ML18206A550

Interim Storage Partners, LLC - Revision 2 to WCS Consolidated Interim Storage Facility System Safety Analysis Report, Part 1 of 26, Chapter 1

ML18206A550
Person / Time
Site:	Consolidated Interim Storage Facility
Issue date:	07/19/2018
From:	Consolidated Interim Storage Facility
To:	Division of Spent Fuel Management
Shared Package
ML18206A595	List: ML18206A482 ML18206A483 ML18206A518 ML18206A519 ML18206A520 ML18206A521 ML18206A523 ML18206A525 ML18206A526 ML18206A527 ML18206A528 ML18206A529 ML18206A531 ML18206A532 ML18206A533 ML18206A534 ML18206A536 ML18206A538 ML18206A546 ML18206A548 ML18206A549 ML18206A550 ML18206A551 ML18206A552 ML18206A555 ML18206A557 ML18206A559 ML18206A560 ML18206A561 ML18206A562 ML18206A564 ML18206A565 ML18206A566 ML18206A567 ML18206A569 ML18206A570 ML18206A571
References
E-52247
Download: ML18206A550 (87)

Text

WCS Consolidated Interim Storage Facility System Safety Analysis Report (Public Version)

Docket Number 72-1050 Revision 2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1 Table of Contents

1.

INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.............................................................................................................. 1-1 Introduction......................................................................................................... 1-2 1.1 General Description of Installation.................................................................... 1-4 1.2 1.2.1 Location and Site Characteristics......................................................... 1-4 1.2.2 Principal Design Criteria..................................................................... 1-5 1.2.3 Facility Descriptions............................................................................. 1-5 1.2.4 Materials To Be Stored......................................................................... 1-6 1.2.5 Waste Products Generated During Operations.................................. 1-11 General Description of Systems and Operations............................................. 1-12 1.3 1.3.1 WCS Consolidated Interim Storage Facility Systems......................... 1-12 1.3.2 WCS Consolidated Interim Storage Facility Operations.................... 1-13 Analysis of Operations...................................................................................... 1-15 1.4 1.4.1 Normal Operations - Dose Assessment.............................................. 1-15 1.4.2 Normal Operations - Establishment of the Controlled Area (Site) Boundary................................................................................... 1-15 1.4.3 Accident Analysis................................................................................ 1-15 1.4.4 Safety Management............................................................................. 1-17 Identification of Agents and Contractors......................................................... 1-18 1.5 Material Incorporated by Reference................................................................ 1-19 1.6 1.6.1 NUHOMS Systems............................................................................ 1-19 1.6.2 NAC International Systems................................................................. 1-19 References......................................................................................................... 1-21 1.7

2.

SITE CHARACTERISTICS............................................................................................ 2-1 Geography and Demography of Site Selected.................................................... 2-2 2.1 Nearby Industrial, Transportation and Military Facilities............................... 2-5 2.2 Meteorology......................................................................................................... 2-6 2.3 2.3.1 Regional Climatology........................................................................... 2-6 2.3.2 Local Meteorology................................................................................ 2-6 2.3.3 Onsite Meteorological Data................................................................. 2-7

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 2 2.3.4 On-Site Meteorological Measurement Program................................ 2-12 2.3.5 Diffusion Estimates............................................................................. 2-12 Surface Hydrology............................................................................................ 2-14 2.4 2.4.1 Hydrologic Description...................................................................... 2-14 2.4.2 Floods................................................................................................. 2-17 2.4.3 Probable Maximum Flood on Streams and Rivers............................. 2-19 2.4.4 Potential Dam Failures (Seismically Induced)................................... 2-19 2.4.5 Probable Maximum Surge and Seiche Flooding................................ 2-19 2.4.6 Probable Maximum Tsunami Flooding.............................................. 2-19 2.4.7 Ice Flooding........................................................................................ 2-19 2.4.8 Flooding Protection Requirements..................................................... 2-20 2.4.9 Environmental Acceptance of Effluents.............................................. 2-20 Subsurface Hydrology....................................................................................... 2-21 2.5 2.5.1 Salt Dissolution and Sink Holes.......................................................... 2-25 Geology And Seismology.................................................................................. 2-26 2.6 2.6.1 Basic Geologic and Seismic Information............................................ 2-26 2.6.2 Vibratory Ground Motion................................................................... 2-28 2.6.3 Surface Faulting.................................................................................. 2-30 2.6.4 Stability of Subsurface Materials........................................................ 2-32 2.6.5 Slope Stability..................................................................................... 2-34 2.6.6 Volcanism............................................................................................ 2-34 Summary of Site Conditions Affecting Construction and 2.7 Operating Requirements................................................................................... 2-35 References......................................................................................................... 2-36 2.8 Attachment A Meteorological Data from Waste Control Specialists On-Site Weather Stations................................................................................. A-1 Attachment B Flood Plain Report.............................................................................. B-1 Attachment C Boring Logs......................................................................................... C-1 Attachment D Seismic Hazard Evaluation for WCS CISF....................................... D-1 Attachment E Geotechnical Investigation for WCS CISF........................................ E-1 Attachment F Evaluation of Halite Dissolution in the Vicinity of Waste Control Specialists Disposal Site, Andrews County, TX................... F-1 Attachment G Technical Specifications for Towers.................................................. G-1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 3 Attachment H Compiled Meteorological and Climatology Data............................... H-1

3.

PRINCIPAL DESIGN CRITERIA................................................................................. 3-1 Purposes of Installation...................................................................................... 3-2 3.1 3.1.1 Materials to Be Stored.......................................................................... 3-2 3.1.2 General Operating Functions............................................................... 3-3 Structural and Mechanical Safety Criteria........................................................ 3-5 3.2 3.2.1 Tornado and Wind Loadings................................................................ 3-6 3.2.2 Water Level (Flood) Design.................................................................. 3-7 3.2.3 Seismic Design...................................................................................... 3-8 3.2.4 Snow and Ice Loadings....................................................................... 3-13 3.2.5 Thermal............................................................................................... 3-13 3.2.6 Volcanic Eruption (Ash Fall).............................................................. 3-13 3.2.7 Lightning............................................................................................. 3-13 3.2.8 Combined Load Criteria..................................................................... 3-14 Safety Protection Systems................................................................................. 3-15 3.3 3.3.1 General............................................................................................... 3-15 3.3.2 Protection by Multiple Confinement Barriers and Systems................ 3-15 3.3.3 Protection by Equipment and Instrumentation Selection................... 3-16 3.3.4 Nuclear Criticality Safety................................................................... 3-16 3.3.5 Radiological Protection...................................................................... 3-17 3.3.6 Fire and Explosion Protection............................................................ 3-19 3.3.7 Material Handling and Storage.......................................................... 3-20 3.3.8 Industrial and Chemical Safety........................................................... 3-21 Classification of Structures, Components, and Systems................................. 3-22 3.4 3.4.1 Cask Handling Building Quality Classification................................. 3-23 3.4.2 Design Criteria for Other SSCs Not Important-to-Safety................... 3-24 Decommissioning Considerations.................................................................... 3-26 3.5 Performance Requirements.............................................................................. 3-27 3.6 3.6.1 Receipt Rate Capability...................................................................... 3-27 3.6.2 SNF and GTCC Waste Receiving Mode............................................. 3-27 3.6.3 Storage Capacity................................................................................. 3-27 3.6.4 Facility Service Life............................................................................ 3-27

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 4 Summary of WCS Consolidated Interim Storage Facility 3.7 Principal Design Criteria................................................................................. 3-28 References......................................................................................................... 3-29 3.8

4.

FACILITY DESIGN......................................................................................................... 4-1 Summary Description........................................................................................ 4-2 4.1 Location and Layout of Installation...................................................... 4-2 4.1.1 Principle Features.................................................................................. 4-3 4.1.2 Storage Structures............................................................................................. 4-6 4.2 Structural Specifications for Storage Pads............................................ 4-7 4.2.1 Storage Pad Layout............................................................................... 4-7 4.2.2 Storage Pad Description........................................................................ 4-7 4.2.3 Auxiliary Systems............................................................................................... 4-9 4.3 Ventilation and Offgas Systems............................................................ 4-9 4.3.1 Electrical Systems................................................................................. 4-9 4.3.2 Air Supply Systems............................................................................... 4-9 4.3.3 Steam Supply and Distribution System.............................................. 4-10 4.3.4 Water Supply System.......................................................................... 4-10 4.3.5 Sewage Treatment System.................................................................. 4-10 4.3.6 Communications and Alarm Systems................................................. 4-10 4.3.7 Fire Protection System........................................................................ 4-11 4.3.8 Maintenance System........................................................................... 4-12 4.3.9 Cold Chemical Systems...................................................................... 4-12 4.3.10 Air Sampling Systems......................................................................... 4-12 4.3.11 Gas Utilities........................................................................................ 4-13 4.3.12 Fueling of on-site vehicles used at the WCS CISF............................. 4-13 4.3.13 Radiation Monitoring Systems........................................................... 4-13 4.3.14 Control Room and Control Area......................................................... 4-13 4.3.15 Security and Administration Building................................................ 4-13 4.3.16 Operation Support Systems................................................................. 4-14 4.3.17 Temporary Facilities........................................................................... 4-14 4.3.18 Decontamination Systems............................................................................... 4-15 4.4 Equipment Decontamination.............................................................. 4-15 4.4.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 5 Personnel Decontamination................................................................ 4-16 4.4.2 Transportation Casks and Associated Components..................................... 4-17 4.5 Transportation Cask Repair and Maintenance Activities................... 4-17 4.5.1 Rail Side Track................................................................................... 4-19 4.5.2 Transportation Cask Queuing Areas................................................... 4-19 4.5.3 Receiving Area.................................................................................... 4-20 4.5.4 Temporary Isolation Areas................................................................. 4-20 4.5.5 Cathodic Protection......................................................................................... 4-21 4.6 Canister Handling Operation Systems.......................................................... 4-22 4.7 Cask Handling Building...................................................................... 4-23 4.7.1 Overhead Bridge Cranes..................................................................... 4-25 4.7.2 NUHOMS Transfer System.............................................................. 4-25 4.7.3 NAC Cask Transfer System................................................................ 4-25 4.7.4 Physical Protection........................................................................................... 4-27 4.8 Introduction......................................................................................... 4-27 4.8.1 Security System Functions.................................................................. 4-27 4.8.2 Physical Protection Plan Components................................................ 4-27 4.8.3 References......................................................................................................... 4-29 4.9 Supplemental Data Drawings......................................................................... 4-30 4.10

5.

OPERATION SYSTEMS & PROCEDURES................................................................ 5-1 Operation Description....................................................................................... 5-1 5.1 5.1.1 Operations at Originating Site.............................................................. 5-1 5.1.2 Operations Between the Originating Sites and the WCS CISF............ 5-2 5.1.3 Operations at the WCS CISF................................................................ 5-2 5.1.4 Flow Sheets........................................................................................... 5-6 5.1.5 Identification of Subjects for Safety Analysis...................................... 5-6 Canister Handling Systems............................................................................... 5-8 5.2 5.2.1 Canister Receipt, Handling, and Transfer............................................. 5-8 5.2.2 Canister Storage.................................................................................. 5-10 Other Operating Systems................................................................................ 5-12 5.3 Operation Support Systems............................................................................ 5-13 5.4 5.4.1 Instrumentation and Control Systems................................................. 5-13

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 6 5.4.2 System and Component Spares........................................................... 5-13 Control Room and Control Areas.................................................................. 5-14 5.5 Analytical Sampling......................................................................................... 5-15 5.6 5.6.1 Liquid Radioactive Waste Sampling.................................................. 5-15 5.6.2 Solid Radwaste Sampling................................................................... 5-15 5.6.3 Gaseous Radioactive Waste Sampling................................................ 5-15 5.6.4 Area Air Monitoring........................................................................... 5-15 References......................................................................................................... 5-17 5.7

6.

WASTE CONFINEMENT AND MANAGEMENT...................................................... 6-1 6.1 On-Site Waste Sources...................................................................................... 6-2 6.1.1 Gaseous Wastes.................................................................................... 6-2 6.1.2 Liquid Wastes....................................................................................... 6-3 6.1.3 Sanitary Wastes..................................................................................... 6-3 6.1.4 Solid Wastes.......................................................................................... 6-3 6.2 Off-Gas Treatment and Ventilation................................................................. 6-4 6.3 Liquid Waste Treatment and Retention.......................................................... 6-5 6.4 Solid Wastes........................................................................................................ 6-6 6.4.1 Design Objectives................................................................................. 6-6 6.4.2 Equipment and System Description...................................................... 6-6 6.4.3 Operating Procedures............................................................................ 6-6 6.4.4 Characteristics, Concentrations, and Volumes of Solid Wastes........... 6-6 6.4.5 Packaging.............................................................................................. 6-7 6.4.6 Storage Facilities................................................................................... 6-7 6.5 Radiological Impact of Normal Operations Summary................................... 6-8 6.5.1 Additional Considerations.................................................................... 6-8 6.6 References........................................................................................................... 6-9

7.

INSTALLATION DESIGN AND STRUCTURAL EVALUATION........................... 7-1 Descriptions of Systems, Structures and Components................................... 7-2 7.1 Confinement SSCs............................................................................................. 7-3 7.2 Pool and Pool Confinement Facilities.............................................................. 7-4 7.3 Reinforced Concrete Structures - Important To Safety................................ 7-5 7.4

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 7 Cask Handling Building.................................................................................... 7-6 7.5 7.5.1 Canister Transfer System...................................................................... 7-8 7.5.2 Vertical Cask Transporter (VCT)....................................................... 7-31 7.5.3 Cask Handling Building Structural Design......................................... 7-33 Other Structures, Systems, and Components Subject to NRC 7.6 Approval........................................................................................................... 7-40 7.6.1 Storage Pads for VCCs....................................................................... 7-40 7.6.2 Soil Liquefaction and VCC Storage Pad Settlement.......................... 7-65 7.6.3 Soil Structure Interaction of the VCC Storage Pad............................ 7-74 7.6.4 Soil Structure Interaction of the NUHOMS NITS Storage Pad....... 7-78 7.6.5 NUHOMS NITS Storage Pad Design............................................... 7-87 References....................................................................................................... 7-101 7.7

8.

THERMAL EVALUATION............................................................................................ 8-1 Thermal Design Criteria and Features............................................................ 8-2 8.1 8.1.1 Criteria.................................................................................................. 8-2 8.1.2 Features................................................................................................. 8-2 Stored Material Specifications.......................................................................... 8-3 8.2 Thermal Assessment.......................................................................................... 8-4 8.3 Thermal Analysis............................................................................................... 8-7 8.4 References........................................................................................................... 8-8 8.5

9.

RADIATION PROTECTION......................................................................................... 9-1 Ensuring That Occupational Radiation Exposures Are ALARA..................... 9-2 9.1 9.1.1 Policy Considerations........................................................................... 9-2 9.1.2 Design Considerations.......................................................................... 9-4 9.1.3 Operational Considerations.................................................................. 9-6 Radiation Sources............................................................................................... 9-9 9.2 9.2.1 Characterization of Sources................................................................. 9-9 9.2.2 Airborne Radioactive Material Sources............................................. 9-11 Radiation Protection Design Features............................................................. 9-13 9.3 9.3.1 Installation Design Features............................................................... 9-13 9.3.2 Access Control.................................................................................... 9-14 9.3.3 Shielding............................................................................................. 9-15

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 8 9.3.4 Ventilation........................................................................................... 9-16 9.3.5 Area Radiation and Airborne Radioactivity Monitoring System........ 9-17 Estimated On-Site Collective Dose Assessment............................................... 9-19 9.4 9.4.1 Radiation Dose Rate Within the Controlled Area............................... 9-19 9.4.2 Doses to Workers................................................................................ 9-21 9.4.3 Dose Contributions to the Annual Doses for the Proposed WCS CISF.................................................................................................... 9-22 Radiation Protection Program During Operation........................................... 9-25 9.5 9.5.1 Organization and Functions............................................................... 9-25 9.5.2 Equipment, Instrumentation and Facilities......................................... 9-25 9.5.3 Procedures.......................................................................................... 9-27 Doses to Off-Site Public.................................................................................... 9-29 9.6 9.6.1 Site Boundary Dose............................................................................. 9-29 9.6.2 Effluent and Environmental Monitoring Program............................. 9-29 9.6.3 Maximum Off-Site Annual Dose......................................................... 9-30 9.6.4 Liquid Releases................................................................................... 9-30 9.6.5 Features to Prevent Transport of Radioactive Material to the Environment........................................................................................ 9-30 References......................................................................................................... 9-32 9.7

10. CRITICALITY EVALUATION................................................................................... 10-1 Criticality Design Criteria and Features....................................................... 10-2 10.1 10.1.1 Criteria................................................................................................ 10-2 10.1.2 Features............................................................................................... 10-2 Stored Material Specifications........................................................................ 10-4 10.2 Criticality Assessment..................................................................................... 10-5 10.3 Criticality Analysis........................................................................................... 10-6 10.4 References......................................................................................................... 10-7 10.5

11. CONFINEMENT EVALUATION................................................................................ 11-1 Confinement Design Characteristics.............................................................. 11-2 11.1 Confinement Monitoring................................................................................. 11-3 11.2 Potential Release Source Term....................................................................... 11-4 11.3 Confinement Analysis...................................................................................... 11-5 11.4

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 9 Protection of Stored Materials from Degradation........................................ 11-6 11.5 References......................................................................................................... 11-7 11.6

12. ACCIDENT ANALYSIS................................................................................................ 12-1 Off-Normal Events........................................................................................... 12-2 12.1 Accidents........................................................................................................... 12-3 12.2 12.2.1 Canister Transfer System Fire Accident............................................. 12-3 12.2.2 Offsite Accident Analysis................................................................... 12-5 12.2.3 Adiabatic Heat Up/Blockage of Air Inlets/Outlets............................. 12-7 References......................................................................................................... 12-9 12.3

13. CONDUCT OF OPERATIONS.................................................................................... 13-1 Organizational Structure.................................................................................. 13-2 13.1 13.1.1 Corporate Organization...................................................................... 13-3 13.1.2 Operating Organization, Management, and Administrative Control System.................................................................................... 13-8 13.1.3 Personnel Qualification Requirement............................................... 13-11 13.1.4 Liaison With Outside Organizations................................................. 13-15 Pre-Operational Testing and Operation......................................................... 13-16 13.2 13.2.1 Administrative Procedures for Conducting Test Program............... 13-16 13.2.2 Test Program Description................................................................. 13-16 13.2.3 Test Discussion................................................................................. 13-19 Training Program........................................................................................... 13-20 13.3 13.3.1 Program Description........................................................................ 13-20 13.3.2 Retraining Program.......................................................................... 13-28 13.3.3 Administration and Records............................................................. 13-28 Facility Operations.......................................................................................... 13-29 13.4 13.4.1 Facility Procedures........................................................................... 13-29 13.4.2 Facility Records................................................................................ 13-32 13.4.3 Facility Review and Audit Program................................................. 13-34 13.4.4 Modifications to Facilities and Equipment....................................... 13-34 13.4.5 Employee Concerns Program........................................................... 13-36 Emergency Response Planning...................................................................... 13-37 13.5 Decommissioning Plan................................................................................... 13-40 13.6

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 10 13.6.1 WCS CISF Decommissioning Plan................................................... 13-40 13.6.2 Cost of Decommissioning................................................................. 13-40 13.6.3 Decommissioning Facilitation.......................................................... 13-40 13.6.4 Recordkeeping for Decommissioning............................................... 13-41 Physical Security and Safeguards Contingency Plans.................................. 13-42 13.7 References....................................................................................................... 13-44 13.8 B 2.0 SAFETY LIMITS (SLs).................................................................................................. 14-1 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY..................... 14-2 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY...................................... 14-6 B.3.1 RADIATION PROTECTION..................................................................................... 14-11 B.3.2 NAC-MPC SYSTEM Integrity.................................................................................... 14-13 B.3.3 NAC-UMS SYSTEM Integrity.................................................................................... 14-18 B.3.4 MAGNASTOR SYSTEM Integrity............................................................................. 14-24

15. MATERIALS EVALUATION...................................................................................... 15-1 Material Selection............................................................................................ 15-2 15.1 15.1.1 ITS Storage Pads................................................................................. 15-2 15.1.2 Canister Transfer System.................................................................... 15-2 15.1.3 Vertical Cask Transporter................................................................... 15-2 15.1.4 Canisters and Storage Overpacks........................................................ 15-2 Applicable Codes and Standards.................................................................... 15-4 15.2 15.2.1 Canisters.............................................................................................. 15-4 15.2.2 Storage Overpacks.............................................................................. 15-5 15.2.3 Transfer Casks for Vertical Systems................................................... 15-6 Material Properties.......................................................................................... 15-7 15.3 15.3.1 ITS Storage Pads................................................................................. 15-7 15.3.2 Canister Transfer System.................................................................... 15-7 15.3.3 Vertical Cask Transporter................................................................... 15-9 References....................................................................................................... 15-11 15.4

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 11 Appendix A NUHOMS-MP187 Cask System A.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.......................................................................................................... A.1-1 A.2. SITE CHARACTERISTICS........................................................................................ A.2-1 A.3. PRINCIPAL DESIGN CRITERIA............................................................................. A.3-1 SSCs Important to Safety.............................................................................. A.3-2 A.3.1 FO-, FC-, FF-DSCs and GTCC Canister......................................... A.3-2 A.3.1.1 Horizontal Storage Module............................................................... A.3-2 A.3.1.2 NUHOMS Basemat and Approach Slab......................................... A.3-2 A.3.1.3 NUHOMS Transfer Equipment...................................................... A.3-2 A.3.1.4 Spent Fuel to Be Stored................................................................................. A.3-4 A.3.2 FO-, FC-DSC.................................................................................... A.3-4 A.3.2.1 FF-DSC............................................................................................. A.3-4 A.3.2.2 Design Criteria for Environmental Conditions and Natural A.3.3 Phenomena..................................................................................................... A.3-5 Tornado Wind and Tornado Missiles............................................... A.3-5 A.3.3.1 Water Level (Flood) Design............................................................. A.3-5 A.3.3.2 Seismic Design.................................................................................. A.3-5 A.3.3.3 Snow and Ice Loading...................................................................... A.3-6 A.3.3.4 Lightning........................................................................................... A.3-6 A.3.3.5 Safety Protection Systems............................................................................. A.3-7 A.3.4 General.............................................................................................. A.3-7 A.3.4.1 Structural........................................................................................... A.3-7 A.3.4.2 Thermal............................................................................................. A.3-8 A.3.4.3 Shielding/Confinement/Radiation Protection................................... A.3-8 A.3.4.4 Criticality.......................................................................................... A.3-8 A.3.4.5 Material Selection............................................................................. A.3-9 A.3.4.6 Operating Procedures........................................................................ A.3-9 A.3.4.7 References..................................................................................................... A.3-10 A.3.5

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 12 A.4. OPERATING SYSTEMS............................................................................................. A.4-1 Concrete Pad Structures............................................................................... A.4-2 A.4.1 A.4.1.1 Operating Functions.......................................................................... A.4-2 A.4.1.2 Design Description............................................................................ A.4-2 A.4.1.3 Safety Considerations....................................................................... A.4-4 Cask Storage System...................................................................................... A.4-5 A.4.2 A.4.2.1 Operating Function........................................................................... A.4-5 A.4.2.2 Design Description............................................................................ A.4-6 A.4.2.3 Safety Considerations....................................................................... A.4-6 Cask Transporter System.............................................................................. A.4-7 A.4.3 A.4.3.1 Operating Function........................................................................... A.4-7 A.4.3.2 Design Description............................................................................ A.4-7 A.4.3.3 Safety Considerations....................................................................... A.4-7 Storage Module Thermal Monitoring System............................................. A.4-8 A.4.4 References....................................................................................................... A.4-9 A.4.5 Supplemental Data Drawings..................................................................... A.4-10 A.4.6 A.5. OPERATING PROCEDURES.................................................................................... A.5-1 Procedures for Receiving the Transport Cask and Transfer to A.5.1 the HSM.......................................................................................................... A.5-2 Receipt of the Loaded NUHOMS-MP187 Cask............................. A.5-2 A.5.1.1 Transfer to the HSM......................................................................... A.5-3 A.5.1.2 Monitoring Operations...................................................................... A.5-5 A.5.1.3 Procedures for Retrieval and Off-Site Shipment........................................ A.5-6 A.5.2 DSC Retrieval from the HSM........................................................... A.5-6 A.5.2.1 References....................................................................................................... A.5-8 A.5.3 A.6. WASTE CONFINEMENT AND MANAGEMENT.................................................. A.6-1 A.7. STRUCTURAL EVALUATION................................................................................. A.7-1 Discussion........................................................................................................ A.7-2 A.7.1 Summary of Mechanical Properties of Materials....................................... A.7-4 A.7.2 Structural Analysis of MP187 Cask with a Canister (Transfer A.7.3 Configuration)................................................................................................ A.7-5

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 13 Normal and Off-Normal Conditions................................................. A.7-5 A.7.3.1 Accident Conditions.......................................................................... A.7-6 A.7.3.2 Load Combinations (Volume I of [A.7-4])....................................... A.7-6 A.7.3.3 Structural Analysis of HSM Model 80 with a Canister (Storage A.7.4 Configuration)................................................................................................ A.7-8 Normal and Off-Normal Conditions................................................. A.7-9 A.7.4.1 Accident Conditions.......................................................................... A.7-9 A.7.4.2 Load Combinations......................................................................... A.7-10 A.7.4.3 Seismic Reconciliation of the MP187 Cask, Canisters, and A.7.5 HSM Model 80............................................................................................. A.7-11 MP187 Cask.................................................................................... A.7-11 A.7.5.1 Canisters.......................................................................................... A.7-12 A.7.5.2 HSM Model 80............................................................................... A.7-14 A.7.5.3 Thermal Stress Reconciliation of the MP187 Cask System A.7.6 Components.................................................................................................. A.7-15 Reconciliation of WCS CISF Environmental Ambient A.7.6.1 Conditions with Environmental Ambient Conditions in the Standardized NUHOMS UFSAR................................................. A.7-15 Reconciliation of WCS CISF Environmental Ambient A.7.6.2 Conditions with Environmental Ambient Conditions in the Rancho Seco ISFSI FSAR.............................................................. A.7-15 Structural Evaluation of Canister Confinement Boundary A.7.7 under Normal Conditions of Transport.................................................... A.7-16 Evaluation of FC-and FF-DSC Shells............................................ A.7-16 A.7.7.1 Structural Analysis of MP187 FO-and 24PT1 DSCs A.7.7.2 (Transport Configuration)............................................................... A.7-21 Conclusions of the Structural Analysis...................................................... A.7-27 A.7.8 References..................................................................................................... A.7-28 A.7.9 A.8. THERMAL EVALUATION........................................................................................ A.8-1 Discussion........................................................................................................ A.8-2 A.8.1 Summary of Thermal Properties of Materials............................................ A.8-3 A.8.2 Ambient Conditions at the WCS CISF........................................................ A.8-4 A.8.3 Ambient Temperature Specification at WCS CISF.......................... A.8-4 A.8.3.1 Comparison of WCS CISF Ambient Conditions with Ambient A.8.3.2 Conditions Used in the Rancho Seco ISFSI FSAR [A.8-3].............. A.8-4

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 14 Thermal Analysis of HSM Model 80 with FO/FC/FF DSCs...................... A.8-5 A.8.4 Qualification of the HSM Model 80 for Storage of Canisters.......... A.8-5 A.8.4.1 Thermal Model of Rancho Seco HSM and Canisters....................... A.8-5 A.8.4.2 Rancho Seco HSM Thermal Model Results..................................... A.8-5 A.8.4.3 Evaluation of HSM Model 80 Performance with a Canister............ A.8-6 A.8.4.4 Thermal Analysis of MP187 Cask with FO/FC/FF DSCs.......................... A.8-7 A.8.5 Thermal Model MP187 Cask with FO/FC/FF DSCs........................ A.8-7 A.8.5.1 MP187 Cask Thermal Model Results............................................... A.8-7 A.8.5.2 Accident Conditions.......................................................................... A.8-7 A.8.5.3 Evaluation of MP187 Cask Performance.......................................... A.8-7 A.8.5.4 References....................................................................................................... A.8-8 A.8.6 A.9. RADIATION PROTECTION..................................................................................... A.9-1 Radiation Protection Design Features......................................................... A.9-2 A.9.1 Occupational Exposure Evaluation.............................................................. A.9-3 A.9.2 Analysis Methodology...................................................................... A.9-3 A.9.2.1 Dose Assessment.............................................................................. A.9-3 A.9.2.2 References....................................................................................................... A.9-5 A.9.3 A.10. CRITICALITY EVALUATION............................................................................... A.10-1 Discussion and Results................................................................................. A.10-2 A.10.1 Package Fuel Loading.................................................................................. A.10-4 A.10.2 Model Specification...................................................................................... A.10-5 A.10.3 Criticality Calculation................................................................................. A.10-6 A.10.4 Critical Benchmark Experiments............................................................... A.10-7 A.10.5 References..................................................................................................... A.10-8 A.10.6 A.11. CONFINEMENT EVALUATION............................................................................ A.11-1 Confinement Boundary............................................................................... A.11-2 A.11.1 Potential Release Source Term................................................................... A.11-3 A.11.2 Confinement Analysis.................................................................................. A.11-4 A.11.3 Methodology................................................................................... A.11-4 A.11.3.1 Specific Activities for Release........................................................ A.11-5 A.11.3.2 Leakage Rates................................................................................. A.11-5 A.11.3.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 15 Atmospheric Dispersion Coefficients............................................. A.11-6 A.11.3.4 Dose Computations......................................................................... A.11-6 A.11.3.5 References..................................................................................................... A.11-9 A.11.4 A.12. ACCIDENT ANALYSIS............................................................................................ A.12-1 Off-Normal Operations............................................................................... A.12-2 A.12.1 A.12.1.1 Off-Normal Transfer Loads............................................................ A.12-2 A.12.1.2 Off-Normal HSM Storage Events (Extreme Temperatures).......... A.12-2 A.12.1.3 Off-Normal Release of Radionuclides............................................ A.12-2 Postulated Accident..................................................................................... A.12-3 A.12.2 A.12.2.1 Blockage of Air Inlets/Outlets........................................................ A.12-3 A.12.2.2 Drop Accidents............................................................................... A.12-3 A.12.2.3 Earthquakes..................................................................................... A.12-4 A.12.2.4 Lightning......................................................................................... A.12-4 A.12.2.5 Fire and Explosion.......................................................................... A.12-5 A.12.2.6 Flood............................................................................................... A.12-5 A.12.2.7 Tornado Wind and Missiles............................................................ A.12-5 References..................................................................................................... A.12-6 A.12.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 16 Appendix B Standardized Advanced NUHOMS System B.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION...........................................................................................................B.1-1 B.2. SITE CHARACTERISTICS.........................................................................................B.2-1 B.3. PRINCIPAL DESIGN CRITERIA..............................................................................B.3-1 SSCs Important to Safety...............................................................................B.3-2 B.3.1 24PT1 DSC........................................................................................B.3-2 B.3.1.1 Horizontal Storage Module................................................................B.3-2 B.3.1.2 NUHOMS Basemat and Approach Slab..........................................B.3-2 B.3.1.3 NUHOMS Transfer Equipment.......................................................B.3-3 B.3.1.4 Spent Fuel to Be Stored..................................................................................B.3-4 B.3.2 Design Criteria for Environmental Conditions and Natural B.3.3 Phenomena......................................................................................................B.3-5 Tornado Wind and Tornado Missiles................................................B.3-5 B.3.3.1 Water Level (Flood) Design..............................................................B.3-5 B.3.3.2 Seismic Design...................................................................................B.3-5 B.3.3.3 Snow and Ice Loading.......................................................................B.3-6 B.3.3.4 Lightning............................................................................................B.3-6 B.3.3.5 Safety Protection Systems..............................................................................B.3-7 B.3.4 General...............................................................................................B.3-7 B.3.4.1 Structural............................................................................................B.3-7 B.3.4.2 Thermal..............................................................................................B.3-8 B.3.4.3 Shielding/Confinement/Radiation Protection....................................B.3-8 B.3.4.4 Criticality...........................................................................................B.3-8 B.3.4.5 Material Selection..............................................................................B.3-9 B.3.4.6 Operating Procedures.........................................................................B.3-9 B.3.4.7 References......................................................................................................B.3-10 B.3.5 B.4. OPERATING SYSTEMS..............................................................................................B.4-1 Concrete Pad Structures................................................................................B.4-2 B.4.1 Operating Functions...........................................................................B.4-2 B.4.1.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 17 Design Description.............................................................................B.4-2 B.4.1.2 Safety Considerations........................................................................B.4-4 B.4.1.3 Cask Storage System.......................................................................................B.4-5 B.4.2 Operating Function............................................................................B.4-5 B.4.2.1 Design Description.............................................................................B.4-5 B.4.2.2 Safety Considerations........................................................................B.4-6 B.4.2.3 Cask Transporter System...............................................................................B.4-7 B.4.3 Operating Function............................................................................B.4-7 B.4.3.1 Design Description.............................................................................B.4-7 B.4.3.2 Safety Considerations........................................................................B.4-7 B.4.3.3 Storage Module Thermal Monitoring System..............................................B.4-8 B.4.4 References........................................................................................................B.4-9 B.4.5 Supplemental Data Drawings......................................................................B.4-10 B.4.6 B.5. OPERATING PROCEDURES.....................................................................................B.5-1 Procedures for Loading the DSC and Transfer to the AHSM...................B.5-2 B.5.1 Receipt of the Loaded NUHOMS-MP187 Cask..............................B.5-2 B.5.1.1 Transfer to the AHSM.......................................................................B.5-3 B.5.1.2 Monitoring Operations.......................................................................B.5-5 B.5.1.3 Procedures for Retrieval and Off-Site Shipment.........................................B.5-6 B.5.2 DSC Retrieval from the AHSM.........................................................B.5-6 B.5.2.1 References........................................................................................................B.5-8 B.5.3 B.6. WASTE CONFINEMENT AND MANAGEMENT...................................................B.6-1 B.7. STRUCTURAL EVALUATION..................................................................................B.7-1 Discussion.........................................................................................................B.7-3 B.7.1 Summary of Mechanical Properties of Materials........................................B.7-4 B.7.2 Structural Evaluation of MP187 Transfer Cask with Canister B.7.3 (Transfer Configuration at WCS CISF).......................................................B.7-5 Evaluation of MP187 Cask Loaded with a Canister..........................B.7-5 B.7.3.1 Evaluation of the Canister in the MP187 Transfer Cask...................B.7-6 B.7.3.2 Structural Analysis of AHSM with a Canister (Storage B.7.4 Configuration).................................................................................................B.7-7

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 18 Seismic Reconciliation of the Advanced NUHOMS 24PT1 B.7.5 DSC and AHSM Storage Components and the MP187 Transfer Cask.................................................................................................B.7-8 Thermal Stress Reconciliation of the Standardized Advanced B.7.6 NUHOMS System Components...................................................................B.7-9 Reconciliation of WCS CISF Environmental Ambient B.7.6.1 Conditions with Environmental Ambient Conditions used for the AHSM Analyses in the Standardized Advanced NUHOMS UFSAR..........................................................................B.7-9 Reconciliation of WCS CISF Environmental Ambient B.7.6.2 Conditions with Environmental Ambient Conditions used for the Canister Analysis in the Standardized Advanced NUHOMS UFSAR..........................................................................B.7-9 Conclusions of the Structural Analysis.......................................................B.7-10 B.7.7 Alternate Cask Stability and Missile Penetration Evaluation of B.7.8 the MP187 Cask (On-Site Transfer Configuration)..................................B.7-11 Assumptions.....................................................................................B.7-11 B.7.8.1 Material Properties...........................................................................B.7-11 B.7.8.2 Design Criteria.................................................................................B.7-11 B.7.8.3 Methodology....................................................................................B.7-12 B.7.8.4 Design Input Loads & Data.............................................................B.7-14 B.7.8.5 Tornado & Missile Impact Loads Analysis - Stability B.7.8.6 Evaluations.......................................................................................B.7-16 Tornado Wind and Missile Analysis - Stress Evaluations...............B.7-19 B.7.8.7 Tornado Missile Analysis - Penetration Evaluations.......................B.7-20 B.7.8.8 Summary of Results.........................................................................B.7-21 B.7.8.9 Structural Evaluation of 24PT1-DSC Confinement Boundary B.7.9 under Normal Conditions of Transport.....................................................B.7-22 References......................................................................................................B.7-23 B.7.10 B.8. THERMAL EVALUATION.........................................................................................B.8-1 Discussion.........................................................................................................B.8-2 B.8.1 Summary of Thermal Properties of Materials.............................................B.8-3 B.8.2 Specification for Components........................................................................B.8-4 B.8.3 Ambient Conditions at the WCS CISF.........................................................B.8-5 B.8.4 Ambient Temperature Specification at WCS CISF...........................B.8-5 B.8.4.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 19 Comparison of WCS CISF Ambient Conditions with Ambient B.8.4.2 Conditions Used in the AHSM Thermal Evaluation from ANUH UFSAR [B.8-1] for Storage Conditions................................B.8-5 Comparison of WCS CISF Ambient Conditions with Ambient B.8.4.3 Conditions Used in the Rancho Seco ISFSI SAR [B.8-4] for Transfer Conditions...........................................................................B.8-5 Thermal Analysis of AHSM with 24PT1 DSC for Storage B.8.5 Conditions........................................................................................................B.8-6 Thermal Model of the AHSM with 24PT1 DSC...............................B.8-6 B.8.5.1 AHSM Thermal Model Results.........................................................B.8-6 B.8.5.2 Evaluation of AHSM Performance with 24PT1 DSC.......................B.8-7 B.8.5.3 NUHOMS-24PT1 DSC Basket Model Results...............................B.8-7 B.8.5.4 Thermal Analysis of MP187 Transfer Cask with 24PT1 DSC B.8.6 for Transfer Conditions.................................................................................B.8-8 Evaluation of MP187 Cask Performance...........................................B.8-9 B.8.6.1 References......................................................................................................B.8-10 B.8.7 B.9. RADIATION PROTECTION......................................................................................B.9-1 Radiation Protection Design Features..........................................................B.9-2 B.9.1 Occupational Exposure Evaluation...............................................................B.9-3 B.9.2 Analysis Methodology.......................................................................B.9-3 B.9.2.1 Dose Assessment...............................................................................B.9-3 B.9.2.2 References........................................................................................................B.9-5 B.9.3 B.10. CRITICALITY EVALUATION................................................................................B.10-1 Discussion and Results..................................................................................B.10-2 B.10.1 Package Fuel Loading...................................................................................B.10-3 B.10.2 Model Specification.......................................................................................B.10-4 B.10.3 Criticality Calculation..................................................................................B.10-5 B.10.4 Critical Benchmark Experiments................................................................B.10-6 B.10.5 References......................................................................................................B.10-7 B.10.6 B.11 CONFINEMENT EVALUATION.............................................................................B.11-1 Confinement Boundary................................................................................B.11-2 B.11.1 Requirements for Normal Conditions of Storage......................................B.11-3 B.11.2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 20 Confinement Requirements for Hypothetical Accident B.11.3 Conditions......................................................................................................B.11-4 References......................................................................................................B.11-5 B.11.4 B.12. ACCIDENT ANALYSIS.............................................................................................B.12-1 Off-Normal Operations................................................................................B.12-2 B.12.1 Off-Normal Transfer Loads.............................................................B.12-2 B.12.1.1 Extreme Ambient Temperatures......................................................B.12-2 B.12.1.2 Off-Normal Release of Radionuclides.............................................B.12-3 B.12.1.3 Postulated Accident......................................................................................B.12-4 B.12.2 Blockage of Air Inlet/Outlets...........................................................B.12-4 B.12.2.1 Drop Accidents................................................................................B.12-4 B.12.2.2 Earthquakes......................................................................................B.12-5 B.12.2.3 Lightning..........................................................................................B.12-6 B.12.2.4 Fire and Explosion...........................................................................B.12-6 B.12.2.5 Flood................................................................................................B.12-7 B.12.2.6 Tornado Wind and Missiles.............................................................B.12-8 B.12.2.7 References......................................................................................................B.12-9 B.12.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 21 Appendix C Standardized NUHOMS-61BT System C.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.......................................................................................................... C.1-1 C.2. SITE CHARACTERISTICS........................................................................................ C.2-1 C.3. PRINCIPAL DESIGN CRITERIA............................................................................. C.3-1 SSCs Important to Safety.............................................................................. C.3-2 C.3.1 61BT-DSCs........................................................................................C.3-2 C.3.1.1 Horizontal Storage Module................................................................C.3-2 C.3.1.2 NUHOMS Basemat and Approach Slab..........................................C.3-2 C.3.1.3 NUHOMS Transfer Equipment.......................................................C.3-2 C.3.1.4 Spent Fuel to Be Stored................................................................................. C.3-4 C.3.2 Design Criteria for Environmental Conditions and Natural C.3.3 Phenomena..................................................................................................... C.3-5 Tornado Wind and Tornado Missiles................................................C.3-5 C.3.3.1 Water Level (Flood) Design..............................................................C.3-5 C.3.3.2 Seismic Design...................................................................................C.3-5 C.3.3.3 Snow and Ice Loading.......................................................................C.3-6 C.3.3.4 Lightning............................................................................................C.3-6 C.3.3.5 Safety Protection Systems............................................................................. C.3-7 C.3.4 General...............................................................................................C.3-7 C.3.4.1 Structural............................................................................................C.3-7 C.3.4.2 Thermal..............................................................................................C.3-7 C.3.4.3 Shielding/Confinement/Radiation Protection....................................C.3-8 C.3.4.4 Criticality...........................................................................................C.3-8 C.3.4.5 Material Selection..............................................................................C.3-9 C.3.4.6 Operating Procedures.........................................................................C.3-9 C.3.4.7 References..................................................................................................... C.3-10 C.3.5 C.4. OPERATING SYSTEMS............................................................................................. C.4-1 Concrete Pad Structures............................................................................... C.4-2 C.4.1 Operating Functions...........................................................................C.4-2 C.4.1.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 22 Design Description.............................................................................C.4-2 C.4.1.2 Safety Considerations........................................................................C.4-4 C.4.1.3 Cask Storage System...................................................................................... C.4-5 C.4.2 Operating Function............................................................................C.4-5 C.4.2.1 Design Description.............................................................................C.4-6 C.4.2.2 Safety Considerations........................................................................C.4-6 C.4.2.3 Cask Transporter System.............................................................................. C.4-7 C.4.3 Operating Function............................................................................C.4-7 C.4.3.1 Design Description.............................................................................C.4-7 C.4.3.2 Safety Considerations........................................................................C.4-7 C.4.3.3 Storage Module Thermal Monitoring System............................................. C.4-8 C.4.4 References....................................................................................................... C.4-9 C.4.5 Supplemental Data Drawings..................................................................... C.4-10 C.4.6 C.5. OPERATING PROCEDURES.................................................................................... C.5-1 Procedures for Loading the DSC and Transfer to the HSM..................... C.5-2 C.5.1 Receipt of the Loaded NUHOMS-MP197HB Cask........................C.5-2 C.5.1.1 Transfer to the HSM..........................................................................C.5-3 C.5.1.2 Monitoring Operations.......................................................................C.5-5 C.5.1.3 Procedures for Unloading the DSC.............................................................. C.5-6 C.5.2 DSC Retrieval from the HSM............................................................C.5-6 C.5.2.1 References....................................................................................................... C.5-8 C.5.3 C.6. WASTE CONFINEMENT AND MANAGEMENT.................................................. C.6-1 C.7. STRUCTURAL EVALUATION................................................................................. C.7-1 Discussion........................................................................................................ C.7-3 C.7.1 Summary of Mechanical Properties of Materials....................................... C.7-4 C.7.2 Seismic Reconciliation of the 61BT DSC, HSM Model 102, and C.7.3 MP197HB Cask.............................................................................................. C.7-5 HSM Model 102................................................................................C.7-5 C.7.3.1 MP197HB Transfer Cask...................................................................C.7-5 C.7.3.2 61BT DSC..........................................................................................C.7-6 C.7.3.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 23 Reconciliation of Thermal Loads for the 61BT DSC in the C.7.4 HSM Model 102 and MP197HB Cask......................................................... C.7-7 Structural Analysis of 61BT DSC (Storage and Transfer)........................ C.7-8 C.7.5 Normal Loads (Storage in HSM Model 102 and Transfer in C.7.5.1 MP197HB Cask)................................................................................C.7-9 Off-Normal Loads............................................................................C.7-10 C.7.5.2 Accident Loads................................................................................C.7-10 C.7.5.3 Structural Analysis of HSM Model 102 with 61BT DSC C.7.6 (Storage Configuration).............................................................................. C.7-12 Normal Loads...................................................................................C.7-12 C.7.6.1 Off-Normal Loads............................................................................C.7-13 C.7.6.2 Accident Loads................................................................................C.7-13 C.7.6.3 Load Combinations..........................................................................C.7-15 C.7.6.4 Structural Analysis of MP197HB Cask as On-Site Transfer C.7.7 Cask............................................................................................................... C.7-16 General Information.........................................................................C.7-16 C.7.7.1 Normal and Off-Normal Conditions................................................C.7-20 C.7.7.2 Accident Conditions.........................................................................C.7-24 C.7.7.3 MP197HB Cask Stability and Missile Penetration Analyses..........C.7-26 C.7.7.4 Structural Evaluation of 61BT DSC Confinement Boundary C.7.8 under Normal Conditions of Transport.................................................... C.7-39 References..................................................................................................... C.7-40 C.7.9 C.8. THERMAL EVALUATION........................................................................................ C.8-1 Discussion........................................................................................................ C.8-2 C.8.1 Summary of Thermal Properties of Materials............................................ C.8-3 C.8.2 Specification for Neutron Absorber Thermal Conductivity...................... C.8-4 C.8.3 Thermal Analysis of HSM Model 102 with 61BT DSC for C.8.4 Storage Conditions........................................................................................ C.8-5 Ambient Temperature Specification at WCS CISF...........................C.8-5 C.8.4.1 Thermal Model of HSM Model 102 with 61BT DSC.......................C.8-5 C.8.4.2 HSM Model 102 and 61BT DSC Thermal Model Results................C.8-6 C.8.4.3 Evaluation of 61BT DSC Storage in HSM Model 102......................C.8-6 C.8.4.4 Thermal Analysis of MP197HB Cask with 61BT DSC for C.8.5 Transfer Operations...................................................................................... C.8-7

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 24 Thermal Model of MP197HB Cask with 61BT DSC........................C.8-7 C.8.5.1 MP197HB Cask Thermal Model Results..........................................C.8-8 C.8.5.2 Evaluation of MP197HB Cask Performance...................................C.8-11 C.8.5.3 References..................................................................................................... C.8-12 C.8.6 C.9. RADIATION PROTECTION..................................................................................... C.9-1 Radiation Protection Design Features......................................................... C.9-2 C.9.1 Occupational Exposure Evaluation.............................................................. C.9-3 C.9.2 Analysis Methodology.......................................................................C.9-3 C.9.2.1 Dose Assessment...............................................................................C.9-3 C.9.2.2 References....................................................................................................... C.9-5 C.9.3 C.10. CRITICALITY EVALUATION............................................................................... C.10-1 Discussion and Results................................................................................. C.10-2 C.10.1 Package Fuel Loading.................................................................................. C.10-3 C.10.2 Model Specification...................................................................................... C.10-4 C.10.3 Criticality Calculation................................................................................. C.10-5 C.10.4 Critical Benchmark Experiments............................................................... C.10-6 C.10.5 References..................................................................................................... C.10-7 C.10.6 C.11 CONFINEMENT EVALUATION............................................................................ C.11-1 Confinement Boundary............................................................................... C.11-2 C.11.1 Requirements for Normal Conditions of Storage..................................... C.11-3 C.11.2 Confinement Requirements for Hypothetical Accident C.11.3 Conditions..................................................................................................... C.11-4 References..................................................................................................... C.11-5 C.11.4 C.12. ACCIDENT ANALYSIS............................................................................................ C.12-1 Off-Normal Operations............................................................................... C.12-2 C.12.1 Off-Normal Transfer Loads.............................................................C.12-2 C.12.1.1 Extreme Ambient Temperatures......................................................C.12-2 C.12.1.2 Off-Normal Release of Radionuclides.............................................C.12-3 C.12.1.3 Postulated Accident..................................................................................... C.12-4 C.12.2 Blockage of Air Inlets/Outlets.........................................................C.12-4 C.12.2.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 25 Drop Accidents................................................................................C.12-5 C.12.2.2 Earthquakes......................................................................................C.12-6 C.12.2.3 Lightning..........................................................................................C.12-6 C.12.2.4 Fire and Explosion...........................................................................C.12-7 C.12.2.5 Flood................................................................................................C.12-8 C.12.2.6 Tornado Wind and Missiles.............................................................C.12-8 C.12.2.7 Reduced HSM Air Inlet and Outlet Shielding.................................C.12-9 C.12.2.8 References................................................................................................... C.12-10 C.12.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 26 Appendix D Standardized NUHOMS-61BTH Type 1 System D.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.......................................................................................................... D.1-1 D.2. SITE CHARACTERISTICS........................................................................................ D.2-1 D.3. PRINCIPAL DESIGN CRITERIA............................................................................. D.3-1 SSCs Important to Safety.............................................................................. D.3-2 D.3.1 61BTH-DSCs (Type 1)..................................................................... D.3-2 D.3.1.1 Horizontal Storage Module............................................................... D.3-2 D.3.1.2 NUHOMS Basemat and Approach Slab......................................... D.3-2 D.3.1.3 NUHOMS Transfer Equipment...................................................... D.3-2 D.3.1.4 Spent Fuel to Be Stored................................................................................. D.3-4 D.3.2 Design Criteria for Environmental Conditions and Natural D.3.3 Phenomena..................................................................................................... D.3-5 Tornado Wind and Tornado Missiles............................................... D.3-5 D.3.3.1 Water Level (Flood) Design............................................................. D.3-5 D.3.3.2 Seismic Design.................................................................................. D.3-5 D.3.3.3 Snow and Ice Loading...................................................................... D.3-6 D.3.3.4 Lightning........................................................................................... D.3-6 D.3.3.5 Safety Protection Systems............................................................................. D.3-7 D.3.4 General.............................................................................................. D.3-7 D.3.4.1 Structural........................................................................................... D.3-7 D.3.4.2 Thermal............................................................................................. D.3-7 D.3.4.3 Shielding/Confinement/Radiation Protection................................... D.3-8 D.3.4.4 Criticality.......................................................................................... D.3-8 D.3.4.5 Material Selection............................................................................. D.3-9 D.3.4.6 Operating Procedures........................................................................ D.3-9 D.3.4.7 References..................................................................................................... D.3-10 D.3.5 D.4. OPERATING SYSTEMS............................................................................................. D.4-1 Concrete Pad Structures............................................................................... D.4-2 D.4.1 Operating Functions.......................................................................... D.4-2 D.4.1.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 27 Design Description............................................................................ D.4-2 D.4.1.2 Safety Considerations....................................................................... D.4-4 D.4.1.3 Cask Storage System...................................................................................... D.4-5 D.4.2 Operating Function........................................................................... D.4-5 D.4.2.1 Design Description............................................................................ D.4-5 D.4.2.2 Safety Considerations....................................................................... D.4-6 D.4.2.3 Cask Transporter System.............................................................................. D.4-7 D.4.3 Operating Function........................................................................... D.4-7 D.4.3.1 Design Description............................................................................ D.4-7 D.4.3.2 Safety Considerations....................................................................... D.4-7 D.4.3.3 Storage Module Thermal Monitoring System............................................. D.4-8 D.4.4 References....................................................................................................... D.4-9 D.4.5 Supplemental Data Drawings..................................................................... D.4-10 D.4.6 D.5. OPERATING PROCEDURES.................................................................................... D.5-1 Procedures for Loading the DSC and Transfer to the HSM..................... D.5-2 D.5.1 Receipt of the Loaded NUHOMS-MP197HB Cask....................... D.5-2 D.5.1.1 Transfer to the HSM......................................................................... D.5-3 D.5.1.2 Monitoring Operations...................................................................... D.5-5 D.5.1.3 Procedures for Unloading the DSC.............................................................. D.5-6 D.5.2 DSC Retrieval from the HSM........................................................... D.5-6 D.5.2.1 References....................................................................................................... D.5-8 D.5.3 D.6. WASTE CONFINEMENT AND MANAGEMENT.................................................. D.6-1 D.7. STRUCTURAL EVALUATION................................................................................. D.7-1 Discussion........................................................................................................ D.7-3 D.7.1 Summary of Mechanical Properties of Materials....................................... D.7-4 D.7.2 Seismic Reconciliation of the Canister, HSM Model 102, and D.7.3 MP197HB Cask.............................................................................................. D.7-5 HSM Model 80 and Model 102........................................................ D.7-5 D.7.3.1 MP197HB Cask as On-Site Transfer Cask....................................... D.7-8 D.7.3.2 61BTH Type 1 DSC.......................................................................... D.7-8 D.7.3.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 28 Reconciliation of Thermal Loads for the Canister in the HSM D.7.4 Model 102 and in the MP197HB Cask......................................................... D.7-9 Structural Analysis of Canister (Storage and Transfer).......................... D.7-10 D.7.5 Normal Loads (Storage in HSM Model 102 and Transfer in D.7.5.1 MP197HB Cask)............................................................................. D.7-11 Off-Normal Loads........................................................................... D.7-12 D.7.5.2 Accident Loads............................................................................... D.7-12 D.7.5.3 Structural Analysis of HSM Model 102 with Canister (Storage D.7.6 Configuration).............................................................................................. D.7-14 Structural Analysis of MP197HB Cask as On-Site Transfer D.7.7 Cask............................................................................................................... D.7-15 Structural Evaluation of 61BTH Type 1 DSC Confinement D.7.8 Boundary under Normal Conditions of Transport.................................. D.7-16 References..................................................................................................... D.7-17 D.7.9 D.8. THERMAL EVALUATION........................................................................................ D.8-1 Discussion........................................................................................................ D.8-2 D.8.1 Summary of Thermal Properties of Materials............................................ D.8-3 D.8.2 Specification for Components....................................................................... D.8-4 D.8.3 Thermal Analysis of HSM Model 102 with Canister for D.8.4 Storage Conditions........................................................................................ D.8-5 Ambient Temperature Specification at WCS CISF.......................... D.8-5 D.8.4.1 Thermal Model of HSM Model 102 with 61BTH Type 1 DSC....... D.8-5 D.8.4.2 HSM Model 102 Thermal Model Results......................................... D.8-6 D.8.4.3 61BTH Type 1 DSC Thermal Model Results................................... D.8-6 D.8.4.4 Evaluation of the 61BTH Type 1 DSC Storage in HSM Model D.8.4.5 102..................................................................................................... D.8-6 Thermal Analysis of MP197HB Cask with Canister for D.8.5 Transfer Operations...................................................................................... D.8-7 Thermal Model of MP197HB TC with 61BTH Type 1 DSC........... D.8-7 D.8.5.1 MP197HB TC Thermal Model Results (Normal and Off-D.8.5.2 Normal Conditions):......................................................................... D.8-8 MP197HB Cask and 61BTH Type 1 DSC Thermal Analysis D.8.5.3 (Accident Conditions)....................................................................... D.8-9 Evaluation of MP197HB TC Performance..................................... D.8-11 D.8.5.4 References..................................................................................................... D.8-12 D.8.6

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 29 D.9. RADIATION PROTECTION..................................................................................... D.9-1 Radiation Protection Design Features......................................................... D.9-2 D.9.1 Occupational Exposure Evaluation.............................................................. D.9-3 D.9.2 Analysis Methodology...................................................................... D.9-3 D.9.2.1 Dose Assessment.............................................................................. D.9-3 D.9.2.2 References....................................................................................................... D.9-5 D.9.3 D.10. CRITICALITY EVALUATION............................................................................... D.10-1 Discussion and Results................................................................................. D.10-2 D.10.1 Package Fuel Loading.................................................................................. D.10-3 D.10.2 Model Specification...................................................................................... D.10-4 D.10.3 Criticality Calculation................................................................................. D.10-5 D.10.4 Critical Benchmark Experiments............................................................... D.10-6 D.10.5 References..................................................................................................... D.10-7 D.10.6 D.11 CONFINEMENT EVALUATION............................................................................ D.11-1 Confinement Boundary............................................................................... D.11-2 D.11.1 Requirements for Normal Conditions of Storage..................................... D.11-3 D.11.2 Confinement Requirements for Hypothetical Accident D.11.3 Conditions..................................................................................................... D.11-4 References..................................................................................................... D.11-5 D.11.4 D.12. ACCIDENT ANALYSIS............................................................................................ D.12-1 Off-Normal Operations............................................................................... D.12-2 D.12.1 Off-Normal Transfer Loads............................................................ D.12-2 D.12.1.1 Extreme Ambient Temperatures..................................................... D.12-2 D.12.1.2 Off-Normal Release of Radionuclides............................................ D.12-3 D.12.1.3 Postulated Accident..................................................................................... D.12-4 D.12.2 Blockage of Air Inlets/Outlets........................................................ D.12-4 D.12.2.1 Drop Accidents............................................................................... D.12-5 D.12.2.2 Earthquakes..................................................................................... D.12-6 D.12.2.3 Lightning......................................................................................... D.12-6 D.12.2.4 Fire and Explosion.......................................................................... D.12-7 D.12.2.5 Flood............................................................................................... D.12-8 D.12.2.6

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 30 Tornado Wind and Missiles............................................................ D.12-8 D.12.2.7 Reduced HSM Air Inlet and Outlet Shielding................................ D.12-9 D.12.2.8 References................................................................................................... D.12-10 D.12.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 31 Appendix E NAC-MPC E.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION...........................................................................................................E.1-1 E.2. SITE CHARACTERISTICS.........................................................................................E.2-1 E.3 PRINCIPAL DESIGN CRITERIA..............................................................................E.3-1 Yankee Rowe MPC and Connecticut Yankee MPC....................................E.3-2 E.3.1 Design Criteria for Environmental Conditions and Natural E.3.1.1 Phenomena......................................................................................... E.3-2 Safety Protection Systems.................................................................. E.3-6 E.3.1.2 Decommission Considerations........................................................... E.3-8 E.3.1.3 La Crosse MPC...............................................................................................E.3-9 E.3.2 Design Criteria for Environmental Conditions and Natural E.3.2.1 Phenomena....................................................................................... E.3-10 Safety Protection Systems................................................................ E.3-12 E.3.2.2 Decommissioning Considerations................................................... E.3-14 E.3.2.3 References......................................................................................................E.3-15 E.3.3 E.4 OPERATING SYSTEMS..............................................................................................E.4-1 Yankee Rowe MPC and Connecticut Yankee MPC....................................E.4-2 E.4.1 Transportable Storage Canister and Baskets...................................... E.4-2 E.4.1.1 Vertical Concrete Cask...................................................................... E.4-2 E.4.1.2 Transfer Cask..................................................................................... E.4-3 E.4.1.3 Ancillary Equipment.......................................................................... E.4-4 E.4.1.4 Storage Pad........................................................................................ E.4-5 E.4.1.5 La Crosse MPC...............................................................................................E.4-6 E.4.2 Transportable Storage Canister and Baskets...................................... E.4-6 E.4.2.1 Vertical Concrete Cask...................................................................... E.4-6 E.4.2.2 Transfer Cask..................................................................................... E.4-7 E.4.2.3 Ancillary Equipment.......................................................................... E.4-8 E.4.2.4 Storage Pad........................................................................................ E.4-9 E.4.2.5 References......................................................................................................E.4-10 E.4.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 32 Supplemental Data........................................................................................E.4-11 E.4.4 E.5 OPERATING PROCEDURES.....................................................................................E.5-1 Yankee Rowe MPC and Connecticut Yankee MPC....................................E.5-2 E.5.1 Loading the Vertical Concrete Cask.................................................. E.5-2 E.5.1.1 Transport and Placement of the Vertical Concrete Cask................... E.5-4 E.5.1.2 Removal of the Transportable Storage Canister from the E.5.1.3 Vertical Concrete Cask...................................................................... E.5-5 Receiving the NAC-STC Transport Cask and Unloading the E.5.1.4 Transportable Storage Canister.......................................................... E.5-6 La Crosse MPC...............................................................................................E.5-9 E.5.2 Loading the Vertical Concrete Cask.................................................. E.5-9 E.5.2.1 Transport and Placement of the Vertical Concrete Cask................. E.5-10 E.5.2.2 Removal of the Transportable Storage Canister from the E.5.2.3 Vertical Concrete Cask.................................................................... E.5-11 Receiving the NAC-STC Transport Cask and Unloading the E.5.2.4 Transportable Storage...................................................................... E.5-12 References......................................................................................................E.5-13 E.5.3 E.6. WASTE CONFINEMENT AND MANAGEMENT...................................................E.6-1 E.7 STRUCTURAL EVALUATION..................................................................................E.7-1 Yankee Rowe MPC and Connecticut Yankee MPC....................................E.7-2 E.7.1 Structural Design............................................................................... E.7-2 E.7.1.1 Weights and Centers of Gravity......................................................... E.7-2 E.7.1.2 Mechanical Properties of Materials................................................... E.7-2 E.7.1.3 Chemical and Galvanic Reactions..................................................... E.7-2 E.7.1.4 Positive Closure................................................................................. E.7-2 E.7.1.5 Lifting Devices................................................................................... E.7-2 E.7.1.6 NAC-MPC Components Under Normal Operating Loads................ E.7-2 E.7.1.7 Cold.................................................................................................... E.7-3 E.7.1.8 Fuel Rods........................................................................................... E.7-3 E.7.1.9 Coating Specifications....................................................................... E.7-3 E.7.1.10 Structural Evaluation of Yankee-MPC and CY-MPC Canister E.7.1.11 Confinement Boundaries under Normal Conditions of Transport............................................................................................ E.7-3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 33 La Crosse MPC...............................................................................................E.7-4 E.7.2 Structural Design............................................................................... E.7-4 E.7.2.1 Weights and Centers of Gravity......................................................... E.7-4 E.7.2.2 Mechanical Properties of Materials................................................... E.7-4 E.7.2.3 Chemical and Galvanic Reactions..................................................... E.7-4 E.7.2.4 Positive Closure................................................................................. E.7-4 E.7.2.5 Lifting Devices................................................................................... E.7-4 E.7.2.6 MPC-LACBWR Components Under Normal Operating Loads....... E.7-4 E.7.2.7 Fuel Rods........................................................................................... E.7-5 E.7.2.8 Canister Closure Weld Evaluation..................................................... E.7-5 E.7.2.9 Coating Specifications....................................................................... E.7-5 E.7.2.10 Structural Evaluation of MPC-LACBWR Canister E.7.2.11 Confinement Boundaries under Normal Conditions of Transport............................................................................................ E.7-5 References........................................................................................................E.7-6 E.7.3 E.8 THERMAL EVALUATION.........................................................................................E.8-1 Connecticut Yankee MPC, Yankee Rowe MPC, and La Crosse E.8.1 MPC.................................................................................................................E.8-2 Maximum Average Yearly Ambient Temperature............................ E.8-2 E.8.1.1 Maximum Average 3-Day Ambient Temperature............................. E.8-2 E.8.1.2 Maximum Extreme 3-Day Ambient Temperature Range.................. E.8-2 E.8.1.3 References........................................................................................................E.8-3 E.8.2 E.9 RADIATION PROTECTION......................................................................................E.9-1 Yankee Rowe MPC and Connecticut Yankee MPC....................................E.9-3 E.9.1 Yankee-MPC System Shielding Discussion and Results.................. E.9-3 E.9.1.1 CY-MPC System Shielding Discussion and Results......................... E.9-7 E.9.1.2 LaCrosse MPC..............................................................................................E.9-10 E.9.2 Shielding Discussion and Results for the MPC-LACBWR E.9.2.1 Storage System................................................................................. E.9-10 References......................................................................................................E.9-14 E.9.3 E.10 CRITICALITY EVALUATION................................................................................E.10-1 Connecticut Yankee MPC............................................................................E.10-3 E.10.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 34 CY-MPC System Criticality Discussion and Results...................... E.10-3 E.10.1.1 Yankee Rowe MPC.......................................................................................E.10-5 E.10.2 Yankee-MPC System Criticality Discussion and Results............... E.10-5 E.10.2.1 LaCrosse MPC..............................................................................................E.10-7 E.10.3 MPC-LACBWR System Criticality Discussion and Results........... E.10-7 E.10.3.1 References....................................................................................................E.10-10 E.10.4 E.11 CONFINEMENT EVALUATION.............................................................................E.11-1 Yankee Rowe MPC and Connecticut Yankee MPC..................................E.11-2 E.11.1 Confinement Boundary.................................................................... E.11-2 E.11.1.1 Requirements for Normal Conditions of Storage............................ E.11-2 E.11.1.2 Confinement Requirements for Hypothetical Accident E.11.1.3 Conditions........................................................................................ E.11-3 LaCrosse MPC..............................................................................................E.11-4 E.11.2 Confinement Boundary.................................................................... E.11-4 E.11.2.1 Requirements for Normal Conditions of Storage............................ E.11-4 E.11.2.2 Confinement Requirements for Hypothetical Accident E.11.2.3 Conditions........................................................................................ E.11-5 References......................................................................................................E.11-6 E.11.3 E.12 ACCIDENT ANALYSIS.............................................................................................E.12-1 Yankee Rowe MPC and Connecticut Yankee MPC..................................E.12-2 E.12.1 Off-Normal Events........................................................................... E.12-2 E.12.1.1 Accidents.......................................................................................... E.12-2 E.12.1.2 Concrete Cask Non-Mechanistic Tip-Over Analysis...................... E.12-4 E.12.1.3 La Crosse MPC...........................................................................................E.12-17 E.12.2 Off-Normal Events......................................................................... E.12-17 E.12.2.1 Accidents........................................................................................ E.12-17 E.12.2.2 Concrete Cask Non-Mechanistic Tip-Over Analysis.................... E.12-18 E.12.2.3 References....................................................................................................E.12-29 E.12.3

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 35 Appendix F NAC-UMS F.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION........................................................................................................... F.1-1 F.2. SITE CHARACTERISTICS......................................................................................... F.2-1 F.3 PRINCIPAL DESIGN CRITERIA.............................................................................. F.3-1 Maine Yankee.................................................................................................. F.3-2 F.3.1 Design Criteria for Environmental Conditions and Natural F.3.1.1 Phenomena......................................................................................... F.3-2 Safety Protection Systems.................................................................. F.3-5 F.3.1.2 Decommissioning Considerations..................................................... F.3-7 F.3.1.3 References........................................................................................................ F.3-8 F.3.2 F.4 OPERATING SYSTEMS.............................................................................................. F.4-1 Maine Yankee.................................................................................................. F.4-2 F.4.1 Transportable Storage Canister and Baskets...................................... F.4-2 F.4.1.1 Vertical Concrete Cask...................................................................... F.4-2 F.4.1.2 Transfer Cask..................................................................................... F.4-3 F.4.1.3 Auxiliary Equipment.......................................................................... F.4-4 F.4.1.4 References........................................................................................................ F.4-7 F.4.2 Supplemental Data.......................................................................................... F.4-8 F.4.3 F.5 OPERATING PROCEDURES..................................................................................... F.5-1 Maine Yankee.................................................................................................. F.5-2 F.5.1 Loading the Vertical Concrete Cask.................................................. F.5-2 F.5.1.1 Transport and Placement of the Vertical Concrete Cask................... F.5-4 F.5.1.2 Removal of the Transportable Storage Canister from the F.5.1.3 Vertical Concrete Cask...................................................................... F.5-5 Receiving the NAC-UMS Transport Cask and Unloading the F.5.1.4 Transportable Storage Canister.......................................................... F.5-6 References...................................................................................................... F.5-10 F.5.2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 36 F.6. WASTE CONFINEMENT AND MANAGEMENT................................................... F.6-1 F.7 STRUCTURAL EVALUATION.................................................................................. F.7-1 Maine Yankee.................................................................................................. F.7-2 F.7.1 Structural Design............................................................................... F.7-2 F.7.1.1 Weights and Centers of Gravity......................................................... F.7-2 F.7.1.2 Mechanical Properties of Materials................................................... F.7-2 F.7.1.3 Chemical and Galvanic Reactions..................................................... F.7-2 F.7.1.4 Positive Closure................................................................................. F.7-3 F.7.1.5 Lifting Devices................................................................................... F.7-3 F.7.1.6 NAC-UMS Components Under Normal Operating Conditions........ F.7-3 F.7.1.7 Cold.................................................................................................... F.7-3 F.7.1.8 Fuel Rods........................................................................................... F.7-3 F.7.1.9 Coating Specifications....................................................................... F.7-4 F.7.1.10 Structural Evaluation of NAC-UMS Canister Confinement F.7.1.11 Boundaries under Normal Conditions of Transport........................... F.7-4 References........................................................................................................ F.7-5 F.7.2 F.8 THERMAL EVALUATION......................................................................................... F.8-1 Maine Yankee.................................................................................................. F.8-2 F.8.1 Maximum Average Yearly Ambient Temperature............................ F.8-2 F.8.1.1 Maximum Average 3-Day Ambient Temperature............................. F.8-2 F.8.1.2 Maximum Extreme 3-Day Ambient Temperature............................. F.8-2 F.8.1.3 References........................................................................................................ F.8-3 F.8.2 F.9 RADIATION PROTECTION...................................................................................... F.9-1 Maine Yankee.................................................................................................. F.9-2 F.9.1 NAC-UMS System Shielding Discussion......................................... F.9-2 F.9.1.1 NAC-UMS System Shielding Radiation Sources.............................. F.9-3 F.9.1.2 NAC-UMS System Shielding Analysis and Results......................... F.9-4 F.9.1.3 References........................................................................................................ F.9-6 F.9.2 F.10 CRITICALITY EVALUATION................................................................................ F.10-1 Maine Yankee................................................................................................ F.10-3 F.10.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 37 NAC-UMS System Criticality Discussion....................................... F.10-3 F.10.1.1 NAC-UMS System Criticality Analysis and Results....................... F.10-4 F.10.1.2 References...................................................................................................... F.10-5 F.10.2 F.11 CONFINEMENT EVALUATION............................................................................. F.11-1 Maine Yankee................................................................................................ F.11-2 F.11.1 Confinement Boundary.................................................................... F.11-2 F.11.1.1 Confinement Requirements for Normal Conditions of Storage...... F.11-3 F.11.1.2 Confinement Requirements for Hypothetical Accident F.11.1.3 Conditions........................................................................................ F.11-3 References...................................................................................................... F.11-4 F.11.2 F.12 ACCIDENT ANALYSIS............................................................................................. F.12-1 Maine Yankee................................................................................................ F.12-2 F.12.1 Off-Normal Events........................................................................... F.12-2 F.12.1.1 Accidents.......................................................................................... F.12-2 F.12.1.2 Concrete Cask Non-Mechanistic Tip-Over Analysis...................... F.12-4 F.12.1.3 References.................................................................................................... F.12-14 F.12.2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 38 Appendix G NAC-MAGNASTOR G.1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.......................................................................................................... G.1-1 G.2. SITE CHARACTERISTICS........................................................................................ G.2-1 G.3 PRINCIPAL DESIGN CRITERIA............................................................................. G.3-1 Undamaged and Damaged PWR Fuel......................................................... G.3-2 G.3.1 Design Criteria for Environmental Conditions and Natural G.3.1.1 Phenomena........................................................................................ G.3-2 Safety Protection Systems................................................................. G.3-7 G.3.1.2 Decommissioning Considerations.................................................... G.3-8 G.3.1.3 References....................................................................................................... G.3-9 G.3.2 G.4 OPERATING SYSTEMS............................................................................................. G.4-1 Undamaged and Damaged PWR Fuel......................................................... G.4-2 G.4.1 Transportable Storage Canister (TSC).............................................. G.4-2 G.4.1.1 Fuel Baskets...................................................................................... G.4-2 G.4.1.2 Concrete Cask................................................................................... G.4-3 G.4.1.3 Transfer Cask.................................................................................... G.4-5 G.4.1.4 Damaged Fuel Can............................................................................ G.4-5 G.4.1.5 Storage Pad....................................................................................... G.4-6 G.4.1.6 Auxiliary Equipment......................................................................... G.4-6 G.4.1.7 References....................................................................................................... G.4-7 G.4.2 Supplemental Data......................................................................................... G.4-8 G.4.3 G.5 OPERATING PROCEDURES.................................................................................... G.5-1 Undamaged and Damaged PWR Fuel......................................................... G.5-2 G.5.1 Transferring the TSC to the Concrete Cask...................................... G.5-2 G.5.1.1 Transporting and Placing the Loaded Concrete Cask....................... G.5-5 G.5.1.2 Removing the Loaded TSC from a Concrete Cask........................... G.5-7 G.5.1.3 Receiving the MAGNATRAN Transport Cask and Unloading G.5.1.4 the Loaded TSC................................................................................ G.5-8

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 39 References..................................................................................................... G.5-13 G.5.2 G.6. WASTE CONFINEMENT AND MANAGEMENT.................................................. G.6-1 G.7 STRUCTURAL EVALUATION................................................................................. G.7-1 Undamaged and Damaged PWR Fuel......................................................... G.7-2 G.7.1 Structural Design.............................................................................. G.7-2 G.7.1.1 Weights and Centers of Gravity........................................................ G.7-2 G.7.1.2 Materials........................................................................................... G.7-2 G.7.1.3 Chemical and Galvanic Reactions.................................................... G.7-2 G.7.1.4 Positive Closure................................................................................ G.7-2 G.7.1.5 Lifting Devices.................................................................................. G.7-2 G.7.1.6 Normal Operating Conditions........................................................... G.7-2 G.7.1.7 Fuel Rods.......................................................................................... G.7-3 G.7.1.8 Structural Evaluation of NAC-MAGNASTOR Canister G.7.1.9 Confinement Boundaries under Normal Conditions of Transport........................................................................................... G.7-3 References....................................................................................................... G.7-4 G.7.2 G.8 THERMAL EVALUATION........................................................................................ G.8-1 Undamaged and Damaged PWR Fuel......................................................... G.8-2 G.8.1 Maximum Average Yearly Ambient Temperature........................... G.8-2 G.8.1.1 Maximum Average 3-Day Ambient Temperature............................ G.8-2 G.8.1.2 Maximum Extreme 3-Day Ambient Temperature Range................. G.8-2 G.8.1.3 Thermal Performance Surveillance Requirements........................... G.8-2 G.8.1.4 References....................................................................................................... G.8-3 G.8.2 G.9 RADIATION PROTECTION..................................................................................... G.9-1 Undamaged and Damaged PWR Fuel......................................................... G.9-3 G.9.1 Transfer Cask Shielding Discussion and Dose Results.................... G.9-3 G.9.1.1 Concrete Cask Shielding Discussion and Dose Results................... G.9-5 G.9.1.2 Offsite Dose Discussion and Results................................................ G.9-7 G.9.1.3 References....................................................................................................... G.9-9 G.9.2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 40 G.10 CRITICALITY EVALUATION............................................................................... G.10-1 Undamaged and Damaged PWR Fuel....................................................... G.10-2 G.10.1 Undamaged Fuel Criticality Results............................................... G.10-4 G.10.1.1 Damaged Fuel Criticality Results................................................... G.10-5 G.10.1.2 References..................................................................................................... G.10-6 G.10.2 G.11 CONFINEMENT EVALUATION............................................................................ G.11-1 Undamaged and Damaged PWR Fuel....................................................... G.11-2 G.11.1 Confinement Boundary................................................................... G.11-2 G.11.1.1 Requirements for Normal Conditions of Storage........................... G.11-2 G.11.1.2 Confinement Requirements for Hypothetical Accident G.11.1.3 Conditions....................................................................................... G.11-2 References..................................................................................................... G.11-3 G.11.2 G.12 ACCIDENT ANALYSIS............................................................................................ G.12-1 Undamaged and Damaged PWR Fuel....................................................... G.12-2 G.12.1 Off-Normal Events.......................................................................... G.12-2 G.12.1.1 Accidents and Natural Phenomena................................................. G.12-3 G.12.1.2 Concrete Cask Non-Mechanistic Tip-Over Analysis..................... G.12-4 G.12.1.3 References................................................................................................... G.12-15 G.12.2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 41 Appendix H Canisterized GTCC Waste H.1 INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.......................................................................................................... H.1-1 Introduction.................................................................................................... H.1-1 H.1.1 Principal Functions of the Installation.............................................. H.1-1 H.1.1.1 General Description of the Installation........................................................ H.1-2 H.1.2 GTCC Waste Canisters..................................................................... H.1-2 H.1.2.1 General System Description.......................................................................... H.1-3 H.1.3 Storage Systems................................................................................ H.1-3 H.1.3.1 Transfer System................................................................................ H.1-3 H.1.3.2 Identification of Agents and Contractors.................................................... H.1-4 H.1.4 Material Incorporated by Reference............................................................ H.1-5 H.1.5 References....................................................................................................... H.1-6 H.1.6 H.2 SITE CHARACTERISTICS........................................................................................ H.2-1 H.3 PRINCIPAL DESIGN CRITERIA............................................................................. H.3-1 Purpose of Installation................................................................................... H.3-2 H.3.1 Material to be Stored......................................................................... H.3-2 H.3.1.1 General Operating Functions............................................................ H.3-2 H.3.1.2 Structural and Mechanical Safety Criteria................................................. H.3-3 H.3.2 Seismic Design.................................................................................. H.3-3 H.3.2.1 Load Combination Criteria............................................................... H.3-3 H.3.2.2 Safety Protection System............................................................................... H.3-4 H.3.3 General.............................................................................................. H.3-4 H.3.3.1 Protection by Equipment and Instrumentation Selection.................. H.3-4 H.3.3.2 Nuclear Criticality Safety................................................................. H.3-4 H.3.3.3 Radiological Protection..................................................................... H.3-4 H.3.3.4 Fire and Explosion Protection........................................................... H.3-4 H.3.3.5 Materials Handling and Storage........................................................ H.3-5 H.3.3.6 Industrial and Chemical Safety......................................................... H.3-5 H.3.3.7 Decommissioning Considerations................................................................. H.3-6 H.3.4

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 42 Summary of WCS CISF Design Criteria..................................................... H.3-7 H.3.5 References....................................................................................................... H.3-8 H.3.6 H.4 INSTALLATION DESIGN.......................................................................................... H.4-1 Summary Description.................................................................................... H.4-1 H.4.1 Storage Systems.............................................................................................. H.4-2 H.4.2 H.4.2.1 Design Basis and Safety Assurance.................................................. H.4-2 H.4.2.2 Compliance with General Design Criteria........................................ H.4-2 H.4.2.3 Structural Specifications................................................................... H.4-4 H.4.2.4 Individual Unit Description.............................................................. H.4-4 Decontamination System............................................................................... H.4-5 H.4.3 H.4.3.1 Equipment Decontamination............................................................ H.4-5 H.4.3.2 Personnel Decontamination.............................................................. H.4-5 Repair and Maintenance............................................................................... H.4-6 H.4.4 H.4.4.1 Repair................................................................................................ H.4-6 H.4.4.2 Maintenance...................................................................................... H.4-6 Cathodic Protection....................................................................................... H.4-7 H.4.5 Waste Handling Operation Systems............................................................. H.4-8 H.4.6 References....................................................................................................... H.4-9 H.4.7 Supplemental Data Drawings..................................................................... H.4-10 H.4.8 H.5 OPERATION SYSTEMS............................................................................................. H.5-1 Operation Description................................................................................... H.5-2 H.5.1 GTCC Waste Handling Systems.................................................................. H.5-3 H.5.2 H.6 WASTE CONFINEMENT AND MANAGEMENT.................................................. H.6-1 Waste Sources................................................................................................. H.6-1 H.6.1 Off-gas Treatment and Ventilation.............................................................. H.6-2 H.6.2 Liquid Waste Treatment and Retention...................................................... H.6-3 H.6.3 Solid Wastes.................................................................................................... H.6-4 H.6.4 Radiological Impact of Normal Operations - Summary............................ H.6-5 H.6.5

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 43 H.7 RADIATION PROTECTION..................................................................................... H.7-1 Ensuring that Occupational Radiation Exposures Are As Low H.7.1 As Is Reasonably Achievable (ALARA)...................................................... H.7-1 Radiation Sources.......................................................................................... H.7-2 H.7.2 Characterization of Sources.............................................................. H.7-2 H.7.2.1 Airborne Radioactive Material Sources............................................ H.7-2 H.7.2.2 Radiation Protection Design Features......................................................... H.7-3 H.7.3 Shielding........................................................................................... H.7-3 H.7.3.1 Ventilation......................................................................................... H.7-3 H.7.3.2 Area Radiation and Airborne Radioactivity Monitoring H.7.3.3 Instrumentation................................................................................. H.7-3 Estimated Onsite Collective Dose Assessment............................................ H.7-4 H.7.4 Operational and Site Dose Assessment............................................. H.7-4 H.7.4.1 Health Physics Program................................................................................ H.7-5 H.7.5 Estimated Offsite Collective Dose Assessment............................................ H.7-6 H.7.6 Effluent and Environmental Monitoring Program............................ H.7-6 H.7.6.1 Analysis of Multiple Contributions.................................................. H.7-6 H.7.6.2 Estimated Dose Equivalents............................................................. H.7-6 H.7.6.3 Liquid Release.................................................................................. H.7-6 H.7.6.4 References....................................................................................................... H.7-7 H.7.7 H.8 ANALYSIS OF DESIGN............................................................................................. H.8-1 Normal and Off-Normal Operations............................................................ H.8-2 H.8.1 Accident Analyses for the WCS CISF.......................................................... H.8-3 H.8.2 Accidental GTCC Canister/Cask Drop............................................. H.8-3 H.8.2.1 GTCC Canister Leakage................................................................... H.8-3 H.8.2.2 Accident Pressurization.................................................................... H.8-3 H.8.2.3 Earthquake........................................................................................ H.8-3 H.8.2.4 Fire.................................................................................................... H.8-3 H.8.2.5 References....................................................................................................... H.8-4 H.8.3 H.9 CONDUCT OF OPERATIONS.................................................................................. H.9-1 Organizational Structure.............................................................................. H.9-2 H.9.1 Pre-Operational Testing and Operation...................................................... H.9-3 H.9.2

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 44 Training Program.......................................................................................... H.9-4 H.9.3 Normal Operations........................................................................................ H.9-5 H.9.4 Emergency Planning...................................................................................... H.9-6 H.9.5 Decommissioning Plan................................................................................... H.9-7 H.9.6 H.10 OPERATING CONTROLS AND LIMITS.............................................................. H.10-1 Proposed Operating Controls and Limits................................................. H.10-1 H.10.1 Development of Operating Controls and Limits....................................... H.10-2 H.10.2 References..................................................................................................... H.10-3 H.10.3 H.11 QUALITY ASSURANCE.......................................................................................... H.11-1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-i CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION Table of Contents 1.

INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION.............................................................................................................. 1-1 Introduction............................................................................................................... 1-2 1.1 General Description of Installation.......................................................................... 1-4 1.2 1.2.1 Location and Site Characteristics............................................................... 1-4 1.2.2 Principal Design Criteria........................................................................... 1-5 1.2.3 Facility Descriptions................................................................................... 1-5 1.2.4 Materials To Be Stored............................................................................... 1-6 1.2.5 Waste Products Generated During Operations........................................ 1-11 General Description of Systems and Operations................................................... 1-12 1.3 1.3.1 WCS Consolidated Interim Storage Facility Systems............................... 1-12 1.3.2 WCS Consolidated Interim Storage Facility Operations.......................... 1-13 Analysis of Operations............................................................................................ 1-15 1.4 1.4.1 Normal Operations - Dose Assessment.................................................... 1-15 1.4.2 Normal Operations - Establishment of the Controlled Area (Site)

Boundary................................................................................................... 1-15 1.4.3 Accident Analysis...................................................................................... 1-15 1.4.4 Safety Management................................................................................... 1-17 Identification of Agents and Contractors............................................................... 1-18 1.5 Material Incorporated by Reference...................................................................... 1-19 1.6 1.6.1 NUHOMS Systems.................................................................................. 1-19 1.6.2 NAC International Systems....................................................................... 1-19 References............................................................................................................... 1-21 1.7

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-ii List of Tables Table 1-1 Storage Systems at the WCS CISF..................................................................... 1-22 Table 1-2 Summary of WCS CISF Principal Design Criteria............................................ 1-23 Table 1-3 WCS CISF Facilities and Functions.................................................................. 1-26 Table 1-4 Table of Topical Reports (SARs) Incorporated by Reference............................ 1-27 Table 1-5 Ground Surface DRS.......................................................................................... 1-30

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-iii List of Figures Figure 1-1 WCS CISF Location........................................................................................... 1-31 Figure 1-2 WCS CISF Site Boundary Layout...................................................................... 1-32 Figure 1-3 WCS CISF Site Overview................................................................................... 1-33 Figure 1-4 Site Location Map.............................................................................................. 1-34 Figure 1-5 10,000-Year Return Period Response Spectra (5% Damped)........................... 1-35 Figure 1-6 WCS CISF Storage Pad Layout......................................................................... 1-36 Figure 1-7 Cask Handling Building Plan............................................................................ 1-37 Figure 1-8 Cask Handling Building Section View............................................................... 1-38 Figure 1-9 Security Administration Building Plan.............................................................. 1-39

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-1

1.

INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION This Safety Analysis Report (SAR) describes the design and forms the licensing basis for the 10 CFR 72 [1-1] facility license of the Interim Storage Partners (ISPs) WCS Consolidated Interim Storage Facility (WCS CISF) to be located in Andrews County, Texas.

The quality assurance (QA) program applicable to this design satisfies the requirements of 10 CFR 72, Subpart G and is described in the Quality Assurance Program Description [1-2]. To facilitate U.S. Nuclear Regulatory Commission (NRC) review of this application, this SAR has been prepared in compliance with the information and methods defined in Revision 0 of NRC NUREG-1567 [1-3].

This SAR describes a facility designed to accept commercial spent nuclear fuel and Greater-than-Class C (GTCC) waste contained in dual-purpose (transportation/storage) cask and canister systems that have been approved by the NRC for spent nuclear fuel. The NUHOMS-MP187 GTCC waste canister is currently included in a specific license for storage and is also certified by the NRC for transport under 10 CFR Part 71. The GTCC waste canisters for the NAC systems are certified by the NRC for transport under 10 CFR Part 71. The WCS CISF will ultimately accommodate 40,000 metric tons Uranium or Mixed-Oxide, or metric tons heavy metal (MTHM), and will have a service life of at least 40 years. This initial SAR, however, is for phase 1 of the project, which is to material defined in Conditions 8A and 8B of the license for storage in the same canisters and overpacks as those currently in use at several reactor sites in the United States.

This chapter provides a summary of the SAR. The following information is included:

(1) a general description of the WCS CISF; (2) a general description of the systems and operations; (3) analysis of the WCS CISF operations; (4) identification of agents and contractors; and (5) material incorporated into this SAR by reference.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-2 Introduction 1.1 Interim Storage Partners (ISP) is a joint venture (JV) between Waste Control Specialists LLC and Orano CIS LLC formed to design, license, construct, and operate the WCS CISF.

Waste Control Specialists currently operates two separate Low-Level Radioactive Waste (LLRW) disposal facilities at the Andrews County site, including the Texas Compact Disposal Facility. Orano CIS, through its parent Orano USA, is a leading company in the safe management, dry storage and transportation of spent nuclear fuel with more than 30 years of experience in the United States.

The need for an interim storage facility for spent nuclear fuel arises as a result of the ongoing decades long search for a disposal solution for the nations spent nuclear fuel.

In 2012, the presidential-appointed Blue Ribbon Commission on Americas Nuclear Future issued a report recommending that at least one interim storage facility be sited in the U.S., while a permanent disposal site is being developed.

Consistent with the recommendation of the Blue Ribbon Commission on Americas Nuclear Future, the WCS CISF will provide dry storage capacity for canisterized spent nuclear fuel and GTCC waste at the WCS CISF site in the same storage overpack designs as those currently licensed and used at the original storage sites. ISP is seeking a license to operate a CISF for spent fuel and GTCC waste storage for 40 years in accordance with 10 CFR Part 72.

Construction of the WCS CISF is planned to start in September 2021 and operation is planned to begin in July 2023.

The WCS CISF will be located within the owner-controlled area of the existing Waste Control Specialists site, which is operated by Waste Control Specialists. The site comprises approximately 14,000 acres in Andrews County, Texas. It is characterized by isolation from population centers, a sound foundation for structures, and favorable conditions of meteorology, seismology, and hydrology.

The proposed location of the CISF site within the Waste Control Specialists site is on the north west corner. Figure 1-1 shows the general location of the WCS CISF at the Waste Control Specialists site.

Spent nuclear fuel at the WCS CISF will be stored in cask systems that have been previously approved by the NRC. These cask systems include transportable canister-based storage systems. It is ISPs intent that all NRC approved dual-purpose (transportation/storage) or multi-purpose (transportation/storage/ disposal) cask systems be acceptable for use at the WCS CISF over time. For Phase I of the WCS CISF application, six (6) cask systems consisting of eleven (11) different canisters plus GTCC waste canisters stored in five (5) overpacks are proposed for storage at the WCS CISF. These cask systems are described in SARs that are docketed by the NRC.

Appendix H of the SAR addresses canisterized GTCC waste. Table 1-1 provides a listing of the various cask systems proposed for storage at the WCS CISF.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-3 The cask systems listed in Table 1-1 were originally approved for 20 years. An application for License Renewal for the cask systems associated with CoC 1004 for an additional 40 years is currently being reviewed by the NRC. Work is also currently underway to develop an application for License Renewal for SNM-2510 for timely submittal to the NRC. The remaining cask systems in the WCS CISF License Application have not yet reached 20 years of time in service and therefore work has not yet begun to develop the applications for License Renewal for these systems. As these systems approach 20 years of service time, their applications for License Renewal, including Aging Management Program (AMP) requirements, will be submitted to the NRC for review and approval. Any canisters stored at the WCS CISF will have been loaded under these previously approved NRC CoCs and licenses, and their time in service clock for triggering the implementation of required AMP activities will have begun at the time of loading for each individual canister.

Therefore, the AMP activities for any of the canisters stored at the site will be established and approved well in advance of license renewal for the site-specific license for the WCS CISF. Similarly, AMP activities for the storage overpacks at the WCS CISF will be established by their respective CoCs and licenses, but their time in service clocks will begin at the time of their loading at the WCS CISF. As the aging management activities associated with the individual CoCs and licenses under which the systems were originally loaded have not been approved at this time, a condition imposed on this license [1-4] is to incorporate the required aging management activities into this license within 120 days of the effective date of the renewal authorization of a given authorized cask systems CoC or license, or within 120 days of the effective date of this license, whichever is later.

The canister-based cask systems require transfer of the canister from the transportation cask to the storage overpack. These transfers are performed in either the Cask Handling Building or the Storage Area, depending on the cask system design. All transfer and handling activities are accomplished in a dry mode using cask transfer equipment and WCS CISF structures, systems, and components (SSCs). The WCS CISF design, as presented in the SAR, does not employ a spent fuel pool or other bare fuel handling capability.

Chapter 3 identifies the important-to-safety (ITS) SSCs for the cask systems and the WCS CISF and those not-important-to-safety (NITS) SSCs that are necessary for the operation of the WCS CISF. Cask system SSCs are used to the maximum extent possible in the design of the WCS CISF and are described in the design and licensing basis documents associated with each cask system. The use of previously approved cask systems is an integral part of the WCS CISF design basis. The WCS CISF SSCs that are ITS include the Canister Transfer System in the Cask Handling Building and the storage pads for the vertical storage systems.

The physical, thermal, and radiological characteristics of the spent nuclear fuel (SNF) to be stored at the WCS CISF are defined in the respective cask system SARs.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-4 General Description of Installation 1.2 The WCS CISF is designed as a stand-alone facility and consists of a storage area, and support facilities. The facility boundary is established at the outer limits by the Part 73 Owner Controlled Area (OCA). The Protected Area (PA) boundary is approximately 660 feet inside of the OCA boundary. The storage area is approximately 330 feet inside of the PA boundary. These areas are shown in Figure 1-2, WCS CISF Site Boundary Layout.

Figure 1-3 is a blow-up view of the facility showing the storage area and the support facilities inside the Protected Area. Support facilities include the Cask Handling Building, the Security and Administration Building, Transport Haul Route, and Rail Access.

The SSCs that are important-to-safety are listed in Table 3-5. Table 3-5 also lists the SSCs that are classified as not important-to-safety. Because there is no waste generated during the storage phase, there are no gaseous, liquid, or solid radioactive waste treatment systems associated with the storage system. Likewise, heat removal is totally passive in the overpacks and no active cooling system is required. Therefore, there are no required Instrumentation and Control Systems for the WCS CISF.

1.2.1 Location and Site Characteristics The WCS CISF is located approximately 32 miles west of the city of Andrews, Texas, and five miles east of the city of Eunice, New Mexico. The WCS CISF facility is located approximately one-half mile east of the Texas-New Mexico state boundary and one mile north of Texas Highway 176. The Waste Control Specialists site occupies parts of Section 16 and 17, Block A-29, Public School Land, Andrews County, Texas included in approximately 25 square miles of property (primarily in Texas with nominal acreage in New Mexico) controlled by Waste Control Specialists LLC in northwestern Andrews County, Texas. Waste Control Specialists LLC will retain control of the Site, free and clear of any liens, claims or encumbrances, and will make available the portion of the Site to be used for the WCS CISF under a long-term lease.

The WCS CISF is situated in an arid, isolated part of the state. Figure 1-4 shows the location of the facility with respect to known or easily identifiable landmarks.

Figure 1-4, as supplemented by Figure 1-1, illustrates county boundaries, rail access, highways, and major roads.

The approximate coordinates of the site are 32° 27' 08" north latitude and 103° 03' 35" west longitude.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-5 1.2.2 Principal Design Criteria The WCS CISF principal design criteria are based on the site characteristics, the design criteria associated with the cask systems listed in Table 1-1 that have been previously approved by the NRC, and specific criteria required for the WCS CISF design.

The cask systems listed in Table 1-1 meet the WCS CISF design criteria. Table 1-2 provides a summary of the WCS CISF principal design criteria.

1.2.3 Facility Descriptions The major facilities at the WCS CISF are the Cask Handling Building and the storage area. The Cask Handling Building is approximately 140 feet long by 130 feet wide by 70 feet high. The building is a two-bay steel structure designed to support two commercial overhead cranes used to move transportation casks from the rail car to the transport vehicle. One bay of the building will house the Canister Transfer System described in Section 1.3.1.2 and the other bay will be available for direct transfer of transportation casks from the rail car to the transport vehicle. A 2,400 square foot area of the building is set aside for cask storage. The building plan view is shown in Figure 1-7. Figure 1-8 is a section through the building showing the overhead crane location. Air monitors and dosimeters are located in the building for monitoring purposes. The building is not designed or intended to provide confinement or shielding for SNF or GTCC materials. The building is classified as ITS - Category C.

The purpose of the Cask Handling Building is to receive and prepare for storage shipments of dual-purpose canister systems. It will also receive GTCC waste canisters for storage at the site. It is also designed to process canisters stored at the site for off-site shipment. The Cask Handling Building is designed to handle canisterized material and does not have the capability to handle bare fuel.

As Low As Reasonably Achievable (ALARA) principles are incorporated, to the maximum extent practical, throughout the facility design to reduce radiation exposure to facility personnel. Cranes/lifting devices for transferring the NUHOMS transportation/transfer casks from the transportation skid to the transfer trailer/skid are designed to minimize the need for facility personnel to be near the loaded cask. This equipment is NITS as the lift heights of the loaded casks are maintained below 80 inches at all times after removal of the impact limiters. The analysis of bounding drop scenarios shows that a NUHOMS transportation/transfer cask will maintain structural integrity of the DSC confinement boundary and maintain basket geometry from an 80 inch (from the bottom of the cask to the ground) drop. The ITS canister transfer system for the vertical transfer of canisters is remotely operated and the transfer equipment used to make the transfer to the storage overpacks is substantially identical to that used to transfer the canister into dry storage at the reactor facilities where the material was initially stored.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-6 The storage area is a large area comprised of concrete storage pads and storage overpacks. The purpose of the storage area is to provide safe storage for the canisterized spent nuclear fuel in cask systems that were previously approved by the NRC. The pads and approach aprons are designed to meet the applicable requirements of these previously approved cask systems. The storage area will be constructed in phases, as necessary. Phase 1 is designed to accommodate approximately 5,000 MTHM of spent nuclear fuel and GTCC waste in approximately 470 storage overpacks. Figure 1-6 shows the Phase 1 storage area. The individual storage pads are constructed of reinforced concrete at approximately ground level. Horizontal storage module pads will have concrete approach aprons. Vertical storage module pads will be surrounded by gravel approach roads.

The Security and Administration Building is a commercially designed and fabricated steel building with a reinforced concrete floor and foundation. The building primarily functions as the location for the Central Alarm Station and for Health Physics spaces.

Additionally, the building provides additional security and administration spaces and is the main personnel entrance and exit for the facility. Figure 1-9 shows the Security and Administration Building Layout.

The remainder of the WCS CISF facilities provide support functions such as fuel receipt, security, and fire protection. Table 1-3 provides a list of the WCS CISF facilities and their functions.

1.2.4 Materials To Be Stored Only canisters that have been previously approved by the NRC to store and transport commercial light water (PWR and BWR) spent nuclear fuel and GTCC waste will be received at the WCS CISF. The controls for limiting the types and forms of spent nuclear fuel received at the WCS CISF include those placed on the cask systems by the NRC-issued site licenses or certificates of compliance for the included transportation and storage systems. The approved systems are listed in Section 2.1 of the Technical Specifications [1-4], which include an additional limitation on uncanned high burnup fuel. The type, form and sources authorized for storage include:

Canisterized spent nuclear fuel elements from commercial nuclear utilities licensed pursuant to 10 CFR Part 50 and associated radioactive materials related to the receipt, transfer, and storage of that spent nuclear fuel.

Uranium or Mixed-Oxide (MOX) in the form of intact spent fuel assemblies, damaged fuel assemblies, and fuel debris, as specified in Section 2.1 of the WCS CISF Technical Specifications [1-4].

Canisterized GTCC waste that consists of only reactor related low-level radioactive waste generated as a result of plant operation and decommissioning where the radionuclide concentration limits of Class C waste in 10 CFR 61.55 are exceeded. This waste may include such components as incore components, core support structures, and small reactor related miscellaneous parts resulting from the reactor vessel internals segmentation/decommissioning processes.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-7 All waste stored within the various GTCC canisters will be in the physical form of activated metals that may have surface contamination. The GTCC canisters will not contain process wastes containing paper, plastics or ion exchange resins that could result in the generation of combustible gases or chemical or galvanic corrosion reactions with the canister.

Aging Management considerations for the canisters and storage overpacks are discussed in Section 11.5.

Use of NRC Approved Storage Cask Systems 1.2.4.1 For Phase 1 of the ISP application, canisterized spent nuclear fuel and GTCC waste are stored at the WCS CISF in six cask storage systems previously approved by the NRC. The six storage systems used at the WCS CISF during Phase 1 are:

1. NUHOMS MP187 Storage System as Configured for the WCS CISF NUHOMS MP187 Cask Storage System as configured for the WCS CISF is described in Rancho Seco Independent Spent Fuel Storage Installation Safety Analysis Report Revision 4, NRC Docket No. 72-11. This configuration includes the overpack and canisters included in NRC SNM License 2510, Amendment 4. Specifically, the NUHOMS MP187 Storage System will use the HSM (Model 80) overpack to house one of three types of approved spent fuel canisters, the FO-DSC, FC-DCS or FF-DSC. The contents of the NUHOMS MP187 Storage System during Phase 1 are those contents currently authorized in NRC SNM License 2510, Amendment 4.

2. Advanced Standardized NUHOMS Storage System as Configured for the WCS CISF Advanced Standardized NUHOMS Storage System as configured for the WCS CISF is described in Updated Final Safety Analysis Report for the Standardized Advanced NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel TN Americas Document No. ANUH-01.0150, Revision 6, NRC Docket No. 72-1029. This configuration includes the overpack and canister included in NRC Certificate of Compliance 72-1029, Amendments 0, 1, and 3. Specifically, the Advanced Standardized NUHOMS Storage System will use the AHSM overpack to house the NUHOMS 24PT1 spent fuel canister. The contents of the Advanced Standardized NUHOMS Storage System during Phase 1 are those contents currently authorized in NRC Certificate of Compliance 72-1029, Amendments 0, 1, and 3.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-8

3. Standardized NUHOMS Storage System as Configured for the WCS CISF Standardized NUHOMS Storage System as configured for the WCS CISF is described in Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel TN Americas Document No. NUH-003, Revision 14, NRC Docket No. 72-1004. This configuration includes the overpack and canisters included in NRC Certificate of Compliance 72-1004, Amendments 3-13. Specifically, the Standardized NUHOMS Storage System will use the HSM Model 102 overpack to house either the NUHOMS 61BT or NUHOMS 61BTH Type 1 spent fuel canister. The contents of the Standardized NUHOMS Storage System during Phase 1 are those contents currently authorized in NRC Certificate of Compliance 72-1004, Amendments 3-13.

4. NAC-MPC Storage System as Configured for the WCS CISF NAC-MPC Storage System as configured for the WCS CISF is described in NAC Multipurpose Cask Final Safety Analysis Report, Revision 10, NRC Docket No. 72-1025. This configuration includes the overpack and canisters included in NRC Certificate of Compliance 72-1025, Amendments 0-6.

Specifically, the NAC-MPC Storage System will use the VCC overpack to house one of three approved spent fuel canisters, the Yankee Class, Connecticut Yankee or LACBWR. The contents of the NAC-MPC Storage System during Phase 1 are those contents currently authorized in NRC Certificate of Compliance 72-1025, Amendments 0-6.

5. NAC-UMS Storage System as Configured for the WCS CISF NAC-UMS Storage System as configured for the WCS CISF is described in Final Safety Analysis Report for the UMS Universal Storage System, Revision 10, NRC Docket No. 72-1015. This configuration includes the overpack and canisters included in NRC Certificate of Compliance 72-1015, Amendments 0-5. Specifically, the NAC-UMS Storage System will use the VCC overpack to house NAC-UMS Class 1 through 5 canisters. The contents of the NAC-UMS Storage System during Phase 1 are those contents currently authorized in NRC Certificate of Compliance 72-1015, Amendments 0-5.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-9

6. MAGNASTOR Storage System as Configured for the WCS CISF MAGNASTOR Storage System as configured for the WCS CISF is described in MAGNASTOR Final Safety Analysis Report, Revision 7, NRC Docket No. 72-1031. This configuration includes the overpacks and canisters included in NRC Certificate of Compliance 72-1031, Amendments 0-3, Revision 1, and Amendments 4 and 5. The MAGNASTOR Storage System will use the CC1, CC2, CC3 or CC4 overpacks to house four approved types of canisters, the TSC1 through TCS4 canisters. The contents of the MAGNASTOR Storage System during Phase 1 are those contents currently authorized in NRC Certificate of Compliance 72-1031, Amendments 0-3, Revision 1, and Amendments 4 and 5.

Descriptions of the storage systems used at the WCS CISF are summarized in Table 1-1.

In addition Table 1-1 addresses the canisters for storing GTCC waste in the storage overpack designs described in Appendix H under the WCSs CISF license.

The GTCC Canister to be stored in the NUHOMS MP187 Cask Storage System as configured for the WCS CISF is described in Appendix C of the Rancho Seco Independent Spent Fuel Storage Installation Safety Analysis Report Revision 4, NRC Docket No. 72-11. This configuration includes the overpack and canister included in NRC SNM License 2510, Amendment 4. Specifically, the NUHOMS MP187 Storage System will use the HSM (Model 80) overpack to house the GTCC waste canister. The contents of the NUHOMS MP187 Storage System during Phase 1 are those contents currently authorized in NRC SNM License 2510, Amendment 4 for the GTCC waste.

The GTCC-Canister-CY and GTCC-Canister-YR to be stored in the NAC MPC Storage System as configured for the WCS CISF are described in Appendix H and NAC-STC, NAC Storage Transport Cask Safety Analysis Report, Revision 17, USNRC Docket No. 71-9235. This configuration includes the overpack included in NRC Certificate of Compliance 72-1025, Amendments 0-6 and the GTCC-Canister-CY and GTCC-Canister-YR included in NRC Certificate of Compliance No. 9235. Specifically, the NAC-MPC Storage System will use the VCC overpack to house either the GTCC-Canister-CY or GTCC-Canister-YR.

The contents of the GTCC-Canister-CY or GTCC-Canister-YR during Phase 1 are those contents currently authorized in NRC Certificate of Compliance No 9235.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-10 The GTCC-Canister-MY to be stored in the NAC UMS Storage System as configured for the WCS CISF is described in Appendix H and Safety Analysis Report for the UMS Universal Transport Cask, Revision 2, USNRC Docket No. 71-9270. This configuration includes the overpack included in NRC Certificate of Compliance 72-1015, Amendments 0-5 and the GTCC-Canister-MY included in NRC Certificate of Compliance No. 9270. Specifically, the NAC-UMS Storage System will use the VCC overpack to house the GTCC-Canister-MY. The contents of the GTCC-Canister-MY during Phase 1 are those contents currently authorized in NRC Certificate of Compliance No 9270.

The GTCC-Canister-ZN to be stored in the MAGNASTOR Storage System as configured for the WCS CISF is described in Appendix H and Safety Analysis Report for the MAGNATRAN Transport Cask, Revisions 12A, 14A and 15A, USNRC Docket No. 71-9356. This configuration includes the overpack included in NRC Certificate of Compliance 72-1031, Amendments 0-3, Revision 1, and Amendments 4 and 5 and the GTCC-Canister-ZN included in Safety Analysis Report for the MAGNATRAN Transport Cask, Revisions 12A, 14A and 15A, USNRC Docket No. 71-9356. Specifically, the MAGNASTOR Storage System will use one of the CC1 through CC4 overpacks to house the GTCC-Canister-ZN.

The contents of the GTCC-Canister-ZN during Phase 1 are those contents currently addressed in Safety Analysis Report for the MAGNATRAN Transport Cask, Revisions 12A, 14A and 15A, USNRC Docket No. 71-9356.

Pre-Shipment Review of Canisters 1.2.4.2 ISP will verify that every spent fuel canister received at the WCS CISF would comply with the terms, conditions of use, and technical specifications of one of the six storage systems listed in Section 2.1 of the Technical Specifications [1-4], when stored in the canisters approved overpack.

This verification will include a determination of the Certificate amendment under which the canister was loaded and an evaluation of any changes made to the canister under 10 CFR 72.48.

If it is determined, prior to acceptance, that a loaded canister does not comply, ISP would undertake further evaluation to determine if their site specific license should be amended, or if an evaluation done under 10 CFR 72.48 for the WCS CISF would support such a change without an amendment.

ISP will review 10 CFR 72.48 evaluations completed by other licensees or Certificate holders and determine if these evaluations can be clearly shown to be applicable to WCS CISF. ISP will prepare its own 72.48 evaluations in such instances.

ISP shall maintain procedures for and records of its reviews performed according to this section.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-11 1.2.5 Waste Products Generated During Operations As described in Chapter 6, there are minimal radioactive wastes generated at the WCS CISF. Gaseous and liquid wastes are not generated at the WCS CISF. Small volumes of solid radioactive waste may be produced from routine operations involving contamination surveys and decontamination activities involving incoming and outgoing transportation casks and equipment. Potential solid waste streams are collected and temporarily stored on site until authorization under Waste Control Specialists Low Level Radioactive Waste (LLRW) License RML R04100 allows for processing and disposal.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-12 General Description of Systems and Operations 1.3 A general description of the WCS CISF systems and operations is provided in this section. The systems described relate to the receipt, handling, transfer, and storage of canisterized spent nuclear fuel and GTCC waste. In general, the same systems provide the corresponding function for canister retrieval and off site shipment operations.

1.3.1 WCS Consolidated Interim Storage Facility Systems The major systems for the WCS CISF include the following: Cask Off-Loading and Loading System in the Cask Handling Building, Canister Transfer System (for vertical systems) and Transfer Cask or Storage Overpack Carrier System. These systems are used to transfer canisterized spent nuclear fuel and GTCC waste from transportation systems to storage overpacks and are used to retrieve canisters for off-site shipment.

Cask Off-Loading and Loading System 1.3.1.1 The purpose of the Cask Off-Loading and Loading System is to remove transportation casks from the cask railcars and to move transportation casks onto the railcars for shipment from the WCS CISF. Major components include two 130-ton capacity overhead bridge cranes and a Vertical Cask Transporter (VCT), which is also used to carry and position the loaded vertical concrete cask (VCC) to its storage pad position.

The overhead bridge cranes and associated lifting fixtures are used to perform a horizontal transfer of the NUHOMS transportation/transfer cask from the railcar (skid) onto the transfer skid for transfer operations. This transfer is performed without lifting the loaded NUHOMS transportation/transfer cask above a height of 80 and these cranes are classified as NITS. The ITS VCT is used to upright transportation casks and place the casks under the Canister Transfer System for the vertical storage systems. The VCT is also used to collect the vertical transportation cask following loading with the Canister Transfer System and place/down end the transportation cask onto the railcar for offsite transport.

Canister Transfer System 1.3.1.2 For vertical systems, the ITS Canister Transfer System is used to transfer spent nuclear fuel and GTCC waste canisters from the uprighted transportation casks to vertical storage overpacks. Major components include a shielded transfer cask, mobile gantry crane and ancillary equipment used to move the canisters from the upright transportation cask to the vertical storage overpack. This system is not used with the NUHOMS Systems.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-13 Transfer Cask or Storage Overpack Carrier System 1.3.1.3 For NUHOMS Systems the purpose of this equipment is to transfer the cask out to the Horizontal Storage Module (HSM) and transfer the canister into the HSM or retrieval of same. For vertical systems, the purpose of this equipment is to upright the transportation cask and place it under the Canister Transfer System and to transfer the storage overpack from the transfer station to the storage pad or to return the overpack to the transfer station when the canister is to be shipped off-site. Major components for the NUHOMS System include the transfer trailer, skid, skid positioning system, HSM/cask restraint system, hydraulic ram and alignment equipment. The major component for the vertical system is a VCT to move the cask from the transfer station to the storage pad.

Waste Management Systems 1.3.1.4 The WCS CISF does not have any major radioactive waste management systems. The only radioactive wastes generated are the result of residual quantities of radioactive contamination on the transportation casks. Solid wastes generated during the decontamination process are disposed of at a licensed disposal facility.

Not Used 1.3.1.5 Storage Pad 1.3.1.6 For the NUHOMS Systems the basemat and approach slabs are not relied upon to provide any safety function. There are no structural connections or other positive means to transfer shear between the modules and the foundation slab. The HSMs are not connected to the basemat. They resist horizontal forces by friction. Therefore, basemat and approach slabs are considered NITS and are designed, constructed, maintained, and tested as commercial-grade items.

The concrete storage pads loaded with NAC-MPC, NAC-UMS, and MAGNASTOR VCC systems meet the concrete storage pad properties presented in CoC No. 1025, Section B 3.4, CoC No. 1015, Section B 3.4, and CoC No. 1031, Sections 4.3.1 and 5.4, respectively. There are no structural connections or other positive means to transfer shear between the VCC systems and the slab. The VCC systems are not connected to the basemat, and resist horizontal forces by friction. The storage pads used for placement of NAC-MPC, NAC-UMS, and MAGNASTOR VCCs are classified as ITS, as identified in Chapter 3 and Chapter 7.

1.3.2 WCS Consolidated Interim Storage Facility Operations Loaded transportation casks containing spent fuel or GTCC waste canisters are received via rail car. Security inspections and radiation surveys are performed in accordance with 10 CFR Part 71 and transportation cask CoC requirements.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-14 The transportation casks are radiologically surveyed, impact limiters removed, their cavities are vented and tested, and they are decontaminated as necessary. Once receipt is completed under the provisions of 10 CFR Part 71, the cask is prepared to be removed from the railcar so that the canister can be transferred to the storage overpack. For NUHOMS Systems, the cask is lifted horizontally from the transportation skid and placed on the transfer trailer where it is readied to be transferred to the storage pad and its designated HSM. The canister/cask is then transferred to the storage pad where the canister is inserted into its HSM. For vertical systems, the transportation cask is uprighted, placed in the transfer station, and made ready such that the canister can be retrieved with a shielded transfer cask and the canister transferred to the storage overpack. Once the canister is transferred to the storage overpack, the overpack is then moved using the VCT out to the storage pad and placed in its designated location for storage.

For canister retrieval operations, the operational sequences for placing the canister into storage are reversed.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-15 Analysis of Operations 1.4 This section provides a summary of the analyses performed for normal operations, off-normal and accident conditions.

1.4.1 Normal Operations - Dose Assessment ALARA practices and dose reduction techniques are incorporated into the design of the WCS CISF. The receipt and transfer operations incorporate the ALARA principles and operational experience gained from the operations of these NRC licensed cask systems. The calculated operational exposures are very conservative, as the assumed dose rates on and around the transport/transfer casks are assumed to be for design basis transportation sources and the assumed dose rates on and around the storage overpacks are based on design basis source terms in the existing storage FSARs. These storage source terms, in most cases, are much higher than what can be accommodated by the transportation cask and therefore significant decay is required prior to shipment to the WCS CISF.

The maximum calculated occupational exposure for normal transfer operations is 232 person-rem when the 5,000 MTHM and GTCC waste canisters are placed into storage.

Chapter 9 and its associated appendices provide a detailed evaluation of occupational exposures.

1.4.2 Normal Operations - Establishment of the Controlled Area (Site) Boundary An analysis was performed to identify the location of the controlled area boundary to ensure compliance with 10 CFR 72.104 (a) (dose rate 25 mrem/yr). As noted above, the dose rates assumed on the surface of the storage overpacks are based on the design basis source terms in the licensed storage systems at the reactor sites.

The annual expected yearly dose at the nearest site boundary for the fully loaded (5,000 MTHM plus GTCC waste canisters) WCS CISF is 4.29E-5 person-rem, including direct radiation (including skyshine) and contributions due to inhalation, submersion and ingestion from non-leak-tight containers. Chapters 9 and 11 and their associated appendices provide a detailed evaluation of site boundary exposures.

1.4.3 Accident Analysis Safety Analysis Process 1.4.3.1 Chapter 12 and design specific appendices provide analysis for the off-normal and accident conditions for the approved storage systems. Chapter 12 defines the design basis events for each authorized cask system. The WCS CISF Technical Specifications [1-4] complete the design safety basis by defining the operational controls and limits placed on WCS CISF operations and lists the necessary administrative controls or programs established for the site. Chapter 14 provides the basis for the Technical Specifications.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-16 Safety Analysis Methodology 1.4.3.2 The storage of spent nuclear fuel at the WCS CISF is based on the use of cask systems that have been previously approved by the NRC. The associated systems storage FSARs and transportation SARs provide design basis information regarding radiological hazards for the individual systems to be used at the WCS CISF. The FSARs/SARs identify design basis events that are classified as either normal, off-normal or accidents for each approved system. Normal events include such operations as transportation package receipt, inspection, transfer of the canisters to the storage overpack and storage at the WCS CISF until ready to be transported off-site. Off-normal events are those events which are expected to occur with moderate frequency during transfer and storage operations. In general, the consequences of these events have no radiological safety implications and do not have a significant impact on ITS design functions. Accident conditions are those events that occur infrequently and could reasonably be expected to occur during the lifetime of the WCS CISF. These events include low probability design basis accidents which establish a conservative design basis for ITS SSCs. These events include natural phenomena such as earthquakes and tornados, and man-made events such as cask drop.

Results 1.4.3.3 For most of the accidents analyzed, there are no radiological consequences produced as a direct result of the event, and there are no impacts on ITS design functions. These negligible consequences are attributed primarily to the use of NRC approved storage systems and the implementation of operating controls and limits. However, recovery operations may involve some occupational exposure to personnel. The analyses results indicate that there are no credible accident scenarios for the WCS CISF which would result in a loss of confinement accident or a radiological release in excess of the radiological dose criterion of 10 CFR 72.106.

Technical Specifications 1.4.3.4 The WCS CISF Technical Specifications [1-4] define the operating controls and limits and the administrative controls. The Technical Specifications, including the relevant portions of the individual storage system Technical Specifications, provide defined operating limits and controls for each system for storage at the WCS CISF.

The administrative controls presented in this SAR include the organization and management structure, response plans, procedures, programs, controls, record keeping requirements, review and audit procedures, and reporting necessary to assure that the operations involved in the storage of canisterized spent nuclear fuel and GTCC waste at the WCS CISF are performed in a safe manner.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-17 1.4.4 Safety Management The ISP management policy and highest priority is to ensure that all operations are conducted safely. Implementation of this policy is made through a consolidated safety management program. This program entails radiation protection, conduct of operations, and quality assurance.

Radiation Protection Program 1.4.4.1 The radiation protection program ensures that all operations are performed in a manner that ensures occupational exposures are maintained within prescribed regulatory limits and are ALARA. ALARA considerations have been integrated into the design of the WCS CISF and incorporated into all operating procedures.

Conduct of Operations Program 1.4.4.2 The conduct of operations program ensures that the WCS CISF is operated in a professional and safe manner. Highlights of this program include the following:

The ISP organization provides clear lines of responsibilities and ensures independence of organizations. This ensures ISP has an effective organization with appropriate oversight.

ISP performs an extensive test program, including an operational readiness review, prior to beginning normal operations. The test program ensures that the WCS CISF structures, systems, and components are operated in a dependable manner so as to perform their intended function.

ISP maintains a systematic training program to ensure proficiency of all facility personnel.

ISP maintains a formal procedure management program that ensures all ITS operations are performed using detailed written, approved, and controlled procedures.

ISP joint venture member Waste Control Specialists has a detailed emergency preparedness program and conducts periodic drills and training. This ensures that site personnel are prepared to respond to emergencies as they arise.

Quality Assurance Program 1.4.4.3 Interim Storage Partners has adopted the TN Americas Quality Assurance Program for its use. The TN Americas Quality Assurance Program Description Manual (QAPDM) is docketed under 71-0250. The activities associated with the WCS CISF are governed by the applicable portions of the TN Americas QA program as described in TN Americas LLC Quality Assurance Program Description Manual for 10 CFR Part 71, Subpart H and 10 CFR Part 72, Subpart G, [1-2]. The QA program meets the requirements of 10 CFR 72, Subpart G.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-18 Identification of Agents and Contractors 1.5 ISP has overall responsibility for the engineering, design, licensing, and construction of the WCS CISF.

TN Americas and Waste Control Specialists are the contractors for the design and operation of the WCS CISF. TN Americas is also the contractor for the design and fabrication of the HSMs, and associated auxiliary systems for the NUHOMS systems. TN Americas is also the contractor for the NUHOMS cask systems and is responsible for cask transportation licensing, fabrication, testing, and delineation of any cask specific requirements.

NAC International is the contractor for the design and fabrication of the NAC storage overpacks and ITS storage pads on which the NAC storage overpacks will be stored.

NAC International is also the contractor for the NAC cask systems and is responsible for cask transportation licensing, fabrication, testing, and delineation of any cask specific requirements.

ISP will also use various contractors for site preparation and construction, as necessary.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-19 Material Incorporated by Reference 1.6 This section provides a list of the safety analysis reports incorporated by reference as part of the SAR. The list of the SAR sections that reference one or more of the below documents is provided in Table 1-4.

1.6.1 NUHOMS Systems Transportation SARs 1.6.1.1 TN Americas, NUHOMS-MP197 Transport Packaging Safety Analysis Report, Revision 17, USNRC Docket Number 71-9302.

TN Americas, Safety Analysis Report for the NUHOMS-MP187 Multi-purpose Cask, Revision 17, USNRC Docket Number 71-9255.

Storage SARs 1.6.1.2 Rancho Seco Independent Spent Fuel Storage Installation Safety Analysis Report, NRC Docket No. 72-11, Revision 4.

TN Americas, Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, NRC Docket No. 72-1004, TN Americas Document No. NUH-003, Revision 14.

TN Americas, Updated Final Safety Analysis Report for the Standardized Advanced NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, NRC Docket No. 72-1029, TN Americas Document No. ANUH-01.0150, Revision 6.

1.6.2 NAC International Systems Transportation SARs 1.6.2.1 NAC International, NAC-STC, NAC Storage Transport Cask Safety Analysis Report, Revision 17, USNRC Docket Number 71-9235.

NAC International, Safety Analysis Report for the UMS Universal Transport Cask, Revision 2, USNRC Docket Number 71-9270.

NAC International, Safety Analysis Report for the MAGNATRAN Transport Cask, Revisions 12A, 14A, and 15A, USNRC Docket Number 71-9356.

Storage SARs 1.6.2.2 NAC International, NAC Multipurpose Cask Final Safety Analysis Report, Revision 10, USNRC Docket Number 72-1025.

NAC International, Final Safety Analysis Report for the UMS Universal Storage System, Revision 10, USNRC Docket Number 72-1015.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-20 NAC International, MAGNASTOR Final Safety Analysis Report, Revision 7, USNRC Docket Number 72-1031.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-21 References 1.7 Title 10, Code of Federal Regulations, Part 72, Licensing Requirements for the 1-1 Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste.

TN Americas LLC Quality Assurance Program Description Manual for 10 CFR Part 1-2 71, Subpart H and 10 CFR Part 72, Subpart G, current revision.

NUREG-1567, Standard Review Plan for Spent Fuel Dry Storage Facilities, 1-3 Revision 0, U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, March 2000.

Proposed SNM-1050, WCS Consolidated Interim Storage Facility Technical 1-4 Specifications, Amendment 0.

Reg Guide 1.76, Design-Basis Tornado and Tornado Missiles For Nuclear Power 1-5 Plants, Revision 1, March 2007.

NUREG-0800, Standard Review Plan, Section 3.3.1 Wind Loading, 3.3.2 Tornado 1-6 Loads and Section 3.5.1.4 Missiles Generated by Tornado and Extreme Winds, Rev 3, March 2007.

NUREG-0800, Standard Review Plan, Section 3.5.1.4 Missiles Generated by Natural 1-7 Phenomena, Revision 2, July 1981.

WCS document Environmental Report for the Consolidated Interim Storage Facility, 1-8 Docket No. 72-1050, Revision 1.

Reg Guide 1.60. Design Response Spectra for Seismic Design of Nuclear Power 1-9 Plants, Revision 2, July 2014.

AECOM Site Specific Seismic Hazzard Evaluation and Development of Seismic 1-10 Design Ground Motions, Study Number WCS-12-05-100-001, Revision 0.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-22 Table 1-1 Storage Systems at the WCS CISF Cask System NRC Docket No.

Canister Overpack NUHOMS MP187 Cask System 71-9255 72-11 (SNM-2510)

FO-DSC HSM (Model 80)

FC-DSC FF-DSC GTCC Canister Advanced Standardized NUHOMS System 71-9255 72-1029 NUHOMS 24PT1 AHSM Standardized NUHOMS System 71-9302 72-1004 NUHOMS 61BT HSM Model 102 NUHOMS 61BTH Type 1 NAC-MPC 71-9235 72-1025 Yankee Class VCC Connecticut Yankee LACBWR GTCC-Canister-CY GTCC-Canister-YR NAC-UMS 71-9270 72-1015 Classes 1 through 5 VCC GTCC-Canister-MY MAGNASTOR 71-9356 72-1031 TSC1 through TSC4 CC1 through CC4 GTCC-Canister-ZN

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-23 Table 1-2 Summary of WCS CISF Principal Design Criteria (3 pages)

Design Parameter Design Criteria Condition Applicable Codes, Standards and Basis Type of fuel Commercial, light water reactor spent fuel Normal N/A Storage Systems Transportable canisters and storage overpacks docketed by the NRC Normal See Table 1-1 Fuel Characteristics Criteria as specified in previously approved CoCs and licenses for included systems Normal See Table 1-1 Tornado (Wind Load)

Max translational speed:

40 mph Max rotational speed:

160 mph Max tornado wind speed:

200 mph Radius of max rotational speed:

150 ft Tornado pressure drop:

0.9 psi Rate of pressure drop:

0.4 psi/sec Accident Reg Guide 1.76

[1-5]

NUREG-800[1-6]

Tornado (Missile)

Automobile 4000 lb, 112 ft/s Schedule 40 Pipe 287 lb, 112 ft/s Solid Steel Sphere 0.147 lb, 23 ft/s Accident NUREG-800[1-7]

Floods The WCS CISF is not in a floodplain and is above the Probable Maximum Flood elevation, and will remain dry in the event of a flood.

Accident Section 2.4.2.2 Seismic (Ground Motion)

Site-specific ground-surface uniform hazard response spectra (UHRS) with 1E-4 annual frequency of exceedance (AFE) having peak ground acceleration (PGA) of 0.250 g horizontal and 0.175 g vertical. (Table 1-5 and Figure 1-5)

Accident AECOM Study Number WCS 05-100-001[1-10]

Vent Blockage For NUHOMS Systems:

Inlet and outlet vents blocked 40 hrs For MPC and UMS Systems:

Inlet and outlet vents blocked 24 hrs For MAGNASTOR Systems:

Inlet vents blocked 58 hrs Accident N/A Fire/Explosion For NUHOMS Systems:

Equivalent fire 300 gallons of diesel fuel For Vertical Systems:

Equivalent fire 50 gallons of fuel Accident N/A

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-24 Table 1-2 Summary of WCS CISF Principal Design Criteria (3 pages)

Design Parameter Design Criteria Condition Applicable Codes, Standards and Basis Cask Drop For NUHOMS Systems:

Transfer Cask Horizontal side drop or slap down 80 inches VCCs for MPC Systems:

Drop height 6 inches VCCs for UMS and MAGNASTOR Systems:

Drop height 24 inches Accident N/A Transfer Load For NUHOMS Systems only:

Normal insertion load 60 kips Normal extraction load 60 kips Normal NA Transfer Load For NUHOMS Systems only:

Maximum insertion load 80 kips Maximum extraction load 80 kips Off-Normal/

Accident N/A Ambient Temperatures (NUHOMS Systems)

Normal temperature 44.1 - 81.5°F Normal Section 2.3.3.1 Off-Normal Temperature (NUHOMS Systems)

Maximum temperature 113°F Off-Normal Section 2.3.3.1 Extreme Temperature (NUHOMS Systems)

Maximum temperature 113°F Accident Section 2.3.3.1 Solar Load (Insolation)

Horizontal flat surface insolation 2949.4 BTU/day-ft2 Curved surface solar insolation 1474.7 BTU/day-ft2 Normal 10 CFR Part 71 Ambient Temperatures (NAC Systems)

Yearly Average Temperature 67.1°F Normal Section 2.3.3.1 Off-Normal Temperature (NAC Systems)

Minimum 3 Day Average temperature 27.9°F Maximum 3 Day Average temperature 89.4°F Off-Normal Section 2.3.3.1

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-25 Table 1-2 Summary of WCS CISF Principal Design Criteria (3 pages)

Design Parameter Design Criteria Condition Applicable Codes, Standards and Basis Extreme Temperature (NAC Systems)

Maximum Temperature 113°F Minimum Temperature

-1°F Accident Section 2.3.3.1 Snow and Ice Snow Load 10 psf Normal Section 2.3.2.4 Dead Weight Per design basis for systems listed in Table 1-1 Normal N/A Internal and External Pressure Loads Per design basis for systems listed in Table 1-1 Normal N/A Design Basis Thermal Loads Per design basis for systems listed in Table 1-1 Normal N/A Operating Loads Per design basis for systems listed in Table 1-1 Normal N/A Live Loads Per design basis for systems listed in Table 1-1 Normal N/A Radiological Protection Public wholebody 5 Rem Public deep dose plus individual organ or tissue 50 Rem Public shallow dose to skin or extremities 50 Rem Public lens of eye 15 Rem Accident 10 CFR 72.106 Radiological Protection Public wholebody 25 mrem/yr (1)

Public thyroid 75 mrem/yr(1)

Public critical organ 25 mrem/yr(1)

Normal 10 CFR 72.104 Confinement Per design basis for systems listed in Table 1-1 N/A N/A Nuclear Criticality Per design basis for systems listed in Table 1-1 N/A N/A Decommissioning Minimize potential contamination Normal 10 CFR 72.130 Materials Handling and Retrieval Capability Cask/canister handling system prevent breach of confinement boundary under all conditions Storage system allows ready retrieval of canister for shipment off-site Normal 10 CFR 72.122(1)

Cask Handling Building Prevent building collapse in accordance with 2006 International Building Code Accident 10 CFR 72.122(b)(2)(ii)

Note:

1. In accordance with 10 CFR 72.104 (a)(3) limits include any other radiation from uranium fuel cycle operations within the region.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-26 Table 1-3 WCS CISF Facilities and Functions Facility Function Cask Handling Building Receive, inspect and prepare for storage, shipments of canisterized spent nuclear fuel and GTCC waste.

Prepare canisterized spent nuclear fuel and GTCC waste stored at the site for off-site transport.

Provide for transportation cask light maintenance.

Storage Area Provide location for safe storage of canisterized spent nuclear fuel and GTCC waste.

Security and Administration Building Provide main operation center and armory for site security and emergency equipment; control personnel, rail and vehicle access to the WCS CISF facilities; and provide administrative functions related to transport, communication and tracking center/facility, training and visitor center.

Receiving Area Location to perform DOT/NRC required inspections of arriving railcars.

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-27 Table 1-4 Table of Topical Reports (SARs) Incorporated by Reference (3 pages)

Chapter Description Applicable SARs (Docket Number) 01 INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION Section 1.6 (1.6 Material Incorporated by Reference)

A.3 Appendix A.3 - Design Criteria for NUHOMS MP187 System 72-11 71-9255 B.3 Appendix B.3 - Design Criteria for Advanced Standardized NUHOMS System 72-1029 72-11 71-9255 C.3 Appendix C.3 - Design Criteria for Standardized NUHOMS System 61BT 72-1004 71-9302 D.3 Appendix D.3 - Design Criteria for Standardized NUHOMS System 61BTH 72-1004 71-9302 E.3 Appendix E.3 - Design Criteria for NAC-MPC 72-1025 F.3 Appendix F.3 - Design Criteria for NAC-UMS 72-1015 G.3 Appendix G.3 - Design Criteria for NAC-MAGNASTOR 72-1031 A.4 Appendix A.4 - Operating Systems for NUHOMS MP187 System 72-11 B.4 Appendix B.4 - Operating Systems for Advanced Standardized NUHOMS System 72-1029 C.4 Appendix C.4 - Operating Systems for Standardized NUHOMS System 61BT 72-1004 D.4 Appendix D.4 - Operating Systems for Standardized NUHOMS System 61BTH 72-1004 E.4 Appendix E.4 - Operating Systems for NAC-MPC 72-1025 F.4 Appendix F.4 - Operating Systems for NAC-UMS 72-1015 G.4 Appendix G.4 - Operating Systems for NAC-MAGNASTOR 72-1031 A.7 Appendix A.7 - Structural Evaluation for NUHOMS MP187 System 72-11 71-9255 B.7 Appendix B.7 - Structural Evaluation for Advanced Standardized NUHOMS System 72-1029 72-11 71-9255 C.7 Appendix C.7 - Structural Evaluation for Standardized NUHOMS System 61BT 72-1004 71-9302 D.7 Appendix D.7 - Structural Evaluation for Standardized NUHOMS System 61BTH 72-1004 71-9302 E.7 Appendix E.7 - Structural Evaluation for NAC-MPC 72-1025

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-28 Table 1-4 Table of Topical Reports (SARs) Incorporated by Reference (3 pages)

Chapter Description Applicable SARs (Docket Number)

F.7 Appendix F.7 - Structural Evaluation for NAC-UMS 72-1015 G.7 Appendix G.7 - Structural Evaluation for NAC-MAGNASTOR 72-1031 A.8 Appendix A.8 - Thermal Evaluation for NUHOMS MP187 System 72-11 71-9255 B.8 Appendix B.8 - Thermal Evaluation for Advanced Standardized NUHOMS System 72-1029 72-11 71-9255 C.8 Appendix C.8 - Thermal Evaluation for Standardized NUHOMS System 61BT 72-1004 71-9302 D.8 Appendix D.8 - Thermal Evaluation for Standardized NUHOMS System 61BTH 72-1004 71-9302 E.8 Appendix E.8 - Thermal Evaluation for NAC-MPC 72-1025 F.8 Appendix F.8 - Thermal Evaluation for NAC-UMS 72-1015 G.8 Appendix G.8 - Thermal Evaluation for NAC-MAGNASTOR 72-1031 A.9 Appendix A.9 - Radiation Protection for NUHOMS MP187 System 72-11 71-9255 B.9 Appendix B.9 - Radiation Protection for Advanced Standardized NUHOMS System 72-1029 71-9255 C.9 Appendix C.9 - Radiation Protection for Standardized NUHOMS System 61BT 72-1004 71-9302 D.9 Appendix D.9 - Radiation Protection for Standardized NUHOMS System 61BTH 72-1004 71-9302 E.9 Appendix E.9 - Radiation Protection for NAC-MPC 72-1025 F.9 Appendix F.9 - Radiation Protection for NAC-UMS 72-1015 G.9 Appendix G.9 - Radiation Protection for NAC-MAGNASTOR 72-1031 A.10 Appendix A.10 - Criticality Evaluation for NUHOMS MP187 System 72-11 B.10 Appendix B.10 - Criticality Evaluation for Advanced Standardized NUHOMS System 72-1029 C.10 Appendix C.10 - Criticality Evaluation for Standardized NUHOMS System 61BT 72-1004 D.10 Appendix D.10 - Criticality Evaluation for Standardized NUHOMS System 61BTH 72-1004 E.10 Appendix E.10 - Criticality Evaluation for NAC-MPC 72-1025

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-29 Table 1-4 Table of Topical Reports (SARs) Incorporated by Reference (3 pages)

Chapter Description Applicable SARs (Docket Number)

F.10 Appendix F.10 - Criticality Evaluation for NAC-UMS 72-1015 G.10 Appendix G.10 - Criticality Evaluation for NAC-MAGNASTOR 72-1031 A.11 Appendix A.11 - Confinement Evaluation for NUHOMS MP187 System 72-11 B.11 Appendix B.11 - Confinement Evaluation for Advanced Standardized NUHOMS System 72-1029 C.11 Appendix C.11 - Confinement Evaluation for Standardized NUHOMS System 61BT 72-1004 D.11 Appendix D.11 - Confinement Evaluation for Standardized NUHOMS System 61BTH 72-1004 E.11 Appendix E.11 - Confinement Evaluation for NAC-MPC 72-1025 F.11 Appendix F.11 - Confinement Evaluation for NAC-UMS 72-1015 G.11 Appendix G.11 - Confinement Evaluation for NAC-MAGNASTOR 72-1031 A.12 Appendix A.12 - Accident Analyses for NUHOMS MP187 System 72-11 71-9255 B.12 Appendix B.12 - Accident Analyses for Advanced Standardized NUHOMS System 72-1029 72-11 71-9255 C.12 Appendix C.12 - Accident Analyses for Standardized NUHOMS System 61BT 72-1004 71-9302 D.12 Appendix D.12 - Accident Analyses for Standardized NUHOMS System 61BTH 72-1004 71-9302 E.12 Appendix E.12 - Accident Analyses for NAC-MPC 72-1025 F.12 Appendix F.12 - Accident Analyses for NAC-UMS 72-1015 G.12 Appendix G.12 - Accident Analyses for NAC-MAGNASTOR 72-1031

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-30 Table 1-5 Ground Surface DRS Period (sec)

Horizontal (g)

Vertical (g) 0.01 0.250 0.175 0.03 0.347 0.287 0.04 0.406 0.377 0.05 0.473 0.471 0.08 0.586 0.539 0.10 0.610 0.466 0.15 0.504 0.310 0.20 0.399 0.216 0.25 0.314 0.157 0.30 0.262 0.126 0.40 0.198 0.094 0.50 0.154 0.076 0.60 0.124 0.063 0.75 0.096 0.051 1.00 0.067 0.038 1.50 0.039 0.024 2.00 0.025 0.016 3.00 0.014 0.0088 4.00 0.0094 0.0063 5.00 0.0068 0.0047 7.52 0.0029 0.0020 10.00 0.0016 0.0011

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-31 Figure 1-1 WCS CISF Location

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-32 Figure 1-2 WCS CISF Site Boundary Layout

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-33 Figure 1-3 WCS CISF Site Overview

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-34 Figure 1-4 Site Location Map

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-35 Figure 1-5 10,000-Year Return Period Response Spectra (5% Damped)

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-36 Figure 1-6 WCS CISF Storage Pad Layout

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-37 Figure 1-7 Cask Handling Building Plan

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-38 Figure 1-8 Cask Handling Building Section View

WCS Consolidated Interim Storage Facility Safety Analysis Report Revision 2 Page 1-39 Figure 1-9 Security Administration Building Plan