Yucca Mountain Repository License Application: Safety Analysis Report

Cover page through Figure 1.1-9 in Section 1, "Site Description as It Pertains to Preclosure Safety Analysis"

Section 1.1, Figures 1.1-10 through 1.1-73

Section 1.1, Figures 1.1-74 through 1.1-155

Section 1.2, "Surface Facility Structures, Systems, and Components and Operational Process Activities"
Section 1.2.1, "Surface Operations Overview"
Section 1.2.2, "Surface Facilities Structural, Mechanical Handling Equipment, and Heating, Ventilation, and Air-Conditioning System Design"
Section 1.2.3, "Initial Handling Facility"

Section 1.2.4, "Canister Receipt and Closure Facility"

Section 1.2.5, "Wet Handling Facility"

Section 1.2.6, "Receipt Facility"
Section 1.2.7, "Aging Facility"
Section 1.2.8, "Balance of Plant Facilities"

Section 1.3, "Subsurface Structures, Systems, and Components and Operational Process Activities"
Section 1.3.1, "Subsurface Operations Overview"
Section 1.3.2, "General Subsurface Design Considerations"
Section 1.3.3, "Nonemplacement Areas of the Subsurface Facility"

Section 1.3.4, "Emplacement Areas of the Subsurface Facility"
Section 1.3.5, "Subsurface Facility Ventilation"
Section 1.3.6, "Subsurface Facility Closure"

Section 1.4, "Infrastructure Structures, Systems, Components, Equipment, and Operational Process Activities"

Section 1.5, "Waste Form and Waste Package"

Section 1.6, "Identification of Hazards and Initiating Events"
Section 1.7, "Event Sequence Analysis"
Section 1.8, "Consequence Analysis"

Section 1.9, "Structures, Systems, and Components Important to Safety; Natural and Engineered Barriers Important to Waste Isolation; Safety Controls; and Measures to Ensure Availability of the Safety Systems"
Section 1.10, "Meeting the As Low As Is Reasonably Achievable Requirements for Normal Operations and Category 1 Event Sequences"
Section 1.11, "Plans for Retrieval and Alternate Storage of Radioactive Wastes"
Section 1.12, "Plans for Permanent Closure, Decontamination, and Dismantlement of Surface Facilities"
Section 1.13, "Equipment Qualification Program"
Section 1.14, "Nuclear Criticality Safety"

Section 2.1, Figures 2.1-10 through 2.1-43

Section 2.2, "Scenario Analysis and Event Probability"

Section 2.3, "Model Abstraction,"
Introduction through Figure 2.3.1-26 in
Section 2.3.1, "Climate and Infiltration"

Section 2.3.1, Figures 2.3.1-27 through 2.3.1-55

Section 2.3.2, "Unsaturated Zone Flow,"
through Figure 2.3.2-8

Section 2.3.2, Figures 2.3.2-9 through 2.3.2-52

Section 2.3.3, "Water Seeping into Drifts,"
through Figure 2.3.3-29

Section 2.3.3, Figures 2.3.3-30 through 2.3.3-52

Section 2.3.4, Figures 2.3.4-10 through 2.3.4-53

Section 2.3.4, Figures 2.3.4-54 through 2.3.4-98

Section 2.3.5, "In-Drift Physical and Chemical Environment"

Section 2.3.6, "Waste Package and Drip Shield Corrosion"

Section 2.3.7, "Waste Form Degradation and Mobilization and Engineered Barrier System Flow and Transport"

Section 2.3.8, "Radionuclide Transport in Unsaturated Zone"

Section 2.3.9, "Saturated Zone Flow and Transport,"
through Figure 2.3.9-22

Section 2.3.9, Figures 2.3.9-23 through 2.3.9-48

Section 2.4, "Demonstration of Compliance with the Postclosure Public Health and Environmental Standards," through Figure 2.4-32

Section 2.4, Figures 2.4-33 through 2.4-114

Section 2.4, Figures 2.4-115 through 2.4-181