ML20007E326

GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Tier 2 - Table of Contents

ML20007E326
Person / Time
Site:	05200001, 05200045
Issue date:	12/20/2019
From:	Michelle Catts GE-Hitachi Nuclear Energy Americas
To:	Office of Nuclear Reactor Regulation
Shea J
References
GEHITACHIABWR, GEHITACHIABWR.SUBMISSION.8, 25A5675.P, 25A5675.P.7
Download: ML20007E326 (184)

Text

25A5675AB Revision 7 October 2019 ABWR Design Control Document Tier 2 Table of Contents Copyright 1994, 2010, 2016, 2019 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 LEGAL NOTICE The design, engineering, and other information contained in this document is furnished by GE-Hitachi Nuclear Energy Americas LLC (GEH) for the purpose of supporting the GEH Certification Renewal Application to the United States Nuclear Regulatory Commission (NRC) for renewal of the certification of the ABWR nuclear plant design pursuant to Title 10 Code of Federal Regulations (10 CFR) Part 52.

No use of or right to copy any of the information contained in this document, other than by the NRC and its contractors in support of GEHs application, is authorized except by contract with GEH. The information provided in this document is part of and dependent upon a larger set of knowledge, technology, and intellectual property rights pertaining to standardized, nuclear powered, electric generating facilities that utilize the design certification, as designed and certified to U.S. Codes, Standards, and Regulations by GEH, and referred to as the ABWR nuclear power plant design. Without access and a GEH grant of rights to that larger set of knowledge, technology, and intellectual property rights, this document is not practically or rightfully usable by others, except by the NRC or through contractual agreements with Combined License Applicants and Licensees or customers and participating utilities.

Table of Contents 1

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 Table of Contents 1.0 Introduction and General Description of Plant ..............................................................................1.1-1 1.1 Introduction....................................................................................................................................1.1-1 1.1.1 Format and Content .......................................................................................................1.1-1 1.1.2 ABWR Standard Plant Scope........................................................................................1.1-1 1.1.3 Engineering Documentation..........................................................................................1.1-3 1.1.4 Design Process...............................................................................................................1.1-3 1.1.5 Type of License Required .............................................................................................1.1-3 1.1.6 Number of Plant Units...................................................................................................1.1-3 1.1.7 Description of Location.................................................................................................1.1-3 1.1.8 Type of Nuclear Steam Supply......................................................................................1.1-3 1.1.9 Type of Containment.....................................................................................................1.1-3 1.1.10 Core Thermal Power Levels..........................................................................................1.1-4 1.1.11 COL License Information..............................................................................................1.1-4 1.2 General Plant Description ..............................................................................................................1.2-1 1.2.1 Principal Design Criteria ...............................................................................................1.2-1 1.2.2 Plant Description ...........................................................................................................1.2-7 1.2.3 COL License Information............................................................................................1.2-38 1.3 Comparison Tables ........................................................................................................................1.3-1 1.3.1 Nuclear Steam Supply System Design Characteristics .................................................1.3-1 1.3.2 Engineered Safety Features Design Characteristics ......................................................1.3-1 1.3.3 Containment Design Characteristics .............................................................................1.3-1 1.3.4 Structural Design Characteristics ..................................................................................1.3-1 1.3.5 Instrumentation and Electrical Systems Design Characteristics ...................................1.3-1 1.4 Identification of Agents and Contractors.......................................................................................1.4-1 1.4.1 Technical Qualifications of Applicant...........................................................................1.4-1 1.4.2 Use of Contractors.........................................................................................................1.4-2 1.5 Requirements for Further Technical Information ..........................................................................1.5-1 1.6 GEH Topical Reports and Other Documents ................................................................................1.6-1 1.7 Drawings........................................................................................................................................1.7-1 1.7.1 Piping and Instrumentation and Process Flow Drawings..............................................1.7-1 1.7.2 Instrument, Control and Electrical Drawings................................................................1.7-1 1.7.3 ASME Standard Units to Preferred Metric Conversion Factors ...................................1.7-1 1.7.4 Preferred Metric Conversion to ASME Standard Units ................................................1.7-1 1.7.5 Drawing Standards ........................................................................................................1.7-1 1.7.6 COL License Information..............................................................................................1.7-1 1.8 Conformance with Standard Review Plan and Applicability of Codes and Standards .................1.8-1 1.8.1 Conformance with Standard Review Plan.....................................................................1.8-1 1.8.2 Applicability of Codes and Standards ...........................................................................1.8-1 1.8.3 Applicability of Experience Information.......................................................................1.8-1 1.8.4 COL License Information..............................................................................................1.8-2 2 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 Table of Contents (Continued) 1.9 COL License Information ..............................................................................................................1.9-1 1A Response to TMI Related Matters .................................................................................................1A-1 1A.1 Introduction ...................................................................................................................1A-1 1A.2 NRC Positions/Responses .............................................................................................1A-1 1A.3 COL License Information............................................................................................1A-33 1A.4 References ...................................................................................................................1A-34 1AA Plant Shielding to Provide Access to Vital Areas and Protective Safety Equipment for Post-Accident Operation [II.B.2] .................................... 1AA-1 1AA.1 Introduction ................................................................................................................ 1AA-1 1AA.2 Summary of Shielding Design Review ...................................................................... 1AA-1 1AA.3 Containment Description and Post Accident Operations ........................................... 1AA-3 1AA.4 Design Review Bases ................................................................................................. 1AA-4 1AA.5 Results of the Review................................................................................................. 1AA-6 1B Not Used ........................................................................................................................................ 1B-1 1C ABWR Station Blackout Considerations....................................................................................... 1C-1 1C.1 Introduction ................................................................................................................... 1C-1 1C.2 Discussion...................................................................................................................... 1C-1 1C.3 Conclusions ................................................................................................................... 1C-8 1C.4 COL License Information.............................................................................................. 1C-8 1C.5 References ..................................................................................................................... 1C-8 Table of Contents 3

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 List of Tables Table 1.3-1 Comparison of Nuclear Steam Supply System Design Characteristics ........................1.3-2 Table 1.3-2 Comparison of Engineered Safety Features Design Characteristics .............................1.3-7 Table 1.3-3 Comparison of Containment Design Characteristics ....................................................1.3-9 Table 1.3-4 Comparison of Structural Design Characteristics .......................................................1.3-11 Table 1.4-1 Commercial Nuclear Reactors Completed, Under Construction, by GE/GEH.............1.4-3 Table 1.6-1 Referenced Reports .......................................................................................................1.6-2 Table 1.6-2 Reports Incorporated by Reference ...............................................................................1.6-7 Table 1.7-1 Piping and Instrumentation and Process Flow Diagrams..............................................1.7-2 Table 1.7-2 Instrument Engineering, Interlock Block and Single-Line Diagrams ...........................1.7-4 Table 1.7-3 Conversion to ASME Standard Units............................................................................1.7-6 Table 1.7-4 Conversion TablesMetric to ASME Standard Units .................................................1.7-9 Table 1.7-5 Drawing Standards ......................................................................................................1.7-11 Table 1.8-1 Summary of Differences from SRP Section 1...............................................................1.8-3 Table 1.8-2 Summary of Differences from SRP Section 2...............................................................1.8-3 Table 1.8-3 Summary of Differences from SRP Section 3...............................................................1.8-3 Table 1.8-4 Summary of Differences from SRP Section 4...............................................................1.8-4 Table 1.8-5 Summary of Differences from SRP Section 5...............................................................1.8-4 Table 1.8-6 Summary of Differences from SRP Section 6...............................................................1.8-5 Table 1.8-7 Summary of Differences from SRP Section 7...............................................................1.8-5 Table 1.8-8 Summary of Differences from SRP Section 8...............................................................1.8-6 Table 1.8-9 Summary of Differences from SRP Section 9...............................................................1.8-6 Table 1.8-10 Summary of Differences from SRP Section 10.............................................................1.8-7 Table 1.8-11 Summary of Differences from SRP Section 11.............................................................1.8-7 Table 1.8-12 Summary of Differences from SRP Section 12.............................................................1.8-7 Table 1.8-13 Summary of Differences from SRP Section 13.............................................................1.8-7 Table 1.8-14 Summary of Differences from SRP Section 14.............................................................1.8-7 4 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 List of Tables (Continued)

Table 1.8-15 Summary of Differences from SRP Section 15.............................................................1.8-7 Table 1.8-16 Summary of Differences from SRP Section 16.............................................................1.8-9 Table 1.8-17 Summary of Differences from SRP Section 17.............................................................1.8-9 Table 1.8-18 Summary of Differences from SRP Section 18.............................................................1.8-9 Table 1.8-19 Standard Review Plans and Branch Technical Positions Applicable to ABWR.........1.8-10 Table 1.8-20 NRC Regulatory Guides Applicable to ABWR ..........................................................1.8-25 Table 1.8-21 Industrial Codes and Standards Applicable to ABWR................................................1.8-36 Table 1.8-22 Experience Information Applicable to ABWR ...........................................................1.8-49 Table 1.9-1 Summary of ABWR Standard Plant COL License Information ...................................1.9-2 Table 1A-1 Responses to Questions Posed by Mr. C. Michelson [II.K.3(46)] ..............................1A-36 Table 1AA-1 Radiation Source Comparison.................................................................................. 1AA-10 Table 1AA-2 Post-Accident Emergency Core Cooling Systems and Auxiliaries.......................... 1AA-11 Table 1AA-3 Post-Accident Combustible Gas Control Systems and Auxiliaries.......................... 1AA-13 Table 1AA-4 Post-Accident Fission Product Removal and Control Systems and Auxiliaries.......................................................................................................... 1AA-14 Table 1AA-5 Post-Accident Instrumentation and Controls, Power and Habitability Systems and Auxiliaries.......................................................................................................... 1AA-15 Table 1C-1 ABWR Design Compliance with 10CFR50.63 Regulations......................................... 1C-9 Table 1C-2 ABWR Design Compliance with Regulatory Guide 1.155......................................... 1C-13 Table 1C-3 ABWR Design Compliance with NUMARC 87-00 Guidelines ................................. 1C-29 Table of Contents 5

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 List of Figures Figure 1.1-1 ABWR Standard Plant Nomenclature........................................................................1.1-5 Figure 1.1-2 Heat Balance at Rated Power .....................................................................................1.1-6 Figure 1.2-1 Site Plan ...................................................................................................................1.2-39 Figure 1.2-2 Reactor Building, Arrangement Elevation, Section A-A.........................................1.2-40 Figure 1.2-2a Reactor Building, Arrangement Elevation, Section B-B .........................................1.2-40 Figure 1.2-3 Upper Drywell, Arrangement Elevation, Section A-A ............................................1.2-40 Figure 1.2-3a Upper Drywell, Arrangement Elevation, Section B-B.............................................1.2-40 Figure 1.2-3b Lower Drywell, Arrangement Elevation, Section A-A............................................1.2-40 Figure 1.2-3c Wetwell, Arrangement Elevation, Sections A-A & B-B .........................................1.2-40 Figure 1.2-4 Reactor Building, Arrangement Plan at Elevation -8200 mm .................................1.2-40 Figure 1.2-5 Reactor Building, Arrangement Plan at Elevation -1700 mm .................................1.2-40 Figure 1.2-6 Reactor Building, Arrangement Plan at Elevation 4800/8500 mm..........................1.2-40 Figure 1.2-7 Not Used...................................................................................................................1.2-40 Figure 1.2-8 Reactor Building, Arrangement Plan at Elevation 12300 mm.................................1.2-40 Figure 1.2-9 Reactor Building, Arrangement Plan at Elevation 18100 mm.................................1.2-40 Figure 1.2-10 Reactor Building, Arrangement Plan at Elevation 23500 mm.................................1.2-40 Figure 1.2-11 Reactor Building, Arrangement Plan at Elevation 27200 mm.................................1.2-40 Figure 1.2-12 Reactor Building, Arrangement Plan at Elevation 31700/38200 mm......................1.2-40 Figure 1.2-13a Drywell, Arrangement Plan at Elevation 12300 mm ...............................................1.2-40 Figure 1.2-13b Drywell, Arrangement Plan at Elevation 15600 mm ...............................................1.2-40 Figure 1.2-13c Drywell, Arrangement Plan at Elevation 18100 mm ...............................................1.2-40 Figure 1.2-13d Drywell Steel Structure at Elevation 18100 mm......................................................1.2-40 Figure 1.2-13e Lower Drywell, Arrangement Plan at Elevation -6600 to -1850 mm .....................1.2-40 Figure 1.2-13f Lower Drywell, Arrangement Plan at Elevation -1850 to 1750 mm .......................1.2-40 Figure 1.2-13g Lower Drywell, Arrangement Plan at Elevation 1750 to 4800 mm ........................1.2-40 Figure 1.2-13h Lower Drywell, Arrangement Plan at Elevation 4800 to 6700 mm ........................1.2-40 6 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 List of Figures (Continued)

Figure 1.2-13i Wetwell, Arrangement Plan at Elevation -8200 mm ...............................................1.2-40 Figure 1.2-13j Wetwell, Arrangement Plan at Elevation -1700 mm ...............................................1.2-40 Figure 1.2-13k Wetwell, Arrangement Plan at Elevation 4800 mm.................................................1.2-41 Figure 1.2-14 Control and Service Building, Arrangement Elevation, Section A-A .....................1.2-41 Figure 1.2-15 Control and Service Building, Arrangement Elevation, Section B-B......................1.2-41 Figure 1.2-16 Control Building, Arrangement Plan at Elevation -8200 mm .................................1.2-41 Figure 1.2-17 Control and Service Building, Arrangement Elevation -2150 mm .........................1.2-41 Figure 1.2-18 Control and Service Building, Arrangement Elevation 3500 mm ...........................1.2-41 Figure 1.2-19 Control and Service Building, Arrangement Elevation 7900 mm ...........................1.2-41 Figure 1.2-20 Control and Service Building, Arrangement Elevation 12300 mm .........................1.2-41 Figure 1.2-21 Control and Service Building, Arrangement Elevation 17150 mm .........................1.2-41 Figure 1.2-22 Control and Service Building, Arrangement Elevation 22200 mm .........................1.2-41 Figure 1.2-23a Radwaste Building at Elevation -1500 mm .............................................................1.2-41 Figure 1.2-23b Radwaste Building at Elevation 4800 mm...............................................................1.2-41 Figure 1.2-23c Radwaste Building at Elevation 12300 mm.............................................................1.2-41 Figure 1.2-23d Radwaste Building at Elevation 21000 mm.............................................................1.2-41 Figure 1.2-23e Radwaste Building, Section A-A .............................................................................1.2-41 Figure 1.2-23f Not Used...................................................................................................................1.2-41 Figure 1.2-23g Not Used...................................................................................................................1.2-41 Figure 1.2-24 Turbine Building, General Arrangement at Elevation 5300 mm .............................1.2-41 Figure 1.2-25 Turbine Building, General Arrangement at Elevation 12300 mm ...........................1.2-41 Figure 1.2-26 Turbine Building, General Arrangement at Elevation 20300 mm ...........................1.2-41 Figure 1.2-27 Turbine Building, General Arrangement at Elevation 30300 mm ...........................1.2-41 Figure 1.2-28 Turbine Building, General Arrangement, Longitudinal Section A-A......................1.2-41 Figure 1.2-29 Turbine Building, General Arrangement, Section B-B............................................1.2-41 Figure 1.2-30 Turbine Building, General Arrangement, Section C-C............................................1.2-41 Table of Contents 7

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 1 List of Figures (Continued)

Figure 1.2-31 Turbine Building, General Arrangement, Section D-D ...........................................1.2-41 Figure 1.7-1 Piping and Instrumentation Diagram Symbols (Sheets 1-2) ...................................1.7-21 Figure 1.7-2 Graphical Symbols for Use in IBDs.........................................................................1.7-22 Figure 1.7-3 Graphical Symbols for Use in Electrical SLDs (Sheets 1-4) ..................................1.7-30 8 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 2 Table of Contents 2.0 Site Characteristics ........................................................................................................................2.0-1 2.0.1 Summary........................................................................................................................2.0-1 2.0.2 References .....................................................................................................................2.0-1 2.1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant .....................2.1-1 2.2 Requirements for Determination of ABWR Site Acceptability ....................................................2.2-1 2.2.1 Design Basis Events ......................................................................................................2.2-1 2.2.2 Severe Accidents ...........................................................................................................2.2-1 2.3 COL License Information ..............................................................................................................2.3-1 2.3.1 Envelope of Standard Plant Design Parameters ............................................................2.3-1 2.3.2 Standard Review Plant Site Characteristics ..................................................................2.3-2 2.3.3 Severe Accident Consequence Computer Code Calculations .......................................2.3-7 2A Input to CRAC 2 Computer Code for Determination of ABWR Site Acceptability.....................2A-1 Table of Contents 9

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 2 List of Tables Table 2.0-1 Envelope of ABWR Standard Plant Site Design Parameters........................................2.0-2 Table 2.1-1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Design.................2.1-2 Table 2.2-1 Dose-Related Goals .......................................................................................................2.2-3 Table 2.2-2 CRAC 2 Data Input Listing...........................................................................................2.2-3 Table 2A-1 Spatial Subgroup (NUREG/CR-2326, pg 2-11) ...........................................................2A-1 Table 2A-2 Site Subgroup (NUREG/CR-2326, pg 2-13) ................................................................2A-1 Table 2A-3 Economic Subgroup (NUREG/CR-2326, pg 2-22) ......................................................2A-2 Table 2A-4 Population Subgroup (NUREG/CR-2326, pg 2-26) .....................................................2A-3 Table 2A-5 Topography Subgroup, (NUREG/CR-2326, pg 2-33)..................................................2A-3 Table 2A-6 Isotopic Subgroup (NUREG/CR-2326, pg 2-37) .........................................................2A-4 Table 2A-7 Leakage Subgroup (NUREG/CR-2326, pg 2-41).........................................................2A-5 Table 2A-8 Dispersion Subgroup (NUREG/CR-2326, pg 2-45) .....................................................2A-6 Table 2A-9 Evacuation Subgroup (NUREG/CR-2326, pg 2-47) ....................................................2A-6 Table 2A-10 Acute Subgroup (NUREG/CR-2326, pg 2-53).............................................................2A-6 Table 2A-11 Latent Subgroup (NUREG/CR-2326, pg 2-57) ............................................................2A-7 Table 2A-12 Chronic Subgroup (NUREG/CR-2326, pg 2-62) .........................................................2A-8 Table 2A-13 Scale Subgroup (NUREG/CR-2326, pg 2-72)............................................................2A-13 Table 2A-14 Results Subgroup (NUREG/CCR-2326, pg 2-72)......................................................2A-14 Table 2A-15 Individual Accident Event Groups Leakage Subgroup (NUREG/CR-2326, pg 2-41)......................................................................................2A-15 Table 2A-16 File 21 Dose Conversion File (NUREG/CR-2326, pg 4-3)........................................2A-16 10 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 Table of Contents 3.0 Design of Structures, Components, Equipment and Systems........................................................3.1-1 3.1 Conformance with NRC General Design Criteria .........................................................................3.1-1 3.1.1 Summary Description....................................................................................................3.1-1 3.1.2 Evaluation Against Criteria ...........................................................................................3.1-1 3.2 Classification of Structures, Components, and Systems................................................................3.2-1 3.2.1 Seismic Classification ...................................................................................................3.2-1 3.2.2 Quality Group Classifications .......................................................................................3.2-1 3.2.3 Safety Classifications ....................................................................................................3.2-2 3.2.4 Correlation of Safety Classes with Industry Codes.......................................................3.2-5 3.2.5 Non-Safety-Related Structures, Systems, and Components..........................................3.2-5 3.2.6 Quality Assurance .........................................................................................................3.2-8 3.3 Severe Wind and Extreme Wind (Tornado and Hurricane) Loadings...........................................3.3-1 3.3.1 Severe Wind Loads........................................................................................................3.3-1 3.3.2 Extreme Wind Loads (Hurricanes and Tornados).........................................................3.3-2 3.3.3 COL License Information..............................................................................................3.3-3 3.3.4 References .....................................................................................................................3.3-3 3.4 Water Level (Flood) Design ..........................................................................................................3.4-1 3.4.1 Flood Protection ............................................................................................................3.4-2 3.4.2 Analytical and Test Procedures ...................................................................................3.4-14 3.4.3 COL License Information............................................................................................3.4-14 3.4.4 References ...................................................................................................................3.4-15 3.5 Missile Protection ..........................................................................................................................3.5-1 3.5.1 Missile Selection and Description .................................................................................3.5-1 3.5.2 Structures, Systems, and Components to be Protected from Externally Generated Missiles ......................................................................................................3.5-11 3.5.3 Barrier Design Procedures...........................................................................................3.5-11 3.5.4 COL License Information............................................................................................3.5-12 3.5.5 References ...................................................................................................................3.5-13 3.6 Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping..............3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside of Containment ........3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping.........................................................................................3.6-9 3.6.3 Leak-Before-Break Evaluation Procedures.................................................................3.6-28 3.6.4 As-Built Inspection of High-Energy Pipe Break Mitigation Features ........................3.6-31 3.6.5 COL License Information............................................................................................3.6-31 3.6.6 References ...................................................................................................................3.6-32 3.7 Seismic Design ..............................................................................................................................3.7-1 3.7.1 Seismic Input .................................................................................................................3.7-2 3.7.2 Seismic System Analysis...............................................................................................3.7-5 3.7.3 Seismic Subsystem Analysis .......................................................................................3.7-19 3.7.4 Seismic Instrumentation ..............................................................................................3.7-42 3.7.5 COL License Information............................................................................................3.7-44 Table of Contents 11

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 Table of Contents (Continued) 3.7.6 References ...................................................................................................................3.7-45 3.8 Seismic Category I Structures........................................................................................................3.8-1 3.8.1 Concrete Containment ...................................................................................................3.8-1 3.8.2 Steel Components of the Reinforced Concrete Containment......................................3.8-17 3.8.3 Concrete and Steel Internal Structures of the Concrete Containment.........................3.8-23 3.8.4 Other Seismic Category I Structures ...........................................................................3.8-30 3.8.5 Foundations .................................................................................................................3.8-44 3.8.6 COL License Information............................................................................................3.8-47 3.9 Mechanical Systems and Components ..........................................................................................3.9-1 3.9.1 Special Topics for Mechanical Components.................................................................3.9-1 3.9.2 Dynamic Testing and Analysis......................................................................................3.9-6 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures .......................................................................................................3.9-26 3.9.4 Control Rod Drive (CRD) ...........................................................................................3.9-56 3.9.5 Reactor Pressure Vessel Internals ...............................................................................3.9-58 3.9.6 Testing of Pumps and Valves ......................................................................................3.9-69 3.9.7 COL License Information............................................................................................3.9-78 3.9.8 References ...................................................................................................................3.9-80 3.10 Seismic and Dynamic Qualification of Mechanical and Electrical Equipment...........................3.10-1 3.10.1 Seismic Qualification Criteria (Including Other Dynamic Loads)..............................3.10-1 3.10.2 Methods and Procedures for Qualifying Electrical Equipment and Instrumentation............................................................................................................3.10-3 3.10.3 Methods and Procedures of Analysis or Testing of Supports of Electrical Equipment and Instrumentation ..................................................................................3.10-8 3.10.4 Operating License Review (Tests and Analyses Results) .........................................3.10-11 3.10.5 COL License Information..........................................................................................3.10-11 3.11 Environmental Qualification of Safety-Related Mechanical and Electrical Equipment .............3.11-1 3.11.1 Equipment Identification and Environmental Conditions...........................................3.11-1 3.11.2 Qualification Tests and Analyses ................................................................................3.11-3 3.11.3 Qualification Test Results ...........................................................................................3.11-4 3.11.4 Loss of Heating, Ventilating, and Air Conditioning ...................................................3.11-4 3.11.5 Estimated Chemical and Radiation Environment........................................................3.11-4 3.11.6 COL License Information............................................................................................3.11-5 3.11.7 References ...................................................................................................................3.11-5 3.12 Tunnels.........................................................................................................................................3.12-1 3.12.1 Main Steam Tunnel .....................................................................................................3.12-1 3.12.2 Safety-Related Tunnels ...............................................................................................3.12-1 3.12.3 Miscellaneous Non-Safety Related Tunnels ...............................................................3.12-3 3.13 Secondary Containment and Divisional Separation Zones - Barrier Considerations .................3.13-1 3.13.1 Introduction .................................................................................................................3.13-1 3.13.2 Secondary Containment and Divisional Separation Barriers - General Design Basis ............................................................................................................................3.13-3 12 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 Table of Contents (Continued) 3.13.3 General ABWR Containment Structures, Systems and Barrier Descriptions.............3.13-6 3.13.4 General Safety Evaluation...........................................................................................3.13-8 3.13.5 Hardened-Softened Barrier Concept Approach- Special Critique ...........................3.13-12 3.13.6 Specific Barrier Design Basis and Safety Evaluation ...............................................3.13-14 3.13.7 Protection of Environmentally Sensitive Equipment ................................................3.13-16 3.13.8 Summary Conclusions...............................................................................................3.13-19 3A Seismic Soil Structure Interaction Analysis ..................................................................................3A-1 3A.1 Introduction ...................................................................................................................3A-1 3A.2 ABWR Standard Plant Site Plan ...................................................................................3A-1 3A.3 Generic Site Conditions.................................................................................................3A-2 3A.4 Input Motion and Damping Values ...............................................................................3A-6 3A.5 Soil-Structure Interaction Analysis Method..................................................................3A-6 3A.6 Free-Field Site Responses Analysis ............................................................................3A-12 3A.7 Soil-Structure Interaction Analysis Cases ...................................................................3A-13 3A.8 Analysis Models ..........................................................................................................3A-14 3A.9 Analysis Results ..........................................................................................................3A-17 3A.10 Site Enveloping Seismic Response .............................................................................3A-22 3A.11 References ...................................................................................................................3A-24 3B Containment Hydrodynamic Loads ............................................................................................... 3B-1 3B.1 Introduction ................................................................................................................... 3B-1 3B.2 Review of Phenomena................................................................................................... 3B-1 3B.3 Safety/Relief Valve Discharge Loads ........................................................................... 3B-6 3B.4 Loss-of-Coolant Accident Loads................................................................................. 3B-11 3B.5 Submerged Structure Loads ........................................................................................ 3B-27 3B.6 Loads Combination ..................................................................................................... 3B-29 3B.7 References ................................................................................................................... 3B-29 3C Computer Programs Used in the Design and Analysis of Seismic Category I Structures............. 3C-1 3C.1 Introduction ................................................................................................................... 3C-1 3C.2 Static and Dynamic Structural Analysis Systems (STARDYNE) ................................ 3C-1 3C.3 Concrete Element Cracking Analysis Program (CECAP) ............................................ 3C-1 3C.4 Finite Element Program for Cracking Analysis (FINEL) ............................................. 3C-2 3D Computer Programs Used in the Design of Components, Equipment and Structures ..................3D-1 3D.1 Introduction ...................................................................................................................3D-1 3D.2 Fine Motion Control Rod Drive ....................................................................................3D-1 3D.3 Reactor Pressure Vessel and Internals...........................................................................3D-1 3D.4 Piping.............................................................................................................................3D-1 3D.5 Pumps and Motors.........................................................................................................3D-4 3D.6 Heat Exchangers............................................................................................................3D-4 3D.7 Soil-Structure Interaction ..............................................................................................3D-5 3E Guidelines for LBB Application.................................................................................................... 3E-1 3E.1 Introduction ................................................................................................................... 3E-1 3E.2 Material Fracture Toughness Characterization ............................................................. 3E-4 3E.3 Fracture Mechanics Methods ...................................................................................... 3E-10 Table of Contents 13

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 Table of Contents (Continued) 3E.4 Leak Rate Calculation Methods .................................................................................. 3E-16 3E.5 Leak Detection Capabilities ........................................................................................ 3E-21 3E.6 Guidelines for Preparation of an LBB Report............................................................. 3E-22 3E.7 References ................................................................................................................... 3E-27 3F Not Used .........................................................................................................................................3F-1 3G Response of Structures to Containment Loads ..............................................................................3G-1 3G.1 Scope .............................................................................................................................3G-1 3G.2 Dynamic Response ........................................................................................................3G-1 3G.3 Hydrodynamic Load Analysis Results ..........................................................................3G-4 3H Design Details and Evaluation Results of Seismic Category I Structures..................................3H.1-1 3H.1 Reactor Building.........................................................................................................3H.1-1 3H.2 Control Building.........................................................................................................3H.2-1 3H.3 Radwaste Building......................................................................................................3H.3-1 3H.4 Structural Evaluation of R/B Compartment Walls Due to HELB..............................3H.4-1 3H.5 Structural Analysis Reports........................................................................................3H.5-1 3H.6 Summary of Key Structural Design Features.............................................................3H.6-1 3I Equipment Qualification Environmental Design Criteria .............................................................. 3I-1 3I.1 Introduction .................................................................................................................... 3I-1 3I.2 Plant Zones ..................................................................................................................... 3I-1 3I.3 Environmental Conditions Parameters ........................................................................... 3I-2 3J Not Used ......................................................................................................................................... 3J-1 3K Designated NEDE-24326-1-P Material Which May Not Change Without Prior NRC Staff Approval................................................................................................................................3K-1 3K.1 General Requirements for Dynamic Testing (4.4.2.5.1) ...............................................3K-1 3K.2 Product and Assembly Testing (4.4.2.5.2) ....................................................................3K-3 3K.3 Multiple-Frequency Tests (4.4.2.5.3) ............................................................................3K-3 3K.4 Single- and Multi-axis Tests (4.4.2.5.4) ........................................................................3K-3 3K.5 Single Frequency Tests (4.4.2.5.6)................................................................................3K-4 3K.6 Damping (4.4.2.5.7).......................................................................................................3K-4 3K.7 Qualification Determination (4.4.3.3) ...........................................................................3K-4 3K.8 Dynamic Qualification by Analysis (4.4.4.1.4).............................................................3K-4 3K.9 Required Response Spectra (4.4.4.1.4.6.2) ...................................................................3K-5 3K.10 Time History Analysis (4.4.4.1.4.6.3) ...........................................................................3K-5 3L Evaluation of Postulated Ruptures in High Energy Pipes ............................................................. 3L-1 3L.1 Background and Scope .................................................................................................. 3L-1 3L.2 Identification of Rupture Locations and Rupture Geometry......................................... 3L-2 3L.3 Design and Selection of Pipe Whip Restraints.............................................................. 3L-2 3L.4 Pipe Rupture Evaluation................................................................................................ 3L-3 3L.5 Jet Impingement on Essential Piping ............................................................................ 3L-6 3M Resolution Of Intersystem Loss Of Coolant Accident For ABWR.............................................. 3M-1 3M.1 Introduction .................................................................................................................. 3M-1 14 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 Table of Contents (Continued) 3M.2 ABWR Regulatory Requirements ................................................................................ 3M-1 3M.3 Boundary Limits of URS.............................................................................................. 3M-2 3M.4 Evaluation Procedure.................................................................................................... 3M-4 3M.5 Systems Evaluated........................................................................................................ 3M-5 3M.6 Piping Design Pressure for URS Compliance .............................................................. 3M-6 3M.7 Applicability of URS Non-piping Components ........................................................... 3M-6 3M.8 Results .......................................................................................................................... 3M-7 3M.9 Valve Misalignment Due To Operator Error................................................................ 3M-8 3M.10 Additional Operational Considerations ........................................................................ 3M-8 3M.11 Summary....................................................................................................................... 3M-8 3M.12 References .................................................................................................................... 3M-9 3MA System Evaluation For ISLOCA ............................................................................................... 3MA-1 3MA.1 General Comments About the Appendix .................................................................. 3MA-1 3MA.2 Residual Heat Removal System ................................................................................ 3MA-1 3MA.3 High Pressure Core Flooder System........................................................................ 3MA-10 3MA.4 Reactor Core Isolation Cooling System .................................................................. 3MA-14 3MA.5 Control Rod Drive System ...................................................................................... 3MA-21 3MA.6 Standby Liquid Control System .............................................................................. 3MA-25 3MA.7 Reactor Water Cleanup System............................................................................... 3MA-27 3MA.8 Fuel Pool Cooling Cleanup System......................................................................... 3MA-28 3MA.9 Nuclear Boiler System............................................................................................. 3MA-30 3MA.10 Reactor Recirculation System ................................................................................. 3MA-31 3MA.11 Makeup Water System Condensate......................................................................... 3MA-33 3MA.12 Makeup Water System Purified............................................................................... 3MA-36 3MA.13 Radwaste System..................................................................................................... 3MA-38 3MA.14 Condensate and Feedwater (CFS) System .............................................................. 3MA-40 3MA.15 Sampling (SAM) System......................................................................................... 3MA-41 Table of Contents 15

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables Table 3.2-1 Classification Summary.................................................................................................3.2-9 Table 3.2-2 Minimum Design Requirements for an Assigned Safety Designation........................3.2-60 Table 3.2-3 Quality Group DesignationsCodes and Industry Standards ....................................3.2-61 Table 3.3-1 Importance Factor (I) for Wind Loads ..........................................................................3.3-4 Table 3.4-1 Structures, Penetrations, and Access Openings Designed for Flood Protection .........3.4-16 Table 3.5-1 Requirement for the Probability of Missile Generation for ABWR Standard Plant.............................................................................................................................3.5-15 Table 3.6-1 Essential Systems, Components, and Equipment for Postulated Pipe Failures Inside Containment......................................................................................................3.6-34 Table 3.6-2 Essential Systems, Components, and Equipment for Postulated Pipe Failures Outside Containment ...................................................................................................3.6-35 Table 3.6-3 High-Energy Piping Inside Containment ....................................................................3.6-36 Table 3.6-4 High-Energy Piping Outside Containment..................................................................3.6-36 Table 3.6-5 Moderate-Energy Piping Inside Containment .............................................................3.6-37 Table 3.6-6 Moderate-Energy Piping Outside Containment ..........................................................3.6-37 Table 3.6-7 Additional Criteria for Integrated Leakage Rate Test .................................................3.6-38 Table 3.7-1 Damping for Different Materials.................................................................................3.7-47 Table 3.7-2 Natural Frequencies of the Reactor Building Complex in X Direction (0°-180° Axis)Fixed Base Condition......................................................................3.7-48 Table 3.7-3 Natural Frequencies of the Reactor Building Complex in Y Direction (90°-270° Axis)Fixed Base Condition....................................................................3.7-49 Table 3.7-4 Natural Frequencies of the Reactor Building Complex in Z Direction (Vertical)Fixed Base Condition...............................................................................3.7-50 Table 3.7-5 Natural Frequencies of the Control BuildingFixed Base Condition .......................3.7-50 Table 3.7-6 Natural Frequencies of the Radwaste BuildingFixed Base Condition ....................3.7-51 Table 3.8-1 Load Combinations, Load Factors and Acceptance Criteria for the Reinforced Concrete Containment .................................................................................................3.8-49 Table 3.8-2 Major Allowable Stresses in Concrete and Reinforcing Steel ....................................3.8-51 Table 3.8-3 Stress Intensity Limits .................................................................................................3.8-51 16 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3.8-4 Codes, Standards, Specifications, and Regulations Used in the Design and Construction of Seismic Category I Internal Structures of the Containment..............3.8-52 Table 3.8-5 Load Combination, Load Factors and Acceptance Criteria for Reinforced Concrete Structures Inside the Containment ...............................................................3.8-54 Table 3.8-6 Load Combination, Load Factors and Acceptance Criteria for Steel Structures Inside the Containment ...............................................................................................3.8-55 Table 3.8-7 Load Combinations for Foundation Design ................................................................3.8-56 Table 3.8-8 Welding Activities and Weld Examination Requirements for Containment Vessel ..........................................................................................................................3.8-57 Table 3.8-9 Staff Position on the Use of Standard ANSI/AISC N690 Nuclear Facilities-Steel Safety-Related Structures ............................................................................................3.8-58 Table 3.8-10 Staff Position on Steel Embedments ...........................................................................3.8-59 Table 3.9-1 Plant Events .................................................................................................................3.9-82 Table 3.9-2 Load Combinations and Acceptance Criteria for Safety-Related, ASME Code Class 1, 2 and 3 Components, Component Supports, and Class CS Structures ..........3.9-84 Table 3.9-3 Pressure Differentials Across Reactor Vessel Internals ..............................................3.9-88 Table 3.9-4 Deformation Limit for Safety Class Reactor Internal Structures Only .......................3.9-89 Table 3.9-5 Primary Stress Limit for Safety Class Reactor Internal Structures Only ....................3.9-90 Table 3.9-6 Buckling Stability Limit for Safety Class Reactor Internal Structures Only ..............3.9-92 Table 3.9-7 Fatigue Limit for Safety Class Reactor Internal Structures Only................................3.9-93 Table 3.9-8 Inservice Testing Safety-Related Pumps and Valves..................................................3.9-94 Table 3.9-9 Reactor Coolant System Pressure Isolation Valves...................................................3.9-138 Table 3.9-10 Welding Activities and Weld Examination Requirements for ASME Code,Section III Welds.......................................................................................................3.9-139 Table 3A-1 Soil Properties for UB Profile .....................................................................................3A-26 Table 3A-2 Average Shear Wave Velocities in Layers..................................................................3A-27 Table 3A-3 Strain-Dependent Shear Modulus................................................................................3A-28 Table 3A-4 Strain-Dependent Soil Damping..................................................................................3A-28 Table 3A-5 Case IDs for Site Conditions Considered....................................................................3A-29 Table of Contents 17

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3A-6 SSE Free-Field Site Response Results for all Soil Profiles (Average Properties) ......3A-30 Table 3A-7 Summary of SSI Cases Considered (Reactor and Control Buildings) ........................3A-31 Table 3A-8 Effect Of Soil Stiffness on Maximum Forces .............................................................3A-33 Table 3A-9 Effect Of Depth to Base Rock, UB Case.....................................................................3A-34 Table 3A-10 Effect Of Depth to Base Rock, VP3 Case ...................................................................3A-35 Table 3A-11 Effect Of Depth to Water Table Location ...................................................................3A-36 Table 3A-12 Effect of Concrete Cracking........................................................................................3A-37 Table 3A-13 Effect of Change in Soil Degradation Curves .............................................................3A-38 Table 3A-14 Effect Of Separation Between the Side Soil and Foundation Walls ...........................3A-39 Table 3A-15 Effect Of Adjacent Buildings, UB Case......................................................................3A-40 Table 3A-16 Effect Of Adjacent Buildings, VP3 Case ....................................................................3A-41 Table 3A-17 Effect Of Adjacent Buildings, VP5 Case ....................................................................3A-42 Table 3A-18 Effect of Adjacent Buildings Enveloping Seismic Soil Pressures ..............................3A-43 Table 3A-19a ABWR Reactor Building Walls and Floors Summary of Enveloping Seismic Loads ...........................................................................................................................3A-44 Table 3A-19b ABWR Reactor Building RCCVSummary of Enveloping Seismic Loads .................3A-45 Table 3A-19c ABWR Reactor Building RSW/Pedestal Summary of Enveloping Seismic Loads....3A-46 Table 3A-19d ABWR Reactor Building Key RPV/Internal Components Summary of Enveloping Seismic Loads..............................................................................................................3A-47 Table 3A-20 ABWR Control Building Summary of Enveloping Seismic Loads ............................3A-48 Table 3A-21a ABWR Reactor Building Walls and Floors Summary of Enveloping Maximum Vertical Accelerations .................................................................................................3A-49 Table 3A-21b ABWR Reactor Building RCCV Summary of Enveloping Maximum Vertical Accelerations ...............................................................................................................3A-50 Table 3A-21c ABWR Reactor Building RSW/PED Summary of Enveloping Maximum Vertical Accelerations .................................................................................................3A-51 Table 3A-22 ABWR Control Building Summary of Enveloping Maximum Vertical Accelerations ...............................................................................................................3A-52 18 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3A-23a ABWR Reactor Building Walls and Floors Summary of Enveloping Maximum Accelerations ...............................................................................................................3A-53 Table 3A-23b ABWR Reactor Building RCCV Summary of Enveloping Maximum Accelerations ...............................................................................................................3A-54 Table 3A-23c ABWR Reactor Building RSW/PED Summary of Enveloping Maximum Accelerations ...............................................................................................................3A-55 Table 3A-23d ABWR Reactor Building RPV/Internals Summary of Enveloping Maximum Accelerations ...............................................................................................................3A-56 Table 3A-24 ABWR Control Building Summary of Enveloping Maximum Accelerations............3A-57 Table 3A-25a ABWR Reactor Building Walls and Floors Summary of Enveloping Maximum Relative Displacements with Respect to Input Motion ...............................................3A-58 Table 3A-25b ABWR Reactor Building RCCV Summary of Enveloping Maximum Relative Displacements with Respect to Input Motion .............................................................3A-59 Table 3A-25c ABWR Reactor Building RSW/PED Summary of Enveloping Maximum Relative Displacements with Respect to Input Motion .............................................................3A-60 Table 3A-25d ABWR Reactor Building RPV/Internals Summary of Enveloping Maximum Relative Displacements with Respect to Input Motion ...............................................3A-61 Table 3A-26 ABWR Control Building Summary of Enveloping Maximum Relative Displacements with Respect to Input Motion .............................................................3A-62 Table 3A-27a ABWR Reactor Building Walls and Floors Summary of Enveloping Maximum Relative Displacements with Respect to Basemat.......................................................3A-63 Table 3A-27b ABWR Reactor Building RCCV Summary of Enveloping Maximum Relative Displacements with Respect to Basemat.....................................................................3A-64 Table 3A-27c ABWR Reactor Building RSW/PED Summary of Enveloping Maximum Relative Displacements with Respect to Basemat.......................................................3A-65 Table 3A-27d ABWR Reactor Building RPV/Internals Summary of Enveloping Maximum Relative Displacements with Respect to Basemat.......................................................3A-66 Table 3A-28 ABWR Control Building Summary of Enveloping Maximum Relative Displacements with Respect to Basemat.....................................................................3A-67 Table 3B-1 Pool Swell Calculated Values ..................................................................................... 3B-31 Table 3B-2 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-32 Table of Contents 19

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3B-3 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-34 Table 3B-4 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-34 Table 3B-5 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-35 Table 3B-6 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-35 Table 3B-7 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-36 Table 3B-8 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-36 Table 3B-9 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] .................................................................................. 3B-37 Table 3E-1 Leak Before Break Candidate Piping System ............................................................. 3E-31 Table 3E-2 Electrodes and Filler Metal Requirements for Carbon Steel Welds............................ 3E-31 Table 3E-3 Supplier Provided Chemical Composition and Mechanical Properties Information .................................................................................................................. 3E-32 Table 3E-4 Standard Tension Test Data at Temperature ............................................................... 3E-32 Table 3E-5 Summary of Carbon Steel J-R Curve Tests................................................................. 3E-33 Table 3E-6 Mass Flow Rate for Several fl/Dh Values................................................................... 3E-33 Table 3E-7 Stresses in the Main Steam Lines (Assumed for Example) ........................................ 3E-34 Table 3E-8 Critical Crack Length and Instability Load Margin Evaluations for Main Steam Lines (Example) .......................................................................................................... 3E-34 Table 3E-9 Data for Feedwater System Piping (Example) ............................................................ 3E-34 Table 3E-10 Stresses in Feedwater Lines (Assumed for Example) ................................................. 3E-35 Table 3E-11 Critical Crack Length and Instability Load Margin Evaluations for Feedwater Lines (Example) .......................................................................................................... 3E-35 Table 3G-1 Analysis Parameters in Terms of Time/Frequency Steps..............................................3G-5 Table 3G-2 Maximum Accelerations for AP Loadings (g) ..............................................................3G-7 Table 3G-3 Maximum Accelerations for Hydrodynamic Loads (g) ................................................3G-7 20 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3G-4 Maximum Displacements for AP Loadings (mm) ........................................................3G-7 Table 3G-5 Maximum Displacements for Hydrodynamic Loads (mm)...........................................3G-7 Table 3H.1-1 Equivalent Linear Temperature Distributions at Various Sections..........................3H.1-18 Table 3H.1-2 SIT and LOCA Pressure Loads ................................................................................3H.1-19 Table 3H.1-3 Hydrodynamic Loads ...............................................................................................3H.1-19 Table 3H.1-4 Maximum Vertical Acceleration ..............................................................................3H.1-20 Table 3H.1-5 Load Combinations, Load Factors and Acceptance Criteria for the Reinforced Concrete Containment ..............................................................................................3H.1-21 Table 3H.1-5a Selected Load Combinations for the RCCV ............................................................3H.1-21 Table 3H.1-5b Selected Load Combinations for the Reactor Building............................................3H.1-22 Table 3H.1-6 Results of "Stardyne" Analysis for Unit Drywell Pressure: 6.9 kPa [Pd] ................3H.1-23 Table 3H.1-7 Results of "Stardyne" Analysis for Unit Wetwall Pressure: 6.9 kPa [Pw]...............3H.1-30 Table 3H.1-8 Results of "Stardyne" Analysis for Safe Shutdown Earthquake (SSE) SRSS of Three Components [Ess] ..........................................................................................3H.1-37 Table 3H.1-9 Results of "Stardyne" Analysis for Thermal Loads (6 Hours) [TA-II] ...................3H.1-44 Table 3H.1-10 Load Combination 1 .................................................................................................3H.1-51 Table 3H.1-11 Load Combination 8 .................................................................................................3H.1-56 Table 3H.1-12 Load Combination 15 ...............................................................................................3H.1-61 Table 3H.1-13 Load Combination 15a and 15b ...............................................................................3H.1-64 Table 3H.1-14 Rebar Ratios Used in the Analysis ...........................................................................3H.1-67 Table 3H.1-15 Rebar and Concrete Stresses Due to Load Combination 1.......................................3H.1-69 Table 3H.1-16 Rebar and Concrete Stresses Due to Load Combination 8.......................................3H.1-70 Table 3H.1-17 Rebar and Concrete Stresses Due to Load Combination 15.....................................3H.1-72 Table 3H.1-18 Rebar and Concrete Stresses Due to Load Combinations 15a and 15b ...................3H.1-74 Table 3H.1-19 Containment Liner Plate Strains (Max)....................................................................3H.1-76 Table 3H.1-20 Stresses in Pedestal...................................................................................................3H.1-79 Table of Contents 21

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3H.1-21 Maximum Moments and Shears in Walls Due to Lateral Soil Pressure (At-Rest Condition).................................................................................................................3H.1-79 Table 3H.1-22 Maximum Moments and Shears in Walls Due to SSE Soil Pressure (SSE Condition).................................................................................................................3H.1-79 Table 3H.1-23 Factors of Safety for Foundation Stability ...............................................................3H.1-80 Table 3H.2-1 Control Building SSE Loads ....................................................................................3H.2-16 Table 3H.2-2 Control Building Base Shear and Overturning Moments for Stability Evaluation.................................................................................................................3H.2-16 Table 3H.2-3 Base Mat, Floor and Roof Slabs-Design Forces and Reinforcement ......................3H.2-17 Table 3H.2-4 Walls-Design Forces and Reinforcement ................................................................3H.2-18 Table 3H.2-5 Stability Evaluation-Factors of Safety.....................................................................3H.2-20 Table 3H.3-1 Radwaste Building Design Seismic Loads...............................................................3H.3-12 Table 3H.3-2 Forces and Moments in Critical Elements for Dead Load (D).................................3H.3-13 Table 3H.3-3 Forces and Moments in Critical Elements for Live Loads (L).................................3H.3-14 Table 3H.3-4 Forces and Moments in Critical Elements for Soil Pressure @ Rest (H).................3H.3-15 Table 3H.3-5 Forces and Moments in Critical Elements for Seismic Soil Pressure (H) ..............3H.3-16 Table 3H.3-6 Forces and Moments in Critical Elements for Seismic Load (E).............................3H.3-17 Table 3H.3-7 Forces and Moments in Critical Elements for Load Combination:

1.4D + 1.7L + 1.7H ..................................................................................................3H.3-18 Table 3H.3-8 Forces and Moments in Critical Elements for Load Combination (D + L + H +/- E)Max. Tension ................................................................................3H.3-19 Table 3H.3-9 Forces and Moments in Critical Elements for Load Combination (D + L + H +/- E)Max. Compression ........................................................................3H.3-20 Table 3H.3-10 Rebar and Concrete Stresses for Load Combination: 1.4D + 1.7L + 1.7H..............3H.3-21 Table 3H.3-11 Rebar and Concrete Stresses for Load Combination (D + L + H +/- E)Max. Tension ................................................................................3H.3-22 Table 3H.3-12 Rebar and Concrete Stresses for Load Combination (D + L + H +/- E)Max. Compression ........................................................................3H.3-23 Table 3H.3-13 Summary of Reinforced Steel ..................................................................................3H.3-24 Table 3H.3-14 Summary of Reinforcing Steel Ratios......................................................................3H.3-25 22 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3H.3-15 Summary of Structural Steel Safety Margins...........................................................3H.3-27 Table 3H.3-16 Maximum Soil Bearing Pressures ............................................................................3H.3-28 Table 3H.4-1 Design of Type 1 (Shear) Walls Exposed to HELB Loadings...................................3H.4-3 Table 3H.4-2 Design of Type 2 (Non-Shear) Walls Exposed to HELB Loadings...........................3H.4-4 Table 3H.4-3 Design of Concrete Blocks for Removable Wall Exposed to HELB Loadings .........3H.4-5 Table 3I-1 Plant Environment Location and Condition Cross Reference of Table Numbers.......... 3I-5 Table 3I-2 Thermodynamic Environment Conditions Inside Primary Containment Vessel Plant Normal Operating Conditions1 ............................................................................. 3I-5 Table 3I-3 Thermodynamic Environment Conditions Inside Reactor Building (Secondary Containment) Plant Normal Operating Conditions ........................................................ 3I-6 Table 3I-4 Thermodynamic Environment Conditions Inside Reactor Building (Outside Secondary Containment) Plant Normal Operating Conditions ...................................... 3I-7 Table 3I-5 Thermodynamic Environment Conditions Inside Control Building Plant Normal Operating Conditions...................................................................................................... 3I-7 Table 3I-6 Thermodynamic Environment Conditions Inside Turbine Building Plant Normal Operating Conditions...................................................................................................... 3I-8 Table 3I-7 Radiation Environment Conditions Inside Primary Containment Vessel Plant Normal Operating Conditions ........................................................................................ 3I-8 Table 3I-8 Radiation Environment Conditions Inside Reactor Building (Secondary Containment) Plant Normal Operating Conditions ........................................................ 3I-9 Table 3I-9 Radiation Environment Conditions Inside Reactor Building (Outside Secondary Containment) Plant Normal Operating Conditions ...................................................... 3I-10 Table 3I-10 Radiation Environment Conditions Inside Control Building Plant Normal Operating Conditions.................................................................................................... 3I-10 Table 3I-11 Radiation Environment Conditions Inside Turbine Building Plant Normal Operating Conditions.................................................................................................... 3I-11 Table 3I-12 Thermodynamic Environment Conditions Inside Primary Containment Vessel Plant Accident Conditions............................................................................................ 3I-11 Table 3I-13 Thermodynamic Environment Conditions Inside Reactor Building (Secondary Containment) Plant Accident Conditions..................................................................... 3I-12 Table 3I-14 Thermodynamic Environment Conditions Inside Reactor Building (Outside Secondary Containment) Plant Accident Conditions ................................................... 3I-15 Table of Contents 23

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Tables (Continued)

Table 3I-15 Thermodynamic Environment Conditions Inside Control Building Plant Accident Conditions..................................................................................................................... 3I-15 Table 3I-16 Radiation Environment Conditions Inside Primary Containment Design Basis Accident Conditions ..................................................................................................... 3I-16 Table 3I-17 Radiation Environment Conditions Inside Reactor Building Design Basis Accident (Secondary Containment) ............................................................................. 3I-16 Table 3I-18 Radiation Environment Conditions Inside Reactor Building Design Basis Accident Conditions (Outside Secondary Containment) ............................................. 3I-17 Table 3I-19 Radiation Environment Conditions Inside Control Building Design Basis Accident Conditions ..................................................................................................... 3I-17 Table 3M-1 Low Pressure Sink Component Sizes......................................................................... 3M-10 24 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures Figure 3.2-1 Quality Group and Seismic Category Classification Applicable to Power Conversion System...................................................................................................3.2-62 Figure 3.2-2 Quality Group and Seismic Category Classification Applicable to Feedwater System ......................................................................................................................3.2-63 Figure 3.5-1 Missile Velocity and Displacement Characteristics Resulting from Saturated Steam and Water Blowdowns (7.2 MPaA Stagnation Pressure) .............................3.5-16 Figure 3.5-2 ABWR Standard Plant Low-Trajectory Turbine Missile Ejection Zone .................3.5-17 Figure 3.6-1 Jet Characteristics.....................................................................................................3.6-39 Figure 3.6-2 Typical Pipe Whip Restraint Configuration.............................................................3.6-40 Figure 3.6-3 Initial Blowdown and Wave Forces .........................................................................3.6-41 Figure 3.6-4 Acceptable Types of Pipe Whip Restraints..............................................................3.6-42 Figure 3.7-1 Horizontal Safe Shutdown Earthquake Design Spectra...........................................3.7-52 Figure 3.7-2 Vertical Safe Shutdown Earthquake Design Spectra ...............................................3.7-53 Figure 3.7-3 Horizontal, H1 Component Time History................................................................3.7-54 Figure 3.7-4 Horizontal, H2 Component Time History................................................................3.7-55 Figure 3.7-5 Vertical, Component Time History..........................................................................3.7-56 Figure 3.7-6 2% Damped Response Spectra, H1 Component ......................................................3.7-57 Figure 3.7-7 3% Damped Response Spectra, H1 Component ......................................................3.7-58 Figure 3.7-8 4% Damped Response Spectra, H1 Component ......................................................3.7-59 Figure 3.7-9 5% Damped Response Spectra, H1 Component ......................................................3.7-60 Figure 3.7-10 7% Damped Response Spectra, H1 Component ......................................................3.7-61 Figure 3.7-11 2% Damped Response Spectra, H2 Component ......................................................3.7-62 Figure 3.7-12 3% Damped Response Spectra, H2 Component ......................................................3.7-63 Figure 3.7-13 4% Damped Response Spectra, H2 Component ......................................................3.7-64 Figure 3.7-14 5% Damped Response Spectra, H2 Component ......................................................3.7-65 Figure 3.7-15 7% Damped Response Spectra, H2 Component ......................................................3.7-66 Figure 3.7-16 2% Damped Response Spectra, Vt Component .......................................................3.7-67 Table of Contents 25

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3.7-17 3% Damped Response Spectra, Vt Component .......................................................3.7-68 Figure 3.7-18 4% Damped Response Spectra, Vt Component .......................................................3.7-69 Figure 3.7-19 5% Damped Response Spectra, Vt Component .......................................................3.7-70 Figure 3.7-20 7% Damped Response Spectra, Vt Component .......................................................3.7-71 Figure 3.7-21 Not Used...................................................................................................................3.7-72 Figure 3.7-22 Not Used...................................................................................................................3.7-72 Figure 3.7-23 Not Used...................................................................................................................3.7-72 Figure 3.7-24 Power Spectral Density Function, H1 Component ..................................................3.7-73 Figure 3.7-25 Power Spectral Density Function, H2 Component ..................................................3.7-74 Figure 3.7-26 Power Spectral Density Function, VT Component..................................................3.7-75 Figure 3.7-27 Damping Values for Electrical Raceway Systems...................................................3.7-76 Figure 3.7-28 Seismic System Analytical Model ...........................................................................3.7-77 Figure 3.7-29 Reactor Building Elevation (0°-180° Section) ........................................................3.7-78 Figure 3.7-30 Reactor Building Elevation (90°-270° Section) ......................................................3.7-79 Figure 3.7-31 Reactor Building Model (see Figure 3A-8) .............................................................3.7-80 Figure 3.7-32 Reactor Pressure Vessel (RPV) and Internals Model (see Figure 3A-9) .................3.7-80 Figure 3.7-33 Control Building Dynamic Model (see Figure 3A-27) ............................................3.7-80 Figure 3.7-34 Radwaste Building Seismic Model ..........................................................................3.7-81 Figure 3.8-1 Reactor Building Arrangement Floor B2F Elevation -1700 mm ............................3.8-61 Figure 3.8-2 Reactor Building Arrangement Floor B3F Elevation -8200 mm ............................3.8-62 Figure 3.8-3 Reactor Building Arrangement Floor B1F Elevation 4800 mm ..............................3.8-63 Figure 3.8-4 Reactor Building Arrangement Floor 1F Elevation 12300 mm...............................3.8-64 Figure 3.8-5 Reactor Building Arrangement Floor 2F Elevation 18100 mm...............................3.8-65 Figure 3.8-6 Reactor Building Arrangement Floor 3F Elevation 23500 mm...............................3.8-66 Figure 3.8-7 Reactor Building Arrangement Floor 4F Elevation 31700 mm...............................3.8-67 Figure 3.8-8 Reactor Building Arrangement Elevation 38200 mm..............................................3.8-68 26 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3.8-9 Typical Section of Containment Liner Plate and Anchor ........................................3.8-69 Figure 3.8-10 Not Used...................................................................................................................3.8-70 Figure 3.8-11 Not Used...................................................................................................................3.8-70 Figure 3.8-12 Not Used...................................................................................................................3.8-70 Figure 3.8-13 Not Used...................................................................................................................3.8-70 Figure 3.8-14 Not Used...................................................................................................................3.8-70 Figure 3.8-15 Reactor BuildingContainment Upper Drywell Equipment Hatch .......................3.8-71 Figure 3.8-16 Not Used...................................................................................................................3.8-72 Figure 3.8-17 Reactor Building RCCV Internal Structures Nomenclature ....................................3.8-73 Figure 3.8-18 Reactor BuildingRCCV Configuration ................................................................3.8-74 Figure 3.8-19 Not Used...................................................................................................................3.8-75 Figure 3.8-20 Annual Temperature Profile of Suppression Pool Water During Normal Operation of a Typical Plant in Southern States ......................................................3.8-76 Figure 3.9-1 Transient Pressure Differentials Following a Steam Line Break...........................3.9-146 Figure 3.9-2 Reactor Internal Flow Paths and Minimum Floodable Volume ............................3.9-147 Figure 3.9-3 ABWR Recirculation Flow Path ............................................................................3.9-148 Figure 3.9-4 Fuel Support Pieces................................................................................................3.9-149 Figure 3.9-5 Pressure Nodes for Depressurization Analysis ......................................................3.9-150 Figure 3.9-6 Stress-Strain Curve for Blowout Restraints ...........................................................3.9-151 Figure 3.10-1 Typical Vertical Board ...........................................................................................3.10-13 Figure 3.10-2 Instrument Panel.....................................................................................................3.10-13 Figure 3.10-3 Typical Local Rack ................................................................................................3.10-14 Figure 3.10-4 NEMA Type-12 Enclosure ....................................................................................3.10-14 Figure 3A-1 (Refer to Figure 1.2-1) .............................................................................................3A-68 Figure 3A-2 0°-180° Section View ..............................................................................................3A-69 Figure 3A-3 Shear Wave Velocity Profiles Considered for SSI Analyses...................................3A-70 Table of Contents 27

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-4 Range of Shear Wave Velocities for Nuclear Power Plant Sites in High Seismic Areas...........................................................................................................3A-71 Figure 3A-5 Strain Dependent Soil Properties .............................................................................3A-72 Figure 3A-6 Strain Dependent Rock Properties ...........................................................................3A-73 Figure 3A-7 Substructuring of Interaction Model ........................................................................3A-74 Figure 3A-8 Reactor Building Stick Model..................................................................................3A-75 Figure 3A-9 RPV Stick Model .....................................................................................................3A-76 Figure 3A-10 Reactor Building Stick Model with Rigid Arms for X & Z Shaking.......................3A-77 Figure 3A-11 Reactor Building Stick Model with Rigid Arms for Y Shaking ..............................3A-78 Figure 3A-12 Reactor Building Foundation 2-D Model XZ Direction ..........................................3A-79 Figure 3A-13 The Excavated Soil Elements of Reactor Building 2-D Model ...............................3A-80 Figure 3A-14 Connection of the Main Stick to the Side Walls (For Reactor Building UB Cases).................................................................................................................3A-81 Figure 3A-15 R/B Excavated Soil Model (UB Soil Profiles).........................................................3A-82 Figure 3A-16 UB Case: Nodal Points at Elevation -13.70m .........................................................3A-83 Figure 3A-17 UB Case: Nodal Points at Elevation -10.95m .........................................................3A-84 Figure 3A-18 UB Case: Nodal Points at Elevation -8.20m ...........................................................3A-85 Figure 3A-19 UB Case: Nodal Points at Elevation -4.95m ...........................................................3A-86 Figure 3A-20 UB Case: Nodal Points at Elevation -1.70m ...........................................................3A-87 Figure 3A-21 UB Case: Nodal Points at Elevation 1.55m .............................................................3A-88 Figure 3A-22 UB Case: Nodal Points at Elevation 4.80m .............................................................3A-89 Figure 3A-23 UB Case: Nodal Points at Elevation 8.40m .............................................................3A-90 Figure 3A-24 UB Case: Nodal Points at Elevation 12.00m ...........................................................3A-91 Figure 3A-25 Plate Elements of the Side Wall (X = 29.80m)........................................................3A-92 Figure 3A-26 Plate Elements of the Side Wall (Y = 28.30m)........................................................3A-93 Figure 3A-27 Stick Model for the Control Building ......................................................................3A-94 Figure 3A-28 1/4 Stick Model Showing Rigid Arms .....................................................................3A-95 28 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-29 Control Building Foundation 2-D Model XZ Direction ..........................................3A-96 Figure 3A-30 Control Building Excavated Soil 2-D Model XZ Direction ....................................3A-97 Figure 3A-31 Connection of the Main Stick to the Side Wall (Control Building for UB Soil Profiles).............................................................................................................3A-98 Figure 3A-32 C/B Excavated Soil Model (UB Soil Profiles).........................................................3A-99 Figure 3A-33 UB Case: Nodal Points at Elevation -11.20m .......................................................3A-100 Figure 3A-34 UB Case: Nodal Points at Elevation -8.20m .........................................................3A-101 Figure 3A-35 UB Case: Nodal Points at Elevation -6.20m .........................................................3A-102 Figure 3A-36 UB Case: Nodal Points at Elevation -4.20m .........................................................3A-103 Figure 3A-37 UB Case: Nodal Points at Elevation -2.15m .........................................................3A-104 Figure 3A-38 UB Case: Nodal Points at Elevation 0.60m ...........................................................3A-105 Figure 3A-39 UB Case: Nodal Points at Elevation 3.50m ...........................................................3A-106 Figure 3A-40 UB Case: Nodal Points at Elevation 5.50m ...........................................................3A-107 Figure 3A-41 UB Case: Nodal Points at Elevation 7.90m ...........................................................3A-108 Figure 3A-42 UB Case: Nodal Points at Elevation 9.50m ...........................................................3A-109 Figure 3A-43 UB Case: Nodal Points at Elevation 12.00m .........................................................3A-110 Figure 3A-44 Plate Elements of the Side Wall (X = 12.00m)......................................................3A-111 Figure 3A-45 Plate Elements of the Side Wall (Y = 28.00m)......................................................3A-112 Figure 3A-46 Turbine Building Model.........................................................................................3A-113 Figure 3A-47 ABWR Reactor Bldg. Soil Stiffness Effect, Node 208 XZ Basemat Bottom, 2% Damping...........................................................................................................3A-114 Figure 3A-48 ABWR Reactor Bldg. Soil Stiffness Effect, Node 33 X RPV/MS Nozzle, 2% Damping...........................................................................................................3A-115 Figure 3A-49 ABWR Reactor Bldg. Soil Stiffness Effect, Node 89 X RCCV Top, 2% Damping...........................................................................................................3A-116 Figure 3A-50 ABWR Reactor Bldg. Soil Stiffness Effect, Node 95 X R/B Top, 2% Damping...........................................................................................................3A-117 Figure 3A-51 ABWR Reactor Bldg. Soil Stiffness Effect, Node 208 X Basemat Bottom, 2% Damping...........................................................................................................3A-118 Table of Contents 29

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-52 ABWR Control Bldg. Soil Stiffness Effect, Node 121 XZ Basemat Top, 2% Damping...........................................................................................................3A-119 Figure 3A-53 ABWR Control Bldg. Soil Stiffness Effect, Node 181 X C/B Top, 2% Damping...........................................................................................................3A-120 Figure 3A-54 ABWR Control Bldg. Soil Stiffness Effect, Node 121 X Basemat Top, 2% Damping...........................................................................................................3A-121 Figure 3A-55 ABWR Reactor Bldg. Soil Stiffness Effect, Node 33 Z RPV/MS Nozzle, 2% Damping...........................................................................................................3A-122 Figure 3A-56 ABWR Reactor Bldg. Soil Stiffness Effect, Node 89 Z RCCV Top, 2% Damping...........................................................................................................3A-123 Figure 3A-57 ABWR Reactor Bldg. Soil Stiffness Effect, Node 95 Z R/B Top, 2% Damping...........................................................................................................3A-124 Figure 3A-58 ABWR Reactor Bldg. Soil Stiffness Effect, Node 208 Z Basemat Bottom, 2% Damping...........................................................................................................3A-125 Figure 3A-59 ABWR Control Bldg. Soil Stiffness Effect, Node 108 Z C/B Top, 2% Damping...........................................................................................................3A-126 Figure 3A-60 ABWR Control Bldg. Soil Stiffness Effect, Node 102 Z Basemat Top, 2% Damping...........................................................................................................3A-127 Figure 3A-61 ABWR Reactor Bldg. Depth to Base Rock, Node 33 RPV/MS Nozzle, 2% Damping, UB ...................................................................................................3A-128 Figure 3A-62 ABWR Reactor Bldg. Depth to Base Rock, Node 89 X RCCV Top, 2% Damping, UB ...................................................................................................3A-129 Figure 3A-63 ABWR Reactor Bldg. Depth to Base Rock, Node 95 X R/B Top, 2% Damping, UB ...................................................................................................3A-130 Figure 3A-64 ABWR Reactor Bldg. Depth to Base Rock, Node 208 X Basemat Bottom, 2% Damping, UB ...................................................................................................3A-131 Figure 3A-65 ABWR Reactor Bldg. Depth to Base Rock, Node 33 X RPV/MS Nozzle, 2% Damping, VP3 .................................................................................................3A-132 Figure 3A-66 ABWR Reactor Bldg. Depth to Base Rock, Node 89 X RCCV Top, 2% Damping, VP3 .................................................................................................3A-133 Figure 3A-67 ABWR Reactor Bldg. Depth to Base Rock, Node 95 X R/B Top, 2% Damping, VP3 .................................................................................................3A-134 Figure 3A-68 ABWR Reactor Bldg. Depth to Base Rock, Node 208 X Basemat Bottom, 2% Damping, VP3 .................................................................................................3A-135 30 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-69 ABWR Control Bldg. Depth to Base Rock, Node 181 X C/B Top, 2% Damping, UB ...................................................................................................3A-136 Figure 3A-70 ABWR Control Bldg. Depth to Base Rock, Node 121 X Basemat Top, 2% Damping, UB ...................................................................................................3A-137 Figure 3A-71 ABWR Control Bldg. Depth to Base Rock, Node 181 X C/B Top, 2% Damping, VP3 .................................................................................................3A-138 Figure 3A-72 ABWR Control Bldg. Depth to Base Rock, Node 121 X Basemat Top, 2% Damping, VP3 .................................................................................................3A-139 Figure 3A-73 ABWR Reactor Bldg. Depth to Water Table, Node 33 X RPV/MS Nozzle, 2% Damping...........................................................................................................3A-140 Figure 3A-74 ABWR Reactor Bldg. Depth to Water Table, Node 89 X RCCV Top, 2% Damping...........................................................................................................3A-141 Figure 3A-75 ABWR Reactor Bldg. Depth to Water Table, Node 95 X R/B Top, 2% Damping...........................................................................................................3A-142 Figure 3A-76 ABWR Reactor Bldg. Depth to Water Table, Node 210 X Basemat Bottom, 2% Damping...........................................................................................................3A-143 Figure 3A-77 ABWR Control Bldg. Depth to Water Table, Node 181 X C/B Top, 2% Damping...........................................................................................................3A-144 Figure 3A-78 ABWR Control Bldg. Depth to Water Table, Node 121 X Basemat Top, 2% Damping...........................................................................................................3A-145 Figure 3A-79 ABWR Reactor Bldg. Depth to Water Table, Node 33 Z RPV/MS Nozzle, 2% Damping...........................................................................................................3A-146 Figure 3A-80 ABWR Reactor Bldg. Depth to Water Table, Node 89 Z RCCV Top, 2% Damping...........................................................................................................3A-147 Figure 3A-81 ABWR Reactor Bldg. Depth to Water Table, Node 95 Z R/B Top, 2% Damping...........................................................................................................3A-148 Figure 3A-82 ABWR Reactor Bldg. Depth to Water Table, Node 210 Z Basemat Bottom, 2% Damping...........................................................................................................3A-149 Figure 3A-83 ABWR Control Bldg. Depth to Water Table, Node 108 Z C/B Top, 2% Damping...........................................................................................................3A-150 Figure 3A-84 ABWR Control Bldg. Depth to Water Table, Node 102 Z Basemat Top, 2% Damping...........................................................................................................3A-151 Figure 3A-85 ABWR Reactor Bldg. Concrete Cracking, Node 33 X RPV/MS Nozzle, 2% Damping...........................................................................................................3A-152 Table of Contents 31

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-86 ABWR Reactor Bldg. Concrete Cracking, Node 89 X RCCV Top, 2% Damping...........................................................................................................3A-153 Figure 3A-87 ABWR Reactor Bldg. Concrete Cracking, Node 95 X R/B Top, 2% Damping...........................................................................................................3A-154 Figure 3A-88 ABWR Reactor Bldg. Concrete Cracking, Node 208 X Basemat Bottom, 2% Damping...........................................................................................................3A-155 Figure 3A-89 ABWR Control Bldg. Concrete Cracking, Node 181 X C/B Top, 2% Damping...........................................................................................................3A-156 Figure 3A-90 ABWR Control Bldg. Concrete Cracking, Node 121 X Basemat Top, 2% Damping...........................................................................................................3A-157 Figure 3A-91 Shear Modulus vs Shear Strain ..............................................................................3A-158 Figure 3A-92 ABWR Reactor Bldg. Soil Curves, Node 33 X RPV/MS Nozzle, 2% Damping...........................................................................................................3A-159 Figure 3A-93 ABWR Reactor Bldg. Soil Curves, Node 89 X RCCV Top, 2% Damping...........3A-160 Figure 3A-94 ABWR Reactor Bldg. Soil Curves, Node 95 X R/B Top, 2% Damping ...............3A-161 Figure 3A-95 ABWR Reactor Bldg. Soil Curves, Node 208 X Basemat Bottom, 2% Damping...........................................................................................................3A-162 Figure 3A-96 ABWR Control Bldg. Soil Curves, Node 181 X C/B Top, 2% Damping .............3A-163 Figure 3A-97 ABWR Control Bldg. Soil Curves, Node 121 X Basemat Top, 2% Damping ......3A-164 Figure 3A-98 ABWR Reactor Bldg. Side Soil Separation, Node 33 X RPV/MS Nozzle, 2% Damping...........................................................................................................3A-165 Figure 3A-99 ABWR Reactor Bldg. Side Soil Separation, Node 89 X RCCV Top, 2% Damping...........................................................................................................3A-166 Figure 3A-100 ABWR Reactor Bldg. Side Soil Separation, Node 95 X R/B Top, 2% Damping...........................................................................................................3A-167 Figure 3A-101 ABWR Reactor Bldg. Side Soil Separation, Node 208 X Basemat Bottom, 2% Damping...........................................................................................................3A-168 Figure 3A-102 ABWR Reactor Bldg. Side Soil Separation, Node 33 Z RPV/MS Nozzle, 2% Damping...........................................................................................................3A-169 Figure 3A-103 ABWR Reactor Bldg. Side Soil Separation, Node 89 Z RCCV Top, 2% Damping...........................................................................................................3A-170 32 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-104 ABWR Reactor Bldg. Side Soil Separation, Node 95 Z R/B Top, 2% Damping...........................................................................................................3A-171 Figure 3A-105 ABWR Reactor Bldg. Side Soil Separation, Node 208 Z Basemat Bottom, 2% Damping...........................................................................................................3A-172 Figure 3A-106 ABWR Control Bldg. Side Soil Separation, Node 181 X C/B Top, 2% Damping...........................................................................................................3A-173 Figure 3A-107 ABWR Control Bldg. Side Soil Separation, Node 121 X Basemat Top, 2% Damping...........................................................................................................3A-174 Figure 3A-108 ABWR Control Bldg. Side Soil Separation, Node 108 Z C/B Top, 2% Damping...........................................................................................................3A-175 Figure 3A-109 ABWR Control Bldg. Side Soil Separation, Node 102 Z Basemat Top, 2% Damping...........................................................................................................3A-176 Figure 3A-110 ABWR Reactor Bldg. Structure-to-Structure, Node 33 X RPV/MS Nozzle, 2% Damping, UB1D150 ........................................................................................3A-177 Figure 3A-111 ABWR Reactor Building Structure-to-Structure, Node 89 X, RCCV Top, 2% Damping, UB1D150 ........................................................................................3A-178 Figure 3A-112 ABWR Reactor Building Structure-to-Structure, Node 95 X, R/B Top, 2% Damping, UB1D150 ........................................................................................3A-179 Figure 3A-113 ABWR Reactor Building Structure-to-Structure, Node 210 (201 for 2D) X, Basemat Bottom, 2% Damping, UB1D150 ...........................................................3A-180 Figure 3A-114 ABWR Reactor Building Structure-to-Structure, Node 33 X, RPV/MS Nozzle, 2% Damping, VP3D150.........................................................................................3A-181 Figure 3A-115 ABWR Reactor Bldg. Structure-to-Structure, Node 89 X RCCV Top, 2% Damping, VP3D150.........................................................................................3A-182 Figure 3A-116 ABWR Reactor Bldg. Structure-to-Structure, Node 95 X R/B Top, 2% Damping, VP3D150.........................................................................................3A-183 Figure 3A-117 ABWR Reactor Bldg. Structure-to-Structure, Node 208 (201 for 2 D) X Basemat Bottom, 2% Damping, VP5D150............................................................3A-184 Figure 3A-118 ABWR Reactor Bldg. Structure-to-Structure, Node 33X RPV/MS Nozzle, 2% Damping, VP5D150.........................................................................................3A-185 Figure 3A-119 ABWR Reactor Bldg. Structure-to-Structure, Node 89 X RCCV Top, 2% Damping, VP5D150.........................................................................................3A-186 Figure 3A-120 ABWR Reactor Bldg. Structure-to-Structure, Node 95 X R/B Top, 2% Damping, VP5D150.........................................................................................3A-187 Table of Contents 33

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-121 ABWR Reactor Bldg. Structure-to-Structure, Node 208 (201 for 2 D) X, Basemat Bottom, 2% Damping, VP3D150............................................................3A-188 Figure 3A-122 ABWR Control Bldg. Structure-to-Structure, Node 181 X C/B Top, 2% Damping, UB1D150 ........................................................................................3A-189 Figure 3A-123 ABWR Control Bldg. Structure-to-Structure, Node 121 X Basemat Top, 2% Damping, UB1D150 ........................................................................................3A-190 Figure 3A-124 ABWR Control Bldg. Structure-to-Structure, Node 181 X C/B Top, 2% Damping, VP3D150.........................................................................................3A-191 Figure 3A-125 ABWR Control Bldg. Structure-to-Structure, Node 121 X Basemat Top, 2% Damping, VP3D150.........................................................................................3A-192 Figure 3A-126 ABWR Control Bldg. Structure-to-Structure, Node 181 X C/B Top, 2% Damping, VP5D150.........................................................................................3A-193 Figure 3A-127 ABWR Control Bldg. Structure-to-Structure, Node 121 X Basemat Bottom, 2% Damping, VP5D150.........................................................................................3A-194 Figure 3A-128 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 17-Horizontal...........3A-195 Figure 3A-129 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 18-Horizontal...........3A-196 Figure 3A-130 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 25-Horizontal...........3A-197 Figure 3A-131 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 27-Horizontal...........3A-198 Figure 3A-132 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 28-Horizontal...........3A-199 Figure 3A-133 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 33-Horizontal...........3A-200 Figure 3A-134 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 36-Horizontal...........3A-201 Figure 3A-135 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 38-Horizontal...........3A-202 Figure 3A-136 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 46-Horizontal...........3A-203 Figure 3A-137 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 50-Horizontal...........3A-204 Figure 3A-138 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 51-Horizontal...........3A-205 Figure 3A-139 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 52-Horizontal...........3A-206 Figure 3A-140 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 60-Horizontal...........3A-207 Figure 3A-141 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 66-Horizontal...........3A-208 Figure 3A-142 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 70-Horizontal...........3A-209 34 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-143 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 71-Horizontal...........3A-210 Figure 3A-144 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 72-Horizontal...........3A-211 Figure 3A-145 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 73-Horizontal...........3A-212 Figure 3A-146 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 78-Horizontal...........3A-213 Figure 3A-147 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 80-Horizontal...........3A-214 Figure 3A-148 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 82-Horizontal...........3A-215 Figure 3A-149 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 84-Horizontal...........3A-216 Figure 3A-150 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 86-Horizontal...........3A-217 Figure 3A-151 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 88-Horizontal...........3A-218 Figure 3A-152 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 89-Horizontal...........3A-219 Figure 3A-153 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 90-Horizontal...........3A-220 Figure 3A-154 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 91-Horizontal...........3A-221 Figure 3A-155 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 92-Horizontal...........3A-222 Figure 3A-156 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 93-Horizontal...........3A-223 Figure 3A-157 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 94-Horizontal...........3A-224 Figure 3A-158 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 95-Horizontal...........3A-225 Figure 3A-159 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 96-Horizontal...........3A-226 Figure 3A-160 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 98-Horizontal...........3A-227 Figure 3A-161 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 100-Horizontal.........3A-228 Figure 3A-162 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 102-Horizontal.........3A-229 Figure 3A-163 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 103-Horizontal.........3A-230 Figure 3A-164 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 104-Horizontal.........3A-231 Figure 3A-165 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 105-Horizontal.........3A-232 Figure 3A-166 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 17-Vertical ...............3A-233 Figure 3A-167 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 18-Vertical ...............3A-234 Figure 3A-168 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 25-Vertical ...............3A-235 Table of Contents 35

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-169 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 27-Vertical ...............3A-236 Figure 3A-170 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 28-Vertical ...............3A-237 Figure 3A-171 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 33-Vertical ...............3A-238 Figure 3A-172 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 36-Vertical ...............3A-239 Figure 3A-173 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 38-Vertical ...............3A-240 Figure 3A-174 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 46-Vertical ...............3A-241 Figure 3A-175 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 50-Vertical ...............3A-242 Figure 3A-176 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 51-Vertical ...............3A-243 Figure 3A-177 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 52-Vertical ...............3A-244 Figure 3A-178 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 60-Vertical ...............3A-245 Figure 3A-179 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 66-Vertical ...............3A-246 Figure 3A-180 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 70-Vertical ...............3A-247 Figure 3A-181 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 71-Vertical ...............3A-248 Figure 3A-182 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 72-Vertical ...............3A-249 Figure 3A-183 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 73-Vertical ...............3A-250 Figure 3A-184 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 78-Vertical ...............3A-251 Figure 3A-185 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 80-Vertical ...............3A-252 Figure 3A-186 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 82-Vertical ...............3A-253 Figure 3A-187 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 84-Vertical ...............3A-254 Figure 3A-188 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 86-Vertical ...............3A-255 Figure 3A-189 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 88-Vertical ...............3A-256 Figure 3A-190 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 89-Vertical ...............3A-257 Figure 3A-191 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 90-Vertical ...............3A-258 Figure 3A-192 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 91-Vertical ...............3A-259 Figure 3A-193 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 92-Vertical ...............3A-260 Figure 3A-194 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 93-Vertical ...............3A-261 36 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-195 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 94-Vertical ...............3A-262 Figure 3A-196 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 95-Vertical ...............3A-263 Figure 3A-197 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 96-Vertical ...............3A-264 Figure 3A-198 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 98-Vertical ...............3A-265 Figure 3A-199 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 100-Vertical .............3A-266 Figure 3A-200 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 102-Vertical .............3A-267 Figure 3A-201 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 103-Vertical .............3A-268 Figure 3A-202 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 104-Vertical .............3A-269 Figure 3A-203 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 105-Vertical .............3A-270 Figure 3A-204 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 107-Vertical .............3A-271 Figure 3A-205 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 108-Vertical .............3A-272 Figure 3A-206 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 109-Vertical .............3A-273 Figure 3A-207 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 110-Vertical .............3A-274 Figure 3A-208 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 111-Vertical .............3A-275 Figure 3A-209 ABWR Reactor Bldg. Broadened (Env of all Cases) Node 112-Vertical .............3A-276 Figure 3A-210 ABWR Control Bldg. Broadened (Env of all Cases) Node 102-Horizontal .........3A-277 Figure 3A-211 ABWR Control Bldg. Broadened (Env of all Cases) Node 103-Horizontal .........3A-278 Figure 3A-212 ABWR Control Bldg. Broadened (Env of all Cases) Node 104-Horizontal .........3A-279 Figure 3A-213 ABWR Control Bldg. Broadened (Env of all Cases) Node 105-Horizontal .........3A-280 Figure 3A-214 ABWR Control Bldg. Broadened (Env of all Cases) Node 106-Horizontal .........3A-281 Figure 3A-215 ABWR Control Bldg. Broadened (Env of all Cases) Node 107-Horizontal .........3A-282 Figure 3A-216 ABWR Control Bldg. Broadened (Env of all Cases) Node 108-Horizontal .........3A-283 Figure 3A-217 ABWR Control Bldg. Broadened (Env of all Cases) Node 102-Vertical .............3A-284 Figure 3A-218 ABWR Control Bldg. Broadened (Env of all Cases) Node 103-Vertical .............3A-285 Figure 3A-219 ABWR Control Bldg. Broadened (Env of all Cases) Node 104-Vertical .............3A-286 Figure 3A-220 ABWR Control Bldg. Broadened (Env of all Cases) Node 105-Vertical .............3A-287 Table of Contents 37

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3A-221 ABWR Control Bldg. Broadened (Env of all Cases) Node 106-Vertical .............3A-288 Figure 3A-222 ABWR Control Bldg. Broadened (Env of all Cases) Node 107-Vertical .............3A-289 Figure 3A-223 ABWR Control Bldg. Broadened (Env of all Cases) Node 108-Vertical .............3A-290 Figure 3A-224 ABWR Control Bldg. Broadened (Env of all Cases) Node 109-Vertical .............3A-291 Figure 3A-225 ABWR Control Bldg. Broadened (Env of all Cases) Node 110-Vertical .............3A-292 Figure 3A-226 ABWR Control Bldg. Broadened (Env of all Cases) Node 111-Vertical .............3A-293 Figure 3A-227 ABWR Control Bldg. Broadened (Env of all Cases) Node 112-Vertical .............3A-294 Figure 3A-228 ABWR Control Bldg. Broadened (Env of all Cases) Node 113-Vertical .............3A-295 Figure 3B-1 ABWR Primary Containment Configuration........................................................... 3B-38 Figure 3B-2 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-39 Figure 3B-3 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-40 Figure 3B-4 Dimensions for P(r) Calculation .............................................................................. 3B-41 Figure 3B-5 Circumferential Distribution .................................................................................... 3B-42 Figure 3B-6 Quencher Bubble Pressure Time History................................................................. 3B-43 Figure 3B-7 Spatial Load Distribution for SRV Loads ................................................................ 3B-44 Figure 3B-8 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-45 Figure 3B-9 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-46 Figure 3B-10 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-47 Figure 3B-11 Pool Boundary Pressure During Pool Swell, Normalized to Bubble Pressure ........ 3B-48 Figure 3B-12 Deleted ..................................................................................................................... 3B-49 Figure 3B-13 Schematic of the Pool Swell Phenomenon............................................................... 3B-50 Figure 3B-14 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-51 38 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3B-15 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-52 Figure 3B-16 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-53 Figure 3B-17 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-54 Figure 3B-18 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-55 Figure 3B-19 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-56 Figure 3B-20 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-57 Figure 3B-21 ABWR CO Source Load Methodology ................................................................... 3B-58 Figure 3B-22 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-59 Figure 3B-23 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-60 Figure 3B-24 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-61 Figure 3B-25 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-62 Figure 3B-26 ABWR Chug Source Load Methodology ................................................................ 3B-63 Figure 3B-27 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-64 Figure 3B-28 Spatial Load Distribution for CH ............................................................................. 3B-65 Figure 3B-29 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-66 Figure 3B-30 Circumferential Pressure Distribution on Access Tunnel Due to CH...................... 3B-67 Figure 3B-31 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-68 Figure 3B-32 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-69 Table of Contents 39

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3B-33 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-70 Figure 3B-34 [Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ...................................................................................................... 3B-71 Figure 3E-1 Schematic Representation of Material J-Integral R and J-T Curves........................ 3E-36 Figure 3E-2 Carbon Steel Test Specimen Orientation Code........................................................ 3E-37 Figure 3E-3 Toughness Anisotropy of ASTM 106 Pipe (152 mm Sch. 80) ................................ 3E-38 Figure 3E-4 Charpy Energies for Pipe Test Material as a Function of Orientation and Temperature ............................................................................................................. 3E-39 Figure 3E-5 Charpy Energies for Plate Test Material as a Function of Orientation and Temperature ............................................................................................................. 3E-40 Figure 3E-6 Comparison of Base Metal, Weld and HAZ Charpy Energies for SA 333 Grade 6 ........................................................................................................ 3E-41 Figure 3E-7 Plot of 288°C True Stress-True Strain Curves for SA 333 Grade 6 Carbon Steel ............................................................................................................. 3E-42 Figure 3E-8 Plot of 288°C True Stress-True Strain Curves for SA 516 Grade 70 Carbon Steel ............................................................................................................. 3E-43 Figure 3E-9 Plot of 117°C True Stress-True Strain Curves for SA 333 Grade 6 Carbon Steel ............................................................................................................. 3E-44 Figure 3E-10 Plot of 177°C True Stress-True Strain Curves for SA 516 Grade 70 Carbon Steel ............................................................................................................. 3E-45 Figure 3E-11 Plot of 288°C Test J-R Curve for Pipe Weld ........................................................... 3E-46 Figure 3E-12 Plot of 288°C Jmod, Tmod Data from Test J-R Curve............................................... 3E-47 Figure 3E-13 Carbon Steel J-T Curve for 216°C ........................................................................... 3E-48 Figure 3E-14 Schematic Illustration of Tearing Stability Evaluation ............................................ 3E-49 Figure 3E-15 A Schematic Representation of Instability Tension and Bending Stresses as a Function of Flaw Strength........................................................................................ 3E-50 Figure 3E-16 SA 333 Grade 6 Stress-Strain Data at 288°C in the Ramberg-Osgood Format....... 3E-51 Figure 3E-17 Carbon Steel Stress-Strain Data at 177°C in the Ramberg-Osgood Format............ 3E-52 Figure 3E-18 Comparison of PICEP Predictions with Measured Leak Rates ............................... 3E-53 Figure 3E-19 Pipe Flow Model ...................................................................................................... 3E-54 40 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3E-20 Mass Flow Rates for Steam/Water Mixtures ........................................................... 3E-55 Figure 3E-21 Friction Factors for Pipes ......................................................................................... 3E-56 Figure 3E-22 Leak Rate as a Function of Crack Length in Main Steam Pipe (Example) ............. 3E-57 Figure 3G-1 Horizontal Beam Model for AP Load ........................................................................3G-8 Figure 3G-2 Nodal Point (R/B Horizontal/Vertical Shell Model)..................................................3G-9 Figure 3G-3 Nodal Point No. (RPV/Internal Vertical Shell Model) ............................................3G-10 Figure 3G-4 Floor Response SpectrumCase: APA1, Node: 33, Horizontal.............................3G-11 Figure 3G-5 Floor Response SpectrumCase: APA1, Node: 81, Horizontal.............................3G-12 Figure 3G-6 Floor Response SpectrumCase: APA1, Node: 85, Horizontal.............................3G-13 Figure 3G-7 Floor Response SpectrumCase: APA2, Node: 33, Horizontal.............................3G-14 Figure 3G-8 Floor Response SpectrumCase: APA2, Node: 81, Horizontal.............................3G-15 Figure 3G-9 Floor Response SpectrumCase: APA2, Node: 85, Horizontal.............................3G-16 Figure 3G-10 Floor Response SpectrumCase: APB1, Node: 33, Horizontal .............................3G-17 Figure 3G-11 Floor Response SpectrumCase: APB1, Node: 81, Horizontal .............................3G-18 Figure 3G-12 Floor Response SpectrumCase: APB1, Node: 85, Horizontal .............................3G-19 Figure 3G-13 Floor Response SpectrumCase: APB2, Node: 33, Horizontal .............................3G-20 Figure 3G-14 Floor Response SpectrumCase: APB2, Node: 81, Horizontal .............................3G-21 Figure 3G-15 Floor Response SpectrumCase: APB2, Node: 85, Horizontal .............................3G-22 Figure 3G-16 Floor Response SpectrumCase: APC1, Node: 33, Horizontal .............................3G-23 Figure 3G-17 Floor Response SpectrumCase: APC1, Node: 81, Horizontal .............................3G-24 Figure 3G-18 Floor Response SpectrumCase: APC1, Node: 85, Horizontal .............................3G-25 Figure 3G-19 Floor Response SpectrumCase: APC2, Node: 33, Horizontal .............................3G-26 Figure 3G-20 Floor Response SpectrumCase: APC2, Node: 81, Horizontal .............................3G-27 Figure 3G-21 Floor Response SpectrumCase: APC2, Node: 85, Horizontal .............................3G-28 Figure 3G-22 Floor Response SpectrumCase: SRVV, Node: 7, Vertical ..................................3G-29 Figure 3G-23 Floor Response SpectrumCase: SRVV, Node: 125, Vertical ..............................3G-30 Table of Contents 41

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3G-24 Floor Response SpectrumCase: SRVV, Node: 148, Vertical ..............................3G-31 Figure 3G-25 Floor Response SpectrumCase: SRVV, Node: 157, Vertical ..............................3G-32 Figure 3G-26 Floor Response SpectrumCase: SRVV, Node: 165, Vertical ..............................3G-33 Figure 3G-27 Floor Response SpectrumCase: SRVH1, Node: 33, Horizontal ..........................3G-34 Figure 3G-28 Floor Response SpectrumCase: SRVH1, Node: 71, Horizontal ..........................3G-35 Figure 3G-29 Floor Response SpectrumCase: SRVH1, Node: 125, Horizontal ........................3G-36 Figure 3G-30 Floor Response SpectrumCase: SRVH1, Node: 157, Horizontal ........................3G-37 Figure 3G-31 Floor Response SpectrumCase: SRVH1, Node: 165, Horizontal ........................3G-38 Figure 3G-32 Floor Response SpectrumCase: SRVH2, Node: 33, Horizontal ..........................3G-39 Figure 3G-33 Floor Response SpectrumCase: SRVH2, Node: 71, Horizontal ..........................3G-40 Figure 3G-34 Floor Response SpectrumCase: SRVH2, Node: 80, Horizontal ..........................3G-41 Figure 3G-35 Floor Response SpectrumCase: SRVH2, Node: 125, Horizontal ........................3G-42 Figure 3G-36 Floor Response SpectrumCase: SRVH2, Node: 157, Horizontal ........................3G-43 Figure 3G-37 Floor Response SpectrumCase: SRVH2, Node: 165, Horizontal ........................3G-44 Figure 3G-38 Floor Response SpectrumCase: SRVH3, Node: 33, Horizontal ..........................3G-45 Figure 3G-39 Floor Response SpectrumCase: SRVH3, Node: 71, Horizontal ..........................3G-46 Figure 3G-40 Floor Response SpectrumCase: SRVH3, Node: 80, Horizontal ..........................3G-47 Figure 3G-41 Floor Response SpectrumCase: SRVH3, Node: 125, Horizontal ........................3G-48 Figure 3G-42 Floor Response SpectrumCase: SRVH3, Node: 157, Horizontal ........................3G-49 Figure 3G-43 Floor Response SpectrumCase: SRVH3, Node: 165, Horizontal ........................3G-50 Figure 3G-44 Floor Response SpectrumCase: HVV, Node: 7, Vertical ....................................3G-51 Figure 3G-45 Floor Response SpectrumCase: HVV, Node: 125, Vertical ................................3G-52 Figure 3G-46 Floor Response SpectrumCase: HVV, Node: 148, Vertical ................................3G-53 Figure 3G-47 Floor Response SpectrumCase: HVV, Node: 157, Vertical ................................3G-54 Figure 3G-48 Floor Response SpectrumCase: HVV, Node: 165, Vertical ................................3G-55 Figure 3G-49 Floor Response SpectrumCase: HVH, Node: 33, Horizontal ..............................3G-56 42 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3G-50 Floor Response SpectrumCase: HVH, Node: 71, Horizontal ..............................3G-57 Figure 3G-51 Floor Response SpectrumCase: HVH, Node: 125, Horizontal ............................3G-58 Figure 3G-52 Floor Response SpectrumCase: HVH, Node: 157, Horizontal ............................3G-59 Figure 3G-53 Floor Response SpectrumCase: HVH, Node: 165, Horizontal ............................3G-60 Figure 3G-54 Floor Response SpectrumCase: CHV1, Node: 7, Vertical ..................................3G-61 Figure 3G-55 Floor Response SpectrumCase: CHV1, Node: 125, Vertical ..............................3G-62 Figure 3G-56 Floor Response SpectrumCase: CHV1, Node: 148, Vertical ..............................3G-63 Figure 3G-57 Floor Response SpectrumCase: CHV1, Node: 157, Vertical ..............................3G-64 Figure 3G-58 Floor Response SpectrumCase: CHV1, Node: 165, Vertical ..............................3G-65 Figure 3G-59 Floor Response SpectrumCase: CHV2, Node: 7, Vertical ..................................3G-66 Figure 3G-60 Floor Response SpectrumCase: CHV2, Node: 125, Vertical ..............................3G-67 Figure 3G-61 Floor Response SpectrumCase: CHV2, Node: 148, Vertical ..............................3G-68 Figure 3G-62 Floor Response SpectrumCase: CHV2, Node: 157, Vertical ..............................3G-69 Figure 3G-63 Floor Response SpectrumCase: CHV2, Node: 165, Vertical ..............................3G-70 Figure 3G-64 Floor Response SpectrumCase: CHV3, Node: 7, Vertical ..................................3G-71 Figure 3G-65 Floor Response SpectrumCase: CHV3, Node: 125, Vertical ..............................3G-72 Figure 3G-66 Floor Response SpectrumCase: CHV3, Node: 148, Vertical ..............................3G-73 Figure 3G-67 Floor Response SpectrumCase: CHV3, Node: 157, Vertical ..............................3G-74 Figure 3G-68 Floor Response SpectrumCase: CHV3, Node: 165, Vertical ..............................3G-75 Figure 3G-69 Floor Response SpectrumCase: CHV4, Node: 7, Vertical ..................................3G-76 Figure 3G-70 Floor Response SpectrumCase: CHV4, Node: 125, Vertical ..............................3G-77 Figure 3G-71 Floor Response SpectrumCase: CHV4, Node: 148, Vertical ..............................3G-78 Figure 3G-72 Floor Response SpectrumCase: CHV4, Node: 157, Vertical ..............................3G-79 Figure 3G-73 Floor Response SpectrumCase: CHV4, Node: 165, Vertical ..............................3G-80 Figure 3G-74 Floor Response SpectrumCase: CHH1, Node: 33, Horizontal ............................3G-81 Figure 3G-75 Floor Response SpectrumCase: CHH1, Node: 71, Horizontal ............................3G-82 Table of Contents 43

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3G-76 Floor Response SpectrumCase: CHH1, Node: 125, Horizontal ..........................3G-83 Figure 3G-77 Floor Response SpectrumCase: CHH1, Node: 157, Horizontal ..........................3G-84 Figure 3G-78 Floor Response SpectrumCase: CHH1, Node: 165, Horizontal ..........................3G-85 Figure 3G-79 Floor Response SpectrumCase: CHH2, Node: 33, Horizontal ............................3G-86 Figure 3G-80 Floor Response SpectrumCase: CHH2, Node: 125, Horizontal ..........................3G-87 Figure 3G-81 Floor Response SpectrumCase: CHH2, Node: 71, Horizontal ............................3G-88 Figure 3G-82 Floor Response SpectrumCase: CHH2, Node: 157, Horizontal ..........................3G-89 Figure 3G-83 Floor Response SpectrumCase: CHH2, Node: 165, Horizontal ..........................3G-90 Figure 3G-84 Floor Response SpectrumCase: CHH3, Node: 33, Horizontal ............................3G-91 Figure 3G-85 Floor Response SpectrumCase: CHH3, Node: 71, Horizontal ............................3G-92 Figure 3G-86 Floor Response SpectrumCase: CHH3, Node: 125, Horizontal ..........................3G-93 Figure 3G-87 Floor Response SpectrumCase: CHH3, Node: 157, Horizontal ..........................3G-94 Figure 3G-88 Floor Response SpectrumCase: CHH3, Node: 165, Horizontal ..........................3G-95 Figure 3G-89 Floor Response SpectrumCase: CHH4, Node: 33, Horizontal ............................3G-96 Figure 3G-90 Floor Response SpectrumCase: CHH4, Node: 71, Horizontal ............................3G-97 Figure 3G-91 Floor Response SpectrumCase: CHH4, Node: 125, Horizontal ..........................3G-98 Figure 3G-92 Floor Response SpectrumCase: CHH4, Node: 157, Horizontal ..........................3G-99 Figure 3G-93 Floor Response SpectrumCase: CHH4, Node: 165, Horizontal ........................3G-100 Figure 3G-94 Floor Response SpectrumCase: COV1, Node: 7, Vertical ................................3G-101 Figure 3G-95 Floor Response SpectrumCase: COV1, Node: 125, Vertical ............................3G-102 Figure 3G-96 Floor Response SpectrumCase: COV1, Node: 148, Vertical ............................3G-103 Figure 3G-97 Floor Response SpectrumCase: COV1, Node: 157, Vertical ............................3G-104 Figure 3G-98 Floor Response SpectrumCase: COV1, Node: 165, Vertical ............................3G-105 Figure 3G-99 Floor Response SpectrumCase: COV2, Node: 7, Vertical ................................3G-106 Figure 3G-100 Floor Response SpectrumCase: COV2, Node: 125, Vertical ............................3G-107 Figure 3G-101 Floor Response SpectrumCase: COV2, Node: 148, Vertical ............................3G-108 44 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3G-102 Floor Response SpectrumCase: COV2, Node: 157, Vertical ............................3G-109 Figure 3G-103 Floor Response SpectrumCase: COV2, Node: 165, Vertical ............................3G-110 Figure 3G-104 Floor Response SpectrumCase: COV3, Node: 7, Vertical ................................3G-111 Figure 3G-105 Floor Response SpectrumCase: COV3, Node: 125, Vertical ............................3G-112 Figure 3G-106 Floor Response SpectrumCase: COV3, Node: 148, Vertical ............................3G-113 Figure 3G-107 Floor Response SpectrumCase: COV3, Node: 157, Vertical ............................3G-114 Figure 3G-108 Floor Response SpectrumCase: COV3, Node: 165, Vertical ............................3G-115 Figure 3H.1-1 (Refer to Figure 1.2-1) ..........................................................................................3H.1-81 Figure 3H.1-2 Containment Structure ASME Code Jurisdictional Boundary..............................3H.1-82 Figure 3H.1-3 Normal Operating Temperature (°C) and Sections Location for Thermal Distribution Analysis ............................................................................................3H.1-83 Figure 3H.1-4 Distribution of Condensation-Oscillation (CO) Pressure .....................................3H.1-84 Figure 3H.1-5 Distribution of Chugging Pressure........................................................................3H.1-85 Figure 3H.1-6 Distribution of Safety-Relief Valve (SRV) Actuation Pressure ...........................3H.1-86 Figure 3H.1-7 Not Used................................................................................................................3H.1-87 Figure 3H.1-8 Design Seismic Shears and Moments for Reactor Building Outer Walls.............3H.1-88 Figure 3H.1-9 Design Seismic Shears and Moments for RCCV..................................................3H.1-89 Figure 3H.1-10 Design Seismic Shears and Moments for RPV Pedestal Reactor Shield Wall .....3H.1-90 Figure 3H.1-11 Design Lateral Soil Pressures for RB Outerwalls .................................................3H.1-91 Figure 3H.1-12 F.E.M. Isometric View of Model Representing Half of Structure........................3H.1-92 Figure 3H.1-13 F.E.M. Location of Elements at Diaphragm Floor Elevation ...............................3H.1-93 Figure 3H.1-14 F.E.M. Isometric View of Liner Plate...................................................................3H.1-94 Figure 3H.1-15 F.E.M. Developed Elevation of RCCV Wall ........................................................3H.1-95 Figure 3H.1-16 Section 0°-180° Soil Springs................................................................................3H.1-96 Figure 3H.1-17 Deformed ShapeDrywell Pressure (6.9 kPa) ....................................................3H.1-97 Figure 3H.1-18 Deformed ShapeWetwell Pressure (6.9 kPa) ....................................................3H.1-98 Table of Contents 45

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3H.1-19 Deformed ShapeThermal Load (6 Hours).........................................................3H.1-99 Figure 3H.1-20 Deformed ShapeSSE 0°-180° .........................................................................3H.1-100 Figure 3H.1-21 Section Considered for Analysis .........................................................................3H.1-101 Figure 3H.1-22 Flow Chart for Structural Analysis and Design ..................................................3H.1-102 Figure 3H.1-24 Not Used..............................................................................................................3H.1-103 Figure 3H.1-25 Not Used..............................................................................................................3H.1-103 Figure 3H.1-26 Not Used..............................................................................................................3H.1-103 Figure 3H.1-27 Not Used..............................................................................................................3H.1-103 Figure 3H.1-28 Configuration of RPV Pedestal...........................................................................3H.1-103 Figure 3H.1-29 Rebar Arrangement of F/P Girder and Slab (1/2) ...............................................3H.1-103 Figure 3H.1-30 Containment Structure Wall Reinforcement .......................................................3H.1-103 Figure 3H.1-31 Containment Structure Opening Reinforcement .................................................3H.1-103 Figure 3H.1-32 Containment Structure Opening Reinforcement .................................................3H.1-103 Figure 3H.1-33 Containment Structure Top Slab Reinforcement ................................................3H.1-103 Figure 3H.1-34 Reactor Building Foundation Reinforcement (Sheet 1)......................................3H.1-103 Figure 3H.1-35 Reactor Building Foundation Reinforcement (Sheet 2)......................................3H.1-103 Figure 3H.1-36 Diaphragm Floor Reinforcement ........................................................................3H.1-103 Figure 3H.1-37 List of Seismic Wall Sections .............................................................................3H.1-103 Figure 3H.2-1 Not Used................................................................................................................3H.2-21 Figure 3H.2-2 Not Used................................................................................................................3H.2-21 Figure 3H.2-3 Not Used................................................................................................................3H.2-21 Figure 3H.2-4 Not Used................................................................................................................3H.2-21 Figure 3H.2-5 Not Used................................................................................................................3H.2-21 Figure 3H.2-6 Not Used................................................................................................................3H.2-21 Figure 3H.2-7 Not Used................................................................................................................3H.2-21 Figure 3H.2-8 Not Used................................................................................................................3H.2-21 46 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3H.2-9 Not Used................................................................................................................3H.2-21 Figure 3H.2-10 Not Used................................................................................................................3H.2-21 Figure 3H.2-11 Dead Load (D).......................................................................................................3H.2-22 Figure 3H.2-12 Live and Snow Loads (L)......................................................................................3H.2-23 Figure 3H.2-13 Live and Snow Loads During SSE (Lo)................................................................3H.2-24 Figure 3H.2-14 At Rest Lateral Soil Pressures on Walls (H and H) .............................................3H.2-25 Figure 3H.2-15 Active and Passive Lateral Soil Pressures on Walls .............................................3H.2-26 Figure 3H.2-16 Wind Loads (W)....................................................................................................3H.2-27 Figure 3H.2-17 Tornado Loads (Wt) ..............................................................................................3H.2-28 Figure 3H.2-18 Accident Pressure Load (Pa) .................................................................................3H.2-29 Figure 3H.2-19 Accident Hydrostatic Load (Fa) ............................................................................3H.2-30 Figure 3H.2-20 Control Building Static Analysis Model ...............................................................3H.2-31 Figure 3H.2-21 Control Building Floor Plan at Elevation -8200 mm ............................................3H.2-32 Figure 3H.2-22 Control Building Framing Plan at Elevation -2150 mm .......................................3H.2-32 Figure 3H.2-23 Control Building Framing Plan at Elevation 3500 mm ........................................3H.2-32 Figure 3H.2-24 Control Building Framing Plan at Elevation 7900 mm ........................................3H.2-32 Figure 3H.2-25 Control Building Framing Plan at Elevation 12300 and 13100 mm.....................3H.2-32 Figure 3H.2-26 Control Building Framing Plan at Elevation 17150 and 18250 mm.....................3H.2-32 Figure 3H.2-27 Control Building Framing Plan at Elevation 22200 and 22750 mm.....................3H.2-32 Figure 3H.2-28 Control Building Section.......................................................................................3H.2-32 Figure 3H.2-29 Control Building Section and Details ...................................................................3H.2-32 Figure 3H.2-30 Control Building Details .......................................................................................3H.2-32 Figure 3H.3-1 Lateral Soil Pressure on Walls ..............................................................................3H.3-29 Figure 3H.3-2 Active and Passive Lateral Soil Pressures on Walls .............................................3H.3-30 Figure 3H.3-3 Stardyne Modal of Radwaste Building (Front Wall Removed for Clarity) ..........3H.3-31 Figure 3H.3-4 Basemat Element Reinforcing Regions ................................................................3H.3-32 Table of Contents 47

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 3 List of Figures (Continued)

Figure 3H.3-5 Wall Elements 0° Wall.....................................................................................3H.3-33 Figure 3H.3-6 Wall Elements 90° Wall...................................................................................3H.3-34 Figure 3H.3-7 Wall Elements 180° Wall.................................................................................3H.3-35 Figure 3H.3-8 Wall Elements 270° Wall.................................................................................3H.3-36 Figure 3H.3-9 Section Locations ..................................................................................................3H.3-37 Figure 3H.3-10 Element Coordinate System ..................................................................................3H.3-38 Figure 3H.3-11 Radwaste Building, Reinforced Concrete Basemat ..............................................3H.3-39 Figure 3H.3-12 Radwaste Building, Structural Steel Framing Plan, Typical Floor.......................3H.3-39 Figure 3H.3-13 Radwaste Building, Structural Steel Framing Plan, Elevation 28000 mm ...........3H.3-39 Figure 3H.3-14 Radwaste Building, Section A-A ..........................................................................3H.3-39 Figure 3H.3-15 Radwaste Building, Exterior Walls Sections ........................................................3H.3-39 Figure 3H.3-16 Radwaste Building, Sections and Details..............................................................3H.3-39 Figure 3H.4-1 Location of Walls Exposed to HELB, El. -8200 mm ............................................3H.4-6 Figure 3H.4-2 Location of Walls Exposed to HELB, El. -5100 mm ............................................3H.4-7 Figure 3H.4-3 Location of Walls Exposed to HELB, El. -1700 mm.............................................3H.4-8 Figure 3H.4-4 Location of Walls Exposed to HELB, El. 1500 mm...............................................3H.4-9 Figure 3H.4-5 Location of Walls Exposed to HELB, El. 4800 mm.............................................3H.4-10 Figure 3H.4-6 Location of Walls Exposed to HELB, El. 8500 mm.............................................3H.4-11 Figure 3H.4-7 Location of Walls Exposed to HELB, El. 12300 mm...........................................3H.4-12 Figure 3H.4-8 Removable Precast Concrete Blocks ....................................................................3H.4-13 Figure 3I-1 Zones in Primary Containment Vessel...................................................................... 3I-18 Figure 3L-1 Simplified Piping Models .......................................................................................... 3L-8 Figure 3L-2 Representation of Pipe With Both Ends Supported With a Longitudinal Break ....... 3L-9 Figure 3L-3 Not Used................................................................................................................... 3L-10 48 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 Table of Contents 4.0 Reactor ...........................................................................................................................................4.1-1 4.1 Summary Description ....................................................................................................................4.1-1 4.1.1 Reactor Pressure Vessel ................................................................................................4.1-1 4.1.2 Reactor Internal Components ........................................................................................4.1-1 4.1.3 Reactivity Control Systems ...........................................................................................4.1-3 4.1.4 Analysis Techniques......................................................................................................4.1-4 4.1.5 References .....................................................................................................................4.1-8 4.2 Fuel System Design .......................................................................................................................4.2-1 4.2.1 Design Bases .................................................................................................................4.2-1 4.2.2 Description and Design Drawings.................................................................................4.2-2 4.2.3 Design Evaluation .........................................................................................................4.2-5 4.2.4 Testing, Inspection, and Surveillance Plans ..................................................................4.2-7 4.2.5 COL License Information..............................................................................................4.2-7 4.2.6 References .....................................................................................................................4.2-7 4.3 Nuclear Design ..............................................................................................................................4.3-1 4.3.1 Design Basis ..................................................................................................................4.3-1 4.3.2 Description ....................................................................................................................4.3-1 4.3.3 Analytical Methods .......................................................................................................4.3-6 4.3.4 Changes .........................................................................................................................4.3-6 4.3.5 COL License Information..............................................................................................4.3-6 4.3.6 References .....................................................................................................................4.3-6 4.4 Thermal-Hydraulic Design............................................................................................................4.4-1 4.4.1 Design Basis ..................................................................................................................4.4-1 4.4.2 Description of Thermal-Hydraulic Design of the Reactor Core ...................................4.4-1 4.4.3 Description of the Thermal-Hydraulic Design of the Reactor Coolant System ...........4.4-7 4.4.4 Loose-Parts Monitoring System ..................................................................................4.4-11 4.4.5 Evaluation....................................................................................................................4.4-14 4.4.6 Testing and Verification ..............................................................................................4.4-16 4.4.7 COL License Information............................................................................................4.4-17 4.4.8 References ...................................................................................................................4.4-17 4.5 Reactor Materials ...........................................................................................................................4.5-1 4.5.1 Control Rod Drive System Structural Materials ...........................................................4.5-1 4.5.2 Reactor Internal Materials .............................................................................................4.5-5 4.5.3 COL License Information..............................................................................................4.5-8 4.6 Functional Design of Reactivity Control System ..........................................................................4.6-1 4.6.1 Information for Control Rod Drive System...................................................................4.6-1 4.6.2 Evaluations of the CRD System ..................................................................................4.6-18 4.6.3 Testing and Verification of the CRDs .........................................................................4.6-23 4.6.4 Information for Combined Performance of Reactivity Control Systems....................4.6-26 4.6.5 Evaluation of Combined Performance ........................................................................4.6-27 4.6.6 COL License Information............................................................................................4.6-27 Table of Contents 49

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 Table of Contents (Continued) 4A Typical Control Rod Patterns and Associated Power Distribution for ABWR .................................................................................................................4A-1 4A.1 Introduction ...................................................................................................................4A-1 4A.2 Power Distribution Strategy ..........................................................................................4A-1 4A.3 Results of Core Simulation Studies...............................................................................4A-1 4A.4 References .....................................................................................................................4A-1 4B Fuel Licensing Acceptance Criteria............................................................................................... 4B-1 4B.1 Introduction ................................................................................................................... 4B-1 4B.2 References ..................................................................................................................... 4B-1 4C Control Rod Licensing Acceptance Criteria .................................................................................. 4C-1 4C.1 Introduction ................................................................................................................... 4C-1 4C.2 General Criteria ............................................................................................................. 4C-1 4C.3 Basis for Acceptance Criteria........................................................................................ 4C-1 4D Reference Fuel Design Compliance with Acceptance Criteria .....................................................4D-1 50 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 List of Tables Table 4.3-1 Definition Of Fuel Design Limits..................................................................................4.3-8 Table 4.3-2 Calculated Core Effective Multiplication and Control System WorthNo Voids, 20°C ...............................................................................................4.3-8 Table 4.4-1 Typical Thermal-Hydraulic Design Characteristics of the Reactor Core...................4.4-19 Table 4.4-2 Void Distribution for Analyzed Core ..........................................................................4.4-20 Table 4.4-3 Flow Quality Distribution for Analyzed Core.............................................................4.4-21 Table 4.4-4 Axial Power Distribution Used to Generate Void and Quality Distributions for Analyzed Core .......................................................................................................4.4-22 Table 4.4-5 Reactor Coolant System Geometric Data....................................................................4.4-23 Table 4A-1 Basic Control Strategy for Typical ABWR...................................................................4A-2 Table 4A-2 Incremental Exposure Steps and Related Figures Numbers..........................................4A-2 Table of Contents 51

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 List of Figures Figure 4.1-1 Core Configuration with Location of Instrumentation...............................................4.1-9 Figure 4.2-1 [Fuel Assembly] .........................................................................................................4.2-8 Figure 4.2-2 [Control Rod Assembly] ............................................................................................4.2-9 Figure 4.3-1 [Core Loading Map Used for Response Analyses]....................................................4.3-9 Figure 4.3-2 [Proprietary information not included in DCD (Refer to SSAR Section 4.3, Amendment 31)] ......................................................................................................4.3-10 Figure 4.4-1 Power-Flow Operating Map Used for System Response Study ..............................4.4-24 Figure 4.4-2 Power-Flow Operating Map Used for System Response Study (9 RIPs Operation) ...................................................................................................4.4-25 Figure 4.4-3 ABWR Stability .......................................................................................................4.4-26 Figure 4.4-4 Stability Controls and Protection Logic...................................................................4.4-27 Figure 4.6-1 Fine Motion Control Rod Drive Schematic .............................................................4.6-28 Figure 4.6-2 Fine Motion Control Rod Drive Unit (Cutaway).....................................................4.6-29 Figure 4.6-3 Continuous Full-in Indicating Device ......................................................................4.6-30 Figure 4.6-4 Control Rod Separation Detection ...........................................................................4.6-31 Figure 4.6-5 Control Rod to Control Rod Drive Coupling ...........................................................4.6-32 Figure 4.6-6 FMCRD Electro-mechanical Brake .........................................................................4.6-33 Figure 4.6-7 Internal Blowout Support Schematic .......................................................................4.6-34 Figure 4.6-8 Control Rod Drive System P&ID (Sheets 1-3) ........................................................4.6-35 Figure 4.6-9 Control Rod Drive System PFD...............................................................................4.6-35 Figure 4.6-10 FMCRD Anti-Rotation Devices...............................................................................4.6-36 Figure 4A-1a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-3 Figure 4A-1b Relative Axial Power at 8.5 GWd/t Cycle Exposure (Haling)...................................4A-4 Figure 4A-1c Relative Axial Exposure at 8.5 GWd/t Cycle Exposure (Haling)..............................4A-4 Figure 4A-1d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-5 52 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 List of Figures (Continued)

Figure 4A-1e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-5 Figure 4A-2a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-6 Figure 4A-2b Relative Axial Power at 9.0 GWd/t Cycle Exposure (Haling)...................................4A-7 Figure 4A-2c Relative Axial Exposure at 9.0 GWd/t Cycle Exposure (Haling)..............................4A-7 Figure 4A-2d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-8 Figure 4A-2e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-8 Figure 4A-3a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ........................................................................................................4A-9 Figure 4A-3b Relative Axial Power at 0.2 GWd/t Cycle Exposure ...............................................4A-10 Figure 4A-3c Relative Axial Exposure at 0.2 GWd/t Cycle Exposure ..........................................4A-10 Figure 4A-3d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-11 Figure 4A-3e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-11 Figure 4A-4a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-12 Figure 4A-4b Relative Axial Power at 1.1 GWd/t Cycle Exposure ...............................................4A-13 Figure 4A-4c Relative Axial Exposure at 1.1 GWd/t Cycle Exposure ..........................................4A-13 Figure 4A-4d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-14 Figure 4A-4e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-14 Figure 4A-5a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-15 Figure 4A-5b Relative Axial Power at 2.2 GWd/t Cycle Exposure ...............................................4A-16 Figure 4A-5c Relative Axial Exposure at 2.2 GWd/t Cycle Exposure ..........................................4A-16 Table of Contents 53

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 List of Figures (Continued)

Figure 4A-5d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-17 Figure 4A-5e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-17 Figure 4A-6a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-18 Figure 4A-6b Relative Axial Power at 3.3 GWd/t Cycle Exposure ...............................................4A-19 Figure 4A-6c Relative Axial Exposure at 3.3 GWd/t Cycle Exposure ..........................................4A-19 Figure 4A-6d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-20 Figure 4A-6e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-20 Figure 4A-7a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-21 Figure 4A-7b Relative Axial Power at 4.4 GWd/t Cycle Exposure ...............................................4A-22 Figure 4A-7c Relative Axial Exposure at 4.4 GWd/t Cycle Exposure ..........................................4A-22 Figure 4A-7d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-23 Figure 4A-7e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-23 Figure 4A-8a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-24 Figure 4A-8b Relative Axial Power at 5.5 GWd/t Cycle Exposure ...............................................4A-25 Figure 4A-8c Relative Axial Exposure at 5.5 GWd/t Cycle Exposure ..........................................4A-25 Figure 4A-8d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-26 Figure 4A-8e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-26 Figure 4A-9a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-27 Figure 4A-9b Relative Axial Power at 6.6 GWd/t Cycle Exposure ...............................................4A-28 54 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 List of Figures (Continued)

Figure 4A-9c Relative Axial Exposure at 6.6 GWd/t Cycle Exposure ..........................................4A-28 Figure 4A-9d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-29 Figure 4A-9e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-29 Figure 4A-10a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-30 Figure 4A-10b Relative Axial Power at 7.7 GWd/t Cycle Exposure ...............................................4A-31 Figure 4A-10c Relative Axial Exposure at 7.7 GWd/t Cycle Exposure ..........................................4A-31 Figure 4A-10d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-32 Figure 4A-10e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-32 Figure 4A-11a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-33 Figure 4A-11b Relative Axial Power at 8.0 GWd/t Cycle Exposure ...............................................4A-34 Figure 4A-11c Relative Axial Exposure at 8.0 GWd/t Cycle Exposure ..........................................4A-34 Figure 4A-11d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-35 Figure 4A-11e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-35 Figure 4A-12a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-36 Figure 4A-12b Relative Axial Power at 8.4 GWd/t Cycle Exposure ...............................................4A-37 Figure 4A-12c Relative Axial Exposure at 8.4 GWd/t Cycle Exposure ..........................................4A-37 Figure 4A-12d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-38 Figure 4A-12e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-38 Figure 4A-13a [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-39 Table of Contents 55

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 4 List of Figures (Continued)

Figure 4A-13b Relative Axial Power at 9.0 GWd/t Cycle Exposure ...............................................4A-40 Figure 4A-13c Relative Axial Exposure at 9.0 GWd/t Exposure.....................................................4A-40 Figure 4A-13d [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-41 Figure 4A-13e [Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] ......................................................................................................4A-41 Figure 4A-14 Minimum Critical Power Ratio (MCPR) as a Function of Cycle Exposure ............4A-42 56 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 5 Table of Contents 5.0 Reactor Coolant System and Connected Systems .........................................................................5.1-1 5.1 Summary Description ....................................................................................................................5.1-1 5.1.1 Schematic Flow Diagrams.............................................................................................5.1-3 5.1.2 Piping and Instrumentation Diagrams ...........................................................................5.1-3 5.1.3 Elevation Drawings .......................................................................................................5.1-3 5.2 Integrity of Reactor Coolant Pressure Boundary ...........................................................................5.2-1 5.2.1 Compliance with Codes and Code Cases ......................................................................5.2-1 5.2.2 Overpressure Protection ................................................................................................5.2-1 5.2.3 Reactor Coolant Pressure Boundary Materials............................................................5.2-10 5.2.4 Preservice and Inservice Inspection and Testing of Reactor Coolant Pressure Boundary .....................................................................................................................5.2-23 5.2.5 Reactor Coolant Pressure Boundary and Core Cooling Systems Leakage Detection......................................................................................................................5.2-31 5.2.6 COL License Information............................................................................................5.2-46 5.2.7 References ...................................................................................................................5.2-47 5.3 Reactor Vessel ...............................................................................................................................5.3-1 5.3.1 Reactor Vessel Materials...............................................................................................5.3-1 5.3.2 Pressure/Temperature Limits.........................................................................................5.3-9 5.3.3 Reactor Vessel Integrity ..............................................................................................5.3-11 5.3.4 COL License Information............................................................................................5.3-18 5.3.5 References ...................................................................................................................5.3-19 5.4 Component and Subsystem Design ...............................................................................................5.4-1 5.4.1 Reactor Recirculation System .......................................................................................5.4-1 5.4.2 Steam Generators (PWR) ..............................................................................................5.4-8 5.4.3 Reactor Coolant Piping..................................................................................................5.4-8 5.4.4 Main Steamline Flow Restrictors ..................................................................................5.4-9 5.4.5 Main Steamline Isolation System................................................................................5.4-11 5.4.6 Reactor Core Isolation Cooling System ......................................................................5.4-16 5.4.7 Residual Heat Removal System ..................................................................................5.4-26 5.4.8 Reactor Water Cleanup System...................................................................................5.4-45 5.4.9 Main Steamlines and Feedwater Piping ......................................................................5.4-49 5.4.10 Pressurizer ...................................................................................................................5.4-51 5.4.11 Pressurizer Relief Discharge System...........................................................................5.4-51 5.4.12 Valves ..........................................................................................................................5.4-51 5.4.13 Safety/Relief Valves....................................................................................................5.4-53 5.4.14 Component Supports ...................................................................................................5.4-53 5.4.15 COL License Information............................................................................................5.4-54 5.4.16 References ...................................................................................................................5.4-55 5A Method Of Compliance For Regulatory Guide 1.150 ...................................................................5A-1 5A.1 Introduction ...................................................................................................................5A-1 5A.2 Discussion......................................................................................................................5A-1 5A.3 Inspection System Performance Checks .......................................................................5A-1 5A.4 Calibration .....................................................................................................................5A-3 Table of Contents 57

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 5 Table of Contents (Continued) 5A.5 Examination...................................................................................................................5A-4 5A.6 Beam Profile..................................................................................................................5A-4 5A.7 Scanning Weld Metal Interface .....................................................................................5A-5 5A.8 Recording and Sizing ....................................................................................................5A-5 5A.9 Reporting Of Results .....................................................................................................5A-6 5A.10 Conclusion.....................................................................................................................5A-6 5B RHR Injection Flow And Heat Capacity Analysis Outlines.......................................................... 5B-1 5B.1 Introduction ................................................................................................................... 5B-1 5B.2 Outline For Injection Flow Confirmation...................................................................... 5B-1 5B.3 Outline For Heat Exchanger Confirmation ................................................................... 5B-3 58 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 5 List of Tables Table 5.2-1 Reactor Coolant Pressure Boundary Components Applicable Code Cases ................5.2-49 Table 5.2-1a Reactor Coolant Pressure Boundary Components Applicable Code Cases ................5.2-50 Table 5.2-2 Systems Which May Initiate During Overpressure Event ..........................................5.2-52 Table 5.2-3 Nuclear System Safety/Relief Valve Setpoints Set Pressures and Capacities ............5.2-52 Table 5.2-4 Reactor Coolant Pressure Boundary Materials............................................................5.2-53 Table 5.2-5 BWR Water Chemistry................................................................................................5.2-56 Table 5.2-6 LDS Control and Isolation Function vs. Monitored Process Variables ......................5.2-57 Table 5.2-7 Leakage Sources vs. Monitored Trip Alarms..............................................................5.2-58 Table 5.2-8 Examination Categories...............................................................................................5.2-59 Table 5.2-9 Ultrasonic Examination of RPV: Reg. Guide 1.150 Compliance ...............................5.2-72 Table 5.3-1 Comparison of 40 Year Fluences ................................................................................5.3-20 Table 5.3-2 Key Dimensions of RPV System Components and Acceptable Variations................5.3-20 Table 5.4-1 Reactor Recirculation System Design Characteristics ................................................5.4-56 Table 5.4-1a Net Positive Suction Head (NPSH) Available to RCIC Pumps ..................................5.4-57 Table 5.4-2 Design Parameters for RCIC System Components .....................................................5.4-58 Table 5.4-3 RHR Pump/Valve Logic..............................................................................................5.4-62 Table 5.4-4 RHR Heat Exchanger Design and Performance Data .................................................5.4-64 Table 5.4-5 Component and Subsystem Relief Valves ..................................................................5.4-65 Table 5.4-6 Reactor Water Cleanup System Equipment Design Data ...........................................5.4-66 Table of Contents 59

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 5 List of Figures Figure 5.1-1 Rated Operating Conditions of the ABWR................................................................5.1-4 Figure 5.1-2 Coolant Volumes of the ABWR ................................................................................5.1-5 Figure 5.1-3 Nuclear Boiler System P&ID (Sheets 1-11)..............................................................5.1-6 Figure 5.2-1 Safety-Action Valve Lift Characteristics .................................................................5.2-73 Figure 5.2-2 MSIV Closure with Flux Scram and Installed Safety/Relief Valve Capacity .........5.2-74 Figure 5.2-3 Safety/Relief Valve Schematic Elevation ................................................................5.2-75 Figure 5.2-4 Safety /Relief Valve and Steamline Schematic........................................................5.2-76 Figure 5.2-5 Not Used...................................................................................................................5.2-77 Figure 5.2-6 Not Used...................................................................................................................5.2-77 Figure 5.2-7a RPV Examination Areas ..........................................................................................5.2-78 Figure 5.2-7b Typical Piping System Isometric (Feedwater Line from RPV to Valve F005A) ....5.2-79 Figure 5.2-8 Leak Detection and Isolation System IED (Sheets 1-10) ........................................5.2-80 Figure 5.3-1 Minimum Temperature Required Versus Reactor Pressure.....................................5.3-21 Figure 5.3-2a Reactor Pressure Vessel System Key Features ........................................................5.3-22 Figure 5.3-2b Pump Penetration and Shroud Leg Arrangement.....................................................5.3-23 Figure 5.3-3 Fast Neutron Flux as Function of Water Thickness.................................................5.3-24 Figure 5.4-1 Reactor Internal Pump Cross Section ......................................................................5.4-67 Figure 5.4-2 ABWR Recirculation Flow Path ..............................................................................5.4-68 Figure 5.4-3 Reactor Internal Pump Performance Characteristics ...............................................5.4-69 Figure 5.4-4 Reactor Recirculation System P&ID (Sheets 1-2) ..................................................5.4-70 Figure 5.4-5 Reactor Recirculation System PFD..........................................................................5.4-70 Figure 5.4-6 Main Steamline Flow Restrictor ..............................................................................5.4-71 Figure 5.4-7 Main Steamline Isolation Valve...............................................................................5.4-72 Figure 5.4-8 Reactor Core Isolation Cooling System P&ID (Sheets 1-3) ...................................5.4-73 Figure 5.4-9 Reactor Core Isolation Cooling System PFD (Sheets 1-2) .....................................5.4-73 Figure 5.4-10 Residual Heat Removal System P&ID (Sheets 1-7) ...............................................5.4-73 60 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 5 List of Figures (Continued)

Figure 5.4-11 Residual Heat Removal System PFD (Sheets 1-2)..................................................5.4-73 Figure 5.4-12 Reactor Water Cleanup System P&ID (Sheets 1-4)................................................5.4-73 Figure 5.4-13 Reactor Water Cleanup System PFD (Sheets 1-2) ..................................................5.4-73 Figure 5.4-14 Reactor Water Cleanup System IBD (Sheets 1-11) ................................................5.4-73 Figure 5A-1 GERIS-2000 Depth Sizing Results ............................................................................5A-7 Figure 5B-1 Injection Flow ............................................................................................................ 5B-5 Table of Contents 61

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 Table of Contents 6.0 Engineered Safety Features ...........................................................................................................6.0-1 6.0 General...........................................................................................................................................6.0-1 6.1 Engineered Safety Feature Materials .............................................................................................6.1-1 6.1.1 Metallic Materials..........................................................................................................6.1-1 6.1.2 Organic Materials ..........................................................................................................6.1-3 6.1.3 COL License Information..............................................................................................6.1-4 6.2 Containment Systems ....................................................................................................................6.2-1 6.2.1 Containment Functional Design ....................................................................................6.2-1 6.2.2 Containment Heat Removal System............................................................................6.2-37 6.2.3 Secondary Containment Functional Design ................................................................6.2-41 6.2.4 Containment Isolation System.....................................................................................6.2-53 6.2.5 Combustible Gas Control in Containment ..................................................................6.2-66 6.2.6 Containment Leakage Testing.....................................................................................6.2-86 6.2.7 COL License Information............................................................................................6.2-93 6.2.8 References ...................................................................................................................6.2-94 6.3 Emergency Core Cooling Systems ................................................................................................6.3-1 6.3.1 Design Bases and Summary Description ......................................................................6.3-1 6.3.2 System Design ...............................................................................................................6.3-5 6.3.3 ECCS Performance Evaluation ...................................................................................6.3-13 6.3.4 Tests and Inspections...................................................................................................6.3-20 6.3.5 Instrumentation Requirements.....................................................................................6.3-23 6.3.6 COL License Information............................................................................................6.3-23 6.3.7 Reference.....................................................................................................................6.3-24 6.4 Habitability Systems ......................................................................................................................6.4-1 6.4.1 Design Basis ..................................................................................................................6.4-2 6.4.2 System Design ...............................................................................................................6.4-4 6.4.3 System Operation Procedures........................................................................................6.4-7 6.4.4 Design Evaluations........................................................................................................6.4-8 6.4.5 Testing and Inspection...................................................................................................6.4-9 6.4.6 Instrumentation Requirements.....................................................................................6.4-10 6.4.7 COL License Information............................................................................................6.4-10 6.5 Fission Products Removal and Control Systems ...........................................................................6.5-1 6.5.1 Engineered Safety Features Filter Systems ...................................................................6.5-1 6.5.2 Containment Spray Systems........................................................................................6.5-11 6.5.3 Fission Product Control Systems.................................................................................6.5-11 6.5.4 Not Used......................................................................................................................6.5-12 6.5.5 COL License Information............................................................................................6.5-12 6.5.6 References ...................................................................................................................6.5-12 6.6 Preservice and Inservice Inspection and Testing of Class 2 and 3 Components and Piping.........6.6-1 6.6.1 Class 2 and 3 System Boundaries..................................................................................6.6-1 6.6.2 Accessibility ..................................................................................................................6.6-3 6.6.3 Examination Categories and Methods...........................................................................6.6-5 62 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 Table of Contents (Continued) 6.6.4 Inspection Intervals .......................................................................................................6.6-7 6.6.5 Evaluation of Examination Results ...............................................................................6.6-7 6.6.6 System Pressure Tests ...................................................................................................6.6-7 6.6.7 Augmented Inservice Inspection ...................................................................................6.6-8 6.6.8 Code Exemptions...........................................................................................................6.6-9 6.6.9 COL License Information..............................................................................................6.6-9 6.7 High Pressure Nitrogen Gas Supply System .................................................................................6.7-1 6.7.1 Functions .......................................................................................................................6.7-1 6.7.2 System Description........................................................................................................6.7-1 6.7.3 System Evaluation .........................................................................................................6.7-2 6.7.4 Inspection and Testing Requirements ...........................................................................6.7-3 6.7.5 Instrumentation Requirements.......................................................................................6.7-3 6.7.6 Analysis and Testing of ADS Accumulator Capacity...................................................6.7-3 6A Regulatory Guide 1.52, Section C, Compliance Assessment ........................................................6A-1 6B SRP 6.5.1, Table 6.5.1-1 Compliance Assessment........................................................................ 6B-1 6C Containment Debris Protection for ECCS Strainers...................................................................... 6C-1 6C.1 Background.................................................................................................................... 6C-1 6C.2 ABWR Mitigating Features........................................................................................... 6C-1 6C.3 Design Considerations................................................................................................... 6C-3 6C.4 Discussion Summary ..................................................................................................... 6C-5 6C.5 Strainer Sizing Analysis Summary................................................................................ 6C-6 6C.6 COL License Information.............................................................................................. 6C-7 6C.7 References ..................................................................................................................... 6C-7 6D HPCF Analysis Outlines................................................................................................................6D-1 6D.1 Introduction ...................................................................................................................6D-1 6D.2 Outline for Injection Flow Confirmation ......................................................................6D-1 6E Additional Bypass Leakage Considerations .................................................................................. 6E-1 6E.1 Bypass Mechanism through ACS Interconnection........................................................ 6E-1 6E.2 Other Bypass Pathways ................................................................................................. 6E-1 6E.3 Effect on Existing Bypass Analyses.............................................................................. 6E-1 6E.4 Conclusion..................................................................................................................... 6E-3 Table of Contents 63

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Tables Table 6.1-1 Engineered Safety Features Component Materials .......................................................6.1-5 Table 6.2-1 Containment Parameters..............................................................................................6.2-95 Table 6.2-2 Containment Design Parameters .................................................................................6.2-96 Table 6.2-2a Engineered Safety Systems Information for Containment Response Analyses..........6.2-97 Table 6.2-2b Net Positive Suction Head (NPSH) Available to RHR Pumps ...................................6.2-98 Table 6.2-2c Net Positive Suction Head (NPSH) Available to HPCF Pumps .................................6.2-99 Table 6.2-2d Secondary Containment Design and Performance Data ...........................................6.2-100 Table 6.2-3 Subcompartment Nodal Description .........................................................................6.2-103 Table 6.2-4 Subcompartment Vent Path Description ...................................................................6.2-105 Table 6.2-4a Flow Loss Factor .......................................................................................................6.2-107 Table 6.2-4b Mass and Energy Release Rate..................................................................................6.2-109 Table 6.2-5 Reactor Coolant Pressure Boundary (RCPB) Influent Lines Penetrating Drywell ......................................................................................................................6.2-114 Table 6.2-6 Reactor Coolant Pressure Boundary (RCPB) Effluent Lines Penetrating Drywell ......................................................................................................................6.2-114 Table 6.2-7 Containment Isolation Valve Information.................................................................6.2-115 Table 6.2-8 Primary Containment Penetration List ......................................................................6.2-163 Table 6.2-9 Secondary Containment Penetration List ..................................................................6.2-173 Table 6.2-10 Potential Bypass Leakage Paths ................................................................................6.2-175 Table 6.3-1 Significant Input Variables Used in the Loss-of-Coolant Accident Analysis.............6.3-25 Table 6.3-2 Operational Sequence of Emergency Core Cooling System Maximum Core Flooder Line Break......................................................................................................6.3-27 Table 6.3-3 Single Failure Evaluation ............................................................................................6.3-28 Table 6.3-4 Summary of Results of LOCA Analysis including Renewal PCT with 10 CFR § 50.46 Adjustments ..............................................................................6.3-29 Table 6.3-5 Key to Figures .............................................................................................................6.3-30 Table 6.3-6 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)]..........................................................................................................6.3-31 64 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Tables (Continued)

Table 6.3-7 MAPLHGR Versus Exposure .....................................................................................6.3-32 Table 6.3-8 Design Parameters for HPCF System Components ....................................................6.3-33 Table 6.3-9 Design Parameters for RHR System Components ......................................................6.3-35 Table 6.3-10 Single Failure Evaluation With One HPCF Subsystem Out of Service......................6.3-38 Table 6.3-11 Single Failure Evaluation With One RHR/LPFL Subsystem Out of Service .............6.3-39 Table 6.3-12 Single Failure Evaluation With ECCS Division A Out of Service .............................6.3-40 Table 6.3-13 Single Failure Evaluation With ECCS Division B Out of Service .............................6.3-41 Table 6.3-14 Single Failure Evaluation With ECCS Division C Out of Service .............................6.3-42 Table 6.3-15 Single Failure Evaluation With Two ADS Valves Out of Service .............................6.3-43 Table 6.4-1 Identification of Failure/Effect in the Control Room Habitability Area HVAC System .........................................................................................................................6.4-11 Table 6.4-2 Control Room Habitability Area HVAC System Failure Analysis.............................6.4-12 Table 6.5-1 Summary of Major Standby Gas Treatment System Components..............................6.5-13 Table 6.5-2 Source Terms Used for SGTS Charcoal Adsorber Design .........................................6.5-15 Table 6.6-1 Examination Categories and Methods.........................................................................6.6-10 Table 6.7-1 Nitrogen Gas Demand ...................................................................................................6.7-5 Table 6C-1 ECCS Strainer Debris Load........................................................................................... 6C-8 Table of Contents 65

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures Figure 6.2-1 A Break in a Feedwater Line .................................................................................6.2-183 Figure 6.2-2 Feedwater Line BreakRPV Side Break Area .....................................................6.2-184 Figure 6.2-3 Feedwater Line Break FlowFeedwater System Side of Break...........................6.2-185 Figure 6.2-4 Feedwater Line Break Flow EnthalpyFeedwater System Side of Break ...........6.2-186 Figure 6.2-5 Lower Drywell Air Transfer Percentage for Model Assumption Versus Actual Case ............................................................................................................6.2-187 Figure 6.2-6 Pressure Response of the Primary Containment for Feedwater Line Break ..........6.2-188 Figure 6.2-7 Temperature Response of the Primary Containment for Feedwater Line Break ......................................................................................................................6.2-189 Figure 6.2-8 Temperature Time History After a Feedwater Line Break ....................................6.2-190 Figure 6.2-8a Pressure Time History After a Feedwater Line Break ...........................................6.2-191 Figure 6.2-9 ABWR Main Steamlines with a Break ..................................................................6.2-192 Figure 6.2-10 MSLB Area as a Function of Time ........................................................................6.2-193 Figure 6.2-11 Feedwater Specific Enthalpy as a Function of Integrated Feedwater Flow Mass .......................................................................................................................6.2-194 Figure 6.2-12 Pressure Time History for MSLB with Two-Phase Blowdown Starting at 2 Seconds............................................................................................................6.2-195 Figure 6.2-13 Temperature Time History for MSLB with Two-Phase Blowdown Starting at two Seconds........................................................................................................6.2-196 Figure 6.2-14 Pressure Time History for Long-term MSLB ........................................................6.2-197 Figure 6.2-15 Temperature Time History for Long-term MSLB .................................................6.2-198 Figure 6.2-16 General Pressure Trends in the Containment During a Post-LOCA Depressurization Transient.....................................................................................6.2-199 Figure 6.2-17 Differential Pressures in Wetwell and Drywell Relative to Reactor Building for Vacuum Breaker Size of 0.82 m2 .....................................................................6.2-200 Figure 6.2-18 Differential Pressures in Wetwell and Drywell Relative to Reactor Building with Wetwell Spray for Vacuum Breaker Size of 82 m2 .......................................6.2-201 Figure 6.2-19 Temperature and Pressure Time Histories in the Containment During Stuck Open Relief Valve Transient..................................................................................6.2-202 Figure 6.2-20 Not Used.................................................................................................................6.2-203 66 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.2-21 Not Used.................................................................................................................6.2-204 Figure 6.2-22 Break Flow Rate and Specific Enthalpy for the Feedwater Line Break Flow Coming from the Feedwater System Side..............................................................6.2-205 Figure 6.2-23 Break Flow Rate and Specific Enthalpy for the Feedwater Line Break Flow Coming from the RPV Side ...................................................................................6.2-206 Figure 6.2-24 Break Flow Rate and Specific Enthalpy for the Main Steamline Break with Two-Phase Blowdown Starting When the Collapsed Water Level Reaches the Steam Nozzle....................................................................................................6.2-207 Figure 6.2-25 Not Used.................................................................................................................6.2-208 Figure 6.2-26 ABWR Containment Boundary Nomenclature......................................................6.2-209 Figure 6.2-27 Three Basic Types of Leakage Paths .....................................................................6.2-210 Figure 6.2-28 Containment Boundaries in the Reactor BuildingPlan Section A-A (0°-180°) ................................................................................................................6.2-211 Figure 6.2-29 Containment Boundaries in the Reactor BuildingPlan Section B-B (90°-270°) ..............................................................................................................6.2-211 Figure 6.2-30 Containment Boundaries in the Reactor BuildingPlan at Elevation -8200 mm ..............................................................................................6.2-211 Figure 6.2-31 Containment Boundaries in the Reactor BuildingPlan at Elevation -1700 mm ..............................................................................................6.2-211 Figure 6.2-32 Containment Boundaries in the Reactor BuildingPlan at Elevation 4800/8500 mm .......................................................................................6.2-211 Figure 6.2-33 Containment Boundaries in the Reactor BuildingPlan at Elevation 12300 mm ..............................................................................................6.2-211 Figure 6.2-34 Containment Boundaries in the Reactor BuildingPlan at Elevation 18100 mm ..............................................................................................6.2-211 Figure 6.2-35 Containment Boundaries in the Reactor BuildingPlan at Elevation 23500 mm ..............................................................................................6.2-211 Figure 6.2-36 Containment Boundaries in the Reactor BuildingPlan at Elevation 31700 mm ..............................................................................................6.2-211 Figure 6.2-37a Secondary Containment Schematic Flow Diagram (ECCS/RCIC) .......................6.2-212 Figure 6.2-37b Secondary Containment Schematic Flow Diagram (Main Steam/Feedwater) ......6.2-213 Figure 6.2-37c Secondary Containment Schematic Flow Diagram (CUW) ..................................6.2-214 Table of Contents 67

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.2-37d Secondary Containment Schematic Flow Diagram (CUW) (Continued) ..............6.2-215 Figure 6.2-37e Secondary Containment Schematic Flow Diagram (CUW) (Continued) ..............6.2-216 Figure 6.2-37f Secondary Containment Schematic Flow Diagram (CUW) (Continued) ..............6.2-217 Figure 6.2-37g Secondary Containment Schematic Flow Diagram (CUW) (Continued) ..............6.2-218 Figure 6.2-37h Secondary Containment Flow Schematic Diagram (CUW) (Continued) ..............6.2-219 Figure 6.2-37i Pressure Transient Due to High Energy Line Break in RCIC Compartments Isolated Cases.........................................................................................................6.2-220 Figure 6.2-37j Temperature Transient Response Due to High Energy Line Break in RCIC Compartments ........................................................................................................6.2-221 Figure 6.2-37k Pressure Transient Due to High Energy Line Breaks in CUW Compartments .....6.2-222 Figure 6.2-37l Temperature Transient Due to High Energy Line Breaks in CUW Compartments ........................................................................................................6.2-223 Figure 6.2-37m Pressure Transient Due to High Energy Line Break in Steam Tunnel Compartments ........................................................................................................6.2-224 Figure 6.2-37n Temperature Transient Due to High Energy Line Break in Steam Tunnel Compartments ........................................................................................................6.2-225 Figure 6.2-37o Compartment Temperature Response Due to High Energy Line Break in CUW Rooms ..........................................................................................................6.2-226 Figure 6.2-37p Compartment Transient Temperature Response Due to High Energy Line Break in CUW-Unisolated Case ............................................................................6.2-227 Figure 6.2-38 Group Classification and Containment Isolation Diagram (Sheets 1-2) ...............6.2-228 Figure 6.2-39 Atmospheric Control System P&ID (Sheets 1-3) .................................................6.2-228 Figure 6.2-40 Flammability Control System P&ID (Sheets 1-2).................................................6.2-228 Figure 6.2-41 Hydrogen and Oxygen Concentrations in Containment After Design Basis LOCA ...........................................................................................................6.2-229 Figure 6.2-42 Allowable Steam Bypass Leakage Capacity..........................................................6.2-230 Figure 6.2-43 Typical Pressure Fluctuation Due to CO (See Figure 3B-22)................................6.2-231 Figure 6.2-44 Typical Pressure Fluctuation Due To CH (See Figure 3B-24) ..............................6.2-232 Figure 6.2-45 Quencher Bubble Pressure Time History...............................................................6.2-233 Figure 6.3-1 High Pressure Core Flooder System PFD (Sheets 1-2)...........................................6.3-44 68 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.3-2 Not Used (See Figure 5.4-9) ....................................................................................6.3-44 Figure 6.3-3 Not Used (See Figure 5.4-11) ..................................................................................6.3-44 Figure 6.3-4 Pressure Versus High Pressure Core Flooder Flow (Per System) Used in LOCA Analysis....................................................................................................................6.3-45 Figure 6.3-5 Pressure Versus Reactor Core Isolation Cooling Flow Used in LOCA Analysis....................................................................................................................6.3-46 Figure 6.3-6 Pressure Versus Low Pressure Flooder Flow (Per System) Used in LOCA Analysis....................................................................................................................6.3-47 Figure 6.3-7 High Pressure Core Flooder System P&ID (Sheets 1-2).........................................6.3-48 Figure 6.3-8 Not Used (See Figure 5.4-8) ....................................................................................6.3-48 Figure 6.3-9 Not Used (See Figure 5.4-10) ..................................................................................6.3-48 Figure 6.3-10 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-49 Figure 6.3-11 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-50 Figure 6.3-12 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-51 Figure 6.3-13 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-51 Figure 6.3-14 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-52 Figure 6.3-15 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-52 Figure 6.3-16 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-53 Figure 6.3-17 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-53 Figure 6.3-18 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-54 Figure 6.3-19 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-54 Table of Contents 69

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.3-20 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-55 Figure 6.3-21 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-55 Figure 6.3-22 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-56 Figure 6.3-23 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-56 Figure 6.3-24 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-57 Figure 6.3-25 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-57 Figure 6.3-26 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-58 Figure 6.3-27 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-58 Figure 6.3-28 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-59 Figure 6.3-29 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-59 Figure 6.3-30 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-60 Figure 6.3-31 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-60 Figure 6.3-32 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-61 Figure 6.3-33 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-61 Figure 6.3-34 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-62 Figure 6.3-35 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-62 Figure 6.3-36 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-63 70 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.3-37 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-63 Figure 6.3-38 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-64 Figure 6.3-39 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-64 Figure 6.3-40 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-65 Figure 6.3-41 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-65 Figure 6.3-42 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-66 Figure 6.3-43 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-66 Figure 6.3-44 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-67 Figure 6.3-45 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-67 Figure 6.3-46 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-68 Figure 6.3-47 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-68 Figure 6.3-48 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-69 Figure 6.3-49 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-69 Figure 6.3-50 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-70 Figure 6.3-51 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-70 Figure 6.3-52 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-71 Figure 6.3-53 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-71 Table of Contents 71

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.3-54 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-72 Figure 6.3-55 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-72 Figure 6.3-56 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-73 Figure 6.3-57 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-73 Figure 6.3-58 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-74 Figure 6.3-59 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-74 Figure 6.3-60 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-75 Figure 6.3-61 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-75 Figure 6.3-62 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-76 Figure 6.3-63 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-76 Figure 6.3-64 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-77 Figure 6.3-65 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-77 Figure 6.3-66 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-78 Figure 6.3-67 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-78 Figure 6.3-68 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-79 Figure 6.3-69 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-79 Figure 6.3-70 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-80 72 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 6 List of Figures (Continued)

Figure 6.3-71 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-80 Figure 6.3-72 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-81 Figure 6.3-73 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-81 Figure 6.3-74 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-82 Figure 6.3-75 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-82 Figure 6.3-76 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-83 Figure 6.3-77 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-84 Figure 6.3-78 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-85 Figure 6.3-79 [Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ......................................................................................................6.3-86 Figure 6.4-1 Plant Layout .............................................................................................................6.4-13 Figure 6.5-1 Standby Gas Treatment System P&ID (Sheets 1-3)................................................6.5-16 Figure 6.5-2 Secondary Containment Pressure Transient After Design Basis LOCA .................6.5-17 Figure 6.7-1 High Pressure Nitrogen Gas Supply System P&ID ...................................................6.7-6 Figure 6D-1 Injection Flow ............................................................................................................6D-3 Table of Contents 73

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 7 Table of Contents 7.0 Instrumentation and Control Systems............................................................................................7.1-1 7.1 Introduction....................................................................................................................................7.1-1 7.1.1 Identification of Safety-Related Systems ......................................................................7.1-1 7.1.2 Identification of Safety Criteria.....................................................................................7.1-5 7.2 Reactor Protection (Trip) System (RPS)Instrumentation and Controls.....................................7.2-1 7.2.1 Description ....................................................................................................................7.2-1 7.2.2 Conformance Analysis ................................................................................................7.2-22 7.3 Engineered Safety Feature Systems, Instrumentation and Control ...............................................7.3-1 7.3.1 Description ....................................................................................................................7.3-1 7.3.2 Analysis .......................................................................................................................7.3-64 7.3.3 COL License Information............................................................................................7.3-91 7.3.4 References ...................................................................................................................7.3-91 7.4 Systems Required for Safe Shutdown ...........................................................................................7.4-1 7.4.1 Description ....................................................................................................................7.4-1 7.4.2 Analysis .......................................................................................................................7.4-17 7.4.3 References ...................................................................................................................7.4-27 7.5 Information Systems Important to Safety ......................................................................................7.5-1 7.5.1 Systems Descriptions.....................................................................................................7.5-1 7.5.2 Systems Analysis...........................................................................................................7.5-4 7.5.3 COL License Information............................................................................................7.5-13 7.5.4 References ...................................................................................................................7.5-14 7.6 All Other Instrumentation Systems Required for Safety ...............................................................7.6-1 7.6.1 Description ....................................................................................................................7.6-1 7.6.2 Analysis .......................................................................................................................7.6-20 7.6.3 COL License Information............................................................................................7.6-32 7.7 Control Systems Not Required for Safety .....................................................................................7.7-1 7.7.1 Description ....................................................................................................................7.7-1 7.7.2 Analysis ......................................................................................................................7.7-74 7.8 COL License Information ..............................................................................................................7.8-1 7.8.1 Effects of Station Blackout on the HVAC ....................................................................7.8-1 7.8.2 Electrostatic Discharge on Exposed Equipment Components ......................................7.8-1 7.8.3 Localized High Heat Spots in Semiconductor Materials for Computing Devices........7.8-1 7A Design Response to Appendix B, ABWR LRB Instrumentation and Controls.............................7A-1 7A.1 Introduction ...................................................................................................................7A-1 7A.2 Multiplexing Systems....................................................................................................7A-1 7A.3 Electrical Isolators .......................................................................................................7A-12 7A.4 Fiber Optic Cable ........................................................................................................7A-16 7A.5 Programmable Digital Computer Software .................................................................7A-16 7A.6 Programmable Digital Computer Hardware ...............................................................7A-16 7A.7 Responses to Subsections 7A.5 & 7A.6; Computer Hardware and Software .............7A-17 74 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 7 Table of Contents (Continued) 7B Implementation Requirements for Hardware/Software Development .......................................... 7B-1 7B.1 Software Management Plan........................................................................................... 7B-1 7B.2 Configuration Management Plan................................................................................... 7B-4 7B.3 Verification and Validation Plan ................................................................................... 7B-5 7C Defense Against Common-Mode Failure in Safety-Related, Software-Based I&C Systems ....... 7C-1 7C.1 Introduction ................................................................................................................... 7C-1 7C.2 Design Techniques for Optimizing ABWR Safety-Related Hardware and Software......................................................................................................................... 7C-2 7C.3 Defense Against Common-Mode Failure...................................................................... 7C-3 7C.4 Common Mode Failure Analysis................................................................................... 7C-5 7C.5 Details of Final Implementation of Diversity in ABWR Protection System .............. 7C-11 7C.6 References ................................................................................................................... 7C-14 Table of Contents 75

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 7 List of Tables Table 7.1-1 Comparison of GESSAR II and ABWR I&C Safety Systems....................................7.1-33 Table 7.1-2 Regulatory Requirements Applicability Matrix for I&C Systems ..............................7.1-36 Table 7.2-1 Reactor Protection System Instrumentation Specifications ........................................7.2-45 Table 7.2-2 Channels Required for Functional Performance of RPS.............................................7.2-46 Table 7.4-1 Reactor Shutdown Cooling Bypasses and Interlocks..................................................7.4-28 Table 7.5-1 Design and Qualification Criteria for Instrumentation................................................7.5-15 Table 7.5-2 ABWR PAM Variable List .........................................................................................7.5-22 Table 7.5-3 ABWR Type A Variables............................................................................................7.5-24 Table 7.5-4 Anticipated Operational Transients.............................................................................7.5-25 Table 7.5-5 Abnormal Operational Transients ...............................................................................7.5-26 Table 7.5-6 Design Basis Accidents ...............................................................................................7.5-27 Table 7.5-7 Special Events .............................................................................................................7.5-28 Table 7.5-8 Summary of Manual Actions.......................................................................................7.5-29 Table 7.5-9 Definition of Symbols for Tables 7.5-4 Through 7.5-8...............................................7.5-30 Table 7.6-1 SRNM Trip Function Summary ..................................................................................7.6-33 Table 7.6-2 APRM Trip Function Summary ..................................................................................7.6-34 Table 7.6-3 High Pressure/Low Pressure System Interlock Interfaces...........................................7.6-35 Table 7.6-4 Outputs From SPTM System to Other Systems ..........................................................7.6-36 Table 7.6-5 Reactor Operator Information for NMS ......................................................................7.6-37 Table 7.7-1 RCIS Module Operation Environment........................................................................7.7-84 Table 7A-1 List of Equipment Interface with Essential MUX Signals ..........................................7A-22 76 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 7 List of Figures Figure 7.1-1 SSLC Self-Test System............................................................................................7.1-40 Figure 7.1-2 Assignment of Interfacing Safety System Logic to SSLC Controllers....................7.1-41 Figure 7.2-1 ABWR SSLC Control Power Scheme (See also Figure 8.3-3) ...............................7.2-47 Figure 7.2-2 Reactor Protection System Equipment Arrangement (From Sensors Through Trip Actuators) .........................................................................................................7.2-48 Figure 7.2-3 Division 1 Trip Logic Turbine Stop Valve Closure and Turbine Control Valve Fast Closure ...................................................................................................7.2-49 Figure 7.2-4 Division 1 Trip Logic...............................................................................................7.2-50 Figure 7.2-5 Division 1 Trip Logic Coincident and Non-Coincident NMS Trips........................7.2-51 Figure 7.2-6 Division 1 Trip Logic...............................................................................................7.2-52 Figure 7.2-7 Not Used...................................................................................................................7.2-53 Figure 7.2-8 SCRAM Solenoids and Air Header Dump Valves Power Distribution...................7.2-54 Figure 7.2-9 Reactor Protection System IED (Sheets 1-11) ........................................................7.2-55 Figure 7.2-10 Reactor Protection System IBD (Sheets 1-72) ........................................................7.2-55 Figure 7.3-1 High Pressure Core Flooder System IBD (Sheets 1-17) .........................................7.3-92 Figure 7.3-2 Nuclear Boiler System IBD (Sheets 1-37) ..............................................................7.3-92 Figure 7.3-3 Reactor Core Isolation Cooling System IBD (Sheets 1-17) ....................................7.3-92 Figure 7.3-4 Residual Heat Removal System IBD (Sheets 1-20) ................................................7.3-92 Figure 7.3-5 Leak Detection and Isolation System IBD (Sheet 1-77) .........................................7.3-92 Figure 7.3-6 Standby Gas Treatment System IBD (Sheets 1-11) ................................................7.3-92 Figure 7.3-7 Reactor Building Cooling Water / Reactor Service Water System IBD (Sheets 1-19)....................................................................................................7.3-92 Figure 7.3-8 Not Used...................................................................................................................7.3-92 Figure 7.3-9 HVAC Emergency Cooling Water System IBD (Sheets 1-11)...............................7.3-92 Figure 7.3-10 High Pressure Nitrogen Gas System IBD (Sheets 1-3) ...........................................7.3-92 Figure 7.4-1 Standby Liquid Control System IBD (Sheets 1-6) ..................................................7.4-29 Figure 7.4-2 Remote Shutdown System IED................................................................................7.4-29 Table of Contents 77

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 7 List of Figures (Continued)

Figure 7.4-3 Remote Shutdown System IBD (Sheets 1-27) ........................................................7.4-29 Figure 7.6-1 Neutron Monitoring System IED (Sheets 1-4) ........................................................7.6-40 Figure 7.6-2 Neutron Monitoring System IBD (Sheets 1-28)......................................................7.6-40 Figure 7.6-3 LPRM Detector Location .........................................................................................7.6-41 Figure 7.6-4a Basic Configuration of a Typical Neutron Monitoring System Division ................7.6-42 Figure 7.6-4b Neutron Flux Monitoring Range ..............................................................................7.6-43 Figure 7.6-5 Process Radiation Monitoring System IED (Sheets 1-11) ......................................7.6-44 Figure 7.6-6 Not Used...................................................................................................................7.6-44 Figure 7.6-7 Containment Atmospheric Monitoring System IED (Sheets 1-4)...........................7.6-44 Figure 7.6-8 Containment Atmospheric Monitoring System IBD (Sheets 1-10) ........................7.6-44 Figure 7.6-9 Instrumentation Location Definition for the Suppression Pool Temperature Monitoring System...................................................................................................7.6-45 Figure 7.6-10 Suppression Pool Temperature Monitoring System Sensor and Envelope Definition .................................................................................................................7.6-46 Figure 7.6-11 Suppression Pool Temperature Monitoring System IED (Sheets 1-3)....................7.6-47 Figure 7.6-12 Suppression Pool Temperature Monitoring System IBD (Sheets 1-6) ...................7.6-47 Figure 7.6-13 LPRM Assignments to OPRM Channels .................................................................7.6-48 Figure 7.6-14 OPRM Logic ............................................................................................................7.6-49 Figure 7.7-1 Water Level Range Definition .................................................................................7.7-85 Figure 7.7-2 Rod Control and Information System IED (Sheets 1-5) .........................................7.7-86 Figure 7.7-3 Rod Control and Information System IBD (Sheets 1-87) .......................................7.7-86 Figure 7.7-4 Control Rod Drive System IBD (Sheets 1-8) ..........................................................7.7-86 Figure 7.7-5 Recirculation Flow Control System IED (Sheets 1-2) ............................................7.7-86 Figure 7.7-6 Not Used...................................................................................................................7.7-86 Figure 7.7-7 Recirculation Flow Control System IBD (Sheets 1-9) ............................................7.7-86 Figure 7.7-8 Feedwater Control System IED (Sheets 1-3) ..........................................................7.7-86 Figure 7.7-9 Feedwater Control System IBD (Sheets 1, 2, 2a, and 3-14)....................................7.7-86 78 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 7 List of Figures (Continued)

Figure 7.7-10 Assignment of LPRM Strings to TIP Machines ......................................................7.7-87 Figure 7.7-11 Simplified Functional Diagram of the Automatic Power Regulation System .........7.7-88 Figure 7.7-12 Steam Bypass and Pressure Control System IED (Sheets 1-2) ...............................7.7-89 Figure 7.7-13 Steam Bypass and Pressure Control System IBD (Sheets 1-5)...............................7.7-89 Figure 7.7-14 Fuel Pool Cooling and Cleanup System IBD (Sheets 1-8)......................................7.7-89 Figure 7A-1 Safety System Logic and Control (SSLC) ...............................................................7A-63 Figure 7A-2 Structure for Control and Instrumentation System Design ......................................7A-64 Figure 7C-1 Implementation of Additional Diversity in SSLC to Mitigate Effects of Common-Mode Failures ...................................................................................... 7C-15 Table of Contents 79

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 8 Table of Contents 8.0 Electric Power................................................................................................................................8.1-1 8.1 Introduction....................................................................................................................................8.1-1 8.1.1 Offsite Transmission Network ......................................................................................8.1-1 8.1.2 Electric Power Distribution System ..............................................................................8.1-1 8.1.3 Design Bases .................................................................................................................8.1-5 8.1.4 COL License Information............................................................................................8.1-10 8.1.5 References ...................................................................................................................8.1-11 8.2 Offsite Power Systems...................................................................................................................8.2-1 8.2.1 Description ....................................................................................................................8.2-1 8.2.2 Analysis .........................................................................................................................8.2-6 8.2.3 Interface Requirements..................................................................................................8.2-8 8.2.4 COL License Information..............................................................................................8.2-9 8.2.5 Conceptual Design.......................................................................................................8.2-10 8.2.6 References ...................................................................................................................8.2-14 8.3 Onsite Power Systems ...................................................................................................................8.3-1 8.3.1 AC Power Systems ........................................................................................................8.3-1 8.3.2 DC Power Systems ......................................................................................................8.3-27 8.3.3 General Onsite Power System Information.................................................................8.3-37 8.3.4 COL License Information............................................................................................8.3-54 8.3.5 References ...................................................................................................................8.3-58 8A Miscellaneous Electrical Systems..................................................................................................8A-1 8A.1 Station Grounding and Surge Protection.......................................................................8A-1 8A.2 Cathodic Protection .......................................................................................................8A-3 8A.3 Electric Heat Tracing.....................................................................................................8A-4 80 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 8 List of Tables Table 8.1-1 Onsite Power System SRP Criteria Applicable Matrix...............................................8.1-12 Table 8.2-1 Additional Requirements IEEE-765............................................................................8.2-15 Table 8.3-1 D/G Load TableLOCA + LOPP ..............................................................................8.3-61 Table 8.3-2 D/G Load TableLOPP (W/O LOCA)......................................................................8.3-62 Table 8.3-3 Notes for Tables 8.3-1 and 8.3-2 .................................................................................8.3-63 Table 8.3-4 D/G Load Sequence Diagram Major Loads ................................................................8.3-64 Table 8.3-5 Diesel Generator Alarms .............................................................................................8.3-65 Table of Contents 81

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 8 List of Figures Figure 8.2-1 Power Distribution System Routing Diagram (Sheets 1-7) ....................................8.2-16 Figure 8.3-1 Electrical Power Distribution System SLD (Sheets 1-3) ........................................8.3-67 Figure 8.3-2 Instrument and Control Power Supply System SLD................................................8.3-67 Figure 8.3-3 Plant Vital AC Power Supply System SLD (Sheets 1-2) ........................................8.3-67 Figure 8.3-4 Plant DC Power Supply System SLD (Sheets 1-3) .................................................8.3-67 Figure 8A-1 Site Plan (Grounding) ................................................................................................8A-6 82 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 Table of Contents 9.0 Auxiliary Systems..........................................................................................................................9.1-1 9.1 Fuel Storage and Handling ............................................................................................................9.1-1 9.1.1 New-Fuel Storage..........................................................................................................9.1-1 9.1.2 Spent-Fuel Storage ........................................................................................................9.1-2 9.1.3 Fuel Pool Cooling and Cleanup System........................................................................9.1-7 9.1.4 Light Load Handling System (Related to Refueling)..................................................9.1-13 9.1.5 Overhead Heavy Load Handling Systems (OHLH)....................................................9.1-33 9.1.6 COL License Information............................................................................................9.1-41 9.1.7 References ...................................................................................................................9.1-43 9.2 Water Systems ...............................................................................................................................9.2-1 9.2.1 Station Service Water System .......................................................................................9.2-1 9.2.2 Closed Cooling Water System.......................................................................................9.2-1 9.2.3 Demineralized Water Makeup System..........................................................................9.2-1 9.2.4 Potable and Sanitary Water System ..............................................................................9.2-1 9.2.5 Ultimate Heat Sink ........................................................................................................9.2-5 9.2.6 Condensate Storage Facilities and Distribution System..............................................9.2-10 9.2.7 Plant Chilled Water System.........................................................................................9.2-10 9.2.8 Makeup Water (MWP) Preparation System................................................................9.2-10 9.2.9 Makeup Water Condensate System.............................................................................9.2-15 9.2.10 Makeup Water Purified System...................................................................................9.2-17 9.2.11 Reactor Building Cooling Water System ....................................................................9.2-19 9.2.12 HVAC Normal Cooling Water System .......................................................................9.2-26 9.2.13 HVAC Emergency Cooling Water System .................................................................9.2-28 9.2.14 Turbine Building Cooling Water System ....................................................................9.2-32 9.2.15 Reactor Service Water System ....................................................................................9.2-35 9.2.16 Turbine Service Water System....................................................................................9.2-40 9.2.17 COL License Information............................................................................................9.2-43 9.3 Process Auxiliaries ........................................................................................................................9.3-1 9.3.1 Compressed Air Systems...............................................................................................9.3-1 9.3.2 Process and Post-Accident Sampling System ...............................................................9.3-1 9.3.3 Non-Radioactive Drainage System ...............................................................................9.3-7 9.3.4 Chemical and Volume Control System (PWR)...........................................................9.3-10 9.3.5 Standby Liquid Control System ..................................................................................9.3-10 9.3.6 Instrument Air System.................................................................................................9.3-16 9.3.7 Service Air System ......................................................................................................9.3-19 9.3.8 Radioactive Drain Transfer System.............................................................................9.3-21 9.3.9 Hydrogen Water Chemistry System............................................................................9.3-27 9.3.10 Oxygen Injection System ............................................................................................9.3-29 9.3.11 Zinc Injection System..................................................................................................9.3-30 9.3.12 COL License Information............................................................................................9.3-31 9.4 Air Conditioning, Heating, Cooling and Ventilating Systems ......................................................9.4-1 9.4.1 Control Building HVAC................................................................................................9.4-1 9.4.2 Spent Fuel Pool Area HVAC System............................................................................9.4-9 9.4.3 Auxiliary Area HVAC System......................................................................................9.4-9 Table of Contents 83

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 Table of Contents (Continued) 9.4.4 Turbine Island HVAC System.......................................................................................9.4-9 9.4.5 Reactor Building HVAC System.................................................................................9.4-15 9.4.6 Radwaste Building HVAC System .............................................................................9.4-29 9.4.7 R/B Safety-Related Diesel Generator HVAC System.................................................9.4-32 9.4.8 Service Building HVAC System .................................................................................9.4-32 9.4.9 Drywell Cooling System .............................................................................................9.4-35 9.4.10 COL License Information............................................................................................9.4-37 9.5 Other Auxiliary Systems................................................................................................................9.5-1 9.5.1 Fire Protection System ..................................................................................................9.5-1 9.5.2 Communication Systems .............................................................................................9.5-28 9.5.3 Lighting and Servicing Power Supply System............................................................9.5-33 9.5.4 Diesel-Generator Fuel Oil Storage and Transfer System ............................................9.5-43 9.5.5 Diesel-Generator Jacket Cooling Water System .........................................................9.5-47 9.5.6 Diesel-Generator Starting Air System.........................................................................9.5-49 9.5.7 Diesel Generator Lubrication System .........................................................................9.5-51 9.5.8 Diesel-Generator Combustion Air Intake and Exhaust System ..................................9.5-52 9.5.9 Suppression Pool Cleanup System ..............................................................................9.5-55 9.5.10 Motor-Generator Set....................................................................................................9.5-56 9.5.11 Combustion Turbine/Generator...................................................................................9.5-59 9.5.12 Lower Drywell Flooder ...............................................................................................9.5-62 9.5.13 COL License Information............................................................................................9.5-67 9.5.14 Reference.....................................................................................................................9.5-73 9A Fire Hazard Analysis ..................................................................................................................9A.1-1 9A.1 Introduction ................................................................................................................9A.1-1 9A.2 Analysis Criteria.........................................................................................................9A.2-1 9A.3 Analysis Approach .....................................................................................................9A.3-1 9A.4 Analysis ......................................................................................................................9A.4-1 9A.5 Special Cases ..............................................................................................................9A.5-1 9A.6 Fire Hazard Analysis Database ..................................................................................9A.6-1 9B Summary of Analysis Supporting Fire Protection Design Requirements ..................................... 9B-1 9B.1 Introduction ................................................................................................................... 9B-1 9B.2 Fire Containment System .............................................................................................. 9B-1 9B.3 References ................................................................................................................... 9B-10 9C Regulatory Guide 1.52, Section C, Compliance Assessment ........................................................ 9C-1 9C.1 ABWR Compliance with RG 1.52, Revision 2, Section C ........................................... 9C-1 9D SRP 6.5.1, Table 6.5.1-1 Compliance Assessment........................................................................9D-1 84 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Tables Table 9.1-1 Not Used......................................................................................................................9.1-44 Table 9.1-2 Fuel Servicing Equipment ...........................................................................................9.1-44 Table 9.1-3 Reactor Vessel Servicing Equipment ..........................................................................9.1-45 Table 9.1-4 Under-Reactor Vessel Servicing Equipment and Tools..............................................9.1-45 Table 9.1-5 Tools and Servicing Equipment ..................................................................................9.1-46 Table 9.1-6 Reference Codes and Standards ..................................................................................9.1-47 Table 9.1-7 Heavy Load Equipment Used to Handle Light Loads and Related Refueling Handling Tasks............................................................................................................9.1-48 Table 9.1-8 Heavy Load Operations...............................................................................................9.1-49 Table 9.1-9 Legend for In-Plant Locations/Elevations...................................................................9.1-53 Table 9.1-10 Single-Failure-Proof Cranes........................................................................................9.1-53 Table 9.1-11 Fuel Pool Cooling Heat Exchanger and Performance Data ........................................9.1-54 Table 9.1-12 RHR-FPC Joint Heat Removal Performance Table (150 Hours Following Shutdown)....................................................................................................................9.1-55 Table 9.2-1 Users of Makeup Water-Condensate...........................................................................9.2-45 Table 9.2-2 Users of Makeup Water-Purified.................................................................................9.2-45 Table 9.2-2a Water Quality Characteristics for the Makeup Water Purified System ......................9.2-46 Table 9.2-3 Capacity Requirements for Condensate Storage Tank................................................9.2-47 Table 9.2-4a Reactor Building Cooling Water Division A ..............................................................9.2-48 Table 9.2-4b Reactor Building Cooling Water Division B...............................................................9.2-49 Table 9.2-4c Reactor Building Cooling Water Division C...............................................................9.2-50 Table 9.2-4d Design Characteristics for Reactor Building Cooling Water System Components ....9.2-51 Table 9.2-5a Reactor Building Cooling Water Active Failure Analysis ..........................................9.2-52 Table 9.2-5b Reactor Building Cooling Water System Passive Failure Analysis............................9.2-53 Table 9.2-6 HVAC Normal Cooling Water System Component Description................................9.2-54 Table 9.2-7 HVAC Normal Cooling Water Loads .........................................................................9.2-55 Table 9.2-8 HECW System Component Description .....................................................................9.2-56 Table of Contents 85

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Tables (Continued)

Table 9.2-9 HVAC Emergency Cooling Water System Heat Loads..............................................9.2-57 Table 9.2-10 HVAC Emergency Cooling Water System Active Failure Analysis ..........................9.2-58 Table 9.2-11 Turbine Island Auxiliary Equipment...........................................................................9.2-58 Table 9.2-12 Not Used......................................................................................................................9.2-59 Table 9.2-13 Reactor Service Water System (Interface Requirements) ...........................................9.2-59 Table 9.2-14 Potable and Sanitary Water System Components (Interface Requirements) ..............9.2-60 Table 9.2-15 Makeup Water Preparation System Component (Interface Requirements) ................9.2-62 Table 9.2-16 Turbine Service Water System (Interface Requirement) ............................................9.2-64 Table 9.3-1 Standby Liquid Control System Operating Pressure/Temperature Conditions...........9.3-32 Table 9.3-2 Water Quality Instrumentation ....................................................................................9.3-33 Table 9.3-3 Service Air Consumption During Normal Plant Operation ........................................9.3-37 Table 9.3-4 Instrument Air Consumption During Normal Plant Operation (Response to Question 430.215) .......................................................................................................9.3-37 Table 9.4-1 Drywell Cooling System Non-Safety-Related Components .......................................9.4-38 Table 9.4-2 Drywell Cooling System Non-Safety-Related Heat Loads .........................................9.4-39 Table 9.4-3 HVAC Flow Rates (Response to Question 430.243) ..................................................9.4-40 Table 9.4-4 HVAC System Component DescriptionsSafety-Related Heating/Cooling Coils (Response to Question 430.243) ........................................................................9.4-41 Table 9.4-4a HVAC System Component DescriptionsSafety-Related Fans (Response to Question 430.243) .......................................................................................................9.4-42 Table 9.4-4b HVAC System Component DescriptionsSafety-Related Filter (Response to Question 430.243) .......................................................................................................9.4-43 Table 9.4-4c HVAC System Component DescriptionsEmergency Use Adsorption Units (Safety Related) (Response to Question 430.243) ......................................................9.4-43 Table 9.4-4d Not Used......................................................................................................................9.4-44 Table 9.4-4e HVAC System Component DescriptionsSafety-Related Fan Coil Units (Response to Question 430.243)..................................................................................9.4-44 Table 9.4-4f HVAC System Component DescriptionsNon-Safety-Related Heating Cooling Coils (Response to Question 430.243) ........................................................................9.4-45 86 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Tables (Continued)

Table 9.4-4g HVAC System Component DescriptionsNon-Safety-Related Fans (Response to Question 430.243).................................................................................9.4-45 Table 9.4-4h HVAC System Component DescriptionsNon-Safety-Related Filters (Response to Question 430.243).................................................................................9.4-45 Table 9.4-4i HVAC System Component DescriptionsNon-Safety-Related Air Handling Units (Response to Question 430.243) .......................................................................9.4-46 Table 9.4-5 Turbine Building and Electrical Building HVAC SystemNon-Safety-Related Equipment....................................................................................................................9.4-47 Table 9.4-5a Turbine Building and Electrical Building HVAC SystemNon-Safety-Related Equipment (Continued) ...............................................................................................9.4-48 Table 9.4-5b Turbine Building and Electrical Building HVAC SystemNon-Safety-Related Equipment (Continued) ...............................................................................................9.4-49 Table 9.4-5c Turbine Building and Electrical Building HVAC SystemNon-Safety-Related Equipment (Continued) ...............................................................................................9.4-50 Table 9.5-1 Normal and/or Standby Lighting (Non-Class 1E AC Power Supply).........................9.5-74 Table 9.5-2 Lighting and Power Sources........................................................................................9.5-75 Table 9.5-3 Standby Lighting (Class 1E AC Power Supply) .........................................................9.5-75 Table 9.5-4 DC Emergency Lighting..............................................................................................9.5-76 Table 9.5-5 Summary of Automatic Fire Suppression Systems .....................................................9.5-77 Table 9A.2-1 Core Cooling ..............................................................................................................9A.2-8 Table 9A.5-1 Redundant Instrumentation or Equipment in Same Fire Area .................................9A.5-19 Table 9A.5-2 Summary of the Reactor Building Special Cases.....................................................9A.5-20 Table 9A.6-1 Fire Hazard Analysis Equipment Data BaseSorted by MPL Number ...................9A.6-5 Table 9A.6-2 Fire Hazard Analysis Equipment Database Sorted by RoomReactor Building .....9A.6-6 Table 9A.6-3 Fire Hazard Analysis Equipment Data BaseSorted by RoomControl Building ....................................................................................................................9A.6-96 Table 9A.6-4 Fire Hazard Analysis Equipment DatabaseSorted by RoomTurbine Building ..................................................................................................................9A.6-106 Table 9A.6-5 Fire Hazard Analysis Equipment DatabaseControl Building Annex .................9A.6-116 Table 9B-1 Estimated Fire Severity for Offices and Light Commercial Occupancies .................. 9B-11 Table of Contents 87

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Tables (Continued)

Table 9B-2 Fire Severity Expected by Occupancy ........................................................................ 9B-12 Table 9B-3 Cable Type and Configuration for Ul Tests ................................................................ 9B-13 Table 9B-4 Summary of Burning Rate Calculations...................................................................... 9B-13 88 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Figures Figure 9.1-1 Fuel Pool Cooling and Cleanup System P&ID (Sheets 1-3)...................................9.1-56 Figure 9.1-2 Fuel Pool Cooling and Cleanup System PFD (Sheets 1-2) .....................................9.1-56 Figure 9.1-3 Fuel Preparation Machine Shown Installed in Facsimile Fuel Pool ........................9.1-57 Figure 9.1-4 New-Fuel Inspection Stand ......................................................................................9.1-58 Figure 9.1-5 Channel Bolt Wrench ...............................................................................................9.1-59 Figure 9.1-6 Channel-Handling Tool............................................................................................9.1-60 Figure 9.1-7 Fuel Pool Vacuum Sipper ........................................................................................9.1-61 Figure 9.1-8 General-Purpose Grapple .........................................................................................9.1-62 Figure 9.1-9 Not Used...................................................................................................................9.1-63 Figure 9.1-10 Jib Crane Channel-Handling Boom .........................................................................9.1-64 Figure 9.1-11 Fuel Assembly Sampler ...........................................................................................9.1-65 Figure 9.1-12 Plant Refueling and Servicing Sequence .................................................................9.1-66 Figure 9.1-13 Simplified Section of Refueling Facilities ...............................................................9.1-67 Figure 9.1-14 Simplified Section of New-Fuel Handling Facilities ...............................................9.1-68 Figure 9.2-1 Reactor Building Cooling Water System P&ID (Sheets 1-9) .................................9.2-65 Figure 9.2-1a Not Used...................................................................................................................9.2-65 Figure 9.2-2 HVAC Normal Cooling Water System P&ID .........................................................9.2-65 Figure 9.2-3 HVAC Emergency Cooling Water System P&ID (Sheets 1-3) ..............................9.2-65 Figure 9.2-4 Makeup Water System (Condensate) P&ID ............................................................9.2-65 Figure 9.2-5 Makeup Water System (Purified) P&ID (Sheets 1-3) .............................................9.2-65 Figure 9.2-6a Turbine Building Cooling Water System Diagram..................................................9.2-66 Figure 9.2-6b Turbine Building Cooling Water System Diagram..................................................9.2-67 Figure 9.2-6c Turbine Building Cooling Water System Diagram..................................................9.2-68 Figure 9.2-7 Reactor Service Water System P&ID (Sheets 1-3) .................................................9.2-69 Figure 9.2-8 Turbine Building Service Water System..................................................................9.2-70 Figure 9.2-9 Potable and Sanitary Water System .........................................................................9.2-71 Table of Contents 89

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Figures (Continued)

Figure 9.2-10 Makeup Water Preparation System..........................................................................9.2-72 Figure 9.3-1 Standby Liquid Control System P&ID ....................................................................9.3-38 Figure 9.3-1a Standby Liquid Control System PFD.......................................................................9.3-38 Figure 9.3-2 Sodium Pentaborate Volume Concentration Requirements.....................................9.3-39 Figure 9.3-3 Saturation Temperature of Sodium Pentaborate Solution........................................9.3-40 Figure 9.3-4 Sample Probe ...........................................................................................................9.3-41 Figure 9.3-5 Sample Probe ...........................................................................................................9.3-42 Figure 9.3-6 Instrument Air System P&ID (Sheets 1-2)..............................................................9.3-43 Figure 9.3-7 Station Service Air System P&ID (Sheets 1-2).......................................................9.3-43 Figure 9.3-8 Hydrogen Water Chemistry System.........................................................................9.3-44 Figure 9.3-9 Divisional Radioactive Floor Drains........................................................................9.3-45 Figure 9.4-1 Control Building HVAC Flow Diagram (Sheets 1-5) .............................................9.4-51 Figure 9.4-2a Turbine Building Ventilation System Air Flow Diagram........................................9.4-51 Figure 9.4-2b Turbine Building Ventilation System Control Diagram (Sheets 1-2) .....................9.4-51 Figure 9.4-2c Electrical Building HVAC System Diagram ...........................................................9.4-52 Figure 9.4-3 Secondary Containment HVAC System (Sheets 1-3) .............................................9.4-53 Figure 9.4-4 R/B Safety-Related Electrical Equipment HVAC System (Sheets 1-3) .................9.4-53 Figure 9.4-5 Reactor Internal Pump Control Panel Room HVAC System...................................9.4-53 Figure 9.4-6 Not Used...................................................................................................................9.4-53 Figure 9.4-7 Not Used...................................................................................................................9.4-53 Figure 9.4-8 Drywell Cooling System P&ID ...............................................................................9.4-53 Figure 9.4-9 Drywell Heat Load Area Drawing ...........................................................................9.4-54 Figure 9.4-10 Radwaste Building HVAC (Sheets 1-3)..................................................................9.4-55 Figure 9.5-1 Suppression Pool Cleanup System P&ID ................................................................9.5-79 Figure 9.5-2 OutlineTelephonic Communication Systems.......................................................9.5-80 Figure 9.5-3 Lower Drywell Flooder System Arrangement/Configuration .................................9.5-81 90 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Figures (Continued)

Figure 9.5-4 Fire Protection Water Supply System ......................................................................9.5-82 Figure 9.5-5 Fire Protection Yard Main Piping ............................................................................9.5-84 Figure 9.5-6 Standby Diesel Generator Fuel Oil and Combustion Air Intake and Exhaust Systems ....................................................................................................................9.5-86 Figure 9.5-7 Standby Diesel Generator Jacket Cooling Water System ........................................9.5-86 Figure 9.5-8 Standby Diesel Generator Starting Air System........................................................9.5-86 Figure 9.5-9 Standby Diesel Generator Lubricating Oil System ..................................................9.5-86 Figure 9A.4-1 Reactor Building Fire Protection at Elevation -8200 mm...................................9A.4-466 Figure 9A.4-2 Reactor Building Fire Protection at Elevation -1700 mm...................................9A.4-466 Figure 9A.4-3 Reactor Building Fire Protection at Elevation 4800/8500 mm ...........................9A.4-466 Figure 9A.4-4 Reactor Building Fire Protection at Elevation 12300 mm ..................................9A.4-466 Figure 9A.4-5 Reactor Building Fire Protection at Elevation 18100 mm ..................................9A.4-466 Figure 9A.4-6 Reactor Building Fire Protection at Elevation 23500 mm ..................................9A.4-466 Figure 9A.4-7 Reactor Building Fire Protection at Elevation 27200 mm ..................................9A.4-466 Figure 9A.4-8 Reactor Building Fire Protection at Elevation 31700/38200 mm .......................9A.4-466 Figure 9A.4-9 Reactor Building Fire Protection, Section A-A ..................................................9A.4-466 Figure 9A.4-10 Reactor Building Fire Protection, Section B-B...................................................9A.4-466 Figure 9A.4-11 Control Building Fire Protection, Section B-B ...................................................9A.4-466 Figure 9A.4-12 Control Building Fire Protection at Elevation -8200 mm ...................................9A.4-466 Figure 9A.4-13 Control Building Fire Protection at Elevation -2150 mm ...................................9A.4-466 Figure 9A.4-14 Control Building Fire Protection at Elevation 3500 mm ....................................9A.4-466 Figure 9A.4-15 Control Building Fire Protection at Elevation 7900 mm ....................................9A.4-466 Figure 9A.4-16 Control Building Fire Protection at Elevation 12300 mm ..................................9A.4-466 Figure 9A.4-16a Control Building Fire Protection at Elevation 17150 mm ..................................9A.4-466 Figure 9A.4-16b Control Building Fire Protection at Elevation 22200 mm ..................................9A.4-466 Figure 9A.4-17 Turbine Building Fire Protection, Section A-A ..................................................9A.4-466 Table of Contents 91

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 9 List of Figures (Continued)

Figure 9A.4-18 Turbine Building Fire Protection at Elevation 5300 mm....................................9A.4-466 Figure 9A.4-19 Turbine Building Fire Protection at Elevation 12300 mm..................................9A.4-466 Figure 9A.4-20 Turbine Building Fire Protection at Elevation 20300 mm..................................9A.4-466 Figure 9A.4-21 Turbine Building Fire Protection at Elevation 30300 mm..................................9A.4-466 Figure 9A.4-22 Service Building Fire Protection, Section B-B (See Figure 9A.4-11) ................9A.4-467 Figure 9A.4-23 Service Building Fire Protection at Elevation -2150 mm (See Figure 9A.4-13)...........................................................................................9A.4-467 Figure 9A.4-24 Service Building Fire Protection at Elevation 3500 mm (See Figure 9A.4-14)...........................................................................................9A.4-467 Figure 9A.4-25 Service Building Fire Protection at Elevation 7900 mm (See Figure 9A.4-15)...........................................................................................9A.4-467 Figure 9A.4-26 Service Building Fire Protection at Elevation 12300 mm (See Figure 9A.4-16)...........................................................................................9A.4-467 Figure 9A.4-27 Service Building Fire Protection at Elevation 17150 mm (See Figure 9A.4-16a) .........................................................................................9A.4-467 Figure 9A.4-28 Radwaste Building Fire Protection, Section A-A ...............................................9A.4-467 Figure 9A.4-29 Radwaste Building Fire Protection at Elevation -1500 mm ...............................9A.4-467 Figure 9A.4-30 Radwaste Building Fire Protection at Elevation 4800 mm.................................9A.4-467 Figure 9A.4-31 Radwaste Building Fire Protection at Elevation 12300 mm ...............................9A.4-467 Figure 9A.4-32 Radwaste Building Fire Protection at Elevation 21000 mm ...............................9A.4-467 Figure 9A.5-1 Typical RPS Contact Interface Turbine Building to Control Building.................9A.5-28 Figure 9A.5-2 Typical Electrical Equipment Connection Block Diagrams of Special Cases......9A.5-29 Figure 9B-1 Possible Classification of Building Contents for Fire Severity and Duration ......... 9B-14 92 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 10 Table of Contents 10.0 Steam and Power Conversion System .........................................................................................10.1-1 10.1 Summary Description ..................................................................................................................10.1-1 10.1.1 Protective Features ......................................................................................................10.1-2 10.2 Turbine Generator........................................................................................................................10.2-1 10.2.1 Design Bases ...............................................................................................................10.2-1 10.2.2 Description ..................................................................................................................10.2-2 10.2.3 Turbine Integrity........................................................................................................10.2-10 10.2.4 Evaluation..................................................................................................................10.2-14 10.2.5 COL License Information..........................................................................................10.2-15 10.2.6 References .................................................................................................................10.2-15 10.3 Main Steam Supply System .........................................................................................................10.3-1 10.3.1 Design Bases ...............................................................................................................10.3-1 10.3.2 Description ..................................................................................................................10.3-2 10.3.3 Evaluation....................................................................................................................10.3-3 10.3.4 Inspection and Testing Requirements .........................................................................10.3-3 10.3.5 Water Chemistry (PWR) .............................................................................................10.3-3 10.3.6 Steam and Feedwater System Materials......................................................................10.3-3 10.3.7 COL License Information............................................................................................10.3-5 10.4 Other Features of Steam and Power Conversion System ............................................................10.4-1 10.4.1 Main Condenser...........................................................................................................10.4-1 10.4.2 Main Condenser Evacuation System...........................................................................10.4-6 10.4.3 Turbine Gland Sealing System....................................................................................10.4-8 10.4.4 Turbine Bypass System .............................................................................................10.4-11 10.4.5 Circulating Water System..........................................................................................10.4-14 10.4.6 Condensate Purification System................................................................................10.4-18 10.4.7 Condensate and Feedwater System ...........................................................................10.4-22 10.4.8 Steam Generator Blowdown System (PWR) ............................................................10.4-28 10.4.9 Auxiliary Feedwater System (PWR) .........................................................................10.4-28 10.4.10 COL License Information..........................................................................................10.4-29 Table of Contents 93

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 10 List of Tables Table 10.1-1 Summary of Important Design Features and Performance Characteristics of the Steam and Power Conversion System.........................................................................10.1-4 Table 10.3-1 Main Steam Supply System Design Data....................................................................10.3-6 Table 10.4-1 Condenser Design Data .............................................................................................10.4-30 Table 10.4-2 Main Condenser Evacuation System.........................................................................10.4-30 Table 10.4-3 Circulating Water System..........................................................................................10.4-31 Table 10.4-4 Condensate Purification System................................................................................10.4-31 Table 10.4-5 Condensate and Feedwater System Design Data ......................................................10.4-32 Table 10.4-6 Condensate and Feedwater System Component Failure Analysis ............................10.4-33 94 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 10 List of Figures Figure 10.1-1 Reference Steam & Power Conversion System .......................................................10.1-7 Figure 10.1-2 Reference Heat Balance for Guaranteed Reactor Rating .........................................10.1-8 Figure 10.1-3 Reference Heat Balance for Valves-Wide-Open (VWO) ........................................10.1-8 Figure 10.2-1 Turbine Stop Valve Closure Characteristic............................................................10.2-16 Figure 10.2-2 Turbine Control Valve Fast Closure Characteristic ...............................................10.2-17 Figure 10.2-3 Acceptable Range for Control Valve Normal Closure Motion..............................10.2-18 Figure 10.2-4 Generator Hydrogen and CO2 System...................................................................10.2-19 Figure 10.3-1 Main Steam Supply System .....................................................................................10.3-7 Figure 10.3-2 Main Turbine System ...............................................................................................10.3-8 Figure 10.4-1 Main Condenser Evacuation System .....................................................................10.4-34 Figure 10.4-2 Turbine Gland Seal System....................................................................................10.4-35 Figure 10.4-3 Circulating Water System ......................................................................................10.4-36 Figure 10.4-4 Condensate Purification System ............................................................................10.4-37 Figure 10.4-5 Condensate System ................................................................................................10.4-39 Figure 10.4-6 Feedwater System ..................................................................................................10.4-41 Figure 10.4-7 LP Extraction Steam Drains and Vent Systems .....................................................10.4-42 Figure 10.4-8 HP Extraction Steam Drains and Vent System ......................................................10.4-43 Figure 10.4-9 Bypass Valve Control, Electro-Hydraulic Control Unit ........................................10.4-44 Figure 10.4-10 Signal Flow Chart for Turbine Bypass Control Unit .............................................10.4-45 Table of Contents 95

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 11 Table of Contents 11.0 Radioactive Waste Management.................................................................................................11.1-1 11.1 Source Terms ..............................................................................................................................11.1-1 11.1.1 Fission Products...........................................................................................................11.1-1 11.1.2 Activation Products .....................................................................................................11.1-3 11.1.3 Radionuclide Concentration Adjustment ....................................................................11.1-5 11.1.4 Fuel Fission Production Inventory ..............................................................................11.1-6 11.1.5 Process Leakage Sources.............................................................................................11.1-6 11.1.6 References ...................................................................................................................11.1-7 11.2 Liquid Waste Management System ............................................................................................11.2-1 11.2.1 Design Basis ................................................................................................................11.2-1 11.2.2 System Description......................................................................................................11.2-4 11.2.3 Estimated Releases ......................................................................................................11.2-5 11.2.4 Tank Resistance to Vacuum Collapse .........................................................................11.2-6 11.2.5 COL License Information............................................................................................11.2-6 11.3 Gaseous Waste Management System..........................................................................................11.3-1 11.3.1 General ........................................................................................................................11.3-1 11.3.2 Design Criteria.............................................................................................................11.3-1 11.3.3 Process Description .....................................................................................................11.3-2 11.3.4 Offgas System Description..........................................................................................11.3-4 11.3.5 Other Radioactive Gas Sources .................................................................................11.3-19 11.3.6 Instrumentation and Control......................................................................................11.3-19 11.3.7 Quality Control..........................................................................................................11.3-19 11.3.8 Seismic Design ..........................................................................................................11.3-20 11.3.9 Testing .......................................................................................................................11.3-21 11.3.10 Radioactive Releases .................................................................................................11.3-23 11.3.11 COL License Information..........................................................................................11.3-24 11.3.12 References .................................................................................................................11.3-24 11.4 Solid Waste Management System...............................................................................................11.4-1 11.4.1 Design Bases ...............................................................................................................11.4-1 11.4.2 System Description......................................................................................................11.4-2 11.4.3 COL License Information............................................................................................11.4-6 11.5 Process and Effluent Radiological Monitoring and Sampling Systems......................................11.5-1 11.5.1 Design Bases ...............................................................................................................11.5-1 11.5.2 System Description......................................................................................................11.5-4 11.5.3 Effluent Monitoring and Sampling............................................................................11.5-13 11.5.4 Process Monitoring and Sampling.............................................................................11.5-13 11.5.5 Calibration and Maintenance.....................................................................................11.5-15 11.5.6 COL License Information..........................................................................................11.5-17 11.6 Offsite Radiological Monitoring Program ..................................................................................11.6-1 11A.0 Radioactive Waste Management - Additional Information ........................................................11A-1 11A.1 Introduction .................................................................................................................11A-1 11A.2 Liquid Waste Management..........................................................................................11A-1 96 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 11 Table of Contents (Continued) 11A.3 Not Used......................................................................................................................11A-1 11A.4 Solid Waste Management System ...............................................................................11A-1 Table of Contents 97

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 11 List of Tables Table 11.1-1 Noble Radiogas Source Terms in Steam .....................................................................11.1-8 Table 11.1-2 Iodine Radioisotopes in Reactor Water.......................................................................11.1-8 Table 11.1-3 Non-Volatile Fission Products in Reactor Water ........................................................11.1-9 Table 11.1-4 Coolant Activation Products in Reactor Water and Steam .......................................11.1-10 Table 11.1-5 Non-coolant Activation Products in Reactor Water..................................................11.1-10 Table 11.1-6 Plant Parameters for Source Term Adjustment .........................................................11.1-11 Table 11.1-7 Removal Parameters for Source Term Adjustment...................................................11.1-11 Table 11.2-1 Equipment Codes for Radwaste Equipment (from Table 1, RG 1.143)......................11.2-8 Table 11.2-2 Capability of Liquid Radwaste Subsystems to Process Expected Wastes ..................11.2-8 Table 11.2-3 Reactor Coolant Activity (RCA) Fraction...................................................................11.2-9 Table 11.2-4 Capacities of Tanks, Pumps, and Other Components ...............................................11.2-10 Table 11.3-1 Estimated Air Ejector Offgas Release Rates Per Unit (51 sm3/h Inleakage) ............11.3-25 Table 11.3-2 Offgas System Major Equipment Items ....................................................................11.3-26 Table 11.3-3 Equipment Malfunction Analysis..............................................................................11.3-28 Table 11.3-4 Offgas System Instrument Setpoints .........................................................................11.3-31 Table 11.4-1 Expected Waste Volume Generated Annually by Each Wet Solid Waste Source and Tank Capacities ....................................................................................................11.4-7 Table 11.4-2 Estimate of Expected Annual Dry Solid Wastes and Becquerel Content................11.4-7 Table 11.4-3 Calculated Shipped Solid Waste Volumes and Becquerel Count ...............................11.4-7 Table 11.5-1 Process and Effluent Radiation Monitoring Systems................................................11.5-19 Table 11.5-2 Process Radiation Monitoring System (Gaseous and Airborne Monitors) ...............11.5-21 Table 11.5-3 Process Radiation Monitoring System (Liquid Monitors) ........................................11.5-24 Table 11.5-4 Radiological Analysis Summary of Liquid Process Samples ...................................11.5-25 Table 11.5-5 Radiological Analysis Summary of Gaseous Process Samples ................................11.5-26 Table 11.5-6 Radiological Analysis Summary of Liquid Effluent Samples ..................................11.5-27 Table 11.5-7 Radiological Analysis Summary of Gaseous Effluent Samples................................11.5-28 98 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 11 List of Figures Figure 11.2-1 Radwaste System PFD ...........................................................................................11.2-12 Figure 11.3-1 Offgas System PFD (Sheets 1-2) ...........................................................................11.3-37 Figure 11.3-2 Offgas System P&ID (Sheets 1-3) .........................................................................11.3-37 Table of Contents 99

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 Table of Contents 12.0 Radiation Protection ....................................................................................................................12.1-1 12.1 Ensuring that Occupational Radiation Exposures are ALARA...................................................12.1-1 12.1.1 Policy Considerations..................................................................................................12.1-1 12.1.2 Design Considerations.................................................................................................12.1-2 12.1.3 Operational Considerations .........................................................................................12.1-5 12.1.4 COL License Information............................................................................................12.1-6 12.2 Radiation Sources ........................................................................................................................12.2-1 12.2.1 Contained Sources .......................................................................................................12.2-1 12.2.2 Airborne and Liquid Sources for Environmental Consideration.................................12.2-9 12.2.3 COL License Information..........................................................................................12.2-11 12.2.4 References .................................................................................................................12.2-11 12.3 Radiation Protection Design Features..........................................................................................12.3-1 12.3.1 Facility Design Features ..............................................................................................12.3-1 12.3.2 Shielding....................................................................................................................12.3-17 12.3.3 Ventilation .................................................................................................................12.3-25 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation ................12.3-28 12.3.5 Post-Accident Access Requirements.........................................................................12.3-30 12.3.6 Post-Accident Radiation Zone Maps.........................................................................12.3-31 12.3.7 COL License Information..........................................................................................12.3-32 12.3.8 References .................................................................................................................12.3-32 12.4 Dose Assessment .........................................................................................................................12.4-1 12.4.1 Drywell Dose...............................................................................................................12.4-1 12.4.2 Reactor Building Dose ................................................................................................12.4-4 12.4.3 Radwaste Building Dose .............................................................................................12.4-5 12.4.4 Turbine Building Dose ................................................................................................12.4-6 12.4.5 Work at Power.............................................................................................................12.4-6 12.4.6 References ...................................................................................................................12.4-7 12.5 Health Physics Program...............................................................................................................12.5-1 12.5.1 Operational Considerations .........................................................................................12.5-1 12.5.2 In-Plant and Airborne Radioactivity Monitoring ........................................................12.5-1 12.5.3 COL License Information............................................................................................12.5-1 12A Appendix 12A Calculation of Airborne Radionuclides...............................................................12A-1 12A.1 Calculation of Airborne Radionuclides .......................................................................12A-1 12A.2 References ...................................................................................................................12A-4 100 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 List of Tables Table 12.2-1a Basic Reactor Data ....................................................................................................12.2-13 Table 12.2-1b Basic Reactor DataMaterial Densities (g/cm3) .....................................................12.2-14 Table 12.2-1c Basic Reactor DataTypical Core Exposure Distribution.......................................12.2-15 Table 12.2-1d Basic Reactor DataTypical Core Exposure DistributionAxial Relative Exposure ....................................................................................................................12.2-16 Table 12.2-2 Core Boundary Neutron Fluxes.................................................................................12.2-17 Table 12.2-3a Gamma Ray Source Energy SpectraGamma Ray Sources in the Core During Operation.......................................................................................................12.2-18 Table 12.2-3b Gamma Ray Source Energy SpectraPost-Operation Gamma Sources in the Core (pJ/W-sec).........................................................................................................12.2-18 Table 12.2-3c Gamma Ray Source Energy SpectraGamma Ray Source External to the Core During Operation.......................................................................................................12.2-19 Table 12.2-4a Gamma Ray and Neutron Fluxes Outside the Vessel WallNeutron Fluxes..........12.2-20 Table 12.2-4b Gamma Ray and Neutron Fluxes Outside the Vessel WallGamma Ray Energy Fluxes............................................................................................................12.2-20 Table 12.2-5a Radiation Sources Radiation Sources....................................................................12.2-21 Table 12.2-5b Radiation SourcesSource Geometry......................................................................12.2-23 Table 12.2-5c Radiation SourcesShielding Geometry in Meters .................................................12.2-25 Table 12.2-5d Radiation SourcePipe Chase Detail.......................................................................12.2-27 Table 12.2-6 Fission Product Gamma Source Strength in the RHR Heat Exchanger....................12.2-29 Table 12.2-7 Fission Product Inventory in the RHR Heat Exchanger 2 Hours After Shutdown ...12.2-30 Table 12.2-8 Reactor Coolant Concentration Values Entering the RCIC Turbine.........................12.2-32 Table 12.2-9 CUW Filter Demineralizer ........................................................................................12.2-34 Table 12.2-10 Reactor Water Cleanup, Regenerative Heat Exchanger Tube Sides.........................12.2-35 Table 12.2-11 Reactor Water Cleanup, Non-Regenerative Heat Exchanger Tube Sides.................12.2-36 Table 12.2-12 Reactor Water Cleanup, Regenerative Heat Exchanger Shell Side ..........................12.2-37 Table 12.2-13a Liquid Radwaste Component InventoriesLCW Collector Tank ...........................12.2-38 Table 12.2-13b Liquid Radwaste Component InventoriesLCW Filter...........................................12.2-39 Table of Contents 101

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 List of Tables (Continued)

Table 12.2-13c Liquid Radwaste Component InventoriesLCW Demineralizer ............................12.2-40 Table 12.2-13d Liquid Radwaste Component InventoriesLCW Sample Tank ..............................12.2-41 Table 12.2-13e Liquid Radwaste Component InventoriesHCW Collector Tank...........................12.2-42 Table 12.2-13f Liquid Radwaste Component InventoriesHCW Demineralizer ............................12.2-43 Table 12.2-14 Offgas System Inventories ........................................................................................12.2-44 Table 12.2-15a Solid Radwaste Component Inventories CUW Backwash Receiving Tank .............12.2-46 Table 12.2-15b Solid Radwaste Component Inventories CF Backwash Receiving Tank..................12.2-47 Table 12.2-15c Solid Radwaste Component Inventories Phase Separator.........................................12.2-48 Table 12.2-15d Solid Radwaste Component Inventories Spent Resin Storage Tank.........................12.2-49 Table 12.2-15e Solid Radwaste Component Inventories Concentrated Waste Tank.........................12.2-50 Table 12.2-15f Solid Radwaste Component Inventories Solids Dryer Feed Tank ............................12.2-51 Table 12.2-15g Solid Radwaste Component Inventories Solids Dryer (Outlet) ................................12.2-52 Table 12.2-15h Solid Radwaste Component Inventories Solids Dryer Pelletizer ..............................12.2-53 Table 12.2-15i Solid Radwaste Component Inventories Solids Mist Separator (Steam) ..................12.2-54 Table 12.2-15j Solid Radwaste Component Inventories Solids Condenser ......................................12.2-55 Table 12.2-15k Solid Radwaste Component Inventories Solids Drum ..............................................12.2-56 Table 12.2-16 FPC Filter Demineralizer ..........................................................................................12.2-57 Table 12.2-17 Radioactive Sources in the Suppression Pool Cleanup System ................................12.2-58 Table 12.2-18a Radioactive Sources in the Control Rod Drive System.............................................12.2-59 Table 12.2-18b Control Blade Principal Isotopes...............................................................................12.2-59 Table 12.2-19 Annual Airborne Releases for Offsite Dose Evaluations (MBq) ..............................12.2-60 Table 12.2-20 Airborne Concentrations ...........................................................................................12.2-63 Table 12.2-21 Average Annual Doses from Airborne Releases.......................................................12.2-66 Table 12.2-22 Annual Average Liquid Releases ..............................................................................12.2-67 Table 12.2-23 Liquid Pathway Dose Analysis (Assuming 5678 L/min Flow and a Dilution Factor of 10) ..............................................................................................................12.2-69 102 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 List of Tables (Continued)

Table 12.2-24 Activity Levels of the Transversing In-Core Probe System......................................12.2-71 Table 12.2-25 Activity Levels in the Reactor Internal Pump ...........................................................12.2-71 Table 12.2-26 Activity in the Turbine Moisture Separator/Reheater ...............................................12.2-72 Table 12.2-27 Activity in the Turbine Condenser ............................................................................12.2-74 Table 12.2-28 Activity in the Condenser Demineralizer ..................................................................12.2-76 Table 12.2-29 Steam Jet Air Ejector Inventory ................................................................................12.2-78 Table 12.2-30 Standby Gas Treatment System Inventory ................................................................12.2-80 Table 12.3-1 Computer Codes Used in Shielding Design Calculations .........................................12.3-34 Table 12.3-2 Typical Nickel and Cobalt Content of Materials.......................................................12.3-34 Table 12.3-3 Area Radiation Monitors Reactor Building...............................................................12.3-35 Table 12.3-4 Area Radiation Monitors Control Building...............................................................12.3-36 Table 12.3-5 Area Radiation Monitors Service Building ...............................................................12.3-36 Table 12.3-6 Area Radiation Monitors Radwaste Building............................................................12.3-36 Table 12.3-7 Area Radiation Monitors Turbine Building ..............................................................12.3-37 Table 12.3-8 Regulatory Guide 4.21 Design Objective and Applicable DCD Subsection Information ................................................................................................................12.3-38 Table 12.4-1 Projected Annual Radiation Exposure.........................................................................12.4-8 Table of Contents 103

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 List of Figures Figure 12.2-1 Radiation Source Model.........................................................................................12.2-81 Figure 12.3-1 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation -8200 mm (B3F) ...............................................................12.3-47 Figure 12.3-2 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation -1700 mm (B2F) ...............................................................12.3-47 Figure 12.3-3 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 4800/8500 mm (B1F)........................................................12.3-47 Figure 12.3-4 Not Used.................................................................................................................12.3-47 Figure 12.3-5 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 12300 mm (1F) .................................................................12.3-47 Figure 12.3-6 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 18100 mm (2F) .................................................................12.3-47 Figure 12.3-7 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 23500 mm (3F) .................................................................12.3-47 Figure 12.3-8 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 27200 mm (3.5F) ..............................................................12.3-47 Figure 12.3-9 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 31700/38200 mm (4FM)...................................................12.3-47 Figure 12.3-10 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation, Section A-A..........................................................................................12.3-47 Figure 12.3-11 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation, Section B-B ..........................................................................................12.3-47 Figure 12.3-12 Reactor Building Radiation Zone Map Post LOCA at Elevation -8200 mm (B3F) ....................................................................................12.3-47 Figure 12.3-13 Reactor Building Radiation Zone Map Post LOCA at Elevation -1700 mm (B2F) ....................................................................................12.3-47 Figure 12.3-14 Reactor Building Radiation Zone Map Post LOCA at Elevation 4800/8500 mm (B1F).............................................................................12.3-47 Figure 12.3-15 Not Used.................................................................................................................12.3-47 Figure 12.3-16 Reactor Building Radiation Zone Map Post LOCA at Elevation 12300 mm (1F) ......................................................................................12.3-47 Figure 12.3-17 Reactor Building Radiation Zone Map Post LOCA at Elevation 18100 mm (2F) ......................................................................................12.3-47 104 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 List of Figures (Continued)

Figure 12.3-18 Reactor Building Radiation Zone Map Post LOCA at Elevation 23500 mm (3F) ......................................................................................12.3-48 Figure 12.3-19 Reactor Building Radiation Zone Map Post LOCA at Elevation 27200 mm (3.5F) ...................................................................................12.3-48 Figure 12.3-20 Reactor Building Radiation Zone Map Post LOCA at Elevation 31700/38200 mm (4FM)........................................................................12.3-48 Figure 12.3-21 Reactor Building Radiation Zone Map Post LOCA, Section A-A ........................12.3-48 Figure 12.3-22 Reactor Building Radiation Zone Map Post LOCA, Section B-B.........................12.3-48 Figures 12.3-23 thru 12.3-36 Not Used............................................................................................12.3-48 Figure 12.3-37 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation -1500 mm ...............................................................................................12.3-48 Figure 12.3-38 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation -4800 mm...............................................................................................12.3-48 Figure 12.3-39 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation 12300 mm ..............................................................................................12.3-48 Figure 12.3-40 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation 21000 mm ..............................................................................................12.3-48 Figure 12.3-41 Radwaste Building, Radiation Zone Map, Normal Operation, Section A-A.........12.3-48 Figure 12.3-42 Control Building, Radiation Zone, Normal Operation at Elevation -8200 mm ....12.3-48 Figure 12.3-43 Control and Service Building, Radiation Zone, Normal Operation at Elevation -2150 mm...............................................................................................12.3-48 Figure 12.3-44 Control and Service Building, Radiation Zone, Normal Operation at Elevation 3500 mm ................................................................................................12.3-48 Figure 12.3-45 Control and Service Building, Radiation Zone, Normal Operation at Elevation 7900 mm ................................................................................................12.3-48 Figure 12.3-46 Control and Service Building, Radiation Zone, Normal Operation at Elevation 12300 mm ..............................................................................................12.3-48 Figure 12.3-47 Control and Service Building, Radiation Zone, Normal Operation at Elevation 17150 mm ..............................................................................................12.3-48 Figure 12.3-48 Control and Service Building, Radiation Zone, Normal Operation, Side View, Cross Section B-B .......................................................................................12.3-48 Figure 12.3-49 Turbine Building, Radiation Zone at Elevation 5300 mm .....................................12.3-49 Table of Contents 105

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 12 List of Figures (Continued)

Figure 12.3-50 Turbine Building, Radiation Zone at Elevation 12300 mm ...................................12.3-49 Figure 12.3-51 Turbine Building, Radiation Zone at Elevation 20300 mm ...................................12.3-49 Figure 12.3-52 Turbine Building, Radiation Zone at Elevation 30300 mm ...................................12.3-49 Figure 12.3-53 Turbine Building, Radiation Zone at Normal Operation Longitudinal Section A-A............................................................................................................12.3-49 Figure 12.3-54 Control and Service Building, Radiation Zone, Post LOCA, Section B-B............12.3-49 Figure 12.3-55 Turbine Building, Radiation Zone, Post LOCA, Longitudinal Section A-A.........12.3-49 Figure 12.3-56 Reactor Building, Area Radiation Monitors at Elevation -8200 mm.....................12.3-49 Figure 12.3-57 Reactor Building, Area Radiation Monitors at Elevation -1700 mm.....................12.3-49 Figure 12.3-58 Reactor Building, Area Radiation Monitors at Elevation 4800/8500 mm.............12.3-49 Figure 12.3-59 Reactor Building, Area Radiation Monitors at Elevation 12300 mm ....................12.3-49 Figure 12.3-60 Reactor Building, Area Radiation Monitors at Elevation 23500 mm ....................12.3-49 Figure 12.3-61 Reactor Building, Area Radiation Monitors at Elevation 27200 mm ....................12.3-49 Figure 12.3-62 Reactor Building, Area Radiation Monitors at Elevation 31700/38200 mm.........12.3-49 Figure 12.3-63 Reactor Building, Area Radiation Monitors, Section B-B.....................................12.3-49 Figure 12.3-64 Control and Service Buildings, Area Radiation Monitors, Section B-B................12.3-49 Figure 12.3-65 Radwaste Building, Area Radiation Monitors at Elevation -1500 mm .................12.3-49 Figure 12.3-66 Radwaste Building, Area Radiation Monitors at Elevation 4800 mm...................12.3-49 Figure 12.3-67 Radwaste Building, Area Radiation Monitors at Elevation 12300 mm.................12.3-49 Figure 12.3-68 Radwaste Building, Area Radiation Monitors at Elevation 21000 mm.................12.3-49 Figure 12.3-69 Not Used.................................................................................................................12.3-49 Figure 12.3-70 Turbine Building, Area Radiation Monitors at Elevation 12300 mm....................12.3-49 Figure 12.3-71 Turbine Building, Area Radiation Monitors at Elevation 20300 mm....................12.3-50 Figure 12.3-72 Turbine Building, Area Radiation Monitors at Elevation 30300 mm....................12.3-50 Figure 12.3-73 Turbine Building, Area Radiation Monitors, Longitudinal Section A-A ..............12.3-50 Figure 12.3-74 Upper Drywell Shielding Radiation Dose Rates with Fuel Bundle on Refueling Bellows (Gy/h) .......................................................................................................12.3-51 106 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 13 Table of Contents 13.0 Conduct of Operations .................................................................................................................13.1-1 13.1 Organizational Structure of Applicant.........................................................................................13.1-1 13.2 Training........................................................................................................................................13.2-1 13.2.1 Reactor Operator Training...........................................................................................13.2-1 13.2.2 Training For Non-Licensed Plant Staff .......................................................................13.2-1 13.2.3 COL License Information............................................................................................13.2-1 13.3 Emergency Planning ....................................................................................................................13.3-1 13.3.1 COL License Information............................................................................................13.3-1 13.3.2 References ...................................................................................................................13.3-1 13.4 Review and Audit ........................................................................................................................13.4-1 13.4.1 COL License Information............................................................................................13.4-1 13.5 Plant Procedures ..........................................................................................................................13.5-1 13.5.1 Administrative Procedures ..........................................................................................13.5-1 13.5.2 Operating and Maintenance Procedures......................................................................13.5-1 13.5.3 COL License Information............................................................................................13.5-1 13.5.4 References ...................................................................................................................13.5-9 13.6 Physical Security..........................................................................................................................13.6-1 13.6.1 Preliminary Planning ...................................................................................................13.6-1 13.6.2 Security Plan................................................................................................................13.6-1 13.6.3 COL License Information............................................................................................13.6-1 Table of Contents 107

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 13 List of Tables Table 13.3-1 ABWR Design Considerations for Emergency Planning Requirements ....................13.3-2 108 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 14 Table of Contents 14.0 Initial Test Program .....................................................................................................................14.1-1 14.1 Specific Information to be Included in Preliminary Safety Analysis Reports.............................14.1-1 14.2 Specific Information to be Included in Final Safety Analysis Reports .......................................14.2-1 14.2.1 Summary of Test Programs and Objectives ................................................................14.2-1 14.2.2 Organization and Staffing............................................................................................14.2-3 14.2.3 Test Procedures ...........................................................................................................14.2-5 14.2.4 Conduct of Test Program.............................................................................................14.2-5 14.2.5 Review, Evaluation, and Approval of Test Results.....................................................14.2-6 14.2.6 Test Records ................................................................................................................14.2-6 14.2.7 Conformance of Test Program with Regulatory Guides .............................................14.2-6 14.2.8 Utilization of Reactor Operating and Testing Experience in the Development of Test Program ...........................................................................................................14.2-7 14.2.9 Trial Use of Plant Operating and Emergency Procedures...........................................14.2-7 14.2.10 Initial Fuel Loading and Initial Criticality...................................................................14.2-8 14.2.11 Test Program Schedule................................................................................................14.2-9 14.2.12 Individual Test Descriptions......................................................................................14.2-10 14.2.13 COL License Information........................................................................................14.2-181 14.3 Tier 1 Selection Criteria and Processes .......................................................................................14.3-1 14.3.1 Tier 1 Section: 1.0 Introduction...................................................................................14.3-3 14.3.2 Tier 1 Section: 2.0 Certified Design Material for ABWR Systems ............................14.3-3 14.3.3 Tier 1 Section: 3.0 Additional Design Material ........................................................14.3-14 14.3.4 Tier 1 Section: 4.0 Interface Requirements...............................................................14.3-19 14.3.5 Tier 1 Section: 5.0 Site Parameters ...........................................................................14.3-21 14.3.6 Summary....................................................................................................................14.3-21 Table of Contents 109

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 14 List of Tables Table 14.2-1 Startup Test Matrix..................................................................................................14.2-183 Table 14.3-1 Core Cooling Analysis ..............................................................................................14.3-23 Table 14.3-2 Containment Pressure/Temperature Response ..........................................................14.3-26 Table 14.3-3 Transient Analysis .....................................................................................................14.3-28 Table 14.3-4 Radiological Analysis................................................................................................14.3-31 Table 14.3-5 Overpressure Protection ............................................................................................14.3-32 Table 14.3-6 Flooding Protection ...................................................................................................14.3-33 Table 14.3-7 Fire Protection ...........................................................................................................14.3-36 Table 14.3-8 ATWS Analysis.........................................................................................................14.3-37 Table 14.3-9 Generic Safety Issues ................................................................................................14.3-40 Table 14.3-10 TMI Issues .................................................................................................................14.3-48 Table 14.3-11 Example of Tier 1 ITAAC Entry: Standby Liquid Control (SLC) System...............14.3-57 Table 14.3-12 Interface Requirements for the Ultimate Heat Sink ..................................................14.3-58 110 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 14 List of Figures Figure 14.2-1 Power-Flow Operating Map and Testing Plateau Definitions .............................14.2-191 Table of Contents 111

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 Table of Contents 15.0 Accident and Analysis .................................................................................................................15.0-1 15.0.1 Nuclear Safety Operational Analysis ..........................................................................15.0-1 15.0.2 Event Analytical Objective..........................................................................................15.0-2 15.0.3 Analytical Categories ..................................................................................................15.0-2 15.0.4 Event Evaluation .........................................................................................................15.0-2 15.0.5 COL License Information............................................................................................15.0-6 15.1 Decrease in Reactor Coolant Temperature ..................................................................................15.1-1 15.1.1 Loss of Feedwater Heating..........................................................................................15.1-1 15.1.2 Feedwater Controller FailureMaximum Demand ...................................................15.1-3 15.1.3 Pressure Regulator FailureOpen..............................................................................15.1-7 15.1.4 Inadvertent Safety/Relief Valve Opening .................................................................15.1-10 15.1.5 Spectrum of Steam System Piping Failures Inside and Outside Containment in a PWR....................................................................................................................15.1-12 15.1.6 Inadvertent RHR Shutdown Cooling Operation........................................................15.1-12 15.2 Increase in Reactor Pressure ........................................................................................................15.2-1 15.2.1 Pressure Regulator FailureClosed ...........................................................................15.2-1 15.2.2 Generator Load Rejection............................................................................................15.2-4 15.2.3 Turbine Trip.................................................................................................................15.2-8 15.2.4 MSIV Closures ..........................................................................................................15.2-12 15.2.5 Loss of Condenser Vacuum.......................................................................................15.2-16 15.2.6 Loss of Non-Emergency AC Power to Station Auxiliaries.......................................15.2-19 15.2.7 Loss of Feedwater Flow ............................................................................................15.2-22 15.2.8 Feedwater Line Break................................................................................................15.2-24 15.2.9 Failure of RHR Shutdown Cooling ...........................................................................15.2-24 15.2.10 COL License Information..........................................................................................15.2-25 15.2.11 References .................................................................................................................15.2-25 15.3 Decrease in Reactor Coolant System Flow Rate .........................................................................15.3-1 15.3.1 Reactor Internal Pump Trip .........................................................................................15.3-1 15.3.2 Recirculation Flow Control FailureDecreasing Flow..............................................15.3-5 15.3.3 Reactor Internal Pump Seizure....................................................................................15.3-7 15.3.4 Reactor Internal Pump Shaft Break.............................................................................15.3-9 15.3.5 References .................................................................................................................15.3-10 15.4 Reactivity and Power Distribution Anomalies ............................................................................15.4-1 15.4.1 Rod Withdrawal ErrorLow Power...........................................................................15.4-1 15.4.2 Rod Withdrawal Error at Power ..................................................................................15.4-5 15.4.3 Control Rod Maloperation (System Malfunction or Operator Error) .........................15.4-6 15.4.4 Abnormal Startup of Idle Reactor Internal Pump........................................................15.4-6 15.4.5 Recirculation Flow Control Failure with Increasing Flow..........................................15.4-7 15.4.6 Chemical and Volume Control System Malfunctions...............................................15.4-10 15.4.7 Mislocated Bundle Accident .....................................................................................15.4-10 15.4.8 Misoriented Fuel Bundle Accident............................................................................15.4-12 15.4.9 Rod Ejection Accident...............................................................................................15.4-13 15.4.10 Control Rod Drop Accident.......................................................................................15.4-14 15.4.11 COL License Information..........................................................................................15.4-16 112 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 Table of Contents (Continued) 15.4.12 References .................................................................................................................15.4-16 15.5 Increase in Reactor Coolant Inventory ........................................................................................15.5-1 15.5.1 Inadvertent HPCF Startup ...........................................................................................15.5-1 15.5.2 Chemical Volume Control System Malfunction (or Operator Error) .........................15.5-2 15.5.3 BWR Transients Which Increase Reactor Coolant Inventory.....................................15.5-2 15.6 Decrease in Reactor Coolant Inventory .......................................................................................15.6-1 15.6.1 Inadvertent Safety/Relief Valve Opening ...................................................................15.6-1 15.6.2 Failure of Small Line Carrying Primary Coolant Outside Containment.....................15.6-1 15.6.3 Steam Generator Tube Failure.....................................................................................15.6-3 15.6.4 Steam System Piping Break Outside Containment .....................................................15.6-3 15.6.5 Loss-of-Coolant Accident (Resulting from Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary)Inside Containment.........15.6-7 15.6.6 Cleanup Water Line BreakOutside Containment ..................................................15.6-18 15.6.7 COL License Information..........................................................................................15.6-21 15.6.8 References .................................................................................................................15.6-21 15.7 Radioactive Release from Subsystems and Components ............................................................15.7-1 15.7.1 Radiological Consequences of a Radioactive Gas Waste System Leak or Failure.....15.7-1 15.7.2 Liquid Radioactive System Failure .............................................................................15.7-2 15.7.3 Postulated Radioactive Release Due to Liquid Radwaste Tank Failure .....................15.7-2 15.7.4 Fuel-Handling Accident ..............................................................................................15.7-4 15.7.5 Spent Fuel Cask Drop Accident ..................................................................................15.7-9 15.7.6 COL License Information..........................................................................................15.7-10 15.7.7 References .................................................................................................................15.7-10 15.8 Anticipated Transients Without Scram........................................................................................15.8-1 15.8.1 Requirements...............................................................................................................15.8-1 15.8.2 Plant Capabilities.........................................................................................................15.8-1 15A Plant Nuclear Safety Operational Analysis (NSOA) ...................................................................15A-1 15A.1 Objectives ....................................................................................................................15A-1 15A.2 Approach to Operational Nuclear Safety ....................................................................15A-2 15A.3 Method of Analysis .....................................................................................................15A-8 15A.4 Display of Operational Analysis Results...................................................................15A-17 15A.5 Bases for Selecting Surveillance Test Frequencies and Allowable Outage Times.............................................................................................................15A-19 15A.6 Operational Analyses.................................................................................................15A-20 15A.7 Remainder of NSOA .................................................................................................15A-43 15A.8 Conclusions ...............................................................................................................15A-44 15B Failure Modes and Effects Analysis (FMEA) ............................................................................. 15B-1 15B.1 Introduction ................................................................................................................. 15B-1 15B.2 Control Rod Drive System .......................................................................................... 15B-1 15B.3 Reactor Internal Pump................................................................................................. 15B-9 15B.4 Essential Multiplexing System .................................................................................. 15B-16 15C Not Used ...................................................................................................................................... 15C-1 Table of Contents 113

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 Table of Contents (Continued) 15D Probability Analysis of Pressure Regulator Downscale Failure ..................................................15D-1 15D.1 Introduction .................................................................................................................15D-1 15D.2 System Description......................................................................................................15D-1 15D.3 Analysis .......................................................................................................................15D-1 15D.4 Results .........................................................................................................................15D-2 15E ATWS Performance Evaluation .................................................................................................. 15E-1 15E.1 Introduction ................................................................................................................. 15E-1 15E.2 Performance Requirements ......................................................................................... 15E-1 15E.3 Analysis Conditions..................................................................................................... 15E-1 15E.4 ATWS Logic and Setpoints......................................................................................... 15E-2 15E.5 Selection of Events ...................................................................................................... 15E-3 15E.6 Transient Responses .................................................................................................... 15E-5 15E.7 Conclusion................................................................................................................... 15E-9 15E.8 Reference..................................................................................................................... 15E-9 15F LOCA Inventory Curves...............................................................................................................15F-1 15F.1 Introduction ..................................................................................................................15F-1 114 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Tables Table 15.0-1 Input Parameters and Initial Conditions for System Response Analysis Transients ....................................................................................................................15.0-7 Table 15.0-1a Computer Codes Used in the Analysis of Transients and Accidents ........................15.0-10 Table 15.0-2 Results Summary of System Response Analysis Transient Events ..........................15.0-12 Table 15.0-3 Summary of Accidents ..............................................................................................15.0-17 Table 15.0-4 Core-Wide Transient Analysis Results To Be Provided for Different Core Design ...............................................................................................................15.0-17 Table 15.0-5 Scram Reactivity Curves ...........................................................................................15.0-18 Table 15.0-6 ABWR FMCRD Scram Time ...................................................................................15.0-18 Table 15.1-1 Sequence of Events for Loss of Feedwater Heating..................................................15.1-14 Table 15.1-2 Loss of 55.6°C Feedwater Heating............................................................................15.1-14 Table 15.1-2a Loss of 16.7°C Feedwater Heating............................................................................15.1-14 Table 15.1-3 Single Failure Modes for Digital Controls ................................................................15.1-15 Table 15.1-4 Sequence of Events for Figure 15.1-2 .......................................................................15.1-15 Table 15.1-5 Sequence of Events for Figure 15.1-3 .......................................................................15.1-16 Table 15.1-6 Sequence of Events for Figure 15.1-4 .......................................................................15.1-16 Table 15.1-7 Sequence of Events for Figure 15.1-5 .......................................................................15.1-17 Table 15.1-8 Sequence of Events for Inadvertent Safety/Relief Valve Opening ...........................15.1-17 Table 15.1-9 Sequence of Events for Inadvertent RHR Shutdown Cooling Operation .................15.1-18 Table 15.2-1a Sequence of Events for Figure 15.2-1 .......................................................................15.2-26 Table 15.2-1b Sequence of Events for Figure 15.2-1a .....................................................................15.2-26 Table 15.2-2 Sequence of Events for Figure 15.2-2 .......................................................................15.2-26 Table 15.2-3 Sequence of Events for Figure 15.2-3 .......................................................................15.2-27 Table 15.2-4 Sequence of Events for Figure 15.2-4 .......................................................................15.2-27 Table 15.2-5 Sequence of Events for Figure 15.2-5 .......................................................................15.2-28 Table 15.2-6 Sequence of Events for Figure 15.2-6 .......................................................................15.2-28 Table 15.2-7 Sequence of Events for Figure 15.2-7 .......................................................................15.2-28 Table of Contents 115

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Tables (Continued)

Table 15.2-8 Sequence of Events for Figure 15.2-8 .......................................................................15.2-29 Table 15.2-9 Sequence of Events for Figure 15.2-9 .......................................................................15.2-29 Table 15.2-10 Post-Transient Primary Containment Inventory (Air Plus Water)

(megabecqueral) ........................................................................................................15.2-30 Table 15.2-11 Activity Released to the Environment (megabecqueral)...........................................15.2-31 Table 15.2-12 Dose Evaluation and Meteorology ............................................................................15.2-31 Table 15.2-13 Typical Rates of Decay for Condenser Vacuum .......................................................15.2-32 Table 15.2-14 Sequence of Events for Figure 15.2-10 .....................................................................15.2-32 Table 15.2-15 Trip Signals Associated with Loss of Condenser Vacuum .......................................15.2-32 Table 15.2-16 Sequence of Events for Figure 15.2-11 .....................................................................15.2-33 Table 15.2-17 Sequence of Events for Figure 15.2-12 .....................................................................15.2-34 Table 15.3-1 Sequence of Events for Figure 15.3-1 .......................................................................15.3-11 Table 15.3-2 Sequence of Events for Figure 15.3-2 .......................................................................15.3-11 Table 15.3-3 Sequence of Events for Figure 15.3-3 .......................................................................15.3-11 Table 15.3-4 Sequence of Events for Figure 15.3-4 .......................................................................15.3-12 Table 15.3-5 Sequence of Events for Figure 15.3-5 .......................................................................15.3-12 Table 15.4-1 Causes of Control Rod Withdrawal Error .................................................................15.4-17 Table 15.4-2 Sequence of Events for Continuous Control Rod Withdrawal Error During Reactor Startup ..........................................................................................................15.4-17 Table 15.4-3 Sequence of Events for Abnormal Startup of Idle RIP .............................................15.4-18 Table 15.4-4 Sequence of Events for Figure 15.4-2 .......................................................................15.4-18 Table 15.4-5 Sequence of Events for Figure 15.4-3 .......................................................................15.4-18 Table 15.4-6 Sequence of Events of the Mislocated Bundle Accident...........................................15.4-19 Table 15.4-7 Sequence of Events of the Misoriented Fuel Bundle Accident.................................15.4-19 Table 15.5-1 Sequence of Events for Figure 15.5-1 .........................................................................15.5-3 Table 15.6-1 Instrument Line Break Accident Parameters.............................................................15.6-22 Table 15.6-2 Instrument Line Break Accident Isotopic Inventory .................................................15.6-23 116 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Tables (Continued)

Table 15.6-3 Instrument Line Break Accident Results...................................................................15.6-24 Table 15.6-4 Sequence of Events for Steamline Break Outside Containment ...............................15.6-24 Table 15.6-5 Steamline Break Accident Parameters ......................................................................15.6-25 Table 15.6-6 Main Steamline Break Accident Activity Released to Environment (megabecquerel) ........................................................................................................15.6-26 Table 15.6-7 Main Steamline Break Meteorology Parameters and Radiological Effects ..............15.6-27 Table 15.6-8 Loss of Coolant Accident Parameters .......................................................................15.6-28 Table 15.6-9 Iodine Activities ........................................................................................................15.6-30 Table 15.6-10 Iodine Activity Release to the Environment .............................................................15.6-32 Table 15.6-11 Noble Gas Activities..................................................................................................15.6-34 Table 15.6-12 Noble Gas Activity Release to Environment.............................................................15.6-37 Table 15.6-13 Loss of Coolant Accident Meteorology and Offsite Dose Results............................15.6-38 Table 15.6-14 Loss of Coolant Accident Meteorology and Control Room Dose Results................15.6-38 Table 15.6-15 Sequence of Events for Cleanup Line Break Outside Containment..........................15.6-39 Table 15.6-16 Cleanup Line Break Accident Parameters.................................................................15.6-39 Table 15.6-17 Clean Up Water Line Break Isotopic Releases (megabecquerel) .............................15.6-40 Table 15.6-18 Clean Up Water Line Break Meteorology and Dose Results....................................15.6-40 Table 15.7-1 Offgas System Failure Accident Parameters.............................................................15.7-11 Table 15.7-2 Isotopic Source and Release to the Environment ......................................................15.7-12 Table 15.7-3 Offgas System Failure Meteorology and Dose Results.............................................15.7-12 Table 15.7-4 Not Used....................................................................................................................15.7-13 Table 15.7-5 Radwaste System Failure Accident Parameters ........................................................15.7-14 Table 15.7-6 Isotopic Release to Environment (megabecquerel)...................................................15.7-14 Table 15.7-7 Radwaste System Failure Accident Meteorology and Dose Results.........................15.7-14 Table 15.7-8 Fuel-Handling Accident Parameters..........................................................................15.7-15 Table 15.7-9 Fuel-Handling Accident Reactor Building Inventory (megabecquerel) ...................15.7-16 Table of Contents 117

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Tables (Continued)

Table 15.7-10 Fuel-Handling Accident Isotopic Release to Environment (megabecquerel) ..........15.7-17 Table 15.7-11 Fuel-Handling Accident Meteorologial Parameters And Radiological Effects ........15.7-18 Table 15.7-12 Fuel Cask Drop Accident Parameters........................................................................15.7-18 Table 15.7-13 Cask Drop Accident Radiological Results Fission Product Releases (megabecquerel) ........................................................................................................15.7-19 Table 15A-1 Unacceptable Consequences Criteria Plant Event Category: Normal Operation......15A-45 Table 15A-2 Unacceptable Consequences Criteria Plant Event Category: Moderate Frequency Incidents (Anticipated Operational Transients).........................................................15A-45 Table 15A-3 Unacceptable Consequences Criteria Plant Event Category: Infrequent Incidents (Abnormal Operational Transients)...........................................................................15A-45 Table 15A-4 Unacceptable Consequences Criteria Plant Event Category: Limiting Faults (Design Basis Accidents) ..........................................................................................15A-46 Table 15A-5 Capability Consequences Plant Event Category: Special Events..............................15A-46 Table 15A-6 General Nuclear Safety Operational Criteria ............................................................15A-47 Table 15A-7 BWR Operating States ..............................................................................................15A-47 Table 15A-8 Normal Operation......................................................................................................15A-48 Table 15A-9 Moderate Frequency Accidents (Anticipated Operational Transients) .....................15A-49 Table 15A-10 Infrequent Accidents (Abnormal Operational Transients) ........................................15A-51 Table 15A-11 Limiting Faults (Design Basis Accidents).................................................................15A-52 Table 15A-12 Special Events ...........................................................................................................15A-53 Table 15A-13 Safety Actions for Infrequent Incidents ....................................................................15A-53 Table 15A-14 Safety Actions for Design Basis Accidents...............................................................15A-54 Table 15A-15 Safety Actions for Special Events .............................................................................15A-55 Table 15B-1 Failure Mode and Effects Analysis for FMCRD....................................................... 15B-17 Table 15B-2 Failure Mode and Effects Analysis for HCU Charging Water.................................. 15B-26 Table 15B-3 EMS Failure Mode and Effects Analysis .................................................................. 15B-28 Table 15D-1 Logic Equations...........................................................................................................15D-3 Table 15E-1 Performance Requirements ....................................................................................... 15E-10 118 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Tables (Continued)

Table 15E-2 Initial Operating Conditions ...................................................................................... 15E-10 Table 15E-3 Equipment Performance Characteristics ................................................................... 15E-11 Table 15E-4 MSIV Closure Summary (ARI)................................................................................. 15E-12 Table 15E-5 MSIV Closure Summary (FMCRD Run-In) ............................................................. 15E-12 Table 15E-6 MSIV Closure Summary (Boron Injection) .............................................................. 15E-12 Table 15E-7 Loss of AC Power Summary (ARI) .......................................................................... 15E-12 Table 15E-8 Loss of AC Power Summary (FMCRD Run-In)....................................................... 15E-13 Table 15E-9 Loss of AC Power Summary (Boron Injection) ........................................................ 15E-13 Table 15E-10 Loss of Feedwater Summary (ARI) .......................................................................... 15E-13 Table 15E-11 Loss of Feedwater Summary (FMCRD Run-In) ....................................................... 15E-13 Table 15E-12 Loss of Feedwater Summary (Boron Injection) ........................................................ 15E-14 Table 15E-13 Loss of Feedwater Heating Summary (FMCRD Run-In) ......................................... 15E-14 Table 15E-14 Turbine Trip with Bypass Summary (ARI)............................................................... 15E-14 Table 15E-15 Turbine Trip with Bypass Summary (FMCRD Run-In) ........................................... 15E-14 Table 15E-16 Turbine Trip with Bypass Summary (Boron Injection) ............................................ 15E-15 Table 15E-17 Loss of Condenser Vacuum Summary (ARI) ........................................................... 15E-15 Table 15E-18 Loss of Condenser Vacuum (FMCRD Run-In)......................................................... 15E-15 Table 15E-19 Loss of Condenser Vacuum Summary (Boron Injection) ......................................... 15E-15 Table 15E-20 Feedwater Controller Failure Summary (ARI).......................................................... 15E-16 Table 15E-21 Feedwater Controller Failure Summary (FMCRD Run-In) ...................................... 15E-16 Table 15E-22 Feedwater Controller Failure Summary (Boron Injection) ....................................... 15E-16 Table of Contents 119

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures Figure 15.0-1 System Response Analysis Power/Flow Map........................................................15.0-19 Figure 15.1-1 Simplified Block Diagram of Fault-Tolerant Digital Controller System...............15.1-19 Figure 15.1-2 Runout of One Feedwater Pump ............................................................................15.1-20 Figure 15.1-3 Feedwater Controller FailureMaximum Demand ..............................................15.1-21 Figure 15.1-4 Inadvertent Opening of One Bypass Valve............................................................15.1-22 Figure 15.1-5 Opening of All Control and Bypass Valves ...........................................................15.1-23 Figure 15.2-1 Fast Closure of One Turbine Control Valve ..........................................................15.2-35 Figure 15.2-1a Slow Closure of One Turbine Control Valve.........................................................15.2-39 Figure 15.2-2 Pressure Regulator Downscale Failure ..................................................................15.2-43 Figure 15.2-3 Generator Load Rejection with Bypass..................................................................15.2-44 Figure 15.2-4 Load Rejection with One Bypass Valve Failure ....................................................15.2-45 Figure 15.2-5 Load Rejection with All Bypass Valves Failure ....................................................15.2-46 Figure 15.2-6 Turbine Trip with Bypass.......................................................................................15.2-47 Figure 15.2-7 Turbine Trip with One Bypass Valve Failure ........................................................15.2-48 Figure 15.2-8 Turbine Trip with All Bypass Valves Failure ........................................................15.2-49 Figure 15.2-9 MSIV Closure Direct Scram ..................................................................................15.2-50 Figure 15.2-10 Loss of Condenser Vacuum ...................................................................................15.2-51 Figure 15.2-11 Loss of AC Power ..................................................................................................15.2-52 Figure 15.2-12 Loss of All Feedwater Flow ...................................................................................15.2-53 Figure 15.2-13 Loss of All Feedwater Flow ...................................................................................15.2-54 Figure 15.3-1 Three Pump Trip ....................................................................................................15.3-13 Figure 15.3-2 All Pump Trip ........................................................................................................15.3-14 Figure 15.3-2a Cladding Temperature During All Pump Trip .......................................................15.3-15 Figure 15.3-3 Fast Runback of One RIP.......................................................................................15.3-16 Figure 15.3-4 Fast Runback of All RIPs.......................................................................................15.3-17 Figure 15.3-5 One RIP Seizure .....................................................................................................15.3-18 120 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures (Continued)

Figure 15.4-1 Transient Changes for Control Rod Withdrawal Error During Startup .................15.4-20 Figure 15.4-2 Fast Runout of One RIP .........................................................................................15.4-21 Figure 15.4-3 Fast Runout of All RIPs .........................................................................................15.4-22 Figure 15.5-1 Inadvertent Startup of HPCF....................................................................................15.5-4 Figure 15.6-1 Steam Flow Schematic for Steam Break Outside Containment.............................15.6-41 Figure 15.6-2 LOCA Radiological Analysis ................................................................................15.6-42 Figure 15.6-3 Airborne Iodine in Primary Containment During Blowdown Phase .....................15.6-43 Figure 15.6-4 ABWR Plant Layout ..............................................................................................15.6-43 Figure 15.6-5 Leakage Path for Clean Up Water Line Break.......................................................15.6-44 Figure 15.6-6 ABWR Limiting LPZ CHI/Q.................................................................................15.6-45 Figure 15.7-1 Leakage Path for Fuel-Handling Accident.............................................................15.7-20 Figure 15.7-2 Offgas System (See Subsection 11.3) ....................................................................15.7-21 Figure 15A-1 Block Diagram of Method Used to Derive Nuclear Safety Operational Requirements System-Level Qualitative Design Basis Confirmation Audits and Technical Specifications..................................................................................15A-56 Figure 15A-2 Possible Inconsistencies in the Selection of Nuclear Safety Operational Requirements..........................................................................................................15A-57 Figure 15A-3 Format for Protection Sequence Diagrams ............................................................15A-58 Figure 15A-4 Format for Safety System Auxiliary Diagrams......................................................15A-59 Figure 15A-5 Format for Commonality of Auxiliary Diagrams ..................................................15A-60 Figure 15A-6 Safety System Auxiliaries Group 1...................................................................15A-61 Figure 15A-7 Safety System Auxiliaries Group 2...................................................................15A-62 Figure 15A-8 Safety Action Sequences for Normal Operation in State A ...................................15A-63 Figure 15A-9 Safety Action Sequences for Normal Operation in State B ...................................15A-64 Figure 15A-10 Safety Action Sequences for Normal Operation in State C ...................................15A-65 Figure 15A-11 Safety Action Sequences for Normal Operation in State D ...................................15A-66 Figure 15A-12 Protection Sequence for Manual or Inadvertent Scram .........................................15A-67 Table of Contents 121

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures (Continued)

Figure 15A-13 Protection Sequence for Loss of Plant Instrument or Service Air System ............15A-68 Figure 15A-14 Protection Sequence for Recirculation Flow Control FailureMaximum DemandOne Reactor Internal Pump (RIP) Runout............................................15A-69 Figure 15A-15 Protection Sequence for Recirculation Flow Control FailureDecreasing Flow Runback of One Reactor Internal Pump (RIP) ......................................................15A-70 Figure 15A-16 Protection Sequence for Trip of Three Reactor Internal Pumps (RIPs).................15A-71 Figure 15A-17 Protection Sequences for Isolation of All Main Steamlines ..................................15A-72 Figure 15A-18 Protection Sequences for Isolation of One Main Steamline ..................................15A-73 Figure 15A-19 Protection Sequence for Loss of All Feedwater Flow ...........................................15A-74 Figure 15A-20 Protection Sequence for a Loss of Feedwater Heating ..........................................15A-75 Figure 15A-21 Protection Sequence for Feedwater Controller FailureRunout of One Feedwater Pump.....................................................................................................15A-76 Figure 15A-22 Pressure Regulator FailureOpening of One Bypass Valve ................................15A-77 Figure 15A-23 Pressure Regulator FailureClosure of One Control Valve .................................15A-78 Figure 15A-24 Protection Sequences for Main Turbine Trip, Bypass On .....................................15A-79 Figure 15A-25 Protection Sequences for Loss of Main Condenser Vacuum.................................15A-80 Figure 15A-26 Protection Sequences for Generator Load Rejection, Bypass On..........................15A-81 Figure 15A-27 Protection Sequence for Loss of Normal AC PowerAuxiliary Transformer Failure ....................................................................................................................15A-82 Figure 15A-28 Protection Sequence for Inadvertent Startup of HPCF Pumps ..............................15A-83 Figure 15A-29 Protection Sequences for Inadvertent Opening of a Safety Relief Valve ..............15A-84 Figure 15A-30 Protection Sequence for Control Rod Withdrawal Error for Startup and Refueling Operations .............................................................................................15A-85 Figure 15A-31 Protection Sequences for Main Turbine Trip with Failure of One Bypass Valve ......................................................................................................................15A-86 Figure 15A-32 Protection Sequences for Generator Load Rejection with One Bypass Valve Failure ....................................................................................................................15A-87 Figure 15A-33 Protection Sequence for Control Rod Ejection Accident.......................................15A-88 Figure 15A-34 Protection Sequence for Control Rod Drop Accident............................................15A-89 122 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures (Continued)

Figure 15A-35 Protection Sequence for a Control Rod Withdrawal Error During Power Operation................................................................................................................15A-90 Figure 15A-36 Protection Sequences for Fuel-Handling Accident ................................................15A-91 Figure 15A-37 Protection Sequences for Loss of Coolant Piping Breaks in RCPBInside Containment ...........................................................................................................15A-92 Figure 15A-38 Protection Sequence for Loss of Coolant Piping Breaks in RCPBInside Primary Containment .............................................................................................15A-93 Figure 15A-39 Protection Sequences for Liquid and Steam, Large and Small Piping Breaks Outside Containment..............................................................................................15A-94 Figure 15A-40 Protection Sequence for Liquid and Steam, Large and Small Piping Breaks Outside Primary Containment................................................................................15A-95 Figure 15A-41 Protection Sequence for Gaseous Radwaste System Leak or Failure....................15A-96 Figure 15A-42 Protection Sequence for Augmented Offgas Treatment System Failure ...............15A-97 Figure 15A-43 Protection Sequence for Liquid Radwaste System Leak or Failure.......................15A-98 Figure 15A-44 Protection Sequence for Liquid Radwaste System Storage Tank Failure..............15A-99 Figure 15A-45 Protection Sequence for Abnormal Startup of a Reactor Internal Pump .............15A-100 Figure 15A-46 Protection Sequence for Recirculation Flow Control FailureMaximum DemandAll Reactor Internal Pumps (RIPs) Runout ........................................15A-101 Figure 15A-47 Protection Sequence for Recirculation Flow Control FailureDecreasing FlowRunback of All Reactor Internal Pumps (RIPs).......................................15A-102 Figure 15A-48 Protection Sequence for Trip of All Reactor Internal Pumps (RIPs)...................15A-103 Figure 15A-49 Protection Sequence for RHRLoss of Shutdown Cooling ...............................15A-104 Figure 15A-50 RHRShutdown Cooling FailureIncreased Cooling ......................................15A-105 Figure 15A-51 Protection Sequences for Feedwater Controller FailureRunout of Two Feedwater Pumps .................................................................................................15A-106 Figure 15A-52 Protection Sequences for Pressure Regulator FailureOpening of All Bypass and Control Valves ..................................................................................15A-107 Figure 15A-53 Pressure Regulator FailureClosure of All Bypass Valves and Control Valves...................................................................................................................15A-108 Figure 15A-54 Not Used...............................................................................................................15A-109 Figure 15A-55 Protection Sequences Main Turbine Tripwith Bypass Failure ........................15A-110 Table of Contents 123

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures (Continued)

Figure 15A-56 Protection Sequences Main Generator Load Rejectionwith Bypass Failure ...15A-111 Figure 15A-57 Protection Sequence for Misplaced Fuel Bundle Accident..................................15A-112 Figure 15A-58 Protection Sequence for Reactor Internal Pump Seizure .....................................15A-113 Figure 15A-59 Protection Sequence for RIP Shaft Break ............................................................15A-114 Figure 15A-60 Protection Sequence for Shipping Cask Drop......................................................15A-115 Figure 15A-61 Protection Sequence for Reactor Shutdownfrom Anticipated Transient Without Scram .....................................................................................................15A-116 Figure 15A-62 Protection Sequence for Reactor Shutdownfrom Outside Main Control Room ....................................................................................................................15A-117 Figure 15A-63 Protection Sequence for Reactor ShutdownWithout Control Rods .................15A-118 Figure 15A-64 Protection Sequence for Core and Containment Cooling for Loss of Feedwater and Vessel Isolations ..........................................................................15A-119 Figure 15A-65 Commonality of Auxiliary SystemsDC Power Systems (125/250 Volts) .......15A-120 Figure 15A-66 Commonality of Standby AC Power Systems (120/480/6900 Volts)..................15A-121 Figure 15A-67 Commonality of Auxiliary SystemsReactor Building Cooling Water System (RCWS) ...................................................................................................15A-122 Figure 15A-68 Commonality of Auxiliary SystemsReactor Building Cooling Water System (RCWS) (Continued)...............................................................................15A-123 Figure 15A-69 Commonality of Auxiliary SystemsReactor Building Cooling Water System (RCWS) (Continued)...............................................................................15A-124 Figure 15A-70 Commonality of Auxiliary SystemsSuppression Pool Storage........................15A-125 Figure 15B-1 Simplified CRD System Process Flow Diagram ................................................... 15B-29 Figure 15B-2 Simplified Hydraulic Control Unit P&ID .............................................................. 15B-30 Figure 15B-3 Fine Motion Control Rod Drive ............................................................................. 15B-31 Figure 15B-4 Control Rod Drop Accident Scenario for FMCRD................................................ 15B-32 Figure 15B-5 Control Rod Separation Detection ......................................................................... 15B-33 Figure 15B-6 Internal CRD Blowout Support Schematic ............................................................ 15B-34 Figure 15B-7 FMCRD Internal Support....................................................................................... 15B-35 Figure 15D-1 Triple Redundant Control System............................................................................15D-4 124 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures (Continued)

Figure 15E-1a ATWS Mitigation Logic (ARI, FMCRD Run-In, RPT, Manual Initiation) .......... 15E-17 Figure 15E-1b ATWS Mitigation Logic (SLCS Initiation, Feedwater Runback) ......................... 15E-18 Figure 15E-1c ATWS Mitigation Logic (ADS Inhibit)................................................................. 15E-19 Figure 15E-2 ABWR MSIV Closure, ARI .................................................................................. 15E-20 Figure 15E-3 ABWR MSIV Closure, FMCRD Run-in............................................................... 15E-24 Figure 15E-4 ABWR MSIV Closure, SLCS................................................................................ 15E-28 Figure 15E-5 ABWR MSIV Closure, FMCRD Run-in............................................................... 15E-32 Figure 15E-6 ABWR Loss of AC Power, ARI ............................................................................ 15E-33 Figure 15E-7 ABWR Loss of AC Power, FMCRD Run-in ........................................................ 15E-37 Figure 15E-8 ABWR Loss of AC Power, SLCS.......................................................................... 15E-41 Figure 15E-9 ABWR Loss of Feedwater Flow, ARI ................................................................... 15E-45 Figure 15E-10 ABWR Loss of Feedwater Flow, FMCRD Run-in ............................................... 15E-49 Figure 15E-11 ABWR Loss of Feedwater Flow, SLCS ................................................................ 15E-53 Figure 15E-12 ABWR Loss of Feedwater Heating, ARI............................................................... 15E-57 Figure 15E-13 ABWR Loss of Feedwater Heating, FMCRD Run-in........................................... 15E-61 Figure 15E-14 ABWR Loss of Feedwater Heating, SLCS ............................................................ 15E-65 Figure 15E-15 ABWR Loss of Feedwater Heating, Max. LHGR ................................................. 15E-69 Figure 15E-16 ABWR Loss of Feedwater Heating, FMCRD Run-in........................................... 15E-70 Figure 15E-17 ABWR Turbine Trip w/ Bypass, ARI.................................................................... 15E-71 Figure 15E-18 ABWR Turbine Trip w/ Bypass, FMCRD Run-in ................................................ 15E-75 Figure 15E-19 ABWR Turbine Trip w/ Bypass, SLCS ................................................................. 15E-79 Figure 15E-20 ABWR Loss of Condenser Vacuum, ARI ............................................................. 15E-83 Figure 15E-21 ABWR Loss of Condenser Vacuum, FMCRD Run-in ......................................... 15E-87 Figure 15E-22 ABWR Loss of Condenser Vacuum, SLCS........................................................... 15E-91 Figure 15E-23 ABWR Feedwater Controller Failure Maximum Demand, ARI ........................... 15E-95 Figure 15E-24 ABWR Feedwater Controller Failure Maximum Demand, FMCRD Run-in ....... 15E-99 Table of Contents 125

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 15 List of Figures (Continued)

Figure 15E-25 ABWR Feedwater Contoller Failure Maximum Demand, SLCS ........................ 15E-103 Figure 15F-1 Iodine Airborne Inventory in Primary Containment as a Function of Time.............15F-2 Figure 15F-2 Reactor Building Airborne Inventory as a Function of Time ...................................15F-3 Figure 15F-3 Condenser Inventory from Primary Containment as a Function of Time.................15F-4 Figure 15F-4 Non-Organic I in Pipes and Condenser as a Function of Time.................................15F-5 Figure 15F-5 Releases from Plant as a Function of Time...............................................................15F-6 126 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 16 Table of Contents 16.0 Technical Specifications ..............................................................................................................16.0-1 1.0 Use and Application.......................................................................................................................1.1-1 1.1 Definitions .....................................................................................................................1.1-1 1.2 Logical Connectors........................................................................................................1.2-1 1.3 Completion Times .........................................................................................................1.3-1 1.4 Frequency ......................................................................................................................1.4-1 2.0 Safety Limits (SLs) ........................................................................................................................2.0-1 2.1 SLs.................................................................................................................................2.0-1 2.2 SL Violations.................................................................................................................2.0-1 3.0 Limiting Condition For Operation (LCO) Applicability ...............................................................3.0-1 3.0 Surveillance Requirement (SR) Applicability ...............................................................................3.0-3 3.1 Reactivity Control Systems ...........................................................................................3.1-1 3.1.1 Shutdown Margin (SDM) ...........................................................................3.1-1 3.1.2 Reactivity Anomalies ..................................................................................3.1-4 3.1.3 Control Rod Operability..............................................................................3.1-6 3.1.4 Control Rod Scram Times.........................................................................3.1-10 3.1.5 Control Rod Scram Accumulators ............................................................3.1-13 3.1.6 Rod Pattern Control ..................................................................................3.1-15 3.1.7 Standby Liquid Control (SLC) System .....................................................3.1-17 3.2 Power Distribution Limits .............................................................................................3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) .........................3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) ....................................................3.2-2 3.2.3 Linear Heat Generation Rate (LHGR) (Non-GE Fuel)...............................3.2-3 3.3 Instrumentation..............................................................................................................3.3-1 3.3.1.1 Safety System Logic and Control (SSLC) Sensor Instrumentation ............3.3-1 3.3.1.2 Reactor Protection System (RPS) and Main Steam Isolation Valve (MSIV) Actuation .....................................................................................3.3-20 3.3.1.3 Standby Liquid Control (SLC) and Feedwater Runback (FWRB)

Actuation ...................................................................................................3.3-27 3.3.1.4 ESF Actuation Instrumentation.................................................................3.3-31 3.3.2.1 Startup Range Monitor (SRNM) Instrumentation.....................................3.3-44 3.3.3.1 Essential Multiplexing System (EMS)......................................................3.3-49 3.3.4.1 Anticipated Transient Without Scram (ATWS) and End-of-Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation ............................3.3-51 3.3.4.2 Feedwater and Main Turbine Trip Instrumentation ..................................3.3-58 3.3.5.1 Control Rod Block Instrumentation ..........................................................3.3-60 3.3.6.1 Post Accident Monitoring (PAM) Instrumentation...................................3.3-64 3.3.6.2 Remote Shutdown System ........................................................................3.3-68 3.3.7.1 Control Room Habitability Area (CRHA) Emergency Filtration (EF) System Instrumentation ....................................................................3.3-72 3.3.8.1 Electric Power Monitoring........................................................................3.3-75 3.3.8.2 Reactor Coolant Temperature Monitoring - Shutdown............................3.3-77 3.4 Reactor Coolant System (RCS) .....................................................................................3.4-1 3.4.1 Reactor Internal Pumps (RIPs) - Operating................................................3.4-1 3.4.2 Safety/Relief Valves (S/RVs) .....................................................................3.4-2 Table of Contents 127

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 16 Table of Contents (Continued) 3.4.3 RCS Operational Leakage...........................................................................3.4-4 3.4.4 RCS Pressure Isolation Valve (PIV) Leakage ............................................3.4-6 3.4.5 RCS Leakage Detection Instrumentation....................................................3.4-8 3.4.6 RCS Specific Activity ...............................................................................3.4-11 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System -

Hot Shutdown ...........................................................................................3.4-13 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System -

Cold Shutdown..........................................................................................3.4-16 3.4.9 RCS Pressure and Temperature (P/T) Limits............................................3.4-18 3.4.10 Reactor Steam Dome Pressure ..................................................................3.4-21 3.5 Emergency Core Cooling Systems (ECCS) ..................................................................3.5-1 3.5.1 ECCS - Operating.......................................................................................3.5-1 3.5.2 ECCS - Shutdown ......................................................................................3.5-6 3.6 Containment Systems ....................................................................................................3.6-1 3.6.1.1 Primary Containment ..................................................................................3.6-1 3.6.1.2 Primary Containment Air Locks .................................................................3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs).........................................3.6-8 3.6.1.4 Drywell Pressure .......................................................................................3.6-17 3.6.1.5 Drywell Air Temperature..........................................................................3.6-18 3.6.1.6 Wetwell-to-Drywell Vacuum Breakers.....................................................3.6-19 3.6.2.1 Suppression Pool Average Temperature...................................................3.6-21 3.6.2.2 Suppression Pool Water Level ..................................................................3.6-24 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ......................3.6-25 3.6.2.4 Residual Heat Removal (RHR) Containment Spray.................................3.6-27 3.6.3.1 Primary Containment Hydrogen Recombiners .........................................3.6-29 3.6.3.2 Primary Containment Oxygen Concentration...........................................3.6-31 3.6.4.1 Secondary Containment ............................................................................3.6-32 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)...................................3.6-34 3.6.4.3 Standby Gas Treatment (SGT) System .....................................................3.6-38 3.7 Plant Systems.................................................................................................................3.7-1 3.7.1 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Operating............3.7-1 3.7.2 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Shutdown ...........3.7-4 3.7.3 Reactor Building Cooling Water (RCW) System and Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Refueling............3.7-7 3.7.4 Control Room Habitability Area (CRHA) - Emergency Filtration (EF) System.................................................................................................3.7-9 3.7.5 Control Room Habitability Area (CRHA) - Air Conditioning (AC) System..............................................................................................3.7-12 3.7.6 Main Condenser Offgas ............................................................................3.7-15 3.7.7 Main Turbine Bypass System ...................................................................3.7-17 3.7.8 Fuel Pool Water Level ..............................................................................3.7-19 3.8 Electrical Power Systems ..............................................................................................3.8-1 3.8.1 AC Sources - Operating..............................................................................3.8-1 3.8.2 AC Sources - Refueling............................................................................3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ..............................................3.8-21 128 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 16 Table of Contents (Continued) 3.8.4 DC Sources - Operating............................................................................3.8-24 3.8.5 DC Sources - Shutdown ...........................................................................3.8-28 3.8.6 Battery Cell Parameters.............................................................................3.8-30 3.8.7 Inverters - Operating.................................................................................3.8-34 3.8.8 Inverters - Shutdown ................................................................................3.8-36 3.8.9 Distribution Systems - Operating .............................................................3.8-38 3.8.10 Distribution Systems - Shutdown.............................................................3.8-42 3.8.11 AC Sources - Shutdown (Low Water Level) ...........................................3.8-44 3.9 Refueling Operations.....................................................................................................3.9-1 3.9.1 Refueling Equipment Interlocks .................................................................3.9-1 3.9.2 Refuel Position Rod-Out Interlock..............................................................3.9-2 3.9.3 Control Rod Position...................................................................................3.9-3 3.9.4 Control Rod Position Indication .................................................................3.9-4 3.9.5 Control Rod Operability - Refueling..........................................................3.9-6 3.9.6 Reactor Pressure Vessel (RPV) Water Level..............................................3.9-7 3.9.7 Residual Heat Removal (RHR) - High Water Level ..................................3.9-8 3.9.8 Residual Heat Removal (RHR) - Low Water Level.................................3.9-10 3.10 Special Operations.......................................................................................................3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation...................................3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ...................................................3.10-3 3.10.3 Control Rod Withdrawal - Hot Shutdown................................................3.10-5 3.10.4 Control Rod Withdrawal - Cold Shutdown ..............................................3.10-8 3.10.5 Control Rod Drive (CRD) Removal - Refueling....................................3.10-11 3.10.6 Multiple Control Rod Withdrawal - Refueling ......................................3.10-13 3.10.7 Control Rod Testing - Operating............................................................3.10-15 3.10.8 Shutdown Margin (SDM) Test - Refueling............................................3.10-16 3.10.9 Reactor Internal Pumps (RIPs) - Testing................................................3.10-19 3.10.10 Training Startups.....................................................................................3.10-20 3.10.11 Low Power Physics Test .........................................................................3.10-21 3.10.12 Multiple Control Rod Drive Subassembly Removal - Refueling...........3.10-24 4.0 Design Features..............................................................................................................................4.0-1 4.1 Site.................................................................................................................................4.0-1 4.2 Reactor Core..................................................................................................................4.0-1 4.3 Fuel Storage...................................................................................................................4.0-1 5.0 Administrative Controls.................................................................................................................5.0-1 5.1 Responsibility ................................................................................................................5.0-1 5.2 Organization ..................................................................................................................5.0-2 5.3 Unit Staff Qualifications................................................................................................5.0-5 5.4 Technical Specifications (TS) Bases Control................................................................5.0-6 5.5 Procedures, Programs, and Manuals .............................................................................5.0-7 5.6 Safety Function Determination Program (SFDP)........................................................5.0-15 5.7 Reporting Requirements..............................................................................................5.0-17 Table of Contents 129

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 16 Table of Contents (Continued)

B 2.0 Safety Limits (SLs) .................................................................................................................... B 2.0-1 B 2.1.1 Reactor Core SLs .................................................................................... B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL .......................................... B 2.0-6 B 3.0 Limiting Condition For Operation (LCOs) and Surveillance Requirements (SRs)................... B 3.0-1 B 3.1 Reactivity Control Systems ....................................................................................... B 3.1-1 B 3.1.1 Shutdown Margin (SDM) ....................................................................... B 3.1-1 B 3.1.2 Reactivity Anomalies .............................................................................. B 3.1-6 B 3.1.3 Control Rod Operability........................................................................ B 3.1-10 B 3.1.4 Control Rod Scram Times..................................................................... B 3.1-19 B 3.1.5 Control Rod Scram Accumulators ........................................................ B 3.1-25 B 3.1.6 Rod Pattern Control .............................................................................. B 3.1-29 B 3.1.7 Standby Liquid Control (SLC) System ................................................. B 3.1-33 B 3.2 Power Distribution Limits ......................................................................................... B 3.2-1 B 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ..................... B 3.2-1 B 3.2.2 Minimum Critical Power Ratio (MCPR) ................................................ B 3.2-4 B 3.2.3 Linear Heat Generation Rate (LHGR) (Non-GE Fuel)........................... B 3.2-8 B 3.3 Instrumentation.......................................................................................................... B 3.3-1 B 3.3.1.1 Safety System Logic and Control (SSLC) Sensor Instrumentation ........ B 3.3-1 B 3.3.1.2 Reactor Protection System (RPS) and Main Steam Isolation Valve (MSIV) Actuation ................................................................................. B 3.3-74 B 3.3.1.3 Standby Liquid Control (SLC) and Feedwater Runback (FWRB)

Actuation ............................................................................................... B 3.3-89 B 3.3.1.4 Engineered Safety Features (ESF) Actuation Instrumentation ............. B 3.3-96 B 3.3.2.1 Startup Range Neutron Monitor (SRNM) Instrumentation ................ B 3.3-130 B 3.3.3.1 Essential Multiplexing System (EMS)................................................ B 3.3-139 B 3.3.4.1 Anticipated Transient Without Scram (ATWS) and End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation ...................... B 3.3-144 B 3.3.4.2 Feedwater and Main Turbine Trip Instrumentation ............................ B 3.3-166 B 3.3.5.1 Control Rod Block Instrumentation .................................................... B 3.3-172 B 3.3.6.1 Post Accident Monitoring (PAM) Instrumentation............................. B 3.3-181 B 3.3.6.2 Remote Shutdown System .................................................................. B 3.3-192 B 3.3.7.1 Control Room Habitability Area (CRHA) Emergency Filtration (EF) System Instrumentation .............................................................. B 3.3-202 B 3.3.8.1 Electric Power Monitoring.................................................................. B 3.3-209 B 3.3.8.2 Reactor Coolant Temperature Monitoring .......................................... B 3.3-214 B 3.4 Reactor Coolant System (RCS) ................................................................................. B 3.4-1 B 3.4.1 Reactor Internal Pumps (RIPs) - Operating............................................ B 3.4-1 B 3.4.2 Safety/Relief Valves (S/RVs) ................................................................. B 3.4-4 B 3.4.3 RCS Operational Leakage....................................................................... B 3.4-8 B 3.4.4 RCS Pressure Isolation Valve (PIV) Leakage ...................................... B 3.4-12 B 3.4.5 RCS Leakage Detection Instrumentation.............................................. B 3.4-17 B 3.4.6 RCS Specific Activity ........................................................................... B 3.4-22 B 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown .............................................................................................. B 3.4-27 B 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .............................................................................................. B 3.4-31 B 3.4.9 RCS Pressure and Temperature (P/T) Limits........................................ B 3.4-35 130 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 16 Table of Contents (Continued)

B 3.4.10 Reactor Steam Dome Pressure .............................................................. B 3.4-42 B 3.5 Emergency Core Cooling Systems (ECCS) .............................................................. B 3.5-1 B 3.5.1 ECCS - Operating................................................................................... B 3.5-1 B 3.5.2 ECCS - Shutdown ................................................................................ B 3.5-17 B 3.6 Containment Systems ................................................................................................ B 3.6-1 B 3.6.1.1 Primary Containment .............................................................................. B 3.6-1 B 3.6.1.2 Primary Containment Air Locks ............................................................. B 3.6-5 B 3.6.1.3 Primary Containment Isolation Valves (PCIVs)................................... B 3.6-12 B 3.6.1.4 Drywell Pressure ................................................................................... B 3.6-27 B 3.6.1.5 Drywell Air Temperature...................................................................... B 3.6-29 B 3.6.1.6 Wetwell-to-Drywell Vacuum Breakers................................................. B 3.6-32 B 3.6.2.1 Suppression Pool Average Temperature............................................... B 3.6-37 B 3.6.2.2 Suppression Pool Water Level .............................................................. B 3.6-42 B 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .................. B 3.6-45 B 3.6.2.4 Residual Heat Removal (RHR) Containment Spray............................. B 3.6-49 B 3.6.3.1 Primary Containment Hydrogen Recombiners ..................................... B 3.6-54 B 3.6.3.2 Primary Containment Oxygen Concentration....................................... B 3.6-59 B 3.6.4.1 Secondary Containment ........................................................................ B 3.6-62 B 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)............................... B 3.6-67 B 3.6.4.3 Standby Gas Treatment (SGT) System ................................................. B 3.6-73 B 3.7 Plant Systems............................................................................................................. B 3.7-1 B 3.7.1 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System, and Ultimate Heat Sink (UHS) - Operating....... B 3.7-1 B 3.7.2 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Shutdown ....... B 3.7-9 B 3.7.3 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Refueling...... B 3.7-14 B 3.7.4 Control Room Habitability Area (CRHA) - Emergency Filtration (EF) System........................................................................................... B 3.7-18 B 3.7.5 Control Room Habitability Area (CRHA) - Air Conditioning (AC)

System ................................................................................................... B 3.7-24 B 3.7.6 Main Condenser Offgas ........................................................................ B 3.7-28 B 3.7.7 Main Turbine Bypass System ............................................................... B 3.7-31 B 3.7.8 Fuel Pool Water Level .......................................................................... B 3.7-34 B 3.8 Electrical Power Systems .......................................................................................... B 3.8-1 B 3.8.1 AC Sources - Operating.......................................................................... B 3.8-1 B 3.8.2 AC Sources - Refueling........................................................................ B 3.8-34 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air Subsystem........................ B 3.8-40 B 3.8.4 DC Sources - Operating........................................................................ B 3.8-48 B 3.8.5 DC Sources - Shutdown ....................................................................... B 3.8-58 B 3.8.6 Battery Cell Parameters......................................................................... B 3.8-61 B 3.8.7 Inverters - Operating............................................................................. B 3.8-66 B 3.8.8 Inverters - Shutdown ............................................................................ B 3.8-70 B 3.8.9 Distribution Systems - Operating ......................................................... B 3.8-73 B 3.8.10 Distribution Systems - Shutdown......................................................... B 3.8-82 B 3.8.11 AC Sources - Shutdown (Low Water Level) ....................................... B 3.8-86 Table of Contents 131

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 16 Table of Contents (Continued)

B 3.9 Refueling Operations................................................................................................. B 3.9-1 B 3.9.1 Refueling Equipment Interlocks ............................................................. B 3.9-1 B 3.9.2 Refuel Position Rod-Out Interlock.......................................................... B 3.9-4 B 3.9.3 Control Rod Position............................................................................... B 3.9-7 B 3.9.4 Control Rod Position Indication ............................................................. B 3.9-9 B 3.9.5 Control Rod Operability - Refueling.................................................... B 3.9-12 B 3.9.6 Reactor Pressure Vessel (RPV) Water Level........................................ B 3.9-15 B 3.9.7 Residual Heat Removal (RHR) - High Water Level ............................ B 3.9-17 B 3.9.8 Residual Heat Removal (RHR) - Low Water Level............................. B 3.9-21 B 3.10 Special Operations................................................................................................... B 3.10-1 B 3.10.1 Inservice Leak and Hydrostatic Testing Operation............................... B 3.10-1 B 3.10.2 Reactor Mode Switch Interlock Testing ............................................... B 3.10-5 B 3.10.3 Control Rod Withdrawal - Hot Shutdown............................................ B 3.10-9 B 3.10.4 Control Rod Withdrawal - Cold Shutdown ........................................ B 3.10-13 B 3.10.5 Control Rod Drive (CRD) Removal - Refueling................................ B 3.10-17 B 3.10.6 Multiple Control Rod Withdrawal - Refueling .................................. B 3.10-21 B 3.10.7 Control Rod Testing - Operating........................................................ B 3.10-24 B 3.10.8 Shutdown Margin (SDM) Test - Refueling........................................ B 3.10-27 B 3.10.9 Reactor Internal Pumps - Testing ....................................................... B 3.10-31 B 3.10.10 Training Startups................................................................................. B 3.10-34 B 3.10.11 Low Power Physics Tests.................................................................... B 3.10-36 B 3.10.12 Multiple Control Rod Drive Subassembly Removal - Refueling....... B 3.10-40 132 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 17 Table of Contents 17.0 Quality Assurance........................................................................................................................17.0-1 17.0 Introduction..................................................................................................................................17.0-1 17.0.1 COL License Information............................................................................................17.0-1 17.1 Quality Assurance During Design and Construction...................................................................17.1-1 17.1.1 Organization ................................................................................................................17.1-1 17.1.2 Quality Assurance Program.........................................................................................17.1-1 17.1.3 Design Control.............................................................................................................17.1-2 17.1.4 Procurement Document Control..................................................................................17.1-2 17.1.5 Instruction, Procedures, and Drawings........................................................................17.1-2 17.1.6 Document Control .......................................................................................................17.1-3 17.1.7 Control of Purchased Material, Equipment, and Services...........................................17.1-3 17.1.8 Identification and Control of Materials, Parts, and Components ................................17.1-3 17.1.9 Control of Special Processes .......................................................................................17.1-3 17.1.10 Inspection ....................................................................................................................17.1-3 17.1.11 Test Control .................................................................................................................17.1-4 17.1.12 Control of Measuring and Test Equipment .................................................................17.1-4 17.1.13 Handling, Storage, and Shipping.................................................................................17.1-4 17.1.14 Inspection, Test, and Operating Status ........................................................................17.1-4 17.1.15 Nonconforming Materials, Parts, or Components.......................................................17.1-4 17.1.16 Corrective Action ........................................................................................................17.1-4 17.1.17 Quality Assurance Records .........................................................................................17.1-4 17.1.18 Audits ..........................................................................................................................17.1-5 17.1.19 References ...................................................................................................................17.1-5 17.2 Quality Assurance During the Operations Phase.........................................................................17.2-1 17.3 Reliability Assurance Program During Design Phase .................................................................17.3-1 17.3.1 Introduction .................................................................................................................17.3-1 17.3.2 Scope ...........................................................................................................................17.3-1 17.3.3 Purpose ........................................................................................................................17.3-1 17.3.4 Objective......................................................................................................................17.3-2 17.3.5 GE Hitachi Nuclear Energy Organization for D-RAP ................................................17.3-2 17.3.6 SSC Identification/Prioritization .................................................................................17.3-2 17.3.7 Design Considerations.................................................................................................17.3-3 17.3.8 Defining Failure Modes...............................................................................................17.3-3 17.3.9 Operational Reliability Assurance Activities ..............................................................17.3-4 17.3.10 Owner/Operators Reliability Assurance Program......................................................17.3-4 17.3.11 D-RAP Implementation...............................................................................................17.3-6 17.3.12 Glossary of Terms .....................................................................................................17.3-11 17.3.13 COL License Information..........................................................................................17.3-13 17.3.14 References .................................................................................................................17.3-13 Table of Contents 133

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 17 List of Tables Table 17.0-1 ABWR Compliance with Quality Related Regulatory Guides ...................................17.0-2 Table 17.3-1 SLCS Components with Largest Contribution to System Unavailability .................17.3-14 Table 17.3-2 Risk-Significant SSCs for SLCS ...............................................................................17.3-14 Table 17.3-3 Examples of SLCS Failure Modes and O-RAP Activities........................................17.3-15 134 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 17 List of Figures Figure 17.3-1 Design Evaluations for SSCs .................................................................................17.3-16 Figure 17.3-2 Process for Determining Dominant Failure Modes of Risk-Significant SSCs ......17.3-17 Figure 17.3-3 Use of Failure History to Define Modes ................................................................17.3-18 Figure 17.3-4 Analytical Assessment to Define Failure Modes ...................................................17.3-19 Figure 17.3-5 Inlusion of Maintenance Requirements in the Definition of Failure Modes .........17.3-20 Figure 17.3-6 Identification of Risk-Significant SSC O-Rap Activities ......................................17.3-21 Figure 17.3-7 Standby Liquid Control System (Standby Mode)..................................................17.3-22 Figure 17.3-8 Standby Liquid Control System Top Level Fault Tree ..........................................17.3-23 Table of Contents 135

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 18 Table of Contents 18.0 Human Factors Engineering ........................................................................................................18.1-1 18.1 Introduction..................................................................................................................................18.1-1 18.2 Design Goals and Design Bases ..................................................................................................18.2-1 18.3 Planning, Development, and Design............................................................................................18.3-1 18.3.1 Introduction .................................................................................................................18.3-1 18.3.2 Standard Design Features ............................................................................................18.3-1 18.3.3 Inventory of Controls and Instrumentation .................................................................18.3-2 18.3.4 Detailed Design Implementation Process....................................................................18.3-2 18.4 Control Room Standard Design Features ....................................................................................18.4-1 18.4.1 Introduction .................................................................................................................18.4-1 18.4.2 Standard Design Feature Descriptions ........................................................................18.4-1 18.4.3 Control Room HSI Technology.................................................................................18.4-10 18.5 Remote Shutdown System ...........................................................................................................18.5-1 18.6 Systems Integration......................................................................................................................18.6-1 18.6.1 Safety-Related Systems ...............................................................................................18.6-1 18.6.2 Non-Safety-Related Systems.......................................................................................18.6-1 18.7 Detailed Design of the Operator Interface System ......................................................................18.7-1 18.8 COL License Information ............................................................................................................18.8-1 18.8.1 HSI Design Implementation Process...........................................................................18.8-1 18.8.2 Number of Operators Needing Controls Access .........................................................18.8-1 18.8.3 Automation Strategies and Their Effect on Operator Reliability................................18.8-1 18.8.4 SPDS Integration With Related Emergency Response Capabilities ...........................18.8-1 18.8.5 Standard Design Features Design Validation..............................................................18.8-1 18.8.6 Remote Shutdown System Design Evaluation ............................................................18.8-1 18.8.7 Local Valve Position Indication ..................................................................................18.8-1 18.8.8 Operator Training ........................................................................................................18.8-2 18.8.9 Safety System Status Monitoring ................................................................................18.8-2 18.8.10 PGCS Malfunction ......................................................................................................18.8-2 18.8.11 Local Control Stations.................................................................................................18.8-2 18.8.12 As-Built Evaluation of MCR and RSS........................................................................18.8-2 18.8.13 Accident Monitoring Instrumentation .........................................................................18.8-2 18.8.14 In-Core Cooling Instrumentation ................................................................................18.8-3 18.8.15 Performance of Critical Tasks .....................................................................................18.8-3 18.8.16 Plant Status and Post-Accident Monitoring ................................................................18.8-3 18A Emergency Procedure Guidelines................................................................................................18A-1 18A.1 Table of Contents ........................................................................................................18A-2 18A.2 Introduction .................................................................................................................18A-3 18A.3 Operator Precautions ...................................................................................................18A-8 18A.4 RPV Control Guideline .............................................................................................18A-12 18A.5 Primary Containment Control Guideline...................................................................18A-27 136 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 18 Table of Contents (Continued) 18A.6 Secondary Containment Control Guideline...............................................................18A-51 18A.7 Radioactivity Release Control Guideline ..................................................................18A-63 18A.8 Contingency #1, Alternative Level Control ..............................................................18A-64 18A.9 Contingency #2, Emergency RPV Depressurization.................................................18A-69 18A.10 Contingency #3, Steam Cooling................................................................................18A-72 18A.11 Contingency #4, RPV Flooding ................................................................................18A-73 18A.12 Contingency #5, Level/Power Control ......................................................................18A-81 18A.13 Contingency #6, Primary Containment Flooding......................................................18A-90 18B Differences Between BWROG EPG Revision 4 and ABWR EPG............................................. 18B-1 18B.1 Introduction ................................................................................................................. 18B-1 18C Operator Interface Equipment Characterization .......................................................................... 18C-1 18C.1 Control Room Arrangement ........................................................................................ 18C-1 18C.2 Main Control Room Configuration ............................................................................. 18C-1 18C.3 Large Display Panel Configuration ............................................................................. 18C-2 18C.4 Systems Integration ..................................................................................................... 18C-2 18D Emergency Procedures GuidelinesInput Data and Calculation Results ..................................18D-1 18D.1 Introduction .................................................................................................................18D-1 18D.2 Input Parameters..........................................................................................................18D-1 18D.3 Calculation Results......................................................................................................18D-1 18E ABWR Human-System Interface Design Implementation Process ............................................ 18E-1 18E.1 Introduction ................................................................................................................. 18E-1 18E.2 HSI Design Implementation Process........................................................................... 18E-1 18E.3 HSI Implementation Requirements ............................................................................. 18E-4 18F Emergency Operation Information and Controls..........................................................................18F-1 18F.1 Introduction ..................................................................................................................18F-1 18G Design Development and Validation Testing ..............................................................................18G-1 18G.1 Introduction .................................................................................................................18G-1 18G.2 Design Development ...................................................................................................18G-1 18G.3 Validation Testing .......................................................................................................18G-7 18H Supporting Analysis for Emergency Operation Information and Controls .................................18H-1 18H.1 Introduction .................................................................................................................18H-1 18H.2 Presentation of Results ................................................................................................18H-3 18H.3 Analysis of Changes to EPGs......................................................................................18H-5 18H.4 References ...................................................................................................................18H-6 Table of Contents 137

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 18 List of Tables Table 18B-1 Differences Between BWROG EPG Revision 4 and ABWR EPG ............................ 18B-2 Table 18D-1 BWROG EPG Rev. 4 Appendix C Input Data for ABWR .........................................18D-2 Table 18D-2 BWROG EPG Rev. 4 Appendix C Results for ABWR ............................................18D-12 Table 18E-1 Human Factors Engineering Design Team and Plans ................................................. 18E-6 Table 18E-2 HFE Analysis............................................................................................................. 18E-37 Table 18E-3 Human System Interface Design ............................................................................... 18E-40 Table 18E-4 Human Factors Verification and Validation.............................................................. 18E-41 Table 18F-1 Inventory of Controls Based Upon the ABWR EPGs and PRA ..................................18F-3 Table 18F-2 Inventory of Displays Based Upon the ABWR EPGs and PRA ................................18F-10 Table 18F-3 Inventory of Alarms Based Upon the ABWR EPGs and PRA ..................................18F-13 Table 18G-1 Large Screen Utilization Topics................................................................................18G-11 Table 18G-2 Validation Test Schedules .........................................................................................18G-11 Table 18G-3 Test Scenarios and Evaluations .................................................................................18G-12 138 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 18 List of Figures Figure 18C-1 Control Room Arrangement..................................................................................... 18C-3 Figure 18C-2 Main Control Console Configuration....................................................................... 18C-4 Figure 18C-3 Main Control Console Cross-Section A-A .............................................................. 18C-5 Figure 18C-4 Main Control Console Cross-Section B-B ............................................................... 18C-6 Figure 18C-5 Arrangement of Equipment of Main Control Console............................................. 18C-7 Figure 18C-6 Side View of Relative Positions of Main Console and Wide Display Device......... 18C-8 Figure 18C-7 Fixed-Position Display............................................................................................. 18C-9 Figure 18C-8 Overall Configuration of Operator Interface System............................................. 18C-10 Figure 18E-1 ABWR Human-System Interface Design Implementation Process....................... 18E-42 Figure 18G-1 Typical Data from Touch Screen Precision Tests..................................................18G-13 Table of Contents 139

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents 19.0 Response to Severe Accident Policy Statement ..........................................................................19.1-1 19.1 Purpose and Summary ..............................................................................................................19.1-1 19.1.1 Purpose.....................................................................................................................19.1-1 19.1.2 Summary ..................................................................................................................19.1-1 19.1.3 References ................................................................................................................19.1-2 19.2 Introduction ..............................................................................................................................19.2-1 19.2.1 Definitions................................................................................................................19.2-1 19.2.2 Objective and Scope.................................................................................................19.2-1 19.2.3 PRA Basis ................................................................................................................19.2-2 19.2.4 Methodology ............................................................................................................19.2-5 19.2.5 References ................................................................................................................19.2-8 19.3 Internal Event Analysis ............................................................................................................19.3-1 19.3.1 Frequency of Core Damage .....................................................................................19.3-1 19.3.2 Frequency of Radioactive Release .........................................................................19.3-12 19.3.3 Magnitude and Timing of Radioactive Release .....................................................19.3-19 19.3.4 Consequence of Radioactive Release.....................................................................19.3-20 19.3.5 References ..............................................................................................................19.3-21 19.4 External Event Analysis and Shutdown Risk Analysis ............................................................19.4-1 19.4.1 External Event Review.............................................................................................19.4-1 19.4.2 Tornado Strike Analysis...........................................................................................19.4-2 19.4.3 Seismic Margins Analysis........................................................................................19.4-3 19.4.4 Fire Protection Probabilistic Risk Assessment ......................................................19.4-10 19.4.5 ABWR Probabilistic Flooding Analysis ................................................................19.4-11 19.4.6 ABWR Shutdown Risk ..........................................................................................19.4-12 19.4.7 References ..............................................................................................................19.4-13 19.5 Source Term Sensitivity Studies...............................................................................................19.5-1 19.5.1 Core Melt Progression and Hydrogen Generation ...................................................19.5-1 19.5.2 Effect of Overpressure Relief Rupture Disk on Fission Product Release................19.5-1 19.5.3 Alternate Definition of Containment Failure ...........................................................19.5-2 19.6 Measurement Against Goals.....................................................................................................19.6-1 19.6.1 Goals ........................................................................................................................19.6-1 19.6.2 Prevention of Core Damage .....................................................................................19.6-1 19.6.3 Prevention of Early Containment Failure For Dominant Accident Sequences........19.6-1 19.6.4 Hydrogen from 100% of Active Zirconium.............................................................19.6-2 19.6.5 Reliable Heat Removal to Reduce Probability of Containment Failure ..................19.6-2 19.6.6 Prevention of Hydrogen Deflagration and Detonation ............................................19.6-3 19.6.7 Offsite Dose/Large Release......................................................................................19.6-4 19.6.8 Containment Conditional Failure Probability ..........................................................19.6-4 19.6.9 Safety Goal Policy Statement...................................................................................19.6-5 19.6.10 Not Used...................................................................................................................19.6-5 19.6.11 Conclusion................................................................................................................19.6-5 19.6.12 References ................................................................................................................19.6-6 140 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents (Continued) 19.7 PRA as a Design Tool ..............................................................................................................19.7-1 19.7.1 ABWR Design and Operating Experience...............................................................19.7-1 19.7.2 Early PRA Studies....................................................................................................19.7-1 19.7.3 PRA Studies During the Certification Effort ...........................................................19.7-3 19.7.4 Conduct of the PRA Evaluations .............................................................................19.7-9 19.7.5 Evaluation of Potential Design Improvements ........................................................19.7-9 19.8 Important Features Identified by the ABWR PRA...................................................................19.8-1 19.8.1 Important Features from Level 1 Internal Events Analyses.....................................19.8-2 19.8.2 Important Features from Seismic Analyses .............................................................19.8-7 19.8.3 Important Features from Fire Analyses....................................................................19.8-9 19.8.4 Important Features from Suppression Pool Bypass and Ex-Containment LOCA Analyses .....................................................................................................19.8-12 19.8.5 Important Features from Flooding Analyses..........................................................19.8-15 19.8.6 Important Features from Shutdown Events Analyses ............................................19.8-18 19.8.7 ABWR Features to Mitigate Severe Accidents......................................................19.8-21 19.9 COL License Information.........................................................................................................19.9-1 19.9.1 Post Accident Recovery Procedure for Unisolated CUW Line Break.....................19.9-1 19.9.2 Confirmation of CUW Operation Beyond Design Bases ........................................19.9-1 19.9.3 Event Specific Procedures for Severe External Flooding ........................................19.9-2 19.9.4 Confirmation of Seismic Capacities Beyond the Plant Design Bases .....................19.9-3 19.9.5 Plant Walkdowns .....................................................................................................19.9-3 19.9.6 Confirmation of Loss of AC Power Event ...............................................................19.9-3 19.9.7 Procedures and Training for Use of AC-Independent Water Addition System.......19.9-3 19.9.8 Actions to Avoid Common-Cause Failures in the Essential Multiplexing System (EMUX) and Other Common-Cause Failures.............................................19.9-4 19.9.9 Actions to Mitigate Station Blackout Events ...........................................................19.9-5 19.9.10 Actions to Reduce Risk of Internal Flooding...........................................................19.9-6 19.9.11 Actions to Avoid Loss of Decay Heat Removal and Minimize Shutdown Risk .....19.9-7 19.9.12 Procedures for Operation of RCIC from Outside the Control Room.......................19.9-8 19.9.13 ECCS Test and Surveillance Intervals .....................................................................19.9-9 19.9.14 Accident Management .............................................................................................19.9-9 19.9.15 Manual Operation of MOVs ..................................................................................19.9-10 19.9.16 High Pressure Core Flooder Discharge Valve .......................................................19.9-10 19.9.17 Capability of Containment Isolation Valves ..........................................................19.9-10 19.9.18 Procedures to Insure Sample Lines and Drywell Purge Lines Remain Closed During Operation ...................................................................................................19.9-10 19.9.19 Procedures for Combustion Turbine Generator to Supply Power to Condensate Pumps .....................................................................................................................19.9-10 19.9.20 Actions to Assure Reliability of the Supporting RCW and Service Water Systems ..................................................................................................................19.9-11 19.9.21 Housing of ACIWA Equipment.............................................................................19.9-11 19.9.22 Procedures to Assure SRV Operability During Station Blackout..........................19.9-11 19.9.23 Procedures for Ensuring Integrity of Freeze Seals.................................................19.9-11 19.9.24 Procedures for Controlling Combustibles During Shutdown ................................19.9-11 19.9.25 Outage Planning and Control .................................................................................19.9-11 19.9.26 Reactor Service Water Systems Definition............................................................19.9-11 Table of Contents 141

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents (Continued) 19.9.27 Capability of Vacuum Breakers .............................................................................19.9-12 19.9.28 Capability of the Containment Atmospheric Monitoring System..........................19.9-12 19.9.29 Plant Specific Safety-Related Issues and Vendors Operating Guidance ...............19.9-12 19.9.30 PRA Update ...........................................................................................................19.9-12 19.10 Assumptions and Insights Related to Systems Outside of ABWR Design Certification.......19.10-1 19.10.1 Reactor Service Water (RSW) System and Safety-Related Ultimate Heat Sink (UHS) Assumptions ...............................................................................................19.10-1 19.10.2 Reactor Service Water (RSW) System and Safety-Related Ultimate Heat Sink (UHS) Insights .......................................................................................................19.10-2 19.10.3 Power Cycle Heat Sink Assumptions ....................................................................19.10-3 19.10.4 Power Cycle Heat Sink Insights.............................................................................19.10-3 19.10.5 Offsite Power Assumptions....................................................................................19.10-3 19.10.6 Offsite Power Insights............................................................................................19.10-3 19.10.7 Fire Truck Assumption ..........................................................................................19.10-3 19.10.8 Fire Truck Insights .................................................................................................19.10-3 19.11 Human Action Overview........................................................................................................19.11-1 19.12 Input to the Reliability Assurance Program ...........................................................................19.12-1 19.13 Summary of Insights Gained from the PRA...........................................................................19.13-1 19.13.1 Licensing Review Bases Goals ..............................................................................19.13-1 19.13.2 The Search for Vulnerabilities ...............................................................................19.13-1 19.13.3 The Most Important Aspects of the Design ...........................................................19.13-2 19.13.4 Additional Studies ..................................................................................................19.13-2 19.13.5 Uncertainty and Sensitivity Studies .......................................................................19.13-3 19.13.6 Systems and Effects Not Modeled in the PRA ......................................................19.13-3 19A Response to CP/ML Rule 10 CFR 50.34(f)..............................................................................19A-1 19A.1 Introduction ..............................................................................................................19A-1 19A.2 NRC Positions/Responses........................................................................................19A-2 19A.3 COL License Information ......................................................................................19A-19 19B Resolution of Applicable Unresolved Safety Issues and Generic Safety Issues ...................... 19B-1 19B.1 Introduction .............................................................................................................. 19B-9 19B.2 Safety Issues........................................................................................................... 19B-10 19B.3 COL License Information .................................................................................... 19B-124 19C Design Considerations Reducing Sabotage Risk...................................................................... 19C-1 19D Probabilistic Evaluations ..........................................................................................................19D-1 19E Deterministic Evaluations......................................................................................................... 19E-1 19E.1 Introduction .............................................................................................................. 19E-1 19E.2 Deterministic Analysis of Plant Performance .......................................................... 19E-2 19E.3 Consequence Analysis ......................................................................................... 19E-292 142 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents (Continued) 19EA Direct Containment Heating.................................................................................................. 19EA-1 19EA.1 Summary Description............................................................................................ 19EA-1 19EA.2 Description of Event Tree Analysis ...................................................................... 19EA-2 19EA.3 Deterministic Model for DCH ............................................................................ 19EA-11 19EA.4 Summary of Results ............................................................................................ 19EA-25 19EA.5 Conclusions ......................................................................................................... 19EA-27 19EA.6 References ........................................................................................................... 19EA-27 19EB Fuel Coolant Interactions........................................................................................................19EB-1 19EB.1 Introduction ............................................................................................................19EB-1 19EB.2 Applicability of Experiments .................................................................................19EB-3 19EB.3 Explosive Steam Generation ..................................................................................19EB-7 19EB.4 Impulse Loads ........................................................................................................19EB-9 19EB.5 Water Missiles......................................................................................................19EB-14 19EB.6 Containment Overpressurization..........................................................................19EB-16 19EB.7 References ............................................................................................................19EB-22 19EC Debris Coolability and Core Concrete Interaction .................................................................19EC-1 19EC.1 Applicability of Experiments to ABWR ................................................................19EC-1 19EC.2 Description of Event Tree Analysis .......................................................................19EC-3 19EC.3 Deterministic Model for Core Concrete Interaction ............................................19EC-13 19EC.4 Pedestal Strength ..................................................................................................19EC-17 19EC.5 Application of CCI Model to ABWR ..................................................................19EC-17 19EC.6 Sensitivity to Various Parameters ........................................................................19EC-21 19EC.7 Impact on Offsite Dose ........................................................................................19EC-24 19EC.8 Conclusions ..........................................................................................................19EC-24 19EC.9 References ............................................................................................................19EC-24 19ED Corium Shield........................................................................................................................ 19ED-1 19ED.1 Issue....................................................................................................................... 19ED-1 19ED.2 Design Description................................................................................................ 19ED-1 19ED.3 Success Criteria ..................................................................................................... 19ED-2 19ED.4 Channel Length Analysis ...................................................................................... 19ED-3 19ED.5 Long-Term Capability of the Shield Walls ......................................................... 19ED-21 19ED.6 Related Experimental and Analytical Work ....................................................... 19ED-24 19ED.7 References ........................................................................................................... 19ED-25 19EE Suppression Pool Bypass........................................................................................................19EE-1 19EE.1 Suppression Pool Bypass .......................................................................................19EE-1 19EE.2 Description of Decomposition Event Tree Analysis..............................................19EE-1 19EE.3 Deterministic Analysis ...........................................................................................19EE-6 19EE.4 Summary of Results .............................................................................................19EE-11 19EE.5 Conclusions ..........................................................................................................19EE-12 19EE.6 References ............................................................................................................19EE-13 19F Containment Ultimate Strength .................................................................................................19F-1 19F.1 Introduction and Summary........................................................................................19F-1 19F.2 RCCV Nonlinear Analysis ........................................................................................19F-3 Table of Contents 143

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents (Continued) 19F.3 Prediction of Containment Ultimate Strength...........................................................19F-5 19F.4 References ...............................................................................................................19F-16 19FA Containment Ultimate Strength ..............................................................................................19FA-1 19G Aircraft Impact Assessment......................................................................................................19G-1 19G.1 Introduction and Background...................................................................................19G-1 19G.2 Scope of the Assessment ..........................................................................................19G-1 19G.3 Assessment Methodology ........................................................................................19G-2 19G.4 Results of Assessment..............................................................................................19G-2 19G.5 Conclusions of Assessment......................................................................................19G-6 19G.6 References ................................................................................................................19G-6 19H Seismic Capacity Analysis .......................................................................................................19H-1 19H.1 Introduction ..............................................................................................................19H-1 19H.2 Fragility Formulation ...............................................................................................19H-1 19H.3 Structural Fragility ...................................................................................................19H-3 19H.4 Component Fragility ..............................................................................................19H-13 19H.5 COL License Information ......................................................................................19H-16 19H.6 References ..............................................................................................................19H-19 19I Seismic Margins Analysis ......................................................................................................... 19I-1 19I.1 Introduction ............................................................................................................... 19I-1 19I.2 Component and Structure Fragility - AM, C ............................................................ 19I-2 19I.3 Event Tree Analysis .................................................................................................. 19I-2 19I.4 System Analysis ........................................................................................................ 19I-4 19I.5 Accident Sequence HCLPF Analysis........................................................................ 19I-5 19I.6 Results of the Analyses ............................................................................................. 19I-8 19I.7 Containment Isolation and Bypass Analysis............................................................. 19I-8 19I.8 References ............................................................................................................... 19I-10 19J Not Used .................................................................................................................................... 19J-1 19K PRA-Based Reliability and Maintenance .................................................................................19K-1 19K.1 Introduction ..............................................................................................................19K-1 19K.2 General Approach ....................................................................................................19K-1 19K.3 Determination of Important Structures, Systems and Components for Level 1 Analysis....................................................................................................................19K-1 19K.4 Determination of Important Structures, Systems and Components for Level 2 Analysis....................................................................................................................19K-3 19K.5 Determination of Important Structures, Systems and Components for Seismic Analysis....................................................................................................................19K-4 19K.6 Determination of Important Structures, Systems and Components for Fire Analysis....................................................................................................................19K-5 19K.7 Determination of Important Structures, Systems and Components for Flood Analysis....................................................................................................................19K-6 19K.8 Determination of Important Structures, Systems and Components for Shutdown Analysis...................................................................................................19K-6 144 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents (Continued) 19K.9 Identification of Important Systems with Redundant Trains ...................................19K-6 19K.10 Identification of Important Capabilities Outside the Control Room........................19K-7 19K.11 Reliability and Maintenance Actions .......................................................................19K-8 19K.12 References ..............................................................................................................19K-17 19L ABWR Shutdown Risk Evaluation .......................................................................................... 19L-1 19L.1 Purpose..................................................................................................................... 19L-1 19L.2 Conclusions .............................................................................................................. 19L-1 19L.3 Introduction .............................................................................................................. 19L-1 19L.4 Scope of the Study ................................................................................................... 19L-2 19L.5 Reactivity Excursion Events .................................................................................... 19L-3 19L.6 Reactor Pressure Vessel Draining Events .............................................................. 19L-10 19L.7 Loss of Core Cooling ............................................................................................. 19L-18 19L.8 Loss of Decay Heat Removal Events..................................................................... 19L-20 19L.9 Noncore-Related Accidents ................................................................................... 19L-22 19L.10 References .............................................................................................................. 19L-24 19M Fire Protection Probabilistic Risk Assessment........................................................................ 19M-1 19M.1 Introduction ............................................................................................................. 19M-1 19M.2 Basis of the Analysis ............................................................................................... 19M-1 19M.3 Summary of Results ................................................................................................ 19M-2 19M.4 Phase I Scenario and Phase II Fire Frequency Analysis ......................................... 19M-3 19M.5 Calculation of the Fire Ignition Frequency ............................................................. 19M-7 19M.6 Calculation of Core Damage Frequencies............................................................... 19M-9 19M.7 COL License Information ..................................................................................... 19M-11 19M.8 References ............................................................................................................. 19M-11 19N Analysis of Common-Cause Failure of Multiplex Equipment.................................................19N-1 19N.1 Introduction ..............................................................................................................19N-1 19N.2 Results and Conclusions ..........................................................................................19N-1 19N.3 Basis for the Analysis...............................................................................................19N-4 19N.4 Potential Causes of and Defenses Against EMUX CCF..........................................19N-6 19N.5 Discussion of the Effect on Core Damage Frequency .............................................19N-9 19N.6 Discussion of the Effect on Isolation Capability....................................................19N-16 19N.7 Summary ................................................................................................................19N-17 19N.8 References ..............................................................................................................19N-18 19O Not Used ...................................................................................................................................19O-1 19P Evaluation of Potential Modifications to the ABWR Design....................................................19P-1 19Q ABWR Shutdown Risk Assessment.........................................................................................19Q-1 19Q.1 Introduction ..............................................................................................................19Q-1 19Q.2 Evaluation Scope......................................................................................................19Q-1 19Q.3 Summary of Results .................................................................................................19Q-2 19Q.4 Features to Minimize Shutdown Risk ......................................................................19Q-4 19Q.5 Instrumentation ......................................................................................................19Q-15 19Q.6 Flooding and Fire Protection..................................................................................19Q-16 Table of Contents 145

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 Table of Contents (Continued) 19Q.7 Decay Heat Removal Reliability Study .................................................................19Q-21 19Q.8 Use of Freeze Seals in ABWR ...............................................................................19Q-33 19Q.9 Shutdown Vulnerability Resulting from New Features .........................................19Q-33 19Q.10 Procedures ..............................................................................................................19Q-34 19Q.11 Summary of Review of Significant Shutdown Events: Electrical Power and Decay Heat Removal..............................................................................................19Q-37 19Q.12 Results and Interface Requirements.......................................................................19Q-40 19QA Fault Trees ............................................................................................................................. 19QA-1 19QB DHR Reliability Study........................................................................................................... 19QB-1 19QB.1 Offsite Dose and Operator Recovery Calculations ............................................... 19QB-1 19QB.2 Time to Reach Boiling .......................................................................................... 19QB-2 19QB.3 Time for RPV Water Level to Reach Top of Active Fuel .................................... 19QB-2 19QB.4 Human Reliability Analysis (HRA) ...................................................................... 19QB-2 19QB.5 Decay Heat Removal Capability of CUW and FPC ............................................. 19QB-4 19QB.6 References ............................................................................................................. 19QB-4 19QC Review of Significant Shutdown Events: Electrical Power and Decay Heat Removal ........ 19QC-1 19QC.1 Review of Significant Shutdown Events............................................................... 19QC-1 19R Probabilistic Flooding Analysis................................................................................................ 19R-1 19R.1 Introduction and Summary....................................................................................... 19R-1 19R.2 Scope of Analysis..................................................................................................... 19R-3 19R.3 Screening Analysis (Water Sources and Buildings) ................................................ 19R-3 19R.4 Deterministic Flood Analysis................................................................................... 19R-4 19R.5 Probabilistic Flood Assessment ............................................................................. 19R-15 19R.6 Results and Interface Requirements....................................................................... 19R-27 146 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Tables Table 19.2-1 Key PRA Assumptions ..........................................................................................19.2-10 Table 19.3-1 Initiating Event Frequencies ..................................................................................19.3-22 Table 19.3-2 Success Criteria to Prevent Initial Core Damage for Transient and LOCA Events With RPS Scram ........................................................................................19.3-23 Table 19.3-3 Success Criteria and Required Operator Actions For ATWS Events....................19.3-26 Table 19.3-4 Frequency of Core Damage by Accident Class .....................................................19.3-28 Table 19.3-5 Frequency of Core Damage by Initiating Event ....................................................19.3-29 Table 19.3-6 Frequency Of Fission Product Release ..................................................................19.3-30 Table 19.6-1 Summary of Goals in Licensing Review Bases .......................................................19.6-7 Table 19.8-1 Important Features from Level 1 Internal Events Analyses ..................................19.8-27 Table 19.8-2 Important Features from Seismic Analyses ...........................................................19.8-30 Table 19.8-3 Important Features from Fire Protection Analyses ................................................19.8-32 Table 19.8-4 Important Features from Suppression Pool Bypass and Ex-Containment LOCA Analyses .....................................................................................................19.8-33 Table 19.8-5 Important Features from Flooding Analyses .........................................................19.8-35 Table 19.8-6 Important Features From Shutdown Events Analyses...........................................19.8-37 Table 19.8-7 Key Severe Accident Parameters...........................................................................19.8-39 Table 19A-1 ABWRCP/ML Rule Cross Reference................................................................19A-21 Table 19E.2-1 Potential Suppression Pool Bypass Lines ............................................................ 19E-150 Table 19E.2-2 ABWR Plant Ability to Cope with Station Blackout for up to 8 Hours .............. 19E-154 Table 19E.2-3 Definition of Accident Sequence Codes .............................................................. 19E-155 Table 19E.2-4 Grouping of Accident Classes into Base Sequences............................................ 19E-156 Table 19E.2-5 Sequence of Events for LCLP-PF-R-N................................................................ 19E-156 Table 19E.2-6 Sequence of Events for LCLP-FS-R-N................................................................ 19E-157 Table 19E.2-7 Sequence of Events for LCHP-PS-R-N ............................................................... 19E-157 Table 19E.2-8 Sequence of Events for LCHP-PF-P-M ............................................................... 19E-158 Table 19E.2-9 Sequence of Events for SBRC-FA-R-0 ............................................................... 19E-158 Table of Contents 147

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Tables (Continued)

Table 19E.2-10 Sequence of Events for SBRC-PF-R-N ............................................................... 19E-159 Table 19E.2-11 Sequence of Events for LHRC-00-R-0 ................................................................ 19E-159 Table 19E.2-12 Sequence of Events for LBLC-PF-R-N ............................................................... 19E-160 Table 19E.2-13 Sequence of Events for NSCL-PF-R-N ............................................................... 19E-160 Table 19E.2-14 Sequence of Events for NSCH-PF-P-M............................................................... 19E-161 Table 19E.2-15 Sequence of Events for NSRC-PF-R-N ............................................................... 19E-161 Table 19E.2-16 Summary of Critical Parameters for Severe Accident Sequences ....................... 19E-162 Table 19E.2-17 Important Parameters for Steam Explosion Analysis .......................................... 19E-163 Table 19E.2-18 Potential Bypass Pathway Matrix ........................................................................ 19E-163 Table 19E.2-19 Flow Split Fractions ............................................................................................. 19E-164 Table 19E.2-20 Failure Probabilities ............................................................................................. 19E-165 Table 19E.2-21 Summary of Bypass Probabilities ........................................................................ 19E-166 Table 19E.2-22 NUREG/CR-4551 Grand Gulf APET Events by Category ................................. 19E-167 Table 19E.2-23 NRC Identified Parameters for Sensitivity Study from NUREG-1335 ............... 19E-172 Table 19E.2-24 Issues to be investigated in ABWR Sensitivity Analysis .................................... 19E-173 Table 19E.2-25 Comparison of Volatile Fission Product Releases............................................... 19E-174 Table 19E.2-26 Comparison of Low Pressure Core Melt Performance with and without Containment Overpressure Protection System .................................................... 19E-175 Table 19E.2-27 Probability of Release Mode With and Without COPS....................................... 19E-175 Table 19E.2-28 Sensitivity Studies for Passive Flooder Reliability Frequencies of Important CET Results ......................................................................................................... 19E-176 Table 19E.2-29 Equipment and Instrumentation Required to Survive Severe Accident Scenarios .............................................................................................................. 19E-177 Table 19E.2-30 Material Properties Used in Tunnel Integrity Analysis ....................................... 19E-178 Table 19E.3-1 GESSAR Reactor Release Parameters................................................................. 19E-297 Table 19E.3-2 Population Density for Each Geographical Region ............................................. 19E-298 Table 19E.3-3 Evacuation Parameters......................................................................................... 19E-298 148 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Tables (Continued)

Table 19E.3-4 Evacuation Parameter Definition ......................................................................... 19E-299 Table 19E.3-5 Site and Reactor Data for Meteorological Modeling ........................................... 19E-299 Table 19E.3-6 Event Release Parameters .................................................................................... 19E-300 Table 19E.3-7 Consequence Goals and Results .......................................................................... 19E-301 Table 19EA-1 Containment Pressure at RPV Failure ................................................................ 19EA-30 Table 19EA-2 Comparison of Assumed Debris Mass Participating in DCH with BWRSAR Debris Discharge Results .................................................................................... 19EA-30 Table 19EB-1 Core Concrete Interaction Tests with Water Addition to Debris.........................19EB-24 Table 19EB-2 Maximum Steam Generation for Steam Spikes...................................................19EB-24 Table 19EC-1 Summary of Timing for Core Concrete Interaction Base Case ...........................19EC-26 Table 19EC-2 Summary of CCI Deterministic Analysis for ABWR..........................................19EC-27 Table 19ED-1 Material Properties.............................................................................................. 19ED-27 Table 19ED-2 Scenario Parameters............................................................................................ 19ED-27 Table 19ED-3 Constituent Material Properties .......................................................................... 19ED-28 Table 19ED-4 Results of Channel Length Calculation .............................................................. 19ED-28 Table 19ED-5 Effect of Parameter Variations............................................................................ 19ED-29 Table 19ED-6 Change in Energy due to Superheat.................................................................... 19ED-30 Table 19ED-7 Plug Formation Times with Superheat ............................................................... 19ED-30 Table 19ED-8 Required Channel Lengths with Superheat......................................................... 19ED-31 Table 19EE-1 Summary of Volatile Fission Product Releases for Severe Accidents with Suppression Pool Bypass Leakage through Vacuum Breaker Valves.................19EE-14 Table 19EE-2 Effect of Eliminating Aerosol Plugging Credit on Source Term Category Frequencies ..........................................................................................................19EE-15 Table 19F-1 Summary of Stresses and Strains ............................................................................19F-17 Table 19F-2 Summary of Pressure Capabilities of Various Components of the RCCV.............19F-18 Table 19H-1 Seismic Capacity Summary ...................................................................................19H-21 Table 19H-2 Seismic Fragility For Reactor Building .................................................................19H-23 Table of Contents 149

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Tables (Continued)

Table 19H-3 Seismic Fragility For Containment ........................................................................19H-24 Table 19H-4 Seismic Fragility For RPV Pedestal ......................................................................19H-25 Table 19H-5 Seismic Fragility For Control Building .................................................................19H-26 Table 19H-6 Seismic Fragility For Reactor Pressure Vessel ......................................................19H-27 Table 19H-7 Seismic Fragility For Shroud Support ...................................................................19H-28 Table 19H-8 Seismic Fragility For CRD Guide Tubes...............................................................19H-29 Table 19H-9 Seismic Fragility For CRD Housings ....................................................................19H-30 Table 19H-10 Seismic Fragility For Fuel Assemblies ..................................................................19H-31 Table 19I-1 ABWR Systems and Components/Structures Fragilities........................................ 19I-11 Table 19I-2 Seismic Margins for ABWR Accident Sequences (Convolution Method)............. 19I-14 Table 19I-3 Seismic Margins for ABWR Accident Classes (Convolution Method) ................. 19I-15 Table 19I-4 HCLPF Derivation for the ABWR Accident Sequences (MIN-MAX Method)..... 19I-16 Table 19K-1 ABWR SSCs of Greatest Importance for CDF, Level 1 Analysis.........................19K-18 Table 19K-2 ABWR SSCs With Moderate Risk Achievement Worth For CDF, Level 1 Analysis..................................................................................................................19K-19 Table 19K-3 ABWR Initiating Event Contribution to CDF, Level 1 Analysis ..........................19K-20 Table 19K-4 Failure Modes and RAP Activities ........................................................................19K-21 Table 19L-1 ABWR Modes of Operation .................................................................................. 19L-26 Table 19L-2 Control Rod Drop Accident ................................................................................... 19L-27 Table 19L-3 Control Rod Ejection Accident .............................................................................. 19L-29 Table 19L-4 Refueling Error ...................................................................................................... 19L-30 Table 19L-5 Potential for Draining RPV During RIP Maintenance........................................... 19L-30 Table 19L-6 Potential for Draining RPV Through Control Rod Drive Hydraulic System at Shutdown ........................................................................................................... 19L-31 Table 19L-7 Potential for Draining RPV Through Reactor Water Cleanup System.................. 19L-33 Table 19L-8 Potential for Draining RPV Through Residual Heat Removal System ................. 19L-36 Table 19L-9 Dependency of Core Cooling Systems on Electrical Power.................................. 19L-41 150 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Tables (Continued)

Table 19L-10 Success Criteria for Long-Term Heat Removal for Operating Mode 4................. 19L-42 Table 19L-11 Dependency of Heat Removal Systems on Electrical Power ................................ 19L-42 Table 19L-12 ABWR Seismic PRA: Highest Class I Accident Frequency Sequences ............... 19L-43 Table 19M-1 Fire Risk Screening Analysis Summary ............................................................... 19M-12 Table 19M-2 Weighting Factors for Adjusting Generic Location Fire Frequencies for Application to Plant-Specific Locations (References FIVE Table1.1)................. 19M-13 Table 19M-3 Fire Compartment-Division 1 Ignition Source Data Sheet (ISDS) (Taken from Draft FIVE Methodology) .................................................................................... 19M-15 Table 19M-4 Fire Compartment - Division 2 Ignition Source Data Sheet (ISDS) (Taken from Draft FIVE Methodology)............................................................................ 19M-16 Table 19M-5 Fire Compartment - Division 3 Ignition Source Data Sheet (ISDS) (Taken from Draft FIVE Methodology)............................................................................ 19M-17 Table 19M-6 Reactor and Control Building Fire Areas Explanatory Notes (for Tables 19M-3,4 & 5) (FIVE, Table 3) .................................................................. 19M-18 Table 19M-7 Fire Compartment - Turbine Building Ignition Source Data Sheet (ISDS)

(Taken from Draft FIVE Methodology) ............................................................... 19M-19 Table 19M-8 Turbine Building Explanatory Notes (For Table 19M-7) (FIVE, Table 3) .......... 19M-20 Table 19M-9 Fire Compartment - Control Room Complex Ignition Source Data Sheet (ISDS) (Taken from Draft FIVE Methodology) ................................................... 19M-21 Table 19M-10 Control Room Complex Explanatory Notes (For Table 19M-9) (FIVE, Table 3) ................................................................................................................. 19M-22 Table 19M-11 ABWR Fire Screening Analysis Summary........................................................... 19M-23 Table 19M-12 Divisional and Control Room Fire Risk W/Remote Control of RCIC & 4SRVs for CR Fires........................................................................................................... 19M-24 Table 19M-13 Summary of ABWR Risk Screening Analyses for Turbine Building Fire ........... 19M-25 Table 19M-14 ABWR Control Room Fire Risk Screening Analysis Summary .......................... 19M-26 Table 19Q-1 ABWR Features That Minimize Shutdown Risk...................................................19Q-44 Table 19Q-2 Success Criteria for Prevention of Core Damage ..................................................19Q-49 Table 19Q-3 Minimum Sets of Systems for Modes 3 and 4 .......................................................19Q-49 Table 19Q-4 Minimum Sets of Systems for Mode 5 (Unflooded)..............................................19Q-50 Table of Contents 151

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Tables (Continued)

Table 19Q-5 Minimum Sets of Systems for Mode 5 (Flooded) .................................................19Q-50 Table 19Q-6 Shutdown Vulnerability Evaluation of new ABWR Features ...............................19Q-51 Table 19QB-1 Time to Boiling for the RPV and RPV Plus SFP.................................................. 19QB-5 Table 19QB-2 Time for RPV Water Level to Reach TAF ........................................................... 19QB-5 Table 19QB-3 Probability of Failure to Diagnose ........................................................................ 19QB-5 Table 19QB-4 Probability of Failure to Start a Specified Minimum-Set System..................... 19QB-6 Table 19QB-5 Control Room Alarms and Indications Aiding Diagnosis of One RHR Lost ............................................................................................................ 19QB-6 Table 19QB-6 Times Available (in Hours)................................................................................... 19QB-6 Table 19QC-1 Loss of Offsite Power Precursors.......................................................................... 19QC-3 Table 19QC-2 Decay Heat Removal Precursors......................................................................... 19QC-14 Table 19R-1 Sources of Water.................................................................................................... 19R-30 Table 19R-2 Reactor Building Floor Descriptions ..................................................................... 19R-32 Table 19R-3 ABWR Flood Frequency ....................................................................................... 19R-33 Table 19R-4 Reliability Data for ABWR Probabilistic Flood Analysis ..................................... 19R-34 Table 19R-5 Conditional Failure Probability of Safe Shutdown ................................................ 19R-35 Table 19R-6 Internal Flooding Core Damage Frequency (CDF) ............................................... 19R-35 Table 19R-7 ABWR Features to Prevent/Mitigate Flooding...................................................... 19R-36 152 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures Figure 19.3-1 Overview of Methodology for Assessing Frequency of Core Damage and Fission Product Releases ..........................................................................19.3-31 Figure 19.3-2 Reactor Shutdown Event Tree .........................................................................19.3-32 Figure 19B-1 Double Feedwater Nozzle-Thermal Sleeve ................................................... 19B-125 Figure 19E.2-1 Simplified Sketch of N2 Supplies to Safety Grade ADS Valves................... 19E-179 Figure 19E.2-2a LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Vessel Pressure.......................................................................................................... 19E-180 Figure 19E.2-2b LCLP-PF-R-N: Loss of all core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Drywell Pressure.......................................................................................................... 19E-181 Figure 19E.2-2c LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Gas Temperature................................................................................................... 19E-182 Figure 19E.2-2d LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: UO2 Temperature................................................................................................... 19E-183 Figure 19E.2-2e LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Water Mass............................................................................................................... 19E-184 Figure 19E.2-2f LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Mass of Non-Condensables......................................................................................... 19E-185 Figure 19E.2-2g LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Noble Gases.............................................................................................................. 19E-186 Figure 19E.2-2h LCLP-PF-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Volatile Fission Products............................................................................................. 19E-187 Figure 19E.2-2i LCLP-PF-R-N: Loss of All Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Water Height ............................................................................................................ 19E-188 Figure 19E.2-2j LCLP-PF-R-N: Loss of All Core Cooling with Vessel Failure at Low Pressure, Passive Flooder Operates and Rupture Disk Opens: Water Temperature................................................................................................... 19E-189 Table of Contents 153

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19E.2-3a LCLP-FS-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Drywell Pressure.......................................................................................................... 19E-190 Figure 19E.2-3b LCLP-FS-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Gas Temperature................................................................................................... 19E-191 Figure 19E.2-3c LCLP-FS-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Water Mass............................................................................................................... 19E-192 Figure 19E.2-3d LCLP-FS-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Noble Gas ... 19E-193 Figure 19E.2-3e LCLP-FS-R-N: Loss of all Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Volatile Fission Products............................................................................................. 19E-194 Figure 19E.2-3f LCLP-FS-R-N: Loss of All Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Water Height ............................................................................................................ 19E-195 Figure 19E.2-3g LCLP-FS-R-N: Loss of All Core Cooling with Vessel Failure at Low Pressure, Firewater Spray Operates and Rupture Disk Opens: Water Temperature................................................................................................... 19E-196 Figure 19E.2-4a LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Vessel Pressure.................................................................................. 19E-197 Figure 19E.2-4b LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Drywell Pressure ............................................................................... 19E-198 Figure 19E.2-4c LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: UO2 Temperature .............................................................................. 19E-199 Figure 19E.2-4d LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Gas Temperature ............................................................................... 19E-200 Figure 19E.2-4e LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: UO2 Mass .......................................................................................... 19E-201 154 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19E.2-4f LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Water Mass........................................................................................ 19E-202 Figure 19E.2-4g LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Global Mass....................................................................................... 19E-203 Figure 19E.2-4h LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Noble Gases....................................................................................... 19E-204 Figure 19E.2-4i LCHP-PS-R-N: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder and Drywell Sprays Operate, Rupture Disk Opens: Volatiles ............................................................................................ 19E-205 Figure 19E.2-5a LCHP-PF-P-M: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder Operates, Penetration Leakage: Drywell Pressure.......................................................................................................... 19E-206 Figure 19E.2-5b LCHP-PF-P-M: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder Operates, Penetration Leakage: Gas Temperature................................................................................................... 19E-207 Figure 19E.2-5c LCHP-PF-P-M: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder Operates, Penetration Leakage: UO2 Temperature................................................................................................... 19E-208 Figure 19E.2-5d LCHP-PF-P-M: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder Operates, Penetration Leakage: Water Mass ....... 19E-209 Figure 19E.2-5e LCHP-PF-P-M: Loss of all Core Cooling with Vessel Failure at High Pressure, Passive Flooder Operates, Penetration Leakage: Fission Product Release ............................................................................................. 19E-210 Figure 19E.2-6a SBRC-FA-R-0: Station Blackout, RCIC Runs Eight Hours, Firewater Addition Prevents Core Damage, Rupture Disk Opens: Drywell Pressure.......................................................................................................... 19E-211 Figure 19E.2-6b SBRC-FA-R-0: Station Blackout, RCIC Runs Eight Hours, Firewater Addition Prevents Core Damage, Rupture Disk Opens: Water Temperature................................................................................................... 19E-212 Figure 19E.2-6c SBRC-FA-R-0: Station Blackout, RCIC Runs Eight Hours, Firewater Addition Prevents Core Damage, Rupture Disk Opens: UO2 Temperature................................................................................................... 19E-213 Table of Contents 155

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19E.2-6d SBRC-FA-R-0: Station Blackout, RCIC Runs Eight Hours, Firewater Addition Prevents Core Damage, Rupture Disk Opens: Vessel Water Height ............................................................................................................ 19E-214 Figure 19E.2-6e SBRC-FA-R-0: Station Blackout, RCIC Runs Eight Hours, Firewater Addition Prevents Core Damage, Rupture Disk Opens: Water Mass ........... 19E-215 Figure 19E.2-7a SBRC-PF-R-N: Station Blackout with RCIC Operating, Passive Flooder Operates and Rupture Disk Opens: Vessel Pressure ..................................... 19E-216 Figure 19E.2-7b SBRC-PF-R-N: Station Blackout with RCIC Operating, Passive Flooder Operates and Rupture Disk Opens: Drywell Pressure................................... 19E-217 Figure 19E.2-7c SBRC-PF-R-N: Station Blackout with RCIC Operating, Passive Flooder Operates and Rupture Disk Opens: Gas Temperature................................... 19E-218 Figure 19E.2-7d SBRC-PF-R-N: Station Blackout with RCIC Operating, Passive Flooder Operates and Rupture Disk Opens: UO2 Temperature.................................. 19E-219 Figure 19E.2-7e SBRC-PF-R-N: Station Blackout with RCIC Operating, Passive Flooder Operates and Rupture Disk Opens: Water Mass ........................................... 19E-220 Figure 19E.2-7f SBRC-PF-R-N: Station Blackout with RCIC Operating, Passive Flooder Operates and Rupture Disk Opens: Volatile Fission Product Release .......... 19E-221 Figure 19E.2-8a LHRC-00-R-0: Isolation with Loss of Containment Heat Removal and Rupture Disk Opens: Pressure ....................................................................... 19E-222 Figure 19E.2-8b LHRC-00-R-0: Isolation with Loss of Containment Heat Removal and Rupture Disk Opens: Water Temperature ..................................................... 19E-223 Figure 19E.2-8c LHRC-00-R-0: Isolation with Loss of Containment Heat Removal and Rupture Disk Opens: Water Mass ................................................................. 19E-224 Figure 19E.2-9a LBLC-PF-R-N: Large Break LOCA with Loss of all Core Cooling, Passive Flooder Operates and Rupture Disk Opens: Drywell Pressure ........ 19E-225 Figure 19E.2-9b LBLC-PF-R-N: Large Break LOCA with Loss of all Core Cooling, Passive Flooder Operates and Rupture Disk Opens: Gas Temperature ........ 19E-226 Figure 19E.2-9c LBLC-PF-R-N: Large Break LOCA with Loss of all Core Cooling, Passive Flooder Operates and Rupture Disk Opens: Water Mass................. 19E-227 Figure 19E.2-9d LBLC-PF-R-N: Large Break LOCA with Loss of all Core Cooling, Passive Flooder Operates and Rupture Disk Opens: Volatile Fission Product Release ............................................................................................. 19E-228 Figure 19E.2-10a NSCL-PF-R-N: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at Low Pressure, Passive Flooder and Rupture Disk:

Drywell Pressure............................................................................................ 19E-229 156 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19E.2-10b NSCL-PF-R-N: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at Low Pressure, Passive Flooder and Rupture Disk: UO2 Temperature................................................................................................... 19E-230 Figure 19E.2-10c NSCL-PF-R-N: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at Low Pressure, Passive Flooder and Rupture Disk:

Water Mass .................................................................................................... 19E-231 Figure 19E.2-10d NSCL-PF-R-N: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at Low Pressure, Passive Flooder and Rupture Disk:

Volatile Fission Products............................................................................... 19E-232 Figure 19E.2-11a NSCH-PF-P-M: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at High Pressure, Passive Flooder, Penetration Leakage:

Drywell Pressure............................................................................................ 19E-233 Figure 19E.2-11b NSCH-PF-P-M: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at High Pressure, Passive Flooder, Penetration Leakage:

Gas Temperature............................................................................................ 19E-234 Figure 19E.2-11c NSCH-PF-P-M: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at High Pressure, Passive Flooder, Penetration Leakage:

UO2 Mass ...................................................................................................... 19E-235 Figure 19E.2-11d NSCH-PF-P-M: Concurrent Loss of all Core Cooling and ATWS with Vessel Failure at High Pressure, Passive Flooder, Penetration Leakage:

Fission Products............................................................................................. 19E-236 Figure 19E.2-12a NSRC-PF-R-N: Concurrent Station Blackout with ATWS, Passive Flooder Operates and Rupture Disk Opens: Vessel Pressure........................ 19E-237 Figure 19E.2-12b NSRC-PF-R-N: Concurrent Station Blackout with ATWS, Passive Flooder Operates and Rupture Disk Opens: Drywell Pressure ..................... 19E-238 Figure 19E.2-12c NSRC-PF-R-N: Concurrent Station Blackout with ATWS, Passive Flooder Operates and Rupture Disk Opens: Power....................................... 19E-239 Figure 19E.2-12d NSRC-PF-R-N: Concurrent Station Blackout with ATWS, Passive Flooder Operates and Rupture Disk Opens: UO2 Temperature .................... 19E-240 Figure 19E.2-12e NSRC-PF-R-N: Concurrent Station Blackout with ATWS, Passive Flooder Operates and Rupture Disk Opens: Water Mass.............................. 19E-241 Figure 19E.2-12f NSRC-PF-R-N: Concurrent Station Blackout with ATWS, Passive Flooder Operates and Rupture Disk Opens: Volatile Fission Product Release........................................................................................................... 19E-242 Figure 19E.2-13 Steam Explosion Process............................................................................... 19E-243 Figure 19E.2-14a Interfacial Instability...................................................................................... 19E-244 Table of Contents 157

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19E.2-14b Corium Stream in Liquid ............................................................................... 19E-245 Figure 19E.2-15 Important Response Times ............................................................................ 19E-246 Figure 19E.2-16 Self-Triggering Process ................................................................................. 19E-247 Figure 19E.2-17 Conditions for Steam Explosion.................................................................... 19E-248 Figure 19E.2-18 Application to ABWR ................................................................................... 19E-249 Figure 19E.2-19a Suppression Pool Bypass Paths and Configurations ..................................... 19E-250 Figure 19E.2-19b Suppression Pool Bypass Paths and Configurations ..................................... 19E-251 Figure 19E.2-19c Suppression Pool Bypass Paths and Configurations ..................................... 19E-252 Figure 19E.2-19d Suppression Pool Bypass Paths and Configurations ..................................... 19E-253 Figure 19E.2-19e Suppression Pool Bypass Paths and Configurations ..................................... 19E-254 Figure 19E.2-19f Suppression Pool Bypass Paths and Configurations ..................................... 19E-255 Figure 19E.2-19g Suppression Pool Bypass Paths and Configurations ..................................... 19E-256 Figure 19E.2-19h Suppression Pool Bypass Paths and Configurations ..................................... 19E-257 Figure 19E.2-19i Suppression Pool Bypass Paths and Configurations ..................................... 19E-258 Figure 19E.2-19j Suppression Pool Bypass Paths and Configurations ..................................... 19E-259 Figure 19E.2-19k Suppression Pool Bypass Paths and Configurations ..................................... 19E-260 Figure 19E.2-20a Small LOCAs Outside Containment ............................................................. 19E-261 Figure 19E.2-20b Intermediate LOCAs Outside Containment .................................................. 19E-262 Figure 19E.2-20c Large LOCAs Outside Containment ............................................................. 19E-263 Figure 19E.2-21 Sensitivity to Suppression Pool Decontamination Factor ............................. 19E-264 Figure 19E.2-22 Impact of COPS on Risk ............................................................................... 19E-265 Figure 19E.2-23 Lower Drywell Flooder System .................................................................... 19E-266 Figure 19E.2-24 Flooder Valve Assembly ............................................................................... 19E-267 Figure 19E.2-25 Limiting Configuration for COPS Blowdown Study .................................... 19E-268 Figure 19E.2-26a Drywell Pressure for 100% Metal-Water Reaction Scenario ........................ 19E-269 Figure 19E.2-26b Wetwell Pressure for 100% Metal-Water Reaction Scenario ....................... 19E-270 158 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19E.2-26c Drywell Temperature for 100% Metal-Water Reaction Scenario ................. 19E-271 Figure 19E.2-26d Vessel Temperature for 100% Metal-Water Reaction Scenario ................... 19E-272 Figure 19E.2-26e Suppression Pool Water Temperature for 100% Metal-Water Scenario....... 19E-273 Figure 19E.2-27a Drywell Pressure for In-Vessel Core Melt Scenario ..................................... 19E-274 Figure 19E.2-27b Vessel Pressure for In-Vessel Core Melt Scenario........................................ 19E-275 Figure 19E.2-27c Wetwell Pressure for In-Vessel Core Melt Scenario..................................... 19E-276 Figure 19E.2-27d Drywell Temperature for In-Vessel Core Melt Scenario .............................. 19E-277 Figure 19E.2-27e Vessel Temperature for In-Vessel Core Melt Scenario................................. 19E-278 Figure 19E.2-27f Suppression Pool Water Temperature for In-Vessel Core Melt.................... 19E-279 Figure 19E.2-28a Drywell Pressure for High Pressure Ex-Vessel Core Melt Scenario............. 19E-280 Figure 19E.2-28b Vessel Pressure for Ex-Vessel High Pressure Core Melt Scenario ............... 19E-281 Figure 19E.2-28c Wetwell Pressure for Ex-Vessel High Pressure Core Melt Scenario ............ 19E-282 Figure 19E.2-28d Drywell Temperature for Ex-Vessel High Pressure Core Melt Scenario...... 19E-283 Figure 19E.2-28e Vessel Temperature for Ex-Vessel High Pressure Core Melt ....................... 19E-284 Figure 19E.2-28f Suppression Pool Water Temperature for High Pressure Ex-Vessel Core Melt Scenario................................................................................................. 19E-285 Figure 19E.2-29a Drywell Pressure for Low Pressure Ex-Vessel Core Melt Scenario ............. 19E-286 Figure 19E.2-29b Vessel Pressure for Ex-Vessel Low Pressure Core Melt Scenario................ 19E-287 Figure 19E.2-29c Wetwell Pressure for Ex-Vessel Low Pressure Core Melt Scenario............. 19E-288 Figure 19E.2-29d Drywell Temperature for Ex-Vessel Low Pressure Core Melt ..................... 19E-289 Figure 19E.2-29e Vessel Temperature for Ex-Vessel Low Pressure Core Melt Scenario......... 19E-290 Figure 19E.2-29f Suppression Pool Water Temperature for Low Pressure Ex-Vessel Core Melt Scenario................................................................................................. 19E-291 Figure 19E.3-1 Whole Body Dose at 805 m (0.5 Mile) as Probability of Exceedence .......... 19E-302 Figure 19EA-1 DCH Event Tree for Sequences with Low Containment Pressure ............... 19EA-31 Figure 19EA-2 DCH Event Tree for Sequences with Intermediate Containment Pressure......................................................................................................... 19EA-32 Table of Contents 159

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19EA-3 DCH Event Tree for Sequences with High Containment Pressure .............. 19EA-33 Figure 19EA-4 DET for Probability of Early Containment FailureHigh RV Press and Low Cont Press Sequences........................................................................... 19EA-34 Figure 19EA-5 DET for Probability of Early Containment FailureHigh RV Press and Inter Cont Press Sequences........................................................................... 19EA-35 Figure 19EA-6 DET for Probability of Early Containment FailureHigh RV Press and High Cont Press Sequences .......................................................................... 19EA-36 Figure 19EA-7 ABWR Containment Boundary Nomenclature ............................................ 19EA-37 Figure 19EA-8 Calculated Probability Distribution Function for DCH Parameter Ffrag ...... 19EA-38 Figure 19EA-9 Comparison of Calculated and Assumed Ffrag Distributions ....................... 19EA-39 Figure 19EA-10 Effective Drag Coefficient for Dense Dispersions ....................................... 19EA-40 Figure 19EA-11 Zion Reactor Building .................................................................................. 19EA-41 Figure 19EA-12 Schematic of Grand Gulf Containment ........................................................ 19EA-42 Figure 19EA-13 Comparison of Assumed Debris Discharge to ANL Data Fit ...................... 19EA-43 Figure 19EA-14 Cumulative Distribution for Peak Pressure Due to DCH ............................. 19EA-44 Figure 19EA-15 Uncertainty in Whole Body Dose at 805 m (0.5 Mile) Due to DCH ........... 19EA-45 Figure 19EB-1 BETA V6.1 Configuration ............................................................................19EB-25 Figure 19EB-2 HIPS Experimental Configuration.................................................................19EB-26 Figure 19EB-3 Peak Impulse Pressure from FCI ...................................................................19EB-27 Figure 19EB-4 Maximum Response of Elastic-plastic One-degree Systems (Undamped)

Due to Rectangular Load Pulses (Reference 19EB-18) ................................19EB-28 Figure 19EB-5 Rise Height of Water Missile ........................................................................19EB-29 Figure 19EB-6 ABWR Containment Configuration ..............................................................19EB-30 Figure 19EB-7 Pressure Head for Lower Drywell Flooder Flow ..........................................19EB-31 Figure 19EB-8 Ablated Radius of Vessel Failure ..................................................................19EB-32 Figure 19EB-9 Mass Flow of Core Debris Through Vessel Failure ......................................19EB-33 Figure 19EC-1 Core Debris Concrete Attack DET ................................................................19EC-28 Figure 19EC-2 Containment Event Evaluation DET for Pedestal Failure.............................19EC-29 160 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19EC-3 Sample Calculation for CCI Upward Heat Flux 100 kW/m2: Axial Concrete Attack .............................................................................................19EC-30 Figure 19EC-4 Sample Calculation for CCI Upward Heat Flux 100 kW/m2: Wetwell Pressure..........................................................................................................19EC-31 Figure 19EC-5 Sample Calculation for CCI Upward Heat Flux 100 kW/m2: Upper Drywell Temperature.....................................................................................19EC-32 Figure 19EC-6 Sample Calculation for CCI Upward Heat Flux 100 kW/m2: LDW Water Mass ....................................................................................................19EC-33 Figure 19EC-7 Sample Calculation for CCI Upward Heat Flux 100 kW/m2: Average Corium Temperature......................................................................................19EC-34 Figure 19EC-8 Whole Body Dose at 805 m (0.5 Mile) as a Probability of Exceedence .......19EC-35 Figure 19ED-1 Conceptual Design of Lower Drywell Floor Drain Sump Shield ................ 19ED-32 Figure 19ED-2 Temperature Profile in Channel Region ....................................................... 19ED-33 Figure 19ED-3 Channel Flow Height Reduction During Freeze Process ............................. 19ED-34 Figure 19EE-1 Containment Event Evaluation DET for Suppression Pool Bypass ..............19EE-16 Figure 19EE-2 Impact of Aerosol Plugging Credit on Offsite Risk Measured by Whole Body Dose at 805 m (0.5 Mile) as Probability of Exceedence......................19EE-17 Figure 19F-1 ABWR Reactor Building/ Primary Containment (0° - 180° Section View) ....19F-19 Figure 19F-2 Primary Containment Configuration ................................................................19F-19 Figure 19F-3 FINEL Model ...................................................................................................19F-20 Figure 19F-4 Drywell Head....................................................................................................19F-21 Figure 19F-5 Drywell Head Pressure Capability vs Temperature .........................................19F-22 Figure 19F-6 Torispherical Head Buckling Test Data ...........................................................19F-23 Figure 19F-7 Torispherical Head Buckling Test Data Statistical Distribution ......................19F-24 Figure 19F-8 Containment Liner Buckling ............................................................................19F-25 Figure 19F-9 Definition of Squeeze for Seals ........................................................................19F-26 Figure 19H-1 Typical Fragility Curves ..................................................................................19H-32 Figure 19L-1 Potential Paths for Draining RPV Through Control Rod Drive Hydraulic System ............................................................................................................. 19L-44 Table of Contents 161

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19L-2 Potential Path for Draining RPV Through Reactor Water Cleanup System ... 19L-45 Figure 19L-3 Potential Path for Draining RPV Through Residual Heat Removal System (Pump On) ....................................................................................................... 19L-46 Figure 19M-1 Phase I Qualitative Analysis Flow Chart........................................................ 19M-27 Figure 19M-2 Phase II Qualitative Analysis Flow Chart ...................................................... 19M-28 Figure 19M-3 Division 1 Electrical Fire................................................................................ 19M-29 Figure 19M-4 Division 2 Electrical Fire................................................................................ 19M-30 Figure 19M-5 Division 3 Electrical Fire................................................................................ 19M-31 Figure 19M-6 Control Room Fire.......................................................................................... 19M-32 Figure 19M-7 Turbine Building Fire (Loss of Offsite Power and Station Blackout Event Tree)................................................................................................................ 19M-33 Figure 19M-8 Loss of Offsite Power Event Tree (Recovery time: 30 min< t < 2 h) ............ 19M-34 Figure 19M-9 Loss of Offsite Power Event Tree (Recovery time: 2 hrs< t < 8 h)................ 19M-35 Figure 19M-10 Loss of Offsite Power Event Tree (Recovery time: t > 8 h)........................... 19M-36 Figure 19M-11 Station Blackout Event Tree (Recovery time: 30 min < t < 2 h).................... 19M-37 Figure 19M-12 Station Blackout Event Tree (Recovery time: 2 hrs< t <8 h) ......................... 19M-38 Figure 19M-13 Station Blackout Event Tree (Recovery time: t > 8 h) ................................... 19M-39 Figure 19N-1 Not Used ..........................................................................................................19N-19 Figure 19N-2 Not Used ..........................................................................................................19N-19 Figure 19N-3 Event Tree for Analysis of Common-Cause Failure of EMUX ......................19N-20 Figure 19N-4 Event Tree for Failure to Isolate Due to EMUX CCF.....................................19N-21 Figure 19R-1 Control Building .............................................................................................. 19R-39 Figure 19R-2 Reactor Service Water System ........................................................................ 19R-40 Figure 19R-3 Reactor Building ArrangementElevation -8200 mm (B3F)........................ 19R-41 Figure 19R-4 Reactor Building ArrangementElevation -1700 mm (B2F)........................ 19R-42 Figure 19R-5 Reactor Building ArrangementElevation 4800 mm (B1F).......................... 19R-43 Figure 19R-6 Reactor Building ArrangementElevation 12300 mm (1F) .......................... 19R-44 162 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 19 List of Figures (Continued)

Figure 19R-7 Turbine Building Flooding (Low PCHS) ........................................................ 19R-45 Figure 19R-8 Turbine Building Flooding (High PCHS) ....................................................... 19R-46 Figure 19R-9 RSW Control Building Flood .......................................................................... 19R-47 Figure 19R-10 Fire Water Flood in the Control Building ....................................................... 19R-48 Figure 19R-11 Reactor Building Flooding in ECCS Room .................................................... 19R-49 Figure 19R-12 Reactor Building Flooding in Corridor ........................................................... 19R-50 Figure 19R-13 Fire Water Flood in the Reactor Building Outside Secondary Containment..................................................................................................... 19R-51 Table of Contents 163

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 20 Table of Contents 20.0 Question and Response Guide .....................................................................................................20.1-1 20.1 Question Index .............................................................................................................................20.1-1 20.2 Questions .....................................................................................................................................20.2-1 20.2.1 Chapter 1 Questions ....................................................................................................20.2-2 20.2.2 Chapter 2 Questions ....................................................................................................20.2-3 20.2.3 Chapter 3 Questions ....................................................................................................20.2-4 20.2.4 Chapter 4 Questions ..................................................................................................20.2-27 20.2.5 Chapter 5 Questions ..................................................................................................20.2-31 20.2.6 Chapter 6 Questions ..................................................................................................20.2-47 20.2.7 Chapter 7 Questions ..................................................................................................20.2-65 20.2.8 Chapter 8 Questions ..................................................................................................20.2-81 20.2.9 Chapter 9 Questions ................................................................................................20.2-101 20.2.10 Chapter 10 Questions ..............................................................................................20.2-134 20.2.11 Chapter 11 Questions ..............................................................................................20.2-140 20.2.12 Chapter 12 Questions ..............................................................................................20.2-149 20.2.13 Chapter 13 Questions ..............................................................................................20.2-155 20.2.14 Chapter 14 Questions ..............................................................................................20.2-160 20.2.15 Chapter 15 Questions ..............................................................................................20.2-161 20.2.16 Chapter 16 Questions ..............................................................................................20.2-166 20.2.17 Chapter 17 Questions ..............................................................................................20.2-167 20.2.18 Chapter 18 Questions ..............................................................................................20.2-168 20.2.19 Chapter 19 Questions ..............................................................................................20.2-176 20.3 Questions/Responses ...................................................................................................................20.3-1 20.3.1 Response to First RAI Reference 1 ........................................................................20.3-2 20.3.2 Response to Second RAI Reference 2..................................................................20.3-24 20.3.3 Response to Third RAI Reference 3...................................................................20.3-101 20.3.4 Response to Fourth RAI Reference 4.................................................................20.3-126 20.3.5 Response to Fifth RAI Reference 5....................................................................20.3-162 20.3.6 Response to Sixth RAI Reference 6 ...................................................................20.3-183 20.3.7 Response to Seventh RAI Reference 7...............................................................20.3-207 20.3.8 Response to Eighth RAI Reference 8.................................................................20.3-250 20.3.9 Response to Ninth RAI Reference 9 ..................................................................20.3-353 20.3.10 Response to Tenth RAI Reference 10 ................................................................20.3-368 20.3.11 Response to Eleventh RAI Reference 11 ...........................................................20.3-392 20.3.12 Response to Twelfth RAI Reference 12.............................................................20.3-403 20.3.13 Response to Thirteenth RAI Reference 13.........................................................20.3-412 20.3.14 Response to Fourteenth RAIReference 14 ..........................................................20.3-434 20.3.15 Response to Fifteenth RAI Reference 15 ...........................................................20.3-466 20.3.16 Response to Sixteenth RAI Reference 16 ..........................................................20.3-504 20.3.17 Response to Seventeenth RAI Reference 17 ......................................................20.3-542 20.4 References....................................................................................................................................20.4-1 20A ODYNA/REDYA ........................................................................................................................20A-1 20A.1 ODYNA Changes........................................................................................................20A-1 164 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 20 Table of Contents (Continued) 20A.2 REDYA Changes.........................................................................................................20A-2 20A.3 Verification of Code Modifications.............................................................................20A-5 20B Equipment Data Base................................................................................................................... 20B-1 Table of Contents 165

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 20 List of Tables Table 20.1-1 Identification Numbers for NRC Review Questions .............................................20.1-31 Table 20.2-1 Comparison of requirements in ABWR standard safety analyses report and ABWR presentation to NRC staff (October 21 and 22, 1987) ..............................20.2-36 Table 20.3.1-1 Sensitivity Study of Parameters for LOCA Analysis (Response to Question 470.4) ......................................................................................................20.3-23 Table 20.3.2-1 Core Decay Heat Following LOCA Short-Term Analyses (Response to Question 430.21) ....................................................................................................20.3-78 Table 20.3.2-2 Integrated Core Decay Heat Values Short-Term Analysis (Response to Question 430.21) ....................................................................................................20.3-79 Table 20.3.2-3 Isolation Valve Arrangements Not Meeting the Explicit Requirements of GDC56 (Response to Question 430.41).................................................................20.3-80 Table 20.3.2-4 Line Whose Containment Isolation Requirements are Covered By GDC57 (Response to Question 430.44) ..............................................................................20.3-82 Table 20.3.2-5 Hot Startup Criticality Rod Sequence (Response to Question 440.11) .................20.3-83 Table 20.3.3-1 Verification Matrix for SASSI Ver. 1.0 (Response to Question 220.3) ..............20.3-121 Table 20.3.3-2 Not Used...............................................................................................................20.3-123 Table 20.3.4-1 Automatic Rod Movement (Response to Question 440.30) ................................20.3-156 Table 20.3.4-2 Manual Rod Movement (Response to Question 440.30) .....................................20.3-156 Table 20.3.8-1 List of RCIC Equipment with Thermal Overload Relay Bypass (Response to Question 435.60)..............................................................................................20.3-351 Table 20.3.16-1 Safety Related Valves Located in the Main Steam Tunnel (MST) (Response to Question 430.335 .............................................................................................20.3-541 Table 20B-1 Equipment Data Base ............................................................................................... 20B-2 166 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 20 List of Figures Figure 20.3.2-1 Isolation Valve Arrangement of Standby Liquid Control System Line (Response to Question 430.40) ...........................................................................20.3-84 Figure 20.3.2-2 Rod Groups 1 - 4, Sequence A (Response to Question 440.11) ........................20.3-85 Figure 20.3.2-3 Rod Groups 5 - 10, Sequence A (Response to Question 440.11) ......................20.3-86 Figure 20.3.2-4 Hot Recovery Criticality Control (Response to Question 440.11) .....................20.3-87 Figure 20.3.2-5 5% Power Control Rod Pattern (Response to Question 440.11) ........................20.3-88 Figure 20.3.2-6 10% Power Control Rod Pattern (Response to Question 440.11) ......................20.3-89 Figure 20.3.2-7 25% Power Control Rod Pattern (Response to Question 440.11) ......................20.3-90 Figure 20.3.2-8 40% Power Control Rod Pattern (Response to Question 440.11) ......................20.3-91 Figure 20.3.2-9 53% Power Control Rod Pattern (Response to Question 440.11) ......................20.3-92 Figure 20.3.2-10 100% Power Control Rod Pattern (Response to Question 440.11) ....................20.3-93 Figure 20.3.2-11 Grouped HCU to Control Rod Drive Assignments (Response to Question 440.12).................................................................................................20.3-94 Figure 20.3.2-11a Drywell Pressure Versus Time (Response to Question 430.13).........................20.3-95 Figure 20.3.2-11b Drywell Pressure Versus Time (Response to Question 430.13)........................20.3-96 Figure 20.3.2-11c Drywell Pressure Versus Time (Response to Question 430.13).........................20.3-97 Figure 20.3.2-11d Drywell Pressure Versus Time (Response to Question 430.13).........................20.3-98 Figure 20.3.2-11e Drywell Pressure Versus Time (Response to Question 430.13).........................20.3-99 Figure 20.3.2-11f Drywell Pressure Versus Time (Response to Question 430.13).......................20.3-100 Figure 20.3.3-1 Shake Analysis Results - Soil Profile UB1D150 (Response to Question 220.8).................................................................................................20.3-124 Figure 20.3.3-2 Shake Analysis Results - Soil Profile VP2D150 (Response to Question 220.8).................................................................................................20.3-125 Figure 20.3.4-1 MSIV Closure with Flux Scram (Response to Question 440.14).....................20.3-157 Figure 20.3.4-2 Peak Vessel Pressure Versus Safety/Relief Valve Capacity (Response to Question 440.14)...............................................................................................20.3-158 Figure 20.3.4-3 MSIV Closure-Flux Scram (Response to Question 440.16).............................20.3-159 Figure 20.3.4-4 Control Rod Drop Accident Scenario for FMCRD (Response To Question 440.32)...............................................................................................20.3-160 Table of Contents 167

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 20 List of Figures (Continued)

Figure 20.3.4-5a Low Pressure Core Flooder Sparger (Sheet 1) .................................................20.3-161 Figure 20.3.4-5b Low Pressure Core Flooder Sparger (Sheet 2) .................................................20.3-161 Figure 20.3.4-5c High Pressure Core Flooder Sparger (Response to Question 440.59)..............20.3-161 Figure 20.3.7-1 Stability Controls and Protection Logic (Response to Question 100.1) ...........20.3-247 Figure 20.3.7-2 Relationship Between Modes (Response to Question 100.1)...........................20.3-248 Figure 20.3.7-3 Penetration Shielding Relationship to Core Midplane Dose (Response to Question 471.33)...............................................................................................20.3-249 Figure 20.3.8-1 ABWR RPT Logic (Response to Question 420.106) .......................................20.3-352 Figure 20.3.10-1 Simplified Functional Control Diagram of Turbine Digital Control and Monitoring System (Typical of One of Three Channels) .................................20.3-391 Figure 20.3.14-1 Relationship of System Training Material Preparation to Other Plant Design and Procurement Activities (Response to Question 620.8)..................20.3-465 Figure 20.3.15-1 Compressed Gas Systems Interconnections (Response to Question 430.217).............................................................................................20.3-503 168 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 1 List of Figures Figure 1.2-2 Reactor Building, Arrangement Elevation, Section A-A............................................21-1 Figure 1.2-2a Reactor Building, Arrangement Elevation, Section B-B ............................................21-2 Figure 1.2-3 Upper Drywell, Arrangement Elevation, Section A-A ...............................................21-3 Figure 1.2-3a Upper Drywell, Arrangement Elevation, Section B-B................................................21-3 Figure 1.2-3b Lower Drywell, Arrangement Elevation, Section A-A...............................................21-4 Figure 1.2-3c Wetwell, Arrangement Elevation, Sections A-A & B-B ............................................21-5 Figure 1.2-4 Reactor Building, Arrangement Plan at Elevation -8200 mm ....................................21-6 Figure 1.2-5 Reactor Building, Arrangement Plan at Elevation -1700 mm ....................................21-7 Figure 1.2-6 Reactor Building, Arrangement Plan at Elevation 4800/8500 mm.............................21-8 Figure 1.2-8 Reactor Building, Arrangement Plan at Elevation 12300 mm....................................21-9 Figure 1.2-9 Reactor Building, Arrangement Plan at Elevation 18100 mm..................................21-10 Figure 1.2-10 Reactor Building, Arrangement Plan at Elevation 23500 mm..................................21-11 Figure 1.2-11 Reactor Building, Arrangement Plan at Elevation 27200 mm..................................21-12 Figure 1.2-12 Reactor Building, Arrangement Plan at Elevation 31700/38200 mm.......................21-13 Figure 1.2-13a Drywell, Arrangement Plan at Elevation 12300 mm ................................................21-14 Figure 1.2-13b Drywell, Arrangement Plan at Elevation 15600 mm ................................................21-15 Figure 1.2-13c Drywell, Arrangement Plan at Elevation 18100 mm ................................................21-16 Figure 1.2-13d Drywell Steel Structure at Elevation 18100 mm.......................................................21-17 Figure 1.2-13e Lower Drywell, Arrangement Plan at Elevation -6600 to -1850 mm.......................21-18 Figure 1.2-13f Lower Drywell, Arrangement Plan at Elevation -1850 to 1750 mm ........................21-19 Figure 1.2-13g Lower Drywell, Arrangement Plan at Elevation 1750 to 4800 mm .........................21-20 Figure 1.2-13h Lower Drywell, Arrangement Plan at Elevation 4800 to 6700 mm .........................21-21 Figure 1.2-13i Wetwell, Arrangement Plan at Elevation -8200 mm ................................................21-22 Figure 1.2-13j Wetwell, Arrangement Plan at Elevation -1700 mm ................................................21-23 Figure 1.2-13k Wetwell, Arrangement Plan at Elevation 4800 mm..................................................21-24 Figure 1.2-14 Control and Service Building, Arrangement Elevation, Section A-A ......................21-25 Table of Contents 169

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 1 List of Figures (Continued)

Figure 1.2-15 Control and Service Building, Arrangement Elevation, Section B-B.......................21-26 Figure 1.2-16 Control Building, Arrangement Plan at Elevation -8200 mm...................................21-27 Figure 1.2-17 Control and Service Building, Arrangement Plan at Elevation -2150 mm...............21-28 Figure 1.2-18 Control and Service Building, Arrangement Plan at Elevation 3500 mm ................21-29 Figure 1.2-19 Control and Service Building, Arrangement Plan at Elevation 7900 mm ................21-30 Figure 1.2-20 Control and Service Building, Arrangement Plan at Elevation 12300 mm ..............21-31 Figure 1.2-21 Control and Service Building, Arrangement Plan at Elevation 17150 mm ..............21-32 Figure 1.2-22 Control and Service Building, Arrangement Plan at Elevation 22200 mm ..............21-33 Figure 1.2-23a Radwaste Building at Elevation -1500 mm ..............................................................21-34 Figure 1.2-23b Radwaste Building at Elevation 4800 mm................................................................21-35 Figure 1.2-23c Radwaste Building at Elevation 12300 mm..............................................................21-36 Figure 1.2-23d Radwaste Building at Elevation 21000 mm..............................................................21-37 Figure 1.2-23e Radwaste Building, Section A-A ..............................................................................21-38 Figure 1.2-24 Turbine Building, General Arrangement at Elevation 5300 mm .............................21-39 Figure 1.2-25 Turbine Building, General Arrangement at Elevation 12300 mm ............................21-40 Figure 1.2-26 Turbine Building, General Arrangement at Elevation 20300 mm ............................21-41 Figure 1.2-27 Turbine Building, General Arrangement at Elevation 30300 mm ............................21-42 Figure 1.2-28 Turbine Building, General Arrangement, Longitudinal Section A-A.......................21-43 Figure 1.2-29 Turbine Building, General Arrangement, Section B-B.............................................21-44 Figure 1.2-30 Turbine Building, General Arrangement, Section C-C.............................................21-45 Figure 1.2-31 Turbine Building, General Arrangement, Section D-D ............................................21-46 Figure 1.7-1 Piping and Instrumentation Diagram Symbols (Sheets 1-2) ....................................21-47 Figure 3H.1-23 Reactor Building Reactor Cavity Shield Blocks .......................................................21-49 Figure 3H.1-28 Configuration of RPV Pedestal.................................................................................21-50 Figure 3H.1-29 Rebar Arrangement of F/P Girder and Slab (1/2) .....................................................21-51 Figure 3H.1-30 Containment Structure Wall Reinforcement .............................................................21-52 170 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 1 List of Figures (Continued)

Figure 3H.1-31 Containment Structure Opening Reinforcement .......................................................21-53 Figure 3H.1-32 Containment Structure Opening Reinforcement .......................................................21-54 Figure 3H.1-33 Containment Structure Top Slab Reinforcement ......................................................21-55 Figure 3H.1-34 Reactor Building Foundation Reinforcement (Sheet 1)............................................21-56 Figure 3H.1-35 Reactor Building Foundation Reinforcement (Sheet 2)............................................21-57 Figure 3H.1-36 Diaphragm Floor Reinforcement ..............................................................................21-58 Figure 3H.1-37 List of Seismic Wall Sections ...................................................................................21-59 Figure 3H.2-21 Control Building Floor Plan at Elevation -8200 mm ................................................21-60 Figure 3H.2-22 Control Building Framing Plan at Elevation -2150 mm ...........................................21-61 Figure 3H.2-23 Control Building Framing Plan at Elevation 3500 mm ............................................21-62 Figure 3H.2-24 Control Building Framing Plan at Elevation 7900 mm ............................................21-63 Figure 3H.2-25 Control Building Framing Plan at Elevation 12300 and 13100 mm.........................21-64 Figure 3H.2-26 Control Building Framing Plan at Elevation 17150 and 18250 mm.........................21-65 Figure 3H.2-27 Control Building Framing Plan at Elevation 22200 and 22750 mm.........................21-66 Figure 3H.2-28 Control Building Section...........................................................................................21-67 Figure 3H.2-29 Control Building Section and Details .......................................................................21-68 Figure 3H.2-30 Control Building Details ...........................................................................................21-69 Figure 3H.3-11 Radwaste Building, Reinforced Concrete Basemat ..................................................21-70 Figure 3H.3-12 Radwaste Building, Structural Steel Framing Plan, Typical Floor...........................21-71 Figure 3H.3-13 Radwaste Building, Structural Steel Framing Plan, Elevation 28000 mm ...............21-72 Figure 3H.3-14 Radwaste Building, Section A-A ..............................................................................21-73 Figure 3H.3-15 Radwaste Building, Exterior Walls Sections ............................................................21-74 Figure 3H.3-16 Radwaste Building, Sections and Details..................................................................21-75 Figure 4.6-8 Control Rod Drive System P&ID (Sheets 1-3) ........................................................21-76 Figure 4.6-9 Control Rod Drive System PFD................................................................................21-79 Figure 5.1-3 Nuclear Boiler System P&ID (Sheets 1-11).............................................................21-80 Table of Contents 171

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 1 List of Figures (Continued)

Figure 5.2-8 Leak Detection and Isolation System IED (Sheets 1-10) .........................................21-91 Figure 5.4-4 Reactor Recirculation System P&ID (Sheets 1-2) .................................................21-101 Figure 5.4-5 Reactor Recirculation System PFD.........................................................................21-103 Figure 5.4-8 Reactor Core Isolation Cooling System P&ID (Sheets 1-3) ..................................21-104 172 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 2 List of Figures Figure 5.4-9 Reactor Core Isolation Cooling System PFD (Sheets 1-2) ....................................21-107 Figure 5.4-10 Residual Heat Removal System P&ID (Sheets 1-7) ..............................................21-109 Figure 5.4-11 Residual Heat Removal System PFD (Sheets 1-2).................................................21-116 Figure 5.4-12 Reactor Water Cleanup System P&ID (Sheets 1-4)...............................................21-118 Figure 5.4-13 Reactor Water Cleanup System PFD (Sheets 1-2) .................................................21-122 Figure 5.4-14 Reactor Water Cleanup System IBD (Sheets 1-11) ...............................................21-124 Figure 6.2-38 Group Classification and Containment Isolation Diagram (Sheets 1-2) ................21-135 Figure 6.2-39 Atmospheric Control System P&ID (Sheets 1-3) ..................................................21-137 Figure 6.2-40 Flammability Control System P&ID (Sheets 1-2)..................................................21-140 Figure 6.3-1 High Pressure Core Flooder System PFD (Sheets 1-2)..........................................21-142 Figure 6.3-7 High Pressure Core Flooder System P&ID (Sheets 1-2)........................................21-144 Figure 6.5-1 Standby Gas Treatment System P&ID (Sheets 1-3)...............................................21-146 Figure 6.7-1 High Pressure Nitrogen Gas Supply System P&ID ................................................21-149 Figure 7.2-9 Reactor Protection System IED (Sheets 1-11) .......................................................21-150 Figure 7.2-10 Reactor Protection System IBD (Sheets 1-72) .......................................................21-161 Table of Contents 173

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 3 List of Figures Figure 7.3-1 High Pressure Core Flooder System IBD (Sheets 1-17) ........................................21-233 Figure 7.3-2 Nuclear Boiler System IBD (Sheets 1-37) .............................................................21-250 Figure 7.3-3 Reactor Core Isolation Cooling System IBD (Sheets 1-17) ...................................21-287 Figure 7.3-4 Residual Heat Removal System IBD (Sheets 1-20) ...............................................21-304 174 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 4 List of Figures Figure 7.3-5 Leak Detection and Isolation System IBD (Sheets 1-77).......................................21-324 Figure 7.3-6 Standby Gas Treatment System IBD (Sheets 1-11) ...............................................21-401 Figure 7.3-7 Reactor Building Cooling Water / Reactor Service Water System IBD (Sheets 1-19)...........................................................................................................21-412 Table of Contents 175

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 5 List of Figures Figure 7.3-9 HVAC Emergency Cooling Water System IBD (Sheets 1-11) .............................21-431 Figure 7.3-10 High Pressure Nitrogen Gas System IBD (Sheets 1-3) ..........................................21-442 Figure 7.4-1 Standby Liquid Control System IBD (Sheets 1-6) .................................................21-445 Figure 7.4-2 Remote Shutdown System IED...............................................................................21-451 Figure 7.4-3 Remote Shutdown System IBD (Sheets 1-27) .......................................................21-452 Figure 7.6-1 Neutron Monitoring System IED (Sheets 1-4) .......................................................21-479 Figure 7.6-2 Neutron Monitoring System IBD (Sheets 1-28).....................................................21-483 Figure 7.6-5 Process Radiation Monitoring System IED (Sheets 1-11) .....................................21-511 Figure 7.6-7 Containment Atmospheric Monitoring System IED (Sheets 1-4)..........................21-522 Figure 7.6-8 Containment Atmospheric Monitoring System IBD (Sheets 1-10) .......................21-526 Figure 7.6-11 Suppression Pool Temperature Monitoring System IED (Sheets 1-3)...................21-536 Figure 7.6-12 Suppression Pool Temperature Monitoring System IBD (Sheets 1-6) ..................21-539 Figure 7.7-2 Rod Control and Information System IED (Sheets 1-5) ........................................21-545 176 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 6 List of Figures Figure 7.7-3 Rod Control and Information System IBD (Sheets 1-87) ......................................21-550 Figure 7.7-4 Control Rod Drive System IBD (Sheets 1-8) .........................................................21-637 Figure 7.7-5 Recirculation Flow Control System IED (Sheets 1-2) ...........................................21-645 Figure 7.7-7 Recirculation Flow Control System IBD (Sheets 1-9) ...........................................21-647 Figure 7.7-8 Feedwater Control System IED (Sheets 1-3) .........................................................21-656 Figure 7.7-9 Feedwater Control System IBD (Sheets 1, 2, 2a, and 3-14)...................................21-659 Figure 7.7-12 Steam Bypass and Pressure Control System IED (Sheets 1-2) ..............................21-674 Figure 7.7-13 Steam Bypass and Pressure Control System IBD (Sheets 1-5)..............................21-676 Figure 7.7-14 Fuel Pool Cooling and Cleanup System IBD (Sheets 1-8).....................................21-681 Figure 8.2-1 Power Distribution System Routing Diagram (Sheets 1-7) ...................................21-689 Table of Contents 177

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 7 List of Figures Figure 8.3-1 Electrical Power Distribution System SLD (Sheets 1-3) .......................................21-696 Figure 8.3-2 Instrument and Control Power Supply System SLD...............................................21-699 Figure 8.3-3 Plant Vital AC Power Supply System SLD (Sheets 1-2) .......................................21-700 Figure 8.3-4 Plant DC Power Supply System SLD (Sheets 1-3) ................................................21-702 Figure 9.1-1 Fuel Pool Cooling and Cleanup System P&ID (Sheets 1-3)..................................21-705 Figure 9.1-2 Fuel Pool Cooling and Cleanup System PFD (Sheets 1-2) ....................................21-708 Figure 9.1-12 Plant Refueling and Servicing Sequence ................................................................21-710 Figure 9.2-1 Reactor Building Cooling Water System P&ID (Sheets 1-9) ................................21-711 Figure 9.2-1a Not Used Figure 9.2-2 HVAC Normal Cooling Water System P&ID ........................................................21-720 Figure 9.2-3 HVAC Emergency Cooling Water System P&ID (Sheets 1-3) .............................21-721 Figure 9.2-4 Makeup Water System (Condensate) P&ID ...........................................................21-724 Figure 9.2-5 Makeup Water System (Purified) P&ID (Sheets 1-3) ............................................21-725 Figure 9.2-7 Reactor Service Water System P&ID (Sheets 1-3) ................................................21-728 Figure 9.3-1 Standby Liquid Control System P&ID ...................................................................21-731 Figure 9.3-1a Standby Liquid Control System PFD......................................................................21-732 Figure 9.3-6 Instrument Air System P&ID (Sheets 1-2).............................................................21-733 Figure 9.3-7 Station Service Air System P&ID (Sheets 1-2)......................................................21-735 Figure 9.4-1 Control Building HVAC Flow Diagram (Sheets 1-5) ............................................21-737 Figure 9.4-2a Turbine Building Ventilation System Air Flow Diagram.......................................21-742 Figure 9.4-2b Turbine Building Ventilation System Control Diagram (Sheets 1-2) ....................21-743 Figure 9.4-3 Secondary Containment HVAC System (Sheets 1-3) ............................................21-745 Figure 9.4-4 R/B Safety-Related Electrical Equipment HVAC System (Sheets 1-3) ................21-748 Figure 9.4-5 Reactor Internal Pump Control Panel Room HVAC System..................................21-751 Figure 9.4-8 Drywell Cooling System P&ID ..............................................................................21-752 Figure 9.4-10 Radwaste Building HVAC (Sheets 1-3).................................................................21-753 178 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 7 List of Figures (Continued)

Figure 9.5-1 Suppression Pool Cleanup System P&ID ...............................................................21-756 Figure 9.5-6 Standby Diesel Generator Fuel Oil and Combustion Air Intake and Exhaust Systems......................................................................................................21-757 Figure 9.5-7 Standby Diesel Generator Jacket Cooling Water System .......................................21-758 Figure 9.5-8 Standby Diesel Generator Starting Air System.......................................................21-759 Figure 9.5-9 Standby Diesel Generator Lubricating Oil System .................................................21-760 Figure 9A.4-1 Reactor Building Fire Protection at Elevation -8200 mm.......................................21-761 Figure 9A.4-2 Reactor Building Fire Protection at Elevation -1700 mm.......................................21-762 Figure 9A.4-3 Reactor Building Fire Protection at Elevation 4800/8500 mm ...............................21-763 Figure 9A.4-4 Reactor Building Fire Protection at Elevation 12300 mm ......................................21-764 Figure 9A.4-5 Reactor Building Fire Protection at Elevation 18100 mm ......................................21-765 Figure 9A.4-6 Reactor Building Fire Protection at Elevation 23500 mm ......................................21-766 Figure 9A.4-7 Reactor Building Fire Protection at Elevation 27200 mm ......................................21-767 Figure 9A.4-8 Reactor Building Fire Protection at Elevation 31700/38200 mm ...........................21-768 Figure 9A.4-9 Reactor Building Fire Protection, Section A-A ......................................................21-769 Figure 9A.4-10 Reactor Building Fire Protection, Section B-B.......................................................21-770 Figure 9A.4-11 Control Building Fire Protection, Section B-B .......................................................21-771 Figure 9A.4-12 Control Building Fire Protection at Elevation -8200 mm .......................................21-772 Figure 9A.4-13 Control Building Fire Protection at Elevation -2150 mm .......................................21-773 Figure 9A.4-14 Control Building Fire Protection at Elevation 3500 mm ........................................21-774 Figure 9A.4-15 Control Building Fire Protection at Elevation 7900 mm ........................................21-775 Table of Contents 179

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 8 List of Figures Figure 9A.4-16 Control Building Fire Protection at Elevation 12300 mm ......................................21-776 Figure 9A.4-16a Control Building Fire Protection at Elevation 17150 mm ......................................21-777 Figure 9A.4-16b Control Building Fire Protection at Elevation 22200 mm ......................................21-778 Figure 9A.4-17 Turbine Building Fire Protection, Section A-A ......................................................21-779 Figure 9A.4-18 Turbine Building Fire Protection at Elevation 5300 mm........................................21-780 Figure 9A.4-19 Turbine Building Fire Protection at Elevation 12300 mm......................................21-781 Figure 9A.4-20 Turbine Building Fire Protection at Elevation 20300 mm......................................21-782 Figure 9A.4-21 Turbine Building Fire Protection at Elevation 30300 mm......................................21-783 Figure 9A.4-22 Service Building Fire Protection, Section B-B (See Figure 9A.4-11) ....................21-771 Figure 9A.4-23 Service Building Fire Protection at Elevation -2150 mm (See Figure 9A.4-13) ....21-773 Figure 9A.4-24 Service Building Fire Protection at Elevation 3500 mm (See Figure 9A.4-14) .....21-774 Figure 9A.4-25 Service Building Fire Protection at Elevation 7900 mm (See Figure 9A.4-15) .....21-775 Figure 9A.4-26 Service Building Fire Protection at Elevation 12300 mm (See Figure 9A.4-16) ...21-776 Figure 9A.4-27 Service Building Fire Protection at Elevation 17150 mm (See Figure 9A.4-16a) .............................................................................................21-777 Figure 9A.4-28 Radwaste Building Fire Protection, Section A-A ...................................................21-784 Figure 9A.4-29 Radwaste Building Fire Protection at Elevation -1500 mm....................................21-785 Figure 9A.4-30 Radwaste Building Fire Protection at Elevation 4800 mm .....................................21-786 Figure 9A.4-31 Radwaste Building Fire Protection at Elevation 12300 mm ...................................21-787 Figure 9A.4-32 Radwaste Building Fire Protection at Elevation 21000 mm ...................................21-788 Figure 10.1-2 Reference Heat Balance for Guaranteed Reactor Rating ........................................21-789 Figure 10.1-3 Reference Heat Balance for Valves-Wide-Open (VWO) .......................................21-790 Figure 11.2-1 Radwaste System PFD ............................................................................................21-791 Figure 11.3-1 Offgas System PFD (Sheets 1-2)............................................................................21-792 Figure 11.3-2 Offgas System P&ID (Sheets 1-3) .........................................................................21-794 Figure 12.3-1 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation -8200 mm (B3F) ................................................................21-797 180 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 8 List of Figures (Continued)

Figure 12.3-2 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation -1700 mm (B2F) ................................................................21-798 Figure 12.3-3 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 4800/8500 mm (B1F).........................................................21-799 Figure 12.3-5 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 12300 mm (1F) ..................................................................21-800 Figure 12.3-6 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 18100 mm (2F) ..................................................................21-801 Figure 12.3-7 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 23500 mm (3F) ..................................................................21-802 Figure 12.3-8 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 27200 mm (3.5F) ...............................................................21-803 Figure 12.3-9 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation at Elevation 31700/38200 mm (4FM)....................................................21-804 Figure 12.3-10 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation, Section A-A...........................................................................................21-805 Figure 12.3-11 Reactor Building Radiation Zone Map for Full Power and Shutdown Operation, Section B-B ...........................................................................................21-806 Figure 12.3-12 Reactor Building Radiation Zone Map Post LOCA at Elevation -8200 mm (B3F) .................................................................................21-807 Figure 12.3-13 Reactor Building Radiation Zone Map Post LOCA at Elevation -1700 mm (B2F) .................................................................................21-808 Figure 12.3-14 Reactor Building Radiation Zone Map Post LOCA at Elevation 4800/8500 mm (B1F)..........................................................................21-809 Figure 12.3-16 Reactor Building Radiation Zone Map Post LOCA at Elevation 12300 mm (1F) ...................................................................................21-810 Figure 12.3-17 Reactor Building Radiation Zone Map Post LOCA at Elevation 18100 mm (2F) ...................................................................................21-811 Figure 12.3-18 Reactor Building Radiation Zone Map Post LOCA at Elevation 23500 mm (3F) ...................................................................................21-812 Figure 12.3-19 Reactor Building Radiation Zone Map Post LOCA at Elevation 27200 mm (3.5F) ................................................................................21-813 Figure 12.3-20 Reactor Building Radiation Zone Map Post LOCA at Elevation 31700/38200 mm (4FM).....................................................................21-814 Table of Contents 181

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 8 List of Figures (Continued)

Figure 12.3-21 Reactor Building Radiation Zone Map Post LOCA, Section A-A .........................21-815 Figure 12.3-22 Reactor Building Radiation Zone Map Post LOCA, Section B-B..........................21-816 Figure 12.3-37 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation -1500 mm ............................................................................................21-817 Figure 12.3-38 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation -4800 mm ............................................................................................21-818 Figure 12.3-39 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation 12300 mm ...........................................................................................21-819 Figure 12.3-40 Radwaste Building, Radiation Zone Map, Normal Operation at Elevation 21000 mm ...........................................................................................21-820 Figure 12.3-41 Radwaste Building, Radiation Zone Map, Normal Operation, Section A-A..........21-821 Figure 12.3-42 Control Building, Radiation Zone, Normal Operation at Elevation -8200 mm......21-822 Figure 12.3-43 Control and Service Building, Radiation Zone, Normal Operation at Elevation -2150 mm ............................................................................................21-823 Figure 12.3-44 Control and Service Building, Radiation Zone, Normal Operation at Elevation 3500 mm .............................................................................................21-824 Figure 12.3-45 Control and Service Building, Radiation Zone, Normal Operation at Elevation 7900 mm .............................................................................................21-825 Figure 12.3-46 Control and Service Building, Radiation Zone, Normal Operation at Elevation 12300 mm ...........................................................................................21-826 Figure 12.3-47 Control and Service Building, Radiation Zone, Normal Operation at Elevation 17150 mm ...........................................................................................21-827 Figure 12.3-48 Control and Service Building, Radiation Zone, Normal Operation, Side View, Cross Section B-B ................................................................................21-828 Figure 12.3-49 Turbine Building, Radiation Zone at Elevation 5300 mm ......................................21-829 Figure 12.3-50 Turbine Building, Radiation Zone at Elevation 12300 mm ....................................21-830 Figure 12.3-51 Turbine Building, Radiation Zone at Elevation 20300 mm ....................................21-831 Figure 12.3-52 Turbine Building, Radiation Zone at Elevation 30300 mm ....................................21-832 Figure 12.3-53 Turbine Building, Radiation Zone at Normal Operation Longitudinal Section A-A.............................................................................................................21-833 Figure 12.3-54 Control and Service Building, Radiation Zone, Post LOCA, Section B-B.............21-834 182 Table of Contents

25A5675AB Revision 7 ABWR Design Control Document/Tier 2 Chapter 21 Volume 8 List of Figures (Continued)

Figure 12.3-55 Turbine Building, Radiation Zone, Post LOCA, Longitudinal Section A-A..........21-835 Figure 12.3-56 Reactor Building, Area Radiation Monitors at Elevation -8200 mm......................21-836 Figure 12.3-57 Reactor Building, Area Radiation Monitors at Elevation -1700 mm......................21-837 Figure 12.3-58 Reactor Building, Area Radiation Monitors at Elevation 4800/8500 mm..............21-838 Figure 12.3-59 Reactor Building, Area Radiation Monitors at Elevation 12300 mm .....................21-839 Figure 12.3-60 Reactor Building, Area Radiation Monitors at Elevation 23500 mm .....................21-840 Figure 12.3-61 Reactor Building, Area Radiation Monitors at Elevation 27200 mm .....................21-841 Figure 12.3-62 Reactor Building, Area Radiation Monitors at Elevation 31700/38200 mm..........21-842 Figure 12.3-63 Reactor Building, Area Radiation Monitors, Section B-B......................................21-843 Figure 12.3-64 Control and Service Buildings, Area Radiation Monitors, Section B-B.................21-844 Figure 12.3-65 Radwaste Building, Area Radiation Monitors at Elevation -1500 mm ..................21-845 Figure 12.3-66 Radwaste Building, Area Radiation Monitors at Elevation 4800 mm....................21-846 Figure 12.3-67 Radwaste Building, Area Radiation Monitors at Elevation 12300 mm..................21-847 Figure 12.3-68 Radwaste Building, Area Radiation Monitors at Elevation 21000 mm..................21-848 Figure 12.3-70 Turbine Building, Area Radiation Monitors at Elevation 12300 mm.....................21-849 Figure 12.3-71 Turbine Building, Area Radiation Monitors at Elevation 20300 mm.....................21-850 Figure 12.3-72 Turbine Building, Area Radiation Monitors at Elevation 30300 mm.....................21-851 Figure 12.3-73 Turbine Building, Area Radiation Monitors, Longitudinal Section A-A ...............21-852 Figure 15B-3 Fine Motion Control Rod Drive ..............................................................................21-853 Figure 18C-5 Arrangement of Equipment of Main Control Console............................................21-854 Figure 18C-7 Fixed-Position Display............................................................................................21-855 Figure 20.3.4-5a Low Pressure Core Flooder Sparger (Sheet 1)........................................................21-856 Figure 20.3.4-5b Low Pressure Core Flooder Sparger (Sheet 2)........................................................21-857 Figure 20.3.4-5c High Pressure Core Flooder Sparger.......................................................................21-858 Table of Contents 183