermal Conditions............................................................................ A.2.2-3 A.2.3 Safety Protection Systems....................................................................................... A.2.3-1 A.2.3.1 General............................................................................................... A.2.3-1 A.2.3.2 Protection by Multiple Confinement Barriers and Systems............... A.2.3-1 A.2.3.3 Protection by Equipment and Instrumentation Selection................... A.2.3-3 A.2.3.4 Nuclear Criticality Safety................................................................... A.2.3-3 A.2.3.5 Radiological Protection...................................................................... A.2.3-4 A.2.3.6 Fire and Explosion Protection............................................................ A.2.3-5 A.2.3.7 Acceptance Tests and Maintenance................................................... A.2.3-5 A.2.4 Decommissioning Considerations........................................................................... A.2.4-1 A.2.5 Structures, Systems and Components Important to Safety..................................... A.2.5-1 A.2.5.1 Dry Shielded Canister

............................................. A.2.5-1 A.2.5.2 Advanced Horizontal Storage Module............................................... A.2.5-1 A.2.5.3 ISFSI Basemat and Approach Slabs.................................................. A.2.5-1 A.2.5.4 Transfer Equipment............................................................................ A.2.5-2 A.2.5.5 Auxiliary Equipment.......................................................................... A.2.5-2 A.2.6 Supplemental Information....................................................................................... A.2.6-I A.2.6.1 References.......................................................................................... A.2.6-1 ANUH-01.0150

___ _J

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8,.08/18 j A.3 A.4 STRUCTURAL EVALUATION............................................................................................. A.3.1-1 A.3.1 Structural Design..................................................................................................... A.3.1-1 A.3.2 A.3.3 A.3.4 A.3.5 A.3.6 A.3.1.1 Discussion........................................................................................... A.3.1-1 A.3.1.2 24PT4-DSC and AHSM Design Criteria........................................... A.3.1-3 Weights and Centers of Gravity.............................................................................. A.3.2-1 Mechanical Properties of Materials............,............................................................ A.3.3-1 A.3.3.1 24PT4-DSC Material Properties........................................................ A.3.3-1 A.3.3.2

• AHSM Material Properties................................................................ A.3.3-2 A.3.3.3 Materials Durability........................................................................... A.3.3-2 General Standards for 24PT4-DSC and AHSM...................................................... A.3.4-1 A.3.4.1 Chemical and Galvanic Reactions..................................................... A.3.4-1 A.3.4.2 Positive Closure................................................................................. A.3.4-1 A.3.4.3 Lifting Devices................................................................................... A.3.4-2 A.3.4.4 Heat.................................................................................................... A.3.4-2 A.3.4.5 Cold.................................................................................................... A.3.4-4 Fuel Rods General Standards for 24PT4-DSC........................................................ A.3.5-1 A.3.5.1 Fuel Rod Temperature Limits for Westinghouse-CENP, Combustion Engineering 16xl 6 Fuel................................................. A.3.5-1 A.3.5.2 Fuel Assembly Thermal and Irradiation Growth............................... A.3.5-1 A.3.5.3 Fuel Rod Integrity During Drop Scenario.......................................... A.3.5-2 A.3.5.4 Fuel Unloading................................................................................... A.3.5-2 Supplemental Data..........................................................................................,....... A.3.6-1 A.3.6.1 24PT4-DSC StructuralAnalysis........................................................ A.3.6-1 A.3.6.2 Structural Analysis of the AHSM.................................................... A.3.6-17 A.3. 7 References............................................................................................................... A.3. 7-1 THERMAL EVALUATION...................................................................................................... A.4-1 A.4.1 Discussion............................................................................................................... A.4.1-1 A.4.2 A.4.3 A.4.4 A.4.5 A.4.6 A.4.1.1 Overview and Purpose of Thermal Analysis..................................... A.4.1-1 A.4.1.2 Thermal Load Specification/ Ambient Temperature.......................... A.4.1-1 Summary of Thermal Properties of Materials......................................................... A.4.2-1 Specifications for Components............................................................................... A.4.3-1 Thermal Evaluation for Normal and Off-Normal Conditions of Storage and Transfer................................................................................................................... A.4.4-1 A.4.4.1 Overview of Thermal Analysis for Normal and Off-Normal A.4.4.2 A.4.4.3 A.4.4.4 A.4.4.5 A.4.4.6 A.4.4.7 A.4.4.8 A.4.4.9 A.4.4.10 Conditions of Storage and Transfer................................................... A.4.4-1 Thermal Analysis of24PT4-DSC in the AHSM................................ A.4.4-1 Thermal Analysis of 24PT4-DSC in the TC...................................... A.4.4-5 24PT4-DSC Basket Thermal Analysis............................................... A.4.4-6 Test Model....................................................................................... A.4.4-10 Maximum Temperatures.......................,........................................... A.4.4-10 Minimum Temperatures................................................................... A.4.4-10 Maximum Internal Pressure............................................................. A.4.4-10 Maximum Thermal Stresses............................................................. A.4.4-11 Evaluation of System Performance for Normal Conditions of Storage and Transfer........................................................................ A.4.4-12 Thermal Evaluation for Off-Normal Conditions..................................................... A.4.5-1 Thermal Evaluation for Accident Conditions......................................................... A.4.6-1 ANUH-01.0150 ii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I A.4.7 A.4.8 A.4.9 A.4.10 A.4.6.1 A.4.6.2 A.4.6.3 A.4.6.4 A.4.6.5 A.4.6.6 A.4.6.7 Accident Ambient Conditions............................................................ A.4.6-1 Blockage of AHSM Inlet and Outlet Vents....................................... A.4.6-1 TC Loss of Neutron Shield and Sunshade......................................... A.4.6-4 Fire Accident Evaluation................................................................... A.4.6-4 Flood Accident................................................................................... A.4.6-5 Maximum Pressure............................................................................. A.4.6-5 Evaluation of System Perfonnance for Accident Conditions of Storage and Transfer.......................................................................... A.4.6-5 Thermal Evaluation for Loading/Unloading Conditions......................................... A.4.7-1 A.4.7.1 Vacuum Drying Thermal Analysis.................................................... A.4.7-1 A.4.7.2 Pressure during Unloading of Cask.................................................... A.4.7-5 A.4.7.3 Cask Heatup Analysis........................................................................ A.4.7-5 A.4.7.4 Pressure During Loading of Cask...................................................... A.4.7-6 Confirmatory Thermal Analysis of the 24PT4-DSC............................................... A.4.8-1 Determination of Effective Thermal Conductivity of CE 16x16 Fuel Assemblies.............................................................................................................. A.4.9-1 A.4.9.1 Transverse Thermal Conductivity of Fuel in Helium and Vacuum.............................................................................................. A.4.9-1 A.4.9.2 Axial Thermal Conductivity of Fuel.................................................. A.4.9-3 Validation ofFLUENT'/ICEPAK' Computer Codes against NUHOMS-7P Test Data...................................................................................... A.4.10-1 A.4.11 Supplemental Information..................................................................................... A.4.11-1 A.4.11.1 References........................................................................................ A.4.11-1 A.5 SHIELDING EVALUATION................................................................................................. A.5.1-1 A.5.1 Discussion and Results............................................................................................ A.5.1-3 A.5.2 Source Specification................................................................................................ A.5.2-1 A.5.2.1 Gamma Source................................................................................... A.5.2-4 A.5.2.2 Neutron Source Term...................,..................................................... A.5.2-4 A.5.2.3 Response Functions f<;>r Alternate Nuclear Parameters...................... A.5.2-4 A.5.3 Model Specification................................................................................................ A.5.3-1 A.5.3.1 Description ofthe Radial and Axial Shielding Configurations.......... A.5.3-1 A.5.3.2 Shield Regional Densities.................................................................. A.5.3-3 A.5.4 Shielding Evaluation............................................................................................... A.5.4-1 A.5.4.1 Computer Program............................................................................. A.5.4-1 A.5.4.2 Flux-to-Dose Rate Conversion........................................................... A.5.4-2 A.5.5 Supplemental Information....................................................................................... A.5.5-1 A.5.5.1 References.......................................................................................... A.5.5-1 A.5.5.2 Sample SAS2H Input Listing............................................................ A.5.5-3 A.5.5.3 Sample ANISN Model (Neutron Response Function for AHSM).............................................................................................. A.5.5-5 A.5.5.4 Sample AHSM MCNP Analysis Input Files..................................... A.5.5-9 A.5.5.5 Sample OS197H MCNP Analysis Input Files................................ A.5.5-79 A.6 CRITICALITY EVALUATION................................................................................................ A.6-1 A.6.1 Discussion and Results............................................................................................ A.6.1-1 A.6.2 Spent Fuel Loading................................................................................................. A.6.2-1 A.6.3 Model Specification................................................................................................ A.6.3-1 ANUH-01.0150 iii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I A.6.3.1 Description of Criticality Analysis Model......................................... A.6.3-1 A.6.3.2 Neutron Absorber Panel Material Efficacy........................................ A.6.3-5 A.6.4 Criticality Calculation............................................................................................. A.6.4-1 A.6.4.1 Calculational Method......................................................................... A.6.4-1 A.6.4.2 Normal Operating Conditions (NOC)................................................ A.6.4-1 A.6.4.3 Hypothetical Accident Conditions (HAC)......................................... A.6.4-4 A.6.4.4 Damaged Fuel Models....................................................................... A.6.4-4 A.6.4.5 Fuel Assembly Replacement............................................................ A.6.4-10 A.6.4.6 Assembly Reconstitution................................................................. A.6.4-10 A.6.4.7 Criticality Results............................................................................. A.6.4-10 A.6.4.8 Summary and Conclusions............................................................... A.6.4-12 A.6.5 Critical Benchmark Experiments............................................................................ A.6.5-1 A.6.5.1 Benchmark Experiments and Applicability....................................... A.6.5-1 A.6.5.2 Results of the Benchmark Calculations............................................. A.6.5-2 A.6.6 Supplemental Information....................................................................................... A.6.6-1 A.6.6.1 References.......................................................................................... A.6.6-1 A.6.6.2 KENO V.a Input Files......................................................................... A.6.6-2 A.7 CONFINEMENT..,............................................................................................... :................. A.7.1-1 A.7.1 Confinement Boundary......................................... :................................................. A.7.1-1 A.7.1.1 Confinement Vessel........................................................................... A.7.1-1 A. 7.1.2 Confinement Penetrations.................................................................. A. 7.1-2 A.7.1.3 Seals and Welds.................................................................................. A.7.1-2 A.7.1.4 Closure............................................................................................... A.7.1-2 A.7.1.5 Leak Testing Requirements............................................................... A.7.1-2 A.7.2 Requirements for Normal Conditions ofStorage.................................................... A.7.2-1 A.7.2.1 Release of Radioactive Material........................................................ A.7.2-1 A. 7.2.2 Pressurization of Confinement Vessel............................................... A. 7.2-1 A.7.3 Confinement Requirements for Hypothetical Accident Conditions........................ A.7.3-1 A.7.3.1 Fission Gas Products.......................................................................... A.7.3-1 A.7.3.2 Release ofContents............................................................................. A.7.3-1 A.7.4 Supplemental Data.................................................................................................. A.7.4-1 A. 7.4.1 Confinement Monitoring Capability.................................................. A. 7.4-1 A. 7.4.2 References.......................................................................................... A. 7.4-1 A.8 OPERA TING PROCEDURES................................................................................................ A.8.1-1 A.8.1 Procedures for Loading the 24PT4-DSC and Transfer to the AHSM.... :................ A.8.1-1 A.8.1.1 Narrative Description......................................................................... A.8.1-1 A.8.2 Procedures for Unloading the 24PT4-DSC............................................................. A.8.2-1 A.8.2.1 24PT4-DSC Retrieval from the AHSM............................................. A.8.2-1 A.8.2.2 Removal of Fuel from the 24PT4-DSC............................................. A.8.2-1 A.8.3 Supplemental lnformation....................................................................................... A.8.3-1 A.8.3.1 Other Operating Systems................................................................... A.8.3-1 A.8.3.2 Operation Support System................................................................. A.8.3-1 A.8.3.3 Control Room and/or Control Areas.................................................. A.8.3-1 A.8.3.4 Analytical Sampling........................................................................... A.8.3-1 A.8.3.5 References.......................................................................................... A.8.3-1 ANUH-01.0150 iv

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j A.9 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM.............................................. A.9.1-1 A.9.1 Acceptance Criteria................................................................................................. A.9.1-1 A.9.1.1 Visual Inspection................................................................................ A.9.1-1 A.9.1.2 Structural............................................................................................ A.9.1-1 A.9.1.3 Leak Tests and Hydrostatic Pressure Tests........................................ A.9.1-1 A.9.1.4 Components....................................................................................... A.9.1-1 A.9.1.5 Shielding Integrity.............................................................................. A.9.1-2 A.9.1.6 Thermal Acceptance.......................................................................... A.9.1-2 A.9.1.7 Neutron Absorber Tests..................................................................... A.9.1-2 A.9.1.8 Deleted............................................................................................... A.9.1-3 A.9.1.9 Tests forB 4C Encapsulated in Stainless Steel Tubes......................... A.9.1-3 A.9.2 Pre-Operational Testing and Maintenance Program............................................... A.9.2-1 A.9.2.1 Subsystems Maintenance................................................................... A.9.2-1 A.9.2.2 Valves, Rupture Discs, and Gaskets on Confinement Vessel.......... A.9.2-1 a A:9.3 Training Program.................................................................................................... A.9.3-1 A.9.3.1 Program Description.......................................................................... A.9.3-1 A.9.3.2 Retraining Program............................................................................ A.9.3-1 A.9.3.3 Administration and Records............................................................... A.9.3-1 A.9.4 Supplemental Information....................................................................................... A.9.4-1 A.9.4.1 References.......................................................................................... A.9.4-1 A.10 RADIATION PROTECTION............................................................................................... A.10.1-1 A. l 0.1 Ensuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable (ALARA)........................................... :............................ A.10.1-1 A. I 0.2 Radiation Protection Design Features................................................................... A.10.2-1 A.10.2.1 Advanced NUHOMS System Design Features.............................. A.10.2-1 A.10.2.2 Radiation Dose Rates....................................................................... A.10.2-1 A.10.2.3 AHSM Dose Rates.............,............................................................. A.10.2-4 A.10.2.4 ISFSI Array...................................................................................... A.10.2-5 A. l 0.3 Estimated Onsite and Offsite Dose Assessment.................................................... A.10.3-1 A.10.3.1 Occupational Exposures................................................................... A.10.3-1 A.10.3.2 Public Exposure............. '.................................................................. A.10.3-3 A. I 0.4 Supplemental Information...............,..................................................................... A.10.4-1 A. I 0.4.1 References........................................................................................ A. I 0.4-1 A.11 ACCIDENT ANALYSES......................................................................................................... A.11-1 A.11.1 Off-Normal Operations......................................................................................... A.11.1-1 A.11.1.1 Off-Normal Transfer Loads............................................................. A.11.1-1 A.11.1.2 Extreme Ambient Temperatures...................................................... A.11.1-1 A.11.1.3 Radiological Impact from Off-Normal Operations.......................... A.11.1-2 A.11.2 Postulated Accidents............................................................................................. A.11.2-1 A.11.2.1 Earthquake....................................................................................... A.11.2-1 A.11.2.2 Tornado Wind Pressure and Tornado Missiles................................ A.11.2-1 A.11.2.3 Flood................................................................................................ A.11.2-1 A.11.2.4 Fire/Explosion.................................................................................. A.11.2-2 A.11.2.5 Accidental Drop of the 24PT4-DSC Inside the Transfer Cask........ A.11.2-2 ANUH-01.0150 V

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j A.13 A.14 A.11.3 A.12 A.12.1 A.12.2 A.12.3 A.11.2.6 A.11.2.7 A.11.2.8 A.11.2.9 Lightning.......................................................................................... A.11.2-3 Blockage of Air Inlet and Outlet Openings...................................... A.11.2-3 Accidental Pressurization of the 24PT4-DSC.................................. A.11.2-3 Burial................................................................................................ A.11.2-4 A.11.2.10 Inadvertent Loading of a Newly Discharged Fuel Assembly.......... A.11.2-4 Supplemental Information..................................................................................... A.11.3-1 A.11.3.1 References........................................................................................ A.11.3-1 CONDITIONS FOR CASK USE: OPERA TING CONTROLS AND LIMITS OR TECHNICAL SPECIFICATIONS AND BASIS FOR TECHNICAL SPECIFICATIONS FOR24PT4 SYSTEM..................................... A.12-1 TECHNICAL SPECIFICATIONS.......................................................................... A.12-1 Functional and Operating Limits.............................................................................. A.12-2 Limiting Condition for Operation (LCO) and Surveillance Requirements (SR)

Applicability............................................................................................................. A.12-4 A.12.3.1 DSC Integrity.................................................................................... A.12-11 QUALITY ASSURANCE........................................................................................................ A.13-1 DECOMMISSIONING......................................................................................................... A.14.1-1 A.14.1 Decommissioning Considerations......................................................................... A.14.1-1 A.14.2 Supplemental Informational.................................................................................. A.14.2-1 A.14.2.1 References....................................................... :................................ A.14.2-1 ANUH-01.0150 vi

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I LIST OF TABLES Table A.1.2-1 Key Design Parameters of the Advanced NUHOMS System Components........................................................................................................ A. l.4-4 Table A.2.1-1 PWR Fuel Specification oflntact Fuel to be Stored in NUHOMS 24 PT 4-DSC........................................................................................................ A.2.1-4 Table A.2.1-2 PWR Fuel Specifications of Damaged Fuel to be Stored in NUHOMS 24PT4-DSC........................................................................................................ A.2.1-5 Table A.2.1-3 PWR Fuel Assembly Design Characteristics..................................................... A.2.1-6 Table A.2.1-4 Maximum Fuel Enrichment v/s Neutron Poison Requirements for 24PT4-DSC........................................................................................................ A.2.1-7 Table A.2.1-5 PWR Fuel Qualification Table for 1.26 kW per Assembly for the NUHOMS 24PT4-DSC.................................................................................... A.2.1-8 Table A.2.1-6 PWR Fuel Qualification Table for 1.2 kW per Assembly for the NUHOMS 24PT4-DSC.................................................................................... A.2.1-9 Table A.2.1-7 PWR Fuel Qualification Table for 1.0 kW per Assembly for the NUHOMS 24PT4-DSC............................,..................................................... A.2.l-10 Table A.2.1-8 PWR Fuel Qualification Table for 0.9 kW per Assembly for the NUHOMS 24PT4-DSC.................................................................................. A.2.1-11 Table A.2.1-9 PWR Fuel Qualification Table for 1.26 kW per Assembly for the NUHOMS 24PT4-DSC, Reconstituted Fuel with Stainless Steel Rods......... A.2.1-12 Table A.2.1-10 PWR Fuel Qualification Table for 1.2 kW per Assembly for the NUHOMS 24PT4-DSC, Reconstituted Fuel with Stainless Steel Rods......... A.2.1-13, Table A.2.1-11 Table A.2.1-12 PWR Fuel Qualification Table for 1.0 kW per Assembly for the NUHOMS 24PT4-DSC, Reconstituted Fuel with Stainless Steel Rods......... A.2.1-14 PWR Fuel Qualification Table for 0.9 kW per Assembly for the NUHOMS 24PT4-DSC, Reconstituted Fuel with Stainless Steel Rods......... A.2.1-15 Table A.2.5-1 Advanced NUHOMS System Major Components and Safety Classification...................................................................................................... A.2.5-3 Table A.3.1-1 Codes and Standards for the Design, Fabrication and Construction of 24PT4-DSC Principal Components.................................................................... A.3.1-6 Table A.3.1-2 Stress Criteria for Partial Penetration Pressure Boundary Welds..... '.................. A.3.1-7 Table A.3.1-3 24 PT 4-DSC Load Combinations and Service Levels........................................ A.3.1-8 Table A.3.1-4 24PT4-DSC Internal Pressure Loads............................................................... A.3.1-10 Table A.3.1-5 Alternatives to the ASME Code for the 24PT4-DSC (NB).............................. A.3.1-11 Table A.3.1-6 Alternatives to the ASME Code for the 24PT4-DSC Basket (NG/NF)........... A.3.1-12 Table A.3.2-1 Weights and Centers of Gravity of the 24PT4-DSC.......................................... A.3.2-2 Table A.3.3-1 Static Mechanical Properties for ASTM B29 Lead............................................ A.3.3-3 Table A.3.3-2 ASME Code Material Properties for SA-533 Grade B Class 1 Carbon Steel.................................................................................................................... A.3.3-4 Table A.3.3-3 ASME Code Material Properties for SA-4 79 Type XM-19.............................. A.3.3-5 ANUH-01.0150 vii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j Table A.3.5-1 Table A.3.5-2 Table A.3.5-3 Table A.3.5-4 Table A.3.6-1 Table A.3.6-2 Table A.3.6-3 Table A.3.6-4 Table A.3.6-5 Table A.3.6-6 Table A.3.6-7 Table A.3.6-8 Table A.3.6-9 Table A.3.6-10 Table A.3.6-11 Table A.3.6-12 Table A.3.6-13 Table A.3.6-14 Table A.4.1-1 Table A.4.1-2 Table A.4.1-3 Table A.4.4-1 Table A.4.4-2 Table A.4.4-3 Table A.4.4-4 Table A.4.4-5 Table A.4.4-6 Table A.4.4-7 ANUH-01.0150 Summary of Fuel Assembly Thermal and Irradiation Growth Calculations........................................................................................................ A.3.5-4 Fuel Assembly Properties................................................................................... A.3.5-5 Material Properties for Fuel Cladding................................................................ A.3.5-6 Fuel Assembly Loads..................................................... :................................... A.3.5-7 24PT4-DSC On-Site Load Combinations........................................................ A.3.6-18 24PT4-DSC Shell Assembly Normal and Off-Normal Operating Condition Maximum Stress Intensities............................................................ A.3.6-20 24PT4-DSC Shell Assembly Accident Condition Maximum Stress Intensities...................................................................... :.................................. A.3.6-21 24PT4-DSC Shell Assembly Results for Normal and Off-Normal Load Combinations................................................................................................... A.3.6-22 24PT4-DSC Shell Assembly Results for Accident Level C Load Combinations.................................................,................................................. A.3.6-23 24PT4-DSC Shell Assembly Results for Accident Level D Load Combinations................................................................................................... A.3.6-24 Summary of Spacer Disc Maximum Stress Ratios........................................... A.3.6-25 Summary of Guidesleeve Assembly Maximum Stress Ratios......................... A.3.6-26 Summary of Results for Support Rod Assemblies........................................... A.3.6-27 Maximum/Minimum Forces/Moments in the Rail Components in the Local System.................................................................................................. A.3.6-27a Maximum/Minimum Forces/Moments in the Rail Extension Plates in the Local System............................................................................................ A.3.6-27b Maximum/Minimum Axial Forces in the Cross Member Components......... A.3.6-27c Rail Component, Results of Evaluation......................................................... A.3.6-27 d Extension Plates and Cross Members, Results of Evaluation........................ A.3.6-27e Component Minimum and Maximum Temperatures in the Advanced NUH OMS System (Storage or Transfer Mode) for Normal Conditions.......... A.4.1-3 Component Minimum and Maximum Temperatures in the Advanced NUHOMS _System (Storage or Transfer Mode) for Off-Normal Conditions.......................................................................................................... A.4.1-4 Component Minimum and Maximum Temperatures in the Advanced NUHOMS System (Storage and Transfer) for Accident Conditions..... :......... A.4.1-5 AHSM Bulk Air Temperatures........................................................................ A.4.4-13 AHSM Thermal Analysis Results Summary.................................................... A.4.4-14 AHSM Peak Component Temperatures at Normal/Off-Normal Conditions........................................................................................................ A.4.4-15 24PT4-DSC Maximum Shell Temperatures for Normal/Off-Normal Conditions........................................................................................................ A.4.4-16 24PT4-DSC Maximum Shell Temperatures for Accident Conditions............. A.4.4-17 24PT4-DSC Basket Temperature Results........................................................ A.4.4-18 24PT4-DSC Maximum Fuel Cladding Temperature Results........................... A.4.4-19 viii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table A.4.4-8 Table A.4.4-9 Table A.4.4-10 Table A.4. 4-11 Table A.4.7-1 Table A.4.7-2 Table A.4.7-3 Table A.4.9-1 Table A.4.9-2 Table A.4.9-3 Table A.4.9-4 Table A.4.9-5 Table A.4.10-1 Table A.5.1-1 Table A.5.1-2 Table A.5.1-3 Table A.5.1-4 Table A.5.1-5 Table A.5.2-1 Table A.5.2-2 Table A.5.2-3 Table A.5.2-4 Table A.5.2-5 Table A.5.2-6 Table A.5.2-7 Table A.5.2-8 Table A.5.2-9 Table A.5.2-10 Table A.5.3-1 Table A.5.3-2 Table A.5.3-3 Table A.5.4-1 Table A.6.1-1 Table A.6.2-1 Table A.6.3-1 ANUH-01.0150 Summary of Cases Considered for Thermal Stress Analysis........................... A.4.4-20 Fuel Assembly Characteristics for Pressure Analysis...................................... A.4.4-21 24PT4-DSC Cavity Pressure Analysis Summary............................................. A.4.4-22 Technical Specifications 5.2.5.b Temperature Monitoring Limits for the 24PT4 DSC....................................................................................................... A.4.4-23 Gaps between Components of ANSYS Model at the Spacer Disc Plane........... A.4.7-7 Vacuum Drying Results following Blowdown with Air or Helium................... A.4.7-8 Summary of Water Heatup Calculation............................................................. A.4.7-9 Summary of Design Data For CE 16x16 Fuel Assembly Type......................... A.4.9-4 Thermal Properties Used in Calculation of Fuel Effective Conductivities........ A.4.9-5 CE 16xl 6 Computed Effective Transverse Thermal Conductivity.................... A.4.9-6 CE 16x16 Fuel Assembly Transverse Thermal Conductivities.......................... A.4.9-7 CE 16x16 Axial Thermal Conductivity.............................................................. A.4.9-7 Test Vs. Predicted Temperatures for 7P DSC in HSM.................................... A.4.10-5 Advanced NUHOMS System Shielding Materials.......................................... A.5.1-4 Summary of AHSM Dose Rates........................................................................ A.5.1-5 Transfer Cask (Loading/Unloading/Transfer Operations) Side Dose Rate Summary............................................................................................................ A.5.1-6 Transfer Cask (Loading/Unloading/Transfer Operations) Top End Dose Rate Summary.................................................................................................... A.5.1-7 Transfer Cask (Transfer Operations) Bottom End Dose Rate Summary........... A.5.1-7 Fuel Assembly Region Materials, Masses, and Lengths.................................... A.5.2-7 Elemental Composition of L WR Fuel-Assembly Structural Materials.............. A.5.2-8 Flux Fraction By Assembly Region................................................................... A.5.2-9 CASK-81 Energy Group Structure................................................................... A.5.2-10 Design Basis Gamma Sources (per assembly)................................................. A.5.2-11 Design Basis Neutron Source (per assembly).................................................. A.5.2-12 AHSM and TC "Response Function" for Evaluating Fuel with Alternate Parameters........................................................................................................ A.5.2-13 "Response Function" Evaluation of Design Basis Source Terms.. :................. A.5.2-14 "Response Function" Evaluation of Candidate Fuel Assembly Source Terms 57 GWd/MTU, 3.8 wt.% U-235, 8-year Cooled Fuel Case............................ A.5.2-15 Relative Contribution of Source Terms to Dose Rates.................................... A.5.2-16 Materials Composition and Atom Number Densities (Dry)............................... A.5.3-4 Materials Composition and Atom Densities During Decontamination and Wet' Welding Stage Calculation......................................................................... A.5.3-6 Flux to Dose Rate Conversion Factors............................................................... A.5.3-8 Normalized Bum-Up Shape for CE 16x16 Fuel Assembly............................... A.5.4-3 Summary of Limiting Criticality Evaluations for the CE 16xl6 Fuel Asse1nbly............................................................................................................ A.6.1-2 Fuel Parameters for Criticality Analysis of the CE 16x16 Fuel Assemblies...... A.6.2-1 Geometric Parameters Used in the Criticality Analysis***********************:************* A.6.3-7 ix

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table A.6.3-2 Table A.6.3-3 Table A.6.3-4 Table A.6.4-1 Table A.6.4-2 Table A.6.4-3 Table A.6.4-4 Table A.6.4-5 Table A.6.4-6 Table A.6.4-7 Table A.6.4-8 Table A.6.4-9 Table A.6.4-10 Table A.6.4-11 Table A.6.4-12 Table A.6.4-13 Table A.6.4-14 Table A.6.4-15 Table A.6.4-16 Table A.6.4-17 Table A.6.5-1 Table A.6.5-2 Table A.6.5-3 Table A.10.2-1 Table A.10.2-2 Table A.10.2-3 Table A.10.2-4 Table A.10.2-5 Table A.10.2-6 Table A.10.2-7 Table A.10.2-8 Table A.10.2-9 ANUH-01.0150 Parameters for Poison Material Used in Criticality Analysis........................... A.6.3-10 Comparison of Criticality Model vs. Drawing Parameters (DSC Parameters)....................................................................................................... A.6.3-11 Comparison of Criticality Model vs. Drawing Parameters (Bora!

Parameters)................... :................................................................................... A.6.3-13 Parametric Study Results - B-10 Areal density of 0.025 g/cm2 (Type A Basket).............................................................................................................. A.6.4-15 NOC Moderator Varying Results-B-10 Areal density of0.068 g/cm2 (Type B Basket)............................................................................................... A.6.4-16 NOC Moderator Varying Results - B-10 Areal density of0.025 g/cm 2

(Type A Basket)............................................................................................... A.6.4-17 HAC Moderator Varying Results - B-10 Areal density of 0.068 g/cm2 (Type B Basket)............................................................................................... A.6.4-18 HAC Moderator Varying Results - B-10 Areal density of 0.025 g/cm2 (Type A Basket)............................................................................................... A.6.4-19 Damaged Fuel, Rod Pitch Varying Results - B-10 Areal density of0.068 g/cm2 (Type B Basket)..................................................................................... A.6.4-20 Damaged Fuel, Rod Pitch Varying Results with Rod Addition or Subtraction....................................................................................................... A.6.4-21 Damaged Fuel, Single-ended Shear................................................................ A.6.4-22 Damaged Fuel, Double-ended Shear............................................................... A.6.4-22 Damaged Fuel, Rod Pitch Cases - External Moderator Density Varying........ A.6.4-23 Damaged Fuel, Single Shear Cases - External Moderator Density Varying............................................................................................................. A.6.4-23 Damaged Fuel, Double Shear Cases - External Moderator Density Varying............................................................................................................. A.6.4-24 Damaged Fuel, Bare Fuel Added..................................................................... A.6.4-24 Summary of Maximum Enrichment for the Damaged Fuel Assemblies.......... A.6.4-25 Empty Fuel Assembly Locations..................................................................... A.6.4-26 Reconstituted Fuel Assemblies........................................................................ A.6.4-26 Storage Requirements by Fuel Enrichment...................................................... A.6.4-26 Benchmarking Results........................................................................................ A.6.5-3 USL-1 Results.................................................................................................... A.6.5-7 USL Determination for Criticality Analysis....................................................... A.6.5-8 MCNP Front Detector Dose Rate Results for a Single AHSM........................ A.10.2-6 MCNP Side Detector Dose Rate Results for a Single AHSM......................... A.10.2-7 MCNP Back Detector Dose Rate Results for a Single AHSM........................ A.10.2-8 MCNP Front Detector Dose Rate Results for a 2xl O ISFSI............................ A.I 0.2-9 MCNP Side Detector Dose Rate Results for a 2xl O ISFSI............................ A.I 0.2-10 AHSM Gamma-Ray Spectrum Calculation Results....................................... A. I 0.2-11 AHSM Neutron Spectrum Calculations......................................................... A. I 0.2-12 Summary of AHSM Surface Activities.......................................................... A.10.2-13 ANISN Model Details.................................................................................... A.10.2-13 X

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j Table A.10.3-1 Advanced NUHOMS System Operations Estimated Time for Occupational Dose Calculations...................................................................... A.10.3-4 ANUH-01.0150 xi

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j Figure A.1.1-1 Figure A.1.2-1 Figure A.2.1-1 Figure A.2.1-2 Figure A.2.1-3 Figure A.2.1-4 Figure A.3.1-1 Figure A.3.1-2 Figure A.3.1-3 Figure A.3.1-4 Figure A.3.2-1 Figure A.3.2-2 Figure A.3.6-1 Figure A.3.6-2 Figure A.3.6-3 Figure A.3.6-4 Figure A.3.6-5 Figure A.3.6-6 Figure A.3.6-7 Figure A.4.4-1 Figure A.4.4-2 Figure A.4.4-3 Figure A.4.4-4 Figure A.4.4-5 Figure A.4.4-6 Figure A.4.4-7 Figure A.4.4-8 Figure A.4.4-9 Figure A.4.4-10 Figure A.4.4-11 Figure A.4.4-12 Figure A.4.4-13 ANUH-01.0150 LIST OF FIGURES Page Advanced NUHOMS System 24PT4-DSC...................................................... A.1.1-3 24PT4-DSC ASME Code Boundary.................................................................. A.1.2-5 24PT4-DSC Heat Load Configurations #1, kW/Assembly.............................. A.2.1-16 24PT4-DSC Heat Load Configurations #2, kW/Assembly.............................. A.2.1-17 24PT4-DSC Heat Load Configurations #3, kW/Assembly.............................. A.2.1-18 Location of Failed Fuel Cans Inside 24PT4-DSC............................................ A.2.1-19 Advanced NUHOMS System 24PT4-DSC Canister Shell Assembly............ A.3.1-13 Advanced NUHOMS System 24PT4-DSC Pressure Boundary Location............................................................................................................ A.3.1-14 Advanced NUHOMS System 24PT4-DSC Canister Basket (Side View)................................................................................................................ A.3.1-15 Advanced NUHOMS System 24PT4-DSC Canister Basket & Shell (Side and Top End View)................................................................................. A.3.1-16 Schematic Location of Center of Gravity of the 24 PT 4-DSC............................ A.3.2-3 Schematic Location of Center of Gravity of the 24PT4-DSC in the AHSM................................................................................................................ A.3.2-4 24PT4-DSC Shell Assembly Axisymmetric Analysis Analytical Model........ A.3.6-28 24PT4-DSC Shell Assembly 3D ANSYS Models........................................... A.3.6-29 24PT4-DSC Load Support for Shell and Spacer Disc Analyses...................... A.3.6-30 Typical 24PT4-DSC Spacer Disc ANSYS Model for In-Plane Loads (Half Symrnetry).............................................................................................. A.3.6-31 Typical 24PT4-DSC Spacer Disc ANSYS Model for In-Plane Loads (Full Symmetry)............................................................................................... A.3.6-32 Typical 24PT4-DSC Spacer Disc ANSYS Model for Out-of-Plane Loads (Quarter Symmetry)............................................................................... A.3.6-33 Load Application to 24PT4-DSC Spacer Disc................................................. A.3.6-34 Isometric, Wireframe View of the AHSM Model Layout................................ A.4.4-24 Isometric View of Seven (7) Axial Segments Used to Simulate DSC within Module.................................................................................................. A.4.4-25 Isometric View of24PT4-DSC & Heat Shield Layout within Model............. A.4.4-26 Elevation View of Meshing at Z-Y Plane of AHSM....................................... A.4.4-27 Temperature Distribution on 24PT4-DSC Surface.......................................... A.4.4-28 Temperature Distribution on AHSM Heat Shield Surfaces............................. A.4.4-29 Velocity Profile along Y-Z Plane at Center of AHSM.... :............... :................ A.4.4-30 Isometric, Wireframe View ofModel Layout.................................................. A.4.4-31 24PT4-DSC Spacer Disc Schematic................................................................ A.4.4-32 Plan View of Meshing at 24PT4-DSC Spacer Disc...........................,............. A.4.4-33

• 24PT4-DSC HLZC #1, kW/Assembly............................................................. A.4.4-34 24PT4-DSC HLZC #2, kW/Assembly............................................................. A.4.4-35 24PT4-DSC HLZC #3, kW/Assembly............................................................. A.4.4-36 xii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Figure A.4.4-14 Figure A.4.4-15 Figure A.4.4-16 Figure A.4.4-17 Figure A.4.4-18 Figure A.4.4-19 Figure A.4.4-20 Figure A.4.4-21 Figure A.4.4-22 Figure A.4.4-23 Figure A.4.4-24 Figure A.4.4-25 Figure A.4.4-26 Figure A.4.4-27 Figure A.4.4-28 Figure A.4.6-1 Figure A.4.6-2 Figure A.4.6-3 Figure A.4.7-1 Figure A.4.7-2 Figure A.4.7-3 Figure A.4.7-4 Figure A.4.7-5 Figure A.4.7-6 Figure A.4.7-7 Figure A.4.7-8 Figure A.4.7-9 Frgure A,.4.9-1 Figure A.4.9-2 ANUH-01.0150 24PT4-DSC Shell Temperatures, Bounding Condition in AHSM................... A.4.4-37 Fuel Cladding Temperature Distribution within 24PT4-DSC Basket, Bounding Condition in AHSM....................................................................... :.A.4.4-38 24PT4-DSC Spacer Disc Temperature Distribution, Bounding Condition in AHSM......................................................................................... A.4.4-39 24PT4-DSC Poison Sheet Temperature Distribution, Bounding Condition in AHSM......................................................................................... A.4.4-40 Velocity Distribution within 24PT4-DSC Basket, Bounding Condition in AHSM.......................................................................................................... A.4.4-41 24PT4-DSC Shell Temperatures, Bounding Condition in TC......................... A.4.4-42 Fuel Cladding Temperature Distribution within 24PT4-DSC Basket, Bounding Condition in TC............................................................................... A.4.4-43 24PT4-DSC Spacer Disc Temperature Distribution, Bounding Condition in TC................................................................................................ A.4.4-44 24PT4-DSC Poison Sheet Temperature Distribution, Bounding Condition in TC................................................................................................ A.4.4-45 Velocity Distribution within 24PT4-DSC Basket, Bounding Condition in TC................................................................................................................. A.4.4-46 Spacer Disc Radial Temperature Distribution (Storage Conditions)............... A.4.4-4 7 Spacer Disc Radial Temperature Distribution (Transfer Conditions, Hot)...... A.4.4-48 Spacer Disc Radial Temperature Distribution-40°F TC................................... A.4.4-49 Temperature along Vertical Lines through Basket, Bounding Condition in AHSM, HLZC #1......................................................................................... A.4.4-50 Temperature along Vertical Lines through Basket, Bounding Condition in TC.....................................................................-,........................................... A.4.4-51 Transient Temperatures of24PT4-DSC Components during Blocked Vent Case-HLZC # 1......................................................................................... A.4.6-6 Transient Temperatures of24PT4-DSC Components during Blocked Vent Case-HLZC #3.......................................................................................... A.4.6-6 OS197H Cask and 24PT4-DSC Response to Fire Accident.............................. A.4.6-7 Simplified Axial View of the 24PT4-DSC Basket Model............................... A.4.7-10 24PT4-DSC ANSYS Thermal Model; Front And Side Views........................ A.4.7-11 24PT4-DSC ANSYS Thermal Model, Spacer Disc......................................... A.4.7-12 24PT4-DSC ANSYS Thermal Model, Shell and Guidesleeve Assembly........ A.4.7-13 24PT4-DSC ANSYS Thermal Model, Fuel Assemblies.................................. A.4.7-14 Surface Elements for Radiation View Factor Calculation................................ A.4. 7-15 Gaps between Components of ANSYS Model.........................,...................... A.4.7-16 Maximum Fuel Cladding Temperature during Vacuum Drying Using Air for Blowdown............................................................................................ A.4.7-17 Time to Reach Boiling Conditions inside 24PT4-DSC Cavity........................ A.4.7-18 Perspective View of CE 16x16 Thermal Model (1/4 Segment)......................... A.4.9-8 Finite Element Modeling of 1/4 Segment CE 16xl6 Assembly........................ A.4.9-8 xiii

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Figure A.4.9-3 Figure A.4.9-4 Figure A.4.10-1 Figure A.4.10-2 Figure A.4.10-3 Figure A.4.10-4 Figure A.4.10-5 Figure A.4.10-6 Figure A.4.10-7 Figure A.4.10-8 Figure A.4.10-9 Figure A.4.10-10 Figure A.4.10-11 Figure A.4.10-12 Figure A.4.10-13 Figure A.4.10-14 Figure A.5.1-1 Figure A.5.1-2 Figure A.5.1-3 Figure A.5.1-4 Figure A.5.2-1 Figure A.5.2-2 Figure A.5.4-1 Figure A.5.4-2 Figure A.5.4-3 Figure A.5.4-4 Figure A.5.4-5 Figure A.5.4-6 Figure A.5.4-7 Figure A.5.4-8 Figure A.5.4-9 Figure A.5.4-10 Figure A.6.3-1 Figure A.6.3-2 Figure A.6.3-3 Figure A.6.3-4 Figure A.6.3-5 Figure A.6.4-1 Figure A.6.4-2 ANUH-01.0150 Effective Transverse Thermal Conductivity for 1.0 kW CE 16x16 Fuel Assembly - Helium Filled Condition................................................................. A.4.9-9 Effective Transverse Thermal Conductivity for 1.0 kW CE 16x16 Fuel Assembly -Air Filled Condition....................................................................... A.4.9-9 Layout ofNUHOMS-7P HSM Array for Performance Testing..................... A.4.10-7 General Geometry ofNUHOMS-7P Horizontal Storage Module.................. A.4.10-8 Thermocouple Location in Center Module (HSM-2)....................................... A.4.10-9 Thermocouple Locations 5'-2" from Front ofModules................................. A.4.10-10 Thermocouple Locations 7'-2" from Front of Modules................................. A.4.10-11 Thermocouple Locations 9'-3" from Front of Modules (Cetiter)................... A.4.10-12 Thermocouple Locations 15 '-6" from Front of Modules............................... A.4.10-13 Isometric, Wireframe View ofNUHOMS-7P HSM Model Layout............. A.4.10-14 Elevation View of Meshing along Axial Center Plane of7P HSM............... A.4.10-15 Temperature Distribution on 7P DSC Surface............................................... A.4.10-16 Temperature Distribution on Heat Shield Surfaces........................................ A.4.10-17 Temperature Distribution on Side & Rear Concrete Surfaces....................... A.4.10-18 Axial Velocity Profile.................................................................................... A.4.10-19 Velocity Profile along X-Y Plane at Center of Module................................. A.4.10-20 Advanced NUHOMS System (24PT4-DSC in AHSM) Shielding Configuration..................................................................................................... A.5.1-8 24PT4-DSC Shielding Configuration................................................................ A.5.1-9 Right Elevation Cross Section View of AHSM............................................... A.5.1-10 Shielding Configuration of the TC................................................................... A.5.1-11 ANISN AHSM Model...................................................................................... A.5.2-17 ANISN TC Model............................................................................................ A.5.2-18 AHSM Bottom MCNP Model, (x,z) Cut........................................................... A.5.4-4 AHSM Bottom MCNP Model, (y,z) Cut........................................................... A.5.4-5 AHSM Top MCNP Model, (x,z) Cut................................................................. A.5.4-6 AHSM Top MCNP Model, (y,z) Cut................................................................. A.5.4-7 OS197H MCNP Model...................................................................................... A.5.4-8 OS197H Cask MCNP Model-Top Section...................................................... A.5.4-9 OS 197H Cask MCNP Model-Bottom Section.............................................. A.5.4-10 OS 197H Cask MCNP Model (Top) during Decontamination......................... A.5.4-11 OS197H Cask MCNP Model (Top) during Wet Welding............................... A.5.4-12 OS197H Cask MCNP Model (Top) during Dry Welding................................ A.5.4-13 KENO V.a Model of the 24PT4-DSC Basket.................................................. A.6.3-14 Exploded View of KENO V.aModel.............................................................. A.6.3-15 Structure ofKENO V.a Model-UNIT 33...................................................... A.6.3-16 Structure of KENO V.a Model-UNIT 34...................................................... A.6.3-17 Cross Section of the CE 16x16 Fuel Assembly................................................ A.6.3-18 Fuel Assembly Cross Section Showing the Burnable Absorber Rod Configuration................................................................................................... A.6.4-27 Fuel Assemblies Located in the Inner Guidesleeve Comer Closest to the DSC Centerline (Assembly in Case)................................................................ A.6.4-29 xiv

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 j Figure A.6.4-3 Figure A.6.4-4 Figure A.6.4-5 Figure A.6.4-6 Figure A.6.4-7 Figure A.6.4-8 Figure A.6.4-9 Figure A.6.4-10 Figure A.6.4-11 Figure A.6.4-12 Figure A.6.4-13 Figure A.7.1-1 Figure A.8.1-1 Figure A.8.2-1 Figure A.10.2-1 Figure A.10.2-2 ANUH-01.0150 Fuel Assemblies Moved Radially Outwards from the Center of the 24PT4-DSC (Assembly Out Case)................................................................... A.6.4-30 Fuel Assemblies Moved Towards the Upper Left Corner of Each Guidesleeve Assembly Upper Left Corner Case.............................................. A.6.4-31 Single-ended Shear Model............................................................................... A.6.4-32 Double-ended Shear Model.............................................................................. A.6.4-33 Geometry with Bare Fuel Rods Added............................................................ A.6.4-34 Loading Pattern for 4 Damaged Fuel Assemblies...............,............................ A.6.4-35 Loading Pattern for 12 Damaged Fuel Assemblies.......................................... A.6.4-36 Fuel Assembly with Guide Tubes and Poison Rodlets.................................... A.6.4-37 Example of 4 Empty Fuel Assembly Locations............................................... A.6.4-3 8 Example of a Reconstituted Fuel Assembly..................................................... A6.4-39 Failed Fuel Cans Positions............................................................................... A.6.4-40 24 PT 4-DSC Confinement Boundary Welds...................................................... A. 7.1-4 Advanced NUHOMS System Loading Operations Flow Chart....................... A.8.1-9 Advanced NUHOMS System Retrieval Operations Flow Chart...................... A.8.2-6 Annual Exposure from a Single AHSM as a Function of Distance............... A.10.2-14 Annual Exposure from a 2x10 AHSM Array as a Function of Distance....... A.10.2-15 xv

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I A.1.5 Supplemental Data A.1.5.1 References

[Al.I]

U.S. Nuclear Regulatory Commission, Regulatory Guide 3.61, Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask, February 1989.

[ A 1.2]

IO CFR Part 72, Rules and Regulations, Title 10, Code of Federal Regulations -

Energy, U.S. Nuclear Regulatory Commission, Washington, D.C., "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste."

[Al.3]

Deleted.

[Al.4]

TN, Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 9, February 2006, US NRC Docket No. 72-1004.

[Al.5]

NRC Certificate of Compliance 1004, NUHOMS General License Spent Fuel Storage System, Amendment No. 8, December 2005, US NRC Docket No. 72-1004.

A.1.5.2 Drawings

- 24PT4-DSC: ANUH-01-4001, Rev. 7 ANUH-01.0150 A.1.5-1

8 I

H G

F E

D C

B A

8 I

7 I

6 I

5 1

4 I

3 I

2 Proprietary and Security Related Information for Drawing ANUH-01-4001-SAR, Rev. 7 Withheld Pursuant to 10 CFR 2.390 7

I 6

I 5

T 4

I 3

I 2

I H

G F

E D

C 1--

B A

I

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table A.2.5-1 Advanced NUHOMS System Major Components and Safety Classification 10 CFR Part 72 11>

COMPONENT(2J CLASSIFICATION Dry Storage Canister (24PT4-DSC)

Guidesleeves Important to Safety Spacer Discs Important to Safety Support Rods Important to Safety Shield Plugs (Top and Bottom)

Important to Safety Shell Important to Safety Cover Plates (Top and Bottom)

Important to Safety DSC Support Ring Important to Safety Siphon and Vent Block Important to Safety Siphon and Vent Port Cover Plates Important to Safety Grapple Ring and Grapple Support Important to Safety Weld Filler Metal Important to Safety Failed Fuel Can Important to Safety Electroless nickel coating Not Important to Safety Horizontal Storage Module (AHSM)

No change (See Table 2.5-1)

ISFSI Basemat and Approach Slabs No change (See Table 2.5-1)

Transfer Equipment No change (See Table 2.5-1)

Auxiliary Equipment No change (See Table 2.5-1)

(1)

Structures, systems and components "important to safety are defined in 10 CFR 72.3 as those features of the ISFSI whose function is (1) to maintain the conditions required to store spent fuel safely, (2) to prevent damage to the spent fuel container during handling and storage, or (3) to provide reasonable assurance that spent fuel can be received, handled, packaged, stored, and retrieved without undue risk to the health and safety of the public.

(2)

For safety classification of individual parts, see the drawings in Section A.1.5.2.

ANUH-01.0150 A.2.5-3

I.

I I

I Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I Table A.4.4-11 Technical Specifications 5.2.5.b Temperature Monitoring Limits for the 24PT4 DSC Max Temp Rise Max Temp (°F)

(DF)

(in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

Single Thermocouple (y = 34.5", x = 0, z = 4.75")

225 30<1)

Dual Thermocouple (y = 60", x = +/-15", z = -11.25")

200 5(2)

1.

Based on a 24 kW DSC heat load, as noted in Technical Specification Section 5.2.5.b. at the analyzed location in the AHSM base.

2.

Based on a 24 kW DSC heat load, as noted in Technical Specification Section 5.2.5.b. at the "as-built" dual thermocouple locations provided in the AHSM roof.

ANUH-01.0150 A.4.4-23

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 J

Table B.2.5-1 NUHOMS 32PTH2 System Major Components and Safety Classification Componentr1J 32PTH2 DSC Assembly DSC shell Inner and outer bottom cover plates Top and bottom shield plugs Inner and outer top cover plates Siphon/vent port cover plate Siphon and vent block

. DSC support ring Grapple ring and support Test port plug Weld filler metal Siphon tube Quick connect coupling Male connector Electroless nickel coating 32PTH2 DSC Basket Assembly Fuel compartment Poison plate Basket plate Basket support plates (inserts)

Basket rail Weld filler metal Top and bottom End Caps Alignment key AHSM-HS Reinforced Concrete 32PTH2 DSC Support Rail Thermal Instrumentation AHSM-HS/OS200FC TC Restraint Galvanized and zinc rich coatings ISFSI Basemat and Approach Slabs Transfer Equipment OS200FC TC OS200FC TC Lifting Yoke Transfer Trailer/Skid Ram Assembly Dry Film Lubricant Auxiliary Equipment Vacuum Drying System Automated Welding System OS200FC TC/32PTH2 DSC Annulus Seal 10 CFR Part 72 Classification Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Important to Safety Not Important to Safety Important to Safety Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Important to Safety Safety Related Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety Not Important to Safety (1)

For safety classification of individual parts, see the drawings in Section 8.1.5.2.

ANUH-01.0150 B.2.5-3

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I

5.

Connect the TC drain line to the TC, open the TC cavity drain port and allow water from the annulus to drain out until the water level is approximately twelve inches below the top edge of the 32PTH2 DSC shell. Take swipes around the outer surface of the 32PTH2 DSC shell and check for smearable contamination in accordance with the Technical Specification 5.2.4.d limits.

CAUTION: Verify that no inadvertent draining of the TC neutron shield water has occurred.

CAUTION: Radiation dose rates are expected to be high at the vent and siphon port locations. Use proper ALARA practices (e.g., use of temporary shielding, appropriate positioning of personnel, etc.) to minimize personnel exposure.

6.

Drain approximately 60 gallons of water (as indicated on a flowmeter) from the 32PTH2 DSC back into the fuel pool or other suitable location. Consistent with ISG-22 [B8.6]

guidance and Technical Specification 3.1.1.c, helium at 1-3 psig is used to baclifill the DSC with an inert gas as water is being removed.from the DSC. This will lower the water level in the DSC cavity approximately four inches below the bottom of the shield plug. As only the very top of the stainless steel end fittings of the fuel assembly are uncovered during this step, the DSC cavity does not require a helium backfill.

7.

8.

CAUTION: Hydrogen concentration must be monitored as described in Step 10 below to ensure that the maximum allowable concentration of 2.4% is not exceeded.

Monitor TC/DSC annulus water level to be approximately twelve inches below the top of the DSC shell and replenish as necessary until drained.

Possible approaches to monitoring/replenishing include, but are not limited to, monitoring the annulus water level using a sight glass ( or tube) attached to the cask annulus drain port. *.

Install the automated welding machine onto the inner top cover plate and place the inner top cover plate with the automated welding machine onto the 32PTH2 DSC. Optionally, the inner top cover plate and the automated welding machine can be placed separately.

Verify proper fit-up of the inner top cover plate with the 32PTH2 DSC shell.

9.

Check radiation levels on the surface of the inner top cover plate. Temporary shielding may be installed as necessary to minimize personnel exposure.

10.

Continuous hydrogen monitoring of the 32PTH2 DSC cavity during welding of the inner top cover plate is required [B8.2]. Connect a hydrogen monitor to the vent port using flexible tubing or a quick disconnect stem fitting to allow continuous monitoring of the atmosphere in the 32PTH2 DSC cavity during welding of the inner cover plate, in compliance with Technical Specification 5.2.6. Optionally, other methods may be used for continuous monitoring of the hydrogen concentration in the 32PTH2 DSC cavity during welding of the inner top cover plate, to comply with the Technical Specification.

11.

Cover the TC/32PTH2 DSC annulus to prevent debris and weld splatter from entering the annulus.

12.

Ready the automated welding machine and tack weld the inner top cover plate to the 32PTH2 DSC shell. Complete the inner top cover plate weldment (a minimum of two passes is required) and remove the automated welding machine.

ANUH-01.0150 B.8.1-5

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I

13.

14.

15.

16.

17.

18.

19.

20.

CAUTION: Per Technical Specification 5.2.6, continuously monitor the hydrogen concentration in the 32PTH2 DSC cavity using the arrangement or other alternate methods described in Step 10 during the inner top cover plate welding operations. Verify that the measured hydrogen concentration does not exceed a safety limit of 2.4% [B8.2]

and [B8.3]. If this limit is exceeded, stop all welding operations and purge the 32PTH2 DSC cavity to reduce the hydrogen concentration safely below the 2.4% limit.

Perform dye penetrant weld examination of the root and final layers of the inner top cover plate to shell weld in accordance with the Technical Specification 4.3.2 requirements.

Remove purge lines and connect the VDS to the 32PTH2 DSC siphon and vent ports.

Install temporary shielding to minimize personnel exposure throughout the subsequent welding operations as required.

a. If using the blowdown method to remove the cavity water, engage the helium supply (up to 20 psig) and open the valve on the vent port and allow helium to force the water from the 32PTH2 DSC cavity through the siphon port. Use of helium is required per Technical Specification 3.1.1. c.

b. If using water pumps to remove water without blowdown, pump water from the 32PTH2 DSC while backfilling the cavity with helium.

CAUTION: Prior to removal of DSC cavity water, refill the DSC cavity with water to replace residual air with water. Do not over pressurize the cavity.

NOTE: Due to thermal expansion of DSC cavity water during welding operations, only approximately 30 gallons of water will be required to refill the DSC cavity.

Once the water stops flowing from the 32PTH2 DSC, close the siphon port and disengage the helium source and/or turn off the suction pump, as applicable.

Verify that the TC dose rates are compliant with the limits specified in Technical Specification 5.2.4.f.

Connect the hose from the vent port and the siphon port to the intake of the vacuum pump. Connect a hose from the discharge side of the VDS to the plant's radioactive waste system or spent fuel pool. Connect the VDS to a helium source.

CAUTION: Proceed cautiously when evacuating the 32PTH2 DSC to avoid freezing of the lines and fittings.

Open the valve on the suction side of the pump, start the VDS and draw a vacuum on the 32PTH2 DSC cavity. The cavity pressure should be reduced in steps to approximately 100 torr, 50 torr, 25 torr, 15 torr, 10 torr, 5 torr, and 3 torr. This staged drawdown will verify no ice blockage of the evacuation path. After pumping down to each level (these levels are optional), the pump is valved off and the cavity pressure monitored. The cavity pressure will rise as water and other volatiles in the cavity evaporate. When the cavity pressure stabilizes, the pump is valved in to complete the vacuum drying process. It may be necessary to repeat some steps, depending on the rate and extent of the pressure increase. Vacuum drying is complete when the pressure stabilizes for a minimum of 30 minutes at 3 torr or less as specified in Technical Specification 3.1.1.c.

ANUH-01.0150 B.8.1-6

Advanced NUHOMS System Updated Final Safety Analysis Report Rev. 8, 08/18 I

[B8.4]

[B8.5]

[B8.6]

SNT-TC-lA, "American Society for Nondestructive Testing, Personnel Qualification and Certification in Nondestructive Testing," 1992.

U.S. Nuclear Regulatory Commission, NUREG-1536, "Standard Review Plan for Dry Cask Storage Systems - Final Report," U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards", Revision 1, July 2010.

US. Nuclear Regulatory Commission, Interim Staff Guidance (ISG-22), "Potential Rod Splitting due to Exposures to an Oxidizing Atmosphere during Short-term Cask Loading Operations in LWR of Other Uranium Oxide Based Fuel. "

ANUH-01.0150 B.8.3-2